ML13169A192
ML13169A192 | |
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: ML13169A192 (93) | |
Text
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A1a RO 2012 Admin - JPM A1a RO (REV_032812) NUREG 1021, Revision 9
Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:
Task
Title:
Calculate QPTR with an Inoperable JPM No.: 2012 Admin - JPM A1a Power Range Instrument RO K/A
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.
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.
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) 2012 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet 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)
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.
Time Critical Task: NO Validation Time: 25 minutes 2012 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION (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 four handouts listed.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1 (Step 12.14) The operator determines from initial conditions QPTR IF QPTR Alarm inoperable Alarm is inoperable, Unit 1 AND greater than 50% is at 100% power and all RTP, perform the following: PR channels are NOT operable.
(Step 12.14.1) If all Power Range (PR) channel inputs The operator recognizes to QPTR operable, 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 The operator proceeds to than 75% RTP, perform the Enclosure 13.5 (Calculation following: Sheet for Quadrant Power Tilt) Part B.
Calculate QPTR on Enclosure 13.5 (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.
3 (Enclosure 13.5 Part B) The operator enters the current Date and Time at Complete the Form the top of the form.
2012 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 4 (Enclosure 13.5 Part B) The operator identifies the Measured Current - From three operable Power NI cabinets current meter Range Instruments as PR-(located on respective PRB 42, PR-43 and PR-44 on Drawers). Ensure Detector Enclosure 13.5, Part B.
Milliamp Range Switches are in 0.5 position and The operator records the read 0-500 microamp scale. 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) The operator locates Calibration Current - From OP/1/A/6100/022, most recent calibration data Enclosure 4.3, Table 2.2, using 0 Incore Axial Offset Excore Currents and Current in Data Book, Table Voltages Correlated to 2.2 (IT for detector A, 100% Full Power at Various IB for detector B). 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 2012 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 6 (Enclosure 13.5 Part B) The operator correctly Relative Flux (RF) - Divide calculates the average RF line 1 by line 2 to calculate and records the in the Relative Flux (RF) for each Relative Flux (RF) row for upper (A) and lower (B) each of the six (8) detectors detector. 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) The operator records the Quadrant Power Tilts: RF of each of the three (3)
Calculate by dividing each A detectors and calculates upper relative flux by the the Avg RF of A Detectors average upper relative flux as follows:
and dividing each lower relative flux by the average (2.53+2.59+2.78)/3 = 2.63 lower relative flux.
Avg RF of A Detectors
- 8 (Enclosure 13.5 Part B) The operator records the Quadrant Power Tilts: RF of each of the three (3)
Calculate by dividing each B detectors and calculates upper relative flux by the the Avg RF of B Detectors average upper relative flux as follows:
and dividing each lower relative flux by the average (2.46+2.44+2.50)/3 = 2.47 lower relative flux.
Avg RF of B Detectors 2012 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 9 (Enclosure 13.5 Part B) The operator calculates the Quadrant Power Tilts: PR-42A Tilt as follows:
Calculate by dividing each upper relative flux by the 2.53/2.63 = 0.96 + .01 average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-42A Tilt
- 10 (Enclosure 13.5 Part B) The operator calculates the Quadrant Power Tilts: PR-42B Tilt as follows:
Calculate by dividing each upper relative flux by the 2.46/2.47 = 1.00 + .01 average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-42B Tilt
- 11 (Enclosure 13.5 Part B) The operator calculates the Quadrant Power Tilts: PR-43A Tilt as follows:
Calculate by dividing each upper relative flux by the 2.59/2.63 = 0.98 + .01 average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-43A Tilt
- 12 (Enclosure 13.5 Part B) The operator calculates the Quadrant Power Tilts: PR-43B Tilt as follows:
Calculate by dividing each upper relative flux by the 2.44/2.47 = 0.99 + .01 average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-43B Tilt 2012 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 13 (Enclosure 13.5 Part B) The operator calculates the Quadrant Power Tilts: PR-44A Tilt as follows:
Calculate by dividing each upper relative flux by the 2.78/2.63 = 1.06 + .01 average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-44A Tilt
- 14 (Enclosure 13.5 Part B) The operator calculates the Quadrant Power Tilts: PR-44B Tilt as follows:
Calculate by dividing each upper relative flux by the 2.50/2.47 = 1.01 + .01 average upper relative flux And records this value.
and dividing each lower relative flux by the average lower relative flux.
PR-44B Tilt
- 15 (Technical Specification The operator determines 3.2.4) The QPTR shall be that one quadrant is >1.02
< 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:
2012 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 9 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 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:
2012 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 10 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 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 PR-42B Tilt RFA = RF of PR-42A = 2.53 .96* RFB = RF of PR-42B = 2.46 1.00*
2.63 2.47 PR-43A Tilt PR-43B Tilt RFA = RF of PR-43A = 2.59 .98* RFB = RF of PR-43B = 2.44 .99*
2.63 2.47 PR-44A Tilt PR-44B Tilt RFA = RF of PR-44A = 2.78 1.06* RFB = RF of PR-44B = 2.50 1.01*
2.63 2.47
- + .01 2012 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET 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 NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET 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.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A1a SRO 2012 Admin - JPM A1a SRO (Rev_062012) NUREG 1021, Revision 9
Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:
Task
Title:
Determine Proper Shift Staffing JPM No.: 2012 Admin - JPM A1a SRO K/A
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.
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.
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.
2012 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet 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).
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.
Hold over personnel and/or call in additional personnel ONLY if the minimum staffing cannot be met.
Time Critical Task: NO Validation Time: 30 minutes 2012 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION (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- The operator evaluates
- 4) The operator compares Mark (OAC U1 RO) and the work history of the three determines:
employees with OT Work period of 11.75 concerns to the hours (.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> TOT) requirements of NSD 200. 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 />.
NOTE: Identification that
- Mark cannot report to work Mark cannot work is critical.
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 10.5 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.
2012 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 2 (OMP 5-8, Attachment 12.1, The operator observes the Step 1) Minimum Crew Work Schedule and assigns Composition: Operations Tim to position #1.
Shift Manager.
- 3 (Step 2) Minimum Crew The operator observes the Composition: Shift Work Schedule and holds Technical Advisor. over current STA (position
- 2) until replacement for Alex arrives.
- 4 (Step 3) Minimum Crew The operator observes the Composition: Control Room Work Schedule and assigns Supervisor. Eric to position #3.
- 5 (Step 4) Minimum Crew The operator observes the Composition: Off-Site Work Schedule and assigns Communicator. Randy to position #4.
- 6 (Step 5) Minimum Crew The operator observes the Composition: Plant SRO. Work Schedule and assigns Todd to position #5.
- 7 (Step 6) Minimum Crew The operator observes the Composition: Second Active Work Schedule and assigns SRO. Todd or Randy to position
- 6.
- 8 (Step 7) Minimum Crew The operator recognizes Composition: Reactor that Mark cannot be Operators. 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).
2012 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 9 (Step 8) Minimum Crew The operator observes the Composition: Non-Licensed Work Schedule and assigns Operators. 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 The operator observes the Composition: SLC Required Work Schedule and assigns Fire Brigade. 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).
2012 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 11 (Step 10) Minimum Crew The operator observes the Composition: Supplemental Work Schedule and assigns Fire Brigade. 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:
2012 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 8 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 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:
2012 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 9 of 12 Form ES-C-1 VERIFICATION OF COMPLETION KEY:
Shift Crew Position Name Required By
- 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
- 9. SLC Required Fire Brigade A. Leader (RO or SRO) 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:
1 Joe, Kevin, and Rick may fill any one of the RO positions.
2 Dwight, Chris and Wayne are interchangeable in the Fire Brigade Slots.
3 Doug and Monty are interchangeable.
2012 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET 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.
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.
Hold over personnel and/or call in additional personnel ONLY if the minimum staffing cannot be met.
NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET 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)
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)
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. N/A STAFF SRO/RO 2554) N/A SCHEDULED OFF Monday Fred, Steve Tuesday Same Wednesday Same NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET Work History of the three individuals who have arrived for work but expressed concerns regarding Overtime limitations:
Operator Monday Tuesday Wednesday Mark 0700 Relief arrives 1900 Reports to shift 0715 Turnover complete 0715 Relief arrives, but stands relieved plant transient delays 1915 Turnover complete turnover.
assumes duties ------------HOME------------ 0745 Turnover starts 1900 Reports to shift 0800 Turnover complete stands relieved 1930 Turnover complete 0800-0930 Attends CRIP assumes duties Team meeting.
HOME------------
1900 Reports to shift Owen 1915 Reports to shift 0800 Relief arrives, but 0745 Relief arrives goes home sick 1930 Turnover complete 0845 Alternate relief 0800 Turnover complete assumes duties arrives stands relieved 0900 Turnover complete stands relieved ------------HOME------------
HOME------------
1900 Reports to shift 1900 Reports to shift 1915 Turnover complete assumes duties Dennie 0700 Relief arrives 1915 Reports to shift 0730 Turnover complete 0745 Relief arrives stands relieved 1930 Turnover complete 0800 Turnover complete assumes duties ------------HOME------------ stands relieved 1730 Reports to shift for ------------HOME------------
scheduled Just In Time Training (JITT) 1815 Turnover starts 1830 Turnover complete 1900 Reports to shift assumes duties NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A1b RO 2012 Admin - JPM A1b RO (REV_032812) NUREG 1021, Revision 9
Appendix C Page 2 of 8 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:
Task
Title:
Calculate the Boric Acid Addition for JPM No.: 2012 Admin - JPM A1b a specified Rod Change RO K/A
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.
Initial Conditions: Unit #1 Reactor Power is at 100%, 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.
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 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 2012 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Page 3 of 8 Form ES-C-1 Job Performance Measure Worksheet 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)
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.
Time Critical Task: NO Validation Time: 15 minutes 2012 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION (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 Initial inserted steps integral rod worth reactivity worth =
using the 51-150 EFPD column of 153 pcm OP/1/A/6100/22, Enclosure 4.3, Table 6.3.3, IRW in Overlap, HFP, Equilibrium Xe.
- 2 Operator determines 210 Desired Rod height steps integral rod worth inserted reactivity using the 51-150 EFPD worth =
column of OP/1/A/6100/22, 15 pcm Enclosure 4.3, Table 6.3.3, IRW in Overlap, HFP, Equilibrium Xe.
- 3 Operator determines the Change in reactivity to change in reactivity be compensated due to required for the rod rod insertion =
insertion 15 pcm
-153 pcm
-138 pcm
- 4 Using OP/1/A/6100/22, Operator determines the Enclosure 4.3, Graph Differential Boron Worth 6.11 Differential Boron from the graph to be =
Worth (HFP, ARO, Eq -6.07 pcm/ppm Xe, Eq Sm, Unit 1 Cycle
- 21) determines the Differential Boron Worth for present conditions (125 EFPD) 2012 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 5 Using the Differential Operator determines the Boron Worth and the change in Boron Change in reactivity, Concentration to be =
determines the change in -138 /-6.07 pcm/ppm Boron Concentration
22.7 ppm 6 Operator determines Change in Boron
Boron Concentration 950 + 22.7 ppm required
= 972.7 ppm
- 7 Using OP/1/A/6100/22, Using Present Boron Enclosure 4.3 Section 5.1 Concentration 950 ppm Boron and Dilution and the Desired Boron Tables, determines the Concentration of 972.7 Boric Acid addition 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:
2012 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Page 6 of 8 Form ES-C-1 VERIFICATION OF COMPLETION 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:
2012 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION 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 2012 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions: Unit #1 Reactor Power is at 100%, 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.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A1b SRO 2012 Admin - JPM A1b SRO (Rev_032812) NUREG 1021, Revision 9
Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:
Task
Title:
Manual AFD Calculation JPM No.: 2012 Admin - JPM A1b SRO K/A
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.
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 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet 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 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), Step 12.10 for current plant conditions and verify that AFD is within the limits specified in the COLR.
Identify any Technical Specification LCOs and ACTION that is applicable.
Time Critical Task: NO Validation Time: 15 minutes 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION (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 The operator recognizes Monitor Alarm inoperable that the AFD Monitor is AND greater than or equal inoperable, and that present to 50% RTP, perform the power is greater than 50%
following: RTP.
(Step 12.10.1) IF MCB AFD The operator recognizes gauges operable..
that the MCB AFD gauges are inoperable and places an NA in this step.
2 (Step 12.10.2) IF MCB AFD The operator refers to gauges inoperable, perform PT/1/A/4600/021 A the following: Enclosure 13.2 Part B (Step 12.10.2.1) Check AFD by performing Enclosure 13.2 (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.
2012 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 3 (Notes prior to Enclosure The operator reads the 13.2 Part B) Notes and proceeds.
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) 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 4 (Enclosure 13.2 Part B, The operator obtains Column A) From most OP/1/A/6100/022, recent calibration data using Enclosure 4.3, Table 2.2 0 Incore Axial Offset and uses the Full Power current in Data Book, Table Detector Currents 2.2 (T for Detector A and (Microamps) Corresponding B for Detector B. 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, The operator, using the Column B) From NI information provided in the cabinets current meters initial conditions, records (located on respective PR A the following in Column B of and B Drawers). Ensure Enclosure 13.2 Part B:
Detector Milliamp range switches are in 0.5 PR-41A = 342 position and read from 0- PR-41B = 410 500 microamp scale.
Readings should be to PR-42A = 359 nearest microamp for PR-42B = 425 accuracy.
PR-43A = 341 PR-43B = 414 PR-44A = 333 PR-44B = 419 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6 (Enclosure 13.2 Part B, The operator divides Column C) Column B Column B by Column A for Measured Current divided each detector, and by Column A Axial Offset multiplies the quotient by Current for each detector 100, and then records the multiplied by 100. following in Column C of Enclosure 13.2 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, The operator subtracts Column D) Column C Detector B from Detector A Detector A minus Column C for each PR, and divides Detector B for each PR the remainder by 2, and channel divided by 2. 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 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 8 (Enclosure 13.2 Part B, The operator obtains Column E) M Factor from OP/1/A/6100/022, Data Book Table 2.2 AFD Enclosure 4.3, Table 2.2 Incore/Excore Ratios for and uses the AFD Quadrants 1-4. 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, The operator multiplies Column F) Column D Column D by Column E for multiplied by Column E will each PR and records the provide AFD value for each following in Column F of PR channel. Enclosure 13.2 Part B:
PR-41 = -17.48 PR-42 = -18.45 PR-43 = -16.85 PR-44 = -19.87
- 10 Verify calculated AFD is The operator compares the within limits specified in calculated AFD values to COLR. 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%)
2012 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 11 Identify any Technical The operator identifies that Specification LCOs and LCO 3.2.3 Axial Flux ACTION that is applicable. 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:
2012 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 10 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 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:
2012 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 11 of 12 Form ES-C-1 VERIFICATION OF COMPLETION KEY:
(A) (B) (C) (D) (E) (F) 0% Axial Measured (Col B/Col A (Det A-Det B) M Factor AFD Detectors Offset Currents x 100) 2 (Col D x Col E)
Currents 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 2012 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET 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), Step 12.10 for current plant conditions and verify that AFD is within the limits specified in the COLR.
Identify any Technical Specification LCOs and ACTION that is applicable.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A2 RO 2012 Admin - JPM A2 RO (REV_032812) NUREG 1021, Revision 9
Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:
Task
Title:
Perform a Manual NC Leakage JPM No.: 2012 Admin - JPM A2 Calculation RO K/A
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.
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)
Enclosure 13.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) has been completed through Step 1.10.
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 2012 Admin - JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet 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.
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 2012 Admin - JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 4 of 12 Form ES-C-1 Job Performance Measure Worksheet Initiating Cue: Using Enclosure 13.2 (NC Leakage Determination Using Manual Calculations), AND the attached Datasheet, complete the NC System Leakage Calculation, by performing Steps 1.11 and 1.12.
Indicate whether or not a Technical Specification has been exceeded.
Time Critical Task: NO Validation Time: 25 minutes 2012 Admin - JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION (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 The operator transposes 1.11.1 through 6, 8 through raw data from the Data 13, 22, 26 and 1.12.1) Sheet provided.
Record raw data.
2 (Enclosure 13.2, Step The operator calculates the 1.11.14) Calculate change change in NC System Tave in NC System Tave: to be -0.2oF, and records.
3 (Enclosure 13.2, Step The operator calculates the 1.11.15) Calculate VCT VCT Leakage Rate to be Leakage Rate: 5.02 gpm, and records.
4 (Enclosure 13.2, Step The operator calculates the 1.11.16) Calculate PZR PZR Leakage Rate to be -
Leakage Rate: 0.017 gpm, and records.
5 (Enclosure 13.2, Step The operator calculates the 1.11.17) Calculate Total Total Leakage to be 5.003 Leakage: gpm, and records.
2012 Admin - JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6 (Enclosure 13.2, Step The operator uses 1.11.18) Using Enclosure Enclosure 13.4 and an 13.4 (PRT Volume), record initial PRT Level of 76.0 %,
the following: and determines that initial PRT Volume is 10636.1 Initial PRT Volume gal, and records.
Final PRT Volume The operator uses Enclosure 13.4 and interpolates a PRT Volume for 77.0% to be 10770.4 gal, and records.
7 (Enclosure 13.2, Step The operator calculates the 1.11.19) Calculate PRT PRT Leakage Rate to be Leakage Rate: 2.13 gpm, and records.
8 (Enclosure 13.2, Step 1.11. The operator uses
- 20) Using Enclosure 13.3 Enclosure 13.3 and an (NCDT Volume), record the initial NCDT Level of 44.0%,
following: and determines that initial Initial NCDT Volume NCDT Volume is 155.0 gal, and records.
Final NCDT Volume The operator uses Enclosure 13.3 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 The operator calculates the 1.11.21) Calculate NCDT NCDT Leakage Rate to be Leakage Rate: .29 gpm, and records.
10 (Enclosure 13.2, Step The operator calculates the 1.11.23) Calculate Total Total Background Leakage Background Leakage: to be 0 gpm, and records.
2012 Admin - JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 11 (Enclosure 13.2, Step The operator calculates the 1.11.24) Calculate Identified Identified Leakage to be Leakage: 2.42 (+/-10%) gpm, and records.
- 12 (Enclosure 13.2, Step The operator calculates the 1.11.25) Calculate Unidentified Leakage to be Unidentified Leakage: 2.58 (+/-10%) gpm, and records.
- 13 (Enclosure 13.2, Step The operator calculates the 1.11.26) Determine Total Total NC Pumps #1 Seal NC Pump #1 Seal Leakoff: Leakoff to be 14.5 (+/-10%)
gpm, and records.
- 14 (Enclosure 13.2, Step The operator calculates the 1.11.27) Calculate Total Total Accumulative Accumulative Leakage: Leakage to be 19.50
(+/-10%) gpm, and records.
15 (Enclosure 13.2) Calculated The operator places their By/ Date/Time: name in the Calculated by BLOCK, and signs.
The operator enters the Date and Time.
2012 Admin - JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 16 Technical Specification The operator returns the LCO 3.4.13: completed Enclosure 13.2 and reports that LCO 3.4.13 RCS operational LEAKAGE has been exceeded shall be limited to: because there is greater than 1 gpm unidentified
- a. No pressure boundary LEAKAGE.
LEAKAGE;
- b. 1 gpm unidentified Examiner NOTE:
LEAKAGE; See KEY on Page 10 of
- c. 10 gpm identified this JPM.
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.
Terminating Cue: Evaluation on this JPM is complete.
STOP TIME:
2012 Admin - JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 9 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 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:
2012 Admin - JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 10 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 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.
2012 Admin - JPM A2 RO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET 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 NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET 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)
Enclosure 13.2 (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, by performing Steps 1.11 and 1.12.
Indicate whether or not a Technical Specification has been exceeded.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A2 SRO 2012 Admin - JPM A2 SRO (Rev_032812) NUREG 1021, Revision 9
Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:
Task
Title:
Perform/Review a Manual NC JPM No.: 2012 Admin - JPM A2 Leakage Calculation SRO K/A
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.
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)
Enclosure 13.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) has been completed through Step 1.10.
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 2012 Admin - JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet 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.
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 2012 Admin - JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 4 of 12 Form ES-C-1 Job Performance Measure Worksheet Initiating Cue: Using Enclosure 13.2 (NC Leakage Determination Using Manual Calculations), AND the attached Datasheet, complete the NC System Leakage Calculation, by performing Steps 1.11 and 1.12.
Identify any Technical Specifications impacted and any required ACTION.
Time Critical Task: NO Validation Time: 25 minutes 2012 Admin - JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION (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 The operator transposes 1.11.1 through 6, 8 through raw data from the Data 13, 22, 26 and 1.11.1) Sheet provided.
Record raw data.
2 (Enclosure 13.2, Step The operator calculates the 1.11.14) Calculate change change in NC System Tave in NC System Tave: to be -0.2oF, and records.
3 (Enclosure 13.2, Step The operator calculates the 1.11.15) Calculate VCT VCT Leakage Rate to be Leakage Rate: 5.02 gpm, and records.
4 (Enclosure 13.2, Step The operator calculates the 1.11.16) Calculate PZR PZR Leakage Rate to be -
Leakage Rate: 0.017 gpm, and records.
5 (Enclosure 13.2, Step The operator calculates the 1.11.17) Calculate Total Total Leakage to be 5.003 Leakage: gpm, and records.
2012 Admin - JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6 (Enclosure 13.2, Step The operator uses 1.11.18) Using Enclosure Enclosure 13.4 and an 13.4 (PRT Volume), record initial PRT Level of 76.0 %,
the following: and determines that initial PRT Volume is 10636.1 Initial PRT Volume gal, and records.
Final PRT Volume The operator uses Enclosure 13.4 and interpolates a PRT Volume for 77.0% to be 10770.4 gal, and records.
7 (Enclosure 13.2, Step The operator calculates the 1.11.19) Calculate PRT PRT Leakage Rate to be Leakage Rate: 2.13 gpm, and records.
8 (Enclosure 13.2, Step 1.11. The operator uses
- 20) Using Enclosure 13.3 Enclosure 13.3 and an (NCDT Volume), record the initial NCDT Level of 44.0%,
following: and determines that initial Initial NCDT Volume NCDT Volume is 155.0 gal, and records.
Final NCDT Volume The operator uses Enclosure 13.3 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 The operator calculates the 1.11.21) Calculate NCDT NCDT Leakage Rate to be Leakage Rate: .29 gpm, and records.
10 (Enclosure 13.2, Step The operator calculates the 1.11.23) Calculate Total Total Background Leakage Background Leakage: to be 0 gpm, and records.
2012 Admin - JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 11 (Enclosure 13.2, Step The operator calculates the 1.11.24) Calculate Identified Identified Leakage to be Leakage: 2.42 (+/-10%) gpm, and records.
- 12 (Enclosure 13.2, Step The operator calculates the 1.11.25) Calculate Unidentified Leakage to be Unidentified Leakage: 2.58 (+/-10%) gpm, and records.
- 13 (Enclosure 13.2, Step The operator calculates the 1.11.26) Determine Total Total NC Pumps #1 Seal NC Pump #1 Seal Leakoff: Leakoff to be 14.5 (+/-10%)
gpm, and records.
- 14 (Enclosure 13.2, Step The operator calculates the 1.11.27) Calculate Total Total Accumulative Accumulative Leakage: Leakage to be 19.50
(+/-10%) gpm, and records.
15 (Enclosure 13.2) Calculated The operator places their By/ Date/Time: name in the Calculated by BLOCK, and signs.
The operator enters the Date and Time.
2012 Admin - JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 16 Technical Specification The operator returns the LCO 3.4.13: completed Enclosure 13.2 and reports that LCO 3.4.13 RCS operational LEAKAGE has been exceeded shall be limited to: because there is greater than 1 gpm unidentified
- a. No pressure boundary LEAKAGE.
LEAKAGE;
- b. 1 gpm unidentified The operator identifies that LEAKAGE; CONDITION A is met, RCS Operational LEAKAGE not
- c. 10 gpm identified within limits for reasons LEAKAGE; other than pressure boundary LEAKAGE or
- d. 389 gallons per day primary to secondary total primary to LEAKAGE; AND that the secondary LEAKAGE REQUIRED ACTION is to through all steam Reduce LEAKAGE to within generators (SGs); and limits, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- e. 135 gallons per day primary to secondary LEAKAGE through any one steam Examiner NOTE:
generator (SG).
See KEY on Page 10 of this JPM.
APPLICABILITY:
MODES 1, 2, 3, and 4.
Terminating Cue: Evaluation on this JPM is complete.
STOP TIME:
2012 Admin - JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 9 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 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:
2012 Admin - JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 10 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 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 />.
2012 Admin - JPM A2 SRO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET 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 NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET 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)
Enclosure 13.2 (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, by performing Steps 1.11 and 1.12.
Identify any Technical Specifications impacted and any required ACTION.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A3 RO 2012 Admin - JPM A3 RO (REV_032812) NUREG 1021, Revision 9
Appendix C Page 2 of 9 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:
Task
Title:
Predict Radiation Levels While JPM No.: 2012 Admin - JPM A3 Responding to a Damaged Spent RO Fuel Pool K/A
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.
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.
2012 Admin - JPM A3 RO NUREG 1021, Revision 9
Appendix C Page 3 of 9 Form ES-C-1 Job Performance Measure Worksheet 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: Enclosure 13 (Loss of Spent Fuel Pool Cooling or Level) of AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level)
McGuire Selected Licensee Commitments 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.
Time Critical Task: NO Validation Time: 15 minutes 2012 Admin - JPM A3 RO NUREG 1021, Revision 9
Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION (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 The operator recognizes expected radiation levels in that the present level of the Spent Fuel Pool area in 1 Spent Fuel Pool hour. 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 Enclosure 13, 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].
2012 Admin - JPM A3 RO NUREG 1021, Revision 9
Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 2 (Enclosure 13) Determine The operator recognizes expected radiation levels in that the Spent Fuel Pool is Spent Fuel Pool area in 2 lowering at a rate of 4 feet hours. per hour, and will be approximately 15 feet above the Spent Fuel Pool in two hours.
The Operator uses Enclosure 13, 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 The operator recognizes expected radiation levels in that the Spent Fuel Pool is Spent Fuel Pool area in 3 lowering at a rate of 4 feet hours. per hour, and will be approximately 11 feet above the Spent Fuel Pool in three hours.
The Operator uses Enclosure 13, 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].
2012 Admin - JPM A3 RO NUREG 1021, Revision 9
Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 4 (Enclosure 13) Determine The operator recognizes expected radiation levels in that the Spent Fuel Pool is Spent Fuel Pool area in 4 lowering at a rate of 4 feet hours. per hour, and will be approximately 7 feet above the Spent Fuel Pool in four hours.
The Operator uses Enclosure 13, 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:
2012 Admin - JPM A3 RO NUREG 1021, Revision 9
Appendix C Page 7 of 9 Form ES-C-1 VERIFICATION OF COMPLETION 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:
2012 Admin - JPM A3 RO NUREG 1021, Revision 9
Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION 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) 2012 Admin - JPM A3 RO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET 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.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A3 SRO 2012 Admin - JPM A3 SRO (Rev_032812) NUREG 1021, Revision 9
Appendix C Page 2 of 9 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:
Task
Title:
Calculate Spent Fuel Pool Boiloff JPM No.: 2012 Admin - JPM A3 rate and predict when Spent Fuel SRO Pool Radiation levels will exceed 1Rem/Hour K/A
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.
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.
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.
2012 Admin - JPM A3 SRO NUREG 1021, Revision 9
Appendix C Page 3 of 9 Form ES-C-1 Job Performance Measure Worksheet 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: Enclosure 5 (Spent Fuel Pool Boiloff rate) of AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level)
Enclosure 13 (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 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.
Time Critical Task: NO Validation Time: 15 minutes 2012 Admin - JPM A3 SRO NUREG 1021, Revision 9
Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION (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 The operator reads the Step 1) The following step Note and proceeds.
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.
2 (Step 1) Determine "Time The operator recognizes After Shutdown" as follows: that this Step is NA and proceeds to Step 1.a.2.
(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,..
- 3 (Step 1.a.2) IF less than The operator recognizes 193 fuel assemblies are that Unit 1 was shut down 9 currently in the reactor, days ago (Initial THEN perform the Conditions), and proceeds following: to Step 2.
Use number of days since reactor was shutdown as "Time After Shutdown".
Observe Notes prior to Step 2 and GO TO Step 2.
2012 Admin - JPM A3 SRO NUREG 1021, Revision 9
Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 4 (Notes prior to Step 2) The operator reads the Notes and proceeds.
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).
- 5 (Step 2) IF less than 193 The operator recognizes fuel assemblies are that the core has been currently in the reactor, offloaded, and that the THEN use the following following Table applies.
tables to estimate Spent The operator locates 9 days Fuel Pool boiloff rate: since shutdown and determines the boiloff rate of 68 gpm and a level decrease rate of 4.4 inches/hour.
2012 Admin - JPM A3 SRO NUREG 1021, Revision 9
Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 6 (Enclosure 13) REFER TO The Operator uses the table below to Enclosure 13, and determine estimated Spent determines that an Fuel Pool radiation levels. 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:
2012 Admin - JPM A3 SRO NUREG 1021, Revision 9
Appendix C Page 7 of 9 Form ES-C-1 VERIFICATION OF COMPLETION 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:
2012 Admin - JPM A3 SRO NUREG 1021, Revision 9
Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION 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.
2012 Admin - JPM A3 SRO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET 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.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A4 SRO 2012 Admin - JPM A4 SRO (Rev_061512) NUREG 1021, Revision 9
Appendix C Page 2 of 7 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:
Task
Title:
Classify an Emergency Event JPM No.: 2012 Admin - JPM A4 SRO K/A
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.
Initial Conditions: A plant event is in progress on Unit 1.
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.
Required Materials: Blank Copies of RP/0/A/5700/000, Enclosure 4.1, Fission Product Barrier Matrix.
General
References:
RP/0/A/5700/000 (Classification of Emergency) Rev 18 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 2012 Admin - JPM A4 SRO NUREG 1021, Revision 9
Appendix C Page 3 of 7 Form ES-C-1 Job Performance Measure Worksheet Handouts: RP/0/A/5700/000 (Classification of Emergency)
McGuire Technical Specifications Initiating Cue: Classify the Event in accordance with RP/0/A/5700/000 (Classification of Emergency).
Time Critical Task: YES - 15 minute Validation Time: 15 minutes 2012 Admin - JPM A4 SRO NUREG 1021, Revision 9
Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)
Provide Candidate with Last Page of this JPM and the required handouts.
START TIME:
1 (OMP 4-3, Steps The operator enters 7.20.1/7.20.1.1) OSM RP/0/A/5700/000,Step 2.1.
Responsibilities Assume role of Emergency Coordinator upon activation of the Emergency Plan until properly relieved by the Station Manager.
2 (RP/0/A/5700/000, Steps The operator enters 2.1) Determine operating determines that the plant mode that existed at the was in Mode 1 at the start time the event occurred of the event.
prior to any protection system or operator action initiated in response of the event.
3 (RP/0/A/5700/000, Steps The operator reviews 2.2) IF the plant was in Enclosure 4.1, and Mode 1-4 and a valid determines a Loss of condition affects fission Containment exists, based product barriers, THEN on 4.1.C.4, SG Secondary proceed to Enclosure 4.1 Side Release With Primary-(Fission Product Barrier to-Secondary Leakage.
Matrix).
The operator records 3 points for the loss of the Containment Barrier in Table on Page 2 of 5 of Enclosure 4.1.
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.
2012 Admin - JPM A4 SRO NUREG 1021, Revision 9
Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION 4 RP/0/A/5700/000, Steps The operator reviews 2.3) IF a General Enclosure 4.4, and Emergency is NOT determines a Failure of declared in Step 2.2, OR Reactor Protection System the condition does not affect Instrumentation to fission product barriers, Complete or Initiate an THEN review the listing of Automatic Reactor Trip enclosures to determine if Once a Reactor Protection the event is applicable to System Setpoint Has Been one of the categories Exceeded and Manual Trip shown. WAS NOT Successful.
- 5 RP/0/A/5700/000, Steps The operator determines 2.4) Compare actual plant that a SAE exists, based on conditions to the 4.4.S.1, Loss of Emergency Action Levels Containment.
evaluated in 2.2 and/or 2.3, then declare the appropriate Emergency Class as indicated.
Terminating Cue: Evaluation on this JPM is complete.
TIME CRITICAL STOP TIME:
2012 Admin - JPM A4 SRO NUREG 1021, Revision 9
Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION 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:
2012 Admin - JPM A4 SRO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET 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.
INITIATING CUE: Classify the Event in accordance with RP/0/A/5700/000 (Classification of Emergency).
NOTE: If more than one Emergency Action Level(EAL) has been exceeded, identify the EAL resulting in the Highest Emergency Classification.
This is a Time Critical JPM Classification: ____________ EAL #: ________________________
NUREG 1021, Revision 9