ML13169A199
| ML13169A199 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire |
| Issue date: | 06/18/2013 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| 50-369/12-301, 50-370/12-301 | |
| Download: ML13169A199 (96) | |
Text
Appendix C Job Performance Measure Form ES-C-1 Worksheet 2012 Admin - JPM A1a RO (REV_080212)
NUREG 1021, Revision 9 JPM A1a RO
Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A1a RO NUREG 1021, Revision 9 Facility:
McGuire Task No.:
Task
Title:
Calculate QPTR with an Inoperable Power Range Instrument JPM No.:
Reference:
GK/A 2.1.7 (4.4)
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.
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), the Detector Currents (2nd to last Page of this JPM), and the three handouts listed.
Initial Conditions:
At 0000 the Unit 1 OAC failed and is not operating.
The vendor is being consulted concerning repairs.
It is estimated it will take approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> to complete repairs.
On unit 1 at 0600 Power Range N41 upper detector failed.
An attempt to use the Moveable Incore Detector System to determine QPTR has failed due to a failure of the main incoming breaker.
A breaker is on order and will not be on site for seven to ten days.
Unit 1 power has been reduced to 74%.
Power Range N41 has been declared inoperable and removed from service by procedure.
Initiating Cue:
The CRS has directed you to calculate QPTR in accordance with Step 12.14 of PT/1/A/4600/21A, Loss of Operator Aid Computer while in Mode 1. Notify CRS of your results.
Determine all calculations to two (2) decimal places.
Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A1a RO NUREG 1021, Revision 9 Task Standard:
The operator will calculate the QPTR (See Attached Key) and determine that the QPTR Technical Specification has been exceeded.
Required Materials:
Calculator General
References:
PT/1/A/4600/021A (Loss of Operator Aid Computer while in Mode 1),
Rev 36 OP/1/A/6100/022 (MNS Unit #1 Data Book)
McGuire Technical Specifications (LCO 3.2.4/Amendment 184/166)
Handouts:
PT/1/A/4600/021A (Loss of Operator Aid Computer while in Mode 1) marked up through step 12.13.
Detector Currents (Page 12 of 13 of this JPM)
OP/1/A/6100/022 (MNS Unit #1 Data Book), Enclosure 4.3, Table 2.2 (Excore Currents and Voltages Correlated to 100% Full Power at Various Axial Offsets) - Unit 1 Cycle 22 Change N 10/20/11 McGuire Technical Specifications (Available)
Time Critical Task:
NO Validation Time:
25 minutes
Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1a RO NUREG 1021, Revision 9 (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), the Detector Currents (2nd to last Page of this JPM), and the three handouts listed.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1
(Step 12.14)
IF QPTR Alarm inoperable AND greater than 50%
RTP, perform the following:
(Step 12.14.1) If all Power Range (PR) channel inputs to QPTR operable, The operator determines from initial conditions QPTR Alarm is inoperable, Unit 1 is at 100% power and all PR channels are NOT operable.
The operator recognizes that this is not the case and continues.
2 (Step 12.14.2) IF input from one PR channel is inoperable, perform the following:
(Step 12.14.2.1) IF less than 75% RTP, perform the following:
Calculate QPTR on 3.5 (Calculation Sheet For Quadrant Power Tilt) Part B using other 3 PR channels.
Record PR channels used within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter until QPTR Alarm operable or inoperable PR input operable.
The operator proceeds to 3.5 (Calculation Sheet for Quadrant Power Tilt) Part B.
3 (Enclosure 13.5 Part B)
Complete the Form The operator enters the current Date and Time at the top of the form.
Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1a RO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 4 (Enclosure 13.5 Part B)
Measured Current - From NI cabinets current meter (located on respective PRB Drawers). Ensure Detector Milliamp Range Switches are in 0.5 position and read 0-500 microamp scale.
The operator identifies the three operable Power Range Instruments as PR-42, PR-43 and PR-44 on 3.5, Part B.
The operator records the correct amperage reading for each detector (From the Handout provided) in the Measured Current row for each of the six (6) detectors as follows:
PR-42A = 296 PR-42B = 312 PR-43A = 299 PR-43B = 315 PR-44A = 299 PR-44B = 308
- 5 (Enclosure 13.5 Part B)
Calibration Current - From most recent calibration data using 0 Incore Axial Offset Current in Data Book, Table 2.2 (IT for detector A, IB for detector B).
The operator locates OP/1/A/6100/022,.3, Table 2.2, Excore Currents and Voltages Correlated to 100% Full Power at Various Axial Offsets.
The operator records the correct amperage reading for each detector (Table 2.2) in the Calibration Current row for each of the six (6) detectors as follows:
PR-42A = 116.9 PR-42B = 126.6 PR-43A = 115.3 PR-43B = 129.0 PR-44A = 107.5 PR-44B = 123.0
Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1a RO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 6 (Enclosure 13.5 Part B)
Relative Flux (RF) - Divide line 1 by line 2 to calculate Relative Flux (RF) for each upper (A) and lower (B) detector.
The operator correctly calculates the average RF and records the in the Relative Flux (RF) row for each of the six (8) detectors as follows:
PR-42A = 296/116.9 = 2.53 PR-42B = 312/126.6 = 2.46 PR-43A = 299/115.3 = 2.59 PR-43B = 315/129.0 = 2.44 PR-44A = 299/107.5 = 2.78 PR-44B = 308/123.0 = 2.50
- 7 (Enclosure 13.5 Part B)
Quadrant Power Tilts:
Calculate by dividing each upper relative flux by the average upper relative flux and dividing each lower relative flux by the average lower relative flux.
Avg RF of A Detectors The operator records the RF of each of the three (3)
A detectors and calculates the Avg RF of A Detectors as follows:
(2.53+2.59+2.78)/3 = 2.63
- 8 (Enclosure 13.5 Part B)
Quadrant Power Tilts:
Calculate by dividing each upper relative flux by the average upper relative flux and dividing each lower relative flux by the average lower relative flux.
Avg RF of B Detectors The operator records the RF of each of the three (3)
B detectors and calculates the Avg RF of B Detectors as follows:
(2.46+2.44+2.50)/3 = 2.47
Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1a RO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 9 (Enclosure 13.5 Part B)
Quadrant Power Tilts:
Calculate by dividing each upper relative flux by the average upper relative flux and dividing each lower relative flux by the average lower relative flux.
PR-42A Tilt The operator calculates the PR-42A Tilt as follows:
2.53/2.63 = 0.96 +.01 And records this value.
- 10 (Enclosure 13.5 Part B)
Quadrant Power Tilts:
Calculate by dividing each upper relative flux by the average upper relative flux and dividing each lower relative flux by the average lower relative flux.
PR-42B Tilt The operator calculates the PR-42B Tilt as follows:
2.46/2.47 = 1.00 +.01 And records this value.
- 11 (Enclosure 13.5 Part B)
Quadrant Power Tilts:
Calculate by dividing each upper relative flux by the average upper relative flux and dividing each lower relative flux by the average lower relative flux.
PR-43A Tilt The operator calculates the PR-43A Tilt as follows:
2.59/2.63 = 0.98 +.01 And records this value.
- 12 (Enclosure 13.5 Part B)
Quadrant Power Tilts:
Calculate by dividing each upper relative flux by the average upper relative flux and dividing each lower relative flux by the average lower relative flux.
PR-43B Tilt The operator calculates the PR-43B Tilt as follows:
2.44/2.47 = 0.99 +.01 And records this value.
Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1a RO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 13 (Enclosure 13.5 Part B)
Quadrant Power Tilts:
Calculate by dividing each upper relative flux by the average upper relative flux and dividing each lower relative flux by the average lower relative flux.
PR-44A Tilt The operator calculates the PR-44A Tilt as follows:
2.78/2.63 = 1.06 +.01 And records this value.
- 14 (Enclosure 13.5 Part B)
Quadrant Power Tilts:
Calculate by dividing each upper relative flux by the average upper relative flux and dividing each lower relative flux by the average lower relative flux.
PR-44B Tilt The operator calculates the PR-44B Tilt as follows:
2.50/2.47 = 1.01 +.01 And records this value.
- 15 (Technical Specification 3.2.4) The QPTR shall be
< 1.02.
The operator determines that one quadrant is >1.02 and Refers to LCO 3.2.4 OR Informs the CRS of the condition.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
Appendix C Page 9 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A1a RO NUREG 1021, Revision 9 Job Performance Measure No.:
2012 Admin - JPM A1a RO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
Appendix C Page 10 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A1a RO NUREG 1021, Revision 9 KEY:
Part B Page 3 of 4 PR-42 PR-43 PR-44 A
B A
B A
B Measured Current 296 312 299 315 299 308 Calibration Current 116.9 126.6 115.3 129.0 107.5 123.0 Relative Flux (RF) 2.53 2.46 2.59 2.44 2.78 2.50 Part B Page 4 of 4 Avg RF of A Detectors
=
2.53
+
2.59
+
2.78
=
2.63 Avg RF of B Detectors
=
2.46
+
2.44
+
2.50
=
2.47 PR-42A Tilt RFA
=
RF of PR-42A
=
2.53
.96*
PR-42B Tilt RFB
=
RF of PR-42B
=
2.46 1.00*
2.63 2.47 PR-43A Tilt RFA
=
RF of PR-43A
=
2.59
.98*
PR-43B Tilt RFB
=
RF of PR-43B
=
2.44
.99*
2.63 2.47 PR-44A Tilt RFA
=
RF of PR-44A
=
2.78 1.06*
PR-44B Tilt RFB
=
RF of PR-44B
=
2.50 1.01*
2.63 2.47
- +.01
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 The following Detector Currents are observed on the NI cabinet current meters:
NI-41 detector:
A (left) 0 B (right) 0 NI-42 detector:
A (left) 296 B (right) 312 NI-43 detector:
A (left) 299 B (right) 315 NI-44 detector:
A (left) 299 B (right) 308
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 Initial Conditions:
At 0000 the Unit 1 OAC failed and is not operating.
The vendor is being consulted concerning repairs.
It is estimated it will take approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> to complete repairs.
On unit 1 at 0600 Power Range N41 upper detector failed.
An attempt to use the Moveable Incore Detector System to determine QPTR has failed due to a failure of the main incoming breaker.
A breaker is on order and will not be on site for seven to ten days.
Unit 1 power has been reduced to 74%.
Power Range N41 has been declared inoperable and removed from service by procedure.
INITIATING CUE:
The CRS has directed you to calculate QPTR in accordance with Step 12.14 of PT/1/A/4600/21A, Loss of Operator Aid Computer while in Mode 1. Notify CRS of your results.
Determine all calculations to two (2) decimal places.
Appendix C Job Performance Measure Form ES-C-1 Worksheet 2012 Admin - JPM A1a SRO (Rev_080212)
NUREG 1021, Revision 9 JPM A1a SRO
Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A1a SRO NUREG 1021, Revision 9 Facility:
McGuire Task No.:
Task
Title:
Determine Proper Shift Staffing JPM No.:
Reference:
GK/A 2.1.5 (2.9/3.9)
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.
Provide Candidate with Initial Conditions/Cue (Last three Pages of this JPM), OMP 5-8 Shift Supervision Turnovers (Enclosure 12.1, page 4 of 9), and NSD-200.
Initial Conditions:
Units 1 and 2 are at 100% power.
It is Wednesday night at 1900. All persons scheduled to work, except Alex (who has called in sick), have reported for work (See Attached Sheet).
Three individuals have expressed concerns regarding overtime limitations, and present their recent work history (See Attached Sheet).
All SROs and ROs are qualified Fire Brigade Leaders.
The crewmembers currently on-shift do NOT have any holdover concerns.
Initiating Cue:
Evaluate the work history of the three individuals who have expressed overtime limitation concerns; and then assign personnel to a shift position on Attachment 12.1, Control Room Supervisor Turnover Checklist, in accordance with the attached Work Schedule.
Identify any arriving personnel that cannot be assigned to a shift position on Wednesday night at 1900.
Hold over personnel and/or call in additional personnel ONLY if the minimum staffing cannot be met.
Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A1a SRO NUREG 1021, Revision 9 Task Standard:
The operator will evaluate the work history of three individuals in accordance with section 200.6.9 of NSD 200, and determine that Mark (OAC U1 RO) cannot report for work, however, Owen (AUX (ND 695')
UNIT 1) and Dennie (5TH ROUNDS) may report for work. The operator assigns all other personnel reporting to work in accordance with the attached Key, and identifies that STA must be held over from the previous shift, and that one RO must be held over, or a Request for Work Hours Extension must be approved.
Required Materials:
None General
References:
OMP 5-8, Shift Supervision Turnovers, Rev 52 SOMP 01-04, Conduct of Operations.
NSD-200, Work Hour Guidelines and Limits, Rev 14 NSD-112, Fire Brigade Organization, Training and Responsibilities, Rev 9
McGuire Emergency Plan, Figure B-1, MNS Minimum Staffing Requirements for Emergencies.
SLC 16.13.1, Site Fire Brigade.
SLC 16.13.4, Minimum Station Staffing Requirements.
Technical Specification 5.2, Organization.
Handouts:
OMP 5-8, Shift Supervision Turnovers, Enclosure 12.1, page 4 of 9.
NSD-200, Overtime Control.
A Shift Work Schedule (Page 11 of 12 of this JPM).
Work History of the three individuals who have arrived for work but expressed concerns regarding Overtime limitations (Page 12 of 12 of this JPM).
Time Critical Task:
NO Validation Time:
30 minutes
Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1a SRO NUREG 1021, Revision 9 (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue (Last three Pages of this JPM), OMP 5-8 Shift Supervision Turnovers (Enclosure 12.1, page 4 of 9), and NSD-200.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1
(NSD 200, Steps 200.6.9.1-
- 4) The operator compares the work history of the three employees with OT concerns to the requirements of NSD 200.
NOTE: The identification that Mark cannot work is critical.
The operator evaluates Mark (OAC U1 RO) and determines:
Work period of 11.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> (.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> TOT)
Rest period of 11.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> Work period of 14.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> (.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> TOT)
Rest period of 9.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
Mark cannot report to work because a rest period of only 9.5 hrs has occurred.
(Needs at least.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> rest period).
The operator evaluates Owen (AUX (ND 695') UNIT
- 1) and determines:
Work period of 13.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> (.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> TOT)
Rest period of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Work period of 12.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> TOT)
Rest period of 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> Owen meets all OT limits.
The operator evaluates Dennie (5TH ROUNDS) and determines:
Work period of 11.50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> (.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> TOT)
Rest period of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> Work period of 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />
(.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> TOT)
Rest period of 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> Dennie meets all OT limits.
Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1a SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 2 (OMP 5-8, Attachment 12.1, Step 1) Minimum Crew Composition: Operations Shift Manager.
The operator observes the Work Schedule and assigns Tim to position #1.
- 3 (Step 2) Minimum Crew Composition: Shift Technical Advisor.
The operator observes the Work Schedule and holds over current STA (position
- 2) until replacement for Alex arrives.
- 4 (Step 3) Minimum Crew Composition: Control Room Supervisor.
The operator observes the Work Schedule and assigns Eric to position #3.
- 5 (Step 4) Minimum Crew Composition: Off-Site Communicator.
The operator observes the Work Schedule and assigns Randy to position #4.
- 6 (Step 5) Minimum Crew Composition: Plant SRO.
The operator observes the Work Schedule and assigns Todd to position #5.
- 7 (Step 6) Minimum Crew Composition: Second Active SRO.
The operator observes the Work Schedule and assigns Todd or Randy to position
- 6.
- 8 (Step 7) Minimum Crew Composition: Reactor Operators.
The operator recognizes that Mark cannot be assigned to work, and his position (Unit 1 OAC RO) must be held over for 30 minutes. OR A Request for Work Hours Extension per NSD-200 must be completed prior to assuming duty.
The operator observes the Work Schedule and assigns Joe, Kevin, and Rick as U2 OAC RO, U2 BOP, and U1 BOP. (In any order).
Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1a SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 9 (Step 8) Minimum Crew Composition: Non-Licensed Operators.
The operator observes the Work Schedule and assigns Owen to the U1 NLO position.
The operator observes the Work Schedule and assigns Derek to the U2 NLO position.
The operator observes the Work Schedule and assigns Dennie to the Designated SSF position.
Note: (Failure Criteria)
These individuals cannot fill the FB Slot.
- 10 (Step 9) Minimum Crew Composition: SLC Required Fire Brigade.
The operator observes the Work Schedule and assigns Todd to the Fire Brigade Leader position (A).
The operator observes the Work Schedule and assigns Bob to the Fire Brigade member position (B1).
The operator observes the Work Schedule and assigns Ron to the Fire Brigade member position (B2).
The operator observes the Work Schedule and assigns Dwight to the Fire Brigade member position (B3).
The operator observes the Work Schedule and assigns SPOC-Monty to the Fire Brigade member position (B4).
Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1a SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 11 (Step 10) Minimum Crew Composition: Supplemental Fire Brigade.
The operator observes the Work Schedule and assigns Chris to the Supplemental Fire Brigade member position (1).
The operator observes the Work Schedule and assigns Wayne to the Supplemental Fire Brigade member position (2).
The operator observes the Work Schedule and assigns SPOC-Doug to the Supplemental Fire Brigade member position (3).
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
Appendix C Page 8 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A1a SRO NUREG 1021, Revision 9 Job Performance Measure No.:
2012 Admin - JPM A1a SRO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
Appendix C Page 9 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A1a SRO NUREG 1021, Revision 9 KEY:
Shift Crew Position Name Required By
- 1. Operations Shift Manager (OSM)
Tim SLC 16.13.4
Holdover SLC 16.13.4
- 3. Control Room Supervisor (Active SRO)
Eric SLC 16.13.4
- 4. Offsite Communicator (SRO)
Randy E-Plan Sect B, Fig 1
- 5. Plant SRO Todd OMP 2-2
- 7. Reactor Operator (RO)
Unit 1 OATC Holdover SLC 16.13.4 Unit 1 BOP Joe1 SLC 16.13.4 Unit 2 OATC Kevin1 SLC 16.13.4 Unit 2 BOP Rick1 SLC 16.13.4
- 8. Non-Licensed Operators (NLO)
Unit 1 Owen SLC 16.13.4 Unit 2 Derek SLC 16.13.4 Designated SSF Operator Dennie SLC 16.13.4
A. Todd SLC 16.13.1 & 4 B. Brigade Members B1. Ron SLC 16.13.1 & 4 B2. Bob SLC 16.13.1 & 4 B3. Dwight2 SLC 16.13.1 & 4 B4. Monty3 SLC 16.13.1 & 4
- 10. Supplemental Fire Brigade
- 1. Chris2 NSD 112 (Not SLC Related)
- 2. Wayne2 NSD 112
- 3. Doug3 NSD 112 NOTE:
1Joe, Kevin, and Rick may fill any one of the RO positions.
2Dwight, Chris and Wayne are interchangeable in the Fire Brigade Slots.
3Doug and Monty are interchangeable.
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 INITIAL CONDITIONS:
Units 1 and 2 are at 100% power.
It is Wednesday night at 1900. All persons scheduled to work, except Alex (who has called in sick), have reported for work (See Attached Sheet).
Three individuals have expressed concerns regarding overtime limitations, and present their recent work history (See Attached Sheet).
All SROs and ROs are qualified Fire Brigade Leaders.
The crewmembers currently on-shift do NOT have any holdover concerns.
INITIATING CUE:
Evaluate the work history of the three individuals who have expressed overtime limitation concerns; and then assign personnel to a shift position on Attachment 12.1, Control Room Supervisor Turnover Checklist, in accordance with the attached Work Schedule.
Identify any arriving personnel that cannot be assigned to a shift position on Wednesday night at 1900.
Hold over personnel and/or call in additional personnel ONLY if the minimum staffing cannot be met.
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 A Shift DATE August 20, 21, 22/12 SCHEDULE Mon-Wed/Nights OSM Tim (SRO)
WCC/STA Alex (SRO/STA)
Ext 2140 8-777-7534 Ext 4276 8-777-4517 CONTROL ROOM SRO Eric (SRO)
Mark (RO)
Kevin (RO)
OAC RO UNIT 1 OAC RO UNIT 2 Joe (RO)
Rick (RO)
BOP RO UNIT 1 BOP RO UNIT 2 PLANT SRO (8-778-2710)
Todd (SRO)
Owen (NLO)
Derek (NLO)
AUX (ND 695') UNIT 1 AUX (ND MIDGET HOLE) U-2 Bob (NLO)
Ron (NLO)
TURB UNIT 1 Dennie (NLO)
TURB UNIT 2 5TH ROUNDS W.C/EMERG. COMM.SRO (8-777-9881)
Randy (SRO)
WORK CONTROL EXTRAs Monday Dwight (NLO), Chris (NLO), Wayne (NLO)
Tuesday Same Wednesday Same FIRE BRIGADE (Group Call 8-777-5822)
LEADER:
Monday Todd, Bob, Ron, Dwight, Chris, Wayne, SPOC (Monty), SPOC (Doug)
Tuesday Same Wednesday Same CCC U2/Bpr312 (Ext.
2554)
N/A STAFF SRO/RO N/A SCHEDULED OFF Monday Fred, Steve Tuesday Same Wednesday Same
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 Work History of the three individuals who have arrived for work but expressed concerns regarding Overtime limitations:
Operator Monday Tuesday Wednesday Mark 1900 Reports to shift 1915 Turnover complete assumes duties 0700 Relief arrives 0715 Turnover complete stands relieved
HOME------------
1900 Reports to shift 1930 Turnover complete assumes duties 0715 Relief arrives, but plant transient delays turnover.
0745 Turnover starts 0800 Turnover complete stands relieved 0800-0930 Attends CRIP Team meeting.
HOME------------
1900 Reports to shift Owen 1915 Reports to shift 1930 Turnover complete assumes duties 0800 Relief arrives, but goes home sick 0845 Alternate relief arrives 0900 Turnover complete stands relieved
HOME------------
1900 Reports to shift 1915 Turnover complete assumes duties 0745 Relief arrives 0800 Turnover complete stands relieved
HOME------------
1900 Reports to shift Dennie 1915 Reports to shift 1930 Turnover complete assumes duties 0700 Relief arrives 0730 Turnover complete stands relieved
HOME------------
1730 Reports to shift for scheduled Just In Time Training (JITT) 1815 Turnover starts 1830 Turnover complete assumes duties 0745 Relief arrives 0800 Turnover complete stands relieved
HOME------------
1900 Reports to shift
Appendix C Job Performance Measure Form ES-C-1 Worksheet 2012 Admin - JPM A1b RO (REV_073012)
NUREG 1021, Revision 9 JPM A1b RO
Appendix C Page 2 of 8 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A1b RO NUREG 1021, Revision 9 Facility:
McGuire Task No.:
Task
Title:
Calculate the Boric Acid Addition for a specified Rod Change JPM No.:
Reference:
GK/A 2.1.25 (3.9)
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.
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout the three listed handouts.
Initial Conditions:
Unit #1 Reactor Power is at 50%, Steady State.
Core burnup is 125 EFPD.
NC Boron Concentration = 950 PPM.
Present Control Rods Bank D at 165 steps.
Desired Rod Height is Control Rods Bank D at 210 steps.
Initiating Cue:
The CRS has directed you to determine the amount of boric acid needed to obtain the desired Control Rod Height using the McGuire Unit 1 Data Book.
Task Standard:
Boric Acid Addition of approximately 253.3 gallons is calculated within +
4 gallons.
Required Materials:
Calculator General
References:
OP/0/A/6100/006 (Reactivity Balance Calculation), Rev 73 McGuire 1 Cycle 22 Core Operating Limits Report, Rev 01
Appendix C Page 3 of 8 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A1b RO NUREG 1021, Revision 9 OP/1/A/6100/022 (Unit 1 Data Book) Cycle 22, Change E Handouts:
OP/1/A/6100/022 (Unit 1 Data Book) Cycle 22, Enclosure 4.3 - Section 5.1 Boration and Dilution Tables OP/1/A/6100/022 (Unit 1 Data Book) Cycle 22, Enclosure 4.3 - Table 6.3.3 Integral Rod Worth in Overlap HFP, Equilibrium Xenon OP/1/A/6100/022 (Unit 1 Data Book) Cycle 22, Enclosure 4.3 - Graph 6.11 Differential Boron Worth (HFP, ARO, Eq Xe, Eq Sm)
Time Critical Task:
NO Validation Time:
15 minutes
Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1b RO NUREG 1021, Revision 9 (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout the three listed handouts.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 1 Operator determines 165 steps integral rod worth using the 51-150 EFPD column of OP/1/A/6100/22,.3, Table 6.3.3, IRW in Overlap, HFP, Equilibrium Xe.
Initial inserted reactivity worth =
153 pcm
- 2 Operator determines 210 steps integral rod worth using the 51-150 EFPD column of OP/1/A/6100/22,.3, Table 6.3.3, IRW in Overlap, HFP, Equilibrium Xe.
Desired Rod height inserted reactivity worth =
15 pcm
- 3 Operator determines the change in reactivity required for the rod insertion Change in reactivity to be compensated due to rod insertion =
15 pcm
-153 pcm
-138 pcm
- 4 Using OP/1/A/6100/22,.3, Graph 6.11 Differential Boron Worth (HFP, ARO, Eq Xe, Eq Sm, Unit 1 Cycle
Operator determines the Differential Boron Worth from the graph to be =
-6.07 pcm/ppm
Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1b RO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 5
Using the Differential Boron Worth and the Change in reactivity, determines the change in Boron Concentration Operator determines the change in Boron Concentration to be =
-138 /-6.07 pcm/ppm
= 22.7 ppm 6
Operator determines Boron Concentration required Change in Boron =
950 + 22.7 ppm
= 972.7 ppm
- 7 Using OP/1/A/6100/22,.3 Section 5.1 Boron and Dilution Tables, determines the Boric Acid addition Using Present Boron Concentration 950 ppm and the Desired Boron Concentration of 972.7 ppm, determines from Table that change from 950-972.7 ppm will require the addition of 253.2 gallons of Boric Acid.
OR Calculation:
67388 x Ln(6050/6027.3) =
253.32 gallons.
Total Boric Acid to add =
253.3 + 4 gallons (249.3-257.3gallons).
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
Appendix C Page 6 of 8 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A1b RO NUREG 1021, Revision 9 Job Performance Measure No.:
2012 Admin - JPM A1b RO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A1b RO NUREG 1021, Revision 9 KEY:
Tables:
Page 12 of 20 Intersect Present Cb of 950 ppm with Desired Cb 970 ppm and determine 223 gallons.
Intersect Present Cb of 950 ppm with Desired Cb 980 ppm and determine 335 gallons.
335 gallons - 223 gallons = 112 gallons/10ppm = 11.2 gallons/ppm 223 gallons (at 970) + [11.2 gallons/ppm x 2.7 ppm] = 253.24 Calculation:
G = V x Ln [(C-Bi)/(C-Bf)]
Where:
G Volume of boric acid required for boration V
Equivalent System Volume = 67388 Gallons (Constant)
C Concentration of Boric Acid being added = 7000 ppm (Constant)
Bi Present NCS Boron Concentration (ppm B)
Bf Desired NCS Boron Concentration (ppm B)
G = 67388 gallons x Ln [(7000 ppmB - 950 ppmB)/(7000-972.7 ppmB)]
G = 67388 gallons x Ln [(6050 ppmB)/(6027.3 ppmB)]
G = 67388 gallons x Ln [1.003766] = 253.32 gallons
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 Initial Conditions:
Unit #1 Reactor Power is at 50%, Steady State.
Core burnup is 125 EFPD.
NC Boron Concentration = 950 PPM.
Present Control Rods Bank D at 165 steps.
Desired Rod Height is Control Rods Bank D at 210 steps.
INITIATING CUE:
The CRS has directed you to determine the amount of boric acid needed to obtain the desired Control Rod Height using the McGuire Unit 1 Data Book.
Appendix C Job Performance Measure Form ES-C-1 Worksheet 2012 Admin - JPM A1b SRO (Rev_080212)
NUREG 1021, Revision 9 JPM A1b SRO
Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9 Facility:
McGuire Task No.:
Task
Title:
Manual AFD Calculation JPM No.:
Reference:
GK/A 2.1.25 (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.
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1, 2, 3 and 4 marked up as described.
Initial Conditions:
Unit 1 is at 100% power.
The OAC has been out of service for 30 minutes.
PT/1/A/4600/021 A (Loss of Operator Aid Computer While in Mode 1) is being performed.
The Main Control Board AFD meters are INOPERABLE.
The following are the present current values for the Power Range upper and lower detectors:
PR-41 A = 342 MicroAmps PR-41 B = 410 MicroAmps PR-42 A = 359 MicroAmps PR-42 B = 425 MicroAmps PR-43 A = 341 MicroAmps PR-43 B = 414 MicroAmps PR-44 A = 333 MicroAmps PR-44 B = 419 MicroAmps
Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9 Initiating Cue:
The CRS has directed you to calculate AFD per PT/1/A/4600/021A (Loss of Operator Aid Computer while in Mode 1).
Identify all required action(s), if any, that may apply as a result of the AFD calculation.
Determine all calculations to two (2) decimal places.
Task Standard:
AFD is determined to be within (+) 0.2% of the following values: (error band based on rounding numbers)
PR-41
-17.47%
PR-42
-18.45%
PR-43
-16.85%
PR-44
-19.87%
The operator determines the AFD associated with N42 and N44 exceeds the COLR limit of (-18%) at 100% RTP and identifies that Condition A of Technical Specification LCO 3.2.3 Axial Flux Difference is entered.
Required Materials:
Calculator General
References:
PT/1/A/4600/021 A (Loss of Operator Aid Computer While in Mode 1),
Rev 36 OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 2.2 (Excore Currents and Voltages Correlated to 100% Full Power at Various Axial Offsets) Rev 10/20/2011 McGuire Technical Specifications McGuire Unit 1 Cycle 22 Core Operating Limits Report Handouts:
1-PT/1/A/4600/021 A (Loss of Operator Aid Computer While in Mode 1) marked up through Step 12.9.
2 - OP/1/A/6100/022, Enclosure 4.3, Table 2.2, Excore Currents and Voltages Correlated to 100% Full Power at various Axial Offsets (Dated 10/20/2011) 3 - McGuire Unit 1 Cycle 22 Core Operating Limits Report, Figure 5, Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits 4 - McGuire Technical Specifications Time Critical Task:
NO Validation Time:
15 minutes
Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9 (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1, 2, 3 and 4 marked up as described.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1
(Step 12.10) IF AFD Monitor Alarm inoperable AND greater than or equal to 50% RTP, perform the following:
(Step 12.10.1) IF MCB AFD gauges operable..
The operator recognizes that the AFD Monitor is inoperable, and that present power is greater than 50%
RTP.
The operator recognizes that the MCB AFD gauges are inoperable and places an NA in this step.
2 (Step 12.10.2) IF MCB AFD gauges inoperable, perform the following:
(Step 12.10.2.1) Check AFD by performing 3.2 (Axial Flux Difference Monitoring) Part B within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and every hour thereafter until OAC AFD Monitor Alarm or MCB AFD gauges operable.
The operator refers to PT/1/A/4600/021 A 3.2 Part B
Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 3
(Notes prior to Enclosure 13.2 Part B)
Manual AFD calculations using PR detector currents will provide a means to check AFD is within the limits as specified in the COLR. A difference may exist between manual AFD calculations and functioning OAC calculated values and functioning Control Board AFD gauges due to accuracy of readings and calibration of PR current meters.
IF more accurate Power Range (PR) detector current readings are desired or required, SPOC should be contacted to obtain PR detector current readings with a digital voltmeter (DVM) per Reactor Engineering procedure PT/0/A/4600/002 G (Incore and NIS Recalibration)
The operator reads the Notes and proceeds.
Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 4
(Enclosure 13.2 Part B, Column A) From most recent calibration data using 0 Incore Axial Offset current in Data Book, Table 2.2 (T for Detector A and B for Detector B.
The operator obtains OP/1/A/6100/022,.3, Table 2.2 and uses the Full Power Detector Currents (Microamps) Corresponding to Various Incore Axial Offsets Chart, and an Incore Axial Offset of 0, records the following in Column A of Enclosure 13.2 Part B:
PR-41A = 112.2 PR-41B = 123.5 PR-42A = 116.9 PR-42B = 126.6 PR-43A = 115.3 PR-43B = 129.0 PR-44A = 107.5 PR-44B = 123.0 5
(Enclosure 13.2 Part B, Column B) From NI cabinets current meters (located on respective PR A and B Drawers). Ensure Detector Milliamp range switches are in 0.5 position and read from 0-500 microamp scale.
Readings should be to nearest microamp for accuracy.
The operator, using the information provided in the initial conditions, records the following in Column B of 3.2 Part B:
PR-41A = 342 PR-41B = 410 PR-42A = 359 PR-42B = 425 PR-43A = 341 PR-43B = 414 PR-44A = 333 PR-44B = 419
Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6
(Enclosure 13.2 Part B, Column C) Column B Measured Current divided by Column A Axial Offset Current for each detector multiplied by 100.
The operator divides Column B by Column A for each detector, and multiplies the quotient by 100, and then records the following in Column C of 3.2 Part B:
PR-41A = 304.81 PR-41B = 331.98 PR-42A = 307.10 PR-42B = 335.70 PR-43A = 295.75 PR-43B = 320.93 PR-44A = 309.77 PR-44B = 340.65 7
(Enclosure 13.2 Part B, Column D) Column C Detector A minus Column C Detector B for each PR channel divided by 2.
The operator subtracts Detector B from Detector A for each PR, and divides the remainder by 2, and then records the following in Column D of Enclosure 13.2 Part B:
PR-41 = -13.59 PR-42 = -14.30 PR-43 = -12.59 PR-44 = -15.44
Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 8
(Enclosure 13.2 Part B, Column E) M Factor from Data Book Table 2.2 AFD Incore/Excore Ratios for Quadrants 1-4.
The operator obtains OP/1/A/6100/022,.3, Table 2.2 and uses the AFD Incore/Excore Ratios for Quadrants 1-4 Chart, and records the following in Column E of Enclosure 13.2 Part B:
PR-41 = 1.286 PR-42 = 1.290 PR-43 = 1.338 PR-44 = 1.287 9
(Enclosure 13.2 Part B, Column F) Column D multiplied by Column E will provide AFD value for each PR channel.
The operator multiplies Column D by Column E for each PR and records the following in Column F of 3.2 Part B:
PR-41 = -17.48 PR-42 = -18.45 PR-43 = -16.85 PR-44 = -19.87
- 10 Verify calculated AFD is within limits specified in COLR.
The operator compares the calculated AFD values to Figure 5 (Percent of rated Thermal Power Versus Percent Axial Flux Difference Limits) of the COLR and determines that AFD for N42 and N44 exceeds the COLR limit of
(-18%)
Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 11 Identify any Technical Specification LCOs and ACTION that is applicable.
The operator identifies that LCO 3.2.3 Axial Flux Difference must be entered and that Condition A is applicable.
The operator identifies that plant power must be reduced to less than 50%
RTP within the next 30 minutes.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
Appendix C Page 10 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9 Job Performance Measure No.:
2012 Admin - JPM A1b SRO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
Appendix C Page 11 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9 KEY:
Detectors (A) 0% Axial Offset Currents (B)
Measured Currents (C)
(Col B/Col A x 100)
(D)
(Det A-Det B) 2 (E)
M Factor (F)
AFD (Col D x Col E)
PR-41A 112.2 342 304.81
-13.59 1.286
-17.48 PR-41B 123.5 410 331.98 PR-42A 116.9 359 307.10
-14.30 1.290
-18.45 PR-42B 126.6 425 335.70 PR-43A 115.3 341 295.75
-12.59 1.338
-16.85 PR-43B 129.0 414 320.93 PR-44A 107.5 333 309.77
-15.44 1.287
-19.87 PR-44B 123.0 419 340.65
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 INITIAL CONDITIONS:
Unit 1 is at 100% power.
The OAC has been out of service for 30 minutes.
PT/1/A/4600/021 A (Loss of Operator Aid Computer While in Mode 1) is being performed.
The Main Control Board AFD meters are INOPERABLE.
The following are the present current values for the Power Range upper and lower detectors:
PR-41 A = 342 MicroAmps PR-41 B = 410 MicroAmps PR-42 A = 359 MicroAmps PR-42 B = 425 MicroAmps PR-43 A = 341 MicroAmps PR-43 B = 414 MicroAmps PR-44 A = 333 MicroAmps PR-44 B = 419 MicroAmps INITIATING CUE:
The CRS has directed you to calculate AFD per PT/1/A/4600/021A (Loss of Operator Aid Computer while in Mode 1).
Identify all required action(s), if any, that may apply as a result of the AFD calculation.
Determine all calculations to two (2) decimal places.
Appendix C Job Performance Measure Form ES-C-1 Worksheet 2012 Admin - JPM A2 RO (REV_080212)
NUREG 1021, Revision 9 JPM A2 RO
Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A2 RO NUREG 1021, Revision 9 Facility:
McGuire Task No.:
Task
Title:
Perform a Manual NC Leakage Calculation JPM No.:
Reference:
GK/A 2.2.12 (3.7)
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.
Provide Candidate with Initial Conditions/Cue, and associated Datasheet (Last two (2)
Pages of this JPM); and Handout PT/1/A/4150/001B procedure body marked up as described, Enclosure 13.2 marked up as described, Enclosure 13.3 and Enclosure 13.4.
Initial Conditions:
Unit 1 is at 100% power.
The Unit 1 OAC point M1L4554 (U1 Unidentified Leakage > 1 GPM in CONT) is out of service.
PT/1/A/4200/040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm.
A manual NC System leakage calculation is in progress in accordance with PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) 3.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) has been completed through Step 1.10.
Initiating Cue:
Using Enclosure 13.2 (NC Leakage Determination Using Manual Calculations), AND the attached Datasheet, complete the NC System Leakage Calculation, through Step 1.12.
Based on this calculation, is any limiting condition for operation (LCO) NOT met? If so, identify the specification and the limit that is not met.
Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A2 RO NUREG 1021, Revision 9 Task Standard:
The operator will complete all calculations in accordance with the attached Key, and identify that the Unidentified RCS Leakage Technical Specification has been exceeded.
Required Materials:
Calculator General
References:
PT/1/A/4200/040 (Reactor Coolant Leakage Detection), Rev 15 PT/1/A/4150/001B (Reactor Coolant Leakage Calculation), Rev 77 McGuire Unit 1 Technical Specifications Handouts:
PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) marked up as follows:
Step 7.1 - Initialed Steps 8.1 through 8.5 - Initialed.
Step 12.1 Enclosure 13.2 Checkbox is checked.
Appendix C Page 4 of 12 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A2 RO NUREG 1021, Revision 9 PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) Enclosure 13.2 (NC Leakage Determinations Using Manual Calculations) marked up as follows:
Step 1.1 - Checkbox is checked/Initialed.
Step 1.2 - Initialed.
Step 1.3 - Initialed.
Determine VCT Purge Status Checkbox is checked.
Secured Checkbox is checked Determine Waste Gas System Status Checkbox checked In Service Checkbox checked NC System leakage calculation is in progress Checkbox is checked.
To refrain from sampling.. Checkbox is checked.
Person Notified Mike Smith Todays Date/Time Step 1.4 - Initialed.
NC System leakage calculation is in progress Checkbox is checked.
To check that NC sample.. Checkbox is checked.
NC System sampling.. Checkbox is checked.
Person Notified Melvin Smith Todays Date/Time Step 1.5 - Initialed.
Step 1.6 - All Checkboxes checked/Initialed.
Step 1.7 - Initialed.
Step 1.7.1 - Initialed.
Step 1.7.2 - Initialed.
Step 1.8 - Initialed.
Step 1.9 - Initialed.
Step 1.10 - NAd and initialed Step 1.11.7 - Initialed.
Enclosure 13.3 (NCDT Volume) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation)
Enclosure 13.4 (PRT Volume) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation)
McGuire Unit 1 Technical Specifications Time Critical Task:
NO Validation Time:
25 minutes
Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A2 RO NUREG 1021, Revision 9 (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue, and associated Datasheet (Last two (2)
Pages of this JPM); and Handout PT/1/A/4150/001B procedure body marked up as described, Enclosure 13.2 marked up as described, Enclosure 13.3 and Enclosure 13.4.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1
(Enclosure 13.2, Steps 1.11.1 through 6, 8 through 13, 22, 26 and 1.12.1)
Record raw data.
The operator transposes raw data from the Data Sheet provided.
2 (Enclosure 13.2, Step 1.11.14) Calculate change in NC System Tave:
The operator calculates the change in NC System Tave to be -0.2oF, and records.
3 (Enclosure 13.2, Step 1.11.15) Calculate VCT Leakage Rate:
The operator calculates the VCT Leakage Rate to be 5.02 gpm, and records.
4 (Enclosure 13.2, Step 1.11.16) Calculate PZR Leakage Rate:
The operator calculates the PZR Leakage Rate to be -
0.017 gpm, and records.
5 (Enclosure 13.2, Step 1.11.17) Calculate Total Leakage:
The operator calculates the Total Leakage to be 5.003 gpm, and records.
Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A2 RO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6
(Enclosure 13.2, Step 1.11.18) Using Enclosure 13.4 (PRT Volume), record the following:
Initial PRT Volume Final PRT Volume The operator uses 3.4 and an initial PRT Level of 76.0 %,
and determines that initial PRT Volume is 10636.1 gal, and records.
The operator uses 3.4 and interpolates a PRT Volume for 77.0% to be 10770.4 gal, and records.
7 (Enclosure 13.2, Step 1.11.19) Calculate PRT Leakage Rate:
The operator calculates the PRT Leakage Rate to be 2.13 gpm, and records.
8 (Enclosure 13.2, Step 1.11.
- 20) Using Enclosure 13.3 (NCDT Volume), record the following:
Initial NCDT Volume Final NCDT Volume The operator uses 3.3 and an initial NCDT Level of 44.0%,
and determines that initial NCDT Volume is 155.0 gal, and records.
The operator uses 3.3 and a final NCDT Level of 49.0%, and determines that final NCDT Volume is 173.0 gal, and records.
9 (Enclosure 13.2, Step 1.11.21) Calculate NCDT Leakage Rate:
The operator calculates the NCDT Leakage Rate to be
.29 gpm, and records.
10 (Enclosure 13.2, Step 1.11.23) Calculate Total Background Leakage:
The operator calculates the Total Background Leakage to be 0 gpm, and records.
Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A2 RO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 11 (Enclosure 13.2, Step 1.11.24) Calculate Identified Leakage:
The operator calculates the Identified Leakage to be 2.42 (+/-10%) gpm, and records.
- 12 (Enclosure 13.2, Step 1.11.25) Calculate Unidentified Leakage:
The operator calculates the Unidentified Leakage to be 2.58 (+/-10%) gpm, and records.
- 13 (Enclosure 13.2, Step 1.11.26) Determine Total NC Pump #1 Seal Leakoff:
The operator calculates the Total NC Pumps #1 Seal Leakoff to be 14.5 (+/-10%)
gpm, and records.
- 14 (Enclosure 13.2, Step 1.11.27) Calculate Total Accumulative Leakage:
The operator calculates the Total Accumulative Leakage to be 19.50
(+/-10%) gpm, and records.
15 (Enclosure 13.2) Calculated By/ Date/Time:
The operator places their name in the Calculated by BLOCK, and signs.
The operator enters the Date and Time.
Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A2 RO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 16 Technical Specification LCO 3.4.13:
RCS operational LEAKAGE shall be limited to:
- a.
- b.
1 gpm unidentified LEAKAGE;
- c.
10 gpm identified LEAKAGE;
- d.
389 gallons per day total primary to secondary LEAKAGE through all steam generators (SGs); and
- e.
135 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).
APPLICABILITY:
MODES 1, 2, 3, and 4.
The operator returns the completed Enclosure 13.2 and reports that LCO 3.4.13 has been exceeded because there is greater than 1 gpm unidentified LEAKAGE.
Examiner NOTE:
See KEY on Page 10 of this JPM.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
Appendix C Page 9 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A2 RO NUREG 1021, Revision 9 Job Performance Measure No.:
2012 Admin - JPM A2 RO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
Appendix C Page 10 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A2 RO NUREG 1021, Revision 9 KEY:
3.2, Step 1.11.14 (JPM Step 2): Change in NC System Tave:
584.8oF - 585.0oF = -0.2oF 3.2, Step 1.11.15 (JPM Step 3): VCT Leakage Rate:
(59.9% - 43.5%) x19.3 gallons/%/63 minutes = 5.02 gallons per minute (gpm) 3.2, Step 1.11.16 (JPM Step 4): PZR Leakage Rate:
(54.7% - 55.2%) x 132.5 gallons/% x.01613 /63 minutes = -0.017 gallons per minute (gpm) 3.2, Step 1.11.17 (JPM Step 5): Total Leakage:
5.02 gpm + (-0.017) gpm = 5.003 gpm 3.2, Step 1.11.19 (JPM Step 7): Total PRT Leakage:
(10770.4 gallons - 10636.1 gallons)/63 minutes = 2.13 gallons per minute (gpm) 3.2, Step 1.11.21 (JPM Step 9): Total NCDT Leakage:
(173 gallons - 155 gallons)/63 minutes = 0.29 gallons per minute (gpm) 3.2, Step 1.11.23 (JPM Step 10): Total Background Leakage:
(0 gpm + 0 gpm) = 0 gpm 3.2, Step 1.11.24 (JPM Step 11): Identified Leakage:
(2.13 gpm +.29 gpm + 0 gpm) = 2.42 gpm 3.2, Step 1.11.25 (JPM Step 12): Unidentified Leakage:
(5.003 gpm - 2.42 gpm) = 2.58 gpm 3.2, Step 1.11.26 (JPM Step 13): Total NC Pumps #1 Seal Leakoff:
(3.8 gpm + 3.3 gpm + 3.9 gpm + 3.5 gpm) = 14.5 gpm 3.2, Step 1.11.27 (JPM Step 14): Total Accumulative Leakage:
(2.42 gpm + 2.58 gpm + 14.5 gpm) = 19.50 gpm LCO 3.4.13 (1 gpm unidentified LEAKAGE) has been exceeded.
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 Data Sheet Start Time 0300 Stop Time 0403 Initial Final VCT Level 59.9 43.5 Pzr Level 54.7 55.2 NC System Tave 584.8 585.0 PRT Level 76.0 77.0 NCDT Level 44 49 NC Sample Purge Flow value recorded in Autolog 0
Any quantified (measured) leakage that has been identified 0
NC Pump 1A #1 Seal Leakoff Flow 3.8 NC Pump 1B #1 Seal Leakoff Flow 3.3 NC Pump 1C #1 Seal Leakoff Flow 3.9 NC Pump 1D #1 Seal Leakoff Flow 3.5 1EMF71 Reading 1.6 1EMF72 Reading 1.1 1EMF73 Reading 1.8 1EMF74 Reading 1.2
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 Initial Conditions:
Unit 1 is at 100% power.
The Unit 1 OAC point M1L4554 (U1 Unidentified Leakage > 1 GPM in CONT) is out of service.
PT/1/A/4200/040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm.
A manual NC System leakage calculation is in progress in accordance with PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) 3.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) has been completed through Step 1.10.
INITIATING CUE:
Using Enclosure 13.2 (NC Leakage Determination Using Manual Calculations), AND the attached Datasheet, complete the NC System Leakage Calculation, through Step 1.12.
Based on this calculation, is any limiting condition for operation (LCO) NOT met? If so, identify the specification and the limit that is not met.
Appendix C Job Performance Measure Form ES-C-1 Worksheet 2012 Admin - JPM A2 SRO (Rev_080212)
NUREG 1021, Revision 9 JPM A2 SRO
Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A2 SRO NUREG 1021, Revision 9 Facility:
McGuire Task No.:
Task
Title:
Perform/Review a Manual NC Leakage Calculation JPM No.:
Reference:
GK/A 2.2.12 (4.1)
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.
Provide Candidate with Initial Conditions/Cue, and associated Datasheet (Last two (2)
Pages of this JPM); and Handout PT/1/A/4150/001B procedure body marked up as described, Enclosure 13.2 marked up as described, Enclosure 13.3 and Enclosure 13.4.
Initial Conditions:
Unit 1 is at 100% power.
The Unit 1 OAC point M1L4554 (U1 Unidentified Leakage > 1 GPM in CONT) is out of service.
PT/1/A/4200/040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm.
A manual NC System leakage calculation is in progress in accordance with PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) 3.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) has been completed through Step 1.10.
Initiating Cue:
Using Enclosure 13.2 (NC Leakage Determination Using Manual Calculations), AND the attached Datasheet, complete the NC System Leakage Calculation through Step 1.12.
Identify all required action(s), if any, that apply as a result of the NC Leakage Calculation.
Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A2 SRO NUREG 1021, Revision 9 Task Standard:
The operator will complete all calculations in accordance with the attached Key, identify that the Unidentified RCS Leakage Technical Specification has been exceeded, and the required ACTION.
Required Materials:
Calculator General
References:
PT/1/A/4200/040 (Reactor Coolant Leakage Detection), Rev 15 PT/1/A/4150/001B (Reactor Coolant Leakage Calculation), Rev 77 McGuire Unit 1 Technical Specifications Handouts:
PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) marked up as follows:
Step 7.1 - Initialed Steps 8.1 through 8.5 - Initialed.
Step 12.1 Enclosure 13.2 Checkbox is checked.
Appendix C Page 4 of 12 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A2 SRO NUREG 1021, Revision 9 PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) Enclosure 13.2 (NC Leakage Determinations Using Manual Calculations) marked up as follows:
Step 1.1 - Checkbox is checked/Initialed.
Step 1.2 - Initialed.
Step 1.3 - Initialed.
Determine VCT Purge Status Checkbox is checked.
Secured Checkbox is checked.
Determine Waste Gas System Status Checkbox checked In Service Checkbox checked NC System leakage calculation is in progress Checkbox is checked.
To refrain from sampling.. Checkbox is checked.
Person Notified Mike Smith Todays Date/Time Step 1.4 - Initialed.
NC System leakage calculation is in progress Checkbox is checked.
To check that NC sample.. Checkbox is checked.
NC System sampling.. Checkbox is checked.
Person Notified Melvin Smith Todays Date/Time Step 1.5 - Initialed.
Step 1.6 - All Checkboxes checked/Initialed.
Step 1.7 - Initialed.
Step 1.7.1 - Initialed.
Step 1.7.2 - Initialed.
Step 1.8 - Initialed.
Step 1.9 - Initialed.
Step 1.10 - NAd and initialed.
Step 1.11.7 - Initialed.
3.3 (NCDT Volume) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) 3.4 (PRT Volume) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation)
McGuire Unit 1 Technical Specifications Time Critical Task:
NO Validation Time:
25 minutes
Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A2 SRO NUREG 1021, Revision 9 (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue, and associated Datasheet (Last two (2)
Pages of this JPM); and Handout PT/1/A/4150/001B procedure body marked up as described, Enclosure 13.2 marked up as described, Enclosure 13.3 and Enclosure 13.4.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1
(Enclosure 13.2, Steps 1.11.1 through 6, 8 through 13, 22, 26 and 1.11.1)
Record raw data.
The operator transposes raw data from the Data Sheet provided.
2 (Enclosure 13.2, Step 1.11.14) Calculate change in NC System Tave:
The operator calculates the change in NC System Tave to be -0.2oF, and records.
3 (Enclosure 13.2, Step 1.11.15) Calculate VCT Leakage Rate:
The operator calculates the VCT Leakage Rate to be 5.02 gpm, and records.
4 (Enclosure 13.2, Step 1.11.16) Calculate PZR Leakage Rate:
The operator calculates the PZR Leakage Rate to be -
0.017 gpm, and records.
5 (Enclosure 13.2, Step 1.11.17) Calculate Total Leakage:
The operator calculates the Total Leakage to be 5.003 gpm, and records.
Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A2 SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6
(Enclosure 13.2, Step 1.11.18) Using Enclosure 13.4 (PRT Volume), record the following:
Initial PRT Volume Final PRT Volume The operator uses 3.4 and an initial PRT Level of 76.0 %,
and determines that initial PRT Volume is 10636.1 gal, and records.
The operator uses 3.4 and interpolates a PRT Volume for 77.0% to be 10770.4 gal, and records.
7 (Enclosure 13.2, Step 1.11.19) Calculate PRT Leakage Rate:
The operator calculates the PRT Leakage Rate to be 2.13 gpm, and records.
8 (Enclosure 13.2, Step 1.11.
- 20) Using Enclosure 13.3 (NCDT Volume), record the following:
Initial NCDT Volume Final NCDT Volume The operator uses 3.3 and an initial NCDT Level of 44.0%,
and determines that initial NCDT Volume is 155.0 gal, and records.
The operator uses 3.3 and a final NCDT Level of 49.0%, and determines that final NCDT Volume is 173.0 gal, and records.
9 (Enclosure 13.2, Step 1.11.21) Calculate NCDT Leakage Rate:
The operator calculates the NCDT Leakage Rate to be
.29 gpm, and records.
10 (Enclosure 13.2, Step 1.11.23) Calculate Total Background Leakage:
The operator calculates the Total Background Leakage to be 0 gpm, and records.
Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A2 SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 11 (Enclosure 13.2, Step 1.11.24) Calculate Identified Leakage:
The operator calculates the Identified Leakage to be 2.42 (+/-10%) gpm, and records.
- 12 (Enclosure 13.2, Step 1.11.25) Calculate Unidentified Leakage:
The operator calculates the Unidentified Leakage to be 2.58 (+/-10%) gpm, and records.
- 13 (Enclosure 13.2, Step 1.11.26) Determine Total NC Pump #1 Seal Leakoff:
The operator calculates the Total NC Pumps #1 Seal Leakoff to be 14.5 (+/-10%)
gpm, and records.
- 14 (Enclosure 13.2, Step 1.11.27) Calculate Total Accumulative Leakage:
The operator calculates the Total Accumulative Leakage to be 19.50
(+/-10%) gpm, and records.
15 (Enclosure 13.2) Calculated By/ Date/Time:
The operator places their name in the Calculated by BLOCK, and signs.
The operator enters the Date and Time.
Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A2 SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 16 Technical Specification LCO 3.4.13:
RCS operational LEAKAGE shall be limited to:
- a.
- b.
1 gpm unidentified LEAKAGE;
- c.
10 gpm identified LEAKAGE;
- d.
389 gallons per day total primary to secondary LEAKAGE through all steam generators (SGs); and
- e.
135 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).
APPLICABILITY:
MODES 1, 2, 3, and 4.
The operator returns the completed Enclosure 13.2 and reports that LCO 3.4.13 has been exceeded because there is greater than 1 gpm unidentified LEAKAGE.
The operator identifies that CONDITION A is met, RCS Operational LEAKAGE not within limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE; AND that the REQUIRED ACTION is to Reduce LEAKAGE to within limits, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Examiner NOTE:
See KEY on Page 10 of this JPM.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
Appendix C Page 9 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A2 SRO NUREG 1021, Revision 9 Job Performance Measure No.:
2012 Admin - JPM A2 SRO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
Appendix C Page 10 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A2 SRO NUREG 1021, Revision 9 KEY:
3.2, Step 1.11.14 (JPM Step 2): Change in NC System Tave:
584.8oF - 585.0oF = -0.2oF 3.2, Step 1.11.15 (JPM Step 3): VCT Leakage Rate:
(59.9% - 43.5%) x19.3 gallons/%/63 minutes = 5.02 gallons per minute (gpm) 3.2, Step 1.11.16 (JPM Step 4): PZR Leakage Rate:
(54.7% - 55.2%) x 132.5 gallons/% x.01613 /63 minutes = -0.017 gallons per minute (gpm) 3.2, Step 1.11.17 (JPM Step 5): Total Leakage:
5.02 gpm + (-0.017) gpm = 5.003 gpm 3.2, Step 1.11.19 (JPM Step 7): Total PRT Leakage:
(10770.4 gallons - 10636.1 gallons)/63 minutes = 2.13 gallons per minute (gpm) 3.2, Step 1.11.21 (JPM Step 9): Total NCDT Leakage:
(173 gallons - 155 gallons)/63 minutes = 0.29 gallons per minute (gpm) 3.2, Step 1.11.23 (JPM Step 10): Total Background Leakage:
(0 gpm + 0 gpm) = 0 gpm 3.2, Step 1.11.24 (JPM Step 11): Identified Leakage:
(2.13 gpm +.29 gpm + 0 gpm) = 2.42 gpm 3.2, Step 1.11.25 (JPM Step 12): Unidentified Leakage:
(5.003 gpm - 2.42 gpm) = 2.58 gpm 3.2, Step 1.11.26 (JPM Step 13): Total NC Pumps #1 Seal Leakoff:
(3.8 gpm + 3.3 gpm + 3.9 gpm + 3.5 gpm) = 14.5 gpm 3.2, Step 1.11.27 (JPM Step 14): Total Accumulative Leakage:
(2.42 gpm + 2.58 gpm + 14.5 gpm) = 19.50 gpm LCO 3.4.13.b (1 gpm unidentified LEAKAGE) has been exceeded, CONDITION A is met, RCS Operational LEAKAGE not within limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE; AND that the REQUIRED ACTION is to Reduce LEAKAGE to within limits, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 Data Sheet Start Time 0300 Stop Time 0403 Initial Final VCT Level 59.9 43.5 Pzr Level 54.7 55.2 NC System Tave 584.8 585.0 PRT Level 76.0 77.0 NCDT Level 44 49 NC Sample Purge Flow value recorded in Autolog 0
Any quantified (measured) leakage that has been identified 0
NC Pump 1A #1 Seal Leakoff Flow 3.8 NC Pump 1B #1 Seal Leakoff Flow 3.3 NC Pump 1C #1 Seal Leakoff Flow 3.9 NC Pump 1D #1 Seal Leakoff Flow 3.5 1EMF71 Reading 1.6 1EMF72 Reading 1.1 1EMF73 Reading 1.8 1EMF74 Reading 1.2
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 Initial Conditions:
Unit 1 is at 100% power.
The Unit 1 OAC point M1L4554 (U1 Unidentified Leakage > 1 GPM in CONT) is out of service.
PT/1/A/4200/040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm.
A manual NC System leakage calculation is in progress in accordance with PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) 3.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) has been completed through Step 1.10.
INITIATING CUE:
Using Enclosure 13.2 (NC Leakage Determination Using Manual Calculations), AND the attached Datasheet, complete the NC System Leakage Calculation through Step 1.12.
Identify all required action(s), if any, that apply as a result of the NC Leakage Calculation.
Appendix C Job Performance Measure Form ES-C-1 Worksheet 2012 Admin - JPM A3 RO (REV_073012)
NUREG 1021, Revision 9 JPM A3 RO
Appendix C Page 2 of 9 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A3 RO NUREG 1021, Revision 9 Facility:
McGuire Task No.:
Task
Title:
Predict Radiation Levels While Responding to a Damaged Spent Fuel Pool JPM No.:
Reference:
GK/A 2.3.14 (3.4)
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.
Provide Candidate with Initial Conditions/Cue and handout Enclosure 13 of AP/1/A/5500/41.
Initial Conditions:
Due to an Earthquake, Unit 2 tripped from 100% power.
Unit 1 is 11 days into a Refueling Outage and a full core off-load has just been completed.
A Loss of Offsite Power has occurred, and only one EDG is running on each unit.
The Unit 1 Spent Fuel Pool has sustained damage, and is leaking.
The crew is implementing several EPs/APs simultaneously including AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level).
The TSC is manned.
All attempts to add makeup water to the Unit 1 Spent Fuel Pool have been unsuccessful.
The Control Room Spent Fuel Pool Level and Temperature instrumentation are unavailable.
It is expected that the ability to add makeup water to the Spent Fuel Pool will be regained within four hours.
Appendix C Page 3 of 9 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A3 RO NUREG 1021, Revision 9 An operator who has just left the Spent Fuel Pool Area has reported that during the 15 minutes that he was in the Spent Fuel Pool Area, the Aztec Level Gauge dropped about 1 foot, and the present level is 23 feet above the top of the Spent Fuel.
Initiating Cue:
The OSC Coordinator has directed you to refer to Enclosure 13 (Spent Fuel Pool Radiation Level vs. Water level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), and determine the expected radiation levels one hour, two hours, three hours and four hours from now, based on the last known leak rate.
Task Standard:
The operator will use Enclosure 13 of AP/1/A/5500/41 and determine that the expected radiation levels will be as follows:
One hour 0.2 mr/hr (+/-50%)
Two hours 1.0 mr/hr (+/-50%)
Three hours 400 mr/hr (+/-50%)
Four hours 32 R/hr (+/-50%)
Required Materials:
Calculator General
References:
AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), Rev 10 EP/1/A/5000/G-1 (Generic Enclosures), Rev 31 McGuire Selected Licensee Commitments Handouts: 3 (Loss of Spent Fuel Pool Cooling or Level) of AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level)
Time Critical Task:
NO Validation Time:
15 minutes
Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A3 RO NUREG 1021, Revision 9 (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue and handout Enclosure 13 of AP/1/A/5500/41.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 1 (Enclosure 13) Determine expected radiation levels in Spent Fuel Pool area in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The operator recognizes that the present level of the Spent Fuel Pool approximates the SLC Limit of 23 feet above the Fuel, and uses this as a reference.
The operator recognizes that the Spent Fuel Pool is lowering at a rate of 4 feet per hour, and will be approximately 19 feet above the Spent Fuel Pool in one hour.
The Operator uses 3, locates the Dose Rate at 20 feet and 15 feet, and then approximates between these two values for 19 feet.
When this is accomplished the operator will determine that the expected Dose Rate in one hour is approximately 0.2 mrem/hr
(+/-50%) [See Key on Page 8].
Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A3 RO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 2 (Enclosure 13) Determine expected radiation levels in Spent Fuel Pool area in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
The operator recognizes that the Spent Fuel Pool is lowering at a rate of 4 feet per hour, and will be approximately 15 feet above the Spent Fuel Pool in two hours.
The Operator uses 3, locates the Dose Rate at 15 feet, and determines that the expected Dose Rate in two hours is approximately 1 mrem/hr (+/-50%)[See Key on Page 8].
- 3 (Enclosure 13) Determine expected radiation levels in Spent Fuel Pool area in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
The operator recognizes that the Spent Fuel Pool is lowering at a rate of 4 feet per hour, and will be approximately 11 feet above the Spent Fuel Pool in three hours.
The Operator uses 3, locates the Dose Rate at 12.5 feet and 10 feet, and then approximates between these two values for 11 feet.
When this is accomplished the operator will determine that the expected Dose Rate in three hours is approximately 400 mrem/hr
(+/-50%)[See Key on Page 8].
Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A3 RO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 4 (Enclosure 13) Determine expected radiation levels in Spent Fuel Pool area in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
The operator recognizes that the Spent Fuel Pool is lowering at a rate of 4 feet per hour, and will be approximately 7 feet above the Spent Fuel Pool in four hours.
The Operator uses 3, locates the Dose Rate at 7 feet, and determines that the expected Dose Rate in four hours is approximately 32 Rem/hr (+/-50%)[See Key on Page 8].
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
Appendix C Page 7 of 9 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A3 RO NUREG 1021, Revision 9 Job Performance Measure No.:
2012 Admin - JPM A3 RO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A3 RO NUREG 1021, Revision 9 KEY:
1 Hour Dose rate at 20 feet 1.21 x10-6 R/hr x 103mrem/hr/R/hr =.001 mrem/hr Dose rate at 15 feet 9.51 x10-4 R/hr x 103mrem/hr/R/hr =.951 mrem/hr Assume Dose Rate rises linearly as level drops between 20 and 15 feet.
.951 mrem/hr -.001 mrem/hr / 5 feet=.19 mrem/hr/ft Since the rise in radiation level from level dropping one foot from 20 feet is 0.19 mrem/hr, the expected Dose Rate at 19 feet is.19 mrem/hr higher than the Dose Rate at 20 feet; or.19 mrem/hr. (.095 -.285 mrem/hr) 2 Hours This is a direct read from the Table.
Dose rate at 15 feet 9.51 x10-4 R/Hr x 103mrem/hr/R/Hr =.951 mrem/hr (.476 -1.427 mrem/hr) 3 Hours Dose rate at 12.5 feet 2.52 x10-2 R/Hr x 103mrem/hr/R/Hr = 25.2 mrem/hr Dose rate at 10 feet 6.49 x10-1 R/Hr x 103mrem/hr/R/Hr = 649 mrem/hr Assume Dose Rate rises linearly as level drops between 12.5 and 10 feet.
649 mrem/hr - 25.2 mrem/hr / 2.5 feet= 249.5 mrem/hr/ft Since the rise in radiation level from level dropping one foot from 12.5 feet is 249.5, the expected Dose Rate at 11 feet is 1.5 times that or 374.2 mrem/hr rise from the Dose Rate at 12.5 feet (25.2 mrem/hr), or 399.4 mrem/hr. (199.7 - 599.1 mrem/hr) 4 Hours This is a direct read from the Table.
Dose rate at 7 feet 3.2 x101 R/Hr = 32 Rem/hr (16 - 48 Rem/hr)
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 Initial Conditions:
Due to an Earthquake, Unit 2 tripped from 100% power.
Unit 1 is 11 days into a Refueling Outage and a full core off-load has just been completed.
A Loss of Offsite Power has occurred, and only one EDG is running on each unit.
The Unit 1 Spent Fuel Pool has sustained damage, and is leaking.
The crew is implementing several EPs/APs simultaneously including AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level).
The TSC is manned.
All attempts to add makeup water to the Unit 1 Spent Fuel Pool have been unsuccessful.
The Control Room Spent Fuel Pool Level and Temperature instrumentation are unavailable.
It is expected that the ability to add makeup water to the Spent Fuel Pool will be regained within four hours.
An operator who has just left the Spent Fuel Pool Area has reported that during the 15 minutes that he was in the Spent Fuel Pool Area, the Aztec Level Gauge dropped about 1 foot, and the present level is 23 feet above the top of the Spent Fuel.
INITIATING CUE:
The OSC Coordinator has directed you to refer to Enclosure 13 (Spent Fuel Pool Radiation Level vs. Water level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), and determine the expected radiation levels one hour, two hours, three hours and four hours from now, based on the last known leak rate.
Appendix C Job Performance Measure Form ES-C-1 Worksheet 2012 Admin - JPM A3 SRO (Rev_073012)
NUREG 1021, Revision 9 JPM A3 SRO
Appendix C Page 2 of 9 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A3 SRO NUREG 1021, Revision 9 Facility:
McGuire Task No.:
Task
Title:
Calculate Spent Fuel Pool Boiloff rate and predict when Spent Fuel Pool Radiation levels will exceed 1Rem/Hour JPM No.:
Reference:
GK/A 2.3.14 (3.8)
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.
Provide Candidate with Initial Conditions/Cue and handout Enclosures 5 and 13 of AP/1/A/5500/41.
Initial Conditions:
Due to an Earthquake, Unit 2 tripped from 100% power.
Unit 1 was shutdown 9 days ago and a full core off-load has just been completed.
A loss of Offsite Power has occurred, and only one EDG is running on each unit.
The Unit 1 Spent Fuel Pool cooling has been lost.
The crew is implementing several EPs/APs simultaneously including AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level).
The TSC is manned.
The earthquake lowered the Spent Fuel Pool level to 23 feet above the top of the Spent Fuel due to wave action.
All attempts to add makeup water to the Unit 1 Spent Fuel Pool have been unsuccessful.
The Spent Fuel Pool has just started to boil.
Appendix C Page 3 of 9 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A3 SRO NUREG 1021, Revision 9 Initiating Cue:
The OSC Coordinator has directed you to use Enclosure 5 (Spent Fuel Pool Boiloff rate) of AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), and estimate how fast the Spent Fuel Pool level will go down as the pool boils.
THEN Use this boiloff rate and Enclosure 13 (Spent Fuel Pool Radiation Level vs. Water level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), and predict when the radiation levels in the Spent Fuel Pool area will be greater than 1 Rem/hour if no makeup water is added.
Task Standard:
The operator will determine that the boiloff rate is 4.4 inches/hour, and that the expected time that the Dose Rate in the Spent Fuel Area exceeds 1000 mrem/hour is 36+/-2 hours.
Required Materials:
Calculator General
References:
AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), Rev 10 EP/1/A/5000/G-1 (Generic Enclosures), Rev 31 McGuire Technical Specifications McGuire Selected Licensee Commitments Handouts: (Spent Fuel Pool Boiloff rate) of AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level) 3 (Loss of Spent Fuel Pool Cooling or Level) of AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level)
McGuire Technical Specifications McGuire Selected Licensee Commitments Time Critical Task:
NO Validation Time:
15 minutes
Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A3 SRO NUREG 1021, Revision 9 (Denote Critical Steps with an asterisk*)
Provide Candidate with Initial Conditions/Cue and handout Enclosures 5 and 13 of AP/1/A/5500/41.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1
(Enclosure 5, Note prior to Step 1) The following step calculates "Time After Shutdown". This value is used to determine how much decay heat exists in the pool and will be used in subsequent steps to calculate boiloff rate.
The operator reads the Note and proceeds.
2 (Step 1) Determine "Time After Shutdown" as follows:
(Step 1.a) IF Unit 1 is currently shutdown for a refueling outage, THEN perform the following:
(Step 1.a.1) IF core offload has not occurred,..
The operator recognizes that this Step is NA and proceeds to Step 1.a.2.
- 3 (Step 1.a.2) IF less than 193 fuel assemblies are currently in the reactor, THEN perform the following:
Use number of days since reactor was shutdown as "Time After Shutdown".
Observe Notes prior to Step 2 and GO TO Step 2.
The operator recognizes that Unit 1 was shut down 9 days ago (Initial Conditions), and proceeds to Step 2.
Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A3 SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 4
(Notes prior to Step 2)
Tables assume complete core offload has occurred. For partial offload, tables are conservative.
If Spent Fuel Pool makeup has occurred, tables are conservative.
There is approximately 940 gallons of water per inch of Spent Fuel Pool level.
Table does not consider additional inventory loss if Standby Makeup pump is on (approximately 2 inches/hr).
The operator reads the Notes and proceeds.
- 5 (Step 2) IF less than 193 fuel assemblies are currently in the reactor, THEN use the following tables to estimate Spent Fuel Pool boiloff rate:
The operator recognizes that the core has been offloaded, and that the following Table applies.
The operator locates 9 days since shutdown and determines the boiloff rate of 68 gpm and a level decrease rate of 4.4 inches/hour.
Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A3 SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 6 (Enclosure 13) REFER TO the table below to determine estimated Spent Fuel Pool radiation levels.
The Operator uses 3, and determines that an estimated Dose rate of 1R/hour will occur with a SFP Level between 10 and 9 feet above the Spent Fuel.
The operator calculates/approximates the water depth above the Spent Fuel yielding Dose Rates of 1 R/hour to be 9 feet, 9.5 inches. (See Key on Page 8)
The operator recognizes that the present level of the Spent Fuel Pool (Minus 34 inches) approximates the SLC Limit of 23 feet above the Fuel, and uses this as a reference point.
The operator calculates/approximates the Time that the water level will drop to the point at which the Dose Rate will exceed 1 Rem/hour to be 36+/-2 hours. (See Key on Page 8)
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
Appendix C Page 7 of 9 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A3 SRO NUREG 1021, Revision 9 Job Performance Measure No.:
2012 Admin - JPM A3 SRO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A3 SRO NUREG 1021, Revision 9 KEY:
Depth of Spent Fuel Pool water that will yield a Dose Rate in the Spent Fuel area of 1Rem/hour:
Dose rate at 10 feet 6.49 x10-1 R/Hr x 103mrem/hr/R/Hr = 649 mrem/hr Dose rate at 9 feet 2.38 x100 R/Hr x 103mrem/hr/R/Hr = 2380 mrem/hr Assume Dose Rate rises linearly as level drops between 10 and 9 feet.
2380 mrem/hr - 649 mrem/hr / 1 feet x 1 foot/12 inches= 144.25 mrem/hr/inch Since the rise in radiation level from level dropping one inch from 10 feet is 144.25, amount in inches that the level must drop to yield a Dose rate of 1 Rem/hour (or 1000 mrem/hour) can be calculated as follows:
(1000 mrem/hr-649 mrem/hr)/144.25 mrem/hr/inch = 2.43 inches or approximately 2.5 inches.
Consequently, the operator can estimate that the level in the Spent Fuel Pool that (Above the top of the fuel) that the water must drop to, which will result in a Dose Rate in the Spent Fuel area of 1Rem/hour is [10 feet - 2.5 inches] or 9 feet 9.5 inches.
Time that the water level will drop to the point at which the Dose Rate will exceed 1 Rem/hour:
[Present Level in inches - Level inches when DR 1R/hr]/4.4 inches/hour
[(23ft x 12in/ft) - (9ft x 12in/ft + 9.5in)]/4.4in/hour
[(276in) - (117.5in)]/4.4in/hour = 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> NOTE: If the operator conservatively used the 10 foot level to estimate time this would be acceptable. However, if the operator used the 9 foot level, which is not conservative, this would not be acceptable
[Present Level in inches - Level inches when DR 1R/hr]/4.4 inches/hour
[(23ft x 12in/ft) - (10ft x 12in/ft ]/4.4in/hour
[(276in) - (120in)]/4.4in/hour = 35.45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />. (10 foot level used)
[(23ft x 12in/ft) - (9ft x 12in/ft ]/4.4in/hour
[(276in) - (108in)]/4.4in/hour = 38.18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. (10 foot level used)
Consequently, if the acceptable range were +/-2 hour, and the operator used the conservative value (i.e. the ten foot Dose Rate), rather than extrapolating between 9 and 10 feet, the operator would still be correct.
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 Initial Conditions:
Due to an Earthquake, Unit 2 tripped from 100% power.
Unit 1 was shutdown 9 days ago and a full core off-load has just been completed.
A loss of Offsite Power has occurred, and only one EDG is running on each unit.
The Unit 1 Spent Fuel Pool cooling has been lost.
The crew is implementing several EPs/APs simultaneously including AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level).
The TSC is manned.
The earthquake lowered the Spent Fuel Pool level to 23 feet above the top of the Spent Fuel due to wave action.
All attempts to add makeup water to the Unit 1 Spent Fuel Pool have been unsuccessful.
The Spent Fuel Pool has just started to boil.
INITIATING CUE:
The OSC Coordinator has directed you to use Enclosure 5 (Spent Fuel Pool Boiloff rate) of AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), and estimate how fast the Spent Fuel Pool level will go down as the pool boils.
THEN Use this boiloff rate and Enclosure 13 (Spent Fuel Pool Radiation Level vs. Water level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), and predict when the radiation levels in the Spent Fuel Pool area will be greater than 1 Rem/hour if no makeup water is added.
Appendix C Job Performance Measure Form ES-C-1 Worksheet 2012 Admin - JPM A4 SRO (Rev_080712)
NUREG 1021, Revision 9 JPM A4 SRO
Appendix C Page 2 of 10 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A4 SRO NUREG 1021, Revision 9 Facility:
McGuire Task No.:
Task
Title:
Classify an Emergency Event JPM No.:
Reference:
GK/A 2.4.41 (2.9/4.6)
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.
Provide Candidate with Last Page of this JPM and blank copies of RP/0/A/5700/000 and RP/0/B/5700/029.
Initial Conditions:
A plant event is in progress on Unit 1.
Initiating Cue:
Classify the Event in accordance with RP/0/A/5700/000 (Classification of Emergency).
If more than one Emergency Action Level (EAL) has been exceeded, identify the EAL resulting in the Highest Emergency Classification.
Then, prepare a Nuclear Power Plant Emergency Notification Form for the event, and present to the Emergency Coordinator for approval.
Task Standard:
The operator will declare a Site Area Emergency based on 4.4.S.1, Failure of Reactor Protection System Instrumentation to Complete or Initiate an Automatic Reactor Trip Once a Reactor Protection System Setpoint Has Been Exceeded and Manual Trip WAS NOT Successful; and complete the pre-printed ENF 4.4.S.1.
Appendix C Page 3 of 10 Form ES-C-1 Job Performance Measure Worksheet 2012 Admin - JPM A4 SRO NUREG 1021, Revision 9 Required Materials:
Blank Copies of RP/0/A/5700/000, Enclosure 4.1, Fission Product Barrier Matrix.
Pre-printed ENF 4.4.S.1 located in Simulator Emergency Plan Pre-Printed ENF Form Notebook.
General
References:
RP/0/A/5700/000 (Classification of Emergency) Rev 18 RP/0/B/5700/001 (Notification of Unusual Event) Rev 27 RP/0/B/5700/002 (Alert) Rev 27 RP/0/B/5700/003 (Site Area Emergency) Rev 28 RP/0/B/5700/004 (General Emergency) Rev 27 RP/0/B/5700/029 (Notifications to Offsite Agencies From the Control Room) Rev 10 AP/1/A/5500/10 (NC System Leakage Within the Capacity of Both NV Pumps), Rev 22 PT/1/A/4150/001C (Primary to Secondary Leakage Monitoring), Rev 3 EP/1/A/5000/E-0 (Reactor Trip or Safety Injection), Rev 32 EP/1/A/5000/FR-S.1 (Response to Nuclear Power Generation/ATWS),
Rev 13 OMP 4-3 (Use of Abnormal and Emergency Procedures), Rev 34 McGuire Technical Specifications Handouts:
RP/0/A/5700/000 (Classification of Emergency)
RP/0/B/5700/029 (Notifications to Offsite Agencies From the Control Room)
Time Critical Task:
YES - 15 minute to make classification, and THEN 15 minutes to complete ENF.
Validation Time:
30 minutes
Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A4 SRO NUREG 1021, Revision 9 (Denote Critical Steps with an asterisk*)
Provide Candidate with Last Page of this JPM and blank copies of RP/0/A/5700/000 and RP/0/B/5700/029.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1
(OMP 4-3, Steps 7.20.1/7.20.1.1) OSM Responsibilities Assume role of Emergency Coordinator upon activation of the Emergency Plan until properly relieved by the Station Manager.
The operator enters RP/0/A/5700/000,Step 2.1.
2 (RP/0/A/5700/000, Step 2.1) Determine operating mode that existed at the time the event occurred prior to any protection system or operator action initiated in response of the event.
The operator enters determines that the plant was in Mode 1 at the start of the event.
Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A4 SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 3
(RP/0/A/5700/000, Step 2.2) IF the plant was in Mode 1-4 and a valid condition affects fission product barriers, THEN proceed to Enclosure 4.1 (Fission Product Barrier Matrix).
The operator reviews.1, and determines a Loss of Containment exists, based on 4.1.C.4, SG Secondary Side Release With Primary-to-Secondary Leakage.
The operator records 3 points for the loss of the Containment Barrier in Table on Page 2 of 5 of.1.
With a total of 3 points, the operator determines that a NOUE exists, based on 4.1.U.2, Loss of Containment.
The operator reviews Enclosures 4.2 through 4.7.
4 (RP/0/A/5700/000, Step 2.3) IF a General Emergency is NOT declared in Step 2.2, OR the condition does not affect fission product barriers, THEN review the listing of enclosures to determine if the event is applicable to one of the categories shown.
The operator reviews.4, and determines a Failure of Reactor Protection System Instrumentation to Complete or Initiate an Automatic Reactor Trip Once a Reactor Protection System Setpoint Has Been Exceeded and Manual Trip WAS NOT Successful.
Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A4 SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 5 (RP/0/A/5700/000, Step 2.4) Compare actual plant conditions to the Emergency Action Levels evaluated in 2.2 and/or 2.3, then declare the appropriate Emergency Class as indicated.
The operator determines that a SAE exists, based on 4.4.S.1, Failure of Reactor Protection System Instrumentation to Complete or Initiate an Automatic Reactor Trip Once a Reactor Protection System Setpoint Has Been Exceeded and Manual Trip WAS NOT Successful.
The operator records the event declaration time in Step 2.4.1.
Examiner Note: Record Time Critical Stop Time __________
Note that this time is also the Start Time for the 2nd Time Critical action of completing the pre-printed ENF 4.4.S.1.
6 (RP/0/A/5700/000, Step 2.4) Implement the applicable Emergency Response Procedure (RP) for that classification and continue with subsequent steps of this procedure.
Notification of Unusual Event RP/0/A/5700/001 Alert RP/0/A/5700/002 Site Area Emergency RP/0/A/5700/003 General Emergency RP/0/A/5700/004.
The operator proceeds to RP/0/A/5700/003, Immediate Actions.
7 (RP/0/A/5700/003, IA Step 2.1) Have an SRO make offsite notifications PER RP/0/B/5700/029 (Notifications to Offsite Agencies from the Control Room).
The operator proceeds to RP/0/A/5700/029, Immediate Actions.
Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION 2012 Admin - JPM A4 SRO NUREG 1021, Revision 9 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 8 (RP/0/A/5700/029, IA Step 2.2) For Initial Notifications, perform Enclosure 4.1 (Completion and Transmission of an Initial Notification Message).
The operator proceeds to.1 Step 1.
The operator completes the SAE ENF by performing Steps 1-2.13 of Enclosure 4.1 in accordance with the attached KEY (See Page 9 of this JPM).
The operator presents the completed ENF Form to the Emergency Coordinator.
NOTE: The critical nature of this action is that the form is completed within 15 minutes.
Terminating Cue:
Evaluation on this JPM is complete.
TIME CRITICAL STOP TIME:
Appendix C Page 8 of 10 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A4 SRO NUREG 1021, Revision 9 Job Performance Measure No.:
2012 Admin - JPM A4 SRO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF COMPLETION 2012 Admin - JPM A4 SRO NUREG 1021, Revision 9 KEY:
.1 Step #
Block How Completed 2.1.1 Drill/Actual Event Operator checks A (Drill) is already shaded in.
2.1.2 Message #
The operator enters 01 (or equivalent)
Note prior to Step 2.2 Notification Time Left Blank Note prior to Step 2.2 Notification Date Left Blank Note prior to Step 2.2 Authentication #
Left Blank 2.2 Initial/Follow-Up The operator checks A (Initial).
2.3.1 Site McGuire Nuclear Site is pre-recorded 2.3.2 Confirmation Phone #
(704) 875-6044 is pre-recorded 2.4.1 Emergency Classification Operator checks C (Site Area Emergency) is already shaded in.
2.4.2 EAL #
Operator checks 4.4.S.1 is already written in.
2.4.3 EAL Description Operator checks that the following statement is written in: The reactor control rods have failed to automatically or manually shut down the reactor. This condition, by itself, poses no immediate threat to public safety.
2.5.1 Protective Action Recommendations Operator checks None is shaded in.
2.6.1 Emergency Release The operator checks B (Is occurring) 2.7.3 Release Significance The operator checks D (Under Evaluation).
2.8 Event Prognosis The operator checks B (Stable).
2.9.1 Wind Direction The operator records 78.6 degrees, OR leaves Blank 2.9.2 Wind Speed The operator records 2 mph, OR leaves Blank 2.9.3 Precipitation The operator records None, OR leaves Blank 2.9.4 Stability Class Left Blank 2.10.1 Declaration/Termination Operator checks A (Declaration) is shaded in.
2.10.2 Time/Date The operator records the Time recorded in JPM Step 5, and todays date.
2.11 Affected Unit(s)
The operator checks U1 ONLY.
2.12 Unit Status The operator records that Unit 1 is at 0%
power, and shutdown at 0350, Today.
The operator records that Unit 2 is at 100% power.
2.13 Remarks Left Blank
Appendix C Form ES-C-1 JPM CUE SHEET NUREG 1021, Revision 9 Event Timeline Initial Conditions:
0300 Unit 1 and Unit 2 are in Mode 1 at 100% power.
0300 1EMF-33, COND AIR EJECT EXH HI RAD, enters TRIP 2 alarm condition.
0310 RP reports that surveys on the 1B Steam line are higher than the others.
0345 Chemistry has determined that the leakage into the 1B Steam generator is 136 GPD.
0348 The crew enters AP/1/A/5500/04 (Rapid Downpower) with the intent to lower power less than 50% by 0445.
0349 Upon load reduction the Main Turbine trips, however the reactor does NOT trip automatically.
0349 The OATC attempts to manually trip the reactor, however, the reactor does NOT trip manually.
0349 The OATC manually inserts the control rods.
0349 The CRS directs an NEO to trip the reactor locally.
0350 The crew enters EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) and immediately transitions to EP/1/A/5000/FR-S.1 (Response to Nuclear Power Generation/ATWS).
0350 The OATC reports that the controls rods indicate on the bottom, and that both reactor trip breakers are open.
0350 The dispatched NEO indicated that both reactor trip breakers have been opened locally.
0351 The crew continues onward in FR-S.1, all Critical Safety Function Status Trees are GREEN or YELLOW.
0351 The following conditions exist:
Wind direction is 78.6 degrees.
Wind Speed is 2 mph.
There is no precipitation.
RP is NOT available in the Control Room, and is still assessing the radiological conditions.
INITIATING CUE:
Classify the Event in accordance with RP/0/A/5700/000 (Classification of Emergency).
If more than one Emergency Action Level (EAL) has been exceeded, identify the EAL resulting in the Highest Emergency Classification.
Then, prepare a Nuclear Power Plant Emergency Notification Form for the event, and present to the Emergency Coordinator for approval.
This is a Time Critical JPM