ML15203B019
| ML15203B019 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/22/2015 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| Download: ML15203B019 (90) | |
Text
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A1a RO 2015 Admin - JPM A1a RO (REV_030915)
NUREG 1021, Revision 9
Appendix C Page 2 of 11 Form ES-C-1 Job Performance Measure Worksheet Facility:
McGuire Task No.:
Task
Title:
Perform an Estimated Critical Boron Concentration JPM No.:
Reference:
2.1.37 (4.3)
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 1-9.
Initial Conditions:
Unit 1 startup in progress per OP/1/A/6100/001 (Controlling Procedure for Unit Startup).
All steps are complete up to determining the desired estimated critical rod height.
Performance of the estimated critical rod height determination has resulted in the need to perform Enclose 4.1 (Estimated Critical Boron Concentration) of OP/0/A/6100/006 (Reactivity Balance Calculation).
The Unit tripped from 30% power, 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> ago.
The following Cycle 23 conditions exist:
EFPD = 125 NC Boron = 1863 PPM Xenon Worth = 0 PCM Samarium Difference = - 150 PCM It is intended to pull rods to criticality with criticality achieved in approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The desired critical rod position is Bank C at 100 Steps.
The OAC and REACT Program are unavailable.
2015 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 3 of 11 Form ES-C-1 Job Performance Measure Worksheet Initiating Cue:
The CRS has directed you to perform an Estimated Critical Boron Concentration per Enclosure 4.1 (Estimated Critical Boron Concentration) of OP/0/A/6100/006 (Reactivity Balance Calculation).
Task Standard:
The operator determines that the Measured Critical Boron is 1810.5 PPM+/-1% (See attached KEY).
Required Materials:
Calculator General
References:
OP/1/A/6100/001 (Controlling Procedure for Unit Startup), Rev 185 OP/0/A/6100/006 (Reactivity Balance Calculation), Rev 74 OP/1/A/6100/022 (Unit 1 Data Book - Cycle 23), Rev 480 MCEI-0400-261 (Unit 1 Cycle 23 Core Operating Limits Report), Rev 0 AD-OP-ALL-0203 (Reactivity Management), Rev 0 Handouts:
Handout 1: OP/0/A/6100/006 (Reactivity Balance Calculation) Enclosure 4.1 (Estimated Critical Boron Concentration)
Handout 2: OP/0/A/6100/006 (Reactivity Balance Calculation) Enclosure 4.8 (Fission Product Correction Calculation)
Handout 3: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.7, Shutdown Fission Product Correction Handout 4: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Graph 6.1, Critical Boron Concentration HZP, ARO, NO XENON, EQ Sm.
Handout 5: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Graph 6.8, Differential Boron Worth, HZP, ARO, NO XENON, EQ Sm.
Handout 6: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.9, Xenon and Samarium Worths.
Handout 7: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.3.A, Integral Rod Worth in Overlap, HZP, NO XENON.
Handout 8: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.3.B, Integral Rod Worth in Overlap, HZP, PEAK XENON.
Handout 9: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Graph 1.2, Control Rod Insertion Limit as a Function of Power.
Time Critical Task:
NO Validation Time:
20 minutes NOTE:
An Answer KEY is provided as a separate document.
2015 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 4 of 11 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 1-9.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1
(Step 3.1) All curves/tables used in this procedure are found in P/1(2)/A/6100/022 (Unit One (Two) Data Book). These procedures will be referred to as the "Data Book."
The operator reads the Note and proceeds.
2 (Step 3.1) Record the following:
(Step 3.1.1) Unit ___
Cycle ___
The operator records Unit 1 and Cycle 23, and proceeds.
3 (Step 3.1) Record the following:
(Step 3.1.2) Date/Time of Shutdown _____/_____
The operator records Date/Time (70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> ago) from current Date/Time.
4 (Step 3.1) Record the following:
(Step 3.1.3) Anticipated Date/Time of Criticality
_____/_____
The operator records today's date and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from the time calculation is started as the time of criticality.
5 (Step 3.1) Record the following:
(Step 3.1.4) Burnup:
_____ EFPD (P1457)
The operator records 125 EFPD.
2015 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6
(Step 3.1) Record the following:
(Step 3.1.5) NC System Effective Boron concentration:
(Step 3.1.5.1) IF OAC is unavailable, record the current NC Boron Concentration:
(Step 3.1.5.2) IF OAC is available.
(Step 3.1.5.3) Record the Effective Boron Concentration: (Step 3.1.5.1 or Step 3.1.5.2C) =
The operator recognizes from initial conditions that OAC is unavailable and records 1863 in Step 3.1.5.1.
The operator places NA in Step 3.1.5.2.
The operator records 1863 in Step 3.1.5.3.
7 (Step 3.1) Record the following:
(Step 3.1.6) Desired critical rod position: Bank
____ Steps W/D.
The operator recognizes from initial conditions that the desired critical rod position is Bank C at 100 Steps and records Bank C, 100 Step W/D in Step 3.1.6.
8 (Step 3.1) Record the following:
(Step 3.1.7) Xenon worth at anticipated time of criticality (from OAC program Xenon Samarium
- XESM or REACT program).
The operator records 0 from initial conditions.
2015 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 9
(Step 3.1) Record the following:
(Step 3.1.8) IF burnup from step 3.1.4 is > 0 EFPD, record the difference between equilibrium and present samarium worth (P1475, OAC Program Xenon Samarium-XESM, or REACT program). {MCEI-0400-150}
The operator recognizes that burnup is > 0 EFPD and records -150 from initial conditions.
- 10 (Step 3.1) Record the following:
(Step 3.1.9) IF burnup from step 3.1.4 is > 12 EFPD, perform Enclosure 4.8 to determine the fission product correction.
The operator recognizes that burnup is > 12 EFPD and proceeds to.8 (Handout 2).
11 (Enclosure 4.8, Notes prior to Step 3.1) All curves/tables used in this procedure are found in OP/1(2)/A/6100/022 (Unit One (Two) Data Book).
These procedures will be referred to as the "Data Book."
Number of hours shutdown is the difference in time between the time the reactor went subcritical and the expected time of criticality.
The operator reads the Notes, and proceeds.
2015 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 12 (Step 3.1) Shutdown Fission Product Correction Calculation:
(Step 3.1.1) IF Unit operated > 3 EFPD from previous shutdown to current shutdown:
(Step 3.1.1.1) Use Data Book Table 6.7 to determine the shutdown fission product correction:
(Step 3.1.1.2) Number of hours shutdown (Step 3.1.1.3) Shutdown Fission Product Correction:
The operator uses Table 6.7 (Handout 3) and using 71 hours8.217593e-4 days <br />0.0197 hours <br />1.173942e-4 weeks <br />2.70155e-5 months <br /> as the number of hours shutdown, determines that the Shutdown Fission Product Correction is 35 PPM; and records this on Step 3.1.9 of Enclosure 4.1.
13 (Enclosure 4.1, Step 3.2)
IF desired, perform automated calculations using REACT (Reactivity Balance - ECB module)..
The operator recognizes from the initial conditions that the REACT Program is NOT available, and places NA in Step 3.2.
- 14 (Step 3.3) Manual Calculations:
(Step 3.3.1) Boron Concentration:
(Step 3.3.1.1) Determine the all rods out (ARO), hot zero power (HZP), no xenon, equilibrium samarium boron concentration for present burnup from Step 3.1.4.
(from Data Book Graph 6.1)
(Step 3.3.1.2) Record value in Table 4.1 Line A The operator uses Graph 6.1 (Handout 4) and determines that the all rods out (ARO), hot zero power (HZP), no xenon, equilibrium samarium boron concentration for 125 EFPD is 1985 PPMB.
The operator records 1985 on Line A of Table 4.1.
2015 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 15 (Step 3.3) Manual Calculations:
(Step 3.3.2) No xenon rod worth:
(Step 3.3.2.1) Determine the integral rod worth at HZP, no xenon from step 3.1.6 (Data Book Table 6.3.A).
(Step 3.3.2.2) Record value in Table 4.1 Line B.
The operator uses Table 6.3.A (Handout 7) and determines that the integral rod worth at HZP, no xenon for 125 EFPD with Bank C withdrawn to 100 Steps is 1178 PCM.
The operator records1178 on Line B of Table 4.1.
- 16 (Step 3.3) Manual Calculations:
(Step 3.3.3) Peak xenon rod worth:
(Step 3.3.3.1) Determine the integral rod worth at HZP, peak xenon for step 3.1.6 (Data Book Table 6.3.B).
(Step 3.3.3.2) Record value in Table 4.1 Line C.
The operator uses Table 6.3.B (Handout 8) and determines that the integral rod worth at HZP, peak xenon for 125 EFPD with Bank C withdrawn to 100 Steps is 1274 PCM.
The operator records1274 on Line C of Table 4.1.
- 17 (Step 3.3) Manual Calculations:
(Step 3.3.4) Differential Boron Worth:
(Step 3.3.4.1) Determine the ARO differential boron worth for present burnup from step 3.1.4 (Data Book Graph 6.8).
(Step 3.3.4.2) Record value in Table 4.1 Line D The operator uses Graph 6.8 (Handout 5) and determines that ARO differential boron worth for 125 EFPD is -6.34 PCM/PPMB.
The operator records
-6.34 on Line D of Table 4.1.
2015 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 9 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 18 (Step 3.3) Manual Calculations:
(Step 3.3.5) Peak Xenon Worth (Step 3.3.5.1) Determine peak xenon worth for present burnup from step 3.1.4 (Data Book Table 6.9).
(Step 3.3.5.2) Record value in Table 4.1 Line E.
The operator uses Table 6.9 (Handout 6) and determines that peak xenon worth for 125 EFPD is 3887 pcm.
The operator records 3887 on Line E of Table 4.1.
19 (Step 3.3) Manual Calculations:
(Step 3.3.6) Calculations:
(Step 3.3.6.1) Record values from Steps 3.1.7 -
3.1.9 in Table 4.1 The operator records 0 on Line F of Table 4.1.
The operator records -
150 on Line G of Table 4.1.
The operator records 35 on Line H of Table 4.1.
- 20 (Step 3.3) Manual Calculations:
(Step 3.3.6) Calculations:
(Step 3.3.6.2) Complete Table 4.1, recording 0 for any N/A'd Reference Steps.
The operator performs the calculations required of Table 4.1 and determines that the Measured Critical Boron is 1810.5 PPM+/-1% (See attached KEY).
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2015 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2015 Admin - JPM A1a RO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2015 Admin - JPM A1a RO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions:
Unit 1 startup in progress per OP/1/A/6100/001 (Controlling Procedure for Unit Startup).
All steps are complete up to determining the desired estimated critical rod height.
Performance of the estimated critical rod height determination has resulted in the need to perform Enclose 4.1 (Estimated Critical Boron Concentration) of OP/0/A/6100/006 (Reactivity Balance Calculation).
The Unit tripped from 30% power, 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> ago.
The following Cycle 23 conditions exist:
EFPD = 125 NC Boron = 1863 PPM Xenon Worth = 0 PCM Samarium Difference = - 150 PCM It is intended to pull rods to criticality with criticality achieved in approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The desired critical rod position is Bank C at 100 Steps.
The OAC and REACT Program are unavailable.
INITIATING CUE:
The CRS has directed you to perform an Estimated Critical Boron Concentration per Enclosure 4.1 (Estimated Critical Boron Concentration) of OP/0/A/6100/006 (Reactivity Balance Calculation).
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A1a SRO 2015 Admin - JPM A1a SRO (REV_030915)
NUREG 1021, Revision 9
Appendix C Page 2 of 18 Form ES-C-1 Job Performance Measure Worksheet Facility:
McGuire Task No.:
Task
Title:
Reference:
2.1.37 (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 Initial Conditions/Cue (Last Page of this JPM), and Handouts 1-
- 10.
Initial Conditions:
Unit 1 startup in progress per OP/1/A/6100/001 (Controlling Procedure for Unit Startup).
All steps are complete up to determining the desired estimated critical rod height.
The Unit tripped from 30% power, 143 hours0.00166 days <br />0.0397 hours <br />2.364418e-4 weeks <br />5.44115e-5 months <br /> ago.
The following Cycle 23 conditions exist:
EFPD = 200 NC Boron = 1694 PPM Xenon Worth = 0 Samarium Difference = -150 PCM It is intended to pull rods to criticality with criticality achieved in approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Reactor Engineer has been contacted earlier today and has reported that there have been no unusual trends on ECPs.
The OAC and REACT Program are unavailable.
2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 3 of 18 Form ES-C-1 Job Performance Measure Worksheet Initiating Cue:
The CRS has directed you to perform an ECP per Enclosure 4.2 (Estimated Critical Rod Position (ECP)) of OP/0/A/6100/006 (Reactivity Balance Calculation).
Task Standard:
The Actual Estimated Critical Rod Position Bank for No and Peak Xenon at time of Criticality agrees with the attached KEY.
Required Materials:
Calculator General
References:
OP/1/A/6100/003 (Controlling Procedure for Unit Operation), Rev 194 OP/0/A/6100/006 (Reactivity Balance Calculation), Rev 74 OP/1/A/6100/022 (Unit 1 Data Book - Cycle 23), Rev 480 MCEI-0400-261 (Unit 1 Cycle 23 Core Operating Limits Report), Rev 0 AD-OP-ALL-0203 (Reactivity Management), Rev 0 Handouts:
Handout 1: OP/0/A/6100/006 (Reactivity Balance Calculation) Enclosure 4.2 (Estimated Critical Rod Position (ECP)
Handout 2: OP/0/A/6100/006 (Reactivity Balance Calculation) Enclosure 4.8 (Fission Product Correction Calculation)
Handout 3: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.7, Shutdown Fission Product Correction Handout 4: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Graph 6.1, Critical Boron Concentration HZP, ARO, NO XENON, EQ Sm.
Handout 5: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Graph 6.8, Differential Boron Worth, HZP, ARO, NO XENON, EQ Sm.
Handout 6: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.9, Xenon and Samarium Worths.
Handout 7: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.3.A, Integral Rod Worth in Overlap, HZP, NO XENON.
Handout 8: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 6.3.B, Integral Rod Worth in Overlap, HZP, PEAK XENON.
Handout 9: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Graph 1.2, Control Rod Insertion Limit as a Function of Power.
Handout 10: OP/1/A/6100/022 (Unit 1 Data Book), Enclosure 4.3, Table 2.8, Rod Withdrawal Limits.
Time Critical Task:
NO Validation Time:
40 minutes 2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 4 of 18 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-
- 10.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1
(Note prior to Step 3.1) All curves/tables used in this procedure are found in OP/1(2)/A/6100/022 (Unit One (Two) Core Data Book). These procedures will be referred to as the Data Book.
The operator reads the Note and proceeds.
2 (Step 3.1) Record the following:
(Step 3.1.1)
Unit_____ Cycle_____
The operator records Unit 1.
The operator records Cycle 23.
3 (Step 3.1.2) Recent trends on ECP.
Reactor Engineer contacted ____
Date______
The operator recognizes that Chad Adams has been contacted.
The operator records RE name (RE) and todays date.
4 (Step 3.1.3) Date/Time of Shutdown.
The operator records Date/Time (143 hours0.00166 days <br />0.0397 hours <br />2.364418e-4 weeks <br />5.44115e-5 months <br /> ago) from current Date/Time.
2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 5 of 18 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 5
(Step 3.1.4) Anticipated Date/Time of Criticality
_________/_________
The operator records today's date and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from the time calculation is started as the time of criticality.
6 (Step 3.1.5) Burnup:
(P1457)
The operator records 200 EFPD.
7 (Step 3.1.6) NC System Boron Concentration:
(Step 3.1.6.1) If pulling rods to Criticality:
(Step 3.1.6.1A) If OAC is unavailable, record the current NC System boron concentration.
OR (Step 3.1.6.1B) If OAC is available The operator recognizes from initial conditions that OAC is unavailable and it is intended to pull rods to criticality. The operator records 1694 in Step 3.1.6.1A.
The operator places NA in Step 3.1.6.1B.
8 (Step 3.1.6.2) If dilution to Criticality The operator places NA in Step 3.1.6.2.
9 (Step 3.1.6.3) Record the Effective Boron Concentration:
(Step 3.1.6.1A or Step 3.1.6.1B3 or 3.1.6.2)
The operator records 1694 ppm from Step 3.1.6.1A.
2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 6 of 18 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 10 (Step 3.1.7) Xenon worth at anticipated time of Criticality (From OAC program Xenon Samarium
- XESM or REACT Program).
The operator records 0 from initial conditions.
11 (Step 3.1.8) If burnup from Step 3.1.5 is > 0 EFPD, record the difference between equilibrium and present samarium worth (P1475, Samarium program on OAC or REACT).
The operator recognizes that burnup is > 0 EFPD and records -150 from initial conditions.
12 (Step 3.1.9) If burnup from Step 3.1.5 is > 12 EFPD, perform Enclosure 4.8 to determine the fission product correction.
The operator recognizes that burnup is > 12 EFPD and that fission product correction is needed, and proceeds to.8.
13 (Enclosure 4.8/Notes prior to Step 3.1) All curves
/tables used in this procedure are found in OP/1(2)/A/6100/022 (Unit One (Two) Core Data Book). These procedures will be referred to as the Data Book.
Number of hours shutdown is the difference in time between the time the reactor went subcritical and the expected time of criticality.
The operator reads Notes, and proceeds.
2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 7 of 18 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 14 (Step 3.1) Shutdown Fission Product Correction Calculation:
(Step 3.1.1) If Unit operated > 3 EFPD from previous shutdown to current shutdown:
(Step 3.1.1.1) Use Data Book Table 6.7 to determine the shutdown fission product correction:
(Step 3.1.1.2) Number of hours shutdown (Step 3.1.1.3) Shutdown Fission Product Correction:
The operator reviews power history and recognizes that the Unit did operate > 3 EFPD from previous shutdown to current shutdown.
The operator records 144 in Step 3.1.1.2, and proceeds to Step 3.1.1.3.
The operator uses Data Book Table 6, and determines that the Shutdown Fission Product Correction for 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> is 41 PPM, and records this in Step 3.1.1.3.
15 (Step 3.1.2) If Unit operated < 1 EFPD from previous shutdown to current shutdown The operator reviews power history and recognizes that the Unit operated > 1 EFPD from previous shutdown to current shutdown.
Operator records an NA in Step 3.1.2, and proceeds to Step 3.1.3.
16 (Step 3.1.3) If Unit operated between 1 EFPD and 3 EFPD from previous shutdown to current shutdown The operator reviews power history and recognizes that the Unit did NOT operate between 1 and 3 EFPD from previous shutdown to current shutdown.
Operator records an NA in Step 3.1.3, and proceeds to Step 3.1.4.
2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 8 of 18 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 17 (Step 3.1.4) If Unit operated between 1 EFPD and 3 EFPD from previous shutdown to current shutdown The operator reviews power history and recognizes that the Unit did NOT operate between 1 and 3 EFPD from previous shutdown to current shutdown.
Operator records an NA in Step 3.1.4.
Operator records that the Shutdown Fission Product Correction factor is 41 in Enclosure 4.2, Step 3.1.9.
18 (Enclosure 4.2/Step 3.2) If desired, perform automated calculations using REACT..
The operator recognizes from initial conditions that REACT is NOT available and proceeds to Step 3.3.
- 19 (Step 3.3) Manual Calculations:
(Step 3.3.1) Boron Concentration:
(Step 3.3.1.1) Determine the all rods out (ARO), hot zero power (HZP), no xenon, equilibrium samarium, boron concentration for present burnup from Step 3.1.5 (Data Book Graph 6.1)
(Step 3.3.1.2) Record value in Table 4.2.1 Line A.
The operator addresses Data Book Graph 6.1.
(NOTE: The operator should use chart at bottom, and NO interpolation is needed).
The operator records 1793 in Table 4.2.1 Line A.
2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 9 of 18 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 20 (Step 3.3.2) Differential Boron Worth:
(Step 3.3.2.1) Determine the ARO differential boron worth for present burnup of step 3.1.5 (Data Book Graph 6.8)
(Step 3.3.2.2) Record value in Table 4.2.1 Line B The operator addresses Data Book Graph 6.8.
(NOTE: Operator should use chart at bottom, and NO interpolation is needed).
The operator records
-6.52 in Table 4.2.1 Line B.
- 21 (Step 3.3.3) Determine the Rod Inserted Worth:
Step (3.3.3.1) Record values from Steps 3.1.6 -
3.1.9 in Table 4.2.1.
The operator records values from steps 3.1.6 -
3.1.9 in Table 4.2.1 as follows:
C. Present Effective Boron Concentration:
1694 D. Xenon Worth: 0 E. Diff from Eq Sm Worth:
-150 F. Fission Product Correction: 41 2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 10 of 18 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 22 (Step 3.3.3.2) Complete Table 4.2.1, recording 0 for any N/Ad Reference Steps.
The operator records remaining values in Table 4.2.1, as follows:
G. Reactivity Equivalent of Boron Difference (C -
A) x B = (645.5).
(1694 - 1793) x - 6.52 =
-645.5 pcm H. Reactivity Equivalent of Fission Product Correction F x B = -267.3 41 x -6.52 = -267.3 Reactivity of Inserted Rods:
(D + E + G) - H = 762.8 (0 + -150 + (645.5)) -
(-267.3) = 762.8 23 (Step 3.3.4) If result from Table 4.2.1 < 0.
The operator recognizes result from Table 4.2.1 >
0 and records NA in Step 3.3.4.
- 24 (Step 3.3.5) Peak xenon worth:
(Step 3.3.5.1) Determine the peak xenon worth for present burnup from step 3.1.5 (Data Book Table 6.9)
(Step 3.3.5.2) Record value in Table 4.2.2 Line C.
The operator addresses Data Book Table 6.9.
The operator records 3985 in Table 4.2.2 Line C.
2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 11 of 18 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 25 (Step 3.3.6) Calculate the Estimated Critical Rod Positions:
(Step 3.3.6.1) Record values from Step 3.1.7 and Table 4.2.1 in Table 4.2.2.
The operator records values in Table 4.2.2 as follows:
A. Xenon Worth: 0 B. Reactivity of inserted rods: 762.8 C. Peak Xenon Worth:
3985 D. Lower Band Reactivity Worth: 1512.8 E. Upper Band Reactivity Worth: 12.8 2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 12 of 18 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 26 (Step 3.3.6.2) Complete Table 4.2.2.
The operator completes Table 4.2.2 as follows:
The operator addresses Table 6.3.A of the Data Book and determines:
F. No Xenon Rod Position for Reactivity of B - Bank D @ 55 steps,
+0/-5 steps.
G. No Xenon Rod Position for Reactivity of D - Bank C @ 66 steps,
+4/-1 steps.
H. No Xenon Rod Position for Reactivity of E - Bank D @ 217 steps, +3/-2 steps.
The operator addresses Table 6.3.B of the Data Book and determines:
I. Peak Xenon Rod Position for Reactivity of B - Bank D @ 74 steps,
+1/-4 steps.
J. Peak Xenon Rod Position for Reactivity of D - Bank C @ 90 steps,
+0/-5 steps.
K. Peak Xenon Rod Position for Reactivity of E - Bank D @ 220 steps, +0/-5 steps.
- 27 (Table 4.2.2) Estimated Critical Position The operator records Bank D @ 55 steps,
+0/-5 steps.
[(I - F) x (A ÷ C)] + F.
2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 13 of 18 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 28 (Table 4.2.2) Lower Limit of Band The operator records Bank C @ 66 steps,
+4/-1 steps.
[(J - G) x (A ÷ C)] + G
- 29 (Table 4.2.2) Upper Limit of Band The operator records Bank D @ 217 steps,
+3/-2 steps.
[(K - H) x (A ÷ C)] + H
- 30 (Step 3.4) Check the following:
(Step 3.4.1) Rod Positions of Table 4.2.2 or REACT output are greater than insertion limits per Data Book Graph 1.2.
(Step 3.4.2) Rod positions of Table 4.2.2 or REACT Output are less than rod withdrawal limits per Data Book Table 2.8.
The operator addresses Graph 1.2 and determines rod positions are greater than insertion limits.
The operator addresses Table 2.8 and determines that there are no rod withdrawal limits.
31 (Step 3.5) If Step 3.4 CANNOT be met...
The operator recognizes that reactor Engineering does NOT need to be contacted.
2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 14 of 18 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 32 Calculations performed By:
(RO)
_____________ Date The operator records Name and date.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 15 of 18 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2015 Admin - JPM A1a SRO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 16 of 18 Form ES-C-1 VERIFICATION OF COMPLETION KEY:
Table 4.2.1: Rod Inserted Worth Calculation Description Reference Value A. ARO, HZP, No Xenon, Eq.
Samarium Boron Step 3.3.1 1793ppm B. ARO/DBW Step 3.3.2
-6.52pcm/ppm C. Present Effective Boron Concentration Step 3.1.6.3 1694ppm D. Xenon Worth Step 3.1.7 0pcm E. Diff from Eq Sm Worth Step 3.1.8
-150pcm F. Fission Product Correction Step 3.1.9 41ppm G. Reactivity Equivalent of Boron Difference (C-A) x B (1694 - 1793) x -6.52 645.5pcm H. Reactivity Equivalent of Fission Product Correction F x B 41 x -6.52
-267.3pcm Reactivity of Inserted Rods
( D + E + G) -H (0 + -150
+ 645.5) - (-267.3) 762.8pcm 2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Page 17 of 18 Form ES-C-1 VERIFICATION OF COMPLETION KEY(Contd)
Table 4.2.2: Estimated Critical Rod Positions Description Reference Value A. Xenon Worth Step 3.1.7 0pcm B. Reactivity of inserted rods Table 4.2.1 762.8pcm C. Peak Xenon Worth Step 3.3.5
- 3985pcm D. Lower Band Reactivity Worth B + 750 1512.8pcm E. Upper Band Reactivity Worth B - 750 12.8pcm F. No Xenon Rod Position for Reactivity of B Data Book Table 6.3.A BankD 55+5/-0steps w/d G. No Xenon Rod Position for Reactivity of D Data Book Table 6.3.A BankC 66+4/-1steps w/d H. No Xenon Rod Position for Reactivity of E Data Book Table 6.3.A BankD 217+3/-2steps w/d I. Peak Xenon Rod Position for Reactivity of B Data Book Table 6.3.B BankD 74+1/-4steps w/d J. Peak Xenon Rod Position for Reactivity of D Data Book Table 6.3.B BankC 90+1/-4steps w/d K. Peak Xenon Rod Position for Reactivity of E Data Book Table 6.3.B Bank D 220+0/-5 steps w/d Estimated Critical Position
[(I - F) x (A/C)] + F
[(D74 - D55) x (0/3985)]
+ D55 BankD 55+5/-0 steps w/d Lower Limit of Band
[(J - G) x (A/C)] + G
[(C90 - C66) x (0/3985)]
+ C66 BankC 66+4/-1steps w/d Upper Limit of Band
[(K - H) x (A/C)] + H
[(D220 - D217) x (0/3985)]
+ D217 BankD 217+3/-2 steps w/d 2015 Admin - JPM A1a SRO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions:
Unit 1 startup in progress per OP/1/A/6100/001 (Controlling Procedure for Unit Startup).
All steps are complete up to determining the desired estimated critical rod height.
The Unit tripped from 30% power, 143 hours0.00166 days <br />0.0397 hours <br />2.364418e-4 weeks <br />5.44115e-5 months <br /> ago.
The following Cycle 23 conditions exist:
EFPD = 200 NC Boron = 1694 PPM Xenon Worth = 0 Samarium Difference = -150 PCM It is intended to pull rods to criticality with criticality achieved in approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Reactor Engineer has been contacted earlier today and has reported that there have been no unusual trends on ECPs.
The OAC and REACT Program are unavailable.
INITIATING CUE:
The CRS has directed you to perform an ECP per Enclosure 4.2 (Estimated Critical Rod Position (ECP)) of OP/0/A/6100/006 (Reactivity Balance Calculation).
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A1b RO 2015 Admin - JPM A1b RO (REV_030915)
NUREG 1021, Revision 9
Appendix C Page 2 of 11 Form ES-C-1 Job Performance Measure Worksheet Facility:
McGuire Task No.:
Task
Title:
Perform a Manual NC Leakage Calculation JPM No.:
Reference:
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, and associated Datasheet (Last two (2)
Pages of this JPM); and Handouts 1-4.
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 1.9.
Initiating Cue:
Using Enclosure 13.2 (NC Leakage Determination Using Manual Calculations), AND the attached Datasheet, complete the NC System Leakage Calculation, through Step 1.11.
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.
2015 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Page 3 of 11 Form ES-C-1 Job Performance Measure Worksheet 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 OP/1/A/6150/004 (Pressurizer Relief Tank), Rev 58 OP/1/A/6500/001 (Liquid Waste System), Rev 91 PT/1/A/4150/001B (Reactor Coolant Leakage Calculation), Rev 91 McGuire Unit 1 Technical Specifications Handouts:
Handout 1: PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) marked up for this JPM.
Handout 2: PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) 3.2 (NC Leakage Determinations Using Manual Calculations) marked up for this JPM.
Handout 3: Enclosure 13.3 (NCDT Volume) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation)
Handout 4: Enclosure 13.4 (PRT Volume) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation)
Time Critical Task:
NO Validation Time:
18 minutes NOTE:
An Answer KEY is attached to this JPM on Page 9.
2015 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Page 4 of 11 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 Handouts 1-4.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1
(Enclosure 13.2, Steps 1.10.1 through 6, 8 through 13, 22, 23, 26 and 1.11.1)
Record raw data.
The operator transposes raw data from the Data Sheet provided.
2 (Enclosure 13.2, Step 1.10.14) Calculate change in NC System Tave:
The operator calculates the change in NC System Tave to be -
0.1oF, and records.
3 (Enclosure 13.2, Step 1.10.15) Calculate VCT Leakage Rate:
The operator calculates the VCT Leakage Rate to be 4.37 gpm, and records.
4 (Enclosure 13.2, Step 1.10.16) Calculate PZR Leakage Rate:
The operator calculates the PZR Leakage Rate to be 0.03 gpm, and records.
5 (Enclosure 13.2, Step 1.10.17) Calculate Total Leakage:
The operator calculates the Total Leakage to be 4.40 gpm, and records.
2015 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6
(Enclosure 13.2, Step 1.10.18) 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 79.0
%, and determines that initial PRT Volume is 11034.1 gal, and records.
The operator uses 3.4 and a final PRT Level of 80.0
%, and determines that final PRT Volume is 11163.3 gal, and records.
7 (Enclosure 13.2, Step 1.10.19) Calculate PRT Leakage Rate:
The operator calculates the PRT Leakage Rate to be 1.80 gpm, and records.
8 (Enclosure 13.2, Step 1.10.20) 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 51%, and determines that initial NCDT Volume is 180.2 gal, and records.
The operator uses 3.3 and a final NCDT Level of 56%, and determines that final NCDT Volume is 198.2 gal, and records.
9 (Enclosure 13.2, Step 1.10.21) Calculate NCDT Leakage Rate:
The operator calculates the NCDT Leakage Rate to be.25 gpm, and records.
2015 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 10 (Enclosure 13.2, Step 1.10.24) Calculate Identified Leakage:
The operator calculates the Identified Leakage to be 2.05 (+/-10%) gpm, and records.
- 11 (Enclosure 13.2, Step 1.10.25) Calculate Unidentified Leakage:
The operator calculates the Unidentified Leakage to be 2.35 (+/-10%) gpm, and records.
- 12 (Enclosure 13.2, Step 1.10.26) Determine Total NC Pump #1 Seal Leakoff:
The operator calculates the Total NC Pumps #1 Seal Leakoff to be 13.75
(+/-10%) gpm, and records.
- 13 (Enclosure 13.2, Step 1.11.27) Calculate Total Accumulative Leakage:
The operator calculates the Total Accumulative Leakage to be 17.90
(+/-10%) gpm, and records.
14 (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.
2015 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 15 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 9 of this JPM.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2015 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Page 8 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2015 Admin - JPM A1b RO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2015 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Page 9 of 11 Form ES-C-1 VERIFICATION OF COMPLETION KEY:
3.2, Step 1.10.14 (JPM Step 2): Change in NC System Tave:
585.1oF - 585.0oF = 0.1oF 3.2, Step 1.10.15 (JPM Step 3): VCT Leakage Rate:
(57.6% - 41.3%) x19.3 gallons/%/72 minutes = 4.37 gallons per minute (gpm) 3.2, Step 1.10.16 (JPM Step 4): PZR Leakage Rate:
(55.2% - 54.3%) x 132.5 gallons/% x.01613 /72 minutes = 0.03 gallons per minute (gpm) 3.2, Step 1.10.17 (JPM Step 5): Total Leakage:
4.37 gpm + 0.03 gpm = 4.40 gpm 3.2, Step 1.10.19 (JPM Step 7): Total PRT Leakage:
(11163.3 gallons - 11034.1 gallons)/72 minutes = 1.80 gallons per minute (gpm) 3.2, Step 1.10.21 (JPM Step 9): Total NCDT Leakage:
(198.2 gallons - 180.2 gallons)/72 minutes = 0.25 gallons per minute (gpm) 3.2, Step 1.10.24 (JPM Step 11): Identified Leakage:
(1.80 gpm +.25 gpm + 0 gpm) = 2.05 gpm 3.2, Step 1.10.25 (JPM Step 12): Unidentified Leakage:
(4.40 gpm - 2.05 gpm) = 2.35 gpm 3.2, Step 1.10.26 (JPM Step 13): Total NC Pumps #1 Seal Leakoff:
(3.1 gpm + 3.4 gpm + 3.8 gpm + 3.2 gpm + 0.25 gpm) = 13.75 gpm 3.2, Step 1.10.27 (JPM Step 14): Total Accumulative Leakage:
(2.35 gpm + 2.05 gpm + 3.1 gpm + 3.4 gpm + 3.8 gpm + 3.2 gpm) = 17.90 gpm LCO 3.4.13 (1 gpm unidentified LEAKAGE) has been exceeded.
2015 Admin - JPM A1b RO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET Data Sheet Start Time 0900 Stop Time 1012 Initial Final VCT Level 57.6 41.3 Pzr Level 55.2 54.3 NC System Tave 585.1 585.0 PRT Level 79.0 80.0 NCDT Level 51 56 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 3.1 NC Pump 1B #1 Seal Leakoff Flow 3.4 NC Pump 1C #1 Seal Leakoff Flow 3.8 NC Pump 1D #1 Seal Leakoff Flow 3.2 1EMF71 Reading 1.5 1EMF72 Reading 1.3 1EMF73 Reading 1.7 1EMF74 Reading 1.1 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)
- 3.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) has been completed through Step 1.9.
INITIATING CUE:
Using Enclosure 13.2 (NC Leakage Determination Using Manual Calculations), AND the attached Datasheet, complete the NC System Leakage Calculation, through Step 1.11.
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.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A1b SRO 2015 Admin - JPM A1b SRO (REV_030915)
NUREG 1021, Revision 9
Appendix C Page 2 of 11 Form ES-C-1 Job Performance Measure Worksheet Facility:
McGuire Task No.:
Task
Title:
Perform/Review a Manual NC Leakage Calculation JPM No.:
Reference:
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, and associated Datasheet (Last two (2)
Pages of this JPM); and Handouts 1-4.
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 1.9.
Initiating Cue:
Using Enclosure 13.2 (NC Leakage Determination Using Manual Calculations), AND the attached Datasheet, complete the NC System Leakage Calculation, through Step 1.11.
Identify all required action(s), if any, that apply as a result of the NC Leakage Calculation.
2015 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 3 of 11 Form ES-C-1 Job Performance Measure Worksheet 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 OP/1/A/6150/004 (Pressurizer Relief Tank), Rev 58 OP/1/A/6500/001 (Liquid Waste System), Rev 91 PT/1/A/4150/001B (Reactor Coolant Leakage Calculation), Rev 91 McGuire Unit 1 Technical Specifications Handouts:
Handout 1: PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) marked up for this JPM.
Handout 2: PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) 3.2 (NC Leakage Determinations Using Manual Calculations) marked up for this JPM.
Handout 3: Enclosure 13.3 (NCDT Volume) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation)
Handout 4: Enclosure 13.4 (PRT Volume) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation)
Time Critical Task:
NO Validation Time:
20 minutes NOTE:
An Answer KEY is attached to this JPM on Page 9.
2015 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 4 of 11 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 Handouts 1-4.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1
(Enclosure 13.2, Steps 1.10.1 through 6, 8 through 13, 22, 23, 26 and 1.11.1)
Record raw data.
The operator transposes raw data from the Data Sheet provided.
2 (Enclosure 13.2, Step 1.10.14) Calculate change in NC System Tave:
The operator calculates the change in NC System Tave to be -
0.1oF, and records.
3 (Enclosure 13.2, Step 1.10.15) Calculate VCT Leakage Rate:
The operator calculates the VCT Leakage Rate to be 4.37 gpm, and records.
4 (Enclosure 13.2, Step 1.10.16) Calculate PZR Leakage Rate:
The operator calculates the PZR Leakage Rate to be 0.03 gpm, and records.
5 (Enclosure 13.2, Step 1.10.17) Calculate Total Leakage:
The operator calculates the Total Leakage to be 4.40 gpm, and records.
2015 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6
(Enclosure 13.2, Step 1.10.18) 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 79.0
%, and determines that initial PRT Volume is 11034.1 gal, and records.
The operator uses 3.4 and a final PRT Level of 80.0
%, and determines that final PRT Volume is 11163.3 gal, and records.
7 (Enclosure 13.2, Step 1.10.19) Calculate PRT Leakage Rate:
The operator calculates the PRT Leakage Rate to be 1.80 gpm, and records.
8 (Enclosure 13.2, Step 1.10.20) 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 51%, and determines that initial NCDT Volume is 180.2 gal, and records.
The operator uses 3.3 and a final NCDT Level of 56%, and determines that final NCDT Volume is 198.2 gal, and records.
9 (Enclosure 13.2, Step 1.10.21) Calculate NCDT Leakage Rate:
The operator calculates the NCDT Leakage Rate to be.25 gpm, and records.
2015 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 10 (Enclosure 13.2, Step 1.10.24) Calculate Identified Leakage:
The operator calculates the Identified Leakage to be 2.05 (+/-10%) gpm, and records.
- 11 (Enclosure 13.2, Step 1.10.25) Calculate Unidentified Leakage:
The operator calculates the Unidentified Leakage to be 2.35 (+/-10%) gpm, and records.
- 12 (Enclosure 13.2, Step 1.10.26) Determine Total NC Pump #1 Seal Leakoff:
The operator calculates the Total NC Pumps #1 Seal Leakoff to be 13.75
(+/-10%) gpm, and records.
- 13 (Enclosure 13.2, Step 1.11.27) Calculate Total Accumulative Leakage:
The operator calculates the Total Accumulative Leakage to be 17.90
(+/-10%) gpm, and records.
14 (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.
2015 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 15 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 9 of this JPM.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2015 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 8 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2015 Admin - JPM A1b SRO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2015 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Page 9 of 11 Form ES-C-1 VERIFICATION OF COMPLETION KEY:
3.2, Step 1.10.14 (JPM Step 2): Change in NC System Tave:
585.1oF - 585.0oF = 0.1oF 3.2, Step 1.10.15 (JPM Step 3): VCT Leakage Rate:
(57.6% - 41.3%) x19.3 gallons/%/72 minutes = 4.37 gallons per minute (gpm) 3.2, Step 1.10.16 (JPM Step 4): PZR Leakage Rate:
(55.2% - 54.3%) x 132.5 gallons/% x.01613 /72 minutes = 0.03 gallons per minute (gpm) 3.2, Step 1.10.17 (JPM Step 5): Total Leakage:
4.37 gpm + 0.03 gpm = 4.40 gpm 3.2, Step 1.10.19 (JPM Step 7): Total PRT Leakage:
(11163.3 gallons - 11034.1 gallons)/72 minutes = 1.80 gallons per minute (gpm) 3.2, Step 1.10.21 (JPM Step 9): Total NCDT Leakage:
(198.2 gallons - 180.2 gallons)/72 minutes = 0.25 gallons per minute (gpm) 3.2, Step 1.10.24 (JPM Step 11): Identified Leakage:
(1.80 gpm +.25 gpm + 0 gpm) = 2.05 gpm 3.2, Step 1.10.25 (JPM Step 12): Unidentified Leakage:
(4.40 gpm - 2.05 gpm) = 2.35 gpm 3.2, Step 1.10.26 (JPM Step 13): Total NC Pumps #1 Seal Leakoff:
(3.1 gpm + 3.4 gpm + 3.8 gpm + 3.2 gpm + 0.25 gpm) = 13.75 gpm 3.2, Step 1.10.27 (JPM Step 14): Total Accumulative Leakage:
(2.35 gpm + 2.05 gpm + 3.1 gpm + 3.4 gpm + 3.8 gpm + 3.2 gpm) = 17.90 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 />.
2015 Admin - JPM A1b SRO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET Data Sheet Start Time 0900 Stop Time 1012 Initial Final VCT Level 57.6 41.3 Pzr Level 55.2 54.3 NC System Tave 585.1 585.0 PRT Level 79.0 80.0 NCDT Level 51 56 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 3.1 NC Pump 1B #1 Seal Leakoff Flow 3.4 NC Pump 1C #1 Seal Leakoff Flow 3.8 NC Pump 1D #1 Seal Leakoff Flow 3.2 1EMF71 Reading 1.5 1EMF72 Reading 1.3 1EMF73 Reading 1.7 1EMF74 Reading 1.1 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)
- 3.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) has been completed through Step 1.9.
INITIATING CUE:
Using Enclosure 13.2 (NC Leakage Determination Using Manual Calculations), AND the attached Datasheet, complete the NC System Leakage Calculation, through Step 1.11.
Identify all required action(s), if any, that apply as a result of the NC Leakage Calculation.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A2 RO 2015 Admin - JPM A2 RO (REV_030915)
NUREG 1021, Revision 9
Appendix C Page 2 of 7 Form ES-C-1 Job Performance Measure Worksheet Facility:
McGuire Task No.:
Task
Title:
Partial Loss of Annunciators JPM No.:
Reference:
2.2.43 (3.0)
Examinee:
NRC Examiner:
Facility Evaluator:
Date:
Method of testing:
Simulated Performance:
Actual Performance:
X Classroom X
Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1 and 2.
Initial Conditions:
Unit 1 is operating at 100% power.
Due to a lightning strike several of the Unit 1 Control Room Annunciators have failed.
The crew entered PT/1/A4600/033 (Loss of Control Room Annunciators), and has completed Enclosure 13.2 (Partial Loss of Annunciator Panels) through Step 3.3.
The failed Annunciators have been identified (Marked in YELLOW on Attached Handout).
Another operator is reviewing the Annunciator Response Procedures for each failed annunciator.
All other annunciators have been tested satisfactorily.
The IAE Supervisor has been notified and is investigating.
Initiating Cue:
The CRS has directed you to perform steps 3.4 through 3.11 of 3.2 of PT/1/A4600/033 (Loss of Control Room Annunciators), and identify the affected Annunciators, if any, that have an Alternate Method for Surveillance that are applicable.
2015 Admin - JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 3 of 7 Form ES-C-1 Job Performance Measure Worksheet Task Standard:
The operator will determine that 11% of the Annunciators have failed in accordance with the attached Key, and identify five (5) specific annunciators that have an identified Alternative Method for Surveillance.
Required Materials:
Calculator General
References:
PT/1/A/4600/033 (Loss of Control Room Annunciators), Rev 6 Handouts:
Handout 1: PT/1/A4600/033 (Loss of Control Room Annunciators) marked up for place-keeping.
Handout 2: Failed Annunciators Time Critical Task:
NO Validation Time:
15 minutes NOTE:
An Answer KEY is provided as a separate document.
2015 Admin - JPM A2 RO 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 Initial Conditions/Cue (Last Page of this JPM), and Handouts 1 and 2.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 1 (Step 3.4) Perform 3.3 (Loss of Annunciators Determination).
The operator reviews Handout 2 (Failed Annunciators) and determines that the following Panels are affected:
1AD-7 (16) 1AD-8 (10) 1AD-9 (12) 1AD-10 (3) 1AD-12 (6) 1AD-13 (15)
And completes 3.3 in accordance with the attached Key.
- 2 (Step 3.5) Record total percentage of annunciators affected.
The operator records 11% and continues.
Cue:
The critical nature of Step is that the operator determines that 11% of the Annunciators have been affected.
3 (Step 3.6) IF greater than 50% of annunciators are affected,.
The operator recognizes that 50% of the annunciators are NOT affected and continues.
2015 Admin - JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 4
(Step 3.7) IF in Mode 6,.
The operator recognizes that the plant is NOT in Mode 6 and continues.
5 (Step 3.8) IF annunciator panel 1AD-14 or 1AD-15 failed to generate an audible alarm or illuminate,.
The operator recognizes that panel 1AD-14 or 1AD-15 did NOT fail to generate an audible alarm or illuminate.
6 (Step 3.9) Notify I&E to investigate affected annunciator panel(s) or window(s).
The operator recognizes that the I&E Supervisor has been notified and is investigating; and continues.
7 (Step 3.10) Review associated annunciator response procedures for panel(s) or windows affected.
The operator recognizes that another operator is reviewing the ARPs associated with the failed Annunciators.
- 8 (Step 3.11) Perform 3.4 (Annunciator Panel Reference) to evaluate the following:
Alternate indications available for affected alarms Impact to Ops PTs (Semi Daily, Daily, etc.)
The operator addresses 3.4 and identifies that the following Alarms have an identified Alternate Method for Surveillance:
1AD-7 F2 1AD-7 J1 1AD8 C4 1AD-10 C1 1AD-13 C1 Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2015 Admin - JPM A2 RO NUREG 1021, Revision 9
Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2015 Admin - JPM A2 RO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2015 Admin - JPM A2 RO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions:
Unit 1 is operating at 100% power.
Due to a lightning strike several of the Unit 1 Control Room Annunciators have failed.
The crew entered PT/1/A4600/033 (Loss of Control Room Annunciators), and has completed Enclosure 13.2 (Partial Loss of Annunciator Panels) through Step 3.3.
The failed Annunciators have been identified (Marked in YELLOW on Attached Handout).
Another operator is reviewing the Annunciator Response Procedures for each failed annunciator.
All other annunciators have been tested satisfactorily.
The IAE Supervisor has been notified and is investigating.
INITIATING CUE:
The CRS has directed you to perform steps 3.4 through 3.11 of 3.2 of PT/1/A4600/033 (Loss of Control Room Annunciators), and identify the affected Annunciators, if any, that have an Alternate Method for Surveillance that are applicable.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A2 SRO 2015 Admin - JPM A2 SRO (REV_030915)
NUREG 1021, Revision 9
Appendix C Page 2 of 9 Form ES-C-1 Job Performance Measure Worksheet Facility:
McGuire Task No.:
Task
Title:
Perform a Thermal Margin Determination JPM No.:
Reference:
2.2.18 (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 1.
Initial Conditions:
Unit 1 was shutdown 13 days ago for a mid-cycle outage after 200 days of operation.
Unit 1 is currently in Mode 5.
No Core Offload will occur.
The NC system is 125°F with A Train ND in service.
Preparations are being made to lower NC system level to 67 inches above Hot Leg Centerline per Enclosure 4.1 (Draining the NC System) of OP/1/A/6100/SD-20 (Draining the NC System).
Initiating Cue:
Complete Attachment 12.6 of OMP 5-8 (Shift Supervision Turnovers) to determine the new thermal margin with NC system level at 67 inches above Hot Leg Centerline (Complete all required paperwork).
Identify the individuals that must be notified and/or actions that must be taken.
Task Standard:
The operator will complete Attachment 12.6 (Thermal Margin Determination) of OMP 5-8 (Shift Supervision Turnovers) with a new thermal margin calculated and documented on Attachment 12.7 (Shutdown Assessment Status) in accordance with the provided KEY.
2015 Admin - JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 3 of 9 Form ES-C-1 Job Performance Measure Worksheet Required Materials:
None General
References:
OP/1/A/6100/SD-20 (Draining the NC System), Rev 59 OMP 5-8 (Shift Supervision Turnovers), Rev 59 OP/1/A/6100/022 (Unit 1 Data Book - Cycle 23), Rev 480 MCEI-0400-261 (Unit 1 Cycle 23 Core Operating Limits Report), Rev 0 Handouts:
Handout 1: Blank copy of OMP 5-8 (Shift Supervision Turnovers)
Time Critical Task:
NO Validation Time:
15 minutes NOTE:
An Answer KEY is provided on a separate document.
2015 Admin - JPM A2 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 (Last Page of this JPM) and Handout 1.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1
(Attachment 12.6)
Applicable to:
Unit 1 Unit 2 The operator places a check in the Unit 1 checkbox.
2 (Attachment 12.6, Step 1)
Refer to OP/1(2)/A/6100/22, Unit 1 (2) Databook, Enclosure 4.3, Section 2.10 Thermal Margin Curves, to determine appropriate section and/or curve to use.
SECTION/CURVE USED__________
INITIAL_________
The operator obtains the Core Data Book and locates Section 2.10.
The operator recognizes that since the Loops are drained and the Vessel Head has NOT been removed, the Curves of Section 2.10.1 are applicable.
The operator determines that from the Initial conditions given,.3 Section 2.10.1 B is to be used, and records this, placing their initial in the appropriate Block.
Using 2.10.1 B Curve, the operator intersects the point of 13 days after shutdown and the 140oF temperature Curve, and determines that the new Thermal Margin is
.48+/-.02 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or 28.8
+/-1.2 minutes.
2015 Admin - JPM A2 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 3
(Attachment 12.6, Step 2)
Document thermal margin time and maximum NC Temperature allowed (for curve used) in the table below and initial.
The operator records the date in the chart on 2.6.
The operator records the time in the chart on 2.6.
The operator records 28.8 +/-1.2 minutes in the Thermal Margin MIN block on the chart on 2.6.
The operator records 140oF in the Max NC Temp oF block on the chart on Attachment 12.6.
2015 Admin - JPM A2 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 4
(Attachment 12.6, Step 3)
Communicate Thermal Margin as follows:
(Attachment 12.6, Step 3.a) Write thermal margin time and max NC Temp on the Shutdown Assessment/Status (Attachment 12.7).
Include any data Book 4.3 Section 2.10 support parameters (S/G Lvls, Pzr Lvl, etc.) Initial in Table below.
The operator records 28.8 +/-1.2 minutes in the Thermal Margin Column TM Minutes block on 2.7.
The operator records 140oF in the Thermal Margin Column Max NC Temp block on 2.7.
The operator records 67 in the Thermal Margin Column NCS Level block on 2.7.
The operator places their initial in the Thermal Margin Data Written on Shutdown Assessment/Status (Attachment 12.7) block on the chart on 2.6.
5 (Attachment 12.6, Step 3.b) Notify the Containment Closure Coordinator (CCC) of the thermal margin time determined. Initial in the table below.
The operator contacts the CCC and notifies that TM is 28.8 +/-1.2 minutes.
Cue:
The Containment Closure Coordinator has been notified.
The operator places their initial in the CCC Notified block on the chart on Attachment 12.6.
2015 Admin - JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6
(Attachment 12.6, Step 3.c) Notify the Shift Technical Advisor (STA) of the thermal margin time determined. Initial in the table below.
The operator contacts the STA and notifies that TM is 28.8 +/-1.2 minutes.
Cue:
The STA has been notified.
The operator places their initial in the STA Notified block on the chart on Attachment 12.6.
7 (Attachment 12.6, Step 3.d) Write thermal margin time on MC-6 and update MLOG. Initial in the table below.
The operator directs the OATC to write 28.8 +/-1.2 minutes in the TM Block on MC-6, and enter into MLOG.
Cue:
MC-6/MLOG has been updated.
The operator places their initial in the Thermal Margin Time Written on MC-6 and MLOG block on the chart on 2.6.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2015 Admin - JPM A2 SRO NUREG 1021, Revision 9
Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2015 Admin - JPM A2 SRO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2015 Admin - JPM A2 SRO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions:
Unit 1 was shutdown 13 days ago for a mid-cycle outage after 200 days of operation.
Unit 1 is currently in Mode 5.
No Core Offload will occur.
The NC system is 125°F with A Train ND in service.
Preparations are being made to lower NC system level to 67 inches above Hot Leg Centerline per Enclosure 4.1 (Draining the NC System) of OP/1/A/6100/SD-20 (Draining the NC System).
INITIATING CUE:
Complete Attachment 12.6 of OMP 5-8 (Shift Supervision Turnovers) to determine the new thermal margin with NC system level at 67 inches above Hot Leg Centerline (Complete all required paperwork).
Identify the individuals that must be notified and/or actions that must be taken.
New Thermal Margin:
Individuals Notified/Actions Taken:
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A3 RO 2015 Admin - JPM A3 RO (REV_030915)
NUREG 1021, Revision 9
Appendix C Page 2 of 7 Form ES-C-1 Job Performance Measure Worksheet Facility:
McGuire Task No.:
Task
Title:
Evaluate Stay Time with Lowered SFP Level JPM No.:
Reference:
2.3.7 (3.5)
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 1.
Initial Conditions:
A station wide accident has occurred due to an Earthquake.
Unit 1 is in Mode 6 with a full core off-load.
The Unit 1 Spent Fuel Pool level has lowered to 12.5 feet above the top of the fuel, and has stabilized at this level.
The crew is implementing AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level) and EP/1/A/5000/G-1 Generic Enclosures), 2 (Monitoring Unit 1 SFP Level and Temperature).
No installed radiation monitors are operable in the Spent Fuel Building.
A dose limit of 25 mrem has been placed on all personnel performing emergency tasks within the building.
You have been assigned a repetitive task within Generic Enclosure 32 which will require you to enter the Fuel Building and proceed to the area around the Spent Fuel Pool, and remain there for 3 minutes, before exiting the building.
The exposure traveling to and from the Spent Fuel Pool area results in no appreciable exposure.
2015 Admin - JPM A3 RO NUREG 1021, Revision 9
Appendix C Page 3 of 7 Form ES-C-1 Job Performance Measure Worksheet Initiating Cue:
The CRS has directed you to use Enclosure 13 (Spent Fuel Pool Radiation Level Vs. Water Level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level), and determine the number of times you will be able to perform this repetitive task before you must be replaced by another operator.
Task Standard:
The operator will use Enclosure 13 of AP/1/A/5500/41 to determine that the dose rate around the Spent Fuel Pool area is 25.2 mrem/hour and based on this the operator will determine that the repetitive task can be performed 19 times before another operator will need to perform the task.
Required Materials:
Calculator General
References:
AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), Rev 12 EP/1/A/5000/G-1 (Generic Enclosures), Rev 37 MNS SLC 16.9.21 (Water Level - Spent Fuel Storage Pool), Rev 0 Fleet ALARA Manual, Rev 27 Handouts:
Handout 1: Enclosure 13 (Spent Fuel Pool Radiation Level Vs. Water Level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level)
Time Critical Task:
NO Validation Time:
7 minutes 2015 Admin - JPM A3 RO 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 Initial Conditions/Cue (Last Page of this JPM), and Handout 1.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 1 (AP/1/A/5500/41, 3) Determine the Dose Rate around the Spent Fuel Pool area with water level at 12.5 feet.
The operator uses 3 and determines that the dose rate around the pool area is 25.2 mrem/hour.
2.52E-02R/hr OR (2.52 x 10-2 R/hr) x 103 mrem/R = 25.2 mrem/hr
- 2 Determine Dose received each time task is performed The operator recognizes that the task requires three minutes.
The operator determines that the dose received in that three minute period is 1.3 mrem.
Dose = 25.2 mrem/hr x 1hr/60 minutes x 3 minutes 2015 Admin - JPM A3 RO NUREG 1021, Revision 9
Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 3 Determine the number of times that the repetitive task can be performed while remaining within allowable RWP limit.
The operator recognizes that the maximum allowable dose received is 25 mrem, and that 1.3 mrem will be received on each occasion the task is performed.
The operator identifies that the task can be performed 19 times, before another operator will be required to perform the task.
- Task performances =
25 mrem/1.3 mrem/task
= 19.2 tasks, or 19 tasks.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2015 Admin - JPM A3 RO NUREG 1021, Revision 9
Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2015 Admin - JPM A3 RO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2015 Admin - JPM A3 RO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions:
A station wide accident has occurred due to an Earthquake.
Unit 1 is in Mode 6 with a full core off-load.
The Unit 1 Spent Fuel Pool level has lowered to 12.5 feet above the top of the fuel, and has stabilized at this level.
The crew is implementing AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level) and EP/1/A/5000/G-1 Generic Enclosures), 2 (Monitoring Unit 1 SFP Level and Temperature).
No installed radiation monitors are operable in the Spent Fuel Building.
A dose limit of 25 mrem has been placed on all personnel performing emergency tasks within the building.
You have been assigned a repetitive task within Generic 2 which will require you to enter the Fuel Building and proceed to the area around the Spent Fuel Pool, and remain there for 3 minutes, before exiting the building.
The exposure traveling to and from the Spent Fuel Pool area results in no appreciable exposure.
INITIATING CUE:
The CRS has directed you to use Enclosure 13 (Spent Fuel Pool Radiation Level Vs. Water Level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level), and determine the number of times you will be able to perform this repetitive task before you must be replaced by another operator.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A3 SRO 2015 Admin - JPM A3 SRO (REV_030915)
NUREG 1021, Revision 9
Appendix C Page 2 of 7 Form ES-C-1 Job Performance Measure Worksheet Facility:
McGuire Task No.:
Task
Title:
Evaluate Stay Time with Lowered SFP Level JPM No.:
Reference:
2.3.7 (3.6)
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 Initial Conditions/Cue (Last Page of this JPM), and Handout 1.
Initial Conditions:
A station wide accident has occurred due to an Earthquake.
Unit 1 is in Mode 6 with a full core off-load.
The Unit 1 Spent Fuel Pool level has lowered to 12.5 feet above the top of the fuel, and has stabilized at this level.
The crew is implementing AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level) and EP/1/A/5000/G-1 Generic Enclosures), 2 (Monitoring Unit 1 SFP Level and Temperature).
No installed radiation monitors are operable in the Spent Fuel Building.
A dose limit of 25 mrem has been placed on all personnel performing emergency tasks within the building.
You have been assigned a repetitive task within Generic Enclosure 32 which will require you to enter the Fuel Building and proceed to the area around the Spent Fuel Pool, and remain there for 3 minutes, before exiting the building.
The exposure traveling to and from the Spent Fuel Pool area results in no appreciable exposure.
2015 Admin - JPM A3 SRO NUREG 1021, Revision 9
Appendix C Page 3 of 7 Form ES-C-1 Job Performance Measure Worksheet Initiating Cue:
The CRS has directed you to use Enclosure 13 (Spent Fuel Pool Radiation Level Vs. Water Level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level), and determine the number of times you will be able to perform this repetitive task before you must be replaced by another operator.
Task Standard:
The operator will use Enclosure 13 of AP/1/A/5500/41 to determine that the dose rate around the Spent Fuel Pool area is 25.2 mrem/hour and based on this the operator will determine that the repetitive task can be performed 19 times before another operator will need to perform the task.
Required Materials:
Calculator General
References:
AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), Rev 12 EP/1/A/5000/G-1 (Generic Enclosures), Rev 37 MNS SLC 16.9.21 (Water Level - Spent Fuel Storage Pool), Rev 0 Fleet ALARA Manual, Rev 27 Handouts:
Handout 1: Enclosure 13 (Spent Fuel Pool Radiation Level Vs. Water Level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level)
Time Critical Task:
NO Validation Time:
7 minutes 2015 Admin - JPM A3 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 Initial Conditions/Cue (Last Page of this JPM), and Handout 1.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 1 (AP/1/A/5500/41, 3) Determine the Dose Rate around the Spent Fuel Pool area with water level at 12.5 feet.
The operator uses 3 and determines that the dose rate around the pool area is 25.2 mrem/hour.
2.52E-02R/hr OR (2.52 x 10-2 R/hr) x 103 mrem/R = 25.2 mrem/hr
- 2 Determine Dose received each time task is performed The operator recognizes that the task requires three minutes.
The operator determines that the dose received in that three minute period is 1.3 mrem.
Dose = 25.2 mrem/hr x 1hr/60 minutes x 3 minutes 2015 Admin - JPM A3 SRO NUREG 1021, Revision 9
Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT
- 3 Determine the number of times that the repetitive task can be performed while remaining within allowable RWP limit.
The operator recognizes that the maximum allowable dose received is 25 mrem, and that 1.3 mrem will be received on each occasion the task is performed.
The operator identifies that the task can be performed 19 times, before another operator will be required to perform the task.
- Task performances =
25 mrem/1.3 mrem/task
= 19.2 tasks, or 19 tasks.
Terminating Cue:
Evaluation on this JPM is complete.
STOP TIME:
2015 Admin - JPM A3 SRO NUREG 1021, Revision 9
Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2015 Admin - JPM A3 SRO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2015 Admin - JPM A3 SRO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions:
A station wide accident has occurred due to an Earthquake.
Unit 1 is in Mode 6 with a full core off-load.
The Unit 1 Spent Fuel Pool level has lowered to 12.5 feet above the top of the fuel, and has stabilized at this level.
The crew is implementing AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level) and EP/1/A/5000/G-1 Generic Enclosures), 2 (Monitoring Unit 1 SFP Level and Temperature).
No installed radiation monitors are operable in the Spent Fuel Building.
A dose limit of 25 mrem has been placed on all personnel performing emergency tasks within the building.
You have been assigned a repetitive task within Generic 2 which will require you to enter the Fuel Building and proceed to the area around the Spent Fuel Pool, and remain there for 3 minutes, before exiting the building.
The exposure traveling to and from the Spent Fuel Pool area results in no appreciable exposure.
INITIATING CUE:
The CRS has directed you to use Enclosure 13 (Spent Fuel Pool Radiation Level Vs. Water Level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level), and determine the number of times you will be able to perform this repetitive task before you must be replaced by another operator.
NUREG 1021, Revision 9
Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A4 SRO 2015 Admin - JPM A4 SRO (REV_030915)
NUREG 1021, Revision 9
Appendix C Page 2 of 9 Form ES-C-1 Job Performance Measure Worksheet Facility:
McGuire Task No.:
Task
Title:
Provide an updated PAR JPM No.:
Reference:
2.4.44 (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), and Handouts 1-3.
Initial Conditions:
Unit 2 is at 100% power.
A LOCA inside containment has occurred on Unit 1.
The Emergency Coordinator declared a General Emergency per RP/0/A/5700/000, Enclosure 4.1, EAL # 4.1.G.1 (Loss of All Three Barriers).
An Emergency Release from Containment is in progress due to a piping penetration failure.
An Emergency Notification Form, along with the initial PAR was sent at the appropriate time.
Due to a shift in the 15-minute average wind direction, a re-assessment of the Initial PAR is being made.
The following conditions exist 30 minutes after the start of the event:
The wind speed is 12 mph.
The wind direction is 88.7o.
EMF51 A and B reading is 200 R/hr.
An RP Dose Assessment will be completed in 20 minutes.
Security Reports that there are no security related events in progress, and site evacuation is progressing as expected.
2015 Admin - JPM A4 SRO NUREG 1021, Revision 9
Appendix C Page 3 of 9 Form ES-C-1 Job Performance Measure Worksheet The Communicator is reporting that off-site agencies are reporting that evacuations are proceeding as expected.
Initiating Cue:
Based on the present conditions, prepare an Updated PAR and submit the Emergency Notification Form to the Emergency Coordinator for approval.
THIS JPM IS TIME CRITICAL Task Standard:
The operator will determine the PAR for the current conditions and complete the Emergency Power Plant Emergency Notification Form as reflected on the provided KEY within 15 minutes.
Required Materials:
None General
References:
RP/0/A/5700/000 (Classification of Emergency), Rev 22 RP/0/B/5700/029 (Notifications to Offsite Agencies from the Control Room), Rev 14 Handouts:
Handout 1: Initial Emergency Notification Form and associated paperwork.
Handout 2: RP/0/B/5700/029 (Notifications to Offsite Agencies from the Control Room).
Handout 3: Pre-printed Emergency Notification Forms for EAL # 4.1.G.1.
Time Critical Task:
YES (Enclosure 4.2 of RP/0/B/5700/029 states that Follow-up messages in the General Emergency classification that involve an upgrade in PARs must be communicated to the offsite agencies as soon as possible and within 15 minutes).
Validation Time:
15 minutes NOTE:
An Answer KEY is provided Page 8 of this JPM.
2015 Admin - JPM A4 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 (Last Page of this JPM), and Handouts 1-3.
START TIME:
STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1
(RP/0/B/5700/029,.2, Steps 1-2.4) Obtain ENF Form start completing the Follow Up Message.
The operator addresses.2, Completion and Transmission of a Follow-Up Message.
The operator completes lines 1-4 of the ENF in accordance with the attached KEY (Page 8 of this document)
- 2 (Enclosure 4.2, Step 2.5)
Update the PAR using page 2 of 4, Expanded PAR Determination, of.4 Protective Action Recommendation.
The operator enters the Flowchart from the Initial PAR.
The operator recognizes that the reason to reassess the PAR is because of Bullet 3 (Shift in 15-Minute average wind direction resulting in additional sectors being affected).
The operator recognizes that there is NOT a Hostile Action Based event in progress, and proceeds Initial Conditions).
The operator recognizes that there is NOT a known offsite impediment to evacuation, and proceeds (Initial Conditions).
2015 Admin - JPM A4 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
- 2 (Contd)
The operator recognizes that there is NOT a short-term release in progress, and proceeds (Initial Conditions).
The operator recognizes that a General Emergency has been declared (Initial Conditions) and using Table 1, and a Wind Direction of 88o, determines that PAZ B, C, D, L, M, N, O, and R must be evacuated.
The operator recognizes that PAZ A has already been evacuated, and cannot be removed.
The operator recognizes that the RP Dose Projected Dose Assessments are still about 20 minutes away.
The operator completes line 5 of the ENF in accordance with the attached KEY (Page 8 of this document)
- 3 (RP/0/B/5700/029,.2, Steps 2.6 -
2.13) Continue completing the Follow Up Message.
The operator completes lines 6-13 of the ENF in accordance with the attached KEY (Page 8 of this document) 2015 Admin - JPM A4 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
- 4 (RP/0/B/5700/029,.2, Steps 2.14)
Complete the Follow Up Message.
The operator recognizes that the follow-Up Message will change the PAR, and proceeds to Line 17 (EC Approval).
The operator submits the ENF to the Examiner in accordance with the attached KEY (Page 8 of this document)
Terminating Cue:
Evaluation on this JPM is complete.
TIME CRITICAL STOP TIME:
2015 Admin - JPM A4 SRO NUREG 1021, Revision 9
Appendix C Page 7 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.:
2015 Admin - JPM A4 SRO Examinees Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to Complete:
Question Documentation:
Result:
SAT UNSAT Examiners Signature:
Date:
2015 Admin - JPM A4 SRO NUREG 1021, Revision 9
Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION KEY:
.2 Step #
Block How Completed 2.1.1 Drill/Actual Event Operator checks Actual Event.
2.1.2 Message #
The operator enters 02 (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 B (Follow-Up).
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 D (General Emergency) is already shaded in.
2.4.2 EAL #
Operator checks 4.1.G.1 is already written in.
2.4.3 EAL Description Operator checks that the following statement is written in: Loss of All Three Fission Product Barriers. Plant Operators will recommend protective actions for the public.
2.5.1 Protective Action Recommendations Operator checks in B and C ONLY.
Evacuate: A, B, C, D, L, M, N, O, and R within a 2-Mile Radius and 2-5 Miles downwind.
Shelter: None 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) or C (Degrading).
2.9.1 Wind Direction The operator records 88.7 degrees 2.9.2 Wind Speed The operator records 12 mph 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, 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 T-10, Today. The operator records that Unit 2 is at 100%
power.
2.13 Remarks Left Blank RED denotes Critical Information 2015 Admin - JPM A4 SRO NUREG 1021, Revision 9
Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions:
Unit 2 is at 100% power.
A LOCA inside containment has occurred on Unit 1.
The Emergency Coordinator declared a General Emergency per RP/0/A/5700/000, Enclosure 4.1, EAL # 4.1.G.1 (Loss of All Three Barriers).
An Emergency Release from Containment is in progress due to a piping penetration failure.
An Emergency Notification Form, along with the initial PAR was sent at the appropriate time.
Due to a shift in the 15-minute average wind direction, a re-assessment of the Initial PAR is being made.
The following conditions exist 30 minutes after the start of the event:
The wind speed is 12 mph.
The wind direction is 88.7o.
EMF51 A and B reading is 200 R/hr.
An RP Dose Assessment will be completed in 20 minutes.
Security Reports that there are no security related events in progress, and site evacuation is progressing as expected.
The Communicator is reporting that off-site agencies are reporting that evacuations are proceeding as expected.
INITIATING CUE:
Based on the present conditions, prepare an Updated PAR and submit the Emergency Notification Form to the Emergency Coordinator for approval.
THIS JPM IS TIME CRITICAL NUREG 1021, Revision 9