ML14090A457
| ML14090A457 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/31/2014 |
| From: | NRC/RGN-II |
| To: | Progress Energy Carolinas |
| Shared Package | |
| ML14091A073 | List: |
| References | |
| 50-400/14-301 | |
| Download: ML14090A457 (58) | |
Text
Appendix C Page 1 of 12 Form ES-C-1 Worksheet Facility: Shearon Harris Task No.: 301079H401 Task
Title:
During a Loss of Shutdown Cooling, JPM No.: 2013 NRC Retest Exam determine the time that the RCS will Admin JPM SRO A1-1 reach Core Boiling and Boil-Off K/A
Reference:
G2.1.20 RO 4.6 SRO 4.6 Examinee: ________________________ NRC Examiner: _________________
Facility Evaluator: ________________________ Date: ________
Method of testing:
Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
The unit was operating at 100% power for the last 15 months.
On 2/05/14 at 0000 the plant was shut down for a refueling outage.
- While the Reactor cavity was being filled the A RHR pump tripped.
Motor repairs are not expected to be completed until 2/25/14.
- The Reactor cavity fill was completed to the normal refueling levels with the B RHR pump.
- No fuel has been moved due to problems with the Manipulator Crane and Initial Conditions: the Source Range audible count rate.
The current date and time is 2/18/14 at 1200
- Fuel still remains in the vessel due to complications with the Manipulator crane.
- The B RHR pump just tripped.
- Core exit thermocouples are rising; they are currently reading 135°F.
In Accordance with AOP-020 you are directed to determine:
- 1. The time to reach core boiling and
- 2. Core boil-off time Initiating Cue:
Mark up your curves to indicate where you are determining these times.
Write your estimates of time to boil and time to boil-off on the lines at the bottom of this page (below).
Calculate your times in hours and minutes 2013 NRC Retest Exam Admin JPM SRO A1-1 Rev. 2
Appendix C Page 2 of 12 Form ES-C-1 Worksheet 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. 37) Curve Book curves H-X-8, 9, 10 and 11 (All Rev. 3)
Time Critical Task: No Validation Time: 10 minutes Critical Step Justification Step required in order to accurately determine time to boil using the Step 3 appropriate curve.
Step required in order to accurately determine time to boil-off using the Step 4 appropriate curve.
2013 NRC Retest Exam Admin JPM SRO A1-1 Rev. 2
Appendix C Page 3 of 12 Form ES-C-1 VERIFICATION OF COMPLETION START TIME:
Performance Step: 1 OBTAIN CURVES NEEDED FOR CALCULATION (Curve Book will be provided to the candidate)
Standard: Refers to curves H-X-8 through H-X-11 Comment:
Performance Step: 2 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 Standard: Reviews curves and determines which ones are appropriate to determine the time to boil and boil-off time Comment:
Performance Step: 3 Based on time since shutdown (2/05/14 - 2/18/14) 13 days 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> since shutdown and current RCS temperature of 135°F using curve H-X-9 determine time to boil.
(Interpolate 125°-150° lines)
Standard: Reviews curve H-X-9 Determines that time to boil is ~18 minutes
(+ 2 minutes, 16 - 20 min is acceptable)
Comment:
2013 NRC Retest Exam Admin JPM SRO A1-1 Rev. 2
Appendix C Page 4 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Performance Step: 4 Based on time since shutdown (2/05/14 - 2/18/14) 13 days 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> since shutdown and current RCS temperature of 135°F using curve H-X-11 determine time to boil-off Standard: Reviews curve H-X-11 Determines that time to boil-off is 4 hrs
(+ 15 minutes) or (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 15 minutes to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 45 minutes)
Comment:
Terminating Cue: After completing the time to boil and time to boil-off calculation, the evaluation on this JPM is complete.
END OF JPM STOP TIME:
2013 NRC Retest Exam Admin JPM SRO A1-1 Rev. 2
Appendix C Page 5 of 12 Form ES-C-1 VERIFICATION OF COMPLETION KEY Initial conditions: Reactor cavity filled for refueling without fuel movement due to Manipulator Crane and Source Range problems. Core cooling is lost at 1200 and 13 days after shutdown. Core Exit Thermocouples are rising and are currently 135°F. Estimated time to boiling onset will be approximately 18 minutes from the time of the loss of cooling event.
2013 NRC Retest Exam Admin JPM SRO A1-1 Rev. 2
Appendix C Page 6 of 12 Form ES-C-1 VERIFICATION OF COMPLETION KEY Initial conditions: Reactor cavity filled for refueling without fuel movement due to Manipulator Crane and Source Range problems. Core cooling is lost at 1200 and 13 days after shutdown. Core Exit Thermocouples are rising and are currently 135°F. Estimated time to reach boil off will be approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from the time of the loss of cooling event.
2013 NRC Retest Exam Admin JPM SRO A1-1 Rev. 2
Appendix C Page 7 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 NRC Retest Exam Admin JPM SRO A1-1 During a Loss of Shutdown Cooling, determine the time that the RCS will reach Core Boiling and Boil-Off Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
2013 NRC Retest Exam Admin JPM SRO A1-1 Rev. 2
Appendix C Form ES-C-1 JPM CUE SHEET On 2/05/14 at 0000 the plant was shut down for a refueling outage.
- While the Reactor cavity was being filled the A RHR pump tripped. Motor repairs are not expected to be completed until 2/25/14.
- The Reactor cavity fill was completed to the normal refueling levels with the B RHR pump.
- No fuel has been moved due to problems with the Manipulator Crane and the Source Range audible count rate.
Initial Conditions:
The current date and time is 2/18/14 at 1200
- Fuel still remains in the vessel due to complications with the Manipulator crane
- The B RHR pump just tripped.
- Core exit thermocouples are rising; they are currently reading 135°F.
In Accordance With AOP-020 you are directed to determine:
- 1. The time to reach core boiling and
- 2. Core boil-off time Initiating Cue:
Mark up your curves to indicate where you are determining these times.
Return all work including 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).
Calculate your times in hours and minutes Name ___________________________________________________________
Record your calculations here and return your curves to the examiner:
TIME TO BOIL (hours / minutes) _________________________
TIME TO BOIL-OFF (hours / minutes) _____________________
2013 NRC Retest Exam Admin JPM SRO A1-1 Rev. 2
Appendix C Form ES-C-1 JPM CUE SHEET 2013 NRC Retest Exam Admin JPM SRO A1-1 Rev. 2
Appendix C Form ES-C-1 JPM CUE SHEET 2013 NRC Retest Exam Admin JPM SRO A1-1 Rev. 2
Appendix C Form ES-C-1 JPM CUE SHEET 2013 NRC Retest Exam Admin JPM SRO A1-1 Rev. 2
Appendix C Form ES-C-1 JPM CUE SHEET 2013 NRC Retest Exam Admin JPM SRO A1-1 Rev. 2
Appendix C Page 1 of 9 Form ES-C-1 Worksheet Facility: Shearon Harris Task No.:
Task
Title:
Determine the amount of RCS JPM No.: 2013 NRC Retest Exam inventory that will be drained from Admin JPM SRO A1-2 RCS during the performance of GP-008, Draining the RCS K/A
Reference:
G2.2.25 RO 3.9 SRO 4.2 ALTERNATE PATH: No 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.
- A shift turnover is underway
- The previous shift is implementing GP-008, Draining The Reactor Coolant System
- A drain down of the RCS is in progress in preparation for the upcoming Refueling Outage Initial Conditions:
- The drain is on hold for turnover and level is currently being maintained stable at the Reactor Vessel Flange
- After turnover, the directions are to drain the RCS to -70 in preparation for Nozzle Dam installation
- The Shift Manager has given permission to enter lower inventory conditions.
You are the CRS. The Shift Manager wants to know how many gallons of water will be drained from the RCS to ensure adequate drain tank volume.
You are required to calculate the amount of additional water that will be Initiating Cue: drained from the RCS from the current level to the directed level using GP-008, Draining the Reactor Coolant System, Attachment 5.
Record your total to the nearest gallon.
2013 NRC Retest Exam Admin JPM SRO A1-2 Rev. 2
Appendix C Page 2 of 9 Form ES-C-1 Worksheet Task Standard: Determine the calculated amount of RCS to be drained within specified limits.
Required Materials: Calculator, GP-008, Draining the RCS, Attachment 5 - Vessel Volume to Level Comparison General
References:
GP-008, RCS, Attachment 5 , Rev. 43 Time Critical Task: No Validation Time: 10 minutes Critical Step Justification Step 6 Total of RCS drained is required to be provided to the Shift Manager 2013 NRC Retest Exam Admin JPM SRO A1-2 Rev. 2
Appendix C Page 3 of 9 Form ES-C-1 PERFORMANCE INFORMATION START TIME:
Step 1 Performance Step: 1 Obtain procedure Standard: Obtains GP-008, Draining The Reactor Coolant System, Attachment 5, Vessel Volume to level comparison Comment:
Step 2 Performance Step: 2 Determine current RCS volume Standard: Using GP-008, Attachment 5 Determines current RCS volume with RCS level at Vessel Flange with SGs FULL to be 60,595 gallons Comment:
Step 3 Performance Step: 3 Determine RCS volume Top of Loops with SGs FULL Standard: Using GP-008, Attachment 5 Determines RCS volume with RCS level at Top of Loops with SGs FULL to be 55,965 gallons Comment:
- Denotes Critical Steps 2013 NRC Retest Exam Admin JPM SRO A1-2 Rev. 2
Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION Step 4 Performance Step: 4 Determine RCS volume at Top of Loops after SGs drain Standard: Using GP-008, Attachment 5 Determines RCS volume with RCS level at Top of Loops with SGs DRAINED to be 28,925 gallons (-65)
Comment:
Step 5 Performance Step: 5 Determine RCS volume at -70 with SGs DRAINED Standard: Using GP-008, Attachment 5 Determines RCS volume with RCS level at -70 with SGs DRAINED to be 28,925 gallons Mid Loop -82 (24,744 gallons)
Top of Loops -65 (28,925 gallons) 17 (4,181 gallons) between Top of Loops and Mid Loop 245.941 gallons per inch
-65 to -70 = 5 inches x 245.941 = 1,229.705 1,230 gallons Comment:
- Denotes Critical Steps 2013 NRC Retest Exam Admin JPM SRO A1-2 Rev. 2
Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION Step 6 Performance Step: 6 Determine total RCS volume drained from Vessel Flange with SGs FULL to -70 Standard: Using GP-008, Attachment 5 Determines total volume drained to be:
32,900 gallons (+ 1000 gallons since curve could be used)
Current level Vessel Flange with SGs Full to Top of Loops with SGs FULL 60,595 - 55,965 = 4,630 gallons SGs Drained level maintained at Top of Loops 55,965 - 28,925 = 27,040 gallons Top of Loops with SGs Drained to -70 1,230 gallons Total drained volume = 4,630 + 27,040 + 1,230 = 32,900 Comment:
Terminating Cue: After the total volume of RCS from Vessel Level at Flange with SGs FULL to -70 below the Flange is calculated:
Evaluation on this JPM is complete.
END OF JPM STOP TIME:
- Denotes Critical Steps 2013 NRC Retest Exam Admin JPM SRO A1-2 Rev. 2
Appendix C Page 6 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 NRC Retest Exam Admin JPM SRO A1-2 Determine the amount of RCS inventory that will be drained from RCS during the performance of GP-008, Draining the RCS.
Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
2013 NRC Retest Exam Admin JPM SRO A1-2 Rev. 2
Appendix C Page 7 of 9 JPM CUE SHEET
- A shift turnover is underway
- The previous shift is implementing GP-008, Draining The Reactor Coolant System
- A drain down of the RCS is in progress in preparation for the upcoming Refueling Outage Initial Conditions:
- The drain is on hold for turnover and level is currently being maintained stable at the Reactor Vessel Flange
- After turnover, the directions are to drain the RCS to -70 in preparation for Nozzle Dam installation
- The Shift Manager has given permission to enter lower inventory conditions.
You are the CRS. The Shift Manager wants to know how many gallons of water will be drained from the RCS to ensure adequate drain tank volume.
You are required to calculate the amount of additional water that will be Initiating Cue:
drained from the RCS from the current level to the directed level using GP-008, Draining the Reactor Coolant System, Attachment 5.
Record your total to the nearest gallon.
2013 NRC Retest Exam Admin JPM SRO A1-2 Rev. 2
Appendix C Page 8 of 9 Form ES-C-1 JPM CUE SHEET Name:
Date:
Show how the calculation was performed in the space provided below:
Total number of RCS gallons to be drained:
2013 NRC Retest Exam Admin JPM SRO A1-2 Rev. 2
Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET 2013 NRC Retest Exam Admin JPM SRO A1-2 Rev. 2
Appendix C Page 1 of 6 Form ES-C-1 PERFORMANCE INFORMATION Facility: Shearon-Harris Task No.: 002001H201 Task
Title:
Review (for approval) a completed JPM No.: 2013 NRC Retest Exam surveillance procedure for PORV Admin SRO JPM A2 block valves.
K/A
Reference:
G2.2.12 (3.4) ALTERNATE PATH - No 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.
- Today is 2/6/14
- The unit is operating at 100% power.
- PRZ PORV PCV-445B has a failure in the SHUT circuit. RC-115 has been closed and power is removed.
Initial Conditions:
- TS 3.4.4 Action b is in effect. EIR 20140285 has been initiated.
- The control room crew has completed OST-1017, PRESSURIZER PORV BLOCK VALVE FULL STROKE TEST QUARTERLY INTERVAL MODES 1-2-3-4.
Initiating Cue: You are the CRS. Review the completed OST for approval. Identify any discrepancies (if applicable).
2013 NRC Retest Admin Exam JPM SRO A2 Rev. 2
Appendix C Page 2 of 6 Form ES-C-1 PERFORMANCE INFORMATION Task Standard: All errors identified.
Required Materials: None General
References:
OST-1017, PRESSURIZER PORV BLOCK VALVE FULL STROKE TEST QUARTERLY INTERVAL MODES 1-2-3-4, Revision 21 Handout: Completed OST-1017 with errors that align with the JPM content.
Time Critical Task: No Validation Time: 15 Minutes Critical Task Justification Note: There are 2 items that will make the surveillance UNSAT. Either of which when identified would require a performance retest.
Step 2 The stopwatch is beyond the calibration date -all timing data collected with the use of this out of calibration device is non usable therefore the test is invalid until a satisfactory stop watch calibration check is performed.
The shut time for valve 1RC-113 has exceeded the limit - if not Step 4 identified an inoperable component could be relied upon and possibly fail when needed to perform its intended action.
Missing the initial on step 4.l indicating that the step was completed is NOT critical since it can be attributed to a place keeping error and would NOT invalidate the surveillance.
2013 NRC Retest Admin Exam JPM SRO A2 Rev. 2
Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION START TIME:
Performance Step: 1 Obtain procedure.
Standard: Reviews Sections 3.0, 4.0, 5.0, 6.0.
Evaluator Cue: Provide handout for 2013 NRC Retest JPM SRO A2.
Evaluator Note:
- The steps of reviewing the procedure can be completed in any order.
- There are three errors in the procedure. Only the errors are documented in the JPM.
Comment:
Performance Step: 2 Review the completed OST-1017.
Standard: Identifies Stopwatch beyond calibration date per Prerequisite
3.0.4. Comment
Performance Step: 3 Review the completed OST-1017.
Standard: Identifies that step 4.l is not initialed.
Comment:
- Denotes Critical Steps 2013 NRC Retest Admin Exam JPM SRO A2 Rev. 2
Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Review the completed OST-1017.
Standard: Identifies SHUT time for 1RC-113 exceeds LIMITING VALUE.
Comment:
Terminating Cue:
STOP TIME:
- Denotes Critical Steps 2013 NRC Retest Admin Exam JPM SRO A2 Rev. 2
Appendix C Page 5 of 6 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 NRC Retest Admin SRO JPM A2 Review (for approval) a completed surveillance procedure for PORV block valves. OST-1017 Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
2013 NRC Retest Admin Exam JPM SRO A2 Rev. 2
Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET
- Today is 2/6/14
- The unit is operating at 100% power.
- PRZ PORV PCV-445B has a failure in the SHUT circuit. RC-115 has been closed and power is removed.
Initial Conditions:
- TS 3.4.4 Action b is in effect. EIR 20140285 has been initiated.
- The control room crew has completed OST-1017, PRESSURIZER PORV BLOCK VALVE FULL STROKE TEST QUARTERLY INTERVAL MODES 1-2-3-4.
You are the CRS. Review the completed OST for approval. Identify any Initiating Cue:
discrepancies (if applicable).
NAME: ___________________________________________
DATE: _____________________
- IF discrepancies were identified from your review of OST-1017 list them all on the lines below.
2013 NRC Retest Admin Exam JPM SRO A2 Rev. 2
Appendix C Page 1 of 9 Form ES-C-1 Worksheet Facility: Shearon Harris Task No.: 345013H602 Task
Title:
Given a Declared Emergency, JPM No.: 2013 NRC Retest Exam Determine the Dose Rate, Dose Admin JPM SRO A-3 Limit, and the Number of People to Perform a Task.
K/A
Reference:
G2.3.4 RO 3.2 SRO 3.7 ALTERNATE PATH: No 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.
- The unit was operating at 100% power when a Reactor Trip and Safety Injection occurred due to RCS leakage.
- An Alert has been declared.
- All Emergency Facilities have been manned and are activated.
- RHR Pump A was under clearance for motor replacement.
- RHR Pump B has tripped.
- The Emergency Engineering Organization has determined that the RHR Pump A can be repaired and restarted with parts available in the storeroom.
Initial Conditions:
- There are 10 mechanics qualified to work the repair of the A RHR pump.
- The repairs do not involve protecting valuable property, lifesaving or protection of large populations.
- The Site Emergency Coordinator has determined this to be an emergency repair which he has ranked as the highest priority. The SEC wants the pump back as soon as possible.
- The general radiation levels in the A RHR pump work area are 16.5 R/hour.
- The OSC estimates that the total task repair time will be 1.75 man-hours.
2013 NRC Retest Exam Admin JPM SRO A3 Rev. 2
Appendix C Page 2 of 9 Form ES-C-1 Worksheet The 10 site emergency mechanics listed in the table below are available.
Site Emergency Mechanic Accumulated TEDE Dose This Year A 680 mr B 950 mr C 1060 mr D 1290 mr E 1340 mr F 1480 mr G 1500 mr H 1550 mr I 1680 mr Initiating Cue: J 1720 mr They will be utilized from lowest to highest accumulated TEDE dose.
Using the minimum number of workers possible, DETERMINE:
- The total number of workers required to perform the repairs to the A RHR pump AND
- The maximum stay time for each individual who will be utilized for the repairs without exceeding their exposure limits under these emergency conditions.
ASSUME NO DOSE IN TRANSIT AND ROUND OFF TO THE NEAREST MINUTE BELOW THE LIMIT.
Place answer on the line provided and show your work in space provide (use back of page if needed):
In the table write YES or NO in the line next to each of the 10 mechanics if they will be or will not be required to perform repair work AND the stay time for those that will perform the repair rounded to the nearest minute prior to exceeding the limit.
Example - if 4.55 minutes is the Maximum Stay Time for Mechanic A when the radiation exposure limit is reached then the Maximum Stay Time prior to exceeding the limit would be 4 minutes.
2013 NRC Retest Exam Admin JPM SRO A3 Rev. 2
Appendix C Page 3 of 9 Form ES-C-1 Worksheet Task Standard: Number of people and stay times calculated within specified limits.
Required Materials: Calculator General
References:
PEP-330, Radiological Consequences, Attachment 1, Rev. 12 Time Critical Task: No Validation Time: 20 minutes Critical Step Justification Must determine the number of people required to complete the task to Step 3 perform calculations.
Must determine the stay time for workers to prevent each worker from Step 4 exceeding their dose allotments.
2013 NRC Retest Exam Admin JPM SRO A3 Rev. 2
Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION START TIME:
Step 1 Performance Step: 1 Determine total estimated dose for the task.
Standard: 16.5 R/hour x 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> = 28.875 Rem Comment:
Step 2 Performance Step: 2 Determine the dose limit for site emergency workers Standard: Per PEP-330 - Attachment 1 Comment:
- Denotes Critical Steps 2013 NRC Retest Exam Admin JPM SRO A3 Rev. 2
Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION Step 3 Performance Step: 3 Determine the number of people required to complete the task Standard: Workers A, B, C, D, E, and F would have to be used () to reach the 28.875 Rem total estimated dose (8 workers total)
(4320 + 4050 + 3940 + 3710 + 3660 + 3520 + 3500 + 3450) =
30.150 Rem (more than required)
Comment: - Workers A-H would be required to complete the task.
Worker H would complete the task and still have margin before reaching his/her limit of 5 Rem (1275 m/Rem) therefore worker H would not be required to work the entire 12 minutes.
Step 4 Performance Step: 4 Maximum Stay Time for Workers in minutes
- ROUND OFF TO THE NEAREST MINUTE BEFORE THE LIMIT IS REACHED Standard: A: 4.32/16.5 x 60 minutes = 15 (15.709 minutes)
B: 4.05/16.5 x 60 minutes = 14 (14.727 minutes)
C: 3.94/16.5 x 60 minutes = 14 (14.327 minutes)
D: 3.71/16.5 x 60 minutes = 13 (13.490 minutes)
E: 3.66/16.5 x 60 minutes = 13 (13.309 minutes)
F: 3.52/16.5 x 60 minutes = 12 (12.800 minutes)
G: 3.5/16.5 x 60 minutes = 12 (12.727 minutes)
H: 3.45/16.5 x 60 minutes = 12 (12.545 minutes)
Comment:
Terminating Cue: After the maximum stay time for the workers to be used is calculated: Evaluation on this JPM is complete.
END OF JPM STOP TIME:
- Denotes Critical Steps 2013 NRC Retest Exam Admin JPM SRO A3 Rev. 2
Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION KEY In the table below write YES or NO in the line next to the mechanic if he will be or will not be required to perform repair work and the MAXIMUM stay time prior to exceeding the radiation limit for those that will perform the repair.
NOTE: the times are rounded to the nearest minute BEFORE the exposure limit is reached.
(8 WORKERS REQUIRED)
Site Emergency Mechanic YES / NO Maximum Stay Time A YES 15 minutes B YES 14 minutes C YES 14 minutes D YES 13 minutes E YES 13 minutes F YES 12 minutes G YES 12 minutes H YES 12 minutes I NO XXX J NO XXX
- Denotes Critical Steps 2013 NRC Retest Exam Admin JPM SRO A3 Rev. 2
Appendix C Page 7 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 NRC Retest Exam Admin JPM SRO A-3 Given a Declared Emergency, Determine the Dose Rate, Dose Limit, and the Number of People to Perform a Task.
Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
2013 NRC Retest Exam Admin JPM SRO A3 Rev. 2
Appendix C Page 8 of 9 Form ES-C-1 JPM CUE SHEET Initial Conditions:
- The unit was operating at 100% power when a Reactor Trip and Safety Injection occurred due to RCS leakage.
- An Alert has been declared.
- All Emergency Facilities have been manned and are activated.
- RHR Pump A was under clearance for motor replacement.
- RHR Pump B has tripped.
- The Emergency Engineering Organization has determined that the RHR Pump A can be repaired and restarted with parts available in the storeroom.
- There are 10 mechanics qualified to work the repair of the A RHR pump.
- The repairs do not involve protecting valuable property, lifesaving or protection of large populations.
- The Site Emergency Coordinator has determined this to be an emergency repair which he has ranked as the highest priority.
The SEC wants the pump back as soon as possible.
- The general radiation levels in the A RHR pump work area are 16.5 R/hour.
- The OSC estimates that the total task repair time will be 1.75 man-hours.
Initiating Cue: The 10 site emergency mechanics listed in the table below are available.
Site Emergency Mechanic Accumulated TEDE Dose This Year A 680 mr B 950 mr C 1060 mr D 1290 mr E 1340 mr F 1480 mr G 1500 mr H 1550 mr I 1680 mr J 1720 mr They will be utilized from lowest to highest accumulated TEDE dose.
Using the minimum number of workers possible, DETERMINE:
- The total number of workers required to perform the repairs to the A RHR pump AND
- The maximum stay time for each individual who will be utilized for the repairs without exceeding their exposure limits under these emergency conditions.
ASSUME NO DOSE IN TRANSIT AND ROUND OFF TO THE NEAREST MINUTE BEFORE THE LIMIT IS REACHED.
2013 NRC Retest Exam Admin JPM SRO A3 Rev. 2
Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET Name:
Date:
Place answer below and show work in space provide (use back of page if needed):
In the table below write YES or NO in the line next to each of the 10 mechanics if they will be or will not be required to perform repair work AND the stay time for those that will perform the repair rounded to the nearest minute prior to exceeding the limit.
Example - if 4.55 minutes is the Maximum Stay Time for Mechanic A when the radiation exposure limit is reached then the Maximum Stay Time prior to exceeding the limit would be 4 minutes.
Site Emergency Mechanic YES / NO Maximum Stay Time (In Minutes)
A B
C D
E F
G H
I J
WORK IN SPACE BELOW (and on back of page if needed) 2013 NRC Retest Exam Admin JPM SRO A3 Rev. 2
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Shearon-Harris Task No.: 345001H602 345010H602 Task
Title:
Classify an EAL and JPM No.: 2013 NRC Retest Exam Determine a PAR Admin JPM SRO A4 K/A
Reference:
G2.4.41 RO 2.9 SRO 4.6 Examinee: _______________________ NRC Examiner: _________________
Facility Evaluator: _______________________ Date: _________________
Method of testing: This JPM can be performed in any setting with the required references available.
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.
(The initial conditions and initiating cue is on the next page) 2013 NRC Retest Exam Admin JPM SRO A4 Rev. 2
Appendix C Job Performance Measure Form ES-C-1 Worksheet You are the Site Emergency Coordinator.
The unit was operating at 100% with the A MDAFW pump under clearance At 0801
- A Main Feedwater pump tripped
- The crew attempted to trip the Reactor but the Reactor trip breakers failed to manually open
- The crew is implementing FR-S.1, Response to Nuclear Power Generation/ATWS
- The BOP has manually tripped the Turbine from the MCB switch
- Reactor power is ~32% and slowly lowering At 0802
- B Main Feedwater pump tripped on overcurrent
- B MDAFW pump has failed to start
- Low-Low Steam Generator levels have caused the TDAFW pump Initial Conditions: to auto start At 0804
- The OATC reports RCS pressure is lowering and B SG level is rising slowly uncontrollably. Estimations of leakage is ~ 25 gpm.
- All SG PORVs are in auto and open
- The AO directed to locally trip the Reactor reports he is unable to locally open the Reactor trip breakers OR the MG set breakers At 0805
- The TDAFW pump trips
- Reactor power is ~5.5% and slowly decreasing At 0806
- All SG levels are ~20% NR and decreasing At 0807
- The A Reactor trip breaker is opened, all rods insert and Reactor power is <1% and decreasing
- B MDAFW pump has been restarted and is supplying all SGs Evaluate the EAL Matrix and determine the highest classification Initiating Cue:
required for these plant conditions. This is a time critical JPM.
DO NOT READ This is a two (2) part TIME CRITICAL JPM where each part will be THIS TO THE timed separately.
CANDIDATE:
2013 NRC Retest Exam Admin JPM SRO A4 Rev. 2
Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Classify the highest EAL as a GE and correctly identify the PAR Required Materials: None General
References:
PEP-110 EAL Matrix, Rev. 12 PEP 110, Rev. 22 EP-EAL, Rev. 12 Handouts:
- Attached Initial Conditions
- PEP-110 EAL Matrix, Rev. 12
- PEP 110, Rev. 22
Validation Time: 30 minutes (accounts for 15 minute criteria for classification and PAR)
CRITICAL TASK JUSTIFICATION Classification of the event is critical for determining State and County Step 1 notifications, public information notices, site information notices, and event reportability to the Nuclear Regulatory Commission.
Identification of protective recommendation to the State and County is Step 2 part of the standard goal of protecting the health and safety of the public.
2013 NRC Retest Exam Admin JPM SRO A4 Rev. 2
Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION Start Time for this portion of JPM begins when the Evaluator Cue:
individual has been briefed.
START TIME:
Performance Step: 1 Identify EAL Classification for events in progress.
Standard : The correct EAL is: General Emergency SG3.1 At 0801 EAL SS3.1 (Site Area Emergency) was met since an automatic trip failed to shutdown the Reactor (Turbine trip with P-7 either Rx power or Turbine power > 10%) manual actions at the Rx controls failed to shutdown the Reactor and Rx power is > 5%.
At time 0806 CSFST Heat Sink - RED entry conditions are met since NO AFW flow exists (<210 KPPH) and ALL SG levels are
< 25%
EAL FS1.1 (Site Area Emergency) would be met:
Loss or Potential loss of any two barriers (Table F-1), Potential Loss of BOTH Fuel Clad Barrier and RCS Barrier due to CSFST Heat Sink-RED Additionally at 0806, EAL SG3.1 General Emergency is met:
An automatic trip fails to shut down the reactor AND all manual actions do not shut down the reactor as indicated by Reactor power > 5% AND EITHER of the following exist or have occurred due to continued power generation:
CSFST Core Cooling-RED entry conditions met OR CSFST Heat Sink-RED entry conditions met EAL classification is determined in < 15 minutes Comments:
STOP TIME:
Terminating Cue: EAL classification(s) completed and provided to evaluator.
- Denotes Critical Steps 2013 NRC Retest Exam Admin JPM SRO A4 Rev. 2
Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION DO NOT ASK THE CANDIDATE FOR A PAR UNLESS A GENERAL EMERGENCY HAS BEEN DECLARED.
IF the candidate has determined that a General Emergency is declared then CUE:
Make a protective action recommendation (PAR) based on Evaluator Cue: the wind blowing from 273.
Provide them page 7 of this JPM to evaluate and write out the associated PAR.
Start Time for this portion of JPM begins when the individual has been provided the directions to make a PAR and given the wind direction.
START TIME:
Performance Step: 2 Determine PAR. Refers to PEP-110 Attachment 3.
Time of PAR determination:
Standard: PROTECTIVE ACTION RECOMMENDATION:
- Evacuate 2 Mile Radius & 5 Miles downwind. Shelter all other subzones
- EVACUATE Subzones: A, C
- SHELTER Subzones: B,D,E,F,G,H,I,J,K,L,M,N PAR is determined < 15 minutes from time of classification.
Comment:
Terminating Cue: After the PAR is specified: This JPM is complete.
STOP TIME:
- Denotes Critical Steps 2013 NRC Retest Exam Admin JPM SRO A4 Rev. 2
Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION KEY
- Denotes Critical Steps 2013 NRC Retest Exam Admin JPM SRO A4 Rev. 2
Appendix C Page 7 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 NRC Retest Exam Admin JPM SRO A4 Classify an Event and Identify PARs Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Question:
Response
Result: SAT UNSAT Examiners Signature: Date:
2013 NRC Retest Exam Admin JPM SRO A4 Rev. 2
Appendix C Form ES-C-1 JPM CUE SHEET Name:
Date:
Make a protective action recommendation (PAR) based on the wind blowing from 273 Protective Action Recommendation:
2013 NRC Retest Exam Admin JPM SRO A4 Rev. 2
Appendix C Form ES-C-1 JPM CUE SHEET Name:
Date:
You are the Site Emergency Coordinator.
The unit was operating at 100% with the A MDAFW pump under clearance At 0801
- A Main Feedwater pump tripped
- The crew attempted to trip the Reactor but the Reactor trip breakers failed to manually open
- The crew is implementing FR-S.1, Response to Nuclear Power Generation/ATWS
- The BOP has manually tripped the Turbine from the MCB switch
- Reactor power is ~32% and slowly lowering At 0802
- B Main Feedwater pump tripped on overcurrent
- B MDAFW pump has failed to start
- Low-Low Steam Generator levels have caused the TDAFW pump to auto start Conditions:
At 0804
- The OATC reports RCS pressure is lowering and B SG level is rising slowly uncontrollably. Estimations of leakage is ~ 25 gpm.
- All SG PORVs are in auto and open
- The AO directed to locally trip the Reactor reports he is unable to locally open the Reactor trip breakers OR the MG set breakers At 0805
- The TDAFW pump trips
- Reactor power is ~5.5% and slowly decreasing At 0806
- All SG levels are ~20% NR and decreasing At 0807
- The A Reactor trip breaker is opened, all rods insert and Reactor power is
<1% and decreasing
- B MDAFW pump has been restarted and is supplying all SGs Evaluate the EAL Matrix and determine the classification(s) required for these plant conditions.
Initiating Cue:
This is a time critical JPM.
EAL Classification:
EAL: