Revision as of 07:02, 10 April 2019

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 CPNPP 2016 NRC JPM RA1 (RO1307D) Rev. 0 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:

Appendix C JPM STEPS Form ES-C-1 CPNPP 2016 NRC JPM RA1 (RO1307D) Rev. 0 CLASSROOM SETUP Handout: PROVIDE the examinee with a copy of: SOP-104A, Reactor Make-up and Chemical Control System. Attachment 2, BOL Borati on for Long-Term Use Page 1. (labeled Procedure 1)

A ppendi x - Che c Examin Examin Perfor m 1.0 Standa r Comm e Perfor m 2.A Standa r Comm e x C c k Mark D e er Note: er Note: m Step: 1 r d: e nt: m Step: 2 r d: e nt: C e notes Cri t The fol Refer t o RECO R R B B ENTE R CALC U R CALC U first cal c C PNPP 201 6 t ical Step lowing st e o answer k R D Refere n RCS Boron BAT Boron B 10 WT Fr a R ED data o n ULATE volu R CS Corre c ULATED 15 c ulation an JPM STE P 6 NRC JPM e ps are f ro key for cal c n ce Data a s ___ ___a ction ___n Attachm e mes in pot c ted Boron:12.5 +/- 0.1

.d then per f P SRA1 (RO1 3 S Tm SOP-10 4 culated v a s follows:

________ ________ ________ e nt 2 at Ste p settings a s: [allowable forming se c 3 07D)T ART TIM E 4 A, A ttac h a lues. p 1.0 S A s follows:

error base c ond calcul a S A F o E: h ment 2 p a A T UN S d on round ation] A T UN S orm ES-C-1 Rev. 0 a ge 1 S AT ing after S AT 0 A ppendi x Perfor m 2.B Standa r Comm e Perfor m 2.C Standa r Comm e Perfor m 2.D Standa r Comm e x C m Step: 3 r d: e nt: m Step: 4 r d: e nt: m Step: 5 r d: e nt: C CALC U G V CALC U roundi n CALC U B CALC U CALC U B CALC U accura c C PNPP 201 6 ULATE volu G allons of R V CT make u ULATED 13 ng carried f r ULATE volu B oron gallo ULATED 10 ULATE volu B oric Acid P ULATED 4.6 c y of Pot s e JPM STE P 6 NRC JPM mes in pot R MUW to o u p: 2.75 +/- 0.2 g r om Step 2 mes in pot ns for a M a.4 +/- 0.1 ga mes in pot P ot Setting 6 9 +/- 0.1. [a e ttings] P SRA1 (RO1 3 settings a s o ffset boro n gallons. [a and those settings a s a nual Blen d llons. [allo w settings a sfor a Man u llowable er 3 07D)s follows:

n in Blende r a llowable e r performed S A s follows:

d: w able error S A s follows:

u al Blend:

r ror based o S A F o r Pipe duri n r ror based o in this ste p A T UN S based on r A T UN S o n roundin g A T UN S orm ES-C-1 Rev. 0 n g normal o n p] S AT r ounding] S AT g and S AT 0 A ppendi x Perfor m 2.E Standa r Comm e Perfor m 2.F Standa r Termin a Comm e x C m Step: 6 r d: e nt: m Step: 7 r d: ating Cue:

e nt: C CALC U B CALC U accura c CALC U G M CALC U carried This J P C PNPP 201 6 ULATE volu B oric Acid P ULATED 6.6 c y of Pot s e ULATE volu G allons of R M akeup Sy s ULATED 86from Step 2 PM is com p JPM STE P 6 NRC JPM mes in pot P ot Setting 6 2 +/- 0.1. [a e ttings] mes in pot R MUW to o stem to Au t.5 +/- 0.2 ga 2 and thos e p lete. P SRA1 (RO1 3 settings a s for AUTO M llowable er settings a s o ffset boro n t omatic: llons. [allo w e performe d S 3 07D)s follows:

M akeup: r ror based o S A s follows:

n in Blende r wable erro r d in this st e S A S TOP TIM E F o o n roundin g A T UN S r Pipe whe n r based on e p] A T UN S E: orm ES-C-1 Rev. 0 g and S AT n returning rounding S AT 0 Appendix C JPM CUE SHEET Form ES-C-1 CPNPP 2016 NRC JPM RA1 (RO1307D) Rev. 0 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

ATTACHMENT 2PAGE 1 OF 7BOL BORATION FOR LONG TERM USECPNPP SYSTEM OPERATING PROCEDURE MANUALUNIT 1PROCEDURE NO.SOP-104AREACTOR MAKE-UP AND CHEMICAL CONTROL SYSTEMREVISION NO. 15PAGE 75 OF 82lCONTINUOUS USEThis attachment describes the steps to periodically add boron to the RCS at BOL while keeping thesystem 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 RCSBoron Concentration must be < 1600 ppm to use this attachment. 1.0RECORD Reference Data as follows:

Q! RCS Boron

! BAT Boron

! B10 Wt Fraction 2.0CALCULATE volumes and pot settings as follows:A.RCS Corrected Boron:

RCS PPM X B-10 Wt Fraction = 0.1834 RCS (c) PPM BORONCorrectedB.Gallons of RMUW to offset boron in Blender Pipe for Normal VCT Makeup:

BAT PPM X 35 GAL - 35 GAL = RCS(c) BORON BORON 1-FY-111B, RMUW Gallons to Offset Boron in Blender PipeC.Boron gallons for a Manual Blend:50 Total Gallons X RCS(c)

= BAT PPM 1-FY-110B, Boron Gallons for Manual BlendD.Boric Acid Pot Setting for a Manual Blend:90 Total Flowrate X RCS(c)

= 4 BAT PPM 1-FK-110, BA Pot Setting for

Manual Blend E. Boric Acid Pot Setting for AUTO Makeup:127 Total Flowrate X RCS(c)

= 4 BAT PPM 1-FK-110, BA Pot Setting forAuto MakeupF.Gallons of RMUW to offset boron in Blender Pipe when returning Makeup System to Automatic: BAT PPM X 22.8 GAL - 22.8 GAL = RCS(c) BORON BORON 1-FY-111B, RMUW Gallons toOffset Boron in Blender Pipewhen returning to Automatic Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 5 CPNPP 2016 NRC JPM RA2 (RO1310E) REV. 0 Facility: CPNPP JPM # NRC RA2 Task # RO1310 K/A # 2.1.43 4.1 / 4.3 Title: Determine Reactivity Effects When St arting 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 5 CPNPP 2016 NRC JPM RA2 (RO1310E) REV. 0 CLASSROOM SETUP Handout: PROVIDE the examinee with a copy of: SOP-103A, Chemical and Volume C ontrol System, Step 5.3.1.C. (labeled Procedure

1) 90.4 EFPD Reactivity Briefing Sheet. (labeled Handout 1)

A ppendi x Page 3 o - Che c Examin Perfor m 5.3.1.C.calculat i Standa r Comm e Perfor m 5.3.1.C.

calculat i Standa r Comm e Perfor m 5.3.1.C.

calculat i Standa r Comm e x C o f 5 c k Mark D e er Note: m Step: 1 1) + i on r d: e nt: m Step: 2 2).a) + i on r d: e nt: m Step: 3 2).a) + i on r d: e nt: e notes Cri t The fol DETE R due to t CALC UB = ( 2 IF in M O DETE R perfor mB = -1 From t h ITC ___DETE R ITC = - HFP Di fCalcul a ITC / H CALC U- 10.9 p CPNPP 2 0 t ical Step lowing st e R MINE the c t he PDP ru nB = Chan g ULATED B 2 5 ppm P D ODE 1 or 2 R MINE the i m ing the foll

.53 ppm he Reactivi t___ pcm/ºF R MINED th e 10.9 pcm/ºf ferential B a te: FP Differe n ULATED ch a p cm/ ºF / -

7 JPM STE P 016 NRC J P e ps are f ro c hange in R n: g e in RCS B B = Chang e D P - 1222 p p THEN PE R mpact of w owing calc u t y Briefing S F HFP Dif f e following fºF oron Wort h n tial Boron W a nge in pp m 7.0 pcm/pp m P S PM RA2 (R O S Tm SOP-10 3 R CS Boron Boron Con c e in RCS B o pm RCS) x R FOM the w ater in the u lation: Sheet, obt a f erential Bo f rom the R e h = - 7.0 pc W orth = p p m /ºF: m = 0.156 +/-O 1310E) T ART TIM E 3 A, Step 5 concentra t centration d o ron Conc e x 0.00128 =S Afollowing:

PDP pipin g a in the follo w o ron Worth

_e activity B r cm/ppm S A pm / ºF +/- 0.01 pp m S A F o E: .3.1. t ion which w d ue to PD P e ntration:

= -1.53 +/- 0.

0 A T UN S g on reacti v w ing infor m_____ pc m r iefing She e A T UN S m/ºF A T UN S orm ES-C-1 REV. 0 will occur P run 0 1 ppm S AT v ity by the m ation: m/ppm e t: S AT S AT 0 Appendix C JPM STEPS Form ES-C-1 Page 4 of 5 CPNPP 2016 NRC JPM RA2 (RO1310E) REV. 0 Examiner Note: Rounding off of TAVE may occur.

Perform Step: 4 5.3.1.C.2).a) +

calculation Calculate: T AVE = (-1) B ppm / ppm / ºF Standard:

CALCULATED change in T AVE as follows: T AVE = (-1) B ppm / ppm / ºF = (-1)(-1.53 ppm) / 1.56 ppm/ºF =

0.98 +/- 0.02 ºF Comment: SAT UNSAT Perform Step: 5 5.3.1.C.2).b)

IF T AVE calculated above is > 0.5 ºF, THEN NOTIFY the Unit Supervisor and discuss contingency actions.

Standard: DETERMINED T AVE calculated is greater t han 0.5 ºF and NOTIFIED Unit Supervisor. Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Appendix C JPM CUE SHEET Form ES-C-1 Page 5 of 5 CPNPP 2016 NRC JPM RA2 (RO1310E) REV. 0 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.

Appendix C JPM STEPS Form ES-C-1 Page 1 of 6 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 0 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.

Appendix C JPM STEPS Form ES-C-1 Page 2 of 6 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 0 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:

Appendix C JPM STEPS Form ES-C-1 Page 3 of 6 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 0 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

Appendix C JPM STEPS Form ES-C-1 Page 4 of 6 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 0 - 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 ca lculation 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 th at 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 Ra tio 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 th at INTERSECTS with CBD at 10 +/- 50 steps. LOG an Estimated Critical Condition with CBD at 10 +/- 50 steps. Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 Page 5 of 6 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 0 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 Rati o 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 th at 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 ca lculation for Control Bank B at 85 steps and plot on 1/M Data Sheet.

Standard:

CALCULATED Inverse Count Rate Rati o 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 th at 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, 4 th bullet. Perform Step: 5 RECORD any required action based on 1/M Data obtained on , Page 3 of 4 and/or the JPM Cue Sheet.

Standard: DETERMINED Estimated Critical Condition occurs below the Rod Insertion Limit within the next re activity 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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 6 of 6 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 0 INITIAL CONDITIONS: Given the following conditions: Unit 2 is performing a React or 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 pred icted 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: ____________________________________________

ATTACHMENT 2 PAGE 1 OF 4 INVERSE COUNT RATE RATIO CALCULATION CPSESINTEGRATED PLANT OPERATING PROCEDURES MANUALUNIT 2 PROCEDURE NO.

IPO-002BPLANT STARTUP FROM HOT STANDBYREVISION NO. 10PAGE 64 OF 83 NOTE:This calculation is not required when Core Performance Engineering is performing ICRR calculations per NUC-111.1.0PREREQUISITES

!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.2.0LIMITATIONS2.1Rod withdrawal increments should be performed at approximately 50 steps. The Shift Manager mayauthorize withdrawal of rods at any other increment less than 50 steps as the Reactor approaches

criticality.3.0INSTRUCTIONS3.1The 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. Ifcount 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.BFor 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).

ATTACHMENT 2 PAGE 2 OF 4 INVERSE COUNT RATE RATIO CALCULATION CPSESINTEGRATED PLANT OPERATING PROCEDURES MANUALUNIT 2 PROCEDURE NO.

IPO-002BPLANT STARTUP FROM HOT STANDBYREVISION NO. 10PAGE 65 OF 833.3The 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 CountsG.Plot the ICRR values at the appropriate rod position on graph paper similar to the one attached.3.4Perform a linear extrapolation of the ICRR plot, using the last two data points, to the point at which theextrapolation intersects the horizontal axis. This point defines the rod position at which criticality is estimated.3.5List rod position estimation on the ICRR worksheet.

3.6Continue to perform Steps 3.3 thru 3.5 until either of the following occurs:A.The Reactor is critical ORB.The Shift Manager terminates ICRR data collection.

ATTACHMENT 2 PAGE 3 OF 4 INVERSE COUNT RATE RATIO CALCULATION CPSESINTEGRATED PLANT OPERATING PROCEDURES MANUALUNIT 2 PROCEDURE NO.

IPO-002BPLANT STARTUP FROM HOT STANDBYREVISION NO. 10PAGE 66 OF 83N-31N-32AVEAVEICRRICRRBANKATSTEPSECCBANK STEPECCBANK STEPREFERENCEN-31COUNTSN-32AVEAVEN-31N-32AVE AVEICRRICRRBANKATSTEPSECCBANK STEPECCBANK STEPN-31N-32 AVE AVEICRRICRRBANKATSTEPSECCBANKSTEP ECCBANK STEPN-31N-32AVEAVE ICRRICRRBANKATSTEPSECCBANK STEPECCBANK STEPN-31N-32AVEAVE ICRRICRRBANKATSTEPSECCBANK STEPECCBANK STEP INVERSE COUNT RATE RATIO Estimated Critical Condition:Bank at steps Boron Concentration ppm Completed by Date Time ATTACHMENT 2 PAGE 4 OF 4 INVERSE COUNT RATE RATIO CALCULATION CPSESINTEGRATED PLANT OPERATING PROCEDURES MANUALUNIT 2 PROCEDURE NO.

IPO-002BPLANT STARTUP FROM HOT STANDBYREVISION NO. 10PAGE 67 OF 83 1/M D A T A S H E E T IC R R 1.0.9.8.7.6.5.4.3.2.1 0 0100200300400500565 01 0050207035850555105155205 G P 'A'G P 'C'G P 'B'G P 'D'01 00 50 15020025030035040045050055060 0

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0 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 cm 2 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

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0 Comments:

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

Appendix C JPM WORKSHEET Form ES-C-1 Page 3 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0 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.

Appendix C JPM STEPS Form ES-C-1 Page 4 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0 - 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 loca ted 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 Requ irements 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 contami nation level in dpm/100 cm 2 for the room.

Standard:

IDENTIFIED the highest cont amination level in dpm/100 cm 2 for the room is < 1000 dpm/100 cm

2. Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 Page 5 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0 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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 6 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0 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 Sa feguards 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 Monitori ng Requirements to enter the room. DETERMINE the Protective Clothing Requirements to enter the valve area. IDENTIFY the highest contam ination level in dpm/100 cm 2 for the room. IDENTIFY the highest dose rate in mR/hr for the room.

Dose Monitoring Requirements to enter the room:

________________________

_______________

______________

__________________

___________________________________

__________________

___________________________________

Minimum Protective Cl othing Requirements to enter the room:

__________________

___________________________________

__________________

___________________________________

__________________

___________________________________

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

__________________

___________________________________

Highest dose rate in mR/hr for the room:

__________________

___________________________________

Appendix C JPM CUE SHEET Form ES-C-1 Page 6 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 0 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 Sa feguards 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 Monitori ng Requirements to enter the room. DETERMINE the Protective Clothing Requirements to enter the valve area. IDENTIFY the highest contam ination level in dpm/100 cm 2 for the room. IDENTIFY the highest dose rate in mR/hr for the room.

Dose Monitoring Requirements to enter the room:

________________________

_______________

______________

__________________

___________________________________

__________________

___________________________________

Minimum Protective Cl othing Requirements to enter the room:

__________________

___________________________________

__________________

___________________________________

__________________

___________________________________

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

__________________

___________________________________

Highest dose rate in mR/hr for the room:

__________________

___________________________________

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0 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/cm 2 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

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0 Comments:

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

Appendix C JPM WORKSHEET Form ES-C-1 Page 3 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0 CLASSROOM SETUP Handout: PROVIDE the examinee with a copy of: STA-124, Electrical Sa fe Work Practices. (labeled Procedure 1)

Appendix C JPM STEPS Form ES-C-1 Page 4 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0 - 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/cm 2 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 wit h 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 heari ng protection is required. Circled YES Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 Page 5 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0 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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 6 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0 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/cm 2 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

Appendix C JPM CUE SHEET Form ES-C-1 Page 6 of 6 CPNPP 2016 NRC JPM SA1 (SO1028) REV. 0 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/cm 2 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

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 5 CPNPP 2016 NRC JPM SA2 (SO1017B) REV. 0 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 Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 5 CPNPP 2016 NRC JPM SA2 (SO1017B) REV. 0 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 3 of 5 CPNPP 2016 NRC JPM SA2 (SO1017B) REV. 0 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)

Appendix C JPM STEPS Form ES-C-1 Page 4 of 5 CPNPP 2016 NRC JPM SA2 (SO1017B) REV. 0 - 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 Atta chment 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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 5 of 5 CPNPP 2016 NRC JPM SA2 (SO1017B) REV. 0 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

Appendix C JPM CUE SHEET Form ES-C-1 Page 5 of 5 CPNPP 2016 NRC JPM SA2 (SO1017B) REV. 0 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

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 0 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.

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 0 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 3 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 0 CLASSROOM SETUP EXAMINER: PROVIDE the examinee with a copy of: STA-738, Fire Protection Syst ems/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)

Appendix C JPM STEPS Form ES-C-1 Page 4 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 0 - Check Mark Denotes Critical Step START TIME:

Examiner Note: The following in formation 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 WAT CH 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 WAT CH 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 FI RE BRIGADE STRATEGY.

Standard:

DETERMINED that Fire Brigade St rategy is affected and circled YES. Comment: SAT UNSAT

Appendix C JPM STEPS Form ES-C-1 Page 5 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 0 Perform Step: 7 Determine if OTHER compensatory m easure 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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 6 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 0 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.

STA-738-2INFORMATION USEPAGE 1 OF 1 lREV. 7lFIRE 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:

AFFECTED LOCATION: BLDG.

ELEV. ROOM/OTHER PERMIT WORK DESCRIPTION:

lREQUESTED 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:

____ 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

____ AFFECTS FIRE BRIGADE STRATEGY? YES NO l____ OTHER INSTRUCTIONS/ADDITIONAL INFORMATION 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0 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:

JPM Cue Sheet 1 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:

JPM Cue Sheet 1 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 cm 2 for the room. IDENTIFY the highest dose rate in mR/hr for the room.

Initial Conditions:

JPM Cue Sheet 1 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:

JPM Cue Sheet 2 The Shift Manager directs you to PERFORM the following: Determine Oral and Written Reportability Requirements, if any. Oral Reporting Requirement ____________________ Written Reporting Requirement ____________________

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 3 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0 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.

Appendix C JPM STEPS Form ES-C-1 Page 4 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0 - 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 loca ted 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 Requ irements 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 contami nation level in dpm/100 cm 2 for the room.

Standard:

IDENTIFIED the highest cont amination level in dpm/100 cm 2 for the room is < 1000 dpm/100 cm

2. Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 Page 5 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0 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 Attachment 8.D/4 Pages 1 of 12 or 7 of

12 Determine Oral Reporting R equirements per STA-501.

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 Attachment 8.D/4 Pages 1 of 12 or 7 of

12 Determine Written Reporting Requirements per STA-501.

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:

Appendix C JPM CUE SHEET 1 Form ES-C-1 Page 6 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0 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 Sa feguards 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 Monitori ng Requirements to enter the room. DETERMINE the Protective Clothing Requirements to enter the valve area. IDENTIFY the highest contam ination level in dpm/100 cm 2 for the room. IDENTIFY the highest dose rate in mR/hr for the room.

Dose Monitoring Requirements to enter the room:

__________________

___________________________________

__________________

___________________________________

__________________

___________________________________

Minimum Protective Cl othing Requirements to enter the room:

________________________

__________________

___________

__________________

___________________________________

__________________

___________________________________

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

__________________

___________________________________

Highest dose rate in mR/hr for the room:

__________________

___________________________________

Appendix C JPM CUE SHEET 2 Form ES-C-1 Page 7 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 0 Initial Conditions:

JPM Cue Sheet 1 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:

JPM Cue Sheet 2 The Shift Manager directs you to PERFORM the following: Determine Oral and Written Reportability Requirements, if any. Oral Reporting Requirement ____________________ Written Reporting Requirement ____________________

Appendix C JPM CUE SHEET 1 Form ES-C-1 Page 6 of 7 CPNPP 2016 NRC JPM SA4 (SO1112B) REV. 0 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 Sa feguards 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 Monitori ng Requirements to enter the room. DETERMINE the Protective Clothing Requirements to enter the valve area. IDENTIFY the highest contam ination level in dpm/100 cm 2 for the room. IDENTIFY the highest dose rate in mR/hr for the room.

Dose Monitoring Requirements to enter the room: _____________________________________________________ _____________________________________________________

_____________________________________________________

Minimum Protective Cl othing Requirements to enter the room: __________________________________________

___________ _____________________________________________________

_____________________________________________________

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

Highest dose rate in mR/hr for the room: _____________________________________________________

Appendix C JPM CUE SHEET 2 Form ES-C-1 Page 7 of 7 CPNPP 2016 NRC JPM SA4 (SO1112B) REV. 0 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 _______________ Written Reporting Requirement _______________

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0 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 Time: ________ minutes Comments: Result: SAT UNSAT Examiner (Print / Sign): Date:

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0 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)

Appendix C JPM STEPS Form ES-C-1 Page 3 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0 - 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 Appendix C JPM STEPS Form ES-C-1 Page 4 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0 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.

Appendix C JPM STEPS Form ES-C-1 Page 5 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0 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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 6 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0 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 Appendix C JPM CUE SHEET Form ES-C-1 Page 6 of 6 CPNPP 2016 NRC JPM SA5 (SO1136I) REV.0 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 C ontrol Room Annunciators 10 minutes ago. Electrical Maintenance is in vestigating 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

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 8 CPNPP 2016 NRC JPM S-1 (RO1024A) REV. 0 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 8 CPNPP 2016 NRC JPM S-1 (RO1024A) REV. 0 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)

A ppendi x Page 3 o - Che c Examin Perfor m 3.3.14 Standa r Comm e Perfor m 3.3.15.a Standa r Comm e Perfor m 3.3.15.a Standa r Comm e Perfor m 3.3.15.a Standa r Comm e x C o f 8 c k Mark D e er Note: m Step: 1 r d: e nt: m Step: 2 & 1 st line r d: e nt: m Step: 3 & 2 nd line r d: e nt: m Step: 4 & 3 rd line r d: e nt: C e notes Cri t The fol Transf e ROTA T positio n Record A ffe RECO R Record Ban RECO R Record Gro u OBSE R at 215 S C PNPP 201 6 t ical Step lowing st e e r 1/u-RBS S T ED 1/1-R B n. positions f cted Rod (D RDED Rod positions fk (DRPI) _

_RDED Ban kpositions f u p 1 step c R VED 1-S C S teps. JPM STE P 6 NRC JPM e ps are f ro S , CONTR O B SS, CON T f or affected D RPI) ____H8 DRPI a f or affected

____ k CBD DR P f or affected ounter ____C-CBD1, C T P S S-1 (RO10 2 S T m ABN-71 2 O L ROD B A TROL ROD Rod: __ a t 204 Step s Rod: P I at 216 S t Rod: ___ TRL BANK 2 4 A)T ART TIM E 2, Section A NK SELE BANK SE L S A s. S A t eps. S A D GROUP S A F o E: 3.3. CT to affe c L ECT to B a A T UN S A T UN S A T UN S 1 and RE C A T UN S orm ES-C-1 REV. 0 c ted bank.ank CBD S AT S AT S AT C ORDED S AT 0 A ppendi x Page 4 o Perfor m 3.3.15.a Standa r Comm e Perfor m 3.3.15.b Standa r Simula t Operat o Comm e Perfor m 3.3.15.c Standa r Comm e Perfor m 3.3.15.d Standa r Comm e x C o f 8 m Step: 5 & 4 th line r d: e nt: m Step: 6 r d: t or o r: e nt: m Step: 7 r d: e nt: m Step: 8 r d: e nt: C Record Gro u OBSE R at 215 S If resto r P/A Co n MANU A CONT A When c Conve r Move a PLACE until D R Place a EXCE P At rear Rods D C PNPP 201 6positions f u p 2 step c R VED 1-S C S teps. r ing a Cont r nverter Au t A L A CTED NE O c ontacted, r ter is in M ffected groD 1/1-FLR M R PI lights f o a ll lift coil di s P T for affec t of Control B D 4, M12, D 1 JPM STE P 6 NRC JPM f or affected ounte r ____C-CBD2, C T r ol Bank ro t o-Manual s O to place Insert Ma l M anual. up outwar d M , CONT R o r Bank D i n s connect s w t ed rod to t h B oard, PL A 1 2, and M4 P S S-1 (RO10 2 Rod: ___ TRL BANK d, Then L o selector sw P/A Conve l function R d to the de s R OL ROD M n dicated 2 2 w itches for he UP (dis c A CED Lift C in ROD DI 2 4 A)D GROUP S A o cally POSI T w itch (SFG D rtor in MA N R DR03 an d S A s ired DRPI MOTION C T 2 2 Steps. S A affected b a c onnected)Coil Discon n SCONNE C S A F o 2 and RE C A T UN S T ION and M D 832 Rm 1 NUAL d report th a A T UN SLight. T RL in OU T A T UN S a nk, group s position.

n ect Switc h CTED (up) p A T UN S orm ES-C-1 REV. 0 C ORDED S AT M AINTAIN -096) - at the P/A S AT T position S AT s 1 AND 2, h es for p osition. S AT 0 A ppendi x Page 5 o Examin Perfor m 3.3.15.e.Standa r Comm e Perfor m 3.3.15.e.Standa r Comm e Perfor m 3.3.15.e.Standa r Comm e Perfor m 3.3.15.f Standa r Comm e x C o f 8 er Cue: m Step: 9 1) & all bull e r d: e nt: m Step: 10

2) r d: e nt: Step m Step: 11

3) r d: e nt: m Step: 12r d: e nt: C IF Nec e establi s e tsMaintai necess a Tur b MONIT Verify t h VERIFI Ensure movem ENSU R movem WITHD its grou PLACE until D R C PNPP 201 6 essary, Re s hed. Othn Tave wit h a ry: b ine Power/ORED T AV E h at only af fED that on l last move m ent of affe c RED last m o ent of Con t RAW the a p by DRPI D 1/1-FLR M R PI light fo r JPM STE P 6 NRC JPM state Stab er operat o hin 2°F of T/Steam Du m E. f ected Rod l y Rod H8 i m ent of aff e c ted group.

o vement o f t rol Bank C a ffected rod

indication.

M , CONT R r Rod H8 in P S S-1 (RO10 2 le Plant C o o rs will adj T ref by con t m ps/Borati o is moving.

i s moving.e cted rod i s f Control R o C BD as enti r d in controll e R OL ROD Mdicated 22 2 2 4 A)o nditions h ust turbin e t rolling the f o n/Dilution S A S A s in same d o d H8 is in re bank w a S A e d increm e MOTION C T 2 Steps. S A F o h ave been e load if r e f ollowing a s A T UN S A T UN S irection as same dire c a s moved o u A T UN S e nts until ali T RL in OU T A T UN S orm ES-C-1 REV. 0 e quired. s S AT S AT last c tion as las t u tward. S AT gned with T position S AT 0 t A ppendi x Page 6 o Perfor m 3.3.15.g Standa r Comm e Examin Perfor m 3.3.15.h Standa r Comm e Perfor m 3.3.15.h Examin Standa r Comm e Perfor m 3.3.15.h Standa r Comm e x C o f 8 m Step: 13r d: e nt: er Note: m Step: 14 r d: e nt: m Step: 15

& RNO a er Cue: r d: e nt: m Step: 16& RNO b r d: e nt: C Place a A t rear Rods D The fol VERIF Y OBSE R FAIL is VERIF Y Clear t h Ens u cabi ONLY t PLACE VERIF Y Clear t h DE PDEPR E C PNPP 201 6 a ll lift coil di s of Control B D 4, M12, D 1 lowing st e Y Rod Con t R VED 1-A L LIT Y Rod Con t h e Rod Co n u re only lift net (See A t he lift reg KEPT ste p Y Rod Con t h e Rod Co n PRESS 1/1-ESSED 1/1-JPM STE P 6 NRC JPM s connect s w B oard, PL A 1 2, and M4 e ps repres e t rol Urgent B-6D, Win d t rol Urgent n trol Urgen t reg white l LB-6D 1.6 white ligh

p. t rol Urgent n trol Urgen t-RCAR, C O-RCAR, C O P S S-1 (RO10 2 w itches to t A CED Lift C in ROD C O e nt the Al t Failure ala r d ow 1.6, C O Failure ala r t Failure al a l ight on de s logic diagr a t on desig Failure ala r t Failure al a ONTROL R ONTROL R O 2 4 A)the DOWN Coil Discon n ONNECTE D S A t ernate Pa t rm - CLEA R O NTROL R S A rm - CLEA R arm as foll o signated ci r am) - LIT nated circ S A rm - CLEA R arm as foll o OD CTRL A O D CTRL A S A F o (connecte d n ect Switc h D (down) p A T UN S t h of this J R. R OD CTRL A T UN S R. o ws: rcuit card i n uit card is A T UN S R. o ws: A LARM R E ALARM R E A T UN S orm ES-C-1 REV. 0 d) position.

h es for osition. S AT J PM. URGENT S AT n affected LIT S AT E SET E SET S AT 0 Appendix C JPM STEPS Form ES-C-1 Page 7 of 8 CPNPP 2016 NRC JPM S-1 (RO1024A) REV. 0 Perform Step: 17 3.3.15.h & RNO a VERIFY Rod Control Urgent Failure alarm - CLEAR.

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 3.3.15.i RESTORE affected bank to the DRPI position recorded in step 15a.

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

Comment:

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

Standard:

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

Comment:

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

When contacted, MODIFY RDR03, to AUTO Comment:

SAT UNSAT Perform Step: 21 3.3.15.l PLACE 1/u-RBSS, CONTROL ROD BANK SELECT to MANUAL.

Standard: ROTATED 1/1-RBSS, CONTROL ROD BANK SELECT to MANUAL position. Terminating Cue: This JPM is complete.

Comment:

SAT UNSAT STOP TIME:

Appendix C JPM CUE SHEET Form ES-C-1 Page 8 of 8 CPNPP 2016 NRC JPM S-1 (RO1024A) REV. 0 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.

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 7 CPNPP 2016 NRC JPM S-2 (RO1205) REV. 0 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 7 CPNPP 2016 NRC JPM S-2 (RO1205) REV. 0 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 follo wing 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)

A ppendi x Page 3 o - Che c Examin Perfor m 8.1.1 Standa r Comm e Perfor m 8.1.2 Standa r Comm e Perfor m 8.1.3 Standa r Comm e Perfor m 8.2.1 Standa r Comm e x C o f 7 c k Mark D e er Note: m Step: 1 r d: e nt: m Step: 2 r d: e nt: m Step: 3 r d: e nt: m Step: 4 r d: e nt: e notes Cri t The fol Stroke t ENSU R DETE R Stroke t CLOS E PLA C OBS E CIR C Stroke t OPEN 1 PLA C OBS E CIR C Stroke t ENSU R DETE R CPNPP 2 t ical Step lowing st e t est of 1-8 0 R E 1/1-800 0 R MINED 1/1 t est of 1-8 0 E 1/1-8000 A CED 1/1-8 0 E RVED gr e CLED CLO S t est of 1-8 0 1/1-8000A, CED 1/1-8 0 E RVED re d C LED OPE N t est of 1-8 0 R E 1/1-800 0 R MINED 1/1 JPM STE P 2 016 NRC J e ps are f ro 0 00A, PRZ R 0 A, PRZR P 1-8000A, P 0 00A, PRZ R A , PRZR P O 0 00A, PRZ R e en CLOS E SED on Fo r 0 00A, PRZ R PRZR PO 0 00A, PRZ R d OPEN lig h N on Form 0 00B, PRZ R 0 B, PRZR P 1-8000B, P P SPM S-2 (R O S T m OPT-10 9 R PORV B L PORV BL KRZR POR V R PORV B L O RV BLK V R PORV B L E light LIT (r m OPT-1 0 R PORV B L RV BLK V L R PORV B L ht LIT (NO TOPT-109 A R PORV B L PORV BL KRZR POR V O 1205) T ART TIM E 9 A, Sectio LK VLV: K VLV is O P V BLK VLV S A LK VLV: VLV (REC O LK VLV in C (NOT criti c 0 9 A-1 at St e S A LK VLV: L V (RECO R LK VLV in O T critical) A-1 at Step 8 S A LK VLV: K VLV is O P V BLK VLV S A F o E: n 8.0. P EN. is OPEN A T UN S O RD). C LOSE (cr c al) e p 8.1.2 (N A T UN S R D). O PEN (crit 8.1.3 (NO T A T UN S P EN. is OPEN A T UN S orm ES-C-1 REV. 0 S AT itical) OT critica l S AT ical) T critical)

S AT S AT 0 )

Appendix C JPM STEPS Form ES-C-1 Page 4 of 7 CPNPP 2016 NRC JPM S-2 (RO1205) REV. 0 Perform Step: 5 8.2.2 Stroke test of 1-8000B, PRZR PORV BLK VLV:

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 8.2.3 Stroke test of 1-8000B, PRZR PORV BLK VLV:

OPEN 1/1-8000B, PRZR PO RV 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 OPERATOR NOTE: When 1/1-8000B is reopened, EXECUTE malfunction RX16B at 30%. Ensure the conditional inserted the malfunction.

{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 A ppendi x Page 5 o Examin Examin Examin Perfor m 1 Standa r Comm e Perfor m 2 & 2.A Standa r Comm e Examin Perfor m 2, 2.B, &

Standa r Comm e x C o f 7 er Note: er Note: er Note: m Step: 8 r d: e nt: m Step: 9 r d: e nt: er Note: m Step: 10 2 nd bullet r d: e nt: The fol The ap refere n The fol Provid e board c Determ DETE R Monito r I f r DETE R approxi 1/1-PC V Monito r I f p PLACE OPEN a CPNPP 2 lowing st e plicant m a n cing the A lowing st e e a copy t o copy ine affecte d R MINED af f r pressuriz e f one chan n r emaining o R MINED all mately the V-456, PR Z r pressuriz e f reactor is p sig, Then c 1/1-PC VD 1/1-PC V a nd green C JPM STE P 2 016 NRC J e ps repres e ay recogni z A LM. e ps are f ro o the exa m d PORV. f ected PO R e r pressure nel is indic a operable ch Pressuriz e same valu e Z R PORV w e r pressure in Mode 1, c lose affec t V-456, PRZ V-456, PRZ R C LOSE lig h P SPM S-2 (R O e nt the Al t z e the fail um ALM-00 minee whe n R V is 1/1-P C. a ting > 60 p annels, go e r pressure e w ill be stu

c. 2 or 3 wit h t ed PORV.R PORV R PORV in h ts both LI T O 1205) t ernate Pa t ure and ta k 53A, 1-AL B n they rea c C V-456 S A p sig differe n to ABN-7 0 indication s S A c k in mid-p h pressuriz eCLOSE a n T S A F o t h of this J k e action p B-5C, Win d c h for the c A T UN S n ce betwe e 0 5. s are readi n A T UN S p osition. e r pressur e n d OBSER V A T UN S orm ES-C-1 REV. 0 J PM. p rior to dow 1.4. c ontrol S AT e n the n g S AT e < 2335 VED red S AT 0 Appendix C JPM STEPS Form ES-C-1 Page 6 of 7 CPNPP 2016 NRC JPM S-2 (RO1205) REV. 0 Perform Step: 11 3 With reactor in Mode 4, 5 or 6, Th en refer to TDM-301A to determine 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 4, 4.A, & 2 nd bullet Verify pressurizer or RCS wide range pressure stabilizes. 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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 7 of 7 CPNPP 2016 NRC JPM S-2 (RO1205) REV. 0 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 Appendix C JPM STEPS Form ES-C-1 Page 1 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0 Facility: CPNPP JPM # NRC S-3 Task # RO1412 K/A # 025.AA1.02 3.8 / 3.9 SF-4-PTitle: 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:

Appendix C JPM STEPS Form ES-C-1 Page 2 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0 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 1 st 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 lo wer 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:

Appendix C JPM STEPS Form ES-C-1 Page 3 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0 Simulator Operator: When examinee is ready, PLACE Simulator in RUN.

Simulator Operator: INSERT remote function CVR17 for CCP 1-02 Breaker (Key 1); 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 Step 8 RNO 1)

Dispatch operators to ra ck in the breaker to affected units non-operating 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 Step 8 RNO 2)

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

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 Step 8 RNO 3) Stop both RHR pumps AND place HSs in PULL-OUT: 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 Step 8 RNO 3) Stop both RHR pumps AND place HSs in PULL-OUT: 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 Appendix C JPM STEPS Form ES-C-1 Page 4 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0 Perform Step: 5 Step 8 RNO 4)

Close 1/u-8701A, RHRP 1 HL RE CIRC ISOL VLV AND 1/u-8702B, RHRP 2 HL RECIRC ISOL VLV.

Standard: OBSERVED 1/1-8701A, RHRP 1 HL RE CIRC ISOL VLV in CLOSE and DE-ENERGIZED Comment: SAT UNSAT Perform Step: 6 Step 8 RNO 4)

Close 1/u-8701A, RHRP 1 HL RE CIRC ISOL VLV AND 1/u-8702B, RHRP 2 HL RECIRC ISOL VLV.

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

Comment: SAT UNSAT Perform Step: 7 Step 8 RNO 5)

Identify AND Isolate Leak per Attach ment 7, while continuing this procedure.

Standard: IDENTIFY and ISOLATE Leak pe r 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 Step 8 RNO 6) GO TO Step 11.

Standard:

PLACEKEPT to Step 11.

Comment: SAT UNSAT Perform Step: 9 Step 11 Verify RWST level - GREATER THAN 33%: 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 Appendix C JPM STEPS Form ES-C-1 Page 5 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0 Perform Step: 10 Step 12.a Verify ONE CCP - RUNNING.

Standard: DETERMINED CCP 1-01 was RUNNING.

Comment: SAT UNSAT Perform Step: 11 Step 12.b STOP 1/u-APPD, PDP.

Standard: PLACED 1/1-APPD, PDP handswitch in STOP and OBSERVED Green Pump light LIT Comment: SAT UNSAT Perform Step: 12 Step 12.c 1 st bullet Verify CCP suction aligned from RWST: 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 Step 12.c 2 nd bullet Verify CCP suction aligned from RWST: 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 Step 12.c 3 rd bullet Verify CCP suction aligned from RWST: 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 Appendix C JPM STEPS Form ES-C-1 Page 6 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0 Perform Step: 15 Step 12.c 4 th bullet Verify CCP suction aligned from RWST: 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 Step 12.d Verify the following valves closed: 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 Step 12.e 1 st bullet Align CCP injection: 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 Appendix C JPM STEPS Form ES-C-1 Page 7 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0 Perform Step: 18 Step 12.e 2 nd bullet Align CCP injection: 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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 8 of 8 CPNPP 2016 NRC JPM S-3 (RO1412C) REV. 0 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 C oolant 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

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 8 CPNPP 2016 NRC JPM S-4 (RO3113) REV. 0 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 8 CPNPP 2016 NRC JPM S-4 (RO3113) REV. 0 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)

A ppendi x Page 3 o - Che c Examin Perfor m Step 8.1 Standa r Comm e Perfor m 8.1 & 8.1 Standa r Comm e Perfor m 8.1, 8.1.3 Standa r Comm e x C o f 8 c k Mark D e er Note: m Step: 1 1 & 8.1.1 r d: e nt: m Step: 2 .2 r d: e nt: m Step: 3 3 & 8.1.3A r d: e nt: e notes Cri t The fol Latch t h On the Bar Re d DETE R Latch t h Verify t h 1 2 3 VERIFI Latch t h On the Trip as A OPEN E CPNPP 2 t ical Step lowing st e h e turbine a TG Contro l d. R MINED th a h e turbine a h e followin g 1.7 - TURB 2.7 - TURB 3.7 - TURB ED on 1-T S h e turbine a TG Contro l follows. A. Click th e"Osd" E D the Tur b JPM STE P 2 016 NRC J e ps are f ro a s follows:

l Display, e a t Turbine T a s follows:

g light indi c TRIP FLU TRIP FLU TRIP FLU SLB-3 that a s follows:

l Display in e Turbine L b ine Latch S P SPM S-4 (R O S T m OPT-41 0 e nsure the t T rip bar wa c ations on C ID LO 1-6 3 ID LO 1-6 3 ID LO 1-6 3 windows 1 the "Start-Latch Subg r S ubgroup C O 3113) T ART TIM E 0 A, Sectio t urbine is tr s red. S A C B-04, 1-T S 3AST 1 3AST 2 3AST 3 .7, 2.7 and S A Up" Sectio n r oup Contr o C ontroller O S A F o E: n 8.0. ipped, "Tu r A T UN S S LB-3 are o 3.7 are LI T A T UN S n , reset th e oller to brin O sd. A T UN S orm ES-C-1 REV. 0 r bine Trip" S AT o n: T. S AT e Tu r bine g up the S AT 0 A ppendi x Page 4 o Perfor m 8.1, 8.1.3 Standa r Comm e Perfor m 8.1, 8.1.3 Standa r Comm e Perfor m 8.1, 8.1.3 Standa r Comm e x C o f 8 m Step: 4 3 & 8.1.3B r d: e nt: m Step: 5 3 & 8.1.3C r d: e nt: m Step: 6 3 & 8.1.3D r d: e nt: Latch t h On the Trip as B CLICK E (green/r Latch t h On the Trip as C VERIFI RPM). Latch t h On the Trip as D CLICK E red. CPNPP 2 h e turbine a TG Contro l follows. B. IF the T u THEN C Controll e E D the "0/1 r ed). h e turbine a TG Contro l follows. C. On the T verify S pED speed t h e turbine a TG Contro l follows. D. In the "

O Turbine.E D the "1" a JPM STE P 2 016 NRC J a s follows:

l Display in u rbine Lat c Click "0/1" t h er. " and Exec a s follows:

l Display in T G Control p eed Targ e t arget (134 a s follows:

l Display in Osd" click "

1. a nd Execut P SPM S-4 (R O the "Start-c h Subgrou h en Execu t c ute. Subgr o the "Start-Display in e t Controlle RPM) is l o the "Start-1" then Ex e t e. Subgro u O 3113) Up" Sectio n p Controll e t e to turn O o up Contr o S A Up" Sectio n the Speed r lower or e o wer than a S A Up" Sectio n e cute to st a u p controlle S A F o n , reset th e e r is OFF (g N (green/r e o ller indicat e A T UN S n , reset th eControl S e e qual to ac t ctual spee d A T UN S n , reset th e a rt the Latc h r indicated A T UN S orm ES-C-1 REV. 0 e Tu r bine green/grey)

, e d) the e d ON S AT e Tu r bine e ction, t ual speed.

d (194 S AT e Tu r bine h ing of the blinking S AT 0 ,

Appendix C JPM STEPS Form ES-C-1 Page 5 of 8 CPNPP 2016 NRC JPM S-4 (RO3113) REV. 0 Perform Step: 7 8.1, 8.1.4 & 1 st bullet Latch the turbine as follows:

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 8.1, 8.1.4 & 2 nd bullet Latch the turbine as follows:

Verify the following parameters: 1-PI-6559, TURB L/O PR ESS - greater than 25 PSIG Standard:

VERIFIED Turbine Lube Oil Pressu re is approximately 42 psig. Comment: SAT UNSAT Perform Step: 9 8.1, 8.1.4 & 3 rd bullet Latch the turbine as follows:

Verify the following parameters: 1-PI-6561, EHC FL UID PRESS - greater than 114 PSIG Standard:

VERIFIED EHC Fluid Pressure is approximately 170 psig. Comment: SAT UNSAT Perform Step: 10 8.1, 8.1.4 & 4 th bullet Latch the turbine as follows:

Verify the following parameters: 1-PI-6566, HP EHC FLUID PRESS - approximately 455 PSIG Standard:

VERIFIED HP EHC Fluid Pressu re 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 A ppendi x Page 6 o Perfor m 8.2 Standa r Comm e Perfor m 8.3 Standa r Comm e Examin Examin Perfor m 8.4 Standa r Comm e x C o f 8 m Step: 11 r d: e nt: m Step: 12 r d: e nt: er Note: er Note: m Step: 13r d: e nt: Verify t h 1 2 3 4 VERIFI Verify H 1 1 1 1 VERIFI valve. The fol The tu r RPM a b Trip. On the Stop V a CLICK E CPNPP 2 h e followin g 1.6 - MSL 1 2.6 - MSL 2 3.6 - MSL 3 4.6 - MSL 4ED on 1-T S H P stop val v 1-ZL-2429 A 1-ZL-2431 A 1-ZL-2430 A 1-ZL-2428 AED on CB-lowing st e r bine spee b ove the o TG Contro l a lves" Subl o E D the "0/1 JPM STE P 2 016 NRC J g light indi c HP STO P 2 HP STO P 3 HP STO P 4 HP STO P SLB-3 that v es are clo A , HPT ST O A , HPT ST O A , HPT ST O A , HPT ST O 10 that Gr e e ps repres ed will con t o riginal tur n l Display in o op Contr o" and Exec P SPM S-4 (R O c ations on C P VLV 4 CL O P VLV 1 CL O P VLV 3 CL O P VLV 2 CL O windows 1 sed on CB-O P VLV 1 O P VLV 2 O P VLV 3 O P VLV 4 een light LI T e nt the Al t t inue to in c n ing gear s the "Start-o ller to ope n c ute. Subgr o O 3113) C B-04, 1-T S OSE UV-2 4 OSE UV-2 4 OSE UV-2 4 OSE UV-2 4.6, 2.6, 3.6 S A-10: T and Red S A t ernate Pa t c rease to g s peed req u Up" Sectio n n the HP a n oup contro l S A F o S LB-3 are o 4 28A 4 29A 4 30A 4 31A and 4.6 ar e A T UN Slight DAR K A T UN S t h of this J g reater th a u iring a T u n , turn ON nd LP stop l ler turned r A T UN S orm ES-C-1 REV. 0 o n: e LIT. S AT K for each S AT J PM. a n 100 u rbine the "Open valves. r ed. S AT 0 Appendix C JPM STEPS Form ES-C-1 Page 7 of 8 CPNPP 2016 NRC JPM S-4 (RO3113) REV. 0 Perform Step: 14 5.1 & Caution The normal turning gear speed for th e turbine may increase when the 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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 8 of 8 CPNPP 2016 NRC JPM S-4 (RO3113) REV. 0 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.

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 6 CPNPP 2016 NRC JPM S-5 (RO2002C) REV. 0 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 6 CPNPP 2016 NRC JPM S-5 (RO2002C) REV. 0 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 equi valent 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, TR ANSFER 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)

A ppendi x Page 3 o - Che c Examin Examin Perfor m 4.a. Standa r Comm e Once a p Examin Perfor m 4.b.1) & Standa r Comm e Perfor m 4.b.1) & 2 Standa r Comm e x C o f 6 c k Mark D e er Note: er Note: m Step: 1 r d: e nt: p plicant r e er Note: m Step: 2 1 st bullet r d: e nt: m Step: 3 2 nd bullet r d: e nt: C e notes Cri t The fol CUE t h Check R OBSE RCHAN I e ads level l Steps 2 Open C 1 PERF O P V O Realig n O PERF O P V O C PNPP 201 6 t ical Step lowing st e h e Simulat o RWST lev e R VED 1-LI-9 I I and VER l ess than 6 2 and 3 m a CNTMT SM 1-HS-4782 ORMED the P LACED 1-V LV to OP E O BSERVE D n Containm e O pen CNT M 1-HS-4 7 ORMED the P LACED 1-V LV to OP E O BSERVE D JPM STE P 6 NRC JPM e ps are f ro o r Operat o e l - LESS T 9 30, RWS T IFY level i s 6%. ay be perf o P TO CSP following:

-HS-4782, C E N (critica l D red OPE N e nt Spray S M T SMP T O 7 83 following:

-HS-4783, C E N. D green C L P S S-5 (RO20 0 S Tm EOS-1.3 o r to PLAC THAN 6%.T LVL CHA s less than 6 Ti m ST A ormed in a n 1 & 3 A N D C NTMT S M l). N light LIT (S ystem as f O CSP 1 & C NTMT S M L OSE light L 0 2C)T ART TIM E 3 , Attachm E the Sim u N I or 1-LI-6%. S A m e Critical A RT TIME: ny order. D 2 & 4 SU C M P TO CS P (NOT criti c S A f ollows: 3 AND 2 &M P TO CS P L IT. S A F o E: ent 1.H. ulator in R 931, RWS T A T UN S: C T ISOL V L P 1 & 3 SU C c al). A T UN S& 4 SUCT I S P 2 & 4 SU C A T UN S orm ES-C-1 REV. 0 UN. T LVL S AT L Vs: C T ISOL S AT S OL VLVs: C T ISOL S AT 0 Appendix C JPM STEPS Form ES-C-1 Page 4 of 6 CPNPP 2016 NRC JPM S-5 (RO2002C) REV. 0 Examiner Note: The following step represen ts the Alternate Path of this JPM.

Perform Step: 4 4.b.1) RNO IF CNTMT SMP TO CSP VLV(s) can NOT be opened, THEN Place 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 4.b.2) & 1 st bullet Close RWST TO CSP 1 & 3 AND 2 & 4 SUCT VLVs: 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 4.b.2) & 2 nd bullet Close RWST TO CSP 1 & 3 AND 2 & 4 SUCT VLVs: 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 Appendix C JPM STEPS Form ES-C-1 Page 5 of 6 CPNPP 2016 NRC JPM S-5 (RO2002C) REV. 0 Perform Step: 7 4.b.3) Verify containment spray flows.

Standard: OBSERVED Containment Spray flows on: 1-FI-4772-1, CSP 1 DI SCH FLO at ~3600 GPM. 1-FI-4772-2, CSP 3 DI SCH 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 4.b.3) RNO 3) A)

IF containment spray train(s) NOT providing spray flow, THEN perform 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 4.b.3) RNO 3) B)

IF containment spray train(s) NOT providing spray flow, THEN perform the following: Notify Plant Staff of containm ent spray train(s) condition.

Standard: CONSULTED Plant Staff to det ermine 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 4.b.4) IF containment spray pumps have been stopped due to RWST 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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 6 of 6 CPNPP 2016 NRC JPM S-5 (RO2002C) REV. 0 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

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 6 CPNPP 2016 NRC JPM S-6 (RO4215C) REV. 0 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 6 CPNPP 2016 NRC JPM S-6 (RO4215C) REV. 0 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 CL OSED 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)

Appendix C JPM STEPS Form ES-C-1 Page 3 of 6 CPNPP 2016 NRC JPM S-6 (RO4215C) REV. 0 - Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from SOP-609A, Section 5.7.

Perform Step: 1 5.7.A & 2 nd bullet TURN the synchroscope for the selected breaker ON. 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 5.7.B Using the DG VOLT CTRL, ADJUST running voltage to match incoming 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 5.7.C Using DG SPD CTRL, ADJUST the s peed so that the synchroscope is 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 synchrosc ope is moving 2 to 4 RPM in the SLOW direction.

Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 Page 4 of 6 CPNPP 2016 NRC JPM S-6 (RO4215C) REV. 0 Perform Step: 4 5.7.D & 1 st bullet IF Grid induced load, voltage, OR frequency fluctuations occur while the DG is synchronized to the bus, THEN OPEN the DG Output Breaker: CS-1EG1, DG 1 BKR 1EG1 Standard:

OBSERVED Note bef ore Step 5.7.D.

Comment:

SAT UNSAT Perform Step: 5 5.7.E & 2 nd bullet CLOSE the feeder breaker when the synchroscope is slightly before the 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 represen t the Alternate Path of this JPM.

Simulator Operator:

VERIFY malfunction ED09, Grid Frequency Fluctuation at 58.2 Hz over 90 seconds has initiated.

Perform Step: 6

Acknowledge annunciator alarm 1-AL B-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 Appendix C JPM STEPS Form ES-C-1 Page 5 of 6 CPNPP 2016 NRC JPM S-6 (RO4215C) REV. 0 Perform Step: 7 5.7.F RAISE DG load to 0.5 MW as necessary , to prevent a reverse power trip using DG SPD CTRL handswitch.

Standard: OBSERVED load on W-1EG1, DG 1 MEGAWATTS at approximately 1 MWe. Comment:

SAT UNSAT Perform Step: 8 5.7.G TURN OFF the synchroscope for the selected breaker.

Standard: PLACED SS-1EA1-2, BKR 1EA1-2 SYNCHROSCOPE in OFF.

Comment:

SAT UNSAT Examiner Note: This step may be performed if frequency degr adation has not yet been identified.

Perform Step: 9 5.7.H MAINTAIN 0-500 KVAR out by adjusting the selected DG VOLT CTRL 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 Acti on Step 5.7.D to avo id excessive loading.

Perform Step: 10 5.7.D NOTE OBSERVE Emergency Diesel Generator 1-01 MWe frequency lowering 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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 6 of 6 CPNPP 2016 NRC JPM S-6 (RO4215C) REV. 0 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.

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 5 CPNPP 2016 NRC JPM S-7 (RO1820) REV. 0 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 5 CPNPP 2016 NRC JPM S-7 (RO1820) REV. 0 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)

Appendix C JPM CUE SHEET Form ES-C-1 Page 3 of 5 CPNPP 2016 NRC JPM S-7 (RO1820) REV. 0 - Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from ABN-703, Step 2.3.3.

Perform Step: 1 2.3.3.a Perform the following for failed channel: 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 2.3.3.b Perform the following for failed channel: 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 2.3.3.c Perform the following for failed channel: 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 2.3.3.d Perform the following for failed channel: 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 2.3.3.e Perform the following for failed channel: 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 Appendix C JPM CUE SHEET Form ES-C-1 Page 4 of 5 CPNPP 2016 NRC JPM S-7 (RO1820) REV. 0 Perform Step: 6 2.3.3.f Perform the following for failed channel: 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 2.3.3.g & 1st bullet Perform the following for failed channel: 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 2.3.3.g & 2nd bullet Perform the following for failed channel: 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 2.3.4 & bullet Ensure N16 Recorder selected to - OPERABLE CHANNEL: 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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 5 of 5 CPNPP 2016 NRC JPM S-7 (RO1820) REV. 0 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.

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0 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.

Appendix C JPM STEPS Form ES-C-1 Page 3 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0 - 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 5.3.6 Perform an emergency start on Trn B Diesel Generator: 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 5.3.7 Place 1/1-APRH 1, RHRP 1 - PULL OUT Standard: PERFORMED the following: PLACED 1/1-APRH 1, RHRP 1 in PULLOUT (Critical). OBSERVED pump lights DA RK (NOT critical). Comment: SAT UNSAT Perform Step: 3 5.3.8 CLOSE 1/1-8812A, RWST TO RHRP 1 SUCT VLV Standard: PERFORMED the following: PLACED 1/1-8812A, RWST TO RHRP 1 SUCT VLV in CLOSE (Critical). OBSERVED green CLOSE light LIT (NOT critical). Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 Page 4 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0 Perform Step: 4 5.3.9 CLOSE 1/1-8100, RCP SEAL WTR RET ISOL VLV 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 5.3.10.a Transfer Charging Pump suction to the RWST : IF charging pump performance indicates possible cavitation, THEN stop charging pump until below valv es 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-112 D OR 1/1-LCV-112E can be opened.

Perform Step: 6 5.3.10.b Transfer Charging Pump suction to the RWST : Ensure 1/1-LCV-112D OR 1/1-LC V-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 Appendix C JPM STEPS Form ES-C-1 Page 5 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0 Examiner Note: Both 1/1-LCV-112B AND 1/1-LCV-112C must be closed.

Perform Step: 7 5.3.10.c Transfer Charging Pump suction to the RWST : 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 5.3.10.d Transfer Charging Pump suction to the RWST : 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 5.3.10.e Transfer Charging Pump suction to the RWST : 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 CLO SE lights LIT. Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 Page 6 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0 Perform Step: 10 5.3.11 Ensure 1/1-APCH2, CCP 2 - RUNNING.

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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 7 of 7 CPNPP 2016 NRC JPM S-8 (RO4405) REV. 0 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 th e 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.

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 6 CPNPP 2016 NRC JPM P-1 (AO5202A) (U1) REV. 0 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 6 CPNPP 2016 NRC JPM P-1 (AO5202A) (U1) REV. 0 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)

A ppendi x Page 3 o - Che c Examin e Perform 3.3.4 n Standar d Examin e Comme n Examin e Examin e Perform 5.3.1 D Standar d Examin e Comme n

x C o f 6 c k Mark De n e r Note: Step: 1 d: e r Cue: n t: e r Note: e r Note: Step: 2 d: e r Cue: n t: C notes Critic a Remin d ABN-3 0 Reset a i P/A Co nDEPRE S Displac e The 1-0 The foll The foll Coolan t IF Stuffi nOBSER V The sigDO NO T tank m u Anothe r C PNPP 201 6 a l Step d examinee 0 1, Section 3 ir to PDP h y nverte r. S SED the c o e ment Pum p1 PDP Hyd rowing stepowing step t Tank is o u n g Box Coo l V ED Stuffin g ht glass is T provide th e ust be filled.

r operator w JPM STE P 6 NRC JPM to simulat e 3.0. y draulic spe e o ntrol air R E p Fluid Driv e r aulic Spee d s are from S s represen t u t of specifi l ant Tank is g Box Cool a E MPTY. e second p a w ill monito r P S P-1 (A O52 0 S T e all action s ed change r b E SET button e in the PDP d Change r SOP-103A, t the Altern cation. low, THEN a nt Tank sig h art of the cu e r sight glas s 0 2A) (U1) TART TIME s. The follo w b y pushing t n located at oRoom. is RESET.

SA T Section 5.

3 ate Path w hFILL per th e htglass leve e until opera s level as t h SA T F o: wing step i she brass bu op the Positi v T UNS 3.1. hen the Stu e following s tl. tor demons t h e tank is f i T UNS orm ES-C-1 REV. 0 s from tton on the v e AT ffing Box teps: t rates that t h illed. AT 0 h e Appendix C JPM STEPS Form ES-C-1 Page 4 of 6 CPNPP 2016 NRC JPM P-1 (AO5202A) (U1) REV. 0 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 5.3.1 D 1) IF Stuffing Box Coolant Tank is low, THEN fill per the following steps: 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 5.3.1 D 2) WHEN the desired tank level has been established, THEN CLOSE 1CS-0119, 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

Appendix C JPM STEPS Form ES-C-1 Page 5 of 6 CPNPP 2016 NRC JPM P-1 (AO5202A) (U1) REV. 0 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 5.3.1 E Ensure 1-8388-RO, PD CHRG PMP 1-01 DISCH VLV RMT OPER, is OPEN. Examiner Cue: Once the operator has lifted t he 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 5.3.1 F OPEN the following valves: 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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 6 of 6 CPNPP 2016 NRC JPM P-1 (AO5202A) (U1) REV. 0 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.

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0 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.

A ppendi x Page 3 o - Che c Examin Perfor m Note Standa r Comm e Perfor m 2a Examin Standa r Examin Comm e x C o f 11 c k Mark D e er Note: m Step: 1 r d: e nt: m Step: 2 er Cue: r d: er Cue: e nt: C e notes Cri t The fol Determ Determ IF 2EA 1 followi n ECB 7 9 Ensure DISTRI in Unit 2 Key Lo c XED1-1 LIGHT PLACE XED1-1 LIGHT PNPP 2016 t ical Step lowing st e ine approp ined that S 1 is energi z ng: 92, U1 UP S transfer s w BUTION P A 2 (LOAD C c ker requir e 1 S is in th eis LIT. D XED1-1 S 1 S is in th eis LIT. JPM STE P NRC JPM P e ps are f ro riate secti o ection 2 s h z ed and 2E A S Corridor S w itch on C P A NEL XE D ONNECT E e d). e Unit 1 po S in Unit 2.

e Unit 2 po P S P-2 (RO421 S T m ECA-0.0 o n of Attac h h ould be p e A 2 is de-e n S outh Wall PX-ECDPE D D 1-1 AUTO ED TO UNI T sition. LO A sition. LO A7H) (U1) T ART TIM E 0 A, Attach m h ment 2A t o e rformed. S A n ergized, T D-01S, 12 5 TRANSF E T 2 LIGHT A D CONN E A D CONN E S A F o E: m ent 2A o perform.

A T UN S HEN perfo r 5 VDC ER SWITC H lit) (Key #1 ECTED T O ECTED T O A T UN S orm ES-C-1 Rev. 0 S AT r m the H XED1-1S 50 from O UNIT 1 O UNIT 2 S AT 0 Appendix C JPM STEPS Form ES-C-1 Page 4 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0 Examiner Note: Perform Steps 3-25 are bulleted and may be performed in any order. Perform Step: 3 2b 1 st bullet Place the followin g breakers OFF: ECB 792, U1 UPS Corridor South Wall XED2-1/1/BKR, CABLE TERMINAT ION 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 2b 2 nd bullet Place the followin g breakers OFF: ECB 792, U1 UPS Corridor South Wall XED2-1/3/BKR, CABLE TERMINAT ION 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 2b 3 rd bullet Place the followin g breakers OFF: 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 2b 4 th bullet Place the followin g breakers OFF: 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 Appendix C JPM STEPS Form ES-C-1 Page 5 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0 Perform Step: 7 2b 5 th bullet Place the followin g breakers OFF: 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 2b 6 th bullet Place the followin g breakers OFF: 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 2b 7 th bullet Place the followin g breakers OFF: 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 2b 8 th bullet Place the followin g breakers OFF: 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 Appendix C JPM STEPS Form ES-C-1 Page 6 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0 Perform Step: 11 2b 9 th bullet Place the followin g breakers OFF: 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 2b 10 th bullet Place the followin g breakers OFF: 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 2b 11 th bullet Place the followin g breakers OFF: 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 2b 12 th bullet Place the followin g breakers OFF: ECB 807, U1 CSR East Wall 1PC4/10/BKR, NSSS AUXILI ARY RELAY RACK 2 1-LAR-01 SUPPLY BREAKER Standard: PLACED 1PC4/10/BKR in OFF. Examiner Cue: The breaker is OFF.

Comment:

SAT UNSAT Appendix C JPM STEPS Form ES-C-1 Page 7 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0 Perform Step: 15 2b 13 th bullet Place the followin g breakers OFF: 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 2b 14 th bullet Place the followin g breakers OFF: ECB 807, U1 CSR East Wall 1PC4/13/BKR, UPGRADE PROT ECTION 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 2b 15 th bullet Place the followin g breakers OFF: 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 2b 16 th bullet Place the followin g breakers OFF: 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 Appendix C JPM STEPS Form ES-C-1 Page 8 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0 Perform Step: 19 2b 17 th bullet Place the followin g breakers OFF: 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 2b 18 th bullet Place the followin g breakers OFF: 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 2b 19 th bullet Place the followin g breakers OFF: 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 2b 20 th bullet Place the followin g breakers OFF: 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 Appendix C JPM STEPS Form ES-C-1 Page 9 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0 Perform Step: 23 2b 21 st bullet Place the followin g breakers OFF: 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 2b 22 nd bullet Place the followin g breakers OFF: ECB 807, U1 CSR East Wall 1PC3/14/BKR, UPGRADE PROT ECTION 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 2b 23 rd bullet Place the followin g breakers OFF: 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 2c ECB 807, U1 CSR South Wall 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 Appendix C JPM STEPS Form ES-C-1 Page 10 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0 Examiner Note:

Perform Steps 27 and 28 are bulleted and may be performed in any order. Perform Step: 27 2d 1 st bullet Place the followin g breakers OFF: 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 2d 2 nd bullet Place the followin g breakers OFF: 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 2e Notify Unit Supervisor attachment instructions complete AND DC load 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 Attach ment 2.A Section 2 is complete. Examiner Cue: The JPM is complete.

Comment:

SAT UNSAT STOP TIME:

Appendix C JPM CUE SHEET Form ES-C-1 Page 11 of 11 CPNPP 2016 NRC JPM P-2 (RO4217H) (U1) Rev. 0 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.

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 5 CPNPP 2016 NRC JPM P-3 (RO5115B) (U2) REV. 0 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:

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 5 CPNPP 2016 NRC JPM P-3 (RO5115B) (U2) REV. 0 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.

A ppendi x Page 3 o - Che c Examin e Perform Step 1. 1 Standar d Examin e Comme n Examin e Perform Step 1. 2 Standar d Examin e Comme n Examin e Perform Step 1. 3 Standar d Examin e Comme n x C o f 5 c k Mark De n er CUE: Step: 1 st Bullet d: e r Cue: n t: e r Note: Step: 2 2 nd Bullet d: e r Cue: n t: e r Note: Step: 3 3 rd Bullet d: e r Cue: n t: C notes Critic a Shutdo w Reacto r Perfor m Transfe r 43/2 - CONTAREPO R cannot When p (RSP) w Transfe r 43/2 - TURNE D INDICA T When v (RSP) w Transfe r 43/2 - TURNE D INDICA T C PNPP 201 a l Step w n Transfe r Operator.

m Steps 1-3 r the followi n APBA1L, B A CTED Extr aT 43/2 - A P B be transfer p ump is tra n w ill be on.

r the followi n APBA2L, B A D the switc h TE switch i s alve is tran w ill be on.

r the followi n8104L, EM E D the switc h TE switch i s JPM STE P6 NRC JP Mr Panel (ST are bullete d ng from CR t A XFER PM a Reactor O p BA1L, BA Xred at this t n sferred gr e ng from CR t A XFER PM h to HSP s in the HS P sferred gr e ng from CR t ER BORAT E h to HSP s in the HS P P S M P-3 (RO51 S T TP) switche s d and may to HSP: P 1 CTRL X p erator at S T XFER PMP 1 time. e en light o n to HSP: P 2 CTRL X P position a e en light on to HSP: E VLV CTR L P position a 15B) (U2)

TART TIME s will be opbe perform X FER (STP)

T P to have s 1 CTRL XF E SA T n 1/2-A PBA 2 XFER (RSP)a nd pump g SA T 1/2-8104L, L XFER (R S a nd valve g SA T F o: erated by t hed in any o s witch trans f ER switch i s T UNS A 2L, BA XFE g reen light i T UNS AEMER BO R SP) g reen light i s T UNS A orm ES-C-1 REV. 0 he Extra rder. ferred. s broke an d A T R PMP 2 i s ON A T R ATE VLV s ON A T 0 d Appendix C JPM STEPS Form ES-C-1 Page 4 of 5 CPNPP 2016 NRC JPM P-3 (RO5115B) (U2) REV. 0 Perform Step: 4 Step 2. Start one Boric Acid Transfer Pump: 1/2 - APBA1L, BA XFER PMP 1 (RSP) 1/2 - APBA2L, BA XFER PMP 2 (RSP)

Standard: TURNED 1/2-APBA2L Handswitch momentarily to START.

Examiner Cue: INDICATE red light ON, green light OFF for pump started Comment: SAT UNSAT Perform Step: 5 Step 3. Open 1/2-8104L, EMER BORATE VLV (RSP).

Standard: TURNED the switch to OPEN Examiner Cue: INDICATE red light ON, green light OFF Comment: SAT UNSAT Perform Step: 6 Step 6. Monitor 2-FI-183B, EMER BORATE FLO (RSP).

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:

Appendix C JPM CUE SHEET Form ES-C-1 Page 5 of 5 CPNPP 2016 NRC JPM P-3 (RO5115B) (U2) REV. 0 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.

Appendix D Scenario Outline Form ES-D-1 CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 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 1 CC02A CC03A C (BOP, SRO) TS (SRO) Train A Component Cooling Water Pump 1-01 Trip Train B Component Cooling Water Pump 1-02 Auto Start Failure 2 RX15B C (RO, SRO) Pressurizer Spray Valve PCV-455C Fails Open 3 ED07B C (RO, BOP, SRO)TS (SRO) Loss of Inverter (IV1PC2) 4 RC03B R (RO) N (BOP, SRO) High Vibrations on RCP 1-02 requiring Rapid Downpower 5 RC19B M (RO, BOP, SRO)Reactor Coolant Leak on Loop 2 Cold Leg 6 SI04D C (BOP, SRO) Safety Injection Pump (1-02) Auto Start Failure on Safety Injection Signal 7 RC09B2 M (RO, BOP, SRO)Large Break Loss of Coolant Accident on Loop 2 Cold Leg 8 RP10A RP10B RP19C C (BOP, SRO) Train A and B Containment Isolation Phase B Automatic and Manual Actuation Failure 9 HS-4755 Override C (BOP, SRO) Train B Chemical Addition Tank Discharge Valve Fail to Auto Open *(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)

Scenario Event Description NRC Scenario 1 CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 SCENARIO

SUMMARY

NRC 1 Event 1 (Key 1) The crew will assume the watch at 100% power with no scheduled activities per IP O-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.

Scenario Event Description NRC Scenario 1 CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 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.

Scenario Event Description NRC Scenario 1 CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 Risk Significance Determination Risk Significance Event Guidance Failure of risk important systems prior to Reactor Trip

Event 1 - Loss of Component Cooling Water

Event 3 - Loss of Protection System Inverter STI-214.01 TCA-1.6 - Stop RCPs 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 is excessive feedwater flow. Hi-Hi SG level closes FW control and isolation valves, trips FW turbine and main turbine. Risk significant core damage sequence Events 5 and 7 - Reactor Coolant Leak then LBLOCA STI-214.01 TCA 2.2 - Complete 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 Restore Pressurizer Pressure Control

Start Train B Safety Injection Pump

Manually Align Phase B Containment Isolation

Initiate Containment Spray

Additive Flow ODA-102 1) The operator may place a controller in the manual mode of operation when continued automatic control is inappropriate.

2) The Unit RO and/or US shall place the Reactor in a safe 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 isolation is mandatory in the event of a LOCA. The CIS isolates the Containment to prevent or limit the escape of fission products that may result from postulated accidents.

Technical Specification 3.6.7 Basis - 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 Scenario Event Description NRC Scenario 1 CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 Critical Task Determination Critical Task Safety Significance Cueing Measurable Performance Indicators Performance Feedback CT Manually Start Safety Injection Pump 1-02

Prior to completing Attachment 2 of EOP-0.0A, Reactor Trip or Safety Injection.

Recognize a failure or an incorrect automatic actuation of an ESF system or component to preclude degradation of any barrier to fission product release. FSAR 6.2.4.1.1 Procedurally driven from EOP-0.0A, Attachment 2 to provide makeup

inventory to the RCS during accident conditions.

The operator will start SI Pump 1-02 using the handswitch on CB-02. Indications of pump start including light, flow and discharge pressure on CB-02. CT 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.

Recognize a failure or an incorrect

automatic actuation of an ESF system or component to preclude degradation of any barrier to fission product release. FSAR 6.2.4.1.1 Procedural direction at FRZ-0.1A Step 4 to determine if Containment Spray is required. 1-ALB-2A, Window 1.8, CS ACT is LIT, Containment pressure is >18 psig and 1-ALB-2A, Window 4.11 is DARK indicating Phase B has NOT actuated. Also, Orange lights will be DARK on valve position indication for each Phase B valve at MLBs 4A3 and 4B3. The operator will attempt to manually actuate CS/Phase B using BOTH handswitches (simultaneously) at CB-07 or CB-

02. The operator will then manually align Phase B Isolation using Attachment 5 of FRZ-0.1A. Valve position indication for each

Phase B valve indicated by an Orange light LIT on MLBs 4A3 and 4B3 for Phase B.

Scenario Event Description NRC Scenario 1 CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP Initialize to IC-18 and 2016 NRC Scenario 1.

EVENT TYPE MALF # DESCRIPTION DEMAND VALUE INITIATING 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 2 RX15B Loop 4 Spray Valve (PCV-455C) Fails Open 50%

K2 (120 sec. ramp)2 Override PK-455C Green Light Off IOR LORXPK455C_4 OFF K2 2 Override PCV-455C Closes when PK-455C put in Manual {DIRXPK455C_2.Value=1} DMF RX15B 2 Override PCV-455C Green Lower Light LIT / Delete {DIRXPK455C_2.Value=1} DOR LORXPK455C_4 ON K0 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 5 RC19B Reactor Coolant Leak Loop 2 Cold Leg 600 GPM K5 (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 9 Override 1-HS-4755 CHEM ADD TK DISCH VLV IOR DICSHS4755 f:0 CLOSED K0 9 HS-4755 Opens with Handswitch {DICSHS4755.Value=2} DOR DICSHS4755

Scenario Event Description NRC Scenario 1 CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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.

BOP RECOGNIZE Train A CCW Pump trip with failure of Train B CCW Pump to start. US DIRECT implementation of ABN-502, Component Cooling Water System 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]

BOP VERIFY CCW Heat Exchanger outlet flow - LESS THAN 17,500 GPM PER HEAT EXCHANGER. [Step 2.3.4]

1-FI-4536A, CCW HX 1 OUT FLO 1-FI-4537A, CCW HX 2 OUT FLO BOP VERIFY required Train B equipment for existing plant conditions - IN OPERATION. [Step 2.3.5]

Control Room Air Conditioning Units 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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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]

BOP VERIFY CCW Heat Exchanger outlet temperature did NOT exceed 122ºF 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 Examiner's discretion, PROCEED to Event 2.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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. RO RECOGNIZE PZR pressure lowering and DETERMINE 1-PCV-455C, Pressurizer Spray Valve malfunction. US DIRECT implementation of ABN-705, Pressurizer Pressure Malfunction, 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 US REFER to Technical Specifications listed in Section 4.1, this procedure.

[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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 When Technical Specifications are addressed, or at Lead Examiner discretion, PROCEED to Event 3.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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 incl ude 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.

US DIRECT performance of ABN-603, Loss of Protection or Instrument Bus, Section 2.0.

US/RO VERIFY Reactor did NOT trip. [Step 2.3.1]

US DETERMINE Unit in MODE 1. [Step 2.3.2]

RO/BOP Manually CONTROL parameters to MAINTAIN or RESTORE to normal as follows: [Step 2.3.3]

RO PLACE 1/1-RBSS, CONTROL ROD BANK SELECT Switch in MANUAL.

[Step 2.3.3.a]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 RO VERIFY RCP Seal Injection Flow - WITHIN NORMAL OPERATING 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]

RO VERIFY Pressurizer level controlled - BETWEEN 25% and 70%.

[Step 2.3.3.c]

RO VERIFY Pressurizer pressure - WITHIN NORMAL OPERATING RANGE FOR CONDITIONS. [Step 2.3.3.d]

BOP VERIFY Steam Generator levels being controlled - BETWEEN 60%

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 reenergi ze 1PC2, EXECUTE remote function EDR02 (Key 11), Inverter IV1PC2 Alternate Power Supply.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 RO VERIFY Unit - IN MODE 1. [Step 2.3.6]

RO PLACE 1/1-RBSS, CONTROL ROD BANK SELECT Switch in MANUAL.

[Step 2.3.6.a]

RO SELECT LOOP 2 on 1-TS-412T, T AVE CHAN DEFEAT Switch.

[Step 2.3.6.b]

RO/BOP DISPATCH an operator to REENERGIZE Protection Bus 1PC2.

[Step 2.3.6.c]

BOP VERIFY PCIP, Window 3.4 - TURB LOAD REJ STM DMP ARMED C-7, not ARMED. [Step 2.3.6.d]

RO RESTORE 1-TS-412T, T AVE CHAN DEFEAT Switch to the NONE Position. [Step 2.3.6.e]

RO PLACE 1/1-RBSS, CONTROL ROD BANK SELECT Switch in AUTO.

[Step 2.3.6.f]

US/RO INVESTIGATE and INITIATE Corrective Action on loss of power to 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.

US CHECK Status of Affected Control Systems and Instrumentation.

[Step 2.3.10]

BOP RESTORE Feedwater System to normal operation. [Step 2.3.10.a]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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.

RO PLACE N-42A, RATE MODE Switch to RESET on Drawer N-42A, Power 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 .

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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.

US DIRECT implementation of ABN-101, Reactor Coolant Pump 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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.

US DIRECT load reduction to 200 MWe per IPO-003A, Power Operations, 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 RO NOTIFY Chemistry and Radiation Protection that power will be lowered 15% within a one hour period. [5.6.3]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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]

RO If desired, DETERMINE the rate of Boration required to allow slow Control Rod inward motion as Turbine load lowers. [5.6.4.B]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 RO REFER to Attachment 2 for guidance in controlling AFD during power ramp.

[5.6.4.C]

RO INITIATE RCS boration per SOP-104A, Reactor Make-up and Chemical 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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.

BOP WHEN the following are met: [5.6.4.E] 1) No TSE alarms are active 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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.

US DIRECT performance of ABN-103, Excessive Reactor Coolant Leakage, Section 2.0.

RO VERIFY Charging Pump - AT LEAST ONE RUNNING. [Step 2.3.1]

RO ENSURE Pressurizer level - AT OR TRENDING TO PROGRAM LEVEL 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]

US If Pressurizer level decreases in an uncontrolled manner, PERFORM the following: [Step 2.3.2 RNO]

RO TRIP the Reactor. [Step 2.3.2 RNO]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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.

US/BOP INITIATE Proper Safeguards Equipment Operation Per Attachment 2.

[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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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]

RO/BOP DETERMINE proper Containment Spray alignment was NOT verified in EOP-0.A. [Step 1 RNO]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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.

RO/BOP VERIFY Containment Isolation Phase A - APPROPRIATE MLB LIGHT INDICATION (RED WINDOWS). [Step 2]

RO/BOP VERIFY Containment Ventilation Isolation - APPROPRIATE MLB LIGHT 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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.

CRITICAL TASK STATEMENT 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.

CRITICAL TASK 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 1-HS-4701, RCP CLR CCW RET ISOL VLV 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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.

RO/BOP 1-MLB-4A3 AND 4B3 - BLUE LIGHTS LIT. [Step 1] Recognizes Blue Light NOT lit for 1-HS-4755, CHEM ADD TK DISCH 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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 Cont ainment 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 US RETURN to Procedure and Step in Effect. [Step 7]

Examiner Note: FRP-0.1A, Response to Immi nent Pressurized Thermal Shock Condition, steps begin here.

US CHECK RCS pressure - GREATER THAN 325 PSIG (425 PSIG FOR ADVERSE CONTAINMENT). [Step 1]

RO/BOP VERIFY RHR Pump flow greater than 750 GPM and RETURN to 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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]

RO/BOP VERIFY RCS pressure - GREATER THAN 325 PSIG (425 PSIG 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]

RO/BOP VERIFY both AC Safeguards Buses ENERGIZED by Offsite Power.

[Step 10.a] RO/BOP PLACE both EDG EMERG STOP/START handswitches in STOP.

[Step 10.b]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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)]

RO/BOP CHECK Auxiliary Building and Safeguards Building radiation - NORMAL:

[Step 11.b]

CHECK PC-11 monitors - NORMAL OR Notify Radiation Protection to take local Radiation Surveys. [Step 11.b]

US NOTIFY Chemistry to obtain RCS samples to assist in determining 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 RO/BOP RCS pressure - GREATER THAN 325 PSIG (425 PSIG FOR ADVERSE CONTAINMENT). [Step 12.a]

RO/BOP VERIFY RHR Pump flow greater than 750 GPM and GO to Step 13. [Step 12.a RNO a]

US CHECK If Transfer to Cold Leg Recirculation Is Required. [Step 13]

RO/BOP VERIFY RWST Level - LESS THAN LO-LO LEVEL.

[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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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 STATEMENT Manually Start Safety Injection Pump 1-02 Prior to completing Attachment 2 of EOP-0.0A, Reactor Trip or Safety Injection.

BOP VERIFY Safety Injection Pumps - RUNNING. [Step 2] CRITICAL TASK Recognizes Safety Injection Pump 1-02 has failed to start and manually starts Safety Injection Pump 1-02. [Step 2 RNO]

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 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)]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 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]

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]

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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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 VLVCLOSED CB-08 1-HS-2398A SG 2 BLDN HELB ISOL VLVCLOSED CB-08 1-HS-2399A SG 3 BLDN HELB ISOL VLVCLOSED CB-08 1-HS-2400A SG 4 BLDN HELB ISOL VLVCLOSED 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 DMPR STOPPED/DEENERGIZED CV-01 X-HS-6188 PRI PLT SPLY FN 18 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6195 PRI PLT SPLY FN 19 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6202 PRI PLT SPLY FN 20 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6209 PRI PLT SPLY FN 21 & INTK DMPR STOPPED/DEENERGIZED 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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 CV-01 X-HS-6216 PRI PLT SPLY FN 22 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6223 PRI PLT SPLY FN 23 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6230 PRI PLT SPLY FN 24 & INTK DMPR STOPPED/DEENERGIZED 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 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 FN 3 & EXH DMPR STOPPED/DEENERGIZED CV-01 1-HS-5603 MS & FW PIPE AREA EXH FN 4 & EXH DMPR STOPPED/DEENERGIZED CV-01 1-HS-5618 MS & FW PIPE AREA SPLY FN 17 STOPPED/DEENERGIZED CV-01 1-HS-5620 MS & FW PIPE AREA SPLY 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 1 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 DMPRCLOSED CB-03 2-HS-5536 AIR PRG SPLY ISOL DMPRCLOSED BOP NOTIFY Unit Supervisor attachment instructions complete AND to IMPLEMENT FRGs as required.

EOP-0.0A, Attachment 2 steps are now complete.

Scenario Event Description NRC Scenario 1 CPNPP 2016 NRC SIMULATOR SCENARIO 1 REV. 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 GUARDED EQUIPMENT MANAGEMENT (GEM) SIGN POSTING LOG REASON FOR POSTING SIP 1-01 INOPERABLE STI-600.01-1 Page 1 of 1 REFERENCE USE Rev. 0 Component to be Posted Nomenclature Posting Installed Initial Posting Checked Initial Posting Removed Initial 1/1-APSI2 SIP 2 => CB / 830 / X-135 JGR RB 1APSI2 SAFETY INJECTION PUMP 1-02 MOTOR BREAKER => SG / 852 / 1-103 JGR RB S1-2 SAFETY INJECTION PUMP 1-02 ROOM => SG

/ 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.

Appendix D Scenario Outline Form ES-D-1 CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 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 No. Malf. No. Event Type* Event Description 1 RX05A I (RO, SRO) TS (SRO) PRZR level instrument LT-459 fails low 2 RX18 I (BOP, SRO) Feed Header Pressure Transmitter (PT-508) Fails High 3 RX09A I (RO, SRO) TS (SRO) Main Turbine 1 st Stage Pressure (PT-505A) Fails Low 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 6 ED02 C (BOP, SRO) TS (SRO) Loss of XST1 Transformer 7 ED01 EG06A M (RO,BOP,SRO)

Loss of offsite power Failure of the DG 1-01 to start (air start failure) 8 Emergency Boration due to loss of DRPI 9 FW09A M (RO,BOP,SRO)

Loss of all AFW 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) 1 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3)

Scenario Event Description NRC Scenario 2 CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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 1 st Stage Pressure Transmitter will fail low.

Crew actions are per ABN-709, Steam Line Pressure, Steam Header Pressure, Turbine 1 st Stage Pressure, and Feed Header Pressure Instrument Malfunction, Section 4.0 is required. Section 4.0 is designated for Turbine 1 st Stage Pressure Malfunction. Actions include placing Rod Control in Manual and bypassing the failed Turbine 1 st 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.

Scenario Event Description NRC Scenario 2 CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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.

Scenario Event Description NRC Scenario 2 CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 Risk Significance Determination Risk Significance Event Guidance Failure of risk important systems prior to Reactor Trip Loss of Transformer XST1 FSAR 8.2.1.2.1 - Two 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 sequence FSAR 15.2.6.3 Loss of Non-emergency AC power to the

station auxiliaries

Loss of Secondary Heat Sink EOS-0.2A, Natural Circulation Cooldown - For Units 1 and 2, 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.

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 Negative Reactivity to the Core (TSA 2.14)

STI 214.01; ABN-107, Emergency Boration; 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.

Scenario Event Description NRC Scenario 2 CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 Critical Task Determination Critical Task Safety Significance Cueing Measurable Performance Indicators Performance Feedback Initiate Emergency

Boration prior to exiting EOS-0.1A, Reactor Trip Response.

Shutdown Margin must be maintained. Since there are NO DRPI lights lit the bases states

to borate at least 3600 gallons of

7000 ppm borated water to ensure shutdown

margin is

maintained. This gallon value corresponds to 2 of the most

reactive rods stuck out. After the loss of offsite power and the failure

of the DG 1-01, DRPI will be dark and no CCP will be running.

Per attachment 1.A of

EOS-0.1A, ABN-107 will be performed.

Started CCP 1-02, started

Boric Acid Transfer Pump 1-02, and

opened 1/1-

8104, EMER BORATE VLV. Boration flow will be indicated on

1-FI-183A, EMER BORATE FLO. Establish an RCS bleed and feed path prior to exiting FRH-0.1A, Response to a

Loss of Secondary Heat

Sink. Actuating SI will ensure a feed

path of cool water to the RCS (core) and isolate the containment to confine any

RCS releases

from the bleed flow. The bleed flow through both

PORVs will

ensure that

enough cool water will feed from the ECCS

flow path to

remove sufficient

decay heat.

AFW flow will not be indicated on any AFW

flow meter. Also no AFW pumps will be running. A RED path showing on CSFST for heat sink. The need

for a heat sink as indicated by RCS temperature and pressure.

Actuated SI, ensured at least one CCP and SI pump is running with flow

indicated

providing a feed

path for the

RCS. Both PRZR PORVs open providing a bleed path for the RCS. Flow indicated on both a CCP and an SI pump. PRZR PORVs open with block

valves open.

RCS pressure

and temperature

lowering.

Scenario Event Description NRC Scenario 2 CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP Initialize to IC-16 and 2016 NRC Scenario 2.

EVENT TYPE MALF # DESCRIPTION DEMAND VALUE INITIATING 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 9 Condition FW09A TDAFWP trips on 1/1-8104 valve opening (60 second delay) TRIP 8104 Open 1 RX05A PRZR level channel LT-459 fails low 0 % K1 2 RX18 Main Feedwater Header Pressure transmitter fails high 1500 psig K2 3 RX09A Main Turbine First Stage pressure PT-505A fails low 0 % K3 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 9 Cond. FW09A TDAFWP trips on 1/1-8104 valve opening (60 second delay) TRIP 8104 Open

Scenario Event Description NRC Scenario 2 CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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 US Direct the performance of ABN-706, Pressurizer Level Instrumentation Malfunction Section 2.3 RO 1. Manually CONTROL u-LK-459, PRZR LVL CTRL OR u-FK-121, CCP CHRG FLO CTRL to maintain level at program.

RO 2. TRANSFER 1/u-LS-459D, PRZR LVL CTRL CHAN SELECT to an operable alternate controlling channel.

RO 3. ENSURE 1/u-LS-459E, u-LR-459 PRZR LVL SELECT selected to a valid channel.

RO 4. VERIFY normal letdown aligned - NO RO 4. RNO - WHEN pressurizer level is greater than 17%, THEN RESTORE letdown per Attachment 6.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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. RO 5. If necessary, RECLOSE 1/u-PCPR, PRZR CTRL HTR GROUP C by placing the control switch in the "ON" position.

RO 6. If desired, PLACE controller used in Step 1 in AUTO.

RO 7. VERIFY instruments on common instrument line - NORMAL (see )

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.

RO 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 switches for failed channel in CLOSED position per Attachment 3.

RO 9. VERIFY appropriate alarm AND trip status lights ON per Attachment 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 RO 1. OPEN OR VERIFY open both letdown isolation valves.

1/u-LCV-459, LTDN ISOL VLV

1/u-LCV-460, LTDN ISOL VLV RO 2. ENSURE u-PK-131, LTDN HX OUT PRESS CTRL in MANUAL AND 30% demand (50% if two orifice valves will be opened).

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 RO 3. ENSURE u-TK-130, LTDN HX OUT TEMP CTRL in MANUAL AND 50% demand.

RO 4. ADJUST charging to desired flow WHILE maintaining seal injection flow between 6 and 13 gpm.

RO 5. OPEN the desired orifice isolation valves.

1/u-8149A, LTDN ORIFICE ISOL VLV (45 GPM)

1/u-8149B, LTDN ORIFICE ISOL VLV (75 GPM)

1/u-8149C, LTDN ORIFICE ISOL VLV (75 GPM)

RO 6. ADJUST u-PK-131, LTDN HX OUT PRESS CTRL to obtain approximately 310 psig on u-PI-131, LTDN HX OUT PRESS, THEN PLACE in automatic.

RO 7. ADJUST u-TK-130, LTDN HX OUT TEMP CTRL to obtain 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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.

US DIRECT performance of ABN-709, Steam Line Pressure, Steam Header Pressure, Turbine 1 st 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.

BOP 2. ADJUST 1-SK-509A, FWPT Master Speed Controller to MAINTAIN 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 US 4. WHEN repairs are complete, THEN PLACE 1-SK-509A, FWP MASTER SPD CTRL in - AUTO as follows: 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.

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 3 Page 13 of 32 Event

Description:

Main Turbine 1 st Stage Pressure (PT-505A) Fails Low Time Position Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 Simulator Operator: When directed, EXECUTE Event 3 (Key 3). - RX09A, Main Turbine 1 st Stage Pressure Transmitter (PT-505) Fails Low.

Indications Available:

6D-1.10 - AVE TAVE T REF 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 T REF Deviation indication to maximum RO/BOP RESPOND to Annunciator Alarm Procedures.

RO/BOP RECOGNIZE Control Rods INSERTING due to Turbine Impulse Pressure Instrument failure.

RO/BOP REPORT PT-505, Turbine Impulse Pressure Channel I has failed low.

US DIRECT implementation of ABN-709, Steam Line Pressure, Steam Header Pressure, Turbine 1 st 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.

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 3 Page 14 of 32 Event

Description:

Main Turbine 1 st Stage Pressure (PT-505A) Fails Low Time Position Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 RO 3. RESTORE steam dump availability by placing Steam Dumps in STM PRESS Mode per Attachment 7.

Examiner Note: ABN-709 Attachment 7 steps are after the steps for section 4.0 (next page)

RO 4. TRANSFER 1-PS-505Z, TURB IMP PRESS CHAN SELECT to PT-506. Examiner Note: The crew will conduct a Reactivity Brief and execute a Reactivity Plan to restore TAVE to T REF. RO 5. ENSURE TAVE within 1ºF of T REF. 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.

US 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, IN PROPER STATE for existing plant conditions (DARK). - YES Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 3 Page 15 of 32 Event

Description:

Main Turbine 1 st Stage Pressure (PT-505A) Fails Low Time Position Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 US 10. VERIFY PCIP Window 1.3 - AMSAC BLK TURB < 40% PWR C 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 1 st 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.

BOP 2. MATCH 1-PK-507, STM DUMP PRESS CTRL demand to current Steam Dump Valve position.

BOP 3. VERIFY 1-PCIP, Window 1.4 - CNDSR AVAIL STM DMP ARMED C-9 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.

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 3 Page 16 of 32 Event

Description:

Main Turbine 1 st Stage Pressure (PT-505A) Fails Low Time Position Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 BOP 6. IF desired to control Steam Dumps in AUTO, THEN PERFORM the following:

a. VERIFY 1-PI-507, MS HDR PRESS indicates current MSL 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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 BOP 1. DETERMINE affected fan from the associated handswitch light 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 Simulator Operator: When contacted to investigate the fan trip wait 2 minutes and report back the breaker has tripped on motor overload.

RO/BOP 4. DISPATCH an operator to affected fan breaker to determine cause of trip. US 5. WHEN conditions permit, THEN PERFORM a Containment entry per STA-620 to check the fan for signs of damage (smoke, acrid odor, overheating).

US 6. CORRECT the condition OR INITIATE a CR per STA-421, as applicable.

When the plant is stable or at Lead Examiner discretion, PROCEED to Event 5

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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.

US Direct entry into ABN-302, Feedwater, Condensate, Heater Drain System 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 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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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. RO/BOP 4. Dispatch Operator to isolate affected recirc valve:

u-FV-2289, FWP A RECIRC VALVE

u-FV-2290, FWP B RECIRC VALVE BOP 5. Verify Main Feedwater pump suction pressure - GREATER THAN 200 PSIG

u-PI-2295, FWP A SUCT PRESS

u-PI-2297, FWP B SUCT PRESS RO/US 6. Verify the following: a. Rods - ABOVE ROD INSERTION LIMIT

b. Flux - (AFD) WITHIN LIMITS US 7. Verify Reactor Power change - LESS THAN 15% RTP WITHIN ONE HOUR. Examiner Note: The following steps will not be performed as power is unchanged for this event US 8. Notify QSE Generation Controller and update GAPS to "Create 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.

US 9. Plant Management has determined continued operation of the Feedwater pump is required with recirc flowpath isolated.

US 10. Restore power to level specified by Shift Manager.

BOP 11. WHEN steam dumps have closed, THEN reset C-7, if armed.

43/u-SD, STM DMP MODE SELECT

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 US 12. Initiate equipment repairs per STA-606.

BOP 13. Close u-HS-2286, LP FW HTR BYP VLV by performing Section 7.0 of 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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 US Direct entry into ABN-601, RESPONSE TO A 138/345 KV SYSTEM 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 US/BOP 1. Determine AC Power Status: a. Check the Unit - IN MODES 1, 2, 3 OR 4 - YES

b. Check 6.9 KV Safeguard Buses - AT LEAST ONE ENERGIZED - YES US/BOP c. Check Unit 6.9 KV Non-Safeguard Buses - ALL REMAINED ENERGIZED WITH LOADS CONNECTED TO THE BUS - YES d. GO TO Step 4 BOP 4. Check Switchyard Bus Status - ALL ENERGIZED

V-E BUS, 345 KV E. BUS VOLT (CB-12) - BETWEEN 340 KV and 361 KV

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)

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 BOP 5. Monitor Blackout Sequencer Status: a. Affected bus - ENERGIZED - YES 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.

BOP 6. Check Transformer XST1 Status: 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 US 1. Determine the origin for the loss of power by performing the following:

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/A'd 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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 STATEMENT Initiate Emergency Boration prior to exiting EOS-0.1A, Reactor Trip 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 RO 6. IF EMER BORATE FLOW OR CHRG FLOW can NOT be verified, THEN initiate Emergency Boration Flow per another method of ABN-107. RO 7. WHEN desired to terminate emergency boration (Reference Attachment 7 of ABN-107), THEN GO TO Step 8 of ABN-107.

Appendix D Operator Action Form ES-D-2 Operating Test : NRC Scenario # 2 Event # 9 Page 28 of 32 Event

Description:

Lo ss of Heat Sink Time Position Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 Examiner Note: FRH-0.1A, Response to Loss of Heat Sink, steps begin here US 1. Check If Secondary Heat Sink Is Required: a. RCS pressure - GREATER THAN ANY NON-FAULTED SG 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 RO 14. Verify RCS Feed Path: a. Check CCP SI flow indicator - CHECK FOR FLOW

b. Check SI pumps - BOTH RUNNING - NO RO 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 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 STATEMENT Establish an RCS bleed and feed path prior to exiting FRH-0.1A, Response to a Loss of Secondary Heat Sink.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 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.

Scenario Event Description NRC Scenario 2 CPNPP 2016 NRC SIMULATOR SCENARIO 2 REV. 1 ;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 GUARDED EQUIPMENT MANAGEMENT (GEM) SIGN POSTING LOG REASON FOR POSTING MD AFWP 1-02 INOPERABLE STI-600.01-1 Page 1 of 1 REFERENCE USE Rev. 0 Component to be Posted Nomenclature Posting Installed Initial Posting Checked Initial Posting Removed Initial 1-HS-2450A MD AFWP 1 => CB / 830 / X-135 JGR RB 1APMD1 AUXILIARY FEEDWATE R PUMP 1-01 MOTOR BREAKER => SG / 810 / 1-083 JGR RB S1-16 MOTOR DRIVEN AUXILIARY FEEDWATER 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.

Appendix D Scenario Outline Form ES-D-1 CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 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 1 RP05D I (RO, SRO) TS (SRO) Cold Leg Loop 4 NR Temperature Transmitter Failure (TE-441B) Fails High 2 RP03A I (BOP, SRO) TS (SRO) Steam Generator (1-01) Steam Line Pressure Instrument (PT-514) Fails Low. 3 Override C (RO, SRO) Letdown HX Outlet Flow Controller Failure (TK-130) Fails Low 4 FW22 C (BOP, SRO) TS (SRO) Station Service Water Pump 1-01 Trip 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)

Scenario Event Description NRC Scenario 3 CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 SCENARIO

SUMMARY

NRC 3 Event 1 (Key 1) The crew will assume the watch at 100% power with no scheduled activities per IP O-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, T c/N-16 Instrumentation Malfunction, Section 2.0. Section 2.0 is designated for T c/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 1 st-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 Specificati on LCO 3.7.8, Station Servic e 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 cr ew 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.

Scenario Event Description NRC Scenario 3 CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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.

Scenario Event Description NRC Scenario 3 CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 Risk Significance Determination Risk Significance Event Guidance Failure of risk important system prior to Reactor Trip

Event 4 - Station Service Water Pump Trip

ABN-501; DBD-ME-011 - Initial 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 Reactor by momentarily de-energizing 1B3 and 1B4

Event 8 - Closing all intact SG MSIVs upon failure of the

ruptured SG MSIV to close FSAR 15.8 - The worst common mode failure which is postulated to occur is the failure to trip the reactor after an anticipated transient has occurred.

FSAR 15.6.3.2 - The closing of all intact SG MSIVs falls in line 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.

Risk significant core damage sequence Events 5 - Steam Generator Tube Rupture (1) STI-214.01 TCA-1.9 - Manual 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

Scenario Event Description NRC Scenario 3 CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 Critical Task Determination Critical Task Safety Significance Cueing Measurable Performance Indicators Performance Feedback CT Manually Trip Reactor due to Failure to Automatically Trip prior to exiting EOP-0.0A, Reactor Trip or Safety Injection Recognize a failure or an incorrect automatic actuation of an ESF system or component. FSAR

7.1.2.1 Procedural direction at EOP-0.0A Step 1 to determine if a reactor trip has occurred. Position indication of the Reactor Trip breakers and Reactor Power, Annunciator First out alarms. The operator will attempt to manually trip the Reactor with the handswitches on both CB-07 and CB-10; however, the Reactor will fail to trip. The operator will then momentarily deenergize the 480V normal switchgear 1B3 and 1B4 to secure

power to the Rod Drive MG sets. De-energizing the Rod Drive MG sets will result in a loss of power to the Rod Drive Mechanisms and the Control

Rods will insert into the core. Reactor Trip Breakers will remain closed, neutron flux will lower and rod bottom lights will be lit. CT Identify and Isolate the Ruptured Steam Generator Prior to Commencing an Operator Induced Cooldown per EOP-

3.0A, Steam Generator Tube Rupture. Take one or more actions that would

prevent a challenge to plant safety. STI-214.01, TCA-1.9; FSAR 15.6.3.1.1; WCAP-16871-P, Section 6.4; DBD-ME-027 Procedurally driven from EOP-3.0A, to identify and isolate a ruptured SG. Indications include MSL Radiation alarms and SG level.

The operator will attempt close the ruptured SG MSIV from the control room, however, the MSIV will fail to close and all other MSIVs must be closed. The MSIV will be locally closed in the field. The operator will stop feeding the SG once sufficient level to cover the tubes is available. SG pressure increasing, AFW flow reduced to zero and valve position indications.

Scenario Event Description NRC Scenario 3 CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP Initialize to IC-18 and 2016 NRC Scenario 3.

EVENT TYPE MALF # DESCRIPTION DEMAND VALUE INITIATING 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 3 Override Letdown HX Outlet Flow Controller Failure (TK-130) Fails Low f:10 K3 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 7 RPR112 RPR113 Reactor Trip Breakers Locally Opened OPEN K13 8 MS08C SG 1-03 MSIV Fails to Close OPEN K0

Scenario Event Description NRC Scenario 3 CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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 T REF 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 T COLD failed high.

US DIRECT performance of ABN-704, Tc / N-16 Instrumentation Malfunction, Section 2.0.

Examiner Note: The RO may place 1-FK-121, Charging Flow Controller, in MANUAL to maintain PZR level on setpoint.

RO PLACE 1/1-RBSS, CONTROL ROD BANK SELECT Switch in MANUAL.

[Step 2.3.1]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 RO SELECT LOOP 4 on 1-TS-412T, T AVE Channel Defeat. [Step 2.3.2]

RO/BOP VERIFY Steam Dump System is NOT actuated and NOT armed.

[Step 2.3.3]

Examiner Note: The crew will conduct a Reactivity Brief and execute a Reactivity Plan to restore TAVE to T REF. US/RO RESTORE T AVE to within 1°F of T REF. [Step 2.3.4]

RO/BOP SELECT LOOP 4 on 1/1-JS-411E, N16 Power Channel Defeat.

[Step 2.3.5]

RO ENSURE a valid N16 channel supplying recorder on 1/1-TS-411E, 1 TR 411 CHAN SELECT. [Step 2.3.6]

RO/BOP VERIFY PCIP, Window 3.4 - TURB LOAD REJ STM DMP ARMED C-7, not 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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.

US DIRECT performance of ABN-709, STM LINE, STM HDR, & TURB 1st STAGE PRESS. & FEED HDR PRESS. INSTR MALFUNCTION, Section 2.0, Steam Line Pressure Instrument Malfunction.

BOP CHECK ONE Main Steamline Pressure Channel indicating - GREATER 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]

BOP VERIFY Steam Generator Atmospheric Relief Valves - CLOSED:

[Step 2.3.2]

1-ZL-2325, SG 1 ATMOS RLF VLV 1-ZL-2326, SG 2 ATMOS RLF VLV 1-ZL-2327, SG 3 ATMOS RLF VLV 1-ZL-2328, SG 4 ATMOS RLF VLV 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 BOP PLACE 1-FK-510, SG 1 FW FLO CTRL in MANUAL AND CONTROL Steam Generator 1-01 level in normal operating range: [Step 2.3.3]

BOP Manually CONTROL 1-SK-509A, FWPT MASTER SPD CTRL as necessary.

[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]

BOP PLACE 1-FK-510, SG 1 FW FLO CTRL in AUTO AND 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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.

RO RECOGNIZE 1-TK-130, LTDN HX OUT TEMP CTRL has failed to 0% output 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 BOP VERIFY 1-ZL-4646, LTDN HX CCW RET VLV is OPEN. (1-CB-03) [Step 5]

RO IF 1-ZL-4646 is CLOSED, place 1-TK-130, LTDN HX OUT TEMP CTRL in 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]

US/RO NOTIFY Chemistry and Radiation protection personnel that Letdown has 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 Temperatur e is appropriately controlled, or at Lead Examiner discretion, PROCEED to Event 4.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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.

BOP RECOGNIZE 1-HS-4250A, Service Water Pump 1-01 amber MISMATCH and white TRIP lights illuminated.

US DIRECT performance of ABN-501, Station Service Water System Malfunction, Section 2.0, Station Service Water Pump Trip Examiner Note: Diamond steps () are Initial Operator Actions.

BOP PLACE CS-1DG1E, Train A Diesel Generator Emergency Start/Stop 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 BOP VERIFY CCW Heat Exchanger outlet temperature on Train A remains < 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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 RO Immediately PLACE 1/1-RBSS, CONTROL ROD BANK SELECT Switch in AUTO to allow the Rod Control System to Automatically respond to the plant transient.

US DIRECT performance of ABN-401, Main Turbine Malfunction, Section 9.0, Inadvertent Opening of an HP or LP Stop or Control Valve.

BOP VERIFY operable HP Control Valves are 98% open. [Step 9.3.1]

RO/BOP PERFORM the following: ENSURE 1/1-RBSS, CONTROL ROD BANK SELECT in AUTO.

[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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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]

RO VERIFY PR Delta Flux - (AFD) WITHIN LIMITS: [Step 9.3.3] 1-NI-41C, PR DELTA FLUX CHAN I 1-NI-42C, PR DELTA FLUX CHAN II 1-NI-43C, PR DELTA FLUX CHAN III 1-NI-44C, PR DELTA FLUX CHAN IV RO VERIFY the Steam Dumps AND Rod Control System - RESPONDING TO MAINTAIN Tave to Tref. [Step 9.3.4] 1-TI-412A, AVE Tave-Tref DEV RO VERIFY Pressurizer Level - TRENDING TO PROGRAM LEVEL. [Step 9.3.5] 1-LR-459, PRZR LVL/PRZR LVL STPT RO VERIFY Pressurizer Pressure - TRENDING TO PROGRAM PRESSURE.

[Step 9.3.6] 1PR-455, PRESS

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 BOP CHECK Steam Generator Feedwater Level AND Flow Control Valve status:

[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)

BOP ALL Steam Generator Feedwater Flow Valves - IN AUTO

[Step 9.3.7.b] 1-FK-510, SG 1 FW FLO CTRL 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]

BOP VERIFY Turbine Load - STABLE [Step 9.3.9] GEN MEGAWATTS GEN MEGAVARS BOP VERIFY ALL operable HP Turbine Control Valves - INDICATE LESS THAN 100% OPEN: [Step 9.3.10]

TG Control Display OR 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 US REFER to TS/TR listed in Section 10.1 [Step 9.3.11]

BOP RESET Turbine Runback per Section 8.0, if necessary (NOT required)

[Step 9.3.12]

When the plant has been stabilized, or at Lead Examiner discretion, PROCEED to Events 6, 7

and 8.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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.

RO/BOP DETERMINE Reactor Trip/Safety Injection initiation required. Attempt to 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 STATEMENT Manually Trip Reactor due to Failure to Automatically Trip prior to 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]

BOP IF reactor will not trip, THEN momentarily de-energize 480 V normal switchgear 1B3 and 1B4. [Step 1.a RNO] CRITICAL TASK BOP Momentarily places BOTH CS-1B3-1, INCOMING BKR 1B3-1 AND 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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.

RO PLACE 1/1-SIA2, SI MAN ACT Switch to ACT position at CB-07 and 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 US/BOP INITIATE Proper Safeguards Equipment Operation Per Attachment 2.

[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, .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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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 Generat or 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 CRITICAL TASK STATEMENT Identify and Isolate the Ruptured Steam Generator Prior to 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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]

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 Applicant's 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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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]

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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 VLVCLOSED CB-08 1-HS-2398A SG 2 BLDN HELB ISOL VLVCLOSED CB-08 1-HS-2399A SG 3 BLDN HELB ISOL VLVCLOSED CB-08 1-HS-2400A SG 4 BLDN HELB ISOL VLVCLOSED 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 DMPR STOPPED/DEENERGIZED CV-01 X-HS-6188 PRI PLT SPLY FN 18 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6195 PRI PLT SPLY FN 19 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6202 PRI PLT SPLY FN 20 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6209 PRI PLT SPLY FN 21 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6216 PRI PLT SPLY FN 22 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6223 PRI PLT SPLY FN 23 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-6230 PRI PLT SPLY FN 24 & INTK DMPR STOPPED/DEENERGIZED CV-01 X-HS-3631 UPS & DISTR RM A/C FN 1 &

BSTR FN 42 STARTED 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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 CV-01 X-HS-3632 UPS & DISTR RM A/C FN 2 &

BSTR FN 43 STARTED 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 FN 3 & EXH DMPR STOPPED/DEENERGIZED CV-01 1-HS-5603 MS & FW PIPE AREA EXH FN 4 & EXH DMPR STOPPED/DEENERGIZED CV-01 1-HS-5618 MS & FW PIPE AREA SPLY FN 17 STOPPED/DEENERGIZED CV-01 1-HS-5620 MS & FW PIPE AREA SPLY 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 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 DMPRCLOSED CB-03 2-HS-5536 AIR PRG SPLY ISOL DMPRCLOSED BOP NOTIFY Unit Supervisor attachment instructions complete AND to IMPLEMENT FRGs as required.

EOP-0.0A, Attachment 2 steps are now complete.

Scenario Event Description NRC Scenario 3 CPNPP 2016 NRC SIMULATOR SCENARIO 3 REV. 1 ;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

Appendix D Scenario Outline Form ES-D-1 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 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 1 IA06A C (BOP,SRO) Instrument Air Compressor 1-01 Trip Instrument Air Compressor 1-02 Failure to Start 2 R (RO) N (BOP, SRO) Raise Power to 6% to 8% in Preparation for Synchronizing Main Generator to Electrical Grid 3 RX12 I (BOP,SRO) Main Steam Header Pressure (PT-507) Fails High on 360 second ramp 4 TP06A C (BOP,SRO) Turbine Plant Cooling Water Pump 1 Trip Turbine Plant Cooling Water Pump 2 Failure to Start 5 RX04A I (BOP, SRO) TS (SRO) Steam Generator (1-01) Level Channel (LT-551) Fails Low 6 NI02B I (RO) TS (SRO) Intermediate Range Channel N-36 Fails High 7 RP14B M (RO, BOP, SRO)Spurious Train B Safety Injection Actuation Signal 8 RP01 C (RO,SRO) Automatic Reactor Trip Failure Reactor Protection System Failure requires Manual Reactor Trip 9 CS02H C (RO) Containment Spray Pump 1-04 fails to start on the SI Sequencer 10 RC08C1 M (RO, BOP, SRO)Small Break Loss of Coolant Accident when Safety Injection Pump 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)

Scenario Event Description NRC Scenario 4 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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 1 st-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 Injectio n 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.

Scenario Event Description NRC Scenario 4 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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.

Scenario Event Description NRC Scenario 4 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 Risk Significance Determination Risk Significance Event Guidance Risk significant core damage sequence Event 7 - Automatic Reactor Trip Failure

Event 9 - Small Break Loss of Coolant Accident FSAR 7.2.1.1.1 - The Reactor Trip 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).

STI-214.01 TSA-2.11 - Initiate RCP Trip When SBLOCA Criteria Met within 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

Terminate ECCS Following a Spurious Safety Injection 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.

STI-214.01 TSA-1.7 - ECCS injection terminated within 14 minutes(1) from event initiation. (1) Crew manning for Initial License Examination less than Timed Operator Action validation constraints

Scenario Event Description NRC Scenario 4 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 Critical Task Determination Critical Task Safety Significance Cueing Measurable Performance Indicators Performance Feedback Manually Trip Reactor Due to Reactor Protection

System Failure Prior to Exiting EOP-0.0A, Reactor Trip or Safety Injection.

Recognize a failure or an incorrect automatic actuation of an ESF system or component to preclude degradation of any barrier to fission product release. FSAR 7.2.1.1.1 Procedural direction at EOP-0.0A Step 1 to determine if a reactor trip has occurred. Position indication of the Reactor Trip breakers and Reactor Power, Annunciator First out alarms. The operator will manually trip the Reactor with the handswitch on CB-07 or CB-10 placed to trip. Reactor Trip Breakers open, flux lowering, rod bottom lights lit. Trip Reactor Coolant Pumps within 5 minutes upon a Loss of Subcooling per

EOP-1.0A, Loss of Reactor or Secondary Coolant. Take one or more actions that would

prevent a challenge to plant safety to preclude a degradation of any barrier to fission product release. FSAR II.K.3.5; WCAP-9584; WOG ERG Generic Issue for RCP Trip /

Restart Procedurally driven from EOP-1.0A. Availability of Subcooling indication both on meters and computer.

The operator will secure ALL RCPs using the handswitches on CB-05. Indication of pump stop including light

indication, flow and motor current lowering.

Scenario Event Description NRC Scenario 4 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 SIMULATOR OPERATOR INSTRUCTIONS for SIMULATOR SETUP Initialize to IC-48 and 2016 NRC Scenario 4.

EVENT TYPE MALF # DESCRIPTION DEMAND VALUE INITIATING PARAMETER SETUP Override IA Compressor 1-02 fails to auto start FAIL K0 (1) 4 TP07B Turbine Plant Cooling Water Pump 2 Auto Start Failure FAIL K0 8 RP01 Automatic Reactor Trip Failure FAIL K0 9 CS02H Containment Spray Pump 1-04 fails to start on the SI 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% - -

3 RX12 Main Steam Header Pressure (PT-507) Failure 1500 psig K3 (360 sec. ramp) 4 TP06A Turbine Plant Cooling Water Pump 1 Overcurrent Trip TRIP K4 4 TP07B Turbine Plant Cooling Water Pump 2 Auto Start Failure FAIL K0 5 RX04A SG (1-01) Level Channel (LT-551) Failure 0% K5 6 NI02B IR N-36 detector fails high 7.6e-5 amps K6 7 RP14B Spurious Train B Safety Injection Actuation - K7 8 RP01 Automatic Reactor Trip Failure FAIL K0 9 CS02H Containment Spray Pump 1-04 fails to start on the SI 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.

Scenario Event Description NRC Scenario 4 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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, In strument 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 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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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 BOP F. Slowly INCREASE Reactor power to approximately 6% - 8%.

When power has been raised to 6 - 8%, or at Lead Examiner's discretion, PROCEED to Event 3.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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 - T REF 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.

RO REPORT Reactor Coolant System temperature lowering, Steam Dump Valves opening, and PT-507, Steam Header Pressure Channel failure.

US DIRECT implementation of ABN-709, Steam Line Pressure, Steam Header Pressure, Turbine 1 st Stage Pressure, and Feed Header Pressure Instrument Malfunction.

Section 3.3 BOP 1. CHECK 1-PI-507, MS HDR PRESS indicating HIGHER/LOWER than 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 BOP 3. MONITOR Steam Generator Levels:

a. VERIFY SG levels - STABLE AT OR TRENDING TO NORMAL PROGRAM. - NO BOP 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 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.

BOP 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. 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 BOP 5. MANUALLY CONTROL 1-SK-509A, FWPT MASTER SPD CTRL to MAINTAIN correct differential pressure until malfunction is corrected (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.

US 7. WHEN repairs are complete, THEN PLACE 1-SK-509A, FWPT MASTER SPD CTRL in - AUTO as follows:

When plant conditions are stable, or at Lead Examiner's discretion, PROCEED to Event 4.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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.

BOP RECOGNIZE TPCW Pump 1-01 has Tripped AND TPCW Pump 1-02 has 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.

BOP 1. ENSURE a standby TPCW pump is operating: 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 BOP A. IF NO TPCW pump operating, THEN GO to ABN-306 for Loss of TPCW. BOP B. IF TPCW Pump 1-01 tripped, THEN REFER to ABN-306 for TPCW 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 BOP 1. VERIFY TPCW Head Tank Level - GREATER THAN 6%. 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 BOP 3. VERIFY TPCW Head Tank Level - GREATER THAN 20%. 1-LI-3051, TPCW HEAD TK LVL L6907A, TPCW HEAD TANK LEVEL BOP 4. VERIFY 1-FI-3061, TPCW PMP DISCH FLO - WITHIN LIMITS 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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 (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 Examiner's discretion, PROCEED to Event 5

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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.

BOP RECOGNIZE Steam Generator 1-01 Level Transmitter (LT-551) failed low, 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%.

US DIRECT performance of ABN-710, Steam Generator Level Instrumentation Malfunction.

Section 2.3 BOP 1. VERIFY controlling level channel - FAILED.

BOP 2. Manually CONTROL the following, as necessary to maintain SG - AT PROGRAMMED LEVEL. u-LK-550, SG 1 BYP CTRL BOP 3. VERIFY instruments on common instrument line indicate NORMAL (See Attachment 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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 BOP 4. DETERMINE all HI-HI level bistable windows on Trip Status Light Box (TSLB-3) for Steam Generator 1-01 are DARK. SG 1 (Channels 517, 518, and 519) windows 2.2, 3.2, and 4.2 BOP 5. VERIFY automatic SG level control DESIRED a. Alternate level control channel responding normally.

b. Automatic level control desired, as determined by Unit Supervisor.

BOP 6. SELECT alternate channel: 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.

BOP 8. PLACE Feedwater Flow OR Feedwater Bypass Control Valve in AUTOMATIC AND ENSURE proper control.

US 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 switches for failed level channel in CLOSE utilizing Attachments 2

and 3.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 US 10. VERIFY appropriate Alarms AND Trip Status Lights LIT per 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 Examiner's discretion, PROCEED to

Event 6.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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 RO 2. VERIFY Actual Reactor Power - GREATER THAN P-6 SETPOINT (1X10-10amps) - YES RO 3. VERIFY Reactor Power - GREATER THAN P-10 SETPOINT (10%) -

NO 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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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)

US 4. VERIFY Reactor Power reduction - NOT IN PROGRESS OR REQUIRED - NO Simulator Operator: When contacted as the prompt team, acknowledge the request.

US 5. REFER to Technical Specifications listed in section 3.1 of this 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 Examiner's discretion, PROCEED to Events 7, 8, 9, and 10.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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 STATEMENT Manually Trip Reactor Due to Reactor Protection System Failure Prior 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 BOP 2. VERIFY Turbine Trip: All HP turbine stop valves - CLOSED

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 BOP 3. VERIFY Power to AC Safeguards Buses: a. AC safeguards busses - AT LEAST ONE ENERGIZED 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.

RO 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) 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 RO 6. VERIFY AFW Alignment: a. MDAFW Pumps - RUNNING - YES 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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 RO/BOP 6. ESTABLISH Instrument Air and Nitrogen to Containment. a. ESTABLISH instrument air VERIFY air compressor running Establish instrument air to containment OPEN 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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)

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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. CRITICAL TASK STATEMENT Trip Reactor Coolant Pumps within 5 minutes upon a Loss of 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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 US 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 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.

US 12. CHECK if RCS Cooldown and Depressurization Is Required: a. RCS pressure - GREATER THAN 325 PSIG (425 PSIG FOR 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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.

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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 BOP 13. Verify components on Table 1 are properly aligned:

Unit 1 Main Control Board Component Location Equipment Number 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 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 Panels Component Location Equipment Number Description Condition 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 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 Applicant's Actions or Behavior CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 1 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 DMPR STOPPED/DEENERGIZED CV-01 X-HS-5603 MS & FW PIPE AREA EXH FN 4 & EXH DMPR STOPPED/DEENERGIZED 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 Control Board Component Location Equipment Number Description Condition 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.

Scenario Event Description NRC Scenario 1 CPNPP 2016 NRC SIMULATOR SCENARIO 4 REV. 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

@@ Line 2: / Line 2: @@
 | number = ML16293A974
 | issue date = 07/11/2016
-| title = Comanche Peak-2016-07 Proposed OP Test
+| title = 2016-07 Proposed OP Test
 | author name = Gaddy V
 | author affiliation = NRC/RGN-IV/DRS/OB

ML16293A974: Difference between revisions

Revision as of 07:02, 10 April 2019

Text

50/55 = 0.91 +/- 0.01. RECORD ICRR

50/65 = 0.77 +/- 0.01. RECORD ICRR

50/88 = 0.57 +/- 0.01. RECORD ICRR

50/333 = 0.15 +/- 0.01. RECORD ICRR

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