ML19239A436
| ML19239A436 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/06/2018 |
| From: | Joseph Demarshall Operations Branch III |
| To: | NRC/RGN-III/DRS/OLB, Xcel Energy |
| Demarshall J | |
| Shared Package | |
| ML17164A417 | List: |
| References | |
| Download: ML19239A436 (44) | |
Text
QF1075-01 Rev. 6 (FP-T-SAT-75)
Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
SITE:
MONTICELLO NUCLEAR GENERATING PLANT JPM TITLE:
RO - NRC LICENSE MAINTENANCE RESPONSIBILITIES JPM NUMBER:
JPM-OWI-01.08-001 REV.
4 RELATED PRA INFORMATION:
None TASK NUMBERS /
TASK TITLE(S):
SS299.296 Implement the instructions regarding maintenance of active NRC licenses CR299.169 Adhere to 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
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 2 of 8 JPM-OWI-01.08-001 (RO - NRC License Maintenance Responsibilities) Rev. 4 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
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 Reactor Operator.
You are qualified to stand the following Control Room (CR) watches:
o Balance of Plant (BOP) o Operator at the Controls (OATC) o Nuclear Lead Plant Equipment and Reactor Operator (NLPE&RO)
You are current in Licensed Operator Requalification training and your medical status is acceptable.
Your dates, shift, watch times and positions are provided for the CR watches stood during the 2nd Quarter.
INITIATING CUES:
Identify the number of 2nd quarter qualifying watches stood and determine if you have met the requirements for maintaining your RO license active.
Number of qualifying watches stood ___4___?
Requirements met to maintain your RO license active: YES / NO? (circle one)
Date ShiftShift Actual Watch Time Position 4/1 Days 0600-1800 BOP 4/2 Days 0600-1800 BOP 4/3 Days 0600-1800 BOP 4/6 Nights 1800-0600 OATC 4/7 Nights 1800-0600 BOP 4/8 Nights 1800-0600 BOP 4/9 Nights 1800-0600 BOP 5/2 Days 0600-1800 BOP 5/3 Days 0600-1800 OATC 5/4 Days 0600-1800 BOP 5/5 Relief 0600-1400 OATC 5/6 Days 0600-1800 BOP 5/10 Nights 1800-0600 BOP 5/12 Nights 1800-0600 BOP 5/13 Nights 1800-0600 BOP 5/20 Days 0600-1800 NLPE&RO 5/21 Days 0600-1800 NLPE&RO 5/22 Days 0600-1800 BOP 5/23 Days 0600-1800 BOP 6/4 Days 0600-1800 BOP 6/5 Days 0600-1800 BOP 6/6 Days 0600-1800 BOP 6/24 Nights 1800-0600 BOP 6/30 Nights 1800-0600 BOP INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 3 of 8 JPM-OWI-01.08-001 (RO - NRC License Maintenance Responsibilities) Rev. 4 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
JPM PERFORMANCE INFORMATION Required Materials:
Copy of Procedure OWI-01.08 General
References:
OWI-01.08 (NRC License Maintenance Responsibilities) 2142 (Monticello Active NRC SRO/RO Qualification Checklist) 10CFR55.53 (Conditions of License)
Task Standards:
Determination is made that Operator has not stood the minimum number of required licensed watches and his NRC license is inactive in accordance with OWI-01.08, Section 4.2 (Maintaining NRC Licenses Active).
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 copy of Procedure OWI-01.08 (NRC License Maintenance Responsibilities).
Standard:
Reviews procedure.
Evaluator Cue:
Provide the examinee(s) with a copy of OWI-01.08.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 4 of 8 JPM-OWI-01.08-001 (RO - NRC License Maintenance Responsibilities) Rev. 4 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
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:
May review this general requirement.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
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 NLPE&RO or OATC positions can be counted toward maintenance of their active NRC license.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
QF1075-01 Rev. 6 (FP-T-SAT-75)
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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 OATC or NLPE&RO were performed.
Determines 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:
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 Task is COMPLETE.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues:
Inactive NRC License determination has been made.
Stop Time:
Historical Record: Rev. 4 Updated to new JPM template and allow for group administration.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 6 of 8 JPM-OWI-01.08-001 (RO - NRC License Maintenance Responsibilities) Rev. 4 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1.
Are all items on the cover page filled in correctly?
- 2.
Has the JPM been reviewed and validated by SMEs?
- 3.
Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4.
Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5.
Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6.
If the task is NOT time critical, has the completion time been established based on validation data or incumbent experience?
- 7.
If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8.
Is the Licensee level appropriate for the task being evaluated if required? Not applicable to Non-Licensed Operators
- 9.
Is the K/A appropriate to the task and to the licensee level if required? Not applicable to Non-Licensed Operators
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified?
- 12. Are all references identified, current, and accurate?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All applicable questions must be answered YES or the JPM is not valid for use. If all applicable questions are answered YES then the JPM is considered valid and can be performed as written.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 7 of 8 JPM-OWI-01.08-001 (RO - NRC License Maintenance Responsibilities) Rev. 4 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
ATTACHMENT 2 JPM Number: JPM-OWI-01.08-001 JPM
Title:
RO - NRC License Maintenance Responsibilities Examinee & ID:
Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS:
SAT:
UNSAT:
COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 8 of 8 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
ATTACHMENT 3 TURNOVER SHEET INITIAL CONDITIONS:
You are a Licensed Reactor Operator.
You are qualified to stand the following Control Room (CR) watches:
o Balance of Plant (BOP) o Operator at the Controls (OATC) o Nuclear Lead Plant Equipment and Reactor Operator (NLPE&RO)
You are current in Licensed Operator Requalification training and your medical status is acceptable.
Your dates, shift, watch times and positions are provided for the CR watches stood during the 2nd Quarter.
INITIATING CUES:
Identify the number of 2nd quarter qualifying watches stood and determine if you have met the requirements for maintaining your RO license active.
Number of qualifying watches stood ______?
Requirements met to maintain your RO license active: YES / NO? (circle one)
Date ShiftShift Actual Watch Time Position 4/1 Days 0600-1800 BOP 4/2 Days 0600-1800 BOP 4/3 Days 0600-1800 BOP 4/6 Nights 1800-0600 OATC 4/7 Nights 1800-0600 BOP 4/8 Nights 1800-0600 BOP 4/9 Nights 1800-0600 BOP 5/2 Days 0600-1800 BOP 5/3 Days 0600-1800 OATC 5/4 Days 0600-1800 BOP 5/5 Relief 0600-1400 OATC 5/6 Days 0600-1800 BOP 5/10 Nights 1800-0600 BOP 5/12 Nights 1800-0600 BOP 5/13 Nights 1800-0600 BOP 5/20 Days 0600-1800 NLPE&RO 5/21 Days 0600-1800 NLPE&RO 5/22 Days 0600-1800 BOP 5/23 Days 0600-1800 BOP 6/4 Days 0600-1800 BOP 6/5 Days 0600-1800 BOP 6/6 Days 0600-1800 BOP 6/24 Nights 1800-0600 BOP 6/30 Nights 1800-0600 BOP INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
SITE:
MONTICELLO NUCLEAR GENERATING PLANT JPM TITLE:
CORE THERMAL LIMITS MONITORING JPM NUMBER:
JPM-C.2-05.B.01-002 REV.
4 RELATED PRA INFORMATION:
None TASK NUMBERS /
TASK TITLE(S):
CR200.129 Perform Core Thermal Limits Monitoring K/A NUMBERS:
2.1.19 Rating: SRO/RO:
3.8 / 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
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 2 of 15 JPM-C.2-05.B.1-002 (Core Thermal Limits Monitoring) Rev. 4 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
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:
Reactor power has just been raised from 95% to 98% with the Recirc Flow Control System per C.2-05, Section B.2 (Power Adjustments).
PCIUTL is high OOS and Nuclear Engineering is investigating Both the MPR and EPR are in service with EPR in control and MPR as backup.
Time is 8:00 PM.
INITIATING CUES:
You have been directed to perform the Core Thermal Limits Monitoring for MFLCPR, MAPRAT and MFLPD per Ops Man C.2-05, Section B.1 and determine any required actions if necessary.
Record data on Table 2 of the Operations Daily Log - Part A.
Ops Man C.2-05, Section B.1 and Step 8 of 0000-A are provided.
QF1075-01 Rev. 6 (FP-T-SAT-75)
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JPM PERFORMANCE INFORMATION Required Materials:
Copy of Step 8/ Table 2 from Operations Daily Log - 0000-A General
References:
C.2-05 (Power Operation - System Operation), Rev. 70 0000-A (Operations Daily Log - MODE 1), Rev. 103 Task Standards:
Core Thermal Limits obtained and recorded on Table 2 of 0000-A in accordance with Procedure C.2-05, section B.1.
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 Review Procedure C.2-05, section B.1 (Core Thermal Limits, PCIUTL and Stability Decay Ratio Monitoring).
Standard:
Reviews correct procedure and section.
Based on Initiating Cue, determines PARTs A, B & C need to be performed.
Evaluator Cue:
Provide examinee a copy of C.2-05 B.1 and Table 2 If asked, INFORM Operator that ONLY MFLCPR, MAPRAT and MFLPD need to be evaluated and recorded.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
QF1075-01 Rev. 6 (FP-T-SAT-75)
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Performance Step: 2 Critical: N Procedure Step 1.
If Gardel is not anticipated to be available during a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, Then contact a Nuclear Engineer to arrange determination of MCPR.
Standard:
Observes Process & GARDEL computers are functioning.
Marks Step as N/A.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 3 Critical: N Procedure Step 2.a.
If Gardel is available, Then perform the following:
Evaluate the Margin Summary and the Summary Monitor panels on the Gardel User Interface.
Standard:
Observes MFLCPR values located on the Margin Summary panels.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
QF1075-01 Rev. 6 (FP-T-SAT-75)
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Performance Step: 4 Critical: Y Procedure Step 2.b.
Record the following data in 0000-A (Operations Daily Log - Mode 1),
Surveillance requirement 0225 (Minimum Critical Power Ratio (MCPR)):
- 1) The value of MFLCPR
- 2) Core location of MFLCPR
- 3) Percent rated core flow Standard:
Obtains Step 8/Table 2 from Ops Daily Log - 0000-A.
Records correct value for MFLCPR.
Records correct value for limiting MFLCPR Core Location.
Records correct value for Percent Rated Core Flow.
Evaluator Cue:
PROVIDE Copy of Step8/Table 2 from Operations Daily Log - 0000-A.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
QF1075-01 Rev. 6 (FP-T-SAT-75)
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Performance Step: 5 Critical: Y Procedure Step 2.c.
Verify MFLCPR is below the Action Limit (0.99 times the Tech Spec Limit) and the Tech Spec Limit.
- 1) If MFLCPR is below both limits, Then CHECK Yes for 0225...
- 2) If MFLCPR is not below both limits, Then proceed as follows:
a) If MFLCPR is above the Action Limit, And below the Tech Spec Limit, Then contact a Nuclear Engineer.
b) If MFLCPR exceeds the Tech Spec Limit Standard:
Identifies that MFLCPR is above the Action Limit but below the Tech Spec Limit (.995)
Checks NO for MFLCPR on Table 2.
Non-critical Portion:
Marks Step 2.c.1) N/A.
Notifies CRS that MFLCPR is above the Action Limit.
Marks Step 2.c.2)b) N/A.
Notifies Nuclear Engineering.
Evaluator Cue:
As Nuclear Engineer, ACKNOWLEGE report.
As CRS, ACKNOWLEDGE report. INFORM Operator to continue with the task while Nuclear Engineering is investigating.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 6 Critical: N Procedure Step 2.d.
If MPR or EPR is out of service Standard:
Based on Initial Conditions and/or observation of MPR/EPR status, marks Step as N/A.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
QF1075-01 Rev. 6 (FP-T-SAT-75)
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Performance Step: 7 Critical: N Procedure Step 3.
If Gardel is not anticipated to be available during a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, Then contact a Nuclear Engineer to arrange determination of MAPRAT.
Standard:
Observes Process & GARDEL computers continue to function.
Marks Step as N/A.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 8 Critical: N Procedure Step 4.a.
If Gardel is available, Then perform the following:
Evaluate the Margin Summary and the Summary Monitor panels on the Gardel User Interface.
Standard:
Observes MAPRAT values located on the Margin Summary panels.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
QF1075-01 Rev. 6 (FP-T-SAT-75)
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Performance Step: 9 Critical: Y Procedure Step 4.b.
Record the following data in 0000-A (Operations Daily Log - Mode 1),
Surveillance requirement 0207 (Maximum Average Planar Linear Heat Generation Rate (MAPLHGR):
- 1) The value of MAPRAT.
- 2) Core location of MAPRAT.
- 3) Percent rated core flow.
Standard:
Records correct value for MAPRAT.
Records correct value for limiting MAPRAT Core Location.
Records correct value for Percent Rated Core Flow.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 10 Critical: Y Procedure Step 4.c.
Verify MAPRAT is below the Action Limit (0.99 times the Tech Spec Limit) and the Tech Spec Limit.
- 1) If MAPRAT is below both limits, Then CHECK Yes for 0207...
- 2) If MAPRAT is not below both limits Standard:
Identifies that MAPRAT is below the Action Limit.
Checks YES for MAPRAT on Table 2.
Non-critical Portion:
Initials Nights space on Table 2.
Evaluator Note:
Operator may choose to wait for initialing until after values for MFLPD are recorded. Step 4.d is N/A.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
QF1075-01 Rev. 6 (FP-T-SAT-75)
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Performance Step: 11 Critical: N Procedure Step 5.
If Gardel is not anticipated to be available during a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, Then contact a Nuclear Engineer to arrange determination of MFLPD.
Standard:
Observes Process & GARDEL computers continue to function.
Marks Step as N/A.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 12 Critical: N Procedure Step 6.a.
If Gardel is available, Then perform the following:
Evaluate the Margin Summary and the Summary Monitor panels on the Gardel User Interface.
Standard:
Observes MFLPD values located on the Margin Summary panels.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
QF1075-01 Rev. 6 (FP-T-SAT-75)
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Performance Step: 13 Critical: Y Procedure Step 6.b.
Record the following data for the most limiting fuel bundle on 0000-A (Operations Daily Log - Mode 1), Surveillance requirement 0208 (Maximum Fraction Of The Limiting Power Density (MFLPD)):
- 1) The value of MFLPD.
- 2) Core location of MFLPD.
- 3) Percent rated core flow.
Standard:
Records correct value for MFLPD.
Records correct value for limiting MFLPD Core Location.
Records correct value for Percent Rated Core Flow.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 14 Critical: Y Procedure Step 6.c.
Verify MFLPD is below the Action Limit (0.99 times the Tech Spec Limit) and the Tech Spec Limit.
- 1) If MFLPD is below both limits, Then CHECK Yes for 0208...
- 2) If MFLPD is not below both limits Standard:
Identifies that MFLPD is below the Action Limit.
Checks YES for MFLPD on Table 2.
Non-critical Portion:
Initials nights space on Table 2.
Evaluator Cue:
None Evaluator Note:
Step 5.d is N/A.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
QF1075-01 Rev. 6 (FP-T-SAT-75)
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Performance Step: 15 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:
Values for MFLCPR, MAPRAT & MFLPD have been recorded on Table 2 and MFLCPR above Action Limit reported to Nuclear Engineer.
Stop Time:
Historical Record:
New template and procedure revisions for the 2018 ILT NRC Exam
QF1075-01 Rev. 6 (FP-T-SAT-75)
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Simulator Setup (as required):
- Initialize to a Mode 1 IC.
- Lower Reactor power to 98%.
- Adjust Recirc flow and Control Rod pattern such that MFLCPR as displayed on GARDEL is between 0.99 & 1.00.
Ensure MAPRAT & MFLPD values as displayed on GARDEL are <0.98.
PROCEDURE/PROP CHECKLIST: The following procedures will be used during this JPM. Verify the procedures/props are free of place keeping marks and/or returned to the proper location before and after the JPM is administered. First and second checkers, initial below.
BEFORE AFTER PROCEDURES/PROPS 1st 2nd 1st 2nd C.2-05, section B.1 (Core Thermal Limits, PCIUTL and Stability Decay Ratio Monitoring)
Used/New copy of 0000-A (Operations Daily Log - MODE 1)
QF1075-01 Rev. 6 (FP-T-SAT-75)
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ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1.
Are all items on the cover page filled in correctly?
- 2.
Has the JPM been reviewed and validated by SMEs?
- 3.
Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4.
Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5.
Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6.
If the task is NOT time critical, has the completion time been established based on validation data or incumbent experience?
- 7.
If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8.
Is the Licensee level appropriate for the task being evaluated if required? Not applicable to Non-Licensed Operators
- 9.
Is the K/A appropriate to the task and to the licensee level if required? Not applicable to Non-Licensed Operators
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified?
- 12. Are all references identified, current, and accurate?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All applicable questions must be answered YES or the JPM is not valid for use. If all applicable questions are answered YES then the JPM is considered valid and can be performed as written.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 14 of 15 JPM-C.2-05.B.1-002 (Core Thermal Limits Monitoring) Rev. 4 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
ATTACHMENT 2 JPM Number: JPM-C.2-05.B.1-002 JPM
Title:
Core Thermal Limits Monitoring Examinee & ID:
Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS:
SAT:
UNSAT:
COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 15 of 15 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
ATTACHMENT 3 TURNOVER SHEET INITIAL CONDITIONS:
Reactor power has just been raised from 95% to 98% with the Recirc Flow Control System per C.2-05, Section B.2 (Power Adjustments).
PCIUTL is high OOS and Nuclear Engineering is investigating Both the MPR and EPR are in service with EPR in control and MPR as backup.
Time is 8:00 PM.
INITIATING CUES:
You have been directed to perform the Core Thermal Limits Monitoring for MFLCPR, MAPRAT and MFLPD per Ops Man C.2-05, Section B.1 and determine any required actions if necessary.
Record data on Table 2 of the Operations Daily Log - Part A.
Ops Man C.2-05, Section B.1 and Step 8 of 0000-A are provided.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
SITE:
MONTICELLO NUCLEAR GENERATING PLANT JPM TITLE:
INDEPENDENT VERIFICATION OF HPCI JPM NUMBER:
JPM-4 AWI-04.04.02-004 REV.
1 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: Error! Reference source not found.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:
Developer Date Validated by:
Validator (See JPM Validation Checklist, Attachment 1)
Date Approved by:
Training Supervisor Date
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 2 of 12 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 1 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
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 78.
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 79 of Test 0255-06-IA-1 (HPCI Quarterly Pump & Valve Test).
STEP 79 of Test 0255-06-IA-1 is provided.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 3 of 12 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 1 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
JPM PERFORMANCE INFORMATION Required Materials:
Test 0255-06-IA-1 General
References:
4 AWI-04.04.02 Task Standards:
Verify the HPCI System is in Standby Readiness 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 79 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:
Provide operator with copy of 0255-06-IA-1 Step 79.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 4 of 12 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 1 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
Performance Step: 2 Critical: N Procedure Step 79 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:
Performance Step: 3 Critical: N Procedure Step 79 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 79 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:
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 5 of 12 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 1 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
Performance Step: 5 Critical: N Procedure Step 79 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:
Performance Step: 6 Critical: N Procedure Step 79 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 79 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:
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 6 of 12 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 1 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
Performance Step: 8 Critical: Y Procedure Step 79 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 continue with Independent Verification Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 9 Critical: N Procedure Step 79 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 79 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:
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 7 of 12 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 1 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
Performance Step: 11 Critical: Y Procedure Step 79 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 continue with Independent Verification Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 12 Critical: N Procedure Step 79 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 79 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:
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 8 of 12 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 1 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
Performance Step: 14 Critical: Y Procedure Step 79 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 RUN.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 15 Critical: N Procedure Step 79 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 79 is complete, state the JPM is complete Stop Time:
Historical Record: Procedure 0255-06-IA-1 Revision 101 updates for the 2018 ILT NRC Exam
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 9 of 12 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 1 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
Simulator Setup (as required):
SIMULATOR SETUP:
Initialize to any Mode 1 IC where HPCI is operable.
Fill out Procedure 0255-06-IA-1 as follows:
Provide portion of procedure that includes Step 79 to perform the IV.
Open MO-2067 Position CV-3503 throttled open, valve controller set at 47% open PROCEDURE/PROP CHECKLIST: The following procedures will be used during this JPM. Verify the procedures/props are free of place keeping marks and/or returned to the proper location before and after the JPM is administered. First and second checkers, initial below.
BEFORE AFTER PROCEDURES/PROPS 1st 2nd 1st 2nd Used/New 0255-06-IA-1 (HPCI Quarterly Pump And Valve Tests)
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 10 of 12 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 1 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1.
Are all items on the cover page filled in correctly?
- 2.
Has the JPM been reviewed and validated by SMEs?
- 3.
Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4.
Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5.
Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6.
If the task is NOT time critical, has the completion time been established based on validation data or incumbent experience?
- 7.
If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8.
Is the Licensee level appropriate for the task being evaluated if required? Not applicable to Non-Licensed Operators
- 9.
Is the K/A appropriate to the task and to the licensee level if required? Not applicable to Non-Licensed Operators
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified?
- 12. Are all references identified, current, and accurate?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All applicable questions must be answered YES or the JPM is not valid for use. If all applicable questions are answered YES then the JPM is considered valid and can be performed as written.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 11 of 12 JPM-4 AWI-04.04.02-004 (Independent Verification Of HPCI) Rev. 1 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
ATTACHMENT 2 JPM Number: JPM-4 AWI-04.04.02-004 JPM
Title:
Independent Verification Of HPCI Examinee & ID:
Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS:
SAT:
UNSAT:
COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 12 of 12 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
ATTACHMENT 3 TURNOVER SHEET INITIAL CONDITIONS:
0255-06-IA-1 (HPCI Quarterly Pump And Valve Tests) is complete through STEP 78.
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 79 of Test 0255-06-IA-1 (HPCI Quarterly Pump & Valve Test).
STEP 79 of Test 0255-06-IA-1 is provided.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
SITE:
MONTICELLO NUCLEAR GENERATING PLANT JPM TITLE:
DETERMINE PRIMARY CONTAINMENT WATER LEVEL JPM NUMBER:
JPM-C.5-3403-002 REV.
0 RELATED PRA INFORMATION:
None TASK NUMBERS /
TASK TITLE(S):
CR314.121 Determine Containment Water Levels K/A NUMBERS:
2.4.47 Rating SRO/RO: 4.2 / 4.2 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
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 2 of 9 JPM-C.5-3403-002 (Determine Primary Containment Water Level) Rev. 0 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
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:
A major LOCA has occurred.
RPV level can NOT be maintained above Core Height.
EOPs have been exited and SAMGs entered.
Primary Containment flooding is in progress.
DW pressure on PLR-7251B and PCT101 indicate 13 psig RCIC Suction pressure on PI-13-96 indicates 40 psig INITIATING CUES:
The CRS directs you to determine Primary Containment water level and record results on Special Log C.5-3403-3 (RCIC Suction to Drywell Pressure Comparison Method) IAW C.5-3403, Step 3.e.
The Torus air pressure method in Steps 1 and 2 are not being performed.
KEY
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 3 of 9 JPM-C.5-3403-002 (Determine Primary Containment Water Level) Rev. 0 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
JPM PERFORMANCE INFORMATION Required Materials:
Marked up copy of Procedure C.5-3403 showing Steps 1 & 2 N/A and 3.a-d as complete.
General
References:
C.5-3403 (Methods for Determining Containment Water Level)
Task Standards:
Primary Containment water level has been determined in accordance with Procedure C.5-3403, Special Log C.5-3403-3.
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 Review Procedure C.5-3403 (Methods for Determining Containment Water Level).
Standard:
Reviews procedure.
Evaluator Cue:
PROVIDE Operator with copy of Procedure C.5-3403 marked up as specified in Required Materials.
Performance:
SATISFACTORY UNSATISFACTORY Comments:
QF1075-01 Rev. 6 (FP-T-SAT-75)
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Performance Step: 2 Critical Y Procedure Steps 3.e.
If the RCIC suction to DW pressure comparison method is to be used, Then perform the following:
Determine the DW water level trend by comparing the RCIC suction pressure to the DW pressure. Record values on Special Log C.5-3403-3.
Standard:
Based on data provided in the Initiating Cue, transposes data correctly and determines that differential pressure is 40 psig - 13 psig = 27 psig. This value is recorded in column 3 of Special Log C.5-3403-3.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Performance Step: 3 Critical Y Procedure Steps 3.e.
If the RCIC suction to DW pressure comparison method is to be used, Then perform the following:
Determine the DW water level trend by comparing the RCIC suction pressure to the DW pressure. Record values on Special Log C.5-3403-3.
Standard:
Using the C.5-3403-3 calculation method, multiplies 27 psig x 2.3 = 62.1 Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 5 of 9 JPM-C.5-3403-002 (Determine Primary Containment Water Level) Rev. 0 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
Performance Step: 4 Critical Y Procedure Steps 3.e.
If the RCIC suction to DW pressure comparison method is to be used, Then perform the following:
Determine the DW water level trend by comparing the RCIC suction pressure to the DW pressure. Record values on Special Log C.5-3403-3.
Standard:
Using the C.5-3403-3 calculation method, adds 62.1 + 897.5 ft. = 959.6 ft.
This elevation is the approximate water level in the DW.
Evaluator Cue:
None Performance:
SATISFACTORY UNSATISFACTORY Comments:
Terminating Cues:
Primary Containment water level has been determined and recorded on Special Log C.5-3403-4.
Stop Time:
Historical Record: New Create for the 2018 ILT NRC Exam based on C.5-3403 revision 5.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 6 of 9 JPM-C.5-3403-002 (Determine Primary Containment Water Level) Rev. 0 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
Simulator Setup (as required):
- None SIMULATOR - MALFUNCTIONS:
None SIMULATOR - REMOTE FUNCTIONS:
- 1.
- 2.
- 3.
SIMULATOR - OVERRIDES:
OVR ID OVERRIDE TITLE EVENT DELAY RAMP FINAL VALUE
- 1.
- 2.
- 3.
- 4.
- 5.
SIMULATOR - TRIGGERS:
None PROCEDURE/PROP CHECKLIST: The following procedures will be used during this JPM. Verify the procedures/props are free of place keeping marks and/or returned to the proper location before and after the JPM is administered. First and second checkers, initial below.
BEFORE AFTER PROCEDURES/PROPS 1st 2nd 1st 2nd Used/New copy of C.5-3403 (Methods for Determining Containment Water Level)
QF1075-01 Rev. 6 (FP-T-SAT-75)
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ATTACHMENT 1 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED UPON INITIAL VALIDATION AND PRIOR TO USE.
REVIEW STATEMENTS YES NO N/A
- 1.
Are all items on the cover page filled in correctly?
- 2.
Has the JPM been reviewed and validated by SMEs?
- 3.
Can the required conditions for the JPM be appropriately established in the simulator if required?
- 4.
Do the performance steps accurately reflect trainees actions in accordance with plant procedures?
- 5.
Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?
- 6.
If the task is NOT time critical, has the completion time been established based on validation data or incumbent experience?
- 7.
If the task is time critical, is the time critical portion based upon actual task performance requirements?
- 8.
Is the Licensee level appropriate for the task being evaluated if required? Not applicable to Non-Licensed Operators
- 9.
Is the K/A appropriate to the task and to the licensee level if required? Not applicable to Non-Licensed Operators
- 10. Have the performance steps been identified and typed (Critical /
Sequence / Time Critical) appropriately?
- 11. Have all special tools and equipment needed to perform the task been identified?
- 12. Are all references identified, current, and accurate?
- 13. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?
All applicable questions must be answered YES or the JPM is not valid for use. If all applicable questions are answered YES then the JPM is considered valid and can be performed as written.
QF1075-01 Rev. 6 (FP-T-SAT-75)
Page 8 of 9 JPM-C.5-3403-002 (Determine Primary Containment Water Level) Rev. 0 Retention: Life of Plant Retain in: Training Record Form retained in accordance with record retention schedule identified in FP-G-RM-01.
ATTACHMENT 2 JPM Number: JPM-C.5-3403-002 JPM
Title:
Determine Primary Containment Water Level Examinee & ID:
Evaluator:
Job
Title:
Date:
Start Time Finish Time PERFORMANCE RESULTS:
SAT:
UNSAT:
COMMENTS/FEEDBACK: (Make written comments for any steps graded unsatisfactory).
EVALUATORS SIGNATURE:
NOTE: Only this page needs to be retained in examinees record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.
QF1075-01 Rev. 6 (FP-T-SAT-75)
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ATTACHMENT 3 TURNOVER SHEET INITIAL CONDITIONS:
A major LOCA has occurred.
RPV level can NOT be maintained above Core Height.
EOPs have been exited and SAMGs entered.
Primary Containment flooding is in progress.
DW pressure on PLR-7251B and PCT101 indicate 13 psig RCIC Suction pressure on PI-13-96 indicates 40 psig INITIATING CUES:
The CRS directs you to determine Primary Containment water level and record results on Special Log C.5-3403-3 (RCIC Suction to Drywell Pressure Comparison Method) IAW C.5-3403, Step 3.e.
The Torus air pressure method in Steps 1 and 2 are not being performed.