ML100410110

Initial Exam 2009-302 Final Administrative JPMs

ML100410110
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Site:	Harris
Issue date:	01/05/2010
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IR-09-302
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{{#Wiki_filter:Appendix C Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of testing: Page 1 of 8 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 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: The plant was at 100 percent power when. a Small Break LOCA Initiating Cue: occurred. All RCPs 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 Final Nov. 30, 2009 Appendix C Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of testing: Shearon Harris Page 1 of 8 Worksheet Response to Voids In Reactor Vessel Calculate Reactor Vessel Maximum Vent Time EPE El0 EK3.2 RO 3.2 SRO 3.7 Form ES-C-l Task No.: 301179H601 JPM No.: 2009B NRC Exam Admin JPM RO Al-l NRC Examiner: Date: __ Simulated Pertormance: Actual Pertormance: 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 CondHlons: Initiating Cue: The plant was at 100 percent power when. a Small Break LOCA occurred. All Reps 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

s 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 MeR timer. 2009B NRC Exam Admin JPM RO A 1-1 Rev Final Nov. 30, 2009

Appendix C Page 2 of 8 Worksheet Form ES-C-1 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: Time Critical Task: Validation Time: Step 2 Step 3 Step 4 Step 5 FRP-1.3 Figure 2 and Attachment 1 (Rev. 16) No 10 minutes Critical Step Justification 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 20098 NRC Exam Admin JPM RO A1-1 Rev Final Nov. 30,2009 AppendixC Page 2 of 8 Worksheet Form ES-C-l 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 Step 2 Step 3 Step 4 Step 5 Critical Step Justification 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 RO AI-I Rev Rnal Nov. 30, 2009

Appendix C START TIME: Performance Step: 1 Standard: Comment: ./ Performance Step: 2 Standard: Comment: ./ Performance Step: 3 Standard: Comment: ./ - Denotes a Critical Step Page 3 of 8 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 provided Containment temperature of 195°F Containment Volume at STP 'A' = 1702094.66 FT3 FRP-I.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 Final Nov. 30, 2009 AppendixC STARTnME: Performance Step: 1 Standard: Comment: Performance Step: 2 Standard: Comment: Performance Step: 3 Standard: Comment: ./ - Denotes a Critical Step Page 3 of 8 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-1.3 Attachment 1 Step 1 Calculate the maximum venting time using Attachment 1. Calculate Containment Volume at STP 'A' in FT' Using the provided Containment temperature of 195°F Containment Volume at STP 'A' = 1702094.66 FT' FRP-I.3 Attachment 1 Step 2 Determine Maximum Hydrogen volume that can be vented 'B' in FT' USing provided Containment Hydrogen Concentration of 2.15 percent determine maximum Hydrogen volume that can be vented 'B' = 14467.80 FT' 2oo9B NRC Exam Admin JPM RO A1-1 Rev Final Nov. 30, 2009

Appendix C ./ Performance Step: 4 Standard: Comment: ./ Performance Step: 5 Standard: Comment: Terminating Cue: STOP TIME: ./ - Denotes a Critical Step Page 4 of 8 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 FT3/MIN (Tolerance 4950 - 4750 FT3/MIN) FRP-I.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 Final Nov. 30,2009 Appendix C ./ Performance Step: 4 Standard: Comment: Performance Step: 5 Standard: Comment: Terminating Cue: STOP TIME: "

• Denotes a Critical Step Page 4 of 8 PERFORMANCE INFORMATION FRP-f.3 Attachment 1 Step 3 Form ES'C'1 Determine Hydrogen flow rate as a function of ReS pressure 'C' in FT'/MIN.

Determines from Figure 2 that 1560 psig corresponds to 4850 FT'/MIN (Tolerance 4950 - 4750 FT'/MIN) FRP-I.3 Attachment 1 Stap 4 Calculate maximum venting time '0' in minutes. Calculates 2.98 mlnutea (2 minutes and 59 seconds) T o/erance +/- 5 seconds 3 min 4 seconds to 2 min 54 seconds When calculation Is returned ENDOFJPM 2009B NRC Exam Admin JPM RO A 1-1 Rev Final Nov. 30, 2009

Appendix C Page 5 of 8 PERFORMANCE INFORMATION KEY RESPONSE 1'0 VOIDS IN R8ACTOR: VBSS!I. Form ES-C-1 'IOOU 2: HYDROOINfLOV RA'lI VERSUS Res PRESSOR! 6000 3000 .2000 10'GO o 400 IOP-fU-!.l I -/ - Denotes a Critical Step 800 1200 11560.100 2000 ReS PRESSURE (PSI6) Rev. 16 I Paae 21 of 23 2009B NRC Exam Admin JPM RO A1-1 Rev Final Nov. 30, 2009 AppendixC Page 5 of 8 PERFORMANCE INFORMATION KEY RlSPORSB '1'0 VOIDS DI' RIAC'l'Ol vasSEL Form ES-C-1 lIGORB 2: HtDJtOGIlf fLOIf lA'l'J VDSVS Res PRlSSUlI 6000 4000 3000 2000 1000 o o 400 !OP-'Rr-I.l I " - Denotes a Critical Step SOO 1200 !!@Jo. 2000 2400 ReS PRESSORE (PSIG) lev. 16 ,. e 2:l of 23 2009B NRC Exam Admin JPM RO A1-1 Rev Final Nov. 30, 2009

Appendix C Page 6 of 8 PERFORMANCE INFORMATION KEY RESPOHSK TO VOLDS IN RBACTOR VBSSIL AttacluMnt 1 Sheet 1 of 1 DlSTKUCTIONS fOR DITBlUUNDIG VDlTING TIn Form ES-C-1

1.

DeterUne CHHr VolUlle at STP 'A';

z.

A - U.Z66 x 106 n 3 ) x 4'92°, (CNKT Ulllperature G I! + 460"lt) 1 195 GF I A.11702094.66 (n) Deterldne Ku111Ua t!~~, volWM tbat can be vented 'B'; B - <3,0\\ - aT H *i15 Concentratign) J:: ' A' 11702094.66 I 100Y. B _ 114467.80 I (BT3)

3.

Deterll1ne Hydrogen flow rate a8 a function of RCS pressure 'C';

a.

Check ReS pressure and mark on figure 2.

b.

Udng rrilure 2. reacl bydro&en flow rate *C*. ITOlerance 4750 - 4950 I B 2.98 !faxilllUli venting tiae - IOP-UP-I.3 I c Tolerance 2 min 54 seconds 3 min 4 seconds Rev. 16 I c - 14850 I (FT'/lmo 2 min and 59 seconds J) - (tIllWTBS) Pale 22 of 23 ./ - Denotes a Critical Step 2009B NRC Exam Admin JPM RO A1-1 Rev Final Nov. 30,2009 AppendixC Page 601 8 PERFORMANCE INFORMATION KEY RBSl'ONS& TO VOIDS III UACTOa. VBSSKL AttacllMat. 1 Sheet: 1 of 1 DISTlUCTIONS POI DITBlUIlNDIG VlllTING TIKI Form ES-C-'

1.

D.te~ Qllft'Vol.. a't STP 'A'; A - U.266 J: 106 "3) z ",a°l, (ClIIT '[ ** perature *r + 460-1.) 1.95°F 1

• • 1,702094_66 (n')

Ceura1.n.e M*:l~~~' velUM that can be Yea'te4 'a'; B - (J. 0,

• COQCl;Quu.t.onl :a:
• A' 11702094.66 I 100'1.
  • 1.4467.80 1 (n"

3.

~.ra1a. Hydro,eo flow rate *** tunction of RCS pre ** ure 'C': Check aes pre,aura.nd.. rk OD liKura 2. b_ ITOIefance 4750 - 4950 1

4.

Calc.uhte aaz1.ua ventiDI tiM 'D' ; ~ ... veotlDI UM - -- 1 2.98 I BOP'lRP-I.3 c TOlerance 2 min 54 seconds 3 mio 4 seconds Rw.16 D* I 2 min and 59 seconds (KINUTIS) PaeZ2of21 .r - Denotes a Critical Step 20096 NRC Exam Admin JPM RO A,-, Rev Final Nov. 30, 2009

Appendix C Page 7 of 8 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 20098 NRC Exam Admin JPM RO A1 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: 20098 NRC Exam Admin JPM RO A1-1 Rev Final Nov. 30,2009 Appendix C Page 7 of B VERIFICATION OF COMPLETION Form ES-C-l Job Performance Measure No.: 2oo9B NRC Exam Admin JPM RO Al-l - Response to Voids In Reactor Vessel-Calculate Reactor Vessel Maximum Vent Time Examinee's Name: Date Performed: Facility Evalualor: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiner's Signature: Date: 2oo9B NRC Exam Admin JPM RO Al-l Rev Final Nov. 30, 2009

Appendix C Initial Conditions: Initiating Cue: Form ES-C-1 JPM CUE SHEET The plant was at 100 percent power when a Small Break LOCA occurred. All RCPs 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 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 Final Nov. 30, 2009 AppendixC Initial Condillons: Inilialing Cue: Form ES-C-1 JPM CUE SHEET The plant was at 100 percent power when a Small Break LOCA occurred. All Reps 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. tt 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 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 Final Nov. 30. 2009

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 A1-2 Rev. Final Nov. 30,2009 AppendixC Facility: Task Hie: KIA

Reference:

Examinee: Facility Evaluator: Method of testing: Page 1 of 12 Worksheet Form ES-C-l Shearon Harris Perfonn A Manual Shutdown Margin Calculation G2.1.25 RO 3.9 SRO 4.2 Task No.: ool004Hl0l JPM No.: 2oo9B NRC Exam Admin JPM RO A 1-2 NRC Examiner: Oate: __ _ Simulated Pertormance: Actual Pertonnance: 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 Pertormance Measure will be satisfied. Initial Conditions: Innlatlng 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 ReS boron concentration is 1140 ppm NO rods are believed to be immovable I untrippable POWERTRAX is NOT available The CRS has directed you to complete OST-l036, 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 perfonned. 2oo9B NRC Admin Exam RO AI-2 Rev. Final Nov. 30, 2009

Appendix C Page 2 of 12 Worksheet Form ES-C-1 Task Standard: OST-1036, Attachment 3, Manual SDM Calculation (Modes 1 and 2), completed with SDM 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 A 1-2 Rev. Final Nov. 30, 2009 AppendixC Page 2 of 12 Worksheet Form ES-C*l Task Standard: OST-l036, Attachment 3, Manual SDM Calculation (Modes 1 and 2), completed with SDM of 5195 +/- 75 pcm (tolerance baaed on total 01 curves used and their division readability) Required Materials: Calculator General

References:

OST*l036, Shutdown Margin Calculation Modes t*5 (Rev. 40) Curve Book (Cycle 16) Handouts: OST*l036, Shutdown Margin Calculation Modes 1*5 (Rev. 40) Time Critical Task: No Validation Time: 20 minutes Step 3 Step 6 Step 7 Step 9 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 cOIva 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 01 the inputs to the calculation. The total shutdown margin was the task that the CRS directed applicant to perform. 2oo9B NRC Admin Exam RO At-2 Rev. Final Nov. 30,2009

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% OST-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 A1-2 Rev. Final Nov. 30,2009 AppendixC START TlME: Perlormance Step: 1 Standard: Comment: Perlormance Step: 2 Standard: Comment: y Perlormance Step: 3 Standard: Comment: Performance Step: 4 Standard: Comment: ./ - Denotes Critical Steps Page 3 of 12 PERFORMANCE INFORMATION OST-l036 Form ES-C-l 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-1D36 Attachment 3 Step 1 Enters Reactor Power Level Refers to given conditions and enters 52% OST-1D36 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-103& Attachment 3 Step 3 Enters core 8urn Up Refers to given conditions and enters 140 EFPD 2009B NRC Admin Exam RO AI-2 Rev_ Final Nov. 30, 2009

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. Final Nov. 30,2009 AppendixC 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-t036 Attachment 3 Step 4 Enters ReS Boron Concentration Refers to initial conditions and enters 1140 ppm Form ES-C-l ATT 3, STEP 5 NOT PERFORMED SINCE VALUE IS INCLUDED AS PART OF ATTACHMENT_ OST-l036 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-l036 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) 2oo9B NRC Admin Exam RO Al-2 Rev. Final Nov. 30, 2009

Appendix C Performance Step: 8 Standard: Comment: ./ 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: ./ - Denotes Critical Steps When OST-1036, Attachment 3, Manual SOM Calculation is completed. ENDOFJPM 2009B NRC Admin Exam RO A 1-2 Rev. Final Nov. 30,2009 AppendixC Performance Step: 8 Standard: Comment: v' Performance Step: 9 Standard: Comment: Page 5 of 12 PERFORMANCE INFORMATION OST*l036 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*l036 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*l036 Section 7.3 Performance Step: 10 Signs off Section 7.3 steps Standard: Signs off steps as complete Comment: Terminating Cue: STOP TIME: v' - Denotes Cr~ical Steps When OST-l036, Attachment 3, Manual SDM Calculation Is completed. END OF JPM 20098 NRC Admin Exam RO Al*2 Rev. Final Nov. 30, 2009

AppendixC Page 6 of 12 PERFORMANCE INFORMATION KEY HARRIS UNIT 1 CYCLE 16 CRITICAL BORON CONCENTRATION V$. CYCLE EXPOSURE AT HFP. MO, EQUlUBRIUM XENON CONDmoNS !eFPDlDIV CYCL.EEXPOSURE (EFPD) IDetermination of Boron concen1ration for 140 EFPD CURVE NO. ."lII-'""'I"fr-",~~r---- REV NO. ~~~ ORIGINATOR +Iol~=lPIiWIo,l~"=--- DATE SUPERVISOR ~J;A~~Q~~4== DATE SUPER1NTENOENT

• SHIFT OPERATIO NS OATE Form ES-C-1

./ - Denotes Critical Steps 20098 NRC Admin Exam RO A 1-2 Rev. Final Nov. 30, 2009 Appendix C ,.. 0 '000 1700 '000 '600 '400 i '300 iii ' Page 6 of 12 PERFORMANCE INFORMATION KEY HARRIS UNIT 1 CYCLE 16 CRITlCAL BORON CONCENTRATION ¥s. CYCLE EXPOSURE AT HFP. AAO. EQUIUBRIUM XENON CONDITIONS ~~ N.l000 z 8... ~ 800 600 ~ 500... 300 200 'DO 10PPM'DIV o

• nfPMIIV CYCLE£XPOSURE (EFPD)

IDeferminaiion of Boron concentration for 140 EFPD CURVE NO. 1~~~~~~2~~ REV NO-ORIGINATOR DATE SUPERVISOR DATE ....::tl""+"1 SUPEIIINTENDENT - SHIFT OPERATIONS CATE Form ES-C-l 01' - Denotes Critical Steps 2oo9B NRC Admin Exam RO Al-2 Rev. Final Nov. 30. 2009

Appendix C 2 40 2 20 2 00 ~ 1 ~ 80 n ~ '~ ~O.1 ~II\\ / J ~cj GO '" r-I ~ 40 !.JI',/'r / 20 (0 ~28 I ,_ft Page 7 of 12 PERFORMANCE INFORMATION HARRIS UNIT 1 CYCLE 16 ROD 1NSERTION LIMITS (46 8,,2 5) (~ ~.2 22E ~ 'r / V ,,' V ~, ~ ~ II' '( ... ~ ~~ ~ ~.", B~ f<< V / l/ ~, V ,.; lr If' V. t:. 'I 19 V ~ J'V I'J / i/ ' !--- ~- /,/

I L L

'~.... I\\. F,J" r ~ ~ p'

• E ~N KI 8D

.)V J .~ V 60 y~ /I' / 40 / / 110 10 /./ I 20 "j / ~ 1/ (O,C loG) 0 ~ 0 10 2D 30 40 e GO 10 80 90 1 00 PERCENT OF RATED THERMAL POWER CURVE NQ. R!:VNo. ~ ~~== ~~~~~~;;::::;-:-:: SU~NTeNDENT~ SHIFT OPERATIONS DATE q /..-if Form ES-C-1 {1oo.225) ('00,196) (100,186) ./ - Denotes Critical Steps 2009B NRC Admin Exam RO A 1-2 Rev. Final Nov. 30, 2009 AppendixC o 10 20 Page 7 of 12 PERFORMANCE INFORMATION 40 70 8G Form ES-C-1

o.

100 PERCENT Of RATED THERMAL POWER CURI/ENO. ORICWfoM. TOR SUPERVISOR SUPERINTENDEPCT

• SHIFT OPERATIONS

~ - Denotes Critical Steps 2009B NRC Admin Exam RO A1-2 Rev_ Final Nov. 30, 2009

Appendix C o -2CClO -22DO -2400 o Page 8 of 12 PERFORMANCE INFORMATION KEY HARRIS UNIT 1 CYCLE 16 POWER DEFECT vs. POWER LEVEL for VARIOUS BORON CONCENTRATIONS BOL (0 Iii EFl'D :s. 180) 20 60 80 POWER LEVEL (PERCENT) Form ES-C-1 2tOOppm ',"ppm 1500 ppm 100 CURVE NO. j"""-.otr--"'l~~"""--- REV NO. 0 ORIGINATOR ¥~~~~~~~_ ~TTEE ~. SUPERVISOR UP'\\ SiJPERJNTENm;NT - SHIFT OPERATDNS DATE ~ -/ - Denotes Critical Steps 20098 NRC Admin Exam RO A 1-2 Rev. Final Nov. 30,2009 Appendix C

lOPCMIDIV

, %lDIV Page 8 of 12 PERFORMANCE INFORMATION KEY HARRIS UNIT 1 CYCLE 16 POWER DEFECT vs_ POWER LEVEL for VARIOUS BORON CONCENTRATIONS BOL (0 ~ g:JlD~ teo)

2.

.0 POWER LEVEL IPERCEN1) ORIGINATOR DATE Form ES-C-l 2tOOppm tlOO ppM UO'ppfft 100 CURVE NO. l~~~~~~~~= REVNO. SUPERVISOR DATE l;jj.;o:.If'l'::j SUPERlNTENlreNT - SHIFT OPERATIONS DATE ~ - Denotes Critical Steps 2009B NRC Admin Exam RO AI-2 Rev. Final Nov. 30, 2009

Appendix C 1_ 1700 1_ 1500 1400 1300 1200 1100 1000 -900 ..000 1-72~ -600 -600 400 -300 -200

• 100 IV 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. EQUIUBRIUM XENON ~ m - - ~ ~ .-.. r' ~ g~ ~ 60 80 ~ 120 140 160 180 2QO 220 Form ES-C-1

• 18

~17 .16 -15 2 40 fiSTE'TDIV 103 2.1 .~----------------.--------~~-----------. BAtoIICD 128

• • ----~~~K~C~-------*

~~:::~~ ~~:jJii~a.&,If+~-- ;VTEre NO

• ~

SUPERVISOR ~ SUPERINTENDENT - SHiFf OPERAilOHS DA TE Cr ./

• Denotes Critical Steps 2009B NRC Admin Exam RO A 1-2 Rev. Final Nov. 30,2009 AppendixC

-1800 -1'" -1Il00 .-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 BOLCOSEFPDS160). HFP. EQUIUIlIUUMXENON Form ES-C-l -18 -17 _1. -10 -14 -13 52

• 12 ;i!

ill -11 z -1. ~ ... g .. ~ ~ -7 i .. 3 i -5 ! -4 -3 -2 -1

==1-. 40 60 80 120 140 160 180 200 220 240 ~.. =-___==-----..;2:1 CURVE NO. ORIGINATOR SUPERVISOR SUPERINTEND£NT - SHIFT OPERATLOHS v' - Denotes Critical Steps 2009B NRC Admin Exam RO AI-2 Rev. Final Nov. 30, 2009

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 i... ___ ... pcm 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 CB =" 6980 - 1060 +/ 725 +/ 0 (e) (a) " ./ - Denotes Critical Steps (b) (c) ( d ) 5195 +/- 75 pcm ( e ) 2009B NRC Admin Exam RO A 1-2 Rev. Final Nov. 30,2009 AppendixC Page 10 of 12 PERFORMANCE INFORMATION EXAMINER CALCULATION KEY (SHADED AREA BELOW INDICATES DATA ALREADY PROVIDED) Manual SOM Calculation (Modes 1 and 2)

1. Reactor power level.

2. Rod insertion limit for the above power level 96+2 steps on bank

3. Bum up (POWERTRAXIMCR Status Board).

4. Present RCS Boron Concentration NOTE: Use absolute values of numbers obtained from curves.

Form ES-C-1 52 0 140 EFPO 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-' 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 SOM C, =. 6980 (e) (a ) .(' - Denotes Critical Steps 1060 +/- 50 725 +/- 25 (b) (c) o ( d ) 5195 +/- 75 pcm (. ) 2009B NRC Admin Exam RO A1-2 Rev. Final Nov. 30, 2009

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 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. Final Nov. 30,2009 AppendixC Page 11 of 12 VERIFICATION OF COMPLETION Form ES-C-l Job Performance Measure No.: 2009B NRC EXAM Admin JPM RO AI 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 Examine(s Signature: Date: 2009B NRC Admin Exam RO AI-2 Rev. Final Nov. 30, 2009

Appendix C Initial Conditions: Initiating Cue: Form ES-C-1 JPM CUE SHEET 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 A1-2 Rev. Final Nov. 30,2009 AppendixC Initial Conditions: Initiating Cue: Form ES-C-1 JPM CUE SHEET 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 ReS boron concentration is 1140 ppm NO rods are believed to be immovable I untrippable POWEATRAX is NOT available The CAS has directed you to complete OST-1036, Shuldown Margin Calculation Modes 1-5, Section 7.3, 'Manual SDM Calculation (Modes 1 and 2)' for current plant conditions. NOTE: For this JPM assume Independant verification has been performed. 2009B NACAdmin Exam AO A1-2 Aev. Final Nov. 30,2009

Appendix C Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of testing: Page 1 of 12 PERFORMANCE INFORMATION Shearon Harris Task No.: Form ES-C-1 Determine Clearance Requirements JPM No.: 2009B NRC Exam for a CSIP Admin JPM RO A2 G 2.2.13 RO 4.1 SRO 4.3 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 plant is defueled. CSIP 1 B-SB is required to be placed under a clearance for seal replacement. Cooling water and lube oil systems are NOT required to be placed under clearance. There is no known isolation boundary leakage. You have been directed to determine the clearance requirements for CSI P 1 B-SB using the SFDs, and System Operating Procedures, as necessary. Provide the clearance installation sequence. The complete electrical and mechanical protection and the necessary vent and drain paths. The MSO has approved using single valve isolation. NOTE: LISTING OF CIT'S IS NOT REQUIRED FOR THIS JPM. IT IS NOT INTENDED THAT YOU ACTUALLY GENERATE A CLEARANCE. ONLY PROVIDE THE EVALUATOR WITH A LISTING OF THE REQUIRED COMPONENTS, POSITIONS AND THE INSTALLATION SEQUENCE * ./ - Denotes Critical Steps 2009B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30,2009 AppendixC Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Metl10d of testing; Page 1 of 12 PERFORMANCE INFORMATION Shearon Harris Task No.: Form ES*C*1 Determine Clearance Requirements JPM No.: 2009B NRC Exam for a CSIP Admin JPM RO A2 G2.2.13 RO 4.1 SR04.3 NRC Examiner: Date: Simulated Performance: Actual PeMorrnance: 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: Inilialing Cue: The plant is defueled. CSIP 1 B-SB is required to be placed under a clearance for seal replacement. Cooling water and lube oil systems are NOT required to be placed under clearance. There is no known isolation boundary leakage. You have been directed to determine the clearance requirements for CSIP 1B*SB using the SFDs, and System Operating Procedures, as necessary. Provide the clearance installation sequence, The complete electrical and mechanical protection and the necessary vent and drain paths. The MSO has approved using single valve isolation. NOTE: LISTING OF CIT'S IS NOT REQUIRED FOR THIS JPM. IT IS NOT INTENDED THAT YOU ACTUALLY GENERATE A CLEARANCE. ONLY PROVIDE THE EVALUATOR WITH A LISTING OF THE REQUIRED COMPONENTS, POSITIONS AND THE INSTALLATION SEQUENCE * ./

• Denotes Critical Steps 2oo9B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30, 2009

Appendix C Task Standard: Required Materials: Page 2 of 12 PERFORMANCE INFORMATION Form ES-C-1 Provide complete electrical and mechanical isolation of CSIP 18-S8 OPS-NGGC-1301, Equipment Clearance, pgs. 38 and 41, Rev. 20 OP-107, Chemical and Volume Control System, Rev. 78 OP-107.03, Rev. 5 SFD 2165 S-1304 and S-1305 Additional copies of page 12 of this JPM available General

References:

OPS-NGGC-1301, Equipment Clearance, Rev. 20 OP-107, Chemical and Volume Control System, Rev. 78 OP-107.03, Rev. 5 SFD 2165 S-1304 and S-1305 Handouts: JPM Cue Sheets SFD 2165 S-1304 and S-1305 OP-107, Chemical and Volume Control System Rev. 78 OPS-NGGC-1301, Equipment Clearance Rev. 20 Time Critical Task: No Validation Time: 25 minutes Step 2 Step 3 Step 4 Step 5 Step 6 Step 7 Step 8 Critical Step Justification Critical to remove power from the pump for personnel protection. Critical to isolate suction source to allow pump to be depressurized. Critical to isolate discharge path to allow pump to be depressurized. Critical to isolate miniflow path to allow pump to be depressurized. Critical to isolate miniflow path to allow pump to be depressurized. Critical to open vent path to allow pump to depressurize. Critical to open drain path to allow pump to depressurize. 0/ - Denotes Critical Steps 20098 NRC Exam Admin JPM RO A2 Rev. Final Nov. 30,2009 AppendixC Task Standard: Required Materials: Page 2 of 12 PERFORMANCE INFORMATION Form ES-C-1 Provide complete electrical and mechanical isolation of CSIP 1B-SB OPS-NGGC-1 301, Equipment Clearance, pgs. 38 and 41, Rev. 20 OP-107, Chemical and Volume Control System, Rev. 78 OP-W7.03, Rev. 5 SFD 2165 S-1304 and S-1305 Additional copies of page 12 of this JPM available General

References:

OPS-NGGC-1301, Equipment Clearance, Rev. 20 OP-107, Chemical and Volume Control System, Rev. 78 OP-107.03, Rev. 5 SFD 2165 S-1304 and 501305 Handouts: JPM Cue Sheets SFD 2165 S-1304 and S-1305 OP-107, Chemical and Volume Control System Rev. 78 OPS-NGGC-1301, Equipment Clearance Rev. 20 Time Critical Task: No Validation Time: 25 minutes Step 2 Step 3 Step 4 Step 5 Step 6 Step 7 Step 8 Critical Step Justification Critical to remove power from the pump for personnel protection. Critical to isolate suction source to allow pump to be depressurized. Critical to isolate discharge path to allow pump to be depressurized. Critical to isolate miniflow path to allow pump to be depressurized. Critical to isolate miniflow path to allow pump to be depressurized. Critical to open vent path to allow pump to depressurize. Critical to open drain path to allow pump to depressurize. ./ - Denotes Critical Steps 2oo9B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30,2009

Appendix C START TIME: Performance Step: 1 Standard: Comment: Page 3 of 12 PERFORMANCE INFORMATION Form ES-C-1 Examiner provides applicant the required references. Obtain a copy of the appropriate drawings and procedures (OPS-NGGC-1301, OP-107, SFD 2165 S-1304 and 1305) Operator obtains a copy of OP-107 to determine electrical requirements. SFD 2165 S-1304 and S-1305 to determine mechanical requirements. OPS-NGGC-1301 to determine proper installation sequence for clearance. NOTE: SEE JPM ATTACHMENT FOR A COMPLETE LISTING OF EACH COMPONENT AND REQUIRED POSITION. JPM STEPS ARE NOT REQUIRED TO BE PERFORMED IN THE LISTED SEQUENCE * ./ Performance Step: 2 Standard: Comment: Examiners Note: ./ - Denotes Critical Steps Determine the electrical supply breaker for CSIP 1 B-SB Refers to OP-107 (or any other valid source) and determines the electrical supply breaker for CSIP 1 B-SB to be 6.9 KV Emergency Bus 1 B-SB, Cubicle 4 (BREAKER RACKED OUT) Also determines pump has MCB and ACP switch and includes a CIT on CSIP 'B' switch for each location CRITICAL TO REMOVE POWER FROM PUMP. NOTE: C/rs ARE NOT REQUIRED TO BE INCLUDED FOR CRITICAL PORTION OF THIS STEP 2009B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30, 2009 Appendix C START TIME: Performance Step: 1 Standard: Comment: Page 3 0112 PERFORMANCE INFORMATION Form ES-C-l Examiner provides applicant the required references_ Obtain a copy of the appropriate drawings and procedures (OP5-NGGC-1301, OP-l07, SFD 2165 S-1304 and 1305) Operator obtains a copy 01 OP-1 07 to determine electrical requirements_ SFD 2165 S-1304 and S-1305 to determine mechanical requirements. OPS-NGGC-1301 to determine proper installation sequence for clearance. NOTE: SEE JPM ATTACHMENT FOR A COMPLETE LISTING OF EACH COMPONENT AND REQUIRED POSITION. JPM STEPS ARE NOT REQUIRED TO BE PERFORMED IN THE LISTED SEQUENCE. v' Performance Step: 2 Standard: Comment: Examiners Note: ./ - Denotes Critical Steps Determine the electrical supply breaker for CSIP 1 B-SB Relers to OP-107 (or any other valid source) and detennines the electrical supply breaker lor CSIP lB-SB to be 6.9 KV Emergency Bus 1 B-SB, Cubicle 4 (BREAKER RACKED OUT) Also determines pump has MCB and ACP switch and includes a CIT on CSIP 'B' switch for each location CRITICAL TO REMOVE POWER FROM PUMP. NOTE: Clrs ARE NOT REQUIRED TO BE INCLUDED FOR CRITICAL PORTION OF THIS STEP 2oo9B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30, 2009

Appendix C ./ Performance Step: 3 Standard: Comment: ./ Performance Step: 4 Standard: Comment: ./ Performance Step: 5 Standard: Comment: Evaluator Note: ./ - Denotes Critical Steps Page 4 of 12 PERFORMANCE INFORMATION Determine the suction valve for CSIP 1 B-SB. Form ES-C-1 Refers to S-1305 and determines the suction valve for CSIP 1 B-SB to be 1CS-187, B CSIP Suction Isol Vlv (CLOSE) Determine the discharge isolation for CSIP 1 B-SB Refers to S-1305 and determines the valve to isolate CSI P 1 B-SB discharge is 1CS-197, B CSIP Discharge Isol Vlv (CLOSE) Determine the normal miniflow isolation for CSIP 1 B-SB. Refers to S-1305 and OP-107 and determines the valve to isolate normal miniflow path for CSIP 1B-SB is 1CS-196 SB, CHARGING/SI PUMP B-SB MINI FLOW ISOL, and power supply for valve is 1 B35-SB (Breaker 4E) (VALVE TO BE CLOSED WITH POWER REMOVED - LOCAL HANDWHEEL TO BE IN CLOSED) Also determines valve has MCB switch and includes a CIT on 1 CS-196 switch CIT IS NOT REQUIRED TO BE INCLUDED FOR SATISFACTORY COMPLETION OF THIS STEP. 2009B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30,2009 AppendixC Performance Step: 3 Standard: Comment: ./ Performance Step: 4 Standard: Comment: Performance Step: 5 Standard: Comment: Evaluator Note: ./ - Denotes Critical Steps Page 4 of 12 PERFORMANCE INFORMATION Determine the suction valve for CSIP 18oSB. Form ES-C-1 Refers to S-1305 and determines the suction valve for CSIP 1B-SB to be 1CS-1S7, B CSIP Suction lsol Vlv (CLOSE) Determine the discharge isolation for CSIP 1 B-SB Refers to S-1305 and determines the valve to isolate CSIP 1B-SB discharge is 1CS-197, B CSIP Discharge Isol Vlv (CLOSE) Determine the normal miniflow isolation for CSIP 1 B-S8. Refers to S-1305 and OP-107 and determines the valve to isolate normal miniflow path for CSIP 1B-SB is 1CS-196 SB, CHARGING/51 PUMP B-SB MINIFLOW ISOL, and power supply for valve is 1 B35-SB (Breaker 4E) (VALVE TO BE CLOSED WITH POWER REMOVED - LOCAL HANDWHEEL TO BE IN CLOSED) Also determines valve has MeB switch and includes a CIT on 1 CS-196 switch CIT IS NOT REQUIRED TO BE INCLUDED FOR SATISFACTORY COMPLETION OF THIS STEP. 2009B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30, 2009

Appendix C ./ Performance Step: 6 Standard: Comment: ./ Performance Step: 7 Standard: Comment: Page 5 of 12 PERFORMANCE INFORMATION Form ES-C-1 Determine the alternate miniflow isolation for CSIP 1 B-SB Refers to S-1304 and determines the valve to isolate alternate miniflow path for CSIP 1B-SB is 1CS-751, B CSIP Alt Mini Flow Man Isol (CLOSE) Determine the vent path for CSIP 1 B-SB Refers to S-1305 and determines the valve to vent CSIP 1B-SB is 1 CS-188, B CSI P Suction Px Isol Vlv (OPEN WITH CAP REMOVED) Evaluator Note: EITHER STEP 7 OR STEP 8 IS CRITICAL. ONE OR THE OTHER MUST BE PERFORMED, BUT NOT BOTH. HOWEVER, IF BOTH ARE PERFORMED, THIS IS ALSO ACCEPTABLE. ./ - Denotes Critical Steps 2009B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30, 2009 Appendix C '" Performance Step: 6 Standard: Comment: '" Performance Step: 7 Standard: Comment: Page 5 of 12 PERFORMANCE INFORMATION Form ES-C-1 Determine the alternate miniflow isolation for CSIP 1 B-SB Refers to 8-1304 and determines the valve to isolate alternate minillow path for CSIP 1B-SB is 1CS-751, B CSIP Alt Mini Row Man lsol (CLOSE) Determine the vent path for CSIP 1 B-SB Refers to S-1305 and determines the valve to vent CSIP 1B-SB is 1 CS-188, B CSI P Suction Px Isol Vlv (OPEN WITH CAP REMOVED) Evaluator Note: EITHER STEP 7 Qf1 STEP 8 IS CRITICAL. ONE Qf1 THE OTHER MUST BE PERFORMED, BUT NOT BOTH. HOWEVER, IF BOTH ARE PERFORMED, THIS IS ALSO ACCEPTABLE. '" - Denotes Critical Steps 2009B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30, 2009

Appendix C ./ Performance Step: 8 Standard: Comment: Evaluator Note: Evaluator Cue: Stop Time: ___ _ ./ - Denotes Critical Steps Page 6 of 12 PERFORMANCE INFORMATION Determine the drain path for CSIP 1 B-SB Form ES-C-1 Refers to S-1305 and determines the valves to drain CSIP 1B-SB discharge piping to be 1CS-189, B CSIP Casing Leak Off Drain Vlv, and 1CS-190, B CSIP Casing Leak Off Drain Isol Vlv (BOTH OPEN) EITHER STEP 7 OR STEP 8 IS CRITICAL. ONE OR THE OTHER MUST BE PERFORMED, BUT NOT BOTH. HOWEVER, IF BOTH ARE PERFORMED, THIS IS ALSO ACCEPTABLE. When applicant completes and returns clearance list. ENDOFJPM 2009B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30,2009 AppendixC ./ Performance Step: 8 Standard: Comment: Evaluator Note: Evaluator Cue: Stop Time: ___ _ ./ - Denotes Critical Steps Page 6 of 12 PERFORMANCE INFORMATION Determine the drain path for CSIP 1 B-SB Form ES-C-1 Refers to 5-1305 and delermines the valves to drain CSIP 1 B-SB discharge piping to be 1CS-189, B CSIP Casing Leak 011 Drain Vlv, and 1CS-190, B CSIP Casing Leak Off Drain 1501 Vlv (BOTH OPEN) EITHER STEP 7 OR STEP 81S CRITICAL. ONE OR THE OTHER MUST BE PERFORMED, BUT NOT BOTH. HOWEVER, IF BOTH ARE PERFORMED, THIS IS ALSO ACCEPTABLE. When applicant completes and returns clearance list. ENDOFJPM 2009B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30, 2009

Appendix C Page 7 of 12 Form ES-C-1 VERIFICATION OF COMPLETION KEY JPM ATTACHMENT COMPONENT LISTING AND REQUIRED POSITIONS COMPONENT

1) CSIP 18-S8 P.S. - 6.9 KV Emergency 8us 18-S8, Cubicle 4.

2) 1CS-196 S8, CHARGING/SI PUMP 8-S8 MINIFLOW ISOL

3) 1 CS-196 S8 P.S. - 1835-S8, 8reaker 4E

4) 1CS-197, 8 CSIP Discharge Isol Vlv.

5) 1CS-187, 8 CSIP Suction Isol Vlv.

6) 1CS-751, 8 CSIP Alt Mini Flow Man Isol.

POSITION Racked Out Closed Off Shut Shut Shut

7) Accept - EITHER one vent path OR the drain path or BOTH a vent path and drain path.

NOTE: Any of the following vent valves will support a vent path for the pump. One or more of these vent paths are required to be identified VENT PATHS 1CS-188, 8 CSIP Suction Px Isol Vlv -OR-1CS-802, ECCS Outter Vent Vlv CSIP 8 Disch Upstream of 1 CS-192 - AND-1CS-801, ECCS Inner Vent Vlv CSIP 8 Disch Upstream of 1 CS-192 -OR-1 CS-800, ECCS Outter Vent Vlv CSIP 8 Suct Downstream of 1 CS-187 - AND-1CS-799, ECCS Inner Vent Vlv CSIP 8 Suct Downstream of 1 CS-187 DRAIN PATH 1CS-189, 8 CSIP Casing Leak Off Drain Vlv - AND-1CS-190, 8 CSIP Casing Leak Off Drain Isol Vlv NOTE - CITs are NOT required for satisfactory completion of JPM. Uncapped/Open Uncapped/Open Open Uncapped/Open Open Open Open 20098 NRC Exam Admin JPM RO A2 Rev. Final Nov. 30,2009 AppendixC Page 7 of 12 Form ES-C-1 VERIFICATION OF COMPLETION KEY JPM ATTACHMENT COMPONENT USTING AND REQUIRED POSITIONS COMPONENT

1) CSIP 1B-SB P.S. - 6.9 KV Emergency Bus 1 8-S8, Cubicle 4.

2) 1CS-196 S8, CHARGING/SI PUMP 8-S8 MINIFLOW ISOL

3) 1CS-196 S8 P.S. -1835-S8, 8reaker 4E

4) 1CS-197, B CSIP Discharge Isol Vlv.

5) 1CS-1B7, 8 CSIP Suc1ion Isol Vlv.

6) 1CS-751, B CSIP Alt Mini Flow Man Isol.

POSITIQN Racked Out Closed Off Shut Shut Shut

7) Accept - EITHER one vent path OR the drain path or BOTH a vent path and drain path.

NOTE: Any of the following vent valves will support a vent path for the pump. One or more of these vent paths are required to be identified VENT PATHS 1CS-1BB, 8 CSIP Suc1ion Px Isol Vlv -OR-1 CS-B02, ECCS Outter Vent Vlv CSI P B Disch Upstream of 1 CS-192 - AND-1CS-B01, ECCS Inner Vent Vlv CSIP 8 Disch Upstream of 1 CS-192 -OR-1 CS-Boo, ECCS Outter Vent Vlv CSIP 8 Suc1 Downstream of 1 CS-1B7 -AND-1CS-799, ECCS Inner Vent Vlv CSIP 8 Suc1 Downstream of 1 CS-1B7 DRAIN PATH 1 CS-1B9, 8 CSI P Casing Leak Off Drain Vlv - AND-1CS-190, 8 CSIP Casing Leak Off Drain Isol Vlv NOTE - CITs are NOT required for satisfactory completion of JPM. Uncapped/Open Uncapped/Open Open Uncapped/Open Open Open Open 20098 NRC Exam Admin JPM RO A2 Rev. Final Nov. 30, 2009

Appendix C Page 10 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: Determine Clearance Requirements for a CSIP 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 A2 Rev. Final Nov. 30,2009 Appendix C Page 10 of 12 Form ES-C-l VERIFICATION OF COMPLETION Job Periormance Measure No.: Determine Clearance Requirements for a CSIP Examinee's Name: Date Perlormed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Resu~: SAT UNSAT Examiner's Signature: ______________ Date: 20098 NRC Exam Admin JPM RO A2 Rev. Final Nov. 30,2009

Appendix C Initial Conditions: Initiating Cue: Form ES-C-1 JPM CUE SHEET The plant is defueled. CSIP 1 B-SB is required to be placed under a clearance for seal replacement. Cooling water and lube oil systems are NOT required to be placed under clearance. There is no known isolation boundary leakage. You have been directed to determine the clearance requirements for CSIP 1 B-SB using the SFDs, and System Operating Procedures, as necessary. Provide the clearance installation sequence. The complete electrical and mechanical protection and the necessary vent and drain paths. The MSO has approved using single valve isolation. NOTE: LISTING OF clrs IS NOT REQUIRED FOR THIS JPM. IT IS NOT INTENDED THAT YOU ACTUALLY GENERATE A CLEARANCE. ONLY PROVIDE THE EVALUATOR WITH A LISTING OF THE REQUIRED COMPONENTS, POSITIONS AND THE INSTALLATION SEQUENCE. NOTE: Provide a list of components In the proper installation sequence to the examiner using the following page(s). Additional pages are available upon request. 2009B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30,2009 AppendixC Initial Cond~lons: In~iatlng Cue: Form ES-C-1 JPM CUE SHEET The plant is detueled. CSIP 1 B-SB is required to be placed under a clearance for seal replacement. Cooling water and lube oil systems are NOT required to be placed under clearance. There is no known isolation boundary leakage. You have been directed to determine the clearance requirements tor CSIP 1 B-SB using the SFDs, and System Operating Procedures, as necessary. Provide the clearance installation sequence. The complete electrical and mechanical protection and the necessary vent and drain paths. The MSO has approved using single valve isolation. NOTE: LISTING OF CIT'S IS NOT REQUIRED FOR THIS JPM. IT IS NOT INTENDED THAT YOU ACTUALLY GENERATE A CLEARANCE. ONLY PROVIDE THE EVALUATOR Willi A LISTING OF lliE REQUIRED COMPONENTS, POSmONS AND lliE INSTALLATION SEqUENCE. NOTE: Provide a list 01 components In the proper installation sequence to the examiner using the following page(s). Additional pages are available upon request. 2oo9B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30, 2009

Appendix C Form ES-C-1 JPM CUE SHEET CSIP 1 B-SB CLEARANCE COMPONENT LISTING AND REQUIRED POSITIONS SEQUENCE COMPONENT POSITION 2009B NRC Exam Admin JPM RO A2 Rev. Final Nov. 30, 2009 AppendixC Form ES-C-l JPM CUE SHEET CSIP 1 B-SB CLEARANCE COMPONENT LISTING AND REQUIRED POSITIONS SEQUENCE COMPONENT POSITION 20096 NRC Exam Admin JPM RD A2 Rev. Final Nov. 30, 2009

Appendix C Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of testing: Shearon Harris Page 1 of 7 Worksheet Using survey maps determine stay times G.2.3.4 RO 3.2 SRO 3.7 Form ES-C-1 Task No.: JPM No.: 20098 NRC Exam Admin JPM RO A-3 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: 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 1ED-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 maximum allowable individual stay times for each Operator that would prevent exceeding the Progress Energy Annual Administrative dose limit while performing these activities. 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 com~ete. 20098 NRC Exam Admin JPM RO A3 Rev. Final Nov. 30, 2009 AppendixC Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of tes~ng: Page 1 of 7 Worksheet Form ES-C-l Shearon Harris Using survey maps determine stay ~ G.2.3.4 RO 3.2 SRO 3.7 Task No.: JPM No.: 2oo9B NRC Exam Admin JPM RO A-3 NRC Examiner: Oate: __ Simulated Pertormance: Actual Pertormance: 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 Perlormance 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 1ED-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 maximum allowable individual stay times for each Operator that would prevent exceeding the Progress Energy Annual Administrative dose limit while perfonning these activities. 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. 2oo9B NRC Exam Admin JPM RO A3 Rev. Final Nov. 30,2009

Appendix C Page 2 of 7 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 RO A3 Rev. Final Nov. 30, 2009 AppendixC Page 2 of 7 Worksheet Form ES-C-l 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 Umits" Section 9.3.1 LIMIT = 2 rem Progress Energy dose not to exceed 4 rem total dose ~ 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. 2oo9B NRC Exam Admin JPM RO A3 Rev. Final Nov. 30, 2009

Appendix C START TIME: Evaluator Note: 0/ Performance Step: 1 Standard: Comment: ./ Performance Step: 2 Standard: Comment: ./ - Denotes Critical Steps Page 3 of 7 PERFORMANCE INFORMATION The order of performance does not matter Form ES-C-1 IF THE APPLICANT ASKS FOR IT: Provide a copy of DOS-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. Final Nov. 30,2009 AppendixC START TIME: Evaluator Note: -I' Performance Step: 1 Standard: Comment: -I' Performance Step: 2 Standard: Comment: '" - Denotes Cntical Steps Page 3 of 7 PERFORMANCE INFORMATION The order of performance does not matter Form ES*C*l IF THE APPUCANT ASKS FOR IT: Provide a copy of DOS-NGGC*OOO4, Rev. 10 Using Radiological Survey Record Map A4 and RAB 100' 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 2oo9B NRC Exam Admin JPM RO A3 Rev. Final Nov. 30. 2009

Appendix C ~ Performance Step: 3 Standard: Comment: Terminating Cue: STOP TIME: ./ - Denotes Critical Steps Page 4 of 7 PERFORMANCE INFORMATION Form ES-C-1 Determine stay time for each operator (based on 1 st Operator reaching 2 Rem and the 2nd Operator reaching 4 Rem - for the year) Operator 1: 2 hours 240 mrem + 120mrem/hr = 2 hrs Operator 2: 5 hours 600 mrem + 120 mrem/hr = 5 hours After the stay time has been calculated, this JPM is complete ENDOFJPM 2009B NRC Exam Admin JPM RO A3 Rev. Final Nov. 30,2009 AppendixC ./ Performance Step: 3 Standard: Comment: Terminating Cue: STOP llME: '" - Denotes Critical Steps Page 4 of 7 PERFORMANCE INFORMATION Form ES-C-t Determine stay time for each operator (based on 1st Operator reaching 2 Rem and the 2nd Operator reaching 4 Rem - for the year) Operator t: 2 hours 240 mrem + 120mremihr = 2 hrs Operator 2: 5 hours 600 mrem + 120 mrem/hr = 5 hours Aner the stay time has been calculated, this JPM Is complete ENDOFJPM 2oo9B NRC Exam Admin JPM RO A3 Rev. Final Nov. 30,2009

Appendix C Page 5 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM RO A 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. Final Nov. 30,2009 Appendix C Page 5 of 7 VERIFICATION OF COMPLETION Form ES-C-l Job Perfonmance Measure No.: 2009B NRC Exam Admin JPM RO A Using survey maps determine slay 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 Administra~ve 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. Final Nov. 30,2009

Appendix C Initial Conditions: INITIATING CUE: Form ES-C-1 JPM CUE SHEET 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 1ED-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 maximum allowable individual stay times for each Operator that would prevent exceeding the Progress Energy Annual Administrative dose limit while performing these activities. 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. Final Nov. 30, 2009 AppendixC Form ES-C-I JPM CUE SHEET Initial Conditions: Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Pump. The clearance includes the following valves: IED-12 IED-13 IED-14 lED-IS IED-17 lED-IS INITIATING CUE: Two Operators are being assigned to hang a clearance and pertorm work in a radiological area. Operator 1 has an accumulated annual Whole Body dose 011760 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 sUivey map. determine the maximum allowable individual stay times for each Operator that would prevent exceeding the Progress Energy Annual Administrative dose limit while pertonming these activities. 00 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 I: ___________________ Operator 2: 2009B NRC Exam Admin JPM RO A3 Rev. Final Nov. 30, 2009

AppendixC Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of testing: Page 1 of 6 Worksheet Form ES-C-1 Shearon Harris During a Loss of Shutdown Cooling. determine the time that the RCS will reach Core Boiling and Boil-Off G2.1.20 RO 4.6 SRO 4.6 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. The current date is 9/22/09 The current time is 1400 and the 'A' RHR pump just 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 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 A1-1 Rev. Final Nov. 30,2009 AppendixC Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Shearon Harris Page 1 of 6 Worksheet During a loss of Shutdown Cooling. determine the time that the ReS will reach Core Boiling and Boil-Off G2.1.20 RO 4.6 SRO 4.6 Form ES*C-1 Task No.: JPM No.: 2009B NRC Exam Admin JPM SRO A1-1 NRC Examiner: Oate: __ Method of testing; Simulated Performance: Actual Pertormance: x Classroom X Simulator Plant READ TO 111E EXAMINEE I wlll 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 CondHlons: Initiating Cue: On 9105109 at 0000 the plant was shutdown for a refueling outage. While the Reactor cavity was being lilled the 'B' RHR pump tripped. Motor repairs are not expected to be completed until 9125109. 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. The current date is 9/22/09 The current time is 1400 and the 'A' RHR pump just tripped. The crew is implementing AOP*020, Loss of RCS Inventory or RHR While Shuldown. Core exit thennocouples are rising; they are currently reading 135°F. lAW AOP-020 you are directed to determine the time to reach core boiling and core boil-off time. Mark up your curves to indicate where you are determining these times. Retum the curves to the examiner with this page. Write your estimates of "lime to boil" and time to boil*off" on the lines at Ihe bottom of this page (below). 2oo9B NRC Exam Admin JPM SRO A 1-1 Rev. Final Nov. 30, 2009

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-oft time Required Materials: Curve Book Straight Edge 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-oft" using the appropriate curve. 2009B NRC Exam Admin JPM SRO A1-1 Rev. Final Nov. 30,2009 AppendixC Page 2 of 6 Worksheet Form ES-C-l Task Standard: Candidate obtains curves and correctly identifies the time to reach core boiling and core boil-off time Required Materials: Curve Book Straight Edge 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 Al-l Rev. Final Nov. 30, 2009

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 (Curve Book 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 - 9/22/09) 17 days 14 hours 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 <.+/- 2 minutes) 2Q09B NRC Exam Admin JPM SRO A1-1 Rev. Final Nov. 30,2009 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 (Curve Book will be provided to the candidate) Refers to curves H-X-a 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 - 9122109) 17 days 14 hours since shutdown and current ReS 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 C+/- 2 minutes) 2oo9B NRC Exam Admin JPM SRO A1-1 Rev. Final Nov. 30, 2009

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 - 9/22109) 17 days 14 hours since shutdown and current RCS temperature of 135°F using curve H-X-11 determine time to boil-off' 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 hours) 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. Final Nov. 30,2009 AppendixC v' Performance Step: 4 Standard: Comment: Terminating Cue: STOP TIME: ./ - Denotes Critical Steps Page 40f 6 PERFORMANCE INFORMATION Form ES-C-l Based on time since shutdown (9/5/09 - 9122109) 17 days 14 hours since shutdown and current ReS temperature of 135°F using curve H-X-ll determine.,ime 10 boil-off' Reviews curve H-X-l1 Determines that.,ime to boil-off" is 4 hrs and 45 minutes l+/- 15 minutes) or (4.5 to 5.0 hours) After completing the "time to boll" and utlme to boll-off' calculation, the evaluation on this JPM is complete. ENDOFJPM 2oo9B NRC Exam Admin JPM SRO AH Rev. Final Nov. 30, 2009

Appendix C Page 5 of 6 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM SRO A1 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. Final Nov. 30,2009 AppendixC Page 5 of 6 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No_: 2009B NRC Exam Admin JPM SRO A 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 A 1-1 Rev_ Final Nov. 30, 2009

Appendix C Initial Conditions: INITIATING CUE: Form ES-C-1 JPM CUE SHEET 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. The current date is 9/22109 The current time is 1400 and the 'A' RHR pump just 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 determine the time to reach core boiling and core boil-ott 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. Final Nov. 30, 2009 AppendixC Initial Conditions: INI11ATING CUE: Form ES-C-l JPM CUE SHEET On 9/05109 at 0000 the plant was shutdown for a refueling outage. While the Reactor cavity was being filled the 'S' RHR pump tripped. Motor repairs are not expected to be completed until 9/25109. 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. The current date is 9/22109 The current time is 1400 and the 'A' RHR pump just tripped. The crew is implementing AOP-020, Loss of RCS Inventory or RHR While Shutdown. Core exit thermocouples are rising; they are currently reading 13S'F. lAW AOP-020 you are directed to 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 '1ime 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 ______________ _ 20098 NAC Exam Admin JPM SAO A1-1 Rev. Final Nov. 3D, 2009

Appendix C Facility: Shearon Harris Page 1 of 7 Worksheet Form ES-C-1 Task No.: 301013H401 Task

Title:

Determine Boric Acid Addition Following CR Evacuation JPM No.: 2009B NRC Exam Admin JPM SRO A 1-2 KIA

Reference:

G2.1.25 RO 3.9 SRO 4.2 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: The Control Room has been evacuated and the MCB transfer to the ACP has been completed. Plant management has directed a plant cool down to mode 5 utilizing AOP-004. BAT level is 83% with a concentration of 7205 ppm. The RCS is currently 915 ppm. Initiating Cue: You are the CRS. Perform a calculation of the minimum 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 A 1-2 Rev. Final Nov. 30,2009 Appendix C Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of testing: Shearon Harris Page 1 of 7 Worksheet Determine Boric Acid Addition Following CR Evacuation G2.1.25 RO 3.9 SRO 4.2 Form ES-C-l Task No.: 301013H401 JPM No.: 2009B NRC Exam Admin JPM SRO AI-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 CAS. Perform a calculation of the minimum required boric acid addition to achieve cold shutdown and BAT level change per AOP-004, Section 3.2 Step 25 to obtain an OST-l036 cold shutdown boron requirement of 1740 ppm. 2009B NRC Exam Admin JPMSRO At -2 Rev. Final Nov. 30, 2009

Appendix C Task Standard: Page 2 of 7 Worksheet Form ES-C-1 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 A1-2 Rev. Final Nov. 30,2009 AppendixC Page 2 of 7 Worksheet Form ES-C-l Task Standard: Utilizes Curve E-X-2 to determine required boric acid addition to achieve cold shutdown and Curve 0-2 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) Curve Book nomograph E-X-2 (Rev. 4) and Curve 0-2 (Rev. 0) Time Critical Task: No Validation Time: 15 minutes Step 3 Step 4 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 Al-2 Rev. Final Nov. 30, 2009

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 Form ES-C-1 OBTAIN PROCEDURE Obtains AOP-004 and refers to Section 3.2 Step 25 (Copy of step will be provided to the candidate) 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°F) Va" = _-_M_ln(_70_0_0_-_Q_) 8.33 7000 - Ci M=538.000 2009B NRC Exam Admin JPMSRO A1-2 Rev. Final Nov. 30, 2009 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 Form ES-G-l OBTAIN PROCEDURE Obtains AOP-004 and refers to Section 3.2 Step 25 (Copy of step will be provided to the candidate) Obtain cold shutdown boron concentration using copy of latest OST-l036 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 ReS 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 @ 3500 F) VB= -M 1n( 7000 - 0) 8.33 7000 - C M =538,000 2oo9B NRC Exam Admin JPMSRO A 1-2 Rev. Final Nov. 30, 2009

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 -S3800c) l (7205-1740) V-n -9080 B - 8.33 7Z0S-91S-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) -53800~ l (7000-1740) V= n =9409 B 8.33 '1000-91!i 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) _ -44100~ In (1205-1740) _ VB - a.:n '1205-91!i - 7443 2009B NRC Exam Admin JPMSRO A 1-2 Rev. Final Nov. 30,2009 Appendix C Examiners NOTE: Comment: ~ - Denotes Critical Steps Page 40f 7 VERIFICATION OF COMPLETION Form Es-C-l 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 nos ppm to come to the correct boron addition. CORRECT CALCULATION -S38000 I r¥:0S-1740) V= n =9080 a B.33 7205-915 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) _ - 538"000 in ('000-1740) _ V. - 8.33 700D-9B - 9409 If candidate uses correct BAT BA concentration but uses the wrong Curve (E-X-' verses E-X-2) the result will be 7443 gallons INCORRECT CALCULATION (using wrong RCs Mass - wrong curve) _ HOO&* In (7205-1740) _ Va - 8.)) 720S-91S - 7443 2009B NRC Exam Admin JPMSRO AI-2 Rev. Final Nov. 30, 2009

Appendix C 0/ Performance Step: 4 Standard: 35000 II ! 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 D-2 Utilizes Curve D-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). III I II! 8Grle Actd Tonk ~! 50t,lQ '2QOOrJ 119920 I I~OOU Volumlln allonlJ Curv&Jl Or~g SUpv QC)S . + -.'1 RlIYt...Q. ~( J..... tif-z.f-l'lete~ Oet.~ Q 10 Fe) 30 12QOOO -9080 = 19920 40 50 ~ &0

• In." c.eted
• 70 80~ 90 100 183-55=281

~ONTROL ROOM COpy .... ~... _- ---- - . f Comment: STOP TIME: Terminating Cue: ./ - Denotes Critical Steps When candidate completes the calculations the JPM is completed. ENDOFJPM 2009B NRC Exam Admin JPMSRO A 1-2 Rev. Final Nov. 30, 2009. AppendixC ~ Performance Step: 4 Standard: 51)(1('1 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 finallevol of 54 to 56 percent). Actual is 28% change (or 55% final). IlWOO-9080- '9G2D linolcettca* 183-55:0:281

ONTROL ROOM COpy

~ I Comment: STOP TlME: Terminating Cue: ./ - Denotes Critical Steps When candidate completes the calculations the JPM Is completed. END OF JPM 2oo9B NRC Exam Admin JPMSRO A1 -2 Rev. Final Nov. 30, 2009

Appendix C Page 6 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM SRO A 1 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 2009B NRC Exam Admin JPMSRO A 1-2 Rev. Final Nov. 30, 2009 AppendixC Page 6 of 7 VERIFICATION OF COMPLETION Form ES*C*l Job Performance Measure No.: 2009B NRC Exam Admin JPM SRO Al*2* Detennine 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 2009B NRC Exam Admin JPMSRO Al*2 Rev. Final Nov. 30, 2009

Appendix C Initial Conditions: Initiating Cue: Form ES-C-1 JPM CUE SHEET 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 minimum 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 A 1-2 Rev. Final Nov. 30,2009 AppendixC Inilial Conditions: Initiating Cue: Form ES*C-l JPM CUE SHEET 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 CAS. Perform a calculation of the minimum required boric acid addition to achieve cold shutdown and BAT level change per AOP-004, Section 3.2 Step 25 to obtain an OST-l036 cold shutdown boron requirement of 1740 ppm. 2009B NRC Exam Admin JPMSRO A 1*2 Rev. Final Nov. 30,2009

Appendix C Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of testing: Page 1 of 10 Worksheet Form ES-C-1 Shearon Harris Task No.: 002001 H201 Perform Review of Partial OST-JPM No.: 2009B NRC Exam 1007. CVCS/SI System Operability Admin JPM SRO A2 Train A Quarterly Interval Modes 1-4 G2.2.37 RO 3.6 SRO 4.6 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: The Plant is operating at 100% Power A partial OST-1007, CVCS/SI System Operability Train A Quarterly Interval Modes 1-4, has just been completed on the 'A' BA pump (section 7.2). Initiating Cue: You are the CRS. You are to review the completed OST-1007 then discuss any identified problems with the evaluator. Evaluator Note: Explain to candidate that once he has identified all discrepancies and described them to the evaluator, the cue for the end of the JPM will be his handing the procedure back to the evaluator. If asked, PMID 22958-03 is NOT due. 2009B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30,2009 AppendixC Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of testing: Page 1 of 10 Worksheet Form ES-C-l Shearon Harris Task No.: 002001H201 Perlorm Review of Partial OST-JPM No.: 2009B NRC Exam 1007. CVCS/SI System Operability Admin JPM SRO A2 Train A Quarterly Interval Modes 1-4 G2.2.37 RO 3.6 SRO 4.6 NRC Examiner: Oate: __ _ Simulated Perlormance: 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: The Plant is operating at 100% Power A partial OST-l007, CVCS/SI System Operability Train A Quarterly Interval Modes 1-4, has just been completed on the 'A' BA pump (section 7.2). Initiating Cue: You are the CRS. You are to review the completed OST-l007 then discuss any identified problems with the evaluator. Evaluator Note: Explain to candidate that once he has identified all discrepancies and described them to the evaluator, the cue for the end of the JPM will be his handing the procedure back to the evaluator. If asked, PMIO 22958-03 is NOT due. 2009B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30, 2009

Appendix C Task Standard: Page 2 of 10 Worksheet Identify following errors: Form ES-C-1 Pump differential pressure does not meet acceptance criteria. Pump Outboard Vertical vibration is outside of the Acceptable range. Data correction on Attachment 3 not documented correctly. Declare 'A' Boric Acid Transfer Pump inoperable. Required Materials: Copy of completed OST-1007, CVCS/SI System Operability Train A Quarterly Interval Modes 1-4. General

References:

OST -1007 (Rev. 38) Time Critical Task: Validation Time: Step 2 Step 3 Step 4 No 20 minutes Critical Step Justification Identifies pump performance data is outside Acceptance Criteria. Identifies 'A' Boric Acid Transfer pump is inoperable. Identifies vibration data is outside Acceptance Criteria. 2009B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30,2009 AppendixC Task Standard: Page 2 of 10 Worksheet Identify following errors: Form ES-C-l Pump drtferential pressure does not meet acceptance criteria. Pump Outboard Vertical vibration is outside of the Acceptable range. Data correction on Attachment 3 nol documented correctly. Declare 'A' Boric Acid Transfer Pump inoperable. Required Materials: Copy of completed OST-lOO7, CVCS/SI System Operability Train A Quarterly Interval Modes 1-4. General

References:

OST*loo7 (Rev. 38) Time Critical Task: Validation Time: Step 2 Slep 3 Step 4 No 20 minutes Critical Step Justification Identifies pump pertormance data is outside Acceptance Criteria. Identifies 'A' Boric Acid Transfer pump is inoperable. Identifies vibration data is outside Acceptance Criteria. 2009B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30, 2009

Appendix C START TIME: Performance Step: 1 Standard: Evaluator Cue: Comment: ~ Performance Step: 2 Standard: Evaluator Note: Comment: V' - Denotes Critical Steps Page 3 of 10 PERFORMANCE INFORMATION OST-1007 Obtain procedL!re. Form ES-C-1 Receives copy of completed OST -1007 ready for review. Provide OST-1007 for review OST-1007, Attachment 2 - Performance Data Identifies pump differential pressure recorded on Attachment 2 - Performance Data is outside Quarterly test acceptance criteria. Identifies pump differential pressure does not meet Quarterly test acceptance criteria as listed on Attachment 2 - Performance Data. Copy of Attachment 2 included in back of JPM. 20098 NRC Admin Exam JPM SRO A2 Rev Final Nov. 30,2009 AppendixC START TIME: Perfonmance Step: 1 Standard: Evaluator Cue: Comment: ./ Perfonmance Step: 2 Standard: Evaluator Note: Comment: ./

• Denotes Critical Steps Page 3 of 10 PERFORMANCE INFORMATION OST-l007 Obtain procedure.

Form ES*C-1 Receives copy of completed OST-1 007 ready for review. Provide OST-l00710r review OST-l007, Attachment 2 - Perfonmanc8 Data Identifies pump differential pressure recorded on Attachment 2 - Performance Data is outside Quarterly test acceptance criteria. Identifies pump differential pressure does not meet Quarterly test acceptance criteria as listed on Attachment 2 - Performance Data. Copy 01 Attachment 2 included In back 01 JPM. 2oo9B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30, 2009

Appendix C ~ Performance Step: 3 Standard: Evaluator Cue: Comment: ~ Performance Step: 4 Standard: Evaluator Note: Comment: ,( - Denotes Critical Steps Page 4 of 10 PERFORMANCE INFORMATION Form ES-C-1 Identifies 'A' Boric Acid Transfer pump is inoperable. Identifies Technical Specification 3.1.2.2 applicable but no action required as long as RWST is operable (tracking EIR). Identifies need for NCR per Instruction 1.b of Attachment 2 (sheet 2 of 3). (,() Declares 'A' Boric Acid Transfer pump inoperable. Discusses need to generate EIR (Equipment Inoperability Record) and NCR (Nuclear Condition Report). May need to prompt candidate to discuss operability and related Technical Specifications. If asked, another Operator will generate the EIR and NCR OST-1007, Attachment 3 - Vibration Data Identifies the Outboard Vertical (Out Vert) vibration reading is outside of the Acceptable range but within the Alert Range on - Vibration Data. Identifies the Outboard Vertical vibration reading is outside of the Acceptable range but within the Alert Range on Attachment 3, Vibration Data. Copy of Attachment 3 included in back of JPM. 2009B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30, 2009 AppendixC ~ Performance Step: 3 Standard: Evaluator Cue: Comment: ~ Performance Step: 4 Standard: Evaluator Note: Comment: ./ - Denotes Critical Steps Page 4 of 10 PERFORMANCE INFORMATION Form ES-C-1 Identifies 'A' Boric Acid Transfer pump is inoperable. Identffies Technical Specification 3.1.2.2 applicable but no action required as long as RWST is operable (tracking EIR). Identifies need for NCR per Instruction l.b of Attachment 2 (sheet 2 of 3). (~) Declares 'A' Boric Acid Transfer pump inoperable. Discusses need to generate EIR (Equipment Inoperabillty Record) and NCR (Nuclear Condition Report). May need to prompt candidate to discuss operability and related Technlcsl SpecHlcations. If asked, another Operator will generate the EIR and NCR OST-I007, Attachment 3 - Vibration Data Identifies Ihe Oulboard Vertical (Out Vert) vibration reading is outside of the Acceptable range but within the Alert Range on - Vibration Data. Identifies the Outboard Vertical vibration reading is outside of the Acceptable range but within the Alert Range on Attachment 3, Vibration Data. Copy 01 Attachment 3 Included In back 01 JPM. 20098 NRC Admin Exam JPM SRO A2 Rev Rnal Nov. 30. 2009

Appendix C Performance Step: 5 Standard: Evaluator Cue: Comment: Performance Step: 6 Standard: Comment: ./ - Denotes Critical Steps Page 5 of 10 PERFORMANCE INFORMATION OST-1007, Attachment 3 - Vibration Data Form ES-C-1 Acknowledges that Instruction 1 applies to Outboard Vertical (Out Vert) vibration value and that an STR and NCR should have been written and documented on Attachment 8, Certifications and Reviews. Acknowledges that Instruction 1 applies requiring that an STR (Surveillance Testing Request) and NCR should have been written and documented on Attachment 8, Certifications and Reviews. If asked, another Operator will generate the STR and NCR OST-1007, Attachment 3 - Vibration Data Identifies data correction to Inboard Horizontal (In Horiz) vibration data on Attachment 3 not documented correctly. Identifies operator must correctly document vibration data change on Attachment 3 (single lineout, initial and date) (ref RDC-NGGC-0001 section 9.2.10). 2009B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30, 2009 AppendixC Performance Step: 5 Standard: Evaluator Cue: Comment: Perfonmance Step: 6 Standard: Comment: " - Denotes Critical Steps Page 5 of 10 PERFORMANCE INFORMATION OST-lOO7, Attachment 3 - Vibration Data Form ES-C-I Acknowledges that Instruction I applies to Outboard Vertical (Out Vert) vibration value and that an STR and NCR should have been written and documented on Attachment 8, Certifications and Reviews. Acknowledges that I nstruclon I applies requiring that an STR (Surveillance Testing Request) and NCR should have been written and documented on Attachment 8, Certifications and Reviews. If aaked, another Operator will generate the STR and NCR OST-I007, Attachment 3 - Vibration Data Identifies data correction to Inboard Horizontal (In Horiz) vibration data on Attachment 3 not documented correctly. Identifies operator must correctly document vibration data change on Attachment 3 (single lineout, initial and date) (ref RDC*NGGC-OOOI section 9.2.1O). 20098 NRC Admin Exam JPM SRO A2 Rev Final Nov. 30, 2009

Appendix C Performance Step: 7 Standard: Evaluator Cue: Evaluator Note: Comment: Terminating Cue: STOP TIME: '" - Denotes Critical Steps Page 6 of 10 PERFORMANCE INFORMATION OST-1007 Completes review of procedure. Completes review of procedure. Form ES-C-1 Acknowledges that review has been completed, discrepancies identified and that follow up actions need to be taken before surveillance can be completed and submitted. Candidate wililikely.explain the he would not sign off CRS review signature until he followed up on discrepancies first. CRS hands copy of OST-1007 to evaluator indicating that he has completed his review. ENDOFJPM 2009B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30,2009 AppendixC Performance Step: 7 Standard: Evaluator Cue: Evaluator Note: Comment: Terminating Cue: STOP TIME: v" - Denotes Critical Steps Page 60t 10 PERFORMANCE INFORMATION OST-1oo7 Completes review of procedure. Completes review of procedure. Form ES-C-l Acknowledges that review has been completed, discrepenclee Identified and that follow up actions need to be taken before surveillance can be completed and submitted. Candidate will likely explain the he would not sign off CRS review signature until he followed up on dlscrepencies first CAS hands copy of OST-1 007 to evaluator indicating that he has completed his review. ENDOFJPM 2009B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30, 2009

Appendix C Page 7 of 10 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: Perform Review of Partial OST-1007, CVCS/SI System Operability Train A Quarterly Interval Modes 1-4 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 SRO A2 Rev Final Nov. 30,2009 AppendixC Page 7 of 10 VERIFICATION OF COMPLETION Form ES-C-l Job Pertormance Measure No.: Pertonm Review of Partial OST-l007, CVCS/SI System Operability Train A Quarterly Interval Modes 1-4 Examinee's Name: Date Pertonmed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiner's Signature: Date: 20098 NRC Admin Exam JPM SRO A2 Rev Final Nov. 30, 2009

Appendix C Page 8 of 10 VERIFICATION OF COMPLETION KEY - Performance oata Sheet3c13 Form ES-C-1 1A-SA Boric &:;!d Itm* 8la (conlhied, ~ Quartaft;.. accep..,.ce C1bM. ~ IF PMD 2295&03 it due. U8£ 2~Y.. r a:rr accepta'lce en. ria. This... utiafiel the qu-ft; teat. ~ In the eve<< the.-ft; PUfl1) pre..... dlfefe.... 'r.. dI.. exceeda 2-V.r CPr.~ ... ce criteria bUt,..".... within q.... l'l8rly ac:ceptenC$ c:dIerla, the Pld1),.-..in. Of*81l1e. ~ine"'Wtsr Wli ev.. ale _ pert d b lrefw:Iing pcvram. !iQIE..l

1. IF p&mp hydra~IC." is cuteid_the Ac:c:8pta........ tlUt witt*, fie AIIwt Ran.. :

1IITIA11: *' 8TR 10 died the a..~nce Testing Stttedu-. Coon:!in_ 1O douille the "... tequenc:y d.... PUQ1l.

b.

1IITIA11: *' Nat

c.

AS:ORD lh.srRand NCR nUll'lb<<ain'" Comtna'l.... d an.

2. IF PUfll) h~1ic da......... fie Raqund Adbl C)lelia;

• • I1FO NlEthe ~

NJPalABt.E.

b...mATE an NCR.

CIRClE fie 8Of.ft6. d the Reading. s.p Peranetet 1.2.14 Id e $.Ic:tIan ~ 1;2.16 eerie ACid Pilfll) 1 e~ S81d" 0i8ch Frau 7.2.25 A<-113 Demand 0fJ~'" 1,2.28 ~11301mand 0u~11 7.2.32 Aow Rate 1.2.34 ~gl*d!1FgIII p,..... 1.2.35 ~'*11 &lc:lbI Pta.... 1.2.38 eCl'ic ACid Pilfll)'8- $ald.. 0i8ch Pr-.. 1.2.31 Oi...... dalP..... I06T-1001 I inSlrUtllent R.... ' kcepta.. Cl'itetiil T e8t lnatftitna'll l!!:5.... @1C&034 15.8 PloO,c;s..o11OSW HlA 18.0 (Trendl.. Pwpoaas Odyt 1*-113 HIli. 30t (Ttendi~ ~ 011~ fK.113 HIli. 4n (Trendl~ Pwposes Od~ ~1~ 34 to 38 112m ~l3* 35 Teetln.-ument HIli. o 1CS-S3>'Ji 137 Teatlnatun8lt l!!: 5 pIIig o 1C8-034 15.7 Plo01C8-011OSW HIli. 18.0 (Tren di~ Pu-po.. (ldyt CaIcuIlltiOtl 1121. 3 1 I tmUMd t<<tIlll 99.18 10 121.22 P8id PMI2295IIJ.03 2-Y... CPT ~andtQI£.l 102.49 10 113.5 P8id ~""Ra~.

99. 18 10 <102.49 J)$Id AlertRa...

<99.18 or> 11~.$,*, Req~rad Action ReI... Rev+38 I

p. 37 of 49 I 2009B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30,2009 AppendixC Page 8 of 10 VERIFICATION OF COMPLETION KEY

_",Z

• _DoIa Sheet3d3 Form ES*C*1 lA-SA. BDdt:: &iId IUII* Ptum <<:aIthMdl ItQIU.

~_~r.abIII. ~ IF FlUD 22H&03i11 dut,.... 2-Y-.rCPT ~ta'IOtoi.1II.. nn._...... Cf,I"~ IfIlL l!QlU;. lit 11'1."'" !tit quMeltJ 1111\\1> PH*ftcifeflitillll'.-ta..... 2-V..,CPr ~tMCIt<dllrla w,........ ~q:.rtII1'1~aIMl,ttI.p,IIfCII...... OPfat:!I.. Et1I.....,~.... 1 IIIIV * **,.It db hndh O r:n::vtaft\\ !IQI£.Z

1. IF p.... p I'¥datllC... til cu.eth.~.. RIngt II.It ""Nt til AIII1 All.:

....nATI! _ STR todlNdtht 8.J~ Ttllting Sd'Ied.I.,., Qadrnllcriodoullleh .~ hqUlnty It thI PI""-

• • MTlATI!.., Heft.

~ R&:;c.D lh.srRend HCft nlftktin u. (;(Ift"**"~ 2.. Cfp,ul1lh~lc:dI"". r.A8q.t"-l AdkII 0briI:

• . DE~ItI. ~

fr<<lPfRABl.E.

b...mAlE., Nat CIRCU....... "... "....

7.2.t4 Id e &.IdOl F'Iwan 7.2.18 BCil'Ic Add flU"" 18-SB ld. DiIdI Pt-. 7.2..25 001>" 1.2.28 FIO-I:':'~_ 7.2.. 32 -- 1.2.34 7.2.35 0pIn~ 8.ldDI - 7.2..311 7.2.:11 a,.... tIII P....... I 06T*1007 I 0 15.*

l!:: 5 PIiD PS.olcs.oltOBW 18 **

0"" fK.113 0'" fKo113 0'" ~ 34 to. CPt" 0 137 15. 7 pt.otC8-01108W 1 * ** 0'" CabJtItion IU1.ll ~ lQIU'" !I!llll 102.41110 1 13.5 pIId ~"'Rara. 99.18 110 <IOZ'.... "QIl,"'MRe ** Rev. 38 I Pogo 37 of <091 2009B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30, 2009

Appendix C Page 9 of 10 VERIFICATION OF COMPLETION KEY Attachment J - Vibration Data Sheet 3ot3 Form ES-C-1 INSTRUCTIONS:

1.

IF pump vibration data is outside 1he Acceptable Range, but within 1he Alert Range, THEN:

3.

INITIATE an STR to direct the SUrveillance Testing Scheduling Coordinator to double the testing frequency ot1he pump.

b.

INITIATE an NCR

c.

RECORD the STR and NCR numbers in the CQmmenls Section.

2.

IF pump vibration data meets the Requfred Action Crttena, THEN: a DECLARE the ptBl1) INOPERABLE

b.

INITIATE an NCR. 1A-SA Boric Acid Transfer Pump VIntiart.1.Jx:a1ian INISEC AmI 0.027 OutHariz 0.025 OutVel1 (0.12V In Hariz ~ O. 028 InVerl 0.040 IOST-1D07 ACCEPTANCE CRITERIA ~R Alert Range ~Adian INISEC INlSEC INISEC s 0.01575 > O.fl575 to s 0.138 >0.138 ,;; Q.1l525 > 0..0!i25 to s 0. 120 >0.120 " 0.055

0 0.05/510 " 0.132

>0.132

11.11125

> OJJ125 to,.; 0.174 >0.174

Q,05

> Il.05Io,; 0.12 >0.. '2 Rev. 38 Page 40 of 491 2009B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30, 2009 Appendix C Page 9 of 10 VERIFICATION OF COMPLETION KEY AHachment 3

• VibnIHon Datil Sheet3of3 Form ES-C-1 INSTRUCTIONS:

1.

IF punp vtntion mia Is outside the Aca!pt3tAa Ra1ge, but within the Alert Range, THEN:

a.

INfTlA TE an STR to dIr8d: the SUrveilance Testllg Schedliing Coordilalor 10 double the tasting frequency of the pump..

b.

INmATE an NCR.

c.

RECORD the STR and NCR JWJrnbers In the Comments Section.

2.

IF PlIT1P viII_on data meets the ReqlRd Action Crtteria. IOST-1007 THEN:

a.

DEClARE the IUT1J INOPERABlE

b.

INmATE an NCR. 20096 NRC Admin Exam JPM SRO A2 Rev Rnal Nov. 30, 2009

Appendix C Initial Conditions: Initiating Cue: Form ES-C-1 JPM CUE SHEET The unit is in Mode 1 at 100% Power. A partial OST-1007, CVCS/SI System Operability Train A Quarterly Interval Modes 1-4, has just been completed on the "A" BA pump (section 7.2). You are the CRS. You are to review the completed OST-1007 then discuss any identified problems with the evaluator. 2009B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30,2009 Appendix C Initial Conditions: InHlatlng Cue: Form ES-C-1 JPM CUE SHEET The unit is in Mode 1 at 100% Power. A partiai OST-1OO7, CVCs/SI System Operability Train A Quarterly Interval Modes 1-4, has just been completed on the "A" BA pump (section 7.2). You are the CRS. You are to review the completed OST-1oo7 then discuss any identified problems with the evaluator. 2oo9B NRC Admin Exam JPM SRO A2 Rev Final Nov. 30,2009

Appendix C Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of testing: Page 1 of 7 Worksheet Form ES-C-1 Shearon Harris Using survey maps determine stay times G.2.3.4 RO 3.2 SRO 3.7 Task No.: JPM No.: 2009B NRC Exam Admin JPM SRO A-3 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: Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer . Initiating Cue: 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 maximum allowable individual stay times for each Operator that would prevent exceeding the Progress Energy Annual Administrative dose limit while performing these activities. 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. Final Nov. 30,2009 Appendix C Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of tesling: Shearon Harris Page 1 of 7 Worksheet Using survey maps determine stay times G.2.3.4 RO 3.2 SRO 3.7 Form ES-C-l Task No.: JPM No.: 2009B NRC Exam Admin JPM SRO A-3 NRC Examiner: Date: __ Simulated Pertormance: 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 Condl1lons: Two individuals are tasked to hang a clearance on the 'A' ED Tank Transfer Initiating Cue: Pump. The clearance Includes the following valves: , EO-12 lED-13 1 EO-14 lED-15 lED-17 1ED-1B 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 maximum allowable individual stay times for each Operator that would prevent exceeding the Progress Energy Annual Administrative dose limit while performing these activities. 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. Final Nov. 30, 2009

Appendix C Page 2 of 7 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. Final Nov. 30, 2009 AppendixC Page 2 of 7 Worksheet Form ES-C-l Task Standard: Calculation of stay times based on survey maps, two hours for Operator I, five hours for Operator 2. Required Materials: Survey map A4 RAB 190' North Valve MAP 2 SFD-S-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 W 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. 2oo9B NRC Exam Admin JPM SRO A3 Rev. Final Nov. 30, 2009

Appendix C START TIME: Evaluator Note: ./ Performance Step: 1 Standard: Comment: ./ Performance Step: 2 Standard: Comment: ./ - Denotes Critical Steps Page 3 of 7 PERFORMANCE INFORMATION The order of performance does not matter Form ES-C-1 IF THE APPLICANT ASKS FOR IT: Provide a copy of DOS-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. Final Nov. 30, 2009 AppendixC START TIME: Evaluator Note: ./ Performance Step: 1 Standard: Comment: '" Performance Step: 2 Standard: Comment: ../ - Denotes Critical Steps Page 301 7 PERFORMANCE INFORMATION The order of performance does not matter Form ES-C-l IF THE APPLICANT ASKS FOR IT: Provide a copy of DOS-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 2oo9B NRC Exam Admin JPM SRO AS Rev_ Rnal Nov. 30, 2009

Appendix C -/ Performance Step: 3 Standard: Comment: Terminating Cue: STOP TIME: -/ - Denotes Critical Steps Page 4 of 7 PERFORMANCE INFORMATION Form ES-C-1 Determine stay time for each operator (based on 1 st Operator reaching 2 Rem and the 2nd Operator reaching 4 Rem - for the year) Operator 1: 2 hours 240 mrem + 120mrem/hr = 2 hrs Operator 2: 5 hours 600 mrem + 120 mrem/hr = 5 hours After the stay time has been calculated, this JPM is complete. END OFJPM 2009B NRC Exam Admin JPM SRO A3 Rev. Final Nov. 30,2009 AppendixC ./ Performance Step: 3 Standard: Comment: Terminating Cue: STOP TIME: ./ - Denotes Critical Steps Page 4 of 7 PERFORMANCE INFORMATION Form ES-C-l Detennine stay time for each operator (based on 1 st Operator reaching 2 Rem and the 2nd Operator reaching 4 Rem - for the year) Operator 1: 2 hours 240 mrem + 120mremlhr = 2 hrs Operator 2: 5 hours 600 mrem + 120 mremlhr = 5 hours Aller the stay time has been calculated, this JPM is complete_ END OF JPM 2oo9B NRC Exam Admin JPM SRO A3 Rev. Final Nov. 30, 2009

Appendix C Page 5 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B NRC Exam Admin JPM SRO A 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. Final Nov. 30,2009 AppendixC Page 5 of 7 VERIFICATION OF COMPLETION Form ES-G-l Job Performance Measure No.: 2909B NRC Exam Admin JPM SRO A Using survey maps determine stay times. (DOS-NGGC-0004 Rev. 10) Examinee's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: question Documentation: Question:

Response

Result: DOS-NGGC-0004 "Progress Energy Annual Administrative Dose Umits" 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 detennined. SAT UNSAT Examiner's Signalure: _ _____________ Date: 2009B NRC Exam Admin JPM SRO A3 Rev. Final Nov. 30, 2009

Appendix C Initial Conditions: Initiating Cue: Form ES-C-1 JPM CUE SHEET 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 maximum allowable individual stay times for each Operator that would prevent exceeding the Progress Energy Annual Administrative dose limit while performing these activities. 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 ahd minute. Operator 1: __________________ Operator 2: 2009B NRC Exam Admin JPM SRO A3 Rev. Final Nov. 30, 2009 Appendix C Inhlal Conditions: Inlliatlng Cue: Form ES-C-1 JPM CUE SHEET 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 1ED-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 maximum allowable individual stay times for each Operator that would prevent exceeding the Progress Energy Annual Administrative dose limit while performing these activities. 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: 20098 NRC Exam Admin JPM SRO A3 Rev. Final Nov. 30, 2009

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Appendix C Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of testing: Shearon Harris Classify an event Page 1 of 7 Worksheet Form ES-C-1 Task No.: 345001 H602 JPM No.: 20098 NRC Exam Admin JPM SRO A4 G2.4.41 RO 2.9 SRO 4.6 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: 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. Determine PAR if required. THIS IS A TIME CRITICAL JPM. 20098 NRC Exam Admin JPM SRO A4 Rev. Final Nov. 30,2009 AppendixC Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of testina: Shearon Harris Classify an event Page 1 of 7 Worksheet Form ES-C-l Task No.: 345001 H602 JPM No.: 2009B NRC Exam Admin JPM SRO A4 G2.4.41 RO 2.9 SRO 4.6 NRC Examiner Date: __ Simulated Performance: Actual Pertormance: __ Plant x Classroom X Simulator 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. Inhlal Condilions: Inillaling Cue: A refueling outage has just been completed and a plant heat up is being pertormed 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. Determine PAR if required. THIS IS A TIME CRITICAL JPM. 2009B NRC Exam Admin JPM SRO A4 Rev. Final Nov. 30, 2009

Appendix C Page 2 of 7 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. Final Nov. 30,2009 AppendixC Page 2 of 7 Wor1<sheet Task Standard: Event classified as an Site Area Emergency (2-4-3) Required Materials: None General

References:

PEP-HO EAL Flowpath EP-EAL (allowed reference) Handouts: JPM Cue Sheets Pages 4 and 5 PEP-HO 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-t 2009B NRC Exam Admin JPM SRO A4 Rev. Final Nov. 30, 2009

AppendixC 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. Final Nov. 30,2009 Appendix C Evaluator Note: START TIME: Performance Step: 1 Standard: Comment: ./ - Denotes a Crtlical Step Page 30f 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. Final Nov. 30, 2009

Appendix C ./ Performance Step: 2 Standard: Comment: STOP TIME: Terminating Cue: ./ - Denotes a Critical Step Page 4 of 7 PERFORMANCE INFORMATION CLASSIFY EVENT Identifies a 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. Final Nov. 30,2009 AppendixC ./ Perfonmance Step: 2 Slendard: Comment: STOP TIME: Terminating Cue: -t' - Denotes a Critical Step Page 40f 7 PERFORMANCE INFORMATION CLASSIFY EVENT Identifies a Site Area Emergency (2-4-3), Form ES-C-l 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 Ucensing 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. Final Nov. 30, 2009

Appendix C Page 5 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Job Performance Measure No.: 2009B 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: 2009B NRC Exam Admin JPM SRO A4 Rev. Final Nov. 30,2009 AppendixC Page 5 of 7 VERIFICATION OF COMPLETION Form ES-C-1 Job Perlormance Measure No.: 2QQ9B NRC Exam Admin JPM SRO A4 - Classify an event Examinee's Name: Date Perlormed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: SAT UNSAT Examiners Signature: Date: 2009B NRC Exam Admin JPM SRO A4 Rev. Final Nov. 30. 2009

Appendix C Initial Conditions: Initiating Cue: Form ES-C-1 JPM CUE SHEET 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. Determine PAR if required. THIS IS A TIME CRITICAL JPM 2009B NRC Exam Admin JPM SRO A4 Rev. Final Nov. 30,2009 AppendixC Inilial Condillons: Inillallng Cue: Form ES-C-1 JPM CUE SHEET A relueling outage has just been completed and a plant heat up is being perionmed lAW GP-002, Nonmal 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. Determine PAR if required. THIS IS A TIME CRITICAL JPM 2009B NRC Exam Admin JPM SRO A4 Rev. Final Nov. 30, 2009

Appendix C Form ES-C-1 JPM CUE SHEET CLASSIFICATION INFORMATION SHEET 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. Final Nov. 30, 2009 Appendix C Form ES*C*l JPM CUE SHEET CLASSIFICATION INFORMATION SHEET 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 ReS 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 mrlhr. Classify tile event Name ______________________________________________ _ Record your classification here and return to the examiner. EAL Cla.sirlcatlon: ______________________ _ 2009B NRC Exam Admin JPM SRO A4 Rev. Final Nov. 30,2009

SIDE 1 FPB STATUS MARC .s.CPNIOfztO_ ,,(OI"NIDllO_ ..(Of'AMlZlO_ -...oa _ ~ MOOCD EAI.. TA8L£ 1 RADIATION "'OHIlOR TAC NUMBERS ~4:t -=: =-- EAL. TABLE 2 .. ~--..... = EAL STATUS BOARD lAL'V.MO(S).! SIDE 1 ___..-.n _ =

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