Text

2016-07 Proposed OP Test
	ML16293A974
Person / Time
Site:	Comanche Peak
Issue date:	07/11/2016
From:	Vincent Gaddy; Operations Branch IV
To:	;
References
	Download: ML16293A974 (297)
	v • d • e

Appendix C JPM STEPS Form ES-C-1 Facility: CPNPP JPM # NRC RA1 Task # RO1307 K/A # 2.1.23 4.3 / 4.4 Title: Calculate BOL Boration for Long Term Use 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 startup is in progress following a refueling outage.

Reactor Coolant System boron concentration is 1600 ppm.

Boric Acid Storage Tank boron concentration is 7249 ppm.

Boron-10 Weight Fraction is 0.173367.

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

CALCULATE Beginning-Of-Life Boration values per SOP-104A, Reactor Make-up and Chemical Control System, Attachment 2, BOL Boration for Long-Term Use.

RECORD information on Attachment 2, BOL Boration for Long-Term Use page 1 Task Standard: Utilizing SOP-104A, Attachment 2 calculated Reactor Coolant System Corrected Boron, Gallons of Reactor Makeup Water To Offset Boron in Blender Pipe During Normal Volume Control Tank Makeup, Boron Gallons for a Manual Blend, Boric Acid Pot Setting for a Manual Blend, Boric Acid Pot Setting for AUTO Makeup, Gallons of Reactor Makeup Water to Offset Boron in Blender Pipe When Returning Makeup System to Automatic. (SEE KEY)

Ref. Materials: SOP-104A, Reactor Make-up and Chemical Control System, Rev. 15-2.

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

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

CPNPP 2016 NRC JPM RA1 (RO1307D) Rev. 0

Appendix C JPM STEPS Form ES-C-1 CLASSROOM SETUP Handout:

PROVIDE the examinee with a copy of:

SOP-104A, Reactor Make-up and Chemical Control System.

Attachment 2, BOL Boration for Long-Term Use Page 1. (labeled Procedure 1)

CPNPP 2016 NRC JPM RA1 (RO1307D) Rev. 0

Appendix xC JPM STEP PS Fo orm ES-C-1

- Chec ck Mark Deenotes Crittical Step ST TART TIME E:

Examiner Note: The following ste eps are fro m SOP-104 4A, Attach hment 2 pa age 1 Examiner Note: Refer to o answer key k for calc culated va alues.

Perform m Step: 1 RECOR RD Referen nce Data ass follows:

1.0 RCS R Boron ___

________

BAT B Boron ___

________

B10 B WT Fra action ___

________

Standarrd: ENTER RED data on n Attachmeent 2 at Stepp 1.0 Comme ent: SAAT UNS SAT Perform m Step: 2 CALCU ULATE volumes in pot settings ass follows:

2.A RCS R Correccted Boron::

Standarrd: CALCU ULATED 1512.5 +/- 0.1. [allowable error based on rounding after first calc culation and then perfforming seccond calcula ation]

Comme ent: SAAT UNS SAT CPNPP C 20166 NRC JPM RA1 (RO13 307D) Rev. 0

Appendix xC JPM STEP PS Foorm ES-C-1 Perform m Step: 3 CALCUULATE volumes in pot settings ass follows:

2.B Gallons G of RMUW R to o offset boron n in Blenderr Pipe durin ng normal VCT V makeu up:

Standarrd: CALCUULATED 132.75 +/- 0.2 g gallons. [a allowable errror based oon roundin ng carried frrom Step 2 and those performed in this step p]

Comme ent: SAAT UNS SAT Perform m Step: 4 CALCUULATE volumes in pot settings ass follows:

2.C Boron B gallons for a Ma anual Blendd:

Standarrd: CALCUULATED 10.4 +/- 0.1 gallons. [allow wable error based on rrounding]

Comme ent: SAAT UNS SAT Perform m Step: 5 CALCUULATE volumes in pot settings ass follows:

2.D Boric B Acid Pot P Setting for a Manu ual Blend:

Standarrd: CALCUULATED 4.6 69 +/- 0.1. [allowable errror based oon roundingg and accurac cy of Pot seettings]

Comme ent: SAAT UNS SAT CPNPP C 20166 NRC JPM RA1 (RO13 307D) Rev. 0

Appendix xC JPM STEP PS Foorm ES-C-1 Perform m Step: 6 CALCU ULATE volumes in pot settings ass follows:

2.E Boric B Acid Pot P Setting for AUTO M Makeup:

Standarrd: CALCU ULATED 6.6 62 +/- 0.1. [allowable errror based o on rounding g and accuraccy of Pot se ettings]

Comme ent: SAAT UNS SAT Perform m Step: 7 CALCU ULATE volumes in pot settings ass follows:

2.F Gallons G of RMUW R to o offset boron n in Blenderr Pipe whenn returning Makeup M Sys stem to Auttomatic:

Standarrd: CALCU ULATED 86.5 +/- 0.2 gallons. [allow wable errorr based on rounding carried from Step 2 and those e performedd in this ste ep]

Terminaating Cue: This JPPM is comp plete.

Comme ent: SAAT UNS SAT S

STOP TIME E:

CPNPP C 20166 NRC JPM RA1 (RO13 307D) Rev. 0

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

Unit 1 startup is in progress following a refueling outage.

Reactor Coolant System boron concentration is 1600 ppm.

Boric Acid Storage Tank boron concentration is 7249 ppm.

Boron-10 Weight Fraction is 0.173367.

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

CALCULATE Beginning-Of-Life Boration values per SOP-104A, Reactor Make-up and Chemical Control System, Attachment 2, BOL Boration for Long-Term Use.

RECORD information on Attachment 2, BOL Boration for Long-Term Use page 1 CPNPP 2016 NRC JPM RA1 (RO1307D) Rev. 0

CPNPP 2016 NRC JPM RA1 ANSWER KEY Rev. 0 CPNPP PROCEDURE NO.

UNIT 1 SYSTEM OPERATING PROCEDURE MANUAL SOP-104A REACTOR MAKE-UP AND CHEMICAL REVISION NO. 15 PAGE 75 OF 82 l CONTROL SYSTEM CONTINUOUS USE ATTACHMENT 2 PAGE 1 OF 7 BOL BORATION FOR LONG TERM USE This attachment describes the steps to periodically add boron to the RCS at BOL while keeping the system aligned in the BORATE mode. Instructions are provided to address refilling the VCT due to normal losses as well as if an RCS leak were to occur.

NOTE: This attachment assumes prior automatic operation. Therefore, B-10 Corrected RCS Boron Concentration must be < 1600 ppm to use this attachment.

1.0 RECORD Reference Data as follows:

Q ! RCS Boron 1600 ! BAT Boron 7249 ! B10 Wt Fraction 0.173367 2.0 CALCULATE volumes and pot settings as follows:

A. RCS Corrected Boron:

1600 RCS PPM X 0.173367 B-10 Wt Fraction = 1512.5 +/- 0.1 RCS (c) PPM BORON 0.1834 Corrected B. Gallons of RMUW to offset boron in Blender Pipe for Normal VCT Makeup:

7249 132.75 +/- 0.2 BAT PPM X 35 GAL - 35 GAL = 1-FY-111B, RMUW Gallons to 1512.5 RCS(c) BORON BORON Offset Boron in Blender Pipe C. Boron gallons for a Manual Blend:

1512.5 10.4 +/- 0.1 50 Total Gallons X RCS(c) = 1-FY-110B, Boron Gallons for 7249 BAT PPM Manual Blend D. Boric Acid Pot Setting for a Manual Blend:

1512.5 4.69 +/- 0.1 90 Total Flowrate X RCS(c) = 1-FK-110, BA Pot Setting for 4 7249 BAT PPM Manual Blend E. Boric Acid Pot Setting for AUTO Makeup:

1512.5 6.62 +/- 0.1 127 Total Flowrate X RCS(c) = 1-FK-110, BA Pot Setting for 4 7249 BAT PPM Auto Makeup F. Gallons of RMUW to offset boron in Blender Pipe when returning Makeup System to Automatic:

7249 86.5 +/- 0.2 BAT PPM X 22.8 GAL - 22.8 GAL = 1-FY-111B, RMUW Gallons to 1512.5 RCS(c) BORON BORON Offset Boron in Blender Pipe when returning to Automatic CPNPP 2016 NRC JPM RA1 ANSWER KEY Rev. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA2 Task # RO1310 K/A # 2.1.43 4.1 / 4.3 Title: Determine Reactivity Effects When Starting Positive Displacement Charging Pump 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 100% power.

The Positive Displacement Charging Pump must be placed in service per SOP-103A, Chemical and Volume Control System.

The last time the Positive Displacement Charging Pump was run the Reactor Coolant System Boron concentration was 25 ppm.

Current Reactor Coolant System Boron concentration is 1222 ppm.

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

CALCULATE a Reactivity Evaluation for starting the Positive Displacement Charging Pump per SOP-103A, Chemical and Volume Control System, Steps 5.3.1.C.

REPORT findings to the Shift Manager.

Task Standard: Utilizing SOP-103A, calculated the change in boron concentration and resultant change in temperature when placing the Positive Displacement Pump in service.

Ref. Materials: SOP-103A, Chemical and Volume Control System, Rev. 18-14.

Reactivity Briefing Sheet for 1222 ppm Reactor Coolant System conditions.

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

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

Page 1 of 5 CPNPP 2016 NRC JPM RA2 (RO1310E) REV. 0

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

PROVIDE the examinee with a copy of:

SOP-103A, Chemical and Volume Control System, Step 5.3.1.C. (labeled Procedure 1) 90.4 EFPD Reactivity Briefing Sheet. (labeled Handout 1)

Page 2 of 5 CPNPP 2016 NRC JPM RA2 (RO1310E) REV. 0

AppendixxC JPM STEP PS Fo orm ES-C-1

- Checck Mark Deenotes Crittical Step ST TART TIME E:

Examiner Note: The following ste eps are fro m SOP-103 3A, Step 5.3.1.

Performm Step: 1 DETER RMINE the change c in R RCS Boron concentrattion which w will occur 5.3.1.C.1) + due to the t PDP run n:

calculatiion B

= Chang ge in RCS B Boron Conccentration d due to PDPP run Standarrd: CALCU ULATED B B = Change e in RCS Bo oron Conce entration:

B = ( 25 2 ppm PD DP - 1222 pp pm RCS) x 0.00128 = -1.53 +/- 0.0 01 ppm Comme ent: SAAT UNSSAT Performm Step: 2 IF in MOODE 1 or 2 THEN PER RFOM the following:

5.3.1.C.2).a) + DETER RMINE the impact of w water in the PDP piping g on reactivvity by the calculatiion perform ming the following calcu ulation:

B = -1.53 ppm From thhe Reactivitty Briefing S Sheet, obtaain the followwing inform mation:

ITC ______ pcm/ºF F HFP Diffferential Bo oron Worth _ _____ pcm m/ppm Standarrd: DETER RMINED the e following ffrom the Reeactivity Brriefing Shee et:

ITC = - 10.9 pcm/ººF HFP Diffferential Boron Worth h = - 7.0 pc cm/ppm Comme ent: SAAT UNSSAT Performm Step: 3 Calculaate:

5.3.1.C.2).a) + ITC / HFP Differen ntial Boron WWorth = pppm / ºF calculatiion Standarrd: CALCU ULATED cha ange in ppm m /ºF:

- 10.9 pcm/

p ºF / - 7.0 7 pcm/ppm m = 0.156 +/- 0.01 ppm m/ºF Comme ent: SAAT UNSSAT Page 3 of o 5 CPNPP 20 016 NRC JP PM RA2 (RO O1310E) REV. 0

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Rounding off of TAVE may occur.

Perform Step: 4 Calculate:

5.3.1.C.2).a) + TAVE = (-1) B ppm / ppm / ºF calculation Standard: CALCULATED change in TAVE as follows:

TAVE = (-1) B ppm / ppm / ºF = (-1)(-1.53 ppm) / 1.56 ppm/ºF = 0.98

+/- 0.02 ºF Comment: SAT UNSAT Perform Step: 5 IF TAVE calculated above is > 0.5 ºF, THEN NOTIFY the Unit 5.3.1.C.2).b) Supervisor and discuss contingency actions.

Standard: DETERMINED TAVE calculated is greater than 0.5 ºF and NOTIFIED Unit Supervisor.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 CPNPP 2016 NRC JPM RA2 (RO1310E) REV. 0

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

Unit 1 is 100% power.

The Positive Displacement Charging Pump must be placed in service per SOP-103A, Chemical and Volume Control System.

The last time the Positive Displacement Charging Pump was run the Reactor Coolant System Boron concentration was 25 ppm.

Current Reactor Coolant System Boron concentration is 1222 ppm.

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

CALCULATE a Reactivity Evaluation for starting the Positive Displacement Charging Pump per SOP-103A, Chemical and Volume Control System, Steps 5.3.1.C.

REPORT findings to the Shift Manager.

Page 5 of 5 CPNPP 2016 NRC JPM RA2 (RO1310E) REV. 0

CPNPP 2016 NRC JPM RA2 Answer Key Rev. 0 25 1222

-1.53 +/- .01

-10.9 -7.0

-10.9 1.56 +/- .01

-7.0

-1.53 0.98 +/- .02 1.56

Appendix C JPM STEPS Form ES-C-1 Facility: CPNPP JPM # NRC RA3 Task # RO1003 K/A # 2.2.1 4.5 / 4.4 Title: Perform a 1/M Plot and Predict Critical Conditions 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 performing a Reactor Startup per IPO-002B, Plant Startup from Hot Standby.

Boron is at the Estimated Critical Boron Concentration of 1220 ppm.

Shutdown Control Rod Banks are fully withdrawn.

Critical Rod Height is predicted to be CBD at 78 steps.

The +500 PCM Rod position is CBD at 210 steps.

The -500 PCM Rod position is CBC at 123 or CBD at 8 steps.

The Full Out Position (FOP) is 225 steps.

Control Rods have been withdrawn four times in increments of 50 steps.

The Unit Supervisor wants to re-perform the Inverse Count Rate Ratio Calculation and re-plot the points on a 1/M Data Sheet to re-verify Predicted Critical Rod Height.

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

DETERMINE the Inverse Count Rate Ratio Calculation (ICRR) for the readings shown on IPO-002B, Plant Startup from Hot Standby, Attachment 2, Inverse Count Rate Ratio Calculation.

LOG the ICRR on IPO-002B, Attachment 2, and PLOT the points on the 1/M Data Sheet.

LOG the Predicted Critical Rod Height for each 50 step Control Bank A withdrawal up to 200 steps on the 1/M Data Sheet.

RECORD any required action based on 1/M Data obtained on Attachment 2, Page 3 of 4:

____________________________________________

Task Standard: Utilizing IPO-002B, calculated the Inverse Count Rate, performed a 1/M Plot using provided data, determined criticality predicted below Rod Insertion Limit, and recorded insert all Control Banks to the CBO position on Attachment 2.

Page 1 of 6 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 0

Appendix C JPM STEPS Form ES-C-1 Ref. Materials: IPO-002B, Plant Startup from Hot Standby, Rev. 10.

ERX-15-001, COLR for CPNPP Unit 2 Cycle 16, Figure 2, Rod Bank Insertion Limits Versus Thermal Power, Rev. 0.

Straight edge or ruler Calculator Validation Time: 15 minutes Completion Time: ________ minutes Comments:

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

Page 2 of 6 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 0

Appendix C JPM STEPS Form ES-C-1 CLASSROOM SETUP Handout:

PROVIDE the examinee with a copy of:

IPO-002B, Plant Startup from Hot Standby. (labeled Procedure 1)

COMPLETE Attachment 2 through four sets of data.

Required Materials:

Straight edge or ruler Calculator Page 3 of 6 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 0

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from IPO-002B, Attachment 2.

Perform Step: 1 Calculate Inverse Count Rate Ratio calculation for Control Bank A at 50 steps and plot on 1/M Data Sheet.

Standard: CALCULATED Inverse Count Rate Ratio for Control Bank A at 50 steps, PLOTTED on 1/M Data Sheet, and RECORDED Data:

RECORD an average Count Rate of 55.

CALCULATE ICRR = 1/M = 50/55 = 0.91 +/- 0.01.

RECORD ICRR = 0.91 +/- 0.01.

PLOT points for CBA @ 0 steps and CBA @ 50 steps.

DRAW a line from 1.00 to 0.91 that INTERSECTS with CBD at 190 +/- 100 steps.

LOG an Estimated Critical Condition with CBD at 190 +/- 100 steps.

Comment: SAT UNSAT Perform Step: 2 Calculate Inverse Count Rate Ratio calculation for Control Bank A at 100 steps and plot on 1/M Data Sheet.

Standard: CALCULATED Inverse Count Rate Ratio for Control Bank A at 100 steps, PLOTTED on 1/M Data Sheet, and RECORDED Data:

RECORD an average Count Rate of 65.

CALCULATE ICRR = 1/M = 50/65 = 0.77 +/- 0.01.

RECORD ICRR = 0.77 +/- 0.01.

PLOT points for CBA @ 50 steps and CBA @ 100 steps.

DRAW a line from 0.91 to 0.77 that INTERSECTS with CBD at 10 +/- 50 steps.

LOG an Estimated Critical Condition with CBD at 10 +/- 50 steps.

Comment: SAT UNSAT Page 4 of 6 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 3 Calculate Inverse Count Rate Ratio calculation for Control Bank B at 35 steps and plot on 1/M Data Sheet.

Standard: CALCULATED Inverse Count Rate Ratio for Control Bank B at 35 steps, PLOTTED on 1/M Data Sheet, and RECORDED Data:

RECORD an average Count Rate of 88.

CALCULATE ICRR = 1/M = 50/88 = 0.57 +/- 0.01.

RECORD ICRR = 0.57 +/- 0.01.

PLOT points for CBA @ 100 steps and CBB @ 35 steps.

DRAW a line from 0.77 to 0.57 that INTERSECTS with CBC at 55 +/- 30 steps.

LOG an Estimated Critical Condition with CBC at 55 +/- 30 steps.

Comment: SAT UNSAT Perform Step: 4 Calculate Inverse Count Rate Ratio calculation for Control Bank B at 85 steps and plot on 1/M Data Sheet.

Standard: CALCULATED Inverse Count Rate Ratio for Control Bank B at 85 steps, PLOTTED on 1/M Data Sheet, and RECORDED Data:

RECORD an average Count Rate of 333.

CALCULATE ICRR = 1/M = 50/333 = 0.15 +/- 0.01.

RECORD ICRR = 0.15 +/- 0.01.

PLOT points for CBB @ 35 steps and CBB @ 85 steps.

DRAW a line from 0.57 to 0.15 that INTERSECTS with CBB at 95 +/- 25 steps.

LOG an Estimated Critical Condition with CBB at 95 +/- 25 steps.

Comment: SAT UNSAT Examiner Note: The following Standard is from IPO-002B, Step 5.2.10, 4th bullet.

Perform Step: 5 RECORD any required action based on 1/M Data obtained on Attachment 2, Page 3 of 4 and/or the JPM Cue Sheet.

Standard: DETERMINED Estimated Critical Condition occurs below the Rod Insertion Limit within the next reactivity addition and RECORDED the following on Attachment 2, Page 3 of 4 and/or the JPM Cue Sheet:

INSERT all Control Bank Rods to the CBO position (critical).

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 0

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

Unit 2 is performing a Reactor Startup per IPO-002B, Plant Startup from Hot Standby.

Boron is at the Estimated Critical Boron Concentration of 1220 ppm.

Shutdown Control Rod Banks are fully withdrawn.

Critical Rod Height is predicted to be CBD at 78 steps.

The +500 PCM Rod position is CBD at 210 steps.

The -500 PCM Rod position is CBC at 123 or CBD at 8 steps.

The Full Out Position (FOP) is 225 steps.

Control Rods have been withdrawn four times in increments of 50 steps.

The Unit Supervisor wants to re-perform the Inverse Count Rate Ratio Calculation and re-plot the points on a 1/M Data Sheet to re-verify Predicted Critical Rod Height.

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

DETERMINE the Inverse Count Rate Ratio Calculation (ICRR) for the readings shown on IPO-002B, Plant Startup from Hot Standby, Attachment 2, Inverse Count Rate Ratio Calculation.

LOG the ICRR on IPO-002B, Attachment 2, and PLOT the points on the 1/M Data Sheet.

LOG the Predicted Critical Rod Height for each 50 step Control Bank A withdrawal up to 200 steps on the 1/M Data Sheet.

RECORD any required action based on 1/M Data obtained on Attachment 2, Page 3 of 4:

____________________________________________

Page 6 of 6 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 0

CPSES PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 2 IPO-002B PLANT STARTUP FROM HOT STANDBY REVISION NO. 10 PAGE 64 OF 83 ATTACHMENT 2 PAGE 1 OF 4 INVERSE COUNT RATE RATIO CALCULATION NOTE: This calculation is not required when Core Performance Engineering is performing ICRR calculations per NUC-111.

1.0 PREREQUISITES

! The scalar timer is available for use in the manual mode per SOP-703.

OR

! IF the scalar timer is out-of-service, THEN Nuclear Instrument indication shall be used.

2.0 LIMITATIONS 2.1 Rod withdrawal increments should be performed at approximately 50 steps. The Shift Manager may authorize withdrawal of rods at any other increment less than 50 steps as the Reactor approaches criticality.

3.0 INSTRUCTIONS 3.1 The following steps describe the method for determining the baseline reference count values.

NOTE: When count rate is greater than 50 counts/sec, a 10 second counting interval should be used. If count rate is less than or equal to 50 counts/sec, then a 30 second counting interval should be used.

Once initiated, the same counting interval should be used throughout the ICRR.

A. Obtain ten separate reference counts for each Source Range channel and record values on the ICRR worksheet.

B For each Source Range channel, compute the average count from the 10 reference counts on the ICRR worksheet.

3.2 Mark the graph for the rod heights at + / - 500 pcm (if using OPT-308-1) or for the Expected Criticality Range (if using OPT-308-2).

CPSES PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 2 IPO-002B PLANT STARTUP FROM HOT STANDBY REVISION NO. 10 PAGE 65 OF 83 ATTACHMENT 2 PAGE 2 OF 4 INVERSE COUNT RATE RATIO CALCULATION 3.3 The following steps describe the method used in determining the Inverse Count Rate Ratio (ICRR).

A. After obtaining the Shift Manager's permission, withdraw the Control Rods a maximum of 50 steps.

The Shift Manager may authorize withdrawals of less than 50 steps.

B. Monitor Source Range indication on recorder 2-NR-0045 to determine when the Source Range channels have stabilized.

C. Obtain three separate integral count measurements for each Source Range channel using the counting interval determined in Step 3.1.

D. Ensure audible Source Range counts is returned to service after completion of counting measurements.

E. Calculate the average of these counts for each Source Range channel on the ICRR worksheet.

F. Perform the following calculation and record the result on the ICRR worksheet.

ICRR = Source Range Channel Reference Counts Source Range Channel Average Counts G. Plot the ICRR values at the appropriate rod position on graph paper similar to the one attached.

3.4 Perform a linear extrapolation of the ICRR plot, using the last two data points, to the point at which the extrapolation intersects the horizontal axis. This point defines the rod position at which criticality is estimated.

3.5 List rod position estimation on the ICRR worksheet.

3.6 Continue to perform Steps 3.3 thru 3.5 until either of the following occurs:

A. The Reactor is critical OR B. The Shift Manager terminates ICRR data collection.

Insert all control bank rods to the CBO position.

CPSES PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 2 IPO-002B PLANT STARTUP FROM HOT STANDBY REVISION NO. 10 PAGE 66 OF 83 ATTACHMENT 2 PAGE 3 OF 4 INVERSE COUNT RATE RATIO CALCULATION INVERSE COUNT RATE RATIO Estimated Critical Condition:

Bank CBD at 78 steps Boron Concentration 1220 ppm Completed by Date Time REFERENCE COUNTS N-31 N-32 50 49 49 50 BANK CBA AT 50 STEPS BANK CBA AT 100 STEPS 49 51 N-31 N-32 N-31 N-32 55 55 65 64 51 49 50 56 54 65 67 49 51 51 54 56 65 64 48 52 55 55 65 65 50 50 0.91 AVE 0.91 AVE AVE AVE 0.77 0.77 51 49 ICRR ICRR ICRR ICRR 51 50 ECC ECC ECC ECC 50 50 BANK CBD BANK CBD BANK CBD BANK CBD AVE AVE STEP 190 STEP 190 STEP 10 STEP 10 CBD 190 +/- 100 CBD 10 +/- 50 BANK CBA AT 150 STEPS BANK CBA AT 200 STEPS BANK AT STEPS N-31 N-32 N-31 N-32 N-31 N-32 87 89 335 333 88 88 333 329 89 87 331 337 88 88 333 333 AVE AVE AVE AVE AVE AVE 0.57 0.57 0.15 0.15 ICRR ICRR ICRR ICRR ICRR ICRR ECC ECC ECC ECC ECC ECC BANK CBC BANK CBC BANK CBB BANK CBB BANK BANK STEP 55 STEP 55 STEP 95 STEP 95 STEP STEP CBC 55 +/- 30 CBB 95 +/- 25 Insert all control bank rods to the CBO position.

Insert all control bank rods to the CBO position.

CPSES PROCEDURE NO.

INTEGRATED PLANT OPERATING PROCEDURES MANUAL UNIT 2 IPO-002B PLANT STARTUP FROM HOT STANDBY REVISION NO. 10 PAGE 67 OF 83 ATTACHMENT 2 PAGE 4 OF 4 INVERSE COUNT RATE RATIO CALCULATION 1/MDATASHEET 1.0

.9

.8

.7

.6 ICRR .5

.4

.3

.2

.1 0

0 50 100 150 200 250 300 350 400 450 500 550 600 0 50 100 20 70 GP'A' GP'C' 35 85 05 55 105 155 205 GP'B' GP'D' 0 100 200 300 400 500 565 Insert all control bank rods to the CBO position.

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA4 Task # RWT056B K/A # 2.3.7 3.5 / 3.6 Title: Determine Entry Conditions for Radiation Area Clearance 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 Clearance is required to remove 1-LCV-1003, LWPS RCDT 1-01 LVL CTRL VLV from service.

Tags need to be hung on 1-7168, LWPS RCDT 1-01 LVL CTRL VLV UPSTRM ISOL and 1-7167, LWPS RCDT 1-01 LVL CTRL VLV DNSTRM ISOL.

The valves are located in Safeguards Building Elev. 810' NORTH PENETRATION VLV RM / North Side (Room 77A).

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

DETERMINE the Dose Monitoring Requirements to enter the room.

DETERMINE the minimum Protective Clothing Requirements to enter the valve area.

IDENTIFY the highest contamination level in dpm/100 cm2 for the room.

IDENTIFY the highest dose rate in mR/hr for the room.

Task Standard: Utilizing the General Access Permit, Survey Map, and Valve Locator Guide, determined the Dose Monitoring Requirements, Protective Clothing Requirements, highest contamination level and highest dose rate in the area where tagging is to be performed.

Ref. Materials: RPI-602, Radiological Surveillance and Posting, Rev. 57.

RPI-606, Radiation Work and General Access Permits, Rev. 35.

Valve Locator Map for Unit 1 Safeguards Building Elev. 810' Room 77A.

Survey Map for U-1 SG 810 Pipe Penetration Area Train B Room 1-077A.

CPNPP General Area Permit 20160011, Routine Maintenance, Rev. 02.

Validation Time: 20 minutes Completion Time: ________ minutes Page 1 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0

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

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

Page 2 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0

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

PROVIDE the examinee with a copy of:

Survey Map for U-1 SG 810 Pipe Pen Area Train B Room 1-077A. (labeled Handout 1)

CPNPP General Area Permit 20160011, Tours and inspections for all groups.

Activities for Operations, Chemistry, NOS, and RP. For entry into elevated dose rates. (labeled Handout 2)

Valve Locator Map for Unit 1 Safeguards Building Elev. 810 Room 77A. (labeled Handout 3)

MAKE the following references available in the classroom:

RPI-602, Radiological Surveillance and Posting.

RPI-606, Radiation Work and General Access Permits.

Page 3 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

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

Perform Step: 1 Determine location of 1-7168 and 1-7167 with respect to Survey Map.

Standard: PERFORMED the following:

LOCATED 1-7168 and 1-7167 using Valve Locator Map for Unit 1 Safeguards Building Elev. 810' Room 77N (77A).

COMPARED the location to the Survey Map.

DETERMINED 1-7168 and 1-7167 are located inside a Radiation Area and the area is contaminated.

Comment: SAT UNSAT Perform Step: 2 Determine the Dose Monitoring Requirements to enter the room.

Standard: DETERMINED the Dose Monitoring Requirements to enter the room per the General Access Permit:

TLD.

Alarming Dosimeter.

Comment: SAT UNSAT Perform Step: 3 Determine the minimum Protective Clothing Requirements to enter the valve area.

Standard: DETERMINED the minimum Protective Clothing Requirements to enter the valve area per the General Access Permit:

Deluxe coveralls Booties Hood and hard hat cover Cotton liners Rubber gloves Rubber Overshoes Comment: SAT UNSAT Perform Step: 4 Identify the highest contamination level in dpm/100 cm2 for the room.

Standard: IDENTIFIED the highest contamination level in dpm/100 cm2 for the room is < 1000 dpm/100 cm2.

Comment: SAT UNSAT Page 4 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Identify the highest dose rate in mR/hr for the room.

Standard: IDENTIFIED the highest dose rate at 6.3 mR/hr (Current Trend Point).

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0

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

A Clearance is required to remove 1-LCV-1003, LWPS RCDT 1-01 LVL CTRL VLV from service.

Tags need to be hung on 1-7168, LWPS RCDT 1-01 LVL CTRL VLV UPSTRM ISOL and 1-7167, LWPS RCDT 1-01 LVL CTRL VLV DNSTRM ISOL.

The valves are located in Safeguards Building Elev. 810' NORTH PENETRATION VLV RM / North Side (Room 77A).

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

DETERMINE the Dose Monitoring Requirements to enter the room.

DETERMINE the Protective Clothing Requirements to enter the valve area.

IDENTIFY the highest contamination level in dpm/100 cm2 for the room.

IDENTIFY the highest dose rate in mR/hr for the room.

Dose Monitoring Requirements to enter the room:

_____________________________________________________

Minimum Protective Clothing Requirements to enter the room:

_____________________________________________________

Highest contamination level in dpm/100 cm2 for the room:

_____________________________________________________

Highest dose rate in mR/hr for the room:

_____________________________________________________

Page 6 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0

CPNPP 2016 NRC JPM RA4 Answer Key Rev. 0 Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

A Clearance is required to remove 1-LCV-1003, LWPS RCDT 1-01 LVL CTRL VLV from service.

Tags need to be hung on 1-7168, LWPS RCDT 1-01 LVL CTRL VLV UPSTRM ISOL and 1-7167, LWPS RCDT 1-01 LVL CTRL VLV DNSTRM ISOL.

The valves are located in Safeguards Building Elev. 810' NORTH PENETRATION VLV RM / North Side (Room 77A).

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

DETERMINE the Dose Monitoring Requirements to enter the room.

DETERMINE the Protective Clothing Requirements to enter the valve area.

IDENTIFY the highest contamination level in dpm/100 cm2 for the room.

IDENTIFY the highest dose rate in mR/hr for the room.

Dose Monitoring Requirements to enter the room:

_____________________________________________________

TLD, Alarming Dosimeter

_____________________________________________________

Minimum Protective Clothing Requirements to enter the room:

_____________________________________________________

Deluxe coveralls, Booties, Hood, Hard Hat Cover, Cotton liners, Rubber gloves & Rubber Overshoes

_____________________________________________________

Highest contamination level in dpm/100 cm2 for the room:

2

< 1000 dpm/100 cm

_____________________________________________________

Highest dose rate in mR/hr for the room:

6.3 mR/hr

_____________________________________________________

Page 6 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0 CPNPP 2016 NRC JPM RA4 Answer Key Rev. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA1 Task # SO1028 K/A # 2.1.26 3.6 Title: Determine Electrical Safe Work Practices Requirements Examinee (Print):

Testing Method:

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

Alternate Path: Plant:

Time Critical:

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

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

Initial Conditions: Given the following conditions:

TCX-ESPDTS-01TA, Unit 2 TRAIN A REACTOR TRIP BREAKER RTA is required to be racked from Disconnect to Remove in support of breaker removal.

Initiating Cue: The Shift Manager directs you to DETERMINE the following in accordance with STA-124, Electrical Safe Work Practices:

Hazard Risk Category: ___________________________________

Minimum ATPV in cal/cm2 of FRC: __________________________

Flash Boundary: ________________________________________

Prohibited Boundary: _____________________________________

Arc-rated face shield with balaclava or arc flash suit hood required:

YES NO Ear canal hearing protection required:

YES NO Insulated tools required:

YES NO Task Standard: Utilizing STA-124, determined the Hazard Risk Category, Minimum ATPV, Flash Boundary, Prohibited Boundary and face protection, ear canal and insulated tool requirements.

Ref. Materials: STA-124, Electrical Safe Work Practices, Rev. 2-11 Validation Time: 15 minutes Completion Time: ________ minutes Page 1 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0

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

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

Page 2 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0

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

PROVIDE the examinee with a copy of:

STA-124, Electrical Safe Work Practices. (labeled Procedure 1)

Page 3 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 DETERMINE Hazard Risk Category.

Standard: DETERMINED STA-124 Attachment 8.A, Hazard Risk Category - 2.

Comment: SAT UNSAT Perform Step: 2 DETERMINE Minimum ATPV in cal/cm2 of FRC.

Standard: DETERMINED STA-124 Attachment 8.A, Minimum ATPV in cal/cm2 of FRC - 8 cal/cm2 Comment: SAT UNSAT Perform Step: 3 DETERMINE Flash Boundary.

Standard: DETERMINED STA-124 Attachment 8.A, Flash Boundary - 4 ft.

Comment: SAT UNSAT Perform Step: 4 DETERMINE Prohibited Boundary.

Standard: DETERMINED STA-124 Attachment 8.A, Prohibited Boundary - 1 in.

Comment: SAT UNSAT Perform Step: 5 DETERMINE Arc-rated face shield with balaclava or arc flash suit hood required.

Standard: DETERMINED that an Arc-rated face shield with balaclava or arc flash suit hood required is Required. Circled YES Comment: SAT UNSAT Perform Step: 6 DETERMINE Ear canal hearing protection required.

Standard: DETERMINED that Ear canal hearing protection is required. Circled YES Comment: SAT UNSAT Page 4 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 DETERMINE Insulated tools required.

Standard: DETERMINED that Insulated tools are not required. Circled NO Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

TCX-ESPDTS-01TA, Unit 2 TRAIN A REACTOR TRIP BREAKER RTA is required to be racked from Disconnect to Remove in support of breaker removal.

Initiating Cue: The Shift Manager directs you to DETERMINE the following in accordance with STA-124, Electrical Safe Work Practices:

1. Hazard Risk Category: ___________________________________

2. Minimum ATPV in cal/cm2 of FRC: _________________________

3. Flash Boundary: ________________________________________

4. Prohibited Boundary: ____________________________________

5. Arc-rated face shield with balaclava or arc flash suit hood required:

YES NO

6. Ear canal hearing protection required:

YES NO

7. Insulated tools required:

YES NO Page 6 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0

CPNPP 2016 NRC JPM SA1 Answer Key Rev. 0 Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

TCX-ESPDTS-01TA, Unit 2 TRAIN A REACTOR TRIP BREAKER RTA is required to be racked from Disconnect to Remove in support of breaker removal.

Initiating Cue: The Shift Manager directs you to DETERMINE the following in accordance with STA-124, Electrical Safe Work Practices:

2

1. Hazard Risk Category: ___________________________________

8 cal/cm 2

2. Minimum ATPV in cal/cm2 of FRC: _________________________

4 ft.

3. Flash Boundary: ________________________________________

1 in.

4. Prohibited Boundary: ____________________________________

5. Arc-rated face shield with balaclava or arc flash suit hood required:

YES NO

6. Ear canal hearing protection required:

YES NO

7. Insulated tools required:

YES NO Page 6 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0 CPNPP 2016 NRC JPM SA1 Answer Key Rev. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA2 Task # SO1017 K/A # 2.1.26 3.6 Title: Determine Reactivity Management Severity and Notifications 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 trip of Heater Drain Pump 1-01 occurred Control Rods stabilized below the Rod Insertion Limit Boration was initiated in accordance with ABN-302, Feedwater, Condensate, Heater Drain System Malfunction and the 10000.0 MWD/MTU Reactivity Briefing Sheet The Reactor Operator made an error when performing the boration and set 1-FY-110B, BA BATCH FLO to 17.5 gallons As a result of the error the Control Rods were not restored above the Rod Insertion Limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Initiating Cue: The Shift Manager directs you to DETERMINE the following in accordance with STA-102, Reactivity Management Program:

1. Event Significance Level: ___________________________________

2. Required Notifications: _____________________________________

______________________________________

3. Is a PERC required:

YES NO

4. Is a QERC required:

YES NO Page 1 of 5 CPNPP 2016 NRC JPM SA2 (SO1017B) REV. 0

Appendix C JPM WORKSHEET Form ES-C-1 Task Standard: Utilizing STA-102, determined that a Significance Level 2 event has occurred, that the Shift Operations Manager, Director, Operations and the Reactivity Management Champion are required to be notified, that a PERC is required and that a QERC is not required.

Ref. Materials: STA-102, Reactivity Management Program, Rev. 6-2 ABN-302, Feedwater, Condensate, Heater Drain System Malfunction, Rev. 14-19 Validation Time: 15 minutes Completion Time: ________ minutes Comments:

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

Page 2 of 5 CPNPP 2016 NRC JPM SA2 (SO1017B) REV. 0

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

PROVIDE the examinee with a copy of:

STA-102, Reactivity Management Program. (labeled Procedure 1)

Reactivity Briefing Sheet for 10000.0 MWD/MTU. (labeled Handout 1)

Page 3 of 5 CPNPP 2016 NRC JPM SA2 (SO1017B) REV. 0

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 DETERMINE Event Significance Level.

Standard: DETERMINED STA-102 Attachment 8.B, Significance Level - 2.

Comment: SAT UNSAT Perform Step: 2 DETERMINE Required Notifications.

Standard: DETERMINED STA-102 Attachment 8.A, Required Notifications - Shift Operations Manager, Director, Operations and Reactivity Management Champion Comment: SAT UNSAT Perform Step: 3 DETERMINE PERC Required.

Standard: DETERMINED STA-102 Attachment 8.A, PERC - Required Comment: SAT UNSAT Perform Step: 4 DETERMINE QERC Required.

Standard: DETERMINED STA-102 Attachment 8.A, QERC - NOT Required Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 CPNPP 2016 NRC JPM SA2 (SO1017B) REV. 0

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

A trip of Heater Drain Pump 1-01 occurred Control Rods stabilized below the Rod Insertion Limit Boration was initiated in accordance with ABN-302, Feedwater, Condensate, Heater Drain System Malfunction and the 10000.0 MWD/MTU Reactivity Briefing Sheet The Reactor Operator made an error when performing the boration and set 1-FY-110B, BA BATCH FLO to 17.5 gallons As a result of the error the Control Rods were not restored above the Rod Insertion Limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Initiating Cue: The Shift Manager directs you to DETERMINE the following in accordance with STA-102, Reactivity Management Program:

1. Event Significance Level: ___________________________________

2. Required Notifications: _____________________________________

______________________________________

3. Is a PERC required:

YES NO

4. Is a QERC required:

YES NO Page 5 of 5 CPNPP 2016 NRC JPM SA2 (SO1017B) REV. 0

CPNPP 2016 NRC JPM SA2 Answer Key Rev. 0 Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

A trip of Heater Drain Pump 1-01 occurred Control Rods stabilized below the Rod Insertion Limit Boration was initiated in accordance with ABN-302, Feedwater, Condensate, Heater Drain System Malfunction and the 10000.0 MWD/MTU Reactivity Briefing Sheet The Reactor Operator made an error when performing the boration and set 1-FY-110B, BA BATCH FLO to 17.5 gallons As a result of the error the Control Rods were not restored above the Rod Insertion Limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Initiating Cue: The Shift Manager directs you to DETERMINE the following in accordance with STA-102, Reactivity Management Program:

2

1. Event Significance Level: ___________________________________

2. Required Notifications: _____________________________________

Shift Operations Manager

______________________________________

Director, Operations

______________________________________

Reactivity Management Champion

______________________________________

3. Is a PERC required:

YES NO

4. Is a QERC required:

YES NO Page 5 of 5 CPNPP 2016 NRC JPM SA2 (SO1017B) REV. 0 CPNPP 2016 NRC JPM SA2 Answer Key Rev. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA3 Task # SO1048 K/A # 2.2.14 3.9 / 4.3 Title: Determine Fire Compensatory Measures for an Emergent Condition 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:

FIR-303-1, Halon Fire Suppression System Inspection Sheet has been completed.

Based on the FIR-303-1 a Fire Protection Impairment must be initiated using STA-738-2, Fire Protection System/Equipment Impairment Form.

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

INITIATE the STA-738-2, Fire Protection System/Equipment Impairment Form in accordance with STA-738, Fire Protection Systems/Equipment Impairments and COMPLETE as follows:

RECORD the following information in the **IMPAIRED FIRE PROTECTION SYSTEM/EQUIPMENT** section:

AFFECTED LOCATION.

RECORD the following information in the **COMPENSATORY MEASURE REVIEW/AUTHORIZATION** section:

CONTINUOUS FIRE WATCH required. CHECK if required.

ROVING FIRE WATCH route change required. CHECK if required.

Circle YES or NO.

ROVING FIRE WATCH with OPERABLE detection route change required. CHECK if required. Circle YES or NO.

NONE REQUIRED. CHECK if none required.

AFFECTS FIRE BRIGADE STRATEGY. CHECK if strategy affected. Circle YES or NO.

INSTRUCTIONS/ADDITIONAL INFORMATION. ENTER additional action and specific information if required.

Task Standard: Utilizing STA-738, determined Fire Impairment Compensatory Measures for a disabled Halon System and determined that Fire Brigade Strategy was affected.

Page 1 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 0

Appendix C JPM WORKSHEET Form ES-C-1 Ref. Materials: STA-738, Fire Protection Systems / Equipment Impairments, Rev. 7-1.

STA-738-2, Fire Protection System / Equipment Impairment Form, Rev. 7.

FIR-303-1, Halon Suppression System Inspection Sheet, Rev. 5.

FPI-505, Electrical & Control Building Unit 1 Cable Spread Room Elevation 807-0, Rev. 3-1.

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

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

Page 2 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 0

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

PROVIDE the examinee with a copy of:

STA-738, Fire Protection Systems/Equipment Impairments. (labeled Procedure 1)

STA-738-2, Fire Protection System / Equipment Impairment Form. (labeled Form 1)

FPI-505, Electrical & Control building Unit 1 Cable Spread Room Elevation 807-0.

(labeled Procedure 2)

Completed FIR-303-1, Halon Fire Suppression System Inspection Sheet. (labeled Handout 1)

Page 3 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 0

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following information is from STA-728-2.

Perform Step: 1 Enter information for AFFECTED LOCATION.

Standard: ENTERED the following; BLDG: Electrical Control, ELEV: 807, ROOM/OTHER: Unit 1 Cable Spreading Room.

Comment: SAT UNSAT Perform Step: 2 Determine if CONTINUOUS FIRE WATCH is required.

Standard: DETERMINED that a CONTINUOUS FIRE WATCH was Required and checked box.

Comment: SAT UNSAT Perform Step: 3 Determine if ROVING FIRE WATCH route change is required.

Standard: DETERMINED that a ROVING FIRE WATCH route change was NOT Required and circles NO.

Comment: SAT UNSAT Perform Step: 4 Determine if ROVING FIRE WATCH with operable detection route change is required.

Standard: DETERMINED that a ROVING FIRE WATCH with operable detection route change is NOT Required and circles NO.

Comment: SAT UNSAT Perform Step: 5 Determine if NONE REQUIRED.

Standard: DETERMINED that None Required is not correct and left Blank.

Comment: SAT UNSAT Perform Step: 6 Determine if AFFECTS FIRE BRIGADE STRATEGY.

Standard: DETERMINED that Fire Brigade Strategy is affected and circled YES.

Comment: SAT UNSAT Page 4 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 Determine if OTHER compensatory measure information is required.

Standard: DETERMINED that establishing a continuous fire watch and backup suppression equipment within one hour is required.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 0

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

FIR-303-1, Halon Fire Suppression System Inspection Sheet has been completed.

Based on the FIR-303-1 a Fire Protection Impairment must be initiated using STA-738-2, Fire Protection System/Equipment Impairment Form.

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

INITIATE the STA-738-2, Fire Protection System/Equipment Impairment Form in accordance with STA-738, Fire Protection Systems/Equipment Impairments and COMPLETE as follows:

RECORD the following information in the **IMPAIRED FIRE PROTECTION SYSTEM/EQUIPMENT** section:

AFFECTED LOCATION.

RECORD the following information in the **COMPENSATORY MEASURE REVIEW/AUTHORIZATION** section:

CONTINUOUS FIRE WATCH required. CHECK if required.

ROVING FIRE WATCH route change required. CHECK if required. Circle YES or NO.

ROVING FIRE WATCH with OPERABLE detection route change required. CHECK if required. Circle YES or NO.

NONE REQUIRED. CHECK if none required.

AFFECTS FIRE BRIGADE STRATEGY. CHECK if strategy affected. Circle YES or NO.

INSTRUCTIONS/ADDITIONAL INFORMATION. ENTER additional action and specific information if required.

Page 6 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 0

CPNPP 2016 NRC JPM SA3 Answer Key Rev. 0 FIRE PROTECTION SYSTEM/EQUIPMENT IMPAIRMENT FORM IMPAIRMENT # WORK DOCUMENT NUMBER (S)

CLEARANCE/MTO#

Completed by Fire Protection

- IMPAIRED FIRE PROTECTION SYSTEM/EQUIPMENT**

SUPPRESSION SYSTEM ID Number (i.e., affected valves, system no., etc.)

ISOLATION POINT(S):

DETECTION SYSTEM ID Number ( i.e., panel no., zone, detector)

FIRE PUMP: Electric, G Diesel G ID Number FIRE PROTECTION WATER SUPPLY G ID Number (i.e. tank, loop piv)

FIRE RATED ASSEMBLY G Description/ID Number (i.e. walls, floors, ceilings, penetrations seals, fire doors, fire dampers, radiant energy shield, thermolag, etc.)

OTHER SPECIFY:

807 AFFECTED LOCATION: BLDG. Electrical Control ELEV. ROOM/OTHER Unit 1 Cable Spreading Room PERMIT WORK DESCRIPTION: l REQUESTED BY: EXT. RWO: DATE:

Completed by Fire Protection/Shift Operations (normally performed during the impact review process)

- COMPENSATORY MEASURE REVIEW/AUTHORIZATION**

SCHEDULED IMPAIRED DATE: SCHEDULED COMPLETION DATE:

X CONTINUOUS FIRE WATCH ROUTE NO.:

____ l

____ ROVING FIRE WATCH (route change required) YES NO ROUTE NO.

____ ROVING FIRE WATCH(with operable detection) (route change required) YES NO ROUTE NO.

____ NONE REQUIRED X AFFECTS FIRE BRIGADE STRATEGY? YES NO

____ l

____ OTHER INSTRUCTIONS/ADDITIONAL INFORMATION Establish a continuous fire watch with back up fire suppression equipment within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AUTHORIZED BY: DATE:

Completed by Fire Protection/Shift Operations (This section should be completed just prior to impairing any fire protection systems/equipment)

- IMPAIRMENT/COMPENSATORY MEASURES INITIATION**

- - - - COMPENSATORY MEASURES INITIATED/VERIFIED: YES NO N/A (circle one) *****

BY: DATE: TIME:

Completed by FP/Shift Ops. **RESTORATION**

FIRE PROTECTION SYSTEM/EQUIPMENT BACK IN-SERVICE YES NO (circle one)

BY: DATE: TIME:

STA-738-2 INFORMATION USE PAGE 1 OF 1 l CPNPP 2016 NRC JPM SA3 Answer Key REV. Rev.

7 0 l

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA4 Task # SO1112 K/A # 2.3.7 3.5 / 3.6 Title: Determine Entry Conditions for Radiation Area Clearance And Reporting Requirements Examinee (Print):

Testing Method:

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

Alternate Path: Plant:

Time Critical:

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

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

Initial Conditions: Given the following conditions:

JPM Cue Sheet 1 A Clearance is required to remove 1-LCV-1003, LWPS RCDT 1-01 LVL CTRL VLV from service.

Tags need to be hung on 1-7168, LWPS RCDT 1-01 LVL CTRL VLV UPSTRM ISOL and 1-7167, LWPS RCDT 1-01 LVL CTRL VLV DNSTRM ISOL.

The valves are located in Safeguards Building Elev. 810' NORTH PENETRATION VLV RM / North Side (Room 77A).

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

JPM Cue Sheet 1 DETERMINE the Dose Monitoring Requirements to enter the room.

DETERMINE the minimum Protective Clothing Requirements to enter the valve area.

IDENTIFY the highest contamination level in dpm/100 cm2 for the room.

IDENTIFY the highest dose rate in mR/hr for the room.

Initial Conditions: Given the following conditions:

JPM Cue Sheet 1 The Shift Manager was notified by Radiation Protection that an individual performing maintenance received a Shallow Dose Equivalent (SE) of 275 rads to the skin.

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

JPM Cue Sheet 2 Determine Oral and Written Reportability Requirements, if any.

Oral Reporting Requirement ____________________

Written Reporting Requirement ____________________

Page 1 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0

Appendix C JPM WORKSHEET Form ES-C-1 Task Standard: Utilizing the General Access Permit, Survey Map, and Valve Locator Guide, determined the Dose Monitoring Requirements, Protective Clothing Requirements, highest contamination level and highest dose rate in the area where tagging is to be performed.

Utilizing STA-501, determined Oral and Written Reporting Requirements for an overexposure.

Ref. Materials: RPI-602, Radiological Surveillance and Posting, Rev. 57.

RPI-606, Radiation Work and General Access Permits, Rev. 35.

Valve Locator Map for Unit 1 Safeguards Building Elev. 810' Room 77A.

Survey Map for U-1 SG 810 Pipe Penetration Area Train B Room 1-077A.

CPNPP General Area Permit 20160011, Routine Maintenance, Rev. 02.

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

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

Page 2 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0

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

PROVIDE the examinee with a copy of:

Survey Map for U-1 SG 810 Pipe Pen Area Train B Room 1-077A. (labeled Handout 1)

CPNPP General Area Permit 20160011, Tours and inspections for all groups.

Activities for Operations, Chemistry, NOS, and RP. For entry into elevated dose rates. (labeled Handout 2)

Valve Locator Map for Unit 1 Safeguards Building Elev. 810 Room 77A. (labeled Handout 3)

MAKE the following references available in the classroom:

RPI-602, Radiological Surveillance and Posting.

RPI-606, Radiation Work and General Access Permits.

Page 3 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

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

Perform Step: 1 Determine location of 1-7168 and 1-7167 with respect to Survey Map.

Standard: PERFORMED the following:

LOCATED 1-7168 and 1-7167 using Valve Locator Map for Unit 1 Safeguards Building Elev. 810' Room 77N (77A).

COMPARED the location to the Survey Map.

DETERMINED 1-7168 and 1-7167 are located inside a Radiation Area and the area is contaminated.

Comment: SAT UNSAT Perform Step: 2 Determine the Dose Monitoring Requirements to enter the room.

Standard: DETERMINED the Dose Monitoring Requirements to enter the room per the General Access Permit:

TLD.

Alarming Dosimeter.

Comment: SAT UNSAT Perform Step: 3 Determine the minimum Protective Clothing Requirements to enter the valve area.

Standard: DETERMINED the minimum Protective Clothing Requirements to enter the valve area per the General Access Permit:

Deluxe coveralls Booties Hood and hard hat cover Cotton liners Rubber gloves Rubber Overshoes Comment: SAT UNSAT Perform Step: 4 Identify the highest contamination level in dpm/100 cm2 for the room.

Standard: IDENTIFIED the highest contamination level in dpm/100 cm2 for the room is < 1000 dpm/100 cm2.

Comment: SAT UNSAT Page 4 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Identify the highest dose rate in mR/hr for the room.

Standard: IDENTIFIED the highest dose rate at 6.3 mR/hr (Current Trend Point).

Comment: SAT UNSAT Examiner Note: Provide the examinee with copy of JPM Cue Sheet 2.

Examiner Note: The following steps are from STA-501, Attachment 8.D/4.

Perform Step: 6 Determine Oral Reporting Requirements per STA-501. .D/4 Pages 1 of 12 or 7 of 12 Standard: DETERMINED Oral Reporting Requirements per STA-501:

Event involving byproduct, source, or special nuclear material that may have caused or threatens to cause exposure to individual 250 rad (skin or any one extremity).

DETERMINDED Immediate notification via Emergency Notification System.

Comment: SAT UNSAT Perform Step: 7 Determine Written Reporting Requirements per STA-501. .D/4 Pages 1 of 12 or 7 of 12 Standard: DETERMINED Written Reporting Requirements per STA-501:

Any incident for which notification is required per 10 CFR 20.2202 DETERMINDED Written Report within 30 days (LER).

Comment: SAT UNSAT STOP TIME:

Page 5 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0

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

A Clearance is required to remove 1-LCV-1003, LWPS RCDT 1-01 LVL CTRL VLV from service.

Tags need to be hung on 1-7168, LWPS RCDT 1-01 LVL CTRL VLV UPSTRM ISOL and 1-7167, LWPS RCDT 1-01 LVL CTRL VLV DNSTRM ISOL.

The valves are located in Safeguards Building Elev. 810' NORTH PENETRATION VLV RM / North Side (Room 77A).

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

DETERMINE the Dose Monitoring Requirements to enter the room.

DETERMINE the Protective Clothing Requirements to enter the valve area.

IDENTIFY the highest contamination level in dpm/100 cm2 for the room.

IDENTIFY the highest dose rate in mR/hr for the room.

Dose Monitoring Requirements to enter the room:

_____________________________________________________

Minimum Protective Clothing Requirements to enter the room:

_____________________________________________________

Highest contamination level in dpm/100 cm2 for the room:

_____________________________________________________

Highest dose rate in mR/hr for the room:

_____________________________________________________

Page 6 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0

Appendix C JPM CUE SHEET 2 Form ES-C-1 Initial Conditions: Given the following conditions:

JPM Cue Sheet 1 The Shift Manager was notified by Radiation Protection that an individual performing maintenance received a Shallow Dose Equivalent (SE) of 275 rads to the skin.

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

JPM Cue Sheet 2 Determine Oral and Written Reportability Requirements, if any.

Oral Reporting Requirement ____________________

Written Reporting Requirement ____________________

Page 7 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0

CPNPP 2016 NRC JPM SA4 Answer Key Rev. 0 Appendix C JPM CUE SHEET 1 Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

A Clearance is required to remove 1-LCV-1003, LWPS RCDT 1-01 LVL CTRL VLV from service.

Tags need to be hung on 1-7168, LWPS RCDT 1-01 LVL CTRL VLV UPSTRM ISOL and 1-7167, LWPS RCDT 1-01 LVL CTRL VLV DNSTRM ISOL.

The valves are located in Safeguards Building Elev. 810' NORTH PENETRATION VLV RM / North Side (Room 77A).

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

DETERMINE the Dose Monitoring Requirements to enter the room.

DETERMINE the Protective Clothing Requirements to enter the valve area.

IDENTIFY the highest contamination level in dpm/100 cm2 for the room.

IDENTIFY the highest dose rate in mR/hr for the room.

Dose Monitoring Requirements to enter the room:

_____________________________________________________

TLD, Alarming Dosimeter

_____________________________________________________

Minimum Protective Clothing Requirements to enter the room:

_____________________________________________________

Deluxe coveralls, Booties, Hood, Hard Hat Cover, Cotton liners, Rubber gloves & Rubber Overshoes

_____________________________________________________

Highest contamination 2 level in dpm/100 cm2 for the room:

< 1000 dpm/100 cm

_____________________________________________________

Highest dose rate in mR/hr for the room:

6.3 mR/hr

_____________________________________________________

Page 6 of 7 CPNPP 2016 NRC JPM SA4 (SO1112B) REV. 0 CPNPP 2016 NRC JPM SA4 Answer Key Rev. 0

CPNPP 2016 NRC JPM SA4 Answer Key Rev. 0 Appendix C JPM CUE SHEET 2 Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

The Shift Manager was notified by Radiation Protection that an individual performing maintenance received a Shallow Dose Equivalent (SE) of 275 rads to the skin.

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

DETERMINE Oral and Written Reportability Requirements, if any.

Oral Reporting Requirement Immediate per ENS

_______________

Written Reporting Requirement 30 day LER

_______________

Page 7 of 7 CPNPP 2016 NRC JPM SA4 (SO1112B) REV. 0 CPNPP 2016 NRC JPM SA4 Answer Key Rev. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA5 Task # SO1136 K/A # 2.4.41 2.9 / 4.6 Title: Classify an Emergency Plan Event Examinee (Print):

Testing Method:

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

Alternate Path: Plant:

Time Critical: X READ TO THE EXAMINEE I will explain the Initial Conditions, which steps to simulate or discuss, and provide an Initiating Cue. When you complete the task successfully, the objective for this JPM will be satisfied.

Initial Conditions: Given the following conditions:

EOS-1.1B, Safety Injection Termination is in progress following a Main Steam header break downstream of the Main Steam Isolation Valves.

The Unit Supervisor implemented ABN-740B, Control Room Annunciator System and Status Light Malfunction, Section 2.0, Loss of All Control Room Annunciators 10 minutes ago.

Electrical Maintenance is investigating the tripping of both Annunciator Logic Cabinet breakers.

ABN-906, Plant Process Computer System Malfunction was just entered due to loss of Plant Computer System alarm capability.

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

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

Task Standard: Utilizing EPP-201, determined the Emergency Action Level 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. 0-1.

CPNPP Emergency Action Level Hot, Common, and Cold Classification Charts, Rev.

12A.

Validation Time: 10 minutes Time Critical: 15 minutes Completion ________ minutes Time:

Comments:

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

Page 1 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0

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

MAKE the following available in the classroom:

EPP-201, Assessment of Emergency Action Levels, Emergency Classification, and Plan Activation. (labeled Procedure 1)

EPP-201, Emergency Action Level Technical Bases Document. (labeled Procedure 2)

CPNPP Emergency Action Level Hot, Common, & Cold Classification Charts.

(labeled Handout 1)

Page 2 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0

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 Hot.

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 HOT Conditions (RCS > 200°F)

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

Standard: IDENTIFIED EAL Group / Category as System Malfunction (S).

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

Standard: IDENTIFIED EAL Subcategory as Instrumentation (5).

Comment: SAT UNSAT Page 3 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Candidate should refer to \ EPP-201, Emergency Action Level Technical Bases document for clarification regarding the event classification. The following notes are from Page 235 of 323.

Page 4 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 Classify the event.

Standard: CLASSIFIED the event as an SITE AREA EMERGENCY (SS5.1).

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0

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

EOS-1.1B, Safety Injection Termination is in progress following a Main Steam header break downstream of the Main Steam Isolation Valves.

The Unit Supervisor implemented ABN-740B, Control Room Annunciator System and Status Light Malfunction, Section 2.0, Loss of All Control Room Annunciators 10 minutes ago.

Electrical Maintenance is investigating the tripping of both Annunciator Logic Cabinet breakers.

ABN-906, Plant Process Computer System Malfunction was just entered due to loss of Plant Computer System alarm capability.

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

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

EAL Classification:________________________

THIS JPM IS TIME CRITICAL Page 6 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0

CPNPP 2016 NRC JPM SA5 Answer Key Rev. 0 Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions:

EOS-1.1B, Safety Injection Termination is in progress following a Main Steam header break downstream of the Main Steam Isolation Valves.

The Unit Supervisor implemented ABN-740B, Control Room Annunciator System and Status Light Malfunction, Section 2.0, Loss of All Control Room Annunciators 10 minutes ago.

Electrical Maintenance is investigating the tripping of both Annunciator Logic Cabinet breakers.

ABN-906, Plant Process Computer System Malfunction was just entered due to loss of Plant Computer System alarm capability.

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

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

SS5.1 EAL Classification:________________________

THIS JPM IS TIME CRITICAL Page 6 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0 CPNPP 2016 NRC JPM SA5 Answer Key Rev. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-1 Task # RO1024 K/A # 003.AA1.02 3.6 / 3.4 SF-1 Title: Respond to Control Rod Misalignment Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

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

Time Critical:

CUE THE EXAMINEE Provide the Initial Conditions and Initiating Cue to the Examinee. Any special conditions or instructions should be contained on this sheet.

Initial Conditions: Given the following conditions:

Unit 1 is operating at 100% power.

Control Rod H8 is at 204 steps as indicated on DRPI, all other rods in Control Bank D indicate 216 steps.

Demand counters for Control Bank D are indicating 215 steps.

All necessary verifications, repairs, and determinations have been made in accordance with ABN-712.

Technical Specifications have been referenced.

An NEO is standing by at the P/A Converter AUTO/MANUAL Selector Switch.

Control Rod H8 has been misaligned for 15 minutes.

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

REALIGN Control Rod H8 with Control Bank D at the normal withdrawal rate per ABN-712, Rod Control System Malfunction, Section 3.3, Dropped or Misaligned Rod in MODE 1 or 2, STARTING at Step 14.

DESIRED DRPI light for Step 15 is 222 Steps.

Task Standard: Realigned Control Rod H8 with Control Bank D, positioned Control Bank D to 216 Steps as indicated on DRPI, cleared the Control Rod Urgent Failure Alarm and returned Control Rod Bank Select to Manual.

Ref. Materials: ABN-712, Rod Control System Malfunction Rev. 10 PCN 16.

Validation Time: 10 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

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

Page 1 of 8 CPNPP 2016 NRC JPM S-1 (RO1024A) REV. 0

Appendix C JPM WORKSHEET Form ES-C-1 SIMULATOR SETUP Simulator Operator:

INITIALIZE to IC-33 When contacted, EXECUTE remote function RDR03, P/A Converter to MANUAL.

OR INITIALIZE to IC-18 or any at power Initial Condition and PERFORM the following:

EXECUTE the following malfunctions:

RD13H8, Control Bank D Rod H8 @ 202 Steps.

PLACE Simulator in RUN.

PLACE 1/1-RBSS, Control Rod Bank Select in MANUAL.

DELETE malfunction RD13H8, Control Bank D Rod H8 @ 202 steps.

PLACE Simulator in FREEZE.

When contacted, EXECUTE remote function RDR03, P/A Converter to MANUAL.

Handouts:

PROVIDE the Applicant with a copy of:

ABN-712, Rod Control System Malfunction, Section 3.3, Dropped or Misaligned Rod in MODE 1 or 2, appropriately marked through Step 13. (Labeled Procedure 1)

Page 2 of 8 CPNPP 2016 NRC JPM S-1 (RO1024A) REV. 0

AppendixxC JPM STEPPS Fo orm ES-C-1

- Checck Mark De enotes Crittical Step STTART TIME E:

Examiner Note: The following ste eps are fro m ABN-712 2, Section 3.3.

Performm Step: 1 Transfeer 1/u-RBSS S, CONTRO OL ROD BA ANK SELECT to affeccted bank.

3.3.14 Standarrd: ROTAT TED 1/1-RB BSS, CONT TROL ROD BANK SEL LECT to Ba ank CBD position n.

Comme ent: SA AT UNS SAT Performm Step: 2 Record positions for f affected Rod:

3.3.15.a & 1st line Affected Rod (D DRPI) ____ __

Standarrd: RECOR RDED Rod H8 DRPI a at 204 Stepss.

Comme ent: SA AT UNS SAT Performm Step: 3 Record positions for f affected Rod:

3.3.15.a & 2nd line Bank (DRPI) __ ____

Standarrd: RECOR RDED Bank k CBD DRP PI at 216 Stteps.

Comme ent: SA AT UNS SAT Performm Step: 4 Record positions for f affected Rod:

3.3.15.a & 3rd line Grou up 1 step counter ____

___

Standarrd: OBSER RVED 1-SC C-CBD1, CT TRL BANK D GROUP 1 and REC CORDED at 215 Steps.

S Comme ent: SA AT UNS SAT Page 3 of o 8 CPNPP C 20166 NRC JPM S-1 (RO102 24A) REV. 0

Appendix xC JPM STEP PS Fo orm ES-C-1 Performm Step: 5 Record positions forf affected Rod:

3.3.15.a & 4th line Grou up 2 step counter _______

Standarrd: OBSER RVED 1-SC C-CBD2, CT TRL BANK D GROUP 2 and REC CORDED at 215 Steps.

S Comme ent: SAAT UNS SAT Performm Step: 6 If restorring a Contrrol Bank rod, Then Loocally POSIT TION and MMAINTAIN 3.3.15.b P/A Con nverter Autto-Manual sselector sw witch (SFGD D 832 Rm 1-096) -

MANUA AL Standarrd: CONTA ACTED NEO O to place P/A Convertor in MAN NUAL Simulattor When contacted, c Insert Mallfunction RRDR03 and d report thaat the P/A Operato or: Converrter is in Manual.

M Comme ent: SAAT UNS SAT Performm Step: 7 Move affected group outward d to the dessired DRPI Light.

3.3.15.c Standarrd: PLACED 1/1-FLRM M, CONTR ROL ROD M MOTION CT TRL in OUT T position until DRRPI lights fo or Bank D inndicated 2222 Steps.

Comme ent: SAAT UNS SAT Performm Step: 8 Place all a lift coil dis sconnect swwitches for affected ba ank, groupss 1 AND 2, 3.3.15.d EXCEP PT for affectted rod to th he UP (discconnected) position.

Standarrd: At rear of Control Board, B PLA ACED Lift CCoil Disconnnect Switchhes for Rods D4, D M12, D1 12, and M4 in ROD DISCONNEC CTED (up) p position.

Comme ent: SAAT UNS SAT Page 4 of o 8 CPNPP C 20166 NRC JPM S-1 (RO102 24A) REV. 0

Appendix xC JPM STEPPS Fo orm ES-C-1 Examiner Cue: IF Nece essary, Restate Stab le Plant Co onditions h have been establisshed. Other operato ors will adjust turbine e load if re equired.

Perform m Step: 9 Maintain Tave with hin 2°F of T Tref by conttrolling the ffollowing ass 3.3.15.e.1) & all bulle ets necessa ary:

Turbbine Power//Steam Dum mps/Boratio on/Dilution Standarrd: MONITORED TAVEE.

Comme ent: SA AT UNSSAT Perform m Step: 10 Verify th hat only afffected Rod is moving.

3.3.15.e.2)

Standarrd: VERIFIED that onlly Rod H8 iis moving.

Comme ent: Step SA AT UNSSAT Perform m Step: 11 Ensure last movem ment of affeected rod iss in same direction as last 3.3.15.e.3) movement of affec cted group.

Standarrd: ENSUR RED last mo ovement off Control Ro od H8 is in same direcction as lastt movement of Conttrol Bank C CBD as entirre bank wa as moved ou utward.

Comme ent: SA AT UNSSAT Perform m Step: 12 WITHDRAW the affected a rodd in controlle ed increme ents until aligned with 3.3.15.f its group by DRPI indication.

Standarrd: PLACED 1/1-FLRM M, CONTR ROL ROD M MOTION CT TRL in OUT T position until DR RPI light forr Rod H8 indicated 222 2 Steps.

Comme ent: SA AT UNSSAT Page 5 ofo 8 CPNPP C 2016 6 NRC JPM S-1 (RO102 24A) REV. 0

Appendix xC JPM STEP PS Foorm ES-C-1 Perform m Step: 13 Place all a lift coil dis sconnect sw witches to tthe DOWN (connected d) position.

3.3.15.g Standarrd: At rear of Control Board, B PLAACED Lift C Coil Disconn nect Switch hes for Rods D4, D M12, D1 12, and M4 in ROD CO ONNECTED D (down) position.

Comme ent: SAAT UNS SAT Examiner Note: The following ste eps represe ent the Altternate Patth of this J JPM.

Performm Step: 14 VERIFY Y Rod Conttrol Urgent Failure alarrm - CLEAR R.

3.3.15.h Standarrd: OBSER RVED 1-ALB-6D, Wind dow 1.6, CO ONTROL R ROD CTRL URGENT FAIL is LIT Comme ent: SAAT UNS SAT Performm Step: 15 VERIFY Y Rod Conttrol Urgent Failure alarrm - CLEAR R.

3.3.15.h & RNO a Clear th he Rod Con ntrol Urgentt Failure alaarm as follo ows:

Ensu ure only lift reg white llight on dessignated cirrcuit card in n affected cabinet (See ALB-6D 1.6 logic diagra am) - LIT Examiner Cue: ONLY thet lift reg white light on designated circuit card is LIT Standarrd: PLACE KEPT step p.

Comme ent: SAAT UNS SAT Perform m Step: 16 VERIFY Y Rod Conttrol Urgent Failure alarrm - CLEAR R.

3.3.15.h & RNO b Clear th he Rod Con ntrol Urgentt Failure alaarm as follo ows:

DEP PRESS 1/1--RCAR, CO ONTROL ROD CTRL A ALARM RE ESET Standarrd: DEPRE ESSED 1/1--RCAR, CO ONTROL RO OD CTRL A ALARM RE ESET Comme ent: SAAT UNS SAT Page 6 of o 8 CPNPP C 2016 6 NRC JPM S-1 (RO102 24A) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 17 VERIFY Rod Control Urgent Failure alarm - CLEAR.

3.3.15.h & RNO a Clear the Rod Control Urgent Failure alarm as follows:

Ensure ALL white lights on designated circuit card in affected cabinet (See ALB-6D 1.6 logic diagram) - DARK Examiner Cue: ALL white lights on designated circuit card are DARK Standard: PLACE KEPT step.

Comment: SAT UNSAT Perform Step: 18 RESTORE affected bank to the DRPI position recorded in step 15a.

3.3.15.i Standard: PLACED 1/1-FLRM, CONTROL ROD MOTION CTRL in IN position until DRPI lights for Bank D indicated 216 Steps.

Comment: SAT UNSAT Perform Step: 19 RESET affected bank demand step counters to the values recorded in 3.3.15.j Step 15a.

Standard: ADJUSTED 1-SC-CBD1 and 1-SC-CBD2 to 215 steps.

Comment: SAT UNSAT Perform Step: 20 If operated in step 15b, Then PLACE P/A Converter Auto-Manual 3.3.15.k selector switch - AUTO Standard: CONTACTED NEO to place P/A Convertor in AUTO Simulator When contacted, MODIFY RDR03, to AUTO Operator:

Comment: SAT UNSAT Perform Step: 21 PLACE 1/u-RBSS, CONTROL ROD BANK SELECT to MANUAL.

3.3.15.l Standard: ROTATED 1/1-RBSS, CONTROL ROD BANK SELECT to MANUAL position.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 7 of 8 CPNPP 2016 NRC JPM S-1 (RO1024A) REV. 0

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

Unit 1 is operating at 100% power.

Control Rod H8 is at 204 steps as indicated on DRPI, all other rods in Control Bank D indicate 216 steps.

Demand counters for Control Bank D are indicating 215 steps.

All necessary verifications, repairs, and determinations have been made in accordance with ABN-712.

Technical Specifications have been referenced.

An NEO is standing by at the P/A Converter AUTO/MANUAL Selector Switch.

Control Rod H8 has been misaligned for 15 minutes.

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

REALIGN Control Rod H8 with Control Bank D at the normal withdrawal rate per ABN-712, Rod Control System Malfunction, Section 3.3, Dropped or Misaligned Rod in MODE 1 or 2, STARTING at Step 14.

DESIRED DRPI light for Step 15 is 222 Steps.

Page 8 of 8 CPNPP 2016 NRC JPM S-1 (RO1024A) REV. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-2 Task # RO1205 K/A # 010.A4.03 4.0 / 3.8 SF-3 Title: PORV Block Valve Operability Test 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.

Surveillance on the PORV Block Valves is required.

All Prerequisites have been met.

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

PERFORM the PORV Block Valve Operability Test per OPT-109A, PORV Block Valve Test for both Block Valves.

RECORD data on OPT-109A-1, PORV Block Valve Data Sheet Task Standard: Performed the PORV Block Valve Operability Test through Step 8.2.3 per OPT-109A and Closed the PORV Block Valve upon failure of PORV 1-PCV-456 without receiving a low PZR Pressure automatic reactor trip.

Ref. Materials: OPT-109A, PORV Block Valve Test, Rev. 11.

OPT-109A-1, PORV Block Valve Data Sheet, Rev. 13.

ALM-0053A, 1-ALB-5C, Window 1.4 - PORV 455A/456 NOT CLOSE, Rev. 7-2.

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

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

Page 1 of 7 CPNPP 2016 NRC JPM S-2 (RO1205) REV. 0

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

INITIALIZE to IC-34 OR Load any at power IC AND PERFORM the following:

VERIFY both PRZR Block Valves are OPEN.

ENSURE ALM-0053A, 1-ALB-5C, Window 1.4 - PORV 455A/456 NOT CLOSE is CLEAR.

EXECUTE malfunction RX16B, PRZR PORV 456 fails 30% open when 1/1-8000B, PRZR PORV Block Valve is reopened at Step 8.2.3. use the following conditional command to initiate the malfunction:

{DIRCV8000B.Value=2} IMF RX16B f:30 d:13 Handouts:

INITIALLY PROVIDE the applicant with:

OPT-109A, PORV Block Valve Test. (Labeled Procedure 1)

OPT-109A-1, PORV Block Valve Data Sheet. (Labeled Form 1)

Provide a copy of ALM-0053A, 1-ALB-5C, Window 1.4 - PORV 455A/456 NOT CLOSE when the applicant references the ALM for the above listed annunciator. (Labeled Procedure 2)

Page 2 of 7 CPNPP 2016 NRC JPM S-2 (RO1205) REV. 0

Appendix xC JPM STEPPS Fo orm ES-C-1

- Chec ck Mark Deenotes Crittical Step STTART TIME E:

Examiner Note: The following ste eps are fro m OPT-109 9A, Section 8.0.

Perform m Step: 1 Stroke test t of 1-80 000A, PRZR R PORV BL LK VLV:

8.1.1 ENSUR RE 1/1-8000 0A, PRZR P PORV BLK K VLV is OP PEN.

Standarrd: DETER RMINED 1/1 1-8000A, PRZR PORV V BLK VLV is OPEN Comme ent: SAAT UNS SAT Perform m Step: 2 Stroke test t of 1-80 000A, PRZR R PORV BL LK VLV:

8.1.2 CLOSE E 1/1-8000A A, PRZR PO ORV BLK V VLV (RECO ORD).

Standarrd: PLACCED 1/1-80 000A, PRZR R PORV BL LK VLV in C CLOSE (critical)

OBSE ERVED gre een CLOSE E light LIT ((NOT criticcal)

CIRCCLED CLOS SED on Forrm OPT-10 09A-1 at Ste ep 8.1.2 (NOT critical)

Comme ent: SAAT UNS SAT Perform m Step: 3 Stroke test t of 1-80 000A, PRZR R PORV BL LK VLV:

8.1.3 OPEN 1/1-8000A, 1 PRZR PO RV BLK VL LV (RECOR RD).

Standarrd: PLACCED 1/1-80 000A, PRZR R PORV BL LK VLV in O OPEN (critical)

OBSE ERVED red d OPEN ligh ht LIT (NOT T critical)

CIRCCLED OPEN N on Form OPT-109A A-1 at Step 8 8.1.3 (NOTT critical)

Comme ent: SAAT UNS SAT Perform m Step: 4 Stroke test t of 1-80 000B, PRZR R PORV BL LK VLV:

8.2.1 ENSUR RE 1/1-8000 0B, PRZR P PORV BLK K VLV is OP PEN.

Standarrd: DETER RMINED 1/1 1-8000B, PRZR PORV V BLK VLV is OPEN Comme ent: SAAT UNS SAT Page 3 of o 7 CPNPP 2016 2 NRC J PM S-2 (RO O1205) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Stroke test of 1-8000B, PRZR PORV BLK VLV:

8.2.2 CLOSE 1/1-8000B, PRZR PORV BLK VLV (RECORD).

Standard: PLACED 1/1-8000B, PRZR PORV BLK VLV in CLOSE (critical)

OBSERVED green CLOSE light LIT (NOT critical)

CIRCLED CLOSED on Form OPT-109A-1 at Step 8.2.2 (NOT critical)

Comment: SAT UNSAT Perform Step: 6 Stroke test of 1-8000B, PRZR PORV BLK VLV:

8.2.3 OPEN 1/1-8000B, PRZR PORV BLK VLV (RECORD).

Standard: PLACED 1/1-8000B, PRZR PORV BLK VLV in OPEN (critical)

OBSERVED red OPEN light LIT (NOT critical)

CIRCLED OPEN on Form OPT-109A-1 at Step 8.2.3 (NOT critical)

Comment: SAT UNSAT SIMULATOR When 1/1-8000B is reopened, EXECUTE malfunction RX16B at 30%.

OPERATOR Ensure the conditional inserted the malfunction.

NOTE: {DIRCV8000B.Value=2} IMF RX16B f:30 d:13 Perform Step: 7 Acknowledge annunciator 1-ALB-5C, Window 1.4 - PORV 455A/456 NOT CLOSE.

Standard: ACKNOWLEDGED annunciator 5C, Window 1.4 - PORV 455A/456 NOT CLOSE and RECOGNIZED PORV 456 is OPEN Comment: SAT UNSAT Page 4 of 7 CPNPP 2016 NRC JPM S-2 (RO1205) REV. 0

Appendix xC JPM STEP PS Foorm ES-C-1 Examiner Note: The following ste eps represe ent the Altternate Patth of this J JPM.

Examiner Note: The applicant ma ay recognizze the failu ure and tak ke action p prior to referen ncing the ALM.

A Examiner Note: The following ste eps are fro m ALM-0053A, 1-ALB B-5C, Wind dow 1.4.

Providee a copy to o the exam minee when n they reac ch for the c control board copy c

Perform m Step: 8 Determine affected d PORV.

1 Standarrd: DETER RMINED afffected POR RV is 1/1-PC CV-456 Comme ent: SAAT UNS SAT Perform m Step: 9 Monitorr pressurizeer pressure.

2 & 2.A Iff one chann nel is indicaating > 60 ppsig differen nce betwee en the remaining r operable o ch annels, go to ABN-70 05.

Standarrd: DETER RMINED all Pressurize er pressure indicationss are readinng approximately the same value e Comme ent: SAAT UNS SAT Examiner Note: 1/1-PCVV-456, PRZ ZR PORV w will be stucck in mid-p position.

Perform m Step: 10 Monitorr pressurizeer pressure.

2, 2.B, & 2nd bullet Iff reactor is in Mode 1, 2 or 3 with h pressurize er pressure e < 2335 psig, p Then close c affectted PORV.

1/1-PCV V-456, PRZR PORV Standarrd: PLACED 1/1-PCV V-456, PRZR R PORV in CLOSE an nd OBSERV VED red OPEN and a green CLOSE C ligh hts both LITT Comme ent: SAAT UNS SAT Page 5 of o 7 CPNPP 2016 2 NRC J PM S-2 (RO O1205) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 11 With reactor in Mode 4, 5 or 6, Then refer to TDM-301A to determine 3 RCS pressure and temperature limits.

Standard: DETERMINED Reactor is in MODE 1 Examiner Note: Examinee determines step is N/A.

Comment: SAT UNSAT Perform Step: 12 Verify pressurizer or RCS wide range pressure stabilizes.

4, 4.A, & 2nd bullet IF pressure continues to decrease due to PORV leakage, THEN close both PORV block valves AND determine affected PORV.

1/1-8000B, PRZR PORV BLK VLV Standard: PLACED 1/1-8000B, PRZR PORV BLK VLV in CLOSE (critical)

OBSERVED green CLOSE light LIT (non-critical)

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 CPNPP 2016 NRC JPM S-2 (RO1205) REV. 0

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

Unit 1 is in MODE 1 at 100% power.

Surveillance on the PORV Block Valves is required.

All Prerequisites have been met.

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

PERFORM the PORV Block Valve Operability Test per OPT-109A, PORV Block Valve Test for both Block Valves.

RECORD data on OPT-109A-1, PORV Block Valve Data Sheet Page 7 of 7 CPNPP 2016 NRC JPM S-2 (RO1205) REV. 0

Appendix C JPM STEPS Form ES-C-1 Facility: CPNPP JPM # NRC S-3 Task # RO1412 K/A # 025.AA1.02 3.8 / 3.9 SF-4-P Title: Respond to a Shutdown Loss of Coolant 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 in MODE 4 with the following conditions:

RHR Train B is in service RHR Train A is in ECCS standby with 1/1-8701A and 1/1-8702A, RHRP 1 HL RECIRC ISOL VLVs CLOSED and De-energized CCP 1-02, SIP 1-01 and SIP 1-02 breakers have been racked out to comply with LCO 3.4.12 A Loss of Coolant Accident has occurred ABN-108, Shutdown Loss of Coolant is being implemented Positive Displacement Charging Pump has been started Pressurizer Level is still lowering Initiating Cue: The Unit Supervisor directs you to PERFORM ABN-108, Shutdown Loss of Coolant, starting at Step 2.3.8.b, Check RCS Status, with the Pressurizer Level NOT stable or increasing Task Standard: In accordance with ABN-108, took actions to isolate RCS leak and provide injection to the RCS via CCP injection.

Ref. Materials: ABN-108, Shutdown Loss of Coolant, Rev. 4, PCN-5 Validation Time: 10 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

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

Page 1 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0

Appendix C JPM STEPS Form ES-C-1 SIMULATOR SETUP SIMULATOR OPERATOR:

INITIALIZE to IC-40 or any MODE 4 Initial Condition and then PERFORM the following:

ENSURE Train B RHR Systems in service.

ENSURE 480V MCC BREAKER LOCKED OFF Circles ON 1/1-8701A and 1/1-8702A ENSURE 480V MCC BREAKER LOCKED OFF Circles OFF 1/1-8701B and 1/1-8702B START TREND GTGC MODE 4 for current plant condition.

PERFORM the 1st seven steps of ABN-108 Place PDP in service Place CCP 1-02 and SIP Breakers in Rackout INSERT malfunction RC17A at 600 gpm to lower RCS level and allow Cold Calibrated PRZR level to lower to 50% then FREEZE the Simulator.

PERFORM the following after each JPM:

REMOVE the key from 1/1-8835, SI to CL 1-4 INJ ISOL VLV and RETURN to Key Locker.

Handout:

PROVIDE the examinee with a copy of:

ABN-108, Shutdown Loss of Coolant with initials as appropriate through Step 2.3.8.b.

- Check Mark Denotes Critical Step START TIME:

Page 2 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0

Appendix C JPM STEPS Form ES-C-1 Simulator When examinee is ready, PLACE Simulator in RUN.

Operator:

Simulator INSERT remote function CVR17 for CCP 1-02 Breaker (Key 1);

Operator: SIR01 for SI Pump 1-01 Breaker (Key 2); or SIR02 for SI Pump 1-02 Breaker (Key 3) as directed by the applicant Perform Step: 1 Dispatch operators to rack in the breaker to affected units non-operating Step 8 RNO 1) CCP OR ONE safety injection pump.

Standard: DISPATCHED operator to rack in breaker for one pump Comment: SAT UNSAT Examiner Note: Examinee will obtain key from Key Locker.

Perform Step: 2 Ensure 1/u-8835, SI TO CL 1-4 INJ ISOL VLV, OPEN.

Step 8 RNO 2)

Standard: INSERTED key in switch and TURNED to ON position then PLACED 1/1-8835, SI TO CL 1-4 INJ ISOL VLV in OPEN (Critical)

OBSERVED red OPEN light illuminated (NOT Critical)

Comment: SAT UNSAT Examiner Note: The next two steps may be performed in any order Perform Step: 3 Stop both RHR pumps AND place HSs in PULL-OUT:

Step 8 RNO 3) 1/u-APRH1, RHRP 1 1/u-APRH2, RHRP 2 Standard: PLACED 1/1-APRH1, RHRP 1, in PULL-OUT and OBSERVED the green and red pump lights dark Comment: SAT UNSAT Perform Step: 4 Stop both RHR pumps AND place HSs in PULL-OUT:

Step 8 RNO 3) 1/u-APRH1, RHRP 1 1/u-APRH2, RHRP 2 Standard: PLACED 1/1-APRH2, RHRP 2, in PULL-OUT and OBSERVED the green and red pump lights dark Comment: SAT UNSAT Page 3 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 5 Close 1/u-8701A, RHRP 1 HL RECIRC ISOL VLV AND 1/u-8702B, Step 8 RNO 4) RHRP 2 HL RECIRC ISOL VLV.

Standard: OBSERVED 1/1-8701A, RHRP 1 HL RECIRC ISOL VLV in CLOSE and DE-ENERGIZED Comment: SAT UNSAT Perform Step: 6 Close 1/u-8701A, RHRP 1 HL RECIRC ISOL VLV AND 1/u-8702B, Step 8 RNO 4) RHRP 2 HL RECIRC ISOL VLV.

Standard: PLACED 1/1-8702B, RHRP 2 HL RECIRC ISOL VLV in CLOSE and OBSERVED green CLOSE light illuminated.

Comment: SAT UNSAT Perform Step: 7 Identify AND Isolate Leak per Attachment 7, while continuing this Step 8 RNO 5) procedure.

Standard: IDENTIFY and ISOLATE Leak per Attachment 7, RCS Leak Identification and Isolation.

Examiner Cue: Another operator will perform Attachment 7, RCS Leak Identification and Isolation.

Comment: SAT UNSAT Perform Step: 8 GO TO Step 11.

Step 8 RNO 6)

Standard: PLACEKEPT to Step 11.

Comment: SAT UNSAT Perform Step: 9 Verify RWST level - GREATER THAN 33%:

Step 11 u-LI-932, RWST LVL CHAN III u-LI-933, RWST LVL CHAN IV Standard: DETERMINED RWST level greater than 33% by OBSERVING 1-LI-932, RWST LVL CHAN III and 1-LI-933, RWST LVL CHAN IV.

Comment: SAT UNSAT Page 4 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 10 Verify ONE CCP - RUNNING.

Step 12.a Standard: DETERMINED CCP 1-01 was RUNNING.

Comment: SAT UNSAT Perform Step: 11 STOP 1/u-APPD, PDP.

Step 12.b Standard: PLACED 1/1-APPD, PDP handswitch in STOP and OBSERVED Green Pump light LIT Comment: SAT UNSAT Perform Step: 12 Verify CCP suction aligned from RWST:

Step 12.c 1st bullet 1/u-LCV-112D RWST TO CHRG PMP SUCT VLV - OPEN Standard: VERIFIED 1/1-LCV-112D RWST TO CHRG PMP SUCT VLV in OPEN and OBSERVED red OPEN light illuminated.

Comment: SAT UNSAT Perform Step: 13 Verify CCP suction aligned from RWST:

Step 12.c 2nd bullet 1/u-LCV-112E RWST TO CHRG PMP SUCT VLV - OPEN Standard: VERIFIED 1/1-LCV-112E RWST TO CHRG PMP SUCT VLV in OPEN and OBSERVED red OPEN light illuminated.

Comment: SAT UNSAT Perform Step: 14 Verify CCP suction aligned from RWST:

Step 12.c 3rd bullet 1/u-LCV-112B, VCT TO CHRG PMP SUCT VLV - CLOSED Standard: VERIFIED 1/1-LCV-112B, VCT TO CHRG PMP SUCT VLV in CLOSE and OBSERVED green CLOSE light illuminated.

Comment: SAT UNSAT Page 5 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 15 Verify CCP suction aligned from RWST:

Step 12.c 4th bullet 1/u-LCV-112C, VCT TO CHRG PMP SUCT VLV - CLOSED Standard: VERIFIED 1/1-LCV-112C, VCT TO CHRG PMP SUCT VLV in CLOSE and OBSERVED green CLOSE light illuminated.

Comment: SAT UNSAT Perform Step: 16 Verify the following valves closed:

Step 12.d u-ZL-8220, CHRG PMP SUCT HI POINT VENT VLV - CLOSED u-ZL-8221, CHRG PMP SUCT HI POINT VENT VLV - CLOSED 1/u-8210A, H2/N2 SPLY VLV - CLOSED 1/u-8210B, H2/N2 SPLY VLV - CLOSED 1/u-8202A, VENT VLV - CLOSED 1/u-8202B, VENT VLV - CLOSED Standard: VERIFIED the following valves closed:

1-ZL-8220, CHRG PMP SUCT HI POINT VENT VLV - Green light LIT 1-ZL-8221, CHRG PMP SUCT HI POINT VENT VLV - Green light LIT 1/1-8210A, H2/N2 SPLY VLV - Green light LIT 1/1-8210B, H2/N2 SPLY VLV - Green light LIT 1/1-8202A, VENT VLV - Green light LIT 1/1-8202B, VENT VLV - Green light LIT Comment: SAT UNSAT Examiner Note: Performance of either Step 17 or Step 18 is critical to establish an injection path Examiner Note: The next two steps may be performed in any order Perform Step: 17 Align CCP injection:

Step 12.e 1st bullet 1/u-8801A, CCP SI ISOL VLV - OPEN Standard: PLACED 1/1-8801A, CCP SI ISOL VLV in OPEN and OBSERVED red OPEN light illuminated.

Comment: SAT UNSAT Page 6 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 18 Align CCP injection:

Step 12.e 2nd bullet 1/u-8801B, CCP SI ISOL VLV - OPEN Standard: PLACED 1/1-8801B, CCP SI ISOL VLV in OPEN and OBSERVED red OPEN light illuminated.

Comment: SAT UNSAT Perform Step: 19 Verify ECCS flow:

u-FI-917, CCP SI FLO Standard: OBSERVED flow indication on 1-FI-917, CCP SI FLO.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 7 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Unit 1 is in MODE 4 with the following conditions:

RHR Train B is in service RHR Train A is in ECCS standby with 1/1-8701A and 1/1-8702A, RHRP 1 HL RECIRC ISOL VLVs CLOSED and De-energized CCP 1-02, SIP 1-01 and SIP 1-02 breakers have been racked out to comply with LCO 3.4.12 A Loss of Coolant Accident has occurred ABN-108, Shutdown Loss of Coolant is being implemented Positive Displacement Charging Pump has been started Pressurizer Level is still lowering Initiating Cue: The Unit Supervisor directs you to PERFORM ABN-108, Shutdown Loss of Coolant, starting at Step 2.3.8.b, Check RCS Status, with the Pressurizer Level NOT stable or increasing Page 8 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-4 Task # RO3113 K/A # 045.A4.01 3.1 / 2.9 SF-4P Title: Perform Pre-Startup Turbine Trip Checks Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

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

Time Critical:

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

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

Initial Conditions: Given the following conditions:

Unit 1 is in MODE 3.

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

Perform OPT-410A, Pre-Startup Turbine Trip Checks.

Task Standard: In accordance with OPT-410A, latched the Turbine, commenced opening the HP and LP stop valves and then tripped the Turbine prior to the HP stop valves obtaining the full open position.

Ref. Materials: OPT-410A, Pre-Startup Turbine Trip Checks. Rev. 9 - 4.

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

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

Page 1 of 8 CPNPP 2016 NRC JPM S-4 (RO3113) REV. 0

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

INITIALIZE to IC-37 or Initialize to IC-6 and insert the following:

Insert HP Control Valve leakage

{LOTCZL2414A_2.Value=1} IMF AOTC_JC01DA001_NT1 f:600 d:53 r:60

{LOTCZL2414A_2.Value=1} IMF AOTC_JC01DA001_NT2 f:600 d:53 r:60

{LOTCZL2414A_2.Value=1} IMF AOTC_JC01DA001_NT3 f:600 d:53 r:60

Modify Control Valve Leakage when Turbine tripped

{DITCTCTRP.Value=1} MMF AOTC_JC01DA001_NT1 f:194 r:60

{DITCTCTRP.Value=1} MMF AOTC_JC01DA001_NT2 f:194 r:60

{DITCTCTRP.Value=1} MMF AOTC_JC01DA001_NT3 f:194 r:60 Handout:

PROVIDE the examinee with a copy of:

OPT-410A, Pre-Startup Turbine Trip Checks (Labeled Procedure 1)

OPT-410A-1, Pre-Startup Turbine Trip Checks Data Sheet (Labeled Form 1)

Page 2 of 8 CPNPP 2016 NRC JPM S-4 (RO3113) REV. 0

Appendix xC JPM STEP PS Foorm ES-C-1

- Chec ck Mark De enotes Crittical Step STTART TIME E:

Examiner Note: The following ste eps are fro m OPT-410 0A, Section 8.0.

Perform m Step: 1 Latch thhe turbine as a follows:

Step 8.11 & 8.1.1 On the TG Controll Display, e ensure the tturbine is tripped, Turrbine Trip Bar Red d.

Standarrd: DETER RMINED tha at Turbine T Trip bar was red.

Comme ent: SAAT UNS SAT Perform m Step: 2 Latch thhe turbine as a follows:

8.1 & 8.1.2 Verify th he following g light indiccations on C CB-04, 1-TS SLB-3 are o on:

1.7 1 - TURB TRIP FLUID LO 1-63 3AST 1 2.7 2 - TURB TRIP FLUID LO 1-63 3AST 2 3.7 3 - TURB TRIP FLUID LO 1-63 3AST 3 Standarrd: VERIFIED on 1-TS SLB-3 that windows 1.7, 2.7 and 3.7 are LIT T.

Comme ent: SAAT UNS SAT Perform m Step: 3 Latch thhe turbine as a follows:

8.1, 8.1.3 3 & 8.1.3A On the TG Controll Display in the Start-Up Section n, reset thee Turbine Trip as follows.

A.

A Click thee Turbine L Latch Subgrroup Contro oller to bring up the Osd Standarrd: OPENE ED the Turb bine Latch S Subgroup C Controller OOsd.

Comme ent: SAAT UNS SAT Page 3 of o 8 CPNPP 2016 2 NRC J PM S-4 (RO O3113) REV. 0

Appendix xC JPM STEP PS Fo orm ES-C-1 Perform m Step: 4 Latch th he turbine as a follows:

8.1, 8.1.3 3 & 8.1.3B On the TG Controll Display in the Start-Up Section n, reset the e Turbine Trip as follows.

B.

B IF the Tu urbine Latcch Subgroup Controlle er is OFF (ggreen/grey),,

THEN Click C 0/1 th hen Executte to turn ON (green/re ed) the Controlle er.

Standarrd: CLICKE ED the 0/1 and Execcute. Subgro oup Controoller indicate ed ON (green/rred).

Comme ent: SAAT UNS SAT Perform m Step: 5 Latch th he turbine as a follows:

8.1, 8.1.3 3 & 8.1.3C On the TG Controll Display in the Start-Up Section n, reset the e Turbine Trip as follows.

C.

C On the TG T Control Display in the Speed Control Se ection, verify Sp peed Targe et Controller lower or e equal to acttual speed.

Standarrd: VERIFIED speed target t (134 RPM) is loower than actual speed d (194 RPM).

Comme ent: SAAT UNS SAT Perform m Step: 6 Latch th he turbine as a follows:

8.1, 8.1.3 3 & 8.1.3D On the TG Controll Display in the Start-Up Section n, reset the e Turbine Trip as follows.

D.

D In the O Osd click 1 1 then Exe ecute to sta art the Latchhing of the Turbine..

Standarrd: CLICKE ED the 1 and a Executte. Subgrou up controller indicated blinking red.

Comme ent: SAAT UNS SAT Page 4 of o 8 CPNPP 2016 2 NRC J PM S-4 (RO O3113) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 Latch the turbine as follows:

8.1, 8.1.4 & 1st bullet Verify the following parameters:

On the TG Display, verify the turbine trip is reset, Turbine Trip Bar white.

Standard: VERIFIED Turbine Trip Bar white.

Comment: SAT UNSAT Perform Step: 8 Latch the turbine as follows:

8.1, 8.1.4 & 2nd bullet Verify the following parameters:

1-PI-6559, TURB L/O PRESS - greater than 25 PSIG Standard: VERIFIED Turbine Lube Oil Pressure is approximately 42 psig.

Comment: SAT UNSAT Perform Step: 9 Latch the turbine as follows:

8.1, 8.1.4 & 3rd bullet Verify the following parameters:

1-PI-6561, EHC FLUID PRESS - greater than 114 PSIG Standard: VERIFIED EHC Fluid Pressure is approximately 170 psig.

Comment: SAT UNSAT Perform Step: 10 Latch the turbine as follows:

8.1, 8.1.4 & 4th bullet Verify the following parameters:

1-PI-6566, HP EHC FLUID PRESS - approximately 455 PSIG Standard: VERIFIED HP EHC Fluid Pressure is approximately 525 psig.

Examiner Cue: If the applicant questions whether the HP EHC Fluid Pressure is close enough to 455 psig to continue; Provide the following cue:

The Unit Supervisor directs you to continue with the Turbine Trip Checks.

Comment: SAT UNSAT Page 5 of 8 CPNPP 2016 NRC JPM S-4 (RO3113) REV. 0

Appendix xC JPM STEP PS Fo orm ES-C-1 Perform m Step: 11 Verify th he following g light indiccations on CCB-04, 1-TSSLB-3 are o on:

8.2 1.61 - MSL 1 HP STOP P VLV 4 CLO OSE UV-24 428A 2.62 - MSL 2 HP STOP P VLV 1 CLO OSE UV-24 429A 3.63 - MSL 3 HP STOP P VLV 3 CLO OSE UV-24 430A 4.64 - MSL 4 HP STOP P VLV 2 CLO OSE UV-24 431A Standarrd: VERIFIED on 1-TS SLB-3 that windows 1.6, 2.6, 3.6 and 4.6 are e LIT.

Comme ent: SAAT UNS SAT Perform m Step: 12 Verify HP H stop valv ves are closed on CB--10:

8.3 1-ZL-2429A 1 A, HPT STO OP VLV 1 1-ZL-2431A 1 A, HPT STO OP VLV 2 1-ZL-2430A 1 A, HPT STO OP VLV 3 1-ZL-2428A 1 A, HPT STO OP VLV 4 Standarrd: VERIFIED on CB-10 that Gre een light LIT T and Red light DARK K for each valve.

Comme ent: SAAT UNS SAT Examiner Note: The following ste eps represe ent the Altternate Patth of this JJPM.

Examiner Note: The turrbine speed will conttinue to inc crease to ggreater tha an 100 RPM ab bove the original o turnning gear s speed requ uiring a Tuurbine Trip.

Perform m Step: 13 On the TG Controll Display in the Start-Up Section n, turn ON the Open 8.4 Stop Va alves Sublooop Contro oller to open n the HP annd LP stop valves.

Standarrd: CLICKE ED the 0/1 and Execcute. Subgro oup controlller turned rred.

Comme ent: SAAT UNS SAT Page 6 of o 8 CPNPP 2016 2 NRC J PM S-4 (RO O3113) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 14 The normal turning gear speed for the turbine may increase when the 5.1 & Caution turbine stop valves are open due to some leakage through the control valves. The turbine RPM should not be allowed to increase more than 100 RPM above the original turning gear speed. If the speed continues to increase, the turbine should be tripped and the conditions should be evaluated.

Standard: DEPRESSED 1-TTSW Pushbutton on CB-10 prior to ALL HP Stop Valves obtaining Full Open status on CB-10, Red light LIT and Green light DARK.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 7 of 8 CPNPP 2016 NRC JPM S-4 (RO3113) REV. 0

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

Unit 1 is in MODE 3.

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

Perform OPT-410A, Pre-Startup Turbine Trip Checks.

Page 8 of 8 CPNPP 2016 NRC JPM S-4 (RO3113) REV. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-5 Task # RO2002 K/A # 026.A4.01 4.5 / 4.3 SF-5 Title: Transfer Containment Spray From Injection to Recirculation Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

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

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

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

Initial Conditions: Given the following conditions:

A Large Break LOCA has occurred and Containment Spray has actuated.

The Emergency Core Cooling System has been aligned for Cold Leg Recirculation per EOS-1.3A, Transfer to Cold Leg Recirculation.

Refueling Water Storage Tank (RWST) level is 7% and lowering.

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

When RWST level reaches 6%, Perform EOS-1.3A, Transfer to Cold Leg Recirculation Attachment 1.H, Containment Spray Switchover Criterion.

Task Standard: Utilizing EOS-1.3A, transferred Containment Spray Train A from the Injection Mode to the Recirculation Mode from the Containment Sumps. Stopped Train B Containment Spray Pumps when alignment to the Containment Sump could not be performed.

Ref. Materials: EOS-1.3A, Transfer to Cold Leg Recirculation, Rev. 9-0.

STI-214.01, Control of Timed Operator Actions, Rev. 0-5.

Validation Time: 3 minutes Completion Time: ________ minutes Time Critical Time: 70 seconds Completion Time: ________ seconds Comments:

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

Page 1 of 6 CPNPP 2016 NRC JPM S-5 (RO2002C) REV. 0

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

INITIALIZE to IC #38 or any Post LOCA with RHR Swapover completed IC and PERFORM the following:

INSERT MalfunctionCS05B to fail 1-HS-4783 in CLOSE position.

If IC #38 is not available, RESET to any at power IC and PERFORM the following:

INSERT malfunction RC08A2 (or equivalent Large Break LOCA).

PLACE Simulator in RUN.

REDUCE AFW Flow to all SGs.

RESET SI, SIS, Containment and Isolation Phases A & B and Containment Spray.

STOP both Emergency Diesel Generators.

STOP all Reactor Coolant Pumps.

When RWST level reaches LO-LO level, TRANSFER ECCS to Cold Leg Recirculation by performing Steps 1-3 of EOS-1.3A.

INSERT MalfunctionCS05B to fail 1-HS-4783 in CLOSE position.

FREEZE simulator when RWST level is 7%.

Handout:

PROVIDE the examinee with a copy of:

EOS-1.3A, Transfer to Cold Leg Recirculation.

Attachment 1.H, Containment Spray Switchover Criterion. (labeled Procedure 1)

Page 2 of 6 CPNPP 2016 NRC JPM S-5 (RO2002C) REV. 0

Appendix xC JPM STEP PS Fo orm ES-C-1

- Checck Mark De enotes Crittical Step ST TART TIME E:

Examiner Note: The following ste eps are fro m EOS-1.3 3, Attachment 1.H.

Examiner Note: CUE th he Simulato or Operatoor to PLACE the Simu ulator in RUN.

Perform m Step: 1 Check RWST R leveel - LESS TTHAN 6%.

4.a.

Standarrd: OBSER RVED 1-LI-9 930, RWST T LVL CHAN I or 1-LI-931, RWST T LVL CHAN II I and VERIFY level iss less than 6 6%.

Comme ent: SAAT UNS SAT Once ap pplicant re eads level less l than 6%.

6 Tim me Critical STAART TIME::

Examiner Note: Steps 2 and 3 ma ay be perfo ormed in an ny order.

Perform m Step: 2 Open CNTMT C SMP TO CSP 1 & 3 AND D 2 & 4 SUC CT ISOL VL LVs:

4.b.1) & 1st bullet 1-HS-4782 1

Standarrd: PERFO ORMED the following:

PLACED P 1--HS-4782, CCNTMT SM MP TO CSP P 1 & 3 SUCCT ISOL VLV V to OPE EN (criticall).

OBSERVED O D red OPEN N light LIT ((NOT critic cal).

Comme ent: SAAT UNS SAT Perform m Step: 3 Realignn Containme ent Spray S System as ffollows:

nd 4.b.1) & 2 bullet Open O CNTM MT SMP TO O CSP 1 & 3 AND 2 & 4 SUCT IS SOL VLVs:

1-HS-47 783 Standarrd: PERFO ORMED the following:

PLACED P 1--HS-4783, CCNTMT SM MP TO CSP P 2 & 4 SUCCT ISOL VLV V to OPE EN.

OBSERVED O D green CL LOSE light L LIT.

Comme ent: SAAT UNS SAT Page 3 of o 6 CPNPP C 20166 NRC JPM S-5 (RO200 02C) REV. 0

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

Perform Step: 4 IF CNTMT SMP TO CSP VLV(s) can NOT be opened, THEN Place 4.b.1) RNO affected CSPs in PULL-OUT.

Standard: PERFORMED the following:

PLACED 1-HS-4766, CSP 2 in PULLOUT (critical).

OBSERVED red FAN light LIT (NOT critical).

PLACED 1-HS-4767, CSP 4 in PULLOUT (critical).

OBSERVED red FAN light LIT (NOT critical).

Comment: SAT UNSAT Examiner Note: Perform Steps 5 and 6 may be performed in any order.

Perform Step: 5 Close RWST TO CSP 1 & 3 AND 2 & 4 SUCT VLVs:

4.b.2) & 1st bullet 1-HS-4758 Standard: PERFORMED the following:

PLACED 1-HS-4758, RWST TO CSP 1 & 3 SUCT VLV to CLOSE (critical).

OBSERVED green CLOSE light LIT (NOT critical).

Comment: SAT UNSAT Once 1-HV-4758 is Fully Closed. Time Critical STOP TIME:

Perform Step: 6 Close RWST TO CSP 1 & 3 AND 2 & 4 SUCT VLVs:

4.b.2) & 2nd bullet 1-HS-4759 Standard: PERFORMED the following:

PLACED 1-HS-4759, RWST TO CSP 2 & 4 SUCT VLV to CLOSE.

OBSERVED green CLOSE light LIT Comment: SAT UNSAT Page 4 of 6 CPNPP 2016 NRC JPM S-5 (RO2002C) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 Verify containment spray flows.

4.b.3)

Standard: OBSERVED Containment Spray flows on:

1-FI-4772-1, CSP 1 DISCH FLO at ~3600 GPM.

1-FI-4772-2, CSP 3 DISCH FLO at ~3600 GPM.

1-FI-4773-1, CSP 2 DISCH FLO at 0 GPM.

1-FI-4773-2, CSP 4 DISCH FLO at 0 GPM.

Comment: SAT UNSAT Perform Step: 8 IF containment spray train(s) NOT providing spray flow, THEN perform 4.b.3) RNO 3) A) the following:

Place affected CS HX OUT VLV(s) in PULL-OUT.

Standard: PERFORMED the following:

PLACED 1-HS-4777, CS HX 2 OUT VLV to PULLOUT OBSERVED all lights OFF Comment: SAT UNSAT Perform Step: 9 IF containment spray train(s) NOT providing spray flow, THEN perform 4.b.3) RNO 3) B) the following:

Notify Plant Staff of containment spray train(s) condition.

Standard: CONSULTED Plant Staff to determine contingency actions.

Examiner Cue: Another operator will consult with Plant Staff. The Unit Supervisor directs you to continue with the procedure.

Comment: SAT UNSAT Perform Step: 10 IF containment spray pumps have been stopped due to RWST 4.b.4) level, THEN perform the following:

Standard: DETERMINED Containment Spray Pumps were NOT stopped due to low RWST Level.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP 2016 NRC JPM S-5 (RO2002C) REV. 0

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

A Large Break LOCA has occurred and Containment Spray has actuated.

The Emergency Core Cooling System has been aligned for Cold Leg Recirculation per EOS-1.3A, Transfer to Cold Leg Recirculation.

Refueling Water Storage Tank (RWST) level is 7% and lowering.

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

When RWST level reaches 6%, Perform EOS-1.3A, Transfer to Cold Leg Recirculation Attachment 1.H, Containment Spray Switchover Criterion.

THIS IS A TIME CRITICAL JPM Page 6 of 6 CPNPP 2016 NRC JPM S-5 (RO2002C) REV. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-6 Task # RO4215 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. 21-10.

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

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

Page 1 of 6 CPNPP 2016 NRC JPM S-6 (RO4215C) REV. 0

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

INITIALIZE to IC #39 or any at power Initial Condition and 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.

SIMULATOR 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. (labeled Procedure 1)

Page 2 of 6 CPNPP 2016 NRC JPM S-6 (RO4215C) REV. 0

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 2016 NRC JPM S-6 (RO4215C) REV. 0

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.

Simulator VERIFY malfunction ED09, Grid Frequency Fluctuation at 58.2 Hz Operator: 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 2016 NRC JPM S-6 (RO4215C) REV. 0

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 2016 NRC JPM S-6 (RO4215C) REV. 0

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 2016 NRC JPM S-6 (RO4215C) REV. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-7 Task # RO1820 K/A # 015.A2.01 3.5 / 3.9 SF-7 Title: Respond to a Power Range Channel Malfunction 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.

Power Range Instrument N-44 has failed low.

Rod control is in MANUAL.

Initiating Cue: The Unit Supervisor directs you to continue performing ABN-703, Power Range Instrument Malfunction, START at Step 2.3.3.

Task Standard: Defeated failed power range channel N44 utilizing ABN-703, Power Range Instrument Malfunction.

Ref. Materials: ABN-703, Power Range Instrumentation Malfunction. Rev. 8-8 Validation Time: 5 minutes Completion Time: ________ minutes Comments:

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

Page 1 of 5 CPNPP 2016 NRC JPM S-7 (RO1820) REV. 0

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

INITIALIZE to IC-35.

OR INITIALIZE to any at power Initial Condition and PERFORM the following:

EXECUTE malfunction NI06E, PR N-44 Channel Failure to 0%.

ENSURE rod control is in MANUAL.

SIMULATOR OPERATOR NOTE:

After each JPM, VERIFY the following:

1/1-JS-411E, N16 PWR CHAN DEFEAT (CB-05) is NOT in Loop 4 position.

1-TS-412T, Tave CHAN DEFEAT (CB-07) is NOT in Loop 4 position.

1/1-TS-411E, 1-TR-411 CHAN SELECT N16 Recorder IS in Loop 4 position.

Handout:

PROVIDE the examinee with a copy of ABN-703, Power Range Instrumentation Malfunction, appropriately marked through Step 2.3.2. (Labeled as Procedure 1)

Page 2 of 5 CPNPP 2016 NRC JPM S-7 (RO1820) REV. 0

Appendix C JPM CUE SHEET Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from ABN-703, Step 2.3.3.

Perform Step: 1 Perform the following for failed channel:

2.3.3.a At DETECTOR CURRENT COMPARATOR drawer, select ROD STOP BYPASS switch to failed channel.

Standard: SELECTED Rod Stop Bypass switch to BYPASS PRN44.

Examiner Cue: Another operator will acknowledge alarms.

Comment: SAT UNSAT Perform Step: 2 Perform the following for failed channel:

2.3.3.b At COMPARATOR AND RATE drawer, select COMPARATOR CHANNEL DEFEAT switch to failed channel.

Standard: SELECTED Comparator Channel Defeat switch to N44.

Comment: SAT UNSAT Perform Step: 3 Perform the following for failed channel:

2.3.3.c At DETECTOR CURRENT COMPARATOR drawer, select UPPER SECTION switch to failed channel.

Standard: SELECTED Upper Section switch to PRN44.

Comment: SAT UNSAT Perform Step: 4 Perform the following for failed channel:

2.3.3.d At DETECTOR CURRENT COMPARATOR drawer, select LOWER SECTION switch to failed channel.

Standard: SELECTED Lower Section switch to PRN44.

Comment: SAT UNSAT Perform Step: 5 Perform the following for failed channel:

2.3.3.e At DETECTOR CURRENT COMPARATOR drawer, select POWER MISMATCH BYPASS switch to failed channel.

Standard: SELECTED Power Mismatch Bypass switch to BYPASS PRN44.

Comment: SAT UNSAT Page 3 of 5 CPNPP 2016 NRC JPM S-7 (RO1820) REV. 0

Appendix C JPM CUE SHEET Form ES-C-1 Perform Step: 6 Perform the following for failed channel:

2.3.3.f At POWER RANGE A drawer, select RATE MODE switch momentarily to RESET for failed channel.

Standard: SELECTED Rate Mode switch momentarily to RESET for N44.

Comment: SAT UNSAT Perform Step: 7 Perform the following for failed channel:

2.3.3.g & 1st bullet Select the following switches to loop corresponding to failed channel:

1/u-JS-411E, N16 PWR CHAN DEFEAT (CB-05)

Standard: PLACED 1/1-JS-411E, N16 PWR CHAN DEFEAT in Loop 4 position.

Comment: SAT UNSAT Perform Step: 8 Perform the following for failed channel:

2.3.3.g & 2nd bullet Select the following switches to loop corresponding to failed channel:

u-TS-412T, Tave CHAN DEFEAT (CB-07)

Standard: PLACED 1-TS-412T, Tave CHAN DEFEAT in Loop 4 position.

Comment: SAT UNSAT Perform Step: 9 Ensure N16 Recorder selected to - OPERABLE CHANNEL:

2.3.4 & bullet 1/u-TS-411E, u-TR-411 CHAN SELECT Standard: SELECTED 1/1-TS-411E, 1-TR-411 CHAN SELECT N16 Recorder Loop 1, Loop 2, or Loop 3.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 CPNPP 2016 NRC JPM S-7 (RO1820) REV. 0

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

Unit 1 is at 100% power.

Power Range Instrument N-44 has failed low.

Rod control is in MANUAL.

INITIATING CUE: The Unit Supervisor directs you to continue performing ABN-703, Power Range Instrument Malfunction, START at Step 2.3.3.

Page 5 of 5 CPNPP 2016 NRC JPM S-7 (RO1820) REV. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC S-8 Task # RO4405 K/A # 067.AA2.16 3.3 / 4.0 SF-8 Title: Respond to a Fire in the Safeguards Building Examinee (Print):

Testing Method:

Simulated Performance: Classroom:

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

Time Critical:

READ TO THE EXAMINEE Provide the Initial Conditions and Initiating Cue to the Examinee. Any special conditions or instructions should be contained on this sheet.

Initial Conditions: Given the following conditions:

ABN-804A, Response to a Fire in the Safeguards Building, is in progress.

Other operators are performing ABN-804A, Attachments 5 and 6, which include isolation of Letdown flow.

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

RESPOND to a fire in the Safeguards Building per ABN-804A, Response to a Fire in the Safeguards Building, Section 5.0, Fire Affecting Safeguards Building Fire Area 1SD.

START at Step 5.3.6.

Task Standard: Utilizing ABN-804A, responded to a fire in the Safeguards Building, started the Train B Emergency Diesel Generator, transferred Charging Pump suction to the RWST, started the Train B Centrifugal Charging Pump, and secured Charging flow to the Reactor Coolant System.

Ref. Materials: ABN-804A, Respond to a Fire in the Safeguards Building. Rev. 6-2 Validation Time: 10 minutes Completion Time: ________ minutes Comments:

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

Page 1 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0

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

INITIALIZE to IC-36 Or Initialize to IC-18 and PERFORM the following:

ALARM ON for these Safeguards Fire Protection Panel annunciators:

AFP09_16 for Window 4.2 - 810 SWGR RM TRN A.

AFP09_17 for Window 5.2 - 810 SWGR RM TRN A WTR FLO.

1/1-PCV-455A, PRZR PORV in CLOSE.

1/1-PCV-456, PRZR PORV in CLOSE.

Place the following malfunctions on a conditional for CS-1DG2E in START with a 3 minute delay.

EBR112, 1ED1-1/9/BKR [BOP ARR 1, 1-CR-03]

EBR113, 1ED1-1/10/BKR [1-TC-19,22,26]

EBR115, 1ED1-1/14/BKR [1-TC-07,10]

EBR116, 1ED1-1/17/BKR [1-TC-13,16]

Handout:

PROVIDE the examinee with a copy of:

ABN-804A, Response to a Fire in the Safeguards Building.

Section 5.0, Fire Affecting Safeguards Building Fire Area 1SD appropriately marked through Step 5.3.5.

Page 2 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following is from ABN-804A, and Section 5.0, Step 5.3.6.

Examiner Cue: If an automatic or manual reactor trip occurs during the performance of the procedure inform the examinee that another operator will perform the actions of EOP-0.0A and that they are to continue with ABN-804A.

Perform Step: 1 Perform an emergency start on Trn B Diesel Generator:

5.3.6 CS-1DG2E, DG 2 EMER STOP/ START - START Standard: PERFORMED the following:

PLACED CS-1DG2E, DG 2 EMER STOP/ START switch in START (Critical).

OBSERVED V-1EG2, DG 2 VOLTS at ~6900 Volts (NOT critical).

OBSERVED F-1EG2, DG 2 FREQ at 60 Hertz (NOT critical).

Comment: SAT UNSAT Perform Step: 2 Place 1/1-APRH 1, RHRP 1 - PULL OUT

5.3.7 Standard

PERFORMED the following:

PLACED 1/1-APRH 1, RHRP 1 in PULLOUT (Critical).

OBSERVED pump lights DARK (NOT critical).

Comment: SAT UNSAT Perform Step: 3 CLOSE 1/1-8812A, RWST TO RHRP 1 SUCT VLV

5.3.8 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 Page 3 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 4 CLOSE 1/1-8100, RCP SEAL WTR RET ISOL VLV

5.3.9 Standard

PERFORMED the following:

PLACED 1/1-8100, RCP SEAL WTR RET ISOL VLV in CLOSE (Critical).

OBSERVED green CLOSE light LIT (NOT critical).

Comment: SAT UNSAT Perform Step: 5 Transfer Charging Pump suction to the RWST :

5.3.10.a IF charging pump performance indicates possible cavitation, THEN stop charging pump until below valves manually repositioned.

Standard: OBSERVED 1-PI-120A, CHRG HDR PRESS and 1-FI-121A, CHRG FLO and DETERMINED that pump does not indicate cavitation and MARKED step as N/A.

Comment: SAT UNSAT Examiner Note: Either 1/1-LCV-112D OR 1/1-LCV-112E can be opened.

Perform Step: 6 Transfer Charging Pump suction to the RWST :

5.3.10.b Ensure 1/1-LCV-112D OR 1/1-LCV-112E, RWST TO CHRG PMP SUCT VLV - OPEN.

Standard: PERFORMED ONE of the following:

PLACED 1/1-LCV-112D, RWST TO CHRG PMP SUCT VLV in OPEN (Critical).

OBSERVED red OPEN light LIT (NOT critical).

OR PLACED 1/1-LCV-112E, RWST TO CHRG PMP SUCT VLV in OPEN (Critical).

OBSERVED red OPEN light LIT (NOT critical).

Comment: SAT UNSAT Page 4 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Both 1/1-LCV-112B AND 1/1-LCV-112C must be closed.

Perform Step: 7 Transfer Charging Pump suction to the RWST :

5.3.10.c Ensure 1/1-LCV-112B AND 1/1-LCV-112C, VCT TO CHRG PMP SUCT VLV - CLOSED.

Standard: PERFORMED BOTH of the following:

PLACED 1/1-LCV-112B, VCT TO CHRG PMP SUCT VLV in CLOSE (Critical).

OBSERVED green CLOSE light LIT (NOT critical).

AND PLACED 1/1-LCV-112C, VCT TO CHRG PMP SUCT VLV in CLOSE (Critical).

OBSERVED green CLOSE light LIT (NOT critical).

Comment: SAT UNSAT Perform Step: 8 Transfer Charging Pump suction to the RWST :

5.3.10.d Verify 1-ZL-8220 AND 1-ZL-8221, CHRG PMP SUCT HI POINT VENT VLV - CLOSED.

Standard: OBSERVED 1-ZL-8220 and 1-ZL-8221, CHRG PMP SUCT HI POINT VENT VLVs green CLOSE lights LIT.

Comment: SAT UNSAT Perform Step: 9 Transfer Charging Pump suction to the RWST :

5.3.10.e Ensure 1/1-8202A AND 1/1-8202B, VENT VLV - CLOSED.

Standard: VERIFIED 1/1-8202A and 1/1-8202B, VENT VLVs in CLOSE and OBSERVED green CLOSE lights LIT.

Comment: SAT UNSAT Page 5 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 10 Ensure 1/1-APCH2, CCP 2 - RUNNING.

5.3.11 Standard: PERFORMED the following:

PLACED 1/1-APCH2, CCP 2 in START (Critical).

OBSERVED red PUMP and FAN lights LIT (NOT critical).

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 6 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0

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

ABN-804A, Response to a Fire in the Safeguards Building, is in progress.

Other operators are performing ABN-804A, Attachments 5 and 6, which include isolation of Letdown flow.

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

RESPOND to a fire in the Safeguards Building per ABN-804A, Response to a Fire in the Safeguards Building, Section 5.0, Fire Affecting Safeguards Building Fire Area 1SD.

START at Step 5.3.6.

Page 7 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC P-1 (U1) Task # AO5202 K/A # 004.A4.08 3.8 / 3.4 SF-2 Title: Perform Local Actions to Restart the Positive Displacement Pump Examinee (Print):

Testing Method:

Simulated Performance: X Classroom:

Actual Performance: Simulator:

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

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

Initial Conditions: Given the following conditions on Unit 1:

The crew is performing ABN-301, Instrument Air System Malfunction.

Restart of the Positive Displacement Charging Pump (PDP) is required to establish Charging flow.

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

RESET control air to the Unit 1 PDP Fluid Drive per ABN-301, Instrument Air System Malfunction, Step 3.3.4.n.

RESTORE the Unit 1 PDP to operation per SOP-103A, Chemical and Volume Control System, Section 5.3.1, Positive Displacement Pump Startup, Starting at Step 5.3.1.D.

Task Standard: Reset the PDP hydraulic speed changer, filled the Unit 1 PDP stuffing Box coolant tank and opened the discharge valve.

Ref. Materials: ABN-301, Instrument Air System Malfunction. Rev. 13-0 SOP-103A, Chemical and Volume Control System. Rev. 18-14 Validation Time: 15 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

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

Page 1 of 6 CPNPP 2016 NRC JPM P-1 (AO5202A) (U1) REV. 0

Appendix C JPM WORKSHEET Form ES-C-1 PLANT SETUP Handouts:

PROVIDE the examinee with a copy of:

ABN-301, Instrument Air System Malfunction, Completed through Step 3.3.4.n. (labeled Procedure 1)

SOP-103A, Chemical and Volume Control System, Sections 2.5 and 5.3.1; through Step 5.3.1.C. (labeled Procedure 2)

Page 2 of 6 CPNPP 2016 NRC JPM P-1 (AO5202A) (U1) REV. 0

Appendix xC JPM STEP PS Foorm ES-C-1

- Checck Mark Den notes Criticaal Step STTART TIME:

Examine er Note: Remind d examinee to simulate e all actionss. The followwing step iss from ABN-30 01, Section 3.0.

3 Perform Step: 1 Reset aiir to PDP hy ydraulic speeed changer b by pushing the brass button on the 3.3.4 n P/A Con nverter.

Standard d: DEPRES SSED the co ontrol air RE ESET button n located ato op the Positivve Displaceement Pump p Fluid Drive e in the PDP Room.

Examine er Cue: The 1-01 PDP Hydrraulic Speed d Changer is RESET.

Commen nt: SATT UNSAT Examine er Note: The following steps are from S SOP-103A, Section 5.3 3.1.

Examine er Note: The following steps representt the Alternate Path wh hen the Stuffing Box Coolantt Tank is ou ut of specifi cation.

Perform Step: 2 IF Stuffin ng Box Coollant Tank is low, THEN FILL per the e following stteps:

5.3.1 D Standard d: OBSERV VED Stuffing g Box Coolaant Tank sigh htglass level.

Examine er Cue: The sight glass is EMPTY.

DO NOT T provide the e second pa art of the cue e until operator demonsttrates that th he tank muust be filled.

Anotherr operator willw monitorr sight glass s level as th he tank is fiilled.

Commen nt: SATT UNSAT Page 3 of o 6 CPNPP C 2016 6 NRC JPM P-1 (AO520 02A) (U1) REV. 0

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The Fill Valve is located in the Charging Pump Remote Operator Room (822) directly north of chemical mixing tank on east wall.

The operator should turn the valve in the counter clockwise direction, and there will be flow noise, stem nut should be raised from initial position after operator turns counter clockwise.

Perform Step: 3 IF Stuffing Box Coolant Tank is low, THEN fill per the following steps:

5.3.1 D 1) Slowly crack OPEN 1CS-0119, PD PMP 1-01 STUFFING BOX COOL TK MU ISOL VLV, until desired fill rate is achieved.

Examiner Cue: The valve is found with stem nut all the way down.

Standard: Slowly turned 1CS-0119 in the counterclockwise (OPEN) direction until desired fill rate was achieved.

Examiner Cue: The valve is turning and flow noise is audible.

After the operator has demonstrated that the valve is open, report The NEO at the PDP stuffing box sight glass reports, The sight glass is half-full.

Comment: SAT UNSAT Perform Step: 4 WHEN the desired tank level has been established, THEN CLOSE 1CS-0119, 5.3.1 D 2) PD PMP 1-01 STUFFING BOX COOL TK MU ISOL VLV.

Standard: Turned valve in the clockwise (CLOSED) direction, when level REPORTED in the Stuffing Box Coolant Tank, until stem nut is down and valve will not turn.

Examiner Cue: 1CS-0119 stem nut is down and the valve will no longer turn in the clockwise direction, flow noise is no longer heard.

Comment: SAT UNSAT Page 4 of 6 CPNPP 2016 NRC JPM P-1 (AO5202A) (U1) REV. 0

Appendix C JPM STEPS Form ES-C-1 Examiner Note: The remote operator is located in the Charging Pump Remote Operator Room (822). Unit 1 covers are blue and Unit 2 covers are yellow. This valve is normally OPEN; down in the hole where the remote operator is inserted is a valve position indicator that will indicate OPEN.

Examiner Note: The following steps represent the Alternate Path when the discharge valve is closed.

Perform Step: 5 Ensure 1-8388-RO, PD CHRG PMP 1-01 DISCH VLV RMT OPER, is OPEN.

5.3.1 E Examiner Cue: Once the operator has lifted the cover, report that the indicator indicates CLOSE.

Standard: In the Charging Pump Remote Operator Room, PERFORMED the following:

REMOVED the blue cover for 1-8388-RO, PD CHRG PMP 1-01 DISCH VLV RMT OPER.

OBSERVED valve position indicator and DETERMINED valve CLOSE.

LOCATED a Remote Operator hand tool for 1-8388-RO.

PLACED hand tool on 1-8388-RO and TURNED in OPEN (counter clockwise) direction.

Examiner Cue: If the operator turns the valve (counter clockwise),

Report the valve has rotated and will no longer move, the indicator indicates OPEN.

Comment: SAT UNSAT Examiner Note: These valves are operated from the control room.

Perform Step: 6 OPEN the following valves:

5.3.1 F 1/1-8202A, VENT VLV (MCB) 1/1-8202B, VENT VLV (MCB)

Standard: CONTACTED the Control Room to ENSURE 1/1-8202A and 1/1-8202B, VENT VLVs are OPEN.

Terminating Cue: The vent valves are OPEN. This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP 2016 NRC JPM P-1 (AO5202A) (U1) REV. 0

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions on Unit 1:

The crew is performing ABN-301, Instrument Air System Malfunction.

Restart of the Positive Displacement Charging Pump (PDP) is required to establish Charging flow.

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

RESET control air to the Unit 1 PDP Fluid Drive per ABN-301, Instrument Air System Malfunction, Step 3.3.4.n.

RESTORE the Unit 1 PDP to operation per SOP-103A, Chemical and Volume Control System, Section 5.3.1, Positive Displacement Pump Startup, Starting at Step 5.3.1.D.

Page 6 of 6 CPNPP 2016 NRC JPM P-1 (AO5202A) (U1) REV. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC P-2 (U1) Task # RO4217 K/A # 055.EA1.04 3.5 / 3.9 SF-6 Title: Perform Attachment 2A DC Load Shedding Examinee (Print):

Testing Method:

Simulated Performance: X Classroom:

Actual Performance: Simulator:

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

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

Initial Conditions: Given the following conditions:

Unit 1 is in MODE 3 following a Loss of All AC Power.

Unit 2 is in MODE 3 with 2EA1 energized and 2EA2 de-energized.

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

Perform Unit 1 Initial DC Load Shed in accordance with ECA-0.0A, Loss of All AC Power, Attachment 2A, Initial DC Load Shed.

Task Standard: Completed Section 2 of Attachment 2A, Initial DC Load Shed in accordance with ECA-0.0A, Loss of All AC Power.

Ref. Materials: ECA-0.0A, Loss of All AC Power, Attachment 2A, Rev. 9-0 Validation Time: 15 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

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

Page 1 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0

Appendix C JPM WORKSHEET Form ES-C-1 PLANT SETUP Handout:

PROVIDE the examinee with a copy of:

ECA-0.0A, Loss of All AC Power.

Attachment 2A, Initial DC Load Shed.

EXAMINER NOTE:

Simulate/Discuss actions to obtain and use Key #150.

Page 2 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0

Appendix xC JPM STEP PS Fo orm ES-C-1

- Chec ck Mark Deenotes Crittical Step STTART TIME E:

Examiner Note: The following ste eps are fro m ECA-0.0 0A, Attachmment 2A Perform m Step: 1 Determine appropriate sectio on of Attachhment 2A to o perform.

Note Standarrd: Determined that Section 2 sh hould be pe erformed.

Comme ent: SAAT UNSSAT Perform m Step: 2 IF 2EA1 1 is energiz zed and 2EA A2 is de-en nergized, THEN perforrm the 2a followin ng:

ECB 79 92, U1 UPS S Corridor SSouth Wall Ensure transfer sw witch on CPPX-ECDPED D-01S, 125 5 VDC DISTRIBUTION PA ANEL XED D1-1 AUTO TRANSFE ER SWITCH H XED1-1S in Unit 2 (LOAD CONNECTE ED TO UNIT T 2 LIGHT lit) (Key #150 from Key Loc cker require ed).

Examiner Cue: XED1-1 1S is in thee Unit 1 position. LOA AD CONNE ECTED TO O UNIT 1 LIGHT is LIT.

Standarrd: PLACED XED1-1S S in Unit 2.

Examiner Cue: XED1-1 1S is in thee Unit 2 position. LOA AD CONNE ECTED TO O UNIT 2 LIGHT is LIT.

Comme ent: SAAT UNSSAT Page 3 of o 11 CPNPP 2016 NRC JPM P P-2 (RO4217H) (U1) Rev. 0

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Perform Steps 3-25 are bulleted and may be performed in any order.

Perform Step: 3 Place the following breakers OFF:

2b 1st bullet ECB 792, U1 UPS Corridor South Wall XED2-1/1/BKR, CABLE TERMINATION RACK 1-TC-02 SUPPLY BREAKER Standard: PLACED XED2-1/1/BKR, Breaker in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 4 Place the following breakers OFF:

2b 2nd bullet ECB 792, U1 UPS Corridor South Wall XED2-1/3/BKR, CABLE TERMINATION RACK 1-TC-08 SUPPLY BREAKER Standard: PLACED XED2-1/3/BKR Breaker in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 5 Place the following breakers OFF:

2b 3rd bullet ECB 792, U1 UPS Corridor South Wall XED2-1/7/BKR, HVAC CONTROL PANEL X-CV-01 TRAIN B SUPPLY BREAKER Standard: PLACED XED2-1/7/BKR Breaker in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 6 Place the following breakers OFF:

2b 4th bullet ECB 792, U1 UPS Corridor South Wall XED2-1/8/BKR , CABLE TERMINATION RACK X-TC-04 SUPPLY BREAKER Standard: PLACED XED2-1/8/BKR Breaker in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Page 4 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 7 Place the following breakers OFF:

2b 5th bullet ECB 807, U1 CSR North Wall 1ED1-1/6/BKR, TRAIN A SOLID STATE PROTECTION SYSTEM CABINET 1-SP-01 SUPPLY BREAKER Standard: PLACED 1ED1-1/6/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 8 Place the following breakers OFF:

2b 6th bullet ECB 807, U1 CSR North Wall 1ED1-1/7/BKR, TRAIN A HVAC CONTROL PANEL X-CV-01 SUPPLY BREAKER Standard: PLACED 1ED1-1/7/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 9 Place the following breakers OFF:

2b 7th bullet ECB 807, U1 CSR North Wall Northeast Corner 1ED2-1/6/BKR, TRAIN B SOLID STATE PROTECTION SYSTEM CABINET 1-SP-01 SUPPLY BREAKER Standard: PLACED 1ED2-1/6/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 10 Place the following breakers OFF:

2b 8th bullet ECB 807, U1 CSR North Wall Northeast Corner 1ED2-1/7/BKR, TRAIN B HVAC CONTROL PANEL X-CV-01 SUPPLY BREAKER Standard: PLACED 1ED2-1/7/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Page 5 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 11 Place the following breakers OFF:

2b 9th bullet ECB 807, U1 CSR East Wall 1PC4/6/BKR, SAFEGUARD TEST CABINET (TRAIN B) 1-LTC-01 SUPPLY BREAKER Standard: PLACED 1PC4/6/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 12 Place the following breakers OFF:

2b 10th bullet ECB 807, U1 CSR East Wall 1PC4/7/BKR, SSPS INPUT/LOGIC CABINET 1-SP-01A TRAIN A CHANNEL IV SUPPLY BREAKER Standard: PLACED 1PC4/7/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 13 Place the following breakers OFF:

2b 11th bullet ECB 807, U1 CSR East Wall 1PC4/8/BKR, SSPS INPUT/LOGIC CABINET 1-SP-01B TRAIN B CHANNEL IV SUPPLY BREAKER Standard: PLACED 1PC4/8/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 14 Place the following breakers OFF:

2b 12th bullet ECB 807, U1 CSR East Wall 1PC4/10/BKR, NSSS AUXILIARY RELAY RACK 2 1-LAR-01 SUPPLY BREAKER Standard: PLACED 1PC4/10/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Page 6 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 15 Place the following breakers OFF:

2b 13th bullet ECB 807, U1 CSR East Wall 1PC4/11/BKR, 118 VAC INSTRUMENT FUSE PANEL 1PC4-1 (FU2) SUPPLY BREAKER Examiner Cue: The breaker is OFF.

Standard: PLACED 1PC4/11/BKR in OFF.

Comment: SAT UNSAT Perform Step: 16 Place the following breakers OFF:

2b 14th bullet ECB 807, U1 CSR East Wall 1PC4/13/BKR, UPGRADE PROTECTION CABINET (CH IV) 1-50D SUPPLY BREAKER Standard: PLACED 1PC4/13/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 17 Place the following breakers OFF:

2b 15th bullet ECB 807, U1 CSR East Wall 1PC4/14/BKR, PROTECTIVE RELAY RACK CHANNEL IV 1-CR-11 SUPPLY BREAKER Standard: PLACED 1PC4/14/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 18 Place the following breakers OFF:

2b 16th bullet ECB 807, U1 CSR East Wall 1PC4/18/BKR, ERF TRANSDUCER PANEL 1-LV-17 TRANSDUCER V-XD/1PC4 INPUT SUPPLY BREAKER Standard: PLACED 1PC4/18/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Page 7 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 19 Place the following breakers OFF:

2b 17th bullet ECB 807, U1 CSR East Wall 1PC3/7/BKR, SSPS INPUT/LOGIC CABINET 1-SP-01A TRAIN A CHANNEL III SUPPLY BREAKER Standard: PLACED 1PC3/7/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 20 Place the following breakers OFF:

2b 18th bullet ECB 807, U1 CSR East Wall 1PC3/8/BKR, SSPS INPUT/LOGIC CABINET 1-SP-01B TRAIN B CHANNEL III SUPPLY BREAKER Standard: PLACED 1PC3/8/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 21 Place the following breakers OFF:

2b 19th bullet ECB 807, U1 CSR East Wall 1PC3/9/BKR, 118 VAC INSTRUMENT FUSE PANEL 1PC3-1 (FU4) SUPPLY BREAKER Standard: PLACED 1PC3/9/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 22 Place the following breakers OFF:

2b 20th bullet ECB 807, U1 CSR East Wall 1PC3/10/BKR, PROTECTIVE RELAY RACK CHANNEL III 1-CR-11 SUPPLY BREAKER Standard: PLACED 1PC3/10/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Page 8 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0

Appendix C JPM STEPS Form ES-C-1 Perform Step: 23 Place the following breakers OFF:

2b 21st bullet ECB 807, U1 CSR East Wall 1PC3/11/BKR, 118 VAC INSTRUMENT FUSE PANEL 1PC3-1 (FU2) SUPPLY BREAKER Standard: PLACED 1PC3/14/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 24 Place the following breakers OFF:

2b 22nd bullet ECB 807, U1 CSR East Wall 1PC3/14/BKR, UPGRADE PROTECTION CABINET (CH III) 1-50C SUPPLY BREAKER Standard: PLACED 1PC3/14/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 25 Place the following breakers OFF:

2b 23rd bullet ECB 807, U1 CSR East Wall 1PC3/18/BKR, ERF TRANSDUCER PANEL 1-LV-16 TRANSDUCER V-XD/1PC3 INPUT SUPPLY BREAKER Standard: PLACED 1PC3/18/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 26 ECB 807, U1 CSR South Wall 2c IF XEC1-1/00/BKR-1, 1EC5 TO 118 VAC INSTRUMENT DISTR PANEL XEC1-1 PREFERRED FEEDER BREAKER is ON, THEN perform the following to transfer XEC1-1 supply to Unit 2.

Examiner Cue: XEC1-1/00/BKR-1 is OFF.

Standard: Determined XEC1-1/00/BKR-1 is OFF.

Comment: SAT UNSAT Page 9 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0

Appendix C JPM STEPS Form ES-C-1 Examiner Note: Perform Steps 27 and 28 are bulleted and may be performed in any order.

Perform Step: 27 Place the following breakers OFF:

2d 1st bullet ECB 807, U1 CSR on South Side of Column, Near West Wall, South of Stairs 1EC6/5/BKR, CNTMT RECIRCULATING SUMP 1-02 LEVEL XMTR 1-LT-4781 SUPPLY BREAKER Standard: PLACED 1EC6/5/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 28 Place the following breakers OFF:

nd 2d 2 bullet ECB 807, U1 CSR West Wall, South of Stairs to Control Room 1EC5/5/BKR, CNTMT RECIRCULATING SUMP 1-01 LEVEL XMTR 1-LT-4779 SUPPLY BREAKER Standard: PLACED 1EC5/5/BKR in OFF.

Examiner Cue: The breaker is OFF.

Comment: SAT UNSAT Perform Step: 29 Notify Unit Supervisor attachment instructions complete AND DC load 2e shed status. Perform Attachment 2.B when informed by Unit Supervisor that Containment Isolation Phase A and Containment Ventilation Isolation are complete.

Standard: Notified Unit Supervisor that Attachment 2.A Section 2 is complete.

Examiner Cue: The JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 10 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions:

Unit 1 is in MODE 3 following a Loss of All AC Power.

Unit 2 is in MODE 3 with 2EA1 energized and 2EA2 de-energized.

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

Perform Unit 1 Initial DC Load Shed in accordance with ECA-0.0A, Loss of All AC Power, Attachment 2A, Initial DC Load Shed.

Page 11 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC P-3 (U2) Task #RO5115 K/A #068. AA1.11 3.9 / 4.1 SF-8 Title: Emergency Borate from the Remote Shutdown Panel Examinee (Print):

Testing Method:

Simulated Performance: X Classroom:

Actual Performance: Simulator:

Alternate Path: Plant: X Time Critical:

CUE THE EXAMINEE Provide the Initial Conditions and Initiating Cue to the Examinee. Any special conditions or instructions should be contained on this sheet.

Initial Conditions: Given the following conditions with Unit 2 at 100% power:

The Control Room was evacuated due to a Security threat.

Actions of ABN-905B, Loss of Control Room Habitability are in progress and have progressed to the point where Plant Cooldown is desired.

A Reactor Operator is standing by at the Shutdown Transfer Panel.

All security measures have been satisfied and operation in the area of the Remote Shutdown Panel is allowed Initiating Cue: The Unit Supervisor DIRECTS you to commence emergency boration to the Unit 2 RCS using Attachment 12 of ABN-905B.

Task Standard: Established emergency boration flow from the Remote Shutdown Panel Ref. Materials: ABN-905B, Loss of Control Room Habitability, Rev. 4, PCN-11.

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

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

Page 1 of 5 CPNPP 2016 NRC JPM P-3 (RO5115B) (U2) REV. 0

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

PROVIDE the examinee with a copy of:

ABN-905B, Loss of Control Room Habitability, Attachment 12, Boration. (labeled Procedure 1)

All operations for this JPM will be in Unit 2 Safeguards Building, 832 elevation on the Remote Shutdown Panel, an ABA1 key is required to access the panel.

Page 2 of 5 CPNPP 2016 NRC JPM P-3 (RO5115B) (U2) REV. 0

Appendix xC JPM STEP PS Fo orm ES-C-1

- Checck Mark Dennotes Critica al Step ST TART TIME:

Shutdow wn Transfer Panel (ST TP) switches s will be operated by th he Extra Examine er CUE: Reactorr Operator.

Performm Steps 1-3 are bulleted d and may be performed in any order.

Perform Step: 1 Transferr the followin ng from CR tto HSP:

Step 1. 1st Bullet 43/2 - APBA1L, BA A XFER PM P 1 CTRL X XFER (STP)

Standard d: CONTACTED Extra a Reactor Opperator at ST TP to have sswitch transfferred.

REPORT 43/2 - APB BA1L, BA X XFER PMP 1 CTRL XFE ER switch is s broke and d

Examine er Cue:

cannot be transferred at this ttime.

Commen nt: SATT UNSA AT When pump p is tran nsferred greeen light onn 1/2-APBA2 2L, BA XFER PMP 2 Examine er Note:

(RSP) will w be on.

Perform Step: 2 Transferr the followin ng from CR tto HSP:

Step 1. 2nd 2 Bullet 43/2 - APBA2L, BA A XFER PM P 2 CTRL X XFER (RSP)

Standard d: TURNED D the switchh to HSP INDICAT TE switch is s in the HSP P position aand pump g green light iis ON Examine er Cue:

Commen nt: SATT UNSA AT When valve is transferred gre een light on 1/2-8104L, EMER BOR RATE VLV Examine er Note:

(RSP) will w be on.

Perform Step: 3 Transferr the followin ng from CR tto HSP:

Step 1. 3rd 3 Bullet 43/2 - 8104L, EME ER BORATE E VLV CTRL L XFER (RS SP)

Standard d: TURNED D the switchh to HSP Examine er Cue: INDICAT TE switch is s in the HSP P position aand valve ggreen light is s ON Commen nt: SATT UNSA AT Page 3 of o 5 CPNPP C 2016 NRC JPM M P-3 (RO5115B) (U2) REV. 0

Appendix C JPM STEPS Form ES-C-1 Start one Boric Acid Transfer Pump:

Perform Step: 4 1/2 - APBA1L, BA XFER PMP 1 (RSP)

Step 2.

1/2 - APBA2L, BA XFER PMP 2 (RSP)

Standard: TURNED 1/2-APBA2L Handswitch momentarily to START.

INDICATE red light ON, green light OFF for pump started Examiner Cue:

Comment: SAT UNSAT Perform Step: 5 Open 1/2-8104L, EMER BORATE VLV (RSP).

Step 3.

Standard: TURNED the switch to OPEN Examiner Cue: INDICATE red light ON, green light OFF Comment: SAT UNSAT Perform Step: 6 Monitor 2-FI-183B, EMER BORATE FLO (RSP).

Step 6.

Standard: MONITORED flow on 2-FI-183B.

Examiner Cue: INDICATE flow is 95 gpm for one boric acid pump Comment: SAT UNSAT Perform Step: 7 Notify the Unit 2 Unit Supervisor that emergency boration is in progress from the Remote Shutdown Panel.

Standard: NOTIFIED the Unit 2 Unit Supervisor that emergency boration is in progress from the Remote Shutdown Panel.

Examiner Cue: REPORT the Unit Supervisor acknowledges emergency boration in progress from the Remote Shutdown Panel.

Comment: SAT UNSAT Terminating Cue: This JPM is complete.

STOP TIME:

Page 4 of 5 CPNPP 2016 NRC JPM P-3 (RO5115B) (U2) REV. 0

Appendix C JPM CUE SHEET Form ES-C-1 Initial Conditions: Given the following conditions with Unit 2 at 100% power:

The Control Room was evacuated due to a Security threat.

Actions of ABN-905B, Loss of Control Room Habitability are in progress and have progressed to the point where Plant Cooldown is desired.

A Reactor Operator is standing by at the Shutdown Transfer Panel.

All security measures have been satisfied and operation in the area of the Remote Shutdown Panel is allowed Initiating Cue: The Unit Supervisor DIRECTS you to commence emergency boration to the Unit 2 RCS using Attachment 12 of ABN-905B.

Page 5 of 5 CPNPP 2016 NRC JPM P-3 (RO5115B) (U2) REV. 0

Appendix D Scenario Outline Form ES-D-1 Facility: CPNPP 1 & 2 Scenario No.: 1 Op Test No.: July 2016 NRC Examiners: Operators:

Initial Conditions: 100% power MOL - RCS Boron is 924 ppm.

Turnover: Maintain steady-state power conditions. Safety Injection Pump 1-01 is out of service for bearing replacement.

Critical Tasks: CT-1 Manually Start Safety Injection Pump 1-02 Prior to completing Attachment 2 of EOP-0.0A, Reactor Trip or Safety Injection.

CT-2 Manually align Train A and/or Train B Containment Isolation Phase B due to Failure to Automatically and Manually Actuate Prior to Exiting FRZ-0.1A, Response to High Containment Pressure.

Event No. Malf. No. Event Type* Event Description CC02A C (BOP, SRO) Train A Component Cooling Water Pump 1-01 Trip 1

CC03A TS (SRO) Train B Component Cooling Water Pump 1-02 Auto Start Failure 2 RX15B C (RO, SRO) Pressurizer Spray Valve PCV-455C Fails Open C (RO, BOP, SRO) 3 ED07B Loss of Inverter (IV1PC2)

TS (SRO)

R (RO) 4 RC03B High Vibrations on RCP 1-02 requiring Rapid Downpower N (BOP, SRO) 5 RC19B M (RO, BOP, SRO) Reactor Coolant Leak on Loop 2 Cold Leg Safety Injection Pump (1-02) Auto Start Failure on Safety Injection 6 SI04D C (BOP, SRO)

Signal 7 RC09B2 M (RO, BOP, SRO) Large Break Loss of Coolant Accident on Loop 2 Cold Leg RP10A Train A and B Containment Isolation Phase B Automatic and 8 RP10B C (BOP, SRO)

Manual Actuation Failure RP19C HS-4755 9 C (BOP, SRO) Train B Chemical Addition Tank Discharge Valve Fail to Auto Open Override

(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) 2 Major transients (1-2) 2 EOPs entered/requiring substantive actions (1-2) 1 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3)

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Scenario Event Description NRC Scenario 1 SCENARIO

SUMMARY

NRC 1 Event 1 (Key 1)

The crew will assume the watch at 100% power with no scheduled activities per IPO-003A, Power Operations.

Safety Injection Pump 1-01 is Out of Service for bearing replacement. The first event is a trip of the Train A Component Cooling Water (CCW) Pump and auto start failure of the Train B CCW Pump. The crew will enter ABN-502, Component Cooling Water System Malfunction, Section 2.0, and transfer CCW flow to Train B. The SRO will refer to Technical Specification LCO 3.7.7, Component Cooling Water System; Condition A, One CCW train inoperable. The CCW train must be restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Event 2 (Key 2)

The next event is the Loop 4 Pressurizer Spray Valve, 1-PCV-455C, failing open due to a failure of controller 1-PK-455C to control in automatic. The valve will drift open to 50% over a 2 minute period. The crew will enter ABN-705, Section 3.0, Pressurizer Spray Valve Failure, and take manual control of 1-PCV-455C controller, 1-PK-455C, and close the valve.

Event 3 (Key 3)

The next event is a loss of Inverter IV1PC2. Actions are per ABN-603, Loss of Protection or Instrument Bus, Section 2.0, and include placing Rod Control in MANUAL, controlling Steam Generator (SG) level and RCS pressure and adjusting Charging flow due to a loss of Letdown. The SRO will refer to Technical Specification LCO 3.8.7, Inverters - Operating; Condition A, One required inverter inoperable. Technical Specification LCO 3.8.9, Distribution Systems - Operating; Condition B, One AC vital bus subsystem inoperable, will also apply. Technical Specification LCO 3.8.9.B will be exited when power is restored to the AC vital bus subsystem.

Event 4 (Key 4)

The next event is applicable during the time the bus is deenergized, high shaft vibration will occur on Reactor Coolant Pump 1-02. RCP 1-02 shaft vibrations will be at 15.3 mils and stable, requiring the SRO to consult with Plant Staff. The Shift Manager will inform the SRO to perform a rapid downpower to have the Unit off-line within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Event 5 (Key 5)

During the downpower, a Reactor Coolant Leak inside Containment will commence. Once it is determined that Pressurizer level cannot be maintained, the Reactor will be manually tripped and Safety Injection manually initiated. The crew will enter EOP-0.0A, Reactor Trip or Safety Injection, and then transition to EOP-1.0A, Loss of Reactor or Secondary Coolant.

Event 6 - CT-1 (Auto)

The scenario is complicated by a failure of Safety Injection Pump 1-02 to automatically start. This will require manual action by the crew during performance of Attachment 2 of EOP-0.0A, Reactor Trip or Safety Injection. The crew will then perform CT-1, Manually Start Safety Injection Pump 1-02 Prior to completing Attachment 2 of EOP-0.0A, Reactor Trip or Safety Injection.

Event 7 (Key 7)

When EOP-1.0A is entered, a Large Break Loss of Coolant Accident will occur. The Unit Supervisor should recognize that entry into FRZ-0.1A, Response to High Containment Pressure, is required due to a Critical Safety Function Status Tree ORANGE path inside Containment.

Event 8 - CT-2 (Auto)

During performance of FRZ-0.1A, the crew will identify that Containment Isolation Phase B has failed to automatically actuate on both trains. This will require manual actuation; however, the Containment Isolation Phase B Manual Actuation Switches will fail to actuate Phase B. The crew will then perform CT-2, Manually align Train A and/or Train B Containment Isolation Phase B due to Failure to Automatically and Manually Actuate Prior to Exiting FRZ-0.1A, Response to High Containment Pressure.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Scenario Event Description NRC Scenario 1 Event 9 (Auto)

Also, during performance of FRZ-0.1A, the Train B Chemical Addition Tank Discharge Valve will fail to automatically open requiring manual action. When the actions of FRZ-0.1A are complete, a transition to FRP-0.1A, Response to Imminent Pressurized Thermal Shock Condition, is required. FRP-0.1A will be exited at Step 1 RNO when it is determined that Reactor Coolant System pressure is less than 425 psig and Residual Heat Removal System flow is greater than 750 GPM. The crew will return to EOP-1.0A, Loss of Reactor or Secondary Coolant, as this is the current procedure and step in effect.

Termination Criteria This scenario is terminated when the conditions are reached for a Transfer to Cold Leg Recirculation in accordance with EOS-1.3A.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Scenario Event Description NRC Scenario 1 Risk Significance Determination Risk Significance Event Guidance Failure of risk important systems Event 1 - Loss of Component STI-214.01 TCA-1.6 - Stop RCPs prior to Reactor Trip Cooling Water within 10 minutes(1) of a loss of CCW Non-Safeguards Loop flow to prevent RCP Bearing Damage/Failure. (FSAR 7.1.2.5, 7.3.2.3, 9.2.2.3, 15.2.8.2, II.E.1.1)

FSAR Table 7.6 Bounding event Event 3 - Loss of Protection is excessive feedwater flow. Hi-Hi System Inverter SG level closes FW control and isolation valves, trips FW turbine and main turbine.

Risk significant core damage Events 5 and 7 - Reactor STI-214.01 TCA 2.2 - Complete sequence Coolant Leak then LBLOCA EOP-0.0A to the point of transition to EOP-1.0A within 11.9 minutes(1) prior to Low-Low RWST level to verify immediate and automatic actions for an SI event. (FSAR 6.3.2.8, II.B.2.2.2, DBD-ME-232, DBD-ME-261, WOG E-0 Background)

Risk significant operator actions ODA-102 Restore Pressurizer Pressure 1) The operator may place a Control controller in the manual mode of operation when continued automatic control is inappropriate.

2) The Unit RO and/or US shall Start Train B Safety Injection place the Reactor in a safe Pump condition when the safety of the Reactor is in jeopardy or when operating parameters exceed any Reactor Protection System or Safeguards System setpoint without automatic protection functions occurring.

FSAR 6.2.4.1.1 - Containment Manually Align Phase B isolation is mandatory in the event Containment Isolation of a LOCA. The CIS isolates the Containment to prevent or limit the escape of fission products that may result from postulated accidents.

Initiate Containment Spray Technical Specification 3.6.7 Basis -

Additive Flow The Spray Additive System is essential to the removal of airborne iodine within containment following a DBA.

(1) Crew manning for Initial License Examination less than Timed Operator Action validation constraints CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Scenario Event Description NRC Scenario 1 Critical Task Determination Measurable Safety Performance Critical Task Cueing Performance Significance Feedback Indicators CT Manually Recognize a failure Procedurally driven from The operator will Indications of pump Start Safety or an incorrect EOP-0.0A, Attachment 2 start SI Pump 1-02 start including light, Injection Pump 1-02 automatic to provide makeup using the flow and discharge Prior to completing actuation of an inventory to the RCS handswitch on pressure on CB-02. of ESF system or during accident CB-02.

EOP-0.0A, Reactor component to conditions.

Trip or Safety preclude Injection. degradation of any barrier to fission product release.

FSAR 6.2.4.1.1 CT Manually Recognize a failure Procedural direction at The operator will Valve position align Train A and/or or an incorrect FRZ-0.1A Step 4 to attempt to indication for each Train B automatic determine if Containment manually actuate Phase B valve Containment actuation of an Spray is required. CS/Phase B using indicated by an Isolation Phase B ESF system or 1-ALB-2A, Window 1.8, BOTH Orange light LIT on due to Failure to component to CS ACT is LIT, handswitches MLBs 4A3 and 4B3 Automatically and preclude Containment pressure is (simultaneously) for Phase B.

Manually Actuate degradation of any >18 psig and 1-ALB-2A, at CB-07 or CB-Prior to Exiting barrier to fission Window 4.11 is DARK 02. The operator FRZ-0.1A, product release. indicating Phase B has will then manually Response to High FSAR 6.2.4.1.1 NOT actuated. Also, align Phase B Containment Orange lights will be Isolation using Pressure. DARK on valve position Attachment 5 of indication for each Phase FRZ-0.1A.

B valve at MLBs 4A3 and 4B3.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Scenario Event Description NRC Scenario 1 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP Initialize to IC-18 and 2016 NRC Scenario 1.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER SETUP SIR01 Safety Injection Pump 1-01 Out of Service RACKOUT K0 1 CC03A Train B CCW Pump 1-02 Start Failure FAIL K0 6 SI04D Safety Injection Pump 1-02 Auto Start Failure FAIL K0 8 RP10A Train A Containment Isolation Phase B Failure FAIL K0 8 RP10B Train B Containment Isolation Phase B Failure FAIL K0 8 RP19C Manual Phase B Containment Isolation Failure FAIL K0 9 Override 1-HS-4755 CHEM ADD TK DISCH VLV CLOSED K0 1 CC02A Train A CCW Pump 1-01 Failure TRIP K1 1 CC03A Train B CCW Pump 1-02 Start Failure FAIL K0 K2 2 RX15B Loop 4 Spray Valve (PCV-455C) Fails Open 50%

(120 sec. ramp)

PK-455C Green Light Off 2 Override OFF K2 IOR LORXPK455C_4 PCV-455C Closes when PK-455C put in Manual 2 Override

{DIRXPK455C_2.Value=1} DMF RX15B PCV-455C Green Lower Light LIT / Delete 2 Override ON K0

{DIRXPK455C_2.Value=1} DOR LORXPK455C_4 3 ED07B Loss of Inverter (IV1PC2) OFF K3 3 EDR02 Inverter (IV1PC2) Alternate Power Supply ALT K11 4 RC03B RCP 1-02 High Vibration Rapid Shutdown 15.3 mils K4 K5 5 RC19B Reactor Coolant Leak Loop 2 Cold Leg 600 GPM (600 sec. ramp) 6 SI04D Safety Injection Pump 1-02 Auto Start Failure FAIL K0 7 RC09B2 LOCA on Transition to EOP-1.0A - K7 8 RP10A Train A Containment Isolation Phase B Failure FAIL K0 8 RP10B Train B Containment Isolation Phase B Failure FAIL K0 8 RP19C Manual Phase B Containment Isolation Failure FAIL K0 1-HS-4755 CHEM ADD TK DISCH VLV 9 Override CLOSED K0 IOR DICSHS4755 f:0 HS-4755 Opens with Handswitch 9

{DICSHS4755.Value=2} DOR DICSHS4755 CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Scenario Event Description NRC Scenario 1 Simulator Operator: INITIALIZE to IC-18 and 2016 NRC Scenario 1.

ENSURE all Simulator Annunciator Alarms are ACTIVE.

ENSURE all Control Board Operator Aid Tags are removed.

ENSURE Operator Aid Tags reflect current boron conditions (924 ppm).

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 ENSURE Control Rods are in AUTO with Bank D at 215 steps.

ENSURE RED Danger Tag on SIP 1-01 and place in PULL-OUT.

ENSURE GEM Box PLACED on 1/1-APSI2 for SIP 1-02.

ENSURE RCP Vibration Monitoring Panel is ON and AWAKE.

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 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 1 Page 8 of 46 Event

Description:

Train A Component Cooling Water (CCW) Pump Trip / Train B CCW Pump Start Failure Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 1 (Key 1).

- CC02A, Train A CCW Pump (1-01) trip.

- CC03A, Train B CCW Pump (1-02) start failure.

Indications Available:

3B-2.3 - CCWP 1 / 2 OVRLOAD TRIP 3B-3.3 - CCW TRN B SFGD LOOP PRESS LO Multiple CCW low flow alarms BOP RESPOND to Annunciator Alarm Procedures.

RECOGNIZE Train A CCW Pump trip with failure of Train B CCW Pump to BOP start.

DIRECT implementation of ABN-502, Component Cooling Water System US Malfunctions, Section 2.0.

BOP VERIFY Train B CCW Pump - RUNNING. [Step 2.3.1]

RO Manually START Train B CCW Pump 1-02. [Step 2.3.1 RNO]

Simulator Operator: When asked about status of CCW Pump, REPORT that motor casing is hot. When asked about status of CCW Pump breaker, REPORT that the 50/51 overcurrent relays on Phases A & C are tripped.

BOP VERIFY Train B Station Service Water Pump - RUNNING. [Step 2.3.2]

RO/BOP VERIFY Train B Safety Chiller Recirc Pump 1 RUNNING. [Step 2.3.3]

VERIFY CCW Heat Exchanger outlet flow - LESS THAN 17,500 GPM PER BOP HEAT EXCHANGER. [Step 2.3.4]

1-FI-4536A, CCW HX 1 OUT FLO 1-FI-4537A, CCW HX 2 OUT FLO VERIFY required Train B equipment for existing plant conditions - IN BOP OPERATION. [Step 2.3.5]

Control Room Air Conditioning Units CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 1 Page 9 of 46 Event

Description:

Train A Component Cooling Water (CCW) Pump Trip / Train B CCW Pump Start Failure Time Position Applicants Actions or Behavior Containment Spray System UPS HVAC Unit Excess Letdown RHR System Examiner Note: Common equipment may be turned over to Unit 2.

BOP STOP Train A equipment - AS NECESSARY. [Step 2.3.6]

Control Room Air Conditioning Units [Step 2.3.6]

Containment Spray System [Step 2.3.6]

UPS HVAC Unit [Step 2.3.6]

RHR System [Step 2.3.6]

Safety Chiller Recirculation Pump [Step 2.3.6]

VERIFY CCW Heat Exchanger outlet temperature did NOT exceed 122ºF BOP with pump running. [Step 2.3.7]

US INITIATE a Work Request per STA-606. [Step 2.3.8]

US EVALUATE Technical Specifications. [Step 2.3.9]

LCO 3.7.7.A, Component Cooling Water System.

CONDITION A - One CCW train inoperable.

ACTION A.1 - Restore CCW train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

US REFER to EPP-201. [Step 2.3.10]

When the Technical Specification actions are addressed, or at Lead Examiners discretion, PROCEED to Event 2.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 2 Page 10 of 46 Event

Description:

Pressurizer Spray Valve (PCV-455C) Fails Open Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 2 (Key 2).

- RX15B, Pressurizer Spray Valve (PCV-455C) Fails Open.

Indications Available:

1-ALB-5C, Window 3.3, PRZR PRESS LO BACKUP HTS ON RCS Pressure Lowering 1-PK-455C, Pressurizer Spray Control Loop 4 indicates 0 demand.

1-ZL-455C Red Open light lit, Green closed light lit indicating valve in mid position.

RO RESPOND to Annunciator Alarm Procedures.

RECOGNIZE PZR pressure lowering and DETERMINE 1-PCV-455C, RO Pressurizer Spray Valve malfunction.

DIRECT implementation of ABN-705, Pressurizer Pressure Malfunction, US Section 3.0.

RO CLOSE Pressurizer Spray Valve. [Step 3.3.1]

PLACE 1-PK-455C, RC LOOP 4 PRZR SPR VLV CTRL in MANUAL and CLOSE Spray Valve. [Step 3.3.1]

RO CHECK Pressurizer Pressure - STABLE OR INCREASING. [Step 3.3.2]

RO VERIFY Pressurizer Pressure - TRENDING TO 2235 PSIG. [Step 3.3.3]

Examiner Note: Technical Specification LCO 3.4.1 will ONLY be addressed if Pressurizer pressure drops below 2220 psig. Lowest Pressurizer Pressure:_________psig REFER to Technical Specifications listed in Section 4.1, this procedure.

US

[Step 3.3.4]

LCO 3.4.1.A, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits.

CONDITION A - One or more RCS DNB parameters not within limits.

ACTION A.1 - Restore RCS DNB parameter(s) to within limit in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

RO INITIATE a Condition Report per STA-421, as applicable. [Step 3.3.5]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 2 Page 11 of 46 Event

Description:

Pressurizer Spray Valve (PCV-455C) Fails Open Time Position Applicants Actions or Behavior When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 3.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 3 Page 12 of 46 Event

Description:

Loss of Protection Bus 1PC2 Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 3 (Key 3).

- ED07B, Loss of Protection Bus IV1PC2.

Indications Available:

10B-2.16 - 118V CHAN II INV TRBL Channel 2 Windows on TSLB 1 through 7 and 9 Numerous Loss of Protection Bus 1PC2 Alarms RO/BOP RESPOND to Annunciator Alarm Procedures.

RO/BOP RECOGNIZE loss of Protection Bus 1PC2.

Simulator Operator: If contacted, REPORT Fan Failure Alarm is lit on 1PC2 Inverter.

Examiner Note: Primary side actions include controlling Pressurizer pressure and level due to a loss of Letdown.

Secondary side actions include controlling Steam Generator (SG) levels in SGs 1-02 and 1-03 when Main Feedwater Pump speed lowers.

DIRECT performance of ABN-603, Loss of Protection or Instrument Bus, US Section 2.0.

US/RO VERIFY Reactor did NOT trip. [Step 2.3.1]

US DETERMINE Unit in MODE 1. [Step 2.3.2]

Manually CONTROL parameters to MAINTAIN or RESTORE to normal as RO/BOP follows: [Step 2.3.3]

PLACE 1/1-RBSS, CONTROL ROD BANK SELECT Switch in MANUAL.

RO

[Step 2.3.3.a]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 3 Page 13 of 46 Event

Description:

Loss of Protection Bus 1PC2 Time Position Applicants Actions or Behavior VERIFY RCP Seal Injection Flow - WITHIN NORMAL OPERATING RO RANGE. [Step 2.3.3.b]

Manually CONTROL 1-FK-121, CCP CHG FLO CTRL Valve and charge to RCP Seals ONLY. [Step 2.3.3.b RNO]

VERIFY Pressurizer level controlled - BETWEEN 25% and 70%.

RO

[Step 2.3.3.c]

VERIFY Pressurizer pressure - WITHIN NORMAL OPERATING RO RANGE FOR CONDITIONS. [Step 2.3.3.d]

VERIFY Steam Generator levels being controlled - BETWEEN 60%

BOP AND 70%. [Step 2.3.3.e]

MANUALLY control Steam Generator levels and Feed Pumps as necessary to maintain level. [Step 2.3.3.e RNO]

PLACE 1-SK-509A, FWPT MASTER SPD CTRL in MANUAL.

[Step 2.3.3.e RNO]

PLACE 1-FK-520, SG 2 FW FLO CTRL in MANUAL and CONTROL SG 1-02 level. [Step 2.3.3.e RNO]

PLACE 1-FK-530, SG 3 FW FLO CTRL in MANUAL and CONTROL SG 1-03 level. [Step 2.3.3.e RNO]

US GO to Step 6. [Step 2.3.3.f]

Simulator Operator: When contacted to reenergize 1PC2, EXECUTE remote function EDR02 (Key 11), Inverter IV1PC2 Alternate Power Supply.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 3 Page 14 of 46 Event

Description:

Loss of Protection Bus 1PC2 Time Position Applicants Actions or Behavior RO VERIFY Unit - IN MODE 1. [Step 2.3.6]

PLACE 1/1-RBSS, CONTROL ROD BANK SELECT Switch in MANUAL.

RO

[Step 2.3.6.a]

SELECT LOOP 2 on 1-TS-412T, TAVE CHAN DEFEAT Switch.

RO

[Step 2.3.6.b]

DISPATCH an operator to REENERGIZE Protection Bus 1PC2.

RO/BOP

[Step 2.3.6.c]

VERIFY PCIP, Window 3.4 - TURB LOAD REJ STM DMP ARMED C-7, BOP not ARMED. [Step 2.3.6.d]

RESTORE 1-TS-412T, TAVE CHAN DEFEAT Switch to the NONE RO Position. [Step 2.3.6.e]

PLACE 1/1-RBSS, CONTROL ROD BANK SELECT Switch in AUTO.

RO

[Step 2.3.6.f]

INVESTIGATE and INITIATE Corrective Action on loss of power to US/RO Protection Bus. [Step 2.3.6.g]

US GO to Step 9. [Step 2.3.7]

US/RO VERIFY Unit - IN MODE 1. [Step 2.3.9]

Examiner Note: The following actions will be performed upon Bus 1PC2 restoration.

CHECK Status of Affected Control Systems and Instrumentation.

US

[Step 2.3.10]

BOP RESTORE Feedwater System to normal operation. [Step 2.3.10.a]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 3 Page 15 of 46 Event

Description:

Loss of Protection Bus 1PC2 Time Position Applicants Actions or Behavior PLACE 1-FK-520, SG 2 FW FLO CTRL in AUTO.

PLACE 1-FK-530, SG 3 FW FLO CTRL in AUTO.

PLACE 1-SK-509A, FWPT MASTER SPD CTRL in AUTO.

PLACE N-42A, RATE MODE Switch to RESET on Drawer N-42A, Power RO Range Flux Rate Mode Selector and VERIFY Positive Rate Mode alarm light - DARK. [Step 2.3.10.b]

RO RESTORE Charging and Letdown. [Step 2.3.10.c]

CLOSE 1-HC-182, Seal Flow Control Valve. [Step 2.3.10.c.1)]

ENSURE OPEN 1/1-8105 and 1/1-8106, Charging Isolation Valves.

[Step 2.3.10.c.2)]

ADJUST 1-HC-182, Seal Flow Control Valve and 1-FK-121, Charging Flow Control Valve to CONTROL RCP seal flow.

[Step 2.3.10.c.3)]

RESTORE Letdown flow per Control Board Job Aid or ABN-105.

[Step 2.3.10.c.4)]

US EVALUATE Technical Specifications. [Step 2.3.11]

LCO 3.8.7.A, Inverters - Operating.

CONDITION A - One required inverter inoperable.

ACTION A.1 - Restore inverter to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 3 Page 16 of 46 Event

Description:

Loss of Protection Bus 1PC2 Time Position Applicants Actions or Behavior Examiner Note: LCO 3.8.9.B is entered when power is lost and exited when power is restored.

LCO 3.8.9.B, Distribution Systems - Operating.

CONDITION B - One AC vital bus subsystem inoperable.

ACTION B.1 - Restore AC vital bus subsystem to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

US REFER to EPP-201. [Step 2.3.12]

US NOTIFY Engineering to expedite repairs. [Step 2.3.13]

US INITIATE a Condition Report per STA-421. [Step 2.3.14]

When Tech Specs have been addressed, PROCEED to Event 4.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 17 of 46 Event

Description:

High Vibrations on RCP 1-02 requiring Rapid Downpower Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 4 (Key 4).

- RCP 1-02 High Vibration (15.3 mils and stable)

Indications Available:

1-ALB-5B, Window 2.5, RCP 2 VIBR HI Rising vibration observed on RCP Vibration Monitor RO RESPOND to Annunciator Alarm Procedures.

BOP REPORT RCP 1-02 shaft vibration at 15.3 mils and stable.

DIRECT implementation of ABN-101, Reactor Coolant Pump US Trip/Malfunction, Section 6.0, Excessive Reactor Coolant Pump Vibration.

BOP CHECK RCP Vibration - WITHIN LIMITS: [Step 6.3.1]

RCP shaft vibration: [Step 6.3.1.a]

BETWEEN 15 mils and 20 mils and amplitude is NOT INCREASING.

[Step 6.3.1.a]

BOP RCP frame vibration: [6.3.1.b]

RO LESS than 3 mils. [6.3.1.b]

Simulator Operator: When contacted as the Shift Manager inform the SRO that a Rapid Downpower is to be conducted to have the unit off-line within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and RCP 1-02 secured.

IF contacted as the Duty Manager inform the SRO that a Rapid Downpower is to be conducted to have the unit off-line within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and RCP 1-02 secured.

CHECK RCP vibration within normal operating limits: [6.3.2]

CHECK RCP shaft vibration - NOT LESS THAN 15 mils [6.3.2.a]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 18 of 46 Event

Description:

High Vibrations on RCP 1-02 requiring Rapid Downpower Time Position Applicants Actions or Behavior CONSULT with Shift Manager AND Duty Manager to determine if unit is to be shutdown and affected pump stopped. [6.3.2.a. RNO 1)]

NOTIFY Generation Controller of imminent load reduction.

[6.3.2.a. RNO 2)]

NOTIFY System Engineering. [6.3.2.a. RNO 3)]

REFER to EPP-201. [6.3.2.a. RNO 4)]

INITIATE a Condition Report per STA-421. [6.3.2.a. RNO 5)]

Examiner Note: Crew should implement Reactivity Briefing Sheet for a Rapid Plant Shutdown within one hour.

Examiner Note: The following steps are from IPO-003A, Power Operations, Section 5.6, Reducing Turbine Power from 100% to MODE 3.

DIRECT load reduction to 200 MWe per IPO-003A, Power Operations, US Section 5.6, Reducing Turbine Power from 100% to MODE 3.

RO CONTACT Chemistry and place specified demineralizers in-service. [5.6.1]

RO NOTIFY QSC Generation Controller prior to reducing load. [5.6.2]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 19 of 46 Event

Description:

High Vibrations on RCP 1-02 requiring Rapid Downpower Time Position Applicants Actions or Behavior NOTIFY Chemistry and Radiation Protection that power will be lowered RO 15% within a one hour period. [5.6.3]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 20 of 46 Event

Description:

High Vibrations on RCP 1-02 requiring Rapid Downpower Time Position Applicants Actions or Behavior RO PERFORM the following to reduce Turbine Load to ~200MWe: [5.6.4]

DETERMINE the amount of Boration required to reduce Reactor Power to 200 MWe (~15% power). [5.6.4.A]

If desired, DETERMINE the rate of Boration required to allow slow Control RO Rod inward motion as Turbine load lowers. [5.6.4.B]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 21 of 46 Event

Description:

High Vibrations on RCP 1-02 requiring Rapid Downpower Time Position Applicants Actions or Behavior REFER to Attachment 2 for guidance in controlling AFD during power ramp.

RO

[5.6.4.C]

INITIATE RCS boration per SOP-104A, Reactor Make-up and Chemical RO Control System. [5.6.4.D]

Examiner Note: The following steps are from SOP-104A, Reactor Make-up and Chemical Control System, Section 5.1.2, Borate Mode.

RO PERFORM the following to COMMENCE RCS boration:

ENSURE Prerequisites of Section 2.1 and 2.2 are met. [Step 5.1.2.A]

IF at BOL and desire to periodically Borate for long term THEN Use Attachment 2, BOL Boration for Long Term Use. [5.1.2.B]

ENSURE 1/1-MU, RCS MU MAN ACT is in STOP. [Step 5.1.2.C]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 22 of 46 Event

Description:

High Vibrations on RCP 1-02 requiring Rapid Downpower Time Position Applicants Actions or Behavior ENSURE the following handswitches are in AUTO, and the valves CLOSED: [5.1.2.D]

1/1-FCV-111A, RMUW BLNDR FLO CTRL VLV 1/1-FCV-111B, RCS MU TO VCT ISOL VLV 1/1-FCV-110A, BA BLNDR FLO CTRL VLV 1/1-FCV-110B, RCS MU TO CHRG PMP SUCT ISOL VLV PLACE 43/1-MU, RCS MU MODE SELECT in BORATE. [Step 5.1.2.E]

Examiner Note: The Boration amounts and pot setting are approximations based on the briefing sheets, the crew may vary from the listed values based on plant conditions and desired rate of power reduction.

SET 1-FK-110, BA BLNDR FLO CTRL to ~5.82 pot setting for ~23.3 GPM. [Step 5.1.2.F]

SET 1-FY-110B, BA BATCH FLO counter for 698 gallons. [Step 5.1.2.G]

PLACE 1/1-MU, RCS MU MAN ACT in START. [Step 5.1.2.H]

VERIFY 1/1-APBA1, BA XFR PMP 1 STARTS. [Step 5.1.2.I]

VERIFY 1/1-FCV-110A, BA BLNDR FLO CTRL VLV throttles to

~23.3 GPM. [Step 5.1.2.J]

VERIFY 1/1-FCV-110B, RCS MU TO CHG PMP SUCT ISOL VLV OPEN.

[Step 5.1.2.J]

VERIFY 1-FY-110B, BA BATCH FLO counter operating properly.

[Step 5.1.2.K]

VERIFY 1-FR-110, BA BATCH FLO TO BLNDR red pen operating properly. [Step 5.1.2.K]

OPERATE 1/1-LCV-112A, VCT LVL CTRL VLV AND 1-LK-112C, VCT LVL CTRL as necessary to maintain proper VCT level. [Step 5.1.2.L]

When desired amount of boric acid is added, PLACE 1/1-MU, RCS MU MAN ACT in STOP. [Step 5.1.2.M]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 4 Page 23 of 46 Event

Description:

High Vibrations on RCP 1-02 requiring Rapid Downpower Time Position Applicants Actions or Behavior Examiner Note: The following steps continue from IPO-003A, Power Operations, Section 5.6, Reducing Turbine Power from 100% to Mode 3.

The listed rate of load reduction is based on the Reactivity briefing sheet and is based on ~45 minutes to 200 MWe. The crew may reduce load at a faster or slower rate.

WHEN the following are met: [5.6.4.E]

1) No TSE alarms are active BOP

2) ENSURE turbine load/speed is matched with target load/speed THEN TURN ON TSE influence BOP SET Turbine Load Rate Setpoint Controller to ~23.6 MWe/min. [5.6.4.F]

OPEN Load Rate Setpoint OSD.

SELECT blue bar and ENTER 23.6 MWe/min.

CLOSE Load Rate Setpoint OSD.

BOP SET Turbine Load Target to 200 MWe. [5.6.4.G]

OPEN Load Target OSD.

SELECT blue bar and ENTER 200 MWe.

DEPRESS Accept then VERIFY value in blue bar is desired Load Target (magnitude and direction).

DEPRESS Execute then VERIFY Load Target changes to desired load.

CLOSE Load Target OSD.

When the crew has demonstrated controlled load reduction, or as determined by the lead examiner, proceed to Event 5.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5 Page 24 of 46 Event

Description:

Reactor Coolant System Leak on Loop 2 Cold Leg Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 5 (Key 5).

- RC19B, Reactor Coolant Leak on Loop 2 Cold Leg (600 second ramp).

Indications Available:

CAG197, Containment Air Gaseous Radiation Monitor in ALERT on PC-11 2B-4.12 - CNTMT FAN CLR 1 & 2 CNDS FILL RATE HI 2A-2.8 - ANY CNTMT SMP PMP RUN 2B-3.12 - CNTMT FAN CLR 3 & 4 CNDS FILL RATE HI Containment Sump Pump AUTO start RO RESPOND to Annunciator Alarm Procedures.

RO RECOGNIZE RCS leak into Containment.

DIRECT performance of ABN-103, Excessive Reactor Coolant Leakage, US Section 2.0.

RO VERIFY Charging Pump - AT LEAST ONE RUNNING. [Step 2.3.1]

ENSURE Pressurizer level - AT OR TRENDING TO PROGRAM LEVEL RO SETPOINT. [Step 2.3.2]

PLACE Charging Pump Flow Controller in MANUAL and ADJUST Charging flow to maintain Pressurizer level let setpoint

[Step 2.3.2 RNO]

If Pressurizer level decreases in an uncontrolled manner, PERFORM the US following: [Step 2.3.2 RNO]

RO TRIP the Reactor. [Step 2.3.2 RNO]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 5 Page 25 of 46 Event

Description:

Reactor Coolant System Leak on Loop 2 Cold Leg Time Position Applicants Actions or Behavior PLACE 1/1-RTC, RX TRIP BKR Switch in TRIP position and VERIFY Reactor Trip at CB-07.

RO ACTUATE Safety Injection. [Step 2.3.2 RNO]

PLACE 1/1-SIA2, SI MAN ACT Switch to ACT position at CB-07 and DETERMINE SI has actuated.

US GO to EOP-0.0A. [Step 2.3.2 RNO]

When Reactor is tripped, or at Lead Examiner discretion, PROCEED to Events 6, 7, 8, and 9.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 26 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open Time Position Applicants Actions or Behavior Simulator Operator: When the Reactor is tripped and SI Initiated, Events 6, 7, 8, and 9 will commence.

Do NOT Initiate Key 7 (LBLOCA) until the transition to EOP-1.0A is performed.

- SI04D, SIPP 1-02 AUTO start failure on SI sequencer.

- RC09B2, LBLOCA on Loop 2 Cold Leg when EOP-1.0A is entered.

- RP10A, Train A Containment Isolation Phase B Auto Actuation failure.

- RP10B, Train B Containment Isolation Phase B Auto Actuation failure.

- RP19C, Phase B Containment Isolation Manual Switch Failure (Both).

- Override, Chem Add Tank Discharge Valve Fails to Auto Open.

Indications Available:

Multiple Reactor Trip alarms US DIRECT performance of EOP-0.0A, Reactor Trip or Safety Injection.

Examiner Note: The following steps are from EOP-0.0A, Reactor Trip or Safety Injection.

RO VERIFY Reactor Trip: [Step 1]

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 - BOTH ENERGIZED. [Step 3.b]

RO CHECK SI status: [Step 4]

CHECK if SI is actuated. [Step 4.a]

SI ACTUATED as indicated on the First Out Annunciator 1-ALB-6C

[Step 4.a]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 27 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open Time Position Applicants Actions or Behavior SI ACTUATED blue status light - ON: [Step 4.a]

VERIFY Both Trains SI Actuated: [Step 4.b]

SI ACTUATED blue status light - ON NOT FLASHING.

Examiner Note: EOP-0.0A, Attachment 2 steps performed by BOP are identified on Page 40 the scenario guide.

INITIATE Proper Safeguards Equipment Operation Per Attachment 2.

US/BOP

[Step 5]

RO VERIFY AFW Alignment: [Step *6]

VERIFY both MDAFW Pumps - RUNNING. [Step 6.a]

PLACE TDAFW Pump in PULLOUT per Foldout Page. [Step 6.b]

VERIFY AFW total flow - GREATER THAN 460 GPM. [Step 6.c]

VERIFY AFW valve alignment - PROPER ALIGNMENT. [Step 6.d]

RO VERIFY Containment Spray NOT Required: [Step *7]

VERIFY Containment pressure - HAS REMAINED LESS THAN 18.0 PSIG. [Step 7.a]

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]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 28 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open 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 Steam lines should be ISOLATED: [Step *8]

VERIFY Containment pressure - GREATER THAN 6.0 PSIG.

[Step 8.a]

VERIFY Main Steam Line pressure - LESS THAN 610 PSIG.

[Step 8.a]

GO to Step 9. [Step 8.a RNO a]

RO CHECK RCS Temperature: [Step *9]

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]

Examiner Note: The RCPs may be tripped if subcooling is observed to be < 25ºF.

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 a]

RO/BOP CHECK if Any Steam Generator Is Faulted: [Step 12]

CHECK pressures in all SGs: [Step 12.a]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 29 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open Time Position Applicants Actions or Behavior Any Steam Generator pressure - DECREASING IN AN UNCONTROLLED MANNER. [Step 12.a]

Any Steam Generator pressure - COMPLETELY DEPRESSURIZED. [Step 12.a]

GO to Step 13. [Step 12.a RNO a]

RO/BOP CHECK if Steam Generator Tubes Are NOT Ruptured: [Step 13]

VERIFY Condenser Off Gas radiation - NORMAL.

VERIFY Main Steam Line radiation - NORMAL.

VERIFY SG Blowdown Sample Radiation Monitor - NORMAL.

VERIFY levels in all Steam Generators - NORMAL.

RO/BOP CHECK if RCS is Intact: [Step 14]

VERIFY Containment pressure - LESS THAN 1.3 PSIG.

VERIFY Containment recirculation sump levels - NORMAL.

VERIFY Containment radiation levels - NORMAL GRID 4.

GO to EOP-1.0A, Loss of Reactor or Secondary, Step 1.

[Step 14 RNO]

Examiner Note: INITIATE Event 7, LBLOCA on Loop 2 Cold Leg once the transition to EOP-1.0A has been performed (Key 7).

US TRANSITION to EOP-1.0A, Loss of Reactor or Secondary Coolant, Step 1.

Examiner Note: Shortly after entry into EOP-1.0A, a transition to FRZ-0.1A, Response to High Containment Pressure, must be performed due to an ORANGE path. The Unit Supervisor should exit EOP-1.0A and enter FRZ-0.1A, Response to High Containment Pressure.

Examiner Note: FRZ-0.1A, Response to High Containment Pressure, steps begin here.

US/RO CHECK Containment pressure - GREATER THAN 50 PSIG. [Step 1]

DETERMINE proper Containment Spray alignment was NOT verified in RO/BOP EOP-0.A. [Step 1 RNO]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 30 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open Time Position Applicants Actions or Behavior Examiner Note: The crew must perform a Containment Spray Alignment because it was NOT verified at Step 7 of EOP-0.0A, Reactor Trip or Safety Injection.

VERIFY Containment Isolation Phase A - APPROPRIATE MLB LIGHT RO/BOP INDICATION (RED WINDOWS). [Step 2]

VERIFY Containment Ventilation Isolation - APPROPRIATE MLB LIGHT RO/BOP INDICATION (GREEN WINDOWS). [Step 3]

RO/BOP CHECK if Containment Spray is Required: [Step 4]

Containment pressure - HAS INCREASED TO GREATER THAN 18.0 PSIG. [Step 4.a]

1-ALB-2B Window 1-8, CS ACT - ILLUMINATED. [Step 4.a]

1-ALB-2B Window 4-11, CNTMT ISOL PHASE B ACT - NOT ILLUMINATED. [Step 4.a]

Containment pressure - GREATER THAN 18.0 PSIG. [Step 4.a]

RO/BOP VERIFY all RCPs - STOPPED. [Step 4.b]

Manually STOP all RCPs [Step 4.b RNO b]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 31 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open Time Position Applicants Actions or Behavior RO/BOP VERIFY Containment Isolation Phase B Valves - CLOSED. [Step 4.c]

DETERMINES Phase B has failed to Automatically Actuate.

Manually actuate Phase B. [Step 4.c RNO]

PLACE 1/1-CIPBA1A CS/CNTMT ISOL - PHASE B MAN ACT Switch in ACT position (Simultaneously).

PLACE 1/1-CIPBA2A CS/CNTMT ISOL - PHASE B MAN ACT Switch in ACT position (Simultaneously).

RO/BOP VERIFY 1-MLB-4A3 and 4B3 - ORANGE LIGHTS LIT. [Step 4.c]

IF Valve(s) NOT closed, THEN manually close Valve(s).

(Refer to Attachment 5) [Step 4.c. RNO c.]

Examiner Note: FRZ-0.1A, Attachment 5, Phase B Isolation steps begin here. All Valves are associated with CCW System and located on CB-03. Applicant may use Attachment 5 or Align valves by Orange lights. Both are acceptable.

Manually align Train A and/or Train B Containment Isolation Phase B CRITICAL TASK STATEMENT due to Failure to Automatically and Manually Actuate Prior to Exiting FRZ-0.1A, Response to High Containment Pressure.

RO/BOP 1-HS-4527, NON-SFGD LOOP CCW SPLY VLV 1-HS-4525, NON-SFGD LOOP CCW RET VLV 1-HS-4526, NON-SFGD LOOP CCW SPLY VLV 1-HS-4524, NON-SFGD LOOP CCW RET VLV CRITICAL 1-HS-4701, RCP CLR CCW RET ISOL VLV TASK 1-HS-4708, RCP CLR CCW RET ISOL VLV 1-HS-4700, RCP/THBR CLR CCW SPLY ISOL VLV 1-HS-4709, THBR CLR CCW RET ISOL VLV 1-HS-4699, RCP/THBR CLR CCW SPLY ISOL VLV 1-HS-4696, THBR CLR CCW RET ISOL VLV NOTIFY Unit Supervisor attachment instructions complete and Phase B Isolation Status.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 32 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open Time Position Applicants Actions or Behavior Examiner Note: FRZ-0.1A, Response to High Containment Pressure, steps restart again here.

US VERIFY ECA-1.1A, Loss of Emergency Coolant Recirculation - NOT IN EFFECT. [Step 4.d]

RO/BOP VERIFY Containment Spray Pumps - RUNNING. [Step 4.e]

VERIFY Containment Spray System valve alignment - PROPER EMERGENCY ALIGNMENT PER ATTACHMENT 4. [Step 4.f]

Injection phase Manually ALIGN Valve(s) as necessary. [Step 4.f RNO]

Examiner Note: FRZ-0.1A, Attachment 4, Containment Spray Alignment - Injection Phase, steps begin here. Applicant may use Attachment 4 or Align valves by Blue lights. Both are acceptable.

1-MLB-4A3 AND 4B3 - BLUE LIGHTS LIT. [Step 1]

Recognizes Blue Light NOT lit for 1-HS-4755, CHEM ADD TK DISCH RO/BOP VLV Manually OPENS 1-HS-4755, CHEM ADD TK DISCH VLV, to establish Train B Chem Add Tank Discharge Flow. [Step 4.f RNO]

RO/BOP CHEM ADD TK DISCH VLVs - OPEN [Step 2]

1-HS-4753 1-HS-4752 RO/BOP CNTMT SMP TO CSP 1 & 3 and 2 & 4 SUCT ISOL VLVs - CLOSED

[Step 3]

1-HS-4782 1-HS-4783 CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 33 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open Time Position Applicants Actions or Behavior RO/BOP RWST TO CSP 1 & 3 and 2 & 4 SUCT VLVs - OPEN [Step 4]

1-HS-4758 1-HS-4759 RO/BOP NOTIFY Unit Supervisor Attachment instructions complete AND identify Containment Spray alignment status.

Examiner Note: FRZ-0.1A, Response to High Containment Pressure, steps restart again here.

VERIFY Containment Spray flow. [Step 4.g]

US/RO VERIFY Main Steam Line Isolation Valves - CLOSED. [Step 5]

RO/BOP CHECK IF Feedwater Flow should be isolated to any SG. [Step 6]

CHECK pressures in all SGs: [Step 6.a]

ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER [Step 6.a]

ANY SG COMPLETELY DEPRESSURIZED [Step 6.a]

GO to Step 7 [Step 6.a RNO a]

Examiner Note: The Unit Supervisor should exit FRZ-0.1A, Response to High Containment Pressure and enter FRP-0.1A, Response to Imminent Pressurized Thermal Shock Condition due to a Critical Safety Function Status Tree ORANGE path.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 34 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open Time Position Applicants Actions or Behavior US RETURN to Procedure and Step in Effect. [Step 7]

Examiner Note: FRP-0.1A, Response to Imminent Pressurized Thermal Shock Condition, steps begin here.

CHECK RCS pressure - GREATER THAN 325 PSIG (425 PSIG FOR US ADVERSE CONTAINMENT). [Step 1]

VERIFY RHR Pump flow greater than 750 GPM and RETURN to RO/BOP procedure and step in effect. [Step 1 RNO]

Examiner Note: The Unit Supervisor should exit FRP-0.1A, Response to Imminent Pressurized Thermal Shock Condition and return to EOP-1.0A, Loss of Reactor or Secondary Coolant, which is the Procedure and Step in effect.

Examiner Note: EOP-1.0A, Loss of Reactor or Secondary Coolant, steps begin here.

US/RO CHECK If RCPs Should Be Stopped: [Step 1]

VERIFY RCS subcooling less than 25ºF (55ºF FOR ADVERSE CONTAINMENT). [Step 1.a]

VERIFY ECCS Pumps (CCP or SI) - AT LEAST ONE RUNNING.

[Step 1.b]

RO VERIFY all RCPs stopped. [Step 1.c]

RO/BOP CHECK if Any Steam Generator Is Faulted: [Step 2]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 35 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open Time Position Applicants Actions or Behavior CHECK pressure in all SGs [Step 2.a]

Any Steam Generator pressure - DECREASING IN AN UNCONTROLLED MANNER. [Step 2.a]

Any Steam Generator pressure - COMPLETELY DEPRESSURIZED. [Step 2.a]

GO to Step 3. [Step 2.a RNO]

US CHECK Intact Steam Generator Levels: [Step *3]

Narrow range level - GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT). [Step 3.a]

MAINTAIN total AFW flow greater than 460 GPM until narrow range level GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT) in at least one intact SG. [Step 3.a RNO a]

Control AFW flow to maintain narrow range level between 43% (50%

FOR ADVERSE CONTAINMENT) and 60%. [Step 3.b]

US CHECK Secondary Radiation NORMAL: [Step 4]

VERIFY Condenser off gas radiation - NORMAL. [Step 4]

VERIFY Main Steam Line radiation - NORMAL. [Step 4]

VERIFY SG Blowdown Sample Radiation Monitor - NORMAL. [Step 4]

VERIFY levels in all Steam Generators - NORMAL. [Step 4]

US CHECK PRZR PORVs and Block Valves: [Step *5]

VERIFY power to block valves - AVAILABLE. [Step 5.a]

VERIFY PORVs - CLOSED. [Step 5.b]

VERIFY Block valves - AT LEAST ONE OPEN. [Step 5.c]

US/RO CHECK if ECCS Flow Should Be Reduced: [Step *6]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 36 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open Time Position Applicants Actions or Behavior VERIFY Secondary heat sink conditions - SATISFIED. [Step 6.a]

VERIFY RCS subcooling - GREATER THAN 25°F (55°F FOR ADVERSE CONTAINMENT). [Step 6.b]

GO to Step 7 and OBSERVE CAUTIONS Prior to Step 7.

[Step 6.b RNO b]

RO/BOP RESET ESF Actuation Signals. [Step 7]

CHECK diesel generators - RUNNING [Step 7.a]

PLACE both EDG EMERG STOP/START handswitches in START.

[Step 7.b]

Examiner Note: When Safety Injection is properly RESET, Annunciator 1-ALB-2B, Window 2.8, SFGD SEQR TRN A/B AUTO TEST TRBL, will RESET.

RO/BOP RESET SI. [Step 7.c]

DEPRESS 1/1-SIRA, TRAIN A SI RESET pushbutton.

DEPRESS 1/1-SIRB, TRAIN A SI RESET pushbutton.

RO/BOP RESET SI Sequencers. [Step 7.d]

At SI Sequencer Train A Cabinet, DEPRESS SI SEQR RESET green pushbutton then PLACE ON/RESET toggle switch in RESET.

After ~ 2 seconds, PLACE ON/RESET toggle switch in ON.

At SI Sequencer Train B Cabinet, DEPRESS SI SEQR RESET green pushbutton then PLACE ON/RESET toggle switch in RESET.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 37 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open Time Position Applicants Actions or Behavior After ~ 2 seconds, PLACE ON/RESET toggle switch in ON.

RO/BOP RESET Containment Isolation Phase A and Phase B. [Step 7.e]

DEPRESS 1/1-C1PARA, CNTMT ISOL - PHASE A RESET pushbutton.

DEPRESS 1/1-C1PARB, CNTMT ISOL - PHASE A RESET pushbutton.

DEPRESS 1/1-C1PBRA, CNTMT ISOL - PHASE B RESET pushbutton.

DEPRESS 1/1-C1PBRB, CNTMT ISOL - PHASE B RESET pushbutton.

RO/BOP RESET Containment Spray Signal. [Step 7.f]

DEPRESS 1/1-CSRA, TRAIN A CS RESET pushbutton.

DEPRESS 1/1-CSRB, TRAIN B CS RESET pushbutton.

US CHECK If RHR Pumps Should Be Stopped: [Step *8]

CHECK RCS pressure: [Step 8.a]

VERIFY RCS pressure - GREATER THAN 325 PSIG (425 PSIG RO/BOP FOR ADVERSE CONTAINMENT). [Step 8.a.1)]

GO to Step 10. [Step 8.a.1) RNO 1)]

US CHECK If Diesel Generators Should Be Stopped: [Step *10]

VERIFY both AC Safeguards Buses ENERGIZED by Offsite Power.

RO/BOP

[Step 10.a]

RO/BOP PLACE both EDG EMERG STOP/START handswitches in STOP.

[Step 10.b]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 38 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open Time Position Applicants Actions or Behavior US INITIATE Evaluation of Plant Status. [Step 11]

RO VERIFY Cold Leg Recirculation capability: [Step 11.a]

VERIFY Train A RHR Pump - AVAILABLE. [Step 11.a.1)]

VERIFY CCW to Train A RHR Pump - NOT AVAILABLE.

[Step 11.a.1)]

VERIFY 1/1-8811A, CNTMT SMP TO RHRP 1 SUCT ISOL VLV AVAILABLE. [Step 11.a.1)]

VERIFY Train B RHR Pump - AVAILABLE. [Step 11.a.1)]

VERIFY CCW to Train B RHR Pump - AVAILABLE.

[Step 11.a.1)]

VERIFY 1/1-8811B, CNTMT SMP TO RHRP 2 SUCT ISOL VLV -

AVAILABLE. [Step 11.a.1)]

VERIFY 1/1-8804A, RHRP 1 TO CCP SUCT VLV - AVAILABLE.

[Step 11.a.2)]

VERIFY 1/1-8804B, RHRP 2 TO SIP SUCT VLV - AVAILABLE.

[Step 11.a.2)]

CHECK Auxiliary Building and Safeguards Building radiation - NORMAL:

RO/BOP

[Step 11.b]

CHECK PC-11 monitors - NORMAL OR Notify Radiation Protection to take local Radiation Surveys. [Step 11.b]

NOTIFY Chemistry to obtain RCS samples to assist in determining US extent of the accident. [Step 11.c]

US CONTACT Plant Staff to EVALUATE plant equipment. [Step 11.d]

US CHECK if RCS Cooldown and Depressurization Is Required: [Step 12]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 39 of 46 Event

Description:

Safety Injection Pump 1-02 Auto Start Failure / Large Break LOCA / Train A & B Containment Isolation Phase B Automatic and Manual Failure / Train B Chem Add Tank Discharge Valve Fails to Auto Open Time Position Applicants Actions or Behavior RCS pressure - GREATER THAN 325 PSIG (425 PSIG FOR ADVERSE RO/BOP CONTAINMENT). [Step 12.a]

VERIFY RHR Pump flow greater than 750 GPM and GO to Step 13.

RO/BOP

[Step 12.a RNO a]

US CHECK If Transfer to Cold Leg Recirculation Is Required. [Step 13]

VERIFY RWST Level - LESS THAN LO-LO LEVEL.

RO/BOP

[Step 13.a]

Go To EOS-1.3A, TRANSFER TO COLD LEG RECIRCULATION, Step 1. [Step 13.b]

When conditions are reached for a Transfer to Cold Leg Recirculation in accordance with EOS-1.3A, Transfer to Cold Leg Recirculation, TERMINATE the scenario.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # Attachment 2 Page 40 of 46 Event

Description:

EOP-0.0A, Attachment 2 Time Position Applicants Actions or Behavior Examiner Note: These steps are performed by the BOP per EOP-0.0A, Attachment 2.

BOP VERIFY SSW Alignment: [Step 1]

VERIFY SSW Pumps - RUNNING. [Step 1.a]

VERIFY EDG Cooler SSW return flow. [Step 1.b]

CRITICAL TASK Manually Start Safety Injection Pump 1-02 Prior to completing STATEMENT Attachment 2 of EOP-0.0A, Reactor Trip or Safety Injection.

BOP VERIFY Safety Injection Pumps - RUNNING. [Step 2]

CRITICAL Recognizes Safety Injection Pump 1-02 has failed to start and manually TASK starts Safety Injection Pump 1-02. [Step 2 RNO]

VERIFY Containment Isolation Phase A - APPROPRIATE MLB LIGHT BOP INDICATION (RED WINDOWS). [Step 3]

VERIFY Containment Ventilation Isolation - APPROPRIATE MLB LIGHT BOP INDICATION (GREEN WINDOWS). [Step 4]

BOP VERIFY CCW Pump 1 RUNNING. [Step 5]

BOP VERIFY RHR Pumps - RUNNING. [Step 6]

BOP VERIFY Proper CVCS Alignment: [Step 7]

VERIFY both CCPs - RUNNING. [Step 7.a]

VERIFY Letdown Relief Valve Isolation: [Step 7.b]

Letdown Orifice Isolation Valves - CLOSED. [Step 7.b.1)]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # Attachment 2 Page 41 of 46 Event

Description:

EOP-0.0A, Attachment 2 Time Position Applicants Actions or Behavior Letdown Isolation Valves 1/1-LCV-459 & 1/1-LCV-460 - CLOSED.

[Step 7.b.2)]

BOP VERIFY ECCS flow: [Step 8]

CCP SI flow indicator - CHECK FOR FLOW. [Step 8.a]

RCS pressure - LESS THAN 1700 PSIG (1800 PSIG FOR ADVERSE CONTAINMENT). [Step 8.b]

SIP discharge flow indicator - CHECK FOR FLOW. [Step 8.c]

RCS pressure - LESS THAN 325 PSIG (425 PSIG FOR ADVERSE CONTAINMENT). [Step 8.d]

RHR TO CL INJ flow indicators - CHECK FOR FLOW. [Step 8.e]

BOP VERIFY Feedwater Isolation Complete: [Step 9]

Feedwater Isolation Valves - CLOSED.

Feedwater Isolation Bypass Valves - CLOSED.

Feedwater Bypass Control Valves - CLOSED.

Feedwater Control Valves - CLOSED.

BOP VERIFY both Diesel Generators - RUNNING. [Step 10]

VERIFY Monitor Lights for SI Load Shedding on 1-MLB-9 and BOP 1-MLB LIT. [Step 11]

VERIFY Proper SI alignment - PROPER MLB LIGHT INDICATION.

BOP

[Step 12]

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # Attachment 2 Page 42 of 46 Event

Description:

EOP-0.0A, Attachment 2 Time Position Applicants Actions or Behavior BOP VERIFY Components on Table 1 are properly aligned. [Step 13]

Location Equipment Description Condition CB-03 X-HS-5534 H2 PRG SPLY FN 4 STOPPED CB-03 X-HS-5532 H2 PRG SPLY FN 3 STOPPED CB-04 1/1-8716A RHRP 1 XTIE VLV OPEN CB-04 1/1-8716B RHRP 2 XTIE VLV OPEN CB-06 1/1-8153 XS LTDN ISOL VLV CLOSED CB-06 1/1-8154 XS LTDN ISOL VLV CLOSED CB-07 1/1-RTBAL RX TRIP BKR OPEN CB-07 1/1-RTBBL RX TRIP BKR OPEN CB-07 1/1-BBAL RX TRIP BYP BKR OPEN/DEENERGIZED CB-07 1/1-BBBL RX TRIP BYP BKR OPEN/DEENERGIZED CB-08 1-HS-2397A SG 1 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2398A SG 2 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2399A SG 3 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2400A SG 4 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2111C FWPT A TRIP TRIPPED CB-08 1-HS-2112C FWPT B TRIP TRIPPED CB-09 1-HS-2490 CNDS XFER PUMP STOPPED (MCC deenergized on SI)

CV-01 X-HS-6181 PRI PLT SPLY FN 17 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6188 PRI PLT SPLY FN 18 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6195 PRI PLT SPLY FN 19 & INTK STOPPED/DEENERGIZED DMPR 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 CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # Attachment 2 Page 43 of 46 Event

Description:

EOP-0.0A, Attachment 2 Time Position Applicants Actions or Behavior 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 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 1 Event # Attachment 2 Page 44 of 46 Event

Description:

EOP-0.0A, Attachment 2 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 NOTIFY Unit Supervisor attachment instructions complete AND to BOP IMPLEMENT FRGs as required.

EOP-0.0A, Attachment 2 steps are now complete.

CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

Scenario Event Description NRC Scenario 1

2016 NRC Scenario 1

Rev. 1

SIP 1-01 Out of Service IRF SIR01 f: 0

Event 1 - CCW Pump Trip/Autostart Failure

Train A CCW Pump Trip IMF CC02A f: 1 k:1

Train B CCW Pump Failure to Auto Start IMF CC03A f: 1

Event 2 - Spray Valve Loop 4 Fails Open

PCV-455C Fails 50% Open IMF RX15B f: 50 r:120 k:2

Green Lower Push Button Light Off IOR LORXPK455C_4 f: 0 k:2

Conditional to delete Spray Valve Failure

{DIRXPK455C_2.Value=1} DMF RX15B

{DIRXPK455C_2.Value=1} DOR LORXPK455C_4

Event 3 - IV1PC2 Failure

Loss of IV1PC2 IMF ED07B f: 1 k:3

Restore Power to 1PC2 from Alternate Power IRF EDR02 f: 0 k:11

Event 4 - Rapid Shutdown due to High RCP 1-02 Vibrations

RCP 1-02 Hi Vibration Rapid Shutdown IMF RC03B f: 15.3 k:4

Event 5 - RCS Leak to SBLOCA [Loop 2 Cold Leg]

600 gpm RCS Leak ramped in over 10 min.

IMF RC19B f:600 r:600 k:5

Event 6 - SIP 1-02 Autostart Failure on SI

SIP 2 Safety Injection Sequencer Start Failure IMF SI04D f: 1

Event 7 - LBLOCA after entry into EOP-1.0A

LBLOCA [Loop 2 Cold Leg]

IMF RC09B2 f:1 k:7

Event 8 - Phase B Containment Isolation Failure

Train A Phase B Containment Isolation Auto Failure IMF RP10A f: 1

Train B Phase B Containment Isolation Auto Failure IMF RP10B f: 1

Phase B Containment Isolation Manual Switch Failure IMF RP19C f: 1

Event 9 - Chemical Addition Tank Isolation Valve Fails to Auto Open

1-HS-4755 Fails to Open IOR DICSHS4755 f: 0

1-HS-4755 Opens Manually

{DICSHS4755.Value=2} DOR DICSHS4755 CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1

GUARDED EQUIPMENT MANAGEMENT (GEM) SIGN POSTING LOG REASON FOR POSTING SIP 1-01 INOPERABLE Component to be Nomenclature Posting Installed Posting Checked Posting Removed Posted Initial Initial Initial SIP 2 => CB / 830 / X-135 1/1-APSI2 JGR RB SAFETY INJECTION PUMP 1-02 MOTOR 1APSI2 BREAKER => SG / 852 / 1-103 JGR RB SAFETY INJECTION PUMP 1-02 ROOM => SG S1-2 / 773 / 1-060 JGR RB Authorized By UnitSupervisor Date Today Posting Removal Authorized By Date Open Narrative Log Entry Entered Open Narrative Log Entry Closed Comments: This form is not maintained. Verify correct items Guarded per STI-600.01 prior to use.

STI-600.01-1 Page 1 of 1 REFERENCE USE Rev. 0

Appendix D Scenario Outline Form ES-D-1 Facility: CPNPP 1 & 2 Scenario No.: 2 Op Test No.: July 2016 NRC Examiners: Operators:

Initial Conditions: 53% power MOL - RCS Boron is 1054 ppm Turnover: 600 MWe due to a B MFP trip. 1-02 MDAFWP in Pull Out (DANGER tagged) with breaker de-energized for scheduled maintenance. Restored B MFP following the trip but 1-PV-2286 was damaged and is DANGER tagged out for repairs. Hold power per load dispatch.

Critical Tasks: CT-1 Initiate Emergency Boration prior to exiting EOS-0.1A, Reactor Trip Response.

CT-2 Establish an RCS bleed and feed path prior to exiting FRH-0.1A, Response to a Loss of Secondary Heat Sink.

Event Malf. Event Type* Event Description No. No.

I (RO, SRO) 1 RX05A PRZR level instrument LT-459 fails low TS (SRO) 2 RX18 I (BOP, SRO) Feed Header Pressure Transmitter (PT-508) Fails High I (RO, SRO) 3 RX09A Main Turbine 1st Stage Pressure (PT-505A) Fails Low TS (SRO) 4 CH03 C (BOP, SRO) Neutron Detector Well Fan 9 trips on motor overload 5 FW06A C (BOP, SRO) Main Feed Pump A Recirc valve fails open C (BOP, SRO) 6 ED02 Loss of XST1 Transformer TS (SRO)

ED01 Loss of offsite power 7 M (RO,BOP,SRO)

EG06A Failure of the DG 1-01 to start (air start failure) 8 Emergency Boration due to loss of DRPI Loss of all AFW 9 FW09A M (RO,BOP,SRO)

TDAFWP Overspeed Trip

(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) 6 Abnormal events (2-4) 2 Major transients (1-2) 1 EOPs entered/requiring substantive actions (1-2)

EOP contingencies requiring substantive actions 1

(0-2) 2 Critical tasks (2-3)

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Scenario Event Description NRC Scenario 2 SCENARIO

SUMMARY

NRC 2 Turnover:

The plant is at 600 MW following a B MFP trip. Reactor power is being held stable per instruction of the Load Dispatcher. MDAFWP 1-02 is Danger tagged for planned maintenance. When the B MFP tripped it caused damage to 1-PV-2286, Low Pressure Feedwater Heater Bypass Valve. The MFP has been restored to operation but 1-PV-2286 is Danger tagged to complete repairs.

Event 1 (Key 1)

The first event will be a PRZR level channel failing low. Entry into ABN-706, PRZR Level Instrumentation Malfunction, section 2.0, will be required. Letdown will isolate, charging will be placed in manual to control PRZR level. Actions will include selecting an operable channel, restoring letdown, and then restoring PRZR level to program and placing controls back in automatic. The SRO will determine the loss of this channel is a TS entry for LCO 3.3.1, Reactor Trip System Instrumentation; function 9, Condition M.

Event 2 (Key 2)

The next event is Main Feedwater (MFW) Header Pressure Transmitter (PT-508) will fail high. Entry into ABN-709, Steam Line Pressure, Steam Header Pressure, Turbine 1st Stage Pressure, and Feed Header Pressure Instrument Malfunction Section 5.0, is required. Section 5.0 is designated for Feed Header Pressure Malfunction. Actions include placing the MFW Pump Turbine Master Speed Controller in MANUAL. This controller will remain in MANUAL for the duration of the scenario and require monitoring/adjustment.

Event 3 (Key 3)

Once the plant is stabilized, the next event is a Turbine 1st Stage Pressure Transmitter will fail low.

Crew actions are per ABN-709, Steam Line Pressure, Steam Header Pressure, Turbine 1st Stage Pressure, and Feed Header Pressure Instrument Malfunction, Section 4.0 is required. Section 4.0 is designated for Turbine 1st Stage Pressure Malfunction. Actions include placing Rod Control in Manual and bypassing the failed Turbine 1st Stage Pressure channel. The SRO will refer to Technical Specification LCO 3.3.1, Reactor Trip System Instrumentation; Function 18f, Condition T.

Event 4 (Key 4)

The next event will be a trip of the running Neutron Detector Well Fan #9. This will alarm 2.1 CNTMT FN MASTER TRIP. The ALM will direct the crew to determine which fan has tripped and start the other fan as required using SOP-801A, Containment Ventilation System. The crew will place the tripped fan handswitch in Pull Out or Stop as applicable.

Event 5 (Key 5)

The next event is MFP A Recirculation Valve, 1-FCV-2289, opening. ABN-302, Feedwater, Condensate, Heater Drain System Malfunction, section 11.0 will be entered. Since earlier in this scenario the main feedwater header pressure transmitter failed MFP speed control is in manual.

Manual speed control is required to restore S/G levels and stabilize the plant. The RO must ensure rods are in auto for this event. The crew will dispatch an operator to isolate the failed open recirculation valve. Once the failed valve is isolated, the BOP will adjust MFP speed again for the current plant configuration.

Event 6 (Key 6)

The next event is a loss of XST1 which is the alternate offsite power source for Unit 1. The ALM will have the crew enter ABN-601, Response to a 138/345 KV System Malfunction, as well as a TS entry for 3.8.1, Electrical Power Systems, AC Sources - Operating, Condition A.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Scenario Event Description NRC Scenario 2 Event 7 (Key 7)

The major event is a loss of all offsite power causing a reactor trip. The crew will enter EOP-0.0A, Reactor Trip or Safety Injection. Coincident with the loss of offsite power DG 1-01 will fail to auto start and cannot be manually started due to an air start failure. This will cause a complete loss of all safeguards train A power. The crew will transition to EOS-0.1A, Reactor Trip Response, to continue with recovery efforts.

Event 8 - CT-1 (Auto)

Due to the Loss of Offsite Power, DRPI is lost and per EOP-0.0A and EOS-0.1A, Reactor Trip Response, Attachments 1.A, an Emergency Boration will be required. The crew will then perform CT-1; Initiate Emergency Boration prior to exiting EOS-0.1A, Reactor Trip Response. This will be completed by entering ABN-107, Emergency Boration.

Event 9 (Auto Triggered when 1/1-8104 is placed in open per ABN-107)

After the crew has commenced the emergency boration the TDAFWP will trip on Overspeed. This combined with the loss of all Safeguards Train A power as well as the inoperability of MDAFWP 1-02 will place the crew in a loss of heat sink event. The crew will enter FRH-0.1A, Response to Loss of Secondary Heat Sink, and actuate SI. The crew will then perform CT-2, Establish an RCS bleed and feed path prior to exiting FRH-0.1A, Response to a Loss of Secondary Heat Sink.

Termination Criteria This scenario is terminated after the crew establishes a bleed and feed path per FRH-0.1A. One CCP and one SI pump running with both PRZR PORVs open.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Scenario Event Description NRC Scenario 2 Risk Significance Determination Risk Significance Event Guidance Failure of risk important systems Loss of Transformer XST1 FSAR 8.2.1.2.1 - Two prior to Reactor Trip independent power sources are available on an immediate basis following a DBA to ensure operation of the vital safety functions. The second offsite power source will no longer be available on loss of XST1.

Risk significant core damage FSAR 15.2.6.3 Loss of Non- EOS-0.2A, Natural Circulation sequence emergency AC power to the Cooldown - For Units 1 and 2, station auxiliaries the analysis of the natural circulation capability of the RCS has demonstrated that sufficient heat removal capability exists following reactor coolant pump coastdown to prevent fuel or clad damage.

Loss of Secondary Heat Sink CPNPP Accident Sequence Quantification, R&R-PN-022 -

Loss of secondary heat removal, not related to ventilation failures, accounts for about 9% of CDF.

Risk significant operator actions Initiation of Boration to Add STI 214.01; ABN-107, Negative Reactivity to the Core Emergency Boration; (TSA 2.14) WCAP-1687 1-P, Section 6.3.5; TRM Bases 13.1.31 - Within 15 minutes, when local alignment is required to establish boration flow. Boration is initiated within the prescribed time. When local manual control credited, admin controls are utilized to ensure personnel are aware/designated to perform alignment to establish boration flow.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Scenario Event Description NRC Scenario 2 Critical Task Determination Measurable Safety Performance Critical Task Cueing Performance Significance Feedback Indicators Initiate Shutdown Margin After the loss of offsite Started CCP Boration flow will Emergency must be power and the failure 1-02, started be indicated on Boration prior to maintained. of the DG 1-01, DRPI Boric Acid 1-FI-183A, EMER exiting EOS-0.1A, Since there are will be dark and no Transfer Pump BORATE FLO.

Reactor Trip NO DRPI lights lit CCP will be running. 1-02, and Response. the bases states Per attachment 1.A of opened 1/1-to borate at least EOS-0.1A, ABN-107 8104, EMER 3600 gallons of will be performed. BORATE VLV.

7000 ppm borated water to ensure shutdown margin is maintained. This gallon value corresponds to 2 of the most reactive rods stuck out.

Establish an RCS Actuating SI will AFW flow will not be Actuated SI, Flow indicated on bleed and feed ensure a feed indicated on any AFW ensured at least both a CCP and path prior to path of cool flow meter. Also no one CCP and SI an SI pump.

exiting FRH-0.1A, water to the RCS AFW pumps will be pump is running PRZR PORVs Response to a (core) and isolate running. A RED path with flow open with block Loss of the containment showing on CSFST for indicated valves open.

Secondary Heat to confine any heat sink. The need providing a feed RCS pressure Sink. RCS releases for a heat sink as path for the and temperature from the bleed indicated by RCS RCS. Both lowering.

flow. The bleed temperature and PRZR PORVs flow through both pressure. open providing a PORVs will bleed path for ensure that the RCS.

enough cool water will feed from the ECCS flow path to remove sufficient decay heat.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Scenario Event Description NRC Scenario 2 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP Initialize to IC-16 and 2016 NRC Scenario 2.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER SETUP FWR021 1-02 MDAFWP in Pull Out RACKOUT K0 FWR056 1-PV-2286 Isolated for repairs CLOSED K0 (NOTE)

NOTE: See Scenario file on last page for list of event overrides.

7 EG06A 1-01 EDG air start failure FAIL K0 TDAFWP trips on 1/1-8104 valve opening 9 Condition FW09A TRIP 8104 Open (60 second delay) 1 RX05A PRZR level channel LT-459 fails low 0% K1 Main Feedwater Header Pressure transmitter fails 2 RX18 1500 psig K2 high Main Turbine First Stage pressure PT-505A fails 3 RX09A 0% K3 low 4 CH03 Neutron Detector well fan 9 trip TRIP K4 5 FW06A A MFP recirc valve fails open OPEN K5 (NOTE)

NOTE: See Scenario file on last page for list of event overrides.

6 ED02 Loss of XST1 Transformer FAIL K6 7 ED01 Loss of offsite power FAIL K7 7 EG06A 1-01 EDG air start failure FAIL K0 8 Emergency Borate 9 Loss of Secondary Heat Sink TDAFWP trips on 1/1-8104 valve opening 9 Cond. FW09A TRIP 8104 Open (60 second delay)

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Scenario Event Description NRC Scenario 2 Simulator Operator: INITIALIZE to IC-16 and 2016 NRC Scenario 2 and place in RUN.

ENSURE all Simulator Annunciator Alarms are ACTIVE.

ENSURE all Control Board Tags are removed.

ENSURE Operator Aid Tags reflect current boron conditions (1054 ppm).

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:

- IPO-003A, Power Operations ENSURE TT06 on PWROPS and all points ON-SCALE ENSURE Control Rods are in AUTO with Bank D at 167 steps.

ENSURE RED tag on MDAFWP 1-02 with handswitch in Pull Out ENSURE RED tag on 1-PV-2286 with RED & GREEN Lights OFF ENSURE GEM Box PLACED 1-HS-2450A for MDAFWP 1-01 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 9A-3.2 - HDP1 DISCH PRESS HI 9A-7.2 - HDP2 DISCH PRESS HI CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 1 Page 8 of 32 Event

Description:

PRZR level channel LT-459 fails low Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 1 (Key 1).

- PRZR level channel LT-459 fails low Indications Available:

PRZR LVL LO (5B-3.6)

PRZR LVL DEV LO (5C-1.2)

RO RESPOND to Annunciator Alarm Procedures RO RECOGNIZE PRZR level channel LT-459 has failed low Direct the performance of ABN-706, Pressurizer Level Instrumentation US Malfunction Section 2.3

1. Manually CONTROL u-LK-459, PRZR LVL CTRL OR u-FK-121, CCP RO CHRG FLO CTRL to maintain level at program.

2. TRANSFER 1/u-LS-459D, PRZR LVL CTRL CHAN SELECT to an RO operable alternate controlling channel.

3. ENSURE 1/u-LS-459E, u-LR-459 PRZR LVL SELECT selected to a RO valid channel.

RO 4. VERIFY normal letdown aligned - NO

4. RNO - WHEN pressurizer level is greater than 17%, THEN RO RESTORE letdown per Attachment 6.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 1 Page 9 of 32 Event

Description:

PRZR level channel LT-459 fails low Time Position Applicants Actions or Behavior Examiner Note: Attachment 6 steps are located after the steps for ABN-706 (below)

Simulator Operator: If contacted as the prompt team, acknowledge the request to repair LT-459.

5. If necessary, RECLOSE 1/u-PCPR, PRZR CTRL HTR GROUP C by RO placing the control switch in the "ON" position.

RO 6. If desired, PLACE controller used in Step 1 in AUTO.

7. VERIFY instruments on common instrument line - NORMAL (see RO Attachment 1)

Examiner Note: The following two steps are not performed until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months later if repairs are not completed.

8. Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , HAVE an I&C Technician place bistable test RO switches for failed channel in CLOSED position per Attachment 3.

9. VERIFY appropriate alarm AND trip status lights ON per Attachment RO 4 AND NOTE verification in Unit Log.

RO 10. REFER to Technical Specifications per Attachment 5.

3.3.1.1 Function 9 Condition M, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to place in trip RO 11. INITIATE a Condition Report per STA-421, as applicable.

Examiner Note: ABN-706 Attachment 6 steps begin here

1. OPEN OR VERIFY open both letdown isolation valves.

RO

1/u-LCV-459, LTDN ISOL VLV

1/u-LCV-460, LTDN ISOL VLV

2. ENSURE u-PK-131, LTDN HX OUT PRESS CTRL in MANUAL AND RO 30% demand (50% if two orifice valves will be opened).

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 1 Page 10 of 32 Event

Description:

PRZR level channel LT-459 fails low Time Position Applicants Actions or Behavior

3. ENSURE u-TK-130, LTDN HX OUT TEMP CTRL in MANUAL AND RO 50% demand.

4. ADJUST charging to desired flow WHILE maintaining seal injection RO flow between 6 and 13 gpm.

5. OPEN the desired orifice isolation valves.

1/u-8149A, LTDN ORIFICE ISOL VLV (45 GPM)

RO

1/u-8149B, LTDN ORIFICE ISOL VLV (75 GPM)

1/u-8149C, LTDN ORIFICE ISOL VLV (75 GPM)

6. ADJUST u-PK-131, LTDN HX OUT PRESS CTRL to obtain RO approximately 310 psig on u-PI-131, LTDN HX OUT PRESS, THEN PLACE in automatic.

7. ADJUST u-TK-130, LTDN HX OUT TEMP CTRL to obtain RO approximately 95EF on u-TI-130, LTDN HX OUT TEMP, THEN PLACE in automatic.

When the Charging and Letdown flows are stable, or at Lead Examiner discretion, PROCEED to Event 2.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 2 Page 11 of 32 Event

Description:

Feed Header Pressure Transmitter (PT-508) Fails High Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 2 (Key 2).

- RX18, Feed Header Pressure Transmitter (PT-508) Fails High.

Indications Available:

Plant Computer Alarm for high Feed Header pressure 1-PI-508, FWP DISCH HDR PRESS indication fails high BOP RESPOND to Annunciator Alarm Procedures.

BOP RECOGNIZE Feed Header Pressure 1-PT-508 transmitter failure.

Examiner Note: Feed header pressure failing high will cause Feedwater Pump speed to lower.

The Main Feedwater Pump Master Speed Controller will remain in MANUAL for the remainder of the scenario.

DIRECT performance of ABN-709, Steam Line Pressure, Steam Header US Pressure, Turbine 1st Stage Pressure, and Feed Header Pressure Instrument Malfunction, Section 5.0.

Section 5.3 BOP 1. PLACE 1-SK-509A, FWPT Master Speed Controller in MANUAL.

2. ADJUST 1-SK-509A, FWPT Master Speed Controller to MAINTAIN BOP P between FWP Discharge Pressure and Steam Line Pressure.

From 20% to 100% power, RAMP P from 80 PSIG to 181 PSIG.

Simulator Operator: If contacted as prompt team acknowledge request to repair PT-508.

US 3. INITIATE a Condition Report per STA-421.

Examiner Note: Feed header pressure transmitter PT-508 will remain failed for the remainder of the scenario. The Main Feedwater Pump Master Speed Controller will remain in MANUAL for the remainder of the scenario. Step 5.3.4 will NOT be performed.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 2 Page 12 of 32 Event

Description:

Feed Header Pressure Transmitter (PT-508) Fails High Time Position Applicants Actions or Behavior

4. WHEN repairs are complete, THEN PLACE 1-SK-509A, FWP MASTER SPD CTRL in - AUTO as follows:

US a. ENSURE differential pressure appropriate for plant conditions.

b. PLACE 1-SK-509A in - AUTO

c. VERIFY correct differential pressure automatically maintained.

When control of Feedwater is restored, or at Lead Examiner discretion, PROCEED to Event 3.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 3 Page 13 of 32 Event

Description:

Main Turbine 1st Stage Pressure (PT-505A) Fails Low Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 3 (Key 3).

- RX09A, Main Turbine 1st Stage Pressure Transmitter (PT-505) Fails Low.

Indications Available:

6D-1.10 - AVE TAVE TREF DEV PCIP-2.4 - LO TURB PWR ROD WITHDRW BLK C-5 1-PI-505 - Turbine Impulse Pressure Channel I indication fails low 1-TI-412A - Ave TAVE TREF Deviation indication to maximum RO/BOP RESPOND to Annunciator Alarm Procedures.

RECOGNIZE Control Rods INSERTING due to Turbine Impulse Pressure RO/BOP Instrument failure.

RO/BOP REPORT PT-505, Turbine Impulse Pressure Channel I has failed low.

DIRECT implementation of ABN-709, Steam Line Pressure, Steam Header US Pressure, Turbine 1st Stage Pressure, and Feed Header Pressure Instrument Malfunction.

Section 4.3 RO 1. PLACE 1/1-RBSS Control Rod Bank Select Switch in MANUAL.

BOP 2. VERIFY Steam Dumps - CLOSED WITH NO OPEN DEMAND.

2. RNO - IF Steam Dump operation NOT required, THEN PLACE at least one Steam Dump Interlock Select Switch - OFF.

43/1-SDA, STM DMP INTRLK SELECT.

43/1-SDB, STM DMP INTRLK SELECT.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 3 Page 14 of 32 Event

Description:

Main Turbine 1st Stage Pressure (PT-505A) Fails Low Time Position Applicants Actions or Behavior

3. RESTORE steam dump availability by placing Steam Dumps in STM RO PRESS Mode per Attachment 7.

Examiner Note: ABN-709 Attachment 7 steps are after the steps for section 4.0 (next page)

4. TRANSFER 1-PS-505Z, TURB IMP PRESS CHAN SELECT to PT-RO 506.

Examiner Note: The crew will conduct a Reactivity Brief and execute a Reactivity Plan to restore TAVE to TREF.

RO 5. ENSURE TAVE within 1ºF of TREF.

RO 6. PLACE 1/1-RBSS, CONTROL ROD BANK SELECT Switch in AUTO.

US/RO 7. CHECK Reactor Plant in - MODE 1.

US/BOP 8. CHECK Turbine Power - GREATER THAN 10% POWER.

9. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , VERIFY PCIP Window 4.6 - TURB 10% PWR P-13, US IN PROPER STATE for existing plant conditions (DARK). - YES CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 3 Page 15 of 32 Event

Description:

Main Turbine 1st Stage Pressure (PT-505A) Fails Low Time Position Applicants Actions or Behavior

10. VERIFY PCIP Window 1.3 - AMSAC BLK TURB < 40% PWR C US IN PROPER STATE (DARK) for actual Turbine power. - NO US/BOP 10. RNO - IF AMSAC actuation blocked AND turbine power >40%, THEN ENSURE Automatic Actions of ALB-9B 3.7, AMSAC ACT TURB TRIP as necessary.

US 11. INITIATE a Condition Report per STA-421.

US EVALUATE Technical Specifications.

LCO 3.3.1.T, Reactor Trip System Instrumentation.

(Function 18.f, Turbine 1st Stage Pressure P-13)

CONDITION T - One or more required channels inoperable.

ACTION T.1 - Verify interlock is in required state for existing unit conditions within one (1) hour, OR

ACTION T.2 - Be in MODE 2 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

Examiner Note: The following six steps are from ABN-709, Attachment 7, Transferring Steam Dumps and may be performed using the Control Board Job Aid.

BOP 1. ENSURE 1-PK-507, STM DMP PRESS CTRL is in MANUAL.

2. MATCH 1-PK-507, STM DUMP PRESS CTRL demand to current BOP Steam Dump Valve position.

3. VERIFY 1-PCIP, Window 1.4 - CNDSR AVAIL STM DMP ARMED C-9 BOP is ON.

BOP 4. PLACE 43/1-SD, STM DMP MODE SELECT in STM PRESS.

BOP 5. ENSURE both STM DMP INTLK SELECT switches are ON.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 3 Page 16 of 32 Event

Description:

Main Turbine 1st Stage Pressure (PT-505A) Fails Low Time Position Applicants Actions or Behavior

6. IF desired to control Steam Dumps in AUTO, THEN PERFORM the following:

a. VERIFY 1-PI-507, MS HDR PRESS indicates current MSL BOP pressure.

b. ENSURE 1-PK-507, STM DMP PRESS CTRL set to control at 1092 psig for "no load" conditions (Pot setting 6.86).

c. PLACE 1-PK-507, STM DMP PRESS CTRL in AUTO.

When TS are completed or at Lead Examiner discretion, PROCEED to Event 4 CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 4 Page 17 of 32 Event

Description:

Neutron Detector Well Fan #9 trips on motor overload Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 4 (Key 4)

- Neutron Detector well fan #9 trips Indications Available:

CB03-2.1 CNTMT FN MASTER TRIP BOP RESPOND to Annunciator Alarm Procedures.

BOP RECOGNIZE Neutron Detector well fan #9 tripped Examiner Note: ALM-0031A - 2.1 steps begin here

1. DETERMINE affected fan from the associated handswitch light BOP indication.

1-HS-5435, NEUT DET WELL FN CLR FN 9 & DMPR Examiner Note: The steps of SOP-801A, Containment Ventilation System, are only to place the non-affected fan to start.

BOP 2. START an alternate fan, as required per SOP-801A.

BOP 3. PLACE affected fan handswitch in Pull Out OR Stop, as available.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 4 Page 18 of 32 Event

Description:

Neutron Detector Well Fan #9 trips on motor overload Time Position Applicants Actions or Behavior Simulator Operator: When contacted to investigate the fan trip wait 2 minutes and report back the breaker has tripped on motor overload.

4. DISPATCH an operator to affected fan breaker to determine cause of RO/BOP trip.

5. WHEN conditions permit, THEN PERFORM a Containment entry per US STA-620 to check the fan for signs of damage (smoke, acrid odor, overheating).

6. CORRECT the condition OR INITIATE a CR per STA-421, as US applicable.

When the plant is stable or at Lead Examiner discretion, PROCEED to Event 5 CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5 Page 19 of 32 Event

Description:

A MFP recirc valve opens Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 5 (Key 5).

- A MFP Recirc valve opens Indications Available:

ALL S/G levels lowering FWP A/B RECIRC VLV NOT CLOSED (7B-4.8)

SG 1 STM & FW FLO MISMATCH (8A-1.8)

SG 2 STM & FW FLO MISMATCH (8A-2.8)

SG 3 STM & FW FLO MISMATCH (8A-3.8)

SG 4 STM & FW FLO MISMATCH (8A-4.8)

SG 1 LVL DEV (8A-1.12)

SG 2 LVL DEV (8A-2.12)

SG 3 LVL DEV (8A-3.12)

SG 4 LVL DEV (8A-4.12)

BOP RESPOND to Annunciator Alarm Procedures.

BOP RECOGNIZE A MFP Recirc valve is open AND MFP speed control is in MANUAL. Raises MFP speed to restore S/G levels.

Direct entry into ABN-302, Feedwater, Condensate, Heater Drain System US Malfunction.

Section 11.3 RO 1. Ensure 1/u-RBSS, CONTROL ROD BANK SELECT in AUTO Examiner Note: 1-PV-2286 is Red tagged and cannot be opened. The crew will skip this step.

BOP 2. Ensure u-HS-2286, LP FW HTR BYP VLV - OPEN - NO Examiner Note: Turbine power is already 600 MW so the next step will not be performed BOP 3. Reduce Turbine Power to 700 MW CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5 Page 20 of 32 Event

Description:

A MFP recirc valve opens Time Position Applicants Actions or Behavior Simulator Operator: When contacted to isolate the A MFP recirc valve after 2 minutes DELETE MALFUNCTION FW06A Report back that the valve has been manually isolated by closing FW-0023.

4. Dispatch Operator to isolate affected recirc valve:

RO/BOP

u-FV-2289, FWP A RECIRC VALVE

u-FV-2290, FWP B RECIRC VALVE

5. Verify Main Feedwater pump suction pressure - GREATER THAN 200 PSIG BOP

u-PI-2295, FWP A SUCT PRESS

u-PI-2297, FWP B SUCT PRESS

6. Verify the following:

RO/US a. Rods - ABOVE ROD INSERTION LIMIT

b. Flux - (AFD) WITHIN LIMITS

7. Verify Reactor Power change - LESS THAN 15% RTP WITHIN ONE US HOUR.

Examiner Note: The following steps will not be performed as power is unchanged for this event

8. Notify QSE Generation Controller and update GAPS to Create US Current Condition for the down power.

Simulator Operator: When contacted as a member of plant management inform the crew that continued operation of the A MFP with its recirc flowpath isolated at the current power is desired.

9. Plant Management has determined continued operation of the US Feedwater pump is required with recirc flowpath isolated.

US 10. Restore power to level specified by Shift Manager.

11. WHEN steam dumps have closed, THEN reset C-7, if armed.

BOP

43/u-SD, STM DMP MODE SELECT CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 5 Page 21 of 32 Event

Description:

A MFP recirc valve opens Time Position Applicants Actions or Behavior US 12. Initiate equipment repairs per STA-606.

13. Close u-HS-2286, LP FW HTR BYP VLV by performing Section 7.0 of BOP this procedure.

US 14. Return to procedure and step in effect.

When the plant is stabilized or at Lead Examiner discretion, PROCEED to Event 6 CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 6 Page 22 of 32 Event

Description:

Loss of XST1 Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 6 (Key 6).

- Loss of XST1 transformer Indications Available:

138 KV XFMR XST1 TRBL (CB14-1.1) 138 KV XFMR XST1 LOR TRIP (CB14-3.1) 138 KV XFMR XST1 VOLT LO (CB14-3.2)

BOP RESPOND to Annunciator Alarm Procedures.

RO/BOP RECOGNIZE the loss of XST1 transformer and Direct entry into ABN-601, RESPONSE TO A 138/345 KV SYSTEM US MALFUNCTION Examiner Note: The alarms that are received will send the crew to the ABN however they may use the ALMs to start the recovery. The ALM will direct the US to the TS.

Section 2.3

1. Determine AC Power Status:

US/BOP a. Check the Unit - IN MODES 1, 2, 3 OR 4 - YES

b. Check 6.9 KV Safeguard Buses - AT LEAST ONE ENERGIZED -

YES

c. Check Unit 6.9 KV Non-Safeguard Buses - ALL REMAINED US/BOP ENERGIZED WITH LOADS CONNECTED TO THE BUS - YES

d. GO TO Step 4

4. Check Switchyard Bus Status - ALL ENERGIZED

V-E BUS, 345 KV E. BUS VOLT (CB-12) - BETWEEN 340 KV and 361 KV BOP

V-W BUS, 345 KV W. BUS VOLT (CB-12) - BETWEEN 340 KV and 361 KV

V/ST1, INCOMING 138 KV XFMR FDR VOLT (CB-12) -

BETWEEN 135 KV and 144 KV (DE-ENERGIZED)

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 6 Page 23 of 32 Event

Description:

Loss of XST1 Time Position Applicants Actions or Behavior

5. Monitor Blackout Sequencer Status:

a. Affected bus - ENERGIZED - YES BOP b. Verify Blackout Sequencer - OPERATED OUTPUT-STEP TIME lights - ALL LIT - NO Automatic lockouts AL light - LIT - NO US 5. RNO - GO TO Step 6.

6. Check Transformer XST1 Status:

BOP a. V/ST1, STARTUP XFMR XST1 138 KV FDR VOLT (CB-12) -

BETWEEN 135 KV and 144 KV - NO US 6. RNO - INITIATE Attachment 2, Restoration of XST1.

Examiner Note: ABN-601, RESPONSE TO A 138/345 KV SYSTEM MALFUNCTION, Attachment 2 steps begin here

1. Determine the origin for the loss of power by performing the following:

US

Contact the Switchyard Coordinator to provide assistance in determining the transformer status.

Simulator Operator: When contacted as the Switchyard Coordinator inform the US that you will take the lead for the rest of Attachment 2.

Examiner Note: ABN-601 Steps 7, 8 & 9 relate to unaffected transformers and may be N/Ad by the SRO or read and verified.

BOP 10. Verify Diesel Generators - NOT RUNNING BOP 11. Verify 6.9KV Bux XA1 - ENERGIZED Simulator Operator: If contacted as the Shift Manager to have Unit 2 perform SR 3.8.1.1, state that the Extra RO will perform the SR.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 6 Page 24 of 32 Event

Description:

Loss of XST1 Time Position Applicants Actions or Behavior US 12. Refer to the appropriate TS:

MODES 1, 2, 3, OR 4 - Section 3.8.1 AC Sources - Operating

Condition A is applicable This is a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months spec to perform SR 3.8.1.1 - Verification of offsite sources 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore power When the plant is stabilized or at Lead Examiner discretion, PROCEED to Event 7 CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7&8 Page 25 of 32 Event

Description:

Loss of offsite power, failure of 1-01 EDG to start Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 7 (Key 7).

- Loss of offsite power Indications Available:

Reactor Trip Turbine Trip Multiple Annunciators CREW RESPOND to Annunciator Alarm Procedures.

RO/BOP RECOGNIZE the Reactor Trip and perform Immediate Actions US Direct entry into EOP-0.0A, Reactor Trip or Safety Injection RO 1. VERIFY Reactor Trip:

a. Verify the following:

VERIFY Reactor Trip Breakers - OPEN.

VERIFY Neutron flux - DECREASING.

b. VERIFY all Control Rod Position Rod Bottom Lights - ON. - NO BOP 2. VERIFY Turbine Trip:

VERIFY all HP Turbine Stop Valves - CLOSED.

Examiner Note: The EDG 1-01 will fail to start and cannot be started due to an air start failure Simulator Operator: If contacted to investigate the failure of the EDG 1-01 report back that the diesel will not start and an air start failure alarm is locked in BOP 3. VERIFY Power to AC Safeguards Buses:

a. VERIFY AC Safeguards Buses - AT LEAST ONE ENERGIZED.

b. VERIFY both AC Safeguards Buses - ENERGIZED. - NO

b. RNO - Restore power to de-energized AC safeguards bus per ABN-601, RESPONSE TO A 138/345 KV SYSTEM MALFUNCTION or ABN-602, RESPONSE TO A 6900/480 VOLT SYSTEM MALFUNCTION when time permits.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7&8 Page 26 of 32 Event

Description:

Loss of offsite power, failure of 1-01 EDG to start Time Position Applicants Actions or Behavior RO 4. CHECK SI status:

a. CHECK if SI is actuated.

o VERIFY SI indicated on the First Out Annunciator Panel 1-ALB-6C.

o VERIFY SI Actuated blue status light - ON. - NO RO 4. a. RNO - Check if SI is required:

o Steam Line Pressure less than 610 psig. - NO o Pressurizer Pressure less than 1820 psig. - NO o Containment Pressure greater than 3.0 psig. - NO o IF SI is NOT required, THEN go to EOS-0.1A, REACTOR TRIP RESPONSE, Step 1.

Examiner Note: Emergency Boration is required since all DRPI lights are DARK. This is on Attachment 1.A of both EOP-0.0A and EOS-0.1A. The steps are listed as if this is going to be performed in EOS-0.1A since the transition to this procedure will take place very quickly from EOP-0.0A.

Examiner Note: EOS-0.1A, Reactor Trip Response, Attachment 1.A steps begin here with a branching to ABN-107, Emergency Boration. There are no other EOS-0.1A steps listed because the crew will transition out of this procedure prior to taking any steps other than Attachment 1.A.2 actions.

Examiner Note: Based on the above guidance the operator will use Attachment 1 which is an Operator Aid.

Examiner Note: ABN-107, Emergency Boration, Attachment 1, steps begin here CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 7&8 Page 27 of 32 Event

Description:

Loss of offsite power, failure of 1-01 EDG to start Time Position Applicants Actions or Behavior RO 1. Ensure a charging pump is running:

1/u-APCH1, CCP 1 - NO

1/u-APCH2, CCP 2 - YES

1/u-APPD, PDP RO 2. Start a boric acid transfer pump:

1/u-APBA1, BA XFER PMP 1 - AUTO (AFTER START) - NO

1/u-APBA2, BA XFER PMP 2 - AUTO (AFTER START) - YES CRITICAL TASK Initiate Emergency Boration prior to exiting EOS-0.1A, Reactor Trip STATEMENT Response.

CT-1 RO 3. Open 1/u-8104, EMER BORATE VLV Examiner Note: When the RO opens the emergency borate valve 1/1-8104 it will auto insert event 9 (60 second delay) for the loss of all AFW. This will give the crew a RED path on Heat Sink.

RO 4. Verify flow on u-FI-183A, EMER BORATE FLO RO 5. Verify flow on u-FI-121A, CHRG FLOW

6. IF EMER BORATE FLOW OR CHRG FLOW can NOT be verified, RO THEN initiate Emergency Boration Flow per another method of ABN-107.

7. WHEN desired to terminate emergency boration (Reference RO Attachment 7 of ABN-107), THEN GO TO Step 8 of ABN-107.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 9 Page 28 of 32 Event

Description:

Loss of Heat Sink Time Position Applicants Actions or Behavior Examiner Note: FRH-0.1A, Response to Loss of Heat Sink, steps begin here

1. Check If Secondary Heat Sink Is Required:

a. RCS pressure - GREATER THAN ANY NON-FAULTED SG US PRESSURE - YES

b. RCS temperature - GREATER THAN 350°F - YES RO 2. Check CCP Status - BOTH AVAILABLE - NO Examiner Note: There will be no power to the A train PORV block valve but since it was open when it lost power it will still be open when the crew opens the associated PORV RO 2. RNO - Immediately perform the following:

a. STOP ALL RCPs.

b. Verify power to PRZR PORV block valves - AVAILABLE

c. Go to Step 13. OBSERVE CAUTION PRIOR TO STEP 13.

RO 13. Actuate SI CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 9 Page 29 of 32 Event

Description:

Loss of Heat Sink Time Position Applicants Actions or Behavior RO 14. Verify RCS Feed Path:

a. Check CCP SI flow indicator - CHECK FOR FLOW

b. Check SI pumps - BOTH RUNNING - NO

14. b. RNO - Perform the following:

1) Manually start pump(s) and align valves as necessary.

2) IF either of the following RCS feed paths exists, THEN go to RO Step 15.

CCPs - BOTH INJECTING - NO

AT LEAST ONE CCP INJECTING AND ONE SI PUMP RUNNING - YES BOP 15. Check If Diesels Should Be Emergency Started:

a. Check diesel generator(s) - RUNNING - DG 1-02 Only

b. Place D/G EMER STOP/START handswitch(es) in START.

RO 16. Reset SI.

BOP 17. Reset SI Sequencers.

BOP 18. Reset Containment Isolation Phase A And Phase B.

BOP 19. Reset Containment Spray Signal.

BOP 20. Establish Instrument Air And Nitrogen To Containment:

a. Establish instrument air:

1) Verify air compressor running.

Establish instrument air to containment.

b. Establish nitrogen:

1) Verify ACCUM 14 VENT CTRL, 1-HC-943 - CLOSED

2) Open SI/PORV ACCUM N2 ISOL VLV, 1/1-8880.

Examiner Note: There will be no power to the A train PORV block valve but since it was open when it lost power it will still be open when the crew opens the associated PORV CRITICAL TASK Establish an RCS bleed and feed path prior to exiting FRH-0.1A, STATEMENT Response to a Loss of Secondary Heat Sink.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 9 Page 30 of 32 Event

Description:

Loss of Heat Sink Time Position Applicants Actions or Behavior CT-2 RO 21. Establish RCS Bleed Path:

a. Verify power to PRZR PORV block valves - AVAILABLE

b. Verify PRZR PORV block valves - BOTH OPEN

c. Open PRZR PORVs.

RO 22. Verify Adequate RCS Bleed Path:

PRZR PORVs - BOTH OPEN

PRZR PORV block valves- BOTH OPEN US/BOP 23. Verify Steps 1 through 8 of EOP-0.0A, REACTOR TRIP OR SAFETY INJECTION, Have Been Completed.

RO/BOP 24. Maintain RCS Heat Removal:

Maintain ECCS flow.

Maintain PRZR PORVs - BOTH OPEN BOP 25. Check RWST Level - GREATER THAN LO-LO LEVEL After the bleed and feed is initiated, TERMINATE the scenario.

CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

Scenario Event Description NRC Scenario 2

2016 NRC Scenario 2

Rev. 1

Initialize to IC-16

Setup MDAFWP 1-02 in Pull-Out - Breaker Deenergized IRF FWR021 f: 0

1-PV-2286 Isolated for Repairs IOR LOFWHS2286_1 f: 0 IOR LOFWHS2286_2 f:0 IRF FWR056 f:0

Event 1 - PRZ LVL [LT-459] Fails Low IMF RX05A f: 0 k:1

Event 2 - Main Feedwater Header Pressure [PT-508] Fails High

PT-508 Fails High IMF RX18 f: 1500 k:2

Event 3 - Main Turbine 1st Stage Pressure [PT-505A] Fails Low

PT-505A Fails Low IMF RX09A f: 0 k:3

Event 4 - Neutron Detector Well FN 9 Motor Overload IMF CH03 f: 1 k:4

Event 5 - FWP A Recirc Valve Fails Open IMF FW06A f: 100 r:10 k:5

Local Isolation of FV-2289 by FW-0023

Delete Malfunction FW06A IOR LOFWZL2289_1 f: 0 k:5 d:120 IOR LOFWZL2289_2 f:1 k:5 d:120 IOR LOANAN7B_32 f:1 k:5 d:120

Event 6 - Loss of XST1 IMF ED02 f: 1 k:6

Event 7 - Loss of Offsite Power/DG 1-01 Air Start Failure

LOOP IMF ED01 f: 1 k:7

DG 1-01 Air Start Failure IMF EG06A f: 1

Event 8 - Emergency Boration for Loss of DRPI

Event 9 - TDAFWP Trip if Running (FRH Entry)

TDAFWP Trip after emergency borate started

{DICVHS8104.Value=2} IMF FW09A f:1 d:60 CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1

GUARDED EQUIPMENT MANAGEMENT (GEM) SIGN POSTING LOG REASON FOR POSTING MD AFWP 1-02 INOPERABLE Component to be Nomenclature Posting Installed Posting Checked Posting Removed Posted Initial Initial Initial MD AFWP 1 => CB / 830 / X-135 1-HS-2450A JGR RB AUXILIARY FEEDWATER PUMP 1-01 MOTOR 1APMD1 BREAKER => SG / 810 / 1-083 JGR RB MOTOR DRIVEN AUXILIARY FEEDWATER S1-16 PUMP 1-01 ROOM => SG / 790 / 1-072 JGR RB Authorized By Joe UnitSupervisor Date Today Posting Removal Authorized By Date Open Narrative Log Entry Entered Open Narrative Log Entry Closed Comments: This form is not maintained. Verify correct items Guarded per STI-600.01 prior to use.

STI-600.01-1 Page 1 of 1 REFERENCE USE Rev. 0

Appendix D Scenario Outline Form ES-D-1 Facility: CPNPP 1 & 2 Scenario No.: 3 Op Test No.: July 2016 NRC Examiners: Operators:

Initial Conditions: 100% power MOL - RCS Boron is 924 ppm Turnover: Maintain steady-state power conditions.

Critical Tasks: CT-1 Manually Trip Reactor due to Failure to Automatically Trip prior to exiting EOP-0.0A, Reactor Trip or Safety Injection.

CT-2 Identify and Isolate the Ruptured Steam Generator Prior to Commencing an Operator Induced Cooldown per EOP-3.0A, Steam Generator Tube Rupture.

Event No. Malf. No. Event Type* Event Description I (RO, SRO) Cold Leg Loop 4 NR Temperature Transmitter Failure (TE-441B) 1 RP05D TS (SRO) Fails High I (BOP, SRO) Steam Generator (1-01) Steam Line Pressure Instrument (PT-514) 2 RP03A TS (SRO) Fails Low.

3 Override C (RO, SRO) Letdown HX Outlet Flow Controller Failure (TK-130) Fails Low C (BOP, SRO) 4 FW22 Station Service Water Pump 1-01 Trip TS (SRO) 5 TC08C C (BOP, SRO) High Pressure Turbine Stop Valve #3 (UV-2430A) Fails Closed 6 SG02C M (RO, BOP, SRO) Steam Generator 1-03 Tube Rupture 7 RP15E C (BOP, SRO) Automatic Reactor Trip Failure, Manual Trip from 1B3 and 1B4 8 MS08C C (RO, SRO) Steam Generator 1-03 MSIV Fails to Close

(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) 5 Abnormal events (2-4) 1 Major transients (1-2) 1 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3)

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Scenario Event Description NRC Scenario 3 SCENARIO

SUMMARY

NRC 3 Event 1 (Key 1)

The crew will assume the watch at 100% power with no scheduled activities per IPO-003A, Power Operations.

The first event is a failure high of a Reactor Coolant System Loop 4 Narrow Range Temperature element. Crew actions are per ABN-704, Tc/N-16 Instrumentation Malfunction, Section 2.0. Section 2.0 is designated for Tc/N-16 Instrumentation Malfunction. Actions include placing the Control Rods in MANUAL and defeating the failed channel. Control Rods will be restored in Manual to their pre-failure position and remain in Manual until Technical Specification actions are complete. The SRO will refer to Technical Specification LCO 3.3.1, Reactor Trip System Instrumentation (Functions 6 & 7); Condition E, One channel inoperable.

Event 2 (Key 2)

The next event is a failure low of Main Steam Line 1 Pressure Instrument, PT-514. Crew actions are per ABN-709, Steam Line Pressure, Steam Header Pressure, Turbine 1st-Stage Pressure and Feed Header Pressure Instrument Malfunction, Section 2.0. Section 2.0 is designated for Steam Line Pressure Malfunction. The crew must manually control Steam Generator level, transfer to an Alternate Steam Flow Channel, and restore Steam Generator (SG) Feedwater Flow Control to AUTO. The SRO will refer to Technical Specification LCO 3.3.2, Engineered Safety Feature System (ESFAS) Instrumentation (Functions 1.e & 4.d); Condition D, One channel inoperable.

Event 3 (Key 3)

The next event is a failure of the Letdown Heat Exchanger Outlet Flow Controller, TK-130. The controller output will fail to zero demand and cause TCV-4646, LTDN HX OUT TEMP CTRL valve to close. This will result in Letdown Heat Exchanger High temperature alarms and Letdown flow to divert to the VCT on high temperature.

The crew will respond per the ALM, take manual control of TK-130 and raise demand to establish Letdown Heat Exchanger Outlet temperature to approximately 95°F.

Event 4 (Key 4)

The next event is a trip of Station Service Water Pump 1-01. Crew actions are per ABN-501, Station Service Water System Malfunction, Section 2.0. Section 2.0 is designated for Station Service Water Pump Trip. Various equipment controls, as directed by ABN-501, are placed in PULL-OUT to prevent starting with no cooling water available. The SRO will refer to Technical Specification LCO 3.7.8, Station Service Water System; Condition B, One SSWS Train inoperable. The SRO will also refer to Technical Specification LCO 3.8.1, AC Sources -

Operating; Condition B, One DG inoperable as DG 1-01 must be placed in PULL-OUT upon the loss of Train A Station Service Water.

Event 5 (Key 5)

The next event is High Pressure Turbine Stop Valve #3 fails closed. The crew will enter ABN-401, Main Turbine Malfunction, Section 9.0. Section 9.0 is designated for Inadvertent Closure of an HP or LP Stop or Control Valve.

Actions include placing rod control in Auto to allow the rod control system to respond to the plant transient and reducing turbine load to allow all operable HP Control Valves to come off their full open seat.

Event 6 - (Key 6)

The major event is a Tube Rupture on SG 1-03. The Crew will diagnose the Tube Rupture due to multiple Radiation alarms and lowering Pressurizer Pressure and Level. The crew will enter EOP-0.0A, Reactor Trip or Safety Injection and transition to EOP-3.0A, Steam Generator Tube Rupture. A maximum rate RCS cooldown to a target CET temperature as determined in EOP-3.0A will be conducted.

Event 7 - CT-1 (Auto)

The Reactor will be manually tripped and Safety Injection manually initiated. The Reactor will fail to trip from both handswitches at CB-07 and CB-10. The crew will then perform CT-1, Manually Trip Reactor due to Failure to Automatically Trip prior to exiting EOP-0.0A, Reactor Trip or Safety Injection. The Reactor must be manually tripped by momentarily de-energizing 480V Normal Switchgear 1B3 and 1B4 to de-energize the Rod Drive MG Sets.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Scenario Event Description NRC Scenario 3 Event 8 (Auto) CT-2 During performance of CT-2, Identify and Isolate the Ruptured Steam Generator Prior to Commencing an Operator Induced Cooldown per EOP-3.0A, Steam Generator Tube Rupture. SG 1-03 MSIV will fail to close. The crew will close all remaining MSIVs, disable the Steam Dumps, and close the Main Steam to Auxiliary Steam Supply Valve.

The RCS cooldown will then be conducted via the intact SG ARVs to atmosphere.

Termination Criteria This scenario is terminated when the target CET Temperature is reached during the RCS cooldown in accordance with EOP-3.0A, Steam Generator Tube Rupture.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Scenario Event Description NRC Scenario 3 Risk Significance Determination Risk Significance Event Guidance Failure of risk important system Event 4 - Station Service Water ABN-501; DBD-ME-011 - Initial prior to Reactor Trip Pump Trip operator action to place the affected DG Emergency Stop/Start handswitch in PULL-OUT to remove the DG from service as it will ONLY operate for 1 minute under load, without service water cooling flow, before damage will occur.

Risk significant operator actions Event 7 - Manually tripping the FSAR 15.8 - The worst common Reactor by momentarily de- mode failure which is postulated energizing 1B3 and 1B4 to occur is the failure to trip the reactor after an anticipated transient has occurred.

Event 8 - Closing all intact SG FSAR 15.6.3.2 - The closing of MSIVs upon failure of the all intact SG MSIVs falls in line ruptured SG MSIV to close with the conservative analysis of the postulated SGTR which assumes a loss of offsite power.

Thus, a release of steam from the secondary system occurs due to the loss of steam dump capability and the subsequent venting to the atmosphere through the ARVs.

(1)

Risk significant core damage Events 5 - Steam Generator STI-214.01 TCA-1.9 - Manual sequence Tube Rupture Actions to Mitigate Effects of a Steam Generator Tube Rupture:

1) TDAFWP flow stopped (excessive AFW flow) within 3 minutes of reactor trip. 2) Identify and Isolate ruptured SG within 13 minutes after initiation of SGTR. 3) Initiate maximum rate cooldown within 5 minutes after isolation of ruptured SG. 4)

Initiate RCS depressurization with PORVs within 2 minutes after completion of RCS cooldown. 5) Secure ECCS within 2 minutes after completion of RCS depressurization.

(1) Crew manning for Initial License Examination less than Timed Operator Action validation constraints CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Scenario Event Description NRC Scenario 3 Critical Task Determination Measurable Safety Performance Critical Task Cueing Performance Significance Feedback Indicators CT Manually Recognize a failure Procedural direction at The operator will De-energizing the Trip Reactor due to or an incorrect EOP-0.0A Step 1 to attempt to Rod Drive MG sets Failure to automatic determine if a reactor trip manually trip the will result in a loss Automatically Trip actuation of an has occurred. Position Reactor with the of power to the Rod prior to exiting ESF system or indication of the Reactor handswitches on Drive Mechanisms EOP-0.0A, Reactor component. FSAR Trip breakers and both CB-07 and and the Control Trip or Safety 7.1.2.1 Reactor Power, CB-10; however, Rods will insert into Injection Annunciator First out the Reactor will the core. Reactor alarms. fail to trip. The Trip Breakers will operator will then remain closed, momentarily neutron flux will deenergize the lower and rod 480V normal bottom lights will be switchgear 1B3 lit.

and 1B4 to secure power to the Rod Drive MG sets.

CT Identify and Take one or more Procedurally driven from The operator will SG pressure Isolate the actions that would EOP-3.0A, to identify attempt close the increasing, AFW Ruptured Steam prevent a and isolate a ruptured ruptured SG MSIV flow reduced to Generator Prior to challenge to plant SG. Indications include from the control zero and valve Commencing an safety. STI-214.01, MSL Radiation alarms room, however, position indications.

Operator Induced TCA-1.9; FSAR and SG level. the MSIV will fail Cooldown per EOP- 15.6.3.1.1; WCAP- to close and all 3.0A, Steam 16871-P, Section other MSIVs must Generator Tube 6.4; DBD-ME-027 be closed. The Rupture. MSIV will be locally closed in the field. The operator will stop feeding the SG once sufficient level to cover the tubes is available.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Scenario Event Description NRC Scenario 3 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP Initialize to IC-18 and 2016 NRC Scenario 3.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER 7 RP15E Reactor Trip Breakers Jammed Closed - All FAIL K0 8 MS08C SG 1-03 MSIV Fails to Close FAIL K0 1 RP05D Loop 4 Cold Leg Temperature (TE-441B) Failure 630°F K1 2 RP03A MSL 1 Steam Pressure (PT-514) Failure 0 PSIG K2 Letdown HX Outlet Flow Controller Failure 3 Override f:10 K3 (TK-130) Fails Low NOTE: See Scenario file on last page for all event overrides.

4 SW01A SSW Pump 1-01 Trip TRIP K4 4 CVR06 CCP 1-02 Aux Lube Oil Pump to Auto AUTO K11 4 CVR05 CCP 1-01 Aux Lube Oil Pump to Off OFF K12 5 TC08C High Pressure Stop Valve #3 Fails Closed CLOSE K5 6 SG02C SG 1-03 Tube Rupture 1 Tube 1 Tube K6 7 RP15E Reactor Trip Breakers Jammed Closed - All FAIL K0 RPR112 7 RPR113 Reactor Trip Breakers Locally Opened OPEN K13 8 MS08C SG 1-03 MSIV Fails to Close OPEN K0 CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Scenario Event Description NRC Scenario 3 Simulator Operator: INITIALIZE to IC-18 and 2016 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 (924 ppm).

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.

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 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 1 Page 8 of 37 Event

Description:

NR Cold Leg Loop 4 Temperature Instrument failure Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 1 (Key 1).

- NR Cold Leg Loop 4 TI (TE-441B) fails high.

Indications Available:

6D-1.10 - AVE TAVE TREF DEV 6D-2.10 - AVE TAVE HI 6D-3.14 - 1 OF 4 OT N16 ROD STOP & TURB RUNBACK 1-TI-441A, CL 4 TEMP (NR) CHAN IV indication failed high 1-TI-442, RC LOOP 4 TAVE CHAN IV indication failed high RO RESPOND to Annunciator Alarm Procedures.

RO RECOGNIZE Control Rods inserting due to TCOLD failed high.

DIRECT performance of ABN-704, Tc / N-16 Instrumentation Malfunction, US Section 2.0.

Examiner Note: The RO may place 1-FK-121, Charging Flow Controller, in MANUAL to maintain PZR level on setpoint.

PLACE 1/1-RBSS, CONTROL ROD BANK SELECT Switch in MANUAL.

RO

[Step 2.3.1]

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 1 Page 9 of 37 Event

Description:

NR Cold Leg Loop 4 Temperature Instrument failure Time Position Applicants Actions or Behavior RO SELECT LOOP 4 on 1-TS-412T, TAVE Channel Defeat. [Step 2.3.2]

VERIFY Steam Dump System is NOT actuated and NOT armed.

RO/BOP

[Step 2.3.3]

Examiner Note: The crew will conduct a Reactivity Brief and execute a Reactivity Plan to restore TAVE to TREF.

US/RO RESTORE TAVE to within 1°F of TREF. [Step 2.3.4]

SELECT LOOP 4 on 1/1-JS-411E, N16 Power Channel Defeat.

RO/BOP

[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 (Functions 6 & 7).

CONDITION E - One channel inoperable.

ACTION E.1 - Place channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , OR ACTION E.2 - Be in MODE 3 within 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months .

US INITIATE a work request per STA-606. [Step 2.3.12]

US INITIATE a Condition Report per STA-421. [Step 2.3.13]

When Technical Specifications are addressed, or at Lead Examiner discretion, proceed to Event 2.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2 Page 10 of 37 Event

Description:

Steam Generator 1-01 Steam Line Pressure Instrument Failure Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 2 (Key 2).

- RP03A, SG 1-01 Steam Pressure Transmitter PT-514 fails low.

Indications Available:

8A-1.7 - MSL 1 OF 3 PRESS LO 8A-1.8 - SG1 STM & FW FLO MISMATCH 8A-1.16 - SG 1 1 OF 3 PRESS RATE HI Feedwater flow lowering Feedwater pumps lowering in speed BOP RESPOND to Annunciator Alarm Procedures.

DIRECT performance of ABN-709, STM LINE, STM HDR, & TURB 1st US STAGE PRESS. & FEED HDR PRESS. INSTR MALFUNCTION, Section 2.0, Steam Line Pressure Instrument Malfunction.

CHECK ONE Main Steamline Pressure Channel indicating - GREATER BOP THAN 60 psig difference between remaining channels. [Step 2.3.1]

DETERMINE 1-PI-514A indicating approximately 990 psig LOWER than remaining channels. [Step 2.3.1]

VERIFY Steam Generator Atmospheric Relief Valves - CLOSED:

BOP

[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 AND The following channels are indicating - NORMAL: [Step 2.3.2]

1-PI-2325, MSL 1 PRESS 1-PI-2326, MSL 2 PRESS 1-PI-2327, MSL 3 PRESS 1-PI-2328, MSL 4 PRESS CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2 Page 11 of 37 Event

Description:

Steam Generator 1-01 Steam Line Pressure Instrument Failure Time Position Applicants Actions or Behavior PLACE 1-FK-510, SG 1 FW FLO CTRL in MANUAL AND CONTROL Steam BOP Generator 1-01 level in normal operating range: [Step 2.3.3]

Manually CONTROL 1-SK-509A, FWPT MASTER SPD CTRL as necessary.

BOP

[Step 2.3.4]

BOP SELECT Alternate Steam Flow Channel: [Step 2.3.5]

Loop, 1-FS-512C, SG 1 STM FLO CHAN SELECT [Step 2.3.5.a]

Steam pressure/associated steam flow 1-FY-512B (PT-514/FT-512)

OR 1-FY-513B (PT-515/FT-513)

BOP VERIFY Steam Generator 1-01 is stable at program level. [Step 2.3.6]

PLACE 1-FK-510, SG 1 FW FLO CTRL in AUTO AND BOP VERIFY SG 1-01 level - CONTROLLING NORMAL OPERATING RANGE

[Step 2.3.7]

US Evaluate Technical Specifications. [Step 2.3.11]

LCO 3.3.2, Engineered Safety Feature System (ESFAS) Instrumentation, Table 3.3.2-1, Function 1.e, Steam Line Pressure - Low.

LCO 3.3.2, Table 3.3.2-1, Function 4d (1) - Steam Line Pressure Low and Negative Rate - High CONDITION D - One channel inoperable ACTION D.1 - Place channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , OR ACTION D.2.1 - Be in MODE 3 within 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND ACTION D.2.2 - Be in MODE 4, within 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 2 Page 12 of 37 Event

Description:

Steam Generator 1-01 Steam Line Pressure Instrument Failure Time Position Applicants Actions or Behavior US INITIATE a Condition Report per STA-421, as applicable. [Step 2.3.12]

When Technical Specifications have been addressed, or at Lead Examiner discretion, PROCEED to Event 3.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 3 Page 13 of 37 Event

Description:

Letdown HX Outlet Flow Controller Failure (TK-130) Fails Low Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 3 (Key 3).

- Override, LTDN HX Outlet Flow Controller Failure (TK-130) Fails Low.

Indications Available:

6A-1.3 - LTDN HX OUT TEMP HI 6A-2.3 - LTDN HX NORM OUT FLO DIVERT 1-TI-130, LTDN HX OUT TEMP Rising RO RESPOND to Annunciator Procedure Alarms.

RECOGNIZE 1-TK-130, LTDN HX OUT TEMP CTRL has failed to 0% output RO and 1-TI-130, LTDN HX OUT TEMP is rising.

Examiner Note: The operator can take manual control of 1-TK-130 and open TCV-4646 as an automatic control system has malfunctioned.

US DIRECT RO to respond in accordance with the appropriate ALM.

Examiner Note: The following steps are from ALM-0061A, Alarm Procedure 1-ALB-6A Window 1-3, LTDN HX OUT TEMP HI RO MONITOR 1-TI-130, LTDN HX OUT TEMP. [Step 1]

IF temperature increases to 135°F, ensure 1/1-TCV-129, LTDN DIVERT VLV is diverted to the VCT. [Step 1.A]

RO MONITOR 1-TI-381, BTRS DEMIN IN TEMP. [Step 2]

The BTRS system is NOT in service. [Step 2.A]

RO VERIFY charging flow is 12 gpm greater than letdown flow. [Step 3]

RO VERIFY 1-TI-127, REGEN HX LTDN OUT TEMP is 350°F. [Step 4]

1-TI-127, REGEN HX LTDN OUT TEMP is NOT > 350°F. [Step 4.A]

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 3 Page 14 of 37 Event

Description:

Letdown HX Outlet Flow Controller Failure (TK-130) Fails Low Time Position Applicants Actions or Behavior BOP VERIFY 1-ZL-4646, LTDN HX CCW RET VLV is OPEN. (1-CB-03) [Step 5]

IF 1-ZL-4646 is CLOSED, place 1-TK-130, LTDN HX OUT TEMP CTRL in RO manual AND adjust letdown heat exchanger outlet temperature to 95°F.

[Step 5.A]

The controller will respond appropriately in MANUAL to control letdown heat exchanger outlet temperature at 95°F. [Step 5.B]

RO ENSURE 1-TI-130, LTDN HX OUT TEMP is maintained < 125°F. [Step 6]

Letdown heat exchanger outlet temperature can be maintained < 125°F with 1-TK-130 in manual. [Step 6.A]

NOTIFY Chemistry and Radiation protection personnel that Letdown has US/RO diverted to the VCT. [Step 7]

US Correct the condition or initiate a work request per STA-606. [Step 8]

When Letdown Heat Exchanger Outlet Temperature is appropriately controlled, or at Lead Examiner discretion, PROCEED to Event 4.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 4 Page 15 of 37 Event

Description:

Station Service Water Pump 1-01 Trip Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 4 (Key 4).

- SW01A, Station Service Water Pump 1-01 Trip.

Indications Available:

01-1.8 - SSWP 1 / 2 OVRLOAD / TRIP 01-1.11 - CCP 1 L/O CLR SSW RET FLO LO 01-1.12 - SIP 1 L/O CLR SSW RET FLO LO 01-3.8 - CSP 1 & 3 BRG CLR SSW RET FLO LO 3B-4.5 - CCW HX 1 / 2 SPLY FLO LO BOP RESPOND to Annunciator Alarm Procedures.

RECOGNIZE 1-HS-4250A, Service Water Pump 1-01 amber MISMATCH BOP and white TRIP lights illuminated.

DIRECT performance of ABN-501, Station Service Water System US Malfunction, Section 2.0, Station Service Water Pump Trip Examiner Note: Diamond steps () are Initial Operator Actions.

PLACE CS-1DG1E, Train A Diesel Generator Emergency Start/Stop BOP handswitch in PULLOUT. [Step 2.3.1]

BOP VERIFY Train B SSW Pump - RUNNING. [Step 2.3.2]

BOP VERIFY Train B CCW Pump - RUNNING. [Step 2.3.3]

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 4 Page 16 of 37 Event

Description:

Station Service Water Pump 1-01 Trip Time Position Applicants Actions or Behavior Simulator Operator: When asked about status of SSW Pump breaker/motor, REPORT that the SSW Pump 1-01 50/51 overcurrent relays on Phases B & C are tripped and the motor is hot.

RO/BOP VERIFY equipment on Train A not required for operation: [Step 2.3.4]

Centrifugal Charging Pump 1-01 Diesel Generator 1-01 Component Cooling Water Pump 1-01 Safety Injection Pump 1-01 Containment Spray Pumps 1-01 & 1-03 Determines CCP 1-01 is running and CCP 1-02 must be started.

[Step 2.3.4 RNO]

Simulator Operator: When contacted, EXECUTE remote function CVR06 (Key 11) to START CCP 1-02 Auxiliary Oil Pump and CVR05 (Key 12) to STOP CCP 1-01 Auxiliary Lube Oil Pump.

RO START Centrifugal Charging Pump 1-02.

RO/BOP PLACE equipment on Train A in PULL OUT. [Step 2.3.5]

Centrifugal Charging Pump 1-01 Station Service Water Pump 1-01 (may leave as is due to CAUTION)

Safety Injection Pump 1-01 Containment Spray Pumps 1-01 & 1-03 BOP VERIFY CCW Pump 1-01 RUNNING. [Step 2.3.6 and 2.3.6.a]

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 4 Page 17 of 37 Event

Description:

Station Service Water Pump 1-01 Trip Time Position Applicants Actions or Behavior VERIFY CCW Heat Exchanger outlet temperature on Train A remains BOP

< 122ºF. [Step 2.3.6.b]

US Initiate a Work Request per STA-606. [Step 2.3.7]

US Refer to EPP-201. [Step 2.3.8]

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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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 circuits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

ACTION B.2 - Declare required feature(s) supported by the inoperable DG inoperable when its required redundant feature(s) is inoperable within four hours from discovery of Condition B concurrent within inoperability of redundant required feature(s).

ACTION B.3 - Determine OPERABLE DG(s) is not inoperable due to common cause failure within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Simulator Operator: If contacted, INFORM the Unit Supervisor that another operator will perform required Tech Spec Surveillance.

US Complete OPT-215 verification within one hour. [Step 2.3.10]

US Submit a Condition Report per STA-421. [Step 2.3.11]

When Technical Specifications have been addressed, or at Lead Examiner discretion, PROCEED to Event 5.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5 Page 18 of 37 Event

Description:

High Pressure Turbine Stop Valve #3 (UV-2430A) Fails Closed Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 5 (Key 5).

- TC08C, High Pressure Turbine Stop Valve #3 (UV-2430A) Fails Closed.

Indications Available:

6D-1.10 - AVE TAVE TREF DEV 8A-3.6 - SG3 LVL LO 8A-3.8 - SG3 STM & FW FLO MISMATCH 8A-3.12 - SG3 LVL DEV Main Generator Load Decreasing on Turbine Digital Display Steam Dumps operating to control RCS Temperature Various Heater Drain Alarms BOP RESPOND to Annunciator Alarm Procedures BOP RECOGNIZE High Pressure Turbine Stop Valve #3 has Failed Closed Immediately PLACE 1/1-RBSS, CONTROL ROD BANK SELECT Switch in RO AUTO to allow the Rod Control System to Automatically respond to the plant transient.

DIRECT performance of ABN-401, Main Turbine Malfunction, Section 9.0, US Inadvertent Opening of an HP or LP Stop or Control Valve.

BOP VERIFY operable HP Control Valves are 98% open. [Step 9.3.1]

PERFORM the following:

ENSURE 1/1-RBSS, CONTROL ROD BANK SELECT in AUTO.

RO/BOP [Step 9.3.1 RNO a]

Reduce Turbine power to 50 MW less than current load target at a rate of 100 MW per minute. [Step 9.3.1 RNO b]

BOP SET Turbine Load Rate Setpoint Controller to 100 MWe/min.

OPEN Load Rate Setpoint OSD.

SELECT blue bar and ENTER 100 MWe/min.

CLOSE Load Rate Setpoint OSD.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5 Page 19 of 37 Event

Description:

High Pressure Turbine Stop Valve #3 (UV-2430A) Fails Closed Time Position Applicants Actions or Behavior BOP SET Turbine Load Target to 50 MWe less than current load value.

OPEN Load Target OSD.

SELECT blue bar and ENTER appropriate MWe.

DEPRESS Accept then VERIFY value in blue bar is desired Load Target (magnitude and direction).

DEPRESS Execute then VERIFY Load Target changes to desired load.

CLOSE Load Target OSD.

BOP VERIFY Steam Generator levels at or trending to program. [Step 9.3.2]

VERIFY PR Delta Flux - (AFD) WITHIN LIMITS: [Step 9.3.3]

1-NI-41C, PR DELTA FLUX CHAN I RO 1-NI-42C, PR DELTA FLUX CHAN II 1-NI-43C, PR DELTA FLUX CHAN III 1-NI-44C, PR DELTA FLUX CHAN IV VERIFY the Steam Dumps AND Rod Control System - RESPONDING TO RO MAINTAIN Tave to Tref. [Step 9.3.4]

1-TI-412A, AVE Tave-Tref DEV VERIFY Pressurizer Level - TRENDING TO PROGRAM LEVEL. [Step 9.3.5]

RO 1-LR-459, PRZR LVL/PRZR LVL STPT VERIFY Pressurizer Pressure - TRENDING TO PROGRAM PRESSURE.

RO [Step 9.3.6]

1PR-455, PRESS CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5 Page 20 of 37 Event

Description:

High Pressure Turbine Stop Valve #3 (UV-2430A) Fails Closed Time Position Applicants Actions or Behavior CHECK Steam Generator Feedwater Level AND Flow Control Valve status:

BOP

[Step 9.3.7]

Steam Generator Levels - AT 67% [Step 9.3.7.a]

1-LI-551/519, SG 1 LVL (NR) 1-LI-552/529, SG 2 LVL (NR) 1-LI-553/539, SG 3 LVL (NR) 1-LI-554/549, SG 4 LVL (NR)

ALL Steam Generator Feedwater Flow Valves - IN AUTO

[Step 9.3.7.b]

1-FK-510, SG 1 FW FLO CTRL BOP 1-FK-520, SG 2 FW FLO CTRL 1-FK-530, SG 3 FW FLO CTRL 1-FK-540, SG 4 FW FLO CTRL BOP RESET Steam Dump Valves [Step 9.3.8]

VERIFY ALL Steam Dumps - CLOSED [Step 9.3.8.a]

VERIFY 1-UI-500, STM DMP DEMAND - 0% [Step 9.3.8.b]

PLACE 43/1-SD, STM DMP MODE SELECT to RESET AND then TAVE position [Step 9.3.8.c]

VERIFY Turbine Load - STABLE [Step 9.3.9]

BOP GEN MEGAWATTS GEN MEGAVARS VERIFY ALL operable HP Turbine Control Valves - INDICATE LESS THAN 100% OPEN: [Step 9.3.10]

TG Control Display OR BOP 1-ZI-2429B, HPT CTRL VLV 1 POSN 1-ZI-2431B, HPT CTRL VLV 2 POSN 1-ZI-2430B, HPT CTRL VLV 3 POSN 1-ZI-2428B, HPT CTRL VLV 4 POSN Examiner Note: Control Rods may insert below the LO-LO Limit on this transient, if this occurs the Unit Supervisor should refer to TS 3.1.6, Control Bank Insertion Limits.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 5 Page 21 of 37 Event

Description:

High Pressure Turbine Stop Valve #3 (UV-2430A) Fails Closed Time Position Applicants Actions or Behavior US REFER to TS/TR listed in Section 10.1 [Step 9.3.11]

RESET Turbine Runback per Section 8.0, if necessary (NOT required)

BOP

[Step 9.3.12]

When the plant has been stabilized, or at Lead Examiner discretion, PROCEED to Events 6, 7 and 8.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, & 8 Page 22 of 37 Event

Description:

SG 1-03 Tube Rupture / Automatic Reactor Trip Failure, Manual Trip from 1B3 and 1B4 / SG 1-03 MSIV Fails to Close Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Events 6, 7 and 8 (Key 6).

- SG02C, SG 1-03 Tube Rupture

- RP15E, RX Trip Breakers Jammed Closed - ALL

- MS08C, SG 1-03 MSIV Fails to Close Indications Available:

6A-3.4 - CHRG FLO HI / LO 5C-1.2 - PRZR LVL DEV LO 5C-3.3 - PRZR PRESS LO BACKUP HTRS ON PC MSL-180 (1-RE-2327) is RED Main Steam Line Radiation level rising Pressurizer pressure lowering RO/BOP RECOGNIZE lowering RCS temperature and pressure.

DETERMINE Reactor Trip/Safety Injection initiation required. Attempt to RO/BOP manually trip the reactor and manually initiate Safety Injection.

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.

CRITICAL TASK Manually Trip Reactor due to Failure to Automatically Trip prior to STATEMENT exiting 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]

RO/BOP Manually trip reactor from both trip switches [Step 1.a RNO]

IF reactor will not trip, THEN momentarily de-energize 480 V normal BOP switchgear 1B3 and 1B4. [Step 1.a RNO]

CRITICAL Momentarily places BOTH CS-1B3-1, INCOMING BKR 1B3-1 AND TASK BOP CS-1B4-1, INCOMING BKR 1B4-1 to TRIP and then back to CLOSE.

RO VERIFY all Control Rod Position Rod Bottom Lights - ON. [Step 1.b]

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, & 8 Page 23 of 37 Event

Description:

SG 1-03 Tube Rupture / Automatic Reactor Trip Failure, Manual Trip from 1B3 and 1B4 / SG 1-03 MSIV Fails to Close Time Position Applicants Actions or Behavior 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 SI status: [Step 4]

RO CHECK if SI is actuated. [Step 4.a]

RO Manually INITIATE Train A and Train B Safety Injection Signal.

PLACE 1/1-SIA2, SI MAN ACT Switch to ACT position at CB-07 and RO DETERMINE SI has actuated on both Trains. [Step 4.a]

RO VERIFY Both Trains SI Actuated: [Step 4.b]

SI Actuated blue status light - ON NOT FLASHING.

Simulator Operator: If contacted to open the Reactor Trip Breakers, wait 2 minutes and Execute Key 13.

Examiner Note: EOP-0.0A, Attachment 2 steps performed by BOP are identified on Page 32 of the scenario guide.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, & 8 Page 24 of 37 Event

Description:

SG 1-03 Tube Rupture / Automatic Reactor Trip Failure, Manual Trip from 1B3 and 1B4 / SG 1-03 MSIV Fails to Close Time Position Applicants Actions or Behavior INITIATE Proper Safeguards Equipment Operation Per Attachment 2.

US/BOP

[Step 5]

Examiner Note: The crew should stop AFW flow to SG 1-03 promptly after it has been identified as ruptured AND level is greater than 43% per EOP-0.0A, Attachment 1.A, Foldout for EOP-0.0A Reactor Trip or Safety Injection.

RO VERIFY AFW Alignment: [Step *6]

VERIFY both MDAFW Pumps - RUNNING. [Step 6.a]

PLACE TDAFW Pump in PULLOUT per Foldout Page. [Step 6.b]

VERIFY AFW total flow - GREATER THAN 460 GPM. [Step 6.c]

VERIFY AFW valve alignment - PROPER ALIGNMENT. [Step 6.d]

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 2 & 4 - 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 a]

RO CHECK RCS Temperature: [Step *9]

VERIFY RCS Average Temperature - STABLE AT OR TRENDING TO 557°F. [Step 9]

RO CHECK PRZR Valve Status: [Step 10]

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, & 8 Page 25 of 37 Event

Description:

SG 1-03 Tube Rupture / Automatic Reactor Trip Failure, Manual Trip from 1B3 and 1B4 / SG 1-03 MSIV Fails to Close Time Position Applicants Actions or Behavior 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 25°F (55°F FOR ADVERSE CONTAINMENT). [Step 11.a]

GO to Step 12. [Step 11.a RNO a]

US/RO CHECK if any SG is Faulted: [Step 12]

VERIFY any Steam Generator pressure - DECREASING IN AN UNCONTROLLED MANNER. [Step 12.a]

VERIFY Steam Generator 1-01 pressure - COMPLETELY DEPRESSURIZED. [Step 12.a]

Go to Step 13. [Step 12.a RNO a]

US/RO CHECK if SG Tubes Are Not Ruptured: [Step 13]

Condenser off gas radiation - NORMAL (COG-182, 1RE-2959)

Main steamline radiation - NORMAL (MSL-178 through 181, 1RE-2325 through 2328)

SG blowdown sample radiation monitor - NORMAL (SGS-164, 1RE-4200)

No Steam Generator level increasing in an uncontrolled manner Go to EOP-3.0A, Steam Generator Tube Rupture, Step 1 based on indications that SG 1-03 is ruptured. [Step 13 RNO]

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, & 8 Page 26 of 37 Event

Description:

SG 1-03 Tube Rupture / Automatic Reactor Trip Failure, Manual Trip from 1B3 and 1B4 / SG 1-03 MSIV Fails to Close Time Position Applicants Actions or Behavior Examiner Note: EOP-3.0A, Steam Generator Tube Rupture, steps begin here.

US/RO CHECK If RCPs Should Be Stopped: [Step *1]

VERIFY RCS subcooling - LESS THAN 25°F (55°F FOR ADVERSE CONTAINMENT). [Step 1.a]

GO to Step 2. [Step 1.a RNO].

US/BOP IDENTIFY Steam Generator 1-03 as ruptured. [Step *2]

OBSERVE high radiation from Steam Generator 1-03 Main Steam Line.

OBSERVE SG 1-03 level rising out of control.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, & 8 Page 27 of 37 Event

Description:

SG 1-03 Tube Rupture / Automatic Reactor Trip Failure, Manual Trip from 1B3 and 1B4 / SG 1-03 MSIV Fails to Close Time Position Applicants Actions or Behavior Identify and Isolate the Ruptured Steam Generator Prior to CRITICAL TASK STATEMENT Commencing an Operator Induced Cooldown per EOP-3.0A, Steam Generator Tube Rupture.

CRITICAL TASK RO/BOP ISOLATE flow from Ruptured Steam Generator 1-03: [Step 3]

ADJUST SG 1-03 Atmospheric Controller Setpoint to 1160 PSIG.

[Step 3.a]

CHECK SG 1-03 Atmospheric Relief Valve - CLOSED. [Step 3.b]

CLOSE SG 1-03 Main Steam Line Isolation Valve. [Step 3.c]

CLOSE SG 1-03 Drip Pot Isolation Valves. [Step 3.c]

RECOGNIZES SG 1-03 MSIV will NOT close and CLOSES all remaining SG MSIVs. [Step 3.c RNO c.1)]

PLACES STM DMP INTLK SELECT switches 43/1-SDA and 43/1-SDB in OFF to close the Steam Dump Valves.

[Step 3.c RNO c.2)]

CLOSES 1-HS-3228, MS TO AUX STM SPLY VLV.

[Step 3.c RNO c.3)]

DISPATCHES operators to LOCALLY close SG 1-03 MSIV.

[Step 3.c RNO c.4)]

Examiner Note: The intact SG ARVs (SGs 1, 2 and 4) should be set to control at 1092 psig, the steam pressure corresponding to the No load RCS average temperature of 557°F.

Simulator Operator: When contacted to Close MSIV 1-03, wait 2 minutes and then DELETE Malfunction MS08C.

USE SGs 1, 2 and 4 ARVs during subsequent RCS cooldown.

[Step 3.c RNO c.6)]

PULL-OUT steam supply valve handswitch from ruptured SG(s) to TDAFWP. (NOT Applicable) [Step 3.d]

VERIFY blowdown isolation valves from SG 1 CLOSED [Step 3.e]

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, & 8 Page 28 of 37 Event

Description:

SG 1-03 Tube Rupture / Automatic Reactor Trip Failure, Manual Trip from 1B3 and 1B4 / SG 1-03 MSIV Fails to Close Time Position Applicants Actions or Behavior US/RO CHECK SG 1-03 Level: [Step *4]

Narrow range level - GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT) [Step 4.a]

Stop AFW flow to SG 1-03. [Step 4.b]

BOP/RO CHECK SG 1-03 Pressure - GREATER THAN 420 PSIG [Step 5]

Examiner Note: When ruptured Steam Generator pressure is between two values provided on the Table at Step 6.c, the correlating Core Exit Temperature for the lower pressure value is used.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, & 8 Page 29 of 37 Event

Description:

SG 1-03 Tube Rupture / Automatic Reactor Trip Failure, Manual Trip from 1B3 and 1B4 / SG 1-03 MSIV Fails to Close Time Position Applicants Actions or Behavior BOP/RO INITIATE RCS Cooldown: [Step *6]

CHECK PRZR pressure - LESS THAN 1960 PSIG [Step 6.a]

BLOCK low steamline pressure SI signal [Step 6.b]

DETERMINE required core exit temperature from Table 1. [Step 6.c]

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, & 8 Page 30 of 37 Event

Description:

SG 1-03 Tube Rupture / Automatic Reactor Trip Failure, Manual Trip from 1B3 and 1B4 / SG 1-03 MSIV Fails to Close Time Position Applicants Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # 6, 7, & 8 Page 31 of 37 Event

Description:

SG 1-03 Tube Rupture / Automatic Reactor Trip Failure, Manual Trip from 1B3 and 1B4 / SG 1-03 MSIV Fails to Close Time Position Applicants Actions or Behavior BOP/RO RECOGNIZES that condenser is unavailable due to shutting all intact SG MSIVs. [Step 6.d]

DUMP steam at maximum rate from SGs 1, 2 and 4 using ARVs.

[Step 6.d RNO d]

Make plant announcement and notify Plant Staff of steam release.

[Step 6.d RNO d.1)]

PERFORM the following as necessary to release steam:

[Step 6.d RNO d.2)]

PLACE SGs 1, 2 and 4 ARVs in manual and fully open valves.

PLACE all PRZR heater switches to OFF position. [Step 6.e]

Core exit TCs - LESS THAN REQUIRED TEMPERATURE [Step 6.f]

STOP RCS cooldown. [Step 6.g]

MAINTAIN core exit TCs - LESS THAN REQUIRED TEMPERATURE

[Step 6.h]

When the target CET Temperature is reached during the RCS cooldown in accordance with EOP-3.0A, Steam Generator Tube Rupture, TERMINATE the Scenario.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # Att. 2 Page 32 of 37 Event

Description:

EOP-0.0A, Attachment 2 Time Position Applicants Actions or Behavior Examiner Note: These steps are performed by the BOP per EOP-0.0A, Attachment 2.

BOP VERIFY SSW Alignment: [Step 1]

VERIFY SSW Pump 1 RUNNING. [Step 1.a]

VERIFY EDG 1-02 Cooler SSW return flow. [Step 1.b]

BOP VERIFY Safety Injection Pump 1 RUNNING. [Step 2]

BOP VERIFY Containment Isolation Phase A - APPROPRIATE MLB LIGHT INDICATION (RED WINDOWS). [Step 3]

BOP VERIFY Containment Ventilation Isolation - APPROPRIATE MLB LIGHT INDICATION (GREEN WINDOWS). [Step 4]

BOP VERIFY CCW Pumps - RUNNING. [Step 5]

BOP VERIFY RHR Pumps - RUNNING. [Step 6]

BOP VERIFY Proper CVCS Alignment: [Step 7]

VERIFY CCP 1 RUNNING. [Step 7.a]

VERIFY Letdown Relief Valve Isolation: [Step 7.b]

Letdown Orifice Isolation Valves - CLOSED. [Step 7.b.1)]

Letdown Isolation Valves 1/1-LCV-459 & 1/1-LCV-460 - CLOSED.

[Step 7.b.2)]

BOP VERIFY ECCS flow: [Step 8]

CCP SI flow indicator - CHECK FOR FLOW. [Step 8.a]

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # Att. 2 Page 33 of 37 Event

Description:

EOP-0.0A, Attachment 2 Time Position Applicants Actions or Behavior RCS pressure - LESS THAN 1700 PSIG (1800 PSIG FOR ADVERSE CONTAINMENT). [Step 8.b]

GO to Step 9. [Step 8.b RNO b]

BOP VERIFY Feedwater Isolation Complete: [Step 9]

Feedwater Isolation Valves - CLOSED.

Feedwater Isolation Bypass Valves - CLOSED.

Feedwater Bypass Control Valves - CLOSED.

Feedwater Control Valves - CLOSED.

BOP VERIFY Diesel Generator 1 RUNNING. [Step 10]

BOP VERIFY Monitor Lights for SI Load Shedding on 1-MLB-9 and 1-MLB LIT. [Step 11]

BOP VERIFY Proper SI alignment - PROPER MLB LIGHT INDICATION. [Step 12]

BOP VERIFY Components on Table 1 are Properly Aligned. [Step 13]

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # Att. 2 Page 34 of 37 Event

Description:

EOP-0.0A, Attachment 2 Time Position Applicants Actions or Behavior Location Equipment Description Condition CB-03 X-HS-5534 H2 PRG SPLY FN 4 STOPPED CB-03 X-HS-5532 H2 PRG SPLY FN 3 STOPPED CB-04 1/1-8716A RHRP 1 XTIE VLV OPEN CB-04 1/1-8716B RHRP 2 XTIE VLV OPEN CB-06 1/1-8153 XS LTDN ISOL VLV CLOSED CB-06 1/1-8154 XS LTDN ISOL VLV CLOSED CB-07 1/1-RTBAL RX TRIP BKR OPEN CB-07 1/1-RTBBL RX TRIP BKR OPEN CB-07 1/1-BBAL RX TRIP BYP BKR OPEN/DEENERGIZED CB-07 1/1-BBBL RX TRIP BYP BKR OPEN/DEENERGIZED CB-08 1-HS-2397A SG 1 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2398A SG 2 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2399A SG 3 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2400A SG 4 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2111C FWPT A TRIP TRIPPED CB-08 1-HS-2112C FWPT B TRIP TRIPPED CB-09 1-HS-2490 CNDS XFER PUMP STOPPED (MCC deenergized on SI)

CV-01 X-HS-6181 PRI PLT SPLY FN 17 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6188 PRI PLT SPLY FN 18 & INTK STOPPED/DEENERGIZED DMPR CV-01 X-HS-6195 PRI PLT SPLY FN 19 & INTK STOPPED/DEENERGIZED DMPR 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 CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # Att. 2 Page 35 of 37 Event

Description:

EOP-0.0A, Attachment 2 Time Position Applicants Actions or Behavior 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 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 3 Event # Att. 2 Page 36 of 37 Event

Description:

EOP-0.0A, Attachment 2 Time Position Applicants Actions or Behavior Examiner Note: The next four (4) steps would be performed on Unit 2.

CB-03 2-HS-5538 AIR PRG EXH ISOL DMPR CLOSED CB-03 2-HS-5539 AIR PRG EXH ISOL DMPR CLOSED CB-03 2-HS-5537 AIR PRG SPLY ISOL DMPR CLOSED CB-03 2-HS-5536 AIR PRG SPLY ISOL DMPR CLOSED BOP NOTIFY Unit Supervisor attachment instructions complete AND to IMPLEMENT FRGs as required.

EOP-0.0A, Attachment 2 steps are now complete.

CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Scenario Event Description NRC Scenario 3

2016 NRC Scenario 3

Rev. 1

Event 1 - Loop 4 Tcold Fails High

TE-441B Failure High IMF RP05D f: 630 k:1

Event 2 - Main Steam Line 1 Steam Pressure Fails Low

PT-514 Failure Low IMF RP03A f: 0 k:2

Event 3 TK-130 Fails to 0% Demand - Manual reopens valve IOR AICVTK130 f: 10 k:3

{AOCVTK130.Value=0}IMF CV05 f:0

{AOCVTK130.Value=0}IOR LOCVTK130_1 f:1

{AOCVTK130.Value=0}IOR LOCVTK130_2 f:0

{AOCVTK130.Value=0}IOR DICVTK130_2 f:1

{AOCVTK130.Value=0}IOR DICVTK130_4 f:1

{DICVTK130_2.Value=1}DMF CV05

{DICVTK130_2.Value=1}DOR LOCVTK130_1

{DICVTK130_2.Value=1}DOR LOCVTK130_2

{DICVTK130_2.Value=1}DOR DICVTK130_2

{DICVTK130_2.Value=1}DOR DICVTK130_4

{DICVTK130_1.Value=1}IMF CV05 f:0

Event 4 - Staion Service Water Pump 1-01 Trip

SSWP 1-01 Trips IMF SW01A f: 1 k:4

Event 5 - High Pressure Stop Valve Fails Closed

HP Stop Valve 3 Failure IMF TC08C f: 1 k:5

Event 6 - SGTR #3

SGTR 1 Tube IMF SG02C f: 1 k:6

Event 7 - ALL Automatic & Manual Rx Trip Failures

Rx Trip Breakers Jammed Close - All IMF RP15E f: 1

Event 8 - SG #3 MSIV Fails to Close in Manual

1-HV-2335A Fails to Manually Close IMF MS08C f: 1

KEY 11 CCP 1-02 Aux Lube Oil Pump to Auto IRF CVR06 f: 1 k:11

KEY 12 CCP 1-01 Aux Lube Oil Pump to Off IRF CVR05 f: 0 k:12

KEY 13 Rx Trip Breakers Open IRF RPR112 f: 2 k:13 IRF RPR113 f:2 k:13 CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1

Appendix D Scenario Outline Form ES-D-1 Facility: CPNPP 1 & 2 Scenario No.: 4 Op Test No.: July 2016 NRC Examiners: Operators:

Initial Conditions: ~3% power BOL - RCS Boron is 1669 ppm. Steam Dump System in service for Reactor Coolant System Temperature Control.

Turnover: Raise Reactor power to 6% to 8% in preparation for Turbine Startup.

Critical Tasks: CT-1 Manually Trip Reactor Due to Reactor Protection System Failure Prior to Exiting EOP-0.0A, Reactor Trip or Safety Injection.

CT-2 Trip Reactor Coolant Pumps within 5 minutes upon a Loss of Subcooling per EOP-1.0A, Loss of Reactor or Secondary Coolant, Attachment 1.A.

Event No. Malf. No. Event Type* Event Description Instrument Air Compressor 1-01 Trip 1 IA06A C (BOP,SRO)

Instrument Air Compressor 1-02 Failure to Start R (RO) Raise Power to 6% to 8% in Preparation for Synchronizing Main 2

N (BOP, SRO) Generator to Electrical Grid Main Steam Header Pressure (PT-507) Fails High on 360 second 3 RX12 I (BOP,SRO) ramp Turbine Plant Cooling Water Pump 1 Trip 4 TP06A C (BOP,SRO)

Turbine Plant Cooling Water Pump 2 Failure to Start I (BOP, SRO) 5 RX04A Steam Generator (1-01) Level Channel (LT-551) Fails Low TS (SRO)

I (RO) 6 NI02B Intermediate Range Channel N-36 Fails High TS (SRO) 7 RP14B M (RO, BOP, SRO) Spurious Train B Safety Injection Actuation Signal Automatic Reactor Trip Failure 8 RP01 C (RO,SRO)

Reactor Protection System Failure requires Manual Reactor Trip 9 CS02H C (RO) Containment Spray Pump 1-04 fails to start on the SI Sequencer Small Break Loss of Coolant Accident when Safety Injection Pump 10 RC08C1 M (RO, BOP, SRO) 1-02 is Secured in EOS-1.1A

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 9 Total malfunctions (5-8) 3 Malfunctions after EOP entry (1-2) 5 Abnormal events (2-4) 2 Major transients (1-2) 2 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3)

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Scenario Event Description NRC Scenario 4 SCENARIO

SUMMARY

NRC 4 Event 1 (Key 1)

The crew will assume the watch with power at approximately 3% per IPO-003A, Power Operations, with direction to raise Reactor Power to 6% to 8% in preparation for Turbine startup. Prior to raising power, Instrument Air Compressor 1-01 will trip and Instrument Air Compressor 1-02 will fail to start as the Backup Compressor. The crew will refer to ABN-301, Instrument Air System Malfunction, Section 2.0. The crew will manually start the Backup Air Compressor, Instrument Air Compressor 1-02, and verify Instrument Air Header Pressure recovers.

Event 2 The crew will continue with IPO-003A, Section 5.1, Warmup and Synchronization of the Turbine Generator, Step 5.1.16, and perform a power ascension using the Rod Control System Steam Dump Systems. The crew will raise power to 6% - 8% and hold.

Event 3 (Key 3)

The next event is a failure high of Main Steam Header Pressure Transmitter (PT-507) on a 360 second ramp. The crew enters ABN-709, Steam Line Pressure, Steam Header Pressure, Turbine 1st-Stage Pressure and Feed Header Pressure Instrument Malfunction, Section 3.0. Actions include placing the Steam Dump System in MANUAL to regain control of Reactor Coolant System (RCS) temperature. The controller will remain in MANUAL for the duration of the scenario.

Event 4 ( Key 4)

When RCS temperature control is restored, a trip of the running TPCW Pump will occur. The standby pump will fail to start and manual operator action will be required to start the standby pump. Crew response will be per ABN-306, Turbine Plant Cooling Water System Malfunction, Section 3.0. The crew will start the standby pump and verify other parameters for the system.

Event 5 (Key 5)

The next event is a Steam Generator Level Transmitter (LT-551) failure low. Actions are per ABN-710, Steam Generator Level Instrumentation Malfunction. The BOP will be required to take manual control of the Feedwater Bypass Control Valve and select an alternate controlling channel to return the Feedwater System to automatic control. The SRO will refer to Technical Specification LCO 3.3.1, Reactor Trip System Instrumentation (Function 14); Condition E, One channel inoperable. The SRO will also refer to Technical Specification LCO 3.3.2, ESFAS Instrumentation (Functions 6.c. and 5.b.); Conditions D and I, One channel inoperable (for both conditions).

Event 6 (Key 6)

When conditions are stable, Intermediate Range Channel N-36 will fail high. Actions are per ABN-702, Intermediate Range Instrument Malfunction, Section 2.0. The US will determine that the plant will need to be either lowered in power or raised within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per TS 3.3.1 Function 4 Condition F. The report from the SM will be to raise power to greater than 10% to clear P-10. The RO only performs diagnosis at this time but must energize Source Range following Event 7 as the Source Range instruments will not energize automatically with a failed Intermediate Range Channel.

Events 7 & 8 (Key 7)

When Technical Specifications have been referenced, a spurious Train B Safety Injection Signal will actuate. The crew will determine that the Reactor did not automatically trip and initiate a manual Reactor Trip and enter EOP-0.0A, Reactor Trip or Safety Injection.

Events 9 During performance of EOP-0.0A, Step 7 the RO will be required to start Containment Spray Pump 1-04 as it failed to start on the Safety Injection Sequencer.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Scenario Event Description NRC Scenario 4 Event 10 (Auto)

The crew will exit EOP-0.0A at Step 15 and enter EOS-1.1A, Safety Injection Termination. While in EOS-1.1A, Safeguards Signals are reset, the Charging flow path is realigned, and Safety Injection (SI) Pumps are stopped.

When SI Pump 1-02 is stopped, a Small Break Loss of Coolant Accident will initiate. At this point, the crew will follow guidance of EOS-1.1A, Attachment 1.A, that requires ECCS flow to be reestablished by starting pumps and aligning the CCP ECCS flow path. The SRO will transition to EOP-1.0A, Loss of Reactor or Secondary Coolant.

Termination Criteria The scenario is terminated when it is determined in EOP-1.0A a transition to EOS-1.2 A, Post LOCA Cooldown and Depressurization, is required.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Scenario Event Description NRC Scenario 4 Risk Significance Determination Risk Significance Event Guidance Risk significant core damage Event 7 - Automatic Reactor Trip FSAR 7.2.1.1.1 - The Reactor Trip sequence Failure System automatically initiates a reactor trip whenever necessary to prevent fuel damage for an anticipated operational transient (Condition II), to limit core damage for infrequent faults (Condition III), and so that the energy generated in the core is compatible with the design provisions to protect the RCS pressure boundary for limiting fault conditions (Condition IV).

Event 9 - Small Break Loss of STI-214.01 TSA-2.11 - Initiate RCP Trip When SBLOCA Criteria Met within Coolant Accident 5 mins from time SBLOCA RCP Trip Criteria is satisfied; to prevent peak cladding temperature from exceeding 2200°F. (FSAR II.K.3.5; WCAP-9584; WOG ERG Generic Issue for RCP Trip/Restart)

Risk significant operator actions Manually Trip Reactor FSAR 7.2.1.1 - Whenever a direct process or calculated variable exceeds a setpoint the reactor will be shut down in order to protect against either gross damage to fuel cladding or loss of system integrity which could lead to release of radioactive fission products into containment.

Terminate ECCS Following a STI-214.01 TSA-1.7 - ECCS injection terminated within 14 minutes(1) from Spurious Safety Injection event initiation.

(1) Crew manning for Initial License Examination less than Timed Operator Action validation constraints CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Scenario Event Description NRC Scenario 4 Critical Task Determination Measurable Safety Performance Critical Task Cueing Performance Significance Feedback Indicators Manually Trip Recognize a failure Procedural direction at The operator will Reactor Trip Reactor Due to or an incorrect EOP-0.0A Step 1 to manually trip the Breakers open, flux Reactor Protection automatic determine if a reactor trip Reactor with the lowering, rod System Failure actuation of an has occurred. Position handswitch on bottom lights lit.

Prior to Exiting ESF system or indication of the Reactor CB-07 or CB-10 EOP-0.0A, Reactor component to Trip breakers and placed to trip.

Trip or Safety preclude Reactor Power, Injection. degradation of any Annunciator First out barrier to fission alarms.

product release.

FSAR 7.2.1.1.1 Trip Reactor Take one or more Procedurally driven from The operator will Indication of pump Coolant Pumps actions that would EOP-1.0A. Availability of secure ALL RCPs stop including light within 5 minutes prevent a Subcooling indication using the indication, flow and upon a Loss of challenge to plant both on meters and handswitches on motor current Subcooling per safety to preclude computer. CB-05. lowering.

EOP-1.0A, Loss of a degradation of Reactor or any barrier to Secondary Coolant. fission product release.

FSAR II.K.3.5; WCAP-9584; WOG ERG Generic Issue for RCP Trip /

Restart CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Scenario Event Description NRC Scenario 4 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP Initialize to IC-48 and 2016 NRC Scenario 4.

EVENT TYPE MALF # DESCRIPTION DEMAND INITIATING VALUE PARAMETER SETUP Override IA Compressor 1-02 fails to auto start FAIL K0 (1)

Turbine Plant Cooling Water Pump 2 Auto Start 4 TP07B FAIL K0 Failure 8 RP01 Automatic Reactor Trip Failure FAIL K0 Containment Spray Pump 1-04 fails to start on the SI 9 CS02H Sequencer FAIL K0 1 IA06A IA Compressor 1-01 trip TRIP K1 1 Override IA Compressor 1-02 fails to auto start FAIL K0 2 Raise Power Reactor Power to 6% to 8% - -

K3 3 RX12 Main Steam Header Pressure (PT-507) Failure 1500 psig (360 sec. ramp)

Turbine Plant Cooling Water Pump 1 Overcurrent 4 TP06A TRIP K4 Trip Turbine Plant Cooling Water Pump 2 Auto Start 4 TP07B FAIL K0 Failure 5 RX04A SG (1-01) Level Channel (LT-551) Failure 0% K5 7.6e-5 6 NI02B IR N-36 detector fails high K6 amps 7 RP14B Spurious Train B Safety Injection Actuation - K7 8 RP01 Automatic Reactor Trip Failure FAIL K0 Containment Spray Pump 1-04 fails to start on the SI 9 CS02H Sequencer FAIL K0 10 RC08C1 Small Break LOCA (Loop 3) 3 - (2)

(1) {DIIAHS3463.Value=4} DOR DIIAHS3463 - When the 1-02 compressor is taken to start this will delete the override to prevent auto start and allow a start from the control room switch.

(2) {DISIAPSI2.Value=1} IMF RC08C1 f:1 - When SI Pump 1-02 is stopped in EOS-.1.1A, a Small Break Loss of Coolant Accident will initiate.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Scenario Event Description NRC Scenario 4 Simulator Operator: INITIALIZE to IC-48 and 2016 NRC Scenario 4.

ENSURE all Simulator Annunciator Alarms are ACTIVE.

ENSURE all Control Board Tags are removed.

ENSURE Operator Aid Tags reflect current boron conditions (1669 ppm).

ENSURE Rods are in MAN with Bank C @ 223 steps / Bank D @ 108 steps.

ENSURE Rod Bank Update (RBU) is performed.

SET TT06 screen on MODE 2 and ENSURE ALL Points ON-SCALE.

ENSURE Reactivity Briefing Sheet printout provided with Turnover.

PLACE Plant Computer, RO/US Computer screens- MODE 2 (ON-SCALE).

ENSURE procedures in progress are on SRO desk:

- COPY of IPO-003A, Power Operations, Section 5.1, Warmup and Synchronization of the Turbine Generator, INITIALED to Step 5.1.15.

- COPY of IPO-003A, Power Operations, Attachment 17, MODE 1 Bubble Chart.

ENSURE 1-PK-507, Steam Dump Pressure Control is set at 6.62.

ENSURE all PRZR Heaters energized.

PLACE the Trip Oil Switches placard by MFP B.

PLACE the Steam Isolation Valves Closed placard by MFP B.

Ensure boric acid step counters are set for 1000 gal Significant Control Room Annunciators in Alarm:

PCIP-1.1 - SR TRN A RX TRIP BLK PCIP-1.3 - AMSAC BLK TURB < 40% PWR C-20 PCIP-1.4 - CNDNSR AVAIL STM DUMP ARMED C-9 PCIP-1.7 - RX 50% PWR TURB TRIP PERM P-9 PCIP-2.1 - SR TRN B RX TRIP BLK PCIP-2.4 - LO TURB PWR ROD WTHDRWL BLK C-5 PCIP-2.5 - SR RX TRIP BLK PERM P-6 PCIP-3.5 - RX & TURB 10% PWR P-7 PCIP-4.5 - RX 48% PWR 3-LOOP FLO PERM P-8 PCIP-4.6 - TURB 10% PWR P-13 6D-1.1 - SR HI VOLT FAIL 6D-1.3 - SR SHTDN FLUX ALM BLK 7B-4.8 - FWP A/B RECIRC VLV NOT CLOSED 8A-1.10 - 1 OF 4 TURB STOP VLV CLOSE Numerous 9A Feedwater alarms CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 1 Page 8 of 39 Event

Description:

Trip of the running IA Compressor with a failure of the standby to auto start Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 1 (Key 1).

Trip of IA Compressor 1-01 with a failure of the standby Compressor to start Indications Available:

COMM INSTR AIR COMPR TRBL (CB01-3.2)

INSTR AIR HDR PRESS LO (CB01-3.3)

Lowering IA header pressure BOP RESPOND to Annunciator Alarm Procedures.

BOP RECOGNIZE IA Compressor 1-01 has tripped and the standby Compressor has not started.

Examiner Note: The crew may immediately start IA Compressor 1-02 based on ODA-102 guidance which allows the operator to manually perform an action that should have occurred automatically. Although placed in start, IAC 1-02 will not start until IA pressure drops below 100 psig.

US DIRECT entry into ABN-301, Instrument Air System Malfunction Section 2.3 BOP 1. Verify AT LEAST ONE Instrument Air Compressor - ALIGNED TO THE UNIT AND RUNNING: - NO u-HS-3451, INST AIR COMP 1 u-HS-3463, INST AIR COMP 2 X-ZL-3452, INST AIR COMM COMPR 1 X-ZL-3463, INST AIR COMM COMPR 2 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 1 Page 9 of 39 Event

Description:

Trip of the running IA Compressor with a failure of the standby to auto start Time Position Applicants Actions or Behavior BOP 1. RNO - WHEN Instrument Air Header Pressure - LESS THAN 100 psig, ENSURE the backup OR standby Instrument Air Compressor aligned to Unit - RUNNING.

u-PI-3488, INST AIR AFTFILT OUT PRESS u-HS-3451, INST AIR COMP 1 u-HS-3463, INST AIR COMP 2 X-ZL-3452, INST AIR COMM COMPR 1 X-ZL-3463, INST AIR COMM COMPR 2 Simulator Operator: When contacted to investigate the loss of the IA Compressor 1-01 wait 2 minutes and report that the breaker tripped on phase differential overcurrent on phases A and C.

Simulator Operator: When contacted to check IA Compressor 1-02 wait 2 minutes and report that all indications are normal.

Simulator Operator: When contacted as the prompt team, acknowledge the request.

BOP 2. Verify Instrument Air Header Pressure - GREATER THAN OR EQUAL TO 100 psig AND STABLE OR INCREASING:

u-PI-3488, INST AIR AFTFILT OUT PRESS BOP 3. Verify Instrument Air Header Pressure - STABLE OR INCREASING IF Instrument Air Header Pressure STABLE OR INCREASING THEN PERFORM the following: - YES IF an Instrument Air Compressor tripped AND only three Compressors are available for service between the Units, THEN BRIEF personnel per Attachment 13.

RETURN to procedure and step in effect.

When IA Compressor 1-02 is running and supplying air, the crew should PROCEED to Event 2, which was briefed prior to taking the watch.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 2 Page 10 of 39 Event

Description:

Raise power to 6 -8%

Time Position Applicants Actions or Behavior Simulator Operator: After the crew has completed actions for the tripped IA Compressor they will return to raising power to 6-8% using IPO-003, Power Operations, Section 5.0, beginning at step 5.1.16 5.1.

US 16. PERFORM the following steps to increase Reactor power to approximately 6% - 8% to provide additional steam flow capability:

US/BOP A. IF desired, THEN ENSURE the FW BYP CTRL Controllers are in AUTO.

Simulator Operator: When contacted as the SM about Attachment 1 inform the US that it has been completed and the MODE change to MODE 1 is allowed.

US B. Prior to increasing Reactor power above 5%, ENSURE Attachment 1 has been completed and reviewed by the Shift Manager.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 2 Page 11 of 39 Event

Description:

Raise power to 6 -8%

Time Position Applicants Actions or Behavior BOP C. As Reactor power increases, VERIFY the Steam Dump System continues to maintain steam pressure at approximately 1092 psig.

US D. WHEN Reactor power is >5%, THEN LOG the time MODE 1 is entered:

Simulator Operator: If requested, REPORT OPT-102A, Operations Shiftly Routine Tests will be completed by the Extra RO.

US E. PERFORM OPT-102A for MODE 1 surveillances now AND CONTINUE shiftly, as required.

US/RO F. Slowly INCREASE Reactor power to approximately 6% - 8%.

BOP When power has been raised to 6 - 8%, or at Lead Examiners discretion, PROCEED to Event 3.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 3 Page 12 of 39 Event

Description:

MS Header Pressure Transmitter (PT-507) Fails High Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 3 (Key 3).

- RX12, Steam Header Pressure Transmitter (PT-507) fails high on 360 second ramp.

Indications Available:

6D-1.10 - AVE TAVE - TREF DEV 6D-3.10 - 1 OF 4 TAVE LO-LO (WHEN TAVE 553°F)

PCIP-3.6 - RCS TAVE LO-LO P-12 (WHEN TAVE < 553°F, Steam Dump Valves will close)

Steam Dump Valves opening then closing (IF TAVE < 553°F)

Reactor Coolant System temperature lowering 1-PI-507 - MS HDR PRESS indication fails high RO RESPOND to Annunciator Alarm Procedures.

REPORT Reactor Coolant System temperature lowering, Steam Dump RO Valves opening, and PT-507, Steam Header Pressure Channel failure.

DIRECT implementation of ABN-709, Steam Line Pressure, Steam Header US Pressure, Turbine 1st Stage Pressure, and Feed Header Pressure Instrument Malfunction.

Section 3.3

1. CHECK 1-PI-507, MS HDR PRESS indicating HIGHER/LOWER than BOP Main Steam Line Pressure. - YES higher BOP 2. MANUALLY CONTROL Feedwater Pumps.

a. PLACE 1-SK-509A, FWPT MASTER SPD CTRL in MANUAL.

b. ADJUST 1-SK-509A to maintain feedwater header pressure greater than main steamline pressure.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 3 Page 13 of 39 Event

Description:

MS Header Pressure Transmitter (PT-507) Fails High Time Position Applicants Actions or Behavior BOP 3. MONITOR Steam Generator Levels:

a. VERIFY SG levels - STABLE AT OR TRENDING TO NORMAL PROGRAM. - NO

a. 1) RNO - IF feedwater bypass control valves are controlling level, THEN ENSURE bypass control valves are responding to demand signal.

1-LK-550, SG 1 FW BYP CTRL 1-LK-560, SG 2 FW BYP CTRL BOP 1-LK-570, SG 3 FW BYP CTRL 1-LK-580, SG 4 FW BYP CTRL

2) Manually CONTROL feedwater flow as necessary to maintain levels.

Examiner Note: The following step may not be performed based on plant conditions.

4. DETERMINE Required Operational Mode of Steam Dumps:

a. CHECK 43/1-SD, STM DMP MODE SELECT Switch in - TAVE.

- NO

a. RNO 1) IF Tave OR steam pressure is less than normal for conditions AND rapidly decreasing, THEN perform the following:

a. PLACE both STM DMP INTLK SELECT switches in OFF -

RESET.

43/1-SDA in OFF - RESET.

BOP 43/1-SDB in OFF - RESET.

b. PLACE 1-PK-507, STM DMP PRESS CTRL in MANUAL and 0% DEMAND.

c. PLACE both STM DMP INTLK SELECT switches in ON 43/1-SDA in ON 43/1-SDB in ON

d. PLACE 43/1-SD, STM DMP MODE SELECT Switch in RESET AND then in STM PRESS position.

2) Manually CONTROL u-PK-507, STM DMP PRESS CTRL as necessary for conditions.

Examiner Note: 1-PK-507, STM DMP PRESS CTRL, AND 1-SK-509A, FWPT MASTER SPD CTRL, will remain in MANUAL for the duration of the scenario.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 3 Page 14 of 39 Event

Description:

MS Header Pressure Transmitter (PT-507) Fails High Time Position Applicants Actions or Behavior

5. MANUALLY CONTROL 1-SK-509A, FWPT MASTER SPD CTRL to MAINTAIN correct differential pressure until malfunction is corrected BOP (no load to 20% POWER - 80 psid. 20% to 100% POWER - ramp from 80 psid to 181 psid) (P5446A).

Simulator Operator: When contacted as the prompt team, acknowledge the request.

US 6. INITIATE a Condition Report per STA-421.

7. WHEN repairs are complete, THEN PLACE 1-SK-509A, FWPT US MASTER SPD CTRL in - AUTO as follows:

When plant conditions are stable, or at Lead Examiners discretion, PROCEED to Event 4.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 4 Page 15 of 39 Event

Description:

TPCW Pump Trip w/ Failure of STBY Pump to Start Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 4 (Key 4).

- TP06A, TPCW Pump 1-01 Trip. TP07B, TPCW Pump 1-02 AUTO start fails.

Indications Available:

1-ALB-9A, Window 3.10, TPCW PMP 1 OVRLOAD/TRIP 1-ALB-9A, Window 4.9, TPCW PMP DISCH FLO HI/LO 1-FI-3061, TPCW PMP DISCH FLO, indicating 0 gpm 1-HS-3060, TPCW PMP 1, Orange MISMATCH light LIT AND White TRIP light LIT 1-HS-3139, TPCW PMP 2, Green light ON - Red light OFF, indicating pump NOT running BOP RESPOND to Annunciator Alarm Procedures.

RECOGNIZE TPCW Pump 1-01 has Tripped AND TPCW Pump 1-02 has BOP failed to automatically start.

Examiner Note: The crew may immediately start TPCW Pump 1-02 based on ODA-102 guidance which allows the operator to manually perform an action that should have occurred automatically.

BOP PERFORM 1-ALB-9A, Window 3.10, TPCW PMP OVRLOAD/TRIP Simulator Operator: When contacted about status of TPCW Pump 1-01, wait 3 minutes and REPORT Phase B 50/51 overcurrent relays are tripped at the breaker and an acrid odor is present at the TPCW Pump.

1. ENSURE a standby TPCW pump is operating:

BOP 1-HS-3139, TPCW PMP 2 - NO BOP STARTED TPCW Pump 1-02 using 1-HS-3139 Examiner Note: The following step is Not Applicable as the operator should start TPCW pump 1-02 and verify it is running prior to performing this step.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 4 Page 16 of 39 Event

Description:

TPCW Pump Trip w/ Failure of STBY Pump to Start Time Position Applicants Actions or Behavior A. IF NO TPCW pump operating, THEN GO to ABN-306 for Loss of BOP TPCW.

B. IF TPCW Pump 1-01 tripped, THEN REFER to ABN-306 for TPCW BOP Pump Malfunction.

US DIRECT entry into ABN-306, Turbine Plant Cooling Water System Malfunction Examiner Note: The VCT level may lower to a point where manual make up will be required.

The crew may perform this anytime during the rest of this scenario.

Simulator Operator: When contacted as the prompt team, acknowledge the request.

Examiner Note: The following steps are from ABN-306, TPCW System Malfunction.

Section 3.3

1. VERIFY TPCW Head Tank Level - GREATER THAN 6%.

BOP 1-LI-3051, TPCW HEAD TK LVL L6907A, TPCW HEAD TANK LEVEL BOP 2. VERIFY at least ONE TPCW Pump - RUNNING:

1-HS-3139, TPCW PMP 2

3. VERIFY TPCW Head Tank Level - GREATER THAN 20%.

BOP 1-LI-3051, TPCW HEAD TK LVL L6907A, TPCW HEAD TANK LEVEL BOP 4. VERIFY 1-FI-3061, TPCW PMP DISCH FLO - WITHIN LIMITS CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 4 Page 17 of 39 Event

Description:

TPCW Pump Trip w/ Failure of STBY Pump to Start Time Position Applicants Actions or Behavior (F2701A01, is a one minute average of TPCW flow).

a. VERIFY TPCW flow - GREATER THAN 4700 GPM

b. VERIFY TPCW flow - LESS THAN 22000 GPM BOP 5. CHECK BOTH TPCW Pumps - NOT tripped:

1-HS-3139, TPCW PMP 2 BOP 6. VERIFY TPCW Pumps - ONLY ONE RUNNING:

1-HS-3139, TPCW PMP 2 US 7. INITIATE repair per STA-606.

US 8. INITIATE a SMART Form per STA-421, as applicable.

When the plant is stable or at Lead Examiners discretion, PROCEED to Event 5 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 5 Page 18 of 39 Event

Description:

Steam Generator Level Transmitter Failure Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 5 (Key 5).

- RX04A, Steam Generator 1-01 Level Transmitter (LT-551) fails low.

Indications Available:

8A-1.6 - SG 1 LVL LO 8A-1.8 - SG 1 STM & FW FLO MISMATCH (power level dependent) 8A-1.12 - SG 1 LVL DEV (power level dependent) 8A-1.14 - SG 1 1 OF 4 LVL LO-LO 1-LI-551, SG 1 LVL (NR) CHAN I indication failed low BOP RESPOND to Annunciator Alarm Procedures.

RECOGNIZE Steam Generator 1-01 Level Transmitter (LT-551) failed low, BOP takes manual control of MFRV bypass to maintain SG level.

Examiner Note: Steam Generator level channel failing LOW will cause the Feedwater Control Bypass Valve to OPEN. Unit 1 SG High Level Turbine Trip occurs at 84%.

DIRECT performance of ABN-710, Steam Generator Level Instrumentation US Malfunction.

Section 2.3 BOP 1. VERIFY controlling level channel - FAILED.

2. Manually CONTROL the following, as necessary to maintain SG - AT BOP PROGRAMMED LEVEL.

u-LK-550, SG 1 BYP CTRL

3. VERIFY instruments on common instrument line indicate NORMAL BOP (See Attachment 1).

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 5 Page 19 of 39 Event

Description:

Steam Generator Level Transmitter Failure Time Position Applicants Actions or Behavior

4. DETERMINE all HI-HI level bistable windows on Trip Status Light Box BOP (TSLB-3) for Steam Generator 1-01 are DARK.

SG 1 (Channels 517, 518, and 519) windows 2.2, 3.2, and 4.2

5. VERIFY automatic SG level control DESIRED

a. Alternate level control channel responding normally.

BOP

b. Automatic level control desired, as determined by Unit Supervisor.

6. SELECT alternate channel:

BOP u-LS-519C, SG 1 LVL CHAN SELECT BOP 7. VERIFY affected Steam Generator level is stable at program level.

Simulator Operator: If contacted as the Prompt Team acknowledge request.

8. PLACE Feedwater Flow OR Feedwater Bypass Control Valve in BOP AUTOMATIC AND ENSURE proper control.

9. Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , HAVE an I&C Technician place bistable test US switches for failed level channel in CLOSE utilizing Attachments 2 and 3.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 5 Page 20 of 39 Event

Description:

Steam Generator Level Transmitter Failure Time Position Applicants Actions or Behavior

10. VERIFY appropriate Alarms AND Trip Status Lights LIT per US Attachment 3 AND NOTE this verification in the Unit Log.

US 11. REFER TO TECHNICAL SPECIFICATIONS, PER ATTACHMENT 4.

LCO 3.3.1.E, Reactor Trip System Instrumentation. (Function 14, Steam Generator Water Level Low-Low)

LCO 3.3.2.I, ESFAS Instrumentation. (Function 5.b, SG Water Level High-High P-14)

LCO 3.3.2.D, ESFAS Instrumentation. (Function 6.c, Steam Generator Water Level Low-Low)

US 12. INITIATE a Condition Report per STA-421.

When Technical Specifications are addressed, or at Lead Examiners discretion, PROCEED to Event 6.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6 Page 21 of 39 Event

Description:

N-36 fails mid-scale Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Event 6 (Key 6).

- N-36 fails to 7.6 e-5 Indications Available:

N-36 indication diverges away from N-35 and raises higher Examiner Note: This failure will prevent the SR detectors from auto energizing after the reactor trip and the RO will need to take action at that time to energize the Source Range instruments.

RO RESPOND to Annunciator Alarm Procedures.

RO RECOGNIZE N-36 IR detector has failed mid-scale (higher than N-35)

US DIRECT entry into ABN-702, IR Instrument Malfunction Section 2.3 US/RO 1. VERIFY Reactor - NOT TRIPPED - NO

2. VERIFY Actual Reactor Power - GREATER THAN P-6 SETPOINT RO (1X10-10amps) - YES

3. VERIFY Reactor Power - GREATER THAN P-10 SETPOINT (10%) -

RO NO CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 6 Page 22 of 39 Event

Description:

N-36 fails mid-scale Time Position Applicants Actions or Behavior US 3. RNO - PERFORM action of TS 3.3.1F (TS 3.3.1.4).

Simulator Operator: When contacted as the SM for direction on moving power (based on TS statements) inform US to raise power to greater than 10% (P-10)

4. VERIFY Reactor Power reduction - NOT IN PROGRESS OR US REQUIRED - NO Simulator Operator: When contacted as the prompt team, acknowledge the request.

5. REFER to Technical Specifications listed in section 3.1 of this US procedure.

3.3.1.F Reactor Trip System Instrumentation (Function 4 -

Intermediate Range Neutron Flux)

US 6. REFER to EPP-201 US 7. INITIATE a Condition Report per STA-421, as applicable.

When Technical Specifications are addressed, or at Lead Examiners discretion, PROCEED to Events 7, 8, 9, and 10.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7, 8, 9, & 10 Page 23 of 39 Event

Description:

Spurious Train B Safety Injection Actuation Signal / Automatic Reactor Trip Failure / Containment Spray Pump 1-04 fails to start on the SI Sequencer / Small Break Loss of Coolant Accident Time Position Applicants Actions or Behavior Simulator Operator: When directed, EXECUTE Events 7, 8, 9, and 10 (Key 7).

- RP14B, Spurious Train B Safety Injection Actuation Signal.

- RP01, Automatic Reactor Trip failure.

- CS02H, Containment Spray Pump 1-04 fails to start on SI Sequencer

- RC08C1, SBLOCA inside Cont. when SIP 1-02 is secured in EOS-1.1A.

Indications Available:

Main Turbine trip Both MFP trip Multiple Spurious Train B Safety Injection System Alarms Reactor power stable at pre-event values DRPI lights showing rods withdrawn RO/BOP RECOGNIZE Train B Safety Injection Actuation.

RO/BOP DETERMINE Reactor Trip required but NOT tripped.

CRITICAL TASK Manually Trip Reactor Due to Reactor Protection System Failure Prior STATEMENT to Exiting EOP-0.0A, Reactor Trip or Safety Injection.

CT-1 RO/BOP Manually INITIATE a Reactor Trip.

PLACE 1/1-RTC, RX TRIP Switch in TRIP at CB-07.

PLACE 1/1-RT, RX TRIP Switch in TRIP at CB-10.

US DIRECT entry into EOP-0.0A, Reactor Trip or Safety Injection RO 1. VERIFY Reactor Trip:

a. Verify the following:

Reactor trip breakers - AT LEAST ONE OPEN Neutron flux - DECREASING

b. All control rod position rod bottom lights - ON

2. VERIFY Turbine Trip:

BOP All HP turbine stop valves - CLOSED CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7, 8, 9, & 10 Page 24 of 39 Event

Description:

Spurious Train B Safety Injection Actuation Signal / Automatic Reactor Trip Failure / Containment Spray Pump 1-04 fails to start on the SI Sequencer / Small Break Loss of Coolant Accident Time Position Applicants Actions or Behavior

3. VERIFY Power to AC Safeguards Buses:

a. AC safeguards busses - AT LEAST ONE ENERGIZED BOP AC safeguards bus voltage- 6900 Volts(6500-7100 Volts)

b. AC safeguards busses - BOTH ENERGIZED Examiner Note: Safety Injection must be manually actuated to place both Trains in service.

4. CHECK SI status:

a. Check If SI Is Actuated:

SI actuation as indicated on the First Out Annunciator 1-ALB-6C - YES SI Actuated blue status light - ON (Flashing)

RO

b. Verify Both Trains SI Actuated:

SI Actuated blue status light - ON NOT FLASHING -

NO

b. RNO - Manually Actuate SI - PLACE 1/1-SIA2, SI MAN ACT Switch to ACT position at CB-07 Examiner Note: EOP-0.0A, Attachment 2 steps performed by the BOP are identified on Page 35 of the Scenario Guide.

US/BOP 5. INITIATE Proper Safeguards Equipment Operation Per Attachment 2 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7, 8, 9, & 10 Page 25 of 39 Event

Description:

Spurious Train B Safety Injection Actuation Signal / Automatic Reactor Trip Failure / Containment Spray Pump 1-04 fails to start on the SI Sequencer / Small Break Loss of Coolant Accident Time Position Applicants Actions or Behavior

6. VERIFY AFW Alignment:

a. MDAFW Pumps - RUNNING - YES RO b. TDAFW Pump -RUNNING IF NECESSARY

c. AFW total flow - GREATER THAN460 GPM

d. AFW valve alignment - PROPER ALIGNMENT RO 7. VERIFY Containment Spray NOT Required:

a. Containment pressure - HAS REMAINED LESS THAN 18.0 PSIG - YES 1-ALB-2B window 1-8, CS ACT - NOT ILLUMINATED 1-ALB-2B window 4-11, CNTMT ISOL PHASE B ACT

- NOT ILLUMINATED Containment Pressure - LESS THAN 18.0 PSIG

b. Verify containment spray heat exchanger out valves -

CLOSED

c. Verify containment spray pumps - RUNNING - ONLY 3

c. RNO - Manually start pump(s) - Started 1-04 RO 8. CHECK if Main Steam lines should be ISOLATED:

a. Verify the following:

Containment pressure - GREATER THAN 6.0 PSIG Steamline pressure - LESS THAN 610 PSIG

b. Verify main steam isolation complete:

Main Steam isolation valves Before MSIV drippot isolation valves RO 9. CHECK RCS Temperature:

RCS AVERAGE TEMPERATURE STABLE AT OR TRENDING TO 557°F CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7, 8, 9, & 10 Page 26 of 39 Event

Description:

Spurious Train B Safety Injection Actuation Signal / Automatic Reactor Trip Failure / Containment Spray Pump 1-04 fails to start on the SI Sequencer / Small Break Loss of Coolant Accident Time Position Applicants Actions or Behavior Examiner Note: With an inadvertent SI the PRZR will fill up and the PORV will lift due to injection.

RO 10. CHECK PRZR Valve Status:

a. PRZR Safeties - CLOSED

b. Normal PRZR Spray Valves - CLOSED

c. PORVs - CLOSED

d. Power to at least 1 Block Valve - AVAILABLE

e. Block Valves - AT LEAST ONE OPEN RO 11. CHECK If RCPs Should Be Stopped:

a. RCS subcooling - LESS THAN 25°F (55°F FOR ADVERSE CONTAINMENT) - NO

b. RNO - GO to Step 12 US/RO 12. CHECK if any SG is Faulted: - NO

a. Check pressures in all SGs:

ANY SG PRESSURE DECREASING IN AN UNCONTROLLED MANNER ANY SG COMPLETELY DEPRESSURIZED

a. RNO - Go to Step 13 RO/BOP 13. CHECK if Steam Generator Tubes Are NOT Ruptured: - YES not ruptured Condenser Off Gas radiation - NORMAL Main Steam Line radiation - NORMAL SG Blowdown Sample Radiation Monitor - NORMAL NO Steam Generator level increasing in an uncontrolled manner RO/BOP 14. CHECK if RCS is Intact: - YES Containment pressure - LESS THAN 1.3 PSIG Containment recirculation sump levels - NORMAL Containment radiation - NORMAL GRID 4 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7, 8, 9, & 10 Page 27 of 39 Event

Description:

Spurious Train B Safety Injection Actuation Signal / Automatic Reactor Trip Failure / Containment Spray Pump 1-04 fails to start on the SI Sequencer / Small Break Loss of Coolant Accident Time Position Applicants Actions or Behavior US/RO 15. CHECK if ECCS Flow to Should Be Reduced: - YES

a. Secondary heat sink:

Narrow range level in at least one SG -

GREATERTHAN 43%

Total AFW flow to SGs - GREATER THAN 460 GPM

b. RCS subcooling - GREATER THAN 25°F

c. RCS pressure - STABLE OR INCREASING

d. PRZR level - GREATER THAN 13%

e. Go to EOS-1.1A, SAFETYINJECTION TERMINATION, Step 1.

Examiner Note: EOS-1.1A, Safety Injection Termination steps begin here.

Examiner Note: The US will handoff Attachment 1.D here to the RO, the steps are the same as the first steps of this procedure.

BOP 1. CHECK if Diesels Should Be Emergency Started:

a. CHECK diesel generator(s) - RUNNING

b. PLACE both Diesel EMER START/STOP handswitches in START Examiner Note: When Safety Injection is properly RESET, Annunciator 1-ALB-2B, Window 2.8, SFGD SEQR TRN A/B AUTO TEST TRBL, will RESET.

BOP 2. RESET SI.

DEPRESS 1/1-SIRA, TRAIN A SI RESET pushbutton DEPRESS 1/1-SIRB, TRAIN A SI RESET pushbutton CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7, 8, 9, & 10 Page 28 of 39 Event

Description:

Spurious Train B Safety Injection Actuation Signal / Automatic Reactor Trip Failure / Containment Spray Pump 1-04 fails to start on the SI Sequencer / Small Break Loss of Coolant Accident Time Position Applicants Actions or Behavior BOP 3. RESET SI Sequencers.

At SI Sequencer Train A Cabinet, DEPRESS SI SEQR RESET green pushbutton then PLACE ON/RESET toggle switch in RESET After ~ 2 seconds, PLACE ON/RESET toggle switch in ON At SI Sequencer Train B Cabinet, DEPRESS SI SEQR RESET green pushbutton then PLACE ON/RESET toggle switch in RESET After ~ 2 seconds, PLACE ON/RESET toggle switch in ON BOP 4. RESET Containment Isolation Phase A and B.

DEPRESS 1/1-C1PARA, CNTMT ISOL - PHASE A RESET pushbutton DEPRESS 1/1-C1PARB, CNTMT ISOL - PHASE A RESET pushbutton DEPRESS 1/1-C1PBRA, CNTMT ISOL - PHASE B RESET pushbutton DEPRESS 1/1-C1PBRB, CNTMT ISOL - PHASE B RESET pushbutton BOP 5. RESET Containment Spray Signal.

DEPRESS 1/1-CSRA, TRAIN A CS RESET pushbutton DEPRESS 1/1-CSRB, TRAIN B CS RESET pushbutton

6. ESTABLISH Instrument Air and Nitrogen to Containment.

a. ESTABLISH instrument air VERIFY air compressor running Establish instrument air to containment OPEN RO/BOP 1-HS-3487

b. ESTABLISH Nitrogen Verify ACCUM 14 VENT CTRL, 1-HC-943 -

CLOSED Open SI/PORV ACCUM N2 ISOL VLV, 1/1-8880 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7, 8, 9, & 10 Page 29 of 39 Event

Description:

Spurious Train B Safety Injection Actuation Signal / Automatic Reactor Trip Failure / Containment Spray Pump 1-04 fails to start on the SI Sequencer / Small Break Loss of Coolant Accident Time Position Applicants Actions or Behavior Examiner Note: The US will handoff Attachment 1.J here to the RO, the following steps are the same.

RO 7. STOP all but one CCP and PLACE in Standby.

US/RO 8. CHECK RCS Pressure - STABLE OR INCREASING.

RO 9. ISOLATE CCP Injection Line Flow Path:

a. Check CCP - SUCTION ALIGNED TO RWST

b. Open CCP miniflow valves:

1/1-8110 1/1-8111

c. Close the CCP injection line isolation valves:

1/1-8801A 1/1-8801B RO 10. ESTABLISH Charging Flow Path:

a. OPEN charging line isolation valves, 1/1-8105 and 1/1-8106

b. ADJUST Charging Flow Control Valve to establish Charging flow

c. ADJUST RCP seal flow to maintain between 6 GPM and 13 GPM

d. CLOSE CCP alternate Miniflow isolation valves, 1/1-8511A and 1/1-8511B RO 11. CONTROL Charging Flow to maintain PRZR Level.

Examiner Note: When Safety Injection Pump 1-02 is stopped, a Small Break Loss of Coolant Accident will occur. EOS-1.1A. Attachment 1.A criteria requires entry into EOP-1.0A, Loss of Reactor or Secondary Coolant, if RCS subcooling or Pressurizer level cannot be maintained.

RO 12. CHECK IF SI Pumps Should Be Stopped:

a. CHECK RCS pressure Pressure - STABLE OR INCREASING Pressure - GREATER THAN 1700 PSIG (1800 PSIG FOR ADVERSE CONTAINMENT)

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7, 8, 9, & 10 Page 30 of 39 Event

Description:

Spurious Train B Safety Injection Actuation Signal / Automatic Reactor Trip Failure / Containment Spray Pump 1-04 fails to start on the SI Sequencer / Small Break Loss of Coolant Accident Time Position Applicants Actions or Behavior

b. STOP SI pumps and PLACE in standby Examiner Note: The US should use Attachment 1.A of EOS-1.1A here to restart ECCS pumps and line up the CVCS system back up for injection.

Examiner Note: EOP-1.0A, Loss of Reactor or Secondary Coolant, steps begin here.

Examiner Note: When EOP-1.0A is entered, RCS subcooling has not lowered to the point where the RCPs must be tripped, however, this is a Foldout Page Action on Step 1 of EOP-1.0A, Attachment 1.A, and must be performed when conditions are met.

Trip Reactor Coolant Pumps within 5 minutes upon a Loss of CRITICAL TASK STATEMENT Subcooling per EOP-1.0A, Loss of Reactor or Secondary Coolant, Foldout Page.

Subcooling less than 25°F Start Time: ____________

RCPs Tripped Stop Time: ____________

CT-2 RO 1. CHECK If RCPs Should Be Stopped:

a. RCS subcooling - LESS THAN 25°F (55°F FOR ADVERSE CONTAINMENT)

b. ECCS pumps - AT LEAST ONE RUNNING CCP SI Pump

c. Stop all RCPs.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7, 8, 9, & 10 Page 31 of 39 Event

Description:

Spurious Train B Safety Injection Actuation Signal / Automatic Reactor Trip Failure / Containment Spray Pump 1-04 fails to start on the SI Sequencer / Small Break Loss of Coolant Accident Time Position Applicants Actions or Behavior RO/BOP 2. CHECK if Any Steam Generator Is Faulted:

a. Check pressures in all SGs ANY SG PRESSURE DECREASINGIN AN UNCONTROLLED MANNER ANY SG COMPLETELY DEPRESSURIZED

b. Verify all faulted SG(s)isolated:

Steamlines Feedlines Blowdown and sample lines BOP 3. CHECK Intact Steam Generator Levels:

a. Narrow range level - GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT)

b. Control AFW flow to maintain narrow range level between 43% (50% FOR ADVERSE CONTAINMENT) and 60%

BOP 4. CHECK Secondary Radiation NORMAL:

Condenser Off Gas radiation (COG-182, 1RE-2959)

Main steamline radiation (MSL-178 through 181, 1RE-2325 through 2328)

SG blowdown sample radiation monitor (SGS-164, 1RE-4200)

RO 5. CHECK PRZR PORVs and Block Valves:

a. Power to block valves - AVAILABLE

b. PORVs - CLOSED

c. Block valves - AT LEAST ONE OPEN CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7, 8, 9, & 10 Page 32 of 39 Event

Description:

Spurious Train B Safety Injection Actuation Signal / Automatic Reactor Trip Failure / Containment Spray Pump 1-04 fails to start on the SI Sequencer / Small Break Loss of Coolant Accident Time Position Applicants Actions or Behavior US/RO 6. CHECK if ECCS Flow Should Be Reduced: - NO

a. Secondary heat sink:

Total AFW flow to intact SGs - GREATER THAN 460 GPM Narrow range level in at least one intact SG -

GREATER THAN 43% (50% FOR ADVERSE CONTAINMENT)

b. RCS subcooling - GREATER THAN 25°F(55°F FOR ADVERSE CONTAINMENT) - NO

c. RCS pressure - STABLE OR INCREASING - NO

d. PRZR level - GREATER THAN 13% (34% FOR ADVERSE CONTAINMENT) - NO

b. RNO - Go to Step 7. Observe cautions prior to step 7 RO/BOP 7. RESET ESF Actuation Signals:

a. Check diesel generator(s) - RUNNING

b. Place D/G EMER STOP/START handswitch(es) in START

c. Reset SI.

d. Reset SI Sequencers.

e. Reset Containment Isolation Phase A and Phase B.

f. Reset containment spray signal.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7, 8, 9, & 10 Page 33 of 39 Event

Description:

Spurious Train B Safety Injection Actuation Signal / Automatic Reactor Trip Failure / Containment Spray Pump 1-04 fails to start on the SI Sequencer / Small Break Loss of Coolant Accident Time Position Applicants Actions or Behavior US 8. CHECK If RHR Pumps Should Be Stopped: - YES

a. Check RCS pressure:

RCS pressure - GREATER THAN 325 PSIG (425 PSIG FOR ADVERSE CONTAINMENT)

RCS pressure - STABLE OR INCREASING

b. RHR pumps - ANY RUNNING WITH SUCTION ALIGNED TO RWST

c. Stop RHR pumps and place in standby.

d. Reset RHR auto switchover.

US 9. CHECK RCS and SG Pressures:

Check RCS Pressure - STABLE OR DECREASING Check Pressure in All SGs - STABLE OR INCREASING US 10. CHECK If Diesel Generators Should Be Stopped:

a. Verify AC safeguard busses - ENERGIZED BY OFFSITE POWER

b. Stop any unloaded diesel generator by placing DG EMER STOP/START handswitch in STOP.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # 7, 8, 9, & 10 Page 34 of 39 Event

Description:

Spurious Train B Safety Injection Actuation Signal / Automatic Reactor Trip Failure / Containment Spray Pump 1-04 fails to start on the SI Sequencer / Small Break Loss of Coolant Accident Time Position Applicants Actions or Behavior US 11. INITIATE Evaluation of Plant Status.

a. Verify cold leg recirculation capability:

1) Verify the following conditions for the train related RHR pump(s):

TRAIN A RHR pump A - AVAILABLE CCW to RHR pump A - AVAILABLE 1/1-8811A, CNTMT SMP TO RHRP 1 SUCT ISOL VLV - AVAILABLE TRAIN B RHR pump B - AVAILABLE CCW to RHR pump B - AVAILABLE 1/1-8811B, CNTMT SMP TO RHRP 2 SUCT ISOL VLV - AVAILABLE

2) Verify RHR valve(s) that supply SI pumps and CCPs -

AVAILABLE 1/1-8804A, RHRP 1 TO CCPSUCT VLV 1/1-8804B, RHRP 2 TO SIP SUCT VLV

11. INITIATE Evaluation of Plant Status. - Continued

b. Check auxiliary building and safeguards building radiation -

NORMAL Check PC-11 monitors (GRID 4) - NORMAL Notify Radiation Protection to take local radiation US surveys.

c. Notify Chemistry to obtain RCS samples to assist in determining extent of the accident.

d. Evaluate plant equipment:

Consult Plant Staff to determine equipment that should be available or started to assist in recovery.

12. CHECK if RCS Cooldown and Depressurization Is Required:

a. RCS pressure - GREATER THAN 325 PSIG (425 PSIG FOR US ADVERSE CONTAINMENT)

b. Go to EOS-1.2A, POST LOCA COOLDOWN AND DEPRESSURIZATION, Step 1.

When transition to EOS-1.2 A, Post LOCA Cooldown and Depressurization is reached, terminate the scenario.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # Att. 2 Page 35 of 39 Event

Description:

EOP-0.0A, Attachment 2 Time Position Applicants Actions or Behavior Examiner Note: These steps are performed by the BOP per EOP-0.0A, Attachment 2.

BOP 1. VERIFY SSW Alignment:

a. VERIFY SSW Pumps - RUNNING.

b. VERIFY EDG Cooler SSW Return Flow.

BOP 2. VERIFY Safety Injection Pumps - RUNNING.

BOP 3. Verify Containment Isolation Phase A - APPROPRIATE MLB LIGHT INDICATION (RED WINDOWS).

BOP 4. Verify Containment Ventilation Isolation - APPROPRIATE MLB LIGHT INDICATION (GREEN WINDOWS).

BOP 5. VERIFY CCW Pumps - RUNNING.

BOP 6. VERIFY RHR Pumps - RUNNING.

BOP 7. VERIFY Proper CVCS Alignment:

a. VERIFY CCPs - RUNNING.

b. VERIFY Letdown Relief Valve Isolation:

1. Letdown Orifice Isolation Valves - CLOSED.

2. Letdown Isolation Valves 1/1-LCV-459 & 1/1-LCV-460 -

CLOSED.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # Att. 2 Page 36 of 39 Event

Description:

EOP-0.0A, Attachment 2 Time Position Applicants Actions or Behavior BOP 8. VERIFY ECCS flow:

a. CCP SI flow indicator - CHECK FOR FLOW.

b. RCS pressure - LESS THAN 1700 PSIG (1800 PSIG FOR ADVERSE CONTAINMENT).

c. SIP discharge flow indicator - CHECK FOR FLOW.

d. RCS pressure - LESS THAN 325 PSIG (425 PSIG FOR ADVERSE CONTAINMENT).

d. RNO - GO to Step 9.

BOP 9. VERIFY Feedwater Isolation Complete:

Feedwater Isolation Valves - CLOSED.

Feedwater Isolation Bypass Valves - CLOSED.

Feedwater Bypass Control Valves - CLOSED.

Feedwater Control Valves - CLOSED.

BOP 10. VERIFY Diesel Generators - RUNNING.

BOP 11. VERIFY Monitor Lights for SI Load Shedding on 1-MLB-9 and 1-MLB10 - LIT.

BOP 12. VERIFY Proper SI alignment - PROPER MLB LIGHT INDICATION.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # Att. 2 Page 37 of 39 Event

Description:

EOP-0.0A, Attachment 2 Time Position Applicants Actions or Behavior BOP 13. Verify components on Table 1 are properly aligned:

Unit 1 Main Component Equipment Description Condition Control Board Location Number CB-03 X-HS-5534 H2 PRG SPLY FN 4 STOPPED CB-03 X-HS-5532 H2 PRG SPLY FN 3 STOPPED CB-04 1/1-8716A RHRP 1 XTIE VLV OPEN CB-04 1/1-8716B RHRP 2 XTIE VLV OPEN CB-06 1/1-8153 XS LTDON ISOL VLV CLOSED/H.S. IN CLOSED CB-06 1/1-8154 XS LTDON ISOL VLV CLOSED/H.S. IN CLOSED CB-07 1/1 RTBAL RX TRIP BKR OPEN CB-07 1/1 RTBBL RX TRIP BKR OPEN CB-07 1/1 BBAL RX TRIP BYB BKR OPEN/DEENERGIZED CB-07 1/1 BBBL RX TRIP BYB BKR OPEN/DEENERGIZED CB-08 1-HS-2397A SG 1 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2398A SG 2 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2399A SG 3 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2400A SG 4 BLDN HELB ISOL VLV CLOSED CB-08 1-HS-2111C FWPT A TRIP TRIPPED CB-08 1-HS-2112C FWPT B TRIP TRIPPED CB-09 1-HS-2490 CNDS XFER PUMP STOPPED (MCC DEENERGIZED ON SI)

Ventilation Component Equipment Description Condition Panels Location Number CV-01 X-HS-6181 PRI PLT SYPLY FN 17 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6188 PRI PLT SYPLY FN 18 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6195 PRI PLT SYPLY FN 19 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6202 PRI PLT SYPLY FN 20 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6209 PRI PLT SYPLY FN 21 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6216 PRI PLT SYPLY FN 22 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6223 PRI PLT SYPLY FN 23 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6230 PRI PLT SYPLY FN 24 & INTK DMPR STOPPED/DEENERGIZED CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 4 Event # Att. 2 Page 38 of 39 Event

Description:

EOP-0.0A, Attachment 2 Time Position Applicants Actions or Behavior CV-01 X-HS-3631 UPS & DISTR RM A/C FN 1 & BSTR FN 42 STARTED CV-01 X-HS-3632 UPS & DISTR RM A/C FN 2 & BSTR FN 43 STARTED CV-01 X-HS-5600 ELEC AREA EXH FN 1 STOPPED/DEENERGIZED CV-01 X-HS-5601 ELEC AREA EXH FN 2 STOPPED/DEENERGIZED CV-01 X-HS-5602 MS & FW PIPE AREA EXH FN 3 & EXH STOPPED/DEENERGIZED DMPR CV-01 X-HS-5603 MS & FW PIPE AREA EXH FN 4 & EXH STOPPED/DEENERGIZED DMPR CV-01 X-HS-5618 MS & FW PIPE AREA SYLY FN 17 STOPPED/DEENERGIZED CV-01 X-HS-5620 MS & FW PIPE AREA SYLY FN 18 STOPPED/DEENERGIZED 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 Unit 2 Main Component Equipment Description Condition Control Board Location Number CV-03 2-HS-5538 AIR PRG EXH ISOL DMPR CLOSED CV-03 2-HS-5539 AIR PRG EXH ISOL DMPR CLOSED CV-03 2-HS-5537 AIR PRG EXH ISOL DMPR CLOSED CV-03 2-HS-5536 AIR PRG EXH ISOL DMPR CLOSED Notify Unit Supervisor attachment instructions complete AND to implement FRGs as required.

CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

Scenario Event Description NRC Scenario 1

2016 NRC Scenario 4

Rev. 1

Initialize to IC-48

Event 1 - Instrument Air Compressor 1-01 Trip/1-02 Failure to Start

IAC 1-01 Trip IMF IA06A f: 1 k:1

IAC 1-02 Does not auto start IOR DIIAHS3463 f: 1

IAC 1-02 Starts when taken to manual start

{DIIAHS3463.Value=4} DOR DIIAHS3463

Event 2 - Raise Power to 6 to 8%

Event 3 - Main Steam Header Pressure Failure

PT-507 Fails High IMF RX12 f: 1500 r:360 k:3

Event 4 - TPCW Pump 1 Trip, Pump 2 Auto Start Failure

TPCW Pump 1 Trip IMF TP06A f: 1 k:4

TPCW Pump 2 Auto Start Failure IMF TP07B f: 1

Event 5 - Steam Generator 1-01 Level Channel Failure

LT-551 Fails Low IMF RX04A f: 0 k:5

Event 6 - Intermediate Range Channel N-36 Fails High IMF NI02B f: 7.6e-5 k:6

Event 7 - Spurious Train B Safety Injection

Spurious Train B SI IMF RP14B f: 1 k:7

Event 8 - Reactor Automatic Trip Failure

Rx Auto Trip Failure IMF RP01 f: 1

Event 9 - Containment Spray Pump 1-04 Fail to Start

CT Pump 1-04 Fail to Start on SIS IMF CS02H f: 1

Event 10 - SBLOCA during SI Termination

Loop 3 SBLOCA

{DISIAPSI2.Value=1} IMF RC08C1 f:1 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1

ML16293A974

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5.3.7 Standard

5.3.8 Standard

5.3.9 Standard

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