Text

2016-07 Final Operating Test
	ML16262A037
Person / Time
Site:	Comanche Peak
Issue date:	07/18/2016
From:	Vincent Gaddy; Operations Branch IV
To:	;
References
	Download: ML16262A037 (291)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Task Summary Rev. 1 Facility: CPNPP Units 1 and 2 Date of Examination:

July 20 1 6 Examination Level: RO SRO Operating Test Number:

NRC Administrative Topic (See Note)

Type Code* Describe activity to be performed Conduct of Operations (RA1) D ,R 2.1.2 3 Ability to perform specific system and integrated plant procedures during all modes of plant operation

. (4.3) JPM: Calculate BOL Boration for Long Term Use

. (R O 1 307 D) Conduct of Operations (RA2) M ,R 2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant temperature, secondary plant, fuel depletion etc.

(4.1) JPM: Determine Reactivity Effects When Starting Positive Displacement Charging Pump. (RO1310E) Equipment Control (RA3) D ,R 2.2.1 Ability to perform pre

-startup procedures including operating those controls associated with plant equipment that could affect reactivity. (4.5) JPM: Perform a 1/M Plot and Predict Critical Conditions. (RO1003A) Radiation Control (RA4) D,R 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (3.

5) JPM: Determine Entry Conditions for Radiation Area Clearance. (RWT056 B) Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

ES-301 Administrative Topics Outline Form ES-301-1 Task Summary Rev. 1

Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs;

< 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected)

R A1 The applicant will calculate BOL Boration for long term use per SOP

-104A, Reactor Makeup and Chemical Control System, Attachment 2, BOL Boration for Long-Term Use. Critical steps include determining Reactor Coolant System corrected boron, gallons of Reactor Makeup Water to offset boron, and potentiometer settings for the Chemical and Volume Control System. This is a direct from bank JPM. (K/A 2.1.2 3 - IR 4.3) R A2 The applicant is presented with information pertaining to the boron concentration in the suction piping to the Positive Displacement Charging Pump and the Reactor Coolant System. The applicant will use SOP

-103A, Chemical and Volume Control System to determine the reactivity effects of the planned evolution.

The critical steps will be to calculate the change in RCS boron concentration and RCS temperature

. The JPM is modified from a previous version by changing the RCS boron concentration and the concentration in the PDP suction line. The prior version was a resulting boration. The modified version is a resulting dilution. This is a modified JPM. (K/A 2.1.43

- IR 4.1) R A3 The applicant will perform a 1/M plot for a Reactor Startup per IPO

-002A, Plant Startup From Hot Standby, Attachment 2, Inverse Count Rate Ratio Calculation The critical steps include the critical steps include calculating and plotting 1/M, predicting critical conditions, and identifying action for criticality above the power dependent insertion limit. This is a direct from bank JPM. (K/A 2.2.1

- IR 4.5) R A4 The applicant will determine the radiological requirements for implementing a Clearance in a Radiological Controlled Area per STA

-656, Radiation Work Control, RPI

-602, Radiological Surveillance and Posting, and RPI

-606, Radiation Work and General Access Permits. Critical tasks include identifying Dose Monitoring Requirements, Protective Clothing Requirements, highest contamination level, and highest dose rate. This is a direct from bank JPM. (K/A 2.2.37

- IR 3.5)

Appendix C JPM STEPS Form ES-C-1 CPNPP 2016 NRC JPM RA1 (RO1307D)

Rev. 2 Facility: CPNPP JPM # NRC RA1 Task # RO 1307 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 16 00 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) Re f. 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. 2 CLASSROOM SETUP Handout: PROVIDE the examinee with a copy of:

SOP-104A, Reactor Make

-up and Chemical Control System Attachment 2, BOL Boration for Long

-Term Use Page 1 (labeled Procedure 1)

Appendix C JPM STEPS Form ES-C-1 CPNPP 2016 NRC JPM RA1 (RO1307D)

Rev. 2 - Check Mark Denotes Critical Step START TIME:

Examiner Note

The following steps are from SOP-104A, Attachment 2 page 1 Examiner Note

Refer to answer key for calculated values Perform Step:

1 1.0 RECORD Reference Data as follows: RCS Boron

__________

BAT Boron

__________

B10 WT Fraction

__________

Performance Standard: ENTERED data on Attachment 2 at Step 1.0 Comment: SAT UNSAT Perform Step

2 2.A CALCULATE volumes in pot settings as follows:

RCS Corrected Boron:

Performance Standard: CALCULATED 1512 to 1513. [allowable error based on rounding after first calculation and then performing second calculation]

Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 CPNPP 2016 NRC JPM RA1 (RO1307D)

Rev. 2 Perform Step:

3 2.B CALCULATE volumes in pot settings as follows:

Gallons of RMUW to offset boron in Blender Pipe during normal VCT makeup:

Performance Standard: CALCULATED 132 to 133 gallons. [allowable error based on rounding carried from Step 2 and those performed in this step]

Comment: SAT UNSAT Perform Step:

4 2.C CALCULATE volumes in pot settings as follows:

Boron gallons for a Manual Blend:

Performance Standard: CALCULATED 10 to 11 gallons. [allowable error based on rounding]

Comment: SAT UNSAT Perform Step:

5 2.D CALCULATE volumes in pot settings as follows:

Boric Acid Pot Setting for a Manual Blend:

Performance Standard: CALCULATED 4.69 +/- 0.1. [allowable error based on rounding and accuracy of Pot settings]

Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 CPNPP 2016 NRC JPM RA1 (RO1307D)

Rev. 2 Perform Step:

6 2.E CALCULATE volumes in pot settings as follows:

Boric Acid Pot Setting for AUTO Makeup:

Performance Standard: CALCULATED 6.62 +/- 0.1. [allowable error based on rounding and accuracy of Pot settings]

Comment: SAT UNSAT Perform Step:

7 2.F CALCULATE volumes in pot settings as follows:

Gallons of RMUW to offset boron in Blender Pipe when returning Makeup System to Automatic:

Performance Standard: CALCULATED 86 to 87 gallons. [allowable error based on rounding carried from Step 2 and those performed in this step]

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

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 L ong-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. 1 Facility: CPNPP JPM # NRC RA2 Task # RO 1310 K/A # 2.1.43 4.1 / 4.3 Title: Determine Reactivity Effects When Starting Positive Displacement Charging Pump Examinee (Print):

Testing Method: Simulated Performance:

Classroom:

X Actual Performance:

X Simulator:

Alternate Path:

Plant: Time Critical:

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

Initial Conditions:

Given the following conditions:

Unit 1 is 100% power The Positive Displacement Charging Pump must be placed in service per SOP-103A, Chemical and Volume Control System The last time the Positive Displacement Charging Pump was run the Reactor Coolant System Boron concentration was 2 5 ppm Current Reactor Coolant System Boron concentration is 1 222 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, Step s 5.3.1.C REPORT findings to the Unit Supervisor Task Standard:

Utilizing SOP-103A, calculate d the change in boron concentration and resultant change in temperature when placing the Positive Displacement Pump in service

. Re f. Materials:

SOP-103A, Chemical and Volume Control System , Rev. 18-1 5. Reactivity Briefing Sheet for 1 222 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. 1 CLASSROOM SETUP Handout: PROVIDE the examinee with a copy of:

SOP-103A , Chemical and Volume Control System, Step 5.3.1.C

. (labeled Procedure

1) 90.4 EFPD Reactivity Briefing Sheet. (labeled Handout 1 Rev. 0)

Appendix C JPM STEPS Form ES-C-1 Page 3 of 5 CPNPP 2016 NRC JPM RA2 (RO1310E)

REV. 1 - Check Mark Denotes Critical Step START TIME:

Examiner Note

The following steps are from SOP-103A, Step 5.3.1

. Perform Step: 1 5.3.1.C.1) + calculation DETERMINE the change in RCS Boron concentration which will occur due to the PDP run

Change in RCS Boron Concentration due to PDP run Performance Standard: CALCULATE D Change in RCS Boron Concentration

( 2 5 ppm PDP - 1 222 -1.53 to -1.54 ppm Comment: SAT UNSAT Perform Step: 2 5.3.1.C.2).a) + calculation IF in MODE 1 or 2 THEN PERFOM the following:

DETERMINE the impact of water in the PDP piping on reactivity by the performing the following calculation:

-1.53 ppm From the Reactivity Briefing Sheet, obtain the following information:

ITC _____ pcm/º F HFP Differential Boron Worth _____ pcm/ppm Performance Standard: DETERMINED the following from the Reactivity Briefing Sheet:

- 10.9 pcm/ºF - 7.0 pcm/ppm Comment: SAT UNSAT Perform Step: 3 5.3.1.C.2).a) + calculation Calculate: ITC / HFP Differential Boron Worth

ºF Performance Standard: CALCULATE D change in ppm /

ºF: - 10.9 pcm/ ºF / - 7.0 pcm/ 1.5 to 1.6 ppm/ºF Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 Page 4 of 5 CPNPP 2016 NRC JPM RA2 (RO1310E)

REV. 1 Examiner Note

R ound iAVE may occur. Perform Step: 4 5.3.1.C.2).a) + calculation Calculate: AVE (-1) ppm / ppm / ºF Performance Standard: CALCULATE D change in TAVE as follows:

AVE (-ºF (-1)(-1.53 ppm) / 1.56 ppm/ 0.9 to 1.1 ºF Comment: SAT UNSAT Perform Step: 5 5.3.1.C.2).b) IF AVE calculated above is >

0.5 ºF , THEN NOTIFY the Unit Supervisor and discuss contingency actions.

Performance Standard: DETERMINE D TAVE calculated is greater than 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. 1 Initial Conditions

Given the following conditions:

Unit 1 is 100% power The Positive Displacement Charging Pump must be placed in service per SOP-103A, Chemical and Volume Control System The last time the Positive Displacement Charging Pump was run the Reactor Coolant System Boron concentration was 25 ppm Current Reactor Coolant System Boron concentration is 1222 ppm Initiating Cue

The Unit Supervisor directs you to PERFORM the following:

CALCULATE a Reactivity Evaluation for starting the Positive Displacement Charging Pump per SOP

-103A, Chemical and Volume Control System, Steps 5.3.1.C REPORT findings to the Unit Supervisor

Valid for approximately 7 days.Calculations based on core design values, and assume:Burnup = MWD/MTU EFPDPower = RTPBoron = ppm B10 Conc = w/o Control Bank D = stepsReactivity affects of Control Bank DHFP Diff Worth @ 215.0 steps = pcm / stepHFP Integral Rod Worth for CBD Step Positions:Reactivity affects of BoronHFP Diff Boron Worth @ 1222 ppm = pcm / ppm1-FK-110 Pot Setting for Blended Flow @ 1222 ppm = (Assuming BAT concentration of 7447.0 ppm)Reactivity affects of Powe rPower Coefficient of Reactivity = pcm / % RTPDilution to equal 1% Power Increase = gallons RMUWBoration to equal 1% Power Decrease = gallons boric acidReactivity affects of RCS TemperatureTemperature Coefficient of Reactivity (ITC) = pcm / FBoration to equal 1F Temperature Decrease = gallons boric acid Dilution to equal 1F Temperature Increase = gallons RMUWLoad Reduction equal to 1F Tave Increase = MWe11.05.21-7.0-0.916.6 175Steps205-18.2pcm-61.4 21187.8-11.895.218.0-10.9-9.6206-16.6-15.1Steps-88.6170-103.1195-37.4190-48.9 185-10.8209-12.2 0.0-0.8 210-1.9-1.1-5.4208-1.4214-6.3207-2.4Stepspcm 2152250.0Stepspcm218-3.1 224 223 220 219 222 2210.183400-7.3212-8.4217-3.8216-4.5 213 215 1222Reactivity Briefing Sheet for Stable Operation4000.090.4 100 BOL PROJECTIONS - SIMULATOR USE ONLY 180from assumed inputs.Burnup in the BOL rangeNOTE: Re-create the Briefing Sheetif current values significantly differpcm200-27.1-74.7-13.6 Appendix C JPM STEPS Form ES-C-1 Page 1 of 7 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 1 Facility: CPNPP JPM # NRC RA3 Task # RO 1003 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

-002 B , Plant Startup from Hot Standby Boron is at the Estimated Critical Boron Concentration o f 1220 ppm Shutdown Control Rod Banks are fully withdrawn Critical Rod Height is predicted to be CBD a t 78 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:

PERFORM the Inverse Count Rate Ratio (ICRR) Calculation per for each of the four rod withdrawal readings shown on IPO

-002 B, Plant Startup from Hot Standby, Attachment 2, Inverse Count Rate Ratio Calculation Steps 3.3.E and 3.3.F PLOT the points on the 1/M Data Sheet per IPO-002 B, Plant Startup from Hot Standby, Attachment 2, Inverse Count Rate Ratio Calculation Step 3.3.G DETERMINE the ECC (Predicted Critical Rod Height

) for each of the four rod withdrawals and record on the 1/M Data Sheet per IPO-002 B, Plant Startup from Hot Standby, Attachment 2, Inverse Count Rate Ratio Calculation Steps 3.4 and 3.

5 RECORD any required action(s) based on 1/M Data obtain ed below: ____________________________________________

____________________________________________

Appendix C JPM STEPS Form ES-C-1 Page 2 of 7 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 1 Task Standard:

Utilizing IPO

-002 B , calculate d Inverse Count Rate Ratios , perform ed a 1/M Plot using data provided on Attachment 2 , determine d estimated critical rod position for each the four rod withdrawals, determined criticality predicted below Rod Insertion Limit and recorded insert all Control Banks to the CBO position. Re f. Materials:

IPO-002 B , Plant Startup from Hot Standby , Rev. 10-37. ERX-1 5-00 1, COLR for CPNPP Unit 2 Cycle 1 6, Figure 2, Rod Bank Insertion Limits Versus Thermal Power, Rev. 0.

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 7 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 1 CLASSROOM SETUP Handout s: PROVIDE the examinee with a copy of:

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

COMPLETE Attachment 2 th r ough four sets of data IPO-002 B, Plant Startup from Hot Standby Step 5.2.10 (labeled Procedure

2) COLR for CPNPP Unit 2 Cycle 16 Figure 2 Rod Bank Insertion Limits Versus Thermal Power (labeled Handout 1)

Required Materials

Straight edge or ruler Calculator

Appendix C JPM STEPS Form ES-C-1 Page 4 of 7 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 1 - Check Mark Denotes Critical Step START TIME:

Examiner Note:

The following steps are from IPO

-002 B, Attachment 2.

Perform Step: 1 Calculate Inverse Count Rate Ratio calculation for Control Bank A at 50 steps and plot on 1/M Data Sheet. Performance Standard: CALCULATE D 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 = 50/5 5 = 0.9 1 +/- 0.0 1. RECORD ICRR = 0.91 +/- 0.01. PLOT points for CBA @ 0 steps and CBA @ 50 steps. DRAW a line from 1.00 to 0.9 1 that INTERSECTS with CBD at 190 +/- 100 steps. LOG an Estimated Critical Condition between CBD at 155 and 225 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.

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

, and RECORDED Data

RECORD an average Count Rate of 6 5. CALCULATE ICRR = 1/M = 50/

6 5 = 0.77 +/- 0.01. RECORD ICRR = 0.77 +/- 0.01. PLOT points for CBA @ 50 steps and CBA @ 100 steps. DRAW a line from 0.91 to 0.77 that INTERSECTS with CBD at 10 +/- 50 steps. LOG an Estimated Critical Condition between C B C at 1 0 0 and CBD at 35 steps. Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 Page 5 of 7 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 1 Perform Step: 3 Calculate Inverse Count Rate Ratio calculation for Control Bank B at 35 steps and plot on 1/M Data Sheet.

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

RECORD an average Count Rate of

88. CALCULATE ICRR = 1/M = 50/

88 = 0.57 +/- 0.01. RECORD ICRR = 0.57 +/- 0.01. PLOT points for CB A @ 100 steps and CB B @ 35 steps. DRAW a line from 0.77 to 0.57 that INTERSECTS with CBC at 55 +/- 30 steps. LOG an Estimated Critical Condition between CBC at 40 and 90 steps. Comment: SAT UNSAT Perform Step: 4 Calculate Inverse Count Rate Ratio calculation for Control Bank B at 85 steps and plot on 1/M Data Sheet.

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

RECORD an average Count Rate of 333. CALCULATE ICRR = 1/M = 50/333 =

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

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

DRAW a line from 0.57 to 0.15 that INTERSECTS with CB B at 95 +/- 25 steps. LOG an Estimated Critical Condition between CB B at 80 and 110 steps. Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 Page 6 of 7 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 1 Examiner Note:

The following Performance Standard is from IPO-002 B, Step 5.2.10, 4 th bullet. Perform Step:

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

. Performance Standard: DETERMINED Estimated Critical Condition occurs below the Rod Insertion Limit (CBC @ 49 steps) within the next reactivity addition and RECORDED the following on 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 7 of 7 CPNPP 2016 NRC JPM RA3 (RO1003A) REV. 1 Initial Conditions

Given the following conditions:

Unit 2 is performing a Reactor Startup per IPO

-002B, Plant Startup from Hot Standby Boron is at the Estimated Critical Boron Concentration of 1220 ppm Shutdown Control Rod Banks are fully withdrawn Critical Rod Height is predicted to be CBD at 78 steps The 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:

PERFORM the Inverse Count Rate Ratio (ICRR) Calculation per for each of the four rod withdrawal readings shown on IPO

-002B, Plant Startup from Hot Standby, Attachment 2, Inverse Count Rate Ratio Calculation Steps 3.3.E and 3.3.F PLOT the points on the 1/M Data Sheet per IPO

-002B, Plant Startup from Hot Standby, Attachment 2, Inverse Count Rate Ratio Calculation Step 3.3.G DETERMINE the ECC (Predicted Critical Rod Height) for each of the four rod withdrawals and record on the 1/M Data Sheet per IPO

-002B, Plant Startup from Hot Standby, Attachment 2, Inverse Count Rate Ratio Calculation Steps 3.4 and 3.5 RECORD any required action(s) based on 1/M Data obtained below:

____________________________________________

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 STEPECC BANK STEPREFERENCEN-31COUNTSN-32AVE AVEN-31N-32AVE AVEICRRICRRBANKATSTEPSECC BANK STEPECCBANK STEPN-31N-32 AVE AVEICRRICRRBANKATSTEPSECC BANKSTEP 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 DATA SHEET IC R R 1.0.9.8.7.6.5.4.3.2.1 0 0100200300400500565 01 00 50207035850555105155205GP 'A'G P 'C'GP 'B'G P 'D'01 00 50 15020025030035040045050055060 0

COLR for CPNPP Unit 2 Cycle 16 FIGURE 2 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER NOTES:1.Fully withdrawn shall be the condition where control rods are at a position within the interval of 218 and 231 steps withdrawn, inclusive.2.Control Bank A shall be fully withdrawn.

0 20 40 60 80100120140160180 2002202400102030405060708090100 ROD BANK POSITION (steps withdrawn)

PERCENT OF RATED THERMAL POWER BANK C (79.6,218)

(25.3,218)

(0,164)(0,49)(31,0)(100,146)BANK B BANK D 11 ERX-15-001, Rev. 0 Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 2 Facility: CPNPP JPM # NRC R A4 Task # RWT056B K/A # 2.3.7 3.5 / 3.6 Title: Determine Entry Conditions for Radiation Area Clearanc e 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 RCD T 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 area 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 area dose rate where tagging is to be performed. Re f. Materials: RPI-602, Radiological Surveillance and Posting, Rev.

57-1. RPI-606, Radiation Work and General Access Permits, Rev. 3

5. 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. 4/4/16 CPNPP General Area Permit 201 6001 1, Routine Maintenance, Rev.

02. Validation Time:

2 0 minutes Completion Time:

________ minutes

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 2 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. 2 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 201 6 00 11, 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 (labeled Procedure 1)

RPI-606, Radiation Work and General Access Permits (labeled Procedure 2)

Appendix C JPM STEPS Form ES-C-1 Page 4 of 6 CPNPP 2016 NRC JPM RA4 (RWT056B) REV. 2 - 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

. Performance Standard: PERFORMED the following:

LOCATE D 1-7168 and 1

-7167 using Valve Locator Map for Unit 1 Safeguards Building Elev. 810

' Room 77N (77A)

. COMPARE D the location to the Survey Map. DETERMINE D 1-7168 and 1

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

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

. Performance Standard: DETERMINE D the Dose Monitoring Requirements to enter the room per the General Access Permit

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

. Performance Standard: DETERMINE D the minimum Protective Clothing Requirements to enter the valve area per the General Access Permit

Deluxe coveralls Booties Hood and hard hat cover Cotton liners Rubber gloves Rubber Overshoes Comment: SAT UNSAT Perform Step: 4 Identify the highest contamination level in dpm/100 cm 2 for the room

. Performance Standard: IDENTIFIED the highest contamination level in dpm/100 cm 2 for the room is < 100 0 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. 2 Perform Step: 5 Identify the highest area dose rate in mR/hr for the room.

Performance Standard: IDENTIFIED the highest area dose rate at 8 mR/hr. 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. 2 INITIAL CONDITIONS

Given the following conditions:

A Clearance is required to remove 1

-LCV-1003, LWPS RCDT 1-01 LVL CTRL VLV from service Tags need to be hung on 1

-7168, LWPS RCDT 1

-01 LVL CTRL VLV UPSTRM ISOL and 1

-7167, LWPS RCDT 1-01 LVL CTRL VLV DNSTRM ISOL The valves are located in Safeguards Building Elev. 810' NORTH PENETRATION VLV RM / North Side (Room 77A)

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

DETERMINE the Dose Monitoring Requirements to enter the room DETERMINE the Protective Clothing Requirements to enter the valve area IDENTIFY the highest contamination level in dpm/100

cm 2 for the room IDENTIFY the highest area dose rate in mR/hr for the room Dose Monitoring Requirements to enter the room

_____________________________________________________

Minimum Protective Clothing Requirements to enter the valve area: _____________________________________________________

_____________________________________________________

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

Highest area dose rate in mR/hr for the room

_____________________________________________________

Appendix C JPM CUE SHEET Form ES-C-1 INITIAL CONDITIONS: Given the following conditions: A Clearance is required to remove 1-LCV-1003, LWPS RCDT 1-01 LVL CTRL VLV from service Tags need to be hung on 1-7168, LWPS RCDT 1-01 LVL CTRL VLV UPSTRM ISOL and 1-7167, LWPS RCDT 1-01 LVL CTRL VLV DNSTRM ISOL The valves are located in 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 area dose rate in mR/hr for the room Dose Monitoring Requirements to enter the room: _____________________________________________________ _____________________________________________________

_____________________________________________________

Minimum Protective Cl othing Requirements to enter the valve area:

_____________________________________________________

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

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

&'!"#(

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'(*'(6-#6(-

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F'3-'3-*' &

ES-301 Administrative Topics Outline Form ES-301-1 Task Summary Rev. 1 Facility: CPNPP Units 1 and 2 Date of Examination:

July 20 1 6 Examination Level: RO SRO Operating Test Number:

NRC Administrative Topic (See Note)

Type Code* Describe activity to be performed Conduct of Operations (SA1) N ,R 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperatures, high pressure, caustic, chlorine, oxygen and hydrogen)

. (3.6) JPM: Determine Electrical Safe Work Practices Requirements

. (SO 1028) Conduct of Operations (SA2) N ,R 2.1.37 Knowledge of procedures, guidelines or limitations associated with reactivity management.

(4.6) JPM: Determine Reactivity Management Severity and Notifications

. (SO1017 B) Equipment Control (SA3) D ,R 2.2.14 Knowledge of the process for controlling equipment configuration or status. (4.3) JPM: Determine Fire Compensatory Measures for an Emergent Condition. (SO10 48) Radiation Control (SA4) D,R 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (3.6

) 2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (4.1) JPM: Determine Entry Conditions for Radiation Area Clearance and Reporting Requirements. (SO1112B) Emergency Procedures/Plan (SA5) D , R 2.4.4 1 Knowledge of emergency action level thresholds and classifications. (4.6) JPM: Classify an Emergency Plan Event. (SO1136I)

ES-301 Administrative Topics Outline Form ES-301-1 Task Summary Rev. 1 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs;

< 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected)

SA1 The applicant is presented with a task to determine as the Unit Supervisor, the Personnel Protective Equipment and Safety Boundaries for emergent work of racking the Rx trip breaker from disconnect to remove in accordance with STA-124, Electrical Safe Work Practices

. The critical steps will be to identify the Hazard/Risk Category, Clothing requirements and Boundaries. In addition, the applicant will be required to determine if their position has approval authority for the task. This is a new JPM.

(K/A 2.1.26

- IR 3.6) SA2 The applicant is presented with a plant transient event and response. As Unit Supervisor, the applicant is required to take necessary actions for a reactivity management event in accordance with STA

-102, Reactivity Management Program. The critical steps will be to make a determination of the Severity Level and determine the written and verbal notifications.

This is a new JPM. (K/A 2.1.37

- IR 4.6) SA3 The applicant will evaluate a Fire Protection Impairment per STA

-738, Fire Protection Systems/Equipment Impairments. The critical steps are to determine Fire Watch Implementation and other Compensatory Measures

. This is a direct from bank JPM. (K/A 2.2.14

- IR 4.3) SA4 The applicant will determine the radiological requirements for implementing a Clearance in a Radiological Controlled Area per STA

-656, Radiation Work Control, RPI

-602, Radiological Surveillance and Posting, RPI-606, Radiation Work and General Access Permits and STA

-501, N onroutine Reporting. Critical steps include identifying Dose Monitoring Requirements, Protective Clothing Requirements, highest contamination level, highest dose rate and determination of proper oral and written notifications due to an overexposure event.

This is a direct from bank JPM. (K/A 2.3.7

- IR 3.6 & K/A 2.4.30

- IR 4.1) SA5 The applicant will determine the appropriate Emergency Plan Classification in accordance with EPP

-201, Assessment of Emergency Action Levels, Emergency Classification, and Plan Activation. The critical step will be the determination of the correct classification. This is a direct from bank JPM. (K/A 2.4.41

- IR 4.6)

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 6 CPNPP 2016 NRC JPM SA 1 (SO102 8) REV. 1 Facility: CPNPP JPM # NRC SA 1 Task # SO 102 8 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

. Re f. Materials:

STA-124 , Electrical Safe Work Practices, Rev. 2

-1 2 Validation Time:

15 minutes Completion Time:

________ minutes

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 6 CPNPP 2016 NRC JPM SA 1 (SO102 8) REV. 1 Comments: Result: SAT UNSAT Examiner (Print / Sign):

Date:

Appendix C JPM WORKSHEET Form ES-C-1 Page 3 of 6 CPNPP 2016 NRC JPM SA 1 (SO102 8) REV. 1 CLASSROOM SETUP Handout: PROVIDE the examinee with a copy of:

STA-124 , Electrical Safe Work Practices

. (labeled Procedure 1)

Appendix C JPM STEPS Form ES-C-1 Page 4 of 6 CPNPP 2016 NRC JPM SA 1 (SO102 8) REV. 1 - Check Mark Denotes Critical Step START TIME:

Perform Step: 1 DETERMINE Hazard Risk Category

. Performance Standard: DETERMINED STA

-124 Attachment 8.A, Hazard Risk Category

- 2. Attachment 8A Page 7 of 13 4 th item, Task column number in parentheses is Hazard Risk Category.

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

. Performance Standard: DETERMINED STA

-124 Attachment 8A, Minimum ATPV in cal/cm2 of FRC - 8 cal/cm 2. Attachment 8A Page 7 of 13 4 th item, Clothing Minimum Requirements Column.

Comment: SAT UNSAT Perform Step: 3 DETERMINE Flash Boundary.

Performance Standard: DETERMINED STA

-124 Attachment 8.A, Flash Boundary

- 4 ft. Attachment 8A Page 7 of 13, Boundaries Section at top of page.

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

Performance Standard: DETERMINED STA

-124 Attachment 8.A, Prohibited Boundary - 1 in. Attachment 8A Page 7 of 13, Boundaries Section at top of page.

Comment: SAT UNSAT Perform Step: 5 DETERMINE Arc-rated face shield with balaclava or arc flash suit hood required. Performance Standard: DETERMINED that a n Arc-rated face shield with balaclava or arc flash suit hood required is Required. Attachment 8A Page 7 of 13 4 th item, Clothing Minimum Requirements Column. Circled YES. Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 Page 5 of 6 CPNPP 2016 NRC JPM SA 1 (SO102 8) REV. 1 Perform Step:

6 DETERMINE Ear canal hearing protection required

. Performance Standard: DETERMINED that Ear canal hearing protection is required. Attachment 8A Page 7 of 13 4 th item, Task column Note 11, which is on Page 4 of 13. Circled YES Comment: SAT UNSAT Perform Step:

7 DETERMINE Insulated tools required

. Performance Standard: DETERMINED that Insulated tools are not required

. Attachment 8A Page 7 of 13 4 th item, Insulated Tools column. 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 SA 1 (SO102 8) REV. 1 Initial Conditions:

Given the following conditions:

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

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

1. Hazard Risk Category:

___________________________________

2. Minimum ATPV in cal/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 SA 2 (SO10 17B) REV. 1 Facility: CPNPP JPM # NRC SA 2 Task # SO 10 17 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 SA 2 (SO10 17B) REV. 1 Task Standard:

Utilizing STA

-1 02, 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.

Re f. Materials:

STA-1 02 , 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 SA 2 (SO10 17B) REV. 1 CLASSROOM SETUP Handout: PROVIDE the examinee with a copy of:

STA-1 02 , 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 SA 2 (SO10 17B) REV. 1 - Check Mark Denotes Critical Step START TIME:

Perform Step: 1 DETERMINE Event Significance Level

. Performance Standard: DETERMINED STA

-1 02 Attachment 8.

B , Significance Level

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

. Performance Standard: DETERMINED STA

-1 02 Attachment 8.A, Required Notifications

- Shift Operations Manager, Director, Operations and Reactivity Management Champion Comment: SAT UNSAT Perform Step: 3 DETERMINE PERC Required

. PERC is a Plant Event Review Committee.

Performance Standard: DETERMINED STA

-1 02 Attachment 8.A, PERC - Required Comment: SAT UNSAT Perform Step: 4 DETERMINE QERC Required. QERC is a Quick Event Review Checklist.

Performance Standard: DETERMINED STA

-1 02 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 SA 2 (SO10 17B) REV. 1 Initial Conditions:

Given the following conditions:

A trip of Heater Drain Pump 1

-01 occurred Control Rods stabilized below the Rod Insertion Limit Boration was initiated in accordance with ABN

-302, Feedwater, Condensate, Heater Drain System Malfunction and the 10000.0 MWD/MTU Reactivity Briefing Sheet The Reactor Operator made an error when performing the boration and set 1-FY-110B, BA BATCH FLO to 17.5 gallons As a result of the error the Control Rods were not restored above the Rod Insertion Limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Initiating Cue:

The Shift Manager directs you to DETERMINE the following in accordance with STA-102, Reactivity Management Program:

1. Event Significance Level: ___________________________________

2. Required Notifications

_____________________________________

______________________________________

3. Is a PERC required:

YES NO 4. Is a QERC required: YES NO

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

Valid for approximately 7 days.Calculations based on core design values, and assume:Burnup = MWD/MTU EFPDPower = RTPBoron = ppm B10 Conc = w/o Control Bank D = stepsReactivity affects of Control Bank DHFP Diff Worth @ 215.0 steps = pcm / stepHFP Integral Rod Worth for CBD Step Positions:Reactivity affects of BoronHFP Diff Boron Worth @ 924 ppm = pcm / ppm1-FK-110 Pot Setting for Blended Flow @ 924 ppm = (Assuming BAT concentration of 7447.0 ppm)Reactivity affects of Powe rPower Coefficient of Reactivity = pcm / % RTPDilution to equal 1% Power Increase = gallons RMUWBoration to equal 1% Power Decrease = gallons boric acidReactivity affects of RCS TemperatureTemperature Coefficient of Reactivity (ITC) = pcm / FBoration to equal 1F Temperature Decrease = gallons boric acid Dilution to equal 1F Temperature Increase = gallons RMUWLoad Reduction equal to 1F Tave Increase = MWe15.03.94-7.4-1.426.5 175Steps205-29.1pcm-91.4 211194.5-15.1152.320.7-19.3-15.4206-26.6-24.1Steps-125.3170-142.0195-58.2190-74.6 185-17.4209-19.5 0.0-1.2 210-3.1-1.7-8.7208-2.3214-10.2207-3.9Stepspcm 2152250.0Stepspcm218-4.9 224 223 220 219 222 2210.183400-11.8212-13.6217-6.1216-7.3 213 215 924Reactivity Briefing Sheet for Stable Operation10000.0225.9 100 MOL PROJECTIONS - SIMULATOR USE ONLY 180from assumed inputs.Burnup in the MOL rangeNOTE: Re-create the Briefing Sheetif current values significantly differpcm200-42.8-108.4-21.8 Note: Do not perform these calculations following a Runback. For a Runback, borateper the Reactivity Briefing Sheets as soon as possible.This computer generated form may be substituted for Attachment 1 of NUC-117Contact Core Performance (817-432-0134) if possible to discuss the plan.UnitDate / Time:A.1 Boration Volume gallonsIndicate source (listed in order of preference)BEACON by Core Performance (obtain if time permits)Reactivity Briefing Sheets from the Boration Matrix CHORE output (under 'Tools' ->'Power Change Rx Calc IPO-003 ATT 3')

IPO-003A Attachment 3 Manual Calculation A.2Current Turbine Load Setpoint . . . . . . . . . . . . . . . . . . . . . . . .

. MWeA.3Final Turbine Load Setpoint . . . . . . . . . . . . . . . . . . . . . . . . . . . MWe(200 MWE if plant shutdown planned)A.4Total Turbine Ramp Time . . . . . . . . . . . . . . . . . . . . . . . . . . . . . minutes(Do not include calculation prep and Pre-Job Brief times)Calculations:B.1Load Change . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . MWe= A.2 - A.3B.2Load Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

. MWe/min= B.1 / A.4B.3Total Boration Time . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . minutesIdeally, start time should be 5 minutes BEFORE load change is initiated. If time does not allow, start time should be same as the load change start time.Ideally, end time should be 15minutes BEFORE load change is complete

.B.4Boration Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

. gpm= A.1 / B.3 B.51-FK-110 Pot Setting . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

. turns= B.4 / 4(N/A for Batch Boration)

Load Reduction Calculation Worksheet Reactivity Briefing Sheet for Runback to 900 MWe MOL PROJECTIONS - SIMULATOR USE ONLYBasic Control Strategy:A) A boration of 155 gallons should be initated soon after the runback. This will ensure rods are above RIL within 45 minutes and will likely be needed to restore Target AFD.

B) As rods are withdrawn due to boration, begin dilution when AFD reaches the Target value to maintain Target AFD. Total Dilution Estimate is 1200 gallons.NOTE: Contact Core Performance Engineering following any Runback for additional support.

0 40 80 120 160 200 240 0 20 40 60 80100 120-10123456789101112CBD (steps)Power (% RTP)TimePower and CBD PositionPowerControl Bank DRIL at 74% RTP = 91 steps on CBD.

870 875 880 885 890 895 900-12-10-8 4-2 0 2-10123456789101112Boron (ppm)AFD (%)TimeAxial Flux Difference and Boron AFDBoronBorate as required to keep CBD above RIL, and AFD within limits Reactivity Briefing Sheet for Runback to 800 MWe MOL PROJECTIONS - SIMULATOR USE ONLYBasic Control Strategy:A) A boration of 175 gallons should be initated soon after the runback. This will ensure rods are above RIL within 45 minutes and will likely be needed to restore Target AFD.

B) As rods are withdrawn due to boration, begin dilution when AFD reaches the Target value to maintain Target AFD. Total Dilution Estimate is 1500 gallons.NOTE: Contact Core Performance Engineering following any Runback for additional support.

0 40 80 120 160 200 240 0 20 40 60 80100 120-10123456789101112CBD (steps)Power (% RTP)TimePower and CBD PositionPowerControl Bank DRIL at 67% RTP = 76 steps on CBD.

870 875 880 885 890 895 900-12-10-8 4-2 0 2-10123456789101112Boron (ppm)AFD (%)TimeAxial Flux Difference and Boron AFDBoronBorate as required to keep CBD above RIL, and AFD within limits Reactivity Briefing Sheet for Runback to 700 MWe MOL PROJECTIONS - SIMULATOR USE ONLYBasic Control Strategy:A) A boration of 200 gallons should be initated soon after the runback. This will ensure rods are above RIL within 45 minutes and will likely be needed to restore Target AFD.

B) As rods are withdrawn due to boration, begin dilution when AFD reaches the Target value to maintain Target AFD. Total Dilution Estimate is 2000 gallons.NOTE: Contact Core Performance Engineering following any Runback for additional support.

0 40 80 120 160 200 240 0 20 40 60 80100 120-10123456789101112CBD (steps)Power (% RTP)TimePower and CBD PositionPowerControl Bank DRIL at 59% RTP = 59 steps on CBD.

870 875 880 885 890 895 900 905-12 8

-6

-4

-2 0 2-10123456789101112 Boron (ppm)AFD (%)TimeAxial Flux Difference and Boron AFDBoronBorate as required to keep CBD above RIL, and AFD within limits Reactivity Briefing Sheet for Downpower Boration Matrix MOL PROJECTIONS - SIMULATOR USE ONLYThe boration/dilution estimates are based on BEACON predictions for maintaining Incore Axial Offset.With deep rod insertion, it is expected AFD indications (based on Excore Detectors) will be less than the Incorevalue by ~2-4%. In this case, no immediate action is needed to restore AFD, but contact Core Performance.Borate at a rate sufficient to allow ~15 minutes of mixing before the final power level is reached.Contact Core Performance as soon as possible when planning ANY downpower for additional support.Assumed Initial ConditionsPower100% RTPCBD Position215stepsRCS Boron 864ppm (anticipated boron at middle of validity range)30 Minute Ramp Down Boration Estimates900 MWe800 MWe700 MWe50% RTP(~74% RTP)(~67% RTP)(~59% RTP)Final CBD Position 172 steps161 steps148 steps123 stepsTotal Boration 304 gal384 gal481 gal561 galFollowup Dilution (1st hour)1102 gal1409 gal1792 gal2435 galAve Dilution Rate (1st hour)18.4 gpm23.5 gpm29.9 gpm40.6 gpm 2 Hour Ramp Down Boration Estimates900 MWe800 MWe700 MWe50% RTP(~74% RTP)(~67% RTP)(~59% RTP)Final CBD Position 172 steps158 steps142 steps101 stepsTotal Boration 191 gal232 gal286 gal258 galFollowup Dilution (1st hour)771 gal1017 gal1292 gal1641 galAve Dilution Rate (1st hour)12.9 gpm17 gpm21.5 gpm27.4 gpm1 Hour Rapid Shutdown (Ramp to 20% on Target AFD, 30 minute hold, trip)20% RTPFinal CBD Position 79.2 stepsTotal Boration 698 galCBD Position 107.4 steps2.8 %After 30 minutes, no dilution (withdrawing rods to control power), holding at 20% RTPDilution in first hour to support maintaining reduced power, while holding Incore AFD on Target:Notes: Highlighted values: Max boration rate during downpower may be unable to maintain Target AFD. Restore and hold Target AFD as soon as possible following the Downpower.Dilution in first hour to support maintaining reduced power, while holding Incore AFD on Target:Incore AFD Notes:

Appendix C JPM WORKSHEET Form ES-C-1 Page 1 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 1 Facility: CPNPP JPM # NRC SA3 Task # SO 1048 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 Syste m and determined that Fire Brigade Strategy was affected in accordance with the Answer Key

.

Appendix C JPM WORKSHEET Form ES-C-1 Page 2 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 1 Re f. 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. 1 CLASSROOM SETUP Handouts: PROVIDE the examinee with a copy of:

STA-738, Fire Protection Systems/Equipment Impairments

. (labeled Procedure 1)

STA-738-2, Fire Protection System

/ Equipment Impairment Form

. (labeled Form 1)

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

-0". (labeled Procedure 2)

Completed FIR-303-1, Halon Fire Suppression System Inspection Sheet

. (labeled Handout 1)

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

Examiner Note:

The following information is from STA-7 28-2. Perform Step: 1 Enter information for AFFECTED LOCATION

. Performance Standard: ENTER ED the following; BLDG: Electric al Control, ELEV: 807 , ROOM/OTHER: Unit 1 Cable Spreading Room per FPI-505, Electrical & Control Building Unit 1 Cable Spread Room Elevation 807'

-0" Comment: SAT UNSAT Perform Step:

2 Determine if CONTINUOUS FIRE WATCH is required

. Performance Standard: DETERMINE D that a CONTINUOUS FIRE WATCH wa s Required and checked box per STA-738 Attachment 8.A Item (4).

Comment: SAT UNSAT Perform Step:

3 Determine if ROVING FIRE WATCH route change is required. Performance Standard: DETERMINE D that a ROVING FIRE WATCH route change was NOT Required and circles NO as a continuous fire watch and backup suppression equipment within one hour is required per STA

-738 Attachment 8.A Item (4).

Comment: SAT UNSAT Perform Step:

4 Determine if ROVING FIRE WATCH with operable detection route change is required.

Performance Standard: DETERMINED that a ROVING FIRE WATCH with operable detection route change is NOT Required and circles NO as a continuous fire watch and backup suppression equipment within one hour is required per S TA-738 Attachment 8.A Item (4).

Comment: SAT UNSAT Perform Step:

5 Determine if NONE REQUIRED. Performance Standard: DETERMINED that None Required is not correct and left Blank. Comment: SAT UNSAT Appendix C JPM STEPS Form ES-C-1 Page 5 of 6 CPNPP 2016 NRC JPM SA3 (SO1048) REV. 1 Perform Step: 6 Determine if AFFECTS FIRE BRIGADE STRATEGY

. Performance Standard: DETERMINED that Fire Brigade Strategy is affected and circled YE S per review of FPI

-505 automatic and manual actions for Halon deployment are affected.

Comment: SAT UNSAT Perform Step:

7 Determine if OTHER compensatory measure information is required.

Performance Standard: DETERMINED that establishing a continuous fire watch and backup suppression equipment within one hour is required per STA-738 Attachment 8.A Item (4).

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. 1 Initial Conditions:

Given the following conditions:

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

Based on the FIR

-303-1 a Fire Protection Impairment must be initiated using STA-738-2, Fire Protection System/Equipment Impairment Form

. Initiating Cue:

The Shift Manager directs you to PERFORM the following:

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

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

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

CONTINUOUS FIRE WATCH required. CHECK if required.

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

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

NONE REQUIRED. CHECK if none required.

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

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

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:

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. 2 Facility: CPNPP JPM # NRC S A4 Task # SO1112 K/A # 2.3.7 3.5 / 3.6 Title: Determine Entry Conditions for Radiation Area Clearanc e 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 RCD T 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 area dose rate in mR/hr for the room Initial Conditions:

JPM Cue Sheet 2 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 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. 2 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 area dose rate where tagging is to be performed. Utilizing STA

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

. Re f. Materials:

RPI-602, Radiological Surveillance and Posting, Rev.

57-1. RPI-606, Radiation Work and General Access Permits, Rev. 3

5. 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. 4/14/16. CPNPP General Area Permit 201 6001 1, Routine Maintenance, Rev.

02. STA-501, Nonroutine Reporting, Rev. 21.

Validation Time:

2 0 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. 2 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 201 6 00 11, 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)

STA-501, Nonroutine Reporting (labeled Procedure 3)

MAKE the following references available in the classroom

RPI-602, Radiological Surveillance and Posting (labeled Procedure 1)

RPI-606, Radiation Work and General Access Permits (labeled Procedure 2)

Appendix C JPM STEPS Form ES-C-1 Page 4 of 7 CPNPP 2016 NRC JPM SA4 (SO1112) REV. 2 - 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