ML14169A647
| ML14169A647 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 06/16/2014 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | Luminant Generation Co |
| laura hurley | |
| References | |
| Download: ML14169A647 (222) | |
Text
JPM RA-2 CONTAINS PROPRIETARY INFORMATION AND HAS BEEN WITHHELD FROM PUBLIC DISCLOSURE
JPM SA-2 CONTAINS PROPRIETARY INFORMATION AND HAS BEEN WITHHELD FROM PUBLIC DISCLOSURE
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA1 Task # RO1404 K/A # 2.1.25 3.9 / 4.2
Title:
Determine Minimum and Maximum RHR Flow Rate 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 has been shut down for 20 days and 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
Reactor Coolant System is in a Reduced Inventory Condition.
1-LI-3615A, RX VSL LVL (NR) is 50 inches above Core Plate.
Reactor Coolant System temperature is 160°F.
Initiating Cue: The Unit Supervisor directs you to PERFORM the following in accordance with ABN-104, Residual Heat Removal System Malfunction:
Utilizing ABN-104, Attachment 3, Minimum RHR Flow Guideline For Decay Heat Removal DETERMINE the minimum Residual Heat Removal flow rate given the Time after Shutdown.
__________ gpm DETERMINE the maximum Residual Heat Removal flow rate given Reactor Coolant System level.
__________ gpm Task Standard: Utilizing ABN-104, Attachments 3, 4, and 16, calculated the minimum and maximum Residual Heat Removal System flow rates with the Reactor Coolant System in a Reduced Inventory Condition based on 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> after shutdown, Reactor Vessel Level of 50 inches above Core Plate and Reactor Coolant System temperature of 160°F.
Required Materials: ABN-104, Residual Heat Removal System Malfunction, Rev. 9.
Validation Time: 10 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 1 of 4 CPNPP NRC 2014 JPM RA1 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:
PROVIDE the examinee with a copy of:
ABN-104, Residual Heat Removal System Malfunction.
Attachment 3, Minimum RHR Flow Guideline For Decay Heat Removal.
Attachment 4, RHR Maximum Flow Limit Versus RCS Level.
Attachment 16, Actual Versus Indicated Reactor Vessel Level.
Page 2 of 4 CPNPP NRC 2014 JPM RA1 Draft Submittal
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 3.
Perform Step: 1 DETERMINE the minimum Residual Heat Removal flow rate given the Time after Shutdown.
Standard: PERFORMED the following:
CALCULATED Time after Shutdown as 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />.
REFERENCED ABN-104, Attachment 3 at 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />.
DETERMINED minimum RHR flow is 2200 +/- 50 gpm.
Comment: SAT UNSAT Examiner Note: The following steps are from ABN-104, Attachment 16.
Perform Step: 2 DETERMINE the maximum Residual Heat Removal flow rate given the Time after Shutdown.
Standard: PERFORMED the following:
DETERMINED 1-LI-3615A, RX VSL LVL (NR) is 50 inches above Core Plate indicated level without temperature correction.
REFERENCED ABN-104, Attachment 16, Page 2 of 2 at 50 inches above Core Plate indicated level and 160°F.
DETERMINED 1-LI-3615A, RX VSL LVL (NR) is 55 inches actual level with temperature correction.
Comment: SAT UNSAT Examiner Note: The following steps are from ABN-104, Attachment 4.
Perform Step: 3 DETERMINE the maximum Residual Heat Removal flow rate given the Time after Shutdown with temperature correction applied.
Standard: PERFORMED the following:
DETERMINED actual level of 1-LI-3615A, RX VSL LVL (NR) is 55 inches above Core Plate.
REFERENCED ABN-104, Attachment 4 at 55 inches above Core Plate.
DETERMINED maximum RHR flow is 4000 gpm.
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 3 of 4 CPNPP NRC 2014 JPM RA1 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
Unit 1 has been shut down for 20 days and 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
Reactor Coolant System is in a Reduced Inventory Condition.
1-LI-3615A, RX VSL LVL (NR) is 50 inches above Core Plate.
Reactor Coolant System temperature is 160°F.
INITIATING CUE: The Unit Supervisor directs you to PERFORM the following in accordance with ABN-104, Residual Heat Removal System Malfunction:
Utilizing ABN-104, Attachment 3, Minimum RHR Flow Guideline For Decay Heat Removal DETERMINE the minimum Residual Heat Removal flow rate given the Time after Shutdown.
__________ gpm DETERMINE the maximum Residual Heat Removal flow rate given Reactor Coolant System level.
__________ gpm Page 4 of 4 CPNPP NRC 2014 JPM RA1 Draft Submittal
CPNPP PROCEDURE NO.
ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 9 PAGE 72 OF 125 ATTACHMENT 3 PAGE 1 OF 1
[C] MINIMUM RHR FLOW GUIDELINE FOR DECAY HEAT REMOVAL Attachment 3 CPNPP NRC 2014 JPM RA1 Answer Key Draft Submittal
CPNPP PROCEDURE NO.
ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 9 PAGE 73 OF 125 ATTACHMENT 4 PAGE 1 OF 2
[C] RHR MAXIMUM FLOW LIMIT VERSUS RCS LEVEL CAUTION: Do NOT reduce RHR flow below 1000 gpm. (TS 3.9.6)
NOTE: ! For RHR System limits, see Page 2 this attachment.
! IF RCS temperature exceeds 110°F, THEN actual vessel level will be higher than indicated. Refer to Attachment 16 for the correction.
! The narrow range instrument u-LI-3615A, RX VSL LVL (NR), should be used to verify limits since instrument errors assumed in the limits are based on this instrument.
! These limits reflect analyzed uncertainties in level and flow instrumentation.
MAXIMUM IN. ABOVE CORE RHR FLOW ELEVATION PLATE (u-LI-3615A) u-FI-618/619 827' 7-1/2" 55-1/2" 4800 827' 7" 55" 4000 827' 6" 54" 3300 827' 5" 53" 2800 827' 4" 52" 2400 827' 3" 51" 2000 827' 2" 50" 1700 827' 1" 49" 1400 827' 0" 48" 1100 Attachment 4 CPNPP NRC 2014 JPM RA1 Answer Key Draft Submittal
CPNPP PROCEDURE NO.
ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 9 PAGE 74 OF 125 ATTACHMENT 4 PAGE 2 OF 2 RHR MAXIMUM FLOW LIMIT VERSUS RCS LEVEL RHR System and pump limitations RCS Loops not filled.
! While in MODE 5 with the Reactor Coolant loops not filled, two RHR loops shall be operable and one RHR loop shall be in operation per TS 3.4.8.
! The RHR flow/RCS level limits of page 1 of this attachment shall not be exceeded when RCS level is less than elevation 829' 8".(i.e., indicated level less than five (5) feet below the vessel flange ).
! While in MODE 5, the RHR pump in operation may be de-energized for up to one hour, provided the core outlet temperature is maintained at least 10°F below saturation temperature, no operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1; and no draining operations to further reduce the RCS water volume are permitted.
! While in MODE 6 with the water level above the top of the reactor vessel flange greater than or equal to 23 feet, at least one RHR loop shall be operable and in operation per TS 3.9.5.
! While in MODE 6 with the water level above the top of the reactor vessel flange less than 23 feet, two independent RHR loops shall be operable and one RHR loop shall be in operation per TS 3.9.6.
! While in MODE 6 with greater than or equal to 23 feet of water above the reactor vessel flange, the RHR pump in operation may be stopped up to one hour per eight-hour period during Core Alterations in the vicinity of the hot legs.
! A maximum of two consecutive starts of the RHR pumps are allowed with the motors cold.
With the motor at operating temperture only one consecutive start is allowed. Subsequent starts with the motor running between starts must be 15 minutes apart. Subsequent starts with the motor idle between starts must be 45 minutes apart.
Attachment 4 CPNPP NRC 2014 JPM RA1 Answer Key Draft Submittal
CPNPP PROCEDURE NO.
ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 9 PAGE 108 OF 125 ATTACHMENT 16 PAGE 1 OF 2 ACTUAL VERSUS INDICATED REACTOR VESSEL LEVEL (For Various Temperatures)
Attachment 16 CPNPP NRC 2014 JPM RA1 Answer Key Draft Submittal
CPNPP PROCEDURE NO.
ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 AND 2 ABN-104 RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION REVISION NO. 9 PAGE 109 OF 125 ATTACHMENT 16 PAGE 2 OF 2 ACTUAL VERSUS INDICATED REACTOR VESSEL LEVEL (For Various Temperatures)
Attachment 16 CPNPP NRC 2014 JPM RA1 Answer Key Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # AUDIT RA3 Task # RO1803D K/A # 2.2.12 3.7 / 4.1
Title:
Perform a Manual Quadrant Power Tilt Ratio Calculation 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 operating at a steady-state condition of 100% power.
Rod Control is in AUTO with Control Bank D at 215 steps and all other rods at the FOP of 225 steps.
The Reactor Makeup System is aligned for AUTO operation with VCT level stable at 58%.
NIS Power Range Meters and Power Range Detector Current Meters currently read:
Channel Meter Upper Detector (A) Lower Detector (A)
NI-41 100.3% 163.67 167.30 NI-42 99.2% 191.36 182.35 NI-43 99.3% 158.84 157.25 NI-44 100.4% 182.05 179.11 Initiating Cue: The Unit Supervisor directs you to PERFORM the following:
CALCULATE a Quadrant Power Tilt Ratio per OPT-302, Calculating Power Tilt Ratio through Step 8.13.
RECORD data on OPT-302-1, Quadrant Power Tilt Ratio Data Sheet.
DOCUMENT Acceptance Criteria status for each Upper and Lower Power Range Instrument.
If required, DOCUMENT any notifications in the Comments Section.
Task Standard: Utilizing OPT-302 and OPT-302-1, performed a Manual Quadrant Power Tilt Ratio Calculation and identified SAT Acceptance Criteria for NI-41, NI-42, NI-43 and identified UNSAT Acceptance Criteria for NI-44.
Page 1 of 7 CPNPP NRC 2014 JPM RA3 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Required Materials: OPT-302, Calculating Power Tilt Ratio, Rev. 11-1.
OPT-302-1, Quadrant Power Tilt Ratio Data Sheet, Rev 8.
NUC-203-8, Normalized Power Range Excore Detector Currents for Cycle 17.
Validation Time: 25 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 2 of 7 CPNPP NRC 2014 JPM RA3 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:
PROVIDE the examinee with a copy of:
OPT-302, Calculating Power Tilt Ratio.
OPT-302-1, Quadrant Power Tilt Ratio Data Sheet.
NUC-203-8, Normalized Power Range Excore Detector Currents for Cycle 17.
Calculator.
Page 3 of 7 CPNPP NRC 2014 JPM RA3 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Examiner Note: The following steps are from OPT-302, Section 8.0.
Perform Step: 1 VERIFY Prerequisites in 6.0 are satisfied.
8.1 Standard
DETERMINED Prerequisites in 6.0 are satisfied.
Comment: SAT UNSAT Perform Step: 2 WHEN operating with an inoperable Power Range channel AND 8.2 Reactor Power 75% RTP, THEN the three operable channels shall be used for calculations to determine the QPTR.
Standard: DETERMINED all Power Range Channels OPERABLE.
Comment: SAT UNSAT Perform Step: 3 RECORD the following information onto Form OPT-302-1:
8.3 & 8.3.1 Unit, Cycle, Date, and Time, Standard: DETERMINED Unit, Cycle, Date, and Time already recorded.
Comment: SAT UNSAT Perform Step: 4 RECORD the following information onto Form OPT-302-1:
8.3 & 8.3.2 Power Range NIS power level for each channel (use one minute computer point averages (N6049A01, N6050A01, N6051A01, N6052A01) or NIS Panel).
Standard: RECORDED indication for NI-41, NI-42, NI-43, and NI-44 onto Form OPT-302-1.
Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2014 JPM RA3 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 5 RECORD the following information onto Form OPT-302-1:
8.3 & 8.3.3 Control rod bank positions from the step counters.
Standard: RECORDED Control rod bank positions from the Step Counters onto Form OPT-302-1.
Comment: SAT UNSAT Perform Step: 6 RECORD the following information onto Form OPT-302-1:
8.3 & 8.3.4 DETERMINE the average of the Power Range NIS Power levels recorded in Step 8.3.2.
Standard: CALCULATED average of operable NIS channels and RECORDED onto Form OPT-302-1.
Comment: SAT UNSAT Perform Step: 7 RECORD detector currents from DETECTOR A&B DETECTOR 8.4 CURRENT for each of the power range channels, N-41 through N-44.
Standard: RECORDED upper and lower detector currents for NI-41, NI-42, NI-43, and NI-44 onto Form OPT-302-1.
Comment: SAT UNSAT Examiner Note: NUC-203-8, Normalized Power Range Excore Detector Currents for Cycle 17 is included in the handout.
Perform Step: 8 RECORD 120% Power Normalized Excore Upper (Top) and Lower 8.5 (Bottom) Detector Currents from NUC-203-8, NORMALIZED POWER RANGE EXCORE DETECTOR CURRENTS located in "NUC FORMS" section of the Nuclear Design Report (NDR) for the current cycle.
Standard: RECORDED 120% Power Normalized Excore Upper (Top) and Lower (Bottom) Detector Currents from NUC-203-8 for Cycle 17 onto Form OPT-302-1.
Comment: SAT UNSAT Page 5 of 7 CPNPP NRC 2014 JPM RA3 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 9 DETERMINE the Actual Power Tilt Ratios by one of the following 8.6 & 1st bullet methods:
Manual calculations per QUADRANT POWER TILT RATIO DATA SHEET OPT-302-1.
Standard: PERFORMED manual calculations for NI-41, NI-42, NI-43 and NI-44 and RECORDED onto Form OPT-302-1.
Comment: SAT UNSAT Perform Step: 10 VERIFY the Power Tilt Ratio for each detector is LESS THAN OR 8.7 EQUAL TO 1.02.
IF any power tilt ratio exceeds 1.02, THEN immediately notify the Shift Manager AND reference Section 5.2.
Standard: DOCUMENTED notification of the Shift Manager in the Comments Section of OPT-302-1.
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 6 of 7 CPNPP NRC 2014 JPM RA3 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
Unit 1 is operating at a steady-state condition of 100%
power.
Rod Control is in AUTO with Control Bank D at 215 steps and all other rods at the FOP of 225 steps.
The Reactor Makeup System is aligned for AUTO operation with VCT level stable at 58%.
NIS Power Range Meters and Power Range Detector Current Meters currently read:
Channel Meter Upper Detector (A) Lower Detector (A)
NI-41 100.3% 163.67 167.30 NI-42 99.2% 191.36 182.35 NI-43 99.3% 158.84 157.25 NI-44 100.4% 182.05 179.11 INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:
CALCULATE a Quadrant Power Tilt Ratio per OPT-302, Calculating Power Tilt Ratio through Step 8.13.
RECORD data on OPT-302-1, Quadrant Power Tilt Ratio Data Sheet.
DOCUMENT Acceptance Criteria status for each Upper and Lower Power Range Instrument.
If required, DOCUMENT any notifications in the Comments Section.
Page 7 of 7 CPNPP NRC 2014 JPM RA3 Draft Submittal
QUADRANT POWER TILT RATIO DATA SHEET 8.3.1 UNIT: 1 CYCLE: 17 DATE: 06/09/14 TIME: 0800 POWER N-41A N-42A N-43A N-44A AVERAGE RANGE % % % % %
8.3.2 8.3.4 NIS 100.3 99.2 99.3 100.4 99.8 8.3.3 CONTROL ROD POSITION (steps)
SHUTDOWN BANKS: A1 225 B1 225 C 225 D 225 E 225 A2 225 B2 225 CONTROL BANKS: A1 225 B1 225 C1 225 D1 215 A2 225 B2 225 C2 225 D2 215 8.4 DATA [X] METERS SOURCE:
[ ] DVM - PERFORM Attachment 10.1 8.5 8.6 120%
NIS ACTUAL POWER NORMALIZED POWER RANGE DETECTOR CURRENT DETECTOR CURRENT CALIBRATED CHANNEL MICROAMPS MICROAMPS OUTPUT*
UPPER LOWER UPPER LOWER UPPER LOWER N-41B 163.67 167.30 178.47 181.01 0.917 0.924 N-42B 191.36 182.35 217.39 198.74 0.880 0.918 N-43B 158.84 157.25 179.29 176.12 0.886 0.893 N-44B 182.05 179.11 195.11 190.65 0.933 0.939
- CALIBRATED OUTPUT = ACTUAL CURRENT 8.6 SUM: 3.616 3.674 120% POWER NORMAL CURRENT 0.9185
8.6 AVERAGE
0.904 8.7 NIS ACTUAL POWER 8.6 POWER RANGE POWER TILT TILT RATIO ACCEPTANCE CRITERIA CHANNEL RATIO** LIMIT SATISFIED UPPER YES/NO INITIALS N-41B 1.014 1.02 YES N-42B 0.973 1.02 YES N-43B 0.980 1.02 YES N-44B 1.032 1.02 NO 8.6 LOWER N-41B 1.006 1.02 YES N-42B 0.999 1.02 YES N-43B 0.972 1.02 YES N-44B 1.022 1.02 NO
QUADRANT POWER TILT RATIO DATA SHEET DISCREPANCIES/COMMENTS: NOTFIED the Shift Manager that NI-44 is UNSAT.
CORRECTIVE ACTIONS:
Performed By: Date Reviewed By: Date Unit Supervisor: Date Operations Management Review: Date:
OPT-302-1 REFERENCE USE PAGE 2 OF 2 CPNPP NRC 2014 JPM RA3 Answer Key Draft Submittal R-8
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA4 Task # RWT029D K/A # 2.3.12 3.2 / 3.7
Title:
Determine Radiation Doses During System Aligment 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 high dose alignment is scheduled in the Safeguards Building.
The general dose rate in the area is 50 mrem/hour but can be reduced to 5 mrem/hour if lead shielding is installed.
It will take Nuclear Equipment Operators (NEOs) Alpha & Bravo 60 minutes to install the shielding.
Independent of the shielding, it will take NEO Alpha four hours or NEOs Alpha & Bravo two and a half hours to perform the maintenance.
Initiating Cue: The Work Control Supervisor directs you to PERFORM the following:
CALCULATE the dose received when performing the system alignment for each of the following conditions:
NEO Alpha without shielding. _____ mrem NEOs Alpha & Bravo without shielding. _____ mrem NEO Alpha with shielding (installed by NEOs Alpha and Bravo).
_____ mrem NEOs Alpha & Bravo with shielding (installed by NEOs Alpha and Bravo). _____ mrem Task Standard: Utilizing STA-657, calculated the dose received when performing a system alignment.
Required Materials: STA-657, ALARA Job Planning/Debriefing, Rev. 17-1.
Validation Time: 10 minutes Completion Time: ________ minutes Page 1 of 5 CPNPP NRC 2014 JPM RA4 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 2 of 5 CPNPP NRC 2014 JPM RA4 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:
PROVIDE the examinee with a copy of:
STA-657, ALARA Job Planning/Debriefing.
Page 3 of 5 CPNPP NRC 2014 JPM RA4 Draft Submittal
Appendix C JPM STEPS Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Perform Step: 1 Determine total dose to NEO Alpha without shielding.
Standard: DETERMINED total dose to NEO Alpha without shielding as follows:
50 mrem/hr x 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> = 200 mrem total dose.
Comment: SAT UNSAT Perform Step: 2 Determine total combined dose to NEOs Alpha & Bravo without shielding.
Standard: DETERMINED total combined dose to NEOs Alpha & Bravo without shielding as follows:
50 mrem/hr x 2.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />s/NEO x 2 NEOs = 250 mrem total dose.
Comment: SAT UNSAT Perform Step: 3 Determine total dose to install shielding.
Standard: DETERMINED total dose to install shielding as follows:
50 mrem/hr x 1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br />s/NEO x 2 NEOs = 100 mrem to install.
Comment: SAT UNSAT Perform Step: 4 Determine total dose to NEO Alpha with shielding.
Standard: DETERMINED total dose to NEO Alpha with shielding as follows:
5 mrem/hr x 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> + 100 mrem = 120 mrem total dose.
Comment: SAT UNSAT Perform Step: 5 Determine total combined dose to NEOs Alpha & Bravo with shielding.
Standard: DETERMINED total combined dose to NEOs Alpha & Bravo with shielding as follows:
5 mrem/hr x 2.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />s/NEO x 2 NEOs + 100 mrem = 125 mrem total dose.
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 4 of 5 CPNPP NRC 2014 JPM RA4 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
A high dose alignment is scheduled in the Safeguards Building.
The general dose rate in the area is 50 mrem/hour but can be reduced to 5 mrem/hour if lead shielding is installed.
It will take Nuclear Equipment Operators (NEOs) Alpha
& Bravo 60 minutes to install the shielding.
Independent of the shielding, it will take NEO Alpha four hours or NEOs Alpha & Bravo two and a half hours to perform the maintenance.
INITIATING CUE: The Work Control Supervisor directs you to PERFORM the following:
CALCULATE the dose received when performing the system alignment for each of the following conditions:
NEO Alpha without shielding. _____ mrem NEOs Alpha & Bravo without shielding. _____ mrem NEO Alpha with shielding (installed by NEOs Alpha and Bravo). _____ mrem NEOs Alpha & Bravo with shielding (installed by NEOs Alpha and Bravo). _____ mrem Page 5 of 5 CPNPP NRC 2014 JPM RA4 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA1 Task # SO1005D K/A # 2.1.1 3.8 / 4.2
Title:
Determine Technical Specification 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:
Unit 2 is in MODE 1 when a fault occurs on XST1.
All plant systems responded as required.
ABN-602, Response to a 6900/480V System Malfunction has been completed.
Initiating Cue: The Shift Manager directs you to PERFORM the following:
DETERMINE Technical Specification impacted including CONDITION, REQUIRED ACTION and COMPLETION TIME, if any.
DETERMINE ORAL and WRITTEN Reportability Requirements, if any.
Task Standard: Utilizing STA-501 and CPNPP Technical Specifications, determined Technical Specifications impacted and Reportability Requirements for loss of Preferred Offsite Power and valid actuation of Auxiliary Feedwater.
Required Materials: STA-501, Non-Routine Reporting, Rev. 18.
CPNPP Technical Specifications - Unit 1 and 2 through Amendment 161.
Validation Time: 10 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 1 of 5 CPNPP NRC 2014 JPM SA1 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:
PROVIDE the examinee with a copy of:
STA-501, Non-Routine Reporting.
CPNPP Technical Specifications - Unit 1 and 2.
Page 2 of 5 CPNPP NRC 2014 JPM SA1 Draft Submittal
Appendix C JPM STEPS Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Examiner Note: The following steps are from Technical Specification LCO 3.8.1.
Perform Step: 1 Determine Technical Specification LCO and CONDITION.
Standard: RECOGNIZED loss of Preferred Offsite Power impacted and DETERMINED the following:
Technical Specification LCO 3.8.1, AC Sources - Operating, CONDITION A, One required offsite circuit inoperable Comment: SAT UNSAT Perform Step: 2 Determine Technical Specification LCO 3.8.1.A REQUIRED ACTION and COMPLETION TIME.
Standard: DETERMINED REQUIRED ACTION and COMPLETION TIME:
LCO 3.8.1.A.1 - Perform SR 3.8.1.1 for required OPERABLE offsite circuit 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 LCO 3.8.1.A.2 - Declare required feature(s) with no offsite power available inoperable when its redundant required feature(s) is inoperable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from discovery of no offsite power to one train concurrent within inoperability of redundant required feature(s).
AND LCO 3.8.1.A.3 - Restore required offsite circuit to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR 14 days for two one-time outages on XST1 to complete a plant modification to be completed by March 31, 2014.
Comment: SAT UNSAT Page 3 of 5 CPNPP NRC 2014 JPM SA1 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following step is from STA-501, Attachment 8.B.
Examiner Note: Only the bold item is required for Critical Step acceptance.
Perform Step: 3 Determine oral notification Reporting Requirements per STA-501, Attachment 8.B.
Standard: DETERMINED Oral Reporting Requirements (page 21 of 196) is for the following:
Notification of certain events, conditions and releases described in 10CFR50.72(b)(3).
Any event or condition that results in valid actuation of any of the systems listed below, except when the actuation results from and is part of a preplanned sequence during testing or reactor operation:
PWR auxiliary or emergency feedwater system.
Oral Report within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of occurrence via Emergency Notification System.
Comment: SAT UNSAT Examiner Note: The following step is from STA-501, Attachment 8.D.
Examiner Note: Only the bold item is required for Critical Step acceptance.
Perform Step: 4 Determine written notification Reporting Requirements per STA-501, Attachment 8.D.
Standard: DETERMINED Written Reporting Requirements (page 108 of 196) is for the following:
10CFR50.73(a)(2)(iv)(A/B)
The completion of any nuclear plant shutdown required by the plants Technical Specifications.
Written Report within 60 days (LER).
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 4 of 5 CPNPP NRC 2014 JPM SA1 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
Unit 2 is in MODE 1 when a fault occurs on XST1.
All plant systems responded as required.
ABN-602, Response to a 6900/480V System Malfunction has been completed.
INITIATING CUE: The Shift Manager directs you to PERFORM the following:
DETERMINE Technical Specification impacted including CONDITION, REQUIRED ACTION and COMPLETION TIME, if any.
DETERMINE ORAL and WRITTEN Reportability Requirements, if any.
Page 5 of 5 CPNPP NRC 2014 JPM SA1 Draft Submittal
AC Sources -- Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources -- Operating LCO 3.8.1 The following AC electrical sources shall be OPERABLE:
- a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System;
- b. Two diesel generators (DGs) capable of supplying the onsite Class 1E power distribution subsystem(s); and
- c. Automatic load sequencers for Train A and Train B.
APPLICABILITY: MODES 1, 2, 3, and 4
NOTE----------------------------------------------
One DG may be synchronized with the offsite power source under administrative controls for the purpose of surveillance testing.
COMANCHE PEAK - UNITS 1 AND 2 3.8-1 Amendment No. 150 CPNPP NRC 2014 JPM SA1 Answer Key 1 Draft Submittal
AC Sources -- Operating 3.8.1 ACTIONS
NOTE---------------------------------------------------------------
LCO 3.0.4.b is not applicable to DGs.
CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit A.1 Perform SR 3.8.1.1 for required 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. OPERABLE offsite circuit.
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 A.2 --------------------NOTE--------------------
In MODES 1, 2 and 3, the TDAFW pump is considered a required redundant feature.
Declare required feature(s) with no 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from discovery offsite power available inoperable of no offsite power to when its redundant required one train concurrent feature(s) is inoperable. with inoperability of redundant required feature(s)
AND A.3 Restore required offsite circuit to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.
OR 14 days for two one-time outages on XST1 to complete a plant modification to be completed by March 31, 2014.
COMANCHE PEAK - UNITS 1 AND 2 3.8-2 Amendment No. 150, 152, 160 CPNPP NRC 2014 JPM SA1 Answer Key 1 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA3 Task # SO1202C K/A # 2.2.12 3.7 / 4.1
Title:
Perform a Manual Quadrant Power Tilt Ratio Calculation & 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:
Unit 1 is operating at a steady-state condition of 100% power.
Rod Control is in AUTO with Control Bank D at 215 steps and all other rods at the FOP of 225 steps.
The Reactor Makeup System is aligned for AUTO operation with VCT level stable at 58%.
NIS Power Range Meters and Power Range Detector Current Meters currently read:
Channel Meter Upper Detector (A) Lower Detector (A)
NI-41 100.3% 163.67 167.30 NI-42 99.2% 191.36 182.35 NI-43 99.3% 158.84 157.25 NI-44 100.4% 182.05 179.11 Initiating Cue: The Unit Supervisor directs you to PERFORM the following:
CALCULATE a Quadrant Power Tilt Ratio per OPT-302, Calculating Power Tilt Ratio through Step 8.13.
RECORD data on OPT-302-1, Quadrant Power Tilt Ratio Data Sheet.
DOCUMENT Acceptance Criteria status for each Upper and Lower Power Range Instrument.
If required, DOCUMENT any notifications in the Comments Section.
If required, IDENTIFY any Technical Specification LCO CONDITION, REQUIRED ACTION, and COMPLETION TIME required within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and RECORD in Comments Section of surveillance.
Page 1 of 7 CPNPP NRC 2014 JPM SA3 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Task Standard: Utilizing OPT-302 and OPT-302-1, performed a Manual Quadrant Power Tilt Ratio Calculation and identified SAT Acceptance Criteria for NI-41, NI-42, NI-43 and identified UNSAT Acceptance Criteria for NI-44.
Utilizing Technical Specifications, recorded Technical Specification LCO 3.2.4 CONDITION, REQUIRED ACTION, and COMPLETION TIME in the Comments Section.
Required Materials: OPT-302, Calculating Power Tilt Ratio, Rev. 11-1.
OPT-302-1, Quadrant Power Tilt Ratio Data Sheet, Rev 8.
NUC-203-8, Normalized Power Range Excore Detector Currents for Cycle 17.
CPNPP Technical Specifications - Unit 1 and 2 through Amendment 160.
Validation Time: 25 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 2 of 7 CPNPP NRC 2014 JPM SA3 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:
PROVIDE the examinee with a copy of:
OPT-302, Calculating Power Tilt Ratio.
OPT-302-1, Quadrant Power Tilt Ratio Data Sheet.
NUC-203-8, Normalized Power Range Excore Detector Currents for Cycle 17.
Calculator.
Page 3 of 7 CPNPP NRC 2014 JPM SA3 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Examiner Note: The following steps are from OPT-302, Section 8.0.
Perform Step: 1 VERIFY Prerequisites in 6.0 are satisfied.
8.1 Standard
DETERMINED Prerequisites in 6.0 are satisfied.
Comment: SAT UNSAT Perform Step: 2 WHEN operating with an inoperable Power Range channel AND 8.2 Reactor Power 75% RTP, THEN the three operable channels shall be used for calculations to determine the QPTR.
Standard: DETERMINED all Power Range Channels OPERABLE.
Comment: SAT UNSAT Perform Step: 3 RECORD the following information onto Form OPT-302-1:
8.3 & 8.3.1 Unit, Cycle, Date, and Time, Standard: DETERMINED Unit, Cycle, Date, and Time already recorded.
Comment: SAT UNSAT Perform Step: 4 RECORD the following information onto Form OPT-302-1:
8.3 & 8.3.2 Power Range NIS power level for each channel (use one minute computer point averages (N6049A01, N6050A01, N6051A01, N6052A01) or NIS Panel).
Standard: RECORDED indication for NI-41, NI-42, NI-43, and NI-44 onto Form OPT-302-1.
Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2014 JPM SA3 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 5 RECORD the following information onto Form OPT-302-1:
8.3 & 8.3.3 Control rod bank positions from the step counters.
Standard: RECORDED Control rod bank positions from the Step Counters onto Form OPT-302-1.
Comment: SAT UNSAT Perform Step: 6 RECORD the following information onto Form OPT-302-1:
8.3 & 8.3.4 DETERMINE the average of the Power Range NIS Power levels recorded in Step 8.3.2.
Standard: CALCULATED average of operable NIS channels and RECORDED onto Form OPT-302-1.
Comment: SAT UNSAT Perform Step: 7 RECORD detector currents from DETECTOR A&B DETECTOR 8.4 CURRENT for each of the power range channels, N-41 through N-44.
Standard: RECORDED upper and lower detector currents for NI-41, NI-42, NI-43, and NI-44 onto Form OPT-302-1.
Comment: SAT UNSAT Examiner Note: NUC-203-8, Normalized Power Range Excore Detector Currents for Cycle 17 is included in the handout.
Perform Step: 8 RECORD 120% Power Normalized Excore Upper (Top) and Lower 8.5 (Bottom) Detector Currents from NUC-203-8, NORMALIZED POWER RANGE EXCORE DETECTOR CURRENTS located in "NUC FORMS" section of the Nuclear Design Report (NDR) for the current cycle.
Standard: RECORDED 120% Power Normalized Excore Upper (Top) and Lower (Bottom) Detector Currents from NUC-203-8 for Cycle 17 onto Form OPT-302-1.
Comment: SAT UNSAT Page 5 of 7 CPNPP NRC 2014 JPM SA3 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 9 DETERMINE the Actual Power Tilt Ratios by one of the following 8.6 & 1st bullet methods:
Manual calculations per QUADRANT POWER TILT RATIO DATA SHEET OPT-302-1.
Standard: PERFORMED manual calculations for NI-41, NI-42, NI-43 and NI-44 and RECORDED onto Form OPT-302-1.
Comment: SAT UNSAT Perform Step: 10 VERIFY the Power Tilt Ratio for each detector is LESS THAN OR 8.7 EQUAL TO 1.02.
IF any power tilt ratio exceeds 1.02, THEN immediately notify the Shift Manager AND reference Section 5.2.
Standard: DOCUMENTED notification of the Shift Manager in the Comments Section of OPT-302-1.
Comment: SAT UNSAT Examiner Note: The following is from Technical Specification LCO 3.2.4.
Perform Step: 11 RECORD any required Technical Specification CONDITION, REQUIRED ACTION, and COMPLETION TIME within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in the Comments Section of the Surveillance.
Standard: DETERMINED entry into Technical Specification LCO 3.2.4, Quadrant Power Tilt Ratio (QPTR) and RECORDED in the Comments Section of the Surveillance:
CONDITION A - QPTR not within limits; REQUIRED ACTION A.1 - Reduce THERMAL POWER 3%
from RTP for each 1% of QPTR > 1.00.
COMPLETION TIME - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after each QPTR determination AND REQUIRED ACTION A.2 - Determine QPTR.
COMPLETION TIME - Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 6 of 7 CPNPP NRC 2014 JPM SA3 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
Unit 1 is operating at a steady-state condition of 100%
power.
Rod Control is in AUTO with Control Bank D at 215 steps and all other rods at the FOP of 225 steps.
The Reactor Makeup System is aligned for AUTO operation with VCT level stable at 58%.
NIS Power Range Meters and Power Range Detector Current Meters currently read:
Channel Meter Upper Detector (A) Lower Detector (A)
NI-41 100.3% 163.67 167.30 NI-42 99.2% 191.36 182.35 NI-43 99.3% 158.84 157.25 NI-44 100.4% 182.05 179.11 INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:
CALCULATE a Quadrant Power Tilt Ratio per OPT-302, Calculating Power Tilt Ratio through Step 8.13.
RECORD data on OPT-302-1, Quadrant Power Tilt Ratio Data Sheet.
DOCUMENT Acceptance Criteria status for each Upper and Lower Power Range Instrument.
If required, DOCUMENT any notifications in the Comments Section.
If required, IDENTIFY any Technical Specification LCO CONDITION, REQUIRED ACTION, and COMPLETION TIME required within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and RECORD in Comments Section of surveillance.
Page 7 of 7 CPNPP NRC 2014 JPM SA3 Draft Submittal
QUADRANT POWER TILT RATIO DATA SHEET 8.3.1 UNIT: 1 CYCLE: 17 DATE: 06/09/14 TIME: 0800 POWER N-41A N-42A N-43A N-44A AVERAGE RANGE % % % % %
8.3.2 8.3.4 NIS 100.3 99.2 99.3 100.4 99.8 8.3.3 CONTROL ROD POSITION (steps)
SHUTDOWN BANKS: A1 225 B1 225 C 225 D 225 E 225 A2 225 B2 225 CONTROL BANKS: A1 225 B1 225 C1 225 D1 215 A2 225 B2 225 C2 225 D2 215 8.4 DATA [X] METERS SOURCE:
[ ] DVM - PERFORM Attachment 10.1 8.5 8.6 120%
NIS ACTUAL POWER NORMALIZED POWER RANGE DETECTOR CURRENT DETECTOR CURRENT CALIBRATED CHANNEL MICROAMPS MICROAMPS OUTPUT*
UPPER LOWER UPPER LOWER UPPER LOWER N-41B 163.67 167.30 178.47 181.01 0.917 0.924 N-42B 191.36 182.35 217.39 198.74 0.880 0.918 N-43B 158.84 157.25 179.29 176.12 0.886 0.893 N-44B 182.05 179.11 195.11 190.65 0.933 0.939
- CALIBRATED OUTPUT = ACTUAL CURRENT 8.6 SUM: 3.616 3.674 120% POWER NORMAL CURRENT 0.9185
8.6 AVERAGE
0.904 8.7 NIS ACTUAL POWER 8.6 POWER RANGE POWER TILT TILT RATIO ACCEPTANCE CRITERIA CHANNEL RATIO** LIMIT SATISFIED UPPER YES/NO INITIALS N-41B 1.014 1.02 YES N-42B 0.973 1.02 YES N-43B 0.980 1.02 YES N-44B 1.032 1.02 NO 8.6 LOWER N-41B 1.006 1.02 YES N-42B 0.999 1.02 YES N-43B 0.972 1.02 YES N-44B 1.022 1.02 NO
QUADRANT POWER TILT RATIO DATA SHEET DISCREPANCIES/COMMENTS:
NOTFIED the Shift Manager that NI-44 is UNSAT.
LCO 3.2.4, Quadrant Power Tilt Ratio (QPTR)
CONDITION A - QPTR not within limits.
REQUIRED ACTION A.1 - Reduce THERMAL POWER 3% from RTP for each 1% of QPTR > 1.00 COMPLETION TIME - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after each QPTR determination, AND REQUIRED ACTION A.2 - Determine QPTR.
COMPLETION TIME - Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
CORRECTIVE ACTIONS:
Performed By: Date Reviewed By: Date Unit Supervisor: Date Operations Management Review: Date:
OPT-302-1 REFERENCE USE PAGE 2 OF 2 CPNPP NRC 2014 JPM SA3 Answer Key Draft Submittal R-8
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA4 Task # SO1039C K/A # 2.3.6 2.0 / 3.8
Title:
Review a Gaseous Waste Release Permit 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 with Unit 1 in MODE 5:
A Plant Cooldown is in progress for Refueling.
Both Trains of Residual Heat Removal are in service.
XRE-5570A (PVF-684), Plant Vent Wide Range Gas Release Rate Monitor is out of service.
XRE-5701, Auxiliary Building Exhaust Monitor is out of service.
The Gas Decay Tanks are running out of space and a release of Gas Decay Tank X-02 is required to accommodate more gas.
Chemistry has just brought the Release Permit to the Control Room.
Initiating Cue: The Shift Manager directs you to PERFORM the following:
REVIEW the Gas Decay Tank Release Permit.
INDICATE and CIRCLE if Permit is Acceptable:
Permit is Acceptable? YES / NO If NO, then LIST reasons:
Page 1 of 6 CPNPP NRC 2014 JPM SA4 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Task Standard: Locate and correctly perform Critical Steps of STA-603.
Required Materials: STA-603, Control of Station Radioactive Effluents, Rev. 21-1.
STA-603-11, Gas Decay Tank Radioactive Effluent Release Data Sheet, Rev. 18.
CLI-744-4, Gas Decay Tank Release DRMS Setpoint Data Sheet, Rev. 1.
Validation Time: 15 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 2 of 6 CPNPP NRC 2014 JPM SA4 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 CLASSROOM SETUP EXAMINER:
PROVIDE the examinee with a copy of:
STA-603, Control of Station Radioactive Effluents.
INITIALED STA-603-11 up to Release Data section.
CLI-744, Attachment 4, Gas Decay Tank Release DRMS Setpoint Data Sheet COMPLETE except for setpoint restoration.
Page 3 of 6 CPNPP NRC 2014 JPM SA4 Draft Submittal
Appendix C JPM STEPS Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Perform Step: 1 Review STA-603-11, Gas Decay Tank Radioactive Effluent Release Data Sheet, Pre-Release Data.
Standard: REVIEW STA-603-11, Gas Decay Tank Radioactive Effluent Release Data Sheet, Pre-Release Data and IDENTIFY the following:
DETERMINED XRE-5570A (PVF-684), Plant Vent Wide Range Gas Release Rate Monitor is out of service with no documented LCOAR.
Comment: SAT UNSAT Perform Step: 2 Review STA-603-11, Gas Decay Tank Radioactive Effluent Release Data Sheet, Pre-Release Data.
Standard: REVIEW STA-603-11, Gas Decay Tank Radioactive Effluent Release Data Sheet, Pre-Release Data and IDENTIFY the following:
DETERMINED XRE-5570A (PVF-684), Plant Vent Wide Range Gas Release Rate Monitor and XRE-5701 (AVB-089) are out of service with no documented STA-603-13, Batch Radioactive Effluent Release Verification Sheet.
Comment: SAT UNSAT Perform Step: 3 Review STA-603-11, Gas Decay Tank Radioactive Effluent Release Data Sheet, Pre-Release Data.
Standard: REVIEW STA-603-11, Gas Decay Tank Radioactive Effluent Release Data Sheet, Pre-Release Data and IDENTIFY the following:
DETERMINED at least two independent samples shall be collected and analyzed with the plant vent stack and Auxiliary Building vent duct radiation monitors inoperable and only one sample was taken.
Comment: SAT UNSAT Page 4 of 6 CPNPP NRC 2014 JPM SA4 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 Determine if Gas Decay Tank Release Permit is acceptable.
Standard: DETERMINE Gas Decay Tank Release Permit is NOT acceptable and CIRCLE NO on JPM Cue Sheet.
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 5 of 6 CPNPP NRC 2014 JPM SA4 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions with Unit 1 in MODE 5:
A Plant Cooldown is in progress for Refueling.
Both Trains of Residual Heat Removal are in service.
XRE-5570A (PVF-684), Plant Vent Wide Range Gas Release Rate Monitor is out of service.
XRE-5701, Auxiliary Building Exhaust Monitor is out of service.
The Gas Decay Tanks are running out of space and a release of Gas Decay Tank X-02 is required to accommodate more gas.
Chemistry has just brought the Release Permit to the Control Room.
INITIATING CUE: The Shift Manager directs you to PERFORM the following:
REVIEW the Gas Decay Tank Release Permit.
INDICATE and CIRCLE if Permit is Acceptable:
Permit is Acceptable? YES / NO If NO, then LIST reasons:
Page 6 of 6 CPNPP NRC 2014 JPM SA4 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA5 Task # SO1136G 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:
ABN-907, Acts of Nature, Section 5.0, Severe Weather was implemented 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago.
A tornado has touched down in the Owner Controlled Area and passed through the Protected Area with winds in excess of 180 mph.
Unit 1 has tripped and is in MODE 3.
Both Unit 1 Emergency Diesel Generators are running and loaded.
Unit 2 is in MODE 5 at 120°F and rising.
Unit 2 Protected Train A Emergency Diesel Generator is running and loaded.
All Offsite Power sources are inoperable.
Unit 2 Station Service Water Pumps are tripped and damage has been reported to the Service Water Intake Structure.
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.
EAL Classification __________
Task Standard: Utilizing EPP-201, determined the Event Category and Event Classification using the Emergency Action Level Hot, Common, and Cold Classification Charts.
Required Materials: EPP-201, Assessment of Emergency Action Levels, Emergency Classification, and Plan Activation, Rev. 12.
EPP-201, Emergency Action Level Technical Bases Document, Rev. 0.
CPNPP Emergency Action Level Hot, Common, and Cold Classification Charts, Rev. 12.
Validation Time: 15 minutes Completion Time: ________ minutes Page 1 of 5 CPNPP NRC 2014 JPM SA5 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 2 of 5 CPNPP NRC 2014 JPM SA5 Draft Submittal
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.
EPP-201, Emergency Action Level Technical Bases Document.
CPNPP Emergency Action Level Hot, Common, & Cold Classification Charts.
Page 3 of 5 CPNPP NRC 2014 JPM SA5 Draft Submittal
Appendix C JPM STEPS Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Examiner Note: The following steps are from CPNPP Emergency Action Levels Common.
Perform Step: 1 DETERMINE the Event Category.
Standard: REFERRED to CPNPP Emergency Action Levels Hot, Common, and Cold and DETERMINED the following chart is applicable:
CPNPP EAL Common Conditions 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 Natural or Destructive Phenomena (1).
Comment: SAT UNSAT Perform Step: 4 Classify the event.
Standard: CLASSIFIED the event as an ALERT (HA1.2).
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 4 of 5 CPNPP NRC 2014 JPM SA5 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
ABN-907, Acts of Nature, Section 5.0, Severe Weather was implemented 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago.
A tornado has touched down in the Owner Controlled Area and passed through the Protected Area with winds in excess of 180 mph.
Unit 1 has tripped and is in MODE 3.
Both Unit 1 Emergency Diesel Generators are running and loaded.
Unit 2 is in MODE 5 at 120°F and rising.
Unit 2 Protected Train A Emergency Diesel Generator is running and loaded.
All Offsite Power sources are inoperable.
Unit 2 Station Service Water Pumps are tripped and damage has been reported to the Service Water Intake Structure.
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.
EAL Classification __________
Page 5 of 5 CPNPP NRC 2014 JPM SA5 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC P-1 Unit 1 Task # RO4217D K/A # G 2.4.35 3.8 / 4.0 SF-4S
Title:
Align Main Generator Vent and Purge 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 Loss of Onsite and Offsite Power has occurred on Unit 1.
ABN-601, Response to a 138/345 KV System Malfunction is in progress.
Initiating Cue: The Unit Supervisor directs you to PERFORM the following:
ALIGN Unit 1 Main Generator Vent and Purge per ABN-601, Response to a 138/345 KV System Malfunction, Attachment 11, Main Generator Hydrogen Vent and Argon Purge.
Task Standard: Utilizing ABN-601, aligned Unit 1 Main Generator Hydrogen Vent and Argon Purge and lowered hydrogen pressure to less than 1.5 psig.
Required Materials: ABN-601, Response to a 138/345 KV System Malfunction, Rev. 12-8.
Validation Time: 8 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 1 of 7 CPNPP NRC 2014 JPM P-1 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 PLANT SETUP EXAMINER:
PROVIDE the applicant with a copy of:
ABN-601, Response to a 138/345 KV System Malfunction.
Attachment 11, Main Generator Hydrogen Vent and Argon Purge.
EXAMINER NOTE:
This JPM MUST be performed on Unit 1.
Page 2 of 7 CPNPP NRC 2014 JPM P-1 Draft Submittal
Appendix C JPM STEPS Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Examiner Note: The following steps are from ABN-601, Attachment 11.
Examiner Note: Valves are located in the Turbine Building, Elev. 778', Room 1-005.
Examiner Cue: 1-ST11S523, is the Hydrogen Pressure Reducer Regulator in service.
Perform Step: 1 Close the hydrogen pressure reducer valves that are open.
st 1, 1.a, & 1 bullet u-ST11N523, Uu MN GEN GAS VLV RK H2 PRESS CTRL VLV:
1-ST11S538 U1 MN GEN GAS SYS H2 GAS PRESS CTRL VLV 523 OUT ISOL VLV [TB 778 Rm 1-005]
Standard: ROTATED 1-ST11S538, U1 MN GEN SYS H2 GAS PRESS CTRL VLV 523 OUT ISOL VLV handle 90° in COUNTERCLOCKWISE direction until STOPPED.
Examiner Cue: If valve handle is turned CLOCKWISE, REPORT valve handle does not move.
Examiner Cue: If valve handle is turned COUNTERCLOCKWISE, REPORT valve handle stops after 90°.
Comment: SAT UNSAT Perform Step: 2 Close the hydrogen pressure reducer valves that are open.
1, 1.a, & 2nd bullet u-ST11N523, Uu MN GEN GAS VLV RK H2 PRESS CTRL VLV:
1-ST11S531 U1 MN GEN GAS SYS H2 GAS PCV 523 IN ISOL VLV [TB 778 Rm 1-005]
Standard: ROTATED 1-ST11S531, U1 MN GEN GAS SYS H2 GAS PCV 523 IN ISOL VLV handle 90° in CLOCKWISE direction until STOPPED.
Examiner Cue: If valve handle is turned COUNTERCLOCKWISE, REPORT valve handle does not move.
Examiner Cue: If valve handle is turned CLOCKWISE, REPORT valve handle stops after 90°.
Comment: SAT UNSAT Page 3 of 7 CPNPP NRC 2014 JPM P-1 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 3 Close the hydrogen pressure reducer valves that are open.
1, 1.b, & 1st bullet u-ST11N524, Uu MN GEN GAS VLV RK H2 PRESS CTRL VLV:
1-ST11S539 U1 MN GEN GAS SYS H2 PRESS CTRL 524 OUT ISOL VLV [TB 778 Rm 1-005]
Standard: DETERMINED 1-ST11S539, U1 MN GEN GAS SYS H2 PRESS CTRL 524 OUT ISOL VLV NOT in service and N/Ad step.
Comment: SAT UNSAT Perform Step: 4 Close the hydrogen pressure reducer valves that are open.
1, 1.b, & 2nd bullet u-ST11N524, Uu MN GEN GAS VLV RK H2 PRESS CTRL VLV:
1-ST11S532 U1 MN GEN GAS SYS H2 GAS PRESS CTRL VLV 524 IN ISOL VLV [TB 778 Rm 1-005]
Standard: DETERMINED 1-ST11S532, U1 MN GEN GAS SYS H2 GAS PRESS CTRL VLV 524 IN ISOL VLV NOT in service and N/Ad step.
Comment: SAT UNSAT Examiner Cue: 1-ST11S520 red pointer is POINTING UP, parallel with pipe.
Perform Step: 5 Place 3-way valve u-ST11S520 to valve handle in the HORIZONTAL st 3 & 1 bullet position. (VALVE IS CLOSED):
1-ST11S520 U1 MN GEN RK ARGON 3-WAY ISOL CHNG OVR VLV 02 [TB 778 Rm 1-005]
Standard: ROTATED 1-ST11S520 U1 MN GEN RK ARGON 3-WAY ISOL CHNG OVR VLV 02 handle 90° in COUNTERCLOCKWISE direction and STOPPED handle in HORIZONTAL position.
Examiner Cue: If valve handle is turned CLOCKWISE, REPORT valve handle does not move.
Examiner Cue: If valve handle is turned COUNTERCLOCKWISE, REPORT valve handle stops after 90°.
Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2014 JPM P-1 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Examiner Cue: 1-ST11S516 red pointer is perpendicular with pipe. Valve handle is HORIZONTAL.
Perform Step: 6 ENSURE 3-way valve u-ST11S516 is in the valve handle UP position.
3 & 1st bullet 1-ST11S516 U1 MN GEN RK ARGON 3-WAY ISOL CHNG OVR VLV 01 [TB 778 Rm 1-005]
Standard: ROTATED 1-ST11S516 U1 MN GEN RK ARGON 3-WAY ISOL CHNG OVR VLV 01 handle 90° in COUNTERCLOCKWISE direction and STOPPED handle in VERTICAL or UP position.
Examiner Cue: If valve handle is turned CLOCKWISE, REPORT valve handle does not move.
Examiner Cue: If valve handle is turned COUNTERCLOCKWISE, REPORT valve handle stops after 90°.
Comment: SAT UNSAT Perform Step: 7 Lower hydrogen pressure to approximately 1.5 psig by performing the 3 & 1ST bullet following for the affected unit:
UNLOCK AND OPEN 1-ST11S600, UNIT 1 MAIN GEN HYDROGEN RACK GENERATOR DRAIN PIPE ISOL VALVE (U2 TB 778 - H2 RACK)
Standard: PERFORMED the following:
CUT and REMOVED green locking tab.
ROTATED 1-ST11S600, UNIT 1 MAIN GEN HYDROGEN RACK GENERATOR DRAIN PIPE ISOL VALVE in COUNTERCLOCKWISE direction until STOPPED and handle is PARALLEL with pipe.
OBSERVED 1-ST11P505, U1 MAIN GENERATOR GAS SYSTEM GENERATOR CASING PRESSURE INDICATOR 505 pressure LOWERING.
Examiner Cue: Valve handle is parallel with pipe.
When located, REPORT Indicator 505 is reading 1.5 psig.
Comment: SAT UNSAT Page 5 of 7 CPNPP NRC 2014 JPM P-1 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 WHEN hydrogen pressure reaches approximately 1.5 psig, THEN 4 & 1st bullet perform the following for the affected unit:
CLOSE AND LOCK 1-ST11S600, UNIT 1 MAIN GEN HYDROGEN RACK GENERATOR DRAIN PIPE ISOL VALVE Standard: PERFORMED the following:
OBSERVED 1-ST11P505, U1 MAIN GENERATOR GAS SYSTEM GENERATOR CASING PRESSURE INDICATOR 505 pressure LESS THAN 1.5 psig.
ROTATED 1-ST11S600, UNIT 1 MAIN GEN HYDROGEN RACK GENERATOR DRAIN PIPE ISOL VALVE in CLOCKWISE direction until STOPPED and handle is PERPENDICULAR with pipe.
Terminating Cue: Valve handle is in horizontal position. Green locking tab will be installed by another operator. This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 6 of 7 CPNPP NRC 2014 JPM P-1 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
A Loss of Onsite and Offsite Power has occurred on Unit 1.
ABN-601, Response to a 138/345 KV System Malfunction is in progress.
INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:
ALIGN Unit 1 Main Generator Vent and Purge per ABN-601, Response to a 138/345 KV System Malfunction, Attachment 11, Main Generator Hydrogen Vent and Argon Purge.
Page 7 of 7 CPNPP NRC 2014 JPM P-1 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC P-2 Task # RO2119A K/A # 069.AA1.01 3.5 / 3.7 SF-5
Title:
Perform Containment Phase A Local Isolation 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 experienced a Reactor Trip and Safety Injection.
During performance of EOP-0.0A, Reactor Trip or Safety Injection, Attachment 2, the following valve indications were not correct for the current plant conditions:
1-MLB-1A2/2.1 HV-4166, PRZR LIQ SPACE SMPL LINE IRC ISO VLV.
1-MLB-1A2/3.2 HV-4173, ACCUM 3 LIQ SPACE SMPL LINE IRC ISO VLV.
CB 1-HV-2407, STM GEN 3 SMPL LINE ORC ISO VLV.
Initiating Cue: The Unit Supervisor directs you to PERFORM the following:
CLOSE 1-HV-4166, 1-HV-4173, and 1-HV-2407 locally using EOP-0.0A, Reactor Trip or Safety Injection, Attachment 4, Phase A Isolation.
Task Standard: Utilizing EOP-0.0A Attachment 4, Phase A Isolation CLOSED 1-HV-4166, 1-HV-4173, and 1-HV-2407.
Required Materials: EOP-0.0A, Reactor Trip or Safety Injection, Rev. 8-9.
Validation Time: 4 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 1 of 4 CPNPP NRC 2014 JPM P-2 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 PLANT SETUP EXAMINER:
PROVIDE the applicant with the following:
EOP-0.0A, Reactor Trip or Safety Injection.
Attachment 4, Phase A Isolation.
Page 2 of 4 CPNPP NRC 2014 JPM P-2 Draft Submittal
Appendix C JPM STEPS Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Examiner Note: The following steps are from EOP-0.0A, Attachment 4 and may be performed in any order.
Examiner Note: All valves are located at LV-08, Sample Valve Control Panel, in the Safeguards Building, Elev. 810' near the Penetration Rooms.
Examiner Cue: 1-HS-4166 red light is LIT and green light is DARK.
Perform Step: 1 CLOSE 1-HS-4166 PRZR LIQ SPACE SMPL LINE IRC ISO VLV.
Page 4, Item 1 Standard: PLACED 1-HS-4166 PRZR LIQ SPACE SMPL LINE IRC ISO VLV in the CLOSE position.
Examiner Cue: 1-HS-4166 red light is DARK and green light is LIT.
Comment: SAT UNSAT Examiner Cue: 1-HS-4173 red light is LIT and green light is DARK.
Perform Step: 2 CLOSE 1-HS-4173 ACCUM 3 LIQ SPACE SMPL LINE IRC ISO VLV.
Page 4, Item 7 Standard: PLACED 1-HS-4173 ACCUM 3 LIQ SPACE SMPL LINE IRC ISO VLV in the CLOSE position.
Examiner Cue: 1-HS-4173 red light is DARK and green light is LIT.
Comment: SAT UNSAT Examiner Cue: 1-HS-2407 red light is LIT and green light is DARK.
Perform Step: 3 CLOSE 1-HS-2407 STM GEN 3 SMPL LINE ORC ISO VLV.
Page 6, Item 11 Standard: PLACED 1-HS-2407 STM GEN 3 SMPL LINE ORC ISO VLV in the CLOSE position.
Terminating Cue: 1-HS-2407 red light is DARK and green light is LIT.
This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 3 of 4 CPNPP NRC 2014 JPM P-2 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
Unit 1 has experienced a Reactor Trip and Safety Injection.
During performance of EOP-0.0A, Reactor Trip or Safety Injection, Attachment 2, the following valve indications were not correct for the current plant conditions:
1-MLB-1A2/2.1 HV-4166, PRZR LIQ SPACE SMPL LINE IRC ISO VLV.
1-MLB-1A2/3.2 HV-4173, ACCUM 3 LIQ SPACE SMPL LINE IRC ISO VLV.
CB 1-HV-2407, STM GEN 3 SMPL LINE ORC ISO VLV.
INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:
CLOSE 1-HV-4166, 1-HV-4173 and 1-HV-2407 locally using EOP-0.0A, Reactor Trip or Safety Injection, Attachment 4, Phase A Isolation.
Page 4 of 4 CPNPP NRC 2014 JPM P-2 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC P-3 Task # RO4006 K/A # 060.AA2.06 3.6 / 3.8 SF-9
Title:
Terminate Release of Radioactive Gas 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 Gaseous Decay Tank X-01 release is in progress to the Ventilation System.
Initiating Cue: The Unit Supervisor directs you to PERFORM the following:
TERMINATE the release in accordance with RWS-201, Gaseous Waste Processing System, Section 5.4.5, Gas Decay Tank X-01 Discharge to the Ventilation System.
When tank pressure is less than 5 psig, PERFORM Step 5.4.5.N.
Task Standard: Utilizing RWS-201, repositioned Waste Gas Discharge Pressure Controller to 0%,
closed the Waste Gas Discharge Control Valve, and closed Plant Ventilation Exhaust Plenum Supply to terminate Gaseous Decay Tank X-01 release.
Required Materials: RWS-201, Gaseous Waste Processing System, Rev. 19-7.
Validation Time: 10 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 1 of 5 CPNPP NRC 2014 JPM P-3 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 PLANT SETUP EXAMINER:
PROVIDE the applicant with a copy of:
RWS-201, Gaseous Waste Processing System.
Section 5.4.5, Gas Decay Tank X-01 Discharge to the Ventilation System.
INITIALED and N/Ad to Step 5.4.5.N.
Page 2 of 5 CPNPP NRC 2014 JPM P-3 Draft Submittal
Appendix C JPM STEPS Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Examiner Note: The following steps are from RWS-201, Step 5.4.5.N.
Examiner Note: Pressure gauge and Controller are located in the Auxiliary Building, Elev. 862', Room X-243 on the Waste Gas Process Panel.
Examiner Cue: When X-01 pressure gauge is located, REPORT gauge is in Mode A, Low Range reading 5 psig.
Perform Step: 1 WHEN the pressure in the GDT being discharged reaches the pressure 5.4.5.N & 5.4.5.N.1) specified in the release permit, THEN terminate the release as follows:
Set X-HC-0014, GWPS WASTE GAS DISCHARGE PRESSURE CONTROLLER to 0%.
Standard: OBSERVED X-PIS-1036, GWPS Gas Decay Tank X-01 Pressure Indicating Switch at 5 psig and ROTATED knob on X-HC-0014, GWPS WASTE GAS DISCHARGE PRESSURE CONTROLLER in COUNTERCLOCKWISE direction to 0% position.
Examiner Cue: Controller indicates 0%.
Comment: SAT UNSAT Examiner Note: Valve handswitch is located on the Waste Gas Process Panel.
Perform Step: 2 WHEN the pressure in the GDT being discharged reaches the pressure 5.4.5.N & 5.4.5.N.2) specified in the release permit, THEN terminate the release as follows:
CLOSE X-HS-0014, WASTE GAS DISCHARGE CONTROL VALVE.
Standard: PERFORMED the following:
PLACED X-HS-0014, WASTE GAS DISCHARGE CONTROL VALVE in CLOSE (critical).
OBSERVED green CLOSE light LIT (NOT critical).
Examiner Cue: The green light is LIT and the red light is DARK.
Comment: SAT UNSAT Page 3 of 5 CPNPP NRC 2014 JPM P-3 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Examiner Note: Remote operator is located in Rm. X-243 on floor against wall to the right of Waste Gas Process Panel (behind X-RE-5250, Radiation Monitor).
Examiner Cue: When white cover is removed, REPORT pin is at top of indicator.
Perform Step: 3 WHEN the pressure in the GDT being discharged reaches the pressure 5.4.5.N & 5.4.5.N.3) specified in the release permit, THEN terminate the release as follows:
CLOSE XGH-7898-RO, GWPS H2/N2 TO PLT VENT EXH PLNM SPLY DNSTR ISOL VLV RMT OPER Standard: REMOVED white cover and INSTALLED reach rod and ROTATED XGH-7898-RO, GWPS H2/N2 TO PLT VENT EXH PLNM SPLY DNSTR ISOL VLV RMT OPER in CLOCKWISE direction until STOPPED.
Examiner Cue: REPORT that remote operator has stopped turning and position indicator is all the way down.
Comment: SAT UNSAT Perform Step: 4 WHEN the pressure in the GDT being discharged reaches the pressure 5.4.5.N & 5.4.5.N.4) specified in the release permit, THEN terminate the release as follows:
Inform the Control Room AND Radiation Protection that the release is completed.
Standard: INFORMED the Control Room AND Radiation Protection that the Gaseous Waste Release has been terminated.
Terminating Cue: The Control Room and Radiation Protection have been notified.
This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 4 of 5 CPNPP NRC 2014 JPM P-3 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
A Gaseous Decay Tank X-01 release is in progress to the Ventilation System.
INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:
TERMINATE the release in accordance with RWS-201, Gaseous Waste Processing System, Section 5.4.5, Gas Decay Tank X-01 Discharge to the Ventilation System.
When tank pressure is less than 5 psig, PERFORM Step 5.4.5.N.
Page 5 of 5 CPNPP NRC 2014 JPM P-3 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-1 Task # RO1026A K/A # 001.A2.11 4.4 / 4.7 SF-1
Title:
Respond to Reactor Startup Continuous Control Rod Insertion 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:
A Plant Startup from Hot Standby is in progress in accordance with IPO-002A, Plant Startup from Hot Standby.
Unit 1 Reactor power is at 1x10-8 amps.
Control Bank D is at 100 steps.
Initiating Cue: The Unit Supervisor directs you to PERFORM the following:
RAISE Reactor Power to approximately 2% per IPO-002A, Plant Startup from Hot Standby, Section 5.4, Increasing Reactor Power to Approximately 2% Following Reactor Startup And Establishing Main Feedwater Flow to the SGs.
Task Standard: Utilizing IPO-002A, withdrew Control Rods, established a positive startup rate less than 1.0 dpm to raise Reactor power and responded per ABN-712 to a Continuous Rod Insertion whenever Control Rods were required to be inserted, then tripped the Reactor by deenergizing the Control Rod Drive Motor Generator sets per ABN-712 and EOP-0.0A.
Required Materials: IPO-002A, Plant Startup From Hot Standby, Rev. 20-24.
ABN-712, Rod Control System Malfunction, Rev. 10-14.
EOP-0.0A, Reactor Trip or Safety Injection, Rev. 8-9.
Validation Time: 12 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 1 of 8 CPNPP NRC 2014 JPM S-1 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:
INITIALIZE to IC-8 or any low power Initial Condition and LOAD Scenario File LC22 NRC JPM S1 or PERFORM the following:
EXECUTE the following malfunctions:
RP01, Automatic Reactor Trip Failure.
RP13C, Manual Reactor Trip Failure (CB07 & CB10 switches).
RD02D, Control Bank D Continuous Rod Insertion (Conditional: When 1/1-FLRM, CONTROL ROD MOTION CTRL is placed in the IN position following rod withdrawal to raise power).
PLACE GTGC MODE 2 on front Plant Computer Screen.
EXAMINER:
PROVIDE the applicant with a copy of:
IPO-002, Plant Startup From Hot Standby.
Section 5.4, Increasing Reactor Power to Approximately 2% Following Reactor Startup And Establishing Main Feedwater Flow to the SGs.
When referenced, PROVIDE the applicant with a copy of:
ABN-712, Rod Control System Malfunction.
Page 2 of 8 CPNPP NRC 2014 JPM S-1 Draft Submittal
Appendix C JPM STEPS Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Examiner Note: The following steps are from IPO-002A, Step 5.4.1.
Perform Step: 1 IF the Main Steam Isolation Valves are closed, THEN perform the 5.4.1.A following:
Standard: DETERMINED Main Steam Isolation Valves are OPEN and N/Ad Step 5.4.1.A.
Comment: SAT UNSAT Perform Step: 2 Establish a startup rate of approximately 0.5 dpm to increase Reactor 5.4.1.B power to approximately 2%.
Standard: PLACED 1/1-FLRM, Control Rod Motion Control Switch to the OUT position and WITHDREW Control Bank D rods to establish positive startup rate of less than 1.0 dpm.
Comment: SAT UNSAT Page 3 of 8 CPNPP NRC 2014 JPM S-1 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Examiner Note: When Control Rods are inserted to establish a 0.2 dpm startup rate or any Rod insertion using 1/1-FLRM, Control Rod Motion Control Switch will result in a Continuous Rod Insertion.
Perform Step: 3 Gradually reduce startup rate to attain approximately 0.2 dpm as the 5.4.1.C Intermediate Range channels approach 3x10-6 amps.
Standard: PLACED 1/1-FLRM, Control Rod Motion Control Switch to the IN position and DROVE Control Bank D rods to establish a 0.2 dpm startup rate.
Comment: SAT UNSAT Examiner Note: Entry into ABN-712, Rod Control System Malfunction, or EOP-0.0A, Reactor Trip or Safety Injection, should be implemented.
Examiner Note: The following steps are from ABN-712, Step 2.3.1.
Perform Step: 4 Verify Turbine Runback OR Load Rejection - NOT IN PROGRESS.
2.3.1 & bullets TG Display GEN MEGAWATTS GEN MEGAVARS Standard: VERIFIED Turbine Runback OR Load Rejection is NOT in progress.
Comment: SAT UNSAT N/A Page 4 of 8 CPNPP NRC 2014 JPM S-1 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Verify Rod Motion - NORMAL 2.3.2 Rod direction Rod speed Rod demand Rod sequencing Bank overlap Rod alignment (+/-12 steps)
Standard: DETERMINED Rod Motion is NOT NORMAL.
Comment: SAT UNSAT N/A Perform Step: 6 Ensure 1/u-RBSS, CONTROL ROD BANK SELECT - NOT IN AUTO 2.3.2 RNO a.
Standard: VERIFIED 1/1-RBSS, CONTROL ROD BANK SELECT in MANUAL.
Comment: SAT UNSAT N/A Examiner Note: The following steps represent the Alternate Path for this JPM.
Examiner Note: The following steps are from EOP-0.0A and are performed from memory.
Perform Step: 7 IF any of following occurs, THEN trip Reactor AND GO TO 2.3.2 RNO b. EOP-0.0A/B while other operators continue this procedure:
Rod motion with NO demand.
Standard: At CB-07, PLACED 1/1-RTC, RX TRIP BKR Switch in TRIP and DETERMINED Reactor is NOT tripped.
Comment: SAT UNSAT Perform Step: 8 IF any of following occurs, THEN trip Reactor AND GO TO 2.3.2 RNO b. EOP-0.0A/B while other operators continue this procedure:
Rod motion with NO demand.
Standard: At CB-10, PLACED 1/1-RT, RX TRIP Switch in TRIP and DETERMINED Reactor is NOT tripped.
Comment: SAT UNSAT Page 5 of 8 CPNPP NRC 2014 JPM S-1 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 IF any of following occurs, THEN trip Reactor AND GO TO 2.3.2 RNO b. EOP-0.0A/B while other operators continue this procedure:
Rod motion with NO demand.
Standard: PERFORMED the following:
OPENED CS-1B3-1, INCOMING BREAKER 1B3-1 and CS-1B4-1, INCOMING BREAKER 1B4-1 (critical).
OBSERVED green TRIP lights LIT (NOT critical).
Comment: SAT UNSAT Perform Step: 10 IF any of following occurs, THEN trip Reactor AND GO TO 2.3.2 RNO b. EOP-0.0A/B while other operators continue this procedure:
Rod motion with NO demand.
Standard: PERFORMED the following:
CLOSED CS-1B3-1, INCOMING BREAKER 1B3-1 and CS-1B4-1, INCOMING BREAKER 1B4-1 (critical).
OBSERVED red CLOSE lights LIT (NOT critical).
Comment: SAT UNSAT Perform Step: 11 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 red CLOSED lights LIT.
Comment: SAT UNSAT Perform Step: 12 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 Page 6 of 8 CPNPP NRC 2014 JPM S-1 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 13 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 7 of 8 CPNPP NRC 2014 JPM S-1 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
A Plant Startup from Hot Standby is in progress in accordance with IPO-002A, Plant Startup from Hot Standby.
Unit 1 Reactor power is at 1x10-8 amps.
Control Bank D is at 100 steps.
INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:
RAISE Reactor Power to approximately 2% per IPO-002A, Plant Startup from Hot Standby, Section 5.4, Increasing Reactor Power to Approximately 2%
Following Reactor Startup And Establishing Main Feedwater Flow to the SGs.
Page 8 of 8 CPNPP NRC 2014 JPM S-1 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-2 Task # RO1309A K/A # 004.A2.19 3.1 / 2.8 SF-2
Title:
Lower Letdown Flow and Adjust Charging Flow 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 at 100% power.
Letdown flow is 120 gpm.
Radiation Protection and Chemistry have both been notified of a Letdown flow change.
Initiating Cue: The Unit Supervisor directs you to PERFORM the following:
LOWER Letdown flow from 120 gpm to 75 gpm per SOP-103A, Chemical and Volume Control System, Section 5.2.4, Lowering/Securing Letdown Flow.
ADJUST Charging flow as required per SOP-103A, Chemical and Volume Control System, Section 5.2.2, Raising/Lowering Charging with a CCP in Operation.
Task Standard: Utilizing SOP-103A, lowered Letdown flow from 130 gpm to 80 gpm and adjusted Charging flow to maintain Pressurizer Level of 60%.
Required Materials: SOP-103A, Chemical and Volume Control System, Rev. 18-4.
Validation Time: 8 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 1 of 7 CPNPP NRC 2014 JPM S-2 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:
INITIALIZE to IC-18 or any at power Initial Condition and LOAD Scenario File LC22 NRC JPM S2 & S7 and PERFORM the following:
VERIFY Letdown flow is 130 gpm (as read).
EXAMINER:
PROVIDE the applicant with a copy of:
SOP-103A, Chemical and Volume Control System.
Section 5.2.4, Lowering/Securing Letdown Flow.
Section 5.2.2, Raising/Lowering Charging with a CCP in Operation.
Page 2 of 7 CPNPP NRC 2014 JPM S-2 Draft Submittal
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 5.2.4.
Perform Step: 1 NOTIFY Radiation Protection of letdown flow change.
5.2.4.A Standard: DETERMINED Radiation Protection has been NOTIFIED per Initial Conditions.
Comment: SAT UNSAT Perform Step: 2 NOTIFY Chemistry of letdown flow change so Chemistry can ensure the 5.2.4.B sample flow to the RCS on-line dissolved oxygen and hydrogen analyzer is adjusted to avoid damaging the instrument or the associated components.
Standard: DETERMINED Chemistry has been NOTIFIED per Initial Conditions.
Comment: SAT UNSAT Perform Step: 3 CYCLE Pressurizer Heaters as needed prior to or during subsequent 5.2.4.C steps to maintain desired RCS pressure.
Standard: DETERMINED Pressurizer Heaters will be CYCLED as required.
Comment: SAT UNSAT Perform Step: 4 ENSURE 1-PK-131, LTDN HX OUT PRESS CTRL in AUTO.
5.2.4.D Standard: VERIFIED 1-PK-131, LTDN HX OUT PRESS CTRL white AUTO light LIT.
Comment: SAT UNSAT Page 3 of 7 CPNPP NRC 2014 JPM S-2 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 CLOSE the desired orifice valve(s) to lower letdown flow.
5.2.4.E & 1st bullet 1/1-8149A, LTDN ORIFICE ISOL VLV (45 gpm)
Standard: PERFORMED the following:
CLOSED 1/1-8149A, LTDN ORIFICE ISOL VLV (45 gpm)
(critical).
OBSERVED green CLOSE light LIT and Letdown flow LOWERED to approximately 80 gpm on 1-FI-132, LTDN FLO (NOT critical).
Comment: SAT UNSAT Examiner Note: The candidate may take manual control of 1-PK-131 and then return to AUTO.
Perform Step: 6 ENSURE 1-PK-131, LTDN HX OUT PRESS CTRL, is restoring pressure 5.2.4.F to approximately 310 psig on 1-PI-131, LTDN HX OUT PRESS.
Standard: VERIFIED 1-PK-131, LTDN HX OUT PRESS CTRL, is restoring pressure to approximately 310 psig on 1-PI-131, LTDN HX OUT PRESS.
Comment: SAT UNSAT Perform Step: 7 ENSURE 1-TK-130, LTDN HX OUT TEMP CTRL, is maintaining 5.2.4.G approximately 95°F on 1-TI-130, LTDN HX OUT TEMP.
Standard: VERIFIED 1-TK-130, LTDN HX OUT TEMP CTRL, is maintaining approximately 95°F on 1-TI-130, LTDN HX OUT TEMP Comment: SAT UNSAT Perform Step: 8 ADJUST charging as required per Section 5.2.1 or 5.2.2.
5.2.4.H Standard: REFERRED to SOP-103A, Section 5.2.2, Raising/Lowering Charging with a CCP in operation.
Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2014 JPM S-2 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following steps are from SOP-103A, Section 5.2.2.
Examiner Note: Step 5.2.2.A can be performed in either of the 2 ways listed.
Perform Step: 9a IF necessary, PLACE the following controller(s) in MANUAL AND RAISE 5.2.2.A & 1st bullet or LOWER to achieve the desired flow on 1-FI-121A, CHRG FLO.
1-FK-121, CCP CHRG FLO CTRL Standard: PLACED 1-FK-121, CCP FLO CTRL in MANUAL and LOWERED to MATCH 1-FI-121A, CHRG FLO with 1-FI-132, LTDN FLO.
Comment: SAT UNSAT Perform Step: 9b IF necessary, PLACE the following controller(s) in MANUAL AND RAISE nd 5.2.2.A & 2 bullet or LOWER to achieve the desired flow on 1-FI-121A, CHRG FLO.
1-LK-459, PRZR LVL CTRL Standard: PLACED 1-LK-459, PRZR LVL CTRL in MANUAL and LOWERED to MATCH 1-FI-121A, CHRG FLO with 1-FI-132, LTDN FLO.
Comment: SAT UNSAT Perform Step: 10 ADJUST 1-HC-182, RCP SEAL WTR PRESS CTRL, as needed to 5.2.2.B maintain 8 gpm seal injection flow to each RCP No. 1 seal as charging flow is changed.
Standard: ADJUSTED 1-HC-182, RCP SEAL WTR PRESS CTRL and MAINTAINED 8 gpm seal injection flow to each RCP No. 1 seal.
Comment: SAT UNSAT Page 5 of 7 CPNPP NRC 2014 JPM S-2 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Examiner Note: Step 5.2.2.C can be performed in either of the 2 ways listed.
Perform Step: 11a IF placed in manual in step 5.2.2.A, THEN PERFORM the following for st 5.2.2.C & 1 bullet the selected controller:
WHEN pressurizer program level is established, THEN PLACE 1-FK-121, CCP CHRG FLO CTRL, in AUTO.
Standard: When Pressurizer level is approximately 60%, PLACED 1-FK-121, CCP FLO CTRL in AUTO and OBSERVED white AUTO light LIT.
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT Perform Step: 11b IF placed in manual in step 5.2.2.A, THEN PERFORM the following for 5.2.2.C & 2nd bullet the selected controller:
WHEN pressurizer program level is established, THEN PLACE 1-LK-459, PRZR LVL CTRL, in AUTO.
Standard: When Pressurizer level is approximately 60%, PLACED 1-LK-459, PRZR LVL CTRL in AUTO and OBSERVED white AUTO light LIT.
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 6 of 7 CPNPP NRC 2014 JPM S-2 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
Unit 1 is at 100% power.
Letdown flow is 120 gpm.
Radiation Protection and Chemistry have both been notified of a Letdown flow change.
INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:
LOWER Letdown flow from 120 gpm to 75 gpm per SOP-103A, Chemical and Volume Control System, Section 5.2.4, Lowering/Securing Letdown Flow.
ADJUST Charging flow as required per SOP-103A, Chemical and Volume Control System, Section 5.2.2, Raising/Lowering Charging with a CCP in Operation.
Page 7 of 7 CPNPP NRC 2014 JPM S-2 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-3 Task # RO1222 K/A # 010.A2.02 3.9 / 3.9 SF-3
Title:
Respond to Pressurizer Spray Valve Failure 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 at 100% power.
1-PCV-455C, Loop 4 Pressurizer Spray Valve has failed partially open.
Initiating Cue: The Unit Supervisor directs you to PERFORM the following:
PERFORM actions of ABN-705, Pressurizer Pressure Malfunction, Section 3.0, Pressurizer Spray Valve Failure.
Task Standard: Utilizing ABN-705, performed actions for a failed open Pressurizer Spray Valve, tripped the Reactor when the valve fails to close, and stopped Reactor Coolant Pump 1-04.
Required Materials: ABN-705, Pressurizer Pressure Malfunction, Rev. 12-2.
Validation Time: 5 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 1 of 5 CPNPP NRC 2014 JPM S-3 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:
INITIALIZE to IC-32 or any at power Initial Condition and LOAD Scenario File LC22 NRC JPM S3 or PERFORM the following:
ADJUST all RCP Seal Injection flows to ~ 10 gpm to preclude CHG FLO HI / LO alarm.
EXECUTE malfunction RX15B, Pressurizer Spray Valve [PCV-455C] failure to 60%
open.
FREEZE the Simulator.
EXAMINER:
PROVIDE the applicant with a copy of:
ABN-705, Pressurizer Pressure Malfunction.
Section 3.0, Pressurizer Spray Valve Failure.
Page 2 of 5 CPNPP NRC 2014 JPM S-3 Draft Submittal
Appendix C JPM STEPS Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Booth Operator: When examinee is ready to begin, PLACE the Simulator in RUN.
Examiner Note: The following steps are from ABN-705, Section 3.0.
Perform Step: 1 CLOSE Pressurizer Spray Valve(s).
3.3.1 & 2nd bullet 1-PK-455C, RC LOOP 4 PRZR SPR VLV CTRL Standard: DEPRESSED 1-PK-455C, RC LOOP 4 PRZR SPR VLV CTRL amber MAN pushbutton and green OUTPUT () pushbutton to CLOSE valve and DETERMINED Loop 1 Pressurizer Spray Valve is OPEN.
Examiner Note: Examinee may energize Group D Pressurizer Heaters.
Comment: Step SAT UNSAT Examiner Note: The following steps represent the Alternate Path of this JPM.
Perform Step: 2 IF Pressurizer pressure is decreasing in an uncontrolled manner, THEN 3.3.1.a RNO perform the following:
Standard: OBSERVED RCS pressure indications 1-PI-455A (456/457/458), PRZR PRESS CHAN I (II/III/IV) AND/OR 1-PR-455, PRZR PRESS and DETERMINED Pressurizer pressure is decreasing in an uncontrolled manner.
Comment: SAT UNSAT Perform Step: 3 IF Pressurizer pressure is decreasing in an uncontrolled manner, THEN 3.3.1.a RNO & perform the following:
3.3.1.a.1) RNO Trip the Reactor.
Standard: PERFORMED the following:
PLACED 1/1-RTC, RX TRIP BKR switch in TRIP (critical).
OBSERVED 1/1-RTBAL, RX TRIP BKR green light LIT.
(NOT critical).
OBSERVED 1/1-RTBAL, RX TRIP BKR green light LIT.
(NOT critical).
Examiner Cue: Another operator will perform immediate actions of EOP-0.0A, Reactor Trip or Safety Injection; CONTINUE with ABN-705 actions.
Comment: SAT UNSAT Page 3 of 5 CPNPP NRC 2014 JPM S-3 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Examiner Note: Reactor Coolant Pumps 1 and 4 may both be tripped.
Perform Step: 4 IF Pressurizer pressure is decreasing in an uncontrolled manner, THEN 3.3.1.a RNO & perform the following:
3.3.1.a.2) RNO STOP RCP(s) as necessary to stop spray flow.
Standard: PERFORMED the following:
PLACED 1/1-PCPX4, RCP 4 in STOP (critical).
OBSERVED green STOP light LIT (NOT critical).
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 4 of 5 CPNPP NRC 2014 JPM S-3 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
Unit 1 is in MODE 1 at 100% power.
1-PCV-455C, Loop 4 Pressurizer Spray Valve has failed partially open.
INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:
PERFORM actions of ABN-705, Pressurizer Pressure Malfunction, Section 3.0, Pressurizer Spray Valve Failure.
Page 5 of 5 CPNPP NRC 2014 JPM S-3 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-4 Task # RO1413C K/A # 005.A4.01 3.6 / 3.4 SF-4P
Title:
Recognize and Respond to Residual Heat Removal Pump Cavitation 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 5 with the RCS NOT Filled.
Train A Residual Heat Removal System was in service.
Train A Residual Heat Removal Pump has just tripped.
Train B Residual Heat Removal System is aligned for standby per SOP-102A, Residual Heat Removal System, Section 5.3.
Initiating Cue: The Unit Supervisor directs you to PERFORM the following:
RESPOND to a loss of the Residual Heat Removal System per ABN-104, Residual Heat Removal System Malfunction, Section 7.0, Mode 5 or 6 Erratic RHR Pump Parameters/Loss of Flow Control/RHR Pump Trip-RCS NOT Filled.
Task Standard: Utilizing ABN-104, aligned and started Train B Residual Heat Removal (RHR)
Pump, throttled open Train B Heat Exchanger Flow Control Valve, and aligned RHR Heat Exchanger Component Cooling Water flow.
Required Materials: ABN-104, Residual Heat Removal System Malfunction, Rev. 9.
Validation Time: 15 minutes Completion Time: ________minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 1 of 8 CPNPP NRC 2014 JPM S-4 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:
INITIALIZE to IC-35 and PERFORM the following:
EXECUTE the following malfunction:
RH01A, RHR PUMP 1-01 in TRIP.
ALIGN the following valve:
1-HS-4573, Train B RHR Heat Exchanger Return Valve to CLOSE.
HANG yellow CAUTION tags on the following valves:
1/1-8701B, RHR HL Suction ISO VLV Power Source.
1/1-8702A, RHR HL Suction ISO VLV Power Source.
REMOVE Job Aid Tags (white rings) on the following valves:
1/1-8701A, RHR HL Suction ISO VLV Power Source 1/1-8701B, RHR HL Suction ISO VLV Power Source.
1/1-8702A, RHR HL Suction ISO VLV Power Source.
1/1-8702B, RHR HL Suction ISO VLV Power Source.
PLACE RHR screen on RO Desk Monitor.
FREEZE the Simulator.
When examinee is ready to begin, PLACE Simulator in RUN.
EXAMINER:
PROVIDE the applicant with a copy of:
ABN-104, Residual Heat Removal System Malfunction.
Section 7.0, Mode 5 or 6 Erratic RHR Pump Parameters/Loss of Flow Control/RHR Pump Trip-RCS NOT Filled.
Attachment 18, Standby RHR Train Startup Instruction.
Attachment 4, RHR Maximum Flow Limit.
Page 2 of 8 CPNPP NRC 2014 JPM S-4 Draft Submittal
Appendix C JPM STEPS Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Examiner Note: The following steps are from ABN-104, Section 7.0.
Perform Step: 1 Verify BOTH hot leg RECIRC valves on operating RHR pump(s) - FULL 7.3.1, 1st & 2nd bullets OPEN:
1/u-8701A, RHRP 1 HL RECIRC ISOL VLV 1/u-8702A, RHRP 1 HL RECIRC ISOL VLV Standard: DETERMINED 1/1-8701A, RHRP 1 HL RECIRC ISOL VLV red OPEN light LIT and 1/1-8702A, RHRP 1 HL RECIRC ISOL VLV red OPEN light LIT.
Comment: SAT UNSAT Perform Step: 2 Verify at least one RHR pump running.
7.3.2 Standard
DETERMINED Train A RHR Pump tripped and REFERRED to RNO column.
Comment: SAT UNSAT Examiner Note: The following steps represent the Alternate Path of this JPM.
Perform Step: 3 Start up the standby RHR train per Attachment 18.
7.3.2 RNO 1)
Standard: REFERRED to Attachment 18, Standby RHR Train Startup Instruction.
Examiner Note: Provide examinee with a copy of ABN-104, Attachment 18.
Comment: SAT UNSAT Page 3 of 8 CPNPP NRC 2014 JPM S-4 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following steps are from ABN-104, Attachment 18.
Perform Step: 4 Dispatch personnel to vent the seal cooler for the standby pump and 1 & 2nd bullet check motor bearing oil levels:
uRH-0022, RHR PMP u-02 SEAL CLR VNT VLV, (SFGD u-052 TRN B RHRP Rm)
Standard: DISPATCHED NEO to vent the seal cooler for RHR Pump 2 and check motor bearing oil levels.
Examiner Cue: NEO has been dispatched.
Comment: SAT UNSAT Perform Step: 5 Ensure the following valves are in the correct position for the standby 2.b & 1st bullet RHR Pump:
1/u-8809B, RHR TO CL 3 & 4 INJ ISOL VLV OPEN Standard: DETERMINED 1/1-8809B, RHR TO CL 3 & 4 INJ ISOL VLV in OPEN and OBSERVED red OPEN light LIT.
Comment: SAT UNSAT Perform Step: 6 Ensure the following valves are in the correct position for the standby 2.b & 2nd bullet RHR Pump:
1/u-8701B, RHRP 2 HL RECIRC ISOL VLV OPEN Standard: VERIFIED 1/1-8701B, RHRP 2 HL RECIRC ISOL VLV is Caution tagged OPEN.
Comment: SAT UNSAT Perform Step: 7 Ensure the following valves are in the correct position for the standby 2.b & 3rd bullet RHR Pump:
1/u-8702B, RHRP 2 HL RECIRC ISOL VLV OPEN Standard: DETERMINED 1/1-8702B, RHRP 2 HL RECIRC ISOL VLV in OPEN and OBSERVED red OPEN light LIT.
Comment: SAT UNSAT Page 4 of 8 CPNPP NRC 2014 JPM S-4 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 Ensure the following valves are in the correct position for the standby 2.b & 4th bullet RHR Pump:
1/u-8716B, RHRP XTIE VLV CLOSED Standard: VERIFIED 1/1-8716B, RHRP 2 XTIE VLV green CLOSE light LIT.
Comment: SAT UNSAT Perform Step: 9 Ensure the following valves are in the correct position for the standby 2.b & 5th bullet RHR Pump:
u-HC-607, RHR HX 2 FLO CTRL CLOSED (0%)
Standard: VERIFIED 1-HC-607, RHR HX 2 FLO CTRL in CLOSE at zero (0%)
indicated position.
Comment: SAT UNSAT Perform Step: 10 Ensure the following valves are in the correct position for the standby 2.b & 6th bullet RHR Pump:
u-FK-619, RHR HX 2 BYP FLO CTRL CLOSED (0%)
Standard: VERIFIED 1-FK-619, RHR HX 2 BYP FLO CTRL indicates zero (0%) in CLOSE position.
Comment: SAT UNSAT Perform Step: 11 Ensure the following valves are in the correct position for the standby th 2.b & 7 bullet RHR Pump:
u-HC-128, RHR LTDN FLO CTRL CLOSED (0%)
Standard: ROTATED 1-HC-128, RHR LTDN FLO CTRL to CLOSE at zero (0%)
indicated position.
Comment: SAT UNSAT Perform Step: 12 Verify RCS level adequate for RHR pump start.
3 Standard: DETERMINED Reduced Inventory Condition does NOT exist and RCS level is adequate for RHR Pump start.
Comment: SAT UNSAT Page 5 of 8 CPNPP NRC 2014 JPM S-4 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Examiner Note: Provide examinee with a copy of ABN-104, Attachment 4.
Perform Step: 13 Determine the maximum allowable flow from Attachment 4.
4 Standard: REFERRED to Attachment 4 and DETERMINED maximum flow allowed based on current level is 4800 gpm.
Comment: SAT UNSAT Perform Step: 14 Start the standby RHR pump.
5 & 2nd bullet 1/u-APRH 2, RHRP 2 Standard: PERFORMED the following:
PLACED 1/1-APRH 2, RHRP 2 in START (critical).
OBSERVED red PUMP and FAN lights LIT and proper amps on 1-II-APRH2, RHRP 2 MOT CURRENT (NOT critical).
Comment: SAT UNSAT Examiner Cue: The Unit Supervisor directs you to establish 3800 gpm flow.
Perform Step: 15 Slowly throttle open the heat exchanger flow control valve to establish 6 & 2nd bullet flow below limit determined in Step 4 above.
u-HC-607, RHR HX 2 FLO CTRL Standard: PLACED 1-HC-607, RHR HX 2 FLO CTRL to OPEN and ROTATED potentiometer until approximately 3800 gpm of flow is established as READ on 1-FI-619, RHR TO CL 3 & 4 INJ FLO.
Comment: SAT UNSAT Page 6 of 8 CPNPP NRC 2014 JPM S-4 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Examiner Note: The examinee may close down on RHR HX 1 CCW Return Valve during the performance of this step.
Perform Step: 16 Open RHR Heat Exchanger CCW Return Valve as necessary to control 7 & 2nd bullet RCS temperature:
u-HS-4573, RHR HX 2 CCW RET VLV Standard: PERFORMED the following:
PLACED 1-HS-4573, RHR HX 2 CCW RET VLV in OPEN and RAISED flow to stabilize RCS temperature (critical).
OBSERVED red OPEN and green CLOSE lights LIT (NOT critical).
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 7 of 8 CPNPP NRC 2014 JPM S-4 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
Unit 1 is in MODE 5 with the RCS NOT Filled.
Train A Residual Heat Removal System was in service.
Train A Residual Heat Removal Pump has just tripped.
Train B Residual Heat Removal System is aligned for standby per SOP-102A, Residual Heat Removal System, Section 5.3.
INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:
RESPOND to a loss of the Residual Heat Removal System per ABN-104, Residual Heat Removal System Malfunction, Section 7.0, Mode 5 or 6 Erratic RHR Pump Parameters/Loss of Flow Control/RHR Pump Trip-RCS NOT Filled.
Page 8 of 8 CPNPP NRC 2014 JPM S-4 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-5 Task # RO3516A K/A # 061.A2.07 3.4 / 3.5 SF-4S
Title:
Respond to Inadvertent Start of Turbine Driven Auxiliary Feedwater Pump 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.
Nuclear Instrument NI-43 has failed high.
ABN-703, Power Range Instrument Malfunction, has been performed and troubleshooting is in progress.
No Switchyard activities are in progress.
No other inoperabilities exist.
Initiating Cue: The Unit Supervisor directs you to PERFORM the following:
RESPOND to any alarms.
Task Standard: Utilizing ALM-0082A and ABN-305 Required Materials: ALM-0082A, 1-ALB-8B, Window 4.5 - TD AFWP STM SPLY VLV LEAKING HV-2452-1/2, Rev. 8-14.
ABN-305, Auxiliary Feedwater System Malfunction, Rev. 7-6.
Validation Time: 9 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 1 of 6 CPNPP NRC 2014 JPM S-5 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:
INITIALIZE to IC-33 or any at power Initial Condition and LOAD Scenario File LC22 NRC JPM S5 or PERFORM the following:
When directed, EXECUTE malfunction FW13B, 1-HS-2452-2, AFWPT STM SPLY VLV - MSL 1 to OPEN.
BOOTH OPERATOR NOTE:
After each JPM, VERIFY Alarm Procedure 1-ALB-8B, Window 4.5 - TD AFWP STM SPLY VLV LEAKING HV-2452-1/2, is WIPED CLEAN.
EXAMINER:
When requested, PROVIDE the applicant with a copy of:
ABN-305, Auxiliary Feedwater System Malfunction.
Section 6.0, Inadvertent Turbine Driven AFW Pump Start (Steam Supply Valve Fails Open).
Page 2 of 6 CPNPP NRC 2014 JPM S-5 Draft Submittal
Appendix C JPM STEPS Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Booth Operator: When directed, EXECUTE malfunction FW13B, 1-HS-2452-2, Turbine Driven AFW Pump Steam Supply Valve fails OPEN.
Examiner Note: The candidate may immediately place Control Rods in AUTO and perform a 50 MW load reduction in response to the start of the Auxiliary Feedwater Pump. Those steps are addressed at JPM Perform Steps 7 and 8.
Examiner Note: The following steps are from 1-ALB-8B, Window 4.5.
Perform Step: 1 IF not performing AFWPT startup, THEN ensure 1-HS-2452-1, AFWPT 1 & 1st bullet STM SPLY VLV - MSL 4 and 1-HS-2452-2, AFWPT STM SPLY VLV -
MSL 1 are closed. IF NOT closed, THEN place affected steam supply valve handswitch in PULL OUT 1-HS-2452-1, AFWPT STM SPLY VLV - MSL 4 Standard: DETERMINED 1-HS-2452-1, AFWPT STM SPLY VLV MSL 4 in CLOSE and OBSERVED green CLOSE light LIT.
Comment: SAT UNSAT Perform Step: 2 IF not performing AFWPT startup, THEN ensure 1-HS-2452-1, AFWPT 1 & 2nd bullet STM SPLY VLV - MSL 4 and 1-HS-2452-2, AFWPT STM SPLY VLV -
MSL 1 are closed. IF NOT closed, THEN place affected steam supply valve handswitch in PULL OUT 1-HS-2452-2, AFWPT STM SPLY VLV - MSL 1 Standard: PLACED 1-HS-2452-2, AFWPT STM SPLY VLV MSL 1 in CLOSE and OBSERVED red OPEN light LIT.
Comment: SAT UNSAT Perform Step: 3 Monitor 1-SI-2452A, AFWPT SPD.
2 & 2.A IF inadvertent start of the Turbine Driven AFW Pump has occurred, THEN go to ABN-305, AFW System Malfunction while continuing with this procedure.
Standard: DETERMINED 1-SI-2452A, AFWPT SPD is at ~4075 rpm.
Examiner Cue: The Unit Supervisor directs you to implement ABN-305.
Comment: SAT UNSAT Page 3 of 6 CPNPP NRC 2014 JPM S-5 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Examiner Note: The following steps are from ABN-305, Section 6.0.
Perform Step: 4 Close affected steam supply valves by placing handswitch in - PULL st 6.3.1 & 1 bullet OUT u-HS-2452-2, AFWPT STM SPLY VLV - MSL1 Standard: PLACED 1-HS-2452-2, AFWPT STM SPLY VLV MSL1 in PULL-OUT and OBSERVED red OPEN light LIT.
Comment: SAT UNSAT Examiner Note: The following steps represent the Alternate Path of this JPM.
Perform Step: 5 IF affected steam supply valve is closed, THEN go to Step 5.
6.3.1 & 6.3.1 RNO Continue with Step 2.
Standard: DETERMINED 1-HS-2452-2, AFWPT STM SPLY VLV MSL1 is NOT CLOSED and REFERRED to Step 2.
Comment: SAT UNSAT Perform Step: 6 Verify Reactor Power less than or equal to 100%.
6.3.2 Standard
OBSERVED 1-JI-041B/042B/044B, PR POWER CHAN I (II, IV) and DETERMINED Reactor Power greater than 100%.
Comment: SAT UNSAT Page 4 of 6 CPNPP NRC 2014 JPM S-5 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Examiner Note: Bulleted steps may be performed in any order.
Perform Step: 7 Perform the following:
st 6.3.2 RNO 1 bullet Ensure 1/u-RBSS, CONTROL ROD BANK SELECT in AUTO.
Standard: PLACED 1/1-RBSS, CONTROL ROD BANK SELECT in AUTO.
Comment: SAT UNSAT Perform Step: 8 Perform the following 6.3.2 RNO 2nd bullet Initiate a 50 MW Turbine Load reduction.
Standard: INITIATED a 50 MW Turbine Load reduction as follows:
DEPRESSED 50 MWe Manual Runback button.
CLICKED on 0/1 button.
CLICKED on EXECUTE and VERIFIED Runback in progress.
Comment: SAT UNSAT Examiner Cue: If asked, REMIND candidate to review Initial Conditions.
Perform Step: 9 Verify AFW System Safety Function Status 6.3.3 and all bullets Verify BOTH MD AFW pumps OPERABLE, AND Verify BOTH MD AFW pumps support functions OPERABLE, AND Verify BOTH DGs OPERABLE, AND Verify NO Switchyard Activities in-progress impactive to off-site power or Unit generation Standard: VERIFIED AFW System Safety Function Status per Initial Conditions.
Comment: SAT UNSAT Perform Step: 10 Trip the TDAFW Pump 6.3.4 u-HS-2452-F, AFWPT TRIP Standard: DEPRESSED 1-HS-2452-F, AFWPT TRIP pushbutton and observed 1-HS-2452G, AFWPT TRIP & THROTTLE VLV green VLV light LIT.
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 5 of 6 CPNPP NRC 2014 JPM S-5 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
Unit 1 is at 100% power.
Nuclear Instrument NI-43 has failed high.
ABN-703, Power Range Instrument Malfunction, has been performed and troubleshooting is in progress.
No Switchyard activities are in progress.
No other inoperabilities exist.
INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:
RESPOND to any alarms.
Page 6 of 6 CPNPP NRC 2014 JPM S-5 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-6 Task # RO4215B K/A # 064.A4.07 3.4 / 3.4 SF-6
Title:
Restore Safeguards Bus 1EA1 to Offsite Power 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.
Emergency Diesel Generator (EDG) 1-01 is supplying the 6.9 kV Safeguards Bus 1EA1 due to post-work testing of the EDG.
Power from Transformer XST1 is available to the 6.9 kV Safeguards Bus 1EA1.
Transformer XST2 is NOT available.
Initiating Cue: The Unit Supervisor directs you to PERFORM the following:
RESTORE Offsite Power to 6.9 kV Safeguards Bus 1EA1 from Transformer XST1 per SOP-609A, Diesel Generator System, Section 5.7, Transferring From DG Supplying Alone to Normal or Alternate Supply.
Task Standard: Utilizing SOP-609A, restored Offsite Power to 6.9 kV Safeguards Bus 1EA1 from Transformer XST1 and opened the Train A EDG Output Breaker when an overload condition occurred.
Required Materials: SOP-609A, Diesel Generator System, Rev. 21-4.
Validation Time: 10 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 1 of 6 CPNPP NRC 2014 JPM S-6 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:
INITIALIZE to IC #34 or any at power Initial Condition and LOAD Scenario File LC22 NRC JPM S6 or PERFORM the following:
LOAD the EDG per SOP-609A, Section 5.6, Supplying 6.9 KV SFGD Busses with DG Alone.
EXECUTE remote function EDR13, 480 VAC MCC Undervoltage Load Shedding Fuses to REMOVE (if Step 5.7.I is reached, the fuses will be reinstalled).
OPEN both Offsite Power Breakers CS-1EA1-1 and CS-1EA1-2 for Bus 1EA1.
PLACE CS-1EA1-1, Incoming Breaker 1EA1 in PULLOUT and HANG a Red Tag.
ENSURE EDG and Safeguards Bus voltages are NOT matched prior to SNAP of IC.
When the 1EA1-2 Feeder Breaker is CLOSED at Step 5.7.E, EXECUTE malfunction ED09, Grid Frequency Disturbance at 58.2 Hertz and 90 second ramp
{DIED1EA12.iivPanel=3} IMF ED09 f:58.2 r:90.
BOOTH OPERATOR NOTE:
After each JPM, VERIFY the Synchroscope Key Switch is moved to a different position.
EXAMINER:
PROVIDE the applicant with a copy of:
SOP-609A, Diesel Generator System.
Section 5.7, Transferring From DG Supplying Alone to Normal or Alternate Supply.
Page 2 of 6 CPNPP NRC 2014 JPM S-6 Draft Submittal
Appendix C JPM STEPS Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Examiner Note: The following steps are from SOP-609A, Section 5.7.
Perform Step: 1 TURN the synchroscope for the selected breaker ON.
nd 5.7.A & 2 bullet SS-1EA1-2 BKR 1EA1-2 SYNCHROSCOPE Standard: PLACED SS-1EA1-2, BKR 1EA1-2 SYNCHROSCOPE to ON and OBSERVED the synchroscope move approximately to the 12 o'clock position.
Comment: SAT UNSAT Perform Step: 2 Using the DG VOLT CTRL, ADJUST running voltage to match incoming 5.7.B voltage.
Standard: ADJUSTED 90-1EG1, DG 1 VOLT CTRL to RAISE or LOWER DG Output Voltage to MATCH Running Volts (V-RUN) with Incoming Volts (V-IN) and OBSERVED Running Volts MATCHED with Incoming Volts.
Comment: SAT UNSAT Examiner Note: Synchroscope speed is not considered critical, however, it must be moving in the SLOW direction.
Perform Step: 3 Using DG SPD CTRL, ADJUST the speed so that the synchroscope is 5.7.C moving 2 to 4 RPM in the SLOW direction.
Standard: ADJUSTED 65-1EG1, DG 1 SPD CTRL to RAISE or LOWER Diesel Generator speed so that synchroscope is moving 2 to 4 RPM in the SLOW direction.
Comment: SAT UNSAT Page 3 of 6 CPNPP NRC 2014 JPM S-6 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 IF Grid induced load, voltage, OR frequency fluctuations occur while the 5.7.D & 1st bullet DG is synchronized to the bus, THEN OPEN the DG Output Breaker:
CS-1EG1, DG 1 BKR 1EG1 Standard: OBSERVED Note before Step 5.7.D.
Comment: SAT UNSAT Perform Step: 5 CLOSE the feeder breaker when the synchroscope is slightly before the 5.7.E & 2nd bullet 12 o'clock position AND moving 2 to 4 RPM in the SLOW direction.
CS-1EA1-2 INCOMING BKR 1EA1-2 Standard: PERFORMED the following:
PLACED CS-1EA1-2, INCOMING BKR 1EA1-2, in CLOSE when synchroscope is at 12 o'clock (critical).
OBSERVED red CLOSE light LIT (NOT critical).
Comment: SAT UNSAT Examiner Note: The following steps represent the Alternate Path of this JPM.
Booth Operator: VERIFY malfunction ED09, Grid Frequency Fluctuation at 58.2 Hz over 90 seconds has initiated.
Perform Step: 6 Acknowledge annunciator alarm 1-ALB-10B, Window 3.5 - 6.9 KV BUS 1EA1 / 1EA2 PARALLELED.
Standard: ACKNOWLEDGED annunciator alarm 1-ALB-10B, Window 3.5 - 6.9 KV BUS 1EA1 / 1EA2 PARALLELED.
Comment: SAT UNSAT Page 4 of 6 CPNPP NRC 2014 JPM S-6 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 RAISE DG load to 0.5 MW as necessary, to prevent a reverse power trip 5.7.F using DG SPD CTRL handswitch.
Standard: OBSERVED load on W-1EG1, DG 1 MEGAWATTS at approximately 1 MWe.
Comment: SAT UNSAT Perform Step: 8 TURN OFF the synchroscope for the selected breaker.
5.7.G Standard: PLACED SS-1EA1-2, BKR 1EA1-2 SYNCHROSCOPE in OFF.
Comment: SAT UNSAT Examiner Note: This step may be performed if frequency degradation has not yet been identified.
Perform Step: 9 MAINTAIN 0-500 KVAR out by adjusting the selected DG VOLT CTRL 5.7.H handswitch.
Standard: ADJUSTED 90-1EG1, DG 1 VOLT CTRL to RAISE or LOWER DG Output Voltage to MAINTAIN 0-500 KVAR.
Comment: SAT UNSAT Examiner Note: This is Continuous Action Step 5.7.D to avoid excessive loading.
Perform Step: 10 OBSERVE Emergency Diesel Generator 1-01 MWe frequency lowering 5.7.D NOTE uncontrollably and OPEN the output breaker.
Standard: PERFORMED the following:
OPENED CS-1EG1, DG 1 BKR 1EG1 (critical).
OBSERVED green TRIP light LIT (NOT critical).
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 5 of 6 CPNPP NRC 2014 JPM S-6 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
Unit 1 is in MODE 1.
Emergency Diesel Generator (EDG) 1-01 is supplying the 6.9 kV Safeguards Bus 1EA1 due to post-work testing of the EDG.
Power from Transformer XST1 is available to the 6.9 kV Safeguards Bus 1EA1.
Transformer XST2 is NOT available.
INITIATING CUE: The Unit Supervisor directs you to PERFORM the following:
RESTORE Offsite Power to 6.9 kV Safeguards Bus 1EA1 from Transformer XST1 per SOP-609A, Diesel Generator System, Section 5.7, Transferring From DG Supplying Alone to Normal or Alternate Supply.
Page 6 of 6 CPNPP NRC 2014 JPM S-6 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-7 Task # RO1833 K/A # 059.A2.11 3.0 / 3.3 SF-7
Title:
Respond to Feedwater Flow Instrument Failure 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: Unit 1 is operating at 100% power with all controls in AUTOMATIC.
Initiating Cue: The Unit Supervisor directs you to MAINTAIN Steam Generator levels 67 +/- 5%.
Task Standard: Utilizing 1-ALB-8A-2.8 and/or ABN-708, established control of Steam Generator water level following Feedwater Flow instrument FT-520 failure, aligned the Alternate Channel, and restored level control to AUTO.
Required Materials: ALM-0081A, 1-ALB-8A, Window 2.8 - SG 2 STM & FW FLO MISMATCH, Rev. 8-3.
ABN-708, Feedwater Flow Instrument Malfunction, Rev. 6-5.
Validation Time: 6 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 1 of 8 CPNPP NRC 2014 JPM S-7 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP BOOTH OPERATOR:
INITIALIZE to IC-18 or any full power Initial Condition and LOAD Scenario File LC22 NRC JPM S2 & S7 or PERFORM the following:
ENSURE FT-520B is aligned as the in-service Feed Flow Transmitter on SG 1-02.
When directed by the Examiner, PERFORM the following:
INSERT malfunction RX01C (Key 1), SG 1-02 Feed Flow Transmitter (FT-520) fails to 0%.
BOOTH OPERATOR NOTE:
When the JPM is completed, PERFORM THE FOLLOWING:
VERIFY the blue Control Channel Tag on the Feed Flow Instrument is moved in front of 1-FI-520A prior to next performance.
ENSURE 1-ALB-8A, Window 2.8 - SG 2 STM & FW FLO MISMATCH blue annunciator book is clean.
EXAMINER:
When requested, PROVIDE the applicant with a copy of:
ABN-708, Feedwater Flow Instrument Malfunction.
Page 2 of 8 CPNPP NRC 2014 JPM S-7 Draft Submittal
Appendix C JPM STEPS Form ES-C-1
- Check Mark Denotes Critical Step START TIME:
Examiner Note: Entry into either 1-ALB-8A or directly into ABN-708 is acceptable.
Examiner Note: The candidate may choose to respond to the controller failure per ODA-102 which allows transfer from AUTO to MANUAL control when in the operators judgment AUTO control is inappropriate.
This action would be performed immediately at JPM Step 3 or JPM Step 12.
Booth Operator: When directed, EXECUTE malfunction RX01C (Key 1), SG 1-02 Feed Flow Transmitter (FT-520) failure to 0%.
Perform Step: 1 Evaluate alarms and select appropriate response procedure.
Standard: SELECTED 1-ALB-8A, Window 2.8 - SG 2 STM & FW FLO MISMATCH.
Comment: SAT UNSAT Examiner Note: The following steps are from 1-ALB-8A, Window 2.8.
Perform Step: 2 Monitor steam generator water level:
1, 1.A, & bullets 1-LI-528, SG 2 LVL (NR) CHAN III 1-LI-527, SG 2 LVL (NR) CHAN IV 1-LI-529, SG 2 LVL (NR) CHAN I 1-LI-552, SG 2 LVL (NR) CHAN II If one channel is indicating > 5% difference between remaining operable channels, go to ABN-710.
Standard: MONITORED Steam Generator water level instruments:
1-LI-528, SG 2 LVL (NR) CHAN III 1-LI-527, SG 2 LVL (NR) CHAN IV 1-LI-529, SG 2 LVL (NR) CHAN I 1-LI-552, SG 2 LVL (NR) CHAN II Comment: SAT UNSAT N/A Page 3 of 8 CPNPP NRC 2014 JPM S-7 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 3 If level is NOT maintained at approximately 67%, transfer Steam 1.B Generator Water Level Control to manual and maintain level.
1-FK-520, SG 2 FW FLO CTRL Standard: DEPRESSED 1-FK-520, SG 2 FW FLO CTRL amber MANUAL pushbutton to TRANSFER Steam Generator Water Level Control and DEPRESSED the red RAISE () or green LOWER () pushbuttons to MAINTAIN level at approximately 67%.
Examiner Note: Should the examinee choose to respond immediately to the controller failure they could continue per Alarm Response 1-ALB-8A, Window 2.8 or transition to ABN-708, Feedwater Flow Instrument Malfunction. ABN-708 actions begin at JPM Step 12.
Comment: SAT UNSAT N/A Perform Step: 4 Stop all secondary system power changes.
2 Standard: DETERMINED no secondary system power changes are in progress.
Comment: SAT UNSAT N/A Perform Step: 5 Verify a FWP in service.
3 & bullets 1-ZL-2111A, FWPT A LP STOP VLV 1-ZL-2112A, FWPT B LP STOP VLV 1-ZL-2111B, FWPT A HP STOP VLV 1-ZL-2112B, FWPT B HP STOP VLV Standard: VERIFIED both Main Feedwater Pumps are in service and OBSERVED red OPEN light LIT and green CLOSE light DARK for all Stop Valve positions:
1-ZL-2111A, FWPT A LP STOP VLV 1-ZL-2112A, FWPT B LP STOP VLV 1-ZL-2111B, FWPT A HP STOP VLV 1-ZL-2112B, FWPT B HP STOP VLV Comment: SAT UNSAT N/A Page 4 of 8 CPNPP NRC 2014 JPM S-7 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 6 Verify 1-PI-507, MS HDR PRESS and 1-PI-508, FWP DISCH HDR 4 PRESS differential pressure is maintained on program.
Standard: OBSERVED 1-PI-507, MS HDR PRESS and 1-PI-508, FWP DISCH HDR PRESS and DETERMINED differential pressure is on program.
Comment: SAT UNSAT N/A Perform Step: 7 Monitor main steam line pressure:
5, 5.A, & bullets 1-PI-525A, MSL 2 PRESS CHAN II 1-PI-524A, MSL 2 PRESS CHAN I 1-PI-526A, MSL 2 PRESS CHAN IV 1-PI-2326, MSL 2 PRESS If one channel is indicating > 60 psig difference between remaining operable channels, go to ABN-709 for Steam Line Pressure Instrument Malfunction.
Standard: MONITORED main steam line pressures and DETERMINED all channels are in agreement:
1-PI-525A, MSL 2 PRESS CHAN II 1-PI-524A, MSL 2 PRESS CHAN I 1-PI-526A, MSL 2 PRESS CHAN IV 1-PI-2326, MSL 2 PRESS Comment: SAT UNSAT N/A Perform Step: 8 Monitor main steam line pressure:
5 & 5.B If pressure is < 1125 psig, ensure 1-ZL-2326, SG 2 ATMOS RLF VLV is closed.
Standard: DETERMINED pressure is less than 1125 psig and VERIFIED 1-ZL-2326, SG 2 ATMOS RLF VLV is CLOSED.
Comment: SAT UNSAT N/A Page 5 of 8 CPNPP NRC 2014 JPM S-7 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 9 Monitor 1-FI-522A, SG 2 STM FLO and 1-FI-523A, SG 2 STM FLO.
6 & 6.A If one steam line flow indicates higher or lower than the other, go to ABN-707.
Standard: VERIFIED 1-FI-522A, SG 2 STM FLO AND 1-FI-523A, SG 2 STM FLO are indicating normally.
Comment: SAT UNSAT N/A Perform Step: 10 Monitor 1-FI-520A, SG 2 FW FLO and 1-FI-521A, SG 2 FW FLO.
7 & 7.A If one feed line flow indicates higher or lower than the other, go to ABN-708.
Standard: DETERMINED 1-FI-520A, SG 2 FW FLO has failed low and TRANSITIONED to ABN-708, Feedwater Flow Instrument Malfunction.
Examiner Note: The Alarm Response directs examinee to ABN-708.
Comment: SAT UNSAT N/A Examiner Note: The following steps are from ABN-708, Section 2.0.
Perform Step: 11 Verify controlling channel - FAILED.
2.3.1 Standard
DETERMINED controlling Feed Flow Channel FT-520 has FAILED.
Comment: SAT UNSAT Examiner Note: This action may have already been performed at JPM Step 3.
Perform Step: 12 Manually control affected FCV to maintain SG level at program.
2.3.2 u-FK-520, SG 2 FW FLO CTRL Standard: DEPRESSED 1-FK-520, SG 2 FW FLO CTRL amber MANUAL pushbutton to TRANSFER Steam Generator Water Level Control and DEPRESSED the red RAISE () or green LOWER () pushbuttons to MAINTAIN level at approximately 67%.
Comment: SAT UNSAT Perform Step: 13 Verify automatic SG level control - DESIRED.
2.3.3 & 2.3.3.a Alternate feedwater flow control channel responding normally.
Standard: OBSERVED 1-FI-521A, SG 2 FW FLO and DETERMINED alternate Feedwater Flow Control Channel responding normally.
Comment: SAT UNSAT Page 6 of 8 CPNPP NRC 2014 JPM S-7 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Examiner Cue: The Unit Supervisor desires automatic level control for SG 1-02.
Perform Step: 14 Verify automatic SG level control - DESIRED.
2.3.3 & 2.3.3.b Automatic level control desired, as determined by Unit Supervisor.
Standard: DETERMINED the Unit Supervisor desires automatic level control.
Comment: SAT UNSAT Perform Step: 15 Select an alternate channel:
nd 2.3.4 & 2 bullet u-FS-520C, SG 2 FW FLO CHAN SELECT Standard: PLACED 1-FS-520C, SG 2 FW FLO CHAN SELECT in FY-521B position.
Comment: SAT UNSAT Perform Step: 16 Verify affected SG conditions for auto level control.
st 2.3.5 & 1 bullet Feedwater and steam flows matched.
Standard: DEPRESSED 1-FK-520, SG 2 FW FLO CTRL red RAISE () or green LOWER () pushbuttons as required to manually CONTROL feedwater flow to restore Steam Generator level.
Comment: SAT UNSAT Perform Step: 17 Verify affected SG conditions for auto level control.
2.3.5 & 2nd bullet SG level stable at program.
Standard: VERIFIED Steam Generator 1-02 level stable on program.
Comment: SAT UNSAT Perform Step: 18 Place Feedwater Flow Control Valve in automatic AND ensure proper 2.3.6 control.
Standard: DEPRESSED 1-FK-520, SG 2 FW FLO CTRL controller AUTO pushbutton and DETERMINED white AUTO light LIT with controller in AUTO.
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 7 of 8 CPNPP NRC 2014 JPM S-7 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Unit 1 is operating at 100% power with all controls in AUTOMATIC.
INITIATING CUE: The Unit Supervisor directs you to MAINTAIN Steam Generator levels 67 +/- 5%.
Page 8 of 8 CPNPP NRC 2014 JPM S-7 Draft Submittal
Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-8 Task # RO4406C K/A # 068.AK3.12 4.1 / 4.5 SF-8
Title:
Respond to a Fire in the Control Room Examinee (Print):
Testing Method:
Simulated Performance: Classroom:
Actual Performance: X Simulator: X Alternate Path: Plant:
Time Critical:
Initial Conditions: Given the following conditions:
A fire has started in the Control Room.
Initiating Cue: The Shift Manager directs you to PERFORM the following:
INITIATE actions for a Control Room Fire per ABN-803A, Respond to a Fire in the Control Room or Cable Spreading Room, Attachment 1, Reactor Operator Actions to Achieve Hot Shutdown.
Task Standard: Utilizing ABN-803A, Attachment 1, manually tripped Reactor and Turbine, isolated Main Steam Lines, isolated Letdown, stopped Reactor Coolant Pumps, secured Charging flow, disabled Residual Heat Removal (RHR) Pumps, and isolated suction to the RHR Pumps from the Refueling Water Storage Tank.
Required Materials: ABN-803A, Respond to a Fire in the Control Room or Cable Spreading Room, Rev. 11-1.
Validation Time: 10 minutes Completion Time: ________ minutes Comments:
Result: SAT UNSAT Examiner (Print / Sign): Date:
Page 1 of 9 CPNPP NRC 2014 JPM S-8 Draft Submittal
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:
VERIFY Charging Pump suction is aligned to the VCT.
ENSURE 1/1-8149A, LTDN ORIFICE ISOL VLV AND 1/1-8149B, LTDN ORIFICE ISOL VLV in service.
EXAMINER:
PROVIDE the applicant with a copy of:
ABN-803A, Respond to a Fire in the Control Room or Cable Spreading Room.
Attachment 1, Reactor Operator Actions to Achieve Hot Shutdown.
Page 2 of 9 CPNPP NRC 2014 JPM S-8 Draft Submittal
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 1.
Perform Step: 1 Manually Trip Reactor and verify the following:
st a & 1 bullet Reactor trip and bypass breakers - OPEN Standard: PERFORMED the following:
PLACED 1/1-RTC, RX TRIP BKR switch in TRIP (critical).
OBSERVED 1/1-RTBAL, RX TRIP BKR green light LIT.
(NOT critical).
OBSERVED 1/1-RTBAL, RX TRIP BKR green light LIT.
(NOT critical).
Comment: SAT UNSAT Perform Step: 2 Manually Trip Reactor and verify the following:
Neutron flux - DECREASING nd a & 2 bullet Standard: OBSERVED 1-NI-35B, IR CURRENT CHAN I and 1-NI-36B, IR CURRENT CHAN II lowering.
Comment: SAT UNSAT Perform Step: 3 Manually Trip Reactor and verify the following:
a & 3rd bullet All DRPI RB lights - ON Standard: OBSERVED all Control Rods INSERTED on CTRL ROD POSN bezel.
Comment: SAT UNSAT Perform Step: 4 Ensure Turbine - TRIPPED b
Standard: DETERMINED HP Turbine Stop Valves CLOSED and OBSERVED; 1-ZL2429A, HPT STOP VLV 1 green light LIT.
1-ZL2431A, HPT STOP VLV 2 green light LIT.
1-ZL2430A, HPT STOP VLV 3 green light LIT.
1-ZL2428A, HPT STOP VLV 4 green light LIT.
Comment: SAT UNSAT Page 3 of 9 CPNPP NRC 2014 JPM S-8 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Ensure 1-HS-2452-F, AFWPT TRIP - TRIPPED c
Standard: PERFORMED the following:
DEPRESSED 1-HS-2452-F, AFWPT TRIP pushbutton (critical).
OBSERVED 1-HS-2452G, AFWPT TRIP & THROTTLE VLV green VLV light LIT (NOT critical).
Comment: SAT UNSAT Examiner Note Operation of either switch 1-HS-2337A or 1-HS-2337B will isolate the Main Steam Lines and satisfy both Critical JPM Steps 6 & 7.
Perform Step: 6 Isolate Main Steam Lines.
d & 1st bullet 1-HS-2337A, MSL ISOL MAN ACT/RESET Standard: PERFORMED the following:
PLACED 1-HS-2337A, MSL ISOL MAN ACT/RESET in ACT position (critical).
OBSERVED 1-HS-2333A(2334A/2335A/2336A), MSIV 1(2/3/4),
green CLOSE lights LIT (NOT critical).
Comment: SAT UNSAT N/A Perform Step: 7 Isolate Main Steam Lines.
nd d & 2 bullet 1-HS-2337B, MSL ISOL MAN ACT/RESET Standard: PERFORMED the following:
PLACED 1-HS-2337B, MSL ISOL MAN ACT/RESET in ACT position (critical).
OBSERVED 1-HS-2333A(2334A/2335A/2336A), MSIV 1(2/3/4),
green CLOSE lights LIT (NOT critical).
Comment: SAT UNSAT N/A Page 4 of 9 CPNPP NRC 2014 JPM S-8 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 8 Ensure 1/1-8202A AND 1/1-8202B, VENT VLV - CLOSED.
e Standard: DETERMINED 1/1-8202A AND 1/1-8202B, VENT VLV in CLOSE and OBSERVED green CLOSE lights LIT.
Comment: SAT UNSAT Perform Step: 9 CLOSE the following valves:
f & 1st bullet 1/1-8149A, LTDN ORIFICE ISOL VLV (45 GPM)
Standard: PERFORMED the following:
PLACED 1/1-8149A, LTDN ORIFICE ISOL VLV in CLOSE (critical).
OBSERVED green CLOSE light LIT (NOT critical).
Comment: SAT UNSAT Perform Step: 10 CLOSE the following valves:
f & 2nd bullet 1/1-8149B, LTDN ORIFICE ISOL VLV (75 GPM)
Standard: PERFORMED the following:
PLACED 1/1-8149B, LTDN ORIFICE ISOL VLV in CLOSE (critical).
OBSERVED green CLOSE light LIT (NOT critical).
Comment: SAT UNSAT Perform Step: 11 CLOSE the following valves:
f & 3rd bullet 1/1-8149C, LTDN ORIFICE ISOL VLV (75 GPM)
Standard: DETERMINED 1/1-8149C, LTDN ORIFICE ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.
Comment: SAT UNSAT Perform Step: 12 CLOSE the following valves:
f & 4th bullet 1/1-8153, XS LTDN ISOL VLV Standard: DETERMINED 1/1-8153, XS LTDN ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.
Comment: SAT UNSAT Page 5 of 9 CPNPP NRC 2014 JPM S-8 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 13 CLOSE the following valves:
f & 5th bullet 1/1-8154, XS LTDN ISOL VLV Standard: DETERMINED 1/1-8154, XS LTDN ISOL VLV in CLOSE and OBSERVED green CLOSE light LIT.
Comment: SAT UNSAT Perform Step: 14 Perform the following:
st g & 1 bullet OPEN 1/1-LCV-112E, RWST TO CHRG PMP SUCT VLV.
Standard: PERFORMED the following:
PLACED 1/1-LCV-112E, RWST TO CHRG PMP SUCT VLV in OPEN (critical).
OBSERVED red OPEN light LIT (NOT critical).
Comment: SAT UNSAT Perform Step: 15 Perform the following:
g & 2nd bullet OPEN 1/1-LCV-112D, RWST TO CHRG PMP SUCT VLV.
Standard: PERFORMED the following:
PLACED 1/1-LCV-112D, RWST TO CHRG PMP SUCT VLV in OPEN (critical).
OBSERVED red OPEN light LIT (NOT critical).
Comment: SAT UNSAT Perform Step: 16 Perform the following:
g & 2nd bullet Place 1/1-APCH1, CCP 1 in PULL-OUT.
Standard: PERFORMED the following:
PLACED 1/1-APCH1, CCP 1 in PULL-OUT (critical).
OBSERVED green TRIP light DARK and red FAN light LIT.
(NOT critical).
Comment: SAT UNSAT Page 6 of 9 CPNPP NRC 2014 JPM S-8 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 17 STOP Reactor Coolant Pumps.
h & 1st bullet 1/1-PCPX1, RCP 1 Standard: PERFORMED the following:
PLACED 1/1-PCPX1, RCP 1 in STOP (critical).
OBSERVED green STOP light LIT (NOT critical).
Comment: SAT UNSAT Perform Step: 18 STOP Reactor Coolant Pumps.
h & 2nd bullet 1/1-PCPX2, RCP 2 Standard: PERFORMED the following:
PLACED 1/1-PCPX2, RCP 2 in STOP (critical).
OBSERVED green STOP light LIT (NOT critical).
Comment: SAT UNSAT Perform Step: 19 STOP Reactor Coolant Pumps.
h & 3rd bullet 1/1-PCPX3, RCP 3 Standard: PERFORMED the following:
PLACED 1/1-PCPX3, RCP 3 in STOP (critical).
OBSERVED green STOP light LIT (NOT critical).
Comment: SAT UNSAT Perform Step: 20 STOP Reactor Coolant Pumps.
th h & 4 bullet 1/1-PCPX4, RCP 4 Standard: PERFORMED the following:
PLACED 1/1-PCPX4, RCP 4 in STOP (critical).
OBSERVED green STOP light LIT (NOT critical).
Comment: SAT UNSAT Page 7 of 9 CPNPP NRC 2014 JPM S-8 Draft Submittal
Appendix C JPM STEPS Form ES-C-1 Perform Step: 21 Place BOTH RHR pumps - PULL-OUT.
i & 1st bullet 1/1-APRH1, RHRP 1 Standard: PERFORMED the following:
PLACED 1/1-APRH1, RHRP 1 in PULL-OUT (critical).
OBSERVED green PUMP light DARK (NOT critical).
Comment: SAT UNSAT Perform Step: 22 Place BOTH RHR pumps - PULL-OUT.
i & 2nd bullet 1/1-APRH2, RHRP 2 Standard: PERFORMED the following:
PLACED 1/1-APRH2, RHRP 2 in PULL-OUT (critical).
OBSERVED green PUMP light DARK (NOT critical).
Comment: SAT UNSAT Perform Step: 23 CLOSE following valves:
st j & 1 bullet 1/1-8812A, RWST TO RHRP 1 SUCT VLV Standard: PERFORMED the following:
PLACED 1/1-8812A, RWST TO RHRP 1 SUCT VLV in CLOSE (critical).
OBSERVED green CLOSE light LIT (NOT critical).
Comment: SAT UNSAT Perform Step: 24 CLOSE following valves nd j & 2 bullet 1/1-8812B, RWST TO RHRP 2 SUCT VLV Standard: PERFORMED the following:
PLACED 1/1-8812B, RWST TO RHRP 2 SUCT VLV in CLOSE (critical).
OBSERVED green CLOSE light LIT (NOT critical).
Terminating Cue: This JPM is complete.
Comment: SAT UNSAT STOP TIME:
Page 8 of 9 CPNPP NRC 2014 JPM S-8 Draft Submittal
Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:
A fire has started in the Control Room.
INITIATING CUE: The Shift Manager directs you to PERFORM the following:
INITIATE actions for a Control Room Evacuation per ABN-803A, Respond to a Fire in the Control Room or Cable Spreading Room, Attachment 1, Reactor Operator Actions to Achieve Hot Shutdown.
Page 9 of 9 CPNPP NRC 2014 JPM S-8 Draft Submittal
Appendix D Scenario Outline Form ES-D-1 Facility: CPNPP 1 & 2 Scenario No.: 1 Op Test No.: June 2014 NRC Examiners: Operators:
Initial Conditions: 100% power MOL - RCS Boron is 924 ppm (by sample).
Turnover: Maintain steady-state power conditions. Tornado Warning from the National Weather Service.
Pressurizer Steam Space Sample is in progress by Chemistry.
Critical Tasks: Emergency Stop Train B Diesel Generator within 15 minutes of Breaker Failure in accordance with ECA-0.0A, Loss of All AC Power. (Event 6)
Isolate Reactor Coolant System Leakage Paths in accordance with ECA-0.0A, Loss of All AC Power. (Event 7)
Initiate an Operator Induced Cooldown in accordance with ECA-0.0A, Loss of All AC Power.
(Event 8)
Event No. Malf. No. Event Type* Event Description 1 RP05D I (RO, SRO) Reactor Coolant System Loop (1-04) Narrow Range Cold Leg
+10 min TS (SRO) Temperature Instrument (TI-441A) Fails High.
2 RP03J I (BOP, SRO) Main Steam Line (1-04) Pressure Transmitter (PT-544) Channel I
+20 min TS (SRO) Fails Low.
3 RX05A I (RO, SRO) Pressurizer Level Channel (LT-459A) Fails Low.
+30 min TS (SRO) 4 FW14B R (RO) Heater Drain Pump (1-02) Trip.
+45 min TC09I N (BOP, SRO) Automatic Turbine Runback Failure.
TS (SRO) 5 ED01 M (RO, BOP, SRO) Loss of All AC Power Due to Loss of Offsite Power.
+50 min 6 EG06A C (BOP) Emergency Diesel Generator (1-01) Air Start Failure.
+50 min EG16B Emergency Diesel Generator (1-02) Output Breaker Failure.
7 WDR04 C (RO) Pressurizer Steam Space Sample Valves (1/1-4165A & 1/1-4176A)
+55 min Fail to Auto Close. Manual Closure of 1-HV-4165A Required.
8 MS13A I (BOP) Atmospheric Relief Valve (1-01) Fails Closed due to Steam
+75 min Pressure Instrument (PT-2325) Failure.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 9 Total malfunctions (5-8) 4 Malfunctions after EOP entry (1-2) 4 Abnormal events (2-4) 1 Major transients (1-2) 1 EOPs entered/requiring substantive actions (1-2) 1 EOP contingencies requiring substantive actions (0-2) 3 Critical tasks (2-3)
CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Scenario Event Description NRC Scenario 1 SCENARIO
SUMMARY
NRC 1 The crew will assume the watch at 100% power with no scheduled activities per IPO-003A, Power Operations. A Tornado Warning from the National Weather Service is in progress. ABN-907, Acts of Nature, Section 5.0, Severe Weather, has been performed and includes placing the High Flux at Shutdown switches in BLOCK and realigning Control Room Ventilation to the Emergency Recirculation Mode. A Pressurizer Steam Space sample is in progress.
In the first event a Reactor Coolant System (RCS) Loop 4 TCOLD Instrument will fail high. The crew enters ABN-704, TC/N-16 Instrumentation Malfunction, Section 2.0, places Rod Control in MANUAL and defeats the affected channel. The SRO will refer to Technical Specifications.
The next event is a Main Steam Line 1-04 Channel I Pressure Transmitter failing low. Operator actions are per ABN-709, Steam Line Pressure Instrument Malfunction, Section 2.0, and require taking MANUAL control of the Feedwater Flow Control Valve, transferring to an Alternate Channel, and restoring Feedwater Flow Control to AUTO. The SRO will refer to Technical Specifications.
When plant conditions are stable a low failure of Pressurizer Level Channel, LT-459A, will occur.
Operator actions are per ABN-706, Pressurizer Level Instrument Malfunction, Section 2.0. The crew must manually control either the Charging Flow Controller or the Pressurizer Level Controller, transfer to an Alternate Channel, and restore Reactor Coolant System (RCS) Letdown flow. The SRO will refer to Technical Specifications.
The next event is a trip of a Heater Drain Pump with an automatic Turbine Runback failure. The crew responds per ABN-302, Feedwater, Condensate, Heater Drain System Malfunction, Section 4.0. When it is determined that automatic plant response has not activated, Control Rods are placed in AUTO and a manual Turbine Runback will be initiated. The crew will stabilize load at 700 MWe. During this event, Control Rod position may drop below the Rod Insertion Limit (RIL) and when informed, the SRO will refer to Technical Specifications. Additionally, ABN-401, Main Turbine Malfunction, Section 8.0, must be entered to reset the Turbine Runback.
The major event is a Loss of Offsite Power with an air start failure of Train A Diesel Generator and a breaker failure of Train B Diesel Generator resulting in a Total Loss of All AC Power. The crew enters either EOP-0.0A, Reactor Trip or Safety Injection and then exits to ECA-0.0A, Loss of All AC Power, or enters ECA-0.0A directly. While in ECA-0.0A, Reactor Coolant System leakage paths are isolated and a cooldown is initiated to 270°F. When the cooldown is commenced the crew will restore power to the Train B Safeguards Bus.
The event is complicated by failure of a Pressurizer Steam Space Sample Valve to automatically close and an Atmospheric Relief Valve that must be manually opened in order to facilitate Reactor Coolant System cooldown. This scenario is terminated when power is restored to the Train B Safeguards Bus and transition to ECA-0.0A, Step 26, Stabilize Steam Generator Pressures is performed.
Risk Significance:
Failure of risk important system prior to trip: Turbine Runback Failure Risk significant core damage sequence: Loss of All AC Power Risk significant operator actions: Stop Train B Diesel Generator Isolate RCS Leakage Paths Initiate RCS Cooldown Restore Safeguards Bus Power CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Scenario Event Description NRC Scenario 1 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP INITIALIZE to IC-30 and LOAD LC22 NRC Scenario 1.
EVENT REM. MALF. DESCRIPTION DEMAND INITIATING FUNC. VALUE PARAMETER SETUP EG06A Diesel Generator (1-01) Air Start Failure FAIL K0 EG16B Diesel Generator (1-02) Breaker Failure FAIL K0 WDR04 PRZR Steam Space Sample Valves OPEN K0 (1/1-4165A & 1/1-4176A) Failure MS13A ARV (1-01) Fails Closed due to Steam Pressure 0 psig RTB Opens Instrument (PT-2325) Failure OVRDE EDG 1-02 Breaker Override OPEN K0 TC09I Automatic Turbine Runback Failure FAIL K0 1 RP05D RCS Loop 1 TCOLD Instrument TI-441A Failure 630°F K1 2 RP03J MSL Pressure Transmitter (PT-544) Failure 0 psig K2 3 RX05A Pressurizer Level Channel (LT-459) Failure 0% K3 4 FW14B Heater Drain Pump (1-02) Trip TRIP K4 4 TC09I Automatic Turbine Runback Failure FAIL K0 5 ED01 Loss of Offsite Power OFF K5 6 EG06A Diesel Generator (1-01) Air Start Failure FAIL K0 6 EG16B Diesel Generator (1-02) Breaker Failure FAIL K0 OVRDE EDG 1-02 Breaker Override OPEN K0 7 WDR04 PRZR Steam Space Sample Valves OPEN K0 (1/1-4165A & 1/1-4176A) Failure 8 MS13A ARV (1-01) Fails Closed due to Steam Pressure 0 psig RTB Opens Instrument (PT-2325) Failure CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Scenario Event Description NRC Scenario 1 DEL Removes Override on EDG 1-02 Output Breaker AUTO K7 OVRDE DMF Delete Diesel Generator (1-02) Breaker Failure AUTO K7 EG16B CCR10 1-HV-4709, Thermal Barrier Cooler Return Valve CLOSE K10 CVR21 1/1-8100, RCP Seal Water Return Isolation Valve CLOSE K10 CVR22 1CS-8369A, RCP Seal Injection Throttle Valve CLOSE K10 CVR23 1CS-8369B, RCP Seal Injection Throttle Valve CLOSE K10 CVR24 1CS-8369C, RCP Seal Injection Throttle Valve CLOSE K10 CVR25 1CS-8369D, RCP Seal Injection Throttle Valve CLOSE K10 FWR077 1-HV-2484, CST Discharge Valve CLOSE K11 FWR078 1-HV-2485, CST Discharge Valve CLOSE K11 FWR071 1-HV-2953, Auxiliary Condenser Vacuum Breaker OPEN K12 Isolation Valve FWR072 1-HV-2954, Auxiliary Condenser Vacuum Breaker OPEN K12 Isolation Valve FWR073 1-HV-2955, Main Condenser Vacuum Breaker OPEN K12 Isolation Valve MSR15 MSIV Local Isolation ISOL K13 CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Scenario Event Description NRC Scenario 1 Simulator Operator: INITIALIZE to IC-30 and LOAD LC22 NRC Scenario 1.
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 to 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.
- COPY of ABN-907, Acts of Nature, Section 5.0, Severe Weather and Attachment 3, Severe Weather Preparations.
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 6D-3.1 - SR SHTDN FLUX ALM BLK 13A-3.16 - DAMPER 25 IN EMERGENCY MODE 13A-4.16 - DAMPER 25 IN EMERGENCY MODE CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 1 Evvent # 1 Page 6 of 33 Event Desccription: Rea actor Coolant Loop L Cold Leg Temperature FFailure Time Position n Appliccants Actions o or Behavior Simulato or Operatorr: When dire ected, EXEC CUTE Eventt 1 (Key 1).
- RP05D, R Looop 4 TCOLD NR temperatture instrum ment (TI-441 1A) fails higgh.
Indicatioons Availab ble:
5C-1.5 - ANY N16 DEV D HI / LO 5C-2.5 - 1 OF 4 OT N16 HI 5C-3.5 - ANY TAVE DEV D HI / LO O
6D-1.10 - AVE TAVE TREF DEV 6D-2.10 - AVE TAVE HI 6D-3.14 - 1 OF 4 OT T N16 ROD STOP & TU URB RUNBA ACK 1-TI-441A A, CL 4 TEM MP (NR) CH HAN IV indic cation failedd high 1-TI-442,, RC LOOP 4 TAVE CHA AN IV indicattion failed h high
+30 secs s RO RESPO OND to Annu unciator Alarrm Procedurres.
RO RECOG GNIZE Control Rods insserting due to o TCOLD faile ed high.
DIRECT T performan nce of ABN-7 704, Tc / N-16 Instrumentation Malffunction, US Section n 2.0.
PLACE E 1/1-RBSS, CONTROL ROD BANK K SELECT S Switch in MAANUAL.
[Step 2.3.1]
RO SELEC CT LOOP 4 on o 1-TS-412 2T, TAVE Cha annel Defeatt. [Step 2.3.22]
RO/BOP VERIFY Y Steam Dump System is NOT actu uated and NO OT armed. ((Step 2.3.3]
CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submittaal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 1 Page 7 of 33 Event
Description:
Reactor Coolant Loop Cold Leg Temperature Failure Time Position Applicants Actions or Behavior Examiner Note: Crew will withdraw rods to 215 steps in 5 step increments to restore TAVE.
RO RESTORE TAVE to within 1ºF of TREF. [Step 2.3.4]
WITHDRAW Control Rods in 5 step increments until Control Bank D is at 215 steps.
RO/BOP SELECT LOOP 4 on 1/1-JS-411E, N16 Power Channel Defeat. [Step 2.3.5]
ENSURE a valid N16 channel supplying recorder on 1/1-TS-411E, 1-TR-411 RO CHAN SELECT. [Step 2.3.6]
VERIFY PCIP, Window 3.4 - TURB LOAD REJ STM DMP ARMED C-7, not RO/BOP ARMED (DARK). [Step 2.3.7]
US/BOP VERIFY Steam Dumps were NOT blocked. [Step 2.3.8]
US EVALUATE Technical Specifications. [Step 2.3.11]
LCO 3.3.1.E, Reactor Trip System Instrumentation (Function 6, Overtemperature N-16 & Function 7, Overpower N-16).
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 />.
US INITIATE a work request per STA-606. [Step 2.3.12]
+10 min US INITIATE a SMART Form per STA-421. [Step 2.3.13]
When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 2.
CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 2 Page 8 of 33 Event
Description:
Steam Line Pressure Transmitter Failure Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 2 (Key 2).
- RP03J, Steam Line (1-04) Pressure Transmitter (PT-544) Channel I fails low.
Indications Available:
8A-4.7 - MSL 4 1 OF 3 PRESS LO 8A-4.8 - SG 4 STM & FW FLO MISMATCH 8A-4.16 - SG 1 OF 3 PRESS RATE HI 1-PI-544A, MSL 4 PRESS CHAN I indication fails low
+1 min BOP RESPOND to Annunciator Alarm Procedures.
BOP RECOGNIZE Steam Line Pressure 1-PT-544 transmitter failure.
Examiner Note: Steam Line Channel failure low will cause Feedwater flow to lower and Feedwater Pumps to lower in speed.
Examiner Note: The crew may initially enter ABN-707, Steam Flow Instrument Malfunction, but will be directed to ABN-709 based on diagnosis.
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 Main Steam Line 1-04 Pressure Transmitter (PT-544) -
BOP GREATER THAN 60 PSIG difference between remaining channels.
[Step 2.3.1]
BOP VERIFY Steam Generator Atmospheric Relief Valves - CLOSED. [Step 2.3.2]
1-ZL-2325, SG 1 ATMOS RLF VLV 1-ZL-2326, SG 2 ATMOS RLF VLV 1-ZL-2327, SG 3 ATMOS RLF VLV 1-ZL-2328, SG 4 ATMOS RLF VLV CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 1 Evvent # 2 Page 9 of 33 Event Desccription: Steam Line Pressure Transmitte er Failure Time Position n Appliccants Actions o or Behavior BOP VERIFY Y following channels c aree indicating - NORMAL. [Step 2.3.2]
1-P PI-2325, MS SL 1 PRESS 1-P PI-2326, MS SL 2 PRESS 1-P PI-2327, MS SL 3 PRESS 1-P PI-2328, MS SL 4 PRESS PLACE E 1-FK-540, SGS 4 FW FL LO CTRL in MANUAL and CONTRO OL Steam BOP Generaator 1-04 level. [Step 2.3 3.3]
Manuallly CONTRO OL 1-SK-509 9A, FWPT M MASTER SPD D CTRL as necessary.
[Step 2.3.4]
BOP SELEC CT Alternate Steam Flow w Channel 1--FY-543B. [S Step 2.3.5]
Looop 4, 1-FS-5542C, SG 4 STM FLO C CHAN SELECT. [Step 2..3.5.d]
VERIFY Y Steam Ge enerator 1-04 4 Level - ST TABLE AT P PROGRAM L LEVEL.
[Step 2.3.6]
Steeam flow and Feed flow - MATCHE ED.
PLACE E 1-FK-540, SGS 4 FW FL LO CTRL in AUTO and V VERIFY con ntrolling - IN N
BOP NORMA AL OPERAT TING RANG GE. [Step 2.3 3.7]
VERIFY Y 1-SK-509A A, FWPT MA ASTER SPD D CTRL in AUTO -
BOP CONTR ROLLING NO ORMALLY. [Step 2.3.8]
Examine er Note: Ap pplicant maay identify Technical T S Specification n Table 3.3..2-1, Functio on 4.d.2, fo or tracking purposes p as s this Functtion is applicable only y in MODE 3 3.
CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submittaal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 2 Page 10 of 33 Event
Description:
Steam Line Pressure Transmitter Failure Time Position Applicants Actions or Behavior US EVALUATE Technical Specifications. [Step 2.3.11]
LCO 3.3.2.D, ESFAS Instrumentation (Function 1.e, 4.d.1, & 4.d.2 - Steam Line 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 />.
US INITIATE a SMART Form per STA-421. [Step 2.3.12]
+10 min US INITIATE repairs per STA-606. [Step 2.3.13]
When control of Feedwater is restored, or at Lead Examiner discretion, PROCEED to Event 3.
CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 1 Evvent # 3 Page 11 of 33 Event Desccription: Pressurizer Level Transmitter Fa ailure Time Position n Appliccants Actions o or Behavior Simulato or Operatorr: When dire ected, EXEC CUTE Eventt 3 (Key 3).
- RX05A, R Presssurizer Level Transm mitter (LT-45 59) fails loww.
Indicatioons Availab ble:
5B-1.4 - PRZR HTR R GRP C CTRL TRBL 5B-3.6 - PRZR LVL LO 5C-1.2 - PRZR LVL DEV LO 6A-3.8 - CVCS HEL LB PT-5358AA 6A-4.8 - CVCS HEL LB PT-5358 1-LI-459A A, PRZR LV VL CHAN I indication fa ailed low
+30 sec c RO RESPO OND to Annu unciator Alarrm Procedurres.
RECOG GNIZE PZR level lowerin ng and REP PORT Pressu urizer Level Channel I RO (LT-4599) failed low.
DIRECT T performan nce of ABN-7 706, Pressurizer Level Instrumentattion US Malfuncction, Sectio on 2.0.
PLACE E PZR Level Control or C Charging Flo ow in MANU UAL to maintain level on RO program m using one of the follow wing controlllers: [Step 2.3.1]
1-L LK-459, PRZ ZR LVL CTR RL 1-F FK-121, CCP P CHRG FLO O CTRL TRANS SFER 1/1-LS S-459D, PZR R Level Conttrol Channel Select to an RO/BOP OPERA ABLE channel. [Step 2.3 3.2]
TRANS SFER 1/1-LS S-459E, 1/1--LR-459 PZR R Level Sele ect to an OPERABLE RO/BOP channeel. [Step 2.3.3]
CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submittaal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 3 Page 12 of 33 Event
Description:
Pressurizer Level Transmitter Failure Time Position Applicants Actions or Behavior RO VERIFY Normal Letdown aligned. [Step 2.3.4]
Examiner Note: Letdown flow is re-established using ABN-706, Attachment 6, or the Letdown Restoration Job Aid.
When Pressurizer level is greater than 17%, RESTORE Letdown per RO Attachment 6. [Step 2.3.4 RNO]
OPEN or VERIFY OPEN Letdown Isolation Valves 1/1-LCV-460 &
1/1-LCV 459. [Step 1]
Manually OPEN 1-PK-131, LTDN HX OUT PRESS CTRL to 30% (75 GPM) or 50% (120 GPM) DEMAND. [Step 2]
Manually OPEN 1-TK-130, LTDN HX OUT TEMP CTRL to 50%
DEMAND. [Step 3]
ADJUST Charging to desired flow and MAINTAIN Seal Injection flow between 6 and 13 GPM. [Step 4]
OPEN selected Orifice Isolation Valves. [Step 5]
1/1-8149A, LTDN ORIFICE ISOL VLV (45 GPM) 1/1-8149B, LTDN ORIFICE ISOL VLV (75 GPM) 1/1-8149C, LTDN 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]
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]
RO RESET PZR Control Heater Group C. [Step 2.3.5]
RESTORE PZR Level Control or Charging Flow Control to AUTO as desired.
[Step 2.3.6]
VERIFY other instruments on common instrument line - NORMAL.
US/RO
[Step 2.3.7]
VERIFY Loop 1 Instrument PT-455 responding normally per Attachment 1.
CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 3 Page 13 of 33 Event
Description:
Pressurizer Level Transmitter Failure Time Position Applicants Actions or Behavior US EVALUATE Technical Specifications. [Step 2.3.10]
LCO 3.3.1.M, Reactor Trip System Instrumentation (Function 9 - Pressurizer Water Level - High).
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 />.
US INITIATE repairs per STA-606. [Step 2.3.11]
+10 min US INITIATE a SMART Form per STA-421. [Step 2.3.12]
When Letdown flow has been restored and Technical Specifications have been addressed, or at Lead Examiner discretion, PROCEED to Event 4.
CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 1 Evvent # 4 Page 14 of 33 Event Desccription: Hea ater Drain Pum mp Trip / Automatic Turbine Ru unback Failure e
Time Position n Appliccants Actions o or Behavior Simulato or Operatorr: When dire ected, EXEC CUTE Eventt 4 (Key 4).
- FW14B, F Heaater Drain Pump P (1-02)) trip.
- TC09I, T Autoo Turbine Ru unback failu ure.
Indicatioons Availab ble:
9A-1.2 - HDP 1/2 OV VRLOAD / TRIP 8B-2.8 - CNDS LP HTR H BYP TR RBL 8B-3.8 - CNDS LP HTR H BYP VL LV OPEN PV V-2286 8B-4.8 - TURB GLN ND STM CND DSR CNDS FLO HI 6D-1.9 - ANY TURB RUNBACK K EFFECTIVE E (when Ma anual Runba ack initiated) 6D-1.10 - AVE TAVE-TREF DEV (w when Manua al Runback iinitiated) 1-HS-260 03, HDP 2 TRIP light LIT T Steam Dump D System m Group 1 Valves V OPEN Control Rods R stepping IN
+30 sec c RO/BOP RESPO OND to Annu unciator Alarrm Procedurres.
RECOG GNIZE trip ofo Heater Dra ain Pump 1--02 with no A Automatic Tu urbine BOP Runbac ck.
DIRECT T performan nce of ABN-3 302, Feedwa ater, Condensate, Heateer Drain US System m Malfunction n, Section 4 .0.
Examine er Note: Diiamond step ps () are Innitial Operattor Actions s.
RO/BOP VERIFY Y automatic plant respon nse. [Step 4 4.3.1]
RO VE ERIFY Contro ol Rods in - AUTO.
BOP ERIFY Turbin VE ne Runback - IN PROG GRESS.
CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submittaal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 1 Evvent # 4 Page 15 of 33 Event Desccription: Hea ater Drain Pummp Trip / Automatic Turbine Ru unback Failure e
Time Position n Appliccants Actions o or Behavior If Turbine T Powwer is > appro oximately 80 00 MWe, PE ERFORM the e following:
RO/BOP
[Sttep 4.3.1 RN NO].
PLACE 1/1 1-RBSS, CO ONTROL RO OD BANK SE ELECT in AU UTO.
[Step 4.3.1.a RNO].
BOP ENSURE Turbine T Run back to 700 MWE initiatted. [Step 4..3.1.b RNO]
DEPRE ESS 700 MW We MANUA AL RUNBAC CK button.
CLICK on 0/1 buttton.
CLICK on Execute e then VERIFY Manual Runback in progress.
Simulato or Operatorr: When con ntacted, REPORT an in nstantaneou us ground o overcurrentt 50N relay onn breaker fo or Heater Drrain Pump 1 1-02 BOP VERIFY Y Main Feed d Flow to Ste eam Genera ators. [Step 44.3.2]
Ma ain Feed Pum mp - AT LEA AST ONE R RUNNING. [S Step 4.3.2.a))
Ma ain Feedwate er pump sucction pressurre - GREAT TER THAN 2 250 PSIG.
[Sttep 4.3.2.b]
Feedwater hea ader pressurre - MAINTA AINED GRE EATER THAN N MAIN STTEAM HEAD DER PRESS URE. [Step 4.3.2.c]
Ma ain Feedwate er - ALIGNE ED. [Step 4.3 3.2.d]
VERIFY Y Steam Ge enerator wate er level - ST TABLE OR T TRENDING TO BOP NORMA AL OPERAT TING RANG GE. [Step 4.3 3.3]
CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submittaal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 1 Evvent # 4 Page 16 of 33 Event Desccription: Hea ater Drain Pummp Trip / Automatic Turbine Ru unback Failure e
Time Position n Appliccants Actions o or Behavior BOP VERIFY Y TAVE - TRE ENDING TO O TREF. [Step p 4.3.4]
RO/BOP STABIL LIZE Reacto or power usin ng one or more of the fo ollowing: [Ste ep 4.3.5]
Coontrol Rods / Steam Dum mps / Boratio on / Turbine Load.
VERIFY Y Steam Ge enerator Fee edwater Flow w Control Va alves - IN AUUTO.
[Step 4.3.6]
RO VERIFY Y the following: [Step 4.3 3.7]
Coontrol Rods - ABOVE RO OD INSERT TION LIMIT. [Step 4.3.7.a]
VERIFY SD DM or initiate e boration to o restore SDDM within 1 hhour and restore Rod ds above inssertion limitss with 2 hourrs per TS 3.1.6.
[Step 4.3.77.a RNO]
Flux F - (AFD)) WITHIN LIMITS. [Step p 4.3.7.b]
Examine er Note: Ev vents during this scenario will res sult in exce eeding the R Rod Insertio on Limits (R
RIL). The RO O should infform the SR RO when AL LB-6D, Wind dow 2.7 - AANY COONTROL RO OD BANK AT A LO-LO L LIMIT is LIT. Technical Specificatio ons must bee referenced d.
US EVALU UATE Technical Specificcations.
LCCO 3.1.6.A, Control C Bankk Insertion L Limits.
CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submittaal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 17 of 33 Event
Description:
Heater Drain Pump Trip / Automatic Turbine Runback Failure Time Position Applicants Actions or Behavior CONDITION A - Control bank insertion limits not met.
ACTION A.1.1 - Verify SDM to be within the limits provided in the COLR within one hour, OR ACTION A.1.2 - Initiate Boration to restore SDM to within limit within one hour, AND ACTION A.2 - Restore control bank(s) to within limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
WHEN steam dumps have closed, THEN reset steam dump arming signal BOP (C-7 interlock). [Step 4.3.8]
Examiner Note: LP Feed Heater Bypass Valve closure is not performed due to time constraints.
VERIFY 1-HS-2286, Low Pressure Feedwater Heater Bypass Valve -
BOP CLOSED. [Step 4.3.9]
US NOTIFY QSE Generation Controller. [Step 4.3.10]
US INITIATE repairs per STA-606. [Step 4.3.11]
US CHECK Chemistry Sampling Requirement: [Step 4.3.12]
VERIFY SG Atmospheric Relief Valves - REMAINED CLOSED AND TDAFW Pump - REMAINED STOPPED. [Step 4.3.12.a]
VERIFY Reactor Power change - LESS THAN 15% RTP WITHIN ONE HOUR. [Step 4.3.12.b]
NOTIFY Chemistry to perform RCS Isotopic analysis for iodine US between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after power change. [Step 4.3.12.b RNO]
Examiner Note: Reset of Turbine Runback is not performed due to time constraints.
US RESET Turbine Runback per ABN-401. [Step 4.3.13]
When Chemistry has been notified, PROCEED to Events 5, 6, 7, and 8.
CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, 7, & 8 Page 18 of 33 Event
Description:
Loss of Offsite Power / Train A Diesel Generator Start Failure / Train B Diesel Generator Output Breaker Failure / Pressurizer Steam Space Sample Valve Failure / Atmospheric Relief Valve Failure Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Events 5, 6, 7, and 8 (Key 5).
- ED01, Loss of Offsite Power.
- EG06A, Train A Emergency Diesel Generator start failure.
- EG16B, Train B Emergency Diesel Generator Output Breaker failure.
- OVRDE, EDG 1-02 Output Breaker failure.
- WDR04, Pressurizer Steam Space Sample Valves fail to Auto Close.
- MS13A, PT-2325 fails low.
Indications Available:
Numerous Reactor Trip and Loss of Offsite Power Alarms.
+10 sec RO/BOP RECOGNIZE Reactor Trip due to Loss of Offsite Power.
Simulator Operator: When Unit 1 trips, ANNOUNCE Unit 2 Reactor Trip.
Examiner Note: Crew may recognize a Loss of All AC Power event in progress and immediately enter ECA-0.0A as opposed to EOP-0.0A.
Examiner Note: EOP-0.0A, Reactor Trip or Safety Injection steps begin here.
DIRECT performance of EOP-0.0A, Reactor Trip or Safety Injection or ECA-US 0.0A, Loss of All AC Power.
RO VERIFY Reactor Trip: [Step 1]
VERIFY Reactor Trip Breakers - OPEN. [Step 1.a]
VERIFY Neutron flux - DECREASING. [Step 1.a]
VERIFY all Control Rod Position Rod Bottom Lights - ON.
[Step 1.b]
BOP VERIFY Turbine Trip: [Step 2]
VERIFY all HP Turbine Stop Valves - CLOSED. [Step 2]
BOP VERIFY Power to AC Safeguards Buses: [Step 3]
VERIFY AC Safeguards Buses - AT LEAST ONE ENERGIZED.
[Step 3.a]
CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix xD Operatorr Action Form ES-D-2 Operating Test T : NRC N Scenario S # 1 Even nt # 5, 6, 7, & 8 Page 19 of 33 Event Desccription: Losss of Offsite Power / Train A Diesel D Generatoor Start Failure e / Train B Diessel Generator OOutput Breaker Failure / Pressurizer P Ste eam Space Sam mple Valve Failure / Atmosph heric Relief Vallve Failure Time Position n Appliccants Actions oor Behavior GOO to ECA-0.0 0A, Loss of A All AC Powe er, Step 1. [S Step 3.b]
Examine er Note: EC CA- 0.0A, Lo oss of All ACA Power stteps begin here.
RO VERIFY Y Reactor Trip: [Step 1]
VERIFY Reacto or Trip Breaakers - AT LEAST ONE OPEN. [Ste ep 1]
VERIFY Neutro on flux - DEECREASING G. [Step 1]
BOP VERIFY Y Turbine Trrip: [Step 2]
VEERIFY all HP P Turbine Sto op Valves - CLOSED. [Step 2]
CRITIICAL TASK Isolate Reactor Co oolant Systtem Leakage Paths in a accordance e with STAATEMENT ECA-0..0A, Loss of All AC Pow wer.
RO CHECK K If RCS Is Is solated: [Ste ep 3]
RO CHHECK Letdow wn Isolation Valves - CLOSED. [Ste ep 3.a]
1/1-LCV-4 459 and 1/1--LCV-460 Examine er Note: Th he Letdown n Isolation Valves V are innterlocked with the Le etdown Orifiice Isolation Valv ves. The Le etdown Isola ation Valves s cannot be e closed until the Leetdown Oriffice Isolatio on Valves arre closed.
CRITICAL TASK RO CLLOSE Letdow wn Isolation Valves. [Ste ep 3.a RNO))
PLACE 1//1-8149A AN ND 1/1-8149 9B, Letdown Orifice Isola ation Valves in CLOSE.
PLACE 1//1-LCV-459 A AND 1/1-LC CV-460, Letd down Isolatio on Valves in CLOSE E. [Step 3.a R RNO]
CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submitta al
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, 7, & 8 Page 20 of 33 Event
Description:
Loss of Offsite Power / Train A Diesel Generator Start Failure / Train B Diesel Generator Output Breaker Failure / Pressurizer Steam Space Sample Valve Failure / Atmospheric Relief Valve Failure Time Position Applicants Actions or Behavior CHECK Pressurizer Power Operated Relief Valves - CLOSED.
[Step 3.b]
RO CHECK Excess Letdown Isolation Valves - CLOSED. [Step 3.c]
1/1-8153 and 1/1-8154 RO CHECK Primary Sample System Isolation Valves - CLOSED. [Step 3.d]
1/1-4165A and 1/1-4167A CRITICAL TASK RO CLOSE Primary Sample System Isolation Valves. [Step 3.d RNO]
PLACE 1-HS-4165A, Primary Sample System Isolation Valve in CLOSE. [Step 3.d RNO]
PLACE 1-HS-4167A, Primary Sample System Isolation Valve in CLOSE. [Step 3.d RNO]
RO/BOP VERIFY AFW Flow - GREATER THAN 460 GPM. [Step 4]
Examiner Note: The Unit Supervisor can attempt to restore power to either train. Steps for Train B power restoration are listed first since that EDG is running.
BOP RESTORE Power to Any AC Safeguards Bus: [Step 5]
ENERGIZE selected AC Safeguards Bus with Diesel Generator.
[Step 5.a]
VERIFY Diesel Generator 1 RUNNING. [Step 5.a.1)]
CRITICAL TASK Emergency Stop Train B Diesel Generator within 15 minutes of Breaker STATEMENT Failure in accordance with ECA-0.0A, Loss of All AC Power.
CHECK Diesel Generator 1-02 Output Breaker - CLOSED.
[Step 5.a.2)]
Manually CLOSE Diesel Generator 1-02 Output Breaker.
[Step 5.a.2.A) RNO]
BOP PLACE SS-1EG2, BKR 1EG2 Synchroscope ON.
BOP PLACE CS-1EG2, DG 2 BKR 1EG2 to CLOSE.
CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, 7, & 8 Page 21 of 33 Event
Description:
Loss of Offsite Power / Train A Diesel Generator Start Failure / Train B Diesel Generator Output Breaker Failure / Pressurizer Steam Space Sample Valve Failure / Atmospheric Relief Valve Failure Time Position Applicants Actions or Behavior If Diesel Generator 1-02 Output Breaker NOT closed, BOP PERFORM Emergency Start on Diesel Generator 1-02.
[Step 5.a.2.B) RNO]
If Train B Safeguards Bus NOT energized, PLACE Diesel CRITICAL BOP Generator 1-02 EMER STOP/START switch in PULL-OUT and TASK GO to Step 5b. [Step 5.a.2.C) RNO]
ENERGIZE remaining AC Safeguards Bus with Diesel Generator.
[Step 5.b]
VERIFY Diesel Generator 1 RUNNING. [Step 5.b.1)]
PERFORM Emergency Start on Diesel Generator 1-01.
[Step 5.b.1.A) RNO]
PERFORM Normal Start on Diesel Generator 1-01.
[Step 5.b.1.B) RNO]
DETERMINE Diesel Generator 1 NOT RUNNING and GO US to Step 5c. [Step 5.C) RNO]
Simulator Operator: When contacted, REPORT EDG 1-01 has an air start failure and EDG 1-02 has breaker failure indications. Field Support is investigating.
Examiner Note: The BOP is directed to ABN-601, Response to a 138/345 KV System Malfunction, Section 6.0, Loss of All Offsite and Onsite AC Power. Those steps are located at the end of the scenario.
VERIFY AC Safeguards Buses - AT LEAST ONE ENERGIZED.
US
[Step 5.c]
ENERGIZE Safeguards Bus per ABN-601, Response to a 138/345 KV System Malfunction or ABN-602 Response to a 6900/480 V System Malfunction and continue with this procedure.
[Step 5.c.1) RNO]
GO to Step 6 and OBSERVE CAUTIONS Prior to Step 6.
US
[Step 5.c.2) RNO]
CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix xD Operatorr Action Form ES-D-2 Operating Test T : NRC N Scenario S # 1 Even nt # 5, 6, 7, & 8 Page 22 of 33 Event Desccription: Losss of Offsite Power / Train A Diesel D Generatoor Start Failure e / Train B Diessel Generator OOutput Breaker Failure / Pressurizer P Ste eam Space Sam mple Valve Failure / Atmosph heric Relief Vallve Failure Time Position n Appliccants Actions oor Behavior When Power P Is Res stored to Anny Safeguard ds Bus, CON NTINUE Reccovery US Actions s Starting witth Step 26. ((Step 6]
Examine er Note: Att this point, Safety Inje ection (SI) w will not be a actuated. Wh hen SI actuates, the crrew will retu urn to Steps s 7.b, c, & d and perforrm reset of SI and SI Sequencers.
RO CHECK K Safety Inje ection Signall Status: [Ste ep 7]
VEERIFY Safety y Injection - ACTUATED D. [Step 7.a))
CONTINUE E with Step 8 8. [Step 7.a RNO]
When SI is s actuated, PPERFORM S Steps 7.b, 7..c, & 7.d.
[Step 7.a RNO]
R RO VEERIFY Reacttor Trip Brea akers - OPE EN. [Step 7.b b]
RO/BOP REESET Safety Injection. [S Step 7.c]
DEPRESS 1/1-SIRA, T TRAIN A SI RESET pusshbutton.
DEPRESS 1/1-SIRB, T TRAIN A SI RESET pusshbutton.
RO/BOP REESET Safety y Injection Se equencers. ((Step 7.d]
At SI Sequencer Train A Cabinet, DEPRESS S SI SEQR RE ESET green push hbutton then n PLACE ON N/RESET tog ggle switch in RESET.
PLACE ON N/RESET tog ggle switch iin ON.
CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submitta al
Appendix xD Operatorr Action Form ES-D-2 Operating Test T : NRC N Scenario S # 1 Even nt # 5, 6, 7, & 8 Page 23 of 33 Event Desccription: Losss of Offsite Power / Train A Diesel D Generatoor Start Failure e / Train B Diessel Generator OOutput Breaker Failure / Pressurizer P Ste eam Space Sam mple Valve Failure / Atmosph heric Relief Vallve Failure Time Position n Appliccants Actions oor Behavior At SI Sequencer Train B Cabinet, DEPRESS S SI SEQR RE ESET green push hbutton then n PLACE ON N/RESET tog ggle switch in RESET.
PLACE ON N/RESET tog ggle switch iin ON.
Simulato or Operatorr: When con ntacted to lo ocally break k Condense er vacuum, EXECUTE remote functions FW WR071, FWR R072, & FWR R073 to ope en Auxiliary y and Main Coondenser VacuumV Breeaker Isolatiion Valves ((Key 12).
Simulato or Operatorr: When con ntacted to Manually M Isoolate the MS SIVs, EXEC CUTE remote e functions MS SR15 (Key 13).
Examine er Note: When W Safety Injection and the SI Se equencers are properlly RESET, A Annunciatorr 1-ALB-2B, Window 2.8 - SFGD SEQ QR TRN A/B B AUTO TES ST TRBL, w will RESET.
RO/BOP PLACE E Following Equipment E S Switches in P PULL-OUT: [Step 8]
Saffety Injectionn Pumps Containment Spray S Pumpss Containment Spray S Heat EExchanger O Outlet Valvess Containment Fan F Coolers Component Co ooling Waterr Pumps Saffety Chilled Water Recirrc Pumps Residual Heat Removal Pu umps Centrifugal Cha arging Pump ps Mootor Driven Auxiliary A Feeedwater Pum mps Control Room Air A Conditio ning Units w without powe er available Ventilation Chilled Water R Recirc Pump ps without po ower availab ble CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submitta al
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, 7, & 8 Page 24 of 33 Event
Description:
Loss of Offsite Power / Train A Diesel Generator Start Failure / Train B Diesel Generator Output Breaker Failure / Pressurizer Steam Space Sample Valve Failure / Atmospheric Relief Valve Failure Time Position Applicants Actions or Behavior DISPATCH Personnel to Locally Restore AC power per ABN-601, Response US to a 138/345 KV System Malfunction or ABN-602 Response to a 6900/480 V System Malfunction while continue with this procedure. [Step 9]
Simulator Operator: When contacted, EXECUTE remote functions CVR21 thru 25 to isolate RCP Seal Water flow and EXECUTE remote function CCR10 to isolate Thermal Barrier Cooler cooling water (Key 10).
US DISPATCH Personnel to Locally Isolate RCP Seals. [Step 10]
1/1-8100, RCP Seal Water Return Isolation Valve 1CS-8369A, RCP Seal Injection Throttle Valve 1CS-8369B, RCP Seal Injection Throttle Valve 1CS-8369C, RCP Seal Injection Throttle Valve 1CS-8369D, RCP Seal Injection Throttle Valve 1-HV-4709, Thermal Barrier Cooler CW Return Isolation Valve Simulator Operator: When contacted, EXECUTE remote functions FWR077 and FWR078 to CLOSE Condensate Storage Tank Discharge Valves (Key 11).
RO/BOP VERIFY Condensate Storage Tank Isolated from Hotwell: [Step 11]
Locally ENSURE CST Discharge Valves - CLOSED.
1-HV-2484 and 1-HV-2485 RO/BOP CHECK SG Status: [Step 12]
VERIFY Main Steam Isolation Valves - CLOSED. [Step 12.a]
VERIFY Main Feedwater Control and Bypass Valves - CLOSED.
[Step 12.b]
VERIFY Blowdown and Sample Isolation Valves - CLOSED. [Step 12.c]
VERIFY Upstream Main Steam Drippot Isolation Valves - CLOSED.
[Step 12.d]
CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix xD Operatorr Action Form ES-D-2 Operating Test T : NRC N Scenario S # 1 Even nt # 5, 6, 7, & 8 Page 25 of 33 Event Desccription: Losss of Offsite Power / Train A Diesel D Generatoor Start Failure e / Train B Diessel Generator OOutput Breaker Failure / Pressurizer P Ste eam Space Sam mple Valve Failure / Atmosph heric Relief Vallve Failure Time Position n Appliccants Actions oor Behavior RO/BOP CHECK K If Any SG Is Faulted: [S Step 13]
CH HECK any SG Pressure - DECREAS SING IN AN N UNCONTR ROLLED MA ANNER. [Ste ep 13.a]
CH HECK any SG - COMPL LETELY DEP PRESSURIZ ZED. [Step 1 13.a]
US GO to Ste ep 14. [Step 13 RNO]
RO/BOP CHECK K if SG Tube es are Ruptu ured: [Step 14]
CH HECK Steam m Generator Level - INC CREASING IIN AN UN NCONTROLLED MANN ER. [Step 14 4]
US CONTINU UE with Step p 15. OBSER RVE CAUTIO ON and NOT TE Prior to Step 15. [Step 14 RNO O]
RO/BOP CHECK K Intact SG Levels:
L [Step p 15]
SG G Narrow Ra ange Level - GREATER R THAN 43% % (50% for ADVERSE CO ONTAINMEN NT). [Step 15 5.a]
CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submitta al
Appendix xD Operatorr Action Form ES-D-2 Operating Test T : NRC N Scenario S # 1 Even nt # 5, 6, 7, & 8 Page 26 of 33 Event Desccription: Losss of Offsite Power / Train A Diesel D Generatoor Start Failure e / Train B Diessel Generator OOutput Breaker Failure / Pressurizer P Ste eam Space Sam mple Valve Failure / Atmosph heric Relief Vallve Failure Time Position n Appliccants Actions oor Behavior COONTROL AF FW flow to m maintain narro ow range levvel between n 43% (50%
forr ADVERSE CONTAINM MENT) and 6 60%.[Step 15 5.b]
Examine er Note: EC CA-0.0A, Atttachment 2, 2 DC Load S Shedding is s performed d by Field S Support.
RO/BOP CHECK K DC Bus Lo oads: [Step 1 16]
INITIATE Shed dding of DC Loads per A Attachment 2 2. [Step 16.a a]
VEERIFY voltag ge - GREAT TER THAN 110 VOLTS. [Step 16.a]
RO/BOP CHECK K Condensatte Storage T Tank Level - GREATER R THAN 10% %. [Step 17]
CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submitta al
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, 7, & 8 Page 27 of 33 Event
Description:
Loss of Offsite Power / Train A Diesel Generator Start Failure / Train B Diesel Generator Output Breaker Failure / Pressurizer Steam Space Sample Valve Failure / Atmospheric Relief Valve Failure Time Position Applicants Actions or Behavior Simulator Operator: When the SG depressurization is underway, Field Support will contact the Control Room and report fuses inside the Train B Diesel Generator Output Breaker have been replaced and the Diesel Generator is ready to be started.
Simulator Operator: When the SG depressurization is underway, REMOVE malfunction EG16B and REPORT as Field Support that EDG 1-02 is ready for starting (Key 7).
CRITICAL TASK Initiate an Operator Induced Cooldown in accordance with ECA-0.0A, STATEMENT Loss of All AC Power.
RO/BOP DEPRESSURIZE Intact SGs to 270 PSIG. [Step 18]
CHECK SG Narrow Range Level - GREATER THAN 43% (50% for ADVERSE CONTAINMENT) in at least one SG. [Step 18.a]
MAINTAIN cooldown rate in RCS cold legs - LESS THAN 100°F / HR.
[Step 18.b]
CRITICAL TASK MANUALLY dump steam using SG atmospheric(s). [Step 18.c]
PLACE SG Atmospheric Relief Valve 1-01 in MANUAL and INCREASE demand.
PLACE SG Atmospheric Relief Valves 1-02, 1-03, & 1-04 in MANUAL and INCREASE demand.
CHECK SG pressures - LESS THAN 270 PSIG. [Step 18.d]
MANUALLY control SG atmospheric(s) to maintain SG pressures at 270 PSIG. [Step 18.e]
BOP PERFORM Emergency Start on Diesel Generator 1-02.
VERIFY Diesel Generator 1 RUNNING.
CHECK Diesel Generator 1-02 Output Breaker - CLOSED Examiner Note: When power is restored to the Train B Safeguards Bus a transition to ECA-0.0A, Step 26 should be made.
When Power Is Restored to Any Safeguards Bus, CONTINUE Recovery US Actions Starting with Step 26. [CONTINUOUS ACTION STEP]
CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, 7, & 8 Page 28 of 33 Event
Description:
Loss of Offsite Power / Train A Diesel Generator Start Failure / Train B Diesel Generator Output Breaker Failure / Pressurizer Steam Space Sample Valve Failure / Atmospheric Relief Valve Failure Time Position Applicants Actions or Behavior RO/BOP STABILIZE Steam Generator pressures: [Step 26]
Manually CONTROL SG atmospheric(s). [Step 26.a]
When Steam Generator pressures are stabilized, TERMINATE the scenario.
CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix xD Operatorr Action Form ES-D-2 Operating Test T : NRC N Scenario S # 1 Even nt # 5, 6, 7, & 8 Page 29 of 33 Event Desccription: Losss of Offsite Power / Train A Diesel D Generatoor Start Failure e / Train B Diessel Generator OOutput Breaker Failure / Pressurizer P Ste eam Space Sam mple Valve Failure / Atmosph heric Relief Vallve Failure Time Position n Appliccants Actions oor Behavior Examine er Note: Th he following g steps are from ABN-6 601, Section 6.0. These e steps are peerformed in preparation for restorring onsite a and/or offsite power.
BOP CHECK K the unit in MODES 1, 2 2, 3, or 4. [SStep 6.3.1]
BOP RESTO ORE Power to t Any 6.9 K KV Safeguard ds Bus: [Ste ep 6.3.2]
VER RIFY at leas st one 6.9 KV V Safeguard ds Bus - ENERGIZED.
[Ste ep 6.3.2.e]
INITIATE Attachment A 115, Seconda ary System S Shutdown Fo ollowing a Loss of Pow wer. [Step 66.3.2.e.2 RNO]
GO to Step p 3. [Step 6.3 3.2.e.3 RNO O]
CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submitta al
Appendix xD Operatorr Action Form ES-D-2 Operating Test T : NRC N Scenario S # 1 Even nt # 5, 6, 7, & 8 Page 30 of 33 Event Desccription: Losss of Offsite Power / Train A Diesel D Generato or Start Failure e / Train B Diessel Generator OOutput Breaker Failure / Pressurizer P Ste eam Space Sam mple Valve Failure / Atmosph heric Relief Vallve Failure Time Position n Appliccants Actions oor Behavior Examine er Note: Th he following g steps are from ABN-6 601, Attach hment 15. Th he BOP may y pass off the entire Atttachment to o the Field S Support tea am.
BOP ENSUR RE Turbine - TRIPPED. [Step 1]
BOP CLOSE E Main Steam m Isolation V Valves as follows: [Step 2]
CLO OSE Main SteamS Isolati on Valves. ((Step 2.a]
DISSPATCH ope erator to loca ally isolate M MSIVs air so olenoids. [Ste ep 2.b]
LOC CALLY drain n MSIV upsttream drip po ots. [Step 2.c]
VER RIFY Feedw water Isolatioon Bypass V Valves upstre eam manual isolations
- CLOSED.
C [Sttep 2.d]
BOP VERIFY Y Emergenc cy DC Seal O Oil Pump - R RUNNING. [Step 3]
Examine er Note: Ad dditional ac ctions in AB BN-601, Atta achment 15 5 will be perrformed by tthe Field Suupport team m. ABN-601,, Section 6. 0 steps are e continued here.
BOP CHECK K Switchyard d Bus Statuss - ALL ENE ERGIZED. [S Step 6.3.3]
CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submitta al
Appendix xD Operatorr Action Form ES-D-2 Operating Test T : NRC N Scenario S # 1 Even nt # 5, 6, 7, & 8 Page 31 of 33 Event Desccription: Losss of Offsite Power / Train A Diesel D Generatoor Start Failure e / Train B Diessel Generator OOutput Breaker Failure / Pressurizer P Ste eam Space Sam mple Valve Failure / Atmosph heric Relief Vallve Failure Time Position n Appliccants Actions oor Behavior V-EE BUS, 345 KV K E. BUS V VOLT (CB-12) - BETWE EEN 340 KV V and 361 KV.. [Step 6.3.3.a]
V-WW BUS, 345 KV W. BUS S VOLT (CB--12) - BETW WEEN 340 KV V and 361 KV.. [Step 6.3.3.b]
V/SST1, START XFMR XST T1 138 KV FD DR VOLT (C CB-12) - BET TWEEN 1355 KV and 144 4 KV [Step 6 6.3.3.c]
BOP VERIFY Y Main Turbine and Fee edwater Pum mp Turbine E Emergency D DC Lube Oil Pum mps - RUNN NING. [Step 6 6.3.4]
US/SM M REFER R to EPP-201 1 and STA-5 501. [Step 6..3.5]
BOP DISPAT TCH operato or to locally vverify UPS rroom fan coil units - OPERATING.
[Step 6.3.6]
BOP PLACE E breaker han ndswitches in PULL-OU UT: [Step 6.3 3.7]
CS--1EA1-1, INC COMING BK KR 1EA1-1 CS--1EA1-2, INC COMING BK KR 1EA1-2 CS--1EG1, DG 1 BKR 1EG1 1 CS--1EA2-1, INC COMING BK KR 1EA2-1 CS--1EA2-2, INC COMING BK KR 1EA2-2 CS--1EG2, DG 2 BKR 1EG2 2 CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submitta al
Appendix xD Operatorr Action Form ES-D-2 Operating Test T : NRC N Scenario S # 1 Even nt # 5, 6, 7, & 8 Page 32 of 33 Event Desccription: Losss of Offsite Power / Train A Diesel D Generatoor Start Failure e / Train B Diessel Generator OOutput Breaker Failure / Pressurizer P Ste eam Space Sam mple Valve Failure / Atmosph heric Relief Vallve Failure Time Position n Appliccants Actions oor Behavior BOP INITIAT TE actions to o restore pow wer to at lea ast one AC ssafeguards b bus from any ava ailable sourc ce including the following g attachmen nts as neede ed:
[Step 6.3.8]
Res storation of the t Diesel G Generator - A Attachment 1 Res storation of XST1 X - Atta chment 2 Res storation of XST2 X OR XS ST2A - Atta achment 3 Res storation of the t 345 KV T Transformerr Feeder Line - Attachm ment 4 Res storation fromm a 6.9 KV S Safeguards Bus Fault - Attachmentt 5 SOP-614A/B Alternate Pow wer Generato or Operation n (if connectted)
BOP PLACE E the followin ng non-safeg guards breakker handswitches in PUL LL-OUT:
[Step 6.3.9]
CS--1A1-2 INCO OMING BKR R 1A1-2 CS--1A2-2 INCO OMING BKR R 1A2-2 CS--1A3-2 INCO OMING BKR R 1A3-2 CS--1A4-2 INCO OMING BKR R 1A4-2 BOP OPEN the t following g breakers: ((Step 6.3.10]
CS--T1B1 XFMR R BKR T1B1 1 CS--1B1-1 INCO OMING BKR R 1B1-1 CS--T1B2 XFMR R BKR T1B2 2 CS--1B2-1 INCO OMING BKR R 1B2-1 CS--T1B3 XFMR R BKR T1B3 3 CS--1B3-1 INCO OMING BKR R 1B3-1 CS--T1B4 XFMR R BKR T1B4 4 CS--1B4-1 INCO OMING BKR R 1B4-1 CPNPP NRC 2014 Simulator S Sccenario 1 Dra aft Submitta al
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5, 6, 7, & 8 Page 33 of 33 Event
Description:
Loss of Offsite Power / Train A Diesel Generator Start Failure / Train B Diesel Generator Output Breaker Failure / Pressurizer Steam Space Sample Valve Failure / Atmospheric Relief Valve Failure Time Position Applicants Actions or Behavior BOP When off-site power is available to the 345 KV Switchyard, INITIATE actions to restore power to the AC non-safeguards buses from any available source.
[Step 6.3.11]
Restoration of the 345 KV Transformer Feeder Line - Attachment 4 Restoration 1ST - Attachment 6 Restoration 2ST - Attachment 7 Restoration from a 6.9 KV Non-Safeguards Bus Fault - Attachment 8 Return to Procedure and step in effect.
CPNPP NRC 2014 Simulator Scenario 1 Draft Submittal
Appendix D Scenario Outline Form ES-D-1 Facility: CPNPP 1 & 2 Scenario No.: 2 Op Test No.: Feb 2014 NRC Examiners: Operators:
Initial Conditions: 100% power MOL - RCS Boron is 924 ppm (by sample).
Turnover: Maintain steady-state power conditions.
Critical Tasks: Trip Reactor Coolant Pumps within 10 minutes upon a Loss of Subcooling per EOP-0.0A, Reactor Trip or Safety Injection or EOP-1.0A, Loss of Reactor or Secondary Coolant, Foldout Pages. (Event 5)
Initiate Cooldown of Reactor Coolant System Prior to Exiting EOS-1.2A, Post LOCA Cooldown and Depressurization. (Event 6)
Manually Initiate Train A and Train B Safety Injection Signal Prior to Exiting EOP-0.0A, Reactor Trip or Safety Injection. (Event 7)
Event No. Malf. No. Event Type* Event Description 1 RX12 C (BOP, SRO) Main Steam Header Pressure Transmitter (PT-507) Fails Low.
+5 min 2 RX08A I (RO, SRO) Pressurizer Pressure Channel (PT-455) Fails High.
+15 min TS (SRO) 3 RX04C I (BOP, SRO) Steam Generator (1-03) Level Transmitter (LT-553) Fails High.
+25 min TS (SRO) 4 AFP N (RO, SRO) Fire in Auxiliary Building Fire Area AC.
+40 min 13_89 TS (SRO) Centrifugal Charging Pump (1-02) Manual Start Required.
5 RX16A C (RO) Power Operated Relief Valves (PCV-455A/456) Fail Open.
+45 min RX16B Reactor Trip Required.
6 RCR23 M (RO, BOP, SRO) Power Operated Relief Valve Block Valve (1/1-8000A) Fails Open
+50 min upon Breaker Trip.
7 RP07A C (RO) Train A Safety Injection Fails to Automatically Actuate.
+55 min RP07B Train B Safety Injection Fails to Automatically Actuate.
8 RH01D C (BOP) Residual Heat Removal Pump (1-02) Safety Injection Sequencer
+55 min Start Failure.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 8 Total malfunctions (5-8) 2 Malfunctions after EOP entry (1-2) 4 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) 3 Critical tasks (2-3)
CPNPP NRC 2014 Simulator Scenario 2 Draft Submittal
Scenario Event Description NRC Scenario 2 SCENARIO
SUMMARY
NRC 2 The crew will assume the watch at 100% power with no scheduled activities per IPO-003A, Power Operations.
The first event is a low failure of Main Steam Header Pressure Transmitter (PT-507). The crew enters ABN-709, Steam Header Pressure Instrument Malfunction, Section 3.0, and places the Main Feedwater Pump Master Speed Control in MANUAL and restore required Steam Generator levels. The controller will remain in MANUAL and may require adjustment when the Steam Generator Level Transmitter fails later in the scenario.
The next event 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 Power Operated Relief Valve (PORV) and its associated Block Valve, 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.
When plant conditions are stable a high failure of a Steam Generator (1-03) Level Transmitter will occur. 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 plant parameters are restored to normal, a fire alarm in Auxiliary Building Fire Area AC will be initiated. The crew enters ABN-805A, Response to Fire in the Auxiliary Building or the Fuel Building, Section 3.0. Actions include placing the Train B Centrifugal Charging Pump in service. The fire will continue to spread in the Auxiliary Building resulting in the inadvertent opening of both Power Operated Relief Valves (PORVs) as addressed in ABN-805A, Section 7.0, and will require a manual Reactor Trip.
The crew will enter and perform actions of EOP-0.0A, Reactor Trip or Safety Injection. The Power Operated Relief Valves will fail to close and one PORV Block Valve breaker will trip before the valve closes resulting in a Small Break Loss of Coolant Accident. The crew will then transition from EOP-0.0A to EOP-1.0A, Loss of Reactor or Secondary Coolant, in preparation for an eventual cooldown and depressurization.
The scenario includes a failure of both trains of Safety Injection to automatically actuate along with a Train B Residual Heat Removal Pump that fails to start upon initiation of the Safety Injection Sequencer.
This scenario is terminated when a cooldown is commenced via the Steam Dump Valves in EOS-1.2A, Post LOCA Cooldown and Depressurization.
Risk Significance:
Failure of risk important system prior to trip: Train A Centrifugal Charging Pump Risk significant core damage sequence: Small Break LOCA Risk significant operator actions: Manually Initiate Safety Injection Trip Reactor Coolant Pumps Manually Start Train B RHR Pump Initiate RCS Cooldown CPNPP NRC 2014 Simulator Scenario 2 Draft Submittal
Scenario Event Description NRC Scenario 2 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP INITIALIZE to IC-18 and LOAD LC22 NRC Scenario 2.
EVENT REM. MALF. DESCRIPTION DEMAND INITIATING FUNC. VALUE PARAMETER SETUP RP07A Train A Safety Injection Auto Actuation Failure FAIL K0 RP07B Train B Safety Injection Auto Actuation Failure FAIL K0 RH01D RHR Pump (1-02) SI Sequencer Start Failure FAIL K0 1 RX12 Main Steam Header (PT-507) Failure 200 psig K1 2 RX08A Pressurizer Pressure Channel (PT-455) Failure 2500 psig K2 3 RX04C SG (1-03) Level Transmitter (LT-553) Failure 100% K3 4 AFP 13_89 Fire in Auxiliary Building Fire Area AC ALARM K4 4 CVR16A CCP 1-01 Local Breaker Trip TRIP** K5 4 CVR16 CCP 1-01 Pump Breaker Trip TRIP** K5
- NOTE: EXECUTE remote function CVR16A first, THEN remote function CVR16.
4 CVR05 CCP (1-01) Auxiliary Lube Oil Pump OFF K6 4 CVR06 CCP (1-02) Auxiliary Lube Oil Pump AUTO K8 5 RX16A PORV (PCV-455A) Failure 100% K7 5 RX16B PORV (PCV-456) Failure 100% K7 6 RCR23 PORV Block Valve (1/1-8000A) Breaker Failure OPEN K7 6 A10B_78 1-ALB-10B, Window 2.20 - SFGD BLDG MCC ALARM K7 1EB-1/1EB-3 ANY MOV OVRLOAD 7 RP07A Train A Safety Injection Auto Actuation Failure FAIL K0 7 RP07B Train B Safety Injection Auto Actuation Failure FAIL K0 8 RH01D RHR Pump (1-02) SI Sequencer Start Failure FAIL K0 CPNPP NRC 2014 Simulator Scenario 2 Draft Submittal
Scenario Event Description NRC Scenario 2 Simulator Operator: INITIALIZE to IC-18 and LOAD LC22 NRC Scenario 2.
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 2014 Simulator Scenario 2 Draft Submittal
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Evvent # 1 Page 5 of 33 Event Desccription: Maiin Steam Head der Pressure Trransmitter Failu ure Time Position n Appliccants Actions o or Behavior Simulato or Operatorr: When dire ected, EXEC CUTE Eventt 1 (Key 1).
- RX12, R Steamm Header Pressure Tra ansmitter (P PT-507) failss low.
Indicatioons Availab ble:
8A-1.8 / 2.8 / 3.8 / 4.8 - SG 1 / 2 / 3 / 4 STEA AM & FW F FLO MISMAT TCH (may o or may not a alarm) 1-PI-507 - MS HDR PRESS indication fails s low
+30 secs s BOP RESPO OND to Annu unciator Alarrm Procedurres.
BOP REPOR RT PT-507, Steam S Head der Pressure e Channel has failed low w.
DIRECT T implementation of AB N-709, Stea am Line Presssure, Steam m Header US Pressure, Turbine 1st Stage Pre essure, and Feed Header Pressure Instrument Malfunc ction, Sectio on 3.0.
CHECK K 1-PI-507, MSM HDR PR RESS indicatting LOWER R than Main Steam BOP Line Prressure. [Ste ep 3.3.1]
BOP MANUA ALLY CONT TROL Feedw water Pumpss. [Step 3.3.2 2]
PLLACE 1-SK-5 509A, FWPT T MASTER S SPD CTRL iin MANUAL..
[Sttep 3.3.2.a]
ADDJUST 1-SK K-509A to ma aintain Feedwater Header pressure GREATER TH HAN Main Stteam Line prressure. [Ste ep 3.3.2.b]
BOP MONIT TOR Steam Generator G L evels: [Step p 3.3.3]
VERIFY SG lev vels - STAB BLE AT OR T TRENDING TO NORMA AL PRROGRAM. [S Step 3.3.3.a]
VERIFY Feedw water Contro ol Valves - R RESPONDIN NG TO DEM MAND SIGGNAL. [Step 3.3.3.b]
US DETER RMINE Requ uired Operattional Mode of Steam Du umps: [Step 3.3.4]
CHHECK 43/1-S SD, STM DM MP MODE SE ELECT Swittch in - TAVEE.
[Steep 3.3.4.a]
VERIFY TAVE AND A steam p pressure - S STABLE. [Ste ep 3.3.4.b]
CPNPP NRC 2014 Simulator S Sccenario 2 Dra aft Submittaal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 1 Page 6 of 33 Event
Description:
Main Steam Header Pressure Transmitter Failure Time Position Applicants Actions or Behavior Examiner Note: Time constraints will prevent repairs to PT-507. 1-SK-509A, FWPT MASTER SPD CTRL will remain in MANUAL for the duration of the scenario.
MANUALLY CONTROL 1-SK-509A, FWPT MASTER SPD CTRL to US MAINTAIN differential pressure (ramp from 80 psid @ 20% power to 181 psid @ 100% power. [Step 3.3.5]
US INITIATE a SMART Form per STA-421. [Step 3.3.6]
+10 min US INITIATE repairs per STA-606. [Step 3.3.7]
When plant conditions are stable, or at Lead Evaluators discretion, PROCEED to Event 2.
CPNPP NRC 2014 Simulator Scenario 2 Draft Submittal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 2 Evvent # 2 Page 7 of 33 Event Desccription: Pressurizer Pressure Transmitte er Failure Time Position n Appliccants Actions o or Behavior Simulato or Operatorr: When dire ected, EXEC CUTE Eventt 2 (Key 2).
- RX08A, R Presssurizer Pre essure Cha annel (PT-45 55) fails hig gh.
Indicatioons Availab ble:
5B-1.6 - PRZR LO PRESS P PORRV 456 BLK K 5B-2.6 - PRZR LO PRESS P PORRV 455A BL LK 5B-3.1 - PRZR POR RV OUT TEM MP HI 5B-4.1 - PRZR ANY Y SFTY RLF VLV OUT TEMP T HI 5C-1.4 - PORV 455A A / 456 NOTT CLOSE 5C-2.1 - PRZR PRE ESS HI 5C-3.1 - PRZR 1 OF F 4 PRESS HI H 5C-3.3 - PRZR PRE ESS LO BAC CKUP HTRS S ON 1-PI-455A A, PRZR PR RESS CHAN N I indicatioon failed hig gh
+1 min RO RESPO OND to Annu unciator Alarrm Procedurres.
RO RECOG GNIZE PRZR R pressure llowering.
DIRECT T performan nce of ABN-7 705, Pressurizer Pressu ure Malfunction, US Section n 2.0.
Examine er Note: Diiamond step ps () are In nitial Operattor Actions s.
C [Sttep 2.3.1]
RO PLLACE 1/1-PC CV-455A, PR RZR PORV iin CLOSE. ((Step 2.3.1 R RNO]
RO PLLACE 1/1-8000A, PRZR PORV BLK K VLV in CLO OSE. [Step 22.3.1 RNO]
RO PLACE E 1-PK-455A A, PRZR MA STER PRES SS CTRL in MANUAL. [Step 2.3.2]
RO ADJUS ST 1-PK-455 5A for curren nt RCS presssure. [Step 2 2.3.3]
CPNPP NRC 2014 Simulator S Sccenario 2 Dra aft Submittaal
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Evvent # 2 Page 8 of 33 Event Desccription: Pressurizer Pressure Transmitte er Failure Time Position n Appliccants Actions o or Behavior TRANS SFER 1/1-PS S-455F, PRZ ZR PRESS C CTRL CHAN N SELECT to o an RO Alternate Controllin ng Channel. [Step 2.3.4]
RO PLACE E 1-PK-455A A, PRZR MA STER PRES SS CTRL in AUTO. [Ste ep 2.3.5]
VERIFY Y automatic control resto oring Pressu urizer pressuure to 2235 PSIG.
[Step 2.3.6]
ENSUR RE valid cha annel to reco order 1/1-PS-455G, 1-PR R-455 PRZR R PRESS RO SELEC CT. [Step 2.3 3.7]
IF neceessary, RETURN PORV V closed in Step 1 RNO tto AUTO and d ENSURE RO it remaiins CLOSED D. [Step 2.3. 8]
PLLACE 1/1-PC CV-455A, PR RZR PORV iin AUTO.
RO PLACE E 1/1-8000A,, PRZR POR RV BLK VLV V in OPEN. ((Step 2.3.9]
Within one o hour, VE ERIFY PCIP P Window 2.6 - PRZR PRESS SI BL LK PERM US/RO O P DARK. [Step 2.3.10]
VERIFY Y other instrruments on ccommon insttrument line - NORMAL L.
US/RO O
[Step 2.3.11]
VEERIFY Loop 1 Instrumen nts LT-459 re esponding normally per Atttachment 1.
CPNPP NRC 2014 Simulator S Sccenario 2 Dra aft Submittaal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 2 Page 9 of 33 Event
Description:
Pressurizer Pressure Transmitter Failure Time Position Applicants Actions or Behavior
+10 min US EVALUATE Technical Specifications. [Step 2.3.14]
LCO 3.3.1.E, Reactor Trip System Instrumentation.
(Functions 6, Overtemperature N-16 & 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 />.
US INITIATE a work request per STA-606. [Step 2.3.15]
CPNPP NRC 2014 Simulator Scenario 2 Draft Submittal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 2 Page 10 of 33 Event
Description:
Pressurizer Pressure Transmitter Failure Time Position Applicants Actions or Behavior
+10 min US INITIATE a SMART Form per STA-421. [Step 2.3.16]
When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 3.
CPNPP NRC 2014 Simulator Scenario 2 Draft Submittal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 2 Evvent # 3 Page 11 of 33 Event Desccription: Steam Generator Level Channell Failure Time Position n Appliccants Actions o or Behavior Simulato or Operatorr: When dire ected, EXEC CUTE Eventt 3 (Key 3).
- RX04C, R Steaam Generattor 1-03 Lev vel Channell (LT-553) fa ails high.
Indicatioons Availab ble:
8A-3.8 - SG 3 STM & FW FLO MISMATCH M H 8A-3.12 - SG 3 LVL L DEV 1-LI-553,, SG 3 LVL (NR) CHAN II indicatio on failed hig gh
+30 sec c BOP RESPO OND to Annu unciator Alarrm Procedurres.
BOP RECOG GNIZE Steam Generato or 1-03 level lowering.
Examine er Note: Stteam Generrator (SG) Level L Chann nel II failing HIGH will c cause the Feedwater Coontrol Valvee to CLOSE E, thereby lo owering SG level. Unit 1 LOW LEV VEL REEACTOR TR RIP is at 38% %.
DIRECT T performannce of ABN-7 710, Steam Generator L Level Instrummentation US Malfuncction, Sectio on 2.0.
RECOG GNIZE Steam Generato or 1-03 Levell Channel (L LT-553) failed high AND BOP VERIFY Y controlling g level chann nel - FAILED D. [Step 2.3..1]
PLACE E 1-FK-530, SGS 3 FW FL LO CTRL in MANUAL and CONTRO OL level.
[Step 2.3.2]
BOP VERIFY Y instrumentts on commo on instrument line - NO ORMAL. [Step 2.3.3]
VEERIFY Loop 3 Instrumen nt FT-533 ressponding no ormally per Atttachment 1.
CPNPP NRC 2014 Simulator S Sccenario 2 Dra aft Submittaal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 2 Evvent # 3 Page 12 of 33 Event Desccription: Steam Generator Level Channell Failure Time Position n Appliccants Actions o or Behavior VERIFY Y all HI-HI le evel bistable e windows on n TSLB-3 for SG 1 DARK.
[Step 2.3.4]
OBBSERVE TSLB-3, Windo ow 1.4 - SG G 3 LVL HI-H HI LB-539A iss DARK.
OBBSERVE TSLB-3, Windo ow 3.4 - SG G 3 LVL HI-H HI LB-538A iss DARK.
OBBSERVE TSLB-3, Windo ow 4.4 - SG G 3 LVL HI-H HI LB-537A iss DARK.
BOP VERIFY Y automatic SG level co ontrol - DESIRED: [Step p 2.3.5]
OBBSERVE alte ernate level control chan nnel 1-LI-5399A indicationn NORMAL.
[Sttep 2.3.5.a]
DEETERMINE automatic a levvel control d desired by U Unit Supervissor.
[Sttep 2.3.5.b]
BOP SELEC CT Alternate Channel: [S Step 2.3.6]
PLLACE 1-LS-5 539C, SG 3 LVL CHAN S SELECT to the LY-539 position.
BOP VERIFY Y affected SG S level is sttable at prog gram level: [SStep 2.3.7]
OBBSERVE Fee edwater and d Steam flow ws - MATCH HED.
OBBSERVE Ste eam Genera ator Level - S STABLE AT T PROGRAM M.
PLACE E 1-FK-530, SG S 3 FW FL LO CTRL in AUTO and MONITOR o operation.
[Step 2.3.8]
CPNPP NRC 2014 Simulator S Sccenario 2 Dra aft Submittaal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 3 Page 13 of 33 Event
Description:
Steam Generator Level Channel Failure Time Position Applicants Actions or Behavior US EVALUATE Technical Specifications. [Step 2.3.11]
LCO 3.3.1.E, Reactor Trip System Instrumentation.
(Function 14, Steam Generator Water Level Low-Low)
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 3.3.2.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.
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 />.
US INITIATE a work request per STA-606. [Step 2.3.12]
+10 min US INITIATE a SMART Form per STA-421. [Step 2.3.13]
When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 4.
CPNPP NRC 2014 Simulator Scenario 2 Draft Submittal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 2 Evvent # 4 Page 14 of 33 Event Desccription: Fire e in Auxiliary Bu uilding Time Position n Appliccants Actions o or Behavior Simulato or Operatorr: When dire ected, EXEC CUTE Eventt 4 (Key 4).
- AFP13_89, A Fire F in Auxiiliary Buildi ng Fire Are ea AC.
Indicatioons Availab ble:
Fire Dete ection Main n Control Pa anel Auxiliaary Building g Array Auxiliaryy Building Window W 5.8 - UNIT 1 CCP C ROOM T TRN A
+30 secs s RO/BOP RESPO OND to Annu unciator Alarrm Procedurres.
RO/BOP REPOR RT fire alarm m in the Unit 1 Train A C Centrifugal Charging Pum mp Room.
Simulato or Operatorr: When con ntacted, REPORT lightt layer of sm moke in the Unit 1 Train n A CCP Rooom. Also REPORTR no o visible flam mes or light.
Examine er Note: Th he Unit Sup pervisor may y enter ABN N-901, Fire Protection System Ala arms or Ma alfunctions s prior to enntering ABN N-805A. ABN N-901 provid des directio on to the sppecific 800 series s ABN.
DIRECT T implementation of AB N-805A, Re esponse to F Fire in the Auuxiliary US Building g or the Fueel Building, S Section 3.0.
US VERIFY Y Reactor Trip - NOT IN N PROGRES SS. [Step 3.33.1]
US REFER R to appropriiate Fire Preeplan Instrucction. [Step 3 3.3.2]
Simulato or Operatorr: When con ntacted, REPORT as S hift Manage er to continue in ABN-8 805A.
CPNPP NRC 2014 Simulator S Sccenario 2 Dra aft Submittaal
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Evvent # 4 Page 15 of 33 Event Desccription: Fire e in Auxiliary Bu uilding Time Position n Appliccants Actions o or Behavior CONSU ULT with Shift Manager to determine e if performa ance of proccedure is US necessary based on o fire asses sment and ccurrent plantt conditions.
[Step 3.3.3]
Simulato or Operatorr: When con ntacted, REPORT that Shift Manag ger will adddress Emerg gency Plan.
US REFER R to EPP-201 1. [Step 3.3..4]
If requirred, PERFO ORM an EME ERGENCY S START on D Diesel Generrator 1-01.
US
[Step 3.3.5]
If erratic equipmentt operation o occurs, PER RFORM ABN N-301, Instruument Air US System m Malfunctionn, while conttinuing with this procedu ure. [Step 3.3.6]
Examine er Note: When W it is deetermined thhat Train A Centrifugall Charging P Pump (CCP P) 1-01 mustt bee tripped, th he crew sho ould start Trrain B CCP 1-02.
Simulato or Operatorr: When con ntacted, EXECUTE rem mote functio on CVR06 (K Key 8) for CCentrifugal Chharging Pum mp 1-02 Auxiliary Lube e Oil Pump..
Simulato or Operatorr: When con ntacted, EXECUTE rem mote functio ons CVR16A A, CCP 1-01 1 Local Brreaker Trip (Key 5) THE EN CVR16, CCP 1-01 P Pump Break ker Trip (Keey 5).
DISPAT TCH NEO to o Train A Sw witchgear Ro oom to MANUALLY TRIP P RO/BOP CCP 1--01 motor brreaker AND REMOVE co ontrol power fuses. [Ste ep 3.3.7]
CPNPP NRC 2014 Simulator S Sccenario 2 Dra aft Submittaal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 4 Page 16 of 33 Event
Description:
Fire in Auxiliary Building Time Position Applicants Actions or Behavior Simulator Operator: When contacted, EXECUTE remote function CVR05 (Key 6) for Centrifugal Charging Pump 1-01 Auxiliary Lube Oil Pump.
US EVALUATE Technical Specifications. [Step 3.3.8]
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.
Examiner Note: The next event, opening of both PORVs, is a result of the fire spreading through the Auxiliary Building.
US INITIATE a Condition Report per STA-421. [Step 3.3.9]
When Technical Specifications have been addressed or at Lead Evaluators discretion, PROCEED to Events 5, 6, 7, and 8.
CPNPP NRC 2014 Simulator Scenario 2 Draft Submittal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5, 6, 7, & 8 Page 17 of 33 Event
Description:
Power Operated Relief Valve and Block Valve Failures / Small Break Loss of Coolant Accident /
Automatic Safety Injection Signal Failure / Residual Heat Removal Pump SI Sequencer Failure Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Events 5, 6, 7, and 8 (Key 7).
- RX16A, Power Operated Relief Valve (PCV-455A) fails open.
- RX16B, Power Operated Relief Valve (PCV-456) fails open.
- RCR23, Power Operated Relief Valve Block Valve (1/1-8000A) fails open.
- RP07A, Automatic Train A Safety Injection Signal failure.
- RP07B, Automatic Train B Safety Injection Signal failure.
- RH01D, Train B RHR Pump Safety Injection Sequencer start failure.
Indications Available:
5B-1.6 - PRZR LO PRESS PORV 456 BLK 5B-2.6 - PRZR LO PRESS PORV 455A BLK 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
+30 secs RO RESPOND to Annunciator Alarm Procedures.
RECOGNIZE PRZR pressure LOWERING with heaters OFF and PRZR RO Spray Valves CLOSED.
DETERMINE 1/1-PCV-455A and 1/1-PCV-456, PRZR PORVs NOT closed; RO CLOSE both PORVs.
DETERMINE 1/1-PCV-455A and 1/1-PCV-456, PRZR PORVs will NOT RO CLOSE.
RO CLOSE 1/1-8000A and 1/1-8000B, PRZR PORV BLK VLVs.
RO DETERMINE 1/1-8000A, PRZR PORV BLK VLV will NOT CLOSE.
RO/BOP DETERMINE Reactor Trip required and manually TRIP Reactor.
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.
CPNPP NRC 2014 Simulator Scenario 2 Draft Submittal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5, 6, 7, & 8 Page 18 of 33 Event
Description:
Power Operated Relief Valve and Block Valve Failures / Small Break Loss of Coolant Accident /
Automatic Safety Injection Signal Failure / Residual Heat Removal Pump SI Sequencer Failure Time Position Applicants Actions or Behavior Examiner Note: The following steps are from EOP-0.0A, Reactor Trip or Safety Injection.
RO VERIFY Reactor Trip: [Step 1]
VERIFY Reactor Trip Breakers - OPEN. [Step 1.a]
VERIFY Neutron flux - DECREASING. [Step 1.a]
VERIFY all Control Rod Position Rod Bottom Lights - ON. [Step 1.b]
BOP VERIFY Turbine Trip: [Step 2]
VERIFY all HP Turbine Stop Valves - CLOSED. [Step 2]
BOP VERIFY Power to AC Safeguards Buses: [Step 3]
VERIFY AC Safeguards Buses - AT LEAST ONE ENERGIZED.
[Step 3.a]
VERIFY both AC Safeguards Buses - ENERGIZED. [Step 3.b]
RO CHECK if SI is actuated. [Step 4.a]
RO CHECK if SI is required. [Step 4.a RNO]
VERIFY Steam Line Pressure < 610 PSIG. [Step 4.a RNO]
VERIFY Pressurizer Pressure < 1820 PSIG. [Step 4.a RNO]
VERIFY Containment Pressure > 3.0 PSIG. [Step 4.a RNO]
CRITICAL TASK Manually Initiate Safety Injection due to Failure to Automatically Actuate Prior STATEMENT to Exiting EOP-0.0A. Reactor Trip or Safety Injection.
RO Manually INITIATE both Trains of Safety Injection. [Step 4.a RNO]
CRITICAL PLACE 1/1-SIA2, SI MAN ACT Switch to ACT position at CB-07 and TASK DETERMINE SI has actuated.
VERIFY Both Trains SI Actuated: [Step 4.b]
SI Actuated blue status light - ON NOT FLASHING.
CPNPP NRC 2014 Simulator Scenario 2 Draft Submittal
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Eveent # 5,, 6, 7, & 8 Page 19 of 33 Event Desccription: Powwer Operated Relief R Valve and Block Valve Failures / Sma all Break Loss o of Coolant Accident /
Automatic Safety Injection Signa al Failure / Res idual Heat Rem moval Pump SII Sequencer Fa ailure Time Position n Appliccants Actions o or Behavior Examine er Note: EO OP-0.0A, Atttachment 2 steps perfformed by B BOP are ide entified laterr in the sccenario. The e RCPs may y be tripped d if subcoolling is obse erved to be < 25ºF.
Trip Reactor Coolan nt Pumps witthin 10 minu utes upon a L Loss of Subc cooling per CRITIICAL TASK EOP-0.0 0A, Reactor TripT or Safetty Injection, o or EOP-1.0A A, Loss of Reactor or STAATEMENT Second dary Coolant, Foldout Pag ges.
US CHECK K If RCPs Sh hould Be Sto opped:
VEERIFY RCS subcooling s l ess than 25ºF (55ºF FO OR ADVERS SE COONTAINMEN NT).
VEERIFY ECCS S Pumps (CC CP or SI) - A AT LEAST O ONE RUNNING.
CRITICAL L RO TASK STOP all RCPs s.
INITIAT TE Proper Sa afeguards E Equipment O Operation Pe er Attachmen nt 2.
US/BOP
[Step 5))
RO VERIFY Y AFW Align nment: [Step p 6]
VEERIFY both MDAFWM Pum mps - RUNN NING. [Step 6.a]
PLA ACE TDAFW W Pump in P PULLOUT per Foldout P Page. [Step 6 6.b]
VEERIFY AFW total t flow - G GREATER T THAN 460 G GPM. [Step 6 6.c]
VEERIFY AFW valve alignm ment - PROP PER ALIGNM MENT. [Step p 6.d]
CPNPP NRC 2014 SimulatorS Sccenario 2 Dra aft Submitta al
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5, 6, 7, & 8 Page 20 of 33 Event
Description:
Power Operated Relief Valve and Block Valve Failures / Small Break Loss of Coolant Accident /
Automatic Safety Injection Signal Failure / Residual Heat Removal Pump SI Sequencer Failure Time Position Applicants Actions or Behavior RO VERIFY Containment Spray NOT Required: [Step 7]
VERIFY 1-ALB-2B, Window 1-8, CS ACT - NOT ILLUMINATED.
[Step 7.a]
VERIFY 1-ALB-2B, Window 4-11, CNTMT ISOL PHASE B ACT - NOT ILLUMINATED. [Step 7.a]
VERIFY Containment pressure - LESS THAN 18.0 PSIG.
[Step 7.a]
VERIFY Containment Spray Heat Exchanger Outlet Valves - CLOSED.
[Step 7.b]
VERIFY Containment Spray Pumps - RUNNING. [Step 7.c]
RO CHECK if Main Steam lines should be ISOLATED: [Step 8]
VERIFY Containment pressure - GREATER THAN 6.0 PSIG. [Step 8.a]
VERIFY Steam Line pressure - LESS THAN 610 PSIG. [Step 8.a]
GO to Step 9. [Step 8.a RNO]
RO CHECK RCS Temperature: [Step 9]
VERIFY RCS Average Temperature - STABLE AT OR TRENDING TO 557°F. [Step 9]
If temperature less than 557°F, PERFORM the following:
[Step 9 RNO]
STOP dumping steam. [Step 9.a RNO]
RO CHECK PRZR Valve Status: [Step 10]
VERIFY PRZR Safeties - CLOSED. [Step 10.a]
VERIFY Normal PRZR Spray Valves - CLOSED. [Step 10.b]
VERIFY PORVs - CLOSED. [Step 10.c]
If PRZR pressure less than 2235 PSIG, manually CLOSE PORVs.
[Step 10.c RNO]
If any PORV can NOT be closed, manually CLOSE PORV block valves. [Step 10.c RNO]
DETERMINE 1/1-8000A, PRZR PORV block valve will NOT CLOSE. [Step 10.c RNO]
CPNPP NRC 2014 Simulator Scenario 2 Draft Submittal
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Eve ent # 5,, 6, 7, & 8 Page 21 of 33 Event Desccription: Powwer Operated Relief R Valve and Block Valve Failures / Sma all Break Loss o of Coolant Accident /
Automatic Safety Injection Signa al Failure / Res idual Heat Remmoval Pump SII Sequencer Fa ailure Time Position n Appliccants Actions o or Behavior GO to EO OP-1.0A, Losss of Reactor or Secondary Coolant,, Step 1.
[Step 10.c c RNO]
US TRANS SITION to EO OP-1.0A, Lo ss of Reacto or or Second dary Coolant, Step 1.
Examine er Note: EO OP-1.0A, Lo oss of Reac ctor or Seco ondary Coollant steps b begin here.
Trip Reactor Coolan nt Pumps witthin 10 minu utes upon a L Loss of Subc cooling per CRITIICAL TASK EOP-0.0 0A, Reactor Trip T or Safetty Injection, o or EOP-1.0A A, Loss of Reactor or STAATEMENT Second dary Coolant, Foldout Pag ges.
US CHECK K If RCPs Sh hould Be Sto opped: [Step p 1]
VE ERIFY RCS subcooling s l ess than 25ºF (55ºF FO OR ADVERS SE CO ONTAINMEN NT). [Step 1..a]
VE ERIFY ECCS S Pumps (CC CP or SI) - A AT LEAST O ONE RUNNING.
[Step 1.b]
CRITICAL L RO TASK STOP all RCPs s. [Step 1.c]
RO/BOP CHECK K if Any Stea am Generato or Is Faulted d: [Step 2]
VE ERIFY any SteamS Generrator pressure - DECRE EASING IN A AN UN NCONTROLLED MANN ER. [Step 2..a]
GO to Ste ep 3. [Step 2 2.a RNO]
CPNPP NRC 2014 SimulatorS Sccenario 2 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Eveent # 5,, 6, 7, & 8 Page 22 of 33 Event Desccription: Powwer Operated Relief R Valve and Block Valve Failures / Sma all Break Loss o of Coolant Accident /
Automatic Safety Injection Signa al Failure / Res idual Heat Remmoval Pump SII Sequencer Fa ailure Time Position n Appliccants Actions o or Behavior US CHECK K Intact Stea am Generato or Levels: [SStep 3]
VE ERIFY Narrow range leve el - GREAT TER THAN 4 43% (50% FO OR AD DVERSE CO ONTAINMEN NT). [Step 3.a]
CO ONTROL AF FW flow to m maintain narro ow range levvel between n 43% (50%
FO OR ADVERS SE CONTAIN NMENT) and d 60%. [Step p 3.b]
US CHECK K Secondary y Radiation N NORMAL: [S Step 4]
VE ERIFY Conde enser off ga s radiation - NORMAL.
VE ERIFY Main Steam Line radiation - N NORMAL.
VE ERIFY SG Bllowdown Sa ample Radiation Monitorr - NORMAL L.
VE ERIFY levels s in all Steam m Generatorrs - NORMA AL.
US CHECK K PRZR POR RVs and Blo ock Valves: ((Step 5]
VE ERIFY powerr to Block Va alves - AVA AILABLE. [Sttep 5.a]
VE ERIFY PORV Vs - CLOSE ED. [Step 5.b b]
If PRZR pressure p lesss than 2235 PSIG, manu ually CLOSE E PORVs.
[Step 5.b RNO]
If any POR RV can NOT T be closed, manually C CLOSE PORV V block valves. [Step 5.b RNO O]
VE ERIFY Block Valves - AT T LEAST ON NE OPEN. [S Step 5.c]
Manually OPEN O one P PRZR PORV V block valve unless it w was closed to isolate an a open PO ORV. [Step 5 5.c RNO]
US/RO O CHECK K if ECCS Flow Should B Be Reduced d: [Step 6]
VE ERIFY Secon ndary heat ssink condition ns - SATISF FIED. [Step 6.a]
VERIFY to otal AFW flo ow to Intact S SGs - GREA ATER THAN N 460 GPM.
VERIFY in ntact SG NR R level - GREATER THA AN 43% (50% FOR ADVERSE E CONTAIN MENT).
CPNPP NRC 2014 SimulatorS Sccenario 2 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Eve ent # 5,, 6, 7, & 8 Page 23 of 33 Event Desccription: Powwer Operated Relief R Valve and Block Valve Failures / Sma all Break Loss o of Coolant Accident /
Automatic Safety Injection Signa al Failure / Res idual Heat Remmoval Pump SII Sequencer Fa ailure Time Position n Appliccants Actions o or Behavior VE ERIFY RCS subcooling s - GREATER R THAN 25°F F (55°F FOR R AD DVERSE CO ONTAINMEN NT). [Step 6.b b]
GO to Ste ep 7 and OB SERVE CAU UTIONS prio or to Step 7..
[Step 6.b RNO]
RO/BOP RESET T ESF Actua ation Signalss. [Step 7]
RO/BOP PLA ACE both EDG EMERG G STOP/STA ART handsw witches in ST TART.
[Step 7.a]
Examine er Note: When W Safety Injection and SI Seque encers are properly RE ESET, Annu unciator 1-ALB-2B, Window 2.8 - SFGD SEQ QR TRN A/B B AUTO TES ST TRBL, w will RESET.
RO/BOP RE ESET SI. [Ste ep 7.b]
DEPRESS S 1/1-SIRA, TRAIN A SII RESET pusshbutton.
DEPRESS S 1/1-SIRB, TRAIN B SII RESET pusshbutton.
RO/BOP RE ESET SI Seq quencers. [S tep 7.c]
At SI Sequ uencer Train n A Cabinet,, DEPRESS SI SEQR R RESET green pus shbutton then n PLACE ON N/RESET to oggle switch in RESET.
PLACE ON/RESET to oggle switch in ON.
At SI Sequ uencer Train n B Cabinet,, DEPRESS SI SEQR R RESET green pus shbutton then n PLACE ON N/RESET to oggle switch in RESET.
PLACE ON/RESET to oggle switch in ON.
CPNPP NRC 2014 SimulatorS Sccenario 2 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Eve ent # 5,, 6, 7, & 8 Page 24 of 33 Event Desccription: Powwer Operated Relief R Valve and Block Valve Failures / Sma all Break Loss o of Coolant Accident /
Automatic Safety Injection Signa al Failure / Res idual Heat Remmoval Pump SII Sequencer Fa ailure Time Position n Appliccants Actions o or Behavior RO/BOP RE ESET Containment Isola ation Phase A and Phase e B. [Step 7..d]
DEPRESS S 1/1-C1PAR RA, CNTMT T ISOL - PHASE A RES SET pushbutto on.
DEPRESS S 1/1-C1PAR RB, CNTMT T ISOL - PHASE A RES SET pushbutto on.
DEPRESS S 1/1-C1PBR RA, CNTMT T ISOL - PHASE B RES SET pushbutto on.
DEPRESS S 1/1-C1PBR RB, CNTMT T ISOL - PHASE B RES SET pushbutto on.
RO/BOP RE ESET Containment Spra y Signal. [Sttep 7.e]
DEPRESS S 1/1-CSRA A, TRAIN A C CS RESET p pushbutton.
DEPRESS S 1/1-CSRB B, TRAIN B C CS RESET p pushbutton.
US CHECK K If RHR Pum mps Should Be Stopped d: [Step 8]
VE ERIFY RCS pressure p -G GREATER T THAN 325 PSIG (425 PS SIG FOR RO/BOP AD DVERSE CO ONTAINMEN NT). [Step 8.a a.1)]
RO/BOP VE ERIFY RCS pressure p -S STABLE OR R INCREASIN NG. [Step 8.a.2)]
US GO to Step p 9. [Step 8.b b.2) RNO]
US CHECK K RCS and SG S Pressure es: [Step 9]
RO/BOP VE ERIFY RCS pressure p -S STABLE OR R DECREASING. [Step 9 9]
RO/BOP VE ERIFY all SG G pressures - STABLE O OR INCREA ASING. [Step p 9]
US CHECK K If Diesel Generators S hould Be Sttopped: [Step 10]
CPNPP NRC 2014 SimulatorS Sccenario 2 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Eve ent # 5,, 6, 7, & 8 Page 25 of 33 Event Desccription: Powwer Operated Relief R Valve and Block Valve Failures / Sma all Break Loss o of Coolant Accident /
Automatic Safety Injection Signa al Failure / Res idual Heat Remmoval Pump SII Sequencer Fa ailure Time Position n Appliccants Actions o or Behavior VE ERIFY AC Sa afeguards B Buses ENER RGIZED by O Offsite Power.
RO/BOP
[Sttep 10.a]
PLA ACE both EDG EMERG G STOP/STA ART handsw witches in ST TOP.
[Step 10.b]
US INITIAT TE Evaluatio on of Plant S Status. [Step 11]
RO/BOP VE ERIFY Cold Leg L Recircu lation capab bility: [Step 1 11.a]
VERIFY Train T A RHR R Pump - AV VAILABLE. [S Step 11.a.1))]
VERIFY CCW C to Trainn A RHR Pu ump - AVAIL LABLE. [Step 11.a.1)]
VERIFY 1/1-8811A, C CNTMT SMP P TO RHRP 1 SUCT ISO OL VLV -
AVAILABL LE. [Step 11 .a.1)]
VERIFY Train T B RHR R Pump - AV VAILABLE. [S Step 11.a.1))]
VERIFY CCW C to Trainn B RHR Pu ump - AVAIL LABLE. [Step 11.a.1)]
VERIFY 1/1-8811B, C CNTMT SMP P TO RHRP 2 SUCT ISO OL VLV -
AVAILABL LE. [Step 11 .a.1)]
VERIFY 1/1-8804A, R RHRP 1 TO CCP SUCT VLV - AVA AILABLE.
[Step 11.a a.2)]
VERIFY 1/1-8804B, R RHRP 2 TO SIP SUCT V VLV - AVAIL LABLE.
[Step 11.a a.2)]
CH HECK Auxilia ary Building and Safeguards Buildin ng radiation - NORMAL:
RO/BOP
[Sttep 11.b]
CHECK PC-11P monito ors - NORM MAL OR Notiify Radiation n Protection to PERFO ORM local Ra adiation Surrveys. [Step 11.b]
NO OTIFY Chem mistry to OBT TAIN RCS samples to assist in dete ermining US exttent of the accident. [Ste ep 11.c]
US CO ONTACT Pla ant Staff to E EVALUATE p plant equipm ment. [Step 1 11.d]
CPNPP NRC 2014 SimulatorS Sccenario 2 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Eve ent # 5,, 6, 7, & 8 Page 26 of 33 Event Desccription: Powwer Operated Relief R Valve and Block Valve Failures / Sma all Break Loss o of Coolant Accident /
Automatic Safety Injection Signa al Failure / Res idual Heat Remmoval Pump SII Sequencer Fa ailure Time Position n Appliccants Actions o or Behavior US CHECK K if RCS Coo oldown and Depressurizzation Is Req quired: [Stepp 12]
VEERIFY RCS pressure p -G GREATER T THAN 325 PSIG (425 PS SIG FOR RO/BOP ADDVERSE CO ONTAINMEN NT). [Step 12 2.a]
GO O to EOS-1.2 2A, Post LO OCA Cooldow wn and Deprressurization n, Step 1.
US
[Sttep 12.b]
Examine er Note: EO OS-1.2A, Po ost LOCA Cooldown C annd Depress surization, s steps begin here.
Stteps in [brackets] are from f the ass sociated EO OS-1.2A Atttachments.
RO/BOP [1.D] VERIFY V Diessel Generato ors - NOT R RUNNING. [S Step 1]
RO/BOP [1.D] VERIFY V SI - RESET. [Sttep 2]
RO/BOP [1.D] VERIFY V SI Sequencers - RESET. [S Step 3]
RO/BOP [1.D] VERIFY V Conttainment Iso olation Phase A and Pha ase B - RES SET.
[Step 4))
RO/BOP [1.D] VERIFY V Conttainment Sp pray Signal - RESET. [S Step 5]
RO/BOP [1.D] ESTABLISH E Instrument A Air and Nitro ogen to Conttainment. [S Step 6]
ESSTABLISH In nstrument Ai r: [Step 6.a]
CPNPP NRC 2014 SimulatorS Sccenario 2 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Eve ent # 5,, 6, 7, & 8 Page 27 of 33 Event Desccription: Powwer Operated Relief R Valve and Block Valve Failures / Sma all Break Loss o of Coolant Accident /
Automatic Safety Injection Signa al Failure / Res idual Heat Remmoval Pump SII Sequencer Fa ailure Time Position n Appliccants Actions o or Behavior VERIFY Air A Compresssor - RUNN NING. [Step 6 6.a.1)]
ESTABLIS SH Instrume ent Air to Containment: ((Step 6.a.2)]
ESSTABLISH Nitrogen: [Ste ep 6.b]
VERIFY ACCUM A 14 VENT CTR RL, 1-HC-943 3 - CLOSED D.
[Step 6.b.1)]
OPEN SI/PORV ACC CCUM N2 ISO OL VLV 1/1--8880. [Step p 6.b.2)]
BOP VERIFY Y all AC Bus ses - ENERG GIZED BY O OFFSITE PO OWER. [Step p 7]
RO DEENE ERGIZE PRZ ZR Heaters: [Step 8]
PLA ACE all PRZ ZR heater sw witches in O OFF position.. [Step 8.a]
COONSULT Plant Staff for a recommen nded minimu um indicated PRZR water level that will ensure e heaters are e covered. [S Step 8.b]
US CHECK K If RHR Pum mps Should Be Stopped d. [Step 9]
VEERIFY RHR Pumps P - ANNY RUNNING WITH SUCTION ALIG GNED TO RWWST. [Step 9.a] 9 CHHECK RCS pressure p -GGREATER T THAN 325 PS SIG (425 PS SIG FOR ADDVERSE CO ONTAINMEN NT). [Step 9.b b]
CHHECK RCS pressure p -SSTABLE OR INCREASIN NG. [Step 9..b]
STOP RHR Pu umps and PL LACE in stan ndby. [Step 9.c]
CPNPP NRC 2014 SimulatorS Sccenario 2 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Eve ent # 5,, 6, 7, & 8 Page 28 of 33 Event Desccription: Powwer Operated Relief R Valve and Block Valve Failures / Sma all Break Loss o of Coolant Accident /
Automatic Safety Injection Signa al Failure / Res idual Heat Remmoval Pump SII Sequencer Fa ailure Time Position n Appliccants Actions o or Behavior REESET RHR Auto A Switcho over. [Step 9 9.d]
US CHECK K Intact SG Levels:
L [Stepp 10]
VEERIFY narrow w range leve el - GREAT TER THAN 4 43% (50% FOR ADDVERSE CO ONTAINMEN NT): [Step 10 0.a]
COONTROL AF FW flow to m maintain narro ow range levvel between n 43% (50%
FOOR ADVERS SE CONTAIN NMENT) and d 60%. [Step p 10.b]
CRITIICAL TASK Initiate e Cooldown of Reactorr Coolant Sy ystem Priorr to Exiting EOS-1.2A, STAATEMENT Post LO OCA Cooldown and De epressuriza ation.
US INITIAT TE RCS Coo oldown to Co old Shutdow wn: [Step 11]
MA AINTAIN coo oldown rate iin RCS Cold d Legs - LES SS THAN 10 00°F/HR.
[Step 11.a]
Wh hen Pressuriizer pressure e LESS THA AN 1960 PS SIG - BLOCK K Low Main Steeam Pressurre SI signal. [Step 11.b]
CRITICAL L DUUMP steam to t atmosphe ere via Atmosspheric Relief Valves fro om intact TASK Steeam Generators. [Step 1 11.c]
When a RCS cooldo own is in prrogress, TE ERMINATE tthe scenario o.
CPNPP NRC 2014 SimulatorS Sccenario 2 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Eve ent # 5,, 6, 7, & 8 Page 29 of 33 Event Desccription: Powwer Operated Relief R Valve and Block Valve Failures / Sma all Break Loss o of Coolant Accident /
Automatic Safety Injection Signa al Failure / Res idual Heat Remmoval Pump SII Sequencer Fa ailure Time Position n Appliccants Actions o or Behavior Examine er Note: Th hese steps are perform med by the B BOP per EO OP-0.0A, Atttachment 2.
BOP VERIFY Y SSW Align nment: [Step p 1]
VERRIFY SSW Pumps P - RU UNNING. [Sttep 1.a]
VERRIFY Diesel Generator C Coolers SSW W return flow w. [Step 1.b))
BOP VERIFY Y Safety Inje ection Pump s - RUNNIN NG. [Step 2]
BOP VERIFY Y Containme ent Isolation Phase A - APPROPRIATE MLB LIGHT INDICA ATION (RED D WINDOWS S). [Step 3]
BOP VERIFY Y Containme ent Ventilatio on Isolation - APPROPR RIATE MLB LIGHT INDICA ATION (GRE EEN WINDO OWS). [Step 4]
BOP VERIFY Y CCW Pum mps - RUNN ING. [Step 5 5]
BOP VERIFY Y RHR Pumps - RUNNIING. [Step 6 6]
Ma anually STAR RT Train B R RHR Pump 1 1-02. [Step 6 RNO]
BOP VERIFY Y Proper CV VCS Alignme ent: [Step 7]
VEERIFY Train B CCP 1-02 2 - RUNNING. [Step 7.a a]
VEERIFY Letdow wn Relief Va alve Isolation n: [Step 7.b))
VERIFY Le etdown Orificce Isolation Valves - CL LOSED. [Ste ep 7.b.1)]
VERIFY Le etdown Isola ation Valves 1/1-LCV-45 59 & 1/1-LCV V-460 -
CLOSED. [Step[ 7.b.2)))
CPNPP NRC 2014 SimulatorS Sccenario 2 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Eve ent # 5,, 6, 7, & 8 Page 30 of 33 Event Desccription: Powwer Operated Relief R Valve and Block Valve Failures / Sma all Break Loss o of Coolant Accident /
Automatic Safety Injection Signa al Failure / Res idual Heat Remmoval Pump SII Sequencer Fa ailure Time Position n Appliccants Actions o or Behavior BOP VERIFY Y ECCS flow w: [Step 8]
CCCP SI flow indicators - C CHECK FOR R FLOW. [Ste ep 8.a]
RCCS pressure - LESS THA AN 1700 PS SIG (1800 PS SIG FOR AD DVERSE COONTAINMEN NT). [Step 8. b]
SIPP discharge flow indicato or - CHECK K FOR FLOW W. [Step 8.c))
RCCS pressure - LESS THA AN 325 PSIG (425 PSIG G FOR ADV VERSE COONTAINMEN NT). [Step 8. d]
GO to Step p 9. [Step 8.d d RNO]
BOP VERIFY Y Feedwaterr Isolation C omplete: [Sttep 9]
Fee edwater Isollation Valvess - CLOSED D.
Fee edwater Isollation Bypasss Valves - C CLOSED.
Fee edwater Byp pass Controll Valves - C CLOSED.
Fee edwater Con ntrol Valves - CLOSED..
BOP VERIFY Y Diesel Gen nerators - R RUNNING. [S Step 10]
BOP VERIFY Y Monitor Lig ghts for SI L Load Shedding on 1-MLB B-9 and 1-M MLB10 -
LIT. [Step 11]
BOP VERIFY Y Proper SI alignment - PROPER M MLB LIGHT INDICATION N.
[Step 12 2]
BOP INITIAT TE periodic monitoring m o of Spent Fue el Cooling (G GD_SFP). [Step 13]
Spent Fuel Poo ol temperatu ure (T2900A A, T2901A).
Spent Fuel Poo ol level (L48 800A, L4801A, L4802A, L4803A).
CPNPP NRC 2014 SimulatorS Sccenario 2 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 2 Eve ent # 5,, 6, 7, & 8 Page 31 of 33 Event Desccription: Powwer Operated Relief R Valve and Block Valve Failures / Sma all Break Loss o of Coolant Accident /
Automatic Safety Injection Signa al Failure / Res idual Heat Remmoval Pump SII Sequencer Fa ailure Time Position n Appliccants Actions o or Behavior BOP VERIFY Y Componen nts on Table e 1 are Prope erly Aligned. [Step 14]
Location Equipment Description Conditio on CB-03 X-HS-5534 H2 PR RG SPLY FN N4 STOPPED CB-03 X-HS-5532 H2 PR RG SPLY FN N3 STOPPED CB-04 1/1-8716A RHR RP 1 XTIE VLV V OPEN N CB-04 1/1-8716B RHR RP 2 XTIE VLV V OPEN N CB-06 1/1-8153 XS LT TDN ISOL VL LV CLOSE ED CB-06 1/1-8154 XS LT TDN ISOL VL LV CLOSE ED CB-07 1/1-RTBAL RXX TRIP BKR OPEN N CB-07 1/1-RTBBL RXX TRIP BKR OPEN N CB-07 1/1-BBAL RX TTRIP BYP BK KR OOPEN/DEENE ERGIZED CB-07 1/1-BBBL RX TTRIP BYP BK KR OOPEN/DEENE ERGIZED CB-08 1-HS-2397A A SG 1 BLD DN HELB ISO OL VLV CLOSE ED CB-08 1-HS-2398A A SG 2 BLD DN HELB ISO OL VLV CLOSE ED CB-08 1-HS-2399A A SG 3 BLD DN HELB ISO OL VLV CLOSE ED CB-08 1-HS-2400A A SG 4 BLD DN HELB ISO OL VLV CLOSE ED CB-08 1-HS-2111C C FWWPT A TRIP TRIPPE ED CB-08 1-HS-2112C C FWWPT B TRIP TRIPPE ED CB-09 1-HS-2490 CNDS S XFER PUM MP STOPPED (MCC deenergized on SI)
CV-01 X-HS-6181 PRI PLT S SPLY FN 17 & INTK STO OPPED/DEENERGIZED DMPR CV-01 X-HS-6188 PRI PLT S SPLY FN 18 & INTK STO OPPED/DEENERGIZED DMPR CPNPP NRC 2014 SimulatorS Sccenario 2 Dra aft Submitta al
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5, 6, 7, & 8 Page 32 of 33 Event
Description:
Power Operated Relief Valve and Block Valve Failures / Small Break Loss of Coolant Accident /
Automatic Safety Injection Signal Failure / Residual Heat Removal Pump SI Sequencer Failure Time Position Applicants Actions or Behavior 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 CPNPP NRC 2014 Simulator Scenario 2 Draft Submittal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5, 6, 7, & 8 Page 33 of 33 Event
Description:
Power Operated Relief Valve and Block Valve Failures / Small Break Loss of Coolant Accident /
Automatic Safety Injection Signal Failure / Residual Heat Removal Pump SI Sequencer Failure Time Position Applicants Actions or Behavior Examiner Note: The next four 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 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]
EOP-0.0A, Attachment 2 steps are now complete.
CPNPP NRC 2014 Simulator Scenario 2 Draft Submittal
Appendix D Scenario Outline Form ES-D-1 Facility: CPNPP 1 & 2 Scenario No.: 3 Op Test No.: June 2014 NRC Examiners: Operators:
Initial Conditions: 100% power MOL - RCS Boron is 924 ppm (by sample).
Turnover: Maintain steady-state power conditions.
Critical Tasks: Manually Trip Reactor Due to Reactor Protection System Failure Prior to Exiting EOP-0.0A, Reactor Trip or Safety Injection. (Event 5)
Initiate Train A and/or Train B Containment Isolation Phase A due to Failure to Automatically Actuate Prior to Exiting EOP-0.0A, Reactor Trip or Safety Injection. (Event 8)
Identify and Isolate Ruptured Steam Generator Prior to Commencing an Operator Induced Cooldown per EOP-3.0A, Steam Generator Tube Rupture. (Event 6)
Initiate Cooldown of Reactor Coolant System Prior to Exiting EOP-3.0A, Steam Generator Tube Rupture. (Event 6)
Event No. Malf. No. Event Type* Event Description 1 SG01A Steam Generator (1-01) Tube Leak at 50 gpd (0.0347 gpm).
+10 min 2 RX09A I (RO, BOP, SRO) Main Turbine 1st Stage Pressure Transmitter (PT-505) Fails High.
+20 min TS (SRO) 3 SW01B C (BOP, SRO) Station Service Water Pump 1-02 Trip.
+30 min TS (SRO) 4 FW16 R (RO) Lowering Condenser Vacuum Requiring Power Reduction Followed
+50 min N (BOP, SRO) by Total Loss of Condenser Vacuum.
5 RP01 I (BOP) Automatic Reactor Trip Failure.
+55 min RP13A Manual Reactor Trip Failure from CB-07.
6 SG01A M (RO, BOP, SRO) Steam Generator (1-01) Tube Rupture at 500 gpm (600 second
+65 min ramp) upon Turbine Trip.
7 OVRDE I (RO/BOP) Steam Generator (1-01) Blowdown Isolation Valve (1-HS-2397)
+70 min Fails to Close on Safety Injection.
8 RP09A C (BOP) Containment Isolation Phase A Train A and Train B Auto Actuation
+70 min RP09B Failure.
Actual Target Quantitative Attributes 8 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) 4 Critical tasks (2-3)
CPNPP NRC 2014 Simulator Scenario 3 Draft Submittal
Scenario Event Description NRC Scenario 3 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 Steam Generator #1 tube leak of 50 gpd. Crew actions are per ABN-106, High Secondary Activity, Section 2.0, and include verification of leakage rate to ensure proper procedural action. The SRO will refer to Technical Specifications.
The next event is a Main Turbine 1st Stage Pressure Transmitter failure. The crew responds per ABN-709, Steam Line Pressure, Steam Header Pressure, Turbine 1st-Stage Pressure and Feed Header Pressure Instrument Malfunction, Section 4.0. Several actions are required on the part of the RO and BOP to stabilize plant conditions. The SRO will refer to Technical Specifications.
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 B Emergency Diesel Generator in PULLOUT. The SRO will refer to Technical Specifications.
When Pressurizer conditions are stable, a loss of Condenser vacuum will occur. The crew will respond per ABN-304, Main Condenser and Circulating Water System Malfunction, Section 3.0. Actions include lowering of Main Turbine load in 50 MWe increments in an attempt to maintain Condenser vacuum.
Once a load reduction is performed, Condenser vacuum will continue to deteriorate until a Reactor Trip is required.
Once it is determined that Condenser vacuum cannot be maintained, the Reactor must be manually tripped and EOP-0.0A, Reactor Trip or Safety Injection, entered. The automatic Reactor Trip function and one manual Reactor Trip switch are disabled to ensure appropriate crew actions and communication. The crew will transition from EOP-0.0A to EOS-0.1A, Reactor Trip Response and then return to EOP-0.0 when Foldout Page criteria for Pressurizer level or Reactor Coolant System (RCS) subcooling are not met. A Steam Generator Tube Rupture is diagnosed in EOP-0.0A and a transition to EOP-3.0A, Steam Generator Tube Rupture will be performed.
The scenario is complicated by a Train A and B Containment Isolation Phase A failure and a Steam Generator Blowdown Valve that fails to automatically isolate.
While in EOP-3.0A, the ruptured Steam Generator will be isolated and a RCS cooldown commenced using the Atmospheric Relief Valves. The scenario is terminated when steps to cooldown the Reactor Coolant System are reached in EOP-3.0A.
Risk Significance:
Failure of risk important system prior to trip: Steam Generator Tube Leak Train B Emergency Diesel Generator Risk significant core damage sequence: Automatic Reactor Trip Failure Steam Generator Tube Rupture Risk significant operator actions: Manually Initiate Reactor Trip Isolate SG Blowdown Flow Initiate Containment Phase A Isolation Identify and Isolate Ruptured SG CPNPP NRC 2014 Simulator Scenario 3 Draft Submittal
Scenario Event Description NRC Scenario 3 BOOTHSIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP INITIALIZE to IC-18 and LOAD LC22 NRC Scenario 3.
EVENT REM. MALF. DESCRIPTION DEMAND INITIATING FUNC. VALUE PARAMETER SETUP OVRDE SG BD Isolation Valve (HS-2397) Auto Close FAIL K0 Failure IOR DISGHS2397 f:3 OVRDE SG BD Isolation Valve (HS-2397) Manual Close CLOSE K0
{DISGHS2396.Value =0} DOR DISGHS2397 f:0 RP09A CNTMT Phase A Train A Auto Actuation Failure FAIL K0 RP09B CNTMT Phase A Train B Auto Actuation Failure FAIL K0 RP01 Automatic Reactor Trip Failure FAIL K0 RP13A Manual Reactor Trip Failure from CB-07 FAIL K0 1 SG01A Steam Generator (1-01) Tube Leak at 50 gpd .0347 gpm K1 2 RX09A 1st Stage Pressure Transmitter (PT-505) Failure 120% K2 3 SW01B Station Service Water Pump 1-02 Failure TRIP K3 4 FW16 Initial Loss of Condenser Vacuum 5% K4 4 FW16 Loss of Condenser Vacuum after 1st Runback 35% K5 (600 sec. ramp) 5 RP01 Automatic Reactor Trip Failure FAIL K0 5 RP13A Manual Reactor Trip Failure from CB-07 FAIL K0 6 SG01A Steam Generator (1-01) Tube Rupture 500 gpm On RX Trip (600 sec. ramp) 7 OVRDE SG BD Isolation Valve (HS-2397) Auto Close FAIL K0 Failure IOR DISGHS2397 f:3 7 OVRDE SG BD Isolation Valve (HS-2397) Manual Close CLOSE K0
{DISGHS2396.Value =0} DOR DISGHS2397 f:0 CPNPP NRC 2014 Simulator Scenario 3 Draft Submittal
Scenario Event Description NRC Scenario 3 8 RP09A CNTMT Phase A Train A Auto Actuation Failure FAIL K0 8 RP09B CNTMT Phase A Train B Auto Actuation Failure FAIL K0 CPNPP NRC 2014 Simulator Scenario 3 Draft Submittal
Scenario Event Description NRC Scenario 3 BoothSimulator Operator: INITIALIZE to IC-18 and LOAD LC22 NRC Scenario 3.
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 2014 Simulator Scenario 3 Draft Submittal
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 3 Evvent # 1 Page 6 of 31 Event Desccription: Steam Generator Tube Leak Time Position n Appliccants Actions o or Behavior BoothSimulator Op perator: Wh hen directed d, EXECUTE E Event 1 (K Key 1).
- SG01A, S Stea am Generattor 1-01 Tub be Leak at 5 50 gpd.
Indicatioons Availab ble:
PC N16-174 MS SL 1 (1-RE-22325A) is RED R
PC 182 COG (1 1-RE-2959) is RED (Con ndenser Offf Gas is dellayed)
+1 min RO/BOP RESPO OND to PC-1 11, Digital R adiation Monitoring System alarms.
RO/BOP RECOG GNIZE radia ation monitorr alarms asssociated with h Steam Gen nerator 1-01.
US DIRECT T performannce of ABN-1 106, High Se econdary Acctivity, Sectio on 2.0.
VERIFY Y Main Steaam Line 1-01 radiation allarm 1-RE-2 2325 (MSL-178) -
RO/BOP CLEAR R. [Step 2.3.11]
RO CORRE ELATE Radiiation Monito or readings tto leak rate. [Step 2.3.2))
VE ERIFY with N16 N leak rate e indication 40% powe er.
PO OSTED Cond denser Off GGas (COG) ccorrelation g graphs by PCC-11.
CP PINET, Chem mistry Deparrtment prima ary to secondary leakage e tab.
RO VERIFY Y leak rate < 75 gpd (0.0 052 gpm). [S Step 2.3.3]
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submittaal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 3 Evvent # 1 Page 7 of 31 Event Desccription: Steam Generator Tube Leak Time Position n Appliccants Actions o or Behavior RO VERIFY Y leak rate 30 gpd (0.0 02 gpm). [Sttep 2.3.4]
COOMMENCE trending t RC S leakage ra ates AND se econdary coolant raddiation levels s at 10 minuute intervals. [Step 2.3.4.a]
VEERIFY leakag ge remains - STABLE. [Step 2.3.4.b b]
RO/BOP ISOLAT TE Auxiliary Steam supp plied from th he affected UUnit. [Step 2.3.5]
VERIFY Y Condense er Off Gas Ra adiation Monitor 1-RE-2 2959 (COG-1 182) -
US OPERA ABLE. [Step 2.3.6]
US DIRECT T Chemistry y to impleme ent CHM-113 3. [Step 2.3.7]
Examine er Note: Th he Unit Sup pervisor may y reference e Technical Specificatio ons.
BoothSimulator Op perator: If contacted c as a Shift Man nager, REPO ORT Unit will remain o on line until further chemical analysiis is perform med.
+10 min n ESTAB BLISH Conditions and PE ERFORM R RCS Leak Ra ate Check pe er OPT-303.
US
[Step 2.3.8]
DEETERMINE RCS R leak ratte within Tecchnical Speccification LC CO 3.4.13 lim mits. [Step 2.3 3.8.a]
COONSULT with h Shift Mana ager and Du uty Manager to VERIFY Unit will remmain in operration. [Step 2.3.8.b]
When th he Shift Man nager is conntacted, or ata Lead Exa aminer disc cretion, PRO OCEED to E Event 2.
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submittaal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 3 Evvent # 2 Page 8 of 31 Event Desccription: Maiin Turbine 1st Stage S Pressure e Transmitter F ailure Time Position n Appliccants Actions o or Behavior BoothSimulator Op perator: Wh hen directed d, EXECUTE E Event 2 (K Key 2).
- RX09A, R Main Turbine 1st Stage Pre essure Tran nsmitter (PT T-505) fails high.
Indicatioons Availab ble:
6D-4.14 - CONTROL ROD BAN NK D FULL WTHDRWL W
1-PI-505 - Turbine ImpulseI Preessure Chan nnel I indica ation fails h high Control Rods withd draw to 225 steps
+30 secs s RO/BOP RESPO OND to Annu unciator Alarrm Procedurres.
RECOG GNIZE Control Rods INS SERTING du ue to Turbinne Impulse PPressure RO/BOP Instrumment failure.
RO/BOP REPOR RT PT-505, Turbine T Imp pulse Pressu ure Channel I has failed low.
DIRECT T implementation of AB N-709, Stea am Line Presssure, Steam m Header US Pressure, Turbine 1st Stage Pre essure, and Feed Header Pressure Instrument Malfunc ction, Sectioon 4.0.
RO PLACE E 1/1-RBSS Control C Rod d Bank Selecct Switch in M MANUAL. [S Step 4.3.1]
BOP VERIFY Y Steam Dumps - CLOS SED WITH N NO OPEN D DEMAND. [Step 4.3.2]
1-UUI-500, STM M DMP DEMA AND indicatting 0% - DE EMAND. [Step 4.3.2.a]
STTM DMP VLV V ZL lights in ndicating - C CLOSE. [Ste ep 4.3.2.a]
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submittaal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2 Page 9 of 31 Event
Description:
Main Turbine 1st Stage Pressure Transmitter Failure Time Position Applicants Actions or Behavior RESTORE Steam Dump availability, PLACE Steam Dumps in STEAM BOP PRESSURE Mode per Attachment 7. [Step 4.3.3]
Examiner Note: The following five steps are from ABN-709, Attachment 7, Transferring Steam Dumps and are performed using the Control Board Job Aid.
Are the following steps correct for the high vice low failure of PT-505? Did not observe BOP ENSURE 1-PK-507, STM DMP PRESS CTRL is in MANUAL. [Step 1]
MATCH 1-PK-507, STM DUMP PRESS CTRL demand to current Steam BOP Dump Valve position. [Step 2]
VERIFY 1-PCIP, Window 1.4 - CNDSR AVAIL STM DMP ARMED C-9 is ON.
[Step 3]
BOP PLACE 43/1-SD, STM DMP MODE SELECT in STM PRESS. [Step 4]
BOP ENSURE both STM DMP INTLK SELECT switches are ON. [Step 5]
If desired to control Steam Dumps in AUTO, then PERFORM the following:
[Step 6]
VERIFY 1-PI-507, MS HDR PRESS indicates current MSL pressure.
[Step 6.A]
ENSURE 1-PK-507, STM DMP PRESS CTRL set to control at 1092 psig for "no load" conditions (Pot setting 6.86). [Step 6.B]
PLACE 1-PK-507, STM DMP PRESS CTRL in AUTO. [Step 6.C]
TRANSFER 1-PS-505Z, TURB IMP PRESS CHAN SELECT to PT-506.
[Step 4.3.4]
RO ENSURE TAVE within 1ºF of TREF. [Step 4.3.5]
RESTORE TAVE to within 1ºF of TREF prior to placing Rod Control in AUTO.
CPNPP NRC 2014 Simulator Scenario 3 Draft Submittal
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 3 Evvent # 2 Page 10 of 31 Event Desccription: Maiin Turbine 1st Stage S Pressure e Transmitter F ailure Time Position n Appliccants Actions o or Behavior PLACE E 1/1-RBSS, CONTROL ROD BANK K SELECT S Switch in AUTO.
[Step 4.3.6]
US/RO O CHECK K Reactor Po ower in - MO ODE 1. [Ste ep 4.3.7]
US/BOP CHECK K Turbine Po ower - GRE ATER THAN N 10% POW WER. [Step 4 4.3.8]
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, VER RIFY PCIP W Window 4.6 - TURB 10 0% PWR P-13, IN US PROPE ER STATE fo or existing pplant conditio ons (DARK).. [Step 4.3.9 9]
US EVALU UATE Technical Specificcations. [Step p 4.3.9]
LCCO 3.3.1.T, Reactor R Trip System Instrumentation n.
(Fuunction 18.f, Turbine 1st Stage Presssure P-13)
CONDITIO ON T - One o or more requ uired channe els inoperablle.
ACTION T.1 - Verify in nterlock is in required sta ate for existin ng unit conditions within one h hour, OR ACTION T.2 - Be in MO ODE 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
VERIFY Y PCIP Wind dow 1.3 - A AMSAC BLK TURB < 40% % PWR C-2 20 - IN US PROPE ER STATE (DARK) for a actual Turbin ne power. [S Step 4.3.10]
If AMSAC A actuation blocke ed and Turbine power > 40%, ENSU URE Auttomatic Actioons of ALB-9 9B, Window w 3.7 - AMSA AC ACT TUR RB TRIP as necessary.
US INITIATTE a SMART T Form per S STA-421. [S Step 4.3.11]
+10 min n US INITIATTE repairs pe er STA-606.. [Step 4.3.12]
When Te echnical Sp pecifications s are addressed, or at Lead Evalu uators disc cretion, PRO OCEED to Event 3.
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submittaal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 3 Evvent # 3 Page 11 of 31 Event Desccription: Station Service Water W Pump Tripp Time Position n Appliccants Actions o or Behavior BoothSimulator Op perator: Wh hen directed d, EXECUTE E Event 3 (K Key 3).
- SW01B, S Sta ation Service Water Pu mp 1-02 trip p.
Indicatioons Availab ble:
01-1.8 - SSWP 1 / 2 OVRLOAD D / TRIP 01-2.11 - CCP 2 L/O O CLR SSW W RET FLO LO L 01-2.12 - SIP 2 L/O CLR SSW RET R FLO LO O 01-4.8 - CSP 2 & 4 BRG B CLR SSW S RET FL LO LO Station Service S Watter Pump 1--02 amber MISMATCH M and white T TRIP lights lit
+30 sec c BOP RESPO OND to Annu unciator Alarrm Procedurres.
RECOG GNIZE 1-HS S-4251A, Se rvice Water Pump 1-02 amber MISM MATCH BOP and whhite TRIP ligh hts LIT.
DIRECT T performan nce of ABN-5 501, Station Service Wa ater System US Malfuncction, Sectio on 2.0.
Examine er Note: Diiamond step ps () are In nitial Operattor Actions s.
PLACE E CS-1DG2E E, Train B Di esel Genera ator Emerge ency Start/Sttop BOP handswwitch in PULLOUT. [Step p 2.3.1]
BOP VERIFY Y Train A SSSW Pump - RUNNING. [Step 2.3.2))
BOP VERIFY Y Train A CCCW Pump - RUNNING. [Step 2.3.3))
BoothSimulator Op perator: Wh hen asked about a status s of SSW P Pump, REPO ORT that the e SSW Puump 1-02 50 0/51 overcu urrent relays s on Phases s B & C are e tripped.
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submittaal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 3 Evvent # 3 Page 12 of 31 Event Desccription: Station Service Water W Pump Tripp Time Position n Appliccants Actions o or Behavior VERIFY Y equipmentt on Train B - NOT REQ QUIRED FOR OPERATION:
RO/BOP
[Step 2.3.4]
Cenntrifugal Chaarging Pump p 1-02 Diesel Generator 1-02 Commponent Cooling Water Pump 1-02 Saffety Injection n Pump 1-02 2 Conntainment Sp pray Pumpss 1-02 & 1-04 4 RO/BOP PLACE E equipment on Train B iin PULLOUT T. [Step 2.3.5]
Cenntrifugal Chaarging Pump p 1-02 Saffety Injection n Pump 1-02 2 Conntainment Sp pray Pumpss 1-02 & 1-04 4 Station Service Water Pum mp 1-02 (mayy leave as iss due to CAU UTION)
BOP CHECK K status of Train T B CCW W Pump. [Ste ep 2.3.6]
VER RIFY CCW PumpP - NOT T RUNNING G. [Step 2.3.66.a]
CONTINUE E with Step 7 7. [Step 2.3..6.a RNO]
US INITIAT TE a work re equest per S STA-606. [Step 2.3.7]
US REFER R to EPP-201 1. [Step 2.3..8]
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submittaal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 3 Page 13 of 31 Event
Description:
Station Service Water Pump Trip Time Position Applicants Actions or Behavior US EVALUATE Technical Specifications. [Step 2.3.9]
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 />.
BoothSimulator 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 2.3.10]
+10 min US SUBMIT a SMART Form per STA-421. [Step 2.3.11]
When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 4.
CPNPP NRC 2014 Simulator Scenario 3 Draft Submittal
Appendix xD Operatorr Action Fo orm ES-D-2 Operating Test T : NRC N Scenario S # 3 Evvent # 4 Page 14 of 31 Event Desccription: Los ss of Condense er Vacuum Time Position n Appliccants Actions o or Behavior BoothSimulator Op perator: Wh hen directed d, EXECUTE E Event 4.
- FW16, F Partial Loss of Condenser C Vacuum @ 5%.
Indicatioons Availab ble:
P6600A - CNDSR A PRESS (VA A)
P6601A - CNDSR B PRESS (VA A) 1-PI-2042-1, CNDNS SR A PRESS S lowering 1-PI-2042-2, CNDNS SR B PRESS S lowering Control Rods stepp ping out Main Ste eam pressure lowering g
+1 min BOP REFER R to Annunciator Alarm P Procedures.
Examine er Note: Lo oss of Cond denser vacu uum will oc cur in 2 pha ases. In thee 1st phase, Condenserr vaacuum is lost requiring g a reductio on in Turbin ne load. Onc ce the powe er reduction n
is complete, thet 2nd phas se will resuult in a total loss of vac cuum (600 s sec. ramp).
BOP RECOG GNIZE Main Condenserr vacuum de ecreasing.
DIRECT T implementation of AB N-304, Main n Condenserr and Circula ating Water US Systemm Malfunction n, Section 3 .0.
BOP START T all available e Condense er Vacuum P Pumps. [Step p 3.3.1]
VERRIFY Conde enser Vacuu m Pumps 1 and 2 - RUNNING.
STAART 1-HS-2958, Conde nser Vacuum m Pump 3.
DISPAT TCH an ope erator to VER RIFY CEV se eal water tannk level indiccated.
RO/BOP
[Step 3.3.2]
BOP VERIFY Y Main Cond denser vacu uum > 21 Hg g. [Step 2.3..3]
BOP DETER RMINE Main Condenserr vacuum < 2 26.5 Hg. [Sttep 2.3.4]
ENSSURE Turbine not opera ating in the N NOT PERMISSIBLE reg gion.
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submittaal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 4 Page 15 of 31 Event
Description:
Loss of Condenser Vacuum Time Position Applicants Actions or Behavior Examiner Note: The crew should perform multiple 50 MWe load reductions in an attempt to stabilize Condenser vacuum at greater than 24.5 Hg. After the 1st load reduction, vacuum will continue to deteriorate requiring a Reactor and Turbine trip.
DETERMINE Main Condenser Vacuum NOT being maintained > 24.5 Hg US/BOP and stable. [Step 2.3.5]
CONTROL Turbine load as necessary to maintain vacuum > 24.5 Hg BOP and power less than 100%. [Step 2.3.5 RNO]
As required, LOWER Turbine load to RAISE Condenser vacuum.
NOTIFY Shift Manager and Generation Controller of load changes.
US
[Step 2.3.5 RNO]
RO ENSURE 1/1-RBSS, Control Rod Bank Select Switch in AUTO.
BOP PERFORM the following to LOWER Turbine Load:
DEPRESS 50 MWe Manual Runback button.
CLICK on 0/1 button.
CLICK on Execute then VERIFY Manual Runback in progress.
BoothSimulator Operator: When the 1st load reduction is complete, ADJUST malfunction FW16 to 35% on a 600 second ramp (Key 5).
BOP ENSURE Seal Steam pressure is approximately 4 H2O. [Step 3.3.6]
Examiner Note: The crew should reference this previous step to determine that a Reactor and Turbine Trip are required.
+20 min RO/BOP VERIFY Main Condenser vacuum > 21 Hg. [Step 2.3.3]
If Reactor Power is greater than or equal to 10%, then TRIP Reactor and GO to EOP-0.0A while others continue this procedure. [Step 2.3.3 RNO]
When Reactor and Turbine are tripped, or at Lead Examiner discretion, PROCEED to Events 5, 6, 7, and 8.
CPNPP NRC 2014 Simulator Scenario 3 Draft Submittal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5, 6, 7, & 8 Page 16 of 31 Event
Description:
Steam Generator Tube Rupture / Main Steam Safety Valves Failure / Power Operated Relief Valve Failure / Residual Heat Removal Pump Safety Injection Sequencer Failure Time Position Applicants Actions or Behavior BoothSimulator Operator: Upon Reactor Trip, Events 5, 6, 7, and 8 will occur.
- RP01, Automatic Reactor Trip failure.
- RP13A, Manual Reactor Trip failure from CB-07.
- SG01A, SG 1-01 Tube Rupture at 500 gpm on 600 second ramp.
- OVRDE, SB (1-01) Blowdown Valve (1-HS-2397) fails to close.
- RP09A, Containment Isolation Phase A Train A Auto Actuation failure.
- RP09B, Containment Isolation Phase A Train B Auto Actuation failure.
Indications Available:
Lowering Condenser vacuum.
RECOGNIZE Condenser vacuum LOWERING at a rising rate and TRIP the
+2 min RO/BOP Reactor and Turbine.
Examiner Note: The crew will enter EOP-0.0A, Reactor Trip or Safety Injection and transition to EOS-0.1A, Reactor Trip Response, at Step 4. Once it is determined that a Steam Generator Tube Rupture is in progress the crew will return to EOP-0.0A.
CRITICAL TASK Manually Trip Reactor Due to Reactor Protection System Failure Prior to STATEMENT Exiting EOP-0.0A, Reactor Trip or Safety Injection.
CRITICAL RO Manually TRIP the Reactor.
TASK PLACE 1/1-RTC, RX TRIP Switch in TRIP position and VERIFY Reactor RO Trip at CB-07.
PLACE 1/1-RT, RX TRIP Switch in TRIP position and VERIFY Reactor BOP Trip at CB-10.
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]
VERIFY Reactor Trip Breakers - OPEN. [Step 1.a]
VERIFY Neutron flux - DECREASING. [Step 1.a]
VERIFY all Control Rod Position Rod Bottom Lights - ON. [Step 1.b]
CPNPP NRC 2014 Simulator Scenario 3 Draft Submittal
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 3 Eveent # 5,, 6, 7, & 8 Page 17 of 31 Event Desccription: Steam Generator Tube Rupture / Main Steam S Safety Valves Failure / Poweer Operated Reelief Valve Faillure / Residual Heat Removall Pump Safety Injection Sequ uencer Failure Time Position n Appliccants Actions o or Behavior BOP VERIFY Y Turbine Trrip: [Step 2]
VEERIFY all HP P Turbine Sto op Valves - CLOSED. [Step 2]
BOP VERIFY Y Power to AC A Safeguarrds Buses: ((Step 3]
VEERIFY AC Sa afeguards BBuses - AT L LEAST ONE E ENERGIZE ED.
[Sttep 3.a]
VEERIFY both AC A Safeguarrds Buses - ENERGIZE ED. [Step 3.b b]
[ 4]
CHHECK if SI is s actuated. [SStep 4.a]
CHECK if SIS is required d: [Step 4.a RNO]
Steam Line Pressu ure less than n 610 psig.
Pressurizer Pressu ure less than n 1820 psig.
Containnment Presssure greater than 3.0 psig.
If SI is NOT T required, G GO to EOS-0 0.1A, Reactor Trip Resp ponse, US Step 1. [Steep 4.a RNO ]
Examine er Note: Th he following g steps are from EOS-0 0.1A, Reacttor Trip Res sponse.
RO CHECK K RCS Temp perature: [Sttep 1]
CHHECK RCPs - ANY RUN NNING. [Ste ep 1.a]
VEERIFY RCS average a tem mperature sta able at or treending to 5557ºF.
[Sttep 1.b]
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submitta al
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5, 6, 7, & 8 Page 18 of 31 Event
Description:
Steam Generator Tube Rupture / Main Steam Safety Valves Failure / Power Operated Relief Valve Failure / Residual Heat Removal Pump Safety Injection Sequencer Failure Time Position Applicants Actions or Behavior RO/BOP CHECK FW Status: [Step 2]
VERIFY Reactor Trip Breakers - OPEN. [Step 2.a]
CHECK RCS average temperatures < 564ºF. [Step 2.b]
VERIFY Feedwater Isolation - COMPLETE. [Step 2.c]
VERIFY total AFW flow to SGs - GREATER THAN 460 GPM. [Step 2.d]
RO CHECK PRZR Level Control: [Step 3]
VERIFY PRZR Level - GREATER THAN 17%. [Step 3.a]
VERIFY Charging - IN SERVICE. [Step 3.b]
VERIFY Letdown - IN SERVICE. [Step 3.c]
VERIFY PRZR Level - TRENDING TO 25%. [Step 3.d]
RO CHECK PRZR Pressure Control: [Step 4]
VERIFY Pressurizer Pressure - GREATER THAN 1820 PSIG. [Step 4.a]
VERIFY Pressurizer Pressure - STABLE AT OR TRENDING TO 2235 PSIG. [Step 4.b]
VERIFY PRZR PORVs - CLOSED. [Step 4.b RNO]
VERIFY PRZR Spray Valves - CLOSED. [Step 4.b RNO]
VERIFY PRZR Heaters - ON. [Step 4.b RNO]
RO CHECK Steam Generator Levels: [Step 5]
VERIFY Steam Generator Level - GREATER THAN 43%.
[Step 5.a]
MAINTAIN total feed flow greater than 460 GPM until narrow range level greater than 43% in at least one SG. [Step 5.a RNO]
Examiner Note: In accordance with EOS-0.1A, Reactor Trip Response, Foldout Page, actuation of Safety Injection AND return to EOP-0.0A, Reactor Trip or Safety Injection, is required when subcooling is less than 25°F and/or Pressurizer level cannot be maintained greater than 6%.
CPNPP NRC 2014 Simulator Scenario 3 Draft Submittal
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 3 Eve ent # 5,, 6, 7, & 8 Page 19 of 31 Event Desccription: Steam Generator Tube Rupture / Main Steam S Safety Valves Failure / Poweer Operated Reelief Valve Faillure / Residual Heat Removall Pump Safety Injection Sequ uencer Failure Time Position n Appliccants Actions o or Behavior RO Manuallly INITIATE both Trainss of Safety In njection.
PLLACE 1/1-SIA A2, SI MAN ACT Switch h to ACT possition at CB--07 and RO DEETERMINE SI S has actua ated.
RO VEERIFY Both Trains T SI Acctuated:
SI Actuateed blue statu us light - ON N NOT FLAS SHING.
Examine er Note: Th he following g steps are from EOP-0 0.0A, Reacttor Trip or S Safety Injecttion.
RO VERIFY Y Reactor Trip: [Step 1]
VERIFY Reacto or Trip Breaakers - OPEN. [Step 1.a a]
VERIFY Neutro on flux - DE ECREASING G. [Step 1.a]
VERIFY all Con ntrol Rod Po osition Rod B Bottom Lightts - ON. [Ste ep 1.b]
BOP VERIFY Y Turbine Trrip: [Step 2]
VEERIFY all HPP Turbine Sto op Valves - CLOSED. [Step 2]
BOP VERIFY Y Power to ACA Safeguarrds Buses: ((Step 3]
VEERIFY AC Sa afeguards B Buses - AT L LEAST ONE E ENERGIZE ED.
[Sttep 3.a]
VEERIFY both ACA Safeguarrds Buses - ENERGIZE ED. [Step 3.b b]
[ 4]
CHHECK if SI is s actuated. [S Step 4.a]
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 3 Eveent # 5,, 6, 7, & 8 Page 20 of 31 Event Desccription: Steam Generator Tube Rupture / Main Steam S Safety Valves Failure / Poweer Operated Reelief Valve Faillure / Residual Heat Removall Pump Safety Injection Sequ uencer Failure Time Position n Appliccants Actions o or Behavior VEERIFY Both Trains T SI Acctuated: [Ste ep 4.b]
SI Actuateed blue statu us light - ON N NOT FLAS SHING.
Examine er Note: EO OP-0.0A, Atttachment 2 steps perfformed by the BOP are e identified later in the sccenario.
Examine er Note: Th he RO may trip the RCPs per the F Foldout Pag ge if subcoo oling is < 25°F.
INITIATTE Proper Sa afeguards E Equipment O Operation Pe er Attachmen nt 2.
US/BOP
[Step 5))
RO VERIFY Y AFW Align nment: [Step p 6]
VEERIFY both MDAFW M Pum mps - RUNN NING. [Step 6.a]
PLAACE TDAFW W Pump in P PULLOUT per Foldout P Page. [Step 6 6.b]
VEERIFY AFW total t flow - G GREATER T THAN 460 g gpm. [Step 6.c]
VEERIFY AFW valve alignm ment - PROP PER ALIGNM MENT. [Step p 6.d]
RO DETER RMINE Conta ainment Sprray NOT Req quired: [Step p 7]
VEERIFY 1-ALB B-2B, Window w 1-8, CS A ACT - NOT ILLUMINATE ED.
[Step 7.a]
VEERIFY 1-ALB B-2B, Window w 4-11, CNT TMT ISOL P PHASE B AC CT - NOT ILL LUMINATED D. [Step 7.a]
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submitta al
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5, 6, 7, & 8 Page 21 of 31 Event
Description:
Steam Generator Tube Rupture / Main Steam Safety Valves Failure / Power Operated Relief Valve Failure / Residual Heat Removal Pump Safety Injection Sequencer Failure Time Position Applicants Actions or Behavior VERIFY Containment pressure - LESS THAN 18.0 PSIG. [Step 7.a]
VERIFY Containment Spray Heat Exchanger Outlet Valves - CLOSED.
[Step 7.b]
VERIFY Containment Spray Pumps - RUNNING. [Step 7.c]
RO CHECK If Main Steamlines Should Be ISOLATED: [Step 8]
VERIFY Containment pressure - GREATER THAN 6.0 PSIG. [Step 8.a]
VERIFY Steam Line pressure - LESS THAN 610 PSIG. [Step 8.a]
GO to Step 9. [Step 8.a RNO]
VERIFY RCS Average Temperature - STABLE AT OR TRENDING TO 557°F. [Step 9]
RO CHECK PRZR Valve Status: [Step 10]
VERIFY PRZR Safeties - CLOSED. [Step 10.a]
VERIFY Normal PRZR Spray Valves - CLOSED. [Step 10.b]
VERIFY PORVs - CLOSED. [Step 10.c]
VERIFY Power to at least 1 Block Valve - AVAILABLE. [Step 10.d]
VERIFY Block Valves - AT LEAST ONE OPEN. [Step 10.e]
RO CHECK if RCPs Should Be Stopped: [Step 11]
VERIFY RCS subcooling less than 25ºF (55ºF FOR ADVERSE CONTAINMENT). [Step 11.a]
GO to Step 12. [Step 11.a RNO]
US/RO CHECK if any SG is Faulted: [Step 12]
VERIFY any Steam Generator pressure - DECREASING IN AN UNCONTROLLED MANNER. [Step 12.a]
VERIFY any Steam Generator pressure - COMPLETELY DEPRESSURIZED. [Step 12.a]
GO to Step 13. [Step 12.a RNO]
CPNPP NRC 2014 Simulator Scenario 3 Draft Submittal
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 3 Eve ent # 5,, 6, 7, & 8 Page 22 of 31 Event Desccription: Steam Generator Tube Rupture / Main Steam S Safety Valves Failure / Poweer Operated Reelief Valve Faillure / Residual Heat Removall Pump Safety Injection Sequ uencer Failure Time Position n Appliccants Actions o or Behavior US/RO O CHECK K if SG Tubees are Not R Ruptured: [Sttep 13]
DEETERMINE SG S 1-01 is ru uptured and d TRANSITIO ON to EOP-3 3.0A, Ste eam Genera ator Tube Ru upture, Step 1. [Step 13 RNO]
Examine er Note: EO OP-3.0A, Stteam Generrator Tube R Rupture ste eps begin he ere.
US/RO O CHECK K If RCPs Sh hould Be Sto opped: [Step p 1]
VEERIFY RCS subcooling s - LESS THA AN 25°F. [Step 1.a]
GO to Steep 2. [Step 1 .a RNO]
US/BOP IDENTIFY Steam Generator G 1--01 as rupturred. [Step 2))
OBS SERVE rise in Steam G enerator 1-0 01 narrow ra ange level.
OBS SERVE high h radiation frrom Steam G Generator 1--01 Main Ste eam line.
CRITIICAL TASK Identify y and Isolate Ruptured Stteam Genera ator Prior to Commencing an STAATEMENT Operatoor Induced Cooldown C pe r EOP-3.0A, Steam Gene erator Tube R Rupture.
CRITICAL L TASK RO/BOP ISOLAT TE flow fromm Ruptured S Steam Gene erator 1-01: ((Step 3]
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 3 Eve ent # 5,, 6, 7, & 8 Page 23 of 31 Event Desccription: Steam Generator Tube Rupture / Main Steam S Safety Valves Failure / Poweer Operated Reelief Valve Faillure / Residual Heat Removall Pump Safety Injection Sequ uencer Failure Time Position n Appliccants Actions o or Behavior ADDJUST SG 1-01 Atmosph heric Contro oller Setpoint to 1160 PS SIG.
[Step 3.a]
CHHECK SG 1-0 01 Atmosph heric Relief V Valve - CLO OSED. [Step 3.b]
CLOSE 1-HS-2 2333A, SG 1 1-01 Main Steam Isolatio on Valve. [S Step 3.c]
CLOSE 1-HS-2 2409, SG 1--01 Drip Pot Isolation Va alves. [Step 3 3.c]
PLAACE 1-HS-2 2452-2, SG 1-01 TDAFW W Pump Ste eam Supply V Valve in PUULLOUT. [Ste ep 3.d]
CLOSE 1-HS-2 2397, SG 1--01 Blowdow wn Valve. [Sttep 3.e]
RO/BOP CHECK K Ruptured SGS 1-01 Levvel: [Step 4]
VEERIFY narrow w range leve el - GREATE ER THAN 43 3% (50% FO OR ADDVERSE CO ONTAINMEN NT). [Step 4.a a]
STOP AFW flo ow to SG 1-0 01. [Step 4.b b]
CLOSE 1-F FK-2453A, M MD AFWP 1 SG 1 FLO C CTRL. [Step p 4.b]
RO/BOP CHECK K SG 1-01 Pressure - G GREATER TH HAN 420 PS SIG. [Step 5))
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 3 Eve ent # 5,, 6, 7, & 8 Page 24 of 31 Event Desccription: Steam Generator Tube Rupture / Main Steam S Safety Valves Failure / Poweer Operated Reelief Valve Faillure / Residual Heat Removall Pump Safety Injection Sequ uencer Failure Time Position n Appliccants Actions o or Behavior RO/BOP INITIATTE RCS Coo oldown using g Steam Dum mp Valves. ((Step 6]
Whhen PRZR pressure deccreases to le ess than 1960 psig, BLO OCK Low RO/BOP Ste eam Line Pre essure SI Siignal. [Step 6.a]
RO/BOP PLAACE 1/1-SL LS-1RBA and d 1/1-SLS-1RBB, Main S Steam Line Isolation Saffety Injection n Reset / Blo ock in BLOC CK position.
DEETERMINE required r Corre Exit Therm mocouple (C CET) temperrature from US Tabble 1. [Step 6.b]
OBSERVE ED Steam Ge enerator pre essure = ___ ___ psig TARGET CoreC Exit The ermocouple (CET) temp perature = __ ____ ºF CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 3 Eveent # 5,, 6, 7, & 8 Page 25 of 31 Event Desccription: Steam Generator Tube Rupture / Main Steam S Safety Valves Failure / Poweer Operated Reelief Valve Faillure / Residual Heat Removall Pump Safety Injection Sequ uencer Failure Time Position n Appliccants Actions o or Behavior CRITIICAL TASK Initiate Cooldown of o Reactor Co oolant System m Prior to Ex xiting EOP-3 3.0A, Steam STAATEMENT Generator Tube Rup pture.
CRITICAL L DUUMP steam to t Condense er from intacct SG(s) at m maximum ratte using TASK BOP Ste eam Dump Valves V and AAVOID Main n Steam Isola ation. [Step 6.c.]
DUMP stea am to atmossphere from intact SG(s)) at maximum m rate.
[Step 6.c RNO]
R MAKE plant annou ncement an nd NOTIFY P Plant Staff off steam releasee. [Step 6.c.11) RNO]
PERFO ORM the follo owing as ne ecessary to rrelease steam:
[Step 6.c.2) 6 RNO]
PLA ACE SG Atm mospheric Controllers in MANUAL a and INC CREASE dem mand.
PLA ACE SG Atm mospheric ARV CONTROL OVERRIDEs to OPEN.
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submitta al
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5, 6, 7, & 8 Page 26 of 31 Event
Description:
Steam Generator Tube Rupture / Main Steam Safety Valves Failure / Power Operated Relief Valve Failure / Residual Heat Removal Pump Safety Injection Sequencer Failure Time Position Applicants Actions or Behavior LOCALLY control SG Atmospheric Valves and OPEN.
US VERIFY Core Exit Thermocouples - LESS THAN REQUIRED TEMPERATURE. [Step 6.d]
BOP STOP RCS cooldown. [Step 6.e]
+40 min BOP MAINTAIN Core Exit Thermocouples - LESS THAN REQUIRED TEMPERATURE. [Step 6.f]
When cooldown is initiated via the Steam Dump Valves, TERMINATE the scenario.
CPNPP NRC 2014 Simulator Scenario 3 Draft Submittal
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 3 Eve ent # 5,, 6, 7, & 8 Page 27 of 31 Event Desccription: Steam Generator Tube Rupture / Main Steam S Safety Valves Failure / Poweer Operated Reelief Valve Faillure / Residual Heat Removall Pump Safety Injection Sequ uencer Failure Time Position n Appliccants Actions o or Behavior Examine er Note: Th hese steps are perform med by the B BOP per EO OP-0.0A, Atttachment 2.
BOP VERIFY Y SSW Align nment: [Step p 1]
VER RIFY SSW Pump P 1 RUNNING G. [Step 1.a]
VER RIFY Diesel Generator C Cooler SSW W return flow. [Step 1.b]
BOP VERIFY Y Safety Inje ection Pump 1 RUN NNING. [Ste ep 2]
Initiate e Train A and/or Train B Containm ment Isolatio on Phase A due to CRITICAL TASK Failuree to Automa atically Actu uate Prior to o Exiting EO OP-0.0A, Re eactor Trip STAATEMENT or Safeety Injection n.
BOP VERIFY Y Containme ent Isolation Phase A - APPROPRIATE MLB LIGHT INDICA ATION (RED D WINDOWS S). [Step 3]
CRITICAL L PLAACE 1/1-CIP PAA1 CNTM MT ISOL - P PHASE A / C CNTMT VEN NT ISOL TASK Swwitch in ACT position. [Sttep 3 RNO]
BOP VERIFY Y Containme ent Ventilatio on Isolation - APPROPR RIATE MLB LIGHT INDICA ATION (GRE EEN WINDO OWS). [Step 4]
BOP VERIFY Y CCW Pum mps - RUNN ING. [Step 5 5]
BOP VERIFY Y RHR Pumps - RUNNIING. [Step 6 6]
BOP VERIFY Y Proper CV VCS Alignme ent: [Step 7]
VEERIFY CCP 1-01 1 - RUNN NING. [Step p 7.a]
VEERIFY Letdow wn Relief Va alve Isolation n: [Step 7.b))
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 3 Eve ent # 5,, 6, 7, & 8 Page 28 of 31 Event Desccription: Steam Generator Tube Rupture / Main Steam S Safety Valves Failure / Poweer Operated Reelief Valve Faillure / Residual Heat Removall Pump Safety Injection Sequ uencer Failure Time Position n Appliccants Actions o or Behavior VERIFY Leetdown Orificce Isolation Valves - CL LOSED. [Ste ep 7.b.1)]
VERIFY Leetdown Isola ation Valves 1/1-LCV-45 59 & 1/1-LCV V-460 -
CLOSED. [Step
[ 7.b.2)))
BOP VERIFY Y ECCS flow w: [Step 8]
CCCP SI flow indicators - C CHECK FOR R FLOW. [Ste ep 8.a]
RCCS pressure - LESS THA AN 1700 PS SIG (1800 PS SIG FOR AD DVERSE COONTAINMEN NT). [Step 8. b]
SIP P discharge flow indicato or - CHECK K FOR FLOW W. [Step 8.c))
RCCS pressure - LESS THA AN 325 PSIG (425 PSIG G FOR ADV VERSE COONTAINMEN NT). [Step 8. d]
GO to Step p 9. [Step 8.d d RNO]
BOP VERIFY Y Feedwaterr Isolation C omplete: [Sttep 9]
Feeedwater Isollation Valvess - CLOSED D.
Feeedwater Isollation Bypasss Valves - C CLOSED.
Feeedwater Byppass Controll Valves - C CLOSED.
Feeedwater Con ntrol Valves - CLOSED..
BOP VERIFY Y Diesel Gen nerator 1 RUNNING G. [Step 10))
BOP VERIFY Y Monitor Ligghts for SI LLoad Shedding on 1-MLB B-9 and 1-MLB- LIT. [Step 11]
BOP VERIFY Y Proper SI alignment - PROPER M MLB LIGHT INDICATION N. [Step 12]
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submitta al
Appendix xD Operatorr Action Foorm ES-D-2 Operating Test T : NRC N Scenario S # 3 Eveent # 5,, 6, 7, & 8 Page 29 of 31 Event Desccription: Steam Generator Tube Rupture / Main Steam S Safety Valves Failure / Poweer Operated Reelief Valve Faillure / Residual Heat Removall Pump Safety Injection Sequ uencer Failure Time Position n Appliccants Actions o or Behavior BOP INITIAT TE periodic monitoring m o of Spent Fue el Cooling (G GD_SFP). [Step 13]
Spent Fuel Poo ol temperatu ure (T2900A A, T2901A).
Spent Fuel Poo ol level (L48 800A, L4801A, L4802A, L4803A).
BOP VERIFY Y Componen nts on Tablee 1 are Prope erly Aligned. [Step 14]
Location Equipment Description Conditio on CB-03 X-HS-5534 H2 PR RG SPLY FN N4 STOPPED CB-03 X-HS-5532 H2 PR RG SPLY FN N3 STOPPED CB-04 1/1-8716A RHRRP 1 XTIE VLV V OPEN N CB-04 1/1-8716B RHRRP 2 XTIE VLV V OPEN N CB-06 1/1-8153 XS LT TDN ISOL VL LV CLOSE ED CB-06 1/1-8154 XS LT TDN ISOL VL LV CLOSE ED CB-07 1/1-RTBAL RX X TRIP BKR OPEN N CB-07 1/1-RTBBL RX X TRIP BKR OPEN N CB-07 1/1-BBAL RX T TRIP BYP BK KR O OPEN/DEENE ERGIZED CB-07 1/1-BBBL RX T TRIP BYP BK KR O OPEN/DEENE ERGIZED CB-08 1-HS-2397A A SG 1 BLDDN HELB ISO OL VLV CLOSE ED CB-08 1-HS-2398A A SG 2 BLDDN HELB ISO OL VLV CLOSE ED CB-08 1-HS-2399A A SG 3 BLDDN HELB ISO OL VLV CLOSE ED CB-08 1-HS-2400A A SG 4 BLDDN HELB ISO OL VLV CLOSE ED CB-08 1-HS-2111C C FWWPT A TRIP TRIPPE ED CB-08 1-HS-2112C C FWWPT B TRIP TRIPPE ED CB-09 1-HS-2490 CNDS S XFER PUM MP STOPPED (MCC deenergized on SI)
CPNPP NRC 2014 Simulator S Sccenario 3 Dra aft Submitta al
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5, 6, 7, & 8 Page 30 of 31 Event
Description:
Steam Generator Tube Rupture / Main Steam Safety Valves Failure / Power Operated Relief Valve Failure / Residual Heat Removal Pump Safety Injection Sequencer Failure Time Position Applicants Actions or Behavior 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 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 CPNPP NRC 2014 Simulator Scenario 3 Draft Submittal
Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5, 6, 7, & 8 Page 31 of 31 Event
Description:
Steam Generator Tube Rupture / Main Steam Safety Valves Failure / Power Operated Relief Valve Failure / Residual Heat Removal Pump Safety Injection Sequencer Failure Time Position Applicants Actions or Behavior Examiner Note: The next four 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 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]
EOP-0.0A, Attachment 2 steps are now complete.