ML15174A142
| ML15174A142 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/15/2015 |
| From: | Mcneil D NRC/RGN-III/DRS/OLB |
| To: | Xcel Energy |
| References | |
| Download: ML15174A142 (53) | |
Text
ADMIN JPM RO a Page 1 of 6 JPM-C.6-002 (Determining Power Reduction Based On Discharge Canal Temp) Rev. 1 JOB PERFORMANCE MEASURE (JPM)
SITE:
MONTICELLO NUCLEAR GENERATING PLANT JPM TITLE:
DETERMINING POWER REDUCTION BASED ON DISCHARGE CANAL TEMP JPM NUMBER:
JPM-C.6-002 REV.
1 RELATED PRA INFORMATION:
None TASK NUMBERS /
TASK TITLE(S):
CR999.275 Circulating Water System K/A NUMBERS:
2.1.20 Rating: SRO/RO:
4.6/4.6 APPLICABLE METHOD OF TESTING:
Discussion:
Simulate/walkthrough:
Perform:
EVALUATION LOCATION:
In-Plant:
Control Room:
Simulator:
Other:
Lab:
Time for Completion:
10 Minutes Time Critical:
No Alternate Path:
No TASK APPLICABILITY:
SRO:
RO:
NLO Additional site-specific signatures may be added as desired.
Developed by:
Developer Date Validated by:
Validator (See JPM Validation Checklist, Attachment 1)
Date Approved by:
Training Supervisor Date JPM BRIEFING/TURNOVER
ADMIN JPM RO a Page 2 of 6 JPM-C.6-002 (Determining Power Reduction Based On Discharge Canal Temp) Rev. 1 You may use any approved reference materials normally available including logs. Make all written reports, oral reports, and log entries as if the evolution is actually being performed.
EOP Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.
If this JPM is performed on the simulator, the JPM administrator should only give cues that are not indicated on the simulator. If simulator indication is sufficient to indicate the completion of a step, the JPM administrator should not have to give a cue to the trainee to continue the evolution.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
It is 1900 on a hot 98°F OCTOBER day.
Yesterdays high temperature was 74°F CWT103 (Discharge Canal Wtr Temp - High) is in alarm The Discharge Canal Daily Running Average temperature is reading 95.5°F.
Current Discharge Canal temperature is 96.6°F.
INITIATING CUES:
Using CARP CWT103, determine the amount of power reduction required to ensure that the Discharge Canal Daily Running Average temperature discharge canal temperature (CWT103) is below the limit.
Assume a 10% reduction in reactor power will result in a 1°F reduction in discharge canal temperature.
ADMIN JPM RO a Page 3 of 6 JPM-C.6-002 (Determining Power Reduction Based On Discharge Canal Temp) Rev. 1 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
IMPORTANT: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step SHALL result in failure of this JPM, per FP-T-SAT-73 (Licensed Operator Requalification Program Examinations).
Performance Step: 1 Critical: N Refers to C.6-CWT103 (Discharge Canal Wtr Temp - High)
Standard:
Refers to C.6-CWT103 (Discharge Canal Wtr Temp - High)
Evaluator Cue:
Provide a copy of C.6-CWT103 Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 2 Critical: Y Procedure Step 1 Monitor CWT103 DR Discharge Canal Wtr Temp - Daily Running Avg to ensure that the permit limit of 80°F Dec through Feb, 85°F Mar and Nov, and 95°F Apr through Oct will not be exceeded.
Standard:
Determines that the limit for October is 95oF.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO a Page 4 of 6 JPM-C.6-002 (Determining Power Reduction Based On Discharge Canal Temp) Rev. 1 Performance Step: 3 Critical: N Procedure Step 2 During the summer, perform the following as needed to ensure that the Daily Running Average limit is not exceeded for the end of the day reading.
- a. Verify all available cooling tower fans are in service.
- b. Verify the following are fully closed:
- 1. CW-17 11 CT Riser Drn
- 2. CW-18 11 CT Riser Drn
- 3. CW-19 12 CT Riser Drn
- 4. CW-20 12 CT Riser Drn
- 5. CW-37 108 inch Hdr Drn
- 6. S-106A 11 Cooling Tower Drain Gate
- 7. S-106B 12 Cooling Tower Drain Gate
- 8. Cooling Tower Return Gates
- 9. Deicing Line
- c. Verify that the discharge structure gates are fully opened.
Standard:
Determined status of each item.
Evaluator Cue:
State that all available cooling tower fans are in service, all valves listed are closed and that the discharge structure gates are fully open.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 Critical: N Procedure Step 3 Perform the following during summer:
NOTE 1:
If CWT103 DR Discharge Canal Water Temperature Daily Running Average is less than 94.5°F at 0100, And no significant increase in temperature or humidity is forecast for today as compared to yesterday, Then no power drop should be required.
If CWT103 DR Discharge Canal Water Temp Daily Running Average is 94.5°F at 0100, And no rain or cooling trend is forecast for today as compared to yesterday, Then plant power should be reduced at least 10% from 0100 until such time as needed for the plant to be back at 100% power as specified by the system dispatcher or electric marketing.
Standard:
Determines no actions are required.
Evaluator Cue:
State CWT103 read 92.3°F at 0100.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO a Page 5 of 6 JPM-C.6-002 (Determining Power Reduction Based On Discharge Canal Temp) Rev. 1 Performance Step: 5 Critical: Y NOTE 2:
At 100% power, there is normally about a 30°F rise in circulating water temperature through the condenser. A 10% load drop would result in about a 3°F drop in circ water condenser outlet temperature but could result in only a 0.7 to 1.5°F drop in Discharge Canal temperature depending on how much cooling is being obtained through the cooling towers which is a function of wet bulb temperature.
Also, the Daily Average Discharge Canal water temperature limit is a time weighted average. The following formula can be used to assist in monitoring the discharge canal water temperature in order to determine if a power drop will be required.
[(x hr) (Running Daily Avg discharge temp at x hr)] +
[(24-x)(y)] = [(94.9°F) (24 hr)]
y = avg disch canal wtr temp for rest of day (x hr)(CWT103DR) + (24-x)(y) = 2277.6 Example, assume at 2000, CWT103 DR is 95.5°F: (20)(95.5°F) + (4)(y) =
2277.6 y = 91.9°F which means that the discharge canal water temperature needs to average 91.9°F for the remaining 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the day. If at 2000 the discharge canal water temperature is 95.9°F and if each 10% power drops results in a 1°F drop in discharge canal water temperature, this could require a 40% power drop.
- a. If a power drop is required to meet the Daily Avg Discharge Canal Wtr Temp limit, Then perform the following:
1). Notify Shift Supervisor 2). Notify System Dispatcher 3). Reduce plant power as needed Standard:
(19)(95.5) + (5)(y) = 2277.6 y = 92.6oF 96.6 - 92.6 = 4°F. At a 1°F reduction in canal temperatures for every 10%
reduction in power, this would require a 40% reduction in power or an average power level of 60%.
Evaluator Cue:
None Evaluator Note:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO a Page 6 of 6 JPM-C.6-002 (Determining Power Reduction Based On Discharge Canal Temp) Rev. 1 Performance Step: 6 Critical: N
- 2.
If the Daily Average limit is exceeded for the end of the day reading, Then notify the Gen Supt Oper, Supt Chem & Env Prot and the Gen Supt Engr. If one of these persons can NOT be contacted, notify the Plant Manager.
Standard:
Determines Average limit is NOT exceeded.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 7 Critical: N INFORM EVALUATOR THAT THE TASK HAS BEEN COMPLETED.
Standard:
Operator informs evaluator that the task is completed.
Evaluator Cue:
Acknowledge that the task has been completed.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues:
Stop Time:
ADMIN JPM RO b Page 1 of 6 JPM-FP-S-FMP-01-001 (Overtime Restrictions/Fatigue Management) Rev. 3 JOB PERFORMANCE MEASURE (JPM)
SITE:
MONTICELLO NUCLEAR GENERATING PLANT JPM TITLE:
OVERTIME RESTRICTIONS/FATIGUE MANAGEMENT JPM NUMBER:
JPM-FP-S-FMP-01-001 REV.
3 RELATED PRA INFORMATION:
None TASK NUMBERS /
TASK TITLE(S):
CR299.144 Adhere to the Requirements of Overtime Restrictions and Fitness for Duty Requirements K/A NUMBERS:
Generic 2.1.5 Rating: SRO/RO:
2.9/3.9 APPLICABLE METHOD OF TESTING:
Discussion:
Simulate/walkthrough:
Perform:
EVALUATION LOCATION:
In-Plant:
Control Room:
Simulator:
Other:
Lab:
Time for Completion:
15 Minutes Time Critical:
No Alternate Path:
No TASK APPLICABILITY:
SRO:
RO:
NLO Additional site-specific signatures may be added as desired.
Developed by:
Developer Date Validated by:
Validator (See JPM Validation Checklist, Attachment 1)
Date Approved by:
Training Supervisor Date JPM Number: JPM-FP-S-FMP-01-001
ADMIN JPM RO b Page 2 of 6 JPM-FP-S-FMP-01-001 (Overtime Restrictions/Fatigue Management) Rev. 3 JPM BRIEFING/TURNOVER You may use any approved reference materials normally available including logs. Make all written reports, oral reports, and log entries as if the evolution is actually being performed.
EOP Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.
If this JPM is performed on the simulator, the JPM administrator should only give cues that are not indicated on the simulator. If simulator indication is sufficient to indicate the completion of a step, the JPM administrator should not have to give a cue to the trainee to continue the evolution.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
You are a licensed operator The plant is at rated conditions No outages or power reductions are scheduled INITIATING CUES:
Review your proposed work schedule for the upcoming six weeks. Compare the proposed six week schedule with the normal six week schedule. Identify any proposed overtime, that if worked, will violate the requirements of FP-S-FMP-01 (10 CFR 26 Fatigue Management Fleet Procedure). (Assume NO waivers will be granted, NO overtime was worked in the previous six weeks and NO overtime is scheduled for the following six weeks.)
ADMIN JPM RO b Page 3 of 6 JPM-FP-S-FMP-01-001 (Overtime Restrictions/Fatigue Management) Rev. 3 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
IMPORTANT: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step SHALL result in failure of this JPM, per FP-T-SAT-73 (Licensed Operator Requalification Program Examinations).
Performance Step: 1 Critical: N Attains copy of six week rotating schedule and FP-S-FMP-01 (10 CFR 26 Fatigue Management Fleet Procedure).
Standard:
Locates procedure(s)
Evaluator Cue:
Provide the examinee the copy of fleet procedure (FP-S-FMP-01). The six week schedules are included on the examinee turnover sheet.
Evaluator Note:
The six week schedule is posted in the control room and the fleet procedure would be accessed via the company web in sharepoint. The examinee may also refer to OWI-01.01 for general shift schedule information (section 4.5)
Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO b Page 4 of 6 JPM-FP-S-FMP-01-001 (Overtime Restrictions/Fatigue Management) Rev. 3 Performance Step: 2 Critical: N FP-S-FMP-01 Section 5.1 (10 CFR 26 Work Hour Limits For Covered Individuals)
Section 5.1.1 The following limits apply to covered individuals regardless of unit status:
No more than 16 work hours in any 24-hour period.
No more than 26 work hours in any 48-hour period.
No more than 72 work hours in any 7-day period.
At least a 10-hour break between successive work periods or an 8-hour break when a break of less than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> is necessary to accommodate a crews schedule transition between work schedules.
A 34-hour break in any 9 day period (this limit may be incorporated into the following table of limits)
Section 5.1.2: During online operations, and without issuance of a waiver, an individuals required average minimum days off SHALL adhere to the requirements listed in Table 1 below (averaged over the shift cycle):
Operations 12-Hour Shift: 2.5 days off/week required
- 1. For the purposes of calculating an average number of days off, the duration of the shift cycle may not exceed six (6) weeks.
- 2. A normal operations day for a shift is a day when the unit is not in an outage when the shift starts.
Standard:
Locates and reviews sections 5.1.1 and 5.1.2 Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 3 Critical: N Reviews Week 1 of proposed schedule Standard:
Reviews schedule and determines that no overtime days are scheduled.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 Critical: N Reviews Week 2 of proposed schedule.
Standard:
Reviews schedule and recognizes one overtime day scheduled (Wednesday -Day Shift).
Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO b Page 5 of 6 JPM-FP-S-FMP-01-001 (Overtime Restrictions/Fatigue Management) Rev. 3 Performance Step: 5 Critical: Y Reviews Week 3 of proposed schedule.
Standard:
Reviews schedule and recognizes one overtime day scheduled (Tuesday - Day Shift). Non-Critical Portion Of Standard Recognizes that 72 work hours will be exceeded in a 7-day period.
Non-Critical Portion Of Standard Recognizes working this overtime day in conjunction with the overtime day in week 2 will violate 10CFR26 Overtime restrictions.
Evaluator Cue:
If notified of exceeding limit, acknowledge as supervision.
Evaluator Note:
This would result in 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> worked in a 7 day period.
NOTE: The examinee may wait until the end of the JPM to report the exceeded limit.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 6 Critical: N Reviews Week 4 of proposed schedule.
Standard:
Reviews schedule and determines that no overtime days are scheduled.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 7 Critical: N Reviews Week 5 of proposed schedule.
Standard:
Reviews schedule and determines that no overtime days are scheduled.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO b Page 6 of 6 JPM-FP-S-FMP-01-001 (Overtime Restrictions/Fatigue Management) Rev. 3 Performance Step: 8 Critical: Y Reviews Week 6 of proposed schedule.
Standard:
Reviews schedule and recognizes one overtime day scheduled (Saturday - Night Shift). Non-Critical Portion Of Standard Recognizes that 16 work hours will be exceeded in a 24-hour period. Non-Critical Portion Of Standard Recognizes that 26 work hours will be exceeded in a 48-hour period. Non-Critical Portion Of Standard Recognizes that an 10-hour break is necessary to accommodate schedule transition between work schedules. Non-Critical Portion Of Standard Recognizes working this overtime day will violate 10CFR26 Overtime restrictions.
Evaluator Cue:
If notified of exceeding limit, acknowledge as supervision.
Evaluator Note:
The operator would work 8 training hours from 0700 to 1500 on the week 6 Friday and then start at 1800 on Friday for the Saturday Night shift. This will be 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> worked from 0600 on Friday until 0700 on Saturday morning.
The operator would work 8 training hours from 0700 to 1500 on the week 6 Thursday and Friday and then an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from 1800 on Friday until 0600 on Saturday. This will be 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> worked from 0700 on Thursday until 0600 on Saturday morning.
The operator would only have a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> transition period between completed their training day on Friday and starting the Saturday Night Shift on Friday night at 1800.
The 34-hour break in any 9 day period limit is met throughout the proposed 6 week schedule.
The 2.5 days off per week requirement is met. A total of 16 days off are provided. Averaged over the 6 week period results in 2.67 days off per week.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues:
When examinee notifies the evaluator of the violations, if any, state JPM is complete.
Stop Time:
ADMIN JPM RO c Page 1 of 8 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 0 JOB PERFORMANCE MEASURE (JPM)
SITE:
MONTICELLO NUCLEAR GENERATING PLANT JPM TITLE:
INDEPENDENT VERIFICATION OF HPCI JPM NUMBER:
JPM-4 AWI-04.04.02-004 REV.
0 RELATED PRA INFORMATION:
None TASK NUMBERS /
TASK TITLE(S):
CR206.102 Perform the HPCI Pump Flow and Valve Tests K/A NUMBERS:
Generic 2.2.15 Rating: SRO/RO:
4.3/4.3.9 APPLICABLE METHOD OF TESTING:
Discussion:
Simulate/walkthrough:
Perform:
EVALUATION LOCATION:
In-Plant:
Control Room:
Simulator:
Other:
Lab:
Time for Completion:
15 Minutes Time Critical:
No Alternate Path:
No TASK APPLICABILITY:
SRO:
RO:
NLO Additional site-specific signatures may be added as desired.
Developed by:
Roman Becker Developer Date Validated by:
Validator (See JPM Validation Checklist, Attachment 1)
Date Approved by:
Training Supervisor Date
ADMIN JPM RO c Page 2 of 8 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 0 JPM BRIEFING/TURNOVER You may use any approved reference materials normally available including logs. Make all written reports, oral reports, and log entries as if the evolution is actually being performed.
EOP Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.
If this JPM is performed on the simulator, the JPM administrator should only give cues that are not indicated on the simulator. If simulator indication is sufficient to indicate the completion of a step, the JPM administrator should not have to give a cue to the trainee to continue the evolution.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
0255-06-IA-1 (HPCI Quarterly Pump And Valve Tests) is complete through STEP 77.
Independent verification is now required.
You are an extra licensed operator and did not participate in the test up to this point.
INITIATING CUES:
The CRS directs you to perform independent verification, for the components in the Control Room by performing STEP 78 of Test 0255-06-IA-1 (HPCI Quarterly Pump & Valve Test).
ADMIN JPM RO c Page 3 of 8 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 0 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
IMPORTANT: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step SHALL result in failure of this JPM, per FP-T-SAT-73 (Licensed Operator Requalification Program Examinations).
Performance Step: 1 Critical: N Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- a. MO-2034 open, handswitch 23A-S2 in NEUTRAL.
Standard:
Operator observes MO-2034 open, handswitch 23A-S2 in NEUTRAL.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 2 Critical: N Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- b. MO-2035 open, handswitch 23A-S3 in AUTO.
Standard:
Operator observes MO-2035 open, handswitch 23A-S3 in AUTO.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO c Page 4 of 8 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 0 Performance Step: 3 Critical: N Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- c. MO-2036 closed, handswitch 23A-S1 in AUTO.
Standard:
Operator observes MO-2036 closed, handswitch 23A-S1 in AUTO.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 Critical: N Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- d. MO-2061 closed, handswitch 23A-S14 in AUTO.
Standard:
Operator observes MO-2061 closed, handswitch 23A-S14 in AUTO Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 5 Critical: N Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- e. MO-2062 closed, handswitch 23A-S13 in AUTO.
Standard:
Operator observes MO-2062 closed, handswitch 23A-S13 in AUTO.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO c Page 5 of 8 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 0 Performance Step: 6 Critical: N Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- f.
MO-2063 open, handswitch 23A-S4 in AUTO.
Standard:
Operator observes MO-2063 open, handswitch 23A-S4 in AUTO.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 7 Critical: N Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- g. CV-2065 closed, handswitch 23A-S10 in AUTO.
Standard:
Operator observes CV-2065 closed, handswitch 23A-S10 in AUTO.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 8 Critical: Y Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- h. MO-2067 closed, handswitch 23A-S7 in AUTO.
Standard:
Operator observes MO-2067 OPEN, handswitch 23A-S7 in AUTO.
Evaluator Cue:
Acknowledge the out of position valve, tell examinee to place the switch in the correct position and continue with Independent Verification Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO c Page 6 of 8 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 0 Performance Step: 9 Critical: N Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- i.
MO-2068 closed, handswitch 23A-S6 in AUTO.
Standard:
Operator observes MO-2068 closed, handswitch 23A-S6 in AUTO.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 10 Critical: N Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- j.
MO-2071 closed, handswitch 23A-S8 in AUTO.
Standard:
Operator observes MO-2071 closed, handswitch 23A-S8 in AUTO.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 11 Critical: Y Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- k. CV-3503 closed, valve controller set at 0% open.
Standard:
Operator observes CV-3503 throttled open, valve controller set at 47% open.
Evaluator Cue:
Acknowledge the out of position valve, tell examinee to place the switch in the correct position and continue with Independent Verification Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO c Page 7 of 8 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 0 Performance Step: 12 Critical: N Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- l.
Aux Oil Pmp handswitch 23A-S17 in AUTO.
Standard:
Operator observes Aux Oil Pmp handswitch 23A-S17 in AUTO.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 13 Critical: N Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- m. Gland Seal Condenser Blower Handswitch 23A-S18 in AUTO.
Standard:
Operator observes Gland Seal Condenser Blower Handswitch 23A-S18 in AUTO.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 14 Critical: Y Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- n. Gland Seal Condensate Pump handswitch 23A-S19 in RUN.
Standard:
Operator observes Gland Seal Condensate Pump handswitch 23A-S19 in AUTO.
Evaluator Cue:
Acknowledge the out of position switch, tell examinee to place the switch in the correct position and continue with Independent Verification Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO c Page 8 of 8 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 0 Performance Step: 15 Critical: N Procedure Step 78 Perform independent verification that the following HPCI system components are in the proper ECCS line-up:
- o. Pump Flow Controller, FIC-23-108, in AUTO at 3000 gpm.
Standard:
Operator observes Pump Flow Controller, FIC-23-108, in AUTO at 3000 gpm.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues:
WHEN OPERATOR INFORMS THE EVALUATOR THAT STEP 78.O IS COMPLETE, STATE THE JPM IS COMPLETE.
Stop Time:
ADMIN JPM RO d Page 1 of 6 JPM-0000-D-002 (Main Steam Line Rad Monitor Channel Check) Rev. 1 JOB PERFORMANCE MEASURE (JPM)
SITE:
MONTICELLO NUCLEAR GENERATING PLANT JPM TITLE:
MAIN STEAM LINE RAD MONITOR CHANNEL CHECK JPM NUMBER:
JPM-0000-D-002 REV.
1 RELATED PRA INFORMATION:
None TASK NUMBERS /
TASK TITLE(S):
CR299.349 Perform OPERATIONS DAILY LOG - Parts A, B, D, E, G, H & J K/A NUMBERS:
2.3.5 Rating
SRO/RO:
2.9/2.9 APPLICABLE METHOD OF TESTING:
Discussion:
Simulate/walkthrough:
Perform:
EVALUATION LOCATION:
In-Plant:
Control Room:
Simulator:
Other:
Lab:
Time for Completion:
10 Minutes Time Critical:
No Alternate Path:
No TASK APPLICABILITY:
SRO:
RO:
NLO Additional site-specific signatures may be added as desired.
Developed by:
Developer Date Validated by:
Validator (See JPM Validation Checklist, Attachment 1)
Date Approved by:
Training Supervisor Date JPM BRIEFING/TURNOVER
ADMIN JPM RO d Page 2 of 6 JPM-0000-D-002 (Main Steam Line Rad Monitor Channel Check) Rev. 1 You may use any approved reference materials normally available including logs. Make all written reports, oral reports, and log entries as if the evolution is actually being performed.
EOP Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.
If this JPM is performed on the simulator, the JPM administrator should only give cues that are not indicated on the simulator. If simulator indication is sufficient to indicate the completion of a step, the JPM administrator should not have to give a cue to the trainee to continue the evolution.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The plant is operating at ~ 15% power You are the BOP Operator performing the Night Shift Ops Daily Log INITIATING CUES (IF APPLICABLE):
Perform the following surveillance as part of Ops Daily Log 0000-D 1464 (Main Steam Line Rad Monitor Channel Check)
ADMIN JPM RO d Page 3 of 6 JPM-0000-D-002 (Main Steam Line Rad Monitor Channel Check) Rev. 1 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
IMPORTANT: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step SHALL result in failure of this JPM, per FP-T-SAT-73 (Licensed Operator Requalification Program Examinations).
Performance Step: 1 Critical: N Reviews 0000-D Test 1464 Standard:
Reviews 0000-D Test 1464 Evaluator Cue:
Provide 0000-D page that includes Test 1464 Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 2 Critical: N Procedure Step 7 Table If there is operating steam in a Main Steam Line, or the Mechanical Vacuum Pump is in service, Then from RM-17-251A-D, MSL Radiation Monitor Channel A-D (Panel C-10),
record in table below the indications and determinations.
Channel A (RM-17-251A)
Standard:
Records Channel A (RM-17-251A)
Expected Value: ~ 20 mr/hr Acceptance Criteria: 1 to 1450 mr/hr Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO d Page 4 of 6 JPM-0000-D-002 (Main Steam Line Rad Monitor Channel Check) Rev. 1 Performance Step: 3 Critical: N Procedure Step 7 Table (CONT)
If there is operating steam in a Main Steam Line, or the Mechanical Vacuum Pump is in service, Then from RM-17-251A-D, MSL Radiation Monitor Channel A-D (Panel C-10),
record in table below the indications and determinations.
Channel B (RM-17-251B)
Standard:
Records Channel B (RM-17-251B)
Expected Value: ~ 20 mr/hr Acceptance Criteria: 1 to 1450 mr/hr Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 Critical: N Procedure Step 7 Table (CONT)
If there is operating steam in a Main Steam Line, or the Mechanical Vacuum Pump is in service, Then from RM-17-251A-D, MSL Radiation Monitor Channel A-D (Panel C-10),
record in table below the indications and determinations.
Channel C (RM-17-251C)
Standard:
Records Channel C (RM-17-251C)
Expected Value: ~ 20 mr/hr Acceptance Criteria: 1 to 1450 mr/hr Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO d Page 5 of 6 JPM-0000-D-002 (Main Steam Line Rad Monitor Channel Check) Rev. 1 Performance Step: 5 Critical: Y Procedure Step 7 Table (CONT)
If there is operating steam in a Main Steam Line, or the Mechanical Vacuum Pump is in service, Then from RM-17-251A-D, MSL Radiation Monitor Channel A-D (Panel C-10),
record in table below the indications and determinations.
Channel D (RM-17-251D)
Standard:
Records Channel D (RM-17-251D)
Expected Value: ~ 4000 mr/hr Acceptance Criteria: 1 to 1450 mr/hr Evaluator Cue:
If examinee notifies supervision of the out of tolerance reading, acknowledge the report and inform the examinee to continue with the surveillance.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 6 Critical: Y Procedure Step 7 Table (CONT)
If there is operating steam in a Main Steam Line, or the Mechanical Vacuum Pump is in service, Then from RM-17-251A-D, MSL Radiation Monitor Channel A-D (Panel C-10),
record in table below the indications and determinations.
Lowest indication x 1.4 Standard:
Records the lowest indication x 1.4 Expected Value: ~ 20 x 1.4 = 28 mr/hr Acceptance Criteria: > Highest indication (~4000 mr/hr)
Evaluator Cue:
If examinee notifies supervision of the out of tolerance reading, acknowledge the report and inform the examinee to continue with the surveillance.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM RO d Page 6 of 6 JPM-0000-D-002 (Main Steam Line Rad Monitor Channel Check) Rev. 1 Performance Step: 7 Critical: N Procedure Step 7 Table (CONT)
If there is operating steam in a Main Steam Line, or the Mechanical Vacuum Pump is in service, Then from RM-17-251A-D, MSL Radiation Monitor Channel A-D (Panel C-10),
record in table below the indications and determinations.
At normal full power and HWC at maximum?
Standard:
Determines the plant is NOT at full power, therefore, determines the acceptance criteria of 550 mr/hr is not applicable.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 8 Critical N INFORM EVALUATOR THAT THE TASK HAS BEEN COMPLETED.
Standard:
Operator informs evaluator that the task is completed.
Evaluator Cue:
Acknowledge that the task has been completed.
Evaluator Note:
DO NOT PROMPT.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues:
When the notifications have been made of the out of tolerance readings, state that the JPM is complete.
Stop Time:
ADMIN JPM SRO a Page 1 of 4 JPM-OWI-01.06-002 (Crew Staffing Determination) Rev. 3 JOB PERFORMANCE MEASURE (JPM)
SITE:
MONTICELLO NUCLEAR GENERATING PLANT JPM TITLE:
CREW STAFFING DETERMINATION JPM NUMBER:
JPM-OWI-01.06-002 REV.
3 RELATED PRA INFORMATION:
None TASK NUMBERS /
TASK TITLE(S):
SS299.294 Implement the requirements associated with Control Room staffing and licensed and non-licensed Operator administrative requirements and responsibilities.
K/A NUMBERS:
2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
Rating: SRO/RO:
3.9 APPLICABLE METHOD OF TESTING:
Discussion:
Simulate/walkthrough:
Perform:
EVALUATION LOCATION:
In-Plant:
Control Room:
Simulator:
Other:
Lab:
Time for Completion:
10 Minutes Time Critical:
No Alternate Path:
No TASK APPLICABILITY:
SRO:
RO:
NLO Additional site-specific signatures may be added as desired.
Developed by:
Developer Date Validated by:
Validator (See JPM Validation Checklist, Attachment 1)
Date Approved by:
Training Supervisor Date
ADMIN JPM SRO a Page 2 of 4 JPM-OWI-01.06-002 (Crew Staffing Determination) Rev. 3 JPM BRIEFING/TURNOVER You may use any approved reference materials normally available including logs. Make all written reports, oral reports, and log entries as if the evolution is actually being performed.
EOP Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The time is 0930 Sunday morning with the plant operating at 100% power.
Johnny Craig has just informed you that he is leaving immediately due to a personal emergency.
INITIATING CUES:
Using the Operations Department Organization/Qualification chart and the crew member positions below; you are to identify the staffing adjustments that need to be made, recommendations for call-outs, and time constraints. (Assume the RP Specialist and Chemistry Technician are fully qualified).
POSITION CREW MEMBER 1
Shift Manager Eagle 2
Control Room Supervisor VanCulin 3
STA/SRO Kosey 4
NLPE&RO Teige 5
NPE&RO Craig 6
NPE&RO Yunger 7
NAPEO Waaraniemi 8
NAPEO Gustafson 9
NAPEO West 10 RP Specialist Olson 11 Chemistry Technician Trump 12 Fire Brigade Leader Craig 13 Fire Brigade Member #1 Waaraniemi 14 Fire Brigade Member #2 Gustafson 15 Fire Brigade Member #3 Olson 16 Fire Brigade Member #4 Trump 17 Safe Shutdown Member #1 Eagle 18 Safe Shutdown Member #2 West 19 Safe Shutdown Member #3 Teige 20 Safe Shutdown Member #4 Yunger
ADMIN JPM SRO a Page 3 of 4 JPM-OWI-01.06-002 (Crew Staffing Determination) Rev. 3 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
IMPORTANT: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step SHALL result in failure of this JPM, per FP-T-SAT-73 (Licensed Operator Requalification Program Examinations).
Performance Step: 1 Critical: N Obtains a current copy of the Operations Department Organization/Qualification Chart to determine status of shift staffing.
Standard:
This chart can be obtained from the MNGP Operations Home Page.
Evaluator Cue:
Provide the candidate with the JPM copy of the Modified Org Chart included with this JPM.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 2 Critical: Y Reviews the MNGP Operations Department Organization/Qualification.
Standard:
Identifies that Johnny Craig was filling the position of Fire Brigade Leader in addition to NPE&RO. Additionally the current crew compliment is short one required fire brigade member because John Yunger and Rick Kosey are not qualified Fire Brigade.
Evaluator Note:
If an operator is not qualified fire brigade a superscript 4 will be next to their name or annotated in the left hand column.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM SRO a Page 4 of 4 JPM-OWI-01.06-002 (Crew Staffing Determination) Rev. 3 Performance Step: 3 Critical: Y Identify the time requirements to have minimum staffing positions filled.
Standard:
Determines that minimum staffing must be filled within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 4 AWI-08.01.01 (Fire Prevention Practices) or B.08.05-05, Table A.2-4.
Evaluator Note:
This AWI is Reference Use only. If the examinee doesnt state the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> requirement, ask them what the time requirement is.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 Critical: Y Initiates the process for call-out to fill the Fire Brigade Member position.
Standard:
Directs the NLPE&RO to initiate a call-out for the needed individual.
Evaluator Cue:
State that another operator has been called in to replace Johnny Craig as the NPE&RO and as Fire Brigade Leader and will be here in 45 minutes.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 5 Critical: N INFORM EVALUATOR THAT THE TASK HAS BEEN COMPLETED.
Standard:
Operator informs evaluator that the task is completed.
Evaluator Cue:
Acknowledge that the task has been completed.
Evaluator Note:
DO NOT PROMPT.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues:
Operator informs the evaluator that the task is complete.
Stop Time:
ADMIN JPM SRO b Page 1 of 4 JPM-OWI-01.08-002 (SRO - NRC License Maintenance Responsibilities) Rev. 1 JOB PERFORMANCE MEASURE (JPM)
SITE:
MONTICELLO NUCLEAR GENERATING PLANT JPM TITLE:
SRO - NRC LICENSE MAINTENANCE RESPONSIBILITIES JPM NUMBER:
JPM-OWI-01.08-002 REV.
1 RELATED PRA INFORMATION:
None TASK NUMBERS /
TASK TITLE(S):
SS299.296 Implement the instructions regarding maintenance of active NRC licenses K/A NUMBERS:
2.1
2.1.4 Rating
SRO/RO:
3.8 / 3.3 APPLICABLE METHOD OF TESTING:
Discussion:
Simulate/walkthrough:
Perform:
EVALUATION LOCATION:
In-Plant:
Control Room:
Simulator:
Other:
Lab:
Time for Completion:
10 Minutes Time Critical:
No Alternate Path:
No TASK APPLICABILITY:
SRO:
RO:
NLO Additional site-specific signatures may be added as desired.
Developed by:
Developer Date Validated by:
Validator (See JPM Validation Checklist, Attachment 1)
Date Approved by:
Training Supervisor Date
ADMIN JPM SRO b Page 2 of 4 JPM-OWI-01.08-002 (SRO - NRC License Maintenance Responsibilities) Rev. 1 JPM BRIEFING/TURNOVER Provide briefing/turnover in accordance with applicable program description and/or training procedure.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
You are a Licensed Senior Reactor Operator.
You are qualified to stand the following watches:
o Shift Manager (SM) o Control Room Supervisor (CRS) o Shift Technical Advisor (STA) o Work Execution Center SRO (WEC-SRO)
You are current in Licensed Operator Requalification training and your medical status is acceptable.
The dates, shift times and positions are provided for the watches you stood during the 2nd Quarter.
INITIATING CUES:
Determine if you have met the requirements for maintaining your SRO license active.
Date Shift Position 4/1 Days 0700-1900 WEC-SRO 4/2 Days 0700-1900 WEC-SRO 4/3 Days 0700-1900 WEC-SRO 4/6 Nights 1900-0700 SM 4/7 Nights 1900-0700 WEC-SRO 4/8 Nights 1900-0700 WEC-SRO 4/9 Nights 1900-0700 WEC-SRO 5/2 Days 0700-1900 WEC-SRO 5/3 Days 0700-1900 SM 5/4 Days 0700-1900 WEC-SRO 5/5 Relief 0700-1500 CRS 5/6 Days 0700-1900 WEC-SRO 5/10 Nights 1900-0700 WEC-SRO 5/12 Nights 1900-0700 WEC-SRO 5/13 Nights 1900-0700 WEC-SRO 5/20 Days 0700-1900 SM 5/21 Days 0700-1900 SM 5/22 Days 0700-1900 WEC-SRO 5/23 Days 0700-1900 WEC-SRO 6/4 Days 0700-1900 WEC-SRO 6/5 Days 0700-1900 STA 6/6 Days 0700-1900 WEC-SRO 6/24 Nights 1900-0700 WEC-SRO 6/30 Nights 1900-0700 WEC-SRO
ADMIN JPM SRO b Page 3 of 4 JPM-OWI-01.08-002 (SRO - NRC License Maintenance Responsibilities) Rev. 1 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
IMPORTANT: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step SHALL result in failure of this JPM, per FP-T-SAT-73 (Licensed Operator Requalification Program Examinations).
Performance Step: 1 Critical: N Locate and review controlled copy of Procedure OWI-01.08 (NRC License Maintenance Responsibilities).
Standard:
Obtains and reviews correct procedure.
Evaluator Cue:
If controlled copy is not available for the performance of the JPM, then provide the examinee with a copy of OWI-01.08.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 2 Critical: N Procedure Step 4.2.2.c Maintaining an NRC license active requires the following:
Standing the required number of watches as the Licensed Operator on record during each calendar quarter.
Standard:
Reviews this general requirement Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM SRO b Page 4 of 4 JPM-OWI-01.08-002 (SRO - NRC License Maintenance Responsibilities) Rev. 1 Performance Step: 3 Critical: Y Procedure Step 4.2.4.
Monticellos Technical Specifications requires two SRO and two RO Licensed Operators on shift during routine power operations. Credit for license maintenance is granted when an Operator fills one of these Tech Spec required positions. The Shift Manager, Control Room Supervisor, Nuclear Lead Plant Equipment and Reactor Operator (NLPE&RO) and the Nuclear Plant Equipment and Reactor Operator (NPE&RO) designated as Operator at the Controls (OATC) are considered as licensed duty positions for the purpose of license maintenance credit.
Standard:
Determines that ONLY the SM or CRS positions can be counted toward maintenance of their active NRC license.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 Critical: Y Procedure Step 4.2.6 To maintain active license status, each licensee SHALL actively perform the functions of the OATC (NPE&RO), Nuclear Lead Plant Equipment and Reactor Operator (NLPE&RO) or Senior Reactor Operator (e.g. Control Room Supervisor or Shift Manager) a minimum of five 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts per calendar quarter.
Standard:
Determines that a total of five watches in the required positions of SM or CRS were performed; however, recognizes that the May 5th watch was only an eight hour relief shift.
Determines that the minimum of five twelve hour shifts in a required licensed position has not been met to maintain an active NRC license.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues:
Once the determination has been made whether the minimum number of watches has been / NOT been met then state JPM complete.
Stop Time:
ADMIN JPM SRO c Page 1 of 8 JPM-4 AWI-08.15.03-001 (Shutdown Risk Assessment) Rev. 3 JOB PERFORMANCE MEASURE (JPM)
SITE:
MONTICELLO NUCLEAR GENERATING PLANT JPM TITLE:
SHUTDOWN RISK ASSESSMENT JPM NUMBER:
JPM-4 AWI-08.15.03-001 REV.
3 RELATED PRA INFORMATION:
None TASK NUMBERS /
TASK TITLE(S):
SS299.370 Implement Risk Management for Outages K/A NUMBERS:
2.2 2.2.18 Rating: SRO/RO:
3.9 / 2.6 APPLICABLE METHOD OF TESTING:
Discussion:
Simulate/walkthrough:
Perform:
EVALUATION LOCATION:
In-Plant:
Control Room:
Simulator:
Other:
Lab:
Time for Completion:
15 Minutes Time Critical:
No Alternate Path:
No TASK APPLICABILITY:
SRO:
RO:
NLO Additional site-specific signatures may be added as desired.
Developed by:
Developer Date Validated by:
Validator (See JPM Validation Checklist, Attachment 1)
Date Approved by:
Training Supervisor Date JPM BRIEFING/TURNOVER
ADMIN JPM SRO c Page 2 of 8 JPM-4 AWI-08.15.03-001 (Shutdown Risk Assessment) Rev. 3 You may use any approved reference materials normally available including logs. Make all written reports, oral reports, and log entries as if the evolution is actually being performed.
EOP Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.
If this JPM is performed on the simulator, the JPM administrator should only give cues that are not indicated on the simulator. If simulator indication is sufficient to indicate the completion of a step, the JPM administrator should not have to give a cue to the trainee to continue the evolution.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
Plant is in a Refueling Outage.
Reactor coolant temperature is 100°F with Fuel Pool Gates removed.
Time to boil in the Reactor and Fuel Pool has been calculated to be 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Division 1 AC Outage window is in progress.
Division 1 125 Vdc battery is being supplied from a temporary battery.
All AC systems on Division II are available.
Plant power is being supplied by 1R with 1AR available.
Fuel is currently being moved from the Reactor vessel to the Fuel Pool.
Nuclear Engineering has verified SDM requirements are met during all fuel moves.
Tech Spec requirements for Control Rod position are MET.
The inner and outer Railroad Airlock doors for the Reactor Building are OPEN and can NOT be closed.
INITIATING CUES:
Determine the appropriate Shutdown Risk COLOR of the following Key Safety Functions on Form 2270 Decay Heat Removal - Reactor Cavity Reactivity Control Inventory Control Secondary Containment Control DC Electrical Control AC Electrical Control Form 2270 is NOT required to be filled out.
ADMIN JPM SRO c Page 3 of 8 JPM-4 AWI-08.15.03-001 (Shutdown Risk Assessment) Rev. 3 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
IMPORTANT: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step SHALL result in failure of this JPM, per FP-T-SAT-73 (Licensed Operator Requalification Program Examinations).
Performance Step: 1 Critical: N Locate and review controlled copy of Procedure 4 AWI-08.15.03 (Risk Management for Outages).
Standard:
Obtains and reviews correct procedure.
Evaluator Cue:
PROVIDE operator copy of Form 2270 (Critical Safety System Checklist).
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 2 Critical: N Procedure Step 4.6.4.
Shutdown and Refueling Mode Configuration Requirements Minimum system and off-site power availability for shutdown conditions are assessed using Figure 5.2.
Standard:
Refers to Figure 5.2 (Critical Safety System Requirements) of 4 AWI-08.15.03 and Form 2270 when determining minimum requirements for the shutdown risk assessment.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM SRO c Page 4 of 8 JPM-4 AWI-08.15.03-001 (Shutdown Risk Assessment) Rev. 3 Performance Step: 3 Critical: N Procedure Step 4.6.6.A.
Outage Risk Condition Zone Color Codes Shutdown risk should be assessed using the shutdown risk assessment guidelines in Figure 5.1.
Standard:
Refers to Figure 5.1 (Shutdown Risk Assessment) of 4 AWI-08.15.03 when assessing shutdown risk.
May refer to Form 2270 (Critical Safety System Checklist) during performance of the risk assessment.
Evaluator Cue:
If requested, PROVIDE copy of form 2270.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 Critical: Y Figure 5.2, Decay Heat Removal - Reactor Cavity Provide adequate decay heat removal to prevent coolant boiling and thereby prevent inventory loss and eventual fuel and spent fuel uncovery.
Standard:
Classifies Decay Heat Removal Key Safety Function as GREEN.
Non-Critical Portion:
Based on Initial Conditions, determines Decay Heat Removal - Reactor Cavity section criteria should be used.
Determines at least two Decay Heat Removal systems are required for a condition of GREEN.
Based on Initial Conditions, determines the following systems are available for decay heat removal (total of 4):
o 12 RHR pump and 12 RHRSW pump with RHR HX o 14 RHR pump and 14 RHRSW pump with RHR HX o RWCU in Heat Reject Mode with 12 RWCU pump o 12 Fuel Pool Cooling pump Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM SRO c Page 5 of 8 JPM-4 AWI-08.15.03-001 (Shutdown Risk Assessment) Rev. 3 Performance Step: 5 Critical: Y Figure 5.2, Reactivity Control Maintain adequate shutdown margin in the reactor and fuel pool.
Standard:
Classifies Reactivity Control Key Safety Function as GREEN.
Non-Critical Portion:
Determines both criteria must be met for a condition of GREEN.
Based on Initial Conditions, determines the following conditions are met (total of 2):
o Adequate SDM exists o All Control Rods in fueled cells are fully inserted Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM SRO c Page 6 of 8 JPM-4 AWI-08.15.03-001 (Shutdown Risk Assessment) Rev. 3 Performance Step: 6 Critical: Y Figure 5.2, Inventory Control Control of reactor and spent fuel coolant inventory during shutdown conditions to prevent core and spent fuel uncovery and for maintaining the overall decay heat removal function.
Standard:
Classifies Inventory Control Key Safety Function as GREEN.
Non-Critical Portion:
Determines at least three low pressure injection sources are required for a condition of GREEN in the Reactor.
Determines at least two low pressure injection sources are required for a condition of GREEN in the Spent Fuel Pool.
Based on Initial Conditions, determines the following systems are available for low pressure injection for the Reactor (total of 6):
o 12 Core Spray pump o 12 RHR pump o 14 RHR pump o 12 Condensate pump o 12 Condensate Service pump o 12 CRD pump Based on Initial Conditions, determines the following systems are available for low pressure injection for the Spent Fuel Pool (total of 4):
o 12 Condensate Service pump o 12 Demin Water pump o Fire Diesel o Electric Fire pump Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM SRO c Page 7 of 8 JPM-4 AWI-08.15.03-001 (Shutdown Risk Assessment) Rev. 3 Performance Step: 7 Critical: Y Figure 5.2, Secondary Containment Control Provide a functional barrier to limit airborne fission product release to the environment (elevated/monitored/diluted release) commensurate with the potential likelihood for a release of radioactive products to the Reactor Building.
Standard:
Classifies Secondary Containment Control Key Safety Function as RED.
Non-Critical Portion:
Based on Initial Conditions, determines Secondary Containment Safety Function is required due to movement of irradiated fuel and performance of core alterations.
Due to both inner and outer Railroad Airlock doors open and can NOT be closed, determines that Secondary Containment is currently unavailable.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 8 Critical: Y Figure 5.2, DC Electrical Control Maintain DC electrical power available as required to provide DC instrument and control power necessary to support essential and vital systems which provide Key Safety Functions.
Standard:
Classifies DC Electrical Control Key Safety Function as GREEN.
Non-Critical Portion:
Determines at least two 125 VDC systems are required for a condition of GREEN.
Based on Initial Conditions, determines the following systems are available (total of 2):
o Div 1 125 VDC Battery & Distribution from o Div 2 125 VDC Battery & Distribution Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM SRO c Page 8 of 8 JPM-4 AWI-08.15.03-001 (Shutdown Risk Assessment) Rev. 3 Performance Step: 9 Critical: Y Figure 5.2, AC Electrical Control Manage the configuration of all AC power sources (offsite and onsite) to the station 4KV buses to support Key Safety Functions.
Standard:
Classifies AC Electrical Control Key Safety Function as GREEN.
Non-Critical Portion:
Determines at least two offsite power supplies and one EDG are required for a condition of GREEN.
Based on Initial Conditions, determines the following systems are available (total of 2 offsite power supplies and 1 EDG):
o 1R Transformer o 1AR Transformer o 12 EDG Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues:
JPM is complete with the color of the Key Safety Functions have been determined by the examinee.
Stop Time:
ADMIN JPM SRO d Page 1 of 5 JPM-A.2-401-002 (SRO - Emergency Exposure Control) Rev. 0 JOB PERFORMANCE MEASURE (JPM)
SITE:
MONTICELLO NUCLEAR GENERATING PLANT JPM TITLE:
SRO - EMERGENCY EXPOSURE CONTROL JPM NUMBER:
JPM-A.2-401-002 REV.
0 RELATED PRA INFORMATION:
None TASK NUMBERS /
TASK TITLE(S):
SS304.134 Implement Emergency Exposure Control K/A NUMBERS:
2.3.4 Rating
SRO:
3.7 APPLICABLE METHOD OF TESTING:
Discussion:
Simulate/walkthrough:
Perform:
EVALUATION LOCATION:
In-Plant:
Control Room:
Simulator:
Other:
Lab:
Time for Completion:
10 Minutes Time Critical:
No Alternate Path:
No TASK APPLICABILITY:
SRO:
RO:
NLO Additional site-specific signatures may be added as desired.
Developed by:
Developer Date Validated by:
Validator (See JPM Validation Checklist, Attachment 1)
Date Approved by:
Training Supervisor Date
ADMIN JPM SRO d Page 2 of 5 JPM-A.2-401-002 (SRO - Emergency Exposure Control) Rev. 0 JPM BRIEFING/TURNOVER Provide briefing/turnover in accordance with applicable program description and/or training procedure.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
The plant was at rated conditions when an event occurred. Twenty (20) minutes later the following conditions exist:
A General Emergency has been declared The TSC and EOF have NOT yet been manned Emergency Exposure Authorization has been initiated for Roger Radworker Roger is assigned to manipulate several valves for protection of valuable property Radiation Protection estimates that Roger will receive the following exposure:
o Whole Body: 7 REM o Lens of the Eye: 35 REM o Hands and Forearms: 75 REM You are performing Step 6.1.2 of A.2-401 to determine the authorized exposure limit for this job.
INITIATING CUES:
Using A.2-401 Figure 7.1 determine the following:
What are the AUTHORIZED LIMITs for:
Whole Body Lens of the Eye Hands and Forearms Based on estimated exposure; should you authorize this Emergency Exposure?
ADMIN JPM SRO d Page 3 of 5 JPM-A.2-401-002 (SRO - Emergency Exposure Control) Rev. 0 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
IMPORTANT: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step SHALL result in failure of this JPM, per FP-T-SAT-73 (Licensed Operator Requalification Program Examinations).
Performance Step: 1 Critical: N Locate and review copy of Procedure A.2-401.
Standard:
Obtains and reviews correct procedure and form.
Evaluator Cue:
Procedure A.2-401 should be provided or an Operations Procedure Book Cart available.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 2 Critical: Y A.2-401 Procedure Step 6.1.2.B Using Figure 7.1, Determine the authorized exposure limit.for protection of valuable property.
Standard:
Determines the authorized exposure limit for protection of valuable property is 10 REM (TEDE) to the Whole Body.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM SRO d Page 4 of 5 JPM-A.2-401-002 (SRO - Emergency Exposure Control) Rev. 0 Performance Step: 3 Critical: Y A.2-401 Procedure Step 6.1.2.B Using Figure 7.1, Determine the authorized exposure limit for protection of valuable property.
Standard:
Apply Note 3: Exposure to the lens of the eye should be limited to 3 times the value listed which is 10 REM.
Determines the authorized exposure limit for protection of valuable property is 30 REM to the Lens of the Eye.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 Critical: Y A.2-401 Procedure Step 6.1.2.B Using Figure 7.1, Determine the authorized exposure limit for protection of valuable property.
Standard:
Apply Note 3: Exposure to the skin and/or extremities should be limited to 10 times the value listed which is 10 REM.
Determines the authorized exposure limit for protection of valuable property is 100 REM to the skin and/or extremities Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM SRO d Page 5 of 5 JPM-A.2-401-002 (SRO - Emergency Exposure Control) Rev. 0 Performance Step: 5 Critical: Y A.2-401 Procedure Step 6.1.2.B Based on estimated exposure, determine if Emergency Exposure should be authorized.
Standard:
Estimated Exposure Whole Body: 7 REM Lens of the Eye: 35 REM Hands and Forearms: 75 REM Determines that limit for Lens of the Eye will be exceeded and Emergency Exposure should NOT be approved.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues:
Once the determination has been made whether or not to approve the Emergency Exposure then state JPM complete.
Stop Time:
ADMIN JPM SRO e Page 1 of 6 JPM-A.2-101-018 (Classify Event According To Emergency Classification Guidelines) Rev. 5 JOB PERFORMANCE MEASURE (JPM)
SITE:
MONTICELLO NUCLEAR GENERATING PLANT JPM TITLE:
CLASSIFY EVENT ACCORDING TO EMERGENCY CLASSIFICATION GUIDELINES JPM NUMBER:
JPM-A.2-101-018 REV.
5 RELATED PRA INFORMATION:
None TASK NUMBERS /
TASK TITLE(S):
SS304.104 Implement Monticello Emergency Plan during a Site Area Emergency K/A NUMBERS:
2.4.41 Rating: SRO/RO:
4.6 / 2.9 APPLICABLE METHOD OF TESTING:
Discussion:
Simulate/walkthrough:
Perform:
EVALUATION LOCATION:
In-Plant:
Control Room:
Simulator:
Other:
Lab:
Time for Completion:
15 Minutes Time Critical:
Yes Alternate Path:
No TASK APPLICABILITY:
SRO:
RO:
NLO Additional site-specific signatures may be added as desired.
Developed by:
Developer Date Validated by:
Validator (See JPM Validation Checklist, Attachment 1)
Date Approved by:
Training Supervisor Date
ADMIN JPM SRO e Page 2 of 6 JPM-A.2-101-018 (Classify Event According To Emergency Classification Guidelines) Rev. 5 JPM BRIEFING/TURNOVER Provide briefing/turnover in accordance with applicable program description and/or training procedure.
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.
INITIAL CONDITIONS:
Refueling outage is in progress with the Reactor partially defueled.
Annunciators 6-C-08 (Earthquake) and 6-C-13 (Operational Basis Earthquake) have alarmed.
Indications of a seismic event have been felt in the Control Room and confirmed with Prairie Island.
The Reactor Building Operator reports that the Reactor Building Railroad inner and outer doors are damaged and can NOT be closed.
RPV water level is -60 inches and lowering.
You are the Shift Manager.
INITIATING CUES:
Determine the appropriate emergency classification.
Summon the Shift Emergency Communicator (SEC) to the Control Room.
THIS JPM IS TIME CRITICAL.
INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.
INSTRUCTOR NOTE: This JPM is time critical. Start time is when the initiating cue is acknowledged by the examinee. Stop time is when the examinee returns the JPM paper work to you or verbalizes the EAL declaration.
ADMIN JPM SRO e Page 3 of 6 JPM-A.2-101-018 (Classify Event According To Emergency Classification Guidelines) Rev. 5 JPM PERFORMANCE INFORMATION Start Time:
NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e., the examinee looks or asks for the indication).
IMPORTANT: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM, per FP-T-SAT-73 (Licensed Operator Requalification Program Examinations).
Performance Step: 1 Critical: N Locate Procedure A.2-101 (Classification Of Emergencies) and the EAL Charts.
Procedure A.2-101 Section 6.1.2.A Classification - When informed of plant parameters, radiological release levels or events which indicate that an emergency classification may be appropriate, evaluate the emergency classification.
Standard:
Locates procedure A.2-101 & EAL Matrix.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 2 Critical: N Procedure step 6.1.2.A.1.
Confirm that the indications have been verified using redundant or coincident indications.
Standard:
Verifies indications provides in the initial conditions Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM SRO e Page 4 of 6 JPM-A.2-101-018 (Classify Event According To Emergency Classification Guidelines) Rev. 5 Performance Step: 3 Critical: Y Procedure step 6.1.2.A.2.
Refer to Form 5790-101-02 and identify any EALs applicable to the initiating condition.
Standard:
Refers to the Modes 4, 5, DEF side of the EAL matrix.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 4 Critical: Y Procedure step 6.1.2.A.3.
Locate the applicable EAL on Form 5790-101-02.
Standard:
Locates applicable EAL CS2 (Loss of RPV Inventory Affecting Core Decay Heat Removal Capability with Irradiated Fuel in the RPV) and determines CS2.1 applies based on the following:
o With Secondary Containment not established, RPV inventory as indicated by RPV level LESS THAN -53 in.
Declares Site Area Emergency within 15 minutes of initiating cue.
Evaluator Note:
Ensure to stop clock for time critical portion of JPM. TIME:__________
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM SRO e Page 5 of 6 JPM-A.2-101-018 (Classify Event According To Emergency Classification Guidelines) Rev. 5 Performance Step: 5 Critical: N Procedure step 6.1.2.A.4.
If multiple events and/or indications are involved, classify the emergency based on the event (or indication) that results in the highest (most conservative) emergency classification.
Standard:
None required.
Evaluator Note:
SRO may evaluate HA1 (Natural and Destructive Phenomena Affecting the Plant VITAL AREA) and determine HA1.1 also applies due to the receipt of a confirmed Operating Basis Earthquake. However, since a Site Area Emergency was already declared and this is a higher classification then HA1.1, no additional declaration required.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 6 Critical: N Procedure step 6.1.2.A.5.
Consider the effect that combinations of events have; that, if taken individually, would constitute a lower emergency classification but collectively may exceed the criteria for a higher classification.
Standard:
None required.
Evaluator Note:
May evaluate CS2.1 and HA1.1 as a combination and determine no higher classification exists.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
ADMIN JPM SRO e Page 6 of 6 JPM-A.2-101-018 (Classify Event According To Emergency Classification Guidelines) Rev. 5 Performance Step: 7 Critical: N Procedure step 6.1.2.A.6.
Summon the Shift Emergency Communicator(s) to the Control Room via the Site PA system (Access 305#).
Standard:
Summons the Shift Emergency Communicator (SEC) to the Control Room.
Evaluator Cue:
As SEC, ACKNOWLEDGE summons.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step:
Critical: N INFORM EVALUATOR THAT THE TASK HAS BEEN COMPLETED.
Standard:
Operator informs evaluator that the task is completed.
Evaluator Cue:
Acknowledge that the task has been completed.
Evaluator Note:
DO NOT PROMPT Performance:
SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues:
Site Area Emergency has been declared and the Shift Emergency Communicator (SEC) has been summoned to the Control Room.
Stop Time: