ML051890097
| ML051890097 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/24/2005 |
| From: | Mccall K AmerGen Energy Co |
| To: | D'Antonio J Operations Branch I |
| Conte R | |
| References | |
| -RFPFR | |
| Download: ML051890097 (53) | |
Text
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
TMI - Unit 1 Task No.:
001C030101 Task
Title:
Review and amrove an Estimated JPM No.:
2005 NRC A l - I Critical Boron Concentration calculation.
WA
Reference:
2.1.25 (3.1)
Examinee:
Facility Evaluator:
NRC Examiner:
Date:
Method of testina:
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:
e e
e e
e A sequential trip of both main feedwater pumps resulted in a reactor trip 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> ago.
The unit had been at 100% power for 150 days prior to the reactor trip.
Cycle Burnup is 310 EFPD.
TAVE = 532'F Current Boron Concentration = 985 PPM The Desired Critical Rod Position is: 80% WD on CRG-6.
CRG-8 position is 30%.
The FINAL MIXED BORON DEPLETION CORRECTION FACTOR as specified in the control room log is.95.
The Plant Process Computer is NOT available.
No reactor engineering personnel are on site.
11 03-1 5B, Enclosure 1, ESTIMATED CRITICAL BORON CONCENTRATION, has been prepared by a licensed operator.
Task Standard:
Performs correct calculation, identifies Xe curve reading error, and returns original enclosure unapproved.
Required Materials:
Calculator Straight Edge General
References:
1103-1 5B, ESTIMATED CRITICAL CONDITIONS, Rev. 35 Handouts:
Completed 1103-158, Enclosure 1 e
Figures 1-6 NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue:
You are the Control Room Supervisor on duty. Perform an independent Estimated Critical Boron Concentration calculation using 1 103-1 58,, then evaluate the approval of both calculations in accordance with Step 3.1.2.4.5.2 of 1103-158, ESTIMATED CRITICAL CONDITIONS.
Time Critical Task:
No Validation Time:
17 minutes SIMULATOR SETUP NIA NUREG 1021. Revision 9
Appendix C Page 3 of 7 PERFORMANCE INFORMATION Form ES-C-1 (Denote Critical Steps with a check)
Performance Step: 1 Locates/reviews procedure.
Standard:
0 Determines Section 3.1 applies.
0 Reviews LIMITS AND PRECAUTIONS.
Comment:
Evaluator Cue:
0 Provide a copy of the prepared 1103-15B, Enclosure
- 1.
Provide a clean copy of I 1 03-1 5B Section 1.O through 3.1 and Enclosure 1.
0 Performance Step: 2 Standard:
Records present conditions (TAVE, Burnup, Boron Concentration, Desired Critical Rod Positions).
Completes Enclosure 1, 2.a -2.d, with initial condition information given.
Comment:
Evaluator Cue:
No major boron concentration changes have been made since the last analysis.
4 Performance Step: 3 Determine the FUEL EXCESS REACTIVITY per Figure 1.
Records 11.8% dk/k in Step 3.a Standard:
Comment:
4 Performance Step: 4 Determine the DESIRED CRITICAL CRG 5-7 REACTIVITY WORTH of Step 2.d per Figure 6 Records value between -1.02% to -1.16% dk/k in Step 3.b Standard :
Comment:
4 Performance Step: 5 Determine the DESIRED CRITICAL CRG 8 REACTIVITY WORTH of Step 2.d per Figure 2 Records value between -0.1 16 to -0.121 % dk/k in Step 3.c.
Standard :
Comment:
NUREG 1021, Revision 9
Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 6 Obtain the Xenon worth per Figure 4.
Records value between -0.48% to -0.5% dk/k in Step 3.d.
Standard:
Comment:
Evaluator Cue:
The Plant Process Computer Program and Nuclear Engineering are unavailable. Figure 4 was used for the completed Enclosure 1.
.(
Performance Step: 7 Determine the reactivity associated with SAMARIUM AND PLUTONIUM BUILDUP after shutdown by using Figure 5.
Records value between -0.07 to -0.08 dk/k in Step 3.e Standard:
Comment:
4 Performance Step: 8 Determine the BORON REACTIVITY WORTH REQUIRED FOR CRITICALITY.
Standard:
Calculates BORON REACTIVITY WORTH REQUIRED FOR CRITICALITY and Records values between -1 0.546 to -9.939%
dk/k in Step 4.1.
Comment:
.(
Performance Step: 9 Determine the HZP INVERSE BORON WORTH associated with cycle burnup per Figure 3.
Records value between 141.5 to 4 4 2 ppmB/%dk/k in Step 4.2.
Standard:
Comment:
4 Performance Step: 10 Determine the CORRECTED CRITICAL BORON CONCENTRATION by multiplying the required boron worth (Step 4.1) by the HZP Inverse Boron Worth (Step 4.2)
Standard :
Calculates CORRECTED CRITICAL BORON CONCENTRATION and Records value in Step 4.3.1 Comment:
NUREG 1021, Revision 9
Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 11 Determine the FINAL MIXED BORON DEPLETION CORRECTION FACTOR based on current correction factor and accounting for predicted boron additions.
Records 0.95 in Step 4.3.2 Standard:
Comment:
Evaluator Cue:
If necessary: The FINAL MIXED BORON DEPLETION CORRECTION FACTOR in the control room log is.95.
4 Performance Step: 12 Determine the ESTIMATED MEASURED CRITICAL BORON CONCENTRATION by dividing the CORRECTED CBC (Step 4.3.1) by the DEPLETION CORRECTION FACTOR (4.3.2)
Standard:
Calculates ESTIMATED MEASURED CRITICAL BORON CONCENTRATION and Records value between 1463 to 1523 PPM in Step 4.3.3.
Comment:
1464 to 1524 PPM Band is +/- 2% error around 1494 PPM.
Performance Step: 13 Standard:
Sign the appropriate location on Enclosure 1 Verifies Enclosure 1 completed then signs and dates calculation Comment:
Candidate may not sign Enclosure 1 since the performance of the enclosure is for review purposes.
4 Performance Step: 14 Independent licensed SRO reviews and approves the calculation.
Reviews original Enclosure 1 calculation against independently performed calculation.
Standard:
0 0
Identifies graph reading error of (-0.25) on Step 3.d Identifies ESTIMATED MEASURED CRITICAL BORON CONCENTRATION out of acceptable limit Returns original completed Enclosure 1 unapproved.
0 Comment:
Terminating Cue:
1464 to 1524 PPM Band is +/- 2% error around 1494 PPM.
When the candidate returns Enclosure 1 to the examiner:
This JPM is complete.
NUREG 1021, Revision 9
Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2005 NRC Al-I Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result:
SAT UNSAT Examiners Signature:
Date:
NUREG 1021, Revision 9
Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET L
INITIAL CONDITIONS:
e e
e e
e A sequential trip of both main feedwater pumps resulted in a reactor trip 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> ago.
The unit had been at 100% power for 150 days prior to the reactor trip.
Cycle Burnup is 310 EFPD.
TAVE = 532'F Current Boron Concentration = 985 PPM The Desired Critical Rod Position is: 80% WD on CRG-6.
CRG-8 position is 30%.
The FINAL MIXED BORON DEPLETION CORRECTION FACTOR as specified in the control room log is.95.
The Plant Process Computer is NOT available.
No reactor engineering personnel are on site.
11 03-1 5B, Enclosure 1, ESTIMATED CRITICAL BORON CONCENTRATION, has been prepared by a licensed operator.
INITIATING CUE:
You are the Control Room Supervisor on duty. Perform an independent Estimated Critical Boron Concentration calculation using 1103-1 58, Enclosure 1, then evaluate the approval of both calculations in accordance with Step 3.1.2.4.5.2 of 1 103-1 56, ESTIMATED CRITICAL CONDITIONS.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
TMI - Unit 1 Task No.:
341 0020303 Task
Title:
Venfv the EquiDment Status Taq JPM NO.:
2005 NRC A1-2 Loa SUPPO~~S unit startup.
WA
Reference:
2.1.23 (4.0)
Examinee:
Facility Evaluator:
NRC Examiner:
Date:
Method of testing:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant X
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:
Task Standard:
Required Materials:
General
References:
Handouts:
Initiating Cue:
0 0
The unit is shutdown with TAVE at 190 "F The operating crew is performing OP-AA-108-108, UNIT RESTART REVIEW, in preparation for beginning a plant heatup in accordance with procedure 11 02-1, PLANT HEATUP TO 525 "F.
ldentlfy any item@) that would preclude plant heatup and notify the Shift Manager.
Location with plant references and LAN access or in the control room.
0 0
OP-AA-108-108, UNIT RESTART REVIEW, Rev. 2 1102-1, PLANT HEATUP TO 525 'F, Rev. 163 0
Equipment Status Tag Log with RC-V-1-EX2 in MANUAL (waiting for a replacement card for the AUTO circuit) and 4-5 other items that will not affect startup.
OP-AA-108-108, ATTACHMENT 5 OP-TM-220-000, REACTOR COOLANT SYSTEM 1 102-1, PLANT HEATUP TO 525 "F The Shift Manager has assigned you to complete OP-AA-108-108, ATTACHMENT 5, Step 8, in preparation for initiating a plant heatup IAW 1102-1, PLANT HEATUP TO 525 "F.
Time Critical Task:
No NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time:
12 minutes I
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP NIA NUREG 1021, Revision 9
Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION
.- (Denote Critical Steps with an asterisk)
Performance Step: I Standard:
Reviews OP-AA-108-108, ATTACHMENT 5 Reviews OP-AA-108-108, ATTACHMENT 5, Step 8 Comment:
Evaluator Cue:
0 Provide OP-AA-108-108, ATTACHMENT 5 Provide 1102-1, PLANT HEATUP TO 525 'F Provide a copy of Equipment Status Tag Log Performance Step: 3 Standard :
Evaluate items listed on the Equipment Status Tag Log.
Compare each item listed on the Equipment Status Tag Log to the requirements of procedure 1 102-1.
Comment:
Evaluator Cue:
Provide a copy of OP-TM-220-000 when requested.
4 Performance Step: 4 Identify each item that will preclude plant heatup.
Identifies RC-V-1 -EX2 must be in AUTO per OP-TM-220-000, System Mode Lineups.
Standard:
Comment:
4 Performance Step: 5 Notify Shift Manager.
Standard:
Comment:
Evaluator Cue:
Terminating Cue:
Informs Shift Manager that ATTACHMENT 5, Step 8 cannot be signed until RC-V-1-EX2 can be placed in AUTO.
Respond as Shift Manager.
After the candidate notifies the Shift Manager: This JPM is complete.
NUREG 1021, Revision 9
Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
TMI 2005 NRC JPM A1-2 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result:
SAT UNSAT Examiners Signature:
Date:
NUREG 1021, Revision 9
Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
0 The unit is shutdown with TAVE at 190 "F.
0 The operating crew is performing OP-AA-108-108, UNIT RESTART REVIEW, in preparation for beginning a plant heatup in accordance with procedure 1 102-1, PLANT HEATUP TO 525 "F.
INITIATING CUE:
You are an extra SRO assigned to assist the Shift Manager in the completion of OP-AA-108-108, UNIT RESTART REVIEW. The Shift Manager has assigned you to complete OP-AA-108-108, ATTACHMENT 5, Step 8 - Verify the Equipment Status Tag Log supports startup.
NUREG 1021, Revision 9
E, ment Status Tag Number Date Issued Component System Reason for Applying Approved ACPS #
Resolution for Removed
\\
Removal 1
Desiunation Number Taus Bv Removal Date BY 04.50 PM 20050044 5/10/2005 08.37 AM 20050043 5/09/2005 05.28 PM 20050042 5/08/2005 01.33 PM 20050041 5/08/2005 09.26AM 20050040 5/07/2005 10.47 AM Cooler System correctly and RB-V-37 Stubbs is being used to maintain system IeveVpressure Control Bldg 826 Control AH-E-93NB - 94NB James A Hallway Fan Building &
turned off for testing Stubbs Machine Shop H&V Systems FS-P-0004 811 Fire FS-P-4 running in Hand Jerome M Protection Gingher Service Water System 2005-015 Testing complete 2005-014 Pressure switch FS-PS-586 is repaired RC-V-1 -EX2 220 Reactor RC-V-1 -EX2 placed in David Wilson RC-V-1 -EX2 Auto Coolant System Manual waiting for circuit repaired replacement card for the Auto circuit IA-V-0598, 852 Instrument IA-V-598 & WDG-V-77 Joseph A WDG-V-77 Air CLOSED PER OP Csordas 1104-27 SECT. 3.14.2 WDL-LI-207 232 Liquid WDL-LI-207 leaks.
Kevin Radwaste Sightglass isolated Coughlin Disposal System Repair check valve
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
TMI Unit 1 Task No.:
1198030101 Task
Title:
Evaluate a completed surveillance JPM No.:
2005 NRC JPM A2 procedure and perform appropriate actions IAW AP 1041, IST Program Requirements, Section 4.4.3.
WA
Reference:
2.2.12 (3.4)
Examinee:
NRC Examiner:
Facility Eva1 ua t o r:
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:
0 The unit is shutdown.
RCS temperature is 260 'F.
0 Both DH Trains are in the ES Standby Mode.
0 OP-TM-212-203, IST OF DH-P-1A IN ES STANDBY MODE, was just completed.
Task Standard:
Alert range vibration reading identified and follow-up action initiated.
Required Materials:
AP 1041, IST PROGRAM REQUIREMENTS General
References:
OP-TM-212-203, IST OF DH-P-1A IN ES STANDBY MODE, Rev. 4 AP 1041, IST PROGRAM REQUIREMENTS, Rev. 41 Handouts:
Initiating Cue:
A completed OP-TM-212-203 with one or more vibration readings in the alert range.
You are the Control Room Supervisor. Review the completed OP-TM-212-203. Assume that the current revision of the procedure was utilized to perform the test.
Time Critical Task:
NIA I Validation Time:
16 minutes.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP NIA -
NUREG 1021, Revision 9
Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check)
Evaluator Cue:
Performance Step: 1 Standard:
Comment:
Performance Step: 2 Standard:
Comment:
.I Performance Step: 3 Standard:
Comment:
Eva1 uator Cue:
.I Performance Step: 4 Standard:
Comment:
Evaluator Cue:
Provide completed OP-TM-212-203 and range value table.
Review procedure.
Verify all required steps completed/initialed.
Review collected data.
Compare collected data to the provided range value table.
Identify any data outside of NORMAL range.
Identifies Inboard and Outboard Vib Vertical readings in the ALERT (Double Frequency) region.
Assume that the instruments utilized were properly calibrated and there is no system alignment problem that contributed to the readings.
Review Attachment 7.2, Data Sheet.
Checks/Marks block Pump test data in ALERT range.
If asked relative to the AWCR and burned out light bulb blocks on ATT. 7.2:
No degraded conditions discovered.
0 There are no burned out light bulbs.
NUREG 1021, Revision 9
Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION 4 Performance Step: 5 Refers to AP 1041.
Standard:
Determines 4.4.3.c.7 applies.
0 Submit a CR and document equipment operability status Notify the Engineering Duty Manager (EDM).
Notify the PdM vibration expert.
0 0
Comment:
Evaluator Cue:
Terminating Cue:
0 0
If requested, provide a copy of AP 1041.
If the candidate begins a discussion on re-test of the pump: Re-test of the pump will not be performed at this time.
If the candidate begins discussion on writing a CR: a CR has been submitted and equipment operability status has been logged IAW LS-AA-105.
Respond as the EDM and the PdM vibration expert.
0 0
When AP 1041, 4.4.2.c.7 has been completed: This JPM is complete.
NUREG 1021, Revision 9
Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2005 NRC JPM A2 Examinee's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result:
SAT UNSAT Examiner's Signature:
Date:
NUREG 1021, Revision 9
Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
The unit is shutdown.
0 RCS temperature is 260 "F.
Both DH Trains are in the ES Standby Mode.
MODE, was just completed.
OP-TM-212-203, IST OF DH-P-1A IN ES STANDBY INITIATING CUE:
You are the Control Room Supervisor. Review the completed OP-TM-212-203. Assume that the current revision of the procedure was utilized to perform the test.
NUREG 1021, Revision 9
~-
Appendix C Job Performance Measure Form ES-C-I Worksheet Facility:
TMI Unit 1 Task
Title:
Authorize emergency personnel radiation exposure in excess of 5 Personnel Protective Actions, Section 4.3.3.
Reference:
2.3.4 (3.1)
Examinee:
Facility Evaluator:
Method of testinq:
Simulated Performance:
Classroom X
Simulator Task No.:
5001045013 JPM No.:
2005 NRC JPM A3 NRC Examiner:
Date:
Actual Performance:
X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Task Standard:
Required Materials:
General
References:
Handouts:
Initiating Cue:
Time Critical Task:
0 A large break LOCA occurred; including significant fuel damage.
0 The TSC is manning but has not been activated.
0 A missing operator has been located. He is seriously injured, conscious, but unable to move and lying in an uncontaminated area where the general radiation level is 200 R/hr.
0 It is estimated that four people using a stretcher can move him out of the area in a maximum of 5 minutes.
0 Four people have volunteered to perform the task. Pertinent information is provided below.
0 No radiation management personnel have arrived on site.
Emergency exposure approved IAW EP-AA-113-F-02 Calculator EP-AA-113, PERSONNEL PROTECTIVE ACTIONS, Rev. 5 EP-AA-113 (after clean copy is located by the candidate).
You are the Emergency Director. Perform the required actions prior to dispatching the team of volunteers to rescue the injured man.
N/A NUREG 1021, Revision 9
Job Performance Measure Form ES-C-1 Appendix C Worksheet Validation Time:
15 minutes NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP NIA NUREG 1021, Revision 9
Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an a check mark)
Performance Step: 1 Standard:
Comment:
Evaluator Note:
Evaluator Cue:
Performance Step: 2 Standard:
Comment:
Evaluator Cue:
Performance Step: 3 Standard:
Comment:
4 Performance Step: 4 Standard:
Comment:
Evaluator Cue:
Calculate exposure.
Determines exposure > 5 Rem TEDE will be received.
This step may be performed later in the process.
It may be necessary to direct the candidate to deal with the situation presented and not the overall emergency response effort.
If EPA-400 is requested: Limit your actions to EXELON procedure requirements.
Determine EP-AA-113 applies.'
Locates EP-AA-113 and refers to Section 4.3, Emergency Exposure Limits.
Provide clean copy of EP-AA-113 Apply EP-AA-113, Section 4.3 Determines emergency exposure is for a bonafide emergency.
Apply EP-AA-113, Section 4.3.
6 0
Plan emergency operations prior to entry. (4)
Wear respiratory protection and protective clothing to reduce contamination where possible. (N/A per initial conditions)
Discusses requirement.
Assume that the plan was approved when it was determined that the individual could be moved by four people in 5 minutes, or less.
NUREG 1021, Revision 9
Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION 4
Performance Step: 5 Determine if emergency exposure limits in excess of 5 Rem TEDE are required for EXELON emergency workers.
Determines that maximum stay time would result in >5 Rem TEDE.
Standard:
Comment:
4 Performance Step: 6 Complete an Authorization for Emergency Exposure Form (EP-AA-1 1 3-F-02).
Standard:
0 Completes EP-AA-113-F-02 for each volunteer.
Checks Block 2 (>10<25 Rem).
0 Informs the volunteers and obtains their acknowledgment that the task is voluntary and theyre aware of the risks.
Have volunteer sign after reviewing Attachment 1, EMERGENCY WORKER EXPOSURE LIMITS AND ASSOCIATED RISKS.
0 Signs as Station EmergencyDirector.
Comment:
Evaluator Cue:
Completion of EP-AA-113-F-02 for only ONE volunteer will meet the requirements of this critical task.
Provide 4 copies of EP-AA-113-F-02.
If candidate discusses obtaining volunteers acknowledgment that they have volunteered and they are aware of associated risks involved: All volunteers verbally acknowledge they understand they have volunteered and are aware of the risks associated with Attachment l..
0 NUREG 1021, Revision 9
Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION d
Performance Step: 7 Identifies emergency exposure limit of 25 Rem TEDE exceeded by Volunteer ## 4 Determines emergency exposure in excess of 25 Rem TEDE shall be limited to once in a lifetime Standard:
Comment:
Terminating Cue:
After candidate identifies Volunteer ##4 can not be used for the rescue efforts: This JPM is complete.
NUREG 1021, Revision 9
Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
TMI 2005 NRC JPM A3 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result:
SAT UNSAT Examiners Signature:
Date:
NUREG 1021, Revision 9
Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET NAME Volunteer #1 Volunteer #2 Volunteer #3 Volunteer #4 INITIAL CONDITIONS:
0 0
A large break LOCA occurred; including significant fuel damage.
The TSC is manning but has not been activated.
A missing operator has been located. He is seriously injured, conscious, but unable to move and lying in an uncontaminated area where the general radiation level is 200 Whr.
It is estimated that four people using a stretcher can move him out of the area in a maximum of 5 minutes.
Four people have volunteered to perform the task.
Pertinent information is provided below.
No radiation management personnel have arrived on site.
0 0
0 SSN CURRENT ANNUAL PAST WORK HISTORY EXPOSURE 123-45-6789 300 mRem None 234-56-7890 250 mRem None 345-67-8901 400 mRem None 456-78-901 2 150 mRem Volunteered at Chernobyl - received 30 Rem TEDE INITIATING CUE:
You are the Emergency Director. Perform the required actions prior to dispatching the team of volunteers to rescue the injured man.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
TMI Unit 1 Task No.:
5001045001 Task
Title:
Emergency Action Level JPM No.:
2005 NRC JPM A4 Identification and Event Declaration.
PART A1 K/A
Reference:
2.4.41 (4.1)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testina Simulated Performance:
Actual Performance:
X Classroom Simulator X
Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Task Standard:
Required Materials:
General
References:
Handouts:
Initiating Cue:
Time Critical Task:
Reactor Power is at 80%
AH-E-1A is tagged out of service CRD Aux Programmer is out of service for maintenance The events of your scenario have just occurred and the mitigating actions you have taken are complete Examinee classifies the event as ALERT under FA1 within 15 minutes of direction to classify the event.
EAL Table Shift Emergency Director Book EP-AA-111, EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS, Rev. 9 CHECKLIST, Rev. C EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR EALTable EAL Table Shift Emergency Director Book You are the Shift Manager. Identify the EAL and classify the event based on highest classification reached during the current scenario IAW EP-AA-111. The frozen simulator and all notes taken during the scenario may be used to determine the classification.
YES (415 minutes)
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time:
12 minutes NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP NIA NUREG 1021, Revision 9
Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check)
Evaluator Cue:
If this is to be performed in a classroom environment, provide handouts listed on the cover page.
Mark the START time of the JPM:
Compare current conditions to the EAL Table and identifies the specific EAL(s) applicable.
Determines that an ALERT condition exists based on:
FA1, LOSS OF REACTOR COOLANT SYSTEM BARRIER, (< 25F Sub-cooled Margin) 4 Performance Step: 1 Standard:
0 Comment:
4 Performance Step: 2 Implement EP-AA-112-100-F-01, Section 1.2.A.
Standard:
Comment:
Evaluator NOTE:
STOP TIME:
0 Announce Event Classification to the facility staff.
Declares an ALERT based on FA1 and identifies himself as the Emergency Director.
When the candidate has declared the event classification:
The JPM may be terminated TIME CRITICAL STOP TIME:
NUREG 1021, Revision 9
Appendix C Page 5 of 6 Form ES-C-1 VERI F KAT1 ON OF COM PLETION Job Performance Measure No.:
2005 NRC JPM A4, PART A1 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result:
SAT UNSAT Examiners Signature:
Date:
NUREG 1021, Revision 9
Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
Reactor Power is at 80%
AH-E-1A is tagged out of service CRD Aux Programmer is out of service for maintenance The events of your scenario have just occurred and the mitigating actions you have taken are complete INITIATING CUE:
You are the Shift Manager. identify the EAL and classify the event based on highest classification reached during the current scenario IAW EP-AA-111. The frozen simulator and all notes taken during the scenario may be used to determine the classification.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
TMI Unit 1 Task No.:
5001045001 Task
Title:
Emergency Action Level JPM No.:
2005 NRC JPM A4 Identification and Event Declaration.
PART A2 K/A
Reference:
2.4.41 (4.1)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testing:
Simulated Performance:
Actual Performance:
x Classroom Simulator X
Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Task Standard:
Required Materials:
General
References:
Handouts:
Initiating Cue:
Reactor Power is at 100%
AH-E-1A is tagged out of service DC-P-1A is operating in accordance with OP-TM-543-401 to support chemistry sampling.
CRD Aux Programmer is out of service for maintenance The events of your scenario have just occurred and the mitigating actions you have taken are complete Examinee classifies the event as an UNUSUAL EVENT under !-J&
within 15 minutes of direction to classify the event.
0 EAL Table 0
Shift Emergency Director Book EP-AA-111, EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS, Rev. 9 CHECKLIST, Rev. C EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR 0
Shift Emergency Director Book au are the Shift Manager. Identify the LL and classify the event based on highest classification reached during the current scenario IAW EP-AA-111. The frozen simulator and all notes taken during the scenario may be used to determine the classification.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task:
Validation Time:
12 minutes YES (SI5 minutes)
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP NIA NUREG 1021, Revision 9
Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Y
(Denote Critical Steps with a check)
Evaluator Cue:
If this is to be performed in a classroom environment, provide handouts listed on the cover page.
Mark the START time of the JPM:
Compare current conditions to the EAL Table and identifies the specific EAL(s) applicable.
4 Performance Step: 1 Standard:
Determines that an UNUSUAL EVENT condition exists based on:
0 HU6, A Potential Degradation in the Level of Plant Safety, (Uncontrolled RCS cooldown due to secondary depressurization)
Comment:
4 Performance Step: 2 Implement EP-AA-112-100-F-01, Section 1.2.A.
Standard:
0 Announce Event Classification to the facility staff.
Declares an UNUSUAL EVENT based on HU6 and identifies himself as the Emergency Director.
Comment:
Evaluator NOTE:
When the candidate has declared the event classification:
The JPM may be terminated STOP TIME:
TIME CRITICAL STOP TIME:
NUREG 1021, Revision 9
Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2005 NRC JPM A4. PART A2 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result:
SAT UNSAT Examiners Signature:
Date:
NUREG 1021, Revision 9
Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET IN IT1 AL CONDITIONS:
Reactor Power is at 100%
AH-E-1A is tagged out of service DC-P-1A is operating in accordance with OP-TM-543-401 to support chemistry sampling.
CRD Aux Programmer is out of service for maintenance The events of your scenario have just occurred and the mitigating actions you have taken are complete INITIATING CUE:
You are the Shift Manager. Identify the EAL and classify the event based on highest classification reached during the current scenario IAW EP-AA-111. The frozen simulator and all notes taken during the scenario may be used to determine the classification.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
TMI Unit 1 Task No.:
5001 045001 Task
Title:
Emergency Action Level JPM No.:
2005 NRC JPM A4 v
Identification and Event Declaration.
PART A3 K/A
Reference:
2.4.41 (4.1)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testing:
Simulated Performance:
Actual Performance:
X Classroom Simulator X
Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Reactor Power is at 5%
Plant startup in progress AH-E-1A is tagged out of service ICs in Manual control due to startup operations The events of your scenario have just occurred and the mitigating actions you have taken are complete Task Standard:
Examinee classifies the event as a SITE AREA EMERGENCY under FS1 and/or MS4 within 15 minutes of direction to classify the event.
Required Materials:
0 EAL Table 0
Shift Emergency Director Book General
References:
EP-AA-111, EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS, Rev. 9 CHECKLIST, Rev. C EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR 0
EAL Table Handouts:
Initiating Cue:
0 EALTable Shift Emergency Director Book You are the Shift Manager. Identify the EAL and classify the event based on highest classification reached during the current scenario IAW EP-AA-111. The frozen simulator and all notes taken during the scenario may be used to determine the classification.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task:
YES (SI 5 minutes)
Validation Time:
12 minutes NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP NIA NUREG 1021, Revision 9
Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check)
Evaluator Cue:
If this is to be performed in a classroom environment, provide handouts listed on the cover page.
Mark the START time of the JPM:
4 Performance Step: 1 Compare current conditions to the EAL Table and identifies the specific EAL(s) applicable.
Standard:
Determines that a SITE AREA EMERGENCY condition exists based on:
FS1, POTENTIAL LOSS OF RCS BARRIER, (Calculated leak rate > 160 gpm and Loss of RCS inventory into BARRIER, (Total OTSG leak > 1 gpm and Turbine driven ERN pump exhaust)
MS4, Auto and Manual SCRAM NOT Successful (RPS fails to auto initiate and complete a reactor trip when ANY RPS setpt is exceeded, AND Reactor power >5%, AND Manual trip from the Control Room was NOT successful)
OTSG) -AND-LOSS OF PRIMARY CONTAINMENT Comment:
Evaluator NOTE:
This critical task is met if the candidate selects either FS1 or MS4 for bases of classification 4 Performance Step: 2 Implement EP-AA-112-100-F-01, Section 1.2.A.
Announce Event Classification to the facility staff.
Standard:
Comment:
Evaluator NOTE:
Declares a SITE AREA EMERGENCY based on FS1 and/or MS4 and identifies himself as the Emergency Director.
When the candidate has declared the event classification:
The JPM may be terminated STOP TIME:
TIME CRITICAL STOP TIME:
NUREG 1021, Revision 9
Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2005 NRC JPM A4, PART A3 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result:
SAT UNSAT Examiners Signature:
Date:
NUREG 1021, Revision 9
Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
Reactor Power is at 5%
Plant startup in progress AH-E-1A is tagged out of service ICs in Manual control due to startup operations The events of your scenario have just occurred and the mitigating actions you have taken are complete INITIATING CUE:
You are the Shift Manager. Identify the EAL and classify the event based on highest classification reached during the current scenario IAW EP-AA-111. The frozen simulator and all notes taken during the scenario may be used to determine the classification.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
TMI Unit 1 Task No.:
5001045008 Task
Title:
Given a set of conditions, upgrade JPM No.:
2005 NRC JPM A4 -
.~
an EAL and make a Protective Action Recommendation (PAR) IAW the facility Emergency Plan.
PART B K/A
Reference:
2.4.44 (4.0)
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:
a a
0 a
a a
0 a
a a
A large break LOCA caused an ESAS actuation and reactor trip.
A containment purge was in progress at the time of the trip. The containment purge valves failed to close and all attempts to close them have failed.
The initial declaration was a Site Area Emergency (FS1 - SAE) 20 minutes ago.
CHECKLIST, has been implemented.
The Technical Support Center (TSC) is manning but not activated.
RM-G-22 reads 2.0 E+03 Whr.
RM-G-23 reads 2.2 E+03 Whr.
The RO reports that the RM-G-24 (RB Purge) reading has increased from 4.1 E+05 mWhr to 5E+05 mWhr in the past minute.
Outside temperature is 59 "F.
The wind is from 220" at 12 MPH.
EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR Task Standard:
Critical facility requirements for upgrading to a GE and making a PAR completed within the required time limit.
Required Materials:
0 EALTable 0
Shift Emergency Director Book NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet General
References:
0
-L.
0 0
0 0
0 0
0 0
0 Handouts:
EP-AA-111, EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS, Rev. 9 EP-AA-111-F-09, TMI PLANT BASED PAR FLOWCHART, Rev.
B EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST, Rev. C EP-AA-112-F-09, Rev. A, EMERGENCY PUBLIC ADDRESS ANNOUNCEMENTS FORM, Rev. B NOTI FlCATlONS EP-AA-114-F-01, Rev. A, COMMAND AND CONTROL TURNOVER BRIEFING FORM EAL Table EP-MA-114-F-01, STATEILOCAL EVENT NOTIFICATION EP-MA-114-100, MID-ATLANTIC STATE/LOCAL EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST, Rev. C, completed for an SAE EAL Table completed for FS1 SAE Declaration EP-AA-114-F-01, Rev. A, COMMAND AND CONTROL TURNOVER BRIEFING FORM Initiating Cue:
You are the Shift Manager. Respond in accordance with the EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST.
/
Time Critical Task:
YES (SI 5 minutes)
Validation Time:
12 minutes NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP NIA NUREG 1021, Revision 9
Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check)
Evaluator Cue:
Performance Step: 1 Standard:
Comment:
Performance Step: 2 Standard:
Comment:
.I Performance Step: 3 Standard:
Comment:
Evaluator NOTE:
Performance Step: 4 Standard:
Provide handout listed on the cover page.
Compare current conditions to the EAL Table.
Determine conditions are met for upgrading EAL to a GENERAL EMERGENCY (GE).
Implement EP-AA-112-100-F-01 for GE Refers to Section 1.4 Implement EP-AA-112-100-F-01, Section 1.4.A:
0 Announce Event Classification to the facility staff.
Discusses announcement of upgrade to GE.
Mark the time of the announcement:
Implement EP-AA-112-100-F-01, Section 1.4.8:
0 Use the Emergency Public Address Announcements form to select and direct the appropriate public address announcement for a GE.
Simulates announcement IAW with Tab 1, EMERGENCY PUBLIC ADDRESS ANNOUNCEMENTS.
Comment:
Performance Step: 5 Implement EP-AA-112-100-F-01, Section 1.4.C:
0 If the ERO has not been activated - - -.
Standard:
Comment:
NUREG 1021. Revision 9
Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 Implement EP-AA-112-100-F-01, Section 1.4.D:
Determine the correct plant-based PAR per the Emergency Classification and Protective Action Recommendations procedure and the appropriate site specific PAR flowchart.
Standard:
Refers to Tab 6 - EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS Refers to Tab 7 - TMI PLANT BASED PAR FLOWCHART 0
Comment:
d Performance Step: 7 Implement EP-AA-112-100-F-01, Section 1.4.E:
Initiate required State/Local notifications within 15 minutes of the event classification as required per notifications procedure.
Standard:
Comment:
Evaluator NOTE:
Terminating Cue:
Signs and hands STATE/LOCAL EVENT EMERGENCY NOTIFICATION FORM to Communicator within 15 minutes.
Requirements on ENF to meet critical task:
3.a EMERGENCY CLASSIFICATION - GE ACTION LEVEL NO. - RG1 or FG1 5.b Checked - AIRBORNE non-routine radiological release in-progress 7.b checked - PAR in the TMI Block:
4.a EMERGENCY EVACUATE 360 DEGREES FROM 0 TO fl MILES AND - - - -.
Mark the time that the notification form is provided to the communicator:
When the candidate hands the completed Notification Form to the Communicator - This JPM is complete.
NUREG 1021, Revision 9
Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2005 NRC JPM A4 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result:
SAT UNSAT Examiners Signature:
Date:
NUREG 1021, Revision 9
Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
e e
e e
e e
e e
A large break LOCA caused an ESAS actuation and reactor trip.
A containment purge was in progress at the time of the trip. The containment purge valves failed to close and all attempts to close them have failed.
The initial declaration was a Site Area Emergency (FS1 -
SAE) 20 minutes ago.
CHECKLIST, has been implemented.
The Technical Support Center (TSC) is manning but not activated.
RM-G-22 reads 2.0 E+03 R/hr.
RM-G-23 reads 2.2 E+03 R/hr.
The RO reports that the RM-G-24 (RB Purge) reading has increased from 4.1 E+05 mR/hr to 5E+05 mR/hr in the past minute.
Outside temperature is 59 'F.
The wind is from 220" at 12 MPH.
EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR INITIATING CUE:
You are the Shift Manager. Respond in accordance with the EP-CHECKLIST.
AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR NUREG 1021, Revision 9