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Text

Initial Exam 2009-302 Draft Administrative JPMs
	ML100410114
Person / Time
Site:	Harris
Issue date:	01/05/2010
From:	; NRC/RGN-II
To:	;
References
	IR-09-302
	Download: ML100410114 (80)
	v • d • e

Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Page 1 of 15 Worksheet Form ES-C-1 Shearon Harris Task No.: 301179H601 Response to Voids In Reactor JPM No.: 2009B NRC Exam Vessel-Calculate Reactor Vessel Admin JPM RO A1-1 Maximum Vent Time EPE E10 EK3.2 RO 3.2 SRO 3.7 NRC Examiner:

Date: __ _ Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant DRJ\fT 2009B NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Page 1 of 15 Worksheet Form ES-C-1 Shearon Harris Task No.: 301179H601 Response to Voids In Reactor JPM No.: 2009B NRC Exam Vessel-Calculate Reactor Vessel Admin JPM RO A1-1 Maximum Vent Time EPE E10 EK3.2 RO 3.2 SRO 3.7 NRC Examiner:

Date: __ _ Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant DRJ\fT 2009B NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C Page 2 of 15 Worksheet Form ES-C-1 READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: The plant was at 100 percent power when a Small Break LOCA occurred.

All RCP have been secured.

SI has been terminated.

RVLlS Upper Range reading is 85 percent

Pressurizer level is 90 percent

RCS Pressure is 1560 psig

Containment Temperature is 195°F

Chemistry reports that Containment Hydrogen Concentration is 2.15 percent Based on the present conditions a void has formed in the Reactor Vessel. The CRS and STA have reviewed the CSFSTs. It was determined that FRP-1.3, Response To Voids In Reactor Vessel should be implemented.

The crew has completed preparing the Containment for Reactor Vessel venting. The CRS has directed you to calculate the maximum time the Reactor Vessel should be vented, using Attachment 1 of FRP-1.3 Your calculation should be determined to the second to allow timing using the MCR timer. Task Standard:

Determine maximum Reactor Vessel vent time within +/-5 seconds of calculation.

Required Materials:

Calculator General

References:

FRP-1.3 Figure 2 and Attachment 1 (Rev. 16) Handouts:

FRP-1.3 Figure 2 and Attachment 1 (Rev. 16) Time Critical Task: No Validation Time: 10 minutes 2009B NRC Exam Admin JPM RO A 1-1 Rev 1 Appendix C Page 2 of 15 Worksheet Form ES-C-1 READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: The plant was at 100 percent power when a Small Break LOCA occurred.

All RCP have been secured.

SI has been terminated.

RVLlS Upper Range reading is 85 percent

Pressurizer level is 90 percent

RCS Pressure is 1560 psig

Containment Temperature is 195°F

Chemistry reports that Containment Hydrogen Concentration is 2.15 percent Based on the present conditions a void has formed in the Reactor Vessel. The CRS and STA have reviewed the CSFSTs. It was determined that FRP-1.3, Response To Voids In Reactor Vessel should be implemented.

The crew has completed preparing the Containment for Reactor Vessel venting. The CRS has directed you to calculate the maximum time the Reactor Vessel should be vented, using Attachment 1 of FRP-1.3 Your calculation should be determined to the second to allow timing using the MCR timer. Task Standard:

Determine maximum Reactor Vessel vent time within +/-5 seconds of calculation.

Required Materials:

Calculator General

References:

FRP-1.3 Figure 2 and Attachment 1 (Rev. 16) Handouts:

FRP-1.3 Figure 2 and Attachment 1 (Rev. 16) Time Critical Task: No Validation Time: 10 minutes 2009B NRC Exam Admin JPM RO A 1-1 Rev 1 Appendix C Step 2 Step 3 Step 4 Step 5 Page 3 of 15 Worksheet Critical Step Justification Form ES-C-1 Without the correct Containment volume you cannot determine the maximum venting time Without the correct hydrogen volume you cannot determine the maximum venting time Without the correct hydrogen flow rate you cannot determine the maximum venting time This is the maximum venting time calculation required by the CRS 2009B NRC Exam Admin JPM RD A1-1 Rev 1 Appendix C Step 2 Step 3 Step 4 Step 5 Page 3 of 15 Worksheet Critical Step Justification Form ES-C-1 Without the correct Containment volume you cannot determine the maximum venting time Without the correct hydrogen volume you cannot determine the maximum venting time Without the correct hydrogen flow rate you cannot determine the maximum venting time This is the maximum venting time calculation required by the CRS 2009B NRC Exam Admin JPM RD A1-1 Rev 1 Appendix C START TIME: Performance Step: 1 Standard:

Comment: ./ Performance Step: 2 Standard:

Comment: ./ Performance Step: 3 Standard:

Comment: ./ -Denotes a Critical Step Page 4 of 9 PERFORMANCE INFORMATION FRP-I.3 OBTAIN PROCEDURE (provided with handout) Form ES-C-1 Obtains FRP-1.3 and refers to Figure 2 and Attachment

1. FRP-I.3 Attachment 1 Step 1 Calculate the maximum venting time using Attachment

1. Calculate Containment Volume at STP 'A' in FT3 Using the provide Containment temperature of 195°F Containment Volume at STP 'A' = 1702094.66 FT3 FRP-1.3 Attachment 1 Step 2 Determine Maximum Hydrogen volume that can be vented 'B' in FT3 Using provided Containment Hydrogen Concentration of 2.15 percent determine maximum Hydrogen volume that can be vented 'B' = 14467.80 FT3 2009B NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C START TIME: Performance Step: 1 Standard:

Comment: ./ Performance Step: 2 Standard:

Comment: ./ Performance Step: 3 Standard:

Comment: ./ -Denotes a Critical Step Page 4 of 9 PERFORMANCE INFORMATION FRP-I.3 OBTAIN PROCEDURE (provided with handout) Form ES-C-1 Obtains FRP-1.3 and refers to Figure 2 and Attachment

1. FRP-I.3 Attachment 1 Step 1 Calculate the maximum venting time using Attachment

1. Calculate Containment Volume at STP 'A' in FT3 Using the provide Containment temperature of 195°F Containment Volume at STP 'A' = 1702094.66 FT3 FRP-1.3 Attachment 1 Step 2 Determine Maximum Hydrogen volume that can be vented 'B' in FT3 Using provided Containment Hydrogen Concentration of 2.15 percent determine maximum Hydrogen volume that can be vented 'B' = 14467.80 FT3 2009B NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C ../ Performance Step: 4 Standard:

Comment: ../ Performance Step: 5 Standard:

Comment: Terminating Cue: STOP TIME: ../ -Denotes a Critical Step Page 5 of 9 PERFORMANCE INFORMATION FRP-I.3 Attachment 1 Step 3 Form ES-C-1 Determine Hydrogen flow rate as a function of RCS pressure 'C' in FT3/MIN. Determines from Figure 2 that 1560 psig corresponds to 4850 FT 3/MIN (Tolerance 4950 -4750 FT3/MIN) FRP-1.3 Attachment 1 Step 4 Calculate maximum venting time '0' in minutes. Calculates 2.98 minutes (2 minutes and 59 seconds) Tolerance

+/- 5 seconds 3 min 4 seconds to 2 min 54 seconds When calculation is returned ENDOFJPM 2009B NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C ../ Performance Step: 4 Standard:

Comment: ../ Performance Step: 5 Standard:

Comment: Terminating Cue: STOP TIME: ../ -Denotes a Critical Step Page 5 of 9 PERFORMANCE INFORMATION FRP-I.3 Attachment 1 Step 3 Form ES-C-1 Determine Hydrogen flow rate as a function of RCS pressure 'C' in FT3/MIN. Determines from Figure 2 that 1560 psig corresponds to 4850 FT 3/MIN (Tolerance 4950 -4750 FT3/MIN) FRP-1.3 Attachment 1 Step 4 Calculate maximum venting time '0' in minutes. Calculates 2.98 minutes (2 minutes and 59 seconds) Tolerance

+/- 5 seconds 3 min 4 seconds to 2 min 54 seconds When calculation is returned ENDOFJPM 2009B NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C 6000 4000 3000 2000 1000 o ./ -Denotes a Critical Step Page 6 of 9 PERFORMANCE INFORMATION KEY RESPONSE TO VOIDS IN WC'l'OR VESSEl. 400 800 1200 ReS PRESSURE'

{PStG) I Rev. 16 I Form ES-C-1 2000 2:4A}O 20098 NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C 6000 4000 3000 2000 1000 o ./ -Denotes a Critical Step Page 6 of 9 PERFORMANCE INFORMATION KEY RESPONSE TO VOIDS IN WC'l'OR VESSEl. 400 800 1200 ReS PRESSURE'

{PStG) I Rev. 16 I Form ES-C-1 2000 2:4A}O 20098 NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C Page 7 of 9 PERFORMANCE INFORMATION KEY RESPONSE TO VOIDS IN REACTOR VESSEL Attachment 1 Sheet 1 of 1 INSTRUCTIONS roR DETBRHINING VENTING TIME Form ES-C-1 1. Detet'lline CNHT Volwa.e at STI.> I A' ; A -(2.266 x 106 Fr3) x 492°R (CNtlT 'temperature OF + 460<"R) 1 195°F 1 A .11702094.66

2. (BT3) B _ 114467.80 1 (n l) 3. Deterllin.e Hydrogen flow rate as a funetion of ReS pressure 'C'; a. Cheek ReS pressure and mark on Figure 2. b. Using Figure 2. read hydrogen flQW rate 'C', ITolerance 4750 -4950 I 4. Calculate 1I8X1:awa venting time 'D'; KaxiJnUll venting ti:ne ---EOP-FRP-I.3 c Tolerance 2 min 54 seconds 3 min 4 seconds Rev. 16 I c-1 4850 1 (FT3/MIN) 2 min and 59 seconds n-___ _ (MINUTES)

Page 22 (If 23 ./ -Denotes a Critical Step 2009B NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C Page 7 of 9 PERFORMANCE INFORMATION KEY RESPONSE TO VOIDS IN REACTOR VESSEL Attachment 1 Sheet 1 of 1 INSTRUCTIONS roR DETBRHINING VENTING TIME Form ES-C-1 1. Detet'lline CNHT Volwa.e at STI.> I A' ; A -(2.266 x 106 Fr3) x 492°R (CNtlT 'temperature OF + 460<"R) 1 195°F 1 A .11702094.66

2. (BT3) B _ 114467.80 1 (n l) 3. Deterllin.e Hydrogen flow rate as a funetion of ReS pressure 'C'; a. Cheek ReS pressure and mark on Figure 2. b. Using Figure 2. read hydrogen flQW rate 'C', ITolerance 4750 -4950 I 4. Calculate 1I8X1:awa venting time 'D'; KaxiJnUll venting ti:ne ---EOP-FRP-I.3 c Tolerance 2 min 54 seconds 3 min 4 seconds Rev. 16 I c-1 4850 1 (FT3/MIN) 2 min and 59 seconds D -(MINUTES)

Page 22 (If 23 ./ -Denotes a Critical Step 2009B NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C Page 8 of 9 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM RO A 1-1 -Response to Voids In Reactor Vessel -Calculate Reactor Vessel Maximum Vent Time Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

2009B NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C Page 8 of 9 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM RO A 1-1 -Response to Voids In Reactor Vessel -Calculate Reactor Vessel Maximum Vent Time Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

2009B NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C Initial Conditions:

Initiating Cue: Page 9 of 9 JPM CUE SHEET Form ES-C-1 The plant was at 100 percent power when a Small Break LOCA occurred.

All RCP have been secured.

SI has been terminated.

RVLlS Upper Range reading is 85 percent

Pressurizer level is 90 percent

RCS Pressure is 1560 psig

Containment Temperature is 195°F

Chemistry reports that Containment Hydrogen Concentration is 2.15 percent Based on the present conditions a void has formed in the Reactor Vessel. The CRS and STA have reviewed the CSFSTs. It was determined that FRP-1.3, Response To Voids In Reactor Vessel should be implemented.

The crew has completed preparing the Containment for Reactor Vessel venting. The CRS has directed you to calculate the maximum time the Reactor Vessel should be vented, using Attachment 1 of FRP-1.3 Your calculation should be determined to the second to allow timing using the MCR timer. 2009B NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C Initial Conditions:

Initiating Cue: Page 9 of 9 JPM CUE SHEET Form ES-C-1 The plant was at 100 percent power when a Small Break LOCA occurred.

All RCP have been secured.

SI has been terminated.

RVLlS Upper Range reading is 85 percent

Pressurizer level is 90 percent

RCS Pressure is 1560 psig

Containment Temperature is 195°F

Chemistry reports that Containment Hydrogen Concentration is 2.15 percent Based on the present conditions a void has formed in the Reactor Vessel. The CRS and STA have reviewed the CSFSTs. It was determined that FRP-1.3, Response To Voids In Reactor Vessel should be implemented.

The crew has completed preparing the Containment for Reactor Vessel venting. The CRS has directed you to calculate the maximum time the Reactor Vessel should be vented, using Attachment 1 of FRP-1.3 Your calculation should be determined to the second to allow timing using the MCR timer. 2009B NRC Exam Admin JPM RO A1-1 Rev 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Page 1 of 12 Worksheet Form ES-C-1 Shearon Harris Perform A Manual Shutdown Margin Calculation G 2.1.25 RO 3.9 SRO 4.2 Task No.: 001004H101 JPM No.: 20098 NRC Exam Admin JPM RO A 1-2 NRC Examiner:

Oate: __ _ Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: The plant has been operating at 52% power for 6 weeks while maintenance is replacing the motor on the 'A' Main Feedwater Pump

Core burnup is 140 EFPO

RCS boron concentration is 1140 ppm

NO rods are believed to be immovable

/ untrippable

POWERTRAX is NOT available The CRS has directed you to complete OST -1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, "Manual SOM Calculation (Modes 1 and 2)" for current plant conditions.

NOTE: For this JPM assume independent verification has been performed.

20098 NRC Admin Exam RO A 1-2 Rev. 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Page 1 of 12 Worksheet Form ES-C-1 Shearon Harris Perform A Manual Shutdown Margin Calculation G 2.1.25 RO 3.9 SRO 4.2 Task No.: 001004H101 JPM No.: 20098 NRC Exam Admin JPM RO A 1-2 NRC Examiner:

Oate: __ _ Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: The plant has been operating at 52% power for 6 weeks while maintenance is replacing the motor on the 'A' Main Feedwater Pump

Core burnup is 140 EFPO

RCS boron concentration is 1140 ppm

NO rods are believed to be immovable

/ untrippable

POWERTRAX is NOT available The CRS has directed you to complete OST -1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, "Manual SOM Calculation (Modes 1 and 2)" for current plant conditions.

NOTE: For this JPM assume independent verification has been performed.

20098 NRC Admin Exam RO A 1-2 Rev. 1 Appendix C Page 2 of 12 Worksheet Form ES-C-1 Task Standard:

OST-1036, Attachment 3, Manual SOM Calculation (Modes 1 and 2), completed with SOM of 5195 +/- 75 pcm (tolerance based on total of curves used and their division readability)

Required Materials:

Calculator General

References:

OST-1036, Shutdown Margin Calculation Modes 1-5 (Rev. 40) Curve Book (Cycle 16) Handouts:

Time Critical Task: Validation Time: Step 3 Step 6 Step 7 Step 9 OST-1036, Shutdown Margin Calculation Modes 1-5 (Rev. 40) No 20 minutes Critical Step Justification Must determine correct rod insertion limit based on curve value. The number of rod steps will be an input to the calculation.

Must determine correct power defect based on curve value. The power defect will provide one of the inputs to the calculation.

Must determine the correct rod worth based on curve value. The rod worth will provide one of the inputs to the calculation.

The total shutdown margin was the task that the CRS directed applicant to perform. 2009B NRC Admin Exam RO A1-2 Rev. 1 Appendix C Page 2 of 12 Worksheet Form ES-C-1 Task Standard:

OST-1036, Attachment 3, Manual SOM Calculation (Modes 1 and 2), completed with SOM of 5195 +/- 75 pcm (tolerance based on total of curves used and their division readability)

Required Materials:

Calculator General

References:

OST-1036, Shutdown Margin Calculation Modes 1-5 (Rev. 40) Curve Book (Cycle 16) Handouts:

Time Critical Task: Validation Time: Step 3 Step 6 Step 7 Step 9 OST-1036, Shutdown Margin Calculation Modes 1-5 (Rev. 40) No 20 minutes Critical Step Justification Must determine correct rod insertion limit based on curve value. The number of rod steps will be an input to the calculation.

Must determine correct power defect based on curve value.

The power defect will provide one of the inputs to the calculation.

Must determine the correct rod worth based on curve value. The rod worth will provide one of the inputs to the calculation.

The total shutdown margin was the task that the CRS directed applicant to perform. 2009B NRC Admin Exam RO A1-2 Rev. 1 Appendix C START TIME: Performance Step: 1 Standard:

Comment: Performance Step: 2 Standard:

Comment: ./ Performance Step: 3 Standard:

Comment: Performance Step: 4 Standard:

Comment: ./ -Denotes Critical Steps Page 3 of 12 PERFORMANCE INFORMATION OST-1036 Form ES-C-1 OBTAIN PROCEDURE (OST-1036 will be provided to allow candidates to write on, Curve Book will be included as a reference)

OST-1036, Section 7.3, Attachment 3, and Curve Book OST-1036 Attachment 3 Step 1 Enters Reactor Power Level Refers to given conditions and enters 52% CST -1036 Attachment 3 Step 2 Determine Rod Insertion Limit for power level Refers to Curve F-16-1 and determines TS limit for RIL to be 96 +/- 2 steps (tolerance based on curve division readability)

OST-1036 Attachment 3 Step 3 Enters core Burn Up Refers to given conditions and enters 140 EFPD 2009B NRC Admin Exam RO A 1-2 Rev. 1 Appendix C START TIME: Performance Step: 1 Standard:

Comment: Performance Step: 2 Standard:

Comment: ./ Performance Step: 3 Standard:

Comment: Performance Step: 4 Standard:

Comment: ./ -Denotes Critical Steps Page 3 of 12 PERFORMANCE INFORMATION OST-1036 Form ES-C-1 OBTAIN PROCEDURE (OST-1036 will be provided to allow candidates to write on, Curve Book will be included as a reference)

OST-1036, Section 7.3, Attachment 3, and Curve Book OST-1036 Attachment 3 Step 1 Enters Reactor Power Level Refers to given conditions and enters 52% CST -1036 Attachment 3 Step 2 Determine Rod Insertion Limit for power level Refers to Curve F-16-1 and determines TS limit for RIL to be 96 +/- 2 steps (tolerance based on curve division readability)

OST-1036 Attachment 3 Step 3 Enters core Burn Up Refers to given conditions and enters 140 EFPD 2009B NRC Admin Exam RO A 1-2 Rev. 1 Appendix C Performance Step: 5 Standard:

Comment: Evaluator Note: ./ Performance Step: 6 Standard:

Comment: ./ Performance Step: 7 Standard:

Comment: ./ -Denotes Critical Steps Page 4 of 12 PERFORMANCE INFORMATION OST-1036 Attachment 3 Step 4 Enters RCS Boron Concentration Refers to initial conditions and enters 1140 ppm Form ES-C-1 ATT 3, STEP 5 NOT PERFORMED SINCE VALUE IS INCLUDED AS PART OF ATTACHMENT.

OST-1036 Attachment 3 Step 6 Determines Power Defect for current power level Refers to Curve C-16-1 and determines power defect to be 1060 +/-50 pcm (tolerance based on curve division readability)

OST-1036 Attachment 3 Step 7 Determines Rod Worth for RIL position determined above Refers to Curve A-16-9 and determines rod worth to be 725 + 25 pcm (tolerance based on curve division readability) 2009B NRC Admin Exam RO A 1-2 Rev. 1 Appendix C Performance Step: 5 Standard:

Comment: Evaluator Note: ./ Performance Step: 6 Standard:

Comment: ./ Performance Step: 7 Standard:

Comment: ./ -Denotes Critical Steps Page 4 of 12 PERFORMANCE INFORMATION OST-1036 Attachment 3 Step 4 Enters RCS Boron Concentration Refers to initial conditions and enters 1140 ppm Form ES-C-1 ATT 3, STEP 5 NOT PERFORMED SINCE VALUE IS INCLUDED AS PART OF ATTACHMENT.

OST-1036 Attachment 3 Step 6 Determines Power Defect for current power level Refers to Curve C-16-1 and determines power defect to be 1060 +/-50 pcm (tolerance based on curve division readability)

OST-1036 Attachment 3 Step 7 Determines Rod Worth for RIL position determined above Refers to Curve A-16-9 and determines rod worth to be 725 + 25 pcm (tolerance based on curve division readability) 2009B NRC Admin Exam RO A 1-2 Rev. 1 Appendix C Performance Step: 8 Standard:

Comment: 0/ Performance Step: 9 Standard:

Comment: Page 5 of 12 PERFORMANCE INFORMATION OST-1036 Attachment 3 Step 8 Form ES-C-1 Enters worth of any additional immovable or untrippable rods Refers to given conditions and enters 0 OST-1036 Attachment 3 Step 9 Determines Total Shutdown Margin Determines Total Shutdown Margin to be 5195 +/- 75 pcm (tolerance based on total of all curves used and their division readability)

OST-1036 Section 7.3 Performance Step: 10 Signs off Section 7.3 steps Standard:

Signs off steps as complete Comment: Terminating Cue: STOP TIME: 0/ -Denotes Critical Steps When OST-1036, Attachment 3, Manual SOM Calculation is completed.

ENOOFJPM 2009B NRC Admin Exam RD A 1-2 Rev. 1 Appendix C Performance Step: 8 Standard:

Comment: 0/ Performance Step: 9 Standard:

Comment: Page 5 of 12 PERFORMANCE INFORMATION OST-1036 Attachment 3 Step 8 Form ES-C-1 Enters worth of any additional immovable or untrippable rods Refers to given conditions and enters 0 OST-1036 Attachment 3 Step 9 Determines Total Shutdown Margin Determines Total Shutdown Margin to be 5195 +/- 75 pcm (tolerance based on total of all curves used and their division readability)

OST-1036 Section 7.3 Performance Step: 10 Signs off Section 7.3 steps Standard:

Signs off steps as complete Comment: Terminating Cue: STOP TIME: 0/ -Denotes Critical Steps When OST-1036, Attachment 3, Manual SOM Calculation is completed.

ENOOFJPM 2009B NRC Admin Exam RD A 1-2 Rev. 1 Appendix C 1900 1800 1100 1600 1500 400 300 200 100 Page 6 of 12 PERFORMANCE INFORMATION KEY HARRIS UNIT 1 CYCLE 16 CRITICAL BORON CONCENTRATION

¥s. CYCLE EXPOSURE AT HFP. MO. EQU1UBR1UM XENON CONDmoNS 51!FPDlDIV eYe I.E EXPOSURE (EFPD) I Determination of Boron concentration for 140 EFPD CURVE NO.

REV NO.

ORIGINATOR DATE SUPERVISOR

....

__

....... DATE SUPSRINTENDENT SHIFT OPERATIONS DATE Form ES-C-1 ./ -Denotes Critical Steps 2009B NRC Admin Exam RO A1-2 Rev. 1 Appendix C 1900 1800 1100 1600 1500 400 300 200 100 Page 6 of 12 PERFORMANCE INFORMATION KEY HARRIS UNIT 1 CYCLE 16 CRITICAL BORON CONCENTRATION

¥s. CYCLE EXPOSURE AT HFP. MO. EQU1UBR1UM XENON CONDmoNS 51!FPDlDIV eYe I.E EXPOSURE (EFPD) I Determination of Boron concentration for 140 EFPD CURVE NO.

REV NO.

ORIGINATOR DATE SUPERVISOR DATE SUPSRINTENDENT SHIFT OPERATIONS DATE Form ES-C-1 ./ -Denotes Critical Steps 2009B NRC Admin Exam RO A1-2 Rev. 1 Appendix C 2 40 2 20 2 01) ,,: 1 '" 80 100.1 t L 6D ; / 11" 40 if' / 20 (0 1 nn Page 7 of 12 PERFORMANCE INFORMATION HARRIS UNIT 1 CYCLE 16 ROD INSERTION LIMITS (46 8,.2: t5) (l2.2 , r / / ,.' / , '1', ,. !'-'" << / '. / c/ * / V ,.,; l'f: ':' v: ... 9 V ".Iv 1/"" 1/ l/ / " / / ,,k ,/ Form ES-C-1 ('00,196)

(100,186) m . .. r \. ,. ... j'" E! AN KO 80 /. J /. V /'/ , 60 " / / 40 / L (0 1(1 / / 20 ,/ / lL. 1/ V (0,( 0 0 1Q 20 30 40 ! GO 70 30 90 1 PERCENT OF RATED THERMAL POWER CURVE NO, REYNO ORIGINATOR DATE

SUPERVISOR DATE ' " , SUPERINTENDEIU r SHIFT OPERATIONS DATE 'i .-:1 ./ -Denotes Critical Steps 2009B NRC Admin Exam RO A 1-2 Rev. 1 Appendix C 2 40 2 20 2 01) r: 80 t"lo I' 1 10.1 / / 6D , I /" 40 f ./ / (0 128 20 1 nn Page 7 of 12 PERFORMANCE INFORMATION HARRIS UNIT 1 CYCLE 16 ROD INSERTION LIMITS (46 8,.2 (l 2.2 22! :, 1/ V /' V , V ... ,. !'-'" B AN f<c V " / / j. / / ...: .,; y. ,.' / ./ :;..,; ;I / 1/ / I L / r L Form ES-C-1 ('00,196)

(100,186) ... r '\..' ;" 8 AN KI 80 J /,/ 'I' 60 /' "" 40 / / (0 1(1 /" / 20 1,1 / L. !/ / (0, lOG) 0 0 1Q 20 30 40 E GO 70 30 90 1 PERCENT OF RATED THERMAL POWER CURVE NO, REYNO ORIGINATOR , SUPERVISOR . \ I->;M. SUPERINTENDEIU r SHIFT OPERATIONS DATE 'i .. :1 ./ -Denotes Critical Steps 2009B NRC Admin Exam RO A 1-2 Rev. 1 Appendix C 2D P<:MiD1\f Page 8 of 12 PERFORMANCE INFORMATION KEY HARRIS UNIT 1 CYCLE 16 POWER DEFECT vs. POWER LEVEL for VARIOUS BORON CONCENTRATIONS BOL (0 :I EFPD 160) 20 40 80 POWER LEVEL (peRCENT)

CURVE NO, REV NO 0 ORIGINATOR DATE SUPERVISOR DATE SUPERJNTENIENT

-SHIFT OPERATIONS DATE Form ES-C-1 ./ -Denotes Critical Steps 2009B NRC Admin Exam RO A1-2 Rev. 1 Appendix C 2D P<:MiD1\f Page 8 of 12 PERFORMANCE INFORMATION KEY HARRIS UNIT 1 CYCLE 16 POWER DEFECT vs. POWER LEVEL for VARIOUS BORON CONCENTRATIONS BOL (0 :I EFPD 160) 20 40 80 POWER LEVEL (peRCENT)

CURVE NO, REV NO 0 ORIGINATOR DATE SUPERVISOR DATE SUPERJNTENIENT

-SHIFT OPERATIONS DATE Form ES-C-1 ./ -Denotes Critical Steps 2009B NRC Admin Exam RO A1-2 Rev. 1 Appendix C -1800

-1500 ,-1400 &1300 .... -1200 § e --1100 -1000 0 -900 0 .aoo ..J r2 -725 m I--600 ie .000 -400 -300 -zoo *100 :UPCtM)N 0 0 20 Page 9 of 12 PERFORMANCE INFORMATION KEY HARRIS UNIT 1 CYCLE 16 DIFFERENTIAL AND INTEGRAL ROD WORTH CONTROL BANKS D and C MOVING WITH 103 STEP OVERLAP SOL (0 EfPD S 160). HFP, SQUIUBRIUM XENON Form ES-C-1 *18 *17 *15 *14 40 60 96 80 120 140 160 180 200 220 240 $ STePlilDIV I) tt3 II BANKO 129

CURVE NO. ORIGINATOR SUPERVISOR SUPERlmEMDENT

-SHIFT OPERAilONS

./ -Denotes Critical Steps 2009B NRC Admin Exam RO A1-2 Rev. 1 Appendix C -1800

-1500 ,-1400 &1300 Page 9 of 12 PERFORMANCE INFORMATION KEY HARRIS UNIT 1 CYCLE 16 DIFFERENTIAL AND INTEGRAL ROD WORTH CONTROL BANKS D and C MOVING WITH 103 STEP OVERLAP SOL (0 EfPD S 160). HFP, SQUIUBRIUM XENON Form ES-C-1 *18 *17 *15 *14 40 60 96 80 120 140 160 180 200 220 240 tt3 BANKO CURVE NO. REV NO. SQ ORIGINATOR

___ DATE .. SUPERVISOR DATE SUPERlmEMDENT

-SHIFT OPERA.lIONS DA lE Cr ./ -Denotes Critical Steps 2009B NRC Admin Exam RO A1-2 Rev. 1 Appendix C Page 10 of 12 PERFORMANCE INFORMATION (SHADED AREA BELOW INDICATES DATA ALREADY PROVIDED)

Manual SDM Calculation (Modes 1 and 2) 1. Reactor power level. 2. Rod insertion limit for the above power level 96+/-2 steps on bank 3. Burn up (POWERTRAXIMCR Status Board). 4. Present RCS Boron Concentration NOTE: Use absolute values of numbers obtained from curves. Form ES-C-1 52 % D 140 EFPD 1140 ppm 5. Total worth of all control and shutdown banks, minus the worth of the most reactive rod for Fuel Cycle 16. 6. Cycle 16 Power defect for the power level recorded in Step 1. (Refer to Curves C-X-1 to C-X-3). Curve used C-16-1 NOTE: HFP curves are used for power levels of 10% or greater. 7. Inserted control rod worth at the rod insertion limit recorded in Step 2. (Refer to Curves A-X-6 to A-X-11) Curve used A-16-9 pcm ( a ) 1060 +/-50 pcm ( b ) 725 +/-25 pcm ( c ) 8. Worth of any additional immovable or untrippable rods (for each stuck rod, use the most reactive single rod worth (1129 pcm) or obtain individual withdrawn rod worth from the reactor engineer).

o pcm ( d ) 9. Determine the Total Shutdown Margin using the following formula: Total SDM C B = 6980 -1060 +/- 50 -725 +/- 25 -0 ( e ) ( a ) ./ -Denotes Critical Steps ( b ) (c) ( d ) 5195 +/- 75 pcm ( e) 2009B NRC Admin Exam RO A1-2 Rev. 1 Appendix C Page 10 of 12 PERFORMANCE INFORMATION Manual SDM Calculation (Modes 1 and 2) 1. Reactor power level. 2. Rod insertion limit for the above power level Form ES-C-1 52 % 96 +/- 2 steps on bank D 3. Burn up (POWERTRAXIMCR Status Board). 140 EFPD 4. Present RCS Boron Concentration 1140 ppm NOTE: Use absolute values of numbers obtained from curves. 5. Total worth of all control and shutdown banks, minus the worth of the most reactive rod for Fuel Cycle 16. 6. Cycle 16 Power defect for the power level recorded in Step 1. (Refer to Curves C-X-1 to C-X-3). Curve used C-16-1 NOTE: HFP curves are used for power levels of 10% or greater. 7. Inserted control rod worth at the rod insertion limit recorded in Step 2. (Refer to Curves A-X-6 to A-X-11) Curve used A-16-9 ( a ) 1060 +/-50 pcm ( b ) 725 +/-25 pcm ( c ) 8. Worth of any additional immovable or untrippable rods (for each stuck rod, use the most reactive single rod worth (1129 pcm) or obtain individual withdrawn rod worth from the reactor engineer).

o pcm ( d ) 9. Determine the Total Shutdown Margin using the following formula: Total SDM C B = 6980 -1060 +/- 50 -725 +/- 25 -0 ( e ) ( a ) ./ -Denotes Critical Steps ( b ) (c) ( d ) 5195 +/- 75 pcm ( e) 2009B NRC Admin Exam RO A1-2 Rev. 1 Appendix C Page 11 of 12 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC EXAM Admin JPM RO A 1-2 -Perform A Manual Shutdown Margin Calculation Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

2009B NRC Admin Exam RO A 1-2 Rev. 1 Appendix C Page 11 of 12 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC EXAM Admin JPM RO A 1-2 -Perform A Manual Shutdown Margin Calculation Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

2009B NRC Admin Exam RO A 1-2 Rev. 1 Appendix C Initial Conditions:

Initiating Cue: Page 12 of 12 JPM CUE SHEET Form ES-C-1 The plant has been operating at 52% power for 6 weeks while maintenance is replacing the motor on the 'A' Main Feedwater Pump

Core burnup is 140 EFPD

RCS boron concentration is 1140 ppm

NO rods are believed to be immovable

/ untrippable POWERTRAX is NOT available The CRS has directed you to complete OST-1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, "Manual SDM Calculation (Modes 1 and 2)" for current plant conditions.

NOTE: For this JPM assume independent verification has been performed.

2009B NRC Admin Exam RO A1-2 Rev. 1 Appendix C Initial Conditions:

Initiating Cue: Page 12 of 12 JPM CUE SHEET Form ES-C-1 The plant has been operating at 52% power for 6 weeks while maintenance is replacing the motor on the 'A' Main Feedwater Pump

Core burnup is 140 EFPD

RCS boron concentration is 1140 ppm

NO rods are believed to be immovable

/ untrippable POWERTRAX is NOT available The CRS has directed you to complete OST-1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, "Manual SDM Calculation (Modes 1 and 2)" for current plant conditions.

NOTE: For this JPM assume independent verification has been performed.

2009B NRC Admin Exam RO A1-2 Rev. 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Shearon Harris Page 1 of 12 Worksheet Perform OP-111 , Attachment 3 -Low Head SI Standby Lineup Checklist G2.2.15 RO 3.9 SRO 4.3 Form ES-C-1 Task No.: 005016H101 JPM No.: 2009B NRC Exam Admin JPM RO A2 NRC Examiner:

Date: __ _ Simulated Performance:

Actual Performance:

X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: A plant heatup is in progress lAW GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3 OP-111 RESIDUAL HEAT REMOVAL SYSTEM, Section 7.2-Restoring the RHR System to ECCS Mode, has just been completed.

You are the BOP and the CRS has assigned to perform the independent verification on OP-111, Attachment 3 -Low Head SI Standby Lineup Checklist, for the control room operated valves. An AO is checking the local equipment.

2009B NRC RO Admin Exam JPM RO A2 Rev. 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Shearon Harris Page 1 of 12 Worksheet Perform OP-111 , Attachment 3 -Low Head SI Standby Lineup Checklist G2.2.15 RO 3.9 SRO 4.3 Form ES-C-1 Task No.: 005016H101 JPM No.: 2009B NRC Exam Admin JPM RO A2 NRC Examiner:

Date: __ _ Simulated Performance:

Actual Performance:

X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: A plant heatup is in progress lAW GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3 OP-111 RESIDUAL HEAT REMOVAL SYSTEM, Section 7.2-Restoring the RHR System to ECCS Mode, has just been completed.

You are the BOP and the CRS has assigned to perform the independent verification on OP-111, Attachment 3 -Low Head SI Standby Lineup Checklist, for the control room operated valves. An AO is checking the local equipment.

2009B NRC RO Admin Exam JPM RO A2 Rev. 1 Appendix C Page 2 of 12 Worksheet Form ES-C-1 Task Standard:

All errors identified.

Required Materials:

OP-111, Attachment 3, with CHECK column initialed except for the local valves. General

References:

OP-111 (Rev. 44) Time Critical Task: Validation Time: Step 2 Step 3 Step 4 Step 5 Step 6 No 10 minutes Critical Step Justification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification 2009B NRC RO Admin Exam JPM RO A2 Rev. 1 Appendix C Page 2 of 12 Worksheet Form ES-C-1 Task Standard:

All errors identified.

Required Materials:

OP-111, Attachment 3, with CHECK column initialed except for the local valves. General

References:

OP-111 (Rev. 44) Time Critical Task: Validation Time: Step 2 Step 3 Step 4 Step 5 Step 6 No 10 minutes Critical Step Justification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification 2009B NRC RO Admin Exam JPM RO A2 Rev. 1 Appendix C Page 3 of 12 Worksheet 20098 NRC Exam -SIMULATOR SETUP Simulator Operator

Reset to IC-170 (Password 9newguys)

Silence and Acknowledge annunciators Form ES-C-1 GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.) To recreate the conditions of this JPM:

Initial Simulator IC-16 (Mode 4 with RHR aligned for ECCS)

Place 1 RH-30, RHR HEAT XCHG A OUT FLOW CONT to "0%" open on controller

Place 1 SI-322, SA RWST TO RHR PUMP A-SA to SHUT (closed indication)

Leave control power ON for 1 SI-341 S8

Place 1CC-167, CCW FROM RHR HEAT EXCHANGER 8-S8 to OPEN

Place 1CC-147, CCW FROM RHR HEAT EXCHANGER A-SA to OPEN

Silence Acknowledge and Reset Annunciators

Freeze and Snap these conditions for future use 20098 NRC RO Admin Exam JPM RO A2 Rev. 1 Appendix C Page 3 of 12 Worksheet 20098 NRC Exam -SIMULATOR SETUP Simulator Operator

Reset to IC-170 (Password 9newguys)

Silence and Acknowledge annunciators Form ES-C-1 GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.) To recreate the conditions of this JPM:

Initial Simulator IC-16 (Mode 4 with RHR aligned for ECCS)

Place 1 RH-30, RHR HEAT XCHG A OUT FLOW CONT to "0%" open on controller

Place 1 SI-322, SA RWST TO RHR PUMP A-SA to SHUT (closed indication)

Leave control power ON for 1 SI-341 S8

Place 1CC-167, CCW FROM RHR HEAT EXCHANGER 8-S8 to OPEN

Place 1CC-147, CCW FROM RHR HEAT EXCHANGER A-SA to OPEN

Silence Acknowledge and Reset Annunciators

Freeze and Snap these conditions for future use 20098 NRC RO Admin Exam JPM RO A2 Rev. 1 Appendix C START TIME: Performance Step: 1 Standard:

Evaluator Cue: Evaluator Note: Comment: " Performance Step: 2 Standard:

Evaluator Cue: Comment: ./ -Denotes Critical Steps Page 4 of 12 PERFORMANCE INFORMATION OP-111 Attachment 3 Obtain procedure.

Form ES-C-1 Fills out applicable sections of Sheet 1 of 4 and reviews Attachment.

Provide OP-111, Attachment

3. The Attachment can be performed in any order. The following valves/controls are out of position.

All others are correctly positioned.

OP-111 Attachment 3 continued Locates and compares actual position to required position lAW Attachment

3.

1 RH-30, RHR XCHG A OUT FLOW CO NT -(OPEN) Determines 1 RH-30 is SHUT (0% demand) and notes position condition in REMARKS section. As CRS: Throughout the JPM, acknowledge any verbal communications.

Instruct them to document mis-positioned controls/valves but continue performing the Attachment without re-aligning any equipment.

2009B NRC Admin Exam JPM RO A2 Rev. 1 Appendix C START TIME: Performance Step: 1 Standard:

Evaluator Cue: Evaluator Note: Comment: " Performance Step: 2 Standard:

Evaluator Cue: Comment: ./ -Denotes Critical Steps Page 4 of 12 PERFORMANCE INFORMATION OP-111 Attachment 3 Obtain procedure.

Form ES-C-1 Fills out applicable sections of Sheet 1 of 4 and reviews Attachment.

Provide OP-111, Attachment

3. The Attachment can be performed in any order. The following valves/controls are out of position.

All others are correctly positioned.

OP-111 Attachment 3 continued Locates and compares actual position to required position lAW Attachment

3.

1 RH-30, RHR XCHG A OUT FLOW CO NT -(OPEN) Determines 1 RH-30 is SHUT (0% demand) and notes position condition in REMARKS section. As CRS: Throughout the JPM, acknowledge any verbal communications.

Instruct them to document mis-positioned controls/valves but continue performing the Attachment without re-aligning any equipment.

2009B NRC Admin Exam JPM RO A2 Rev. 1 Appendix C ,j Performance Step: 3 Standard:

Comment: ,j Performance Step: 4 Standard:

Comment: ,j Performance Step: 5 Standard:

Comment: ./ -Denotes Critical Steps Page 5 ot 12 PERFORMANCE INFORMATION OP-111 Attachment 3 continued Form ES-C-1 Locates and compares actual position to required position lAW Attachment

3.

1 SI-341 SB LOW HEAD SI TRAIN B TO COLD LEG CO NT PWR & VLV POS (OFF) Determines 1 SI-341 SB is not OFF and notes out-ot-position condition in REMARKS section. OP-111 Attachment 3 continued Locates and compares actual position to required position lAW Attachment

3.

1 SI-322 SA, RWST TO RHR PUMP A-SA (OPEN) Determines 1SI-322 SA is not OPEN and notes out-ot-position condition in REMARKS section. OP-111 Attachment 3 continued Locates and compares actual position to required position lAW Attachment

3.

1CC-147, CCW FROM RHR HEAT EXCHANGER A-SA Determines 1CC-147 is not SHUT and notes out-ot-position condition in REMARKS section. 2009B NRC Admin Exam JPM RO A2 Rev. 1 Appendix C ,j Performance Step: 3 Standard:

Comment: ,j Performance Step: 4 Standard:

Comment: ,j Performance Step: 5 Standard:

Comment: ./ -Denotes Critical Steps Page 5 ot 12 PERFORMANCE INFORMATION OP-111 Attachment 3 continued Form ES-C-1 Locates and compares actual position to required position lAW Attachment

3.

1 SI-341 SB LOW HEAD SI TRAIN B TO COLD LEG CO NT PWR & VLV POS (OFF) Determines 1 SI-341 SB is not OFF and notes out-ot-position condition in REMARKS section. OP-111 Attachment 3 continued Locates and compares actual position to required position lAW Attachment

3.

1 SI-322 SA, RWST TO RHR PUMP A-SA (OPEN) Determines 1SI-322 SA is not OPEN and notes out-ot-position condition in REMARKS section. OP-111 Attachment 3 continued Locates and compares actual position to required position lAW Attachment

3.

1CC-147, CCW FROM RHR HEAT EXCHANGER A-SA Determines 1CC-147 is not SHUT and notes out-ot-position condition in REMARKS section. 2009B NRC Admin Exam JPM RO A2 Rev. 1 Appendix C --J Performance Step: 6 Standard:

Comment: Performance Step: 7 Standard:

Evaluator Cue: Comment: Terminating Cue: STOP TIME: ./ -Denotes Critical Steps Page 60t 12 PERFORMANCE INFORMATION OP-111 Attachment 3 continued Form ES-C-1 Locates and compares actual position to required position lAW Attachment

3.

1CC-167, CCW FROM RHR HEAT EXCHANGER B-SB Determines 1CC-167 is not SHUT and notes out-ot-position condition in REMARKS section. OP-111 Attachment 3 continued Provide Attachment to CRS. Completes Att. 3, Sheet 1 ot 4 and provides Attachment to CRS. Acknowledge any verbal report. When the applicable section of the Attachment has been returned to the CRS. ENDOFJPM 2009B NRC Admin Exam JPM RO A2 Rev. 1 Appendix C --J Performance Step: 6 Standard:

Comment: Performance Step: 7 Standard:

Evaluator Cue: Comment: Terminating Cue: STOP TIME: ./ -Denotes Critical Steps Page 60t 12 PERFORMANCE INFORMATION OP-111 Attachment 3 continued Form ES-C-1 Locates and compares actual position to required position lAW Attachment

3.

1CC-167, CCW FROM RHR HEAT EXCHANGER B-SB Determines 1CC-167 is not SHUT and notes out-ot-position condition in REMARKS section. OP-111 Attachment 3 continued Provide Attachment to CRS. Completes Att. 3, Sheet 1 ot 4 and provides Attachment to CRS. Acknowledge any verbal report. When the applicable section of the Attachment has been returned to the CRS. ENDOFJPM 2009B NRC Admin Exam JPM RO A2 Rev. 1 Appendix C Page 7 of 12 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM RO A2 -Perform OP-111, Attachment 3 -Low Head SI Standby Lineup Checklist Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

2009B NRC Admin Exam JPM RO A2 Rev. 1 Appendix C Page 7 of 12 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM RO A2 -Perform OP-111, Attachment 3 -Low Head SI Standby Lineup Checklist Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ------------------------------

2009B NRC Admin Exam JPM RO A2 Rev. 1 Appendix C Initial Conditions:

Initiating Cue: Page 8 of 12 JPM CUE SHEET Form ES-C-1 A plant heatup is in progress lAW GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3 OP-111 RESIDUAL HEAT REMOVAL SYSTEM, Section 7.2-Restoring the RHR System to ECCS Mode, has just been completed.

You are the BOP and the CRS has assigned to perform the independent verification on OP-111, Attachment 3 -Low Head SI Standby Lineup Checklist, for the control room operated valves. An AO is checking the local equipment.

2009B NRC Exam Admin JPM RO A2 Rev. 1 Appendix C Initial Conditions:

Initiating Cue: Page 8 of 12 JPM CUE SHEET Form ES-C-1 A plant heatup is in progress lAW GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3 OP-111 RESIDUAL HEAT REMOVAL SYSTEM, Section 7.2-Restoring the RHR System to ECCS Mode, has just been completed.

You are the BOP and the CRS has assigned to perform the independent verification on OP-111, Attachment 3 -Low Head SI Standby Lineup Checklist, for the control room operated valves. An AO is checking the local equipment.

2009B NRC Exam Admin JPM RO A2 Rev. 1 Appendix C Page 9 of 12 JPM CUE SHEET Form ES-C-1 Attachment 3 -Low Head Safety Injection Standby Lineup Checklist Sheet 1 of4 Person(s)

Performing Checklist Initials Name (Print)

Initials Name (Print) TR Terry Right Remarks -Indicate any component not in the prescribed position.

Checklist Started Checklist Completed Approved by UnitSCQ Time 0(;00 Time Date TODAY Date ______ __ Date ----After receiving the final review signature, this OP Attachment becomes a QA RECORD. IOP-111 Rev. 44 Page 142 of 1531 2009B NRC Exam Admin JPM RO A2 Rev. 1 Appendix C Page 9 of 12 JPM CUE SHEET Form ES-C-1 Attachment 3 -Low Head Safety Injection Standby Lineup Checklist Sheet 1 of4 Person(s)

Performing Checklist Initials Name (Print) Initials Name (Print) TR Terry Right Remarks -Indicate any component not in the prescribed position.

Checklist Started Checklist Completed Approved by UnitSCQ Time 0(;00 Time Date TODAY Date ___ _ Date ___ _ After receiving the final review signature, this OP Attachment becomes a QA RECORD. IOP-111 Rev. 44 Page 142 of 1531 2009B NRC Exam Admin JPM RO A2 Rev. 1 Appendix C Page 10 of 12 JPM CUE SHEET Form ES-C-1 Attachment 3 -low Head Safety Injection Standby Uneup Checklist Sheet2of4 COMPONENT NUMBER COMPONENT DESCRIPTION POSmON CHECK VERIFY 1RH-1 RCS lOOP A TO RHR PUMP A-SA Shut TR 1RH-2 RCS lOOP A TO RHR PUMP A-SA Shut TR 1RH-39 RCS lOOP C TO RHR PUMP B-SB Shut TR 1RH-40 RCSlOOPCTO RHRPUMP B-SB Shut TR 1RH-30 RHR HEAT XCHG A OUT flOW CONT Open TR 1RH-66 RHR HEAT XCHG B OUT FLOW CONT (HC-603B1)

Open TR 1RH-20 RHR HEAT XCHG A BVP FLOW CaNT Manual & Shut TR 1RH-58 RHR HEAT XCHG B BVP FLOW CaNT Manual & Shut TR 1RH-26 '"' RHR Header A to eves letdown lsol locked Shut TR Vlv 1RH-64 '"' RHR Header B to eves Letdown lsol Vlv locked Shut TR 1RH-31 RHR PUMP A-SA MINI FLOW Opeo TR 1RH-69 RHR PUMP B-SB MINI FLOW Opeo TR 1CS-28 RHR LETDOWN (HC-1421)

Shut TR 1CC-146 ** RHR HX A OuOet Throttle Valve Locked TR Throttled 1CC-147 CCW FROM RHR HEAT EXCHANGER Shut TR A-SA .. This is a local valve operated in the body of the procedure . ** Throttled

= should be as recorded in the last OST-1216.

This ensures the required flow for E CSfunction.

IOP-111 Rev. 44 Page 143 of 1531 2009B NRC Exam Admin JPM RO A2 Rev. 1 Appendix C Page 10 of 12 JPM CUE SHEET Form ES-C-1 Attachment 3 -low Head Safety Injection Standby Uneup Checklist Sheet2of4 COMPONENT NUMBER COMPONENT DESCRIPTION POSmON CHECK VERIFY 1RH-1 RCS lOOP A TO RHR PUMP A-SA Shut TR 1RH-2 RCS lOOP A TO RHR PUMP A-SA Shut TR 1RH-39 RCS lOOP C TO RHR PUMP B-SB Shut TR 1RH-40 RCSlOOPCTO RHRPUMP B-SB Shut TR 1RH-30 RHR HEAT XCHG A OUT flOW CONT Open TR 1RH-66 RHR HEAT XCHG B OUT FLOW CONT (HC-603B1)

Open TR 1RH-20 RHR HEAT XCHG A BVP FLOW CaNT Manual & Shut TR 1RH-58 RHR HEAT XCHG B BVP FLOW CaNT Manual & Shut TR 1RH-26 '"' RHR Header A to eves letdown lsol locked Shut TR Vlv 1RH-64 '"' RHR Header B to eves Letdown lsol Vlv locked Shut TR 1RH-31 RHR PUMP A-SA MINI FLOW Opeo TR 1RH-69 RHR PUMP B-SB MINI FLOW Opeo TR 1CS-28 RHR LETDOWN (HC-1421)

Shut TR 1CC-146 ** RHR HX A OuOet Throttle Valve Locked TR Throttled 1CC-147 CCW FROM RHR HEAT EXCHANGER Shut TR A-SA .. This is a local valve operated in the body of the procedure . ** Throttled

= should be as recorded in the last OST-1216.

This ensures the required flow for E CSfunction.

IOP-111 Rev. 44 Page 143 of 1531 2009B NRC Exam Admin JPM RO A2 Rev. 1 Appendix C Page 11 of 12 JPM CUE SHEET Attachment 3 -Low Head Safety Injection Standby Uneup Checklist Sheet3of4 Form ES-C-1 COMPONENT NUMBER COMPONENT DESCRIPTION POsmON CHECK VERIFY 1CC-166-RHR HX B Oullet Throttle Vatve Locked TR Throttled 1CC-167 CCW FROM RHR HEAT EXCHANGER Shut TR B-SB 1SI-340SA LOW HEAD 51lRAlN A TO COLD LEG Open & Pull TR to Lock 1SI-340SA LOW HEAD SI TRAIN A TO COLD LEG Off TR CONT PWR & Vl V POS 1SI-341 SB LOW HEAD SI TRAIN B TO COLD LEG TR to Lock 1SI-341 SB LOW HEAD 51 TRAIN B TO COLD LEG Off TR CONT PWR & VlV pas 1SI-326SA LOW HEAD SI TRAIN A TO HOT LEG Open TR CROSSOVER 1SI-327SB LOW HEAD 51 TRAIN B TO HOT LEG Open TR CROSSOVER 1SI-322SA RWST TO RHR PUMP A-SA Open TR 1SI-323SB RWST TO RHR PUMP B-SB Open TR -Throttled position should be as recorded in the last 05T-1216.

This ensures the required flow for ECCS function.

IOP-111 Rev. 44 Page 144 of 153 I 2009B NRC Exam Admin JPM RO A2 Rev. 1 Appendix C Page 11 of 12 JPM CUE SHEET Attachment 3 -Low Head Safety Injection Standby Uneup Checklist Sheet3of4 Form ES-C-1 COMPONENT NUMBER COMPONENT DESCRIPTION POsmON CHECK VERIFY 1CC-166-RHR HX B Oullet Throttle Vatve Locked TR Throttled 1CC-167 CCW FROM RHR HEAT EXCHANGER Shut TR B-SB 1SI-340SA LOW HEAD 51lRAlN A TO COLD LEG Open & Pull TR to Lock 1SI-340SA LOW HEAD SI TRAIN A TO COLD LEG Off TR CONT PWR & Vl V POS 1SI-341 SB LOW HEAD SI TRAIN B TO COLD LEG TR to Lock 1SI-341 SB LOW HEAD 51 TRAIN B TO COLD LEG Off TR CONT PWR & VlV pas 1SI-326SA LOW HEAD SI TRAIN A TO HOT LEG Open TR CROSSOVER 1SI-327SB LOW HEAD 51 TRAIN B TO HOT LEG Open TR CROSSOVER 1SI-322SA RWST TO RHR PUMP A-SA Open TR 1SI-323SB RWST TO RHR PUMP B-SB Open TR -Throttled position should be as recorded in the last 05T-1216.

This ensures the required flow for ECCS function.

IOP-111 Rev. 44 Page 144 of 153 I 2009B NRC Exam Admin JPM RO A2 Rev. 1 Appendix C Page 12 of 12 JPM CUE SHEET Form ES-C-1 Attachment 3 -Low Head Safety Injection Standby Uneup Checklist Sheet4of4 COMPONENT NUMBER COMPONENT DESCRIPTION POSmON CHECK VERIFY 480V MCC-1A21-SA 1A21-SA-7B RCS A to RHR Pump 1A-SA Locked Off TR (1RH-2) oth Bkrs) Locked Off TR 1A21-SA-8A RCS C to RHR PUfll> 1B-SB Locked Off TR (1 RH4O) (Both Bkrs) Locked Off TR 4tlUV MGG-1tl21-S1:i 1B21-SB-5B RCS RHR Pump 1A-SA (1RH-1) Bkrs) Locked Off TR Locked Off TR 1 B21-SB-11A RCS C to RHR PUrIll1B-SB Locked Off TR (1RH-39J (Both Bkrs) Locked Off TR 1 OP-111 Rev. 44 Page 145 of 1531 2009B NRC Exam Admin JPM RO A2 Rev. 1 Appendix C Page 12 of 12 JPM CUE SHEET Form ES-C-1 Attachment 3 -Low Head Safety Injection Standby Uneup Checklist Sheet4of4 COMPONENT NUMBER COMPONENT DESCRIPTION POSmON CHECK VERIFY 480V MCC-1A21-SA 1A21-SA-7B RCS A to RHR Pump 1A-SA Locked Off TR (1RH-2) oth Bkrs) Locked Off TR 1A21-SA-8A RCS C to RHR PUfll> 1B-SB Locked Off TR (1 RH4O) (Both Bkrs) Locked Off TR 4tlUV MGG-1tl21-S1:i 1B21-SB-5B RCS RHR Pump 1A-SA (1RH-1) Bkrs) Locked Off TR Locked Off TR 1 B21-SB-11A RCS C to RHR PUrIll1B-SB Locked Off TR (1RH-39J (Both Bkrs) Locked Off TR 1 OP-111 Rev. 44 Page 145 of 1531 2009B NRC Exam Admin JPM RO A2 Rev. 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Shearon Harris Page 1 of 8 Worksheet Form ES-C-1 Task No.: Using survey maps determine stay JPM No.: 20098 NRC Exam times Admin JPM RD A-3 G.2.3.4 RO 3.2 SRO 3.7 NRC Examiner:

Date: __ _ Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant 20098 NRC Exam Admin JPM ROA3 Rev. 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Shearon Harris Page 1 of 8 Worksheet Form ES-C-1 Task No.: Using survey maps determine stay JPM No.: 20098 NRC Exam times Admin JPM RD A-3 G.2.3.4 RO 3.2 SRO 3.7 NRC Examiner:

Date: __ _ Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant 20098 NRC Exam Admin JPM ROA3 Rev. 1 Appendix C Page 2 of 8 Worksheet Form ES-C-1 READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Pump. The clearance includes the following valves:

1ED-12

1ED-13

1 ED-14

1 ED-15

1 ED-17

1 ED-18 Two Operators are being assigned to hang a clearance and perform work in a radiological area. Operator 1 has an accumulated annual Whole Body dose of 1760 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Saint Lucie earlier this year where he has accumulated 2700 mrem. The clearance and work activity is for the 'A' ED Tank Transfer Pump. Using the supplied survey map, determine the allowable individual stay times for each Operator that would prevent exceeding the annual administrative dose limit while performing these activities.

Calculations should be based on Progress Energy Administrative Dose Limits. Do not consider RWP Administrative Limits. Any required dose extensions have been processed and approved with the exception of any dose extensions requiring the Superintendent

-Radiation Protection approval.

Do not consider dose received during transit. The calculated dose should be ONLY what they would receive while working at the valves for the clearance.

Complete the information below and return to the evaluator when complete.

2009B NRC Exam Admin JPM ROA3 Rev. 1 Appendix C Page 2 of 8 Worksheet Form ES-C-1 READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Pump. The clearance includes the following valves:

1ED-12

1ED-13

1 ED-14

1 ED-15

1 ED-17

1 ED-18 Two Operators are being assigned to hang a clearance and perform work in a radiological area. Operator 1 has an accumulated annual Whole Body dose of 1760 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Saint Lucie earlier this year where he has accumulated 2700 mrem. The clearance and work activity is for the 'A' ED Tank Transfer Pump. Using the supplied survey map, determine the allowable individual stay times for each Operator that would prevent exceeding the annual administrative dose limit while performing these activities.

Calculations should be based on Progress Energy Administrative Dose Limits. Do not consider RWP Administrative Limits. Any required dose extensions have been processed and approved with the exception of any dose extensions requiring the Superintendent

-Radiation Protection approval.

Do not consider dose received during transit. The calculated dose should be ONLY what they would receive while working at the valves for the clearance.

Complete the information below and return to the evaluator when complete.

2009B NRC Exam Admin JPM ROA3 Rev. 1 Appendix C Page 3 of 8 Worksheet Form ES-C-1 Task Standard:

Calculation of stay times based on survey maps, two hours for Operator 1, five hours for Operator 2. Required Materials:

Survey map A4 RAB 190' North Valve MAP 2 SFD-5-S-0684 General

References:

DOS-NGGC-0004 (Rev. 10) Time Critical Task: Validation Time: Step 1 Step 2 Step 3 DOS-NGGC-0004 "Progress Energy Annual Administrative Dose Limits" Section 9.3.1 LIMIT = 2 rem Progress Energy dose not to exceed 4 rem total dose if non-Progress Energy dose for the current year has been determined.

No 12 minutes Critical Task Justification Must determine dose rates in order to calculate stay time Must determine available dose to determine stay time. Calculation of stay time. 2009B NRC Exam Admin JPM ROA3 Rev. 1 Appendix C Page 3 of 8 Worksheet Form ES-C-1 Task Standard:

Calculation of stay times based on survey maps, two hours for Operator 1, five hours for Operator 2. Required Materials:

Survey map A4 RAB 190' North Valve MAP 2 SFD-5-S-0684 General

References:

DOS-NGGC-0004 (Rev. 10) Time Critical Task: Validation Time: Step 1 Step 2 Step 3 DOS-NGGC-0004 "Progress Energy Annual Administrative Dose Limits" Section 9.3.1 LIMIT = 2 rem Progress Energy dose not to exceed 4 rem total dose if non-Progress Energy dose for the current year has been determined.

No 12 minutes Critical Task Justification Must determine dose rates in order to calculate stay time Must determine available dose to determine stay time. Calculation of stay time. 2009B NRC Exam Admin JPM ROA3 Rev. 1 Appendix C START TIME: Evaluator Note: ./ Performance Step: 1 Standard:

Comment: ./ Performance Step: 2 Standard:

Comment: ./ -Denotes Critical Steps Page 4 of 8 PERFORMANCE INFORMATION The order of performance does not matter Form ES-C-1 IF THE APPLICANT ASKS FOR IT: Provide a copy of NGGC-0004, Rev. 10 Using Radiological Survey Record Map A4 and RAB 190' North map, determines dose rates in the area where the clearance will be applied Identifies that General Area Dose Rates are 120 mrem/hr Determine the remaining dose for the year for each individual Operator 1: 240 mrem (2000 mrem -1760 mrem = 240 mrem Operator 2: 600 mrem 4000 mrem -700 mrem (PE) -2700 mrem (SL) = 600 mrem 2009B NRC Exam Admin JPM RO A3 Rev. 1 Appendix C START TIME: Evaluator Note: ./ Performance Step: 1 Standard:

Comment: ./ Performance Step: 2 Standard:

Comment: ./ -Denotes Critical Steps Page 4 of 8 PERFORMANCE INFORMATION The order of performance does not matter Form ES-C-1 IF THE APPLICANT ASKS FOR IT: Provide a copy of NGGC-0004, Rev. 10 Using Radiological Survey Record Map A4 and RAB 190' North map, determines dose rates in the area where the clearance will be applied Identifies that General Area Dose Rates are 120 mrem/hr Determine the remaining dose for the year for each individual Operator 1: 240 mrem (2000 mrem -1760 mrem = 240 mrem Operator 2: 600 mrem 4000 mrem -700 mrem (PE) -2700 mrem (SL) = 600 mrem 2009B NRC Exam Admin JPM RO A3 Rev. 1 Appendix C ./ Performance Step: 3 Standard:

Comment: Terminating Cue: STOP TIME: ../ -Denotes Critical Steps Page 5 of 8 PERFORMANCE INFORMATION Form ES-C-1 Determine stay time for each operator (based on 1 st Operator reaching 2 mrem and the 2nd Operator reaching 4 mrem -for the year) Operator 1: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 240 mrem + 120mrem/hr

= 2 hrs Operator 2: 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 600 mrem + 120 mrem/hr = 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months After the stay time has been calculated, this JPM is complete ENDOFJPM 2009B NRC Exam Admin JPM RO A3 Rev. 1 Appendix C ./ Performance Step: 3 Standard:

Comment: Terminating Cue: STOP TIME: ../ -Denotes Critical Steps Page 5 of 8 PERFORMANCE INFORMATION Form ES-C-1 Determine stay time for each operator (based on 1 st Operator reaching 2 mrem and the 2nd Operator reaching 4 mrem -for the year) Operator 1: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 240 mrem + 120mrem/hr

= 2 hrs Operator 2: 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 600 mrem + 120 mrem/hr = 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months After the stay time has been calculated, this JPM is complete ENDOFJPM 2009B NRC Exam Admin JPM RO A3 Rev. 1 Appendix C Page 6 of 8 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM RO A-3 -Using survey maps determine stay times. (DOS-NGGC-0004 Rev. 10) Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

DOS-NGGC-0004 "Progress Energy Annual Administrative Dose Limits" Section 9.3.1 LIMIT = 2 rem Progress Energy dose not to exceed 4 rem total dose if non-Progress Energy dose for the current year has been determined.

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

2009B NRC Exam Admin JPM RO A3 Rev. 1 Appendix C Page 6 of 8 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM RO A-3 -Using survey maps determine stay times. (DOS-NGGC-0004 Rev. 10) Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

DOS-NGGC-0004 "Progress Energy Annual Administrative Dose Limits" Section 9.3.1 LIMIT = 2 rem Progress Energy dose not to exceed 4 rem total dose if non-Progress Energy dose for the current year has been determined.

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------------------------------------------

2009B NRC Exam Admin JPM RO A3 Rev. 1 Appendix C Initial Conditions:

INITIATING CUE: Page 7 of 8 JPM CUE SHEET Form ES-C-1 Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Pump. The clearance includes the following valves:

1 ED-12

1 ED-13

1 ED-14

1ED-15

1ED-17

1ED-18 Two Operators are being assigned to hang a clearance and perform work in a radiological area. Operator 1 has an accumulated annual Whole Body dose of 1760 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Saint Lucie earlier this year where he has accumulated 2700 mrem. The clearance and work activity is for the 'A' ED Tank Transfer Pump. Using the supplied survey map, determine the allowable individual stay times for each Operator that would prevent exceeding the annual administrative dose limit while performing these activities.

Calculations should be based on Progress Energy Administrative Dose Limits. Do not consider RWP Administrative Limits. Any required dose extensions have been processed and approved with the exception of any dose extensions requiring the Superintendent

-Radiation Protection approval.

Do not consider dose received during transit. The calculated dose should be ONLY what they would receive while working at the valves for the clearance.

Complete the information below and return to the evaluator when complete.

Name ____________________________________

_ Record the maximum allowable stay time calculations below to the nearest hour and minute. Operator 1: _____________________

Operator 2: 2009B NRC Exam Admin JPM RO A3 Rev. 1 Appendix C Initial Conditions:

INITIATING CUE: Page 7 of 8 JPM CUE SHEET Form ES-C-1 Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Pump. The clearance includes the following valves:

1 ED-12

1 ED-13

1 ED-14

1ED-15

1ED-17

1ED-18 Two Operators are being assigned to hang a clearance and perform work in a radiological area. Operator 1 has an accumulated annual Whole Body dose of 1760 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Saint Lucie earlier this year where he has accumulated 2700 mrem. The clearance and work activity is for the 'A' ED Tank Transfer Pump. Using the supplied survey map, determine the allowable individual stay times for each Operator that would prevent exceeding the annual administrative dose limit while performing these activities.

Calculations should be based on Progress Energy Administrative Dose Limits. Do not consider RWP Administrative Limits. Any required dose extensions have been processed and approved with the exception of any dose extensions requiring the Superintendent

-Radiation Protection approval.

Do not consider dose received during transit. The calculated dose should be ONLY what they would receive while working at the valves for the clearance.

Complete the information below and return to the evaluator when complete.

Name ____________________________________

_ Record the maximum allowable stay time calculations below to the nearest hour and minute. Operator 1: ____________________

Operator 2: 2009B NRC Exam Admin JPM RO A3 Rev. 1 I\) o o CD OJ Z JJ () m 3 6: 3 5' c.. "U :s:: JJ o JJ CD ..... MapM Unit I I Sidg/Cleo:

RAB 190'N I Al\l;li; 1f/30/eFt I Tin);;; CCC 1 ptWF#1,l38 CWltJ1'Qtt(!I\t:

NLA W"orkDCSCflpiion!

broio XfIlH" 1?ur"l p. C\:::Qronce SlIl'VC}'OJ!

J.

Sl!:illature:

J. Btu.V'o..

IRlwlew\1dby:

r. 2vl0 ICl:0tlJe.vd d t. .;,(:5 b I >> I ' 1_ / fL.,.,.", '11. i[" L,'." ..... ,." ......

"c..,'

/' ! 1\¥1 X / v'-.. ,.,.(..6 jJ Beta Dose

.. --, % hJWt)t' .. """=='""""!

Jnstnuncnt HRA H4l!t it<Jdiatillfl Areu 11 N Dose: RIIte LI,jR,A Mi:'<1 . R Rcmlh(ouf VHRA Vr:rv High Ramntilm Area XXXX B6undary ARA AirDume Radlnlion Area 0 Suwar LocalllJoll CA Cot'lulminlltinll Afi!tl b Atf SalnJ)le Locatiuu Air Activity No'/UTC 776¥¥O 77(.;1.1.3 NU., __ DAC_, ___ %. tl.ll utL! .. ,. No, OAt %

... .c:::::;:*-----;--I AdlVit)' RMA Maleriuls Nell K toOO lJose Ralell in tnrCwl1r nnje!>s otherwise noted QARb:ord c.. "U >> "0 "0 CD :::l Co x' () :s:: "U C CD m OJ enS. I OJ m " o 3 m en o I ..... I\) o o CD OJ Z JJ () m 3 6: 3 5' c.. "U :s:: JJ o JJ CD MapM Unit I Sidg/Cleo:

RAB 190' N CWltj1'Qtt(!I\t:

NLA """oft DCSCflpiion!

u i SlIl'VC}'OJ!

J. Sl!:illature:

J. Btu.V'o., QARb:ord Tin);;; CCC 1 RWFH1,l38 AkActiYJly

---+--. -. -.-------

.. ----Jnstnuncnt No'/UTC 776¥¥O >> '0 '0 CD :::l Co x' () " o 3 m U> o I ....

Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Shearon Harris Page 1 of 6 Worksheet During a Loss of Shutdown Cooling. determine the time that the RCS will reach Core Boiling and Boil-Off G2.1.20 RD 4.6 SRO 4.6 Form ES-C-1 Task No.: JPM No.: 2009B NRC Exam Admin JPM SRO A1-1 NRC Examiner:

Date: __ _ Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: On 9/05/09 at 0000 the plant was shutdown for a refueling outage.

While the Reactor cavity was being filled the 'B' RHR pump tripped. Motor repairs are not expected to be completed until 9/25/09.

The Reactor cavity fill was completed to the normal refueling levels with the 'A' RHR pump.

No fuel has been moved due to problems with the Manipulator Crane and the Source Range audible count rate.

On 9/22/09 at 1400 the 'A' RHR pump tripped.

The crew is implementing AOP-020, Loss of RCS Inventory or RHR While Shutdown.

Core exit thermocouples are rising; they are currently reading 135°F. lAW AOP-020 you are directed to refer to curves H-X-8 through H-X-11 and determine the time to reach core boiling and core boil-off time. Mark up your curves to indicate where you are determining these times. Return the curves to the examiner with this page. Write your estimates of time to boil" and time to boil-off' on the lines at the bottom of this page (below). 2009B NRC Exam Admin JPM SRO A 1-1 Rev. 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Shearon Harris Page 1 of 6 Worksheet During a Loss of Shutdown Cooling. determine the time that the RCS will reach Core Boiling and Boil-Off G2.1.20 RD 4.6 SRO 4.6 Form ES-C-1 Task No.: JPM No.: 2009B NRC Exam Admin JPM SRO A1-1 NRC Examiner:

Date: __ _ Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: On 9/05/09 at 0000 the plant was shutdown for a refueling outage.

While the Reactor cavity was being filled the 'B' RHR pump tripped. Motor repairs are not expected to be completed until 9/25/09.

The Reactor cavity fill was completed to the normal refueling levels with the 'A' RHR pump.

No fuel has been moved due to problems with the Manipulator Crane and the Source Range audible count rate.

On 9/22/09 at 1400 the 'A' RHR pump tripped.

The crew is implementing AOP-020, Loss of RCS Inventory or RHR While Shutdown.

Core exit thermocouples are rising; they are currently reading 135°F. lAW AOP-020 you are directed to refer to curves H-X-8 through H-X-11 and determine the time to reach core boiling and core boil-off time. Mark up your curves to indicate where you are determining these times. Return the curves to the examiner with this page. Write your estimates of time to boil" and time to boil-off' on the lines at the bottom of this page (below). 2009B NRC Exam Admin JPM SRO A 1-1 Rev. 1 Appendix C Page 2 of 6 Worksheet Form ES-C-1 Task Standard:

Candidate obtains curves and correctly identifies the time to reach core boiling and core boil-off time Required Materials:

Curves H-X-8 through H-X-11 (All Rev. 2) General

References:

AOP-020 (Rev. 31) Curve Book curves H-X-8, 9,10 and 11 (All Rev. 2) Time Critical Task: No Validation Time: 10 minutes Step 3 Step 4 Critical Step Justification Step required in order to accurately determine

time to boil" using the appropriate curve. Step required in order to accurately determine

time to boil-off" using the appropriate curve. 2009B NRC Exam Admin JPM SRO A1-1 Rev. 1 Appendix C Page 2 of 6 Worksheet Form ES-C-1 Task Standard:

Candidate obtains curves and correctly identifies the time to reach core boiling and core boil-off time Required Materials:

Curves H-X-8 through H-X-11 (All Rev. 2) General

References:

AOP-020 (Rev. 31) Curve Book curves H-X-8, 9,10 and 11 (All Rev. 2) Time Critical Task: No Validation Time: 10 minutes Step 3 Step 4 Critical Step Justification Step required in order to accurately determine

time to boil" using the appropriate curve. Step required in order to accurately determine

time to boil-off" using the appropriate curve. 2009B NRC Exam Admin JPM SRO A1-1 Rev. 1 Appendix C START TIME: Performance Step: 1 Standard:

Comment: Performance Step: 2 Standard:

Comment: ./ Performance Step: 3 Standard:

Comment: ./ -Denotes Critical Steps Page 3 of 6 PERFORMANCE INFORMATION OBTAIN CURVES NEEDED FOR CALCULATION (Curves will be provided to the candidate)

Refers to curves H-X-8 through H-X-11 Form ES-C-1 Refers to provided data and determines that curve H-X-9 is required to calculate

time to boil" and curve H-X-11 is required to calculate "boil-off' time Reviews curves and determines which ones are appropriate to determine the time to boil" and "boil-off time" Based on time since shutdown (9/5/09 -9/22109) 17 days 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months since shutdown and current RCS temperature of 135°F using curve H-X-9 determine

time to boil" Reviews curve H-X-9 Determines that time to boil" is 22 minutes (+/- 1 minute) 2009B NRC Exam Admin JPM SRO A1-1 Rev. 1 Appendix C START TIME: Performance Step: 1 Standard:

Comment: Performance Step: 2 Standard:

Comment: ./ Performance Step: 3 Standard:

Comment: ./ -Denotes Critical Steps Page 3 of 6 PERFORMANCE INFORMATION OBTAIN CURVES NEEDED FOR CALCULATION (Curves will be provided to the candidate)

Refers to curves H-X-8 through H-X-11 Form ES-C-1 Refers to provided data and determines that curve H-X-9 is required to calculate

time to boil" and curve H-X-11 is required to calculate "boil-off' time Reviews curves and determines which ones are appropriate to determine the time to boil" and "boil-off time" Based on time since shutdown (9/5/09 -9/22109) 17 days 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months since shutdown and current RCS temperature of 135°F using curve H-X-9 determine

time to boil" Reviews curve H-X-9 Determines that time to boil" is 22 minutes (+/- 1 minute) 2009B NRC Exam Admin JPM SRO A1-1 Rev. 1 Appendix C ./ Performance Step: 4 Standard:

Comment: Terminating Cue: STOP TIME: ./ -Denotes Critical Steps Page 4 of 6 PERFORMANCE INFORMATION Form ES-C-1 Based on time since shutdown (9/5/09 -9/22/09) 17 days 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months since shutdown and current RCS temperature of 135°F using curve H-X-11 determine

time to boil-oft" Reviews curve H-X-11 Determines that time to boil-off' is 4 hrs and 45 minutes <+/- 15 minutes) or (4.5 to 5.0 hours0 days 0 hours 0 weeks 0 months ) After completing the "time to boil" and "time to boil-off" calculation, the evaluation on this JPM is complete.

ENDOFJPM 2009B NRC Exam Admin JPM SRO A1-1 Rev. 1 Appendix C ./ Performance Step: 4 Standard:

Comment: Terminating Cue: STOP TIME: ./ -Denotes Critical Steps Page 4 of 6 PERFORMANCE INFORMATION Form ES-C-1 Based on time since shutdown (9/5/09 -9/22/09) 17 days 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months since shutdown and current RCS temperature of 135°F using curve H-X-11 determine

time to boil-oft" Reviews curve H-X-11 Determines that time to boil-off' is 4 hrs and 45 minutes <+/- 15 minutes) or (4.5 to 5.0 hours0 days 0 hours 0 weeks 0 months ) After completing the "time to boil" and "time to boil-off" calculation, the evaluation on this JPM is complete.

ENDOFJPM 2009B NRC Exam Admin JPM SRO A1-1 Rev. 1 Appendix C Page 5 of 6 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM SRO A1-1 -During a Loss of Shutdown Cooling, determine the time that the RCS will reach Core Boiling and Boil-Off Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

2009B NRC Exam Admin JPM SRO A1-1 Rev. 1 Appendix C Page 5 of 6 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM SRO A1-1 -During a Loss of Shutdown Cooling, determine the time that the RCS will reach Core Boiling and Boil-Off Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

2009B NRC Exam Admin JPM SRO A1-1 Rev. 1 Appendix C Initial Conditions:

INITIATING CUE: Page 6 of 6 JPM CUE SHEET Form ES-C-1 On 9/05/09 at 0000 the plant was shutdown for a refueling outage.

While the Reactor cavity was being filled the '8' RHR pump tripped. Motor repairs are not expected to be completed until 9/25/09.

The Reactor cavity fill was completed to the normal refueling levels with the 'A' RHR pump.

No fuel has been moved due to problems with the Manipulator Crane and the Source Range audible count rate.

On 9/22/09 at 1400 the 'A' RHR pump tripped.

The crew is implementing AOP-020, Loss of RCS Inventory or RHR While Shutdown.

Core exit thermocouples are rising; they are currently reading 135°F. lAW AOP-020 you are directed to refer to curves H-X-8 through H-X-11 and determine the time to reach core boiling and core boil-off time. Mark up your curves to indicate where you are determining these times. Return the curves to the examiner with this page. Write your estimates of time to boil" and time to boil-off' on the lines at the bottom of this page (below). Name ______________________________________________

_ Record your calculations here and return your curves to the examiner:

TIME TO BOIL ________ _ TIME TO BOIL-OFF ________ _ 2009B NRC Exam Admin JPM SRO A1-1 Rev. 1 Appendix C Initial Conditions:

INITIATING CUE: Page 6 of 6 JPM CUE SHEET Form ES-C-1 On 9/05/09 at 0000 the plant was shutdown for a refueling outage.

While the Reactor cavity was being filled the '8' RHR pump tripped. Motor repairs are not expected to be completed until 9/25/09.

The Reactor cavity fill was completed to the normal refueling levels with the 'A' RHR pump.

No fuel has been moved due to problems with the Manipulator Crane and the Source Range audible count rate.

On 9/22/09 at 1400 the 'A' RHR pump tripped.

The crew is implementing AOP-020, Loss of RCS Inventory or RHR While Shutdown.

Core exit thermocouples are rising; they are currently reading 135°F. lAW AOP-020 you are directed to refer to curves H-X-8 through H-X-11 and determine the time to reach core boiling and core boil-off time. Mark up your curves to indicate where you are determining these times. Return the curves to the examiner with this page. Write your estimates of time to boil" and time to boil-off' on the lines at the bottom of this page (below). Name ______________________________________________

_ Record your calculations here and return your curves to the examiner:

TIME TO BOIL ________ _ TIME TO BOIL-OFF _______ _ 2009B NRC Exam Admin JPM SRO A1-1 Rev. 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Page 1 of 7 Form ES-C-1 .... ii Worksheet Shearon Harris Determine Boric Acid Addition Following CR Evacuation G2.1.25 RO 3.9 SRO 4.2 Task No.: 301013H401 JPM No.: 2009B NRC Exam Admin JPM SRO A1-2 NRC Examiner:

Date: __ _ Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: The Control Room has been evacuated and the MCB transfer to the ACP has been completed.

Plant management has directed a plant cooldown to mode 5 utilizing AOP-004. BAT level is 83% with a concentration of 7205 ppm. The RCS is currently 915 ppm. You are the CRS. Perform a calculation of the required boric acid addition to achieve cold shutdown and BAT level change per AOP-004, Section 3.2 Step 25 to obtain an OST -1036 cold shutdown boron requirement of 1740 ppm. DRAFT 2009B NRC Exam Admin JPMSRO A 1-2 Rev. 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Page 1 of 7 Form ES-C-1 .... ii Worksheet Shearon Harris Determine Boric Acid Addition Following CR Evacuation G2.1.25 RO 3.9 SRO 4.2 Task No.: 301013H401 JPM No.: 2009B NRC Exam Admin JPM SRO A1-2 NRC Examiner:

Date: __ _ Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: The Control Room has been evacuated and the MCB transfer to the ACP has been completed.

Plant management has directed a plant cooldown to mode 5 utilizing AOP-004. BAT level is 83% with a concentration of 7205 ppm. The RCS is currently 915 ppm. You are the CRS. Perform a calculation of the required boric acid addition to achieve cold shutdown and BAT level change per AOP-004, Section 3.2 Step 25 to obtain an OST -1036 cold shutdown boron requirement of 1740 ppm. DRAFT 2009B NRC Exam Admin JPMSRO A 1-2 Rev. 1 Appendix C Page 2 of 7 Worksheet Form ES-C-1 Task Standard:

Utilizes Curve E-X-2 to determine required boric acid addition to achieve cold shutdown and Curve D-2 to obtain a change of 27 to 29 percent in BAT level (or a final level of 54 to 56 percent).

Actual is 28% change (or 55% final). Required Materials:

Curve Book Calculator General

References:

AOP-004 (Rev. 46) Time Critical Task: Validation Time: Step 3 Step 4 Curve Book nomograph E-X-2 (Rev. 4) and Curve D-2 (Rev. 0) No 15 minutes Critical Step Justification Step is critical in order to correctly identify the amount of boric acid required boric acid concentration.

Step is critical in order to determine the change in tank level. 2009B NRC Exam Admin JPMSRO A 1-2 Rev. 1 Appendix C Page 2 of 7 Worksheet Form ES-C-1 Task Standard:

Utilizes Curve E-X-2 to determine required boric acid addition to achieve cold shutdown and Curve D-2 to obtain a change of 27 to 29 percent in BAT level (or a final level of 54 to 56 percent).

Actual is 28% change (or 55% final). Required Materials:

Curve Book Calculator General

References:

AOP-004 (Rev. 46) Time Critical Task: Validation Time: Step 3 Step 4 Curve Book nomograph E-X-2 (Rev. 4) and Curve D-2 (Rev. 0) No 15 minutes Critical Step Justification Step is critical in order to correctly identify the amount of boric acid required boric acid concentration.

Step is critical in order to determine the change in tank level. 2009B NRC Exam Admin JPMSRO A 1-2 Rev. 1 Appendix C START TIME: Performance Step: 1 Standard:

Comment: Performance Step: 2 Standard:

Evaluator Cue: Comment: ./ Performance Step: 3 Standard:

./ -Denotes Critical Steps Page 3 of 7 VERIFICATION OF COMPLETION OBTAIN PROCEDURE Obtains AOP-004 and refers to Section 3.2 Step 25 (Copy of step will be provided to the candidate)

Form ES-C-1 Obtain cold shutdown boron concentration using copy of latest OST -1036 in back of book. (If candidate asks: This information is provided in the initiating cue.) Required shutdown boron concentration is 1740 ppm Determine required gallons of boric acid to achieve required RCS boron concentration using the formula on the boron addition nomograph E-2 Utilizes formula on Nomograph E-2 and calculates between 9130 to 9030 gallons of boric acid to be added. Actual is 9080 gallons Boron Addition (ReS @ 350 D F) Vi =. -M 1n(7000-Cf) 8.33 7000 -Ci M =538,000 2009B NRC Exam Admin JPMSRO A1-2 Rev. 1 Appendix C START TIME: Performance Step: 1 Standard:

Comment: Performance Step: 2 Standard:

Evaluator Cue: Comment: ./ Performance Step: 3 Standard:

./ -Denotes Critical Steps Page 3 of 7 VERIFICATION OF COMPLETION OBTAIN PROCEDURE Obtains AOP-004 and refers to Section 3.2 Step 25 (Copy of step will be provided to the candidate)

Form ES-C-1 Obtain cold shutdown boron concentration using copy of latest OST -1036 in back of book. (If candidate asks: This information is provided in the initiating cue.) Required shutdown boron concentration is 1740 ppm Determine required gallons of boric acid to achieve required RCS boron concentration using the formula on the boron addition nomograph E-2 Utilizes formula on Nomograph E-2 and calculates between 9130 to 9030 gallons of boric acid to be added. Actual is 9080 gallons Boron Addition (ReS @ 350 D F) Vi =. -M 1n(7000-Cf) 8.33 7000 -Ci M =538,000 2009B NRC Exam Admin JPMSRO A1-2 Rev. 1 Appendix C Examiners NOTE: Comment: ./ -Denotes Critical Steps Page 4 of 7 VERIFICATION OF COMPLETION Form ES-C-1 The Nomograph formula found on Curve E-X-2 assumes that the BAT boron concentration is 7000 ppm. In this JPM the given information is BAT concentration is 7205 ppm. The candidate MUST use the given concentration of 7205 ppm to come to the correct boron addition.

CORRECT CALCULATION

-538000 InlZ205 -1740). VB = 8. 33 \-7205 -915 . = 9080 If candidate uses 7000 ppm for BAT BA concentration (from the nomograph) instead of changing to 7205 ppm the result will be 9409 gallons INCORRECT CALCULATION (using wrong BAT concentration)

-538000 I (!OOO -1740) VB = 8.. 33 n\7000 -915 . = 9409 If candidate uses correct BAT BA concentration but uses the wrong Curve (E-X-1 verses E-X-2) the result will be 7443 gallons INCORRECT CALCULATION (using wrong RCS Mass -wrong curve) -441000 l (Z205 -1740) VB = 8.33 n\720S -915 ; = 7443 2009B NRC Exam Admin JPMSRO A 1-2 Rev. 1 Appendix C Examiners NOTE: Comment: ./ -Denotes Critical Steps Page 4 of 7 VERIFICATION OF COMPLETION Form ES-C-1 The Nomograph formula found on Curve E-X-2 assumes that the BAT boron concentration is 7000 ppm. In this JPM the given information is BAT concentration is 7205 ppm. The candidate MUST use the given concentration of 7205 ppm to come to the correct boron addition.

CORRECT CALCULATION

-538000 InlZ205 -1740). VB = 8. 33 \-7205 -915 . = 9080 If candidate uses 7000 ppm for BAT BA concentration (from the nomograph) instead of changing to 7205 ppm the result will be 9409 gallons INCORRECT CALCULATION (using wrong BAT concentration)

-538000 I (!OOO -1740) VB = 8.. 33 n\7000 -915 . = 9409 If candidate uses correct BAT BA concentration but uses the wrong Curve (E-X-1 verses E-X-2) the result will be 7443 gallons INCORRECT CALCULATION (using wrong RCS Mass -wrong curve) -441000 l (Z205 -1740) VB = 8.33 n\720S -915 ; = 7443 2009B NRC Exam Admin JPMSRO A 1-2 Rev. 1 Appendix C 0/ Performance Step: 4 Standard:

Page 5 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Determine the change in boric acid tank level equivalent to the required gallons of boric acid using the boric acid tank curve 0-2 Utilizes Curve 0-2 and obtains a change of 27 to 29 percent (or a final level of 54 to 56 percent).

Actual is 28% change (or 55% final). -:':51)00 1IIIIIIIIIIIIIIltill n60r1e Add Tonk Volume in . 15000 f} 10 fO 30 120000 -9080 = 10020 . 40 ROOM COpy .....................

---,...._-

Comment: STOP TIME: Curve Ji. ..:1 Rey W1. arlg '"'L.{ J htit.f.:-z:t-Sup'; . if' OpS * **

It Incnceted

. I III 1111/11 IU'II . ..... 70 80[!!] 90 \83-55=28\

.+ 100 Terminating Cue: When candidate completes the calculations the JPM is completed.

ENDOFJPM 0/-Denotes Critical Steps 2009B NRC Exam Admin JPMSRO A 1-2 Rev. 1 Appendix C 0/ Performance Step: 4 Standard:

Page 5 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Determine the change in boric acid tank level equivalent to the required gallons of boric acid using the boric acid tank curve 0-2 Utilizes Curve 0-2 and obtains a change of 27 to 29 percent (or a final level of 54 to 56 percent).

Actual is 28% change (or 55% final). -:':51)00 IIllllL1l1ll1ll1t II lt60rle Add Tonk Volume in 15000 I I rm III f} 10 fO 30 120000 -9080 = 10020 . 40 ROOM COpy .....................

---,...._-

Comment: STOP TIME: 1l-.1 RevW1. C!KVe..JJ "I.. (-,,; ra...t.f.:-z:t-SI.

arlg SUpy .... u.&( .fI' OpS lUll * * .

It Incnceted

. I U 1/ 70 80[!!] 90 \83-55=28\

.+ 100 Terminating Cue: When candidate completes the calculations the JPM is completed.

ENDOFJPM 0/-Denotes Critical Steps 2009B NRC Exam Admin JPMSRO A 1-2 Rev. 1 Appendix C Page 6 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 20098 NRC Exam Admin JPM SRO A 1-2 -Determine boric acid addition following control room evacuation Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

../ -Denotes Critical Steps 20098 NRC Exam Admin JPMSRO A 1-2 Rev. 1 Appendix C Page 6 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 20098 NRC Exam Admin JPM SRO A 1-2 -Determine boric acid addition following control room evacuation Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

../ -Denotes Critical Steps 20098 NRC Exam Admin JPMSRO A 1-2 Rev. 1 Appendix C Initial Conditions:

Initiating Cue: Page 7 of 7 JPM CUE SHEET Form ES-C-1 The Control Room has been evacuated and the MCB transfer to the ACP has been completed.

Plant management has directed a plant cooldown to mode 5 utilizing AOP-004. BAT level is 83% with a concentration of 7205 ppm. The RCS is currently 915 ppm. You are the CRS. Perform a calculation of the required boric acid addition to achieve cold shutdown and BAT level change per AOP-004, Section 3.2 Step 25 to obtain an OST-1036 cold shutdown boron requirement of 1740 ppm. 2009B NRC Exam Admin JPMSRO A1-2 Rev. 1 Appendix C Initial Conditions:

Initiating Cue: Page 7 of 7 JPM CUE SHEET Form ES-C-1 The Control Room has been evacuated and the MCB transfer to the ACP has been completed.

Plant management has directed a plant cooldown to mode 5 utilizing AOP-004. BAT level is 83% with a concentration of 7205 ppm. The RCS is currently 915 ppm. You are the CRS. Perform a calculation of the required boric acid addition to achieve cold shutdown and BAT level change per AOP-004, Section 3.2 Step 25 to obtain an OST-1036 cold shutdown boron requirement of 1740 ppm. 2009B NRC Exam Admin JPMSRO A1-2 Rev. 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: DRAFT Page 1 of 12 Worksheet Form ES-C-1 Shearon Harris Task No.: 005016H101 Perform OP-111, Attachment 3 -. JPM No.: 2009B NRC Exam Low Head SI Standby Lineup Admin JPM SRO A2 Checklist G2.2.15 RO 3.9 SRO 4.3 NRC Examiner:

Date: __ _ Simulated Performance:

Actual Performance:

X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: A plant heatup is in progress lAW GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3 OP-111 RESIDUAL HEAT REMOVAL SYSTEM, Section 7.2-Restoring the RHR System to ECCS Mode, has just been completed.

You are the BOP and the CRS has assigned to perform the independent verification on OP-111, Attachment 3 -Low Head SI Standby Lineup Checklist, for the control room operated valves. An AD is checking the local equipment.

2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: DRAFT Page 1 of 12 Worksheet Form ES-C-1 Shearon Harris Task No.: 005016H101 Perform OP-111, Attachment 3 -. JPM No.: 2009B NRC Exam Low Head SI Standby Lineup Admin JPM SRO A2 Checklist G2.2.15 RO 3.9 SRO 4.3 NRC Examiner:

Date: __ _ Simulated Performance:

Actual Performance:

X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: A plant heatup is in progress lAW GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3 OP-111 RESIDUAL HEAT REMOVAL SYSTEM, Section 7.2-Restoring the RHR System to ECCS Mode, has just been completed.

You are the BOP and the CRS has assigned to perform the independent verification on OP-111, Attachment 3 -Low Head SI Standby Lineup Checklist, for the control room operated valves. An AD is checking the local equipment.

2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 2 of 12 Worksheet Form ES-C-1 Task Standard:

All errors identified.

Required Materials:

OP-111, Attachment 3, with CHECK column initialed except for the local valves. General

References:

OP-111 (Rev. 44) Time Critical Task: Validation Time: Step 2 Step 3 Step 4 Step 5 Step 6 No 10 minutes Critical Step Justification:

Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification 2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 2 of 12 Worksheet Form ES-C-1 Task Standard:

All errors identified.

Required Materials:

OP-111, Attachment 3, with CHECK column initialed except for the local valves. General

References:

OP-111 (Rev. 44) Time Critical Task: Validation Time: Step 2 Step 3 Step 4 Step 5 Step 6 No 10 minutes Critical Step Justification:

Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification Must identify all out of alignment equipment for Independent Verification 2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 3 of 12 Worksheet 20098 NRC Exam -SIMULATOR SETUP Simulator Operator

Reset to IC-170 (Password 9newguys)

Silence and Acknowledge annunciators Form ES-C-1 GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.) To recreate the conditions of this JPM:

Initial Simulator IC-16 (Mode 4 with RHR aligned for ECCS)

Place 1 RH-30, RHR HEAT XCHG A OUT FLOW CO NT to "0%" open on controller

Place 1 SI-322, SA RWST TO RHR PUMP A-SA to SHUT (closed indication)

Leave control power ON for 1 SI-341 S8

Place 1CC-167, CCW FROM RHR HEAT EXCHANGER 8-S8 to OPEN

Place 1CC-147, CCW FROM RHR HEAT EXCHANGER A-SA to OPEN

Silence Acknowledge and Reset Annunciators

Freeze and Snap these conditions for future use 20098 NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 3 of 12 Worksheet 20098 NRC Exam -SIMULATOR SETUP Simulator Operator

Reset to IC-170 (Password 9newguys)

Silence and Acknowledge annunciators Form ES-C-1 GO TO FREEZE and inform the lead examiner the Simulator is ready. DO NOT GO TO RUN until directed by the lead examiner. (The examiner has provided to the candidate with initial conditions and the initiating cues prior to placing the simulator in RUN.) To recreate the conditions of this JPM:

Initial Simulator IC-16 (Mode 4 with RHR aligned for ECCS)

Place 1 RH-30, RHR HEAT XCHG A OUT FLOW CO NT to "0%" open on controller

Place 1 SI-322, SA RWST TO RHR PUMP A-SA to SHUT (closed indication)

Leave control power ON for 1 SI-341 S8

Place 1CC-167, CCW FROM RHR HEAT EXCHANGER 8-S8 to OPEN

Place 1CC-147, CCW FROM RHR HEAT EXCHANGER A-SA to OPEN

Silence Acknowledge and Reset Annunciators

Freeze and Snap these conditions for future use 20098 NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C START TIME: Performance Step: 1 Standard:

Evaluator Cue: Evaluator Note: Comment: Performance Step: 2 Standard:

Evaluator Cue: Comment: ../ -Denotes Critical Steps Page 4 of 12 PERFORMANCE INFORMATION OP-111 Attachment 3 Obtain procedure.

Form ES-C-1 Fills out applicable sections of Sheet 1 of 4 and reviews Attachment.

Provide OP-111, Attachment

3. The Attachment can be performed in any order. The following valves/controls are out of position.

All others are correctly positioned.

OP-111 Attachment 3 continued Locates and compares actual position to required position lAW Attachment

3.

1 RH-30, RHR XCHG A OUT FLOW CONT -(OPEN) Determines 1 RH-30 is SHUT (0% demand) and notes position condition in REMARKS section. As CRS: Throughout the JPM, acknowledge any verbal communications.

Instruct them to document mis-positioned controls/valves but continue performing the Attachment without re-aligning any equipment.

2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C START TIME: Performance Step: 1 Standard:

Evaluator Cue: Evaluator Note: Comment: Performance Step: 2 Standard:

Evaluator Cue: Comment: ../ -Denotes Critical Steps Page 4 of 12 PERFORMANCE INFORMATION OP-111 Attachment 3 Obtain procedure.

Form ES-C-1 Fills out applicable sections of Sheet 1 of 4 and reviews Attachment.

Provide OP-111, Attachment

3. The Attachment can be performed in any order. The following valves/controls are out of position.

All others are correctly positioned.

OP-111 Attachment 3 continued Locates and compares actual position to required position lAW Attachment

3.

1 RH-30, RHR XCHG A OUT FLOW CONT -(OPEN) Determines 1 RH-30 is SHUT (0% demand) and notes position condition in REMARKS section. As CRS: Throughout the JPM, acknowledge any verbal communications.

Instruct them to document mis-positioned controls/valves but continue performing the Attachment without re-aligning any equipment.

2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C " Performance Step: 3 Standard:

Comment: " Performance Step: 4 Standard:

Comment: " Performance Step: 5 Standard:

Comment: ./ -Denotes Critical Steps Page 5 ot 12 PERFORMANCE INFORMATION OP-111 Attachment 3 continued Form ES-C-1 Locates and compares actual position to required position lAW Attachment

3.

1SI-341 SB LOW HEAD SI TRAIN B TO COLD LEG CONT PWR & VLV POS (OFF) Determines 1 SI-341 SB is not OFF and notes out-ot-position condition in REMARKS section. OP-111 Attachment 3 continued

' Locates and compares actual position to required position lAW Attachment

3.

1 SI-322 SA, RWST TO RHR PUMP A-SA (OPEN) Determines 1 SI-322 SA is not OPEN and notes out-ot-position condition in REMARKS section. OP-111 Attachment 3 continued Locates and compares actual position to required position lAW Attachment

3.

1CC-147, CCW FROM RHR HEAT EXCHANGER A-SA Determines 1CC-147 is not SHUT and notes out-ot-position condition in REMARKS section. 2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C " Performance Step: 3 Standard:

Comment: " Performance Step: 4 Standard:

Comment: " Performance Step: 5 Standard:

Comment: ./ -Denotes Critical Steps Page 5 ot 12 PERFORMANCE INFORMATION OP-111 Attachment 3 continued Form ES-C-1 Locates and compares actual position to required position lAW Attachment

3.

1SI-341 SB LOW HEAD SI TRAIN B TO COLD LEG CONT PWR & VLV POS (OFF) Determines 1 SI-341 SB is not OFF and notes out-ot-position condition in REMARKS section. OP-111 Attachment 3 continued

' Locates and compares actual position to required position lAW Attachment

3.

1 SI-322 SA, RWST TO RHR PUMP A-SA (OPEN) Determines 1 SI-322 SA is not OPEN and notes out-ot-position condition in REMARKS section. OP-111 Attachment 3 continued Locates and compares actual position to required position lAW Attachment

3.

1CC-147, CCW FROM RHR HEAT EXCHANGER A-SA Determines 1CC-147 is not SHUT and notes out-ot-position condition in REMARKS section. 2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C " Performance Step: 6 Standard:

Comment: Performance Step: 7 Standard:

Evaluator Cue: Comment: Terminating Cue: STOP TIME: ./ -Denotes Critical Steps Page 60t 12 PERFORMANCE INFORMATION OP-111 Attachment 3 continued Form ES-C-1 Locates and compares actual position to required position lAW Attachment

3.

1CC-167, CCW FROM RHR HEAT EXCHANGER 8-S8 Determines 1CC-167 is not SHUT and notes out-ot-position condition in REMARKS section. OP-111 Attachment 3 continued Provide Attachment to CRS. Completes Att. 3, Sheet 1 ot 4 and provides Attachment to CRS. Acknowledge any verbal report. When the applicable section of the Attachment has been returned to the CRS: ENDOFJPM 20098 NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C " Performance Step: 6 Standard:

Comment: Performance Step: 7 Standard:

Evaluator Cue: Comment: Terminating Cue: STOP TIME: ./ -Denotes Critical Steps Page 60t 12 PERFORMANCE INFORMATION OP-111 Attachment 3 continued Form ES-C-1 Locates and compares actual position to required position lAW Attachment

3.

1CC-167, CCW FROM RHR HEAT EXCHANGER 8-S8 Determines 1CC-167 is not SHUT and notes out-ot-position condition in REMARKS section. OP-111 Attachment 3 continued Provide Attachment to CRS. Completes Att. 3, Sheet 1 ot 4 and provides Attachment to CRS. Acknowledge any verbal report. When the applicable section of the Attachment has been returned to the CRS: ENDOFJPM 20098 NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 7 of 12 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM SRO A2 -Perform OP-111, Attachment 3 -Low Head SI Standby Lineup Checklist Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 7 of 12 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM SRO A2 -Perform OP-111, Attachment 3 -Low Head SI Standby Lineup Checklist Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Initial Conditions:

Initiating Cue: Page 8 of 12 JPM CUE SHEET Form ES-C-1 A plant heatup is in progress lAW GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3 OP-111 RESIDUAL HEAT REMOVAL SYSTEM, Section 7.2-Restoring the RHR System to ECCS Mode, has just been completed.

You are the BOP and the CRS has assigned to perform the independent verification on OP-111, Attachment 3 -Low Head SI Standby Lineup Checklist, for the control room operated valves. An AO is checking the local equipment.

2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Initial Conditions:

Initiating Cue: Page 8 of 12 JPM CUE SHEET Form ES-C-1 A plant heatup is in progress lAW GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3 OP-111 RESIDUAL HEAT REMOVAL SYSTEM, Section 7.2-Restoring the RHR System to ECCS Mode, has just been completed.

You are the BOP and the CRS has assigned to perform the independent verification on OP-111, Attachment 3 -Low Head SI Standby Lineup Checklist, for the control room operated valves. An AO is checking the local equipment.

2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 9 of 12 JPM CUE SHEET Form ES-C-1 Attacmnent 3 -Low Head Safety Injection Standby Lineup Checklist Sheet1of4 Person(s)

Perfonning Cheddisf Initials Name (Print) Initials Name (Print) TR Terry Ilight Remarks -Indicate any component not in the prescribed positiorL Checklist Started Checklist Completed Approved by Time UnitSCO Date TODAY' Date ___ _ Date ----After receiving the final review signature.

this OP Attadvnent becomes a QA RECORD. IOP-111 Rev. 44 Page 142 of 1531 2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 9 of 12 JPM CUE SHEET Form ES-C-1 Attacmnent 3 -Low Head Safety Injection Standby Lineup Checklist Sheet1of4 Person(s)

Perfonning Cheddisf Initials Name (Print) Initials Name (Print) TR Terry Ilight Remarks -Indicate any component not in the prescribed positiorL Checklist Started Checklist Completed Approved by Time UnitSCO Date TODAY' Date ___ _ Date ----After receiving the final review signature.

this OP Attadvnent becomes a QA RECORD. IOP-111 Rev. 44 Page 142 of 1531 2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 10 of 12 JPM CUE SHEET Attachment 3 -Low Head Safety Injection Standby Uneup Checklist Sheet2of4 COMPONENT NUMBER COMPONENT DESCRIPTION POSITION CHECK 1RH-1 RCS LOOP A TO RHR PUMP A-SA Shut TR 1RH-2 RCS LOOP A TO RHR PUMP A-SA Shut TR 1RH-39 RCS LOOP C TO RHR PUMP B-SB Shut TR 1RH-40 RCSLOOPCTORHRPUMPB-SB Shut TR 1RH-30 RHR HEAT XCHG A OUT FLOW CONT Open TR 1RH-66 RHR HEAT XCHG B OUT FLOW CONT Open TR (HCr03B1) 1RH-20 RHR HEAT XCHG A BVP FLOW CONT Manual & Shut TR 1RH-58 RHR HEAT XCHG B BVP FLOW CONT Manual & Shut TR 1RH-26 ,. RHR Header A to eves Letdown 1501 Locked Shut TR Vlv 1RH-64

RHR Header B to cves Letdown lsol Locked Shut TR Vlv 1RH-31 RHR PUMP A-SA MINI FLOW Open TR 1RH-69 RHR PUMP B-SB MINI FLOW Open TR 1CS-28 RHR LETDOWN (HC-1421)

Shut TR 1CC-146-RHR HX A Outlet Throttle Valve Locked TR ThrotHed 1CC-147 CCW FROM RHR HEAT EXCHANGER Shut TR A-SA ... This is a local valve operated in the body of the procedure . Form ES-C-1 VERIFY -Throttled should be as recorded in the last OST-1216.

This ensures the required flow for E CS function.

IOP-111 Rev. 44 Page 143 of 1531 2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 10 of 12 JPM CUE SHEET Attachment 3 -Low Head Safety Injection Standby Uneup Checklist Sheet2of4 COMPONENT NUMBER COMPONENT DESCRIPTION POSITION CHECK 1RH-1 RCS LOOP A TO RHR PUMP A-SA Shut TR 1RH-2 RCS LOOP A TO RHR PUMP A-SA Shut TR 1RH-39 RCS LOOP C TO RHR PUMP B-SB Shut TR 1RH-40 RCSLOOPCTORHRPUMPB-SB Shut TR 1RH-30 RHR HEAT XCHG A OUT FLOW CONT Open TR 1RH-66 RHR HEAT XCHG B OUT FLOW CONT Open TR (HCr03B1) 1RH-20 RHR HEAT XCHG A BVP FLOW CONT Manual & Shut TR 1RH-58 RHR HEAT XCHG B BVP FLOW CONT Manual & Shut TR 1RH-26 ,. RHR Header A to eves Letdown 1501 Locked Shut TR Vlv 1RH-64

RHR Header B to cves Letdown lsol Locked Shut TR Vlv 1RH-31 RHR PUMP A-SA MINI FLOW Open TR 1RH-69 RHR PUMP B-SB MINI FLOW Open TR 1CS-28 RHR LETDOWN (HC-1421)

Shut TR 1CC-146-RHR HX A Outlet Throttle Valve Locked TR ThrotHed 1CC-147 CCW FROM RHR HEAT EXCHANGER Shut TR A-SA ... This is a local valve operated in the body of the procedure . Form ES-C-1 VERIFY -Throttled should be as recorded in the last OST-1216.

This ensures the required flow for E CS function.

IOP-111 Rev. 44 Page 143 of 1531 2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 11 of 12 JPM CUE SHEET Attachment 3 -Low Head Safety Injection Standby lineup Checklist Sheet 3 of4 Form ES-C-1 COMPONENT NUMBER COMPONENT DESCRIPTION POsmON CHECK VERIFY 1CC-166-RHR HX B Outlet Throttle Valve Locked TR Throttled 1CC-167 CCW FROM RHR HEAT EXCHANGER B-SB Shut TR 1SI-340SA LOW HEAD SI TRAIN A TO COLD LEG Open & Pull TR to Lock 1SI-340SA LOW HEAD SI TRAIN A TO COLD LEG Off TR CONT PWR & VL V POS 1SI-341 SB LOW HEAD SI TRAIN B TO COLD LEG TR to Lock 1SI-341 SB LOW HEAD SI TRAIN B TO COLD LEG Off TR CONT PWR & VLV POS 1SI-326 SA LOW HEAD SI TRAIN A TO HOT LEG Open TR CROSSOVER 1SI-327SB LOW HEAD SI TRAIN B TO HOT LEG Open TR CROSSOVER 1SI-322 SA RWST TO RHR PUMP A-SA Open TR 1SI-323SB RWST TO RHR PUMP B-SB Open TR -Throttled position should be as recorded in the last OST-1216.

This ensures the required flow for ECCS function.

1 OP-111 Rev. 44 Page 144 of 1531 20098 NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 11 of 12 JPM CUE SHEET Attachment 3 -Low Head Safety Injection Standby lineup Checklist Sheet 3 of4 Form ES-C-1 COMPONENT NUMBER COMPONENT DESCRIPTION POsmON CHECK VERIFY 1CC-166-RHR HX B Outlet Throttle Valve Locked TR Throttled 1CC-167 CCW FROM RHR HEAT EXCHANGER B-SB Shut TR 1SI-340SA LOW HEAD SI TRAIN A TO COLD LEG Open & Pull TR to Lock 1SI-340SA LOW HEAD SI TRAIN A TO COLD LEG Off TR CONT PWR & VL V POS 1SI-341 SB LOW HEAD SI TRAIN B TO COLD LEG TR to Lock 1SI-341 SB LOW HEAD SI TRAIN B TO COLD LEG Off TR CONT PWR & VLV POS 1SI-326 SA LOW HEAD SI TRAIN A TO HOT LEG Open TR CROSSOVER 1SI-327SB LOW HEAD SI TRAIN B TO HOT LEG Open TR CROSSOVER 1SI-322 SA RWST TO RHR PUMP A-SA Open TR 1SI-323SB RWST TO RHR PUMP B-SB Open TR -Throttled position should be as recorded in the last OST-1216.

This ensures the required flow for ECCS function.

1 OP-111 Rev. 44 Page 144 of 1531 20098 NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 12 of 12 JPM CUE SHEET Form ES-C-1 Attachment 3 -Low Head Safety Injection Standby Uneup Checklist Sheet4of4 COMPONENT NUMBER COMPONENT DESCRIPTION POSmON CHECK VERIFY 480V MCC-1A21-SA 1A21-SA-7B RCS Lg(B A to RHR Puflll1A-SA Locked Off TR (1RH-2) oth 8krs) Locked Off TR 1A21-SA-8A RCS C to RHR PlIfIl> 1B-SB Locked Off TIt (1RH-40) (Both Bkrs) Locked Off TIt 4tlUV MCG-1tl21-!::)H 1B21-SB-5B RCS RHR Puflll1A-SA (1RH-1) 8krs) Locked Off TIt Locked Off TIt 1B21-SB-11A RCS C to RHR Locked Off TR (1RH-39)(Both Bkrs) Locked Off TIt 1 OP-111 Rev. 44 Page 145 of 1531 2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Page 12 of 12 JPM CUE SHEET Form ES-C-1 Attachment 3 -Low Head Safety Injection Standby Uneup Checklist Sheet4of4 COMPONENT NUMBER COMPONENT DESCRIPTION POSmON CHECK VERIFY 480V MCC-1A21-SA 1A21-SA-7B RCS Lg(B A to RHR Puflll1A-SA Locked Off TR (1RH-2) oth 8krs) Locked Off TR 1A21-SA-8A RCS C to RHR PlIfIl> 1B-SB Locked Off TIt (1RH-40) (Both Bkrs) Locked Off TIt 4tlUV MCG-1tl21-!::)H 1B21-SB-5B RCS RHR Puflll1A-SA (1RH-1) 8krs) Locked Off TIt Locked Off TIt 1B21-SB-11A RCS C to RHR Locked Off TR (1RH-39)(Both Bkrs) Locked Off TIt 1 OP-111 Rev. 44 Page 145 of 1531 2009B NRC Exam Admin JPM SRO A2 Rev. 1 Appendix C Facility:

Page 1 of 8 Worksheet Form ES-C-1 Task No.: Task Title: Using survey maps determine stay JPM No.: 2009B NRC Exam times Admin JPM SRO A-3 KIA

Reference:

G.2.3.4 RO 3.2 SRO 3.7 Examinee:

NRC Examiner:

Facility Evaluator:

Date: __ _ Method of testing: Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant 2009B NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C Facility:

Task Title: KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Page 1 of 8 Worksheet Task No.: Form ES-C-1 Using survey maps determine stay JPM No.: 2009B NRC Exam times Admin JPM SRO A-3 G.2.3.4 RO 3.2 SRO 3.7 NRC Examiner:

Date: __ _ Simulated Performance:

Actual Performance:

x ---Classroom X Simulator Plant 2009B NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C Page 2 of 8 Worksheet Form ES-C-1 READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Pump. The clearance includes the following valves:

1 ED-12

1ED-13

1 ED-14

1 ED-15

1 ED-17

1ED-18 Two Operators are being assigned to hang a clearance and perform work in a radiological area. Operator 1 has an accumulated annual Whole Body dose of 1760 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Saint Lucie earlier this year where he has accumulated 2700 mrem. The clearance and work activity is for the 'A' ED Tank Transfer Pump. Using the supplied survey map, determine the allowable individual stay times for each Operator that would prevent exceeding the annual administrative dose limit while performing these activities.

Calculations should be based on Progress Energy Administrative Dose Limits. Do not consider RWP Administrative Limits. Any required dose extensions have been processed and approved with the exception of any dose extensions requiring the Superintendent

-Radiation Protection approval.

Do not consider dose received during transit. The calculated dose should be ONLY what they would receive while working at the valves for the clearance.

Complete the information below and return to the evaluator when complete.

2009B NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C Page 2 of 8 Worksheet Form ES-C-1 READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Pump. The clearance includes the following valves:

1 ED-12

1ED-13

1 ED-14

1 ED-15

1 ED-17

1ED-18 Two Operators are being assigned to hang a clearance and perform work in a radiological area. Operator 1 has an accumulated annual Whole Body dose of 1760 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Saint Lucie earlier this year where he has accumulated 2700 mrem. The clearance and work activity is for the 'A' ED Tank Transfer Pump. Using the supplied survey map, determine the allowable individual stay times for each Operator that would prevent exceeding the annual administrative dose limit while performing these activities.

Calculations should be based on Progress Energy Administrative Dose Limits. Do not consider RWP Administrative Limits. Any required dose extensions have been processed and approved with the exception of any dose extensions requiring the Superintendent

-Radiation Protection approval.

Do not consider dose received during transit. The calculated dose should be ONLY what they would receive while working at the valves for the clearance.

Complete the information below and return to the evaluator when complete.

2009B NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C Page 3 of 8 Worksheet Form ES-C-1 Task Standard:

Calculation of stay times based on survey maps, two hours for Operator 1 , five hours for Operator 2. Required Materials:

Survey map A4 RAB 190' North Valve MAP 2 SFD-5-S-0684 General

References:

DOS-NGGC-0004 (Rev. 10) Time Critical Task: Validation Time: Step 1 Step 2 Step 3 DOS-NGGC-0004 "Progress Energy Annual Administrative Dose Limits" Section 9.3.1 LIMIT = 2 rem Progress Energy dose not to exceed 4 rem total dose if non-Progress Energy dose for the current year has been determined.

No 12 minutes Critical Task Justification Must determine dose rates in order to calculate stay time Must determine available dose to determine stay time. Calculation of stay time. 2009B NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C Page 3 of 8 Worksheet Form ES-C-1 Task Standard:

Calculation of stay times based on survey maps, two hours for Operator 1 , five hours for Operator 2. Required Materials:

Survey map A4 RAB 190' North Valve MAP 2 SFD-5-S-0684 General

References:

DOS-NGGC-0004 (Rev. 10) Time Critical Task: Validation Time: Step 1 Step 2 Step 3 DOS-NGGC-0004 "Progress Energy Annual Administrative Dose Limits" Section 9.3.1 LIMIT = 2 rem Progress Energy dose not to exceed 4 rem total dose if non-Progress Energy dose for the current year has been determined.

No 12 minutes Critical Task Justification Must determine dose rates in order to calculate stay time Must determine available dose to determine stay time. Calculation of stay time. 2009B NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C START TIME: Evaluator Note: .;' Performance Step: 1 Standard:

Comment: .;' Performance Step: 2 Standard:

Comment: ./ -Denotes Critical Steps Page 4 of 8 PERFORMANCE INFORMATION The order of performance does not matter Form ES-C-1 IF THE APPLICANT ASKS FOR IT: Provide a copy of NGGC-0004, Rev. 10 Using Radiological Survey Record Map A4 and RAB 190' North map, determines dose rates in the area where the clearance will be applied Identifies that General Area Dose Rates are 120 mrem/hr Determine the remaining dose for the year for each individual Operator 1: 240 mrem (2000 mrem -1760 mrem = 240 mrem Operator 2: 600 mrem 4000 mrem -700 mrem (PE) -2700 mrem (SL) = 600 mrem 2009B NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C START TIME: Evaluator Note: .;' Performance Step: 1 Standard:

Comment: .;' Performance Step: 2 Standard:

Comment: ./ -Denotes Critical Steps Page 4 of 8 PERFORMANCE INFORMATION The order of performance does not matter Form ES-C-1 IF THE APPLICANT ASKS FOR IT: Provide a copy of NGGC-0004, Rev. 10 Using Radiological Survey Record Map A4 and RAB 190' North map, determines dose rates in the area where the clearance will be applied Identifies that General Area Dose Rates are 120 mrem/hr Determine the remaining dose for the year for each individual Operator 1: 240 mrem (2000 mrem -1760 mrem = 240 mrem Operator 2: 600 mrem 4000 mrem -700 mrem (PE) -2700 mrem (SL) = 600 mrem 2009B NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C ./ Performance Step: 3 Standard:

Comment: Terminating Cue: STOP TIME: ./ -Denotes Critical Steps Page 5 of 8 PERFORMANCE INFORMATION Form ES-C-1 Determine stay time for each operator (based on 1 st Operator reaching 2 mrem and the 2nd Operator reaching 4 mrem -for the year) Operator 1: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 240 mrem + 120mremihr

= 2 hrs Operator 2: 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 600 mrem + 120 mrem/hr = 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months After the stay time has been calculated, this JPM is complete.

ENDOFJPM 20098 NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C ./ Performance Step: 3 Standard:

Comment: Terminating Cue: STOP TIME: ./ -Denotes Critical Steps Page 5 of 8 PERFORMANCE INFORMATION Form ES-C-1 Determine stay time for each operator (based on 1 st Operator reaching 2 mrem and the 2nd Operator reaching 4 mrem -for the year) Operator 1: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 240 mrem + 120mremihr

= 2 hrs Operator 2: 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 600 mrem + 120 mrem/hr = 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months After the stay time has been calculated, this JPM is complete.

ENDOFJPM 20098 NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C Page 6 of 8 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM SRO A-3 -Using survey maps determine stay times. (DOS-NGGC-0004 Rev. 10) Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

DOS-NGGC-0004 "Progress Energy Annual Administrative Dose Limits" Section 9.3.1 LIMIT = 2 rem Progress Energy dose not to exceed 4 rem total dose if non-Progress Energy dose for the current year has been determined.

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: -------------------------------------------------------------------

2009B NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C Page 6 of 8 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM SRO A-3 -Using survey maps determine stay times. (DOS-NGGC-0004 Rev. 10) Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

DOS-NGGC-0004 "Progress Energy Annual Administrative Dose Limits" Section 9.3.1 LIMIT = 2 rem Progress Energy dose not to exceed 4 rem total dose if non-Progress Energy dose for the current year has been determined.

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: -------------------------------------------------------------------

2009B NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C Initial Conditions:

Initiating Cue: Page 7 of 8 JPM CUE SHEET Form ES-C-1 Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Pump. The clearance includes the following valves:

1 ED-12

1 ED-13

1 ED-14

1 ED-15

1 ED-17

1ED-18 Two Operators are being assigned to hang a clearance and perform work in a radiological area. Operator 1 has an accumulated annual Whole Body dose of 1760 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Saint Lucie earlier this year where he has accumulated 2700 mrem. The clearance and work activity is for the 'A' ED Tank Transfer Pump. Using the supplied survey map, determine the allowable individual stay times for each Operator that would prevent exceeding the annual administrative dose limit while performing these activities.

Calculations should be based on Progress Energy Administrative Dose Limits. Do not consider RWP Administrative Limits: Any required dose extensions have been processed and approved with the exception of any dose extensions requiring the Superintendent

-Radiation Protection approval.

Do not consider dose received during transit. The calculated dose should be ONLY what they would receive while working at the valves for the clearance.

Complete the information below and return to the evaluator when complete.

Name ____________________________________

_ Record the maximum allowable stay time calculations below to the nearest hour and minute. Operator 1: _____________________

Operator 2: 2009B NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C Initial Conditions:

Initiating Cue: Page 7 of 8 JPM CUE SHEET Form ES-C-1 Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Pump. The clearance includes the following valves:

1 ED-12

1 ED-13

1 ED-14

1 ED-15

1 ED-17

1ED-18 Two Operators are being assigned to hang a clearance and perform work in a radiological area. Operator 1 has an accumulated annual Whole Body dose of 1760 mrem (Progress Energy). Operator 2 has an accumulated annual Whole Body dose of 700 mrem (Progress Energy) and worked at Saint Lucie earlier this year where he has accumulated 2700 mrem. The clearance and work activity is for the 'A' ED Tank Transfer Pump. Using the supplied survey map, determine the allowable individual stay times for each Operator that would prevent exceeding the annual administrative dose limit while performing these activities.

Calculations should be based on Progress Energy Administrative Dose Limits. Do not consider RWP Administrative Limits: Any required dose extensions have been processed and approved with the exception of any dose extensions requiring the Superintendent

-Radiation Protection approval.

Do not consider dose received during transit. The calculated dose should be ONLY what they would receive while working at the valves for the clearance.

Complete the information below and return to the evaluator when complete.

Name ____________________________________

_ Record the maximum allowable stay time calculations below to the nearest hour and minute. Operator 1: _____________________

Operator 2: 2009B NRC Exam Admin JPM SRO A3 Rev. 1 Appendix C Job Performance Measure Form ES-C-1 ["'). F.\ Fe:,

Worksheet fl Facility:

Shearon Harris Task No.: 345001 H602 Task Title: Classify an event JPM No.: 2009B NRC Exam Admin JPM SRO A4 KIA

Reference:

G2.4.41 RO 2.9 SRO 4.6 Examinee:

NRC Examiner Facility Evaluator:

Date: __ _ Method of testing: Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant ---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: A refueling outage has just been completed and a plant heat up is being performed lAW GP-002, Normal Plant Heatup From Cold Solid to Hot Subcritical Mode 5 to Mode 3. Using the attached information sheet and the EAL Flow Path, classify the event. Mark the EAL Flow Path appropriately.

THIS IS A TIME CRITICAL JPM. 2009B NRC Exam Admin JPM SRO A4 Rev. 1 Appendix C Job Performance Measure Form ES-C-1 ["'). F.\ Fe:,

Worksheet fl Facility:

Shearon Harris Task No.: 345001 H602 Task Title: Classify an event JPM No.: 2009B NRC Exam Admin JPM SRO A4 KIA

Reference:

G2.4.41 RO 2.9 SRO 4.6 Examinee:

NRC Examiner Facility Evaluator:

Date: __ _ Method of testing: Simulated Performance:

Actual Performance:

x Classroom X Simulator Plant ---READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Initial Conditions:

Initiating Cue: A refueling outage has just been completed and a plant heat up is being performed lAW GP-002, Normal Plant Heatup From Cold Solid to Hot Subcritical Mode 5 to Mode 3. Using the attached information sheet and the EAL Flow Path, classify the event. Mark the EAL Flow Path appropriately.

THIS IS A TIME CRITICAL JPM. 2009B NRC Exam Admin JPM SRO A4 Rev. 1 Appendix C Job Performance Measure Worksheet Task Standard:

Event classified as an Site Area Emergency (2-4-3) Required Materials:

None General

References:

PEP-110 EAL Flowpath EP-EAL (allowed reference)

Handouts:

JPM Cue Sheets Pages 4 and 5 PEP-110 EAL Flowpath EP-EAL (allowed reference)

Time Critical Task: Yes Validation Time: 15 minutes Critical Step Justification Step 2 Classification of the event. Form ES-C-1 2009B NRC Exam Admin JPM SRO A4 Rev. 1 Appendix C Job Performance Measure Worksheet Task Standard:

Event classified as an Site Area Emergency (2-4-3) Required Materials:

None General

References:

PEP-110 EAL Flowpath EP-EAL (allowed reference)

Handouts:

JPM Cue Sheets Pages 4 and 5 PEP-110 EAL Flowpath EP-EAL (allowed reference)

Time Critical Task: Yes Validation Time: 15 minutes Critical Step Justification Step 2 Classification of the event. Form ES-C-1 2009B NRC Exam Admin JPM SRO A4 Rev. 1 Appendix C Evaluator Note: START TIME: Performance Step: 1 Standard:

Comment: ./ -Denotes a Critical Step Page 3 of 7 PERFORMANCE INFORMATION Form ES-C-1 Start Time for this JPM begins when the individual has been briefed OBTAIN EAL FLOW PATH. Obtains EAL Flow Path. (EP-EAL is an allowed reference) 2009B NRC Exam Admin JPM SRO A4 Rev. 1 Appendix C Evaluator Note: START TIME: Performance Step: 1 Standard:

Comment: ./ -Denotes a Critical Step Page 3 of 7 PERFORMANCE INFORMATION Form ES-C-1 Start Time for this JPM begins when the individual has been briefed OBTAIN EAL FLOW PATH. Obtains EAL Flow Path. (EP-EAL is an allowed reference) 2009B NRC Exam Admin JPM SRO A4 Rev. 1 Appendix C -/ Performance Step: 2 Standard:

Comment: STOP TIME: Terminating Cue: -/ -Denotes a Critical Step Page 4 of 7 PERFORMANCE INFORMATION CLASSIFY EVENT Identifies an Site Area Emergency (2-4-3), Form ES-C-1 DAMAGE TO SPENT FUEL with ANY SPENT FUEL POOL AREA RAD MON > 700 mRlHR Basis: Damage to spent fuel in the Fuel Handling Building is assessed to determine if a single or multiple assemblies are affected.

Trigger points for the FHB area radiation monitors were calculated to provide a symptomatic indication of damage the affected assembly(s).

The 700 mRlHR criteria is the dose rate expected at the monitor nearest the damaged assembly(s) based on the expected dose rate from damaging more than 1 spent fuel assembly that had recently been removed from the reactor. CLASSIFICATION GUIDANCE:

Fuel handling accidents are analyzed as part of the HNP Licensing Basis. These accidents (as demonstrated through evaluation) are not expected to exceed Part 100 limits. Emergency filtration units are available to mitigate the consequences of these accidents.

Event classification stated to evaluator.

ENDOFJPM 2009B NRC Exam Admin JPM SRO A4 Rev. 1 Appendix C -/ Performance Step: 2 Standard:

Comment: STOP TIME: Terminating Cue: -/ -Denotes a Critical Step Page 4 of 7 PERFORMANCE INFORMATION CLASSIFY EVENT Identifies an Site Area Emergency (2-4-3), Form ES-C-1 DAMAGE TO SPENT FUEL with ANY SPENT FUEL POOL AREA RAD MON > 700 mRlHR Basis: Damage to spent fuel in the Fuel Handling Building is assessed to determine if a single or multiple assemblies are affected.

Trigger points for the FHB area radiation monitors were calculated to provide a symptomatic indication of damage the affected assembly(s).

The 700 mRlHR criteria is the dose rate expected at the monitor nearest the damaged assembly(s) based on the expected dose rate from damaging more than 1 spent fuel assembly that had recently been removed from the reactor. CLASSIFICATION GUIDANCE:

Fuel handling accidents are analyzed as part of the HNP Licensing Basis. These accidents (as demonstrated through evaluation) are not expected to exceed Part 100 limits. Emergency filtration units are available to mitigate the consequences of these accidents.

Event classification stated to evaluator.

ENDOFJPM 2009B NRC Exam Admin JPM SRO A4 Rev. 1 Appendix C Page 5 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 20098 NRC Exam Admin JPM SRO A4 -Classify an event Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ------------------------------

20098 NRC Exam Admin JPM SRO A4 Rev. 1 Appendix C Page 5 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 20098 NRC Exam Admin JPM SRO A4 -Classify an event Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response:

Result: SAT UNSAT Examiner's Signature:

Date: ----------------------------

20098 NRC Exam Admin JPM SRO A4 Rev. 1 Appendix C Initial Conditions:

Initiating Cue: Page 6 of 7 JPM CUE SHEET Form ES-C-1 A refueling outage has just been completed and a plant heat up is being performed lAW GP-002, Normal Plant Heatup From Cold Solid to Hot Subcritical Mode 5 to Mode 3. Using the attached information sheet and the EAL Flow Path, classify the event. Mark the EAL Flow Path appropriately.

THIS IS A TIME CRITICAL JPM 2009B NRC Exam Admin JPM SRO A4 Rev. 1 Appendix C Initial Conditions:

Initiating Cue: Page 6 of 7 JPM CUE SHEET Form ES-C-1 A refueling outage has just been completed and a plant heat up is being performed lAW GP-002, Normal Plant Heatup From Cold Solid to Hot Subcritical Mode 5 to Mode 3. Using the attached information sheet and the EAL Flow Path, classify the event. Mark the EAL Flow Path appropriately.

THIS IS A TIME CRITICAL JPM 2009B NRC Exam Admin JPM SRO A4 Rev. 1 Appendix C Page 7 of 7 JPM CUE SHEET CLASSIFICATION INFORMATION SHEET Form ES-C-1 A refueling outage has just been completed and a plant heat up is being performed lAW GP-002, Normal Plant Heatup From Cold Solid to Hot Subcritical Mode 5 to Mode 3. Current plant conditions are:

RCS Temp 180°F

RCS Pressure 345 psig * 'A' RHR pump is in operation Fuel handlers are performing a fuel shuffle and moving assemblies from the 'A' Fuel Pool to 'B' Fuel Pool. An emergency landing was being attempted by an aircraft returning to RDU. The pilot has lost control and the aircraft has impacted on the west side of the Fuel Handling Building.

The side of the building has suffered external damage and a fire is burning at the impact site. The impact was so severe that a fuel assembly being moved has dropped from the Fuel Bridge Crane and ruptured.

The highest Fuel Building Radiation monitor is reading 825 mr/hr. Classify the event Name ________________________________________________

__ Record your classification here and return to the examiner.

EAL Classification:

________________________

_ 2009B NRC Exam Admin JPM SRO A4 Rev. 1 Appendix C Page 7 of 7 JPM CUE SHEET CLASSIFICATION INFORMATION SHEET Form ES-C-1 A refueling outage has just been completed and a plant heat up is being performed lAW GP-002, Normal Plant Heatup From Cold Solid to Hot Subcritical Mode 5 to Mode 3. Current plant conditions are:

RCS Temp 180°F

RCS Pressure 345 psig * 'A' RHR pump is in operation Fuel handlers are performing a fuel shuffle and moving assemblies from the 'A' Fuel Pool to 'B' Fuel Pool. An emergency landing was being attempted by an aircraft returning to RDU. The pilot has lost control and the aircraft has impacted on the west side of the Fuel Handling Building.

The side of the building has suffered external damage and a fire is burning at the impact site. The impact was so severe that a fuel assembly being moved has dropped from the Fuel Bridge Crane and ruptured.

The highest Fuel Building Radiation monitor is reading 825 mr/hr. Classify the event Name ________________________________________________

__ Record your classification here and return to the examiner.

EAL Classification:

________________________

_ 2009B NRC Exam Admin JPM SRO A4 Rev. 1

@@ Line 2: / Line 2: @@
 | number = ML100410114
 | issue date = 01/05/2010
-| title = Harris Initial Exam 2009-302 Draft Administrative JPMs
+| title = Initial Exam 2009-302 Draft Administrative JPMs
 | author name =
 | author affiliation = NRC/RGN-II

ML100410114: Difference between revisions

Revision as of 18:53, 16 April 2019

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