ML13301A727
| ML13301A727 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/23/2013 |
| From: | NRC/RGN-II |
| To: | South Carolina Electric & Gas Co |
| References | |
| NJPA-042B | |
| Download: ML13301A727 (80) | |
Text
2013 NRC RO/SRO Common A3: CALCULATE EXPOSURE STAY TIMES V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE CANDIDATE:
EXAMINER:
JPM NO:
NJPA-042B APPROVAL:
APPROVAL DATE:
REV NO:
2 Wednesday, June 26, 2013 Page 1 of 8
TASK:
343-029-03-02 PREFERRED EVALUATION METHOD PERFORM EVALUATION TIME 15 TIME CRITICAL NO TASK STANDARD:
Determines stay time as follows:
Operator 1: 10.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (10-10.2)
Operator 2: 12.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (12-12.6)
Operator 3: 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (5)
PREFERRED EVALUATION LOCATION CLASSROOM TIME START:
TIME FINISH:
PERFORMANCE RATING:
SAT:
UNSAT:
PERFORMANCE TIME:
EXAMINER:
SIGNATURE DATE 10CFR55:
45.a.10 ASSESS EXPOSURE LIMITS OF PERSONNEL FOR ASSIGNED DUTIES TOOLS:
Survey map of area.
CALCULATOR HPP-0153 ADMINISTRATIVE EXPOSURE LIMITS
REFERENCES:
TERMINATING CUE:
Applicant has determined stay time for each of the three workers or has handed in JPM.
CANDIDATE:
HPP-153 ADMINISTRATIVE EXPOSURE LIMITS INDEX NO.
1940012304 Knowledge of radiation exposure limits under normal or emergency conditions.
3.2 3.7 2.3.4 Wednesday, June 26, 2013 Page 2 of 8
INITIATING CUES:
Calculate the available stay times for each of the three operators (if operator can complete work at all) so that work can be completed without approving an increase in access exposure limits. Assume that all work will be done at 1 foot from XVT00028-SI, COLD LEG INJECTION HEADER DRAIN VALVE.
INITIAL CONDITION:
Work is to be done in the vicinity of XVT00028-SI, COLD LEG INJECTION HEADER DRAIN VALVE. Three operators are available to perform the work..
The following are the accumulated total doses for the three operators.
Operator 1: 490 mr Operator 2: 370 mr Operator 3: 750 mr All the workers have been at VC Summer for the full year and have not visited any other nuclear site.
It is not desired to approve an increase in access exposure limits.
READ TO OPERATOR:
SAFETY CONSIDERATIONS:
None.
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.
INSTRUCTIONS TO OPERATOR HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME!
Wednesday, June 26, 2013 Page 3 of 8
STEPS Determines current exposure of each operator. (Given in initial conditions.)
No Operator 1: 490 mr Operator 2: 370 mr Operator 3: 750 mr CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
1 Determines initial administrative exposure limits for each operator of 1000 mr.
Evaluator Note: Applicant may incorrectly think limit is 500 mr (what the limit would be if the operator came from another plant and had not signed a NRC Form 4 yet). If so operator 3 would be said not to be able to do the task and shorter stay times would be calculated for Operator 1 and 2.
No CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
2 Wednesday, June 26, 2013 Page 4 of 8
Subtracts current exposure from administrative limit to determine available dose remaining for each operator.
No Operator 1: 1000-490 mr = 510 mr Operator 2: 1000-370 mr = 630 mr Operator 3: 1000-750 mr = 250 mr CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
3 Determines exposure rate at work site from survey map.
Evaluator Note: The applicant may incorrectly use 550 mr/hr. This is the on contact exposure rate on XVT00028-SI, COLD LEG INJECTION HEADER DRAIN VALVE. The initial cue directs that the applicant assume that the exposure rate at 1 foot from the valve be used.
No Determines exposure rate is 50 mr/hr.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
4 Wednesday, June 26, 2013 Page 5 of 8
Examiner ends JPM at this point.
Determines stay time by dividing exposure left by exposure rate.
Evaluator Note: The applicant may round these stay times but should not round the stay time up in the case of operator 2. Values in parentheses are allowed values.
Yes Operator 1: 510 mr/50 mr/hr = 10.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (10-10.2)
Operator 2: 630 mr/50 mr/hr = 12.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (12-12.6)
Operator 3: 250 mr/50 mr/hr = 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (5)
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
5 Wednesday, June 26, 2013 Page 6 of 8
JPM NO: NJPA-042B DESCRIPTION:
2013 NRC RO/SRO Common A3: CALCULATE EXPOSURE STAY TIMES IC SET:
INSTRUCTIONS:
COMMENTS:
JPM SETUP SHEET Wednesday, June 26, 2013 Page 7 of 8
INITIATING CUES:
Calculate the available stay times for each of the three operators (if operator can complete work at all) so that work can be completed without approving an increase in access exposure limits. Assume that all work will be done at 1 foot from XVT00028-SI, COLD LEG INJECTION HEADER DRAIN VALVE.
INITIAL CONDITION:
Work is to be done in the vicinity of XVT00028-SI, COLD LEG INJECTION HEADER DRAIN VALVE. Three operators are available to perform the work..
The following are the accumulated total doses for the three operators.
Operator 1: 490 mr Operator 2: 370 mr Operator 3: 750 mr All the workers have been at VC Summer for the full year and have not visited any other nuclear site.
It is not desired to approve an increase in access exposure limits.
OPERATOR INSTRUCTIONS:
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
JPM BRIEFING SHEET Wednesday, June 26, 2013
2013 NRC RO A1-a: EOP-18.2 MAXIMUM ALLOWABLE HEAD VENT CALC V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE CANDIDATE:
EXAMINER:
JPM NO:
NJPA-026A APPROVAL:
APPROVAL DATE:
REV NO:
4 Wednesday, June 26, 2013 Page 1 of 8
TASK:
000-097-05-01 PREFERRED EVALUATION METHOD PERFORM EVALUATION TIME 15 TIME CRITICAL NO TASK STANDARD:
Calculation of Head Venting time of approximately 9.9 minutes (tolerance of 8.8-11.7 minutes).
PREFERRED EVALUATION LOCATION CLASSROOM TIME START:
TIME FINISH:
PERFORMANCE RATING:
SAT:
UNSAT:
PERFORMANCE TIME:
EXAMINER:
SIGNATURE DATE 10CFR55:
45.a.12 RESPOND TO VOIDS IN THE REACTOR VESSEL TOOLS:
EOP-18.2, Attachment 2, CALCULATION OF MAXIMUM ALLOWABLE HEAD VENTING TIME Calculator
REFERENCES:
TERMINATING CUE:
A maximum allowable head venting time is calculated.
CANDIDATE:
EOP-18.2 RESPONSE TO VOIDS IN REACTOR VESSEL INDEX NO.
0000112406 Knowledge of EOP mitigation strategies.
3.7 4.7 2.4.6 1940012125 Ability to interpret reference materials such as graphs, curves, tables, etc.
3.9 4.2 2.1.25 Wednesday, June 26, 2013 Page 2 of 8
INITIATING CUES:
The CRS has directed you to determine the maximum allowable head venting time using EOP-18.2, Attachment 2, CALCULATION OF MAXIMUM ALLOWABLE HEAD VENTING TIME.
INITIAL CONDITION:
A LOCA occurred from 100% power.
The crew transitioned to EOP-18.2, RESPONSE TO VOIDS IN REACTOR VESSEL.
The following conditions exist:
- 1. RB Pressure is 0.9 psig on PI-950.
- 2. RB Temperature is 148°F on TI-9201A
- 3. RB Temperature is 146°F on TI-9203A.
- 4. Hydrogen Concentration is 2.1% on CI-8257
- 5. Hydrogen Concentration is 2.3% on CI-8258.
- 6. RCS Pressure is 310 psig on PI-402
- 7. RCS Pressure is 320 psig on PI-403.
READ TO OPERATOR:
SAFETY CONSIDERATIONS:
None WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.
INSTRUCTIONS TO OPERATOR HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME!
Wednesday, June 26, 2013 Page 3 of 8
STEPS Record values for the following parameters:
- a. TI-9201A, RB TEMP "F. "F
- b. TI-9203A, RB TEMP "F. "F
- c. CI-8257, RB H2 CONC %. %H2
- d. CI-8258, RB H2 CONC %. %H2
- f. PI-403, RCS WR PRESS PSIG. Psig Yes 148°F is entered for TI-9201A and 146°F for TI-9203A; 2.1 % Hydrogen Concentration is entered for CI-8257 and 2.3% for CI-8258; 310 psig is entered for PI-402 and 320 psig for PI-403.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
1 Wednesday, June 26, 2013 Page 4 of 8
Use the higher of the two readings recorded above to calculate:
- a. Reactor Building volume (at standard temperature and pressure):
RB AIR VOLUME = (1.84E6 ft3) x [492°R/(RB TEMP (°F) + 460)]
RB AIR VOLUME = ft3 Yes RB Air Volume is approximately 1.489E6 ft3 (1.45E6 - 1.5E6)
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
2 Maximum hydrogen volume to be vented (when RB H2 CONC is LESS THAN 3%):
MAX VENTED VOL = (3% - RB H2 CONC %) x (RB AIR VOLUME (STP)) ft3/100%
MAX VENTED VOL = ft3 Yes Max Vented Volume is approximately 1.0423E4 ft3. (10150-10500)
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
3 Wednesday, June 26, 2013 Page 5 of 8
Examiner ends JPM at this point.
From the graph on the next page, determine the hydrogen flow rate using the higher RCS pressure recorded from Step 1:
HYDROGEN FLOW RATE = SCFM Yes SCFM calculated to be approximately 1050 SCFM (based on 320 psig). Based on a tolerance of +/-
1/2 the smallest increment, the tolerance for RCS pressure would be 300-350 psig (unacceptable to read below 300 psig line), which results in a hydrogen flow rate tolerance of 900-1150 SCFM.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
4 Calculate maximum allowable head venting period:
MAXIMUM ALLOWABLE HEAD VENTING TIME = (MAX VENTED VOL) ft3 /(HYDROGEN FLOW RATE) SCFM MAXIMUM ALLOWABLE HEAD VENTING TIME = Minutes Yes A calculated Maximum Allowable Head Venting Time of approximately 9.9 minutes. Based on the tolerance of 900-1150 SCFM hydrogen flow rate and max hydrogen to be vented 10150-10500 ft3,
the maximum allowable venting time should be from 8.8 minutes to 11.7 minutes.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
5 Wednesday, June 26, 2013 Page 6 of 8
JPM NO: NJPA-026A DESCRIPTION:
2013 NRC RO A1-a: EOP-18.2 MAXIMUM ALLOWABLE HEAD VENT CALC IC SET:
INSTRUCTIONS:
Provide the examinee the following information:
- 1. RB pressure on PI-950 = 0.9psig
- 2. RB temperature on TI-9201A = 148 degrees F
- 3. RB temperature on TI-9203A = 146 degrees F
- 4. H2 concentration on CI-8257 = 2.1%
- 5. H2 concentration on CI-8258 = 2.3%
- 6. RCS pressure on PI-402 = 310psig
- 7. RCS pressure on PI-403 = 320psig COMMENTS:
Examinee must use the highest values provided for the calculation.
JPM SETUP SHEET Wednesday, June 26, 2013 Page 7 of 8
INITIATING CUES:
The CRS has directed you to determine the maximum allowable head venting time using EOP-18.2, Attachment 2, CALCULATION OF MAXIMUM ALLOWABLE HEAD VENTING TIME.
INITIAL CONDITION:
A LOCA occurred from 100% power.
The crew transitioned to EOP-18.2, RESPONSE TO VOIDS IN REACTOR VESSEL.
The following conditions exist:
- 1. RB Pressure is 0.9 psig on PI-950.
- 2. RB Temperature is 148°F on TI-9201A
- 3. RB Temperature is 146°F on TI-9203A.
- 4. Hydrogen Concentration is 2.1% on CI-8257
- 5. Hydrogen Concentration is 2.3% on CI-8258.
- 6. RCS Pressure is 310 psig on PI-402
- 7. RCS Pressure is 320 psig on PI-403.
OPERATOR INSTRUCTIONS:
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
JPM BRIEFING SHEET Wednesday, June 26, 2013
2013 NRC RO A1-b: PERFORM A QPTR CALCULATION WITH DROPPED ROD V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE CANDIDATE:
EXAMINER:
JPM NO:
NJPA-035 APPROVAL:
APPROVAL DATE:
REV NO:
5 Wednesday, June 26, 2013 Page 1 of 10
TASK:
015-004-02-01 PREFERRED EVALUATION METHOD PERFORM EVALUATION TIME 20 TIME CRITICAL No TASK STANDARD:
QPTR has been calculated between 1.02 and 1.05 This is due to potential rounding errors.
PREFERRED EVALUATION LOCATION CLASSROOM TIME START:
TIME FINISH:
PERFORMANCE RATING:
SAT:
UNSAT:
PERFORMANCE TIME:
EXAMINER:
SIGNATURE DATE 10CFR55:
45.a.13 PERFORM A QUADRANT POWER TILT RATIO (QPTR) CALCULATIO TOOLS:
STP-108.001, QUADRANT POWER TILT RATIO CALCULATOR FIGURE V-3A FROM CURVE BOOK
REFERENCES:
TERMINATING CUE:
STP-108.001 completed.
CANDIDATE:
STP-108.001 QUADRANT POWER TILT RATIO INDEX NO.
015000A104 Quadrant power tilt ratio 3.5 3.7 A1.04 1940012137 Knowledge of procedures, guidelines, or limitations associated with reactivity management.
4.3 4.6 2.1.37 Wednesday, June 26, 2013 Page 2 of 10
INITIATING CUES:
The Shift Supervisor directs you, as the Reactor Operator, to perform a QPTR surveillance test, in accordance with STP-108.001, QUADRANT POWER TILT RATIO step 6.2.
INITIAL CONDITION:
The plant was operating at 100% power.
Control Bank B Rod F4 has dropped.
Control Bank D position is 230 steps.
IPCS is not available.
The following detector currents and indicated power readings exist on the power range NI's with them selected to 4000 micro-A/SLOW:
N-41 Detector A: 255 Detector B: 257 Power: 95%
N-42 Detector A: 297 Detector B: 307 Power: 96%
N-43 Detector A: 254 Detector B: 264 Power: 86%
N-44 Detector A: 341 Detector B: 315 Power: 96%
READ TO OPERATOR:
SAFETY CONSIDERATIONS:
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.
INSTRUCTIONS TO OPERATOR HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME!
Wednesday, June 26, 2013 Page 3 of 10
STEPS Record the expected detector current for 100% power for each excore detector using VCS Curve Book Figure V-3A.
Evaluator Note: FIGURE V-3A should be part of the JPM package for classroom performance.
Yes Locates Figure V-3A in the VCS Curve Book. Records the detector current values for 100% power from the Figure V-3A that is provided by the examiner. (Detector A is the upper detector, Detector B is the lower detector.)
N41 Detector A: 264.52 Detector B: 275.75 N42 Detector A: 302.78 Detector B: 322.71 N43 Detector A: 288.02 Detector B: 307.82 N44 Detector A: 346.28 Detector B: 330.10 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
1 Ensure that all detector range selector switches are selected to 4000 microA/SLOW.
Evaluator Note: The initial conditions of the JPM provide this information.
Yes Determines that data given in the initial conditions was taken at the right settings.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
2 Wednesday, June 26, 2013 Page 4 of 10
Record the actual excore detector readings from the digital meters on Attachment II.
Evaluator Note: The initial conditions of the JPM provide this information.
Yes Records on Attachment II of STP-108.001.
N41 Detector A: 255 Detector B: 257 N42 Detector A: 297 Detector B: 307 N43 Detector A: 254 Detector B: 264 N44 Detector A: 341 Detector B: 315 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
3 Record Reactor Power on Attachment II.
Evaluator Note: A note on Attachment II states that with IPCS not available reactor power should come from the NI's. The applicant may record any number of power readings (between 86 and 100%) because the dropped rod has caused different NI readings.
Yes Records reactor power on Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
4 Wednesday, June 26, 2013 Page 5 of 10
Record Control Bank D rod position on Attachment II.
Evaluator Note: Control Bank D position is given as part of initial conditions Yes Records "230" on Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
5 Divide actual readings by expected currents to get normalized readings.
Examiner Note: See key for expected numbers.
Yes Divides actual Detector A current by the Expected Upper Current at 100% for N41, N42, N43 and N44 and records on Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
6 Wednesday, June 26, 2013 Page 6 of 10
Divide the sum of the normalized readings by the number of detectors to obtain average normalized reading.
Examiner Note: See key for expected numbers.
Yes Adds normalized readings for N41, N42, N43, and N44 (Detector "A"s) and records on Attachment II.
Divides that value by 4 to obtain the average normalized reading and records that value on Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
7 Divide the highest normalized reading by the average normalized reading to obtain quadrant power tilt ratio.
Examiner Note: See key for expected numbers.
Yes Divides the maximum normalized reading by the average normalized reading and records on Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
8 Wednesday, June 26, 2013 Page 7 of 10
Examiner ends JPM at this point.
Record the larger of the upper and lower quadrant power tilt ratio.
Examiner Note: See key for expected numbers.
Yes Record the larger of the upper and lower quadrant power tilt ratio on Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
9 Complete Attachment I and attach Attachments I and II to the STTS sheet.
Examiner Cue: Cue applicant that another operator will perform the independent verification.
Yes Signs and dates Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
10 Wednesday, June 26, 2013 Page 8 of 10
JPM NO: NJPA-035 DESCRIPTION:
2013 NRC RO A1-b: PERFORM A QPTR CALCULATION WITH DROPPED ROD IC SET:
INSTRUCTIONS:
The values inthis JPM will need to be verified for the NI detectors to be from the Curve book Fig. V-3A Revision dated 4/25/2013. If the Curve book contains a later revision, these values will need to be changed.
COMMENTS:
The "actual" values will need to be recalculated if the data sheet for expected value from the curve sheet get revised.
JPM SETUP SHEET Wednesday, June 26, 2013 Page 9 of 10
INITIATING CUES:
The Shift Supervisor directs you, as the Reactor Operator, to perform a QPTR surveillance test, in accordance with STP-108.001, QUADRANT POWER TILT RATIO step 6.2.
INITIAL CONDITION:
The plant was operating at 100% power.
Control Bank B Rod F4 has dropped.
Control Bank D position is 230 steps.
IPCS is not available.
The following detector currents and indicated power readings exist on the power range NI's with them selected to 4000 micro-A/SLOW:
N-41 Detector A: 255 Detector B: 257 Power: 95%
N-42 Detector A: 297 Detector B: 307 Power: 96%
N-43 Detector A: 254 Detector B: 264 Power: 86%
N-44 Detector A: 341 Detector B: 315 Power: 96%
OPERATOR INSTRUCTIONS:
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
JPM BRIEFING SHEET Wednesday, June 26, 2013
2013 NRC RO A2: PERFORM "A" TRAIN CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST.
V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE CANDIDATE:
EXAMINER:
JPM NO:
NJPA-209 APPROVAL:
APPROVAL DATE:
REV NO:
2 Wednesday, June 26, 2013 Page 1 of 18
TASK:
088-003-02-01 PREFERRED EVALUATION METHOD PERFORM EVALUATION TIME 20 TIME CRITICAL NO TASK STANDARD:
Performs STP and properly records stroke times in accordance with STP-124.001, CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST PREFERRED EVALUATION LOCATION SIMULATOR TIME START:
TIME FINISH:
PERFORMANCE RATING:
SAT:
UNSAT:
PERFORMANCE TIME:
EXAMINER:
SIGNATURE DATE 10CFR55:
45.a.13 PERFORM CONTROL ROOM EMERGENCY VENT TEST TOOLS:
2 Stopwatches (in cal).
An additional operator to use as a timer during the test.
STP-124.001, CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST
REFERENCES:
TERMINATING CUE:
Section 6.1 is complete.
CANDIDATE:
INDEX NO.
1940012212 Knowledge of surveillance procedures.
3.7 4.1 2.2.12 Wednesday, June 26, 2013 Page 2 of 18
INITIATING CUES:
The CRS directs you to perform STP-124.001, CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST, Section 6.1 and to restore the "A" train to operation after the test. Another operator is available to measure stroke times for XVB00004A-AH, CONTROL RM OUTSIDE AIR INTAKE ISOL VLV.
INITIAL CONDITION:
100% power MOL. Monthly testing of the "A" train of control room emergency filtration system is required in accordance with STP-124.001, CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST. Local verification of valve position indication is not required. RM-A1 is operable and is NOT being testing in parallel using STP-360.032, CONTROL ROOM SUPPLY AIR ATMOSPHERE RADIATION MONITOR. "A" train Control Room Normal Air Handling unit is in service in accordance with SOP-505, CONTROL BUILDING VENTILATION SYSTEM.
READ TO OPERATOR:
SAFETY CONSIDERATIONS:
None.
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.
INSTRUCTIONS TO OPERATOR HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME!
Wednesday, June 26, 2013 Page 3 of 18
STEPS Procedure Note:
- a. Section 6.1 performs Train A Control Room Emergency Filtration System testing.
- b. Section 6.2 performs Train B Control Room Emergency Filtration System testing.
- c. Section 6.3 performs local verification of valve position indication.
Record all calibration data on Attachment IA as required.
Evaluator Note: Due to initial cue the applicant will only perform Section 6.1 of the procedure.
Yes Records calibration data about two stopwatches on Attachment IA.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
1 Ensure that XFN-32A, SPLY FAN A, is in service.
Yes Verifies red light lit, green light off for XFN-32A.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
2 Wednesday, June 26, 2013 Page 4 of 18
Start XFN-30A, EMERG FLTR FAN A.
Evaluator Note: The switch has to be held in start until the dampers open and then the fan will start.
Yes XFN-30A taken to start and held there. Verifies red light lit green light off.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
3 Record XFN-30A, EMERG FLTR FAN A, start time on Attachment IA.
Yes Records start time on Attachment IA.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
4 Wednesday, June 26, 2013 Page 5 of 18
Record the following damper positions on Attachment IA:
- 1) XDP-22A-AH.
- 2) XDP-23A-AH.
- 3) XDP-24A-AH.
Yes Records the following positions on Attachment IA:
- 1) XDP-22A-AH: CLOSED
- 2) XDP-23A-AH: OPEN
- 3) XDP-24A-AH: OPEN CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
5 Verify the outside air intake flow is less than 1000 CFM on FI-9405A, CR OA FLOW A CFM.
Yes Verifies flow on FI-9405A is <1000 CFM.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
6 Wednesday, June 26, 2013 Page 6 of 18
Verify a positive pressure of greater than or equal to 0.125 inch is being maintained as indicated on IPS9419-AH, CONT RM RELIEF HI/LO D/P ALARM SWITCH (CB-463).
Evaluator Cue: Report that IPS9419-AH, CONT RM RELIEF HI/LO D/P ALARM SWITCH (CB-463) reads 0.15 inch and stable.
Evaluator Note: This instrument is not modeled in the simulator and that is why this information is required to be cued.
Yes Determines that positive pressure is 0.15 inches.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
7 Wednesday, June 26, 2013 Page 7 of 18
Procedure Note: Outside air is required to be isolated if RM-A1 is inoperable. RM-A1 is inoperable if STP-360.032, Control Room Supply Air Atmosphere Radiation Monitor is being performed in parallel with this procedure.
Isolate outside air by placing the following switches to ISOL:
- 1) LOOP B ISOL TRAIN A.
- 2) LOOP B ISOL TRAIN B.
- 3) LOOP A ISOL TRAIN A.
- 4) LOOP A ISOL TRAIN B.
Evaluator Cue: Due to initial conditions RM-A1 will remain operable because STP-360.032 is not being performed in parallel.
Yes Places the following switches to ISOL:
- 1) LOOP B ISOL TRAIN A.
- 2) LOOP B ISOL TRAIN B.
- 3) LOOP A ISOL TRAIN A.
- 4) LOOP A ISOL TRAIN B.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
8 Wednesday, June 26, 2013 Page 8 of 18
Continue running the equipment for a minimum of 15 minutes.
Evaluator Cue: Cue applicant that 15 minutes have elapsed.
Yes Simulates running emergency ventilation for 15 minutes.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
9 Wednesday, June 26, 2013 Page 9 of 18
Procedure Note:
- 1) If STP-360.032, Control Room Supply Air Atmosphere Radiation Monitor is being performed in parallel with this procedure, ensure it has been completed satisfactorily prior to securing XFN-30A-AH, EMERG FLTR FAN A.
- 2) Stopping XFN-30A-AH, EMERG FLTR FAN A, will trip XFN-32A-AH, SPLY FAN A, and close XVB-3A-AH and XVB-4A-AH.
- 3) The stroke time testing of XVB00003A-AH and XVB00004A-AH must be performed concurrently with the stopping of XFN-30A-AH, EMERG FLTR FAN A. This will require two operators to simultaneously time closed XVB-3A-AH and XVB-4A-AH.
- 4) Placing XFN-30A, EMERG FLTR FAN A in STOP will activate annunciator window XCP-6210-LCB3 point 20-27, TRAIN A BYP.
Stop XFN-30A, EMERG FLTR FAN A, and measure the stroke time in the fail safe direction to the nearest 0.1 second, from switch actuation until the closed status light is lit and the open status light goes out for the following dampers:
- 1) XVB-3A-AH.
- 2) XVB-4A-AH.
Evaluator Cue: Cue applicant that another operator will time XVB-4A-AH. Cue applicant after XFN-30A is stopped that XVB-4A-AH closed in 1.1 seconds.
Yes Stops XFN-30A, EMERG FLTR FAN and times closure of XVB-3A-AH.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
10 Wednesday, June 26, 2013 Page 10 of 18
Record the following on Attachment IA:
- 1) The closed stroke time for XVB00003A-AH.
- 2) The closed stroke time for XVB00004A-AH.
- 3) The stop time for XFN-30A, EMERG FLTR FAN A.
Evaluator Note: Because of time compression used for the 15 minute run of the ventilation system the time that is recorded here may/or may not be correct.
Yes Records closure time for:
- 1) XVB-3A-AH ~1 seconds (Critical that <2.0 sec).
- 2) XVB-4A-AH. ~1 second (Critical that <2.0 sec).
- 3) XFN-30A, EMERG FLTR FAN A stop time.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
11 Return XFN-30A, EMERG FLTR FAN A, to AUTO.
Evaluator Note: It is critical that XFN-30A is returned to Auto to allow an automatic start in an accident.
Yes XFN-30A, EMERG FLTR FAN A is in AUTO.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
12 Wednesday, June 26, 2013 Page 11 of 18
Procedure Note: 1) Starting XFN-32A-AH, SPLY FAN A, will open XVB-3A-AH and XVB-4A-AH.
- 2) The stroke time testing of XVB00003A-AH and XVB00004A-AH must be performed concurrently with the starting of XFN-32A-AH, SPLY FAN A. This will require two operators to simultaneously time open XVB-3A-AH and XVB-4A-AH.
Restart XFN-32A, SPLY FAN A, and measure the stroke time to the nearest 0.1 second, from switch actuation until the open status light is lit and the closed status light goes out for the following dampers:
- 1) XVB-3A-AH.
- 2) XVB-4A-AH.
Evaluator Cue: Cue applicant that another operator will time XVB-4A-AH. Cue applicant after XFN-32A is started that XVB-4A-AH opened in 3.9 seconds.
Evaluator Note: Applicant must hold the fan in start until the dampers open and the fan starts.
Yes Starts XFN-32A, EMERG FLTR FAN and times opening of XVB-3A-AH.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
13 Wednesday, June 26, 2013 Page 12 of 18
Record the following on Attachment IA:
- 1) The open stroke time for XVB00003A-AH.
- 2) The open stroke time for XVB00004A-AH.
Evaluator Cue: If applicant determines that open stroke time requires an immediate retest, cue applicant to continue with this test to close it out and the CRS will direct another operator to perform the retest.
Yes Records opening time for:
- 1) XVB-3A-AH. (critical that be between 4.3 and 10.0 seconds, malfunction is for 7 seconds).
- 2) XVB-4A-AH. (critical that is <5.8 seconds).
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
14 Wednesday, June 26, 2013 Page 13 of 18
Record the following damper positions on Attachment IA:
- 1) XDP-22A-AH.
- 2) XDP-23A-AH.
- 3) XDP-24A-AH.
Yes Records the following positions on Attachment IA:
- 1) XDP-22A-AH: OPEN
- 2) XDP-23A-AH: CLOSED
- 3) XDP-24A-AH: CLOSED CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
15 Verify that the TRAIN A BYP annunciator is clear for ESF VENTILATING SYSTEMS BYPASSED, and record the status on Attachment IA.
Yes Records on Attachment IA that TRAIN A BYP annunciator is clear.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
16 Wednesday, June 26, 2013 Page 14 of 18
Momentarily place the following CMPT, RELAY AND SAS/CPU-1,2 ventilation switches to OA:
- 1) CHANNEL A.
- 2) CHANNEL B.
Yes Places the following CMPT, RELAY AND SAS/CPU-1,2 ventilation switches to OA:
- 1) CHANNEL A.
- 2) CHANNEL B.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
17 Momentarily place the following CONTROL ROOM VENTILATION switches to OA:
- 1) LOOP A ISOL TRAIN A.
- 2) LOOP A ISOL TRAIN B.
- 3) LOOP B ISOL TRAIN A.
- 4) LOOP B ISOL TRAIN B.
Yes Places the following CONTROL ROOM VENTILATION switches to OA:
- 1) LOOP A ISOL TRAIN A.
- 2) LOOP A ISOL TRAIN B.
- 3) LOOP B ISOL TRAIN A.
- 4) LOOP B ISOL TRAIN B.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
18 Wednesday, June 26, 2013 Page 15 of 18
Examiner ends JPM at this point.
Restore Control Room ventilation to the desired train in service per SOP-505.
Yes Determines from the initial cue that it is desired to leave "A" train running and that it is already in service.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
19 Wednesday, June 26, 2013 Page 16 of 18
JPM NO: NJPA-209 DESCRIPTION:
2013 NRC RO A2: PERFORM "A" TRAIN CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST.
IC SET:
338/10 INSTRUCTIONS:
Start with IC-10.
Event #1:
X16I036S==1 VLV-AH131P Final =0% Ramp=4 sec Delete in 1 sec.
Event #2:
X16I035T==1 VLV-AH131P Final =100% Ramp=7 sec Delete in 1 sec.
Saved to IC-338 for 2013 NRC Exam.
COMMENTS:
JPM SETUP SHEET Wednesday, June 26, 2013 Page 17 of 18
INITIATING CUES:
The CRS directs you to perform STP-124.001, CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST, Section 6.1 and to restore the "A" train to operation after the test. Another operator is available to measure stroke times for XVB00004A-AH, CONTROL RM OUTSIDE AIR INTAKE ISOL VLV.
INITIAL CONDITION:
100% power MOL. Monthly testing of the "A" train of control room emergency filtration system is required in accordance with STP-124.001, CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST. Local verification of valve position indication is not required. RM-A1 is operable and is NOT being testing in parallel using STP-360.032, CONTROL ROOM SUPPLY AIR ATMOSPHERE RADIATION MONITOR. "A" train Control Room Normal Air Handling unit is in service in accordance with SOP-505, CONTROL BUILDING VENTILATION SYSTEM.
OPERATOR INSTRUCTIONS:
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
JPM BRIEFING SHEET Wednesday, June 26, 2013
2013 NRC SRO A1-a: PERFORM NIS POWER RANGE HEAT BALANCE V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE CANDIDATE:
EXAMINER:
JPM NO:
NJPA-066C APPROVAL:
APPROVAL DATE:
REV NO:
2 Wednesday, June 26, 2013 Page 1 of 11
TASK:
015-007-02-01 PREFERRED EVALUATION METHOD PERFORM EVALUATION TIME 40 TIME CRITICAL No TASK STANDARD:
The applicant determines that reactor power is between 26.3% and 26.5%.
PREFERRED EVALUATION LOCATION CLASSROOM TIME START:
TIME FINISH:
PERFORMANCE RATING:
SAT:
UNSAT:
PERFORMANCE TIME:
EXAMINER:
SIGNATURE DATE 10CFR55:
45.a.4 PERFORM CALORIMETRIC AND HEAT BALANCE CALCULATION TOOLS:
STP-102.002, NIS POWER RANGE HEAT BALANCE Steam Tables Station Curve Book Figure V-16.
REFERENCES:
TERMINATING CUE:
Reactor Power is calculated or the JPM is returned to the examiner.
CANDIDATE:
STP-102.002 NIS POWER RANGE HEAT BALANCE INDEX NO.
015000A101 NIS calibration by heat balance 3.5 3.8 A1.01 1940012145 Ability to identify and interpret diverse indications to validate the response of another indicator.
4.3 4.3 2.1.45 Wednesday, June 26, 2013 Page 2 of 11
INITIATING CUES:
Calculate Reactor Power in percent using STP-102.002 Attachment III, REACTOR POWER CALCULATION.
INITIAL CONDITION:
The plant is being started up after an outage. The plant is at 25%
power. GOP-4A, POWER OPERATION (MODE 1 - ASCENDING),
requires that STP-102.002, NIS POWER RANGE HEAT BALANCE be completed. Initial conditions for performance of STP-102.002 have been met. The CALM function on IPCS is not available. Pertinent plant data has been recorded on Attachment II.
READ TO OPERATOR:
SAFETY CONSIDERATIONS:
NONE.
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.
INSTRUCTIONS TO OPERATOR HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME!
Wednesday, June 26, 2013 Page 3 of 11
STEPS Calculates Feedwater flow rates.
Evaluator Note: K2002 is found on Figure V-16 of the station curve book to be 987.497.
Yes Calculates the following ranges for the various loops:
A Loop: 9.97E5 - 9.98E5 B Loop: 9.77E5 - 9.78E5 C Loop: 9.87E5 - 9.88E5 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
1 Calculates Blowdown Flow Rates.
Evaluator Note: K2001 is found on Figure V-16 of the station curve book to be 370.680.
Yes Calculates the following ranges for the various loops:
A Loop: 9200 - 9300 B Loop: 8100 - 8200 C Loop: 10000 - 10100 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
2 Wednesday, June 26, 2013 Page 4 of 11
Calculate Main Steam Flow Rates.
Yes Calculates the following ranges for the various loops:
A Loop: 9.87E5 - 9.89E5 B Loop: 9.68E5 - 9.70E5 C Loop: 9.76E5 - 9.78E5 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
3 Calculate Average Steam Pressures.
Yes Calculates the following ranges for the various loops:
A Loop: 1058 - 1059 B Loop: 1057 - 1058 C Loop: 1055 - 1056 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
4 Wednesday, June 26, 2013 Page 5 of 11
Convert Steam Pressures to PSIA.
Evaluator Note: K2040 is found on Figure V-16 of the station curve book to be 2.470.
Evaluator Note: K2057 is found on Figure V-16 of the station curve book to be 2.700.
Evaluator Note: K2000 is found on Figure V-16 of the station curve book to be 2.270.
Yes Calculates the following ranges for the various loops:
A Loop: 1075 - 1077 B Loop: 1074 - 1076 C Loop: 1072 - 1074 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
5 Determine Enthalpies of Saturated Steam.
Yes Calculates the following ranges for the various loops:
A Loop: 1189 - 1191 B Loop: 1189 - 1191 C Loop: 1189 - 1191 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
6 Wednesday, June 26, 2013 Page 6 of 11
Determines enthalpies of Feedwater.
Yes Calculates the following ranges for the various loops:
A Loop: 290 - 295 B Loop: 290 - 295 C Loop: 290 - 295 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
7 Determines Steam Generators Enthalpy Rise.
Yes Calculates the following ranges for the various loops:
A Loop: 899 - 901 B Loop: 899 - 901 C Loop: 899 - 901 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
8 Wednesday, June 26, 2013 Page 7 of 11
Determine Blowdown Heat Loss Evaluator Note: The blowdown heat loss is so small that it is not critical to it.
Evaluator Note: K2025 is found on Figure V-16 of the station curve book to be 544.670.
Yes Calculates the following items:
Total Blowdown Flow Rate: 74 Average Feedwater Enthalpy: 290 - 295 Blowdown Heat Loss: 5.4E 5.6E-3 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
9 Calculates Steam Generator Powers.
Yes Calculates the following ranges for the various loops:
A Loop: 260 - 261.2 B Loop: 255 - 256.2 C Loop: 257 - 258.3 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
10 Wednesday, June 26, 2013 Page 8 of 11
Examiner ends JPM at this point.
Calculate Reactor Power.
Evaluator Note: K2010 is found on Figure V-16 of the station curve book to be 3.189.
Evaluator Note: K2011 is found on Figure V-16 of the station curve book to be 0.027.
Evaluator Note: K2008 is found on Figure V-16 of the station curve book to be 14.757.
Evaluator Note: K2009 is found on Figure V-16 of the station curve book to be 0.477.
Yes Reactor power is calculated to be: 26.3 - 26.5%
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
11 Wednesday, June 26, 2013 Page 9 of 11
JPM NO: NJPA-066C DESCRIPTION:
2013 NRC SRO A1-a: PERFORM NIS POWER RANGE HEAT BALANCE IC SET:
INSTRUCTIONS:
COMMENTS:
JPM SETUP SHEET Wednesday, June 26, 2013 Page 10 of 11
INITIATING CUES:
Calculate Reactor Power in percent using STP-102.002 Attachment III, REACTOR POWER CALCULATION.
INITIAL CONDITION:
The plant is being started up after an outage. The plant is at 25%
power. GOP-4A, POWER OPERATION (MODE 1 - ASCENDING),
requires that STP-102.002, NIS POWER RANGE HEAT BALANCE be completed. Initial conditions for performance of STP-102.002 have been met. The CALM function on IPCS is not available. Pertinent plant data has been recorded on Attachment II.
OPERATOR INSTRUCTIONS:
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
JPM BRIEFING SHEET Wednesday, June 26, 2013
2013 NRC SRO A1-b: PERFORM A QPTR CALCULATION WITH DROPPED ROD V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE CANDIDATE:
EXAMINER:
JPM NO:
NJPA-035A APPROVAL:
APPROVAL DATE:
REV NO:
5 Wednesday, June 26, 2013 Page 1 of 11
TASK:
015-004-02-01 PREFERRED EVALUATION METHOD PERFORM EVALUATION TIME 20 TIME CRITICAL No TASK STANDARD:
QPTR has been calculated between 1.02 and 1.05 This is due to potential rounding errors.
PREFERRED EVALUATION LOCATION CLASSROOM TIME START:
TIME FINISH:
PERFORMANCE RATING:
SAT:
UNSAT:
PERFORMANCE TIME:
EXAMINER:
SIGNATURE DATE 10CFR55:
45.a.13 PERFORM A QUADRANT POWER TILT RATIO (QPTR) CALCULATIO TOOLS:
STP-108.001, QUADRANT POWER TILT RATIO CALCULATOR FIGURE V-3A FROM CURVE BOOK Technical Specifications
REFERENCES:
TERMINATING CUE:
STP-108.001 completed.
CANDIDATE:
STP-108.001 QUADRANT POWER TILT RATIO INDEX NO.
015000A104 Quadrant power tilt ratio 3.5 3.7 A1.04 1940012137 Knowledge of procedures, guidelines, or limitations associated with reactivity management.
4.3 4.6 2.1.37 Wednesday, June 26, 2013 Page 2 of 11
INITIATING CUES:
Perform a QPTR surveillance test, in accordance with STP-108.001, QUADRANT POWER TILT RATIO step 6.2 and determine if acceptance criteria are met.
INITIAL CONDITION:
The plant was operating at 100% power.
Control Bank B Rod F4 has dropped.
Control Bank D position is 230 steps.
IPCS is not available.
The following detector currents and indicated power readings exist on the power range NI's with them selected to 4000 micro-A/SLOW:
N-41 Detector A: 255 Detector B: 257 Power: 95%
N-42 Detector A: 297 Detector B: 307 Power: 96%
N-43 Detector A: 254 Detector B: 264 Power: 86%
N-44 Detector A: 341 Detector B: 315 Power: 96%
READ TO OPERATOR:
SAFETY CONSIDERATIONS:
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.
INSTRUCTIONS TO OPERATOR HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME!
Wednesday, June 26, 2013 Page 3 of 11
STEPS Record the expected detector current for 100% power for each excore detector using VCS Curve Book Figure V-3A.
Evaluator Note: FIGURE V-3A should be part of the JPM package for classroom performance.
Yes Locates Figure V-3A in the VCS Curve Book. Records the detector current values for 100% power from the Figure V-3A that is provided by the examiner. (Detector A is the upper detector, Detector B is the lower detector.)
N41 Detector A: 264.52 Detector B: 275.75 N42 Detector A: 302.78 Detector B: 322.71 N43 Detector A: 288.02 Detector B: 307.82 N44 Detector A: 346.28 Detector B: 330.10 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
1 Ensure that all detector range selector switches are selected to 4000 microA/SLOW.
Evaluator Note: The initial conditions of the JPM provide this information.
Yes Determines that data given in the initial conditions was taken at the right settings.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
2 Wednesday, June 26, 2013 Page 4 of 11
Record the actual excore detector readings from the digital meters on Attachment II.
Evaluator Note: The initial conditions of the JPM provide this information.
Yes Records on Attachment II of STP-108.001.
N41 Detector A: 255 Detector B: 257 N42 Detector A: 297 Detector B: 307 N43 Detector A: 254 Detector B: 264 N44 Detector A: 341 Detector B: 315 CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
3 Record Reactor Power on Attachment II.
Evaluator Note: A note on Attachment II states that with IPCS not available reactor power should come from the NI's. The applicant may record any number of power readings (between 86 and 100%) because the dropped rod has caused different NI readings.
Yes Records reactor power on Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
4 Wednesday, June 26, 2013 Page 5 of 11
Record Control Bank D rod position on Attachment II.
Evaluator Note: Control Bank D position is given as part of initial conditions Yes Records "230" on Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
5 Divide actual readings by expected currents to get normalized readings.
Examiner Note: See key for expected numbers.
Yes Divides actual Detector A current by the Expected Upper Current at 100% for N41, N42, N43 and N44 and records on Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
6 Wednesday, June 26, 2013 Page 6 of 11
Divide the sum of the normalized readings by the number of detectors to obtain average normalized reading.
Examiner Note: See key for expected numbers.
Yes Adds normalized readings for N41, N42, N43, and N44 (Detector "A"s) and records on Attachment II.
Divides that value by 4 to obtain the average normalized reading and records that value on Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
7 Divide the highest normalized reading by the average normalized reading to obtain quadrant power tilt ratio.
Examiner Note: See key for expected numbers.
Yes Divides the maximum normalized reading by the average normalized reading and records on Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
8 Wednesday, June 26, 2013 Page 7 of 11
Record the larger of the upper and lower quadrant power tilt ratio.
Examiner Note: See key for expected numbers.
Yes Record the larger of the upper and lower quadrant power tilt ratio on Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
9 Complete Attachment I and attach Attachments I and II to the STTS sheet.
Examiner Cue: Cue applicant that another operator will perform the independent verification.
Yes Signs and dates Attachment II.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
No STEP:
10 Wednesday, June 26, 2013 Page 8 of 11
Examiner ends JPM at this point.
Determines if the ACCEPTANCE CRITERIA is met.
Evaluator Cue: If necessary, prompt the applicant to state if the QPTR is acceptable and if not the required action.
Yes Determines that QPTR exceeds 1.02 and so acceptance criteria are not met. Does NOT initial Section 8.0 of Attachment I. Determines that action a of TS 3.2.4 applies.
- a. With the QUADRANT POWER TILT RATIO determined to exceed 1.02 but less than or equal to 1.09:
- 1. Calculate the QUADRANT POWER TILT RATIO at least once per hour until either:
a) The QUADRANT POWER TILT RATIO is reduced to within its limit, or b) THERMAL POWER Is reduced to less than 50% of RATED THERMAL POWER.
- 2. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:
a) Reduce the QUADRANT POWER TILT RATIO to within its limit, or b) Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of Indicated QUADRANT POWER TILT RATIO in excess of 1.0 and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- 3. Verify that the QUADRANT POWER TILT RATIO is within Its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- 4. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL power may proceed provided that the QUADRANT POWER TILT RATIO is verified within Its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified acceptable at 95% or greater RATED THERMAL POWER.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
11 Wednesday, June 26, 2013 Page 9 of 11
JPM NO: NJPA-035A DESCRIPTION:
2013 NRC SRO A1-b: PERFORM A QPTR CALCULATION WITH DROPPED ROD IC SET:
INSTRUCTIONS:
The values inthis JPM will need to be verified for the NI detectors to be from the Curve book Fig. V-3A Revision dated 4/25/2013. If the Curve book contains a later revision, these values will need to be changed.
COMMENTS:
The "actual" values will need to be recalculated if the data sheet for expected value from the curve sheet get revised.
JPM SETUP SHEET Wednesday, June 26, 2013 Page 10 of 11
INITIATING CUES:
Perform a QPTR surveillance test, in accordance with STP-108.001, QUADRANT POWER TILT RATIO step 6.2 and determine if acceptance criteria are met.
INITIAL CONDITION:
The plant was operating at 100% power.
Control Bank B Rod F4 has dropped.
Control Bank D position is 230 steps.
IPCS is not available.
The following detector currents and indicated power readings exist on the power range NI's with them selected to 4000 micro-A/SLOW:
N-41 Detector A: 255 Detector B: 257 Power: 95%
N-42 Detector A: 297 Detector B: 307 Power: 96%
N-43 Detector A: 254 Detector B: 264 Power: 86%
N-44 Detector A: 341 Detector B: 315 Power: 96%
OPERATOR INSTRUCTIONS:
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
JPM BRIEFING SHEET Wednesday, June 26, 2013
2013 NRC SRO A2: REVIEW "A" TRAIN CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST.
V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE CANDIDATE:
EXAMINER:
JPM NO:
NJPA-209A APPROVAL:
APPROVAL DATE:
REV NO:
2 Wednesday, June 26, 2013 Page 1 of 7
TASK:
088-003-02-01 PREFERRED EVALUATION METHOD PERFORM EVALUATION TIME 15 TIME CRITICAL NO TASK STANDARD:
Determines 4 of the 5 following errors/inoperabilities:
- 1) XFN-30 was not run for 15 min.
- 2) XDP-23A-AH did not reposition to CLOSED as desired at the end of the test.
- 3) TRAIN A BYP annunciator status was not clear at the end of the test.
- 4) XVB00003A-AH took too long to close.
- 5) XVB00003A-AH took too long to open.
PREFERRED EVALUATION LOCATION CLASSROOM TIME START:
TIME FINISH:
PERFORMANCE RATING:
SAT:
UNSAT:
PERFORMANCE TIME:
EXAMINER:
SIGNATURE DATE 10CFR55:
45.a.13 PERFORM CONTROL ROOM EMERGENCY VENT TEST TOOLS:
STP-124.001, CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST GTP-302, INSERVICE TESTING OF VALVES THIRD TEN YEAR INTERVAL
REFERENCES:
TERMINATING CUE:
Errors/inoperabilites are discovered or the applicant turns in the JPM.
CANDIDATE:
INDEX NO.
1940012212 Knowledge of surveillance procedures.
3.7 4.1 2.2.12 Wednesday, June 26, 2013 Page 2 of 7
INITIATING CUES:
The SS directs you to review the STP-124.001, CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST, and to determine if the acceptance criteria have been met.
INITIAL CONDITION:
100% power MOL. Monthly testing of the "A" train of control room emergency filtration system was required. RM-A1 remained operable and was not being testing in parallel. The crew performed STP-124.001, CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST, Section 6.1 and restored the "A" train to operation after the test.
READ TO OPERATOR:
SAFETY CONSIDERATIONS:
None.
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.
INSTRUCTIONS TO OPERATOR HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME!
Wednesday, June 26, 2013 Page 3 of 7
STEPS Determines that XFN-30 was not run for 15 min.
Yes Determines that XFN-30 was not run for 15 min.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
1 Determines that XDP-23A-AH did not reposition to CLOSED as desired at the end of the test.
Yes Determines that XDP-23A-AH did not reposition to CLOSED as desired at the end of the test.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
2 Wednesday, June 26, 2013 Page 4 of 7
Examiner ends JPM at this point.
Determines that TRAIN A BYP annunciator status was not clear at the end of the test.
Yes Determines that TRAIN A BYP annunciator status was not clear at the end of the test.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
3 Determines that XVB00003A-AH took too long to close and to open.
Evaluator Cue: If applicant asks for a retest in the open direction, cue the applicant that the retest will be handled by another operator and to continue to investigate the current test.
Yes Determines that XVB00003A-AH took too long to close and to open.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
4 Wednesday, June 26, 2013 Page 5 of 7
JPM NO: NJPA-209A DESCRIPTION:
2013 NRC SRO A2: REVIEW "A" TRAIN CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST.
IC SET:
INSTRUCTIONS:
COMMENTS:
JPM SETUP SHEET Wednesday, June 26, 2013 Page 6 of 7
INITIATING CUES:
The SS directs you to review the STP-124.001, CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST, and to determine if the acceptance criteria have been met.
INITIAL CONDITION:
100% power MOL. Monthly testing of the "A" train of control room emergency filtration system was required. RM-A1 remained operable and was not being testing in parallel. The crew performed STP-124.001, CONTROL ROOM EMERGENCY AIR CLEANUP SYSTEM OPERABILITY TEST, Section 6.1 and restored the "A" train to operation after the test.
OPERATOR INSTRUCTIONS:
HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.
JPM BRIEFING SHEET Wednesday, June 26, 2013
2013 NRC SRO A4: CLASSIFY EMERGENCY (CLASSROOM - ALERT - LOSS OF AC) (ENF)
V.C. SUMMER NUCLEAR STATION JOB PERFORMANCE MEASURE CANDIDATE:
EXAMINER:
JPM NO:
NJPA-805 APPROVAL:
APPROVAL DATE:
REV NO:
5 TIME CRITICAL JPM
TASK:
344-019-03-02 PREFERRED EVALUATION METHOD PERFORM EVALUATION TIME 30 TIME CRITICAL YES TASK STANDARD:
Emergency classification evaluated as an ALERT based on AC power capability to 7.2 KV ESF buses 1DA and 1 DB reduced to a single power source for more than 15 minutes. This is a time critical JPM and the declaration must be made within 15 minutes, and successful completion of EPP-002, Communication and Notification, Attachment I, Nuclear Power Plant Notification Form, must be made within 15 minutes after the emergency declaration.
PREFERRED EVALUATION LOCATION CLASSROOM TIME START:
TIME FINISH:
PERFORMANCE RATING:
SAT:
UNSAT:
PERFORMANCE TIME:
EXAMINER:
SIGNATURE DATE 10CFR55:
45.a.11 CLASSIFY EMERGENCY EVENTS REQUIRING EMERGENCY PLAN IMPLEMENTATION TOOLS:
EPP-002, Communication and Notification, Attachment I, Nuclear Power Plant Notification Form.
REFERENCES:
TERMINATING CUE:
Successful completion of the EPP-002, Communication and Notification, Attachment I, Nuclear Power Plant Notification Form.
CANDIDATE:
EPP-002 COMMUNICATION AND NOTIFICATION EPP-001 ACTIVATION AND IMPLEMENTATION OF THE EMERGENCY PLAN INDEX NO.
0000562429 Knowledge of the emergency plan.
3.1 4.4 2.4.29 0000562441 Knowledge of the emergency action level thresholds and classifications.
2.9 4.6 2.4.41 Wednesday, June 26, 2013 Page 2 of 7
INITIATING CUES:
- 1. Classify the plant event and write down your declaration on this sheet. Notify an examiner when this is done. You will be provided a package from the examiner at that time.
- 2. Complete a NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM (ENF) for the plant event.
INITIAL CONDITION:
THIS IS A DRILL.
0600:
The plant was operating at 100%.
DG "A" is tagged out for bearing repair (Day 1 of 2 Day repair).
Parr Hydro Plant 13.8 KV power is temporarily supplying ESF Bus 1DA.
0605:
Electrical Grid problems resulted in a 100% loss of load.
115 KV power to XTF-4 and XTF-5 is lost.
230 KV power to XTF-31 is lost.
The turbine has tripped.
All RCPs tripped.
The Reactor tripped Reactor Power is < 2% with a negative SUR.
DG "B" has started and is supplying ESF Bus 1DB.
It is currently 0615:
DG "B" just tripped on overspeed.
Met Data - Wind Direction is from 290 degrees Met Data - Wind Speed is 15 mph Met Data - Wind Stability is Class B Met Data - Raining - 0.25 inches accumulation.
THIS IS A DRILL.
READ TO OPERATOR:
SAFETY CONSIDERATIONS:
WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED.
THIS IS A TIME CRITICAL JPM!
INSTRUCTIONS TO OPERATOR HAND JPM BRIEFING SHEET TO OPERATOR AT THIS TIME!
Wednesday, June 26, 2013 Page 3 of 7
STEPS Evaluates plant conditions and classifies per EPP-001.
Evaluator Note: The applicant has 15 min from the end of the Plant Conditions brief, to event classification. If student does not explain basis for the classification, the evaluator must ask him to describe the basis. If the basis is not justified, this constitutes failure, even if the classification is correct, and within time.
Evaluator Note: After the declaration hand the applicant the necessary paperwork to complete the ENF.
Yes Classifies event as an ALERT based on:
- 1. AC power capability to 7.2 KV ESF buses 1DA and 1 DB reduced to a single power source for more than 15 minutes AND,
- 2. Any additional single power source failure will result in loss of all AC power to both 7.2 KV ESF buses.
Initiating Condition - SA1.1 Detection Method:
- 1. Single power source to 1 DA AND,
- 2. Single power source to 1 DB AND,
- 3. No backup power source available to 1DA or 1 DB for > 15 minutes CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
1 Wednesday, June 26, 2013 Page 4 of 7
Examiner ends JPM at this point.
Completes Notification Form from EPP-002, Attachment I Evaluator Note: The student has 15 min from the time of the declaration to complete attachment I from EPP-002.
Yes Successfully completes the Nuclear Power Plant Notification Form, EPP-002, Communication and Notification, Attachment I.
CUES:
SEQUENCED:
STEP STANDARD:
COMMENTS:
SAT UNSAT CRITICAL:
Yes STEP:
2 Wednesday, June 26, 2013 Page 5 of 7
ASSOCIATED DOCUMENTS:
N:\\Databases\\JPM\\JPA-805_ENF.docx JPM NO: NJPA-805 DESCRIPTION:
2013 NRC SRO A4: CLASSIFY EMERGENCY (CLASSROOM - ALERT - LOSS OF AC) (ENF)
IC SET:
INSTRUCTIONS:
The following items, as indicated on the Emergency Notification Form (ENF), are considered as "Critical Items":
- Class of Emergency
- Description of Emergency
- Wind Direction and Speed
- Whether Offsite Protective Measures are necessary
- Potentially affected population and areas
- Whether a release is taking place
- Date and Time of Emergency Declaration
- Whether the event is a Drill or Actual Event COMMENTS:
JPM SETUP SHEET Wednesday, June 26, 2013 Page 6 of 7
INITIATING CUES:
- 1. Classify the plant event and write down your declaration on this sheet. Notify an examiner when this is done. You will be provided a package from the examiner at that time.
- 2. Complete a NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM (ENF) for the plant event.
INITIAL CONDITION:
THIS IS A DRILL.
0600:
The plant was operating at 100%.
DG "A" is tagged out for bearing repair (Day 1 of 2 Day repair).
Parr Hydro Plant 13.8 KV power is temporarily supplying ESF Bus 1DA.
0605:
Electrical Grid problems resulted in a 100% loss of load.
115 KV power to XTF-4 and XTF-5 is lost.
230 KV power to XTF-31 is lost.
The turbine has tripped.
All RCPs tripped.
The Reactor tripped Reactor Power is < 2% with a negative SUR.
DG "B" has started and is supplying ESF Bus 1DB.
It is currently 0615:
DG "B" just tripped on overspeed.
Met Data - Wind Direction is from 290 degrees Met Data - Wind Speed is 15 mph Met Data - Wind Stability is Class B Met Data - Raining - 0.25 inches accumulation.
THIS IS A DRILL.
OPERATOR INSTRUCTIONS:
JPM BRIEFING SHEET Wednesday, June 26, 2013