Text

CP-2011-06-Draft OP Test
	ML112901409
Person / Time
Site:	Comanche Peak
Issue date:	06/06/2011
From:	Brian Larson; Operations Branch IV
To:	;
References
	Download: ML112901409 (335)
	v • d • e

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA1 Task #RO1310 K/A #2.1.43 4.1 / 4.3

Title:

Determine Reactivity Effects When Starting Positive Displacement Charging Pump Examinee (Print):

Testing Method:

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

Alternate Path: Plant:

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

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

Initial Conditions: Given the following conditions:

Unit 1 is operating at approximately 3% power.

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

The Reactor Coolant System Boron concentration the last time the Positive Displacement Charging Pump was run was 2400 ppm.

Current Reactor Coolant System Boron concentration is 1545 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 and 5.3.1.D.

REPORT findings to the Shift Manager.

Task Standard: Calculate the change in boron and resultant change in temperature when placing the Positive Displacement Pump in service per SOP-103A.

Required Materials: SOP-103A, Chemical and Volume Control System, Rev. 17-23.

Reactivity Briefing Sheet for 1545 ppm Reactor Coolant System conditions.

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

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

Page 1 of 5 CPNPP NRC 2011 JPM RA1 Rev d.doc

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

PROVIDE the examinee with a copy of:

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

INITIALED up to Step 5.3.1.C.

89.8 EFPD Reactivity Briefing Sheet.

Page 2 of 5 CPNPP NRC 2011 JPM RA1 Rev d.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from SOP-103A, Step 5.3.1.

Perform Step: 1 IF the RCS boron concentration has changed significantly since the 5.3.1.C 1st line + PDP was last operated, THEN determine the impact of water in the PDP calculation piping on reactivity as follows:

B = RCS Boron Concentration Difference Standard: CALCULATED B = RCS Boron Concentration Difference as follows:

B = ( 2400 ppm PDP - 1545 ppm RCS) x 0.00128 = 1.0944 ppm Comment: SAT UNSAT Examiner Note: Rounding off of ITC and HFP Differential Boron Worth may occur.

Perform Step: 2 On the Reactivity Briefing Sheet get the following information:

5.3.1.C 2nd line + ITC _____ pcm/ºF HFP Differential Boron Worth _____ pcm/ppm calculation Standard: DETERMINED the following from the Reactivity Briefing Sheet:

ITC = - 1.1 +/- 0.1 pcm /ºF HFP Differential Boron Worth = - 6.9 +/- 0.1pcm / ppm Comment: SAT UNSAT Examiner Note: Rounding off of ITC / HFP Differential Boron Worth may occur.

Perform Step: 3 On the Reactivity Briefing Sheet get the following information:

5.3.1.C 2nd line + ITC / HFP Differential Boron Worth = ppm / ºF calculation Standard: CALCULATED change in ppm / ºF:

- 1.1 pcm / ºF / - 6.9 pcm / ppm = 0.1594 +/- 0.02 ppm / ºF Comment: SAT UNSAT Page 3 of 5 CPNPP NRC 2011 JPM RA1 Rev d.doc

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

Perform Step: 4 On the Reactivity Briefing Sheet get the following information:

5.3.1.C 3rd line + TAVE = B / ppm / ºF calculation Standard: CALCULATED change in TAVE as follows:

TAVE = B / ppm / ºF = 1.0944 ppm / 0.1594 ppm / ºF = 6.87 +/- 1.0 ºF Comment: SAT UNSAT Perform Step: 5 IF TAVE calculated above is >1ºF, THEN notify Shift Operations 5.3.1.D Manager to discuss contingency actions.

Standard: DETERMINED TAVE calculated is greater than 1ºF and NOTIFIED Shift Manager.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 4 of 5 CPNPP NRC 2011 JPM RA1 Rev d.doc

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

Unit 1 is operating at approximately 3% power.

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

The Reactor Coolant System Boron concentration the last time the Positive Displacement Charging Pump was run was 2400 ppm.

Current Reactor Coolant System Boron concentration is 1545 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 and 5.3.1.D.

REPORT findings to the Shift Manager.

Page 5 of 5 CPNPP NRC 2011 JPM RA1 Rev d.doc

CPNPP NRC 2011 JPM RA1 Handout Reactivity Briefing Sheet for Stable Operation FOR SIMULATOR SIMULATOR USE on

- Created ONLY02/17/09 SIMULATOR USE ONLY Calculations based on core design values, and assume:

Burnup = 4001.3 MWD/MTU Burnup in the BOL range 89.82 EFPD Power = 0 RTP Boron = 1545 ppm NOTE: Re-create the Briefing Sheet B10 Conc = 0.1776696 w/o if current values significantly differ Control Bank D = 100 steps from assumed inputs.

Reactivity affects of Control Bank D HFP Diff Worth @ 100.0 steps = -4.3 pcm / step HFP Integral Rod Worth for CBD Step Positions:

Steps pcm Steps pcm Steps pcm Steps pcm 110 -269.0 103 -294.7 96 -325.2 85 -382.5 109 -272.4 102 -298.7 95 -329.9 80 -411.7 108 -275.9 101 -302.9 94 -334.8 75 -442.7 107 -279.4 100 -307.1 93 -339.8 70 -475.3 106 -283.1 99 -311.5 92 -344.8 65 -509.2 105 -286.9 98 -316.0 91 -350.0 60 -544.2 104 -290.7 97 -320.5 90 -355.2 55 -580.3 Reactivity affects of Boron HFP Diff Boron Worth @ 1545 ppm = -6.9 pcm / ppm 1-FK-110 Pot Setting for Blended Flow @ 1545 ppm = 6.34 (Assuming BAT concentration of 7492.0 ppm)

Reactivity affects of Power Power Coefficient of Reactivity = -13.1 pcm / % RTP Dilution to equal 1% Power Increase = 83.8 gallons RMUW Boration to equal 1% Power Decrease = 20.9 gallons boric acid Reactivity affects of RCS Temperature Temperature Coefficient of Reactivity (ITC) = -1.1 pcm / EF Boration to equal 1EF Temperature Decrease = 1.8 gallons boric acid Dilution to equal 1EF Temperature Increase = 7.3 gallons RMUW Load Reduction equal to 1EF Tave Increase = 1.0 MWe Page 1 of 1 Rev d

CPNPP NRC 2011 JPM RA1 Procedure COMANCHE PEAK NUCLEAR POWER PLANT UNIT 1 SYSTEM OPERATING PROCEDURE MANUAL ELECTRONIC CONTROLLED COPY CHANGES ARE NOT INDICATED LATEST CHANGE NOTICE EFFECTIVE DATE PCN-1 0--200 1200

__________/________ Verify current status in the Document Control Database prior to use.

INITIAL & DATE QUALITY RELATED CHEMICAL AND VOLUME CONTROL SYSTEM PROCEDURE NO. SOP-103A REVISION NO. 17 EFFECTIVE DATE: 03-05-2008 1200 PREPARED BY (Print): Brad Hancock Ext: 6769 TECHNICAL REVIEW BY (Print): Lisabeth Donley Ext: 6524 APPROVED BY: Alan Hall for Dave Goodwin Date: 02-19-2008 DIRECTOR, OPERATIONS Page 1 of 4 Rev d

CPNPP NRC 2011 JPM RA1 Procedure CPNPP PROCEDURE NO.

SYSTEM OPERATING PROCEDURE MANUAL UNIT 1 SOP-103A CHEMICAL AND VOLUME CONTROL SYSTEM REVISION NO. 17 PAGE 27 OF 131 5.3 Major Component Operation 5.3.1 Positive Displacement Pump Startup This section describes the steps to place the PDP in service.

CAUTION: PDP operation may result in high gaseous activity in the PDP Room due to packing leakage.

NOTE: ! PDP run time should be minimized to conserve pump packing. Run PDP only when required (for example - Slave Relay Testing).

! Following loss of Instrument Air, control air to the PDP fluid drive must be reset. This is done by depressing the RESET pushbutton on the instrument air supply to the PDP fluid drive. This RESET is normally accomplished by ABN-301 restoration section 3.0.

! The reactivity impact for starting the PDP pump is typically very small due to diffusion effects between the PDP piping and the RCS. However, assuming no diffusion, the reactivity effects could potentially approach -15 pcm (and -1.5 °F temperature change) with very large

(>1000 ppm) boron concentration differences between the PDP piping and RCS. (EVAL 0944-04)

! Following several PDP starts, the PDP fluid drive oil may exceed the upper limit mark on the drive units sight glass due to priming) the pump (adding oil) over a period of time. The PROMPT Team should be contacted to drain th e e x c e s s o il.

(SMF-01-0600 and 4-03-149515-00)

! With the PDP stopped, oil level should be in the upper 1/4 of the MIN - MAX range, preferably near the MAX level mark. (SMF-05-2603)

Q A. Ensure the prerequisites in Section 2.5 are met.

B. IF the PDP has not operated for an extended period (month), THEN prime the PDP fluid drive by performing the following:

Q 1) IF pump hydraulic fluid level is at the maximum level of the sightglass, THEN instruct a PROMPT member to drain ~1/2 liter of oil into a clean container. (This oil will be added to the fluid drive at step 5.3.1.B. 3)

Q 2) Remove the pipe plugs from the two priming holes on top of the input end bell (motor side of the fluid drive).

Q 3) Pour oil (collected in step 5.3.1.B. 1) a) and/or from the approved lubrication list) into either hole until oil rises to the bottom of the other hole and remains there.

Q 4) Replace and tighten the pipe plugs.

Page 2 of 4 Rev d

CPNPP NRC 2011 JPM RA1 Procedure CPNPP PROCEDURE NO.

SYSTEM OPERATING PROCEDURE MANUAL UNIT 1 SOP-103A CHEMICAL AND VOLUME CONTROL SYSTEM REVISION NO. 17 PAGE 28 OF 131 5.3.1 NOTE: Steps C and D may be considered NA if in a MODE other than MODE 1 or 2.

Q C. IF the RCS boron concentration has changed significantly since the PDP was last operated, THEN determine the impact of water in the PDP piping on reactivity as follows:

NOTE: This formula was developed using data from Eval 2004-000944-04-00. It assumes 84 gallons for the PDP piping. All the factors that would not change were calculated to give a constant (0.00128) to simplify the formula(updated in EVAL-2009-000420-02). This formula does not take into account the diffusion effect. So, the boron concentration could be less than the PDP plaque indicates. The temperature change calculated below represents worst case. Operating experience has shown actual temperature change was less than results of the calculation below.

)B = RCS Boron Concentration Difference

)B = ( _______ ppm PDP - ________ ppm RCS ) x 0.00128

)B = _______ ppm On the Reactivity Briefing Sheet get the following information:

ITC pcm/°F HFP Differential Boron Worth pcm/ppm ITC = pcm/°F = ppm/°F HFP Differential Boron Worth pcm/ppm

)Tave = B = ppm = °F ppm/°F ppm/°F Q D. IF )Tave calculated above is >1°F, THEN notify Shift Operations Manager to discuss contingency actions.

NOTE: If the Stuffing Box Coolant Tank is overfilled, the PDP Charging Pump Room will become contaminated.

E. IF Stuffing Box Coolant Tank is low, THEN fill per the following steps:

Q 1) Slowly crack OPEN 1CS-0119, PD PMP 1-01 STUFFING BOX COOL TK MU ISOL VLV, until desired fill rate is achieved.

Q 2) When the desired tank level has been established, CLOSE 1CS-0119.

Q F. Ensure 1-8388-RO, PD CHRG PMP 1-01 DISCH VLV RMT OPER, is OPEN.

G. OPEN the following valves:

Q! 1/1-8202A, VENT VLV (MCB)

Q! 1/1-8202B, VENT VLV (MCB)

Page 3 of 4 Rev d

CPNPP NRC 2011 JPM RA1 Procedure CPNPP PROCEDURE NO.

SYSTEM OPERATING PROCEDURE MANUAL UNIT 1 SOP-103A CHEMICAL AND VOLUME CONTROL SYSTEM REVISION NO. 17 PAGE 29 OF 131 5.3.1 Q H. Ensure 1APPD, POSITIVE DISPLACEMENT CHARGING PUMP 1-01 MOTOR BREAKER 1EB1/2B/BKR is racked to the CONNECT position.

Q I. Place 1-SK-459A, PDP SPD CTRL, in MANUAL with demand at 55%.

NOTE: The PDP will not start until 1-8109, PD CHRG PMP 1-01 RECIRC VLV, is open and handswitch 1/1-APPD, PDP, is in the START position. Two minutes after the PDP breaker is closed, 1-8109 will automatically close.

Q J. OPEN 1/1-8109, PDP RECIRC VLV.

NOTE: PDP speed may have to be raised rapidly when a CCP is also in operation to prevent the PDP from stalling on low oil pressure.

Q K. WHEN 1/1-8109, PDP RECIRC VLV is open, THEN start the PDP by placing handswitch 1/1-APPD PDP, to the START position.

Q L. Ensure 1/1-8109, PDP RECIRC VLV, is CLOSED.

NOTE: During PDP operation the following step may be performed to lower PDP suction stabilizer level.

M. IF 1/1-8204, H2/N2 SPLY VLV indicates OPEN (red light on), THEN perform the following to lower suction stabilizer level:

[C] Q! OPEN 1/1-8210A, H2/N2 SPLY VLV and 1/1-8210B, H2/N2 SPLY VLV for no more than 10 seconds to clear the high level, then close.

N. IF a CCP is in operation AND it is to be placed in standby, THEN perform the following:

Q 1) Ensure only ONE letdown orifice is in service per Section 5.2.3.

Q2 Alternately raise PDP speed using 1-SK-459A, PDP SPD CTRL, and lower CCP flow using 1-FK-121, CCP CHRG FLO CTRL, until 1-FK-121 is at minimum.

Q 3) Shut down the running CCP per Section 5.3.4.

[IV] Q O. IF desired, THEN gradually adjust 1-SK-459A, PDP SPD CTRL, to achieve the required flow rate AND place in AUTO.

Q P. Adjust 1-LK-459, PRZR LVL CTRL, as necessary to maintain stable Pressurizer level.

COMMENTS Page 4 of 4 Rev d

CPNPP NRC 2011 JPM RA1 Answer Key CPNPP PROCEDURE NO.

SYSTEM OPERATING PROCEDURE MANUAL UNIT 1 SOP-103A CHEMICAL AND VOLUME CONTROL SYSTEM REVISION NO. 17 PAGE 28 OF 131 5.3.1 NOTE: Steps C and D may be considered NA if in a MODE other than MODE 1 or 2.

Q C. IF the RCS boron concentration has changed significantly since the PDP was last operated, THEN determine the impact of water in the PDP piping on reactivity as follows:

NOTE: This formula was developed using data from Eval 2004-000944-04-00. It assumes 84 gallons for the PDP piping. All the factors that would not change were calculated to give a constant (0.00128) to simplify the formula(updated in EVAL-2009-000420-02). This formula does not take into account the diffusion effect. So, the boron concentration could be less than the PDP plaque indicates. The temperature change calculated below represents worst case. Operating experience has shown actual temperature change was less than results of the calculation below.

)B = RCS Boron Concentration Difference 2400 ppm PDP - ________

)B = ( _______ 1545 ppm RCS ) x 0.00128 1.0944 ppm

)B = _______

On the Reactivity Briefing Sheet get the following information:

ITC -1.1 +/- 0.1 pcm/°F HFP Differential Boron Worth - 6.9 +/- 0.1 pcm/ppm ITC = -1.1 +/- 0.1 pcm/°F = 0.1594 +/- 0.02 ppm/°F HFP Differential Boron Worth - 6.9 +/- 0.1 pcm/ppm

)Tave = B = 1.0944 ppm = 6.87 +/- 1.0 °F ppm/°F 0.1594 +/- 0.02 ppm/°F Q D. IF )Tave calculated above is >1°F, THEN notify Shift Operations Manager to discuss contingency actions.

NOTE: If the Stuffing Box Coolant Tank is overfilled, the PDP Charging Pump Room will become contaminated.

E. IF Stuffing Box Coolant Tank is low, THEN fill per the following steps:

Q 1) Slowly crack OPEN 1CS-0119, PD PMP 1-01 STUFFING BOX COOL TK MU ISOL VLV, until desired fill rate is achieved.

Q 2) When the desired tank level has been established, CLOSE 1CS-0119.

Q F. Ensure 1-8388-RO, PD CHRG PMP 1-01 DISCH VLV RMT OPER, is OPEN.

G. OPEN the following valves:

Q! 1/1-8202A, VENT VLV (MCB)

Q! 1/1-8202B, VENT VLV (MCB)

Page 1 of 1 Rev d

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA2 Task #RO5115 K/A #2.1.25 3.9 / 4.2

Title:

Calculate Pressurizer and Steam Generator Level from Remote Shutdown Panel Examinee (Print):

Testing Method:

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

Alternate Path: Plant:

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

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

Initial Conditions: Given the following conditions:

The Unit 1 Control Room has been evacuated.

ABN-905A, Loss of Control Room Habitability, is in progress.

A cooldown is in progress from the Remote Shutdown Panel.

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

CALCULATE Steam Generator indicated wide range level to maintain Steam Generator actual level between 74% and 83% when at 400ºF.

CALCULATE Pressurizer indicated level to maintain Pressurizer actual level between 25% and 50% when at 467ºF.

Task Standard: Calculate actual Steam Generator and Pressurizer levels during a cooldown per ABN-905A, Attachments 16 and 17.

Required Materials: ABN-905A, Loss of Control Room Habitability, Rev. 9-6.

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

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

Page 1 of 4 CPNPP NRC 2011 JPM RA2 Rev d.doc

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

PROVIDE the examinee with a copy of:

ABN-905A, Loss of Control Room Habitability.

Attachment 16, SG Level Temperature Correction.

Attachment 17, PRZR Level Temperature Correction.

Page 2 of 4 CPNPP NRC 2011 JPM RA2 Rev d.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: Steam Generator Level Graph is from ABN-905A, Attachment 16.

Perform Step: 1 CALCULATE Steam Generator indicated wide range level to maintain Steam Generator actual level between 74% and 83% when at 400ºF.

Standard: CALCULATED Steam Generator indicated wide range level at 64% +/-1%

to maintain Steam Generator actual level at 74% when at 400ºF.

Comment: SAT UNSAT Perform Step: 2 CALCULATE Steam Generator indicated wide range level to maintain Steam Generator actual level between 74% and 83% when at 400ºF.

Standard: CALCULATED Steam Generator indicated wide range level at 71% +/-1%

to maintain Steam Generator actual level at 83% when at 400ºF.

Comment: SAT UNSAT Examiner Note: Pressurizer Level Graph is from ABN-905A, Attachment 17.

Perform Step: 3 CALCULATE Pressurizer indicated level to maintain Pressurizer actual level between 25% and 50% when at 467ºF.

Standard: CALCULATED Pressurizer indicated level at 24% +/-1% to maintain Pressurizer actual level at 25% when at 467ºF.

Comment: SAT UNSAT Perform Step: 4 CALCULATE Pressurizer indicated level to maintain Pressurizer actual level between 25% and 50% when at 467ºF.

Standard: CALCULATED Pressurizer indicated level at 57% +/-1% to maintain Pressurizer actual level at 50% when at 467ºF.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 3 of 4 CPNPP NRC 2011 JPM RA2 Rev d.doc

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

The Unit 1 Control Room has been evacuated.

ABN-905A, Loss of Control Room Habitability, is in progress.

A cooldown is in progress from the Remote Shutdown Panel.

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

CALCULATE Steam Generator indicated wide range level to maintain Steam Generator actual level between 74% and 83% when at 400ºF.

CALCULATE Pressurizer indicated level to maintain Pressurizer actual level between 25% and 50% when at 467ºF.

Page 4 of 4 CPNPP NRC 2011 JPM RA2 Rev d.doc

CPNPP NRC 2011 JPM RA2 Procedure CPNPP PROCEDURE NO.

ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 ABN-905A LOSS OF CONTROL ROOM HABITABILITY REVISION NO. 9 PAGE 59 OF 74 ATTACHMENT 16 PAGE 1 OF 1 SG LEVEL TEMPERATURE CORRECTION NOTE: Normal SG level for Hot Standby and Cooldown (60 - 75% NR) is between 83% and 90%

actual wide range. Operating outside this range could cause uncovering AFW nozzle OR ESF actuation OR moisture carryover. Approximate critical levels (actual wide range) are:

! Lo-Lo (ESF actuation) Unit 1 - 74%

! AFW Nozzle Unit 1 - 83%

! Hi-Hi (moisture carryover) 92%

(L) 100.0 551 0 F 90.0 500 0 F 80.0 ACTUAL SG WIDE RANGE LEVEL (%)

350 0 F 0

400 F 70.0 70 0 F 60.0 50.0 40.0 30.0 20.0 10.0 0.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 INDICATED SG WIDE RANGE LEVEL (%)

Attachment 16 Page 1 of 2 Rev d

CPNPP NRC 2011 JPM RA2 Procedure CPNPP PROCEDURE NO.

ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 ABN-905A LOSS OF CONTROL ROOM HABITABILITY REVISION NO. 9 PAGE 60 OF 74 ATTACHMENT 17 PAGE 1 OF 1 PRZR LEVEL TEMPERATURE CORRECTION PRESSURIZER LEVEL CHANNEL (Hot Calibrated)

(LI-459B, LI-460B) 100 2235 PSIG 653°F 1483 PSIG 90 486 PSIG 80 70 0 PSIG ACTUAL LEVEL (%)

60 596°F 50 70°F 40 467°F 30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 INDICATED LEVEL (%)

Attachment 17 Page 2 of 2 Rev d

CPNPP NRC 2011 JPM RA2 Answer Key CPNPP PROCEDURE NO.

ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 ABN-905A LOSS OF CONTROL ROOM HABITABILITY REVISION NO. 9 PAGE 59 OF 74 ATTACHMENT 16 PAGE 1 OF 1 SG LEVEL TEMPERATURE CORRECTION NOTE: Normal SG level for Hot Standby and Cooldown (60 - 75% NR) is between 83% and 90%

actual wide range. Operating outside this range could cause uncovering AFW nozzle OR ESF actuation OR moisture carryover. Approximate critical levels (actual wide range) are:

! Lo-Lo (ESF actuation) Unit 1 - 74%

! AFW Nozzle Unit 1 - 83%

! Hi-Hi (moisture carryover) 92%

(L) 100.0 551 0 F 90.0 500 0 F 80.0 ACTUAL SG WIDE RANGE LEVEL (%)

350 0 F 0

400 F 70.0 70 0 F 60.0 50.0 40.0 30.0 20.0 10.0 0.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 INDICATED SG WIDE RANGE LEVEL (%)

Attachment 16 Page 1 of 2 Rev d

CPNPP NRC 2011 JPM RA2 Answer Key CPNPP PROCEDURE NO.

ABNORMAL CONDITIONS PROCEDURES MANUAL UNIT 1 ABN-905A LOSS OF CONTROL ROOM HABITABILITY REVISION NO. 9 PAGE 60 OF 74 ATTACHMENT 17 PAGE 1 OF 1 PRZR LEVEL TEMPERATURE CORRECTION PRESSURIZER LEVEL CHANNEL (Hot Calibrated)

(LI-459B, LI-460B) 100 2235 PSIG 653°F 1483 PSIG 90 486 PSIG 80 70 0 PSIG ACTUAL LEVEL (%)

60 596°F 50 70°F 40 467°F 30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 INDICATED LEVEL (%)

Attachment 17 Page 2 of 2 Rev d

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA3 Task #RO1808 K/A #2.2.12 3.7 / 4.1

Title:

Perform Axial Flux Difference Surveillance Examinee (Print):

Testing Method:

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

Alternate Path: Plant:

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 95% power.

The Axial Flux Difference (AFD) alarm was declared INOPERABLE over 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ago.

Power Range Nuclear Instrument AFD data was collected for several hours last shift.

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

PERFORM OPT-403, Axial Flux Difference.

ENTER the Power Range Nuclear Instrument AFD data onto OPT-403-1, AFD Data Sheet.

RECORD findings in the Discrepancies/Comments Section of OPT-403-1.

TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C 0800 9% 10% 11% 9%

0830 9% 11% 12% 10%

0900 10% 11% 12% 11%

0930 11% 14% 12% 14%

1000 11% 13% 12% 13%

1030 12% 14% 13% 14%

Task Standard: Perform Axial Flux Difference surveillance per OPT-403 and record findings on OPT-403-1.

Required Materials: OPT-403, Axial Flux Difference, Rev. 11.

OPT-403-1, AFD Data Sheet, Rev. 10-1.

NUC-204-6, Axial Flux Difference As a Function of Rated Thermal Power, Unit 1 Cycle 15, Rev. 07/26/10.

Page 1 of 6 CPNPP NRC 2011 JPM RA3 Rev d.doc

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

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

Page 2 of 6 CPNPP NRC 2011 JPM RA3 Rev d.doc

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

PROVIDE the examinee with a copy of:

OPT-403, Axial Flux Difference.

OPT-403-1, AFD Data Sheet.

NUC-204-6, Axial Flux Difference As a Function of Rated Thermal Power.

Page 3 of 6 CPNPP NRC 2011 JPM RA3 Rev d.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from OPT-403, Section 8.0 and documented on Form OPT-403-1.

Perform Step: 1 Record the following data for the affected unit:

8.1 & 8.1.1

Unit 1 or 2 as applicable Standard: CIRCLED Unit 1 on OPT-403-1.

Comment: SAT UNSAT Perform Step: 2 Record the following data for the affected unit:

8.1 & 8.1.2

Date Standard: ENTERED Date on OPT-403-1.

Comment: SAT UNSAT Perform Step: 3 Record the following data:

8.2 & 8.2.1

Time Standard: ENTERED Time on OPT-403-1.

Comment: SAT UNSAT Perform Step: 4 Record the following data:

8.2 & 8.2.2

PR FLUX for each operable excore detector Standard: RECORDED PR FLUX for each operable excore detector on OPT-403-1 from JPM Cue Sheet.

Comment: SAT UNSAT Perform Step: 5 Record the following data:

8.2 & 8.2.3

Percent Rated Thermal Power (RTP)

Standard: RECORDED Percent Rated Thermal Power on OPT-403-1.

Comment: SAT UNSAT Page 4 of 6 CPNPP NRC 2011 JPM RA3 Rev d.doc

Appendix C JPM STEPS Form ES-C-1 Perform Step: 6 Perform the following to determine PR FLUX status and record:

8.3 & 8.3.1

Verify at least 3 of 4 PR FLUX channels are within the Acceptable Operation region (Doghouse Region) of NUC-204-6 Axial Flux Difference as a Function of Rated Thermal Power.

Standard: DETERMINED PR FLUX status and RECORDED and INITIALED on OPT-403-1.

Comment: SAT UNSAT Perform Step: 7 Perform the following to determine PR FLUX status and record:

8.3 & 8.3.2

Repeat Steps 8.2 and 8.3 at least once per thirty (30) minutes.

Standard: REPEATED Steps 8.2 and 8.3 at least once per thirty (30) minutes on OPT-403-1.

Comment: SAT UNSAT Perform Step: 8 Record findings in the Discrepancies/Comments Section of OPT-403-1.

Standard: RECORDED findings in the Discrepancies / Comments Section of OPT-403-1.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP NRC 2011 JPM RA3 Rev d.doc

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

Unit 1 is at 95% power.

The Axial Flux Difference (AFD) alarm was declared INOPERABLE over 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ago.

Power Range Nuclear Instrument AFD data was collected for several hours last shift.

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

PERFORM OPT-403, Axial Flux Difference.

ENTER the Power Range Nuclear Instrument AFD data onto OPT-403-1, AFD Data Sheet.

RECORD findings in the Discrepancies/Comments Section of OPT-403-1.

TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C 0800 9% 10% 11% 9%

0830 9% 11% 12% 10%

0900 10% 11% 12% 11%

0930 11% 14% 12% 14%

1000 11% 13% 12% 13%

1030 12% 14% 13% 14%

Page 6 of 6 CPNPP NRC 2011 JPM RA3 Rev d.doc

CPNPP NRC 2011 JPM RA3 Handout 1 FOR SIMULATOR USE ONLY Axial Flux Difference as a Function of Rated Thermal Power Unit 1, Cycle 15 100 15.00 2.4 10.00 95 90 85 UNACCEPTABLE UNACCEPTABLE 80 OPERATION OPERATION 75 70 65 Rated Thermal Power (%)

60 55 50 30.00 30.00 45 40 35 30 25 20 15 10 5

0

-40 -35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 Indicated Axial Flux Difference (%)

Prepared By: MOL IC18 Date:

Approved By: SIMULATOR USE ONLY Date:

Core Performance Engineering Supervisor NUC-204-6 Page 1 of 1 REFERENCE USE Rev. 2 Page 1 of 1 Rev d

CPNPP NRC 2011 JPM RA3 Handout 2 AFD DATA SHEET 8.1.1 UNIT: (Circle one) 1 2 8.1.2 DATE NOTE: ! PR ) FLUX shall be considered outside the Acceptable Operations limits when two or more OPERABLE excore channels indicate ) FLUX to be outside the Acceptable Operations limits.

! PR ) FLUX logging frequency may be shortened at the discretion of the Shift Manager.

! Log PR ) FLUX data at least once per 30 minutes. The 30 minute frequency satisfies the following TRS 13.2.32.1 requirements:

- Once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that the AFD Monitor Alarm is inoperable.

- Once per 30 minutes when the AFD Monitor Alarm is inoperable for > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

PR FLUX 3 of 4 PR WITHIN TIME % RTP INITIAL ACCEPTABLE u -NI-41C u -NI-42C u -NI-43C u -NI-44C OPERATION YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO OPT-403-1 PAGE 1 OF 3 R-10 Page 1 of 3 Rev d

CPNPP NRC 2011 JPM RA3 Handout 2 AFD DATA SHEET PR FLUX 3 of 4 PR WITHIN TIME % RTP INITIAL ACCEPTABLE u -NI-41C u -NI-42C u -NI-43C u -NI-44C OPERATION YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO Additional copies of Page 2 of this data sheet may be used as required to document AFD status. Q Continued Next Page OPT-403-1 PAGE 2 OF 3 R-10 Page 2 of 3 Rev d

CPNPP NRC 2011 JPM RA3 Handout 2 AFD DATA SHEET DISCREPANCIES / COMMENTS:

CORRECTIVE ACTIONS:

PERFORMED BY: DATE:

SIGNATURE REVIEWED BY: DATE:

OPERATIONS MANAGEMENT OPT-403-1 PAGE 3 OF 3 R-10 Page 3 of 3 Rev d

CPNPP NRC 2011 JPM RA3 Procedure COMANCHE PEAK NUCLEAR POWER PLANT UNIT COMMON OPERATIONS TESTING MANUAL ELECTRONIC CONTROLLED COPY CHANGES ARE NOT INDICATED LATEST CHANGE NOTICE EFFECTIVE DATE

__________/________ Verify current status in the Document Control Database prior to use.

INITIAL & DATE QUALITY RELATED AXIAL FLUX DIFFERENCE PROCEDURE NO. OPT-403 REVISION NO. 11 EFFECTIVE DATE: 10/08/08 1200 PREPARED BY (Print): JIM BRAU Ext: 5443 TECHNICAL REVIEW BY (Print): ROB SLOUGH Ext: 5727 APPROVED BY: D.W. McGAUGHEY for Dave Goodwin Date: 09/19/08 DIRECTOR, OPERATIONS Page 1 of 4 Rev d

CPNPP NRC 2011 JPM RA3 Procedure CPNPP PROCEDURE NO.

OPERATIONS TESTING MANUAL UNIT COMMON OPT-403 AXIAL FLUX DIFFERENCE REVISION NO. 11 PAGE 2 OF 4 1.0 PURPOSE This procedure satisfies Axial Flux Difference (AFD) monitoring when automated monitoring is NOT available. The requirements of TRS 13.2.32.1 is met by monitoring and logging indicated AFD for each OPERABLE excore channel. A frequency of 30 minutes for logging data is used to ensure the requirement is met if the AFD Monitor is inoperable for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The actual TRS frequency requirements are as follows:

NOTE: The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging.

! Once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that the AFD Monitor Alarm is inoperable. (TRS 13.2.32.1).

! Once per 30 minutes when the AFD Monitor Alarm is inoperable for >24 hours. (TRS 13.2.32.1).

2.0 ACCEPTANCE CRITERIA 2.1 At > 50% RTP the indicated AFD is within the Acceptable Operation limit of NUC-204-6 Axial Flux Difference as a Function of Rated Thermal Power.

3.0 DEFINITIONS/ACRONYMS 3.1 APLND - Analyzed Power Limit Nuclear Design 3.2 AFD - Axial Flux Difference 3.3 RTP - Rated Thermal Power 3.4 Validated Computer Program - A computer program verified consistent with current procedures and technical data used to calculate AFD and the associated penalty time.

4.0 REFERENCES

4.1 Technical Specification 3.2.3, "AXIAL FLUX DIFFERENCE (AFD) 4.2 Technical Requirement 13.2.32, "AXIAL FLUX DIFFERENCE (AFD)"

4.3 FSAR Section 4.3, Nuclear Design 4.4 COLR, Core Operating Limits Report 4.5 NUC-204, "Target Axial Flux Difference" 4.6 NUC-204-6, Axial Flux Difference as a Function of Rated Thermal Power 4.7 SOP-906, Plant Process Computer System Guidelines Page 2 of 4 Rev d

CPNPP NRC 2011 JPM RA3 Procedure CPNPP PROCEDURE NO.

OPERATIONS TESTING MANUAL UNIT COMMON OPT-403 AXIAL FLUX DIFFERENCE REVISION NO. 11 PAGE 3 OF 4 5.0 PRECAUTIONS, LIMITATIONS AND NOTES 5.1 Precautions None 5.2 Limitations 5.2.1 Core Performance Engineering shall be notified when any acceptance criteria not satisfied.

5.3 Notes None 6.0 PREREQUISITES Q 6.1 MODE 1 at > 50% RTP.

7.0 TEST EQUIPMENT None Page 3 of 4 Rev d

CPNPP NRC 2011 JPM RA3 Procedure CPNPP PROCEDURE NO.

OPERATIONS TESTING MANUAL UNIT COMMON OPT-403 AXIAL FLUX DIFFERENCE REVISION NO. 11 PAGE 4 OF 4 8.0 INSTRUCTIONS NOTE: Record all data on Form OPT-403-1.

8.1 Record the following data for the affected unit:

Q 8.1.1 Unit 1 or 2 as applicable Q 8.1.2 Date 8.2 Record the following data:

Q 8.2.1 Time Q 8.2.2 PR ) FLUX for each operable excore detector Q 8.2.3 Percent Rated Thermal Power (RTP) 8.3 Perform the following to determine PR ) FLUX status and record:

Q A. Verify at least 3 of 4 PR ) FLUX channels are within the Acceptable Operation region (Doghouse Region) of NUC-204-6 Axial Flux Difference as a Function of Rated Thermal Power.

[C]

Q B. Repeat Steps 8.2 and 8.3 at least once per thirty (30) minutes.

9.0 RESTORATION/POST WORK ACTIVITIES None 10.0 ATTACHMENTS/FORMS 10.1 Attachments None 10.2 Forms 10.2.1 OPT-403-1, AFD Data Sheet Page 4 of 4 Rev d

CPNPP NRC 2011 JPM RA3 Answer Key AFD DATA SHEET 8.1.1 UNIT: (Circle one) 1 2 8.1.2 DATE TODAY NOTE: ! PR ) FLUX shall be considered outside the Acceptable Operations limits when two or more OPERABLE excore channels indicate ) FLUX to be outside the Acceptable Operations limits.

! PR ) FLUX logging frequency may be shortened at the discretion of the Shift Manager.

! Log PR ) FLUX data at least once per 30 minutes. The 30 minute frequency satisfies the following TRS 13.2.32.1 requirements:

- Once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that the AFD Monitor Alarm is inoperable.

- Once per 30 minutes when the AFD Monitor Alarm is inoperable for > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

PR FLUX 3 of 4 PR WITHIN TIME % RTP INITIAL ACCEPTABLE u -NI-41C u -NI-42C u -NI-43C u -NI-44C OPERATION YES NO 0800 9% 10% 11% 9% 95 LZ YES NO 0830 9% 11% 12% 10% 95 LZ YES NO 0900 10% 11% 12% 11% 95 LZ YES NO 0930 11% 14% 12% 14% 95 LZ YES NO 1000 11% 13% 12% 13% 95 LZ YES NO 1030 12% 14% 13% 14% 95 LZ YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO OPT-403-1 PAGE 1 OF 3 R-10 Page 1 of 3 Rev d

CPNPP NRC 2011 JPM RA3 Answer Key AFD DATA SHEET PR FLUX 3 of 4 PR WITHIN TIME % RTP INITIAL ACCEPTABLE u -NI-41C u -NI-42C u -NI-43C u -NI-44C OPERATION YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO Additional copies of Page 2 of this data sheet may be used as required to document AFD status. Q Continued Next Page OPT-403-1 PAGE 2 OF 3 R-10 Page 2 of 3 Rev d

CPNPP NRC 2011 JPM RA3 Answer Key AFD DATA SHEET DISCREPANCIES / COMMENTS: Acceptance Criteria not met starting at 0930.

CORRECTIVE ACTIONS:

PERFORMED BY: DATE:

SIGNATURE REVIEWED BY: DATE:

OPERATIONS MANAGEMENT OPT-403-1 PAGE 3 OF 3 R-10 Page 3 of 3 Rev d

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC RA4 Task #RWT029 K/A #2.3.12 3.2 / 3.7

Title:

Determine Radiation Levels During Maintenance and Administrative Exposure Limit Examinee (Print):

Testing Method:

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

Alternate Path: Plant:

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

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

Initial Conditions: Given the following conditions:

JPM Cue Sheet #1

A high dose maintenance activity is scheduled in the Fuel Building.

The general dose rate in the area is 100 mrem/hour but can be reduced to 25 mrem/hour if lead shielding is installed.

It will take Nuclear Equipment Operators (NEOs) Alpha & Bravo 30 minutes to install the shielding.

Independent of the shielding, it will take NEO Alpha two (2) hours or NEOs Alpha & Bravo one and a half (1.5) hours to perform the maintenance.

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

CALCULATE the dose received when performing the maintenance for each of the following conditions:

NEO Alpha without shielding. __________ mrem.

NEOs Alpha & Bravo without shielding. __________ mrem.

NEO Alpha with shielding. __________ mrem.

NEOs Alpha & Bravo with shielding. __________ mrem Initial Conditions: Given the following conditions:

JPM Cue Sheet #2

It was determined that NEO Alpha received a Total Effective Dose Equivalent (TEDE) of 225 mrem while performing the maintenance task.

NEO Alphas year to date whole body exposure is 1785 mrem.

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

IDENTIFY if any applicable CPNPP Administrative Exposure Levels have been exceeded.

REPORT findings to the Shift Manager.

Task Standard: Calculate the dose received when performing the maintenance and determine if an Administrative Exposure Level was exceeded per STA-655.

Page 1 of 7 CPNPP NRC 2011 JPM RA4 Rev d.doc

Appendix C JPM WORKSHEET Form ES-C-1 Required Materials: STA-655, Exposure Monitoring Program, Rev. 19.

Validation Time: 15 minutes Time Critical: N/A Completion Time: ________ minutes Comments:

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

Page 2 of 7 CPNPP NRC 2011 JPM RA4 Rev d.doc

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

PROVIDE the examinee JPM Cue Sheet #1.

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

ENSURE examinee has a calculator.

ENSURE copy of STA-655, Exposure Monitoring Program is available.

Page 3 of 7 CPNPP NRC 2011 JPM RA4 Rev d.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Perform Step: 1 Determine total dose to NEO Alpha without shielding.

Standard: DETERMINED total dose to NEO Alpha without shielding as follows:

100 mrem/hr x 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months = 200 mrem total dose.

Comment: SAT UNSAT Perform Step: 2 Determine total combined dose to NEOs Alpha & Bravo without shielding.

Standard: DETERMINED total combined dose to NEOs Alpha & Bravo without shielding as follows:

100 mrem/hr x 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months s/NEO x 2 NEOs = 300 mrem total dose.

Comment: SAT UNSAT Perform Step: 3 Determine total dose to install shielding.

Standard: DETERMINED total dose to install shielding as follows:

100 mrem/hr x 0.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months s/NEO x 2 NEOs = 100 mrem to install.

Comment: SAT UNSAT Perform Step: 4 Determine total dose to NEO Alpha with shielding.

Standard: DETERMINED total dose to NEO Alpha with shielding as follows:

25 mrem/hr x 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months + 100 mrem = 150 mrem total dose.

Comment: SAT UNSAT Perform Step: 5 Determine total combined dose to NEOs Alpha & Bravo with shielding.

Standard: DETERMINED total combined dose to NEOs Alpha & Bravo with shielding as follows:

25 mrem/hr x 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months s/NEO x 2 NEOs + 100 mrem = 175 mrem total dose.

Comment: SAT UNSAT Page 4 of 7 CPNPP NRC 2011 JPM RA4 Rev d.doc

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

Perform Step: 6 Determine if any applicable CPNPP Administrative Exposure Levels have been exceeded.

Standard: DETERMINED that the CPNPP TEDE Administrative Exposure Limit of 2000 mrem was exceeded per STA-655, Exposure Monitoring Program.

1785 mrem = 225 mrem = 2010 mrem.

Comment: SAT UNSAT Perform Step: 7 Report findings to Shift Manager.

Standard: REPORTED to Shift Manager that the CPNPP TEDE Administrative Exposure Limit of 2000 mrem was exceeded.

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 7 CPNPP NRC 2011 JPM RA4 Rev d.doc

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

A high dose maintenance activity is scheduled in the Fuel Building.

The general dose rate in the area is 100 mrem/hour but can be reduced to 25 mrem/hour if lead shielding is installed.

It will take Nuclear Equipment Operators (NEOs) Alpha

& Bravo 30 minutes to install the shielding.

Independent of the shielding, it will take NEO Alpha two (2) hours or NEOs Alpha & Bravo one and a half (1.5) hours to perform the maintenance.

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

CALCULATE the dose received when performing the maintenance for each of the following conditions:

NEO Alpha without shielding. _____ mrem.

NEOs Alpha & Bravo without shielding. _____ mrem.

NEO Alpha with shielding. _____ mrem.

NEOs Alpha & Bravo with shielding. _____ mrem.

Page 6 of 7 CPNPP NRC 2011 JPM RA4 Rev d.doc

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

It was determined that NEO Alpha received a Total Effective Dose Equivalent (TEDE) of 225 mrem while performing the maintenance task.

NEO Alphas year to date whole body exposure is 1785 mrem.

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

IDENTIFY if any applicable CPNPP Administrative Exposure Levels have been exceeded.

REPORT findings to the Shift Manager.

Page 7 of 7 CPNPP NRC 2011 JPM RA4 Rev d.doc

CPNPP NRC 2011 JPM RA4 Answer Key CPNPP PROCEDURE NO.

STATION ADMINISTRATION STA-655 EXPOSURE MONITORING PROGRAM REVISION NO. 19 Page 23 of 29 ATTACHMENT 8.A PAGE 1 OF 2 ADMINISTRATIVE EXPOSURE LEVELS DEEP DOSE RADIATION WORKERS LEVEL PERIOD CALCULATION Annual TEDE (Total Effective Dose Equivalent) 2000 mrem TODE - (The SUM of Deep-Dose Annual Equivalent and Committed Dose Equivalent to any individual organ or tissue other than 20,000 mrem the lens of the eye).

PERIOD EVENT LEVEL Annual Planned Special Exposure (PSE) 4000 mrem NOT TO EXCEED:

Lifetime Planned Special Exposure (PSE) Five times the annual dose limit.

Page 1 of 2 Rev d

CPNPP NRC 2011 JPM RA4 Answer Key CPNPP PROCEDURE NO.

STATION ADMINISTRATION STA-655 EXPOSURE MONITORING PROGRAM REVISION NO. 19 Page 24 of 29 ATTACHMENT 8.A PAGE 2 OF 2 ADMINISTRATIVE EXPOSURE LEVELS DEEP DOSE EMBRYO/FETUS OF DECLARED PREGNANT RADIATION WORKER PERIOD RECEPTOR LEVEL Gestation Declared Radiation Worker 200 mrem OR: (Not to exceed 50mrem/month)

Declared Escorted Radiation Worker NOTE: If the dose to the embryo/fetus is found to have exceeded 200 mrem by the time the woman declares pregnancy, then any additional dose should not exceed 50 mrem during the remainder of the pregnancy.

NOTE: Administrative Exposure Levels are based on Electronic Dosimeter estimates.

ESCORTED RADIATION WORKERS LEVEL PERIOD CALCULATION Monitoring Period DDE (Deep Dose Equivalent) (with OSL 100 mrem badge)

With appropriate authorization:

Annual DDE (Deep Dose Equivalent) (with OSL 2000 mrem badge)

MEMBER OF THE PUBLIC (VISTOR)

PERIOD CALCULATION LEVEL Quarter DDE (Deep Dose Equivalent) 20 mrem NOTE: A Visitor is not allowed into a contaminated or airborne area and therefore a committed dose equivalent should not be calculated.

NOTE: Administrative Exposure Levels are based on Electronic Dosimeter estimates.

Page 2 of 2 Rev d

Appendix C JPM WORKSHEET Form ES-C-1 Facility: CPNPP JPM # NRC SA1 Task #SO1017 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:

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

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

Initial Conditions: Given the following conditions:

Unit 1 is operating at approximately 3% power.

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

The Reactor Coolant System Boron concentration the last time the Positive Displacement Charging Pump was run was 2400 ppm.

Current Reactor Coolant System Boron concentration is 1545 ppm.

Chemistry has just reported the Unit 1 Refueling Water Storage Tank boron concentration is 2700 ppm.

Initiating Cue: The Shift Manager 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 and 5.3.1.D.

REPORT your findings to the Shift Manager.

IDENTIFY any Technical Specification Limiting Condition for Operation (LCO), Required Action, and Completion Time associated with the REPORT from Chemistry, if any.

LCO _______________

REQUIRED ACTION _______________

COMPLETION TIME _______________

Task Standard: Calculate the change in boron and resultant change in temperature when placing the Positive Displacement Pump in service per SOP-103A and identify any Technical Specification Limiting Condition for Operation, Required Action and Completion Time.

Required Materials: SOP-103A, Chemical and Volume Control System, Rev. 17-23.

CPNPP Technical Specifications Units 1 and 2, Amendment 152.

Reactivity Briefing Sheet for 1545 ppm Reactor Coolant System conditions.

Page 1 of 6 CPNPP NRC 2011 JPM SA1 Rev d.doc

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

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

Page 2 of 6 CPNPP NRC 2011 JPM SA1 Rev d.doc

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

PROVIDE the examinee with a copy of:

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

INITIALED up to Step 5.3.1.C.

89.8 EFPD Reactivity Briefing Sheet.

CPNPP Technical Specifications - Units 1 and 2.

Page 3 of 6 CPNPP NRC 2011 JPM SA1 Rev d.doc

Appendix C JPM STEPS Form ES-C-1

- Check Mark Denotes Critical Step START TIME:

Examiner Note: The following steps are from SOP-103A, Step 5.3.1.

Perform Step: 1 IF the RCS boron concentration has changed significantly since the 5.3.1.C 1st line + PDP was last operated, THEN determine the impact of water in the PDP calculation piping on reactivity as follows:

B = RCS Boron Concentration Difference Standard: CALCULATED B = RCS Boron Concentration Difference as follows:

B = ( 500 ppm PDP - 1545 ppm RCS) x 0.00128 = 1.0944 ppm Comment: SAT UNSAT Examiner Note: Rounding off of ITC and HFP Differential Boron Worth may occur.

Perform Step: 2 On the Reactivity Briefing Sheet get the following information:

5.3.1.C 2nd line + ITC _____ pcm/ºF HFP Differential Boron Worth _____ pcm/ppm calculation Standard: DETERMINED the following from the Reactivity Briefing Sheet:

ITC = - 1.1 +/- 0.1 pcm /ºF HFP Differential Boron Worth = - 6.9 +/- 0.1 pcm / ppm Comment: SAT UNSAT Examiner Note: Rounding off of ITC / HFP Differential Boron Worth may occur.

Perform Step: 3 On the Reactivity Briefing Sheet get the following information:

5.3.1.C 2nd line + ITC / HFP Differential Boron Worth = ppm / ºF calculation Standard: CALCULATED change in ppm / ºF:

- 1.1 pcm / ºF / - 6.9 pcm / ppm = 0.1594 +/- 0.02 ppm / ºF Comment: SAT UNSAT Page 4 of 6 CPNPP NRC 2011 JPM SA1 Rev d.doc

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

Perform Step: 4 On the Reactivity Briefing Sheet get the following information:

5.3.1.C 3rd line + TAVE = B / ppm / ºF calculation Standard: CALCULATED change in TAVE as follows:

TAVE = B / ppm / ºF = 1.0944 ppm / 0.1594 ppm / ºF = 6.87 +/- 1.0 ºF Comment: SAT UNSAT Perform Step: 5 IF TAVE calculated above is >1ºF, THEN notify Shift Operations 5.3.1.D Manager to discuss contingency actions.

Standard: DETERMINED TAVE calculated is greater than 1ºF and NOTIFIED Shift Operations Manager.

Comment: SAT UNSAT Perform Step: 6 Identify Technical Specification Limiting Condition for Operation.

Standard: RECOGNIZED RWST boron concentration greater than 2600 ppm and DETERMINED the following:

Technical Specification LCO 3.5.4, Refueling Water Storage Tank CONDITION A, RWST boron concentration not within limits.

Comment: SAT UNSAT Perform Step: 7 Identify Technical Specification REQUIRED ACTION and COMPLETION TIME.

Standard: DETERMINED Technical Specification REQUIRED ACTION and COMPLETION TIME:

3.5.4.A.1 - Restore RWST to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Terminating Cue: This JPM is complete.

Comment: SAT UNSAT STOP TIME:

Page 5 of 6 CPNPP NRC 2011 JPM SA1 Rev d.doc

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

Unit 1 is operating at approximately 3% power.

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

The Reactor Coolant System Boron concentration the last time the Positive Displacement Charging Pump was run was 2400 ppm.

Current Reactor Coolant System Boron concentration is 1545 ppm.

Chemistry has just reported the Unit 1 Refueling Water Storage Tank boron concentration is 2700 ppm.

INITIATING CUE: The Shift Manager 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 and 5.3.1.D.

REPORT your findings to the Shift Manager.

IDENTIFY any Technical Specification Limiting Condition for Operation (LCO), Required Action, and Completion Time associated with the REPORT from Chemistry, if any.

LCO _______________

REQUIRED ACTION _______________

COMPLETION TIME _______________

Page 6 of 6 CPNPP NRC 2011 JPM SA1 Rev d.doc

CPNPP NRC 2011 JPM SA1 Handout Reactivity Briefing Sheet for Stable Operation FOR SIMULATOR SIMULATOR USE on

- Created ONLY02/17/09 SIMULATOR USE ONLY Calculations based on core design values, and assume:

Burnup = 4001.3 MWD/MTU Burnup in the BOL range 89.82 EFPD Power = 0 RTP Boron = 1545 ppm NOTE: Re-create the Briefing Sheet B10 Conc = 0.1776696 w/o if current values significantly differ Control Bank D = 100 steps from assumed inputs.

Reactivity affects of Control Bank D HFP Diff Worth @ 100.0 steps = -4.3 pcm / step HFP Integral Rod Worth for CBD Step Positions:

Steps pcm Steps pcm Steps pcm Steps pcm 110 -269.0 103 -294.7 96 -325.2 85 -382.5 109 -272.4 102 -298.7 95 -329.9 80 -411.7 108 -275.9 101 -302.9 94 -334.8 75 -442.7 107 -279.4 100 -307.1 93 -339.8 70 -475.3 106 -283.1 99 -311.5 92 -344.8 65 -509.2 105 -286.9 98 -316.0 91 -350.0 60 -544.2 104 -290.7 97 -320.5 90 -355.2 55 -580.3 Reactivity affects of Boron HFP Diff Boron Worth @ 1545 ppm = -6.9 pcm / ppm 1-FK-110 Pot Setting for Blended Flow @ 1545 ppm = 6.34 (Assuming BAT concentration of 7492.0 ppm)

Reactivity affects of Power Power Coefficient of Reactivity = -13.1 pcm / % RTP Dilution to equal 1% Power Increase = 83.8 gallons RMUW Boration to equal 1% Power Decrease = 20.9 gallons boric acid Reactivity affects of RCS Temperature Temperature Coefficient of Reactivity (ITC) = -1.1 pcm / EF Boration to equal 1EF Temperature Decrease = 1.8 gallons boric acid Dilution to equal 1EF Temperature Increase = 7.3 gallons RMUW Load Reduction equal to 1EF Tave Increase = 1.0 MWe Page 1 of 1 Rev d

CPNPP NRC 2011 JPM SA1 Procedure COMANCHE PEAK NUCLEAR POWER PLANT UNIT 1 SYSTEM OPERATING PROCEDURE MANUAL ELECTRONIC CONTROLLED COPY CHANGES ARE NOT INDICATED LATEST CHANGE NOTICE EFFECTIVE DATE PCN-1 0--200 1200

__________/________ Verify current status in the Document Control Database prior to use.

INITIAL & DATE QUALITY RELATED CHEMICAL AND VOLUME CONTROL SYSTEM PROCEDURE NO. SOP-103A REVISION NO. 17 EFFECTIVE DATE: 03-05-2008 1200 PREPARED BY (Print): Brad Hancock Ext: 6769 TECHNICAL REVIEW BY (Print): Lisabeth Donley Ext: 6524 APPROVED BY: Alan Hall for Dave Goodwin Date: 02-19-2008 DIRECTOR, OPERATIONS Page 1 of 4 Rev d

CPNPP NRC 2011 JPM SA1 Procedure CPNPP PROCEDURE NO.