ML20258A049
ML20258A049 | |
Person / Time | |
---|---|
Site: | LaSalle |
Issue date: | 12/11/2018 |
From: | Chuck Zoia Exelon Generation Co |
To: | NRC/RGN-III/DRS/OLB |
Zoia C | |
Shared Package | |
ML17164A413 | List: |
References | |
Download: ML20258A049 (303) | |
Text
Exelon Nuclear Job Performance Measure Review and Determine if Jet Pump Flow Meets Required Flow JPM Number: A-RO-1 Revision Number: 00 Date: 6 / 5 / 2018 Developed By:
Instructor Date Validated By: Pratt / Weaver 7/25/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
A-RO rev 00 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LOA-AA-S101 Rev: 106 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
A-RO rev 00 Revision Record (Summary)
Revision 00, Developed for 17-1 NRC Exam SRRS: 3D.100; There are no retention requirements for this section
A-RO rev 00 SETUP INSTRUCTIONS Materials
- 1. The following material is required to be provided to examinee:
- One copy of the RR Pump Curves
- Copy of DS001 Attachment and Picture of Loop Flows from 1H13-P602
- LOS-AA-S101 SRRS: 3D.100; There are no retention requirements for this section
A-RO rev 00
- 1. INITIAL CONDITIONS You are the assist NSO with Unit 1 at 98% Power INITIATING CUE The Unit Supervisor has ordered you to perform Step E.1.5 of the Shiftly Surveillance LOS-AA-S101 and to report any discrepancies.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
A-RO rev 00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE When the Examinee acknowledges their initiating cue hand them a copy of LOS-AA-S101.
- 1 CHECK Reactor Coolant Inlet Examinee determines that ___ ___ ___
conductivity on 1G33 R601 is conductivity is < 1 µmho.
< 1 µmho.
2 If reading is > 0.3 µmho, Examinee determines this step ___ ___ ___
REFER to CY-AB-120-100, does not apply Reactor Water Chemistry.
- 3 CHECK A and B Recirculation Examinee determines that flows ___ ___ ___
Loop Flows as read from 1B21 agree within 5%
R611A, RR Jet Pmp Flow A Total, and 1B21 R611B, RR Jet Pmp Flow B Total, AGREE 4 If 1B21 R611A, RR Jet Pmp Examinee determines this step ___ ___ ___
Flow A Total is unavailable, does not apply CALCULATE A Recirculation Loop Total Flow by adding A Recirculation Loop Flow data from Computer points B751, B752, B753, B754, B755, B756, B757, B758, B759 and B760:
5 If 1B21 R611B, RR Jet Pmp Examinee determines this step ___ ___ ___
Flow B Total is unavailable, does not apply CALCULATE B Recirculation Loop Total Flow by adding B Recirculation Loop Flow data from Computer points B761, B762, B763, B764, B765, B766, B767, B768, B769 and B770:
- 6 CHECK points fall within Examinee determines that A ___ ___ ___
characteristic curves of valve and B points fall within position versus recirculation characteristic curves of valve loop flow. position versus recirculation loop flow.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
A-RO rev 00 Comment SAT UNSAT STEP ELEMENT STANDARD Number
- 7 CHECK points fall within Examinee determines that ___ ___ ___
characteristic curves of core points fall within characteristic plate versus total core flow. curves of core plate versus total core flow.
- 8 CHECK Jet Pump differential Examinee determines that Jet ___ ___ ___
pressure versus indicated Pump #10 is not within recirculation loop flow fall within differential pressure versus curves. indicated recirculation loop flow curve.
9 Update Unit Supervisor Examinee informs Unit ___ ___ ___
Supervisor of the status of LOS-AA-S101 CUE As Unit Supervisor, acknowledge the report. JPM complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
A-RO rev 00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Review and Determine if Jet Pump Flow Meets Required Flow JPM Number: A-RO-1 Revision Number: 00 Task Number and
Title:
22.00.21Given various plant conditions, predict how the RR System will respond to various system component failures while operating the system or on an exam in accordance with station procedures.
K/A Number and Importance: 2.1.25 (3.9) Ability to interpret reference materials, such as graphs, curves tables, etc.
Suggested Testing Environment: Classroom Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LOS-AA-S101, Unit 1 Shiftly Surveillance, Rev. 106 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 12 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
A-RO rev 00 INITIAL CONDITIONS You are the assist NSO with Unit 1 at 98% Power INITIATING CUE The Unit Supervisor has ordered you to perform Step E.1.5 of the Shiftly Surveillance and to report any discrepancies.
SRRS: 3D.100; There are no retention requirements for this section
Pen 1 = 1B RR Conductivity Exelon Nuclear Job Performance Measure U0BDetermine Availability to Assume Shift per Work Hour Rules Application JPM Number: UA-RO-46 Revision Number: U00 Date: 6 / 6 / 2018 Developed By:
Instructor Date Validated By: Najdonovich / Guzman 7/25/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-RO rev U00 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LS-AA-119 Rev: 12 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
UA-RO rev U00 Revision Record (Summary)
Revision 00, Developed for 17-1 NRC Exam, modified from A-RO-33.
SRRS: 3D.100; There are no retention requirements for this section
UA-RO rev U00 SIMULATOR SETUP INSTRUCTIONS
- 1. Have a copy of LS-AA-119 and a calculator ready to hand to the examinee.
SRRS: 3D.100; There are no retention requirements for this section
UA-RO rev U00 INITIAL CONDITIONS You are a Licensed NSO.
It is Tuesday, 1/8/2019 at 0500.
The on-coming Unit 1 NSO calls in to report he will not be able to come in for his overtime shift due to an illness.
No other licensed individual is available to fill the Safety Related position.
You were on a 7 day vacation, prior to working the following work hours and shifts that count towards 10CFR26 Work Hour Limits, so far this week.
Tue Wed Thu Fri Sat Sun Mon Tue Shift 1/1/19 1/2/19 1/3/19 1/4/19 1/5/19 1/6/19 1/7/19 1/8/19 days (0600-1800) 0600-1400 0600-1800 0600-1800 0600-1800 0600-1000 0600-1800 nights (1800-0600) 1800-2000 1800-2000 INITIATING CUE Determine if you can assume a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift, with the shift starting on 1/8/19 at 1100 and if you cannot, when you must be relieved. Inform the Unit Supervisor of your findings.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
UA-RO rev U00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE When the Examinee acknowledges their initiating cue, hand them a copy of LS-AA-119 1 Reviews procedure to Examinee reviews 10 CFR 26 ___ ___ ___
determine what limits may be Work hour Limits.
exceeded.
- 2 No more than 16 work hours in Examine determines that 14 ___ ___ ___
any 24-hour period hours will be worked in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and no violation will occur.
- 3 No more than 26 work hours in Examine determines that 26 ___ ___ ___
any 48-hour period hours will be worked in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period and no violation will occur.
- 4 No more than 72 work hours in Examine determines that 76 ___ ___ ___
any 7-day (168-hour) period hours will be worked in a 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> period and a violation will occur.
- 5 Determine when you must be Examinee determines that they ___ ___ ___
relieved if you assume the shift. must be relieved at 1900 on 1/8/19 6 Inform Unit Supervisor Examinee informs the Unit ___ ___ ___
Supervisor of their findings CUE As Unit Supervisor, Acknowledge the initiating cue. JPM complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-RO rev U00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BDetermine Availability to Assume Shift per Work Hour Rules Application JPM Number: A-RO-46 Revision Number: 00 Task Number and
Title:
790.020, Determine overtime guidelines IAW overtime controls.
K/A Number and Importance: 2.1.5 - (2.9) Ability to use procedures related to shift staffing, such as minimum crew compliment, overtime limitations, etc.
Suggested Testing Environment: Classroom Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LS-AA-119, Fatigue Management and Work Hour Limits, Rev. 12 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-RO rev U00 INITIAL CONDITIONS You are a Licensed NSO.
It is Tuesday, 1/8/2019 at 0500.
The on-coming Unit 1 NSO calls in to report he will not be able to come in for nights due to an illness.
No other licensed individual is available to fill the Safety Related position.
You were on a 7 day vacation, prior to working the following work hours and shifts that count towards 10CFR26 Work Hour Limits, so far this week.
Tue Wed Thu Fri Sat Sun Mon Tue Shift 1/1/19 1/2/19 1/3/19 1/4/19 1/5/19 1/6/19 1/7/19 1/8/19 days (0600-1800) 0600-1400 0600-1800 0600-1800 0600-1800 0600-1000 0600-1800 nights (1800-0600) 1800-2000 1800-2000 INITIATING CUE Determine if you can assume a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift, with the shift starting on 1/8/19 at 1100 and if you cannot, when you must be relieved. Inform the Unit Supervisor of your findings.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BDetermine Containment Flood Level during Containment Flooding JPM Number: UA-RO-48 Revision Number: U00 Date: 6 / 5 / 2018 Developed By:
Instructor Date Validated By: Pratt / Quinn 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-RO rev U00 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LOP-PC-07 Rev: 1 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
UA-RO rev U00 Revision Record (Summary)
Revision 00, Developed for 17-1 NRC Exam SRRS: 3D.100; There are no retention requirements for this section
UA-RO rev U00 SETUP INSTRUCTIONS
- 1. Provide the examinee with the following:
- A calculator
- A blank copy of LOP-PC-07 SRRS: 3D.100; There are no retention requirements for this section
UA-RO rev U00 INITIAL CONDITIONS You are an extra NSO
- Containment Flooding is in progress
- 1LI-CM179, Containment Floodup Level Indicator is inoperable
- 1LR-CM027, Suppression Pool Level Indication is upscale
- Division 1 containment instrumentation has lost power (CM028, CM031, CM055)
- The flow rate into the Containment has been determined to 12,500 GPM
- 1PI-CM056 indicates 31.1 psig, Suppression Chamber Pressure
- 1PR-CM029 indicates 17.4 psig, Drywell Pressure INITIATING CUE The Unit Supervisor has ordered you to determine how long before injection into the containment must be stopped per E.7 of LOP-PC-07.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
E.5 31.1 psig - 17.4 psig = 13.7 psig, this indicates that containment level is at PT-CM029 = 756 E.6.1 962,500 gal / 12,500 gal/min = 77 minutes or 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 17 minutes UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
UA-RO rev U00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE When the Examinee acknowledges their initiating cue, hand them a copy of LOP-PC-07
- 1 When this differential pressure Examinee determines that the ___ ___ ___
reaches one of the values differential pressure between indicated below: CM056 and CM029 is 13.7 psi CM056 to CM029 13.7 psi
- 2 Determine current Containment Examinee determines that ___ ___ ___
Flood Level containment flood level is at PT-CM029 (756)
- 3 DIVIDE the DW volume Examinee determines that in 77 ___ ___ ___
between the DW pressure minutes or 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 17 minutes instrument elevation and the VQ that injection must be stopped vent path by the flow rate into the containment.
4 Inform Unit Supervisor. Examinee informs Unit ___ ___ ___
Supervisor that containment injection must be stopped in 77 minutes or 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 17 minutes CUE JPM Complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-RO rev U00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BDetermine Containment Flood Level during Containment Flooding JPM Number: A-RO-48 Revision Number: 00 Task Number and
Title:
423.000 Given Unit Supervisor Authorization, evaluate plant conditions and maintain Suppression Pool Level above -12 feet.
K/A Number and Importance: 2.2.44 - (4.2) Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Suggested Testing Environment: Classroom Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LOP-PC-07, Primary Containment Level Determination, Rev.1 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 10 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-RO rev U00 INITIAL CONDITIONS You are an extra NSO
- Containment Flooding is in progress
- 1LI-CM179, Containment Floodup Level Indicator is inoperable
- 1LR-CM027, Suppression Pool Level Indication is upscale
- Division 1 containment instrumentation has lost power (CM028, CM031, CM055)
- The flow rate into the Containment has been determined to 12,500 GPM
- 1PI-CM056 indicates 31.1 psig, Suppression Chamber Pressure
- 1PR-CM029 indicates 17.4 psig, Drywell Pressure INITIATING CUE The Unit Supervisor has ordered you to determine how long before injection into the containment must be stopped per E.7 of LOP-PC-07.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BDetermine Offsite Release Rate JPM Number: UA-RO-47 Revision Number: U00 Date: 6 / 6 / 2018 Developed By:
Instructor Date Validated By: Pratt / Quinn 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-RO rev U00 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LGA-009 Rev: 8 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
UA-RO rev U00 Revision Record (Summary)
Revision 00, Developed for 17-1 NRC Exam, modified from A-RO-02 SRRS: 3D.100; There are no retention requirements for this section
UA-RO rev U00 SETUP INSTRUCTIONS
- 2. Have a Copy of LGA-009 available to the student SRRS: 3D.100; There are no retention requirements for this section
UA-RO rev U00 INITIAL CONDITIONS You are an extra NSO.
- Both Units are at rated conditions.
- A temporary holding tank in Unit 2 Reactor Building has ruptured discharging highly contaminated material.
- VR has isolated.
- Unit 2 VG failed to start.
- Unit 1 VG is running.
INITIATING CUE The Unit 1 Unit Supervisor has requested that you determine stack release.
Inform Unit 1 Unit Supervisor when stack release has been determined and inform them if EOP entry conditions have been met.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
UA-RO rev U00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE Examinee may refer to LOA-PR-101, Unit 1 Process Radiation Monitoring System Abnormal.
- 1. Determine stack release from Examinee determines Main ___ ___ ___
ventilation systems other than Stack WRGM effluent is SBGT. 6.3 E7 µCi/sec.
- 2. Determine stack release from Examinee determines SBGT ___ ___ ___
SBGT. WRGM effluent is 3.1 E7 µCi/sec.
- 3. Determine total release rate. Examinee adds two releases ___ ___ ___
from Main Stack and SBGT WRGMs and determines total release rate is 9.4 E7 µCi/sec.
- 4. Determine EOP entry. Examinee refers to LGA-009, ___ ___ ___
Radioactivity Release Control and determines that entry conditions have been met.
- 5. Inform Unit Supervisor. Examinee informs Unit ___ ___ ___
Supervisor that total release is 9.4 E7 µCi/sec and that LGA-009 entry is required.
CUE As Unit Supervisor, acknowledge information. This JPM is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-RO rev U00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BDetermine Offsite Release Rate JPM Number: A-RO-47 Revision Number: 00 Task Number and
Title:
52.035 Provided initial conditions, respond to a High Rad Release rate IAW station procedures K/A Number and Importance: 2.3.5 - (2.9) Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
Suggested Testing Environment: classroom Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LGA-009 Rev 08, Radioactive Release Control LOA-PR-101 Rev 17, Unit 1 process Radiation Monitoring System Abnormal Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 12 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-RO rev U00 INITIAL CONDITIONS You are an extra NSO.
- Both Units are at rated conditions.
- A temporary holding tank in Unit 2 Reactor Building has ruptured discharging highly contaminated material.
- VR has isolated.
- Unit 2 VG failed to start.
- Unit 1 VG is running.
INITIATING CUE The Unit 1 Unit Supervisor has requested that you determine stack release.
Inform Unit 1 Unit Supervisor when stack release has been determined and inform them if EOP entry conditions have been met.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BRemote Shutdown Monitoring Instrumentation Channel Checks JPM Number: UA-SRO-39 Revision Number: U04 Date: 6 / 11 / 2018 Developed By:
Instructor Date Validated By: Najdonovich / Pratt 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U04 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LOS-RX-M1 Rev: 30 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U04 Revision Record (Summary)
Revision 00 New JPM developed for use in the 07-01 NRC ILT Exam, filed as 07-01 NRC SRO Admin CO1.
Revision 01 Updated for use on 09-01 Cert Exam.
Revision 02 Updated for use on 11-01 Cert Exam.
Revision 03 Updated for ILT Class 13-01 Cert Exam. Revised to include the latest JPM template and procedure revisions. Another JPM, P-AA-01 Verify Reactor Mode Change Requirements was already filed under ASRO01.
Renumbered this JPM from A-SRO-01 Rev. 2 to A-SRO-39 Rev. 3.
Revision 04 Updated for new JPM template.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U04 SETUP INSTRUCTIONS
- 1. Provide the examinee the prepared copy of:
- LOS-RX-M1, Attachment 1A.
- 2. If necessary, the faulted copy of LOS-RX-M1 can be recreated as follows:
- Sections A, B, C, & E steps; circled and slashed
- Sections D & F steps; circled
- Steps 1 & 2; circled and slashed
- Step 2.1; circled with 4 sub-steps checked
- Step 2.2; circled and slashed, record +2.0 inches
- Step 2.3; circled and slashed, blanks initialed by 2 different operators using Today for a date
- Step 3; checked
- Caution; checked
- Step 4; checked
- Step 5 circled and slashed
- Step 5.1; circled, record +1.75 inches
- Step 5.2; circled, record 0.25 inches
- Step 5.3; circled, record +1.5 inches
- Step 5.4; circled, record +0.5 inches (Remaining steps circled / slashed as appropriate)
- Step 6.1 ; circle L122
- Step 6.1 ; record 81 degrees
- Step 6.2 ; record 92 degrees
- Step 6.3 ; record 9 degrees (Faulted value)
- Step 7.1 ; record 77 degrees
- Step 7.2 ; record 80 degrees
- Step 7.3 ; record 3 degrees
- Step 8.1 ; record 0.1 psig
- Step 8.2 ; record 0.0 psig
- Step 8.3 ; record 0.1 psig
- Step 9.1 ; record 92 degrees
- Step 9.2 ; record 95 degrees
- Step 9.3 ; record 3 degrees
- Step 10.1 ; record 62 degrees
- Step 10.2 ; record 56 degrees
- Step 10.3 ; record 6 degrees
- Step 11.1; record 35 inches
- Step 11.2; record 32 inches
- Step 11.3; record 3 inches
- 3. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U04 INITIAL CONDITIONS
- Unit 1 is in Mode 1.
- You are the Unit 1 Supervisor, assigned to review surveillance, LOS-RX-M1, Remote Shutdown Monitoring Instrumentation Channel Checks, Attachment 1A.
- The surveillance was completed last shift and requires review.
INITIATING CUE Your assignment is to review the completed surveillance and determine any actions required as a result of the review.
Inform the Shift Manager of the results of your review.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U04 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE Provide the examinee with a marked up copy of the completed LOS-RX-M1, Attachment 1A.
CUE If the examinee reports that the reading is outside of band, acknowledge the information and inform the examinee that the examinee is to determine any required actions.
- 1. Step 5.2 Examinee compares 5.1 and ___ ___ ___
2.2, and determines that Compare 5.1 and 2.2 and differential level is within the RECORD differential level.
allowable differential of 1
- 2. Step 5.4 Examinee compares 5.3 and ___ ___ ___
2.2, and determines that Compare 5.3 and 2.2 and differential level is within the RECORD differential level. allowable differential of 1 CUE If asked, computer point L123 reads the same as L122.
- 3. Step 6.3 Examinee compares 6.1 and ___ ___ ___
6.2, and determines that a math Compare 6.1 and 6.2 and error was made and differential RECORD differential temperature is outside of the temperature. allowable differential of 10° F.
- 4. Identifies that SR 3.3.3.2 is not Examinee identifies that SR ___ ___ ___
met, and enters LCO 3.3.3.2 is not met, and enters 3.3.3.2.A.1 for an inoperable LCO 3.3.3.2.A.1 for an function. inoperable function.
- 5. (Per Required Action A.1) ___ ___ ___
Identifies that a 30 day Examinee identifies a 30 day completion time is required to completion time to restore the restore the function to operable 1C61-P001 instrument 1TI -
status.
CM037 to operable status.
- 6. Step 7.3 Examinee compares 7.1 and ___ ___ ___
7.2, and determines that Compare 7.1 and 7.2 and differential temperature is within RECORD differential the allowable differential of 10° temperature. F.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U04 Comment SAT UNSAT STEP ELEMENT STANDARD Number
- 7. Step 8.3 Examinee compares 8.1 and ___ ___ ___
8.2, and determines that Compare 8.1 and 8.2 and differential pressure is within the RECORD differential pressure. allowable pressure of 0.25 psig.
- 8. Step 9.3 Examinee compares 9.1 and ___ ___ ___
9.2, and determines that Compare 9.1 and 9.2 and differential temperature is within RECORD differential the allowable differential of 10° temperature. F.
- 9. Step 10.3 Examinee compares 10.1 and ___ ___ ___
10.2, and determines that Compare 10.1 and 10.2 and differential temperature is within RECORD differential the allowable differential of 10° temperature. F.
- 10. Examinee compares 11.1 and ___ ___ ___
Step 11.3 11.2, and determines that Compare 11.1 and 11.2 and differential level is within the RECORD differential level. allowable differential of 10 inches.
- 11. Examinee informs the Shift ___ ___ ___
Inform the Shift Manager of the Manager of the results of the results of the surveillance.
surveillance.
CUE As Shift Manager, acknowledge the report. JPM complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U04 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BRemote Shutdown Monitoring Instrumentation Channel Checks JPM Number: A-SRO-39 Revision Number: 04 Task Number and
Title:
54.012, Provided the initial conditions, perform RSDP Instrumentation Channel Check Surveillance, IAW station procedures.
K/A Number and Importance: 2.1.20 - (4.6) Ability to interpret and execute procedure steps.
Suggested Testing Environment: Classroom or Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LOS-RX-M1 Rev 30, Remote Shutdown Monitoring Instrument Channel Check Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U04 INITIAL CONDITIONS
- Unit 1 is in Mode 1.
- You are the Unit 1 Supervisor, assigned to review surveillance, LOS-RX-M1, Remote Shutdown Monitoring Instrumentation Channel Checks, Attachment 1A.
- The surveillance was completed last shift and requires review.
INITIATING CUE Your assignment is to review the completed surveillance and determine any actions required as a result of the review.
Inform the Shift Manager of the results of your review.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BDetermine LPCS Pump Operability and Reportability Requirements JPM Number: UA-SRO-20 Revision Number: U00 Date: 6 / 23 / 2018 Developed By:
Instructor Date Validated By: Najdonovich / Pratt 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U00 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LS-AA-1110 Rev: 26 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U00 Revision Record (Summary)
Revision 00, New JPM developed for the LORT 2015 NRC Annual Exams.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U00 Materials
- 1. A Copy of the Exelon Reportability Reference Manual.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U00 INITIAL CONDITIONS You are the Unit 2 Supervisor
- Unit 1 is in Mode 3.
- At 0030, while attempting to transition Unit 1 RPV level control from RCIC to LPCS, the LPCS Injection Valve, 1E21-F005, failed to OPEN as required when the associated control switch was held in the OPEN position.
- At that time the Unit 1 Supervisor declared the Unit 1 LPCS system INOPERABLE and Technical Specification 3.5.1 Required Action A.1 has been entered.
INITIATING CUE The Shift Manager has directed you to determine if the event requires an ENS notification. If required, notify the Shift Manager what the event is reportable under and when notification is required. The Shift Manager will complete and transmit ENS notification forms as required.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number 1 Obtain a copy of the Exelon Examinee obtains a copy of the ___ ___ ___
Reportability Reference Manual. Exelon Reportability Reference Manual.
- 2 Utilize Exelon Reportability Examinee determines SAF 1.8 ___ ___ ___
Reference Manual to determine 10CFR50.72(b)(3)(v) for the notification requirements LPCS Pump being INOPERABLE.
NOTE: Notification is required within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from time of discovery of an event or condition that could have prevented fulfilment of a safety function. Time of discovery was at 0030 when the LPCS Pump system was declared INOPERABLE. Notification would be required by 0830 to meet the requirements.
- 3 Utilize Exelon Reportability Examinee determines the ___ ___ ___
Reference Manual to determine notification per SAF 1.8 time reporting requirements 10CFR50.72(b)(3)(v) is required within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from the time of discovery.
4 Notify the Shift Manager of the Examine notifies the Shift ___ ___ ___
notification requirements and Manager that SAF 1.8 most limiting time requirement. 10CFR50.72(b)(3)(v) applies and is due within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from discovery.
CUE As Shift Manager, acknowledge report. JPM is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BDetermine LPCS Pump Operability and Reportability Requirements JPM Number: A-SRO-20 Revision Number: 00 Task Number and
Title:
604.010 Given a situation and the Exelon Reportability Manual, determine notification requirements, IAW station procedures.
K/A Number and Importance: 2.1.18 3.6/3.8 Suggested Testing Environment: Simulator or classroom Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LS-AA-1110, Safety (SAF), Rev. 26 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U00 INITIAL CONDITIONS You are the Unit 2 Supervisor
- Unit 1 is in Mode 3.
- At 0030, while attempting to transition Unit 1 RPV level control from RCIC to LPCS, the LPCS Injection Valve, 1E21-F005, failed to OPEN as required when the associated control switch was held in the OPEN position.
- At that time the Unit 1 Supervisor declared the Unit 1 LPCS system INOPERABLE and Technical Specification 3.5.1 Required Action A.1 has been entered.
INITIATING CUE The Shift Manager has directed you to determine if the event requires an ENS notification. If required, notify the Shift Manager what the event is reportable under and when notification is required. The Shift Manager will complete and transmit ENS notification forms as required.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BComplete and Approve a Fire Protection Impairment Permit JPM Number: UA-SRO-68 Revision Number: U01 Date: 6 / 12 / 2018 Developed By:
Instructor Date Validated By: Najdonovich / Pratt 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U01 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure OP-MW-201-007 Rev: 7 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U01 Revision Record (Summary)
Revision 00, New JPM developed for the LORT 2016 NRC Exam.
Revision 01, Modified fire zone for 17-1 NRC Exam.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U01 SIMULATOR SETUP INSTRUCTIONS
- 1. Have a copy of OP-MW-201-007.
- 2. Copy of partially completed Fire Protection Impairment Permit 2-16-129 to be given to Examinee for Fire Marshall Review and Approval.
- 3. Copy of the Fire Zone Map.pptx located in L:\Fire Marshal.
- 4. VERIFY the Fire Protection Impairment Permit Answer Key is printed on a different color as the rest of the JPM to prevent a loss of exam security during administration.
- 5. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.
- 6. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U01 INITIAL CONDITIONS You are the WEC SRO,
- An Electrical Maintenance Supervisor has requested a permit to allow testing of smoke detectors in the Unit 1 Aux Building 786-6.
- All Fire Barriers in the affected area remain functional.
INITIATING CUE Review the Fire Protection Impairment Permit 1-16-129 and complete the Fire Marshal Review section of the permit. Authorize the permit per section II and provide it back to the Electrical Maintenance Supervisor when complete.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U01 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number NOTE: After the Examinee acknowledges the Initial Conditions and Initiating Cue provide them with a copy of the Fire Protection Impairment Permit.
NOTE: Examinee may utilize the Fire Watch Prints located on the L:\Fire Marshal\Fire Zone Map.pptx drive. If requested provide the Examinee with a print out of the power point slides.
1 REVIEW Fire Protection Examinee REVIEWS Fire ___ ___ ___
Impairment Permit Section I. Protection Impairment Permit Section I.
2 REVIEW TRM 3.3.p. Examinee REVIEWS TRM 3.3.p ___ ___ ___
and determines the following:
- Det. Zone 1-2 required by TRM 3.3.p per Table T3.3.p-1
- Entry into TRM 3.3.p Required Actions A.1, A.2, and A.3.1 or A.3.2 is required.
NOTE: Compare the Fire Protection Impairment Permit completed by the Examinee to the KEY provided in the JPM packet for accuracy.
The following portions of the Fire Marshal Review Section II are required to be completed accurately (Critical Step):
- Fire Watch Required is Hourly
- Fire Marshal (Designee) Authorization signature block signed and dated 3 COMPLETES Fire Protection ___ ___ ___
Impairment Permit Section II.
4 Fire Zone Examinee fills in 4B for Fire ___ ___ ___
Zone SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U01 Comment SAT UNSAT STEP ELEMENT STANDARD Number 5 Barriers Examinee checks Functional for ___ ___ ___
barriers
- 6 Technical Requirements Examinee check YES and ___ ___ ___
Manual? enters Section 3.3p
- 7 Fire Watch required? Examinee circles Hourly ___ ___ ___
8 Fire Watch performed by? Examinee enters EMD ___ ___ ___
9 Comp Measure Examinee checks NO on all 3 ___ ___ ___
blocks Operability check required NEIL Notification required 10 Instructions Examinee fills in to establish ___ ___ ___
hourly fire watch 11 Restoration/Testing Examinee enters to restore the requirements detector
- 12 AUTHORIZES Fire Protection AUTHORIZES Fire Protection ___ ___ ___
Impairment Permit Section II. Impairment Permit Section II.
CUE If asked, as EMD Supervisor, John Smith has been notified to perform required fire watch.
13 RETURN authorized permit to Examinee RETURNS ___ ___ ___
the EMD Supervisor authorized permit to the EMD Supervisor CUE JPM is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U01 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BComplete and Approve a Fire Protection Impairment JPM Number: A-SRO-68 Revision Number: 01 Task Number and
Title:
125.008 Given Unit Supervisor authorization, process (review and log) a Fire Protection Impairment permit, IAW station procedures.
K/A Number and Importance: 2.2.17 - (3.8) Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.
Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): OP-MW-201-007, Fire Protection System Impairment Control, Rev. 7 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U01 INITIAL CONDITIONS You are the WEC SRO,
- An Electrical Maintenance Supervisor has requested a permit to allow testing of smoke detectors in the Unit 1 Aux Building 786-6.
- All Fire Barriers in the affected area remain functional.
INITIATING CUE Review the Fire Protection Impairment Permit 1-16-129 and complete the Fire Marshal Review section of the permit. Authorize the permit per section II and provide it back to the Electrical Maintenance Supervisor when complete.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BAuthorize an Emergency Dose for a Life-Saving Operation JPM Number: UA-SRO-37 Revision Number: U01 Date: 6 / 11 / 2018 Developed By:
Instructor Date Validated By: Najdonovich / Pratt 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U01 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure EP-AA-113 Rev: 13 Procedure RP-AA-203 Rev: 5 Procedure EP-AA-112-100-F-01 Rev: Z
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U01 Revision Record (Summary)
Revision 00, This JPM is based on JPM Admin d. from the NRC Exam for ILT Class 05-1.
It was updated to current procedures and template for ILT 11-1 NRC Exam and provided a JPM number consistent with the current JPM bank.
Revision 01, Updated JPM to new JPM template.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U01 SIMULATOR SETUP INSTRUCTIONS
- 1. The following material is required to be provided to Candidate:
- Three (3) EP-AA-113-F-02 Authorization for Emergency Exposure forms, one for each volunteer. (Attached to this JPM)
- Copy the three (3) EP-AA-113-F-02 forms on the same colored paper as the INITIAL CONDITIONS /INITIATING CUE page (Page 11).
- Provide to the Candidate at the start of this JPM.
- 2. The following materials are required to be available to Candidate:
- EP-AA-113, Personnel Protective Actions
- RP-AA-203, Exposure Control and Authorization
- EP-AA-112-100-F-01, Shift Emergency Director Checklist SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U01 INITIAL CONDITIONS
- A General Emergency has been declared.
- Fuel failure has occurred together with a large break LOCA.
- Containment venting is in progress in order to maintain containment integrity.
- The TSC has been activated, but has not been staffed.
- The appropriate EAL has been declared.
- An emergency life saving operation must be performed.
- The operation is estimated to take between 12 and 15 minutes
- There is a 200 R/hr field in the area
- The operation requires two (2) people to enter the field. Three (3) people have volunteered:
- Phred Burphle, Employee # B537347 Has never received an emergency exposure
- Harvey Owanowitz, Employee # B373479 Has never received an emergency exposure
- George Bush, Employee # B734722 Received a 27 R dose at a reactor in South Africa when he volunteered to assist in a similar life-saving operation.
He is familiar with the procedures for rescuing the victim.
- Per, RP-AA-203 Exposure Control and Authorization, a Rad Protection Supervisor has briefed the three volunteers and presented you with the forms to authorize the emergency exposure.
INITIATING CUE As the acting Station Emergency Director, perform the actions necessary to permit the life-saving operation.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U01 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE Provide the 3 Authorization for Emergency Exposure forms at this time NOTE The following step may be performed in any order.
- 1. Determine emergency exposure Estimated dose for the life saving ___ ___ ___
limits in excess of 5 Rem TEDE operation calculated to be in (EPA-400 lower limits) are required excess of 25 Rem for Exelon emergency workers. (12 to15 minutes in a 200 Rem/Hr field is 40 to 50 Rem)
- 2. For exposures at or above 5 Rem Applicable EP-AA-113-F-02 forms ___ ___ ___
EP-AA-TEDE, complete an Authorization verified to have the REQUESTING 113 for Emergency Exposure form EP- AUTHORIZATION TO EXCEED Step AA-113-F-02. box checked for 25 Rem TEDE 4.3.2.1
- 3. Verify that emergency workers Form EP-AA-113-F-02 for Phred ___ ___ ___
EP-AA- have been briefed on the and Harvey checked for Rad 113 possible health effects of the Protection Management signature Step anticipated exposure.
4.3.2.2
- 4. Verify that emergency workers Form EP-AA-113-F-02 for Phred ___ ___ ___
EP-AA- have volunteered. and Harvey checked for 113 volunteers signature Step 4.3.2.3
- 5. Emergency exposure in excess George Bush is eliminated as a ___ ___ ___
RP-AA- of 25 Rem TEDE is to be limited potential rescuer and the 203 to once in a lifetime. candidate DOES NOT sign this Step volunteers form EP-AA-113-F-02 4.5.1 And EP-AA-113 Step 4.3.3
- 6. Complete an Authorization for EP-AA-113-F-02 for Phred and ___ ___ ___
EP-AA-Emergency Exposure for Phred Harvey signed as Station 113 and Harvey. Emergency Director Step 4.3.3.1 CUE When both forms have been signed inform the candidate that the JPM is complete.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U01 JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U01 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BAuthorize an Emergency Dose for a Life-Saving Operation JPM Number: A-SRO-37 Revision Number: 01 Task Number and
Title:
701.001 Perform actions required as the acting Station Director K/A Number and Importance: 2.3.4 - (3.7) Knowledge of radiation exposure limits under normal and emergency conditions.
Suggested Testing Environment: Simulator or Classroom Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s):
EP-AA-113, Personnel Protective Actions, Rev. 13 EP-AA-113-F02, Authorization for Emergency Exposure, Rev. B EP-AA-112-100-F-01, Shift Emergency Director Checklist, Rev. Z RP-AA-203, Exposure Control and Authorization, Rev. 5 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO rev U01 EP-AA-113-F-02 Revision B Page 9 of 12 Authorization for Emergency exposure Name: Phred Burphle___________________ Date / Time: Today / Current Employee ID Number: B537347 Current Annual Exposure: 152 mRem Reason For Request:
Life saving operation REQUESTING AUTHORIZATION TO EXCEED:
5 Rem TEDE (Authorized to receive greater than 5 Rem TEDE but less than 10 Rem TEDE) 10 Rem TEDE (Authorized to receive greater than 10 Rem TEDE but less than 25 Rem TEDE) 25 Rem TEDE (Authorized to receive greater than 25 Rem TEDE)
Phred Burphle__ Today / 5 minutes ago
- Emergency Worker Signature Date / Time
- Emergency Worker Exposure Limits and Associated Risks (EP-AA-113 Attachment 1) have been reviewed and the potential health affects are understood.
R.P. Manager Today / 5 minutes ago Rad. Protection Management (Review) Date / Time
- Station Emergency Director (Authorization) Date / Time
- The Shift Manager (Shift Emergency Director) may approve prior to transferring Command and Control to the Station Emergency Director.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U01 EP-AA-113-F-02 Revision B Page 10 of 12 Authorization for Emergency exposure Name: Harvey Owanowitz___________________ Date / Time: Today / Current Employee ID Number: B537347 Current Annual Exposure: 57 mRem Reason For Request:
Life saving operation REQUESTING AUTHORIZATION TO EXCEED:
5 Rem TEDE (Authorized to receive greater than 5 Rem TEDE but less than 10 Rem TEDE) 10 Rem TEDE (Authorized to receive greater than 10 Rem TEDE but less than 25 Rem TEDE) 25 Rem TEDE (Authorized to receive greater than 25 Rem TEDE)
Harvey Owanowitz_______________ Today / 5 Minutes ago
- Emergency Worker Signature Date / Time
- Emergency Worker Exposure Limits and Associated Risks (EP-AA-113 Attachment 1) have been reviewed and the potential health affects are understood.
R.P. Manager Today / 5 Minutes ago Rad. Protection Management (Review) Date / Time
- Station Emergency Director (Authorization) Date / Time
- The Shift Manager (Shift Emergency Director) may approve prior to transferring Command and Control to the Station Emergency Director.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U01 EP-AA-113-F-02 Revision B Page 11 of 12 Authorization for Emergency exposure Name: George Bush___________________ Date / Time: Today / Current Employee ID Number: B734722 Current Annual Exposure: 98 mRem Reason For Request:
Life saving operation REQUESTING AUTHORIZATION TO EXCEED:
5 Rem TEDE (Authorized to receive greater than 5 Rem TEDE but less than 10 Rem TEDE) 10 Rem TEDE (Authorized to receive greater than 10 Rem TEDE but less than 25 Rem TEDE) 25 Rem TEDE (Authorized to receive greater than 25 Rem TEDE)
George Bush Today / 5 Minutes ago
- Emergency Worker Signature Date / Time
- Emergency Worker Exposure Limits and Associated Risks (EP-AA-113 Attachment 1) have been reviewed and the potential health affects are understood.
R.P. Manager Today / 5 Minutes ago Rad. Protection Management (Review) Date / Time
- Station Emergency Director (Authorization) Date / Time
- The Shift Manager (Shift Emergency Director) may approve prior to transferring Command and Control to the Station Emergency Director.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO rev U01 INITIAL CONDITIONS
- A General Emergency has been declared.
- Fuel failure has occurred together with a large break LOCA.
- Containment venting is in progress in order to maintain containment integrity.
- The TSC has been activated, but has not been staffed.
- The appropriate EAL has been declared.
- An emergency life saving operation must be performed.
o The operation is estimated to take between 12 and 15 minutes o There is a 200 R/hr field in the area
- The operation requires two (2) people to enter the field. Three (3) people have volunteered:
o Phred Burphle, Employee # B537347 Has never received an emergency exposure o Harvey Owanowitz, Employee # B373479 Has never received an emergency exposure o George Bush, Employee # B734722 Received a 27 R dose at a reactor in South Africa when he volunteered to assist in a similar life-saving operation.
He is familiar with the procedures for rescuing the victim.
- Per, RP-AA-203 Exposure Control and Authorization, a Rad Protection Supervisor has briefed the three volunteers and presented you with the forms to authorize the emergency exposure.
INITIATING CUE As the acting Station Emergency Director, perform the actions necessary to permit the life-saving operation.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BClassify a GSEP Event and Complete a NARS Form JPM Number: UA-SRO-101 Revision Number: U02 Date: 02 / 01 / 2018 Developed By:
Instructor Date Validated By: Najdonovich / Pratt 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO-101- rev U02 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure EP-MW-114-100 Rev: 18 Procedure EP-AA-1005 Add. 3 Rev: 4 Procedure EP-MW-114-100-F-01 Rev: J
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
UA-SRO-101- rev U02 Revision Record (Summary)
Revision 00, New JPM developed for the 2017 CERT Annual Exams.
Revision 01, Revised for EP-MW-114-100-F-01 and EP-MW-114-100 Revision.
Revision 02, Revised to remove that Drywell Pressure turned and is below 45 psig SRRS: 3D.100; There are no retention requirements for this section
UA-SRO-101- rev U02 Materials
- 1. Copy of EP-MW-114-100-F-01
- 2. SED Binder
- 3. EAL Boards
- 4. Notification Hardcards SRRS: 3D.100; There are no retention requirements for this section
UA-SRO-101- rev U02 INITIAL CONDITIONS You are the Shift Manager,
- Unit 1 scrammed due to a LOCA and the CRS has entered LGA-003 and LGA-001.
- Suppression Pool Cooling has been established.
- Chamber and Drywell Sprays are online and functioning normally.
- Drywell Pressure is 57 psig and rising.
- Wind Direction is from 200° and speed is 10 mph.
- Stack radiation levels have remained constant for the last several hours.
INITIATING CUE As the Shift Emergency Director, determine if the event needs to be classified and then, if necessary, classify the event and complete and transmit a NARS form to all agencies required to be notified within 15 minutes.
This is a time critical JPM.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
UA-SRO-101- rev U02 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number NOTE: This JPM has two time critical portions, one to classify the event (15 minutes) and one to transmit the communication (15 minutes). T=0 for event classification is recorded in the JPM Start Time above and begins when the Examinee acknowledges the initial conditions and initiating cue and ends when the Examinee classifies the event. T=0 for the transmittal begins when the event is classified and ends when the contents of the NARs form are transmitted which is all blocks up to and including block 10 Additional Information. Both time critical portion need to be completed within the times identified above the JPM to be completed successfully.
1 Obtain copies of EP-MW-114- Examinee obtains copies EP- ___ ___ ___
100, EP-MW-114-100-F-01, and MW-114-100, EP-MW-114-100-LaSalle EALs. F-01, and LaSalle EALs can be obtained.
- 2 Classify the event. Examinee classifies the GSEP ___ ___ ___
as an ALERT FS1.
Time Classified:
NOTE: After examinee demonstrates where NARS forms can be obtained, provide examinee with a blank NARS form.
3 Obtain blank NARS form. Examinee demonstrates where ___ ___ ___
NARS forms can be obtained.
4 In Utility Message block write 1. Examinee writes the number 1 ___ ___ ___
in Utility Message block.
5 In State Message block write Examinee writes the number ___ ___ ___
N/A. N/A in State Message block.
- 6 In Item 1, marks B. Examinee marks Item 1 B. ___ ___ ___
- 7 In Item 2, marks E. Examinee marks Item 2 E. ___ ___ ___
- 8 In Item 3, marks C. Examinee marks Item 3 C. ___ ___ ___
- 9 In Item 4, write (time & date) Examinee writes (time & date) ___ ___ ___
and EAL FS1. and FS1 in Item 4.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO-101- rev U02 Comment SAT UNSAT STEP ELEMENT STANDARD Number 10 In ACCIDENT TERMINATED Examinee writes N/A in each ___ ___ ___
section write N/A in each blank. blank of ACCIDENT TERMINATED section.
- 11 In Item 5, marks A. Examinee marks Item 5 A. ___ ___ ___
- 12 In Item 6, marks A. Examinee marks Item 6 A. ___ ___ ___
- 13 In Item 7, write 200. Examinee writes 200 in Item 7. ___ ___ ___
- 14 In Item 8 B, write 10. Examinee marks and writes 10 ___ ___ ___
in Item 8 B.
- 15 In Item 9, mark A. Examinee marks Item 9 A. ___ ___ ___
16 In Item 10, write none. Examinee writes none in item ___ ___ ___
10 and writes their name in the approval line.
NOTE: The Examinee may elect to enter their name, Phone Number and date in the A block in item 11. The TIME shall remain blank until the NARS form is actually transmitted.
17 Leave Items 11 and 12 blank. Examinee leaves Items 11 and ___ ___ ___
12 blank.
- 18 CONTACT the agencies that Examinee CONTACTS IEMA by ___ ___ ___
are noted as Required to be pressing code 20.
Notified within 15 minutes.
CUE Respond Beep (pause) Beep 19 Following a short pause, READ Following a short pause, ___ ___ ___
the following message: Examinee READS the following message:
This is the Exelon Nuclear LaSalle County Station, please This is the Exelon Nuclear standby for a NARS message. LaSalle County Station, please standby for a NARS message.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO-101- rev U02 Comment SAT UNSAT STEP ELEMENT STANDARD Number 20 As the agencies respond to the As the agencies respond to the ___ ___ ___
call, READ the following call, Examinee READS the message: following message:
This is the Exelon Nuclear This is the Exelon Nuclear LaSalle County Station, please LaSalle County Station, please standby for a NARS message standby for a NARS message and respond as the roll is and respond as the roll is called. called.
NOTE: Radiological Emergency Assessment Center (REAC) is not staffed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day and will not respond to the INITIAL roll call below.
- 21 CONDUCT an initial roll call for Examinee CONDUCTS an ___ ___ ___
the agencies listed under the initial roll call for the agencies NARS code used on the back of listed under the NARS code the NARS form. CHECK them used on the back of the NARS OFF as they respond to the roll form. CHECKS them OFF as call and record the TIME the they respond to the roll call and first agency is notified. records the TIME the first agency is notified.
CUE Respond HERE when then Examinee performs the initial roll call for IEMA.
- 22 FILL IN the box in the top right Examinee FILLS IN the box in ___ ___ ___
section of Page 2 of the NARS the top right section of Page 2 Form under the heading of the NARS Form under the LASALLE. The Time entered heading LASALLE and in this box corresponds to the records the TIME.
completion of the initial roll call for required agencies.
message #1.
NOTE: Once the Examinee completes transmitting block 10 the second time critical portion is complete. Record the time the Examinees completes transmitting block 10 and compare to the time the event was classified. Time must be less than 15 minutes to be successful.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO-101- rev U02 Comment SAT UNSAT STEP ELEMENT STANDARD Number
- 24 Read the blocks 1-10 one at a Examinee reads the blocks 1-10 ___ ___ ___
time; stating the number, the one at a time; stating the title, the letter (if appropriate) number, the title, the letter (if and the description. appropriate) and the description.
Time Transmitted:
- 25 Section 11, MARK A Exelon. Examinee MARKS A and ___ ___ ___
ENTERS their name and phone number in Section 11.
ENTER your name and an outside phone number that state agencies can use to call back if necessary.
- 26 Section 12, ASK for the name of Examinee ASKS for the name ___ ___ ___
the IEMA representative that of the IEMA representative that received the NARS message, received the NARS message, then ENTER this information on then ENTERS this information the NARS Form. on the NARS Form.
CUE As IEMA Representative, state your name is JOHN DOE from IEMA.
- 27 PERFORM and DOCUMENT Examinee PERFORMS and ___ ___ ___
the roll call for each agency DOCUMENTS the roll call for listed under the NARS code each agency listed under the used and: NARS code used and:
ASK if there are any questions ASKS if there are any questions about the information provided. about the information provided.
CUE Respond HERE when then Examinee performs the roll call for IEMA.
28 STATE NARS communication Examinee states, NARS ___ ___ ___
is complete. communication is complete.
CUE JPM is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO-101- rev U02 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BClassify a GSEP Event and Complete a NARS Form JPM Number: A-SRO-101 Revision Number: 02 Task Number and
Title:
708.001 Given a postulated E-Plan condition, classify the event, IAW EP-AA-1005 715.001 Given an E-Plan condition, complete and transmit a NARS form, IAW station procedures K/A Number and Importance: 2.4.30 2.7/4.1 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): EP-MW-114-100, Midwest Region Offsite Notifications, Rev. 18 EP-AA-1005 Add. 3, Emergency Action Levels For LaSalle Station, Rev. 4 EP-MW-114-100-F-01, Nuclear Accident Reporting System (NARS) Form, Rev.
J Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 30 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UA-SRO-101- rev U02 INITIAL CONDITIONS You are the Shift Manager,
- Unit 1 scrammed due to a LOCA and the CRS has entered LGA-003 and LGA-001.
- Suppression Pool Cooling has been established.
- Chamber and Drywell Sprays are online and functioning normally.
- Drywell Pressure is 57 psig and rising.
- Wind Direction is from 200° and speed is 10 mph.
- Stack radiation levels have remained constant for the last several hours.
INITIATING CUE As the Shift Emergency Director, determine if the event needs to be classified and then, if necessary, classify the event and complete and transmit a NARS form to all agencies required to be notified within 15 minutes.
This is a time critical JPM.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BInhibit and Prevent with a failure of the Division1 Injection Override Switch JPM Number: US-RH-29 Revision Number: U00 Date: 6 / 4 / 2018 Developed By:
Instructor Date Validated By: Pratt / Quinn 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RH rev U00 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LPGP-PSTG-01S14 Rev: 8 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
US-RH rev U00 Revision Record (Summary)
Revision 00, Developed for 17-1 NRC Exam SRRS: 3D.100; There are no retention requirements for this section
US-RH rev U00 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC 358 Password 0358 NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 2. Load and run Smart Scenario S-RH-29.ssf.
- 3. Verify the Inhibit and Prevent Hardcard is Clean.
- 4. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.
- 5. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
US-RH rev U00 INITIAL CONDITIONS You are the Balance of Plant and Unit 1 has experienced an ATWS and LGA-010 has been entered.
INITIATING CUE The Unit Supervisor has ordered you to Inhibit ADS and Prevent ECCS Injection and to inform them when complete.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
US-RH rev U00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number NOTE The Examinee may obtain a copy of the Inhibit and Prevent Hardcard NOTE The IC is a High Power ATWS and Pressure/Level will not Lower, therefore takes Pumps to OFF will not work as there is no Auto-start signal present.
o OVERRIDE 1E22-C001,
o PLACE 1E22-C001, HPCS Pump, in PTL.
- 2 PREVENT All LPCI Injection: Examinee prevents Div 2 LPCI: ___ ___ ___
o PLACE Div 2 Inj Override o PLACE Div 2 Inj Override Switch to ATWS Switch to ATWS
- Verify the Div. 2 Red
- Verify the Div. 2 Red Injection Override Injection Override Switch Light Switch Light Illuminated. Illuminated.
- Verify White Manual
- Verify White Manual Override Light for Override Light for 1E12-F042B AND 1E12-F042B AND 1E12-F042C 1E12-F042C Illuminated. Illuminated.
o OVERRIDE 1E12- o PLACE 1E12-C002C, 1C C002C, 1C RHR Pump, RHR Pump, in PTL.
Off. o PLACE 1E12-C002B, 1B o PLACE 1E12-C002C, 1C RHR Pump, in PTL.
o OVERRIDE 1E12-C002B, 1B RHR Pump, Off.
o PLACE 1E12-C002B, 1B RHR Pump, in PTL.
o At 500 psig in the RPV, OVERRIDE Closed 1E12-F042B, 1B RHR LPCI Injection Valve, if desire to use 1B RHR to cool pool/containment.
- ALTERNATE PATH BEGINS HERE*
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RH rev U00 Comment SAT UNSAT STEP ELEMENT STANDARD Number NOTE When the Div 1 Injection Override Switch is taken to the ATWS position It will fail.
This will be noticed by the Red light above the switch not illuminated AND the white light above the injection valves not illuminated.
NOTE If the Examinee attempts to take Div 1Pump Switches to PTL instead of the Injection Override Switch, the Pump Switches will fail and the Div 1 Injection Override Switch will work. (This is not the expected course for the examinees to take)
- 3 PLACE DIV 1 Inj Override Examinee places the Div 1 ___ ___ ___
Switch to ATWS Injection Override Switch to the ATWS position and notes the
- Verify the Div. 1 Red Failure of the Div 1 Injection Injection Override Switch Override Switch Light Illuminated.
- Verify White Manual Override light for 1E12-F042A AND 1E21-F005 Illuminated 4 OVERRIDE 1E12-C002A, 1A Examinee recognizes no ECCS ___ ___ ___
RHR Pump, Off. Initiation signal is present and this method will not work.
- 5 PLACE 1E12-C002A, 1A RHR Examinee takes 1E12-C002A to ___ ___ ___
Pump, in PTL. PTL 6 At 500 psig in the RPV, Examinee recognizes pressure ___ ___ ___
OVERRIDE Closed 1E12- is not currently lowering.
F042A, 1A RHR LPCI Injection Valve, if desire to use 1A RHR to cool pool/containment.
7 OVERRIDE 1E21-C001, LPCS Examinee recognizes no ECCS ___ ___ ___
Pump, Off. Initiation signal is present and this method will not work.
in INHIBIT. inhibit Switch to Inhibit.
in INHIBIT. inhibit Switch to Inhibit.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RH rev U00 Comment SAT UNSAT STEP ELEMENT STANDARD Number 11 Inform Unit Supervisor The Examinee informs Unit ___ ___ ___
Supervisor that ADS is Inhibited and ECCS is prevented.
CUE As Unit Supervisor acknowledge the report. JPM is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RH rev U00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BInhibit and Prevent with a failure of the Division1 Injection Override Switch JPM Number: S-RH-29 Revision Number: 00 Task Number and
Title:
062.00.21 Given a System Lineup and various plant conditions, predict the system response to various components failures while operating the system K/A Number and Importance: 203000 RHR/LPCI Injection Mode A4.11 Ability to manually operate and/or monitor in the control room: Indicating lights and alarms Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): Plant Specific Technical Guidelines Section 14 - LGA-Related Hard Cards LPGP-PSTG-01S14 Revision 8 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 4 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RH rev U00 INITIAL CONDITIONS You are the Balance of Plant and Unit 1 has experienced an ATWS and LGA-010 has been entered.
INITIATING CUE The Unit Supervisor has ordered you to Inhibit ADS and Prevent ECCS Injection and to inform them when complete.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BPerform LGA-MS-101 Hardcard JPM Number: US-MS-06 Revision Number: U00 Date: 6 / 4 / 2018 Developed By:
Instructor Date Validated By: Pratt / Quinn 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-MS rev U00 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LGA-MS-101 Rev: 2 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
US-MS rev U00 Revision Record (Summary)
Revision 00, Developed for 17-1 NRC Exam SRRS: 3D.100; There are no retention requirements for this section
US-MS rev U00 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC 358 Password 0358 NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 2. The LGA-MS-101 Hardcard is clean.
- 3. Verify keys 84, 85, 86, 87, 252, 253, 254, 255, and 256 are located in the cabinet.
- 4. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.
- 5. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
US-MS rev U00 INITIAL CONDITIONS You are an extra NSO
- Unit 1 has experienced an ATWS
- There are no indications of a Main Steam Line break INITIATING CUE The Unit Supervisor has ordered you to perform the LGA-MS-101 hard card and inform them when complete.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
US-MS rev U00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number NOTE Examinee may obtain a copy of the LGA-MS-101 Hard Card
- 1 At 1H13-P609: Examinee installs and turns ___ ___ ___
keys 253 and 254 at 1H13-
- Install key 253 and turn P609 switch 1B21H-S505A to bypass CHAN A1 MSIV RPV LOW LVL ISOL BYPASS S505A.
- Install key 254 and turn switch 1B21H-S505C to bypass CHAN A2 MSIV RPV LOW LVL ISOL BYPASS S505C.
- 2 At 1H13-P611: Examinee installs and turns ___ ___ ___
keys 255 and 256 at 1H13-
- Install key 255 and turn P611 switch 1B21H-S505B to bypass CHAN B1 MSIV RPV LOW LVL ISOL BYPASS S505B.
- Install key 256 and turn switch 1B21H-S505D to bypass CHAN B2 MSIV RPV LOW LVL ISOL BYPASS S505D.
- 3 PLACE in OPEN 1N62-F057, Examinee places the 1N62- ___ ___ ___
Off Gas Discharge To Stack. F057 control switch to OPEN
- 4 At 1H13-P632: Examinee installs and turns ___ ___ ___
keys 84 and 86 at 1H13-P632
- Install key 84 and turn switch 1E31A-S750 to bypass
- Install key 86 and turn switch 1E31A-S752 to bypass SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-MS rev U00 Comment SAT UNSAT STEP ELEMENT STANDARD Number
- 5 At 1H13-P642: Examinee installs and turns ___ ___ ___
keys 85 and 87 at 1H13-P642
- Install key 85 and turn switch 1E31A-S751 to bypass
- Install key 87 and turn switch 1E31A-S753 to bypass
- 6 At 1PM13J, Install key 252 and Examinee installs and turns key ___ ___ ___
turn switch 1HS-IN035, 1IN017 252 and turns 1HS-IN035 at RPV LOW LVL ISOL BYPASS 1PM13J IN035.
- 7 At 1PM13J, Open 1IN059 and Examinee opens 1IN059 and ___ ___ ___
1IN060. 1IN060 at 1PM13J
- 8 At 1PM13J, Place and hold Examinee holds control switch ___ ___ ___
1IN017 control switch in the until 1IN017 is full open or verify open position until valve already open indicated full open.
9 Inform the Unit Supervisor Examinee informs Unit ___ ___ ___
Supervisor that LGA-MS-101 Hard Card is complete CUE As Unit Supervisor, Acknowledge the report. JPM Complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-MS rev U00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BPerform LGA-MS-101 Hardcard JPM Number: S-MS-06 Revision Number: 00 Task Number and
Title:
432.000 Given Unit Supervisor authorization, evaluate plant conditions and Maintain a Heat Sink, IAW Station procedures.
K/A Number and Importance: 239001 A2.03 (4.0/4.2) Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: MSIV closure Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LGA-MS-101, Unit 1 Using Main Condenser as Heat Sink in ATWS, Rev 2 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 11 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-MS rev U00 INITIAL CONDITIONS You are an extra NSO
- Unit 1 has experienced an ATWS
- There are no indications of a Main Steam Line break INITIATING CUE The Unit Supervisor has ordered you to perform the LGA-MS-101 hard card and inform them when complete.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BAuto Transfer from MDRFP to TDRFP per LOP-RL-01 JPM Number: US-RL-01 Revision Number: U00 Date: 6 / 4 / 2018 Developed By:
Instructor Date Validated By: Pratt / Quinn 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RL rev U00 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LOP-RL-01 Rev: 26 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
US-RL rev U00 Revision Record (Summary)
Revision 00, Developed for 17-1 NRC Exam SRRS: 3D.100; There are no retention requirements for this section
US-RL rev U00 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC 357 Password 0357 NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 2. Have a marked up copy of LOP-RL-01.
- 3. Place the DS001 on the RRFC Screen.
- 4. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.
- 5. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
US-RL rev U00 INITIAL CONDITIONS You are the Unit NSO on Unit 1
- 1A TDRFP is online in manual and ready for operation per LOP-FW-04
- 1B TDRFP and the Both Feed Reg Valves are in Auto INITIATING CUE The Unit Supervisor has directed you automatically transfer from the FRV to 1A TDRFP per LOP-RL-01.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
US-RL rev U00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE When the examinee has acknowledged their imitating cue, hand them a copy of LOP-RL-01 1 Verify FRV is in AUTO control. Examinee verifies that both ___ ___ ___
The LFFRV may also be in FRVs are in auto AUTO.
2 Verify MDRFP min flow valve Examinee verifies that the ___ ___ ___
M/A station is in AUTO. MDRFP Min Flow Valve is in Auto
- 3 Verify Oncoming TDRFP min Examinee places the TDRFP ___ ___ ___
flow valve M/A Station is in Min Flow Valve in Auto AUTO.
4 Verify Oncoming TDRFP is Examinee verifies the 1A ___ ___ ___
ready for operation per LOP- TDRFP is ready per LOP-FW-FW-04. 04 per Initial Conditions
- 5 At 1DS001 Operator Station Examinee Navigates to the ___ ___ ___
RWLC Process Overview RWLC Process Overview screen Screen at the DS001
- 6 SELECT appropriate transfer Examinee selects the FRV to A ___ ___ ___
sequence "FRV to A TDRFP" TDRFP and clicks start and PRESS Start.
7 MONITOR on coming TDRFP Examinee monitors Reactor ___ ___ ___
and reactor water level control water Level and TDRFP Speed as the oncoming TDRFP accelerates and eventually injects to the reactor vessel 8 VERIFY the component(s) in Examinee verifies that the ___ ___ ___
AUTO controls reactor water TDRFP controls Reactor Water level as the TDRFP increases Level its injection rate.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RL rev U00 Comment SAT UNSAT STEP ELEMENT STANDARD Number 9 If reactor water level control is Examinee validates that RWLC ___ ___ ___
compromised, at the 1(2)DS001 is not compromised Operator Station RWLC Process Overview screen, SELECT the appropriate transfer sequence and press RESET OR enter LOA-FW-101(201) as required.
10 ALLOW the oncoming TDRFP Examinee verifies that the FRV ___ ___ ___
demand to ramp to the common is in Manual and the TDRFP is control output. WHEN the in Auto oncoming TDRFP demand reaches the common control output, the following will occur:
- FRV and LFFRV M/A Station transfers to MANUAL.
- Oncoming TDRFP M/A Station transfers to AUTO.
11 After a 3-minute time delay to Examinee verifies after 3 ___ ___ ___
allow system to stabilize, minutes that the FRV is CHECK the FRV/LFFRV start to closing/closed ramp closed.
12 VERIFY the components in Examinee checks MDRFP flow ___ ___ ___
AUTO control reactor water and verifies it is no longer level as the MDRFP decreases injecting its injection rate.
13 If reactor water level control is Examinee validates that RWLC ___ ___ ___
compromised, at the 1(2)DS001 is not compromised Operator Station RWLC Process Overview screen, SELECT the appropriate transfer sequence and press RESET OR ENTER LOA-FW-101(201) as required.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RL rev U00 Comment SAT UNSAT STEP ELEMENT STANDARD Number 14 VERIFY proper operation of the Examinee verifies that the ___ ___ ___
MDRFP min flow valve. The MDRFP Min Flow Valve opens MDRFP min flow valve should below 2.0 Mlb/hr start to open below 2.0 Mlb/hr.
15 Inform Unit Supervisor Examinee informs Unit ___ ___ ___
Supervisor that the transfer sequence is complete CUE As Unit Supervisor, acknowledge the report. JPM complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RL rev U00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BAuto Transfer from MDRFP to TDRFP per LOP-RL-01 JPM Number: S-RL-01 Revision Number: 00 Task Number and
Title:
31.009 Given Ubit Supervisor authorization, perform Control Room Actions to transfer RWLC from Manual to Automatic, IAW Station procedures K/A Number and Importance: 259002 A1.04 (3.6/3.6) Ability to predict and/or monitor changes in parameters associated with operating the REACTOR WATER LEVEL CONTROL SYSTEM controls including: Reactor water level control controller indications Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LOP-RL-01, Operation of the Reactor Level Control System, Re. 26 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 12 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RL rev U00 INITIAL CONDITIONS You are the Unit NSO on Unit 1
- 1A TDRFP is online in manual and ready for operation per LOP-FW-04
- 1B TDRFP and the Both Feed Reg Valves are in Auto INITIATING CUE The Unit Supervisor has directed you automatically transfer from the FRV to 1A TDRFP per LOP-RL-01.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BDefeat Refueling Bridge Position Near or Over the Core Limit Switches Interlock JPM Number: US-RM-02 Revision Number: U01 Date: 6 / 4 / 2018 Developed By:
Instructor Date Validated By: Pratt / Quinn 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RM rev U01 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LOP-RM-02 Rev: 23 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
US-RM rev U01 Revision Record (Summary)
Revision 00, New JPM developed for ILT 15-1 Cert Exam.
Revision 01, Revised JPM for new K/A statement SRRS: 3D.100; There are no retention requirements for this section
US-RM rev U01 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset Simulator to IC # 151.
NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 2. Have a copy of LOP-RM-02 (pages 1-9, 55-56) ready to provide to the Examinee.
- 3. VERIFY the ROD SELECT Display is in CONTROL Mode.
- 4. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.
- 5. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
US-RM rev U01 INITIAL CONDITIONS You are the Unit NSO,
- Unit 1 is at rated conditions.
- A Dry Cask Storage Campaign is in-progress on the Refuel Floor.
INITIATING CUE The Unit Supervisor has directed you to defeat the Pc - Refueling Bridge Position Near or Over the Core Limit Switches IAW LOP-RM-02, Rod Control Management System On Demand Functions, Step E.31 to support the Dry Cask Storage campaign. Notify the Unit Supervisor when complete with E.31.1.8.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
US-RM rev U01 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number NOTE: After the Examinee has demonstrated where to obtain a copy of the procedure, provide them with a copy of LOP-RM-02.
1 Obtain a copy of the procedure. Examinee demonstrates where ___ ___ ___
to obtain a copy of the procedure.
- 2 SELECT SET PARAMETERS Examinee SELECTS SET ___ ___ ___
at the ROD SELECT Display or PARAMETERS at the Display the STATUS Display, whichever that is in the CONTROL mode.
is in the CONTROL mode.
- 3 SELECT SET SYS PARAM. Examinee SELECTS SET SYS ___ ___ ___
PARAM.
CUE If the examinee requests the password, inform the examinee that the password is zero.
- 4 ENTER the correct password Examinee ENTERS password ___ ___ ___
and SELECT ENTER, on the and SELECTS ENTER.
keypad that appears.
- 5 SCROLL down the display Examinee SCROLLS down the ___ ___ ___
menu using the UP/DOWN display menu to HIGHLIGHT arrows to HIGHLIGH Pc- Pc- REFUELING BRIDGE REFUELING BRIDGE POSITION NEAR OR OVER POSITION NEAR OR OVER THE CORE LIMIT SWITCHES THE CORE LIMIT SWITCHES (SET TO NOT OTC/RESTORE (SET TO NOT OTC/RESTORE TO ACTUAL). (can also touch)
TO ACTUAL).
- 6 SELECT SET TO NOT OTC Examinee SELECTS SET TO ___ ___ ___
using the LEFT/RIGHT arrows NOT OTC using the on the display. LEFT/RIGHT arrows on the display. (can also touch)
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RM rev U01 Comment SAT UNSAT STEP ELEMENT STANDARD Number 7 SET TO NOT OTC will be Examinee place keeps ___ ___ ___
highlighted in the area next to procedure step.
the description Pc -
REFUELING BRIDGE POSITION NEAR OR OVER THE CORE LIMIT SWITCHES (SET TO NOT OTC/RESTORE TO ACTUAL.
- 8 SELECT ACCEPT to defeat Examinee SELECTS ACCEPT ___ ___ ___
the interlock. to defeat the interlock.
- 9 ACKNOWLEDGES the pop-up Examinee ACKNOWLEDGES ___ ___ ___
confirmatory message. the pop-up confirmatory message.
10 NOTIFY Unit Supervisor the Examinee NOTIFES the Unit ___ ___ ___
interlock is defeated. Supervisor the interlock is defeated.
CUE As Unit Supervisor, acknowledge report. JPM is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RM rev U01 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BDefeat Refueling Bridge Position Near or Over the Core Limit Switches Interlock JPM Number: S-RM-02 Revision Number: 01 Task Number and
Title:
30.001 Given Unit Supervisor authorization, perform Control Room actions to support the movement of a fuel bundle or control rod blade guide within and between the Reactor and the Spent Fuel Pools.
K/A Number and Importance: 201002 K1.08 (3.2/3.6) Knowledge of the physical connections and/or cause -effect relationships between REACTOR MANUAL CONTROL SYSTEM and the following: Refueling interlocks Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LOP-RM-02, Rod Control Management System On Demand Functions, Rev 23 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 5 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RM rev U01 INITIAL CONDITIONS You are the Unit NSO,
- Unit 1 is at rated conditions.
- A Dry Cask Storage Campaign is in-progress on the Refuel Floor.
INITIATING CUE The Unit Supervisor has directed you to defeat the Pc - Refueling Bridge Position Near or Over the Core Limit Switches IAW LOP-RM-02, Rod Control Management System On Demand Functions, Step E.31 to support the Dry Cask Storage campaign. Notify the Unit Supervisor when complete with E.31.1.8.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BPerform a Loss of 142Y Hard Card with a Failure of the first ACB to Close JPM Number: US-AP-08 Revision Number: U00 Date: 6 / 4 / 2018 Developed By:
Instructor Date Validated By: Pratt / Quinn 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-AP rev U00 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LOA-AP-101 Rev: 58 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
US-AP rev U00 Revision Record (Summary)
Revision 00, Developed for 17-1 NRC Exam SRRS: 3D.100; There are no retention requirements for this section
US-AP rev U00 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to 356 Password 0356.
NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 2. Load and Run Smart Scenario S-AP-08.ssf.
- 3. Verify the Loss of 142Y Hardcard is clean.
- 4. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.
- 5. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
US-AP rev U00 INITIAL CONDITIONS You are the Assist NSO
- A loss of 142Y has occurred
- 1A WR Pump is running and operating properly
- 1A CRD Pump is running and operating properly
- 1H13-P603-A204, CRD Charging Wtr Press Lo is NOT in alarm
- 1A WR Pump is verified operating properly
- RPS Quick Swap Hardcard is complete
- IA to IN Cross-Tie Hardcard is complete INITIATING CUE The Unit Supervisor has directed to you to Re-energize bus 142Y using the Loss of 142Y Hardcard and to inform them when 142Y is energized.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
US-AP rev U00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number NOTE Examinee may obtain the Loss of 142Y hardcard.
NOTE The first method to re-energize 142Y will Fail (Steps 3, 4, or 5) and the second method to re-energize 142Y will Work (Steps 3, 4, or 5). Two of the steps MUST be complete to re-energize 142Y and the third step (and sub-steps of that step) may be N/Ad.
1 VERIFY annunciator 1PM01J- Examinee verifies 1PM01J- ___ ___ ___
B202, 4KV Bus 142X/Y B202 is clear Overcurrent alarm is CLEAR.
2 VERIFY all three phase Examinee verifies all 3 phases ___ ___ ___
voltages are approximately are equal on bus 142X using equal using 142X/Y Voltmeter the Bus 142X-142Y Voltmeter switch. Selector Switch
- ALTERNATE PATH BEGINS HERE*
NOTE If this is the first method chosen ACB 1425 will fail to close.
CUE If the Examinee attempts to enter LOA-AP-101 at any time, inform them that another NSO will follow-up with LOA-AP-101.
- 3 If 142X is energized, Examinee takes the Sync ___ ___ ___
SYNCHRONIZE and CLOSE Scope Selector Switch for ACB ACB 1425. 1425 to ON and takes ACB 1425 to close 4 If desired to re-energize 142Y from Unit-2:
CUE If the Examinee asks what is powering 242Y, inform them that 242Y is powered from the SAT.
4.1 CHECK 242Y energized from Examinee asks Unit 2 what is ___ ___ ___
Unit-2 SAT. powering 242Y CUE If the Examinee asks Unit 2 if ACB 2425 is open, inform them that ACB 2425 is open.
4.2 CHECK ACB 2425 is OPEN Examinee asks Unit 2 the status ___ ___ ___
of ACB 2424 SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-AP rev U00 Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE If the Examinee orders closing ACB 2424, inform them ACB 2424 is closed.
4.3 SYNCHRONIZE and CLOSE Examinee asks Unit 2 if ACB ___ ___ ___
ACB 2424. 2424 is closed NOTE If this is the first method chosen ACB 1424 will fail to close.
- 4.4 SYNCHRONIZE and CLOSE Examinee takes ACB 1424 ___ ___ ___
ACB 1424. Sync Scope Selector Switch to ON and closes ACB 1424 5 If desired to re-energize 142Y from 1A DG:
NOTE If this is the first method chosen the 1A DG will not start.
NOTE If this is the second method chosen the 1A DG Output Breaker will Auto-close.
START using control switch on 1PM01J.
5.2 If 1A DG will not start, REFER Examinee determines this step ___ ___ ___
to LOA-DG-101. is not applicable 5.3 If 1A DG Output Breaker ACB Examinee attempts to enter ___ ___ ___
1423 did not auto-close, LOA-AP-101 if this is the first REFER to LOA-AP-101. method chosen to re-energize 142Y 6 Inform Unit Supervisor Examinee informs Unit ___ ___ ___
Supervisor that Bus 142Y is re-energized CUE As Unit Supervisor, acknowledge the report. JPM complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-AP rev U00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BPerform a Loss of 142Y Hard Card with a Failure of the first ACB to Close JPM Number: S-AP-08 Revision Number: 00 Task Number and
Title:
5.008, Provided initial conditions respond to a loss of 4KV ESS bus IAW station procedures.
K/A Number and Importance: 262001 A2.07 (3.0/3.2) Ability to (a) predict the impacts of the following on A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct control, or mitigate the consequences of those abnormal conditions or operations: Energizing a dead bus Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LOA-AP-101, Unit 1 AC Power System Abnormal Rev. 58 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 8 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-AP rev U00 INITIAL CONDITIONS You are the Assist NSO
- A loss of 142Y has occurred
- 1A WR Pump is running and operating properly
- 1A CRD Pump is running and operating properly
- 1H13-P603-A204, CRD Charging Wtr Press Lo is NOT in alarm
- 1A WR Pump is verified operating properly
- RPS Quick Swap Hardcard is complete
- IA to IN Cross-Tie Hardcard is complete INITIATING CUE The Unit Supervisor has directed to you to Re-energize bus 142Y using the Loss of 142Y Hardcard and to inform them when 142Y is energized.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BShutdown Suppression Pool Cooling with High Rad JPM Number: US-RH-28 Revision Number: U00 Date: 6 / 4 / 2018 Developed By:
Instructor Date Validated By: Pratt / Quinn 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RH rev U00 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LOP-RH-13 Rev: 32 Procedure LOP-RH-05 Rev: 34 Procedure LOR-1H13-P601B212 Rev: 2
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
US-RH rev U00 Revision Record (Summary)
Revision 00, Developed for 17-1 NRC Exam SRRS: 3D.100; There are no retention requirements for this section
US-RH rev U00 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC 355 Password 0355 NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 2. Load and run Smart Scenario S-RH-28.ssf.
- 3. Have marked up copies of LOP-RH-05 and LOP-RH-13.
- 4. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.
- 5. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
US-RH rev U00 INITIAL CONDITIONS You are the assist NSO
- The RCIC Surveillance is complete
- An EO is in the field standing by to assist you INITIATING CUE The Unit Supervisor has directed you to Secure Suppression Pool Cooling and RHR Service Water per LOP-RH-13 and LOP-RH-05 and to inform them when complete.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
US-RH rev U00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE When the Examinee acknowledges their initiating cue, hand them a copy of LOP-RH-05 and LOP-RH-13.
- 1 CLOSE 1E12 F024A, A RHR Examinee closes 1E12-F024A ___ ___ ___
Test to SP Vlv. A RHR Test to SP Vlv control switch to CLOSE.
2 VERIFY 1E12 F064A, A RHR Examinee verifies 1E12-F064A ___ ___ ___
Min Flow Vlv OPENS. A RHR Min Flow Vlv OPENS.
Pump. Pump.
- ALTERNATE PATH BEGINS HERE*
4 Annunciator 1H13-P601-B112 Examinee pulls the LOR-1H13- ___ ___ ___
alarms P601-B112 and follows it.
CUE If the Examinee reports the annunciator, acknowledge as the Unit Supervisor 5 CHECK Recorder 1D18-R602 Examinee notes the following ___ ___ ___
on 1H13-P600 is reading on 1H13-P600 and 1H13-P604:
greater than or equal to alarm
- Recorder 1A WS setpoint and RECORD reading Radiation Monitor, 1D18-in Unit Log.
R602, reading approximately 800 cpm.
- 1A WS Rad Monitor 1D18-K604, Hi alarms in.
RECORD RHR Flow, Heat 6 Examinee notes: ___ ___ ___
Exchanger Pressure, and RHR Service Water Flow in Unit Log.
- RHR Flow
- RHR WS Flow
- RHR Heat exchanger Pressure 7 Notify Chemistry Department to Examinee notifies the ___ ___ ___
sample tube side of RHR and Chemistry dept. to quantify the determine amount of release. release CUE Chemistry acknowledges too sample and quantify the release.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RH rev U00 Comment SAT UNSAT STEP ELEMENT STANDARD Number 8 If the RHR Service Water Examinee verifies PRM is ___ ___ ___
Process Radiation Monitor is operable.
INOPERABLE and samples are being taken, VERIFY that Chemistry has collected the proper samples before shutdown of the pump(s).
CUE Chemistry acknowledges to sample and quantify the release.
9 Place the Thermal Overload Examinee places the Thermal ___ ___ ___
Bypass Switch in TEST for Overload Bypass Switch in 1E12-F068A. TEST for 1E12-F068A.
10 LOG positioning of O/L Bypass Examinee request Unit NSO to ___ ___ ___
switch in the Unit Log. log position of O/L Bypass Switch.
CUE Unit NSO will log position of the O/L Bypass Switch.
- 11 CLOSE 1E12-F068A RHR Hx Examinee close 1E12-F068A ___ ___ ___
Water Outlet Valve RHR HX Water Outlet Valve.
- 12 When flow indicated on 1E12- Examinee stops RHR Service ___ ___ ___
R602A decreases to 4,000 Water Pump 1E12-C300A/B.
gpm, STOP 1E12-C300 A/B.
- 13 When flow indicated on 1E12- Examinee stops RHR Service ___ ___ ___
R602A decreases to 0 gpm, Water Pump one 1E12-STOP one 1E12-C300 A/B. C300A/B.
14 Place the Thermal Overload Examinee places the Thermal ___ ___ ___
Bypass Switch in Normal for Overload Bypass Switch in 1E12-F068A. Normal for 1E12-F068A.
NOTE Additional RHR Service Water Valves may be closed in order to isolate the Heat Exchanger; however, closing the 1E12-F068A will stop the release path to the environment.
CUE Unit NSO will log position of the O/L Bypass Switch.
15 Inform Unit Supervisor that Examinee notifies Unit ___ ___ ___
could not complete the task. Supervisor 1A RHR WS is shutdown and isolated.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RH rev U00 Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE As Unit Supervisor, acknowledge report. JPM is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RH rev U00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BShutdown Suppression Pool Cooling with High Rad JPM Number: S-RH-28 Revision Number: 00 Task Number and
Title:
52.035 Provided initial conditions, respond to a High Release rate, IAW station procedures K/A Number and Importance: 272000 A1.01 (3.2/3.2) Ability to predict and/or monitor changes in parameters associated with operating the RADIATION MONITORING SYSTEM controls including: Lights, alarms, and indications associated with normal operations Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LOP-RH-05, Operation of the RHR Service Water System Rev. 34; LOP-RH-13, Suppression Pool Cooling Operation, Rev. 32 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 12 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RH rev U00 INITIAL CONDITIONS You are the assist NSO
- The RCIC Surveillance is complete
- An EO is in the field standing by to assist you INITIATING CUE The Unit Supervisor has directed you to Secure Suppression Pool Cooling and RHR Service Water per LOP-RH-13 and LOP-RH-05 and to inform them when complete.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BSwap WR Pumps per LOP-WR-02 (Alternate Path)
JPM Number: US-WR-02 Revision Number: U00 Date: 6 / 1 / 2016 Developed By:
Instructor Date Validated By: Pratt / Quinn 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-WR rev U00 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LOP-WR-02 Rev: 26 Procedure LOR-1PM10J-A201 Rev: 2 Procedure LOA-WR-101 Rev: 16
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
US-WR rev U00 Revision Record (Summary)
Revision 00, This JPM was developed NEW for the 2016 NRC Annual Exam.
SRRS: 3D.100; There are no retention requirements for this section
US-WR rev U00 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to any Full Power IC NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 2. VERIFY 1A WR Pump RUNNING.
- 3. LOAD and RUN CAE SWR02r00.cae.
- 4. Have copies of LOP-WR-02
- 5. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.
- 6. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
US-WR rev U00 INITIAL CONDITIONS You are an NSO,
- 1A WR Pump is RUNNING on Unit 1.
- BOTH 1B and 0 WR Pumps are in standby on Unit 1 and ready to be placed in service.
- An Equipment Operator is standing by to assist you.
- Prestart checks are complete INITIATING CUE The Unit Supervisor has directed you to shift WR pump operation from the 1A WR Pump to the 1B Pump IAW LOP-WR-02, Startup and Operation of the Reactor Building Closed Cooling water System, Section E.2. Notify the Unit Supervisor when the WR Pump shift is complete.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
US-WR rev U00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number NOTE: After the Examinee demonstrates where to obtain a copy of the procedure provide them with a copy of LOP-WR-02.
1 OBTAIN a copy of LOP-WR-02. Examinee demonstrates how ___ ___ ___
OBTAIN a copy of LOP-WR-02.
panel 1PM09J. Pump from panel 1PM09J.
CUE As Equipment Operator, if required, when request to perform post start checks report that post start checks of the 1B WR pump are completed SAT.
3 OBSERVE the 1B WR Pump Examinee OBSERVES the 1B ___ ___ ___
amperes on indicator 1II- WR Pump amperes on indicator WR005 on panel 1PM10J is 1II-WR005 on panel 1PM10J is slightly below normal running slightly below normal running amps of 145 to 172 amps. amps of 145 to 172 amps.
4 OBSERVE that the Unit 1 WR Examinee OBSERVES that the ___ ___ ___
Pump Discharge Header Unit 1 WR Pump Discharge Pressure increases on pressure Header Pressure increases on indicator 1PI-WR008 on panel pressure indicator 1PI-WR008 1PM10J and steadies out on panel 1PM10J and steadies slightly above normal operating out slightly above normal system pressure of 52 to 80 operating system pressure of 52 psig. to 80 psig.
NOTE: When the Examinee STOPS the 1A WR Pump a malfunction is automatically inserted to override 1B WR Pump Amps to show degrading amps and degrading WR Discharge Header Pressure.
5 STOP the 1A WR Pump after Examinee STOPS the 1A WR ___ ___ ___
the system pressure stabilizes. Pump after the system pressure stabilizes.
6 OBSERVE that the Unit 1 WR Examinee IDENTIFIES that the ___ ___ ___
Pump Discharge Header Unit 1 WR Pump Discharge Pressure returns to Header Pressure DID NOT approximately the same return to approximately the pressure prior to pump shifting same pressure prior to pump shifting AND pressures IS trending down.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-WR rev U00 Comment SAT UNSAT STEP ELEMENT STANDARD Number 7 OBSERVE 1B WR Pump Examinee IDENTIFIES that the ___ ___ ___
amperes on indicator 1II- 1B WR Pump amperes on WR005 is between 145 and 172 indicator 1II-WR005 is between amps on panel 1PM10J. 145 and 172 amps on panel 1PM10J AND is trending down.
8 NOTIFY Unit Supervisor that 1B Examinee NOTIFIES Unit WR Pump trends are Supervisor that 1B WR Pump ABNORMAL and starting 1A trends are ABNORMAL and is WR Pump. starting 1A WR Pump.
CUE As Unit Supervisor acknowledge report.
- ALTERNATE PATH BEGINS HERE*
9 If header pressure or amps are Examinee RESTARTS 1A WR ___ ___ ___
abnormal, PERFORM following: Pump.
- RESTART the 1A WR Pump
- STOP the 1B WR Pump 10 OBSERVE 1A WR Pump Examinee IDENTIFIES that the amperes on indicator 1II- 1A WR Pump amperes on WR002 is between 145 and 172 indicator 1II-WR002 is 0 amps amps on panel 1PM10J. on panel 1PM10J.
11 OBSERVE that the Unit 1 WR Examinee IDENTIFIES that the Pump Discharge Header Unit 1 WR Pump Discharge Pressure returns to Header Pressure CONTINUES approximately the same TO trend down.
pressure prior to pump shifting 12 NOTIFY Unit Supervisor that 1A Examinee NOTIFIES Unit WR Pump DID NOT START Supervisor that 1A WR Pump and starting 0 WR Pump. DID NOT START and is starting 0 WR Pump.
CUE As Unit Supervisor acknowledge report.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-WR rev U00 Comment SAT UNSAT STEP ELEMENT STANDARD Number
- 13 START Standby Reactor Examinee STARTS 0 WR ___ ___ ___
Building Closed Cooling Water Pump.
Pump per LOP-WR-02, Startup and Operation of Reactor Building Closed Cooling Water System.
14 OBSERVE that the Unit 1 WR Examinee OBSERVES that the ___ ___ ___
Pump Discharge Header Unit 1 WR Pump Discharge Pressure increases on pressure Header Pressure increases on indicator 1PI-WR008 on panel pressure indicator 1PI-WR008 1PM10J and steadies out on panel 1PM10J and steadies slightly above normal operating out slightly above normal system pressure of 52 to 80 operating system pressure of 52 psig. to 80 psig.
15 STOP the 1B WR Pump after Examinee STOPS the 1B WR ___ ___ ___
the system pressure stabilizes. Pump after the system pressure stabilizes.
16 OBSERVE that the Unit 1 WR Examinee OBSERVEs that the ___ ___ ___
Pump Discharge Header Unit 1 WR Pump Discharge Pressure returns to Header Pressure returns to approximately the same approximately the same pressure prior to pump shifting. pressure prior to shifting from 1A pump.
17 NOTIFY Unit Supervisor that Examinee NOTIFIES Unit ___ ___ ___
0WR is RUNNING supplying Supervisor that 0WR is Unit 1. RUNNING supplying Unit 1.
CUE As Unit Supervisor, acknowledge report. JPM is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-WR rev U00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BSwap WR Pumps per LOP-WR-02 (Alternate Path)
JPM Number: S-WR-02 Revision Number: 00 Task Number and
Title:
114.008 Perform the Main Control Room actions to swap Reactor Building Closed Cooling Water (RBCCW) Pumps K/A Number and Importance: 400000 A2.01 3.3/3.4 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LOP-WR-02, Startup and Operation of the Reactor Building Closed Cooling Water System, Rev. 26 LOR-1PM10J-A201 Reactor Building Closed Cooling Water Pump Discharge Header Pressure Low, Rev. 2 LOA-WR-101, Loss of Reactor Building Closed Cooling Water, Rev. 16 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 8 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-WR rev U00 INITIAL CONDITIONS You are an NSO,
- 1A WR Pump is RUNNING on Unit 1.
- Both 1B and 0 WR Pumps are in standby on Unit 1 and ready to be placed in service.
- An Equipment Operator is standing by to assist you.
- Prestart checks are complete INITIATING CUE The Unit Supervisor has directed you to shift WR pump operation from the 1A WR Pump to the 1B Pump IAW LOP-WR-02, Startup and Operation of the Reactor Building Closed Cooling water System, Section E.2. Notify the Unit Supervisor when 1B WR Pump is RUNNING.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BPartial Half Scram per LOA-RP-101 JPM Number: US-RP-05 Revision Number: U00 Date: 6 / 5 / 2018 Developed By:
Instructor Date Validated By: Pratt / Quinn 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RP rev U00 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LOA-RP-101 Rev: 16 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
US-RP rev U00 Revision Record (Summary)
Revision 00, Developed for 17-1 NRC Exam SRRS: 3D.100; There are no retention requirements for this section
US-RP rev U00 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC 151 NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 2. Load and Run Smart Scenario S-RP-05.ssf
- 3. Verify LOA-RP-101 is clean.
- 4. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.
- 5. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
US-RP rev U00 INITIAL CONDITIONS You are the Unit 1 ATC
- A partial Half Scram has occurred on Group 3 of B RPS
- Fuse F18D was found blown and has been replaced
- No testing is in progress
- The light bulb has been check and is good
- An EO in the Field is standing by to assist if necessary INITIATING CUE The Unit Supervisor has directed you to enter LOA-RP-101 and to inform them when complete.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
US-RP rev U00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number NOTE The Examinee may obtain a copy of LOA-RP-101.
1 CHECK and continue to monitor Examinee determines that only ___ ___ ___
the following: one bus is affected and no control rods are moving.
- ONLY one RPS Bus -
affected AND
- Control Rods NOT moving.
2 SUSPEND any HALF SCRAM Examinee determines from the ___ ___ ___
testing in progress. initial conditions that no testing is in progress.
3 CHECK RPS BUS Scram Sol Examinee determines only the ___ ___ ___
Group light(s) out on a single Group 3 light is out on RPS B.
RPS BUS:
o Scram Sol Group 1 and 4 OR o Scram Sol Group 2 and 3 OR o ONLY a single solenoid group light CUE If the Examinee asks the status of Fuse F18D, inform the examinee that the Assist NSO has checked the fuse and it is NOT blown.
4 VERIFY affected 1C71-F18 Examinee determines no fuses ___ ___ ___
fuse(s) NOT blown at panel are currently blown.
1H13 P609 or 1H13-P611.
- ALTERNATE PATH BEGINS HERE*
- 5 RESET HALF SCRAM. Examinee determines the Half ___ ___ ___
Scram will not reset.
CUE If the Examinee asks the status of Fuse F18D, inform the examinee that the Assist NSO has checked the fuse and it is NOT blown.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RP rev U00 Comment SAT UNSAT STEP ELEMENT STANDARD Number
- 6 INSERT a HALF SCRAM on the Examinee will insert a Half ___ ___ ___
affected RPS BUS. Scram on the B RPS Bus by arming and depressing the B1 and/or B2 Manual Scram Pushbuttons.
7 VERIFY proper rod position per Examinee checks Rod Position ___ ___ ___
Auto Scan of All Rod Positions. Auto Scan.
CUE When the Examinee brings up the Work Request, inform them another NSO will handle the Work Request.
8 INITIATE Work Request if Examinee states that a Work ___ ___ ___
necessary to complete Request should be generated.
troubleshooting CUE If the Examinee sends an EO to check SSPV solenoids, inform them that the EO will report back when complete.
9 CHECK all SSPV solenoids are Examinee orders EO to check ___ ___ ___
10° F above ambient RPS solenoids.
temperature.
10 Inform Unit Supervisor. Examinee Informs Unit ___ ___ ___
Supervisor that B.5 of LOA-RP-101 is complete and a Half Scram has been inserted on B RPS.
CUE As Unit Supervisor, acknowledge the report. JPM Complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RP rev U00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BPartial Half Scram per LOA-RP-101 JPM Number: S-RP-05 Revision Number: 00 Task Number and
Title:
49.017 Given Unit Supervisor authorization, Reset the RPS system scram, IAW station procedures K/A Number and Importance: 212000 Reactor Protection System A4.07 (4.0/3.9) Ability to manually operate and/or monitor in the control room: System status and lights Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LOA-RP-101, Unit 1 Loss of Reactor Protection System Power, Rev. 16 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 5 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
US-RP rev U00 INITIAL CONDITIONS You are the Unit NSO
- A partial Half Scram has occurred on Unit 1
- Fuse F18D was found blown and has been replaced
- No testing is in progress
- The light bulb has been check and is good
- An EO in the Field is standing by to assist if necessary INITIATING CUE The Unit Supervisor has directed you to enter LOA-RP-101 and to inform them when complete.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BPlace HCVS Nitrogen Supply In Service JPM Number: UP-PC-06 Revision Number: U00 Date: 6 / 1 / 2018 Developed By:
Instructor Date Validated By: Najdonovich / Shams 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
UP-PC rev U00 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LGA-VQ-102 Rev: 1 Procedure LGA-VQ-202 Rev: 3 Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
UP-PC rev U00 Revision Record (Summary)
Revision 00, Developed for 17-1 NRC Exam SRRS: 3D.100; There are no retention requirements for this section
UP-PC rev U00 SETUP INSTRUCTIONS
- 1. The following material is required to be provided to examinee:
- a. One copy of LGA-VQ-102 or LGA-VQ-202
- b. One laser pointer.
- 2. The following material is to be obtained by the examinee:
- a. Main LGA Support Locker key
- 3. The following material may be identified by the examinee but NOT removed from its normal storage location:
- a. Flashlights/lanterns SRRS: 3D.100; There are no retention requirements for this section
UP-PC rev U00 INITIAL CONDITIONS You are an extra NSO,
- Unit __ has experienced a LOCA
- Drywell pressure is 65 psig and slowly rising
- Suppression Chamber Pressure is 61 psig and slowly rising
- All plant Radiation Levels are normal INITIATING CUE The Unit Supervisor has directed you to align the Unit __ Hardened Containment Vent Nitrogen System per LGA-VQ-__02 Section E.1.a and inform the Control Room when complete through step 1.f Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
UP-PC rev U00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number NOTE The following steps may be performed in any order.
1 Locally PERFORM the following Examinee goes to AB 731 ___ ___ ___
at the ROS (AB 731 R-9/R-19)
- 2 Slowly OPEN, all Nitrogen Examinee slowly opens ___ ___ ___
bottle stop valves to slowly 1(2)PC433A-1 and pressurize piping: 1(2)PC433B-1 by turning the
Cue The components you identified are in the position you described.
3 CHECK Nitrogen pressure Examinee verifies 1(2)PI-PC450 ___ ___ ___
available (nominally 2000 psig) reads 2000 psig at 1(2)PI-PC450 HCVS NITROGEN SUPPLY UPSTREAM PRESS indicator.
Cue Inform the examinee that 1(2)PI-PC-C450 reads 2000 psig.
- 4 UNLOCK and OPEN Examinee unlocks and opens ___ ___ ___
1(2)PC431, HCVS NITROGEN 1(2)PC431 SUPPLY ISOL VLV Cue The components you identified are in the position you described.
5 CHECK Nitrogen pressure Examinee checks 1(2)PI-PC440 ___ ___ ___
available (nominally 110 psig) at reads 110 psig 1(2)PI-PC440 HCVS NITROGEN SUPPLY DOWNSTREAM PRESS.
CUE Inform the examinee that __PI-PC440 reads 105 psig.
CUE If the examinee turns the regulator counter-clockwise inform them that pressure is dropping. (this should cue them to turn the regulator the opposite direction)
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UP-PC rev U00 Comment SAT UNSAT STEP ELEMENT STANDARD Number
- 6 As required ADJUST HCVS Adjust 1(2)PC432 clockwise to ___ ___ ___
NITROGEN SUPPLY PRESS raise pressure to 110 psig REG VLV 1(2)PC432 to obtain approximately 110 psig nitrogen pressure on 1(2)PI-PC440.
CUE Inform the examinee that 1(2)PI-PC440 reads 110 psig.
7 If Nitrogen Pressure is >110psig Examinee determines this step ___ ___ ___
Then, DEPRESSURIZE, piping is not applicable downstream of HCVS NITROGEN SUPPLY PRESS REG VLV 1(2)PC432 8 Inform the Control Room Examinee informs the Control ___ ___ ___
Room that HCVS Nitrogen is lined up for venting CUE Inform the Examinee that the JPM is Complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UP-PC rev U00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BPlace HCVS Nitrogen Supply In Service JPM Number: P-PC-06 Revision Number: 00 Task Number and
Title:
419.040 Given LGA-003 Primary Containment Control, in progress with Drywell Pressure reaching 60 psig, vent the Drywell and/or Suppression Chamber to stay below 60 psig, IAW station procedures K/A Number and Importance: 223001 Primary Containment and Auxiliaries, A2.07 Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT AND AUXILIARIES: and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High Drywell Pressure Suggested Testing Environment: In-Plant Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LGA-VQ-102, Unit 1 Emergency Containment Vent Rev 1; LGA-VQ-202, Unit 2 Emergency Containmenyt Vent Rev 3 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UP-PC rev U00 INITIAL CONDITIONS You are an extra NSO,
- Unit __ has experienced a LOCA
- Drywell pressure is 65 psig and slowly rising
- Suppression Chamber Pressure is 61 psig and slowly rising
- All plant Radiation Levels are normal INITIATING CUE The Unit Supervisor has directed you to align the Unit __ Hardened Containment Vent Nitrogen System per LGA-VQ-__02 Section E.1.a and inform the Control Room when complete through step 1.f SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BLineup 1(2)E12-F009 to Alternate Power Supply IAW LOA-RH-1(2)01 JPM Number: UP-RH-04 Revision Number: U13 Date: 6 / 5 / 2018 Developed By:
Instructor Date Validated By: Najdonovich / Shams 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
UP-RH rev U13 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LOA-RH-101 Rev: 21 Procedure LOA-RH-201 Rev: 21 Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
UP-RH rev U13 Revision Record (Summary)
Revision 05, Utilized new template and made minor editorial changes.
Revision 06, Revised JPM for new task number, K/A values and current procedure revision.
Revision 07, Revised JPM with a Vision task number, added step for revision 8 LOA-RH-101 Revision 08, Added cue to inform candidate of the difference between labeling at MCC 136 Y-1, MCC 135X-1 and LOA-RH-101.
Revision 09, Revised for formatting and procedure revision.
Revision 10, Revised initiating cue for new procedure step. Re-ordered steps in JPM.
Revision 11, Add new Check list.
Revision 12, Revised for editorial changes and changed initial conditions to provide entry conditions into LOA-RH-101.
Revision 13, Revised to allow to be given on either Unit.
SRRS: 3D.100; There are no retention requirements for this section
UP-RH rev U13 SETUP INSTRUCTIONS
- 1. Have a Copy of LOA-RH-__01 Page 9.
- 2. Instructor has a laser pointer to provide to the student (optional).
SRRS: 3D.100; There are no retention requirements for this section
UP-RH rev U13 INITIAL CONDITIONS You are an extra NSO,
- Unit __ is in Mode 4.
- RPV Water Temperature is 180°F.
- A fault on Bus __42Y caused a spurious isolation of __E12-F009, RHR SDC SUCT HEADER INBD ISOL VALVE.
- LOA-RH-__01, Unit __ RHR Abnormal, actions are in progress.
- Isolation signals have been reset by the Control Room.
- The Shift Manager has provided you with a Master lock and key.
- You have a plant radio.
INITIATING CUE The Unit Supervisor has directed you to lineup the __E12-F009 to its alternate power supply IAW LOA-RH-__01 starting at B.1 Step 14.3. Notify the Unit Supervisor when __E12-F009 is OPEN.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
UP-RH rev U13 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number NOTE: After the Examinee demonstrates where to obtain a copy of the procedure provide them with Page 9 of LOA-RH-1(2)01.
1 OBTAIN a copy of LOA-RH- Examinee OBTAINS a copy of ___ ___ ___
1(2)01. LOA-RH-1(2)01.
CUE If Examinee asks, the 1E12-F009 has been declared INOPERBALE.
- 2 OPEN and LOCK Normal Examinee OPENS and LOCK ___ ___ ___
Supply Breaker B2 at MCC Normal Supply Breaker B2 at 1(2)36Y-1 (710 RB E-9/710 RB MCC 1(2)36Y-1.
E-15).
CUE The component you identifies is in the condition you described.
- 3 UNLOCK and CLOSE Alternate Examinee UNLOCKS and ___ ___ ___
Supply C2(C3) MCC 1(2)35X-1 CLOSES Alternate Supply (761 RB A-14). C2(C3) MCC 1(2)35X-1.
CUE The component you identified is in the condition you described.
- 4 OPEN 1(2)E12-F009 using the Examinee OPENS 1(2)E12- ___ ___ ___
local control switch on MCC F009 using the local control 1(2)35X-1 switch on MCC 1(2)35X-1 CUE The component you identified is in the condition you described.
NOTE: Per the Initiating Cue the Examinee is to notify the Unit Supervisor after the 1(2)E12-F009 is OPEN. If the Examinee notifies the Unit Supervisor immediately after OPENING the 1(2)E12-F009 then the following step can be marked N/A.
5 Place an Equipment Status Tag Place an Equipment Status Tag ___ ___ ___
on the 1(2)E12-F009 Valve on the 1(2)E12-F009 Valve Control Switch. Control Switch.
CUE If asked, an Equipment Status Tag is being prepared and will be placed by another NSO.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UP-RH rev U13 Comment SAT UNSAT STEP ELEMENT STANDARD Number 6 NOTIFY the Unit Supervisor Examinee NOTIFIES the Unit ___ ___ ___
that 1(2)E12-F009 is aligned to Supervisor that 1(2)E12-F009 is its alternate power supply and is aligned to its alternate power OPEN. supply and is OPEN.
CUE As Unit Supervisor, acknowledge report. JPM is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UP-RH rev U13 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BLineup 1(2)E12-F009 to Alternate Power Supply IAW LOA-RH-1(2)01 JPM Number: P-RH-04 Revision Number: 13 Task Number and
Title:
64.051 Given Unit Supervisor authorization, perform actions to respond to a TRIP or isolation of shutdown cooling, IAW station procedures.
K/A Number and Importance: 205000 A2.03 (3.2/3.2) Ability to (a) predict the impacts of the following on SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C. failure Suggested Testing Environment: Plant Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LOA-RH-101, Unit 1 RHR Abnormal, Rev. 21; LOA-RH-201, Unit 2 RHR Abnormal, Rev. 21 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 12 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UP-RH rev U13 INITIAL CONDITIONS You are an extra NSO,
- Unit __ is in Mode 4.
- RPV Water Temperature is 180°F.
- A fault on Bus __42Y caused a spurious isolation of __E12-F009, RHR SDC SUCT HEADER INBD ISOL VALVE.
- LOA-RH-__01, Unit __ RHR Abnormal, actions are in progress.
- Isolation signals have been reset by the Control Room.
- The Shift Manager has provided you with a Master lock and key.
- You have a plant radio.
INITIATING CUE The Unit Supervisor has directed you to lineup the __E12-F009 to its alternate power supply IAW LOA-RH-__01 starting at B.1 Step 14.3. Notify the Unit Supervisor when __E12-F009 is OPEN.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure U0BInstall LGA-CY-01 Jumpers to Enable Injection to the RPV JPM Number: UP-CY-05 Revision Number: U03 Date: 5 / 11 / 2016 Developed By:
Instructor Date Validated By: Najdonovich / Shams 7/22/18 SME or Instructor Date Reviewed By:
Training Department Date Approved By:
Operations Representative Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
UP-CY rev U03 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.
Prior to JPM usage, revalidate JPM using steps 9 and 13 below.
________ 1. Task description and number, JPM description and number are identified.
________ 2. Knowledge and Abilities (K/A) references are included.
________ 3. Performance location specified. (in-plant, control room, simulator, or other)
________ 4. Initial setup conditions are identified.
________ 5. Initiating cue (and terminating cue if required) are properly identified.
________ 6. Task standards identified and verified by SME review.
________ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).
________ 8. If an alternate path is used, the task standard contains criteria for successful completion.
________ 9. Verify the procedure(s) referenced by this JPM reflects the current revision:
Procedure LGA-CY-01 Rev: 10 Procedure Rev:
Procedure Rev:
________ 10. Verify cues both verbal and visual are free of conflict.
________ 11. Verify performance time is accurate
________ 12. If the JPM cannot be performed as written with proper responses, then revise the JPM.
________ 13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:
SME / Instructor Date SME / Instructor Date SME / Instructor Date SRRS: 3D.100; There are no retention requirements for this section
UP-CY rev U03 Revision Record (Summary)
Revision 00, New JPM for 2009 Annual Exam.
Revision 01, Revised JPM to revision 6 of LGA-CY-01. Attachment C changed to B. De-unitized JPM so it could be performed on either unit.
Revision 02, Added new Check list. Revised JPM to revision 9 of LGA-CY-01.
Revision 03, Revised for editorial changes.
SRRS: 3D.100; There are no retention requirements for this section
UP-CY rev U03 SETUP INSTRUCTIONS
- 1. Have a copy of LGA-CY-01 Attachments 1B and 2B.
SRRS: 3D.100; There are no retention requirements for this section
UP-CY rev U03 INITIAL CONDITIONS You are an extra NSO,
- Unit __ was SCRAMED and all control rods are FULL-IN.
- Feedwater has been isolated due to a leak.
- All other injection sources are UNAVAILABLE.
- RPV water level is -121 inches and dropping about 1 inch per minute.
- All Condensate Transfer Pumps are RUNNING with Header Pressure at 165 psig.
- The CY Tank is full.
- RPV pressure is 50 psig.
INITIATING CUE The Unit Supervisor has directed you to install the temporary modifications to bypass the Group 6 PCIS Isolation Logic per LGA-CY-01, Use of the Cycled Condensate System in Emergency Conditions, Attachment __B. Notify the Unit Supervisor when the Group 6 PCIS Isolation Logic has been defeated per Attachment __B.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
Information For Evaluators Use:
UNSAT requires written comments on respective step.
- Denotes critical steps.
Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.
Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
SRRS: 3D.100; There are no retention requirements for this section
UP-CY rev U03 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number NOTE: Sequence is not required for this JPM.
NOTE: After the Examinee demonstrates where to obtain a copy of the procedure provide them with a copy of LGA-CY-01 Attachment 1B.
1 OBTAIN a copy of LGA-CY-01. Examinee demonstrates where ___ ___ ___
to OBTAIN a copy of LGA-CY-01.
NOTE: The Main LGA Support Locker is outside U-2 AEER 731' AB and requires an LA Key to open. DO NOT OPEN THE LOCKER. The Examinee may use their own LA Key or it can be obtained from the WEC, Unit Supervisor, Field Supervisor, or Shift Manager.
2 OBTAIN Unit 1(2) LGA-CY-01 Examinee OBTAINS Unit 1(2) ___ ___ ___
equipment bag from the Main LGA-CY-01 equipment bag LGA Support Locker (U-2 AB from the Main LGA Support 731). Locker.
CUE You have the equipment you identified.
NOTE: The Electrical Safety gear required for this Hazard Risk Category (HRC) 1 Clothing, Class 00 Gloves, Safety Glasses, Safety/Leather Shoes, Hard Hat and Hearing Protection.
HRC 1 are Long Sleeve arc-rated FR Shirt and FR Pants or FR Coverall.
3 OBTAIN and DON required OBTAIN and DON required ___ ___ ___
Electrical Safety Electrical Safety gear/equipment. gear/equipment.
CUE You have the equipment you identified.
- 4 In the AEER at 1(2)H13-P623 Examinee INSTALLS a jumper ___ ___ ___
INSTALL a jumper from point from point BB-104 to point BB-104 to point DD-42 to DD-42 in the AEER at DEFEAT1( 2)E12-F053A Group 1(2)H13-P623.
6 isolation signals.
CUE The component you identified is in the condition you described.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UP-CY rev U03 Comment SAT UNSAT STEP ELEMENT STANDARD Number 5 Sign and Date/Time Attachment Examinee signs and puts time ___ ___ ___
1(2)B. and date in appropriate location on Attachment 1(2)B.
LIFT LEAD 10 on Relay Relay 1(2)B21H-K75 to 1(2)B21H-K75 to DEFEAT DEFEAT in the AEER at 1(2)2E12-F053A Group 6 1(2)H13-P623.
isolation signals.
CUE The component you identified is in the condition you described.
7 Sign and Date/Time Attachment Examinee signs and puts time ___ ___ ___
1(2)B. and date in appropriate location on Attachment 1(2)B.
- 8 In the AEER at 1(2)H13-P623 Examinee INSTALLS a jumper ___ ___ ___
INSTALL a jumper from point from point DD-83 to point DD-83 to DD-84 to DEFEAT DD-84 in the AEER at 1(2)E12-F053B Group 6 1(2)H13-P623.
isolation signals.
CUE The component you identified is in the condition you described.
9 Sign and Date/Time Attachment Examinee signs and puts time ___ ___ ___
1(2)B. and date in appropriate location on Attachment 1(2)B.
LIFT LEAD 12 on Relay Relay 1(2)B21H-K75 to 1(2)B21H-K75 to DEFEAT DEFEAT in the AEER at 1(2)E12-F053B Group 6 1(2)H13-P623.
isolation signals.
CUE The component you identified is in the condition you described.
11 Sign and Date/Time Attachment Examinee signs and puts time ___ ___ ___
1(2)B. and date in appropriate location on Attachment 1(2)B.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UP-CY rev U03 Comment SAT UNSAT STEP ELEMENT STANDARD Number
- 12 In the AEER at 1(2)H13-P623 Examinee INSTALLS a jumper ___ ___ ___
INSTALL a jumper from point from point CC-25 to point CC-25 to DD-22 to DEFEAT DD-22 in the AEER at 1(2)E12-F023 Group 6 isolation 1(2)H13-P623.
signals.
CUE The component you identified is in the condition you described.
13 Sign and Date/Time Attachment Examinee signs and puts time ___ ___ ___
1(2)B. and date in appropriate location on Attachment 1(2)B.
LIFT LEAD 8 on Relay Relay 1(2)B21H-K30 to 1(2)B21H-K30 to DEFEAT DEFEAT in the AEER at 1(2)E12-F023 Group 6 isolation 1(2)H13-P623.
signals.
CUE The component you identified is in the condition you described.
15 Sign and Date/Time Attachment Examinee signs and puts time ___ ___ ___
1(2)B. and date in appropriate location on Attachment 1(2)B.
16 Inform Unit Supervisor that Examinee INFORMS Unit ___ ___ ___
attachment 1(2)B is complete. Supervisor that attachment 1(2)B is complete.
CUE As Unit Supervisor, acknowledge report. JPM is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UP-CY rev U03 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
0BInstall LGA-CY-01 Jumpers to Enable Injection to the RPV JPM Number: P-CY-05 Revision Number: 03 Task Number and
Title:
414.000 Given LGA-001, RPV Control, in progress, evaluate plant conditions and restore RPV water level to > -150 inches on WR or > -185 inches on FZ using preferred injection systems and if needed alternate injection systems, IAW station procedures.
K/A Number and Importance: 295031 EA1.08 3.8/3.9 Suggested Testing Environment: Plant Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): LGA-CY-01, Use of the Cycled Condensate System in Emergency Conditions, Rev. 9 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory Comments:
Evaluators Name: (Print)
Evaluators Signature: Date:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
UP-CY rev U03 INITIAL CONDITIONS You are an extra NSO,
- Unit __ was SCRAMED and all control rods are FULL-IN.
- Feedwater has been isolated due to a leak.
- All other injection sources are UNAVAILABLE.
- RPV water level is -121 inches and dropping about 1 inch per minute.
- All Condensate Transfer Pumps are RUNNING with Header Pressure at 165 psig.
- The CY Tank is full.
- RPV pressure is 50 psig.
INITIATING CUE The Unit Supervisor has directed you to install the temporary modifications to bypass the Group 6 PCIS Isolation Logic per LGA-CY-01, Use of the Cycled Condensate System in Emergency Conditions, Attachment __B. Notify the Unit Supervisor when the Group 6 PCIS Isolation Logic has been defeated per Attachment __B.
SRRS: 3D.100; There are no retention requirements for this section
LaSalle County Station LICENSED OPERATOR EVALUATED SCENARIO GUIDE UNRC 17-1-1 Rev. 00 6/13/2018 DEVELOPED BY:
Exam Author Date TECHNICAL REVIEW: Pratt / Polega / Vanderhyden / Neitzel 7/9/18 SME/Tech Reviewer Date REVIEWED BY:
Training Department Date APPROVED BY:
Operations Representative Date
UNRC 17-1-1 Revision 00 Facility: LaSalle County Generating Station Scenario #: NRC 17-1-1 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.
SUMMARY
OF EVENTS
- 2. A RR Pump Bearing Temp High. A RR Pump Upper bearing will have increased temp which will cause the crew to lower Reactor Power. Once Bearing temperature exceeds its limit the crew will take action to trip A RR Pump.
- 3. Single Loop Operations. Once the A RR Pump has been tripped the Unit Supervisor will enter Tech Spec 3.4.1.
- 4. Feed water Pump Flow Instrument Fails Downscale. The A Feed water Pump Flow instrument will fail downscale which will cause the min flow valve to open. This will cause a fluctuation in Reactor Water Level and the crew must take manual control of the min flow valve and close it.
- 5. Single Rod Scrams. Rod 18-59 scrams and the crew must take action to disarm the control rod in RCMS.
- 6. The Unit Supervisor must declare rod 18-59 INOP and enter Tech Spec 3.1.3.
- 7. Reactor Building Closed Cooling Water Pump Trip. When the running WR pump trips the crew will take action to start a standby WR pump.
- 8. Turbine Building Exhaust Fan Trip. When the B VT Fan Trips the crew will take action to start the C VT Fan.
- 9. LOCA with Bypass path through failed vacuum breaker. A LOCA will occur in A RR Loop and when the crew takes scram action the A Vacuum breaker will fail open creating a containment bypass path.
- 10. Blowdown. When containment parameters increase to the point of violating PSP the crew will take action per LGA-004 to blowdown, Critical Tasks 1.) With primary containment pressure above 1.93 psig, containment flood level below 723 feet, and pumps not needed for core cooling available; start suppression chamber spray.
- 2) With suppression chamber pressure above 12 psig, containment flood level below 722 feet, and drywell parameters below the Drywell Spray Initiation Limit; trip all recirculation pumps and start drywell sprays using RHR pumps not needed for adequate core cooling.
- 3) When suppression chamber pressure cannot be maintained below the Pressure Suppression Pressure (PSP),
INITIATE emergency depressurization. (or anticipates Blowdown and depressurizes rapidly via the main turbine bypass valves.)
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 2 of 29
UNRC 17-1-1 Revision 00 TRAINING REQUESTS (if applicable)
- 1. None OPEX (if applicable)
- 1. None Operator Fundamentals
- 1. Monitoring plant indications and conditions closely
- 2. Controlling plant evolutions precisely
- 3. Operating the plant with a conservative bias
- 4. Working effectively as a team
- 5. Having a solid understanding of plant design, engineering principles, and sciences SOER 10-2
- 1. Supervisory oversight role
- 2. Recognition and mitigation of risk
- 3. Worker performance
- 4. Tolerance of repetitive/long standing issues and degradation of standards
- 5. Operating Experience Record of Revisions (Summary)
Rev. 0 Developed new for the ILT 17-1 NRC Exam SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 3 of 29
UNRC 17-1-1 Revision 00 INITIAL SIMULATOR SETUP/ REQUIRED DOCUMENTATION
- 1. Recall a full power IC
- 2. Place simulator in RUN
- 3. Load and run the SmartScenario file NRC 17-1-1.ssf
- 4. Update the Tech Spec Timeclock Sheet as follows:
TS/TRM/ODCM System/ Required REQUIRED ACTION Completion Expiration Component Action Description Time Date/Time N/A N/A N/A N/A N/A N/A
- 5. Perform the pre-scenario checklist (TQ-LA-150-0308)
SCENARIO OUTLINE (NRC Evaluations Only)
Event Malf. Event Event No. No. Type* Description none N (BOP) 1 Swap EHC Pumps (LOP-EH-04) l1076 R (ATC) 2 l1121 A Reactor Recirc Pump Bearing High Temp/Trip none T (US) 3 Single Loop mcf072 I ( ATC) 4 Feedwater Pump Flow Instrument Fails Downscale sri002 C (ATC) 5 Single Rod Scrams none T (US) 6 Rod INOP mcw014 C (BOP) 7 Reactor Building Closed Cooling Water Pump Trip k7d15wpg C (BOP) 8 Turbine Building Exhaust Fan Trip mca006 M 9 mrc036 LOCA with Bypass Path through Failed Vacuum Breaker none M 10 Blowdown
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specification APPROXIMATE SCENARIO RUN TIME 60 Minutes SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 4 of 29
UNRC 17-1-1 Revision 00 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE)
During performance of tasks, dynamic learning activities, or formal evaluations, 769.00.01 demonstrate applicable Human Performance behaviors IAW the appropriate procedures.
Given an operating experience document, paraphrase the lessons learned and 762.04.00 methods to prevent recurrence at LaSalle Station, as described in the training material.
During performance of tasks, apply the administrative requirements of PROCEDURE 614.010 USE AND ADHERENCE EXPECTATIONS, IAW station procedures.
TASKS RO - ATC 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram, IAW station procedures 22.008 Given initial plant conditions, Respond to Reactor Recirc Pump Trouble, IAW station procedures.
Given initial plant conditions, Perform the Control Room actions to respond to a loss of one or 22.015 both RR pumps, IAW station procedures.
Given initial plant conditions, Respond to a Control Rod Drive failures from the Main Control 25.048 Room, IAW station procedures.
Given initial plant conditions, Perform Control Room actions to respond to a RFP recirculation 77.053 valve full open alarm IAW station procedures.
Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 413.000 59.5 IAW LGA-001 Evaluate plant conditions and restore RPV water level to > -150 inches on WR or > -185 inches 414.000 on FZ using preferred injection systems and if needed alternate injection systems, IAW station procedures.
Given LGA-003 in progress, Evaluate plant conditions and control and maintain Primary 419.000 Containment Pressure to less than 1.93 psig, IAW LGA-003.
419.020 Given LGA-003 in progress, spray the Suppression Pool, IAW LGA-003.
419.030 Given LGA-003 in progress, spray the Drywell, IAW LGA-003.
Given LGA-003 in progress, vent the Drywell and/or Suppression Chamber to stay below 60 psig, 419.040 IAW LGA-004.
Given LGA-003 in progress, evaluate plant conditions and control and maintain suppression pool 421.000 temperature less than HCTL, IAW LGA-003.
421.010 Given LGA-003 in progress, cool the Suppression Pool, IAW LGA-003.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 5 of 29
UNRC 17-1-1 Revision 00 RO - BOP/ASSIST 2.010 Respond to a Transformer Trouble and take the appropriate actions to restore.
Given Unit Supervisor authorization, perform the in-plant actions to shift EHC Pumps, IAW 73.005 station procedures.
Given initial plant conditions , Perform the Main Control Room actions for a Trip of a Reactor 114.019 Building Closed Cooling Water (RBCCW) Pump, IAW station procedures.
Given initial plant conditions , Perform the Main Control Room actions for a Reactor Building 114.027 Closed Cooling Water (RBCCW) Pump Discharge Pressure Low Alarm, IAW station procedures.
Given initial plant conditions , Perform Control Room actions for a loss of RBCCW, IAW station 114.029 procedures.
Given initial plant conditions , Start-up the Turbine Building Ventilation System (VT), IAW 119.014 station procedures.
Given entry in LGA-10, Failure to Scram, evaluate plant conditions and maintain a Heat Sink, 432.000 IAW station procedures.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 6 of 29
UNRC 17-1-1 Revision 00 SRO - UNIT SUPERVISOR 22.008 Given initial plant conditions, Respond to Reactor Recirc Pump Trouble, IAW station procedures.
Given initial plant conditions, Perform the Control Room actions to respond to a loss of one or 22.015 both RR pumps, IAW station procedures.
Given initial plant conditions, Respond to a Control Rod Drive failures from the Main Control 25.048 Room, IAW station procedures.
Given Unit Supervisor authorization, perform the in-plant actions to shift EHC Pumps, IAW station 73.005 procedures.
Given initial plant conditions, Perform Control Room actions to respond to a RFP recirculation 77.053 valve full open alarm IAW station procedures.
Given initial plant conditions , Perform the Main Control Room actions for a Trip of a Reactor 114.019 Building Closed Cooling Water (RBCCW) Pump, IAW station procedures.
Given initial plant conditions , Perform the Main Control Room actions for a Reactor Building 114.027 Closed Cooling Water (RBCCW) Pump Discharge Pressure Low Alarm, IAW station procedures.
Given initial plant conditions , Perform Control Room actions for a loss of RBCCW, IAW station 114.029 procedures.
Given initial plant conditions , Start-up the Turbine Building Ventilation System (VT), IAW station 119.014 procedures.
Given a set of plant conditions, identify and prepare the Technical Specification required actions 201.011 IAW Tech Specs.
Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 413.000 59.5 IAW LGA-001 Evaluate plant conditions and restore RPV water level to > -150 inches on WR or > -185 inches 414.000 on FZ using preferred injection systems and if needed alternate injection systems, IAW station procedures.
Given LGA-003 in progress, Evaluate plant conditions and control and maintain Primary 419.000 Containment Pressure to less than 1.93 psig, IAW LGA-003.
419.020 Given LGA-003 in progress, spray the Suppression Pool, IAW LGA-003.
419.030 Given LGA-003 in progress, spray the Drywell, IAW LGA-003.
Given LGA-003 in progress, vent the Drywell and/or Suppression Chamber to stay below 60 psig, 419.040 IAW LGA-004.
Given LGA-003 in progress, evaluate plant conditions and control and maintain suppression pool 421.000 temperature less than HCTL, IAW LGA-003.
421.010 Given LGA-003 in progress, cool the Suppression Pool, IAW LGA-003.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 7 of 29
UNRC 17-1-1 Revision 00 Event - 1
==
Description:==
Swap EHC Pumps Initiation: Per Lead Evaluator, following the crew assuming the shift Cues: Turnover Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor Reactor Power, Level and Pressure ATC
- Provide peer checks as required Per LOP-EH-04
- At the Turbine Control Panel 1PM02J:
- START the oncoming EHC Fluid Pump, 1EH02PB.
- OBSERVE the Discharge Pressure Normal (green) light comes ON for the EHC pump just started.
73.005 BOP
- OBSERVE that EHC Supply header pressure is approximately 1600 psig or slightly above as read on 1PI-EH001.
- STOP the offgoing EHC Fluid Pump from control room panel 1(2)PM02J.
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 8 of 29
UNRC 17-1-1 Revision 00 Event - 1
==
Description:==
Swap EHC Pumps Simulator Operator Actions none Simulator Operator Role Play When, requested, as EO in the field, report that step E1.6 and E.1.7 are complete. (Adjust pressure using local adjusting screw)
When, requested, as EO in the field, report that step E1.11 is complete. (lock nut for adjusting screw is tightened)
Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When A EHC Pump is secured and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 9 of 29
UNRC 17-1-1 Revision 00 Event - 2
==
Description:==
A Reactor Recirc Pump Bearing High Temp/Trip Initiation: Per Lead Evaluator Cues:
Expected Annunciator: 1H13-P602-B507, Reactor Recirculation Pump 1A/1B Temperature High Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOR-1H13-P602-B507
- CHECK Reactor Recirculation Pump Motor 1A/1B Temperatures are equal to or greater
- than alarm setpoints on Pump/Motor 1A/1B Temperature recorder 1B33-R601AA, AB, BA, BB on panel 1H13-P614.
- If Bearing Temperature(s) (Point 1/2/3/4 on 1B33-R601AA/BA) are approaching their limits, REDUCE Reactor Power to stop the bearing temperature increase.
- If above Bearing temperature limits (Point 1/2/3/4 on 1B33-R601AA/BA) are exceeded and cannot be reduced, TRIP the affected RR Pump and refer to LOA-RR-101. Note: Motor Thrust Bearing Upper Face actual limit, requiring manual trip, is 220ºF.
Per LOA-RR-101
- CHECK at least one Recirc pump operating.
22.008
- 1H13-P603-A109, OPRM Hi Alarm- CLEAR.
22.015 ATC
- PERFORM Subsection B.1, Thermal Hydraulic Instabilities, while continuing below.
- VERIFY both RR Loop M/A stations are in MANUAL
- CHECK operating Recirc Pump in HIGH SPEED.
- At 1DS001, initiate TADS by DEPRESSING TDR icon.
- NOTIFY IMD
- DECREASE FCV position to minimum for tripped Recirc pump.
- Check OPEN the 1A and 3A Bkr
- VERIFY CLOSED 2A or 1A and 4A Bkr o If the Reactor Recirc Pump is being shutdown and the unit will remain in single loop operation for > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, CLOSE either of the following to prevent reverse rotation 1B33-F067A/B, RR pump discharge (preferred) o After 5 minutes, RE-OPEN valve closed above to re-establish flow in the idle loop.
- CHECK SLO condition is allowed with current existing Equipment Out of Service conditions
- INSERT control rods to reduce Reactor Power to less than 65.7% FCL Per LOR-1H13-P602-B507 BOP
- VERIFY proper operation of RBCCW System
- VERIFY proper operation of Primary Containment Ventilation System 22.008 22.015 US
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 10 of 29
UNRC 17-1-1 Revision 00 Event - 2
==
Description:==
A Reactor Recirc Pump Bearing High Temp/Trip Simulator Operator Actions When directed by the Lead Evaluator (Initial Temp Release Event 2A increase above alarm setpoint)
When directed by the Lead Evaluator (Temp increase Release Event 2B above max temp for RR Trip)
Simulator Operator Role Play Respond as QNE and inform the crew that you will report to the Control Room.
Respond as IMD and report that preps are being made for LIS-NR-107.
Respond as required Floor Instructor Notes/OPEX/TRs Note: The crew should initially reduce power from the high bearing temp followed by tripping the RR Pump. If the crew fails conservatively and immediately trips the RR Pump the power reduction will occur later in LOA-RR-101 using Control Rods to reduce power below 65.7.% FCL.
Terminus: Following Power reduction and RR Pump Trip and with the concurrence of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 11 of 29
UNRC 17-1-1 Revision 00 Event - 3
==
Description:==
Single Loop Initiation: Per Lead Evaluator Cues: Manual Trip of 1A RR Pump Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Continue with actions of Event 2 BOP
- Continue with actions of Event 2
- INITIATE Tech Spec 3.4.1 Required Action C.1 requirements for Single Loop Operation.
- REDUCE MCPR. (LCO 3.4.1.c) 201.011 US
- REDUCE APLHGR. (LCO 3.4.1.a)
- REDUCE LHGR (LCO 3.4.1.b)
- PERFORM LIP-NR-519A/B, Unit 1 APRM Channel A, B, C, D, E, and F and RBM Channel A/B Single Recirculation Loop Setpoint Entry and Exit. (LCO 3.4.1.d/e)
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 12 of 29
UNRC 17-1-1 Revision 00 Event - 3
==
Description:==
Single Loop Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note: Per NOTE in LOA-RR-101 Tech Spec 3.2.1, 3.2.2 AND 3.2.3 do not need to be entered.
Terminus: Following Tec Spec Call and with concurrence from the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 13 of 29
UNRC 17-1-1 Revision 00 Event - 4
==
Description:==
Feedwater Pump Flow Instrument Fails Downscale Initiation: Per Lead Evaluator Cues:
Automatic Actions: None Expected Annunciator: 1H13-P603-A511, RWLCS Trouble Key Parameter Response: Reactor Level Fluctuations Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOR-1H13-P603-A511
- At the 1DS001 Operation Station Event List, Check alarm message.
- If alarm message is "Dev Header/Pump Flow" then CHECK for failing reactor feed pump discharge flow signal.
77.053 ATC
- If a Reactor feed pump discharge flow signal has failed,
- VERIFY the corresponding reactor feed pump minflow M/A station is in manual.
- POSITION the corresponding reactor feed pump minflow as required for plant conditions.
- REFER to LOP-FW-16 to determine cause of alarm and required actions.
- Monitor plant conditions and update the crew as required 77.053 US
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 14 of 29
UNRC 17-1-1 Revision 00 Event - 4
==
Description:==
Feedwater Pump Flow Instrument Fails Downscale Simulator Operator Actions When directed by the Lead Release Event 4 Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note: The corresponding position for the Min Flow Valve is full closed for plant conditions.
Terminus: When the Min Flow Valve is closed in Manual and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 15 of 29
UNRC 17-1-1 Revision 00 Event - 5
==
Description:==
Single Rod Scrams Initiation: Per Lead Evaluator Cues:
Automatic Actions: None Expected Annunciator: 1H13-P603-A503, CRD Hydraulic Accumulator Trouble 1H13-P603-A504, Control Rod Drive Drift Alarm Key Parameter Response: Rod 18-59 Inserts Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOA-RD-101
- Continually check rod status
- CHECK no control rod currently moving
- VERIFY insert block is OFF
- CHECK control rod remains at position 04 or less
- If insert pushbutton is NOT being held depressed:
- If desired o PLACE control rod OOS on RCMS 25.048 ATC o DISARM control rod electrically on RCMS
- Perform LPRM diagnostic
- RUN OD-20
- If required, restore RWM/CRD to normal as follows o PLACE RWM mode to RUN o PLACE Inop Rods OOS per LOP-RM-02 o PLACE CRD DRIVE FLOW TRIP CIRCUIT BYPASS Switch to ACTIVE
- Refer to LOP-RD-29 BOP
- Provide peer checks as required
- Direct above actions
- Set manual Scram criteria o More than 1 rod moving at the same time 25.048 US o More than 3 rods SCRAMMED OR DRIFTED Full in
- Contact system Engineering and QNE
- Contact Shift Manager SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 16 of 29
UNRC 17-1-1 Revision 00 Event - 5
==
Description:==
Single Rod Scrams Simulator Operator Actions When directed by the Lead Release Event 5 Evaluator Simulator Operator Role Play Respond as QNE and System Engineering.
If asked for Local indications at the HCU, as an EO in the Field report that there are no abnormal; indications at the HCU. Local Accumulator pressure for rod 18-59 is 900 psig.
If requested the to take follow up action per LOR-1H13-P603-A503, inform the crew that Field Supervisor will brief 2 Eos and inform the crew when they are briefed.
Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 17 of 29
UNRC 17-1-1 Revision 00 Event - 6
==
Description:==
Rod INOP Initiation: Event 5 Cues: Rod 18-59 Scrams Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOP-RM-02
- DETERMINE desired control rod to be Electrically disarmed
- SELECT SET PARAMETERS
- SELECT ELECTRICALLY DISARM/RESTORE ROD on the SET HCU screen
- SELECT control rod to be electrically disarmed
- Press ACCEPT to change the desired control rod to electrically disarm
- ACKNOWLEDGE popup messages
- The electrically disarmed rod will appear in white text on light gray back 25.048 ATC round with orange border
- RETURN to the SELECT screen, if desired, when all ED operations are complete.
o May Place Rod OOS per LOP-RM-02
- SELECT SET PARAMETERS on the ROD SELECT Display or the STATUS Display, whichever is in the CONTROL mode.
- SELECT DECLARE/RESTORE ROD OUT OF SERVICE on the SET HCU/ROD screen.
- SELECT the control rod(s) to be declared out-of-service.
- PRESS ACCEPT to place the control rod out of service.
- ACKNOWLEDGE the popup message BOP
- Provide peer checks as required
- Enter Tech Spec 3.1.3 Condition C
- Required action C.1 fully insert inop control rod in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> AND C.2 disarm the associated CRD in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 25.048
- Enter Tech Spec 3.1.5 Condition A US 201.011
- Required Action A.2 declare the associated control rod inoperable.
- Refer to Tech Spec 3.1.6 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 18 of 29
UNRC 17-1-1 Revision 00 Event - 6
==
Description:==
Rod INOP Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Following Tech Spec call and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 19 of 29
UNRC 17-1-1 Revision 00 Event - 7
==
Description:==
Reactor Building Closed Cooling Water Pump Trip Initiation: Per Lead Evaluator Cues:
Automatic Actions: A WR Pump Trip Expected Annunciators: LOR-1PM10J-A101, Reactor Building Closed Cooling Water Pump Automatic Trip Key Parameter Response:
Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor Plant parameters and update the crew as required.
ATC o Refer to LOA-RT-101 Per LOR-1PM10J-A101
- Verify automatic action occurs
- Start standby Reactor Building Closed Cooling Water Pump
- Dispatch operator to Bus 133 for Pump 1A to inspect breaker for Reactor Building Closed Cooling Water Pump for abnormalities
- Dispatch operator to El 786 in Reactor Building to inspect Reactor 114.019 Building Closed Cooling Water Pump for abnormalities 114.027 BOP
- Refer to LOA-WR-101, Loss of Reactor Building Closed Cooling Water 114.029 o Refer to LOP-WR-02, Startup and Operation of the Reactor Building Closed Cooling Water System Per LOA-WR-101
- Check RBBCW header discharge pressure - greater than 50 psig Response not obtained
- Start standby RBCCW pump 114.019 114.027 US
- Direct above actions 114.029 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 20 of 29
UNRC 17-1-1 Revision 00 Event - 7
==
Description:==
Reactor Building Closed Cooling Water Pump Trip Simulator Operator Actions When directed by the Lead Release Event 7 Evaluator Simulator Operator Role Play If sent to investigate the A WR Pump as the Operator in the field, wait 2 minutes and report, A WR Pump tripped on Overcurrent If asked, as Unit 2 inform the Unit 1 that the Common WR Pump is aligned to Unit 1.
Floor Instructor Notes/OPEX/TRs Note: RT may isolate due to WR Pump trip. RT recovery will not be performed.
Terminus: When a standby WR Pump is running and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 21 of 29
UNRC 17-1-1 Revision 00 Event - 8
==
Description:==
Turbine Building Exhaust Fan Trip Initiation: Per Lead Evaluator Cues:
Automatic Actions: 1VT02CB Trips Expected Annunciators: 1PM06J-B403, Turbine Building Exhaust Fan 1VT02CB Automatic Trip Key Parameter Response: None Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor Reactor Power, Level nad Pressure Per LOR-1PM06J-B404
- VERIFY above automatic actions occur
- Start idle exhaust fan
- Determine cause of trip
- Enter LOA-VT-101
- Refer to LOP-VT-01 119.015 BOP
- INITIATE appropraite corrective action Per LOA-VT-101
- CHECK two Turbine Building Exhaust Fans OPERATING
- START additional Turbine Buuilding Exhaust Fan(s)
- Verify Main Stack flow is isokinetic
- Check TB DP between -2.0 and 0 in. H2O 119.015 US
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 22 of 29
UNRC 17-1-1 Revision 00 Event - 8
==
Description:==
Turbine Building Exhaust Fan Trip Simulator Operator Actions When directed by the Lead Release Event 8 Evaluator Simulator Operator Role Play When ordered to investigate the VT Fan Trip, as EO, wait 3 minutes and report it tripped on Over Current.
If requested, as EO, report Turbine Building DP is -1.0 H2O Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Following the start of the 1C VT Exhaust Fan and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 23 of 29
UNRC 17-1-1 Revision 00 Event - 9
==
Description:==
LOCA with Bypass Path through Failed Vacuum Breaker Initiation: Per Lead Evaluator Cues:
Automatic Actions: Reactor Scram, ECCS initiations, PCIS Isolations Expected Annunciators: 1H13P603-B501 PRI CNMT PRESSURE HI/LO Key Parameter Response: Rising Containment Pressure Task/
Position EXPECTED OPERATOR RESPONSE Obj.
o Responds to PRI CONT PRESSURE HI/LO annunciator and informs the Unit supervisor
- When directed, manually scrams the reactor 419.000
- PLACE Reactor Mode Switch in SHUTDOWN 414.000
- CHECK Control Rods INSERTED and Power Decreasing 419.030 ATC
- REPORT to the Unit Supervisor the status of RPV Level and Pressure 421.000
- VERIFY Reactor Recirculation Pumps have downshifted 421.010
- VERIFY Main Turbine and Generator Trip 413.000
- STABILIZE Reactor Pressure <1020 psig
- REFER to LGP-3-2
- Monitors and reports RPV water level throughout
- Controls injection from Condensate and Feed system
- To prevent losing Chamber Spray/ECCS runout with DW Spray prior to 500 psig.
- Place Div 1/2 Inj Override Switch to NON-ATWS
- Div I: With an ECCS signal present Verify White Manual Override light for 1E12-F042A AND 1E21-F005 Illuminated
- Div II: With an ECCS signal present Verify White Manual Override light for 1E12-F042B AND 1E12-F042C Illuminated Per LGA-RH-103
- When directed places Suppression Pool Cooling in service:
419.000
- Startup RHR Service Water as follows:
304.010
- OPEN 1A/1B RHR Hx Service Water Outlet Valve: 1E12-F068A/B 414.000
- At approximately 9 to 10 seconds after taking the 1E12-F068A/B switch to OPEN, 419.020 BOP START first RHR Service Water Pump: 1A or 1B/C or D 419.030
- When indicated flow reaches 3000 gpm, START second RHR Service Water 421.000 Pump.
421.010
- Startup RHR
- Start 1A/1B RHR Pump
- Establish RHR flow of 1500 to 7450 gpm:
- Throttle 1E12-F024A/B (Test Valve) OPEN.
- Close 1E12-F048A/B (HX Bypass) o Place A/B HTX Bypass Throttle/Seal in switch to THROTTLE and THROTTLE CLOSED 1E12-F048A/B. o o Place A/B HTX Bypass Throttle/Seal in switch to SEAL IN and CLOSE 1E12-F048A/B
- When directed establish Suppression Chamber Spray: (CT)
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 24 of 29
UNRC 17-1-1 Revision 00
- VERIFY 1A/1B RHR Pump is running
- OPEN 1E12-F027A/B
- When directed establish Drywell Spray: (CT)
- VERIFY 1A/1B RHR Pump is running
- THROTTLE 1E12-F024A/B CLOSED
- OPEN:1E12-F016A/B and 1E12-F017A/B o May direct a manual reactor scram prior to reaching 1.93 psig in the Drywell
- Enters and directs actions of LGA-001 LEVEL LEG
- Establishes a RPV water level band of 20 to +50 inches
- Enters and directs actions of LGA-001 PRESSURE LEG
- STABILIZE Reactor Pressure below 1059 psig
- When Drywell Pressure exceeds 1.93 psig, enters and directs actions of LGA-003 419.000
- Before Suppression Chamber Pressure exceeds 12 psig 304.010 US
- Verifies Containment Flood level below 723 ft.
414.000
- Directs start of Suppression Chamber Sprays (CT)
- When Suppression Chamber Pressure exceeds 12 psig, direct initiation of Drywell sprays
- Verifies Containment Flood level below 722 ft.
- Verifies Drywell Pressure and Temperature permit Drywell Sprays per Figure D
- Verifies both Recirc Pumps are tripped
- Direct initiation of Drywell sprays (CT)
- When Suppression Pool temperature exceeds 105ºF initiation of direct initiation of Suppression Pool Cooling Event - 9
==
Description:==
LOCA with Bypass Path through Failed Vacuum Breaker Simulator Operator Actions When directed by the Lead Release Event 9 Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note: If level 1 is received LPCS.1C RHR override will clear and LPCS/1C RHR will Inject Terminus: continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 25 of 29
UNRC 17-1-1 Revision 00 Event - 10
==
Description:==
Blowdown Initiation: Automatic Cues:
Automatic Actions: 7 SRVs Open Expected Annunciators: Multiple Key Parameter Response: Lowering RPV Pressure Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Control RPV Level in band
- If directed, opens Turbine Bypass Valves o If directed, prevents LPCS, LPCI, and HPCS not needed for core cooling.
- Arms and depresses both Div 1 ADS MANUAL INITIATION pushbuttons
- Arms and depresses both Div 2 ADS MANUAL INITIATION pushbuttons
- If cannot restore chamber pressure and pool level inside Pressure Suppression Pressure and hold it there, blowdown per LGA-004 or anticipate blowdown using Turbine Bypass Valves.
- Determines if SC pressure will remain within the Pressure Suppression Pressure (PSP) limit.
o May anticipate Blowdown and directs actions to rapidly depressurize via 419.040 US turbine bypass valves
- Verifies DW pressure at or above 1.77 psig.
o May direct NSO to prevent LPCS and LPCI not needed for cooling
- Verifies SP level greater than -18 ft.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 26 of 29
UNRC 17-1-1 Revision 00 Event - 10
==
Description:==
Blowdown Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When ADS has been initiated or blowdown anticipated and at the discretion of the Exam lead.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 27 of 29
UNRC 17-1-1 Revision 00 REFERENCES Procedure Rev Title
- 1. INPO 15-004 Operations Fundamentals
- 2. SOER 10-2 Engaged, Thinking Organizations
- 3. LOP-EH-04 18 SHIFTING PUMPS AND PRESSURE ADJUSTMENT IN THE ELECTRO
- 4. LOA-RR-101 38 UNIT 1, REACTOR RECIRCULATION SYSTEM ABNORMAL
- 5. LOR-1H13-P602-B507 20 Reactor Recirculation Pump 1A/1B Temperature
- 6. LOR-1H13-P603-A511 2 RWLCS Trouble
- 7. LOA-RD-101 21 Control Rod Drive Abnormal
- 8. LOR-1H13-P603-A503 8 CRD Hydraulic Accumulator Trouble
- 9. LOR-1H13-P603-A504 4 Control Rod Drive Drift Alarm
- 10. LGA-001 18 RPV Control
- 11. LGA-003 17 Primary Containment Control
- 12. LGA-004 9 RPV Blowdown
- 13. OP-LA-101-111-1002 71 LaSalle Operations Philosophy Handbook.
- 14. OP-LA-103-102-1002 17 Strategies for Successful Transient Mitigation
- 15. OP-AA-106-101 21 Significant Event Reporting
- 16. OP-LA-STA-1001 5 LaSalle Shift Technical Advisor (STA) Checklists
- 17. EP-AA-1005 Add. 3 3 Emergency Action Levels for LaSalle Station
- 18. EP-MW-114-100-F-01 J Nuclear Accident Reporting System(NARS) Form SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 28 of 29
UNRC 17-1-1 Revision 00 U1 SUPERVISOR TURNOVER Shift: Days Date: Today Mode: 1 OLR: Green Work Week: Non-Div Unit 1 power level Unit 2 power level
- 100 % Power
- 100 % Power U1 Thermal Limit Issues /Power Evolutions U2 Thermal Limit Issues /Power Evolutions
- None
- None Existing LCOs, date of next surveillance Existing LCOs, date of next surveillance
- None
- None LOSs in progress or major maintenance LOSs in progress or major maintenance
- None
- None Equipment removed from service or currently unavailable
- None
- None Grid Status is Green Comments, evolutions, problems, etc. Comments, evolutions, problems, etc.
- Swap to B EHC Pump at 1PM02J per LOP-
- Non-Div Workweek. OLR is Green EH-04 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 29 of 29
LaSalle County Station LICENSED OPERATOR EVALUATED SCENARIO GUIDE NRC 17-1-2 Rev. 00 6/13/2018 DEVELOPED BY:
Exam Author Date TECHNICAL REVIEW: Polega / Pratt / Quinn / Vanderhyden 7/10/18 SME/Tech Reviewer Date REVIEWED BY:
Training Department Date APPROVED BY:
Operations Representative Date
NRC 17-1-2 Revision 00 Facility: LaSalle County Generating Station Scenario #: NRC 17-1-2 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.
SUMMARY
OF EVENTS
- 1. Bypass Valve Surveillance. Following turnover the crew will commence LOS-TG-M4 and bypass valve #1 will operate normally.
- 2. Bypass Valve Fails open. When the crew performs the surveillance on bypass valve #2 the valve will not close. The crew will take action per LOA-EH-101 and lower Reactor Power.
- 3. Bypass Valve INOP. The Unit Supervisor will enter Tech Specs for a failed open bypass valve.
- 4. Off Gas Post Treat B Fails downscale. The crew will take action to bypass the failed PRM.
- 7. TDRFP Oil Leak, Manual Trip. The crew will receive low oil pressure indications and receive field reports of an oil leak. The crew will take action to trip the 1B TDRFP and verify operation of the MDRFP.
- 8. Single MSIV Closure. D MSIV will close and the crew will take action to place RWLC in Single Element.
- 9. Multiple Rods Fail Full in, Hydraulic ATWS. When multiple rods scram full in the crew will take action to manually scram the reactor. This will lead to a hydraulic ATWS and crew will take action per LGA-010 and LGA-NB-01 to insert control rods and lower Reactor Power.
Critical Tasks
- 1) With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron or inserting control rods, to protect the primary containment within 2 minutes following Reactor Level 2 being reached (-55 inches).
- 2) With a reactor scram required, the reactor not shutdown, and conditions for ADS blowdown are met, or will be, INHIBIT ADS prior to initiation to prevent an uncontrolled RPV depressurization, to prevent causing a significant power excursion.
- 3) During an ATWS with reactor power above 3% or unknown, RAPIDLY DROP LEVEL in the RPV to at least -
60 within 16 minutes.
- 4) During an ATWS with reactor power above 3% or unknown, and RPV level less than -60 HOLD RPV level between -60 and -150 on Wide Range.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 2 of 27
NRC 17-1-2 Revision 00 TRAINING REQUESTS (if applicable)
- 1. None OPEX (if applicable)
- 1. None Operator Fundamentals
- 1. Monitoring plant indications and conditions closely
- 2. Controlling plant evolutions precisely
- 3. Operating the plant with a conservative bias
- 4. Working effectively as a team
- 5. Having a solid understanding of plant design, engineering principles, and sciences SOER 10-2
- 1. Supervisory oversight role
- 2. Recognition and mitigation of risk
- 3. Worker performance
- 4. Tolerance of repetitive/long standing issues and degradation of standards
- 5. Operating Experience Record of Revisions (Summary)
Rev. 0 Developed new for the ILT 17-1 NRC Exam SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 3 of 27
NRC 17-1-2 Revision 00 INITIAL SIMULATOR SETUP/ REQUIRED DOCUMENTATION
- 1. Recall a full power IC
- 2. Place simulator in RUN
- 3. Load and run the SmartScenario file NRC 17-1-2.ssf
- 4. Update the Tech Spec Timeclock Sheet as follows:
TS/TRM/ODCM System/ Required REQUIRED ACTION Completion Expiration Component Action Description Time Date/Time N/A N/A N/A N/A N/A N/A
- 5. Perform the pre-scenario checklist (TQ-LA-150-0308)
SCENARIO OUTLINE (NRC Evaluations Only)
Event Malf. Event Event No. No. Type* Description none N (BOP) 1 Bypass Valve Surveillance mms044 R (ATC) 2 Bypass Valve Fails Open none T (US) 3 Bypass Valve INOP mrm012 I (BOP) 4 Off Gas Post Treat B Fails Downscale mnb078 C (BOP) 5 Spurious HPCS Initiation none T (US) 6 HPCS INOP g4c14g1y C (ATC) 7 TDRFP Oil Leak, Manual Trip k1p40e12 C (ATC) 8 Single MSIV Closure sri010/20/ M 20/40 9 mrd277 Multiple Rods Scram Full-In, Hydraulic ATWS mrd278
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specification APPROXIMATE SCENARIO RUN TIME 60 Minutes SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 4 of 27
NRC 17-1-2 Revision 00 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE)
During performance of tasks, dynamic learning activities, or formal evaluations, 769.00.01 demonstrate applicable Human Performance behaviors IAW the appropriate procedures.
Given an operating experience document, paraphrase the lessons learned and 762.04.00 methods to prevent recurrence at LaSalle Station, as described in the training material.
During performance of tasks, apply the administrative requirements of PROCEDURE 614.010 USE AND ADHERENCE EXPECTATIONS, IAW station procedures.
TASKS RO - ATC 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures Given plant conditions, perform control room actions to respond to a failure of automatic RWLCS, 31.014 IAW station procedures.
Given plant conditions, perform Control Room actions to shutdown HPCS after an Auto Initiation, 61.006 IAW station procedures.
Given plant conditions, perform Control Room actions for a Stuck Open Bypass Valve, IAW 73.013 station procedures.
Given plant conditions, perform Control Room actions to respond to a TDRFP low hydraulic 77.046 pressure alarm, IAW station procedures.
Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 413.000 59.5 IAW LGA-001 Given entry in LGA-10, Failure to Scram, evaluate plant conditions and shutdown the reactor IAW 431.000 station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and insert control rods IAW 431.010 station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and perform SBLC injection, 431.020 IAW station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and maintain a Heat Sink, IAW 432.000 station procedures.
Given entry in LGA-10, Failure to Scram, evaluate plant conditions and maintain RPV water level 433.000 IAW LGA-010.
Given entry in LGA-10, Failure to Scram, evaluate plant conditions and control reactor power by 434.000 maintaining RPV water level IAW station procedures.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 5 of 27
NRC 17-1-2 Revision 00 RO - BOP/ASSIST Given plant conditions, perform the Main Control Room actions to startup and operate the 52.004 Combined Off Gas Post-Treatment Monitoring System, IAW station procedures.
Given plant conditions, perform Control Room actions to shutdown HPCS after an Auto 61.006 Initiation, IAW station procedures.
Given Unit Supervisor authorization, perform Control Room actions for main turbine generator 71.042 monthly surveillances, IAW station procedures.
Given plant conditions, perform Control Room actions for a Stuck Open Bypass Valve, IAW 73.013 station procedures.
Given entry in LGA-10, Failure to Scram, evaluate plant conditions and maintain a Heat Sink, 432.000 IAW station procedures.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 6 of 27
NRC 17-1-2 Revision 00 SRO - UNIT SUPERVISOR Given plant conditions, perform control room actions to respond to a failure of automatic RWLCS, 31.014 IAW station procedures.
Given plant conditions, perform the Main Control Room actions to startup and operate the 52.004 Combined Off Gas Post-Treatment Monitoring System, IAW station procedures.
Given plant conditions, perform Control Room actions to shutdown HPCS after an Auto Initiation, 61.006 IAW station procedures.
Given Unit Supervisor authorization, perform Control Room actions for main turbine generator 71.042 monthly surveillances, IAW station procedures.
Given plant conditions, perform Control Room actions for a Stuck Open Bypass Valve, IAW 73.013 station procedures.
Given plant conditions, perform Control Room actions to respond to a TDRFP low hydraulic 77.046 pressure alarm, IAW station procedures.
Given a set of plant conditions, identify and prepare the Technical Specification required actions 201.011 IAW Tech Specs.
Given entry in LGA-10, Failure to Scram, evaluate plant conditions and shutdown the reactor IAW 431.000 station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and insert control rods IAW 431.010 station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and perform SBLC injection, 431.020 IAW station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and maintain a Heat Sink, IAW 432.000 station procedures.
Given entry in LGA-10, Failure to Scram, evaluate plant conditions and maintain RPV water level 433.000 IAW LGA-010.
Given entry in LGA-10, Failure to Scram, evaluate plant conditions and control reactor power by 434.000 maintaining RPV water level IAW station procedures.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 7 of 27
NRC 17-1-2 Revision 00 Event - 1
==
Description:==
Bypass Valve Surveillance Initiation: Per Lead Evaluator, following the crew assuming the shift Cues:
Automatic Actions: #1 Bypass Valve Opens and Closes Expected Annunciators: LOR-1PM02J-B304, Turbine Bypass Valve (BPV) 1/2/3/4/5 Open Key Parameter Response: Reactor Pressure Fluctuates Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor Reactor Power, Level and Pressure ATC
- Provide peer checks as required Per LOS-TG-M4
- On the BV #1 screen, TEST Bypass Valve #1 as follows:
- PUSH the Test START pushbutton and OBSERVE:
- Bypass Valve #1 fully opens in approximately 10 seconds.
71.042 BOP
- Bypass Valve #1 exhibits Fast Open characteristics.
- Approximately 10 seconds after reaching full open, Bypass Valve #1 FULLY CLOSES.
- ALLOW the plant to stabilize for at least 2 minutes before testing the next bypass valve.
71.042 US
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 8 of 27
NRC 17-1-2 Revision 00 Event - 1
==
Description:==
Bypass Valve Surveillance Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note:
Terminus: Continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 9 of 27
NRC 17-1-2 Revision 00 Event - 2
==
Description:==
Bypass Valve Fails Open Initiation: Per Lead Evaluator Cues:
Automatic Actions: #2 Bypass Valve Opens Expected Annunciators: LOR-1PM02J-B304, Turbine Bypass Valve (BPV) 1/2/3/4/5 Open Key Parameter Response: Reactor Pressure Fluctuates Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOA-EH-101
- CHECK EHC is CONTROLLING reactor pressure.
- REFER TO LOA-PWR-101 while continuing.
- REDUCE Reactor power by lowering RR Flow until one of the following conditions exist:
- Core flow is 70 Mlbm/hr.
- Turbine Bypass Valves -CLOSED.
73.013 ATC
- As necessary, INSERT CRAMS or Control Rods in reverse sequence to ensure adequate margin to operational limits.
Per LOA-PWR-101
- CHECK RPS setpoints NOT exceeded.
- CHECK Reactor Power is < 100% RTP (3546 MWt) o REDUCE Power to < 100% RTP by using RR FCVs or Control Rods.
Per LOS-TG-M4
- On the BV #2 screen, TEST Bypass Valve #2 as follows:
- PUSH the Test START pushbutton and OBSERVE:
- Bypass Valve #2 fully opens in approximately 10 seconds.
- Bypass Valve #2 exhibits Fast Open characteristics.
- Approximately 10 seconds after reaching full open, Bypass Valve #1 FULLY 71.042 73.013 BOP CLOSES. (NO)
Per LOA-EH-101
- REFER TO LOA-HD-101 while continuing.
- CHECK Turbine Bypass Valve(s) - OPERABLE.
- CHECK Turbine Bypass Valve(s) - OPEN.
- CHECK both 1H13-P603- A211 and A212 - NOT LIT.
- Set Manual Scram Criteria EHC not controlling Reactor Pressure 71.042 73.013 US
- DECLARE Turbine Bypass Valve(s) - INOPERABLE.
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 10 of 27
NRC 17-1-2 Revision 00 Event - 2
==
Description:==
Bypass Valve Fails Open Simulator Operator Actions none Simulator Operator Role Play As the EO/Field Supervisor, when requested to close 1B21-MSBPV2 (B.4.12), inform the crew that the Field Supervisor and RP will brief for the evolution.
Respond as QNE/System Engineering.
Respond as required.
Floor Instructor Notes/OPEX/TRs Terminus: continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 11 of 27
NRC 17-1-2 Revision 00 Event - 3
==
Description:==
Bypass Valve INOP Initiation: Continued Cues: Event 2 Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor plant conditions and update the crew as required ATC
- Continue with actions of LOA-EH-101
- Monitor plant conditions and update the crew as required BOP
- Continue with actions of LOA-EH-101
- Notify QNE to make applicable LCO 3.2.2 limits for an inoperable Main Turbine Bypass System as specified in the COLR
- Enter TRM 3.6.a
- Enter TS 3.7.7 Required Action
- A.1 Satisfy the requirements of the LCO in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
- Refer to TS 3.3.1.1 and TS 3.3.4.1 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 12 of 27
NRC 17-1-2 Revision 00 Event - 3
==
Description:==
Bypass Valve INOP Simulator Operator Actions none Simulator Operator Role Play Respond as QNE.
Respond as required.
Floor Instructor Notes/OPEX/TRs Terminus: Following Tech Spec call and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 13 of 27
NRC 17-1-2 Revision 00 Event - 4
==
Description:==
Off Gas Post Treat B Fails Downscale Initiation: Per Lead Evaluator Cues:
Automatic Actions: none Expected Annunciators: 1N62-P600-B208, Off Gas Post-Treatment Radiation Trouble Key Parameter Response: B OG Post Treat Rad Monitor Downscale Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor Reactor Power, Level and Pressure and update the crew as required Per LOR-1N62-P600-B208
- IF R1200 is alarming, Then CHECK OG Post Treat PRM's, 1D18-K601A/B, for INOP/DWNSCL alarms and VERIFY proper operation per LOP-PR-03, Startup and Operation of Combined Off Gas Post-treatment Monitoring System.
- NOTIFY Unit Supervisor
- NOTIFY Rad Protection Department to check 0PL99J (OG BLDG 690') for proper
- operation and to RESET any alarms.
52.004 BOP
- VERIFY fuse F1 GOOD, located in 0PL99J Junction box at TB1. (ref. dwg 1E 4565AA)
- IF required to place the channel in trip to comply with ODCM Required Actions:
PLACE the 1A(B) Off Gas Post Treatment Radiation Monitor mode switch in standby.
- Direct above actions 52.004 US
- Enter ODCM12.2.2
- Required action C.1 Place Instrument Channel in Trip in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 14 of 27
NRC 17-1-2 Revision 00 Event - 4
==
Description:==
Off Gas Post Treat B Fails Downscale Simulator Operator Actions When directed by the Lead Release Event 4 Evaluator Simulator Operator Role Play Respond as RP, when asked to check for proper operation of 0PL99J, wait 1 minute and report that it is operating normally and alarms are reset Respond as an EO, when order to check the status of 1AP66E-C5 (134Y-1 C5) and 1AP66E-D1 breaker 6 (134Y-1 D1 Breaker 6), wait 1 minute and report that they are closed.
Respond as an EO, when order to check the status of 0PL99J F1 fuse, wait 1 minute and report that the fuse is not blown.
Respond as required.
Floor Instructor Notes/OPEX/TRs Terminus: When the B OG Post Treat Rad Monitor is bypassed and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 15 of 27
NRC 17-1-2 Revision 00 Event - 5
==
Description:==
Spurious HPCS Initiation Initiation: Per Lead Evaluator Cues:
Automatic Actions: HPCS Pump Starts Expected Annunciators: 1H13-P601-A208, Reactor Vessel Water Level 2 Lo-Lo; 1H13-P601-A308, Reactor Vessel Water Level 2 Lo-Lo Key Parameter Response: HPCS Injection Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOR-1H13-P601-A208/A308
- CHECK Reactor Vessel Water Level indication on panels 1H13-P601 and 1H13-P603.
- If Reactor Vessel Water Level is actually low, REFER to LGA-001, RPV Control and LGA-003, Primary Containment Control. (NO) 61.006 ATC Per LOA-PWR-101
- STOP any power increase.
- STABILIZE the Unit.
o RUN OD-20.
Per LOR-1H13-P601-A208/A308 o If Shutdown of HPCS after Auto Initiation is required, REFER to LOP-HP-04 61.006 BOP Per LOA-PWR-101
o VERIFY lineup of HPCS with LOP-HP-04, Shutdown of HPCS After an Automatic Initiation.
61.006 US
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 16 of 27
NRC 17-1-2 Revision 00 Event - 5
==
Description:==
Spurious HPCS Initiation Simulator Operator Actions When directed by the Lead Release Event 5 Evaluator Simulator Operator Role Play Respond as IMD Respond as required Floor Instructor Notes/OPEX/TRs Note: HPCS will be INOP but available.
Terminus: continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 17 of 27
NRC 17-1-2 Revision 00 Event - 6
==
Description:==
HPCS INOP Initiation: Per Lead Evaluator, following the crew assuming the shift Cues:
Automatic Actions: HPCS Pump Starts Expected Annunciators: 1H13-P601-A208, Reactor Vessel Water Level 2 Lo-Lo; 1H13-P601-A308, Reactor Vessel Water Level 2 Lo-Lo Key Parameter Response: HPCS Injection Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor plant conditions and update the crew as required BOP
- Monitor plant conditions and update the crew as required o Enter TS 3.3.5.1 o Required Action B.2 Declare HPCS inoperable 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of HPCS Initation Capabilty o Required Action B.3 Place channel in trip in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- Enter TS 3.5.1
- Required Action B.1 Verify by adminastrative means RCIC System is OPERABLE when RCIC is required to be operable immediately
- Required Action B.2 Restore HPCS to OPERABLE status in 14 days 201.011 US o Enter TS 3.8.1 (Note in 3.8.1 states not required with HPCS INOP) o Required Action C.1 Perform SR 3.8.1.1 for OPERABLE required offsite circuits in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter o Required Action C.2 Declare required feature(s), supported by the inoperable DG, inoperable when the redundant required feature(s) are inoperable 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery o Required Action C.3.1 Determine OPERABLE DG(s) are not inoperable due to common cause failure in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OR o Required Action C.3.2 Perform SR 3.8.1.2 for OPERABLE DG(s) in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> o Required Action C.4 Restore required DG(s) to OPERABLE status SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 18 of 27
NRC 17-1-2 Revision 00 Event - 6
==
Description:==
HPCS INOP Simulator Operator Actions none Simulator Operator Role Play Respond as IMD Respond as required Floor Instructor Notes/OPEX/TRs Note: The crew may fail conservative an call the lo-lo level instrumentation INOP which would cause entry into TS 3.3.5.1 Terminus: Following Tech Spec call and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 19 of 27
NRC 17-1-2 Revision 00 Event - 7
==
Description:==
TDRFP Oil Leak, Manual Trip Initiation: Per Lead Evaluator Cues:
Automatic Actions: none Expected Annunciators: 1PM03J-A104, Turbine Driven Reactor Feedwater Pump Bearing Oil Pressure Low Key Parameter Response: Lowering B TDRFP Oil Pressure Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOR-1PM03J-A104
- DETERMINE which Turbine Driven Reactor Feedwater Pump (TDRFP) has Low Bearing Oil Pressure.
- If entire Turbine Oil System is failing, immediately REDUCE power per LGP-3-1 and/or LGP-2-1 to within capacity of MDRFP. ENTER LOA-TO-101. (NO) o PLACE an idle Reactor Feedwater Pump in service per procedure LOP-FW-03, Startup of Motor Driven Reactor Feed Pumps (MDRFP), or LOP-FW-04, Startup of a Turbine Driven Reactor Feed Pump (TDRFP).
77.046 ATC o SHUTDOWN affected TDRFP per procedure LOP-FW-05, Shutdown of Turbine Driven Reactor Feed Pump.
- DISPATCH operator to INSPECT Turbine Bearing Oil System for abnormalities and DETERMINE cause for Low Bearing Oil Pressure Alarm Per OP-LA-101-111-1002
- Trip 1B TDRFP
- Verfiy MDRFP Auto starts
- Monitor Reactor Level BOP
- Monitor plant parameters and update the crew as required
- Direct above actions 77.046 US
- Set Manual Scram Criteria of Reactor Level outside of 20-50 and/or not in control SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 20 of 27
NRC 17-1-2 Revision 00 Event - 7
==
Description:==
TDRFP Oil Leak, Manual Trip Simulator Operator Actions When directed by the Lead Release Event 7 Evaluator When directed by the crew Release Isolate 1B TDRFP Oil Simulator Operator Role Play When an EO is dispatched to investigate the B TDRFP, wait 1 minute and report that there an oil leak from one of the bearings on the1B TDRFP and that you cant get close enough to see if you can isolate it or locally trip it.
As an EO, when requested to perform post start checks of the MDRFP, wait 1 minute and report post start checks are SAT.
AFTER the TDRFP is tripped if the crew orders the EO to isolate the oil side of 1B TDRFP by closing 1TO061-HP/LP release the above action and after 1 minute inform the crew that oil to 1B TDRFP is isolated.(M-84 Sh. 4)
Respond as required Floor Instructor Notes/OPEX/TRs Note: The Oil pressure will decrease gradually until it reaches 5.5 psig which is at the alarm set point and above the automatic trip set point of 4 psig.
Terminus: When 1B TDRFP is tripped and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 21 of 27
NRC 17-1-2 Revision 00 Event - 8
==
Description:==
Single MSIV Closure Initiation: Per Lead Evaluator Cues:
Automatic Actions: None Expected Annunciators: 1H13-P603-B202, Main Steam Isolation Valves C and D Not Full Open Key Parameter Response: 1D Outboard MSIV Closes, RPV Level Rises in 3 Element Control Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOR-1H13-P603-B202
- If any steam line is affected, PLACE RWLC in SINGLE Element control.
- At 1H13-P601 panel, INSPECT limit switch indications for 1B21-F022C/D and 1B21-F028C/D:
- If MSIV C Inboard and/or Outboard shows dual indication, TURN handswitch to full OPEN position.
- If MSIV D Inboard and/or Outboard shows dual indication, TURN handswitch to full OPEN position.
- If applicable, STOP all surveillance testing related with Main Steam System.
- ENTER LOA-MS-101 for MSIV closure.
- If RPS Subchannel A2 tripped (NO)
Per LOA-MS-101 31.014 ATC
- CHECK all MSIVs - OPEN (NO)
- If a single MSIV is closed enter LOA-FW-101 to transfer RWLC to Single Element.
- Using Reactor Recirc Flow, LOWER core flow to 70 Mlbm/hr OR 75% Reactor Power
- CONTACT QNE for further direction or guidance to reduce power further by control rod insertion if power is still greater than 75%.
- CONTACT QNE to determine if current degraded condition is covered by the active CMSS Thermal Limit Set.
Per LOA-FW-101
- CHECK RPV level is 20 to 50 and/or IN CONTROL.
- CHECK single MSIV NOT closed, or failure of automatic RWLC not caused by failure of steam flow instruments. (NO)
- SELECT Single Element at the RWLC Level Setpoint Station BOP
- Monitor plant parameters and update the crew as required
- Direct above actions 31.014 US
- Set Manual Scram Criteria of Reactor Level outside of 20-50 and/or not in control SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 22 of 27
NRC 17-1-2 Revision 00 Event - 8
==
Description:==
Single MSIV Closure Simulator Operator Actions When directed by the Lead Release Event 8 Evaluator Simulator Operator Role Play Respond as QNE, inform the crew that you will report to the Control Room If sent to Inspect the MSIV, as an EO/Field Sup inform the crew that we will make preps to inspect the MSIV locally.
Respond as required.
Floor Instructor Notes/OPEX/TRs Note: While in 3 Element Control RWLC will continue itinerary Terminus: When RWLCS is in Single Element Control and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 23 of 27
NRC 17-1-2 Revision 00 Event - 9
==
Description:==
Multiple Rods Scram Full-In, Hydraulic ATWS Initiation: Per Lead Evaluator Cues: Key Parameter Response: Multiple Rods Scram Full-In Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Performs Reactor Scram and LGP 3-2 on US direction.
- PLACE Reactor Mode Switch in SHUTDOWN
- CHECK Control Rods INSERTED and Power Decreasing
- INFORM Unit Supervisor of Control Rod Status and Reactor Power
- Recognize that all rods did not insert and notify US (Hydraulic ATWS)
Per the POWER Leg of LGA-010
- If control rods remain out:
431.000
- Initiate ARI 431.010
- Insert Control rods per LGA-NB-01 (CT) 434.000
- Method 3 Single Rod Insert
- Bypass RWM
- Place CRD Drive Flow Trip Circuit in BYPASS
- Insert control rods using Continuous Insert or Insert Button Per the Level Leg of LGA-010
- If reactor power > 3% or unknown then Rapidly LOWER Level to at least -60 inches (minimizes Feedwater injection) (CT) and use only preferred systems to hold level between -100 and -60 inches. (CT)
- RUNBACK Reactor Recirculation flow to minimum
- If power is >3% then TRIP RR Pumps
- Method 4 Reset Scram/Drain SDV/Re-Scram
- Reset Scram/Drain SDV/Re-Scram Per LGA-010
- Inhibit ADS
- STABILIZE pressure <1059 psig using main turbine bypass valves
- VERIFY required automatic actions occur
- May request LGA-RH-101 jumper installation
- Directs Inhibit ADS
- Directs controlling level -100 to -60.(CT) 433.000
- Directs start of SBLC and/or insert control rods.(CT) (PRA) 434.000 US 431.020
- Directs method of control rod insertion per LGA-NB-01(CT) 431.010
- May direct Method 3 Single Rod Insert
- May direct Method 4 Reset Scram/Drain SDV/Re-Scram
- Directs bypassing MSIV low level isolation per LGA-MS-01 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 24 of 27
NRC 17-1-2 Revision 00
==
Description:==
ATWS, After Control rods inserted Task/
Position Obj. EXPECTED OPERATOR RESPONSE
- When directed, stops SBLC pump 304.010 433.000 ATC
- VERIFY Main Turbine and Generator Trip
- STABILIZE Reactor Pressure <1020 psig BOP
- Monitors control room panels and notifies the SRO of any unusual or unexpected conditions
- When rods inserted, direct securing SBLC injection 433.000 US
- When rods inserted, exits LGA-010 and enters LGA-001
- Directs water level band of +11" to +59.5" (+20" to +50" preferred)
Event - 9
==
Description:==
Multiple Rods Scram Full-In, Hydraulic ATWS Simulator Operator Actions When directed by the Lead Release Event 9 Evaluator When directed by the Crew Release LGA-MS-101 When directed by the Crew Release LGA-NB-01 When directed by the Crew Release LGA-RH-101 Simulator Operator Role Play Role Play Unit 2 NSOs as necessary to complete LGA-NB-01, LGA-MS-101, and LGA-RH-101 ATWS Actions Respond as required Floor Instructor Notes/OPEX/TRs Terminus: All rods fully inserted with RPV level stable and under control in required band and upon approval of Lead Examiner.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 25 of 27
NRC 17-1-2 Revision 00 REFERENCES Procedure Rev Title
- 1. INPO 15-004 Operations Fundamentals
- 2. SOER 10-2 Engaged, Thinking Organizations
- 3. LOS-TG-M4 9 TURBINE BYPASS VALVE SURVEILLANCE
- 4. LOA-EH-101 35 UNIT 1 EHC ABNORMAL
- 5. LOA-PWR-101 14 UNIT 1 UNPLANNED REACTIVITY ADDITION
- 6. LOR-1PM02J-B304 5 Turbine Bypass Valve (BPV) 1/2/3/4/5 Open
- 7. LOR-1N62-P600-B208 5 Off Gas Post-Treatment Radiation Trouble
- 8. LOR-1H13-P601-A208 3 Reactor Vessel Water Level 2 Lo-Lo
- 9. LOR-1H13-P601-A308 3 Reactor Vessel Water Level 2 Lo-Lo
- 10. LOR-1PM03J-A104 1 Turbine Driven Reactor Feedwater Pump Bearing Oil Pressure Low
- 11. LOR-1H13-P603-B202 3 Main Steam Isolation Valves C and D Not Full Open
- 12. LOA-MS-101 13 UNIT 1 MAIN STEAM SYSTEM ABNORMAL
- 13. LOA-FW-101 11 REACTOR LEVEL/FEEDWATER PUMP CONTROL TROUBLE
- 14. LGA-001 18 RPV Control
- 15. LGA-010 18 Failure to Scram
- 16. LGA-MS-101 2 Using Main Condenser as Heat Sink in ATWS
- 17. LGA-RH-101 4 Alternate Vessel Injection Using Shutdown Cooling Return
- 18. LGA-NB-01 19 Alternate Rod Insertion
- 19. OP-LA-101-111-1002 73 LaSalle Operations Philosophy Handbook.
- 20. OP-LA-103-102-1002 17 Strategies for Successful Transient Mitigation
- 21. OP-AA-106-101 21 Significant Event Reporting
- 22. OP-LA-STA-1001 5 LaSalle Shift Technical Advisor (STA) Checklists
- 23. EP-AA-1005 Add. 3 3 Emergency Action Levels for LaSalle Station
- 24. EP-MW-114-100-F-01 J Nuclear Accident Reporting System(NARS) Form SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 26 of 27
NRC 17-1-2 Revision 00 U1 SUPERVISOR TURNOVER Shift: Days Date: Today Mode: 1 OLR: Green Work Week: Non-Div Unit 1 power level Unit 2 power level
- 100 % Power
- 100 % Power U1 Thermal Limit Issues /Power Evolutions U2 Thermal Limit Issues /Power Evolutions
- None
- None Existing LCOs, date of next surveillance Existing LCOs, date of next surveillance
- None
- None LOSs in progress or major maintenance LOSs in progress or major maintenance
- LOS-TG-M4
- None Equipment removed from service or currently unavailable
- None
- None Grid Status is Green Comments, evolutions, problems, etc. Comments, evolutions, problems, etc.
- Perform LOS-TG-M4 on all Bypass Valves
- Non-Div Workweek. OLR is Green
- Generation Dispatch has been Notified and a Gen Manager Ticket has been activated SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 27 of 27
LaSalle County Station LICENSED OPERATOR EVALUATED SCENARIO GUIDE NRC 17-1-3 Rev. 00 6/14/2018 DEVELOPED BY:
Exam Author Date TECHNICAL REVIEW: Polega / Pratt / Quinn / Vanderhyden 7/10/18 SME/Tech Reviewer Date REVIEWED BY:
Training Department Date APPROVED BY:
Operations Representative Date
NRC 17-1-3 Revision 00 Facility: LaSalle County Generating Station Scenario #: NRC 17-1-3 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.
SUMMARY
OF EVENTS
- 2. Raise Reactor Power IAW LGP-1-1. The crew will raise power using RR FCVs at a rate of 300 MWe/hr and above 61 Mlbm/hr.
- 3. B; FCV Fails Closed. After the crew raises Reactor Power using FCVs the B FCV will Fail closed causing a flow mismatch.
- 4. Flow Mismatch. The Unit Supervisor will make a Tech Spec call for the Flow Mismatch.
- 5. 1A VR Exhaust Fan Trip. The crew will take action to start the 1C VR Exhaust fan and verify all parameters are normal.
- 6. 1A GC Pump Trip, Standby Fails to Auto start. The crew will take action to start the standby GC Pump and verify that a Generator Runback ha not occurred.
- 7. SBLC Tank Low Level. The crew will receive an annunciator to indicate that the SBLC Tank level is low, upon investigation it is found to be a leaking valve and the Unit Supervisor will make a Tech Spec Call for SBLC.
- 8. FRV Fails Open. With the MDRFP online the FRV will fail open and the crew will take action per LOA-FW-101 to control level with 1FW003, MDRFP Discharge Stop Valve.
- 9. An EHC Leak will cause the crew to the crew to scram. The crew will scram and follow-up by either taking EHC Pumps to PTL or allowing the Turbine to trip on low EHC pressure.
- 11. Main Steam Line Break Inside Containment. Following all rods inserting by ARI a leak on the Main Steam Line will develop inside Containment.
Critical Tasks
- 1) With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by inserting control rods, to protect the primary containment.
- 2) With suppression chamber pressure above 12 psig, containment flood level below 722 feet, and drywell parameters below the Drywell Spray Initiation Limit; trip all recirculation pumps and start drywell sprays using RHR pumps not needed for adequate core cooling.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 2 of 31
NRC 17-1-3 Revision 00 TRAINING REQUESTS (if applicable)
- 1. None OPEX (if applicable)
- 1. None Operator Fundamentals
- 1. Monitoring plant indications and conditions closely
- 2. Controlling plant evolutions precisely
- 3. Operating the plant with a conservative bias
- 4. Working effectively as a team
- 5. Having a solid understanding of plant design, engineering principles, and sciences SOER 10-2
- 1. Supervisory oversight role
- 2. Recognition and mitigation of risk
- 3. Worker performance
- 4. Tolerance of repetitive/long standing issues and degradation of standards
- 5. Operating Experience Record of Revisions (Summary)
Rev. 0 Developed new for the ILT 17-1 NRC Exam SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 3 of 31
NRC 17-1-3 Revision 00 INITIAL SIMULATOR SETUP/ REQUIRED DOCUMENTATION
- 1. Recall IC 354 Password 0354
- 2. Place simulator in RUN
- 3. Load and run the SmartScenario file 17-1-3.ssf
- 4. Update the Tech Spec Timeclock Sheet as follows:
TS/TRM/ODCM System/ Required REQUIRED ACTION Completion Expiration Component Action Description Time Date/Time N/A N/A N/A N/A N/A N/A
- 5. Perform the pre-scenario checklist (TQ-LA-150-0308)
SCENARIO OUTLINE (NRC Evaluations Only)
Event Malf. Event Event No. No. Type* Description none N (BOP) 1 Reactor Recirc Upshift none R (ATC) 2 Raise Reactor Power using RR FCVs k2l12p1l C (ATC) 3 B FCV fails Closed none T (US) 4 Flow Mismatch k7d18wpg C (BOP) 5 1A VR Exhaust Fan Trip mgc001 C (BOP) 6 mgc004 1A GC Trip, Standby Fails to Auto Start r0744 T (US) 7 SBLC Tank Level Low mcf086 C (ATC) 8 FRV Fails Open mms007 M 9 EHC Leak, Scram mrp017 M 10 Electrical ATWS, ARI inserts rods mcf034 M 11 Main Steam Line Break Inside Containment
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specification APPROXIMATE SCENARIO RUN TIME 60 Minutes SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 4 of 31
NRC 17-1-3 Revision 00 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE)
During performance of tasks, dynamic learning activities, or formal evaluations, 769.00.01 demonstrate applicable Human Performance behaviors IAW the appropriate procedures.
Given an operating experience document, paraphrase the lessons learned and 762.04.00 methods to prevent recurrence at LaSalle Station, as described in the training material.
During performance of tasks, apply the administrative requirements of PROCEDURE 614.010 USE AND ADHERENCE EXPECTATIONS, IAW station procedures.
TASKS RO - ATC 22.008 Given initial plant conditions, Respond to Reactor Recirc Pump Trouble, IAW station procedures.
Given initial plant conditions, Perform the Control Room actions to respond to a loss of one or 22.015 both RR pumps, IAW station procedures.
Given initial plant conditions, Respond to a Reactor Recirc Flow Control System failure to 23.003 minimum demand, IAW station procedures.
Given initial plant conditions, Respond to a Reactor Recirc Flow Control Valve lockup, IAW station 23.004 procedures.
Given plant conditions, perform the in plant actions to respond to SBLC tank LVL Hi/Lo, IAW 28.018 station procedures.
Given plant conditions, complete Control Room actions to respond to a failure of the MDRFP 78.010 FRV/Low Flow FRV, IAW station procedures.
304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 413.000 59.5 IAW LGA-001 Given entry in LGA-10, Failure to Scram, evaluate plant conditions and shutdown the reactor IAW 431.000 station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and insert control rods IAW 431.010 station procedures SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 5 of 31
NRC 17-1-3 Revision 00 RO - BOP/ASSIST Given plant conditions, perform the Main Control Room actions for a loss of Generator Stator 9.001 Water Cooling, IAW station procedures.
Given Unit Supervisor authorization, Transfer Reactor Recirc Pumps from slow to fast speed, 22.002 IAW station procedures Given plant conditions, perform the in plant actions for a hi/lo level in the EHC reservoir, IAW 73.019 station procedures.
Given plant conditions, adjust reactor building to outside differential pressure, IAW station 118.008 procedures.
Given LGA-003 in progress, Evaluate plant conditions and control and maintain Primary 419.000 Containment Pressure to less than 1.93 psig, IAW LGA-003.
419.020 Given LGA-003 in progress, spray the Suppression Pool, IAW LGA-003.
419.030 Given LGA-003 in progress, spray the Drywell, IAW LGA-003.
Given LGA-003 in progress, vent the Drywell and/or Suppression Chamber to stay below 60 419.040 psig, IAW LGA-004.
Given LGA-003 in progress, evaluate plant conditions and control and maintain suppression 421.000 pool temperature less than HCTL, IAW LGA-003.
421.010 Given LGA-003 in progress, cool the Suppression Pool, IAW LGA-003.
Given entry in LGA-10, Failure to Scram, evaluate plant conditions and maintain a Heat Sink, 432.000 IAW station procedures.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 6 of 31
NRC 17-1-3 Revision 00 SRO - UNIT SUPERVISOR Given plant conditions, perform the Main Control Room actions for a loss of Generator Stator 9.001 Water Cooling, IAW station procedures.
Given Unit Supervisor authorization, Transfer Reactor Recirc Pumps from slow to fast speed, 22.002 IAW station procedures 22.008 Given initial plant conditions, Respond to Reactor Recirc Pump Trouble, IAW station procedures.
Given initial plant conditions, Perform the Control Room actions to respond to a loss of one or 22.015 both RR pumps, IAW station procedures.
Given initial plant conditions, Respond to a Reactor Recirc Flow Control System failure to 23.003 minimum demand, IAW station procedures.
Given initial plant conditions, Respond to a Reactor Recirc Flow Control Valve lockup, IAW station 23.004 procedures.
Given plant conditions, perform the in plant actions to respond to SBLC tank LVL Hi/Lo, IAW 28.018 station procedures.
Given plant conditions, perform the in plant actions for a hi/lo level in the EHC reservoir, IAW 73.019 station procedures.
Given plant conditions, complete Control Room actions to respond to a failure of the MDRFP 78.010 FRV/Low Flow FRV, IAW station procedures.
Given plant conditions, adjust reactor building to outside differential pressure, IAW station 118.008 procedures.
Given a set of plant conditions, identify and prepare the Technical Specification required actions 201.011 IAW Tech Specs.
Given LGA-003 in progress, Evaluate plant conditions and control and maintain Primary 419.000 Containment Pressure to less than 1.93 psig, IAW LGA-003.
419.020 Given LGA-003 in progress, spray the Suppression Pool, IAW LGA-003.
419.030 Given LGA-003 in progress, spray the Drywell, IAW LGA-003.
Given LGA-003 in progress, vent the Drywell and/or Suppression Chamber to stay below 60 psig, 419.040 IAW LGA-004.
Given LGA-003 in progress, evaluate plant conditions and control and maintain suppression pool 421.000 temperature less than HCTL, IAW LGA-003.
421.010 Given LGA-003 in progress, cool the Suppression Pool, IAW LGA-003.
Given entry in LGA-10, Failure to Scram, evaluate plant conditions and shutdown the reactor IAW 431.000 station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and insert control rods IAW 431.010 station procedures SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 7 of 31
NRC 17-1-3 Revision 00 Event - 1
==
Description:==
Reactor Recirc Upshift Initiation: Per Lead Evaluator, following the crew assuming the shift Cues: Turnover Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor Reactor Power, Level and Pressure ATC
- Provide peer checks as requird Per LGP-1-1
- TRANSFER Recirculation Pumps to fast speed per LOP-RR-05, Changing Reactor Recirc Pump Speed From Slow to Fast Speed.
Per LOP-RR-05
- UNLOCK the desired RR Flow Control Valve as Follows:
- At Control Room Panel 1(2)H13-P602 VERIFY Individual Loop M/A Transfer Station 1B33-R611A/B is set as follows:
- MANUAL light ON.
- Servo Error at zero.
- DEPRESS valve INHIBIT RESET push-button for Loop B and CHECK MOTION INHIBIT light goes off.
- DEPRESS Lower pushbutton on Reactor Recirc Loop B M/A Station for loop in which pump speed will be changed until BOTH of the following conditions are met:
22.002 BOP
- 1B33-F060B, HI Speed Start Permissive indicating light 1B33-DS02B is ON
- Flow Control Valve minimum position is < 20% indicated.
- PLACE second pump's Breaker 3B Control Switch to START position and RELEASE.
- OBSERVE the following:
- 1B breaker (LFMG Drive Motor) opens.
- 2B breaker (LFMG Generator) opens.
- 3B breaker (RR Motor Bkr) closes after pump speed decreases to 350 rpm.
- Pump speed increases to approximately 1750 rpm.
- Reactor level drops, then returns to level controller setpoint.
- Reactor power initially increases, then stabilizes.
- Loop A flow is approximately the same as Loop B flow.
- At the 1DS001 Operator Station RRFC Interlocks screen, PLACE both A and B RR Interlocks in NORMAL 22.002 US
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 8 of 31
NRC 17-1-3 Revision 00 Event - 1
==
Description:==
Reactor Recirc Upshift Simulator Operator Actions none Simulator Operator Role Play Acknowledge reports as required Floor Instructor Notes/OPEX/TRs Note: The crew should raise power from step E.2.6 of LOP-RR-05 which sends them back to LGP-1-1.
The crew may receive the SAT Under-voltage annunciator, this is expected during an upshift due to the load transient.
LPRM Downscales may come in and clear, this expected during the start-up due to the rod configuration.
Terminus: continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 9 of 31
NRC 17-1-3 Revision 00 Event - 2
==
Description:==
Raise Reactor Power using RR FCVs Initiation: Per Lead Evaluator Cues: Turnover Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOP-RR-07
- VERIFY AUTO light on A AND B Recirculation Loop Flow Controller M/A Station is ON.
- DEPRESS the Ganged Flow Setpoint Station RAISE/LOWER pushbutton(s) as required.
- If FCV Position is 60%, then START RECORDING RR Pump Seal Pressures and Temperatures per Attachment C.
Per LOP-RR-07 BOP
- Monitor FCV Position demand signals to allow for immediate recognition and communication of an abnormal response US
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 10 of 31
NRC 17-1-3 Revision 00 Event - 2
==
Description:==
Raise Reactor Power using RR FCVs Simulator Operator Actions none Simulator Operator Role Play Acknowledge reports as required.
Floor Instructor Notes/OPEX/TRs Terminus: When sufficient power has been raised per the Lead evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 11 of 31
NRC 17-1-3 Revision 00 Event - 3
==
Description:==
B FCV fails Closed Initiation: Per Lead Evaluator Cues:
Automatic Actions: B FCV Closing Expected Annunciators: None Key Parameter Response: Lowering MWe and lowering Core Flow Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOA-RR-101
- CHECK FCV position -STABLE.
- Lock up FCV.
22.008
- If OPRM inop and in or near Regions 1 or 2, PERFORM Subsection B.1, Thermal 22.015 23.003 ATC Hydraulic Instability, while continuing below.
23.004
- CHECK recirculation loop jet pump flows - LESS THAN TECH SPEC MISMATCH.
- At 1DS001, initiate TADS by DEPRESSING TDR icon.
o Perform section B.7 to unlock the FCV o Perform section B.10 to match loop flows BOP
- Monitor plant conditions and update the crew as required.
22.008 22.015 23.003 US
- Direct above actions 23.004 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 12 of 31
NRC 17-1-3 Revision 00 Event - 3
==
Description:==
B FCV fails Closed Simulator Operator Actions When directed by the Lead Release Event 3 Evaluator Simulator Operator Role Play As an EO, when sent to investigate the 1B RR HPU, wait 2 minutes and report that you see no reason for FCV malfunction.
Acknowledge reports as required.
Floor Instructor Notes/OPEX/TRs Terminus: continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 13 of 31
NRC 17-1-3 Revision 00 Event - 4
==
Description:==
Flow Mismatch Initiation: Event 3 Cues: Event 3 Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Continue with actions of Event 3 BOP
- Continue with actions of Event 3
- Enter Tech Spec 3.4.1
- Required Action B.1 Declare the recirculation loop with lower flow to be not in 201.011 US operation
- Supervise above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 14 of 31
NRC 17-1-3 Revision 00 Event - 4
==
Description:==
Flow Mismatch Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note:
TECH SPEC MISMATCH:
- Within 5.425 Mlb/hr as read from 1B21-R611A/B, if core flow is greater than or equal to 75.95 Mlbm/hr.
- Within 10.85 Mlb/hr as read from 1B21-R611A/B, if core flow is less than 75.95 Mlbm/hr.
Terminus: Following Tech Spec call and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 15 of 31
NRC 17-1-3 Revision 00 Event - 5
==
Description:==
1A VR Exhaust Fan Trip Initiation: Per Lead Evaluator Cues:
Automatic Actions: 1A VR Exhaust Fan Trip Expected Annunciators: 1PM06J-A305, Reactor Building Ventilation Exhaust Fan 1VR02CA Auto Trip Key Parameter Response: Rising Reactor Building Differential Pressure Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor plant parameters and update the crew as required.
Per LOR-1PM06J-A305
- Suspend IMFs and OPDRVs
- If at least oe exhaust fan is running, then IMMEDIATELY START standby VR fan 118.008 BOP 1VR02CC
- MONITOR temperature as needed
- Dispatch an operator to SWGR 131X, Comp 403C
- Direct above actions 118.008 US
- Monitor for LGA-002 entry conditions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 16 of 31
NRC 17-1-3 Revision 00 Event - 5
==
Description:==
1A VR Exhaust Fan Trip Simulator Operator Actions When directed by the Lead Release Event 5 Evaluator Simulator Operator Role Play When sent to investigate the fan breaker, as an EO, wait 2 minutes and report that the breaker tripped on overcurrent.
Respond as required.
Floor Instructor Notes/OPEX/TRs Terminus: when the standby VR exhaust fan has been started and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 17 of 31
NRC 17-1-3 Revision 00 Event - 6
==
Description:==
1A GC Pump Trip, Standby Fails to Auto start Initiation: Per Lead Evaluator, following the crew assuming the shift Cues:
Automatic Actions: 1A GC Pump Trip Expected Annunciators: 1PM02J-B310, Generator Stator Coolant Runback Circuit Energized Key Parameter Response: Lowering GC Pump Amps Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor plant parameters and update the crew as required Per LOA-GC-101
- CHECK a Generator Stator Cooling Pump 1GC02P/3P is running.
9.001 BOP
- START a Generator Stator Cooling Pump 1GC03P.
- Continuously CHECK Generator Runback NOT initiated
- DETERMINE cause of Stator Cooling degradation/ loss and RESTORE Cooling.
- Set manual scram criteria of GC runback initated 9.001 US
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 18 of 31
NRC 17-1-3 Revision 00 Event - 6
==
Description:==
1A GC Pump Trip, Standby Fails to Auto start Simulator Operator Actions When directed by the Lead Release Event 6 Evaluator Simulator Operator Role Play As the EO in the field, when sent to investigate the tripped Pump and Breaker, wait 2 minutes and report that the breaker tripped on overcurrent and there is an acrid odor.
As EO, when asked, report that post start checks of the 1B GC Pump are sat.
Respond as required.
Floor Instructor Notes/OPEX/TRs Note: The Runback Circuit energized annunciator does not mean that a generator runback is occurring. There is a 15 second time delay from the annunciator coming in and the generator runback to initiate. If the condition which caused the runback circuit to energize clears within the 15 second time delay, a generator runback will not occur.
Terminus: When the standby GC Pump is running and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 19 of 31
NRC 17-1-3 Revision 00 Event - 7
==
Description:==
SBLC Tank Low Level Initiation: Per Lead Evaluator Cues:
Automatic Actions: none Expected Annunciators: 1H13-P603-A205, Standby Liquid Control Tank 1C41-A001 Level High/Low Key Parameter Response: none Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOR-1H13-P603-A205
- CHECK Standby Liquid Control Tank Level is at one of alarm setpoints.
- T-Square method (preferred)
- DISPATCH operator to Standby Liquid Control Tank area to VERIFY proper air flow thru Standby Liquid Control Tank Instrument Air Pressure Indicating Controller 1C41-R004.
- START Special Log to monitor SBLC Tank level locally until level restored to normal 28.018 ATC band.
- Low Level: Consult Chemistry Lead for recommendations on restoring from low level. Available options are to add water/sodium pentaborate or simply water to the tank. The Chemistry Lead trends solution tank level/concentration and can assist in raising level and maintain optimum point on the Technical Specification concentration vs. volume graph. Level may be raised per LOP-SC-04, "SBLC Solution Tank Filling."
- Monitor plant conditions and update the crew as required
- Direct above actions
- Enter Tech Spec 3.1.7 28.018 US
- Required Action B.1 Restore one SLC subsystem to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 20 of 31
NRC 17-1-3 Revision 00 Event - 7
==
Description:==
SBLC Tank Low Level Simulator Operator Actions When directed by the Lead Release Event 7 Evaluator When directed by the crew to refill the SBLC Tank (After Release SBLC Low Level Clear TS Call)
Simulator Operator Role Play As an EO, when asked to investigate the low level alarm, wait 1 minute and report, There was a leak below the level glass and it stopped when I took the root valve (1C41-F310) to the closed direction, there was a quarter turn of movement. The leak has stopped and all water in is contained in the skid. No drums are overflowing. (M-99)
As the EO in the field, when ordered to check SBLC Tank level, wait 2 minutes and report that Tank Level is 4700 gallons via T-Square method and 1C41-R004 flow is normal.
As Chemistry when asked, report that the last logged Concentration of the Unit 1 SBLC tank, report that it was 13%.
As the Chemistry Lead, when asked, inform the crew that you recommend refilling the SBLC Tank with water to 5000 Gallons with water only.
When ordered to refill tank follow the above actions to clear the alarm and wait 1 minute report that level is 5000 gallons.
Respond as required.
Floor Instructor Notes/OPEX/TRs Note: If the tank is not refilled it will not affect the Event 10 because ARI will work.
Terminus: Following the Tech Spec call and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 21 of 31
NRC 17-1-3 Revision 00 Event - 8
==
Description:==
FRV Fails Open Initiation: Per Lead Evaluator Cues:
Automatic Actions: none Expected Annunciators: 1H13-P603-A511, RWLCS Trouble Key Parameter Response: Reactor Level Fluctuates and MDRFP Flow will go up Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOR-1H13-P603-A511
- At the 1DS001 Operation Station Event List, Check alarm message. (FRV Pos Err)
- REFER to LOP-FW-16 to determine cause of alarm and required actions.
Per LOP-FW-16
- VERIFY proper operation of the FRV
- ENTER LOA-FW-101 78.010 ATC Per LOA-FW-101
- CHECK RPV level is 20 to 50 and/or IN CONTROL.
- CHECK FRV lockout - RESET.
- CHECK FRV operating - NORMALLY
- If desired, attempt to establish flow with the LFFRV.
- Monitor plant conditions and provide peer checks as required
- Set manual scram criteria outside of 20-50 and/or not in control 78.010 US
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 22 of 31
NRC 17-1-3 Revision 00 Event - 8
==
Description:==
FRV Fails Open Simulator Operator Actions When directed by the Lead Release Event 8A Evaluator When directed by the Lead Evaluator if required to force action to take manual control Release Event 8B of feed flow following the review of LOA-FW-101 Simulator Operator Role Play As the EO in the Field, When directed to investigate the FRV, wait 1 minute and report, the feedback arm has fallen off the FRV.
Respond as required.
Floor Instructor Notes/OPEX/TRs Note:
This was an Event on LaSalle Unit 1 on 2/17/17 which resulted in a manual reactor scram due to RPV Level being above 50. In this scenario, reactor power is higher than during the actual event and will result in a much more controlled level transient. IR 3975576 Terminus: Following the crew taking control of level using 1FW003 and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 23 of 31
NRC 17-1-3 Revision 00 Event - 9
==
Description:==
EHC Leak, Scram Initiation: Per Lead Evaluator Cues:
Automatic Actions:
Standby EHC Pump starts (1300 psig EHC Fluid Pressure)
Turbine Trip (1100 psig EHC Fluid Pressure)
Expected Annunciators: 1PM02J-B505, EHC MINOR TROUBLE Key Parameter Response: EHC Fluid Pressure lowering Task/
Position EXPECTED OPERATOR RESPONSE Obj.
304.010 ATC
- Manually Scram the Unit Per LOR-1PM02J-B505
- CHECK EHC Workstation alarm screen
- Refer to LOP-EH-11 Per LOP-EH-11 73.019 BOP
- Dispatch an oerator to look for leaks
- If reservoir level reaches +1 inch, then PLACE both EHC pumps in PTL to prevent pump damage. (The EHC pump suction line is approximately 1 inch from the bottom of the reservoir with the end of the suction pipe cut at a 45 degree angle. Pumps must be secured prior to loss of suction to prevent damage).
- Direct above actions 73.019 US o Establish critical parameter EHC Pressure/Resovoir Level
- Order the crew to manuall scram the reactor SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 24 of 31
NRC 17-1-3 Revision 00 Event - 9
==
Description:==
EHC Leak, Scram Simulator Operator Actions When directed by the Lead Release Event 9 Evaluator When directed by the Crew Release Open 1EH-FV1 Simulator Operator Role Play As the EO sent to investigate the leak, wait 1 minute and report that there is a large leak coming from the upstream side of the A EHC Pump suction valve and is not isolable.
If ordered to open 1EH-FV1, perform the above action, wait 1 minute and report 1EH-FV1 is open.
Respond as required.
Floor Instructor Notes/OPEX/TRs Note: The crew may either depressurize EHC or close MSIVs. When the Leak commences, it will be what controls reactor pressure.
Terminus: continued.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 25 of 31
NRC 17-1-3 Revision 00 Event - 10
==
Description:==
Electrical ATWS, ARI inserts rods Initiation: Event 9 Cues: Event 9 Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- When directed, manually scrams the reactor 419.000
- PLACE Reactor Mode Switch in SHUTDOWN 414.000
- CHECK Control Rods INSERTED and Power Decreasing (NO) 419.030 ATC 421.000
- REPORT to the Unit Supervisor the status of RPV Level and Pressure 431.000
- VERIFY Reactor Recirculation Pumps have downshifted 431.010
- VERIFY Main Turbine and Generator Trip
- STABILIZE Reactor Pressure <1020 psig BOP
- Take action per OP-LA-103-102-1002 431.000
- Direct above actions US 431.010
- Enter LGA-001 and LGA-010 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 26 of 31
NRC 17-1-3 Revision 00 Event - 10
==
Description:==
Electrical ATWS, ARI inserts rods Simulator Operator Actions none Simulator Operator Role Play Respond as required.
Floor Instructor Notes/OPEX/TRs Note: The crew may either depressurize EHC or close MSIVs. When the Leak commences, it will be what controls reactor pressure.
Terminus: continued.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 27 of 31
NRC 17-1-3 Revision 00 Event - 11
==
Description:==
Main Steam Line Break Inside Containment Initiation: Automatic Cues:
Automatic Actions: ECCS Initiation Expected Annunciators: 1H13-P603-B501, Primary Containment Pressure Hi/Lo Key Parameter Response: Rising Containment Pressure Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Control RPV Level and Pressure as directed by the Unit Supervisor
- To prevent losing Chamber Spray/ECCS runout with DW Spray prior to 500 psig.
- Place Div 1/2 Inj Override Switch to NON-ATWS
- Div I: With an ECCS signal present Verify White Manual Override light for 1E12-F042A AND 1E21-F005 Illuminated
- Div II: With an ECCS signal present Verify White Manual Override light for 1E12-F042B AND 1E12-F042C Illuminated Per LGA-RH-103
- Startup RHR Service Water as follows:
- OPEN 1A/1B RHR Hx Service Water Outlet Valve: 1E12-F068A/B
- At approximately 9 to 10 seconds after taking the 1E12-F068A/B switch to OPEN, START first RHR Service Water Pump: 1A or 1B/C or D 419.000
- When indicated flow reaches 3000 gpm, START second RHR Service 304.010 Water Pump.
414.000 419.020 BOP
- Startup RHR 419.030
- Start 1A/1B RHR Pump 421.000
- Establish RHR flow of 1500 to 7450 gpm:
421.010
- Throttle 1E12-F024A/B (Test Valve) OPEN.
- Close 1E12-F048A/B (HX Bypass) o Place A/B HTX Bypass Throttle/Seal in switch to THROTTLE and THROTTLE CLOSED 1E12-F048A/B. o o Place A/B HTX Bypass Throttle/Seal in switch to SEAL IN and CLOSE 1E12-F048A/B
- When directed establish Suppression Chamber Spray: (CT)
- VERIFY 1A/1B RHR Pump is running
- OPEN 1E12-F027A/B
- When directed establish Drywell Spray: (CT)
- VERIFY 1A/1B RHR Pump is running
- THROTTLE 1E12-F024A/B CLOSED
- OPEN:1E12-F016A/B and 1E12-F017A/B 419.000
- Enters and directs actions of LGA-001 LEVEL LEG 304.010 US
- Establishes a RPV water level band of 20 to +50 inches 414.000
- Enters and directs actions of LGA-001 PRESSURE LEG SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 28 of 31
NRC 17-1-3 Revision 00
- STABILIZE Reactor Pressure below 1059 psig
- When Drywell Pressure exceeds 1.93 psig, enters and directs actions of LGA-003
- Before Suppression Chamber Pressure exceeds 12 psig
- Verifies Containment Flood level below 723 ft.
- Directs start of Suppression Chamber Sprays (CT)
- When Suppression Chamber Pressure exceeds 12 psig, direct initiation of Drywell sprays
- Verifies Containment Flood level below 722 ft.
- Verifies Drywell Pressure and Temperature permit Drywell Sprays per Figure D
- Verifies both Recirc Pumps are tripped
- Direct initiation of Drywell sprays (CT)
- When Suppression Pool temperature exceeds 105ºF initiation of direct initiation of Suppression Pool Cooling Event - 11
==
Description:==
Main Steam Line Break Inside Containment Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Following Containment Cooling online and RPV Level in control and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 29 of 31
NRC 17-1-3 Revision 00 REFERENCES Procedure Rev Title
- 1. INPO 15-004 Operations Fundamentals
- 2. SOER 10-2 Engaged, Thinking Organizations
- 3. LGP-1-1 122 Normal Unit Startup
- 4. LOP-RR-05 52 Changing Reactor Recirc Pump Speed from Slow to Fast Speed
- 5. LOP-RR-07 45 Operation of the Reactor Recirculation Flow Control System
- 6. LOA-RR-101 38 Unit 1 Reactor Recirculation System Abnormal
- 7. LOR-1PM02J-B310 3 Generator Stator Coolant Runback Circuit Energized
- 8. LOA-GC-101 10 UNIT 1 GENERATOR STATOR COOLING ABNORMAL
- 9. LOR-1H13-P603-A205 4 Standby Liquid Control Tank 1C41-A001 Level High/Low
- 10. LOA-FW-101 11 REACTOR LEVEL/FEEDWATER PUMP CONTROL TROUBLE
- 11. LOR-1H13-P603-A511 2 RWLCS Trouble
- 12. LOR-1H13-P603-B501 4 Primary Containment Pressure Hi/Lo
- 13. LOP-FW-16 36 1(2)DS001 Operator Station Alarm Message Interpretation
- 14. LOA-EH-101 35 Unit 1 EHC Abnormal
- 15. LOP-EH-11 23 EHC Workstation Alarm Response and other information
- 16. LOR-1PM02J-B505 6 EHC Minor Trouble
- 17. LGA-001 18 RPV Control
- 18. LGA-003 17 Primary Containment Control
- 19. OP-LA-101-111-1002 71 LaSalle Operations Philosophy Handbook.
- 20. OP-LA-103-102-1002 17 Strategies for Successful Transient Mitigation
- 21. OP-AA-106-101 21 Significant Event Reporting
- 22. OP-LA-STA-1001 5 LaSalle Shift Technical Advisor (STA) Checklists
- 23. EP-AA-1005 Add. 3 3 Emergency Action Levels for LaSalle Station
- 24. EP-MW-114-100-F-01 J Nuclear Accident Reporting System(NARS) Form SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 30 of 31
NRC 17-1-3 Revision 00 U1 SUPERVISOR TURNOVER Shift: Days Date: Today Mode: 1 OLR: Green Work Week: Non-Div Unit 1 power level Unit 2 power level
- 35 % Power with LGP-1-1 In-progress
- 100 % Power
- A TDRFP and C MDRFP are in Auto *
- '1A' RR Pump in Fast *
- '1B' RR Pump in Slow
- U1 Thermal Limit Issues /Power Evolutions U2 Thermal Limit Issues /Power Evolutions
- None
- None Existing LCOs, date of next surveillance Existing LCOs, date of next surveillance
- None
- None LOSs in progress or major maintenance LOSs in progress or major maintenance
- None
- None Equipment removed from service or currently unavailable
- None
- None Grid Status is Green Comments, evolutions, problems, etc. Comments, evolutions, problems, etc.
- Currently in step E.8.27 of LGP-1-1
- Non-Div Workweek. OLR is Green
- Raise Reactor Power per LOP-RR-07 using Reactor Recirc 100 MWe (ATC)
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 31 of 31
LaSalle County Station LICENSED OPERATOR EVALUATED SCENARIO GUIDE UNRC 17-1-4 Rev. 00 6/25/18 DEVELOPED BY:
Exam Author Date TECHNICAL REVIEW: Polega / Pratt / Quinn / Vanderhyden 7/10/18 SME/Tech Reviewer Date REVIEWED BY:
Training Department Date APPROVED BY:
Operations Representative Date
UNRC 17-1-4 Revision 00 Facility: LaSalle County Generating Station Scenario #: NRC 17-1-4 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.
SUMMARY
OF EVENTS
- 1. Swap SPE Blowers per LOP-GS-05
- 2. 1E MPT Hot Spot. The crew will receive a report from the field following a 1E MPT trouble that there is a hot spot and the crew must reduce Reactor Power to reduce load on the transformer.
- 3. Condensate Jockey Pump Trip. The crew will respond by re-pressurizing cycled condensate using either the A or B Condensate Transfer Pump.
- 4. A OPRM Trip 1/2 Scram. The crew will respond to the loss of power to A OPRM by bypassing A OPRM and resetting the half Scram.
- 5. MCC 136Y-2 Comp D1 Trips, C LPCI INOP. The Unit Supervisor will enter Tech Specs for C LPCI being INOP.
- 6. Control Rod Drift In. Rod 30-15 will drift in and the crew will take action to insert the control rod and disarm it.
- 7. Control Rod INOP. The Unit Supervisor will enter Tech Specs for rod 30-15 being INOP.
- 8. Fire Protection Jockey Pump Trip. The crew will take action to start the standby jockey pump and verify that Service Water is lined up to backup FP. If Diesel Fire Pumps start they must be manually shutdown.
- 9. Unisolable Feedwater Leak Outside Primary Containment. The crew will scram the reactor and attempt to isolate the leak.
- 10. 1VT79YA/B/C Fail OPEN, High Off-site Release, Blowdown. With a release into the Steam Tunnel in progress and a secondary containment failure the crew will blowdown when release level reaches the General Emergency Level.
Critical Tasks
- 1. With the reactor at power and with a primary system discharging into the secondary containment MANUALLY SCRAM the reactor, before any area exceeds the maximum safe operating levels.
- 2. With a primary system discharging outside primary and secondary containment, manually scram the reactor if a reactor scram has not yet been initiated, enter LGA-001, and INITIATE emergency depressurization before offsite release rate reaches the General Emergency level.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 2 of 29
UNRC 17-1-4 Revision 00 TRAINING REQUESTS (if applicable)
- 1. None OPEX (if applicable)
- 1. None Operator Fundamentals
- 1. Monitoring plant indications and conditions closely
- 2. Controlling plant evolutions precisely
- 3. Operating the plant with a conservative bias
- 4. Working effectively as a team
- 5. Having a solid understanding of plant design, engineering principles, and sciences SOER 10-2
- 1. Supervisory oversight role
- 2. Recognition and mitigation of risk
- 3. Worker performance
- 4. Tolerance of repetitive/long standing issues and degradation of standards
- 5. Operating Experience Record of Revisions (Summary)
Rev. 0 Developed new for the ILT 17-1 NRC Exam SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 3 of 29
UNRC 17-1-4 Revision 00 INITIAL SIMULATOR SETUP/ REQUIRED DOCUMENTATION
- 1. Recall a full power IC 151
- 2. Place simulator in RUN
- 3. Load and run the SmartScenario file 17-1-4.ssf
- 4. Update the Tech Spec Timeclock Sheet as follows:
TS/TRM/ODCM System/ Required REQUIRED ACTION Completion Expiration Component Action Description Time Date/Time N/A N/A N/A N/A N/A N/A
- 5. Perform the pre-scenario checklist (TQ-LA-150-0308)
SCENARIO OUTLINE (NRC Evaluations Only)
Event Malf. Event Event No. No. Type* Description 1 none N (BOP)
Swap SPE Blowers per LOP-GS-05 2 r0342 R (ATC) 1E MPT Hot Spot, Power Reduction 3 k7b53jpy C (BOP)
Condensate Transfer Jockey Pump Trip 4 r1204 I (ATC)
A OPRM Trip, 1/2 Scram 5 d1947 T (US)
MCC 136Y-2 Comp D1 Trips, C LPCI INOP 6 mrd079 C (ATC)
Control Rod Drift In 7 none T (US)
Control Rod INOP 8 k7b22jp9 C (BOP)
Fire Protection Jockey Pump Trip 9 mcf033 M Unisolable Feedwater Leak Outside Containment 10 mvt001 M 1VT79YA/B/C Fail OPEN, High Off-site Release, Blowdown
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specification APPROXIMATE SCENARIO RUN TIME 60 Minutes SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 4 of 29
UNRC 17-1-4 Revision 00 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE)
During performance of tasks, dynamic learning activities, or formal evaluations, 769.00.01 demonstrate applicable Human Performance behaviors IAW the appropriate procedures.
Given an operating experience document, paraphrase the lessons learned and 762.04.00 methods to prevent recurrence at LaSalle Station, as described in the training material.
During performance of tasks, apply the administrative requirements of PROCEDURE 614.010 USE AND ADHERENCE EXPECTATIONS, IAW station procedures.
TASKS RO - ATC 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures 2.010 Respond to a Transformer Trouble and take the appropriate actions to restore.
Given initial plant conditions, Respond to a Control Rod Drive failures from the Main Control 25.048 Room, IAW station procedures.
Given plant conditions, perform the Control Room Actions in response to OPRM Trouble, IAW 55.001 station procedures.
Given plant conditions, perform Control Room actions to startup and shutdown Gland Seal Steam 71.033 System, IAW station procedures.
91.001 Given plant conditions, determine PCIS status, IAW station procedures.
Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 413.000 59.5 IAW LGA-001 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 5 of 29
UNRC 17-1-4 Revision 00 RO - BOP/ASSIST 2.010 Respond to a Transformer Trouble and take the appropriate actions to restore.
Given Plant conditions, perform the Control Room actions to utilize the ESF Status Panel 50.013 Operation and Response functions of the Plant Process Computer, IAW station procedures.
Given plant conditions, perform the Control Room Actions in response to OPRM Trouble, IAW 55.001 station procedures.
70.043 Perform Control Room actions to evaluate Main Steam Tunnel atmosphere Given plant conditions, provide an alternate supply to the fire protection system, IAW station 125.021 procedures.
Given LGA-02, Secondary Containment Control, in progress, evaluate plant conditions and 416.000 control water level in secondary containment by operation of sumps IAW station procedures Given LGA-02, Secondary Containment Control, in progress, evaluate plant conditions and 417.000 control temperature in secondary containment by operation of ventilation, IAW station procedures.
Given LGA-02, Secondary Containment Control, in progress with a system discharging into an 418.000 area, evaluate plant conditions and terminate the release to the Secondary Containment per LGA-002.
Given LGA-03, Primary Containment Control, in progress, evaluate plant conditions and control 421.000 and maintain suppression pool temperature less than HCTL IAW station procedures.
Given LGA-03, Primary Containment Control, in progress, cool the Suppression Pool IAW 421.010 station procedures.
428.000 Evaluate plant conditions and rapidly depressurize the RPV using SRVs via the ADS system, SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 6 of 29
UNRC 17-1-4 Revision 00 SRO - UNIT SUPERVISOR 2.010 Respond to a Transformer Trouble and take the appropriate actions to restore.
Given initial plant conditions, Respond to a Control Rod Drive failures from the Main Control 25.048 Room, IAW station procedures.
Given Plant conditions, perform the Control Room actions to utilize the ESF Status Panel 50.013 Operation and Response functions of the Plant Process Computer, IAW station procedures.
Given plant conditions, perform the Control Room Actions in response to OPRM Trouble, IAW 55.001 station procedures.
70.043 Perform Control Room actions to evaluate Main Steam Tunnel atmosphere Given plant conditions, perform Control Room actions to startup and shutdown Gland Seal Steam 71.033 System, IAW station procedures.
91.001 Given plant conditions, determine PCIS status, IAW station procedures.
Given plant conditions, provide an alternate supply to the fire protection system, IAW station 125.021 procedures.
Given a set of plant conditions, identify and prepare the Technical Specification required actions 201.011 IAW Tech Specs.
Given LGA-02, Secondary Containment Control, in progress, evaluate plant conditions and control 416.000 water level in secondary containment by operation of sumps IAW station procedures Given LGA-02, Secondary Containment Control, in progress, evaluate plant conditions and control 417.000 temperature in secondary containment by operation of ventilation, IAW station procedures.
Given LGA-02, Secondary Containment Control, in progress with a system discharging into an 418.000 area, evaluate plant conditions and terminate the release to the Secondary Containment per LGA-002.
Given LGA-03, Primary Containment Control, in progress, evaluate plant conditions and control 421.000 and maintain suppression pool temperature less than HCTL IAW station procedures.
Given LGA-03, Primary Containment Control, in progress, cool the Suppression Pool IAW station 421.010 procedures.
428.000 Evaluate plant conditions and rapidly depressurize the RPV using SRVs via the ADS system, SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 7 of 29
UNRC 17-1-4 Revision 00 Event - 1
==
Description:==
Swap SPE Blowers per LOP-GS-05 Initiation: Per Lead Evaluator, following the crew assuming the shift Cues:
Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Montior plant conditions and update the crew as required ATC
- Provide peer checks as required Per LOP-GS-05
- Start the idle Blower associated with the operating Steam Packing Exhauster 1CD01SAB
- While maintaining Steam Packing Exhauster Inlet Header A at between 5-12 W.C. on 1PI-GS032, perform the following:
- Partially throttles open the suction valve for the idle Blower until the SPE Steam Inlet Header vacuum increases to 12 W.C.
- Partially throttle shut the suction valve for the Blower that was initially in the 71.033 BOP operation until the SPE Steam Inlet Header vacuum decreases to 5 W.C. or until the suction valve for the blower that was initially operating is closed
- Alternately repeat steps 1 and 2 above until the suction valve for the Blower that was initially in operation indicates closed
- Adjust the position of the Blower suction valve for the on-line Blower, as necessary, to maintain an SPE Steam Inlet Header vacuum of 8-12 W.C.
- Close the Steam Packing Exhauster Blower Suction Valve that was initially open, 1N62-MOV-D1
- Stop the A Steam Packing Exhauster Blower 71.033 US
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 8 of 29
UNRC 17-1-4 Revision 00 Event - 1
==
Description:==
Swap SPE Blowers per LOP-GS-05 Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When SPE Blowers have been swapped.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 9 of 29
UNRC 17-1-4 Revision 00 Event - 2
==
Description:==
1E MPT Transformer Hot Spot Initiation: Per Lead Evaluator Cues:
Automatic Actions: none Expected Annunciators: 1PM01J-A204, MAIN TRANSFORMER 1 EAST TROUBLE Key Parameter Response: none Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Insert Cram Rods Per LOR-1PM01J-A204
- DISPATCH an operator to 1E Transformer
- Verify alarm
- Toggle local alarm switch to determine status of alarm Per LOA-TRAN-101
- Check power available to fans and pumps
- Check all fan and pump banks - operating 2.010 BOP
- Refer to attachment C and attachment E for MPT 1E/1W operating parameters/limits
- Check MPT Hot Spot Temperature below 160C (YES)
- Check MPT Hot Spot Temperature below 120C (NO)
Response not obtained
- Reduce transformer load to reduce MPT Hot Spot temperature <120C
- Record time transformer temperature exceeded 120C
- Contact system engineering and EMD for transformer repairs
- Direct above actions 2.010 US
- Inform TSO SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 10 of 29
UNRC 17-1-4 Revision 00 Event - 2
==
Description:==
1E MPT Transformer Hot Spot Simulator Operator Actions With the concurrence of the Release Event 2 Lead Evaluator When asked to take alarm From Smart Summary place r0342 in OFF toggle switch to RESET/OFF When asked to take alarm From Smart Summary place r0342 in ON toggle switch to ON When asked to take alarm From Smart Summary place r0342 in OFF toggle switch to RESET/OFF With concurrence from the Lead Evaluator (Satisfactory DELETE from smart summary r0342 Reactivity Manipulation)
Simulator Operator Role Play when dispatched to the 1E transformer, wait 2 minutes and report that 1E Transformer has a Hot spot and Temperature is 125 degrees Celsius and rising one degree every 2 minutes and the oil temperature alarm is in.
If asked, inform the crew all fan banks and pumps are running and power is available.
If asked, 6 coolers are running and ambient temperature is 23 degrees Celsius.
If asked to take the oil temperature toggle Switch follow the above Sim Op Actions After initial down power, if the crew stops lowering power prior to 100 MWe inform them temperature is at 125 degrees Celsius and stable.
When power has been lowered by 100 MWe and with concurrence of the Lead Evaluator, call and inform the crew, transformer oil temperature is 115 degrees Celsius and lowering Acknowledge reports as required Floor Instructor Notes/OPEX/TRs Terminus: When power is lowered 100 MWe or at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 11 of 29
UNRC 17-1-4 Revision 00 Event - 3
==
Description:==
Condensate Transfer Jockey Pump Trip Initiation: Per Lead Evaluator Cues:
Automatic Actions: Condensate Transfer Jockey Pump 1CY03P Automatic Trip Expected Annunciators: 1PM10J-A404, Condensate Transfer Jockey Pump 1CY03P Automatic Trip Key Parameter Response: Lowering Cycled Condensate Pressure Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor plant conditions and update the crew as required Per LOR-1PM10J-A404
- DISPATCH operator to MCC 132B-3, Compartment B-2, to DETERMINE cause of trip and INITIATE corrective action as required.
- Have Condensate Transfer Jockey Pump 1CY03P INSPECTED for abnormalities.
- VERIFY at least one Condensate Transfer Pump is running and is capable of
- supplying current demand of cycled condensate.
US
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 12 of 29
UNRC 17-1-4 Revision 00 Event - 3
==
Description:==
Condensate Transfer Jockey Pump Trip Simulator Operator Actions When directed by the Lead Release Event 3 Evaluator Simulator Operator Role Play As the EO sent to investigate the Pump trip, wait 1 minute and report that breaker tripped on overcurrent and there is an acrid odor coming from the Pump motor.
Respond as required.
Floor Instructor Notes/OPEX/TRs Terminus: Following the restoration of Condensate pressure and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 13 of 29
UNRC 17-1-4 Revision 00 Event - 4
==
Description:==
A OPRM Trip, 1/2 Scram Initiation: Per Lead Evaluator Cues:
Automatic Actions: RPS Half Scram Expected Annunciators: 1H13-P603-B507, OPRM Inop/Trouble Key Parameter Response: None Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOR-1H13-P603-B507
- CHECK Alarm monitor to determine which OPRM module is in alarm.
- IF cause of alarm cannot be readily determined contact IMD and System Engineering for assistance.
- REFER to LOA-NR-101.
55.001 ATC Per LOA-NR-101
- STOP all control rod motion/power changes.
- CHECK 1/2 Scram indicated.
- RESET 1/2 Scram.
Per LOR-1H13-P603-B507
- If not in test, Bypass Inoperable OPRM module.
55.001 BOP Per LOA-NR-101
- CHECK power ON to OPRM modules.
- CHECK OPRM Module(s) not in TEST.
- Take affected OPRM module Enable/Normal/Bypass switch to BYPASS.
- Refer to Tech Spec 3.3.1.3 55.001 US
- Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 14 of 29
UNRC 17-1-4 Revision 00 Event - 4
==
Description:==
A OPRM Trip, 1/2 Scram Simulator Operator Actions When directed by the Lead Release Event 4 Evaluator Simulator Operator Role Play Respond as IMD as required.
Respond as required.
Floor Instructor Notes/OPEX/TRs Note: A loss of power to an OPRM module will result in a half scram and an OPRM Trouble alarm.
Terminus: Following the restoration of power to A RPS and at the desertion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 15 of 29
UNRC 17-1-4 Revision 00 Event - 5
==
Description:==
MCC 136Y-2 Comp D1 Trips, C LPCI INOP Initiation: Per Lead Evaluator Cues:
Automatic Actions: ESF Alarm D1947 Expected Annunciators: none Key Parameter Response: 1E12-F042C lights go out Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor plant conditions and update the crew as required
- Dispatch an operator to investigate the valve and breaker 50.103 BOP
- Refer to LOP-CX-03
- Enter Tech Spec 3.5.1 Required Action A.1 Restore Low Pressure Injection subsystem to OPERABLE within 7 days
- Enter TRM 3.8.c Required Action 50.013 201.011 US
- B.1 Declare the affected valve(s) inoperable immediately OR
- B.2 Continously bypass the thermal overload
- Refer to Tech Spec 3.3.3.1 and 3.6.1.3 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 16 of 29
UNRC 17-1-4 Revision 00 Event - 5
==
Description:==
MCC 136Y-2 Comp D1 Trips, C LPCI INOP Simulator Operator Actions When directed by the Lead Release Event 5 Evaluator Simulator Operator Role Play As the EO sent to investigate 136Y-1 D-1, report that it is tripped with no indication of why it tripped.
As the EO, if ordered to reclose the breaker, report that it tripped again.
Respond as required.
Floor Instructor Notes/OPEX/TRs Terminus: Following the Tech Spec call and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 17 of 29
UNRC 17-1-4 Revision 00 Event - 6
==
Description:==
Control Rod Drift Initiation: Per Lead Evaluator, following the crew assuming the shift Cues:
Automatic Actions: Rod 30-15 Drifts In Expected Annunciators: 1H13-P603-A504, Control Rod Drive Drift Alarm Key Parameter Response: Lowering MWe Task/
Position EXPECTED OPERATOR RESPONSE Obj.
Per LOA-RD-101
- CONTINUALLY CHECK control rods status
- CHECK Control Rods - No control rod currently moving.
- SELECT drifting control rod.
- VERIFY insert block indication OFF at ROD SELECT or STATUS Display.
- If required, REMOVE insert block:
25.048 ATC
- PLACE the RWM Select switch to BYPASS.
- INSERT control rod to position 00.
- PLACE CRD DRIVE FLOW TRIP CIRCUIT BYPASS Switch to BYPASS.
- CHECK control rod remains at position 04 or less.
- If Insert push button is NOT being held depressed:
o PLACE control rod OOS on RCMS.
o DISARM control rod electrically on RCMS.
- Monitor plant conditions and provide peer checks as required
- Direct above actions 25.048 US
- Set Manual Scram Criteria More than one rod drifting or more than three rods drifted full in SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 18 of 29
UNRC 17-1-4 Revision 00 Event - 6
==
Description:==
Control Rod Drift Simulator Operator Actions When directed by the Lead Release Event 6 Evaluator Simulator Operator Role Play As the EO when sent to investigate, wait 2 minutes and report you dont see anything reason for the rod drift.
Respond as System Engineering Respond as required.
Floor Instructor Notes/OPEX/TRs Terminus: Rod 30-15 inserted and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 19 of 29
UNRC 17-1-4 Revision 00 Event - 7
==
Description:==
Control Rod INOP Initiation: Event 6 Cues: Event 6 Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Continue with actions of Event 6 BOP
- Continue with actions of Event 6
- Enter Tech Spec 3.1.3 Required Action
- C.1 Fully insert inoperable control rod within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 201.011 US AND
- C.2 Disarm the associated CRD within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 20 of 29
UNRC 17-1-4 Revision 00 Event - 7
==
Description:==
Control Rod INOP Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Following Tech Spec Call and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 21 of 29
UNRC 17-1-4 Revision 00 Event - 8
==
Description:==
Fire Protection Jockey Pump Trip Initiation: Per Lead Evaluator Cues:
Automatic Actions: TRIPS Fire Jockey Pump 0FP25P.
Expected Annunciators: 1PM10J-B301, Fire Protection Jockey Pump 0FP25P Automatic Trip Key Parameter Response: Lowering Fire Main Header Pressure Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor plant parameters and update the crew as required Per LOR-1PM10J-B301
- START Fire Jockey Pump 0FP26P per LOP-FP-01, Fire Protection System Filling, Venting, Startup and Draining.
- DISPATCH operator to Lake Screen House MCC l32Y-1 Compt A-3, to INVESTIGATE cause of alarm and INITIATE corrective action as required.
- INSPECT Fire Jockey Pump 0FP25P for abnormalities.
125.021 BOP o When Fire Jockey Pump 0FP25P Trips, resulting pressure drop may cause Diesel Fire Pump(s) to start. Should this occur, Diesel Fire Pump(s) must be manually shutdown per LOP-FP-02, Fire Pump Diesel Startup and Shutdown, after Fire Jockey Pump 0FP26P is started.
- VERIFY Service Water is lined up to supply Fire Header via valves 1FP058, Service Water Backup Supply to Fire Header Stop, in Lake Screen House.
- Direct above actions 125.021 US o Refer to TRM 3.7.j SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 22 of 29
UNRC 17-1-4 Revision 00 Event - 8
==
Description:==
Fire Protection Jockey Pump Trip Simulator Operator Actions When directed by the Lead Release Event 8 Evaluator Simulator Operator Role Play As the EO sent to investigate the pump trip, wait 2 minutes and report that a contractor in the area has reported bumping the breaker.
As an EO in the Field, if asked, report post start checks are complete for the B Fire Protection Jockey Pump.
As an EO if asked to check Service water lined up to FP, wait 1 minute and report that Service Water is lined up to FP.
Respond as required.
Floor Instructor Notes/OPEX/TRs Terminus: Following the restoration of Fire Header pressure and at the discretion of the Lead Evaluator.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 23 of 29
UNRC 17-1-4 Revision 00 Event - 9
==
Description:==
Unisolable Feedwater Leak Outside Containment Initiation: Per Lead Evaluator Cues:
Automatic Actions: Group 4 isolations Expected Annunciators: 1H13-P601-B209, COMMON AREA MONITORS RADIATION HIGH Key Parameter Response: RWLCS Deviations Task/
Position EXPECTED OPERATOR RESPONSE Obj.
- Monitor plant parameters and update the crew as required 91.001 ATC
- Maintain Reactor Level and Pressure per LGA-001 Per LGA-002
- OPERATE Area Coolers and VR if possible
- Take LGA-002 data
- If any area Temperature or Radiation is above Max Normal or if a sump is 70.043 overflowing, then:
91.001
- ISOLATE discharges into the area except for those needed to fight 416.000 BOP fires or needed by other LGAs 417.000 418.000
- MONITOR release rates for LGA-009 entry conditions
Per LOA-AR-101
- EVACUATE the power block 70.043 91.001
- Direct actions of LGA-002 416.000 US
- Call out for LGA-002 data 417.000
- Direct a Manual Scram (CT) 418.000 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 24 of 29
UNRC 17-1-4 Revision 00 Event - 9
==
Description:==
Unisolable Feedwater Leak Outside Containment Simulator Operator Actions When directed by the Lead Release Event 9 Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 25 of 29
UNRC 17-1-4 Revision 00 Event - 10
==
Description:==
1VT79YA/B/C Fail OPEN, High Off-site Release, Blowdown Initiation: Automatic Cues:
Key Parameter Response: STACK WRGM EFF RAD LEVELS Task/
Position EXPECTED OPERATOR RESPONSE Obj.
428.000 ATC
- Monitor plant parameters and update the crew as required Per LGA-009
- Operate Ventilation that may be releasing radioactivity
- Isolate all primary system discharges outside primary and secondary containment, except systems needed for LGAs
- If Primary system discharging outside primary and secondary containments AND discharges cannot be isolates or isolation attempts fail then:
- ENTER LGA-001
- BLOWDOWN per LGA-004 Per LGA-004
- Arms and depresses both Div 1 ADS MANUAL INITIATION pushbuttons
- Arms and depresses both Div 2 ADS MANUAL INITIATION pushbuttons
- When directed, starts all available Pool Cooling per LGA-RH-103 428.000
- Startup RHR Service Water as follows:
- OPEN 1A/1B RHR Hx Service Water Outlet Valve: 1E12-F068A/B
- At approximately 9 to 10 seconds after taking the 1E12-F068A/B switch to OPEN, START first RHR Service Water Pump:
- 1A or 1B/C or D
- When indicated flow reaches 3000 gpm, START second RHR WS Pump
- Startup RHR
- Start 1A/1B RHR Pump
- Establish RHR flow of 1500 to 7450 gpm:
- Throttle 1E12-F024A/B (Test Valve) OPEN
- Close 1E12-F048A/B (HX Bypass)
- Place A/B HTX Bypass Throttle/Seal in switch to THROTTLE and THROTTLE CLOSED 1E12-F048A/B or
- Place A/B HTX Bypass Throttle/Seal in switch to SEAL IN and CLOSE 1E12-F048A/B 52.035 421.000
- VERIFY Suppression Pool level US 421.010
- Direct actions of LGA-009 and LGA-004(CT) 428.000 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 26 of 29
UNRC 17-1-4 Revision 00 Event - 10
==
Description:==
1VT79YA/B/C Fail OPEN, High Off-site Release, Blowdown Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note:
The crew may anticipate a blowdown on a previous event.
Terminus: When an RPV blowdown has been performed and at the discretion of the Lead Examiner.
SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
Page 27 of 29
UNRC 17-1-4 Revision 00 REFERENCES Procedure Rev Title
- 1. INPO 15-004 Operations Fundamentals
- 2. SOER 10-2 Engaged, Thinking Organizations
- 3. LOR-1PM10J-A404 1 Condensate Transfer Jockey Pump 1CY03P Automatic Trip
- 4. LOR-1H13-P603-B507 5 OPRM Inop/Trouble
- 5. LOA-NR-101 20 Neutron Monitoring Trouble
- 6. LOR-1H13-P603-A504 4 Control Rod Drive Drift Alarm
- 7. LOA-RD-101 21 Control Rod Drive Abnormal
- 8. LOP-CX-03 16 ESF Status Panel Operation and Response to Panel Indications
- 9. LOR-1PM10J-B301 1 Fire Protection Jockey Pump 0FP25P Automatic Trip
- 10. LOR-1H13-P601-B209 1 Common Area Monitors Radiation High
- 11. LGA-001 18 RPV Control
- 12. LGA-002 9 Secondary Containment Control
- 13. LGA-003 17 Primary Containment Control
- 14. LGA-004 9 RPV Blowdown
- 15. LGA-009 8 Radioactivity Release Control
- 17. OP-LA-103-102-1002 17 Strategies for Successful Transient Mitigation
- 18. OP-AA-106-101 21 Significant Event Reporting
- 19. OP-LA-STA-1001 5 LaSalle Shift Technical Advisor (STA) Checklists
- 20. EP-AA-1005 Add. 3 3 Emergency Action Levels for LaSalle Station
- 21. EP-MW-114-100-F-01 J Nuclear Accident Reporting System(NARS) Form SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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UNRC 17-1-4 Revision 00 U1 SUPERVISOR TURNOVER Shift: Days Date: Today Mode: 1 OLR: Green Work Week: Non-Div Unit 1 power level Unit 2 power level
- 100 % Power
- 100 % Power U1 Thermal Limit Issues /Power Evolutions U2 Thermal Limit Issues /Power Evolutions
- None
- None Existing LCOs, date of next surveillance Existing LCOs, date of next surveillance
- None
- None LOSs in progress or major maintenance LOSs in progress or major maintenance
- None
- None Equipment removed from service or currently unavailable
- None
- None Grid Status is Green Comments, evolutions, problems, etc. Comments, evolutions, problems, etc.
- Swap Steam Packing Exhauster Blowers
- Non-Div Workweek. OLR is Green per LOP-GS-05 from 1A SPE Blower A to 1A SPE Blower B SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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