ML16216A548
| ML16216A548 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/02/2016 |
| From: | Palagi B Operations Branch III |
| To: | Exelon Generation Co |
| Shared Package | |
| ML15274A322 | List: |
| References | |
| SVP-16-004 | |
| Download: ML16216A548 (290) | |
Text
Job Performance Measure Enter Substitute Valve for RWCU Pump Flow JPM Number: RO Admin 1 Revision Number: 00 Date: 10/13/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM RO Admin 1 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 QCOP 9950-17 Rev: 01 Procedure QCOP 1200-03 Rev: 27 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
2016 ILT NRC JPM RO Admin 1 Revision Record (Summary)
Revision 00, This JPM was developed as an RO Admin JPM for the 2016 ILT NRC Exam.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM RO Admin 1 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC-21.
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. Manual Actuations:
- Remove the B RWCU Demin from service by inserting the following command:
irf cu10r out
- Throttle the MO 1-1201-133 to maintain the following:
- 1) RWCU Pump discharge pressure 100 to 200 psig above reactor pressure
- 2) A RWCU Demin flow at 230 gpm.
- 3. Malfunctions:
None
- 4. Remotes:
CU10R
- 5. Overrides:
None
- 6. 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.
- 7. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM RO Admin 1 INITIAL CONDITIONS
- The B RWCU Demin has been isolated per QCOP 1200-03 for a backwash and precoat.
- Local flow indication for both A and B RWCU pumps are 230 and 240 gpm, respectively.
- The QNE has been notified that a substitute values for RWCU pump flows are to be entered for the Core Thermal Heat Balance.
INITIATING CUE Enter substitute values for RWCU pump flow in accordance with QCOP 1200-03 step F.3 and QCOP 9950-17.
Provide examinee with: A marked up copy of QCOP 1200-03 and a blank copy of QCOP 9950-17.
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
2016 ILT NRC JPM RO Admin 1 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number EVALUATOR NOTE: QCOP 9950-17 steps F.2.f -F.2.o., will be performed for each point that requires a substitute value. Per QCOP 1200-03 step F.3.b., the points are:
C121_VOL C121_VOL_FILT C122_VOL C122_VOL_FILT
- F.2.d Select Database Management From the Main Menu: ___ ___ ___
Selects Database Management
- F.2.e Select Single Point Display- From the Database ___ ___ ___
Analog (SPAD) Management Menu:
Selects Single Point Display-Analog (SPAD)
- F.2.f Select the Point Name area Selects Point Name area ___ ___ ___
- F.2.g Select the desired Point Name From the Data Point Selection
-h (Point ID) Screen:
Scrolls through Point Names field and clicks on desired point to highlight. Then clicks OK. ___ ___ ___
OR ___ ___ ___
Enters the desired point in the ___ ___ ___
Point Search field, then click OK.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM RO Admin 1 Comment SAT UNSAT STEP ELEMENT STANDARD Number F.2.i Verify desired point is in Point Verifies each point is in the ___ ___ ___
Name field Point Name field of SPDD. ___ ___ ___
- F.2.j Select Change Point Attributes Clicks on Change Point ___ ___ ___
Attributes button at lower ___ ___ ___
portion of display.
- F.2.k Enter desired value for selected When the Single Point Digital points Change Attributes Display appears, enters the following values in the New Value field:
230 gpm for C121_VOL ___ ___ ___
230 gpm for C121_VOL_FILT ___ ___ ___
240 gpm for C122_VOL ___ ___ ___
240 gpm for C122_VOL_FILT ___ ___ ___
- F.2.l Apply the substitute values For each point: ___ ___ ___
Clicks the Apply button twice ___ ___ ___
on the bottom of display and ___ ___ ___
verifies field backround turns grey. ___ ___ ___
EVALUATOR NOTE: For step F.2.m, the change description box cannot be left blank The computer program will not proceed without at least some characters entered.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM RO Admin 1 Comment SAT UNSAT STEP ELEMENT STANDARD Number
- F.2. Enter the reason for the Enters procedure number or ___ ___ ___
m substitute value comment, in change ___ ___ ___
description box.
F.2.n Verify correct point and value Verifies correct point and value ___ ___ ___
are entered appear in pop-up window, then ___ ___ ___
selects OK to close window.
- F.2.o Select Done to return to SPAD Clicks on Done and returns to ___ ___ ___
screen. Single Point Display-Digital ___ ___ ___
(SPAD) screen.
QCOP Initials completed substitute Initials QCOP 1200-03 step ___ ___ ___
1200- values in QCOP 1200-03 step F.3.b.1 thru F.3.b.4 as each 03 ___ ___ ___
F.3.b.(1-4) substitute value is entered for F.3.b the computer points. ___ ___ ___
EVALUATOR NOTE: The examinee should inform you that the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM RO Admin 1 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Enter Substitute Value for RWCU Pump Flow JPM Number: RO Admin 1 Revision Number: 00 Task Number and
Title:
SR-9900-P01 (Freq: LIC=I) Given an operating reactor plant, perform the following process computer operations in accordance with the appropriate QCOP 9950 procedure:
9900.049 Enter a Substitute Value K/A Number and Importance: K/A: 2.1.19 Rating: 3.9/3.8 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOP 9950-17 Rev. 1, Changing Scan Status or Point Attributes of Selected Plant Process Computer Analog and Digital Points 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)
2016 ILT NRC JPM RO Admin 1 INITIAL CONDITIONS
- The B RWCU Demin has been isolated per QCOP 1200-03 for a backwash and precoat.
- Local flow indication for both A and B RWCU pumps are 230 and 240 gpm, respectively.
- The QNE has been notified that a substitute values for RWCU pump flows are to be entered for the Core Thermal Heat Balance.
INITIATING CUE Enter substitute values for RWCU pump flow in accordance with QCOP 1200-03 step F.3 and QCOP 9950-17.
SRRS: 3D.100; There are no retention requirements for this section
Job Performance Measure Verification of SBGTS Lineup JPM Number: RO Admin 2 Revision Number: 00 Date: 10/06/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM RO Admin 2 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 QCOP 7500-01 Rev: 21 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
2016 ILT NRC JPM RO Admin 2 Revision Record (Summary)
Revision 00, Developed for 2016 ILT NRC License Exam.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM RO Admin 2 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC-21 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. Manual Actuations:
- Place the 1/2 A SBGTS TRAIN MODE SELECTOR SWITCH to: A PRIM.
- Place the 1/2 B SBGTS TRAIN MODE SELECTOR SWITCH to: B STDBY.
- Verify all SBGTS annunciators are clear.
- 3. Malfunctions:
None
- 4. Remotes:
Noned
- 5. Overrides:
None
- 6. 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.
- 7. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM RO Admin 2 INITIAL CONDITIONS
- You are the Unit 1 Admin NSO.
- QCOS 7500-04, Unit 1 Standby Gas Treatment Initiation and Reactor Building Ventilation Isolation Test was completed last shift for the 1/2 B Standby Gas Train.
- The Unit Supervisor has requested a verification of the standby lineup for the Standby Gas Treatment System (SBGTS).
INITIATING CUE Verify the SBGTS standby lineup and if necessary report any discrepancies to the Unit Supervisor.
Provide examinee with: A blank copy of QCOP 7500-01, Standby Gas Treatment System (SBGTS) Standby Operation and Start-Up after the examinee obtains it in the simulator.
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
2016 ILT NRC JPM RO Admin 2 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number
MODE SELECTOR SWITCH is improperly selected as PRIM in PRIM. (Primary) instead of STBY (Stand-by).
CUE: As Unit Supervisor, acknowledge the report, and direct the examinee to complete the lineup verification.
MODE SELECTOR SWITCH is improperly selected as STBY in STBDY. (Standby) instead of PRIM (Primary).
- F.1.c Reports the 1-7503 U1 RB Recognizes the 1-7503 is ___ ___ ___
(1) INLET DMPR TO SBGTS is CLOSED (green light lit) and mispositioned. should be in the OPEN (red light lit) position.
- F.1.c Reports the 2-7503 U2 RB Recognizes the 2-7503 is ___ ___ ___
(2) INLET DMPR TO SBGTS is CLOSED (green light lit) and mispositioned. should be in the OPEN (red light lit) position.
F.1.c. Verifies 1/2 -7505A INLET DMPR Verifies 1/2 -7505A INLET DMPR ___ ___ ___
(3) is CLOSED. is closed.
-green light lit.
-red light out F.1.c. Verifies 1/2 -7505B INLET DMPR Verifies 1/2 -7505B INLET DMPR ___ ___ ___
(4) is CLOSED. is closed.
-green light lit.
-red light out SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM RO Admin 2 Comment SAT UNSAT STEP ELEMENT STANDARD Number F.1.c. Verifies the 1/2 -7504A TURB Verifies the 1/2 -7504A TURB ___ ___ ___
(5) BLDG CLG AIR DMPR is BLDG CLG AIR DMPR is OPEN. CLOSED.
-red light lit
-green light out F.1.c. Verifies the 1/2 -7504B TURB Verifies the 1/2 -7504B TURB ___ ___ ___
(6) BLDG CLG AIR DMPR is BLDG CLG AIR DMPR is OPEN. CLOSED.
-red light lit
-green light out F.1.c. Verifies 1/2 -7507A SBGTS FAN Verifies 1/2 -7507A is CLOSED. ___ ___ ___
(7) DISCH DMPR is CLOSED. -green light lit
-red light out F.1.c. Verifies 1/2 -7507B SBGTS FAN Verifies 1/2 -7507B is CLOSED. ___ ___ ___
(8) DISCH DMPR is CLOSED. -green light lit
-red light out F.1.c. Verifies 1/2 -7509 XTIE DMPR is Verifies 1/2 -7509 is OPEN. ___ ___ ___
(9) OPEN. -red light lit
-green light out F.1.c. Verifies 1/2 -7503A SBGTS AIR Verifies 1/2 -7503A is OFF. ___ ___ ___
(10) HTR is OFF. -OFF light lit
-ON light out F.1.c. Verifies 1/2 -7503B SBGTS AIR Verifies 1/2 -7503B is OFF. ___ ___ ___
(11) HTR is OFF. -OFF light lit
-ON light out SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM RO Admin 2 Comment SAT UNSAT STEP ELEMENT STANDARD Number F.1.c. Verifies 1/2 -7506A, 1/2 A Verifies 1/2 -7506A, is OFF. ___ ___ ___
(12) SBGTS FAN is OFF. -OFF light lit
-ON light out F.1.c. Verifies 1/2 -7506B, 1/2 B Verifies 1/2 -7506B, is OFF. ___ ___ ___
(13) SBGTS FAN is OFF. -OFF light lit
-ON light out F.1.c. Verifies Instrument Air is Dispatches EO to verify ___ ___ ___
(14) available to AO 1/2 -7510A and Instrument Air is valved into AO AO 1/2 -7510B SBGT OUTLET 1/2 -7510A and AO 1/2 -7510B VLVS. SBGT valves.
CUE: As EO, report: Instrument Air is valved into AO 1/2-7510A and AO 1/2 -7510B Standby Gas Train A and B Outlet Valves.
F.1.c. Verify all applicable SBGTS Verifies all applicable SBGTS ___ ___ ___
(15) alarms are cleared. annunciators at the 912-5 panel are clear.
CUE: As the Unit Supervisor, inform the examinee that: Another NSO will realign the SBGTS Trains to the correct lineup.
EVALUATOR NOTE: The examinee should inform you that the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM RO Admin 2 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Verification of SBGTS Lineup JPM Number: RO Admin 2 Revision Number: 00 Task Number and
Title:
SR-7500-P01 (Freq: LIC=B) Given SBGTS in a standby lineup, perform the monthly SBGTS monthly operability test and return SBGTS to a standby line up in accordance with QCOS 7500-05.
K/A Number and Importance: K/A: 2.1.31 Rating: 4.6/4.3 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOP 7500-01 Rev. 21, Standby Gas Treatment System (SBGTS) Standby Operation and Start-Up.
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)
2016 ILT NRC JPM RO Admin 2 INITIAL CONDITIONS
- You are the Unit 1 Admin NSO.
- QCOS 7500-04, Unit 1 Standby Gas Treatment Initiation and Reactor Building Ventilation Isolation Test was completed last shift for the 1/2 B Standby Gas Train.
- The Unit Supervisor has requested a verification of the standby lineup for the Standby Gas Treatment System (SBGTS).
INITIATING CUE Verify the SBGTS standby lineup and if necessary report and discrepancies to the Unit Supervisor.
SRRS: 3D.100; There are no retention requirements for this section
Job Performance Measure Print Reading Exercise JPM Number: RO Admin 3 Revision Number: 00 Date: 10/15/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC RO Admin 3-Rev.01 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 QOS 5600-01 Rev: 54 Procedure 4E-1466 Sh.3 Rev: AP 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
2016 ILT NRC RO Admin 3-Rev.01 Revision Record (Summary)
Revision 00, This JPM was developed new for the 2012 ILT NRC Exam.
Revision 01, Reformatted to latest JPM template. Used on 2016 ILT NRC Exam.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC RO Admin 3-Rev.01 SIMULATOR SETUP INSTRUCTIONS
- 1. Simulator not required for this JPM.
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. Manual Actuations:
None
- 3. Malfunctions:
None
- 4. Remotes:
None
- 5. Overrides:
None
- 6. 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.
- 7. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC RO Admin 3-Rev.01 INITIAL CONDITIONS You are the Clearance Order Writer.
QOS 5600-01, Turbine Control Valve (TCV) Fast Closure Scram Instrument Channel Functional Test was being performed.
When #3 TCV went closed during this test, NONE of the expected responses were received:
o DEHC did NOT indicate FAST CLOSURE DETECTED.
o Expected Annunciator 901-5 A-13, CHANNEL A/B TURB-GEN LOAD MISMATCH EHC LOW PRESS, did NOT alarm.
o The Test Box indicating light did NOT illuminate.
o The two sets of associated relay contacts did NOT open.
INITIATING CUE Reference electrical schematics 4E-1464 through 4E-1467.
Identify the following:
- 2) The FUSE that would have to be removed to deenergize the relay identified in Part 1.
Provide Examinee with: A blank copy of QOS 5600-01, when/if it is obtained for reference.
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
2016 ILT NRC RO Admin 3-Rev.01 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number EVALUATOR NOTES:
QOS 5600-01 is NOT provided.
This JPM is performed in the Simulator where the QOS and other necessary reference material can be obtained.
The relay number can be determined from either the QOS or Schematic Drawing 4E-1466 Sheet 3.
The fuse number can be determined from 4E-1466 Sheet 3 but not the QOS.
Do NOT allow the candidate to mark on electrical drawings.
- Part 1 Correctly identify the number Relay 590-121B identified. ___ ___ ___
of the TCV Fast Closure RPS relay associated with TCV #3.
- Part 2 Correctly identify the number Fuse 590-725B identified. ___ ___ ___
of the fuse that would have to be removed to deenergize the relay identified in Part 1.
EVALUATOR NOTE: The examinee should inform you that the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC RO Admin 3-Rev.01 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Print Reading Exercise JPM Number: RO Admin 3 Revision Number: 01 Task Number and
Title:
SRN-EPR-K10 (Freq: LIC=I N=B) Given an Electrical Drawing:
- a. Locate a given component
- b. Determine the component power supply K/A Number and Importance: K/A: 2.2.41 Rating: 3.5/3.9 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QOS 5600-01, Rev. 54, Turbine Control Valve Fast Closure Scram Instrument Channel Functional Test IR1294079, (Dated 11/23/11) Relay 590-123C did not drop out when pressure switch opened 4E-1466 Sheet 3, Schematic Drawing RPS CH B Scram and Aux Trip Relays 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)
2016 ILT NRC RO Admin 3-Rev.01 INITIAL CONDITIONS You are the Clearance Order Writer.
QOS 5600-01, Turbine Control Valve (TCV) Fast Closure Scram Instrument Channel Functional Test was being performed.
When #3 TCV went closed during this test, NONE of the expected responses were received:
o DEHC did NOT indicate FAST CLOSURE DETECTED.
o Expected Annunciator 901-5 A-13, CHANNEL A/B TURB-GEN LOAD MISMATCH EHC LOW PRESS, did NOT alarm.
o The Test Box indicating light did NOT illuminate.
o The two sets of associated relay contacts did NOT open.
INITIATING CUE Reference electrical schematics 4E-1464 through 4E-1467.
Identify the following:
- 2) The FUSE that would have to be removed to deenergize the relay identified in Part 1.
SRRS: 3D.100; There are no retention requirements for this section
Job Performance Measure ARM Trip Unit Set Point Check JPM Number: RO Admin 4 Revision Number: 00 Date: 10/04/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM RO Admin 4.doc 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 QCOP 1800-01 Rev: 15 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
2016 ILT NRC JPM RO Admin 4.doc Revision Record (Summary)
Revision 00, Developed for the 2016 ILT NRC Exam as an RO Admin JPM.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM RO Admin 4.doc SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC-21.
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. Manual Actuations:
None
- 3. Malfunctions:
None
- 4. Remotes:
None
- 5. Overrides:
None
- 6. 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.
- 7. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM RO Admin 4.doc INITIAL CONDITIONS
- You are the Admin NSO.
- The Post Maintenance Test (PMT) requires an operational check of the upscale and downscale set points.
- The Unit NSO will acknowledge and reset the 901-3 panel alarms.
INITIATING CUE Perform QCOP 1800-01 step F.1 for ARM 20 (1B SJAE AREA), on the 901-11 panel. Notify the Unit Supervisor when the test is complete.
Provide examinee with: A blank copy of QCOP 1800-01.
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
2016 ILT NRC JPM RO Admin 4.doc JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number
- F.1.a Depress and hold TRIP -Locates ARM 20 on the 901-11 ___ ___ ___
CHECK pushbutton panel.
-Depresses and holds the TRIP CHECK pushbutton.
MON until the HIGH lamp is lit. SPLY AREA MON
-Slowly turns the TRIP CHECK ADJUST knob in the clockwise direction until the HIGH lamp on ARM 20 Trip Unit is lit.
F.1.b. Verify ARM set point label is Verify alarm set point is ___ ___ ___
(1) correct. adjusted to the set point indicated on the ARM 20 label plate.
F.1.b. Verify high radiation alarm Verifies annunciator 901-3 D-1, ___ ___ ___
(2) annunciates. TURB BLDG HI RADIATION, is in alarm.
CUE: As the Unit NSO, inform the examinee that annunciator 901-3 D-1, TURB BLDG HI RADIATION, is in alarm.
MON until the LOW lamp is lit. SPLY AREA MON
-Slowly turns the TRIP CHECK ADJUST knob in the counter-clockwise direction until the LOW lamp on ARM 20 Trip Unit is lit.
F.1.c. Verify downscale alarm Verifies annunciator 901-3 F-1, ___ ___ ___
(1) annunciates. AREA MONITOR DOWNSCALE, is in alarm.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM RO Admin 4.doc Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE: As the Unit NSO, inform the examinee that annunciator 901-3 F-1, AREA MONITOR DOWNSCALE, is in alarm.
- F.1.d Reset ARM Trip Unit -Release TRIP CHECK ___ ___ ___
pushbutton
-Depress RESET pushbutton on ARM 20.
F.1.e Verify ARM Trip Unit resets -Verify HIGH lamp on ARM 20 ___ ___ ___
Trip Unit is NOT lit
-Verify LOW lamp on ARM 20 Trip Unit is NOT lit.
F.1.f Verify 901-3 panel -Verify annunciator 901-3 D-1 annunciators are clear. resets and clears.
-Verify annunciator 901-3 F-1 resets and clears.
CUE: As the Unit NSO, inform the examinee that annunciators 901-3 D-1, and 901-3 F-1 have reset and cleared.
EVALUATOR NOTE: The examinee should inform you the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM RO Admin 4.doc JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
ARM Trip Unit Set Point Check JPM Number: RO Admin 4 Revision Number: 00 Task Number and
Title:
SR-1800-P03 (Freq: LIC=I) Given a reactor plant, test the high and low trip levels of an ARM trip/indicating unit in accordance with QCOP 1800-01.
K/A Number and Importance: K/A: 2.3.05 Rating: 2.9/2.9 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOP 1800-01 Rev. 15, Operation of ARM Indicator/Trip Units 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)
2016 ILT NRC JPM RO Admin 4.doc INITIAL CONDITIONS
- You are the Admin NSO.
- The Post Maintenance Test (PMT) requires an operational check of the upscale and downscale set points.
- The Unit NSO will acknowledge and reset the 901-3 panel alarms.
INITIATING CUE Perform QCOP 1800-01 step F.1 for ARM 20 (1B SJAE AREA), on the 901-11 panel. Notify the Unit Supervisor when the test is complete.
SRRS: 3D.100; There are no retention requirements for this section
2016 SRO Admin 1 Rev. 02 Job Performance Measure Perform Call Out to Fill Shift Position JPM Number: 2016.SRO Admin 1 Revision Number: 02 Date: 10/02/15 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 1 of 9
2016.SRO Admin 1- Rev 02 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-AA-112-101 Rev: 11 Procedure SY-AA-102-201 Rev: 09 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.105 There are no retention requirements for this section.
Page 2 of 9
2016.SRO Admin 1- Rev 02 Revision Record (Summary)
Revision 02, Developed for 2016 ILT NRC exam. Updated to new format and procedure changes. Name changed to accurately reflect the content of the JPM.
Previous versions:
Revision 00, This JPM was developed IAW guidelines established in NUREG 1021 Rev. 9 Supplement 1, ES-301 and Appendix C. This JPM meets the criteria of ES-301 D.3 for Administrative Topics.
This JPM was developed NEW for the 2009 ILT NRC Exam.
Revision 01, Revised to incorporate procedure changes.
SRRS: 3D.105 There are no retention requirements for this section.
Page 3 of 9
2016.SRO Admin 1- Rev 02 JPM SETUP INSTRUCTIONS
- 1. This is an Administrative JPM that may be performed in any setting where the necessary procedures and support information can be provided.
- 2. Verify the following information is available for the Initiating Cue:
- The current shift schedule
- 3. Verify the following information is available for JPM performance:
- QAP 0300-03, Rev. 41, Operations Shift Staffing
- Tech Spec 5.2, Organization
- OP-AA-112-101, Rev.11, Shift Turnover and Relief
- SY-AA-102-201, Rev.9, Call-Outs for Unscheduled Work
- 4. Copy of SY-AA-102-201, Call-Outs For Unscheduled Work.
- 6. 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.
- 7. This completes the setup for this JPM.
SRRS: 3D.105 There are no retention requirements for this section.
Page 4 of 9
2016.SRO Admin 1- Rev 02 INITIAL CONDITIONS You are the Shift Manager.
Unit 1 and Unit 2 are at full power.
The STAs wife is expecting a baby. He has permission from the Operations Director to leave if necessary to join his wife.
At 0200 the STA departs the site when his wife calls him home because she has gone into labor.
There are no other STA qualified supervisors on shift.
INITIATING CUE If required, identify the staffing adjustments that need to be made, the time constraints involved and perform the callout per SY-AA-102-201, Attachment 1.
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.105 There are no retention requirements for this section.
Page 5 of 9
2016.SRO Admin 1- Rev 02 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number
0300-03 position must be staffed for staff position manning is both Units in Mode 1, 2, or 3. identified.
C.1.d
- T. S. Determine that the STA The requirement to fill the ___ ___ ___
5.2.2.b. position must be staffed in a STA staff position within 2 time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. hours is identified.
ROLE When requested, as Shift Supervisor provide a list containing the phone PLAY: numbers of the STAs available to work AND a blank copy of SY-AA-102-201.
ROLE During the simulated phone calls provide the requested information listed PLAY: below per SY-AA-102-201, Attachment 1 STA #1 Alcohol consumed in last 5 hrs? NO Are you Fit For Duty? YES Will you violate Work Hour Restrictions? NO Comment: Can report On-Site by 0500 STA #2 Alcohol consumed in last 5 hrs? NO Are you Fit For Duty? YES Will you violate Work Hour Restrictions? YES Comment: Can report On-Site by 0300 STA #3 Alcohol consumed in last 5 hrs? NO Are you Fit For Duty? YES Will you violate Work Hour Restrictions? NO Comment: Can report On-Site by 0330 SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 6 of 9
2016.SRO Admin 1- Rev 02 Comment SAT UNSAT STEP ELEMENT STANDARD Number
5.2.2.b work. vacant for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per T. S.
5.2.2.b.
ROLE As STA #3, acknowledge the request and state that you will report to work.
PLAY:
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 7 of 9
SUMMARY
Operators Name: Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Perform Call Out to Fill Shift Position JPM Number: 2016.SRO Admin 1 Revision Number: 02 Task Number and
Title:
SS-S-08 Operations Shift Staffing K/A Number and Importance: K/A: 2.1.5 Rating: 2.9*/3.9 Suggested Testing Environment: Classroom Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QAP 0300-03 Rev. 41, Operations Shift Staffing Tech Spec 5.2, Organization OP-AA-112-101 Rev. 11, Shift Turnover and Relief SY-AA-102-201 Rev. 9, Call-Outs for Unscheduled Work Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 05 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)
Page 8 of 9
INITIAL CONDITIONS You are the Shift Manager.
Unit 1 and Unit 2 are at full power.
The STAs wife is expecting a baby. He has permission from the Operations Director to leave if necessary to join his wife.
At 0200 the STA departs the site when his wife calls him home because she has gone into labor.
There are no other STA qualified supervisors on shift.
INITIATING CUE If required, identify the staffing adjustments that need to be made, the time constraints involved and perform the callout per SY-AA-102-201, Attachment 1.
SRRS: 3D.105 There are no retention requirements for this section.
2016 SRO Admin 2 Rev. 01 Exelon Nuclear Job Performance Measure Review QOS 0005-S01 for Start of Daily Refueling Activities JPM Number: SRO Admin 2 Revision Number: 01 Date: 10/3/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By: ___________________ _________
Training Supervision Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 1 of 11
2016 SRO Admin 2, Rev. 01 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 QOS 0005-S01 Rev: 182 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.105 There are no retention requirements for this section.
Page 2 of 11
2016 SRO Admin 2, Rev. 01 Revision Record (Summary)
Revision 01, Developed for 2016 ILT NRC exam. Updated from SRO-26-I use don the 2009 ILT NRC exam. Revisions included clarifying Elements and updating to the most recent revision of QOS 0005-S01.
Previous Revisions Revision 00, This JPM is developed IAW guidelines established in NUREG 1021 Rev 9 ES-301 and Appendix C. This JPM meets the criteria of Category B.1 "Control Room Systems," for RO/SRO candidates.
This is a new JPM that was developed for the 2009 NRC Initial License exam.
SRRS: 3D.105 There are no retention requirements for this section.
Page 3 of 11
2016 SRO Admin 2, Rev. 01 JPM SETUP INSTRUCTIONS
- 1. This is an Administrative JPM that may be performed in any setting where the necessary procedures and support information can be provided.
- 2. Verify the following information is available for the Initiating Cue:
- QOS 0005-S01 properly completed for the week except for following errors:
o Section 11.c. Channel count rate > 3 cps is incorrectly checked o Section 51.a.4 is inappropriately checked as completed within 7 days.
o Section 33 shows SRM Channel 23 at 2 cps on Sunday shift 3.
- 3. This completes the setup for this JPM.
SRRS: 3D.105 There are no retention requirements for this section.
Page 4 of 11
2016 SRO Admin 2, Rev. 01 INITIAL CONDITIONS You are the Unit Supervisor on Unit 1 during a refueling outage.
Today is Shift 3 on Sunday April 3rd.
Core alterations were suspended for three days during the week for scheduled outage work.
That work has been completed and the second fuel shuffle can begin.
The Mode switch is locked in REFUEL.
All control rods are fully inserted.
The Refueling cavity is flooded.
Communications have been established and tested satisfactorily earlier in the shift.
The following core alteration surveillances were completed satisfactorily:
- SRM Functional Test QCIS 0700-09; completed 3/30 at 0600 hrs. SRM signal to noise ratios are: SRM 21-15:1, SRM 22-17:1, SRM 23 -14:1, SRM 24 -12:1.
- IRM Functional Test QCIS 0700-09; completed 4/01 at 1000 hrs
- SRM/IRM Detector Not Full In Functional Test QCIS 0700-01; completed 4/02 at 1600 hrs
- Refuel interlocks operable per QCFHP 0500-08; completed 3/26 at 0400 hrs
- One Rod out Interlock operable per QCOS 0300-17; completed 4/02 at 2300 hrs INITIATING CUE Review QOS 0005-S01 Sections, 11, 16, 25, 33, 38, 39, and 51 for Start of Daily Refueling Activities.
Contact the Fuel Handling Supervisor when your review has been completed, and authorize the start of fuel moves OR state why fuel moves cannot be allowed.
(Provide prepared exam copy of QOS 0005-S01 to the examinee when the Initiating Cue is acknowledged.)
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 SRRS: 3D.105 There are no retention requirements for this section.
Page 5 of 11
2016 SRO Admin 2, Rev. 01 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.105 There are no retention requirements for this section.
Page 6 of 11
2016 SRO Admin 2, Rev. 01 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number 11 Verify SRMs are operable. Sunday Shift 3 already ___ ___ ___
completed for steps (a) and (b). Step 11.(c), SRM count rates 3 cps is CHECKED IN ERROR.
16 Ensure Reactor Water Level Sunday Shift 3 already ___ ___ ___
indications are entered and verify completed. Both readings are within 12 inches of indicators reading >60 each other. inches with Refueling cavity flooded.
25.b. Verify Rx Coolant Circulation. Sunday Shift 3 already ___ ___ ___
completed. One loop of shutdown Cooling in service.
33 Checks SRM counts and channel Sunday Shift 3 already ___ ___ ___
check within 1 decade of each completed. All channels other. are within 1 decade. May recognize that SRM 23 is reading only 2 cps.
38 Ensure Reactor Water Level Sunday Shift 3 already ___ ___ ___
indications are entered and verify completed. All 4 readings are within 12 inches of indicators reading >60 each other. inches with Refueling cavity flooded.
39 Ensure Reactor Water Level Sunday Shift 3 already ___ ___ ___
indications are entered and verify completed. All 4 readings are within 12 inches of indicators reading >60 each other. inches with Refueling cavity flooded.
51.a.1 Verify SRM Functional completed Sunday Shift 3 checked ___ ___ ___
within 7 days prior to the start of per turnover information.
core alterations.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 7 of 11
2016 SRO Admin 2, Rev. 01 Comment SAT UNSAT STEP ELEMENT STANDARD Number 51.a.2 Verify IRM Functional completed Sunday Shift 3 checked ___ ___ ___
within 7 days prior to the start of per turnover information.
core alterations.
51.a.3 Verify SRM/IRM Detector not Full Sunday Shift 3 checked ___ ___ ___
In Functional completed within 7 per turnover information.
days prior to the start of core alterations.
- 51.a.4 Verify Refueling Interlock test Recognizes Sunday Shift ___ ___ ___
completed within 7 days prior to 3 is CHECKED IN the start of core alterations. ERROR. Performance of QCFHP 0500-08 has exceeded 7 days from the given Initial Conditions.
CUE: If contacted to perform QCFHP 0500-08, as the Fuel Handling Supervisor, state: You will brief the crew and start the surveillance.
51.a.5 Verify Rx water level > 23 ft above Sunday Shift 3 checked ___ ___ ___
the top of the RPV flange. per turnover information.
51.a.6 Verify Rx Mode Switch locked in Sunday Shift 3 marked ___ ___ ___
Refuel with any control rod N/A per turnover withdrawn. information.
51.a.7 Verify One-Rod-Out interlock is Sunday Shift 3 checked ___ ___ ___
operable within 7 days prior to the per turnover information.
start of control rod withdrawal.
51.a.8 Verify Direct Communications Sunday Shift 3 checked ___ ___ ___
have been established. per turnover information.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 8 of 11
2016 SRO Admin 2, Rev. 01 Comment SAT UNSAT STEP ELEMENT STANDARD Number
detector reading of 3 cps or 0.7 3 block is CHECKED IN cps with a signal to noise ratio ERROR. SRM 23 reading 20/1 located in the core was 2 cps and signal to quadrant where Core Alterations noise ration is < 20/1 per will be performed. the turnover.
CUE: If contacted to investigate and troubleshoot SRM 23, as the Instrument Maintenance Supervisor state you will:
Prepare a package and start work as soon as possible.
51.a.10 Verify all control rods fully Sunday Shift 3 checked ___ ___ ___
inserted. per turnover information.
51.a.11 Verify withdrawn control rod Sunday Shift 3 marked ___ ___ ___
accumulator pressures >940 psig N/A per turnover once per 7 days. information.
EVALUATOR NOTE: The examinee should report to the FHS that:
- The requirements of QOS 0500-S01 are NOT satisfied and Refueling activities EXCEPT for performance of QCFHP 0500-08 are NOT authorized.
- Also, SRM 23 is inoperable, which prevents fuel movement in the associated quadrant of the core.
EVALUATOR NOTE: After acknowledging the report, the examinee should inform that the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 9 of 11
SUMMARY
Operators Name: Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Review QOS 0005-S01 for Start of Daily Refueling Activities JPM Number: 2016 SRO Admin 2 Revision Number: 01 Task Number and
Title:
SRL-805-K20 Given refueling equipment related operability status OR parameter indications, various plant conditions, and a copy of Tech Specs, DETERMINE if the Conduct of Refueling related Tech Spec LCOs have been met.
K/A Number and Importance: K/A: 2.1.36 Rating: 4.1 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s):
QOS 0005-S01, Rev 182, Operations Department Weekly Summary of Daily Surveillances 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)
Page 10 of 11
INITIAL CONDITIONS You are the Unit Supervisor on Unit 1 during a refueling outage.
Today is Shift 3 on Sunday April 3rd.
Core alterations were suspended for three days during the week for scheduled outage work.
That work has been completed and the second fuel shuffle can begin.
The Mode switch is locked in REFUEL.
All control rods are fully inserted.
The Refueling cavity is flooded.
Communications have been established and tested satisfactorily earlier in the shift.
The following core alteration surveillances were completed satisfactorily:
- SRM Functional Test QCIS 0700-09; completed 3/30 at 0600 hrs. SRM signal to noise ratios are: SRM 21-15:1, SRM 22-17:1, SRM 23 -14:1, SRM 24 -12:1.
- IRM Functional Test QCIS 0700-09; completed 4/01 at 1000 hrs
- SRM/IRM Detector Not Full In Functional Test QCIS 0700-01; completed 4/02 at 1600 hrs
- Refuel interlocks operable per QCFHP 0500-08; completed 3/26 at 0400 hrs
- One Rod out Interlock operable per QCOS 0300-17; completed 4/02 at 2300 hrs INITIATING CUE Review QOS 0005-S01 Sections, 11, 16, 25, 33, 38, 39, and 51 for Start of Daily Refueling Activities.
Contact the Fuel Handling Supervisor when your review has been completed, and authorize the start of fuel moves OR state why fuel moves cannot be allowed.
SRRS: 3D.105 There are no retention requirements for this section.
2016 SRO Admin 3 - Rev. 00 Job Performance Measure Review a Fire Impairment Permit Requiring Compensatory Actions JPM Number: 2016.SRO Admin 3 Revision Number: 00 Date: 10/5/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 1 of 10
SRO Admin 3 - 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 OP-MW-201-007 Rev: 07 Procedure QCAP 1500-01 Rev: 34 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.105 There are no retention requirements for this section.
Page 2 of 10
SRO Admin 3 - Rev 00 Revision Record (Summary)
Revision 00: Developed for 2016 ILT NRC exam. This is a modified Bank JPM. Also revised to the new template and current procedures.
AD-SRO-6 Revsions:
Revision 01, This is a LORT Bank JPM (AD-SRO-6) that was used on the 2011 ILT NRC License Exam. Updated Fire Permit information.
SRRS: 3D.105 There are no retention requirements for this section.
Page 3 of 10
SRO Admin 3 - Rev 00 SIMULATOR SETUP INSTRUCTIONS
- 1. NOTE: This JPM may be conducted in any appropriate setting; i.e., simulator, classroom, Control Room, provided that the following procedures are available to the candidate:
- OP-MW-201-007, FIRE PROTECTION SYSTEM IMPAIRMENT CONTROL
- QCAP 1500-01, ADMINISTRATIVE REQUIREMENTS FOR FIRE PROTECTION
- 2. Verify the following for this JPM setup:
- A current revision of OP-MW-201-007 Attachment 1 Fire Protection Impairment Permit is filled out as follows:
- 1) Fill out Section I Initiator: of the Fire Protection Permit as follows:
Initiator: IMD Supervisor Station: Quad Unit: 00 Name: A. Smith Phone: X 2210 Dept/Co: IMD/Exelon Sch. Start Date: current Bldg: RX EPN#:
Sch. End Date: current + 1 Elev: 595 Door #:
AR/WR/OOS#: WO 1607822 Det. Zone:
Pent #:
Do NOT check the Structural fireproofing OR Wall Penetration boxes.
Impairment
Description:
Perform QCIS 7600-04 Unit 0 Standby Diesel Generator Cardox Fire Protection Functional Test.
- 2) Fill out section II. FIRE MARSHAL REVIEW of the Fire Protection Impairment Permit as follows:
- a. Fire Zone(s): 9.3 / For Barriers: Check the Functional box.
- b. Technical Requirement Manual? Check the Yes box. QCAP 1500-01
- c. Mark None in the Fire Watch Required: block and N/A below.
- d. Check the NO box for Additional Compensatory Measures.
- e. Fire Detector Operability Check Required? Check the NO box.
- f. NEIL Notification Required? Check the NO box.
- g. Fire Marshal Instructions: Return to operable status in 14 days
- h. Restoration/Testing Requirements: Completion of Work Package. PMT per Work Package.
- i. Sign and date as Fire Marshal for Authorization Block.
- 3. This completes the setup for this JPM.
SRRS: 3D.105 There are no retention requirements for this section.
Page 4 of 10
SRO Admin 3 - Rev 00 INITIAL CONDITIONS
- You are the Operations Field Supervisor.
- An Instrument Maintenance Supervisor has submitted a fire permit to allow performance of QCIS 7600-04, Unit 0 Standby Diesel Generator Cardox Fire Protection Functional Test.
- The Instrument Maintenance Supervisor has informed you that this surveillance will render the Cardox System inoperable.
INITIATING CUE Review Fire Protection Impairment Permit 1234. Approve the permit OR explain the reason(s) why you cannot.
Provide examinee with: A copy of fire permit 1234, OP-MW-201-007, Attachment 1.
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.105 There are no retention requirements for this section.
Page 5 of 10
SRO Admin 3 - Rev 00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number Obtains Procedures. Obtains a copy of QCAP 1500- ___ ___ ___
01.
NOTE: The examinee may perform the following steps in any order.
Att. J Determines effect of Reviews QCAP 1500-01 Att. J ___ ___ ___
disabling the Cardox for 1/2 and determines 1/2 EDG Cardox EDG. is a required EFP Cardox system.
CUE: If the examinee states he cannot approve the permit because of errors, prompt him to explain all of the errors on the permit to you.
The following errors are built into the permit:
The Fire Protection Permit was filled out improperly in section II. FIRE MARSHAL REVIEW as follows:
- None is marked in the Fire Watch Required: block (should be marked hourly with performed by marked as IMD).
- NO is checked in the box for Additional Compensatory Measures (should be marked YES and a Description of the additional Compensatory Measures should be included i.e., backup suppression established or verified.)
The one detector that was chosen to make a detection system inoperable (ref. QCAP 1500-01 Attachment A page 3), and the detection system in turn makes the preaction suppression system inoperable (ref. QCAP 1500-01 Attachment C page 2).
- D.3.c.(2) Determines hourly fire watch Reviews QCAP 1500-01 step ___ ___ ___
established within one hour. D.3.c.(2) and determines an hourly fire watch must be conducted if this permit is approved.
- D.3.c.(4) Determines backup Reviews step D.3.c.(4) and ___ ___ ___
suppression required within determines backup suppression one hour. will also be required.
(page 15 of 93)
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 6 of 10
SRO Admin 3 - Rev 00 Comment SAT UNSAT STEP ELEMENT STANDARD Number Attach. 1 Determines that the Fire Recognizes the N/A is not ___ ___ ___
Watch Performed By field correct for this field.
must be filled in IMD or other appropriate department.
EVALUATOR NOTE: The examinee may choose to correct the provided impairment. This is acceptable.
Reviews the permit for The examinee reviews the ___ ___ ___
accuracy and Notifies the permit for accuracy IAW OP-Evaluator of his conclusions. MW-201-007 FIRE PROTECTION SYSTEM IMPAIRMENT CONTROL step 4.4 and determines the fire impairment permit cannot be approved as written because the Fire Protection Permit was filled out improperly in section II.
FIRE MARSHAL REVIEW None is marked in the Fire Watch Performed By: block (should be marked YES and a Description of the additional Compensatory Measures should be included i.e., backup suppression required).
CUE: After the examinee explains why he cannot approve the fire permit as written, as the IM Supervisor requesting the permit state that:
You will rewrite the permit and bring it back for approval on the next shift.
EVALUATOR NOTE: The examinee should inform you that the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 7 of 10
SUMMARY
Operators Name: Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Review a Fire Impairment Permit Requiring Compensatory Actions JPM Number: SRO Admin 3 Revision Number: 00 Task Number and
Title:
S-4100-K32 (Freq: LIC=B) Given Fire Protection Systems operability status OR key parameter indications, various plant conditions and a copy of QCAP 1500-01, ANALYZE Fire Protection administrative operability requirements and DETERMINE required compensatory actions and reporting requirements, if any.
K/A Number and Importance: K/A: 2.1.25 Rating: 3.9/4.2 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCAP 1500-01, Administrative Requirements For Fire Protection, Rev. 34 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: 12.5 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)
Page 8 of 10
INITIAL CONDITIONS
- You are the Operations Field Supervisor.
- An Instrument Maintenance Supervisor has submitted a fire permit to allow performance of QCIS 7600-04, Unit 0 Standby Diesel Generator Cardox Fire Protection Functional Test.
- The Instrument Maintenance Supervisor has informed you that this surveillance will render the Cardox System inoperable.
INITIATING CUE Review Fire Protection Impairment Permit 1234. Approve the permit OR explain the reason(s) why you cannot.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 SRO Admin 4 Rev. 00 Job Performance Measure Determine Status of the Service Water Radiation Monitor JPM Number: 2016 SRO Admin 4 Revision Number: 00 Date: 10/05/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date Page 1 of 9
2016 SRO Admin 4, 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 QCOS 1700-04 Rev: 13 Procedure QCAN 901(2)-3 G-2 Rev: 05 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.105 There are no retention requirements for this section.
Page 2 of 9
2016 SRO Admin 4, Rev. 00 Revision Record (Summary)
Revision 00, Developed for 2016 ILT NRC exam.
SRRS: 3D.105 There are no retention requirements for this section.
Page 3 of 9
2016 SRO Admin 4, Rev. 00 SIMULATOR SETUP INSTRUCTIONS This is an Admin JPM. It may be conducted in a variety of settings, provided the needed reference material is available.
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.
This completes the setup for this JPM.
SRRS: 3D.105 There are no retention requirements for this section.
Page 4 of 9
2016 SRO Admin 4, Rev. 00 INITIAL CONDITIONS You are the Unit 1 Unit Supervisor.
Main Control Room annunciator 901-3 G-2 is in alarm.
An EO has been dispatched and has reported MCC 17-1-1 breaker 18 is ON.
A Chemistry Technician has been dispatched and reports:
Low flow confirmed via sight glass FI 1-1741-25.
1-3999-542, SERVICE WATER RADIATION MONITOR INLET ISOLATION VALVE verified OPEN EDUCTOR INLET PRESSURE is 15 psig OUTLET PRESSURE is 3 psig.
INITIATING CUE Based on the field reports, determine the status of the Service Water Radiation Monitor.
Complete any required paper work and forward to the Shift Manager for 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.105 There are no retention requirements for this section.
Page 5 of 9
2016 SRO Admin 4, Rev. 00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number QCAN Verify EDUCTOR INLET Directs actions per QCAN to ___ ___ ___
901(2)- PRESSURE is 25-35 psig correct abnormal eductor 3 G-2 pressure.
AND 1.c OUTLET PRESSURE is 5-10 psig.
EVALUATOR NOTE: Provide a copy of QCAN 901(2)-3 G-2 when located by the examinee.
CUE: Throttling of the 1-1799-201 and 1-3999-545 has had no effect on pressures.
EDUCTOR INLET PRESSURE is 15 psig EDUCTOR OUTLET PRESSURE is 3 psig.
- QCAN Evaluates operability of the Determines Service Water ___ ___ ___
901(2)- Service Water Radiation Radiation Monitor is INOP.
3 G-2 Monitor AND 3 Refers to QCOS 1700-04 EVALUATOR NOTE: Provide a copy of QCOS 1700-04 when located by the examinee.
H.1.a H.1. Record the following Records the following ___ ___ ___
information on Attachment A. information on Attachment A:
- a. Unit Number, date, time, and Issue Report number, if applicable.
CUE: IR will be prepared by the Unit 2 Unit Supervisor.
H.1.b H.1. Record the following Records the following ___ ___ ___
information on Attachment A. information on Attachment A:
- b. Instrument being declared inoperable and the date/time of being declared inoperable.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 6 of 9
2016 SRO Admin 4, Rev. 00 Comment SAT UNSAT STEP ELEMENT STANDARD Number EVALUATOR NOTE: Current date and time are acceptable.
H.1.c H.1. Record the following Records the following ___ ___ ___
information on Attachment A. information on Attachment A:
- c. Reason for inoperability.
- H.1.d Records information on Records the following ___ ___ ___
Attachment A. information on Attachment A:
- d. Date and time 30 days from time that instrument was declared inoperable.
- H.2 Notify Chemistry to perform Notifies Chemistry ___ ___ ___
LCO requirements per CY- AND QC-130-650, and record on Attachment A. Records the date, time, and person contacted CUE: As Chemistry contact A. Smith, acknowledge the report.
H.3 Review outage report actions Forwards the Outage Report to ___ ___ ___
for accuracy. the Shift Manager for review CUE: As the Shift Manager, I will review the Outage Report.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 7 of 9
SUMMARY
Operators Name: Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Determine Status of the Service Water Radiation Monitor JPM Number: 2016 SRO Admin 4 Revision Number: 00 Task Number and
Title:
S-1701-K41 (Freq: LIC=B) Given Process Radiation Monitoring System operability status OR key parameter indications, various plant conditions and a copy of the Offsite Dose Calculation Manual (ODCM), DETERMINE if ODCM operability requirements are met and required actions, if any.
K/A Number and Importance: K/A: 272000 K3.01 Importance: 3.2/3.8 Suggested Testing Environment: Simulator/Classroom Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCAN 901(2)-3 G-2 Rev. 5, QCOS 1700-04 Rev. 13 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)
Page 8 of 9
2016 SRO Admin 4, Rev. 00 INITIAL CONDITIONS You are the Unit 1 Unit Supervisor.
Main Control Room annunciator 901-3 G-2 is in alarm.
An EO has been dispatched and has reported MCC 17-1-1 breaker 18 is ON.
A Chemistry Technician has been dispatched and reports:
Low flow confirmed via sight glass FI 1-1741-25.
1-3999-542, SERVICE WATER RADIATION MONITOR INLET ISOLATION VALVE verified OPEN EDUCTOR INLET PRESSURE is 15 psig OUTLET PRESSURE is 3 psig.
INITIATING CUE Based on the field reports, determine the status of the Service Water Radiation Monitor.
Complete any required paper work and forward to the Shift Manager for review.
SRRS: 3D.105 There are no retention requirements for this section.
Page 9 of 9
2016 SRO Admin 5 - Rev. 00 Job Performance Measure Determine Protective Action Recommendations (PARS)
JPM Number: 2016 SRO Admin 5 Revision Number: 00 Date: 10/05/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 1 of 11
2016 SRO Admin 5 - 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 EP-MW-114-100 Rev: 16 Procedure EP-AA-111-F-06 Rev: G Procedure EP-AA-1006 Add. 3 Rev: 01
________ 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.105 There are no retention requirements for this section.
Page 2 of 11
2016 SRO Admin 5 - Rev 00 Revision Record (Summary)
Revision 00: Developed for 2016 NRC ILT Exam. Based on 2012 NRC Exam JPM. This JPM is new as it changes the Initial Conditions and the PARs flow chart was radically changed from the one used in the 2012 JPM.
SRRS: 3D.105 There are no retention requirements for this section.
Page 3 of 11
2016 SRO Admin 5 - Rev 00 SIMULATOR SETUP INSTRUCTIONS Provide examinee with:
1.) Utility Message #1 NARS form completed as follows:
Utility Message 1 State Message N/A Block #1. Status = Drill/Exercise Block #2. Station = Quad Cities Block #3. Onsite Condition = Site Area Emergency Block #4. Accident Classified: Time = T0 -30 minutes Date = today EAL# = FS1 Block #4. Accident Terminated: Time:=N/A, Date:=N/A Block #5. Release Status = None Block #6. Type of Release = N/A Block #7. Wind Direction = 180 degrees Block #8. Wind Speed: Meters/Sec = 2.24 Miles/Hr = 5.0 Block #9. Recommended Actions = None Block #10. Additional Information = None Verified with [provide signature]
Approved by [provide SM signature]
Block #11 Transmitted By [provide name] Phone Number [309-227-2210]
Time/Date T0 -20 minutes/Today Block #12 Received By [provide name] Organization =
IEMA, Time/Date: T0 -20 minutes/Today Initial and Final blocks checked for Quad Cities NARS Code 43 Initial Roll Call complete block on back Time/Date T0 -18 minutes/Today 2.) A marked up Hot EAL Board with the condition for a General Emergency circled.
SRRS: 3D.105 There are no retention requirements for this section.
Page 4 of 11
2016 SRO Admin 5 - Rev 00 INITIAL CONDITIONS Unit 1 was operating at 100% rated power when a transient occurred that caused an automatic scram.
The Emergency Plan was activated and a Site Area Emergency (FS1) was classified 30 minutes ago due to high Drywell radiation of 700 R/hr.
20 minutes ago Transmission of NARS (Utility Message #1) was completed (see attached)
All plant personnel have been notified of the classification level, reason for the classification, and the TSC and OSC have been activated.
The TSC is NOT at minimum staffing and the TSC has NOT assumed Command and Control.
The Shift Communicator has performed Emergency Response Organization (ERO),
Emergency Notification System (ENS), and Emergency Response Data System (ERDS) activation, and the NARS notification.
The Shift Emergency Director has upgraded the classification to a General Emergency (FG1) based on:
o Loss of RCS (DW Radiation >100R/hr) o Loss of Fuel Clad (DW Radiation >6.65E+02 R/hr) o Potential Loss of Containment (DW Radiation >1.55E+03 R/hr)
There has been NO Change in release status, or meteorological data since message #1 was sent T0 is the current time. T0 is _______ (Use the Simulator Clock)
THIS IS AN EXERCISE THIS JPM IS TIME CRITICAL INITIATING CUE As the Shift Emergency Director, prepare the necessary form(s) that would allow the Shift Communicator to complete the required State and Local notifications.
Provide examinee with:
- A copy of EP-MW-114-100-F01 Nuclear Accident Reporting System (NARS)
Form Utility Message #1 form completely filled out as a Site Area Emergency
- EP-MW-114-100 Midwest Region Off-Site Notifications
- A blank copy of EP-MW-114-100-F01 Nuclear Accident Reporting System (NARS) Form
- EP-AA-111-F-06 Rev G, Quad Cities Plant Based PAR Flowchart.
SRRS: 3D.105 There are no retention requirements for this section.
Page 5 of 11
2016 SRO Admin 5 - Rev 00 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.105 There are no retention requirements for this section.
Page 6 of 11
2016 SRO Admin 5 - Rev 00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number EVALUATOR NOTE: The following step (NARs completion) must be completed within 15 minutes from the time the examinee acknowledges the initiating cue.
NARS Fills out Utility Message Records Utility Message #2. ___ ___ ___
form Number.
NARS Fills out State Message Records N/A for State Message ___ ___ ___
form Number. Number.
Block #1 Fills out block #1 information Records [B] Drill/Exercise in ___ ___ ___
regarding Status. block #1.
- Block #2 Fills out block #2 information Records [F] Quad Cities in block ___ ___ ___
regarding Station. #2.
- Block #3 Fills out block #3 information Records [D] General ___ ___ ___
regarding onsite condition. Emergency.
- Block #4 Fills out block #4 information Records Accident Classification ___ ___ ___
regarding Accident Classified as
& Accident Terminated. Time= Classification time Date= todays date EAL=FG1 Records N/A for Accident Terminated in Time and Date space.
Block #5 Fills out block #5 information Records [A] None. ___ ___ ___
regarding Release Status.
Block #6 Fills out block #6 information Records [A] N/A. ___ ___ ___
regarding Type of Release.
CUE: If the examinee inquires about the current meteorological conditions, state:
Meteorological conditions have not changed.
- Block #7 Fills out block #7 information Records 180 degrees. ___ ___ ___
regarding Wind Direction.
- Block #8 Fills out block #8 information Records [A] Meters/Sec = 2.24 ___ ___ ___
regarding Wind Speed. and [B] Miles/Hr = 5.0 SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 7 of 11
2016 SRO Admin 5 - Rev 00 Comment SAT UNSAT STEP ELEMENT STANDARD Number Refers to EP-AA-111-F-06, Obtains and uses EP-AA-111-F- ___ ___ ___
Quad Cities PAR Flow 06, Page 1 Initial Protective Chart, to determine proper Action Recommendation ONLY PARs. to determine:
- Classification is General Emergency? = Yes
- Is this the Initial PAR? =
Yes
- Is there a Loss of Primary Containment? = No
- Is there a Hostile Action event in progress? = No
- Is the PAR being made from the Control Room =
Yes
- Block #9 Fills out block #9 information Utilizes EP-AA-111-F-06, Quad ___ ___ ___
regarding Recommended Cities PAR Flow Chart, and Actions. determines PARs of Evacuate per Table 3 (below)
[D] Illinois sub-areas 1,2
[E] Iowa sub-areas 1,2,3,5 Records the information on the NARS form Block Fills out block #10 information Records NONE. ___ ___ ___
- 10 regarding Additional Information.
NARS Submits NARS form for Submits NARS form for ___ ___ ___
form verification. verification.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 8 of 11
2016 SRO Admin 5 - Rev 00 Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE: When the examinee submits the NARS form for verification, sign the form on the Verified With line, and state: The verification is complete, and return the form to the examinee.
NARS Signs on the Approved By Submits NARS form for form line and submits NARS form transmittal for transmittal.
CUE: Acting as the Shift Communicator, when the examinee submits the NARS form for transmittal, state:
I will transmit it immediately.
Inform the examinee the task is complete.
EVALUATOR NOTE: The examinee must have submitted form filled out for transmittal no later than 15 minutes after classification of the event.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 9 of 11
SUMMARY
Operators Name: Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Determine Protective Action Recommendations (PARS)
JPM Number: 2016 SRO Admin 5 Revision Number: 00 Task Number and
Title:
S-EP-P02 (Freq: LIC=A) (ILT-MP): Given an event, determine the public Protective Action Recommendation in accordance with EP-AA-111.
K/A Number and Importance: K/A: 2.4.44 Rating: 4.4 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): EP-AA-111-F-06 Rev G, QUAD CITIES PLANT BASED PAR FLOWCHART.
EP-AA-1006 Addendum 3, Rev. 1, QUAD CITIES STATION ANEX.
EP-MW-114-100 Rev. 16, MIDWEST REGION OFFSITE NOTIFICATIONS EP-MW-114-100-F-01, Rev. H, NUCLEAR ACCIDENT REPORTING SYSTEM (NARS) FORM Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 Minutes to Notify 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)
Page 10 of 11
INITIAL CONDITIONS Unit 1 was operating at 100% rated power when a transient occurred that caused an automatic scram.
The Emergency Plan was activated and a Site Area Emergency (FS1) was classified 30 minutes ago due to high Drywell radiation of 700 R/hr.
20 minutes ago Transmission of NARS (Utility Message #1) was completed (see attached)
All plant personnel have been notified of the classification level, reason for the classification, and the TSC and OSC have been activated.
The TSC is NOT at minimum staffing and the TSC has NOT assumed Command and Control.
The Shift Communicator has performed Emergency Response Organization (ERO),
Emergency Notification System (ENS), and Emergency Response Data System (ERDS) activation, and the NARS notification.
The Shift Emergency Director has upgraded the classification to a General Emergency (FG1) based on:
o Loss of RCS (DW Radiation >100R/hr) o Loss of Fuel Clad (DW Radiation >6.65E+02 R/hr) o Potential Loss of Containment (DW Radiation >1.55E+03 R/hr)
There has been NO Change in release status, or meteorological data since message #1 was sent.
T0 is the current time. T0 is _______ (Use the Simulator Clock)
THIS IS AN EXERCISE THIS JPM IS TIME CRITICAL INITIATING CUE As the Shift Emergency Director, prepare the necessary form(s) that would allow the Shift Communicator complete the required State and Local notifications.
SRRS: 3D.105 There are no retention requirements for this section.
Page 11 of 11
Exelon Nuclear Job Performance Measure Perform One-Rod-Out Interlock Surveillance JPM Number: 2016 ILT NRC JPM a Revision Number: 01 Date: 09/29/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date 2016 ILT NRC JPM a SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 1 of 10
2016 ILT NRC JPM a - Rev 01 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 QCOS 0300-17 Rev: 12 Procedure QCOP 0207-02 Rev: 11 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 2016 ILT NRC JPM a SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 2 of 10
2016 ILT NRC JPM a - Rev 01 Revision Record (Summary)
Revision 00, This JPM was developed new for the 2011 ILT NRC Exam.
Revision 01, This JPM was revised for the 2016 ILT NRC Exam. Originally titled JPM LS-078-I. Designated step to verify ROD OUT BLOCK annunciator does not clear as critical.
2016 ILT NRC JPM a SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 3 of 10
2016 ILT NRC JPM a - Rev 01 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the Simulator to IC 8.
(Any Shutdown IC in which the Mode Switch can be placed in REFUEL)
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. Go to RUN.
- 3. Lock the Mode Switch in REFUEL.
- 4. Verify the RWM is NOT bypassed.
- 5. Cycle the Rod Select Power Switch to verify no rod is selected. Leave switch in OFF.
- 6. Verify the REFUEL PERMIT light is ON.
- 7. Verify ROD OUT BLOCK annunciator (901-5, C-3) is ON.
- 8. Acknowledge annunciators as necessary.
- 9. Provide a current revision of the following procedures, signed off as follows:
- QCOS 0300-17 o Initial steps D.1 thru D.7, N/A steps D.8-D.9, Initial steps D.10-D.11.
o Steps H.4.b and H.11.b marked N/A.
- QCOP 0207-02 with Prerequisite C.1 signed off and C.2 marked N/A.
- 10. Provide Equipment Status Tag filled out as follows:
- Rod Worth Minimizer in Bypass
- 11. 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.
- 12. This completes the setup for this JPM.
2016 ILT NRC JPM a SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 4 of 10
2016 ILT NRC JPM a - Rev 01 INITIAL CONDITIONS Preparations are being made to begin refueling operations.
The Mode Switch is locked in REFUEL.
All Prerequisites have been completed for QCOS 0300-17, One-Rod-Out Interlock Surveillance.
The Unit Supervisor has reviewed steps of QCOS 0300-17 and identified the Not-Applicable (N/A) steps.
All QCOP 0207-02 prerequisites have been completed for bypassing the Rod Worth Minimizer (RWM).
The Equipment Status Tag has been prepared.
INITIATING CUE Perform the One-Rod-Out Interlock Surveillance, QCOS 0300-17.
EVALULATOR: Provide the prepared support material:
- QCOS 0300-17
- QCOP 0207-02
- Equipment Status Tag 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.
2016 ILT NRC JPM a SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 5 of 10
2016 ILT NRC JPM a - Rev 01 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number H.1 QCOP 0207-02 referenced for Bypass the RWM per QCOP ___ ___ ___
bypassing RWM. 0207-02.
QCOP Initial the reason that the RWM Initials step F.1. f. (Performing a ___ ___ ___
0207-02 is being bypassed. Procedure or Test which F.1.f specifically references bypassing the RWM).
QCOP Fills in Procedure/Test # and Fill in Procedure# as QCOS ___ ___ ___
0207-02 Step#. 0300-17 and Step# as H.1.
F.1.f (1)/(2)
QCOP Attaches the Equipment Status Attaches the prepared ___ ___ ___
0207-02 Tag to the ROD MOVEMENT Equipment Status Tag to the F.2.a CONT SWITCH. ROD MOVEMENT CONT SWITCH on the 901-5 panel.
QCOP RWM MODE SELECT switch Places the RWM MODE ___ ___ ___
0207-02 selected to BYPASS. SELECT switch to BYPASS and
- F.2.b records the date and time.
EVALUATOR NOTE: The ROD OUT BLOCK annunciator will clear when a rod is selected.
- H.2 Select a Control Rod. Selects a peripheral Control ___ ___ ___
Rod.
H.3 Rod Out Permit light is Verify Rod Out Permit light is ___ ___ ___
verified ON. lit on the 901-5 panel.
- H.4.a Withdraw the selected Control Withdraws the selected Control ___ ___ ___
Rod. Rod one (1) notch.
- H.5 ROD SELECT POWER switch Turn ROD SELECT POWER ___ ___ ___
placed in OFF. switch to OFF.
2016 ILT NRC JPM a SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 6 of 10
2016 ILT NRC JPM a - Rev 01 Comment SAT UNSAT STEP ELEMENT STANDARD Number EVALUATOR NOTE: The ROD OUT BLOCK annunciator will alarm when the Rod Select Power switch is placed to OFF.
- H.6 ROD SELECT POWER switch Turn ROD SELECT POWER ___ ___ ___
placed in ON. switch to ON.
- H.7 Select a second Control Rod. Selects a peripheral Control ___ ___ ___
Rod on the opposite side of the core.
- H.8 Verifies Control Rod Verifies annunciator 901-5 C-3, ___ ___ ___
withdrawal block can NOT be ROD OUT BLOCK cannot be cleared. cleared by depressing the annunciator RESET pushbutton OR the alarm is NOT in reflash.
H.9 ROD SELECT POWER switch Turn ROD SELECT POWER ___ ___ ___
placed in OFF. switch to OFF.
H.10 ROD SELECT POWER switch Turn ROD SELECT POWER ___ ___ ___
placed in ON. switch to ON.
H.11.a Withdrawn Control Rod fully Inserts the withdrawn Control ___ ___ ___
inserted. Rod to Position 00 using the ROD MOVEMENT CONT switch.
CUE: As Unit Supervisor, inform the examinee that:
Another NSO will perform step H.12.
EVALUATOR NOTE: The examinee should inform you that the task is complete.
EVALUATOR NOTE: Remove the Equipment Status Tag from the Rod Motion Control Switch at the end of the JPM.
JPM Stop Time:
2016 ILT NRC JPM a SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 7 of 10
2016 ILT NRC JPM a - Rev 01 JPM
SUMMARY
Operators Name: Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Perform One-Rod-Out Interlock Surveillance JPM Number: 2016 ILT NRC JPM a Revision Number: 01 Task Number and
Title:
SR-0280-K20, Given a Reactor Manual Control System (RMCS)/ Rod Position Information System (RPIS) operating mode and various plant conditions, EVALUATE the following Reactor Manual Control System (RMCS)/Rod Position Information System (RPIS) indications/responses and DETERMINE if the indication/ response is expected and normal:
- c. Movement control Indicating lights, (1) Rod Out Permissive
- e. Refuel Permissive K/A Number and Importance: KA: 2.1.44 Rating: 3.9/3.8 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOS 0300-17, Rev. 12, One-Rod-Out Interlock Surveillance QCOP 0207-02, Rev. 11, Rod Worth Minimizer Bypass Control 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
The task is successfully completed when the examinee demonstrates the One-Rod Out Interlock is functional by operating the RMCS and RWM in accordance with QCOS 0300-17.
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)
Page 8 of 10
INITIAL CONDITIONS Preparations are being made to begin refueling operations.
The Mode Switch is locked in REFUEL.
All Prerequisites have been completed for QCOS 0300-17, One-Rod-Out Interlock Surveillance.
The Unit Supervisor has reviewed steps of QCOS 0300-17 and identified the Not-Applicable (N/A) steps.
All QCOP 0207-02 All Prerequisites have been completed for bypassing the Rod Worth Minimizer (RWM).
The Equipment Status Tag has been prepared.
INITIATING CUE Perform the One-Rod-Out Interlock Surveillance, QCOS 0300-17.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Exelon Nuclear Job Performance Measure Injecting Standby Coolant (Engineered Safety Feature)
JPM Number: 2016 ILT NRC JPM b Revision Number: 00 Date: 10/02/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM b-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 QCOP 3200-09 Rev: 17 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.105 There are no retention requirements for this section.
2016 ILT NRC JPM b-Rev 00 Revision Record (Summary)
Revision 00, Developed for the 2016 ILT NRC Exam IAW NUREG 1021 Rev. 10 SRRS: 3D.105 There are no retention requirements for this section.
2016 ILT NRC JPM b-Rev 00 SIMULATOR SETUP INSTRUCTIONS
- 1. RESET the Simulator to IC-20.
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. OVERRIDE the 1A FR ISOL VLV closed light OFF: ior lohs13206a1 off
- 3. OVERRIDE both CCST level indications to 2.0 feet:
ior aoli033403 2 ior aoli033404 2
- 4. OVERRIDE the HW Level Control Switch to HAND: ior dihs13340108 hand
- 5. VERIFY the HW Level Control Switch in AUTO.
- 6. DIAL NORM COND REJ (AO 1-3303) to 0%.
- 7. DIAL EMERG COND REJ (AO 1-3304) to 0%.
- 8. Place the 1B Cond Makeup Pump in PTL.
- 9. VERIFY at least one Service Water pump is operating.
- 10. OVERRIDE LFFRV SLOW/FAST OPEN pushbuttons OFF:
ior difc10643ios off ior difc10643iof off
imf cs01a (trip 1A CS pump) imf cs01b (trip 1B CS pump) irf rh22br open (open breaker for RHR 29B vlv)
- 12. Trip Latch the HPCI turbine.
- 13. Inhibit ADS.
- 14. Insert a manual reactor scram, place the Mode Switch to Shutdown, and allow RPV water level to stabilize.
- 15. Close the 1A FW REG ISOL valve.
- 16. TRIP ALL RFPs and verify discharge valves MO 1-3201A/B/C are OPEN.
- 17. VERIFY 1B FW REG ISOL valve is OPEN.
- 19. VERIFY ONLY the 1B and 1C Condensate/Condensate Booster pumps are operating.
Adjust AO 1-3401 accordingly to maintain pump amps in the green band.
SRRS: 3D.105 There are no retention requirements for this section.
2016 ILT NRC JPM b-Rev 00 SIMULATOR SETUP INSTRUCTIONS
- 20. Verify ONLY 3 Condensate Demins are on-line.
- 21. Set trigger for 1B FRV lockup when the valve opens with the following commands:
trgset 1 fwv1642b.gt.0.02 trg 1 imf fw08b
- 22. Set trigger to RESET the 1B FRV lockup when the RESET pushbutton is depressed with the following:
trgset 2 zdihs10640303b trg 2 dmf fw08b
- 23. INSERT a 0.5% break in the 1A Recirc pump discharge pipe: imf rr11a 0.5.
- 24. Verify RPV water level lowers to < -142 in.
- 25. Open all 5 ADS valves and leave switches in MAN.
- 27. Hang OOS tags on:
a) 1A FW REG ISOL valve b) 1A FRV Controller
- 28. OPEN SimView and set variable cnmliq = 250000. Verify Hotwell level is approx. 14 in.
- 29. Acknowledge annunciators.
- 30. Take a snapshot or save to any open IC.
- 31. 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.
- 32. This completes the setup for this JPM.
SRRS: 3D.105 There are no retention requirements for this section.
2016 ILT NRC JPM b-Rev 00 INITIAL CONDITIONS Unit 1 was operating at 50% power with the 1A FRV OOS when a large LOCA occurred.
QGA 100 and QGA 200 actions are ongoing.
The US has determined that Alternate Injection Systems are needed to restore RPV water level.
Hotwell makeup sources are currently inadequate for continued use of the Condensate System as an RPV injection source.
INITIATING CUE Initiate Standby Coolant in accordance with QCOP 3200-09 and maximize injection.
Report to the Unit Supervisor when the Condensate System is injecting.
Provide examinee with: A blank copy of QCOP 3200-09.
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.105 There are no retention requirements for this section.
2016 ILT NRC JPM b-Rev 00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number F.2.a Verify at least one Service Verifies at least one Service ___ ___ ___
Water Pump operating. Water Pump is operating by observing indications on the 912-1 panel.
- F.2.b Open MO 1-3303, COND Places the switch for the MO 1- ___ ___ ___
DEMIN BYPASS VLV. 3303 valve to the OPEN position and verifies:
- OPEN light lit
- CLOSED light out
- F.2.c Open MO 1-3901, STNBY Places the switch for the MO 1- ___ ___ ___
COOLNT SPLY VLV. 3901 valve to the OPEN position and verifies:
- OPEN light lit
- CLOSED light out
- F.2.d Open MO 1-3902, STNBY Places the switch for the MO 1- ___ ___ ___
COOLNT SPLY VLV. 3902 valve to the OPEN position and verifies:
- OPEN light lit
- CLOSED light out F.2.e Manually control Condenser Monitors Hotwell level on ___ ___ ___
Hotwell level between 30 Recorder 1-3340-6 on the 901-7 inches and 50 inches by panel and reports when Hotwell operation of MO 1-3901. level is rising.
F.3 Verify two For the 1B and 1C Cond/Cond ___ ___ ___
Condensate/Condensate Booster Pumps, verifies:
Booster Pumps are operating. - ON lights lit
- Current indicating EVALUATOR NOTE: Step F.4 is N/A, RPV pressure is < 300 psig.
SRRS: 3D.105 (when used for operator initial or continuing training)
2016 ILT NRC JPM b-Rev 00 Comment SAT UNSAT STEP ELEMENT STANDARD Number F.5 Verify OPEN a RFP Discharge Verifies open at least one, MO Valve. 1-3201A/B/C, RFP DISCH ___ ___ ___
VLV,s:
- OPEN light lit
- CLOSED light out F.6 Verify OPEN a RX FW Inlet Verifies at least one MO 1-Valve. 3205A/B RX FW INLT VLV is ___ ___ ___
open:
- OPEN light lit
- CLOSED light out EVALUATOR NOTE: If the examinee performs step F.7 using the LLFRV for injection, the valve will NOT open. Both pushbuttons, OPEN FAST and OPEN SLOW, will NOT function.
F.8 Verify OPEN the 1B FW Verifies MO 1-3206B, 1B FW Regulator Isolation Valve. REG ISOL VLV is open: ___ ___ ___
- OPEN light lit
- CLOSED light out F.8.a. Regulate flow through the 1B At the 1-640-19B, 1B (2) Feedwater Regulating Station. FEEDWATER MAN/AUTO CONT STA:
(1) Depresses the MAN pushbutton ___ ___ ___
(2) Depresses the OPEN SLOW/FAST pushbutton ___ ___ ___
OR (1) At the 1-640-18, RX LVL ___ ___ ___
MASTER CONTLR, verifies setpoint.
(2) At the 1-640-19B, depresses the AUTO ___ ___ ___
pushbutton SRRS: 3D.105 (when used for operator initial or continuing training)
2016 ILT NRC JPM b-Rev 00 Comment SAT UNSAT STEP ELEMENT STANDARD Number EVALUATOR NOTE: When the 1B FRV begins to open, it will lock-up causing:
- Annunciator 901-5 H-8 to alarm
ALTERNATE PATH STARTS HERE
901-5 least 5 seconds and verifies:
H-8)
- Alarm 901-5 H-8 resets
- RESET pushbutton backlight goes out
- F.8.a. Regulate flow through the 1B At the 1-640-19B, 1B (2) Feedwater Regulating Station. FEEDWATER MAN/AUTO CONT STA:
(1) Depresses the MAN pushbutton ___ ___ ___
(2) Depresses the OPEN SLOW/FAST pushbutton OR (1) At the 1-640-18, RX LVL ___ ___ ___
MASTER CONTLR, verifies setpoint (2) At the 1-640-19B, depresses the AUTO pushbutton CUE: As the Unit Supervisor, when the lockup is reset, and the valve opened further state:
Another NSO will monitor RPV water level and regulate flow EVALUATOR NOTE: The examinee should inform you that the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when used for operator initial or continuing training)
2016 ILT NRC JPM b-Rev 00 SRRS: 3D.105 (when used for operator initial or continuing training)
SUMMARY
Operators Name: Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Injecting Standby Coolant JPM Number: 2016 ILT NRC JPM b Revision Number: 00 Task Number and
Title:
SR-3900-P03 (Freq: LIC=A) (ILT-MP): Given a reactor plant QGA condition requiring the use of Standby Coolant, supply water to the reactor vessel using Standby Coolant as the water source in accordance with QCOP 3200-09.
K/A Number and Importance: K/A: 256000 A2.06 Rating: 3.2/3.2 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOP 3200-09 Rev. 17, EMERGENCY REACTOR VESSEL LEVEL CONTROL USING CONDENSATE/FEEDWATER OR STANDBY COOLANT SUPPLY QCAN 901(2)-5 H-8 Rev. 7, 1 (2) B FEEDWATER ACTUATOR TROUBLE 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 used for operator initial or continuing training)
2016 ILT NRC JPM b-Rev 00 INITIAL CONDITIONS Unit 1 was operating at 50% power with the 1A FRV OOS when a large LOCA occurred.
QGA 100 and QGA 200 actions are ongoing.
The US has determined that Alternate Injection Systems are needed to restore RPV water level.
Hotwell makeup sources are currently inadequate for continued use of the Condensate System as an RPV injection source.
INITIATING CUE Initiate Standby Coolant in accordance with QCOP 3200-09 and maximize injection.
Report to the Unit Supervisor when the Condensate System is injecting.
SRRS: 3D.105 There are no retention requirements for this section.
2016 ILT NRC JPM c Exelon Nuclear Job Performance Measure Control Reactor Pressure using the Main Steam Line Drains JPM Number: 2016 ILT NRC JPM c Revision Number: 00 Date: 10/02/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM c 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 QCOP 0250-05 Rev: 06 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
2016 ILT NRC JPM c Revision Record (Summary)
Revision 00, Developed for the 2016 ILT NRC Exam.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM c SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC-17 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. Manual Actuations:
Insert a manual reactor scram Place the Mode Switch in Shutdown Allow RPV level to stabilize at +30 in.
Close the Inboard and Outboard MSIVs.
Place the RWCU system in Reject Mode with both pumps on at 80 gpm, (FCV 1-1239 approx. 15% open).
- 3. Malfunctions:
None
- 4. Remotes:
None
- 5. Overrides:
None
- 6. 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.
- 7. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM c INITIAL CONDITIONS The Unit has been SCRAMMED due to an Instrument Air leak in the Reactor Building.
The Unit Supervisor has directed actions of QOA 4700-06, Loss of Instrument Air, and attempts to isolate the leak are still in progress.
The Unit Supervisor has entered QGA 100 and has directed a cooldown at < 100°F/hr using RCIC and the Main Steam Line Drains.
An Extra NSO has been assigned to monitor and record the RPV cooldown per QCOS 0201-02.
This JPM is NOT time critical.
INITIATING CUE Initiate an RPV cooldown at < 80°F/hr using the Main Steam Line Drains and the Main Turbine Bypass valves per QCOP 0250-05.
Provide examinee with: A copy of QCOP 0250-05, with step C.1 marked N/A and initialed by the Unit Supervisor.
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
2016 ILT NRC JPM c JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number F.1. Initiate QCOS 0201-02. Verifies surveillance is in ___ ___ ___
progress per Initial Conditions.
. ISOL VLV the OPEN position and verifies:
-Red light lit
-Green light out
. ISOL VLV the OPEN position and verifies:
-Red light lit
-Green light out
- F.2.c Open MO 1-220-3, OUTSIDE Places and holds the C/S for ___ ___ ___
. DRN VLV MO 1-220-3 to the OPEN position and verifies:
-Red light lit
-Green light out
- F.2.d Open MO 1-220-90A, STM Places and holds C/S for MO 1- ___ ___ ___
LINE DRN VLV 220-90A in the OPEN position and verifies:
-Red light lit
-Green light out
- F.2.e Open MO 1-220-90B, STM Places and holds C/S for MO 1- ___ ___ ___
LINE DRN VLV 220-90B in the OPEN position and verifies:
-Red light lit
-Green light out SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM c Comment SAT UNSAT STEP ELEMENT STANDARD Number
- F.2.f Open MO 1-220-90C, STM Places and holds C/S for MO 1- ___ ___ ___
LINE DRN VLV 220-90C in the OPEN position and verifies:
-Red light lit
-Green light out
- F.2.g Open MO 1-220-90D, STM Places and holds C/S for MO 1- ___ ___ ___
LINE DRN VLV 220-90D in the OPEN position and verifies:
-Red light lit
-Green light out EVALUATOR NOTE: Step F.3 is marked as N/A as the valve handle has not been connected.
F.4.a. Verify BPV Status is ENABLED At the DEHC Operator ___ ___ ___
(1) Workstation:
Navigates to the
<CONTROL><BPV JACK>
screen and verifies BPV Status is ENABLED.
- F.4.a Select STPT/RAMP At the DEHC Operator ___ ___ ___
(2) Workstation on the
<CONTROL><BPV JACK>
screen, select STPT/RAMP in the Bypass Valve Manual Opening (JACK) Control Box.
EVALUATOR NOTE: The values entered for set point and ramp will depend on how many bypass valves are initially desired open and how fast. A value of 11, for set point will open 1 bypass valve.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM c Comment SAT UNSAT STEP ELEMENT STANDARD Number
- F.4.a Enter values for Set Point and Enters values > 0 for Set Point ___ ___ ___
(3) Ramp. and Ramp and selects OK.
- F.4.a Confirm values for Set Point Selects OK to confirm values. ___ ___ ___
(4) and Ramp.
F.4.a Adjusts Set Point as necessary On the <CONTROL><BPV (5) to obtain cooldown rate. JACK> screen, Selects RAISE or LOWER to adjust cooldown rate.
CUE: When a discernable cooldown rate is observed, as the Unit Supervisor, state:
Another NSO will monitor and control the RPV cooldown.
EVALUATOR NOTE: The examinee should inform you that the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Control Reactor Pressure using the Main Steam Line Drains JPM Number: 2016 ILT NRC JPM c Revision Number: 00 Task Number and
Title:
SR-0001-P06 (Freq: LIC=B) Given an operating reactor plant when a Group 1 isolation with a failure of relief valves to operate occurs, attempt to stabilize RPV pressure below 1060 psig using Alternate Pressure Control Systems in accordance with QGA 100.
K/A Number and Importance: K/A: 239001.A4.02 Rating: 3.2/3.2 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOP 0250-05 Rev. 6, Reactor Pressure Control Using Main Steam Line Drains.
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)
2016 ILT NRC JPM c INITIAL CONDITIONS The Unit has been SCRAMMED due to an Instrument Air leak in the Reactor Building.
The Unit Supervisor has directed actions of QOA 4700-06, Loss of Instrument Air, and attempts to isolate the leak are still in progress.
The Unit Supervisor has entered QGA 100 and has directed a cooldown at < 100°F/hr using RCIC and the Main Steam Line Drains.
An Extra NSO has been assigned to monitor and record the RPV cooldown per QCOS 0201-02.
This JPM is NOT time critical.
INITIATING CUE Initiate an RPV cooldown at < 80°F/hr using the Main Steam Line Drains and the Main Turbine Bypass valves per QCOP 0250-05.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure RCIC Manual Initiation (Hard Card) with an Inadvertent Isolation JPM Number: 2016 ILT NRC JPM d Revision Number: 03 Date: 09/30/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date 2016 ILT NRC JPM d SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 1 of 10
2016 ILT NRC JPM d - Rev 03 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 through 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 QCOP 1300-02 Rev: 31 Procedure QCOA 1300-01 Rev: 18 Procedure QCAN 901-4 B-15 Rev: 12
________ 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 2016 ILT NRC JPM d SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 2 of 10
2016 ILT NRC JPM d - Rev 03 Revision Record (Summary)
Revision 00, This JPM was developed from Bank JPM B.1.b for ILT Certification Exam 03-1 IAW NUREG 1021 Revision 9 and to update format.
Revision 01, Update for correct procedure revisions.
Revision 02, Update for correct procedure revisions.
Revision 03, Update JPM template and use on 2016 ILT NRC Exam.
2016 ILT NRC JPM d SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 3 of 10
2016 ILT NRC JPM d - Rev 03 SIMULATOR SETUP INSTRUCTIONS
- 2. Manual Actuation:
- Ensure that the RCIC system is in its normal standby lineup.
- 3. Malfunctions / Commands:
- trgset 1 RCNTB.GT.0.5 ( Sets trigger based on 50% RCIC turbine speed)
- trg 1 imf rc12 (inserts RCIC isolation)
- trgset 2 an:9014a15 (sets trigger on annunciator 901-4 A-15)
- trg 2 dmf rc12 (deletes RCIC isolation)
- 4. Remotes: NONE
- 5. Overrides: NONE
- 6. When the above steps are completed for this and other JPMs to be run concurrently, then validate the concurrently run JPMs using the JPM Validation Checklist.
- 7. This completes the setup for this JPM.
2016 ILT NRC JPM d SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 4 of 10
2016 ILT NRC JPM d - Rev 03 INITIAL CONDITIONS
- A loss of feedwater has resulted in a reactor scram and entry into QGA 100.
- The Unit Supervisor has determined that RCIC injection is needed to restore reactor water level and control RPV pressure.
- Hard Card use has been authorized by the Unit Supervisor.
- RCIC is in its normal standby lineup.
- This JPM is NOT time critical INITIATING CUE Establish Unit 1 RCIC injection into reactor vessel using the manual initiation pushbutton per the Hard Card.
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.
2016 ILT NRC JPM d SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 5 of 10
2016 ILT NRC JPM d - Rev 03 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number Obtain Hardcard. Obtains Hardcard for RCIC ___ ___ ___
MANUAL STARTUP from the 901-4 panel.
Hardcard Initiate RCIC using the Depresses and holds the RCIC ___ ___ ___
Step 1 manual initiation pushbutton. MAN INITIATION pushbutton on the 901-4 for at least 30 seconds.
Verifies the system lines up to Using indications on the 901-4 ___ ___ ___
inject. panel verifies system valves are lining up for injection.
Identifies RCIC Isolation and Acknowledges 901-4 B-15 ___ ___ ___
Turbine trip. alarm and verifies RCIC isolation and turbine trip occur by closure of the following valves:
MO 1-1301-16 and MO 1-1301-17 (isolation)
MO 1-1301-61 and MO 1-1301-60 (turbine trip).
Alternate Path Starts Here CUE: If the examinee asks the Unit Supervisor for direction after reporting the RCIC isolation and turbine trip, state, Continue efforts to establish RCIC injection.
901-4 Determines isolation signal Dispatches EO to the RCIC ___ ___ ___
B-15 step was spurious. Room to investigate cause of B.3. isolation.
Performs QCOA 1300-01.
CUE: If dispatched, as EO, report that a contractor inadvertently bumped DP switch (1-1360-1A) on Instrument rack 2201-58. No other malfunctions or issues are present. There are no indications of steam leaks.
If dispatched as IM, report that all DP switches are working properly.
INSTRUCTOR NOTE: Examinee may choose to go directly to QCOA 1300-01Step D.8.b.
2016 ILT NRC JPM d SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 6 of 10
2016 ILT NRC JPM d - Rev 03 Comment SAT UNSAT STEP ELEMENT STANDARD Number QCOA Depress initiation signal seal Depress RCIC initiation signal ___ ___ ___
1300-1 step in and reset. seal in and reset.
D.4.
QCOA Dispatches operator to check Dispatches operator to check ___ ___ ___
1300-1 step status of RCIC room. status of RCIC room.
D.8.b.
CUE: AS EO, report, a contractor inadvertently bumped a DP switch (1-1360-1A)
(If not on Instrument rack 2201-58. There is no indication of a steam line break or dispatched leak.
earlier) If requested as IM report that, switches are working properly.
QCOA Verifies all RCIC isolation Verifies all RCIC trip and ___ ___ ___
1300-1 step and trips are cleared. isolation signals as listed in D.8.d.(1) steps E.1.(a.-d), and E.2.(a.-c) are cleared.
1300-1 step TRIP RESET pushbutton and D.8.d.(2) verifies 901-4 B-15 alarm clears.
- QCOA Reset RCIC Turbine Trip Depresses TURB RESET ___ ___ ___
1300-1 step pushbutton and verifies 901-4 D.8.d.(3) D-15 alarm clears.
QCOA Verify closed MO 1-1301- Verifies MO 1-1301-61, 1300-1 step 61, STM TO TURB VLV. CLOSED light is lit.
D.8.d.(4)
- QCOA Open MO 1-1301-17, STM Places the MO 1-1300-17 ___ ___ ___
1300-1 step SPLY ISOL VLV. control switch to OPEN and D.8.d.(5)* verifies the OPEN light is lit.
- QCOA Open MO 1-1301-16, STM Throttles MO 1-1300-16 until ___ ___ ___
1300-1 step SPLY ISOL VLV. fully open and verifies:
D.8.d.(7) -OPEN light is lit
-CLOSED light is out.
2016 ILT NRC JPM d SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 7 of 10
2016 ILT NRC JPM d - Rev 03 Comment SAT UNSAT STEP ELEMENT STANDARD Number QCOA Obtains QCOP 1300-02 Determines RCIC Turbine ___ ___ ___
1300-1 step Hard Card to initiate RCIC trip/isolation is reset by absence D.9 injection. of any alarms, and that RCIC injection is required. Obtains Hardcard to restart system.
EVALUATOR NOTE: The critical task below is satisfied if the examinee chooses to start RCIC using the Hardcard steps for Manual Pushbutton OR Manual Startup-Level Control.
QCOP 1300-02 step F.5 will also provide instruction for a manual startup and satisfy the task.
step 1 the reactor vessel. MAN INITIATION pushbutton on the 901-4 for at least 30 seconds.
Verifies the system lines up to Using indications on the 901-4 ___ ___ ___
inject. panel and verifies:
-valves align for injection
-RCIC Flow Controller establishes flow at ~ 400 gpm.
EVALUATOR NOTE: The examinee should inform you that the task is complete.
JPM Stop Time:
2016 ILT NRC JPM d SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 8 of 10
2016 ILT NRC JPM d - Rev 03 JPM
SUMMARY
Operators Name: Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
RCIC Manual Initiation (Hard Card) with an Inadvertent Isolation JPM Number: 2016 ILT NRC JPM d Revision Number: 03 Task Number and
Title:
SR-1300-P04 (Freq: LIC=A) Given an operating RCIC system when a spurious RCIC isolation occurs, perform actions to determine the cause and reset the isolation and trip in accordance with QCOA 1300-01 and QCOA 1300-06.
K/A Number and Importance: K/A: 217000 A4.03 Rating: 3.4/3.3 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOP 1300-02, Rev. 31 QCOA 1300-01, Rev. 18 QCAN 901-4 A-15, Rev. 10 QCAN 901-4 D-15, Rev. 7 QCAN 901-4 B-15, Rev. 12 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:
2016 ILT NRC JPM d SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 9 of 10
INITIAL CONDITIONS
- A loss of feedwater has resulted in a reactor scram and entry into QGA 100.
- The Unit Supervisor has determined that RCIC injection is needed to restore reactor water level and control RPV pressure.
- Hard Card use has been authorized by the Unit Supervisor.
- RCIC is in its normal standby lineup.
- This JPM is NOT time critical INITIATING CUE Establish Unit 1 RCIC injection into reactor vessel using the manual initiation pushbutton per the Hard Card.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Exelon Nuclear Job Performance Measure Vent Containment Irrespective of Release Rates with APCV.
(Failure of Torus Valve to Open, Requiring Venting Through the Drywell)
JPM Number: 2016 ILT NRC JPM e Revision Number: 02 Date: 10/02/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 1 of 10
2016 ILT NRC JPM e, 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 through 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 QCOP 1600-13 Rev: 28 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.105 There are no retention requirements for this section.
Page 2 of 10
2016 ILT NRC JPM e, Rev 00 Revision Record (Summary)
Revision Record (Summary)
Revision 00: Developed for 2016 ILT NRC exam (Class 14-1). This JPM is based on existing JPM LS-053-I-A. This JPM is venting for high Primary Containment pressure, vice high H2 as was the case in LS-053-I-A. The actions are the same for both JPMs. The reasons for venting and desired outcomes are different. Therefore, this is not considered a new JPM. It is a revised Bank JPM.
Revisions to LS-053-I-A Revision 00, New JPM Revision 01, JPM revised to reflect procedure revisions.
Revision 02, JPM revised to reflect procedure and K/A revisions.
SRRS: 3D.105 There are no retention requirements for this section.
Page 3 of 10
2016 ILT NRC JPM e, Rev 00 SIMULATOR SETUP INSTRUCTIONS
- 1. RESET the Simulator to IC 21.
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. Trip Latch HPCI.
- 3. INSERT malfunctions to break the D and E Main Steam Relief Valves above the water line.
imf ms16d imf ms16e
- 4. INSERT a malfunction to erode the D Main Steam Relief Valve seat 15%. imf ms06d 15 (This will maintain a high DW pressure such that the examinee gets feed back from their actions.)
- 5. OVERRIDE the AO 1-1601-60, TORUS 18-INCH VENT closed. ior dihs1160160 close
- 6. MANUALLY OPEN the D and E Main Steam Relief Valves on the 901-3 panel.
- 7. PLACE the RX Mode switch to SHUTDOWN.
- 8. Secure the 1A and 1C RFPs and close the Feed Reg Isolation Valves.
- 9. Secure the 1B Condensate Pump.
- 10. MONITOR DW pressure on the 901- 3 panel.
- 11. WHEN DW pressure reaches ~55 psig, THEN CLOSE D and E Main Steam Relief Valves
- 13. Silence the DW/T Vacuum breaker alarms. bat sv
- 14. 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.
- 15. This completes the setup for this JPM.
SRRS: 3D.105 There are no retention requirements for this section.
Page 4 of 10
2016 ILT NRC JPM e, Rev 00 INITIAL CONDITIONS A transient has occurred on Unit One resulting in high Drywell Pressure The US has determined the need to vent the Primary Containment to prevent exceeding the Primary Containment Pressure Limit (PCPL)
All available Radwaste and Turbine Building Exhaust Fans are operating INITIATING CUE Vent the Primary Containment in accordance with QCOP 1600-13 and establish a Primary Containment pressure band of 45 to 50 psig.
It is "OK to exceed release rate limits."
(If the examinee elects to use the procedure instead of the Hard Card, provide a blank copy of QCOP 1600-13 when the procedure is located)
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 at the bottom of the page. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.
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.105 There are no retention requirements for this section.
Page 5 of 10
2016 ILT NRC JPM e, Rev 00 JPM Start Time:
Comment SAT UNSAT Number STEP ELEMENT STANDARD NOTE: Operator may choose to use procedure or Hard Card. Both are acceptable.
C.1. IF QGA or SAMG procedures Signs off Prerequisite as N/A do NOT state "OK to exceed per Initial Conditions.
Release Rate Limits," THEN a vent recommendation has been provided by the Chemistry Department within the last 8 days.
C.2. Verify RPS available to Signs off Prerequisite per Initial ___ ___ ___
operate valves. Conditions.
F.1. Operate fans to provide Signs off as complete per Initial ___ ___ ___
(Hard Card dilution flow. Conditions.
1.a)
F.2.a-f. Verify closed primary Verifies CLOSED lights lit for ___ ___ ___
(Hard Card containment valves. the following valves:
1.b) AO 1-1601-23 AO 1-1601-24 AO 1-1601-60 AO 1-1601-61 AO 1-1601-62 AO 1-1601-63 F.4.a. Evacuate the Reactor Makes announcement to ___ ___ ___
(Hard Card Building AND Turbine evacuate the Reactor Building 1.c) Building. AND Turbine Building
- F.4.b. Place MASTER VENT Positions Master Vent Mode ___ ___ ___
(Hard Card MODE SWITCH in APCV Switch to the APCV position.
1.d) position.
F.4.c. Verify closed AO 1-1699-7, Verifies AO 1-1699-7 closed ___ ___ ___
(Hard Card VENT TO RX BLDG. light lit.
1.e)
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 6 of 10
2016 ILT NRC JPM e, Rev 00 Comment SAT UNSAT Number STEP ELEMENT STANDARD NOTE: The following 2 steps will bypass the 2.5 psig Group II isolation signal to allow opening containment vent valves.
(Hard Card 1-1601-24 valve. OVERRIDE switch to 1.f) OVERRIDE AND holds for 1 second AND Verifies 901-5, E4 alarms
- F.4.e. Override Gp II signal for AO 1- SIMULTANEOUSLY positions ___ ___ ___
(Hard Card 1601-23 AND AO 1-1601-60 the AO 1-1601-23 CIS 1.g) OVERRIDE and the AO 1-1601-60 CIS OVERRIDE switches to OVERRIDE AND holds for 1 second AND Verifies 901-5, E3 and F3 alarm
- F.4.f. Open Vent to Reactor Building Positions AO 1-1601-24 control ___ ___ ___
(Hard Card Exhaust system valve switch to open.
1.h) Verifies the OPEN light lit.
ALTERNATE PATH STARTS HERE F.4.g Open the AO 1-1601-60. Positions AO 1-1601-60 control ___ ___ ___
(Hard Card switch to open AND observes 2.a) the OPEN light is NOT lit.
F.4.h Recognizes inability to vent Operator recognizes inability to ___ ___ ___
(Hard Card the containment through the vent the containment through the 3.) Torus, and need to vent the Torus, and need to vent the Drywell. Drywell.
CUE: Lo Gas monitors 0-1740-19 and 0-1740-202 Gas Activity Recorders are reading slightly higher.
CUE: (IF needed) Restate need to vent the containment.
The operator may dispatch an operator and/or maintenance to investigate.
Role play as necessary to investigate the valve failure.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 7 of 10
2016 ILT NRC JPM e, Rev 00 Comment SAT UNSAT Number STEP ELEMENT STANDARD F.4.h.(1). Verifies the Torus 18-inch Verifies AO-1601-60 closed light ___ ___ ___
(Hard Card Vent valve is closed. lit.
3.a)
(Hard Card vent valve. switch to open.
3.b)
Verifies OPEN light lit
- F.4.h.(3). Control vent flow by cycling Positions AO 1-1699-6 control ___ ___ ___
(Hard Card AO 1-1699-6 open and switch to OPEN 3.c) closed as required. Verifies DW pressure lowering NOTE: Closure of the AO 1-1699-6 valve is not included as a Critical Step.
F.4.h.(3). Control vent flow by cycling Positions AO 1-1699-6 control ___ ___ ___
(Hard Card AO 1-1699-6 open and switch to CLOSE when DW 3.c) closed as required. pressure in the desired band of 45 - 50 psig.
CUE: Another NSO will monitor and control Containment venting.
EVALUATOR NOTE: The examinee should inform you that the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 8 of 10
2016 ILT NRC JPM e, Rev 00 JPM
SUMMARY
Operators Name: Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Vent Containment Irrespective of Release Rates with APCV. (Failure of Torus Valve to Open, Requiring Venting Through the Drywell)
JPM Number: 2016 ILT NRC JPM e Revision Number: 00 Task Number and
Title:
SR-0001-P24 (Freq: LIC=A) Given a reactor plant with rising containment pressure due to a LOCA or steam leak, vent the containment irrespective of off-site radioactivity release rates before torus pressure reaches the Primary Containment Pressure Limit (QGA Figure D) in accordance with QGA 200 and QCOP 1600-13. (Important PRA task. Failure to control contaiment venting or restore IA for venting results in core damage in 20 of top 100 Core Damage Sequences)
K/A Number and Importance: K/A: 295024.EA1.14 Rating: 3.4/3.5 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOP 1600-13, Rev. 28, POST ACCIDENT VENTING OF THE PRIMARY CONTAINMENT 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)
Page 9 of 10
INITIAL CONDITIONS A transient has occurred on Unit One resulting in high Drywell Pressure The US has determined the need to vent the Primary Containment to prevent exceeding the Primary Containment Pressure Limit (PCPL)
All available Radwaste and Turbine Building Exhaust Fans are operating INITIATING CUE Vent the Primary Containment in accordance with QCOP 1600-13 and establish a Primary Containment pressure band of 45 to 50 psig.
It is "OK to exceed release rate limits."
SRRS: 3D.105 There are no retention requirements for this section.
Page 10 of 10
Exelon Nuclear Job Performance Measure Install OPRM Jumpers on RPS B JPM Number: 2016 ILT NRC JPM f Revision Number: 00 Date: 09/30/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM f- rev.0 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 QCOP 7000-03 Rev: 01 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
2016 ILT NRC JPM f- rev.0 Revision Record (Summary)
Revision 00, This is a new JPM written for the 2016 ILT NRC Exam.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM f- rev.0 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC-21 NOTE: This JPM is performed inside the simulator panels and can be done in any IC. The examiners must verify that this JPM is compatible with other JPMs that are scheduled to be run concurrently.
- 2. Manual Actuations:
None
- 3. Malfunctions:
None
- 4. Remotes:
None
- 5. Overrides:
None
- 6. Equipment:
Four (4) Switchable Jumpers and Four (4) TCC tags.
- 7. 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.
- 8. This completes the setup for this JPM.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM f- rev.0 INITIAL CONDITIONS
- Unit 1 is operating steady state at 80% power.
- The A RPS MG set has been returned to service following repairs to the feed breaker.
- The control room has made preparations for re-energizing RPS A from its normal feed.
- Equipment Operators in the Aux Electric Room have requested the control room to perform step C.12 of QCOP 7000-03.
- The Unit Supervisor has authorized installation of the OPRM jumpers on RPS B.
- Short Duration Time Clocks (SDTC) for Tech Spec LCOs 3.3.1.3 Condition A and 3.3.1.3 Condition B have been started.
- An Equipment Status Tag (EST) has been placed on the 901-5 panel stating OPRM trips on B RPS are bypassed.
- Continuity checks have been performed on the jumpers.
- This JPM is NOT time critical.
INITIATING CUE Install jumpers to bypass RPS B OPRM trips per QCOP 7000-03 Attachment A.
Provide examinee with: A copy of QCOP 7000-03 signed off through step C.12.g.
Four (4) switchable jumpers with banana type connectors.
Four (4) TCC tags.
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
2016 ILT NRC JPM f- rev.0 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number Attach Notify Unit Supervisor of Informs the Unit Supervisor of ___ ___ ___
A jumper installation jumper installation on RPS B bypassing OPRM trips.
1.a.
OR Determines completion from Initial Conditions.
CUE: As Unit Supervisor, acknowledge and concur with jumper installation.
Attach Verifies Unit Supervisor has Verifies the Unit Supervisor has ___ ___ ___
A entered SDTCs. entered SDTCs for TS LCOs 3.3.1.3 Condition A and B.
1.b.
OR Determines completion from Initial Conditions.
CUE: If asked, as Unit Supervisor, state: Short Duration Time Clocks are started for Tech Spec LCOs 3.3.1.3 Condition A and B.
CUE: If necessary, as the Unit Supervisor, inform the examinee that step 1.c of QCOP 7000-03 Attachment A (place EST on the 901-5 panel) has been completed by the Unit NSO.
CUE: The examinee may ask for verification of jumper placements in the following steps. If so, then state: There is no one available. The verifications will be done later.
Attach Verify Jumper is open. Verifies jumper switch is in ___ ___ ___
OPEN position.
A 1.d.(1).
(a)
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM f- rev.0 Comment SAT UNSAT STEP ELEMENT STANDARD Number
terminals (PS2)TB4-4 and A
TB1B-4 in the 901-37 panel.
1.d.(1).
(b)
switch to the CLOSE position.
A 1.d.(1).
(c)
Attach Verify Jumper is open. Verifies jumper switch is in ___ ___ ___
OPEN position.
A 1.d.(2).
(a)
terminals (PS4)TB4-1 and A
TB2B-1 in the 901-37 panel.
1.d.(2).
(b)
switch to the CLOSE position.
A 1.d.(2).
(c)
Attach Verify Jumper is open. Verifies jumper switch is in ___ ___ ___
OPEN position.
A 1.d.(3).
(a)
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM f- rev.0 Comment SAT UNSAT STEP ELEMENT STANDARD Number
terminals TB4B-1 and TB4B-14 A
in the 901-37 panel.
1.d.(3).
(b)
switch to the CLOSE position.
A 1.d.(3).
(c)
Attach Verify Jumper is open. Verifies jumper switch is in ___ ___ ___
OPEN position.
A 1.d.(4).
(a)
terminals TB5B-118 and TB5B-A 119 in the 901-37 panel.
1.d.(4).
(b)
A 1.d.(4).
(c)
CUE: As the Unit Supervisor, inform the examinee that you will have another NSO complete the remaining steps QCOP 7000-03 Attachment A.
EVALUATOR NOTE: The examinee should inform you that the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Install OPRM Jumpers on RPS B JPM Number: 2016 ILT NRC JPM f Revision Number: 00 Task Number and
Title:
SRN-TMOD-K12 (Freq: LIC=B NF=B) Describe how to install and remove the following: a.) Jumper wires K/A Number and Importance: K/A: 216000.K1.01 Rating: 3.9/4.1 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOP 7000-03 Rev. 01, Unit 1 Reactor Protection MG Sets 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)
2016 ILT NRC JPM f- rev.0 INITIAL CONDITIONS
- Unit 1 is operating steady state at 80% power.
- The A RPS MG set has been returned to service following repairs to the feed breaker.
- The control room has made preparations for re-energizing RPS A from its normal feed.
- Equipment Operators in the Aux Electric Room have requested the control room to perform step C.12 of QCOP 7000-03.
- The Unit Supervisor has authorized installation of the OPRM jumpers on RPS B.
- Short Duration Time Clocks (SDTC) for Tech Spec LCOs 3.3.1.3 Condition A and 3.3.1.3 Condition B have been started.
- An Equipment Status Tag (EST) has been placed on the 901-5 panel stating OPRM trips on B RPS are bypassed.
- Continuity checks have been performed on the jumpers.
- This JPM is NOT time critical.
INITIATING CUE Install jumpers to bypass RPS B OPRM trips per QCOP 7000-03 Attachment A.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM g.-Rev.00 Exelon Nuclear Job Performance Measure Reverse RHRSW Heat Exchanger Flow JPM Number: 2016 ILT NRC JPM g Revision Number: 00 Date: 12/08/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM g.-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 QCOP 1000-04 Rev: 22 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
2016 ILT NRC JPM g.-Rev.00 Revision Record (Summary)
Revision 00, This JPM was developed for the 2016 ILT NRC Exam.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM g.-Rev.00 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC 21.
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.
- 3. Start up the 1C and 1D RHRSW pumps per QCOP 1000-04, step F.2.b-c.
- 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
2016 ILT NRC JPM g.-Rev.00 INITIAL CONDITIONS The 1C and 1D RHRSW pumps were started earlier this shift at the request of Engineering and the CMO group for performance monitoring.
Both groups have collected the data and are now requesting the 1B RHRSW Heat Exchanger flow reversed and both RHRSW pumps placed in operation.
INITIATING CUE Place the 1B RHR Heat Exchanger in REVERSE FLOW and restart the 1C and 1D RHRSW pumps per QCOP 1000-04.
Provide examinee with: A blank copy of QCOP 1000-04.
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
2016 ILT NRC JPM g.-Rev.00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number
(1) c/s to the OFF position and verifies:
- Off light lit
- RHRSW Hx Outlet pressure lowers
(1) c/s to the OFF position and verifies:
- Off light lit
- RHRSW Hx Outlet pressure lowers
- F.2.e. Close MO 1-1001-5B valve Places the MO 1-1001-5B c/s to ___ ___ ___
(2) the CLOSE position and verifies:
- CLOSED light lit F.2.e. Place MO 1-1001-5B c/s to Places the MO 1-1001-5B c/s to ___ ___ ___
(3) STOP the STOP mid-position.
F.2.e. Verify closed MO 1-1001-5B Verifies: ___ ___ ___
(4) valve - CLOSED light lit
- Valve position indication at 0%
F.3.a-b Verify B Loop RHR and Verifies OFF lights are lit for: ___ ___ ___
RHRSW pumps are OFF - 1C & 1D RHR Pumps
- 1C & 1D RHRSW Pumps EVALUATOR NOTE: Step F.3.c. is N/A SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM g.-Rev.00 Comment SAT UNSAT Number STEP ELEMENT STANDARD
Flow FLOW SELECT switch to the REV position.
F.3.d. Verify 1B RHR Hx valve Verifies:
(1)-(4) positions for Reverse Flow - MO 1-1001-186B valve ___ ___ ___
OPEN light is lit ___ ___ ___
- MO 1-1001-187B valve OPEN light is lit
- MO 1-1001-4B valve ___ ___ ___
CLOSED light is lit
- MO 1-1001-185B valve ___ ___ ___
CLOSED light is lit EVALUATOR NOTE: The examinee should return to step F.2. to restart the 1C and 1D RHRSW pumps. Step F.2.a. is NA.
CUE: If an EO is dispatched to the 1D and 1B/C RHRSW Vaults, then after each pump is started, state:
The pump sounds normal, oil levels are good, and the room cooler is running.
F.2.b. Verify RHR HX B SERVICE Verifies valve position lights for ___ ___ ___
(1) WATER FLOW is in REVERSE REVERSE Flow are lit.
lineup (As indicated on placard above the 1B RHR HX SW FLOW SELECT switch.)
(2) valve. SW DISCH VLV c/s to OPEN, then places it to STOP when valve position indicates >40%
open.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM g.-Rev.00 Comment SAT UNSAT STEP ELEMENT STANDARD Number
- F.2.b. Start the 1C/D RHRSW Pump Places the 1C/1D RHRSW Pmp (3) c/s to the ON position and verifies:
- ON light lit
- Rising pressure indicated on PI 1-1040-3B.
- F.2.b. Throttle MO 1-1001-5B, valve Throttles MO 1-1001-5B closed (4) to establish discharge pressure until the following conditions are ___ ___ ___
and flow met:
- Discharge press is < 350 psig on PI 1-1040-3B
- Flow is < 3600 gpm on FI 1-1040-1B F.2.b. Verify NO increase on 1-1705- At Panel 901-2, verifies:
(5) 12, PROCESS LIQUID No count rate (cps) increase ___ ___ ___
MONITOR indicated on 1-1705-12, PROCESS LIQUID MONITOR, (Channel 2).
EVALUATOR NOTE: The examinee should read the next two steps and then perform them in succession.
- F.2.c. Throttle open MO 1-1001-5B Throttles open MO 1-1001-5B (1) valve to establish discharge to establish a discharge ___ ___ ___
pressure pressure of approx. 140 psig indicated on PI 1-1040-3B.
- F.2.c. Start the 1C/D RHRSW Pump Places the 1C/1D RHRSW Pmp (2) c/s to the ON position and ___ ___ ___
verifies:
- ON light lit Rising pressure indicated on PI 1-1040-3B.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM g.-Rev.00 Comment SAT UNSAT STEP ELEMENT STANDARD Number
- F.2.c Throttle MO 1-1001-5B, valve Throttles MO 1-1001-5B closed (3) to establish discharge pressure until the following conditions are and flow met:
Discharge press is < 350 psig on PI 1-1040-3B Flow is < 7200 gpm on FI 1-1040-1B EVALUATOR NOTE: The examinee should inform you that the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM g.-Rev.00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Reverse RHRSW Heat Exchanger Flow JPM Number: 2016 ILT NRC JPM g Revision Number: 00 Task Number and
Title:
SR-1000-P11 (Freq: LIC=I): Given an operating reactor plant with RHRSW operating, reverse RHRSW flow in accordance with QCOP 1000-04.
K/A Number and Importance: K/A: 400000.A4.01 Rating: 3.1/3.0 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOP 1000-04 Rev. 22, RHR SERVICE WATER SYSTEM OPERATION.
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)
2016 ILT NRC JPM g.-Rev.00 INITIAL CONDITIONS The 1C and 1D RHRSW pumps were started earlier this shift at the request of Engineering and the CMO group for performance monitoring.
Both groups have collected the data and are now requesting the 1B RHRSW Heat Exchanger flow reversed and both RHRSW pumps placed in operation.
INITIATING CUE Place the 1B RHR Heat Exchanger in REVERSE FLOW and restart the 1C and 1D RHRSW pumps per QCOP 1000-04.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure Energize 480 Bus 15 With a Failure of the Normal Feed JPM Number: 2016 ILT NRC JPM h Revision Number: 03 Date: 12/17/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM h-Rev.03 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 QOP 6700-02 Rev: 38 Procedure QCOA 6100-03 Rev: 41 Procedure QOA 6700-01 Rev: 18
________ 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
2016 ILT NRC JPM h-Rev.03 Revision Record (Summary)
Revision 00, New JPM developed for ILT 09-1 NRC Exam.
Revision 01, JPM revised for procedure changes.
Revision 02, JPM revised for procedure changes.
Revision 03, Taken from JPM Bank (LS-082-I-A) and used on 2016 ILT NRC Exam.
Revised JPM number, updated template, and Evaluator notes.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM h-Rev.03 SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC-18 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. Take the following actions:
- Start the 2A Service Water Pump.
- Prevent reclosure of the Bus 15 Main Feed Breaker: imf ed06a
- Trip T-12 using the command: imf ed02
- Insert a manual reactor scram and place the Mode Switch in Shutdown.
- Restore RPS A and B from the normal feeds: irf rp28r reset, irf rp29r reset
- Backfeed Bus 13 and Bus 14.
- Allow the simulator to stabilize, i.e. RPV water level approx. 0 inches (use SSMP if necessary), and RPV pressure stable at < 1060 psig.
- Perform the following steps of QCOA 6100-03, D.3, D.15, D.18, D.23, D.24, and D.28.
- Start the 1/2 Instrument Air Compressor.
- Start the 2A Service Air Compressor.
- Acknowledge annunciators initially and throughout the JPM.
- Snap the setup to IC-0 or any other available IC.
- 3. Prepare a copy of QCOA 6100-03 signed off as complete, N/A, or in progress (circled), as appropriate up to step D.29.
- 4. One blank copy of QOP 6700-02.
- 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
2016 ILT NRC JPM h-Rev.03 INITIAL CONDITIONS A loss of offsite power has occurred on Unit 1.
The Unit Supervisor has entered QGA 100 and directed actions to control RPV water level and pressure.
Actions have been completed per QCOA 6100-03, Loss of Offsite Power up to step D.29.
Hard Cards are authorized.
The Unit Supervisor has directed you to resume Electric Plant restoration activities.
INITIATING CUE Re-energize Bus 15 and Bus 17 from their Normal Feeds per QCOA 6100-03, step D.29.
Do NOT energize Bus 16 due to a Bus fault.
Notify the Unit Supervisor when Bus 15 and Bus 17 are energized.
Provide examinee with: A marked up copy of QCOA 6100-03.
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
2016 ILT NRC JPM h-Rev.03 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number QCOA Close Bus 15 Main Feed Places Bus 15 c/s to the NAT 6100-03 Breaker position to clear the AUTO Step 29.a ___ ___ ___
TRIP.
OR THEN QOA 6700-01 Places Bus 15 c/s to the NAC Hard Card position.
Step 1 CUE: The Bus 15 Main Feed Breaker will not close. If the examinee reports this and asks for direction, as the Unit Supervisor state:
Continue efforts to energize Bus 15 CUE: If an EO is dispatched to investigate the Bus 15 Main Feed Breaker, then report back as appropriate from either:
Bus 13 cubicle 1, BUS 13 TO XFORMER 15 FEED BKR OR Bus 15 cubicle 2B, BUS 13 TO TRANSFORMER 15 EMs are here and they have identified a problem with the closing spring and are unable to charge it. There are no other problems preventing Bus 15 from being energized,
- QCOA Close Bus 17 Main Feed Places Bus 17 c/s to the NAT 6100-03 Breaker position to clear the AUTO Step 29.c TRIP.
OR ___ ___ ___
THEN
- QOA 6700-01 Places the Bus 17 c/s to the Hard Card NAC position and verifies:
Step 1
- CLOSED light lit
- OPEN light out
- Bus 17 LIVE light lit ALTERNATE PATH STARTS HERE EVALUATOR NOTE: The task may be accomplished by using the Hard Card (QOA 6700-01) OR QOP 6700-02. If necessary, provide a copy of QOP 6700-02 when located.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM h-Rev.03 Comment SAT UNSAT STEP ELEMENT STANDARD Number QOA 6700-01 Verify closed the Bus 17 Verifies the Bus 17 Main Feed Hard Card Step Main Feed breaker. Breaker indications:
1 ___ ___ ___
- CLOSED light lit
- OPEN light out QOP 6700-02 - Bus 17 LIVE light lit Step F.1.d.(1)
QOA 6700-01 Verify open Bus 15 Main Verifies Bus 15 Main Feed Hard Card Step Feed Breaker. Breaker OPEN and AUTO TRIP 2.a lights are lit OR ___ ___ ___
OR QOP 6700-02 Step F.1.d.(2) Places Bus 15 c/s to NAT and verifies breaker OPEN light is lit.
QOA 6700-01 Verify open Bus 15 to Verifies Bus 15 to Bus 16 Tie-Hard Card Step Bus 16 Tie-Breaker. Breaker indications:
2.c ___ ___ ___
- OPEN light lit
- CLOSED light out QOP 6700-02 Step F.1.d.(3)
- QOA 6700-01 Close Bus 15 to Bus 17 Places Bus 15 to Bus 17 Tie-Hard Card Step Tie-Breaker. Breaker c/s to NAC and verifies:
2.d ___ ___ ___
- CLOSED light lit OR
- OPEN light out
- QOP 6700-02 - Bus 15 LIVE light lit Step F.1.d.(4)
EVALUATOR NOTE: The examinee should inform you that the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Energize 480 VAC Bus 15 With a Failure of the Normal Feed JPM Number: 2016 ILT NRC JPM h Revision Number: 03 Task Number and
Title:
SR-6500-P04 (Freq: LIC=B): Given a loss of normal power to an emergency bus (13-1 or 14-1) with a failure of the associated emergency diesel to start, supply power to the emergency bus using the crosstie from Unit 2 and restore 480vac busses in accordance with QOA 6500-03, QCOP 6500-08, QOA 6700-04 and QOA 6700-01.
(Determine expected bus loading currents in accordance with QCOP 6500-28)
(SOER 83-6 r4)
K/A Number and Importance: K/A: 262001 A4.01 Rating: 3.4/3.7 Suggested Testing Environment: Simulator Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOA 6100-03 Rev.41, LOSS OF OFFSITE POWER QOA 6700-01 Rev.18, 480V BUS 15, 16 OR 17 (25, 26 OR 27) FAILURE QOP 6700-02, Rev.38, 480 VOLT BUS TIE CIRCUIT BREAKERS 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)
2016 ILT NRC JPM h-Rev.03 INITIAL CONDITIONS A loss of offsite power has occurred on Unit 1.
The Unit Supervisor has entered QGA 100 and directed actions to control RPV water level and pressure.
Actions have been completed per QCOA 6100-03, Loss of Offsite Power up to step D.29.
Hard Cards are authorized.
The Unit Supervisor has directed you to resume Electric Plant restoration activities.
INITIATING CUE Re-energize Bus 15 and Bus 17 from their Normal Feeds per QCOA 6100-03, step D.29.
Do NOT energize Bus 16 due to a Bus fault.
Notify the Unit Supervisor when Bus 15 and Bus 17 are energized.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure Flex 125 VDC Battery Crosstie JPM Number: 2016 ILT NRC JPM i Revision Number: 00 Date: 01/21/2016 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM i-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 QCOP 0050-15 Rev: 01 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
2016 ILT NRC JPM i-rev.00 Revision Record (Summary)
Revision 00, New JPM developed for the 2016 ILT NRC Exam.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM i-rev.00 INITIAL CONDITIONS
- An Extended Loss of AC Power (ELAP) event was declared several hours ago by the Shift Manager.
- The Unit 2 125 VDC Battery Bus voltage is reading 105 VDC as indicated on the 902-8 panel.
- Several delays have been encountered in deployment of the FLEX Generator.
- The Unit Supervisor has determined the 125 VDC Alternate Battery is required to restore system voltage.
- You have been issued a Fire Lock Key.
- 100 ft. of cable fitted with red and black connectors on each end, has been staged at the Junction Box in the Battery Charger Room.
- This JPM is NOT time critical.
INITIATING CUE Connect the Unit 2 125 VDC Alternate Battery to 125 VDC System per QCOP 0050-15, step F.4.
Provide examinee with a marked up copy of QCOP 0050-15.
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
2016 ILT NRC JPM i-rev.00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number F.4.a Verify OPEN: At 125 VDC Distribution Panel ___ ___ ___
2A-2, verifies breaker 12 is in Breaker 12 on 125 VDC the OFF position.
Distribution Panel 2A-2.
CUE: Point to the position indicated by the examinee and state:
The breaker is here.
- F.4.b Connect the FLEX 125 VDC
- Obtains the pre-staged FLEX ___ ___ ___
Battery crosstie cables to JB 2- connecting cable beside the 0030-JB200. Junction Box.
- Opens JB 2-0030-JB200 (adjacent to 125 VDC Dist.
Pnl. 2A-2).
- Attaches connectors, red to red and black to black.
CUE: Point to the connection points indicated by the examinee and state:
The cable is attached.
- F.4.c Connect the FLEX 125 VDC
- Runs FLEX cables from the ___ ___ ___
Battery crosstie cables to the Junction Box to the 125 VDC Unit-2 Alternate 125 VDC Alternate Battery post Battery. connectors.
- Attaches cable and battery post connectors, red to red and black to black.
CUE: Point to the connection points indicated by the examinee and state:
The cable is attached.
- F.4.d Unlock fused disconnect at 125 Using Fire Key, unlocks (or ___ ___ ___
VDC Battery Bus #2 Cub. C04. breaks) and removes lock on fused disconnect at 125 VDC Battery Bus #2 Cub, C04.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM i-rev.00 Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE: The lock is removed.
- F.4.e OPEN disconnect at 125 VDC At 125 VDC Battery Bus #2 ___ ___ ___
Battery Bus #2 Cub. C04. Cub. C04:
Depresses lever and repositions disconnect downward to the OFF position.
CUE: Point to the position indicated by the examinee and state:
The disconnect is here.
- F.4.f CLOSE Breaker 12 on 125 VDC At 125 VDC Distribution Panel ___ ___ ___
Distribution Panel 2A-2. 2A-2, places breaker 12 to the ON position.
CUE: Point to the position indicated by the examinee and state:
The breaker is here.
F.4.g Verify local voltage In the Unit 2 125 VDC Battery ___ ___ ___
Charger Room:
Places the voltmeter select switch to either Bus 2A, 2A-1, or 2A-2 and reads indicated voltage.
CUE: If the voltmeter is selected to Bus 2A, 2A-1, or 2A-2, point to 130 Volts and state:
Meter indication is here.
If the voltmeter is selected to Batt Bus, point to 105 Volts and state:
Meter indication is here.
F.4.h Notify Main Control Room Contacts Control Room and ___ ___ ___
informs Unit Supervisor that QCOP 0050-15 step F.4.a.thru h is complete.
EVALUATOR NOTE: The examinee should inform you the task is complete.
JPM Stop Time: _____
SRRS: 3D.105 (when utilized for operator initial or continuing training)
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Flex 125 VDC Battery Crosstie JPM Number: 2016 ILT NRC JPM i Revision Number: 00 Task Number and
Title:
SRN-FLEX.2-P02 (Freq: LIC=I N=I): Given a reactor plant in an ELAP (Extended Loss of AC Power) Event and 125 VDC battery voltage is expected to drop to < 105 VDC,or 250 VDC battery voltage is expected to drop to <210 VDC swap to the Alternate 125 or Non-Emergency 250 VDC Battery in accordance with QCOP 0050-15 "FLEX 125/250 VDC Operation".
K/A Number and Importance: K/A: 295004. AA1.01 Rating: 3.3/3.4 Suggested Testing Environment: In-Plant Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOP 0050-15 Rev. 1, FLEX 125/250 VDC OPERATION 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)
2016 ILT NRC JPM i-rev.00 INITIAL CONDITIONS
- An Extended Loss of AC Power (ELAP) event was declared several hours ago by the Shift Manager.
- The Unit 2 125 VDC Battery Bus voltage is reading 105 VDC as indicated on the 902-8 panel.
- Several delays have been encountered in deployment of the FLEX Generator.
- The Unit Supervisor has determined the 125 VDC Alternate Battery is required to restore system voltage.
- You have been issued a Fire Lock Key.
- 100 ft. of cable fitted with red and black connectors on each end, has been staged at the Junction Box in the Battery Charger Room.
- This JPM is NOT time critical.
INITIATING CUE Connect the Unit-2 125 VDC Alternate Battery to 125 VDC System per QCOP 0050-15, step F.4.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure Start the Control Room B Train HVAC with a Failure of the FCV JPM Number: 2016 ILT NRC JPM j Revision Number: 00 Date: 11/30/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM j - 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 QCOP 5750-09 Rev: 56 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
2016 ILT NRC JPM j - Rev. 00 Revision Record (Summary)
Revision 00, This JPM was developed for the 2016 ILT NRC test. It is a Safety Function 9, Alternate Path in- plant JPM.
SRRS: 3D.100; There are no retention requirements for this section
2016 ILT NRC JPM j - Rev. 00 INITIAL CONDITIONS
- Units 1 and 2 are operating at rated power.
- The Control Room HVAC B Train is to be placed in operation to support maintenance activities on the A Train.
- Control Room Train A HVAC is currently in operation.
- The 1A RHRSW pump has been started per QCOP 1000-04.
- An EO has verified the valve positions for step F.3.e.(2a-c) of QCOP 5750-09.
- Mechanical Maintenance is in standby to determine if refrigerant needs to be added.
- The US has directed you to locally start the B AHU. Do NOT run the Air Filtration Unit (AFU).
- This JPM is NOT time critical.
INITIATING CUE Place the Control Room B Train HVAC in operation per QCOP 5750-09 step F.3. Contact Mechanical Maintenance when ready for the refrigerant check.
Provide the examinee with a marked-up copy of QCOP 5750-09.
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
2016 ILT NRC JPM j - Rev. 00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number F.3.a. Verify: At Panel 1/2-9400-105: ___ ___ ___
(1) AIR HANDLING UNIT B in Verifies the B Train AHU control AUTO. switch is in the AUTO position.
CUE: Point to the position indicated by the examinee and state:
The switch is positioned here.
F.3.a. Verify: At Panel 1/2-9400-105: ___ ___ ___
(2) A/C UNIT B COMPRESSOR Verifies the A/C UNIT B in AUTO. COMPRESSOR control switch is in the AUTO position.
CUE: Point to the position indicated by the examinee and state:
The switch is positioned here.
F.3.b. Verify: At Panel 1/2-9400-102: ___ ___ ___
STOP/RESET-STANDBY- Verifies the STOP/RESET-AUTO switch in STANDBY. STANDBY-AUTO control switch is in the STANDBY position.
CUE: Point to the position indicated by the examinee and state:
The switch is positioned here.
EVALUATOR NOTE: Steps F.3.c. and F.3.d. are N/A per the Initial Conditions.
F.3.e. Verify RCU is NOT operating. Verifies the RCU is NOT ___ ___ ___
(1) operating.
- F.3.e Place A/C UNIT B COOLING At Panel 1/2-9400-105: ___ ___ ___
(1)(a) WATER SUPPLY SELECTOR Places the A/C UNIT B switch in EMERG. COOLING WATER SUPPLY SELECTOR switch in the EMERG position.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM j - Rev. 00 Comment SAT UNSAT STEP ELEMENT STANDARD Number EVALUATOR NOTE: Per the Initial Conditions, the valves in step F.3.e.(2)(a) through F.3.e.(2)(c) have been verified to be in the correct positions. If the examinee dispatches an EO to verify valve positions, then role play accordingly.
F.3.e. Verify OPEN: Determines from Initial (2) Conditions.
1-5799-385, CR HVAC TRAIN ___ ___ ___
(a-c) B RCU RHRSW SPLY FR OR PMPS 1-1001-65A & 65B Dispatches an EO to the CRD OUTBD SV Pump Level (TB 572 elev) to Verify CLOSED: verify the valves.
1-5799-384, CR HVAC TRAIN ___ ___ ___
B RCU RHRSW SPLY FR PMPS 1-1001-65C & 65D OUTBD SV Verify CLOSED:
1-5799-406, CR HVAC TRAIN ___ ___ ___
B RCU RHRSW SPLY FR PMPS 1-1001-65C & 65D INBD SV CUE: If dispatched/contacted, as EO, report:
The 1-5799-385 valve is OPEN.
The 1-5799-384 and 1-5799-406 valves are CLOSED.
EVALUATOR NOTE: Steps F.3.e.(2)(d) and F.3.e.(3) are N/A.
F.3.e. Verify RHRSW system is Determines from Initial ___ ___ ___
(4) operating. Conditions.
OR Contacts the Control Room.
CUE: If contacted, as the NSO, state:
The 1A RHRSW Pump has been started and is operating in accordance with QCOP 1000-04.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM j - Rev. 00 Comment SAT UNSAT STEP ELEMENT STANDARD Number F.3.e. Place the Control Room HVAC Contacts the NSO to complete f-g in Recirc Mode. step F.3.f & g of QCOP 5750-09 by:
AND ___ ___ ___
Placing the CONTROL ROOM Shut down Control Room A HVAC ISOL SWITCH in the Train HVAC.
ISOLATE position at the 912-5 panel.
AND Shut down Control Room A Train HVAC per step F.2.
CUE: As the NSO, state: Step F.3.f & g of QCOP 5750-09 are complete. The Control Room HVAC system was placed on ISOLATE and the A Train HVAC has been shut down per step F.2.
CUE: If the examinee verifies damper positions at the 1/2-9400-105 panel, then state:
The green lights are lit for the following dampers:
AO 1/2-5741-324A & B, AO 1/2-5741-325A & B, AO 1/2-5741-327A & B, AO 1/2-5741-331 EVALUATOR NOTE: Step F.3.h is N/A per Initial Conditions.
- F.3.i Start AIR HANDLING UNIT B. At Panel 1/2-9400-105: ___ ___ ___
Places control switch, (HS 1/2-5741-316B), to the START position and releases.
CUE: Point to the red light above the B Train HVAC control switch and state:
This light is lit and you hear the Air Handling Unit running.
CUE: If the examinee verifies damper positions at the 1/2-9400-105 panel, then state:
The red lights are lit for the 1/2-5741-330A & B and 1/2-5741-331 dampers.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM j - Rev. 00 Comment SAT UNSAT STEP ELEMENT STANDARD Number F.3.j Reset oil pressure trips and At Panel 1/2-9400-102: ___ ___ ___
allow RCU to cycle on Control Place the STOP/RESET-Room temperature. STANDBY-AUTO switch to the STOP/RESET position, then to the AUTO position.
F.3.k Verify RCU compressor is Verifies Compressor running by ___ ___ ___
running. Checking oil pressure &
temperature or running sound.
CUE: You hear the compressor running.
If compressor oil pressure is checked at PI 1/2-5795-336, point to 105 psig and state: The Indicator is here.
F.3.l Verify RCU compressor oil Verifies oil is visible in ___ ___ ___
level. sightglass located on the side of the RCU compressor.
CUE: Point to the middle of the sightglass and state: Oil level is here.
ALTERNATE PATH STARTS HERE F.3.m Verify adequate RCU At the RCU compressor:
compressor discharge pressure Determines PI 1/2-5795-335, ___ ___ ___
COMPRESSOR DISCHARGE PRESSURE is NOT within 100 psig to 280 psig range.
CUE: At PI 1/2-5795-335, point to the 50 psig mark and state:
Pressure indication is here.
F.3.m. Verify PIC 1/2-5795-333, CR At Panel 1/2-9400-105:
(1)(a) HVAV TRAIN B RCU SERV Verifies AUTO pushbutton back ___ ___ ___
WTR SPLY FCV, is in AUTO. light is lit on PIC 1/2-5795-333.
CUE: When asked about the status of the AUTO pushbutton on PIC 1/2-5795-333, state:
The green light below the AUTO pushbutton is lit SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM j - Rev. 00 Comment SAT UNSAT STEP ELEMENT STANDARD Number
- F.3. Close 1/2-5799-378, CR HVAC Locates 1/2-5799-378 valve m.(1) TRAIN B RCU SERV WTR outside of B HVAC room and (b) SPLY FCV MANUAL ISOL VLV. turns valve handwheel clockwise until it will not turn further.
CUE: After the examinee has made several turns in the clockwise direction, state:
The valve will not turn any further EVALUATOR NOTE: Only ONE of the next two steps will be successful in controlling RCU compressor discharge pressure.
- F.3.
Adjust 1/2-5799-381, CR HVAC Partially throttles open the 1/2-m.(1) TRAIN B RCU SERV WTR 5799-381 valve by turning the (b)* SPLY BYP VLV. handwheel counterclockwise direction.
UNTIL ___ ___ ___
Discharge pressure at PI 1/2-5795-335 is within 100 psig to 280 psig range.
CUE: After the first manipulation, when PI 1/2-5795-335 is checked, point to 250 psig and state:
Pressure indication is here.
CUE: If the examinee attempts to control the RCU compressor discharge pressure by unlocking and throttling the 0- 5799-1073, CR HVAC TRAIN B RCU SERV WTR OUTLET VALVE, state:
The valve will NOT turn F.3.n Contact Mechanical Calls Control Room or Maintenance for refrigerant Mechanical Maintenance and ___ ___ ___
check. informs them that Control Room B Train HVAC is running and requires a refrigerant check.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM j - Rev. 00 Comment SAT UNSAT STEP ELEMENT STANDARD Number CUE: Acknowledge the call and state:
Maintenance personnel are in route to perform the refrigerant check on B Train HVAC.
CUE: Another operator will assist Mechanical Maintenance and perform steps F.3.o and F.3.p.
EVALUATOR NOTE: The examinee should inform you that the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
2016 ILT NRC JPM j - Rev. 00 JPM
SUMMARY
Operators Name: Emp. ID#: ____________
Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Start Control Room B Train HVAC with a Failure of the FCV JPM Number: 2016 ILT NRC JPM j Revision Number: 00 Task Number and
Title:
SR-5750-P05 (Freq: LIC=I) Given an operating reactor plant with the 'A' and 'B' train control room ventilation systems shutdown, start the 'B' train HVAC, RCU and the AFU in accordance with QCOP 5750-09.
K/A Number and Importance: K/A: 290003 G.2.1.20 Rating: 4.6/4.6 Suggested Testing Environment: Plant Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOP 5750-09 Rev. 56 Control Room Ventilation System 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)
2016 ILT NRC JPM j - Rev. 00 INITIAL CONDITIONS
- Units 1 and 2 are operating at rated power.
- The Control Room HVAC B Train is to be placed in operation to support maintenance activities on the A Train.
- Control Room Train A HVAC is currently in operation.
- The 1A RHRSW pump has been started per QCOP 1000-04.
- An EO has verified the valve positions for step F.3.e.(2a-c) of QCOP 5750-09.
- Mechanical Maintenance is in standby to determine if refrigerant needs to be added.
- The US has directed you to locally start the B AHU. Do NOT run the Air Filtration Unit (AFU).
- This JPM is NOT time critical.
INITIATING CUE Place the Control Room B Train HVAC in operation per QCOP 5750-09 step F.3. Contact Mechanical Maintenance when ready for the refrigerant check.
SRRS: 3D.100; There are no retention requirements for this section
Exelon Nuclear Job Performance Measure Locally Start Up the 1/2 A Fire Diesel JPM Number: 2016 ILT NRC JPM k Revision Number: 00 Date: __09/29/2015___
Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 1 of 8
2016 ILT NRC JPM k- 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 through 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 QCOP 4100-03 Rev: 20 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.105 There are no retention requirements for this section.
Page 2 of 8
2016 ILT NRC JPM k- Rev 00 Revision Record (Summary)
ILT 2016 NRC Examination Revision 00, Revised to new format.
ILT 2009 NRC Examination Revision 00, This JPM is developed IAW guidelines established in NUREG 1021 Rev 9 ES-301 and Appendix C. This JPM meets the criteria of Category B.1 "Control Room Systems," for RO/SRO candidates.
This JPM was based on bank JPM LP-002-II, Rev. 18.
JPM revised to match procedure revision and update to latest JPM template.
SRRS: 3D.105 There are no retention requirements for this section.
Page 3 of 8
2016 ILT NRC JPM k- Rev 00 INITIAL CONDITIONS
- You are an extra operator.
- Both Diesel Fire pumps are in a standby condition per QCOP 4100-03, Section F.1.a.
- The Fire Marshall has requested that the 1/2 A Diesel Fire Pump be started locally for observation.
- There are no AUTO start signals present.
- You have been issued a fire protection key.
- This JPM is NOT time critical.
INITIATING CUE Locally start-up the 1/2 A Diesel Fire Pump in the Test Mode, establish proper pressure, and verify proper operation per QCOP 4100-03.
Contact the Fire Marshall when the 1/2A Fire Diesel is running.
Provide the examinee: A copy of QCOP 4100-03 with Prerequisite C.1 and Step F.1.a-b signed off.
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.105 There are no retention requirements for this section.
Page 4 of 8
2016 ILT NRC JPM k- Rev 00 JPM Start Time:
Comment SAT UNSAT STEP ELEMENT STANDARD Number F.1.b. Verify closed MO 1/2-3906. Contacts CR to verify ___ ___ ___
MO 1/2-3906 valve is closed.
CUE: As the Control Room Operator, state, The MO 1/2-3906 valve is closed.
F.1.c.(1) Open the 1/2A Diesel Fire Unlocks the 1-4199-6 valve and ___ ___ ___
PMP MIN FLOW VLV. rotates handwheel counter-clockwise.
CUE: You cannot rotate the handwheel any further.
- F.1.d.(2) Start the 1/2 A Diesel Fire Positions 1/2 A Diesel Fire ___ ___ ___
Pump by placing control Pump control switch to TEST.
switch to TEST.
CUE: The diesel is running.
F.1.d.(3) Verifies engine cooling Checks the intake flume funnel ___ ___ ___
water outlet flow to the for cooling water flow.
intake flume funnel CUE: There is flow into the funnel.
- F.1.d.(4)(a) Throttles the 1/2A DIESEL Rotates 1-4199-6 valve hand ___ ___ ___
FIRE PMP MIN FLOW VLV wheel clockwise to establish to attain proper discharge 140 to 145 psig disch. press on press. PI 1/2-4141-2A.
CUE: When asked, point to 140 psig on PI 1/2-4141-2A and state, the pressure is here after the valve is throttled.
If asked before the valve is throttled, point to 100 psig.
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 5 of 8
2016 ILT NRC JPM k- Rev 00 Comment SAT UNSAT STEP ELEMENT STANDARD Number F.1.d.(5) Verify normal parameters. Verifies oil press. 40 psig and ___ ___ ___
engine temp. is < 200°F.
CUE: When prompted, point to the value for each gauge and state, the pressure is here.
Oil pressure is 60 psig, Water temp. is 180o F.
CUE: The examinee informs the Fire Marshal that the 1/2A Fire Diesel is operating properly.
CUE: The Fire Marshall informs you that maintenance personnel want to walk down the system prior to placing the system in a shutdown lineup and it will be approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> before you can place the system in a shutdown condition.
EVALUATOR NOTE: The examinee should inform you that the task is complete.
JPM Stop Time:
SRRS: 3D.105 (when utilized for operator initial or continuing training)
Page 6 of 8
2016 ILT NRC JPM k- Rev 00 JPM
SUMMARY
Operators Name: Job
Title:
EO RO SRO FS STA/IA SRO Cert JPM
Title:
Locally Start Up The 1/2 A Fire Diesel JPM Number: 2016 ILT NRC JPM k Revision Number: 00 Task Number and
Title:
SRN-4100-P05 (Freq: LIC=B NF=B) Given an operating reactor plant with a loss of service water and a failure of a diesel fire pump to start, locally start the diesel fire pump in accordance with QCOP 4100-03.
K/A Number and Importance: K/A: 286000.2.1.30 Rating: 4.4/4.0 Fire system; Ability to locate and operate components, including local controls Suggested Testing Environment: Plant Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s): QCOP 4100-03 Rev. 20, DIESEL FIRE PUMP OPERATION Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 10.5 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)
Page 7 of 8
INITIAL CONDITIONS
- You are an extra operator.
- Both Diesel Fire pumps are in a standby condition per QCOP 4100-03, Section F.1.a.
- The Fire Marshall has requested that the 1/2 A Diesel Fire Pump be started locally for observation.
- There are no AUTO start signals present.
- You have been issued a fire protection key.
- This JPM is NOT time critical.
INITIATING CUE Locally start-up the 1/2 A Diesel Fire Pump in the Test Mode, establish proper pressure, and verify proper operation per QCOP 4100-03.
Contact the Fire Marshall when the 1/2A Fire Diesel is running.
SRRS: 3D.105 There are no retention requirements for this section.
Quad Cities 2016 NRC EXAM Scenario 1 Exelon Nuclear 2016 ILT NRC Exam Scenario Scenario Number:
NRC Scenario 1 Revision Number: 00 Date: 10/15/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2016 NRC Scenario 1 Op-Test No.: ILT 14-1 Examiners: ________________________ Operators:_____________________________
Initial Conditions:
The plant is operating at 75% power.
RCIC steam line is isolated.
Turnover: Return RCIC to the standby lineup.
Event Malf. No. Event Event No. Type* Description 1 None BOP Re-pressurize the RCIC Steam Lines N
2 SW07B BOP The 1B RBCCW Pump degrades C (QCOP 3700-02) 3 FW06B ATC Feedwater Flow Transmitter Failure I
4 PC04G SRO Drywell-Torus Vacuum Breaker fails open TS 5 RR01A ATC 1A Recirc Pump Trip / Emergency Power R Reductions (QCOA 0202-04) TS 6 RR11A CREW LOCA- Recirc Loop A Discharge Pipe Break M TAF-Blowdown (QGA 100/200/500-1) 7 ED03B/ED04B ATC Loss of Reactor Feed Pumps C
8 DG04A BOP U-1 EDG fails to auto start C
9 HP01/RC01 CREW HPCI Startup and Trip / RCIC Trip C
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:
Total Malfunctions (5-8): 8 BOP Normal: E1 Malfunction(s) after EOP (1-2): E7, 8, & 9 ATC Reactivity (1 per set): E5 Abnormal Events (2-4): E2, 3, 4, & 5 BOP I/C (4 per set): E2 & 8 Major Transient(s) /E-Plan entry (1-2): E6 ATC I/C (4 per set): E3 & 7 EOPs (1-2): QGA 100 & 200 SRO-I I/C (4 per set inc 2 as ATC):
EOP Contingencies (0-2): QGA 100/500-1 E2, 3, 5, 7, 8, 9 Critical Tasks (2-3): 3 SRO Tech Spec (2 per set): E4 & 5 ALL Major Transients (2 per set) E6 Quad Cities 2016 NRC EXAM Scenario 1
SUMMARY
- Initial Conditions:
o The plant is operating at 75% power to support load following per Generation Dispatch.
o RCIC has been returned to service and is to be placed in its normal standby lineup.
- Event 2: The Unit 1 EO on rounds calls the Control Room and reports the 1B RBCCW pump motor is running hot and very noisy. The BOP reports RBCCW discharge pressure lowering and directs the EO to lineup the 1/2C RBCCW pump to Unit 1 per QCOP 3700-02. The 1/2C RBCCW pump is started and the 1B RBCCW pump is secured.
- Event 3: The 1B RFP flow transmitter fails downscale causing a minor level transient. The ATC swaps to 1-element control stabilizing RPV water level. Instrument Maintenance will investigate and report the RFP must be secured to replace the transmitter. The SRO will direct the BOP to start up the 1C RFP and secure the 1B RFP in preparation for a clearance order to repair the transmitter.
- Event 4: The BOP acknowledges and reports annunciators 901-3 C-13 and 901-3 G-11. A short time later, the control room receives a call that a new engineer on a system walkdown inadvertently bumped a test pushbutton on the 2251-24 panel. An EO is dispatched and reports the 1601-33B Drywell to Torus Vacuum Breaker indicates open. Attempts by the EO to close the vacuum breaker are unsuccessful. The Unit Supervisor enters TS 3.6.1.1 Condition A, Primary Containment inoperable, TS 3.6.1.8 Condition C, one Vacuum breaker not closed, and TS 3.6.2.5 Condition A, Drywell to Torus differential pressure < 1.0 psid.
- Event 5: The 1A Recirc Pump will trip causing the crew to enter QCOA 0202-04. The crew will insert CRAM rods to stay within MELLLA and outside of Instability Region II. The Unit Supervisor will enter TS 3.4.1 Condition C, Single Loop operation outside of the LCO requirements.
- Event 6: 1A Recirc Pump Discharge Pipe break. The crew will take actions for rising Drywell pressure in accordance with QCOA 0201-01. A manual scram will be inserted on high Drywell pressure. The crew will take actions in accordance with QGA 100 and QGA 200. With the loss of high pressure injection systems, RPV level will lower to -142 (TAF). The crew will enter QGA 500-1 and execute a blowdown. RPV level will be restored with Low Pressure ECCS systems.
- Event 7: Shortly after the scram, the T-12 reserve feed beaker to Bus 11 will fail to close, leaving Bus 11 de-energized. Simultaneously, Bus 12 will trip on an overcurrent resulting in a loss of all Reactor Feed pumps.
- Event 8: The Unit 1 EDG will fail to auto start on 2.5 psig Drywell pressure. The BOP will manually start the EDG.
- Event 9: The crew will attempt to start RCIC for RPV level control, however, the Trip Throttle valve will trip and not reset. HPCI will initially inject and restore RPV water level but will trip after several minutes. The crew will be unable to re-establish HPCI injection and RPV level will lower to TAF.
- Approximate Run Time: 1.5 Hours Quad Cities 2016 NRC EXAM Scenario 1 CRITICAL TASKS:
Critical Task #1: When Torus pressure exceeds 5 psig, INITIATE drywell sprays while in the safe region of the drywell spray initiation limit (DSIL). (BWROG PC-5.1 INIT DW SPRAY)
Critical Task #2: Given the plant with the inability to maintain level above -59 inches, INHIBIT ADS, to prevent an uncontrolled depressurization IAW QGA 100. (Important PSA task / Inhibiting ADS terminates 5 of top 200 Core Damage Sequences)
Critical task #3: Given the plant with an inability to maintain RPV water level above -142 inches with an injection source lined-up and running, initiate an emergency depressurization before RPV water level drops to -190 inches in accordance with QGA 100 and QGA 500-1. (Important PRA Operator Action - emergency depressurization terminates 19 of top 100 Core Damage Sequences)
Quad Cities 2016 NRC EXAM Scenario 1 EXERCISE PERFORMANCE OBJECTIVES SR-1300-P05 (Freq: LIC=I) Given a reactor plant being started up, warmup the RCIC lines and align the system for standby in accordance with QCOP 1300-01.
SR-3700-K26 (Freq: LIC=B) EVALUATE given key RBCCW parameter indications and/or responses depicting a system specific abnormality/failure and DETERMINE a course of action to correct or mitigate the following abnormal condition(s):
- c. Low RBCCW pressure SR-0600-K26 (Freq: LIC=B) EVALUATE given key Feedwater Level Control System parameter indications and/or responses depicting a system specific abnormality/failure and DETERMINE a course of action to correct or mitigate the following abnormal condition(s):
- a. Feedflow sensor fails high/low SR-1601-K20 Given various plant conditions, EVALUATE the following Containment Systems indications/ responses and DETERMINE if the indication/ response is expected and normal.
- b. Drywell/torus differential pressure
- c. Torus to Drywell vacuum breaker position SR-0202-P04 Given an operating reactor plant with a loss of one recirculation pump, take actions to determine the cause, stabilize plant parameters, and to exit the Instability Region in accordance with QCOA0202-04.
SR-0203-P07 (Freq: LIC=B) Given a reactor plant in a QGA condition, inhibit ADS in accordance with QGA 100 or QGA 101. (Important PSA task / Inhibiting ADS terminates 5 of top 200 Core Damage Sequences)
SR-0001-P01 (Freq: LIC=A) Given the plant with a loss of normal feedwater resulting in the inability to restore RPV water level above 0 inches, inject with Alternate Injection Systems (QGA Detail E) to attempt to hold RPV water level above
-142 inches in accordance with QGA 100. (SOER 86-1 r8)
SR-0001-P02 (Freq: LIC=A) Given the plant with an inability to maintain RPV water level above -142 inches with an injection source lined-up and running, initiate an emergency depressurization before RPV water level drops to -190 inches in accordance with QGA 100 and QGA 500-1. (Important PRA Operator Action
- emergency depressurization terminates 19 of top 100 Core Damage Sequences)
Quad Cities 2016 NRC EXAM Scenario 1 EXERCISE PERFORMANCE OBJECTIVES SR-0001-P03 (Freq: LIC=A) Given a shutdown reactor plant with an emergency depressurization in progress due to an inability to maintain RPV water level above -142 inches, attempt to control RPV level above -142 inches using available injection systems or establish/maintain adequate core cooling using alternate methods in accordance with QGA 500-1 and QGA 100.
SR-0001-P26 (Freq: LIC=B) Given a reactor plant with rising drywell temperature due to a LOCA or steam leak and RHR is not needed for core cooling, verify parameters are in the safe region of the Drywell Spray Initiation Limit (QGA Figure K), verify tripped or trip recirc pumps and drywell coolers, and attempt to initiate drywell sprays before drywell temperature reaches 280 degrees in accordance with QGA 200.
SR-0001-P45 (Freq: LIC=A) Given a reactor plant in a QGA condition, verify the proper actuation of containment isolations and ECCS and emergency DG starts in accordance with QGA 100 or QGA 101.
Quad Cities 2016 NRC EXAM Scenario 1 Simulator Setup:
- 1. Reset to IC-20 (75% power).
- 2. Go to RUN.
- 3. Verify the following RWM Sequence is loaded: 4PHESD (or current shut down sequence)
(The following commands to be utilized for this scenario are contained in the CAEP file:
2016 NRC Scenario 1.cae)
- 4. Insert Commands for setup:
- trgset 1 "pcpdwg.gt.1.5" (sets trigger 1 true when Drywell pressure is greater than 1.5 psig)
- trg 1 "dmf pc04g" (Drywell-Torus Vacuum Breaker failure deleted on trigger 1)
- trgset 2 tcvsv3 .le. 0.1 (sets trigger true when main turbine stop valve #3 is closed)
- trg 2 imf ed03b (trips Bus 12 on overcurrent)
- trgset 3 rcntb.gt.0.5 (sets trigger 3 true when the RCIC turbine speed is > 50%)
- trg 3 imf rc01 (trips the RCIC turbine Trip Throttle Valve)
- imf ed04b (prevents Bus 11 to automatically transfer upon loss of normal power source)
- imf dg04a (prevents an auto start for the Unit 1 EDG)
- 5. Verify the following commands for scenario performance:
- imf sw07b 30 3: (degrade the 1B RBCCW pump 30% over 3 minutes)
- imf fw06b 0 40 (fails the 1B RFP flow transmitter downscale over 40 seconds)
- imf pc04g 20 (fails the 1-1601-33B Drywell-Torus Vacuum Breaker 20% open)
- mmf pc04g 100 (modifies D/T Vacuum Breaker position to 100% open)
- mmf pc04g 20 (modifies D/T Vacuum Breaker position to 20% open)
- imf rr01a (trips the 1A Recirc pump)
- imf rr11a .1 5: (Inserts a .1% break over 5 minutes in the 1A Recirc Pump discharge piping)
- bat sv (silences 901-3 G-11 and C-13 alarms)
- imf hp01 (trips the HPCI turbine)
- mmf rr11a .5 (modifies 1A Recirc piping break to .5%)
- 6. Install Protected System placards and/or rings on the following equipment:
o HPCI o T-12
- 7. Provide a Load Drop REMA.
- 8. Provide a marked up copy of QCOP 1300-01, RCIC System Preparation for Standby Operation.
Quad Cities 2016 NRC EXAM Scenario 1 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901(2)-3, A-9, HPCI TURBINE TRIPPED, Rev. 5 o 901(2)-3, A-16, PRI CNMT HIGH PRESSURE, Rev. 15 o 901(2)-3, C-13, TORUS VACUUM BKR VALVES OPEN DIV I, Rev. 12 o 901(2)-3, G-11, TORUS VACUUM BKR VALVES OPEN DIV II Rev. 10 o 901(2)-3, G-15, REACTOR VESSEL LOW LOW LEVEL, Rev. 17 o 901(2)-4 B-2, RECIRC DRIVE A TRIP, Rev. 10 o 901(2)-5 E-8, RX VESSEL HIGH LEVEL, Rev. 9 o 901(2)-5 F-8, RX VESSEL LOW LEVEL, Rev. 10 o 901(2)-8 F-3, 4KV BUS OVRCUR TRIP, Rev. 6 QCOP 0300-16, Addition of Water to Reactor Vessel Using CRD Hydraulic System, Rev. 8 QOP 3200-04, Reactor Feed Pump Changeover, Rev. 50 QCOP 3700-02, RBCCW System Startup and Operation, Rev. 29 QCGP 2-3, Reactor Scram, Rev. 84 QCGP 3-1, Reactor Power Operations, Rev. 79 QCOA 0201-01, Increasing Drywell Pressure, Rev. 27 QCOA 0202-04, Reactor Recirc Pump TripSingle Pump, Rev. 45 QGA 100, RPV Control, Rev. 10 QGA 200, Primary Containment Control, Rev. 10 QGA 500-1, RPV Blowdown, Rev. 14 Quad Cities 2016 NRC EXAM Scenario 1 CREW TURNOVER 1.) Plant Conditions:
a.) Unit 1 is currently at 75% Power due to a load drop last shift for load following.
b.) Unit 2 is at 100% Power.
c.) Technical Specification limitations:
Day 3/14, TS 3.5.3 Condition A, RCIC inoperable.
d.) On Line Risk is YELLOW.
e.) Fire Risk is Blue.
f.) Protected Equipment:
(1) RBCCW (2) Fuel Pool Cooling (3) Transformer 12 (4) HPCI (5) HPCI Room Cooler (6) U-1 EDG Cooling Water Pump 2.) Significant problems/abnormalities:
a.) RCIC was returned to service last shift as repairs to the steam line drain pot level switch have been completed.
3.) Evolutions/maintenance for the oncoming shift:
a) Perform QCOP 1300-01 step F.3, RCIC System Preparation For Standby Operation and re-pressurize the RCIC steam line.
b.) Continue holding load per QCGP 3-1.
Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No.1 Event No. 1 Page 1 of 2 Event
Description:
Re-pressurize the RCIC Steam Lines.
Time Position Applicants Actions or Behavior SRO Directs and supervises QCOP 1300-01, step F.3.
Verifies RCIC Barometric Condenser Condensate and Vacuum Pump BOP control switches are in AUTO.
BOP Depresses INITIATION SIGNAL SEAL-IN AND RESET pushbutton.
BOP Verifies MO 1-1301-61, STM TO TURB VLV is closed.
BOP Depresses the STM LINE BRK TRIP RESET pushbutton.
BOP Depresses TURB RESET pushbutton.
BOP Verifies AO 1-1301-12 and AO 1-1301-13, COND PMP ISO VLVs are closed.
BOP Verifies TURB SPEED TEST switch is in NORMAL.
BOP Verifies TURB SPEED TEST PWR switch is in OFF.
Verifies AO 1-1301-34 and AO 1-1301-35, STM LINE DRAIN ISOL BOP VLVs are open.
BOP Verifies AO 1-1301-32, COND DRN VLV is closed.
BOP Contacts EO to verify RCIC room is cleared of personnel OR makes a plant announcement to evacuate the RCIC room.
BOP Opens MO 1-1301-17, STM SPLY ISOL VLV.
- Monitors PI 1-1340-6, TURB INLT PRESS, for increase in pressure.
- Verifies annunciator 901-4 F-16, RCIC TURBINE INLET STM DRN HIGH LEVEL, is NOT in alarm.
- When RCIC steam line pressure stops increasing AND 901-4 F-16 is cleared, fully opens MO 1-1301-16.
BOP Verifies GOVERNOR VLV is open.
BOP Verifies TRIP THROTTLE VLV is open.
Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No.1 Event No. 1 Page 2 of 2 Event
Description:
Re-pressurize the RCIC Steam Lines Time Position Applicants Actions or Behavior BOP Verifies RCIC FLOW CONTROLLER is in AUTO.
BOP Verifies RCIC FLOW CONTROLLER flow rate is set as 400 gpm BOP Verifies all RCIC annunciators on the 901-4 panel are cleared.
SRO Exits TS LCO 3.5.3 Condition A.
ATC Monitors reactor power, pressure, and water level.
End of Event 1 Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 2 Event No. 2 Page 1 of 2 Event
Description:
1B RBCCW pump degrades.
Time Position Applicants Actions or Behavior SIM OP: Degrade the 1 B RBCCW pump 30% ramped over 3 minutes using malfunction SW07B:
imf sw07b 30 3:
Key Parameter Response: Degrading RBCCW Discharge Header pressure as indicated on PI 1-3740-4 at the 912-1 panel.
Expected Annunciator(s): None SIM OP ROLE PLAY: As the U-1 EO on rounds, call in and report:
The 1B RBCCW pump is sounding very noisy, the motor is hot to touch and the discharge pressure is 40 psig.
BOP Reports RBCCW Discharge Header pressure on PI 1-3740-4 at the 912-1 panel is low in the green band.
SRO Directs BOP to place the 1/2C RBCCW Pump into operation.
BOP Directs the EO to lineup the 1/2C RBCCW Pump to Unit 1 per QCOP 3700-02 step F.4.
SIM OP ROLE PLAY: As the EO, wait 3 minutes, then call in and report:
The 1/2C RBCCW pump is lined up to Unit 1 per the Hard Card, QCOP 3700-02 Attachment B.
BOP Starts the 1/2C RBCCW Pump, then secures the 1B RBCCW Pump.
BOP Directs the EO to close the 1-3799-59, 1B RBCCW PMP DSCH VLV and the 1-3799-61, 1B RBCCW PMP SUCT VLV per QCOP 3700-02 Attachment A, step 2.
SIM OP ROLE PLAY: As the EO, wait 3 minutes, then report back:
The 1B RBCCW Pump suction and discharge valves are closed. QCOP 3700-02 Attachment A, step 2 is complete.
Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 2 Event No. 2 Page 2 of 2 Event
Description:
1B RBCCW pump degrades Time Position Applicants Actions or Behavior BOP Reports 1/2C RBCCW pump is running, the 1B RBCCW pump is secured, and RBCCW Discharge Header pressure is approx. 53 psig.
ATC Monitors Recirc pump seal cooling water temperatures at TR 1-262-19A/B., PUMP TEMPERATURE, point 2.
ATC Monitors Drywell pressure and temperature.
End of Event 2 Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No.1 Event No. 3 Page 1 of 3 Event
Description:
1B RFP Feedwater Flow Transmitter Fails Downscale Time Position Applicants Actions or Behavior SIM OP: Fail the 1B RFP flow transmitter downscale ramped over 40 seconds using malfunction FW06B:
imf fw06b 0 40 Key Parameter Response: RPV water level transient Expected Annunciator(s): 901-5 E-8 Automatic Actions: None ATC Reports 901-5 E-8, RX VESSEL HIGH LEVEL, alarm and refers to annunciator procedure.
Reports the 1B Reactor Feed Pump flow transmitter is failing ATC downscale.
ATC Transfers to 1-element control by selecting SINGLE on the 1-640-18, Rx Level Master Controller.
ATC Reports RPV water level is stable and controlled at 30 inches.
SRO Determines Core Thermal Power calculation is low due to failed feed flow transmitter and contacts a QNE.
SRO Contacts Instrument Maintenance to investigate the 1B FW Flow Transmitter.
SIM OP ROLE PLAY: If dispatched, as the IM Supervisor, wait 2 minutes, then report the following:
The 1B RFP will have to be shutdown to replace the flow transmitter.
SIM OP ROLE PLAY: If contacted, as the SOS, state:
Generation Dispatch will be requesting a load increase to full power in the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Proceed with the 1B RFP shutdown so that repairs can be started this shift.
SIM OP ROLE PLAY: If contacted, as the QNE, state:
A substitute value for the 1B RFP flow will need to be entered in the Heat Balance if it is not secured. I can do this remotely if the pump is to remain on line.
SRO Directs BOP to start the 1C RFP and secure the 1B RFP per QOP 3200-04.
Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No.1 Event No. 3 Page 2 of 3 Event
Description:
1B RFP Feedwater Flow Transmitter Fails Downscale Time Position Applicants Actions or Behavior BOP Dispatches an EO to the 1A Condensate/Condensate Booster Pump and the1C Reactor Feed Pump for pre-start checks.
SIM OP ROLE PLAY: As the EO dispatched to the 1A Cond/Cond Booster Pump, wait 2 minutes, then call back and report:
Steps F.3.a.(1) thru (14) and F.4.a. are complete. The 1A Cond/Cond Booster Pump is lined up and ready for a start.
BOP Places the COND PMP SELECTOR switch to OFF.
BOP Starts the 1A Cond/Cond Booster Pump and verifies:
- Condensate pump discharge press: 140 psig
- Condensate Booster pump suction press: 80 psig
- Condensate Booster pump discharge press: 220 psig
- Control switch has a red target.
- Yellow AUTO TRIP light is lit.
BOP Places the RFP SELECTOR switch to OFF.
SIM OP ROLE PLAY: As the EO dispatched to the 1C RFP, report the following when contacted:
Steps F.14.(a.) thru (m.) is complete. The 1C RFP is lined up and ready for a start.
BOP Closes MO 1-3201C, 1C RFP DISCH VLV.
BOP Opens AO 1-3201C, 1C RFP RECIRC VLV.
BOP Verifies the 1C RFP Auxiliary Oil Pump trips.
BOP Opens MO 1-3201C, RFP DISCH VLV.
BOP When RFP flow stabilizes, places AO 1-3201C, RFP RECIRC VLV to AUTO.
Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No.1 Event No. 3 Page 3 of 3 Event
Description:
1B RFP Feedwater Flow Transmitter Fails Downscale Time Position Applicants Actions or Behavior BOP Verifies AO 1-3201C closes.
SIM OP ROLE PLAY: When contacted for steps F.24.a,b,d,e, and f., as the EO, wait 2 minutes and report:
RFP bearing oil temp is 120°F, speed changer oil press is 8 psig, oil flow from bearing is visible, no seal leaks, and the RFP seals have been vented.
BOP Opens AO 1-3201B, RFP RECIRC VLV.
BOP Closes MO 1-3201B, RFP DISCH VLV.
BOP Opens MO 1-3201B, RFP DISCH VLV and places AO 1-3201B control switch to AUTO.
BOP Verifies AO 1-3201B closes.
BOP Verifies Feed and Condensate parameters are normal.
BOP Places the RFP SELECTOR SWITCH to STANDBY for the 1B RFP.
BOP Verifies the 1B RFP Auxiliary Oil Pump is running.
SIM OP ROLE PLAY: When contacted, to verify RFP warming line valves are open, (step F.29a.), as EO, wait 30 sec., then report:
The 1-3299-40, and 1-3299-116 downstream and upstream warming line valves for the 1A and 1B RFPs are open.
BOP Stops the 1A Cond/Cond Booster Pump.
BOP Places the COND PP SELECTOR switch to STANDBY for the 1A Cond/Cond Booster Pump.
BOP Verifies correct number of Condensate Demins are in operation.
BOP Checks Flow Control Line to verify thermal limits are NOT exceeded.
End of Event 3 Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 1 Event No. 4 Page 1 of 2 Event
Description:
Drywell-Torus Vacuum Breaker Fails Open Time Position Applicants Actions or Behavior SIM OP: Fail the 1-1601-33B Drywell Torus Vacuum Breaker 20% open using malfunction PC04G:
imf pc04g 20 Key Parameter Response: Drywell and Torus pressure equalize.
Expected Annunciator(s): 901-3 C-13, 901-3 G-11 Automatic Actions: None Reports Division I and Division II Torus Vacuum Breaker Open BOP annunciators are In alarm.
Determines the 1-1601-33B Drywell to Torus Vacuum Breaker is open BOP from the SER.
BOP Refers to QCAN 901-3 C-13 and QCAN 901-3 G-11.
BOP Reports Drywell and Torus pressures starting to equalize.
Dispatches an EO to the 2251-24 panel to verify open and/or dual BOP indication for the 1-1601-33B vacuum breaker SIM OP ROLE PLAY: As a System Engineer on a plant walkdown, 1 minute after the alarm, call into the control and report that you inadvertently bumped a pushbutton on the 2251-24 panel.
SIM OP ROLE PLAY: As EO, wait 1 minute after dispatch then call in from the 2251-24 panel and report: The 1-1601-33B Drywell-Torus Vacuum breaker shows dual indication on both Division I and Division II.
BOP Obtains Unit Supervisor concurrence, then directs the EO to cycle the 1-1601-33B Vacuum breaker by depressing the test pushbutton.
SIM OP ROLE PLAY: If directed by the BOP, cycle the 1-1601-33B by inserting the following commands:
mmf pc04g 100 wait 3 seconds then insert mmf pc04g 20 As the EO, report back that:
Position indication went to OPEN then back to INTERMEDIATE.
Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No.1 Event No. 4 Page 2 of 2 Event
Description:
Drywell-Torus Vacuum Breaker Fails Open Time Position Applicants Actions or Behavior BOP Contacts Instrument Maintenance to investigate.
BOP Reports Drywell to Torus differential pressure is < 1.0 psid.
SRO Enters the following Technical Specification LCOs:
TS 3.6.1.1, Condition A, Primary Containment inoperable. (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)
TS 3.6.1.8, Condition C, One Suppression Chamber-to-Drywell Vacuum Breaker not closed. (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
TS 3.6.2.5 Condition A, Drywell to Suppression Chamber differential pressure not within limit. (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)
ATC Continuously monitors RPV power, pressure, and water level.
End of Event 4 Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 1 Event No. 5 Page 1 of 2 Event
Description:
1A Recirc Pump Trip Time Position Applicants Actions or Behavior SIM OP: Trip the 1A Recirc Pump using malfunction RR01A:
imf rr01a Key Parameter Response: RWL initially oscillates between 36 and 26 inches, Rx power drops to approx. 54%, Rx. pressure lowers to approx. 960 psig.
Expected Annunciator(s): 901-4 A-1, 901-4 A-3, 901-4 A-5, 901-4 B-2, 901-5 E-8, 901-5 F-8 Automatic Actions: None ATC Reports the 1A Recirc Pump has tripped and refers to annunciator procedures.
Trip of 2nd Recirc pump OR Indication of core instabilities.
SRO Directs action of QCOA 0202-04, Reactor Recirc Pump TripSingle Pump.
ATC Monitors for oscillations in SRM period or LPRM/APRM levels.
ATC Places the RWM in Power Reduction Mode and depresses Array Mode to latch all CRAM rods.
ATC Inserts CRAM rods as needed to lower FCL and to avoid /exit Instability Regions I and II.
ATC/BOP Verifies speed on operating Recirc Pump is < 78% and maintains pump motor current < 770 amps as indicated on 1-202-730B, PMP CUR.
ATC/BOP Closes MO 1-202-5A, PMP DISCH VLV, then re-opens it after 5 minutes.
ATC/BOP Verifies operating loop flow is < 49 Mlb/hr.
ATC/BOP Monitor for 50°F differential temperature between Recirc Loops.
BOP Monitors RPV bottom head temperature.
ATC/BOP Dispatch EO to Bus 11 and 1A ASD to investigate.
SIM OP ROLE PLAY: If dispatched, as EO, wait 3 minutes then report from Bus 11:
The breaker has tripped on overcurrent. Ive contacted EMs to assist.
Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 1 Event No. 5 Page 2 of 2 Event
Description:
1A Recirc Pump Trip Time Position Applicants Actions or Behavior SRO Notifies QNE and Generation Dispatch of tripped Recirc Pump.
BOP Contacts Chemistry department and informs then of load drop of >
30%.
SRO Enters TS 3.4.1 Condition C and contacts Instrument Maintenance to apply APRM/RBM set point changes for single loop operation. TS SIM OP ROLE PLAY: If contacted, as the QNE, after being briefed on the 1A Recirc Pump trip inform the caller that you:
Will implement the Single Loop Thermal Limits in Powerplex and review the control rod pattern for any adjustments that may be necessary.
SIM OP ROLE PLAY: If contacted, as Chemistry Technician state that you :
Will start taking reactor coolant samples and analyzing for I-131 equivalent.
SIM OP ROLE PLAY: If contacted, as Generation Dispatch, acknowledge the down power due to the Recirc Pump trip.
SIM OP ROLE PLAY: If contacted, as Instrument Maintenance Supervisor, when contacted to apply APRM/RBM single loop set points state that:
You will brief a crew on QCIPM 0756-06 and have them report to the control room to adjust the APRM/RBM set points.
End of Event 5 Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 1 Event No. 6/7/8/9 Page 1 of 5 Event
Description:
LOCARecirc Loop A Discharge Pipe Break Time Position Applicants Actions or Behavior SIM OP: Insert a .1% break in the A Recirc Loop Discharge piping ramped over 5 minutes using malfunction RR11A:
imf rr11a .1 5:
Key Parameter Response: Drywell and Torus pressure/temperature rises, RPV water level lowers when injection sources are lost, RPV pressure lowers Expected Annunciator(s): 901-3 A-16, 901-3 G-15, 901-4 A-17, 901-4 B-17, 901-5 D-11, 901-5 B-10/B-15 Automatic Actions: Rx. scram, ECCS auto starts, ECCS load shedding Acknowledges 901-3 A-16, PRI CMNT HIGH PRESSURE, alarm and BOP reports rising Drywell pressure.
Enters and directs actions of QCOA 0201-01. Sets scram criteria on SRO high Drywell pressure.
Attempts to locate and isolate leak. Checks Recirc pump seals, BOP RBCCW alarms, PIC1-1640-11, CONTAINMENT PRESS for normal operation.
SIM OP NOTE: Verify trigger 1 goes true when Drywell pressure reaches 1.5 psig. If not, set it true with the following command:
trg! 1 BOP Starts all available Drywell cooling.
BOP Notifies Radiation Protection of elevated Containment pressure and evacuates the Reactor Building.
SRO Directs a manual reactor scram.
Depresses both RX SCRAM CH A and CH B Pushbuttons. Places the ATC Reactor Mode Switch to SHUTDOWN.
Reports all rods in, RPV water level < 0 inches and recovering, RPV ATC pressure < 1060 psig and controlled with Main Turbine Bypass Valves.
Enters QGA 100 on low RPV water level. Re-enters QGA 100 and SRO enters QGA 200 on high Drywell pressure.
ATC Carries out QCGP 2-3, Reactor Scram, actions.
Verify auto actions for 0 in. RPV water level (Group III) and 2.5 psig ATC/BOP Drywell pressure (Group II).
Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 1 Event No. 6/7/8/9 Page 2 of 5 Event
Description:
LOCARecirc Loop A Discharge Pipe Break Time Position Applicants Actions or Behavior Reports Bus 11 and Bus 12 are NOT energized from Transformer 12.
ATC/BOP (Event 7)
Acknowledges 901-8 F-3, 4KV BUS OVRCUR TRIP, alarm and ATC/BOP dispatches an EO to Busses 11 and 12 to investigate. (Event 7)
SIM OP ROLE PLAY: If dispatched, wait 5 minutes, then as the EO report:
Bus 12 has an overcurrent target up and the Reserve Feed Breaker T-12 to Bus 11 did not close. Ive contacted Electrical Maintenance to assist.
Reports the U-1 EDG did NOT auto start, then manually starts the U-1 EDG by placing the control switch to START and verifies the following:
- U-1 EDG Cooling Water Pump starts
- Voltage 3952 to 4368
- Frequency 58.8 to 61.2 Hz. (Event 8)
Directs RPV water level band of 0 to +48 inches using Preferred SRO Systems: HPCI/RCIC/SSMP.
Reports the RCIC Trip Throttle Valve has tripped and dispatches an ATC/BOP EO to investigate. (Event 9)
SIM OP ROLE PLAY: Wait 5 minutes then report back as the EO from the RCIC Room:
The RCIC Trip Throttle Valve linkage is damaged and cannot be reset.
ATC/BOP Starts HPCI and/or SSMP for injection and controls RPV water level within 0 to +48 in. band.
SRO Directs an RPV cooldown at < 100°F/hr using main turbine bypass valves.
SRO Directs actions of QGA 200, Primary Containment Control.
SRO Directs BOP to spray the Torus when Torus pressure exceeds 2.5 psig.
BOP Starts Torus sprays and monitors containment response.
BOP Reports Torus pressure 5 psig and rising. Verifies Torus level below 17 ft.
Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 1 Event No. 6/7/8/9 Page 3 of 5 Event
Description:
LOCARecirc Loop A Discharge Pipe Break Time Position Applicants Actions or Behavior SRO Checks the DSIL curve and verifies both Recirc pumps are tripped and Drywell Coolers are secured.
CT1 SRO Directs BOP to initiate Drywell Sprays.
CT1 BOP Starts Drywell Sprays and reports containment temperature and pressure are lowering.
BOP Secures Drywell or Torus sprays before the respective volume reaches 0 psig.
SRO Directs BOP to initiate Torus Cooling and monitor Torus temperature.
BOP Starts Torus Cooling on one or both loops and monitors Torus temperature.
BOP Reports containment Hydrogen level at 0%.
SIM OP NOTE: When RPV water level is stabilized and Drywell sprays have been initiated, then trip the HPCI turbine using malfunction HP01 and modify the 1A Recirc Discharge Pipe break to .5%:
imf hp01 mmf rr11a .5 BOP Reports HPCI turbine has tripped and dispatches an EO to the HPCI room. (Event 9)
SIM OP ROLE PLAY: If dispatched to the HPCI room, wait 5 minutes, then as the EO call back and report :
The HPCI turbine is not running, the Stop valve is closed, and the Emergency Oil pump is running. Ill call Mechanical and Electrical Maintenance for assistance.
BOP Reports RPV water level lowering.
SRO Directs second CRD pump started for injection per QCOP 0300-16.
SIM OP ROLE PLAY: If dispatched to valve in the 2nd set of CRD suction filters, wait 2 minutes, then as EO report:
The 2nd set of CRD filters are valved in.
BOP Reports RPV water level 0 inches and lowering.
SRO Directs Alternate Systems for injection.
Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No.1 Event No. 6/7/8/9 Page 4 of 5 Event
Description:
LOCARecirc Loop A Discharge Pipe Break Time Position Applicants Actions or Behavior SRO Directs ATC to inject with SBLC system.
ATC Starts both SBLC pumps and reports system injection.
CT2 SRO Directs BOP to inhibit ADS.
BOP Reports RPV water level at -59 in. and lowering.
BOP/ATC Reports Group I isolation on RPV low-low level.
SRO Transitions to Alternate Level Control Leg of QGA 100 and verifies at least 2 Injection Subsystems (Detail F) are available.
BOP Reports all Low Pressure ECCS Subsystems and Safe Shutdown Makeup Pump are available.
BOP Bypasses 2/3 Core Height interlock after receiving permission from the Unit Supervisor.
BOP Reports RPV water level at -142 inches.
SRO Verifies all Injection Subsystems are lined up with pumps running.
SRO Transitions to QGA 500-1 before RPV water level drops to -190 inches.
SRO Verifies all rods are in.
SRO Verifies Drywell pressure < 2.5 psig.
SRO Directs BOP to maximize injection to the RPV.
BOP Secures Containment Sprays and Torus Cooling.
SRO Verifies Torus level is above 5 ft.
CT3 SRO Directs all 5 ADS Valves opened and switches left in Manual.
CT3 BOP Opens all 5 ADS Valves and leaves switches in the MAN position.
BOP Confirms and reports all 5 ADS valves are open by acoustic monitor indication on the 901-21 panel.
BOP Monitors RPV pressure and reports at 325 psig.
Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No.1 Event No. 6/7/8/9 Page 5 of 5 Event
Description:
LOCARecirc Loop A Discharge Pipe Break BOP Verifies all ECCS Subsystems inject at RPV pressure < 325 psig.
ATC Monitors and reports RPV water level rising.
ATC Reports RPV water level above -142 in. (TAF) and rising.
SRO Directs BOP/ATC to establish RPV water level band of 0 to +48 in.
SRO Directs BOP to secure/operate ECCS systems as necessary to restore and maintain RPV water level in band.
ATC/BOP Report RPV water level above 0 inches and controlling in 0 to 48 in.
band.
SIMOP NOTE: When Blowdown has been performed and RPV water level restored in band, with concurrence of the Lead Examiner, place the simulator in FREEZE.
End of Scenario.
Quad Cities 2016 NRC EXAM Scenario 2 Exelon Nuclear 2016 ILT NRC Exam Scenario Scenario Number:
NRC Scenario 2 Revision Number: 00 Date: 10/12/15 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date Quad Cities 2016 NRC EXAM Scenario 2 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2016 NRC Scenario 2 Op-Test No.: ILT 14-1 Examiners: ________________________ Operators:_____________________________
Initial Conditions:
The plant is operating at 50% power. Power was lowered due to Load Following for Grid Stability. Work on the Nelson-345KV Junction is completed. The Unit is returning to full power. 1B Service Water Pump and 1A Stator Cooling Water pump are out of service for repair.
Turnover:
Reverse Main condenser flow and raise power to 100% per ReMA instructions.
Event Malf. No. Event Event No. Type* Description 1 None BOP Reverse Main Condenser flow N
2 None ATC Raise power after Load Following R
3 RD02R2255 ATC Recoverable Stuck Rod / Raise CRD Drive C Pressure (QCOA 0300-02) 4 RM05B SRO B Drywell Rad Monitor Upscale Failure TS 5 NM10A ATC RBM Channel 7 fails high TS I
6 dihs15401 close BOP SJAE suction valves fail shut. BOP recovers C them by QOA 901-7 A-14 actions.
7 TU02A BOP Main Turbine high vibration (Leading to Turbine C Trip) 8 RD 13A Crew ATWS. No rod motion. The Crew will take (Hydraulic ATWS) M actions per QGA 101 to control reactor power, level and pressure.
9 RP10A(B) ATC The Group III (RWCU) fails to actuate. The ATC C will manually isolate RWCU.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:
Total Malfunctions (5-8): 6 BOP Normal: E1 Malfunction(s) after EOP (1-2): E9 ATC Reactivity (1 per set): E2 Abnormal Events (2-4): E3, 5, 6, & 7 BOP I/C (4 per set): E6 & 7 Major Transient(s) /E-Plan entry (1-2):E8 ATC I/C (4 per set): E3, 5 & 9 EOPs (1-2): QGA 100 and 101 SRO-I I/C (4 per set inc 2 as ATC):
EOP Contingencies (0-2): 1 E3, 5, 6, 7, 9 Critical Tasks (2-3): 4 SRO Tech Spec (2 per set): E4 & 5 ALL Major Transients (2 per set) E8 Quad Cities 2016 NRC EXAM Scenario 2
SUMMARY
- Initial conditions:
o The plant is operating at 58% power. Power was lowered due to Load Following for Grid Stability. There was work done on the Nelson-345KV Junction. All work was completed. The Unit is returning to full power. 1B Service Water Pump and 1A Stator Cooling Water pump are out of service for repair.
- Event 1: When Engineering is ready, the BOP operator reverses Main Condenser Flow.
- Event 2: Raise power with control rods and recirculation flow to 100% power.
- Event 3: Recoverable Stuck Rod / Raise CRD Drive Pressure. The ATC and SRO respond per QCOA 0300-02. The control rod is freed after raising drive water pressure per the procedure.
- Event 4: B Drywell Rad Monitor Upscale Failure (TS). The BOP and SRO respond per QCAN 901-56 A-1 and Technical Specifications 3.3.3.1 Condition A and 3.3.6.1 Condition A.
- Event 5: RBM Channel 7 fails high. The ATC and SRO Respond per QCAN 901-5 A-7 to bypass the faulty RBM after the SRO references Technical Specification 3.3.2.1 Condition G.
- Event 6: The on-line SJAE suction valves fail shut due to an intermittent failure. The failure is revealed by annunciator 901-7 A-14 and valve position indication. The BOP will be able to recover the SJAEs by carrying out the QCAN actions and re-opening the valves to maintain Main Condenser vacuum.
- Event 7: The BOP responds to Main Turbine high vibration per QCAN 901-7 D-2 and QCOS 5600-01. The BOP has several actions to complete in an attempt to mitigate the effects of the high vibrations. The vibrations will continue to raise until the crew scrams the reactor and trips the Main Turbine.
- Event 8: When the ATC inserts a manual scram no control rods will insert. The crew will recognize they are in a hydraulic ATWS and enter QGA 100, RPV Control and then they will rapidly transition to QGA 101 RPV Control (ATWS). The crew will attempt to insert control rods per QCOP 0300-28, but they will have little success beyond driving individual driving rods. The SRO will enter the Level/Power Control section of QGA 101 and lower reactor level to control reactor power.
- Event 9: After entry into QGA 101, the Group III (RWCU) will fail to actuate when SBLC is started. The ATC will manually isolate RWCU.
- Approximate Run Time: 1.5 Hours Quad Cities 2016 NRC EXAM Scenario 2 CRITICAL TASKS:
Critical task #1: With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron (prior to exceeding 110°F torus temperature) and/or inserting control rods, to prevent exceeding primary containment design limits. (BWROG RPV-6.1 ATWS PWR/LVL S/D REACTOR)
Critical task #2: With a reactor scram required and the reactor not shutdown, and conditions for ADS blowdown are met, INHIBIT ADS to prevent an uncontrolled RPV depressurization, to prevent causing a significant power excursion. (BWR RPV-6.2 ATWS PWR/LVL INHIBIT ADS)
Critical task #3: During an ATWS with conditions met to perform power/level control, TERMINATE AND PREVENT INJECTION, with the exception of boron, CRD and RCIC into the RPV until conditions are met to re-establish injection.
(BWROG RPV-6.3 PWR/LVL TERM/PREVENT)
Critical task #4: When conditions are met to re-establish injection, use available injection systems to MAINTAIN RPV water level above the Minimum Steam Cooling RPV Water Level (-190"). (BWROG RPV-6.4 ATWS PWR/LVL RESTORE RPV LVL)
Quad Cities 2016 NRC EXAM Scenario 2 EXERCISE PERFORMANCE OBJECTIVES Objective Objective Description SR-0001-P11 Given a reactor plant with an ATWS, take action to reduce heat input into the containment in accordance with QGA 101. (SOER 83-8 r11) (ATWS is a key event in 1 of the 100 most probable PRA Core Damage Sequences)
SR-0001-P13 Given a reactor plant with an ATWS and conditions are met to re-establish RPV injection during power/level control, use Preferred ATWS Systems (QGA Detail G) to attempt to maintain RPV water level between -190 inches and the level to where it was lowered in accordance with QGA 101.
SR-0001-P45 Given a reactor plant in a QGA condition, verify the proper actuation of containment isolations and ECCS and emergency DG starts in accordance with QGA 100 or QGA 101.
SR-0002-P03 Given a reactor plant at power with a reactor scram, place the plant into a stable condition in accordance with QCGP 2-3.
SR-0002-P04 Given a reactor plant at power, perform a power change discernible on neutron monitors using control rods in accordance with QCOP 0280-01, QCGP 3-1 and QCGP 4-1.
SR-0203-P07 Given a reactor plant in a QGA condition, inhibit ADS in accordance with QGA 100 or QGA 101. (Important PSA task / Inhibiting ADS terminates 5 of top 200 Core Damage Sequences)
SR-0300-P05 Given a reactor plant during a startup with a stuck control rod, restore the ability to drive the control rod or declare the rod inoperable in accordance with QCOA 0300-02.
SR-0302-K26 EVALUATE given key Control Rod Drive parameter indications and/or responses depicting a system specific abnormality/failure and DETERMINE a course of action to correct or mitigate the following abnormal condition(s):
- c. Stuck Rod SR-0700-P10 Given an operating reactor plant with control rod moves occurring to adjust FCL, operate and monitor the RBM in accordance with QCOP 0700-05.
SR-1100-P02 Given a reactor plant with an ATWS, inject boron prior to exceeding 110 degrees torus water temperature OR if core instability is observed in accordance with QGA 101 and QCOP 1100-02. (Important PRA Operator Action - starting SBLC terminates 1 of the top 100 most probable Core Damage Sequences and has a RAW of 17.3)
SR-1603-K32 Given Primary Containment Isolation (PCI) System operability status OR key parameter indications, various plant conditions and a copy of Tech Specs, DETERMINE Tech Spec compliance and required actions, if any.
SR-3300-P09 Given a reactor plant at power with a loss of condenser vacuum, take action to attempt to locate and correct the cause for lowering vacuum in accordance with QOA 3300-02 and/or QOA 5450-05. (PRA Initiating Event %TC - Loss of Vacuum accounts for 4.2% of total CDF and initiates 4 of the top 100 Core Damage Sequences)
Quad Cities 2016 NRC EXAM Scenario 2 EXERCISE PERFORMANCE OBJECTIVES Objective Objective Description SR-4400-P02 Given an operating reactor plant, reverse main condenser circ water flow in accordance with QCOP 4400-09.
SR-5600-K20 Given a Main Turbine and Auxiliary Systems operating mode and various plant conditions, EVALUATE the following Main Turbine and Auxiliary Systems indications/responses and DETERMINE if the indication/ response is expected and normal.
- d. Turbine eccentricity, vibrations and bearing metal temperatures Quad Cities 2016 NRC EXAM Scenario 2 Simulator setup:
- 1. Reset to IC-19 (Approximately 50% power).
- 2. Go to RUN.
- 3. Verify the following RWM Sequence is loaded: 4PHESU
- a. Mark up the Control Rod Move Sheet to reflect rod step 30 two rods withdrawn to target out
- 5. Verify the North SJAE suction valves are open (Commands to be utilized during this scenario are contained in the CAEP file:
2016 NRC Scenario 2.cae)
- 5. Insert Commands for setup:
imf rd02r2255 00 stick control rod 38-31 at position 00 trgset 1 'rdpdrivedelta .ge. 340' Set trigger 1 true when CRD pressure exceeds 340psid trg 1 'dmf rd02r2255' Delete stuck rod on trigger 1 imf rd13a 100 Hydraulic ATWS imf rd13b 100 Hydraulic ATWS Group III Failures imf rp10A Group III failure imf rp10B Group III failure
- 6. Verify the following commands for scenario performance:
SJAE suction valve closure trgset 14 'zloil15402asjae(1).and.zloil15401asjae(1)' triggers for SJAE closure trg 14 'dor dihs15401' Delete override on SJAE Control Switch ior dihs15401 close Close SJAE suction with override Malfunctions imf nm10a 100 RBM 7 Fails Upscale imf rm05a 100 5: A Drywell Rad Monitor Upscale Failure, with a five minute ramp imf tu02d 50 15: Main Turbine High Vibrations imf tu02c 30 15: Main Turbine High Vibrations imf tu02e 30 15: Main Turbine High Vibrations In plant support activities irf rd04r closed Close the CRD 25 Valve irf qg09r 1 Bypass isolations per QCOP 0250-02 irf qg08r 1 Bypass all reactor scrams irf qg14r 1 Pull the ARI fuses in the 2201-70A and 2201-70B panels in Aux Electric Room Quad Cities 2016 NRC EXAM Scenario 2
- 1A SCW Pump
- 1B SW Pump
- 8. Complete the following Control Panel setup items:
- Verify Main Condenser Circ Water Flow is South (North SJAE suctions open)
- Verify the LOCA TRIP ENABLED labels are above the 1A and 1C Circ Water Pumps.
- Display the Power/Flow Map on Monitor 3.
- Clear all SBO Panel alarms.
- 9. Provide a current revision of the following procedures, signed off as specified:
- QCOP 4400-09 (no steps signed off)
- QCGP 3-1 marked off through step F.3.d.
- 10. Provide scenario 2 REMA
- Withdraw rods to 95% FCL
- Raise core flow to 98 Mlbm/hr
- Withdraw rods to 100% FCL
- 11. Perform the applicable steps of TQ-QC-201-0113 Simulator Exam Security Actions Checklist.
- 12. Ensure (1) orange ring is available to provide equipment status.
- 13. Ensure 2 ESTs are available to provide equipment status.
Quad Cities 2016 NRC EXAM Scenario 2 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901(2)-5 A-7, RBM HIGH OR INOP, Rev. 5 o 901(2)-5 C-3, ROD OUT BLOCK, Rev. 11 o 901(2)-5 C-6 APRM DOWNSCALE, Rev. 5 o 900-56 A-1 DRYWELL HIGH RAD CONC, Rev. 11 o 900-7 A-14, AIR EJECTOR NORTH SUCTION VALVES CLOSED, Rev. 10 o 901(2)-7 D-2 UNIT 1 TURBINE GENERATOR BEARING HIGH VIBRATION, Rev. 6 QCGP 1-1, Normal Unit 1 Startup, Rev. 104 QCGP 2-3, Reactor Scram, Rev. 84 QCGP 4-1, Control Rod Movements And Control Rod Sequence, Rev. 46 QCOA 0300-02, Inability to Drive A Control Rod: Control Rod Stuck, Rev. 21 QCOA 0700-03, Loss of Neutron Flux Indication. Rev. 9 QCOA 5600-01, Main Turbine High Vibration, Rev. 16 QCOP 1000-30, Post-Accident RHR Operation, Rev. 31 QCOP 300-28, Alternate Control Rod Insertion Rev. 31 QCOP 4400-09, Circulating Water System Flow Reversal, Rev. 28 QCOP1100-02, Injection of Standby Liquid Control, Rev. 12 QCOS 1600-06, ECCS AND Primary Containment Isolation Trip Instruments Outage Report, Rev. 21 QGA 100, RPV Control, Rev. 10 QGA 101, RPV Control (ATWS), Rev. 14 QOP 0700-05, Rod Block Monitor, Rev. 16 Quad Cities 2016 NRC EXAM Scenario 2 CREW TURNOVER
- Plant Conditions:
a.) Unit 1 is at 50% power.
Power was lowered due to Load Following for Grid Stability. There was work done on the Nelson-345KV Junction. All work was completed. The Unit is returning to full power.
b.) Unit 2 is at 100% power.
c.) Technical Specification limitations:
(1) Unit 1: None (2) Unit 2: None d.) On Line Risk is GREEN.
2.) Significant problems/abnormalities:
a.) 1A Stator Cooling Water pump is OOS for replacement. 1B Stator Cooling Water pump is protected.
b.) 1B SW pump is OOS for packing replacement. The expected duration is less than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
3.) Evolutions/maintenance for the oncoming shift:
a.) Engineering is doing an evaluation on Circ Water and wants to monitor some parameters during Condenser Flow Reversal. When they report that they are ready, reverse Main Condenser Flow per QCOP 4400-09. Backpressure is not expected to exceed 6 Hg. All involved personnel have been briefed on the evolution.
b.) Raise reactor power to 100% with rods and recirc.
- i. Withdraw rods to 95% FCL ii. Raise core flow to 98 Mlbm/hr iii. Withdraw rods to 100% FCL Quad Cities 2016 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 1 Page 1 of 1 Event
Description:
Reverse Main Condenser Flow from South to North Time Position Applicants Actions or Behavior SIMOP ROLE PLAY: Contact the Unit Supervisor as the EO standing by with Engineering (phone 2300):
Engineering is ready to monitor Circ Water, Condenser Flow Reversal may proceed.
SRO Directs Main Condenser flow reversal per QCOP 4400-09.
SIMOP ROLE PLAY: As necessary, provide the appropriate acknowledgements as the Equipment Operator stationed at MCC 16-3 or Engineering personnel.
BOP Establish communications with the Equipment Operator stationed at MCC 16-3.
BOP (Continuous) Monitors Condenser Backpressure and Condensate Temperatures.
BOP Verifies OFFGAS FLOW TO MAIN CHIMNEY on FR-1-5440-7 (901-54 panel) is >15 scfm.
BOP Verifies Annunciator 901-7 C-1, COND FLOW REV VLVS ON LOCAL CONT, is NOT in alarm.
BOP Opens South SJAE Suction valves using the Test switch on the 901-7 panel by placing the switch to the SOU position.
BOP Places the Circulating Water Flow Selector switch to the NORTH position when the South SJAE valves are fully open.
BOP Verifies the following:
- SJAE Suction valves change over
- Condenser differential pressure has reversed and vacuum is stable ATC Monitors reactor and RPV parameters.
End of Event 1 Quad Cities 2016 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 2 Page 1 of 1 Event
Description:
Raise Reactor power with control rods Time Position Applicants Actions or Behavior SIMOP ROLE PLAY: If the crew does not promptly begin the task, call the control room as the Shift Manager and prompt them to begin.
LEAD EVALUATOR ROLE PLAY: If the crew decides to verify they are within the thermal limits, role play as the QNE and state: Thermal limits have been verified.
Role Play as the Qualified Verifier (QV) as necessary.
Directly supervises control rod moves and reactor recirculation SRO adjustments.
Directs the RO to begin to raise power to 100%..
ATC (CONTINUOUS) Monitors reactor parameters.
ATC Selects an in-sequence control rod.
On the RWM verifies proper rod is selected, its current position and ATC bounds.
Communicates to the QV. Ready to Withdraw Rod P-8 from position ATC 00 to position 48 using continuous withdrawal.
Replies: Rod P-8 isselected. Understand withdrawing Rod P-8 from QV/BOP position 00 to position 48 using continuous withdrawal.
ATC Replies: That is correct.
ATC Verifies control rod and moves it to the desired position.
ATC/BOP Place keeps rod moves in the rod movement book.
ATC Repeats above steps as necessary for the next control rods BOP Monitors balance of plant parameters.
End of Event 2 Quad Cities 2016 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 3 Page 1 of 1 Event
Description:
Recoverable Stuck Rod / Raise CRD Drive Pressure Time Position Applicants Actions or Behavior EVALUATOR NOTE: Control Rod F-14 will not move from position with normal drive water pressure; CRD Drive Pressure indication is on 901-5, 1-340-4.
Expected Annunciator(s): None Automatic Actions: None ATC Reports CR F-14 will not move.
SRO Directs RO to perform the actions of QCOA 0300-02.
ATC Verifies no Rod Block exists.
ATC Verifies no RWM select block exists.
ATC Verifies the proper control rod is selected.
Raises CRD drive water pressure in 50 psig increments by throttling ATC closed on the 1-302-8 valve.
SIMOP NOTE: When CRD drive water pressure is greater than 340 psid, verify Event Trigger 1 goes true to delete malfunction dmf rd02255.
Attempts to withdraw Control Rod F-14 and identifies normal control ATC rod movement.
ATC Continues normal control rod withdrawal.
ATC Restores drive water pressure to normal.
QV/BOP Provides peer check as required.
BOP Monitors balance of plant parameters.
LEAD EVALUATOR NOTE: If the crew does not continue to raise power, prompt the crew.
This is necessary for moving to the next event.
End of Event 3 Quad Cities 2016 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 4 Page 1 of 1 Event
Description:
RBM Channel 7 fails high Time Position Applicants Actions or Behavior SIMOP NOTE: When rod F-14, has been withdrawn to position 48, initiate the RBM Upscale malfunction. (Malfunction expert command: imf nm10a 100)
Key Parameter Response: Rod Out Permissive light is OFF; RBM CH 7 indicates upscale Expected Annunciator(s):
901-05 A-7 RBM HIGH OR INOP 901-05 C-3 ROD OUT BLOCK Automatic Actions: Rod Block ATC Responds to unexpected annunciators and informs the Unit Supervisor.
ATC Determines RBM channel 7 is UPSCALE.
ATC Verifies that a ROD BLOCK is in effect.
BOP May verify RBM 7 is upscale at the 901-37 panel meter.
ATC Verifies the correct rod was being withdrawn.
ATC May depress the PUSH SETUP button.
May attempt to re-null the RBM by selecting an edge rod and then re-ATC selecting the desired rod.
Contacts Instrument Maintenance to investigate the upscale failure of SRO RBM 7.
SIMOP ROLE PLAY: As Instrument Maintenance, inform the Unit Supervisor you will:
Start a work package to troubleshoot and replace components as needed. It will take approx. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to complete the package and 1 shift to complete the work.
SRO Directs RBM 7 bypassed per QOP 0700-05.
ATC Bypasses RBM 7 by placing the RBM BYPASS joystick to the CH 7 position and logs the time.
SRO Enters TS 3.3.2.1 Control Rod Block Instrumentation, Condition A for one rod block monitor inoperable.
EVALUATOR NOTE: The crew may return to Event 3 to continue the reactivity manipulation.
End of Event 4 Quad Cities 2016 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 5 Page 1 of 1 Event
Description:
Drywell Rad Monitor Failure Time Position Applicants Actions or Behavior SIMOP NOTE: When directed by the Lead examiner, start the Drywell Rad Monitor Failure event (expert command: imf rm05a 100 5:)
Key Parameter Response: 1-2419A Drywell Radiation Monitor indicating full upscale Expected Annunciators:
901-5 A-8, GROUP 2 ISOL CH TRIP 901-55 A-1, DRYWELL HIGH HIGH RAD CONC Automatic Action: 1/2 Group 2 Isolation BOP Acknowledges annunciator 901-55 A-1, DRYWELL HIGH HIGH RAD CONC and reports the 1-2419A Drywell radiation monitor is indicating full upscale.
ATC Acknowledges annunciator 901-5 A-8, GROUP 2 ISOL CH TRIP and refers to annunciator procedure.
SRO Confirms the 1-2419B Drywell radiation monitor is indicating normally (approximately 3-4 R/hr).
EVALUATOR ROLE PLAY: If the BOP goes to confirm the PCI Relays have dropped out:
CUE the following on Panel 901-15
- Relay 595-104A dropped out
SIMOP ROLE PLAY: As RP, inform the Control Room that you will:
Implement compensatory actions for the Drywell Radiation Monitor.
As IMD, if informed of the failed DW radiation monitor, state you will:
Start a work package.
SRO Enters the following Technical Specifications for an inoperable Drywell Radiation monitor:
- PCI 3.3.6.1, Condition A, Place the Channel in Trip Within 24 Hours
- PAM 3.3.3.1, Condition A, Restore Required Channel to Operable Status Within 30 Days End of Event 5 Quad Cities 2016 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 6 Page 1 of 1 Event
Description:
SJAE Suction Valve Closure Time Position Applicants Actions or Behavior SIMOP NOTE: When directed by the Lead Examiner, insert override to cause the SJAE suction valves to shut with the following command (The command is on page 3 of the CAEP file):
ior dihs15401 close Key Parameter Response: SJAE suction valves close Expected Annunciator(s): 901-7 B-14, AIR EJECTOR SOUTH SUCTION VAVLES CLOSED Automatic Actions: None BOP Announces Air Ejector suction valve alarm 901-7 B-14 SRO Directs BOP to perform actions of QCAN 901-7 B-14 SRO Sets scram criteria for high condenser backpressure BOP Verifies SJAE valves closed BOP Verifies Circ Water Flow from South Attempts to open SJAE suction valves by placing SJAE SUCT VLV BOP C/S on Panel 901-7 to OPEN.
BOP Reports SJAE suction valves are open End of Event 6 Quad Cities 2016 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 7 Page 1 of 1 Event
Description:
Main Turbine High Vibration Time Position Applicants Actions or Behavior SIMOP NOTE: When directed by the Lead Examiner, insert malfunctions to cause high Main Turbine vibrations on 3 bearings:
imf tu02d 50 15:
imf tu02c 30 15:
imf tu02e 30 15:
Key Parameter Response: Main Turbine vibrations began to rise Expected Annunciator(s): 901-7 D-2, UNIT 1 TURBINE GENERATOR BEARING HIGH VIBRATION Automatic Actions: None BOP May notice Main Turbine vibrations rising BOP Announces alarm 901-7 D-2 and reports bearing 4 is at 7 mils SRO Directs BOP to perform actions of QCAN 901-7 D-2.
SRO Sets scram criteria for high Main Turbine vibrations of 10 mils Verifies high vibration is valid by observing bearings 3 and 5 also have BOP high vibrations BOP Refers to QCOA 5600-01 BOP Reports when bearing 4 reaches 10 mils ATC Inserts manual scram BOP Trips the Main Turbine Lead Evaluator Note: ATWS actions are contained in Events 8 and 9.
End of Event 7 Quad Cities 2016 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 8 Page 1 of 3 Event
Description:
ATWS Time Position Applicants Actions or Behavior SIMOP NOTE: Be prepared to verify the Group III isolation failed.
ATC Reports control rods did NOT insert SRO Enters QGA 100, transitions to QGA 101 ATC Places the Mode Switch in SHUTDOWN ATC Arms and depresses ARI SRO Directs BOP to inhibit ADS CT2 BOP Inhibits ADS SRO Directs BOP to place both Core Spray pumps in PTL BOP Places both Core Spray pumps in PTL SRO Directs actions for Power Leg of QGA 101 SRO Directs control rod insertion per QCOP 0300-28 ATC May dispatch EO to close the 1-301-25, U-1 CRD CHARGING WTR SV if control rods cannot be inserted SIMOP ROLE PLAY: If requested as EO, close the 1-301-25 valve using: irf rd04r close CT1 ATC Inserts all CRAM rods to position 00 CT1 ATC Continues to insert control rods spiraling outward from center of core SRO Directs actions of QGA 101 Level Control Leg SRO Directs verification of auto actions and isolations for 0 inches RPV water level BOP Verifies auto actions and isolations for 0 inches RPV water level SRO Directs isolations bypassed per QCOP 0250-02 SIM OP ROLE PLAY: If requested, bypass isolations per QCOP 0250-02: irf qg09r 1 Wait 1 minute and report completion Quad Cities 2016 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 8 Page 2 of 3 Event
Description:
ATWS Time Position Applicants Actions or Behavior BOP Contacts EO to bypass RPV low water level MSIV and high offgas radiation isolations per QCOP 0250-02 ATC Directs operator to bypass all reactor scrams per QCOP 0300-28 SIMOP ROLE PLAY: If requested, wait approx. 2 minutes and bypass all reactor scrams using the following command, then report back:
irf qg08r 1 ATC (If RPV Water Level drops below -59 inches) Dispatches EO to de-energize ARI by removing fuses in 2201-70A and 2201-70B panels per QCOP 0300-28 SIMOP ROLE PLAY: If requested as EO, wait 2 minutes, then pull the ARI fuses in the 2201-70A and 2201-70B panels in Aux Electric Room using the command below and report back:
irf qg14r 1 ATC Directs personnel to individually scram control rods from the 901-16 panel SIMOP ROLE PLAY: Attempt to individually scram 4 control rods (one from each bank),
then contact the ATC operator and report:
Control rods will NOT insert from the 901-16 panel.
LEAD EVALUATOR NOTE: The ATC will inject SBLC as part of the Immediate Operator Actions following the failure of the manual scram. The SRO will also back up this action by directing actions per QGA 101.
CT1 SRO Directs SBLC Injection prior to exceeding 110°F Torus Water Temperature CT1 ATC Initiates SBLC Injection as directed (See Event 9)
SRO Verifies reactor power >5% and RPV water level > -35 CT3 SRO Directs all injection except Boron, CRD, and RCIC terminated and RPV water level lowered to at least -35. (Terminate and prevent from 901-3 and 901-5)
CT3 BOP Performs Terminate and Prevent Injection from Panel 901-3 BOP Places HPCI in Trip-Latch Quad Cities 2016 NRC EXAM Scenario 2 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 8 Page 3 of 3 Event
Description:
ATWS Time Position Applicants Actions or Behavior BOP Verifies RHR Discharge Pressure < Reactor Pressure or places RHR Pumps in Pull-To-Lock CT3 ATC Performs Terminate and Prevent Injection from Panel 901-5
- Places A and B Feed Reg Valve Controllers in MANUAL and reduces output to 0 (zero)
- Places the Low Flow Feed Reg Valve Controller in MANUAL and reduces output to 0 (zero)
ATC Closes A and B Feed Reg Valve Isolations, MO-1-3206-A/B.
ATC/BOP Reports level when Rx power < 5%, RPV water level at TAF or ADS valves are closed with DW pressure < 2.5 psig.
CT4 SRO Directs RPV water level maintained between -190 and the level to which it was lowered CT4 ATC/BOP (CONTINUOUS) Maintains level in the directed band with Preferred Injection systems End of Event 8 Quad Cities 2016 NRC EXAM Scenario 1 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 2 Event No.: 9 Page 1 of 1 Event
Description:
Group III (RWCU) Isolation Failure Time Position Applicants Actions or Behavior ATC Reports SBLC tank level and selects a SBLC pump for injection by placing the control switch to SYS 1 or SYS 2 ATC Verifies and reports the following:
ATC Squib A/B light is off ATC Flow Light is on ATC RWCU System failed to isolate CT1 ATC Manually isolates the RWCU system by closing the MO 1-1201-2 and MO 1-1201-5. (May also close the 1-1201-80, but it is not required.)
ATC SBLC Tank level lowering ATC Pump discharge pressure slightly high than reactor pressure ATC Annunciator 901-5 H-6 SBLC Squib valve circuit failure is on ATC Neutron flux is decreasing ATC Monitors SBLC Tank level for 16% decrease (in approximately 21 minutes)
BOP Performs other operator actions of QGA 101 End of Event 9 SIMOP: When available injection systems are maintaining RPV water level above the Minimum Steam Cooling RPV Water Level (-190"). and/or at the discretion of the Lead Examiner, place the simulator in FREEZE.
(Final)
Quad Cities 2016 NRC EXAM Scenario 3 Exelon Nuclear 2016 ILT NRC Exam Scenario Scenario Number:
NRC Scenario 3 Revision Number: 00 Date: 12/18/15 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date Quad Cities 2016 NRC EXAM Scenario 3 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2016 NRC Scenario 3 Op-Test No.: ILT 14-1 Examiners: ________________________ Operators:_____________________________
Initial Conditions:
The plant is operating at 100% power. Maintaining full power. 1B Service Water Pump and 1A Stator Cooling Water pump are out of service for repair.
Turnover:
Swap running EHC pumps for upcoming maintenance.
Event Malf. No. Event Event No. Type* Description 1 None BOP Swap running EHC pumps per QCOP 5650-01 N Step F.4 2 SW02A (degraded) BOP 1A Service Water pump degrades resulting in C swapping to standby pump per QCAN 912-1 B-3.
3 None (cued) BOP 1C RFP bearing failure requiring shutdown of the C 1C RFP 4 None ATC Emergency power reduction, per QCGP 3-1 step R F.1, to secure 1C RFP 5 NM08A ATC APRM channel 1 fails As Is during Emergency I Power reduction TS 6 zdihs11300rm(1) BOP RCIC spurious start and subsequent manual trip C from MCR TS 7 HP12 CREW Fuel failure and HPCI steam line break. Crew HP13 M enters QGA 300 and transitions to QGA 500-1 CR01 when two areas exceed Max Safe radiation levels.
CR02 8 NM03A-D ATC SRMs and IRMs fail to automatically insert. The NM07A-H I ATC will manually insert them per QCGP 2-3 and QCOP 0700-01 guidance
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:
Total Malfunctions (5-8): 6 BOP Normal: E1 Malfunction(s) after EOP (1-2): E8 ATC Reactivity (1 per set): E4 Abnormal Events (2-4): E2, 3, 5, & 6 BOP I/C (4 per set): E2, 3, & 6 Major Transient(s) /E-Plan entry (1-2):E7 ATC I/C (4 per set): E5 & 8 EOPs (1-2): QGA 100, 300, and 500-1 SRO-I I/C (4 per set inc 2 as ATC): E2,3,5,6,8 EOP Contingencies (0-2): 1 SRO Tech Spec (2 per set): E5 & 6 Critical Tasks (2-3): 2 ALL Major Transients (2 per set) E7 Quad Cities 2016 NRC EXAM Scenario 3
SUMMARY
- Initial conditions:
o Unit 1 is at 100% power holding load o 1B Service Water Pump and 1A Stator Cooling Water pump are out of service for repair.
- Event 1: The BOP swaps running EHC pumps per QCOP 5650-01 step F.4 from 1A EHC running to 1B EHC pump.
- Event 2: 1A Service Water pump degrades resulting in swapping to a standby pump per QCAN 912-1 B-3.
- Event 3: EO on Rounds reports the 1C RFP is very noisy and appears to have a rapidly degrading outboard pump bearing. The EO and FS are concerned the 1C RFP will fail catastrophically. The BOP will shutdown the 1C RFP per QCOP 3200-05
- Event 4: Emergency power reduction to secure 1C RFP. The ATC will make an Emergency Power Reduction per QCGP 3-1 Step F.1. The ATC will lower power with recirc and rods to < 2511 MWth (~85%).
- Event 5: APRM channel 1 fails As Is during Emergency Power reduction. The ATC will determine APRM channel 1 has failed at ~ 100 power. The SRO will review TS and determine one APRM inoperable is a Tracking Only LCO. The ATC will bypass APRM 1 when directed by the SRO per QCOP 0700-04 Step F.3
- Event 6: RCIC will spuriously start. The BOP will verify no initiation signal exists and the BOP will trip RCIC per QCOP 1300-05 Step F. The SRO will determine RCIC is inoperable and enter the TS LCO.
- Event 7: A fuel failure leads to scram on high off gas radiation. When the reactor scrams, the fuel failure will worsen and HPCI will develop a steam leak. The combination of the fuel failure and steam leak will cause the crew to enter QGA 300, Secondary Containment Control and subsequently QGA 500-1, RPV Blowdown.
- Event 8: After the scram the SRMs and IRMs will fail to automatically insert. The failure will be revealed when the ATC carries out the actions of QCGP 2-3 Attachment 1.The ATC will manually insert them per QCGP 2-3, QCOP 0700-01, and QCOP 0700-02 guidance.
- Approximate Run Time: 1.5 Hours Quad Cities 2016 NRC EXAM Scenario 3 CRITICAL TASKS:
Critical Task #1: The Crew will take action to isolate the RPV and reduce the release of radioactivity by manually closing the MSIVs, Main Steam drains and/or verifying the Offgas System is isolated as required.
Critical task #2: Given an operating reactor plant with a primary system discharging into the reactor building and the discharge cannot be isolated, INITIATE an emergency depressurization when two or more areas exceed the maximum safe operating levels of the same parameter (radiation, temperature, or water level).
Quad Cities 2016 NRC EXAM Scenario 3 EXERCISE PERFORMANCE OBJECTIVES Objective Objective Description SR-0001-P42 Given a reactor plant with a primary system discharging into the reactor building and the discharge cannot be isolated, verify/initiate an emergency depressurization when two or more areas exceed the maximum safe operating levels of the same parameter (radiation, temperature, or water levels) in accordance with QGA 300 and QGA 500-1.
SR-0001-P45 Given a reactor plant in a QGA condition, verify the proper actuation of containment isolations and ECCS and emergency DG starts in accordance with QGA 100 or QGA 101.
SR-0002-P03 Given a reactor plant at power with a reactor scram, place the plant into a stable condition in accordance with QCGP 2-3.
SR-0002-P04 Given a reactor plant at power, perform a power change discernible on neutron monitors using control rods in accordance with QCOP 0280-01, QCGP 3-1 and QCGP 4-1.
SR-0202-P34 Given U1 reactor plant in operation with the reactor recirc system in dual loop operation, take actions to perform a manual speed runback from the 901-4 panel using the 10% manual runback pushbutton IAW QCOP 0202-03 SR-0700-P01 Given a reactor plant during a reactor startup or shutdown, operate the SRM and IRM subsystems in accordance with QCGP 1-1 or QCGP 2-1 and QCOP 0700-01 and QCOP 0700-02.
SR-0700-P07 Given an operating reactor plant with an APRM failure, take actions to bypass the failed APRM and meet TS requirements in accordance with QCOP 0700-04 and QCAP 0230-19. (SOER 90-3 r1)
SR-1300-K26 EVALUATE given key RCIC System parameter indications and/or responses depicting a system specific abnormality/failure and DETERMINE a course of action to correct or mitigate the following abnormal condition(s):
- a. Inadvertent auto start
- b. Failure to auto start
- c. Backleakage past discharge check SR-1700-P03 Given a reactor plant at power and a fuel clad failure or high activity in off-gas, take action to reduce the release in accordance with QCOA 1700-05 or QCOA 1700-04.
SR-3200-P02 Given a reactor plant during a startup, start the first reactor feed pump in accordance with QOP 3200-02.
Quad Cities 2016 NRC EXAM Scenario 3 EXERCISE PERFORMANCE OBJECTIVES Objective Objective Description SR-3900-P02 Given a reactor plant at power when a loss of service water occurs, take action to scram and control RPV parameters in accordance with QCOA 3900-01, 3700-01 and 3800-03. (PRA Initiating Event %TSW, Loss of Service Water, accounts for 20.3% of total CDF and initiates 14 of the top 100 Core Damage Sequences) (Loss of SW / SW ruptures accounts for 43.6% of total CDF and initiates 32 of the top 100 Core Damage Sequences including the top 4)
SR-5650-K21 Given a Main Turbine Control - EHC Hydraulic System operating mode and various plant conditions, PREDICT how Main Turbine/EHC systems and plant parameters will respond to manipulation of the following Main Turbine Control - EHC Hydraulic System local/remote controls:
- a. EHC pump control switches
- b. EHC pump test start pushbutton
- c. EHC filter pump control switch
- d. Main turbine supervisory trip cutout switch
- e. Hydraulic Fluid Conditioning Skid controls
- f. EHC heater/fan controls Quad Cities 2016 NRC EXAM Scenario 3 Simulator setup:
- 1. Reset to IC-21 (Approximately 100% power).
- 2. Go to RUN
- 3. Verify 1A EHC pump is on
- 4. Verify the following RWM Sequence is loaded: 4PHESD
- a. Mark up the Control Rod Move Sheet to reflect all rods withdrawn up to Step 17.
(Commands to be utilized during this scenario are contained in the CAEP file:
2016 NRC Scenario 3.cae)
- 5. Insert Commands for setup:
Set up for SRM IRM manual insertion following the scram using the batch files.
Ensure the path to the thumb drive matches the CAEP. For instance, if the thumb drive shows up in D drive the path is as shown. However, if the thumb drive shows up in the E drive, the correct syntax is bat e:\srmirm and the CAEP must be modified. The same goes for the batch file that removes the SRM and IRM malfunctions. This is necessary to comply with NRC Examination Security.
bat d:\srmirm Prevents the SRMs and IRMs from driving into the core trgset 5 'zdihs10700din' Sets a trigger to allow the SRMs and IRMs to drive into the core manually trg 5 'bat d:\delsrmirm' Allows the SRMs and IRMs to drive into the core manually trgset 9 'rcntb.gt.0.5' Remove RCIC initiation signal trg 9 'dor dihs11300rmi' Remove RCIC initiation signal imf nm08a 80 Fail APRM 1 As Is imf sw01B Prevent 1B SW pump from starting imf hp12a 45 Bind the HPCI steam isolation valves imf hp12b 45 Bind the HPCI steam isolation valves trgset 1 'tcvsv3.le.0.1' Trigger 1 goes true when TCV 3 goes closed imf hp13(1 5:00)35 15: HPCI steam leak with five minute time delay and a 15 minute ramp imf cr02(1) 2 30: Gross Fuel Failure at 2% Severity, 30 minute ramp, on trigger 1 imf og04 Fail Offgas Isolation Set up complete Commands to execute during the scenario imf sw02a 100 7:00 Degrade 1A SW pump to 100% over 7 minutes ior dihs11300rmi init Spurious initiation of RCIC imf cr01 100 10: Fuel failure imf fw01C If directed Contingency to trip 1C RFP irf sw10r run Start the U1 DGCWP, if needed bat fireout Acknowledge the fire alarms imf rm0115 60 15: If needed, Torus Area ARM to >Max Safe in 15 minutes bat d:\delsrmirm Allows driving in the SRM/IRM Quad Cities 2016 NRC EXAM Scenario 3
- 6. Take the following equipment OOS (hang INFO Card):
- 1B SW Pump
- 1A SCW Pump
- 7. Complete the following Control Panel setup items:
- Verify the LOCA TRIP ENABLED labels are above the 1A and 1C Circ Water Pumps.
- Display the Power/Flow Map on Monitor 3.
- Clear all SBO Panel alarms.
- 8. Provide a current revision of the following procedures, signed off as specified:
- QCOP 5650-01 (no steps signed off)
- QCGP 3-1 , marked up to the point of holding load at 100% power
- 9. Provide scenario 3 REMA for Holding Load.
- 10. Perform the applicable steps of TQ-QC-201-0113 Simulator Exam Security Actions Checklist
- 11. Ensure (1) orange ring is available to provide equipment status.
- 12. Ensure 2 ESTs are available to provide equipment status.
Quad Cities 2016 NRC EXAM Scenario 3 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901(2)-3 A-1 RX BLDG HI RADIATION, Rev. 6 o 901(2)-3 C-2 OFFGAS HIGH HIGH RADIATION, Rev. 9 o 901(2)-3 D-2 OFFGAS HI RADIATION, Rev. 16 o 901(2)-3 F-12 HPCI PUMP AREA HI TEMP, Rev. 7 o 900-3 H-2 AREA HI TEMP STEAM LEAK DETECTION, Rev. 9 o 901(2)-4 D-16, RCIC SYSTEM INITIATED, Rev. 9 o 901(2)-5 A-6, APRM UPSCALE/HIGH, Rev. 8 o 901(2)-5 C-3, ROD OUT BLOCK, Rev. 11 o 901(2)-5 H-1, OPRM TROUBLE/INOP, Rev. 3 o 900-55/56 A-1, DRYWELL HIGH RAD CONC, Rev. 11 o 912-1 B-3 SERVICE WATER SYSTEM LOW PRESSURE, Rev. 6 QCGP 2-3, Reactor Scram, Rev. 84 QCGP 3-1, Reactor Power Operations, Rev. 79 QCGP 4-1, Control Rod Movements and Control Rod Sequence, Rev. 46 QCOA 0201-05, Primary system Leaks Outside Primary Containment, Rev. 11 QCOA 0700-03, Loss of Neutron Flux Indication. Rev. 9 QCOA 1300-02 RCIC Automatic Initiation, Rev. 17 QCOA 1700-04, Abnormal Offgas Radiation, Rev. 20 QCOA 1700-05, Abnormal Main Steam Line Radiation, Rev. 19 QCOA 1800-01, Area High Radiation, Rev. 7 QCOP 0700-01, Source Range Monitor (SRM) Operation, Rev. 16 QCOP 0700-02, Intermediate Range Monitor (IRM) Operation, Rev. 20 QCOP 1000-30, Post-Accident RHR Operation, Rev. 31 QCOP 3200-05, Reactor Feedpump Shutdown, Rev. 37 QCOP 5650-01, Unit 1 EHC System Operation, Rev. 32 QGA 100, RPV Control, Rev. 10 QGA 200, Primary Containment Control, Rev. 10 QGA 300, Secondary Containment Control, Rev. 13 QGA 500-1, RPV Blowdown, Rev. 14 Quad Cities 2016 NRC EXAM Scenario 3 CREW TURNOVER
- 1. Plant Conditions:
a.) Unit 1 is at 100% power holding load b.) Unit 2 is at 100% power.
c.) Technical Specification limitations:
(1) Unit 1: None (2) Unit 2: None d.) On Line Risk is GREEN.
2.) Significant problems/abnormalities:
a.) 1A Stator Cooling Water pump is OOS for replacement. 1B Stator Cooling Water pump is protected.
b.) 1B SW pump is OOS for packing replacement. The expected duration is less than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
3.) Evolutions/maintenance for the oncoming shift:
a.) Swap EHC pumps for maintenance on the 1A EHC pump Quad Cities 2016 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 1 Page 1 of 1 Event
Description:
Swap EHC pumps from 1A in operation to 1B in operation Time Position Applicants Actions or Behavior SRO Directs EHC pump swap per QCOP 5650-01 Step F.4 SIMOP ROLE PLAY: As the Equipment Operator stationed at Unit 1 EHC skid ,when asked about the status of the 1B EHC pump before it is started, report:
The 1B EHC pump pre-start checks are complete. All personnel are clear.
BOP Starts standby 1B EHC OIL PMP BOP Stops off going 1A EHC OILPMP BOP Verifies EHC pump discharge pressure is between 1500 and 1700 psig as indicated on PI 1-5650-12, EHC OIL PRESS SIMOP ROLE PLAY: As the Equipment Operator stationed at Unit 1 EHC skid ,when asked about the status of the 1B EHC pump after it is started, report:
The 1B EHC pump discharge pressure is 1580 psig, no leaks, and it sounds normal.
ATC (CONTINUOUS) Monitors reactor and RPV parameters.
End of Event 1 Quad Cities 2016 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 2 Page 1 of 1 Event
Description:
Degraded Service Water (SW) Pressure resulting in starting a standby SW pump Time Position Applicants Actions or Behavior SIMOP NOTE: When directed by the Lead Evaluator, degrade the 1A SW pump 100%
ramped over 7 minutes using malfunction SW02:
imf sw02a 100 7:00 There is a seven minute ramp to ensure the examinees have time to start a standby pump and preclude taking actions for a total loss of SW. Consideration could be given to starting this malfunction quickly after the EHC pump swap to prevent scenario dead time.
Key Parameter Response: Service Water header pressure lowers as indicated on PI 1/2-3940-18, SW PMP SPLY PRESS on the 912-1 panel. Low pressure annunciator received at 80 psig.
Expected Annunciator(s):
912-1 B-3, SERVICE WATER LOW PRESSURE Automatic Actions: None ATC (CONTINUOUS) Monitors reactor parameters.
BOP Reports annunciator 912-1 B-3, SERVICE WATER LOW PRESSURE SRO Directs BOP to restore SW pressure Confirms SW pressure < 80 psig on PI 1/2-3940-18, SW PMP SPLY BOP PRESS BOP Verifies MO 1/2-3906, FIRE PROT SW SPLY VLV shut Evaluator Note: The BOP may elect to start the 1/2 SW pump (from either Unit) or the 2A SW pump to restore SW pressure.
BOP Starts standby SW pump Confirms SW pressure returns to normal band on PI 1/2-3940-18, SW BOP PMP SPLY PRESS SIMOP ROLE PLAY: As the Equipment Operator sent to the SW pumps, wait 2 minutes and report as appropriate:
The 1A SW pump is vibrating and it is noisy.
The (which ever pump they started) is operating normally.
(When the 1A SW pump is secured) The 1A SW pump is no longer running.
End of Event 2 Quad Cities 2016 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 3 Page 1 of 1 Event
Description:
1C RFP bearing degradation requiring the pump to come off line.
Time Position Applicants Actions or Behavior SIMOP NOTE: When directed by the lead evaluator, call in as the Unit 1 EO and report:
The outboard pump bearing on the 1C RFP is making a lot of noise. I am concerned the pump will fail catastrophically. The FS is here also and concurs.
Key Parameter Response: None Expected Annunciator(s): None Automatic Actions: None Evaluator Note: An Emergency Power Reduction will occur before the 1C RFP is secured.
The Emergency Power Reduction is Event 4 in the scenario guide.
SRO Directs securing 1C RFP per QCOP 3200-05 BOP Places RFP SELECTOR switch to OFF.
Verifies Auxiliary Oil Pump control switch for RFP to be shut down:
BOP (1) Has a red target.
(2) Yellow AUTO TRIP light is lit. .
BOP/ATC Verifies Reactor water level is stable BOP Places control switch for RFP to be shut down to STOP BOP Verifies Auxiliary Oil Pump starts as RFP coasts down.
BOP/ATC Verifies Reactor water level remains stable.
BOP Verifies RFP current on running pump is< 1115 amps.
BOP Verifies RFP discharge header pressure has stabilized.
Evaluator Note: Securing a Condensate Pump is not integral to rest of the scenario. The following actions have no affect on the rest of the scenario and may be skipped if desired.
BOP Verifies RFP suction pressure is> 250 psig.
BOP Places control switch for COND PMP to be shut down to STOP.
BOP IF a Condensate/Condensate Booster pump is to be placed in standby, THEN, selects that pump for standby using COND PMP SELECTOR switch End of Event 3 Quad Cities 2016 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 4 Page 1 of 1 Event
Description:
Emergency Power Reduction Time Position Applicants Actions or Behavior Directs Emergency Power Reduction to < 2511 MWth (~85%) per SRO QCGP 3-1 Reduces Recirc flow by depressing the MANUAL RUNBACK pushbutton (PB) as desired, up to a maximum of three times within a 5 ATC second period.
-OR-Lowering flow using the Master/Individual Controllers.
Verifies the MANUAL Pushbutton is lit at both LOOP A and B SPEED ATC CONTROLLER.
Verifies the Speed Demand at both LOOP A and B SPEED ATC CONTROLLERs decreases 10% for each time the MANUAL RUNBACK Pushbutton is depressed.
Verifies the Recirc Pump Speed at both LOOP A and B SPEED ATC CONTROLLERs decrease at approximately 2.5% per second ATC Drives CRAM rods to lower FCL ATC Selects POWER REDUCTION from any menu on the RWM.
ATC Depresses ARRAY MODE to latch all CRAM Rods ATC Selects the first CRAM Rod in sequence.
SRO Refers to QCOA 0400-02 to determine target power level ATC Continuously inserts CRAM Rod(s) in sequence to position 00 as needed to lower FCL AND/OR avoid/exit ICA Region I/II as indicated in QCOA 0400-02 EVALUATOR NOTE: The crew may return to Event 3 to continue securing Feed and Condensate pumps.
End of Event 4 Quad Cities 2016 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 5 Page 1 of 1 Event
Description:
APRM 1 Failure Time Position Applicants Actions or Behavior SIMOP NOTE: Verify APRM 1 displays a constant 100% power.
Key Parameter Response: APRM 1 reads 100% power following the Emergency Power Reduction Expected Annunciator(s):
901-5 A-6, APRM UPSCALE/HIGH 901-5 C-3, ROD OUT BLOCK 901-5 H-1, OPRM TROUBLE/INOP Automatic Action: Rod Withdrawal block ATC Verifies rod out block and other annunciators ATC Reports APRM 1 is reading ~ 100%
SRO Refers to QCOA 0700-03.
SRO Determines APRM 1 is INOP SIMOP ROLE PLAY: If contacted, as IMD and/or other support personnel, report:
I will come to the Control Room in a few minutes to take a look at the APRM.
SRO Verifies minimum number of operable channels is met per T S 3.3.1.1 for RPS trip functions and TRM Section 3.3.a for Rod Block functions.
SRO Directs bypassing APRM 1 per QCOP 0700-04 ATC Positions APRM BYPASS joystick to bypass APRM Channel 1 ATC Verifies white BYPASS light comes ON for that APRM End of Event 5 Quad Cities 2016 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 6 Page 1 of 1 Event
Description:
RCIC Spurious start.
Time Position Applicants Actions or Behavior SIMOP NOTE: When directed by the Lead Evaluator cause a spurious start of RCIC by overriding the initiation pushbutton:
ior dihs11300rmi init Key Parameter Response: RCIC valves reposition and the Flow controller ramps up to a steady 400 gpm.
Expected Annunciator(s):
901-4 D-16, RCIC SYSTEM INITIATED Automatic Action: RCIC starts up and injects.
BOP Reports annunciator 901-1 D-16 and refers to QCAN BOP Verifies AUTOMATIC ACTIONS occur..
BOP Performs QCOA 1300-02 Immediate Operator Actions:
Trip RCIC turbine by performing one or more of the following, listed in preferred order:
- a. Depress the Remote RCIC Turb Trip pushbutton.
- b. Lower flow controller setpoint to zero.
- c. Isolate steam supply:
(1) Close MO 1-1301-17, STM SPLY ISOL VLV.
(2) Close MO 1-1301-16, STM SPLY ISOL VLV.
ATC Monitors FCL, LPRMs and APRMs for reactivity addition.
SRO Determines applicable Technical Specifications:
- TS 3.5.3, RCIC System, Condition A SIMOP ROLE PLAY: If requested as as IMD (other Maintenance), state:
I will be up shortly to discuss the RCIC issues.
End of Event 6 Quad Cities 2016 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 7-8 Page 1 of 5 Event
Description:
Fuel failure and HPCI steam line break. Crew enters QGA 300 and transitions to QGA 500-1 when two areas exceed Max Safe radiation levels.
Time Position Applicants Actions or Behavior SIMOP NOTE: When directed by the Lead Evaluator, cause a Fuel failure by inserting malfunction CR01:
imf cr01 100 10:
Key Parameter Response: Rising Rad levels for Offgas, MSL, Drywell, Reactor & Turb Bldg Expected Annunciator(s):
(in 1.5 min) 901-3 D-2 OFFGAS HI RADIATION (in 4 min) 901-55/56 A-1, DRYWELL HIGH RAD CONC (in 5 min) 901-5 A-8 & D-8, GROUP 2 & CONTROL ROOM VENT ISOLATED (in 14 min) 901-3 C-2, OFFGAS HIGH HIGH RADIATION Automatic Actions: Group 2 Isol, CR Vent Isol, Offgas Isolation 15-Min timer Starts BOP Responds to Annunciator OFF GAS HI RADIATION SRO Enters and directs actions of QCOA 1700-04 and QCOA 1700-05 SRO Directs reactor power be held constant BOP Reports Off Gas radiation levels are steadily rising as indicated on the A & B SJAE Rad monitors (901-10) and Recorder (901-02)
BOP Monitors Main Steam Line Radiation monitors and reports to US BOP Monitors Area Radiation Monitors at the 901-11 panel and reports to US SRO/BOP Evacuates any areas of high radiation and refers to QCOA 1800-01 as needed SRO/BOP Notifies Chemistry and the QNE of abnormal Off Gas activity SRO/BOP Directs Chemistry to draw Reactor Coolant and Recombiner outlet samples within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SRO/BOP Checks for indications of high coolant conductivity SRO/BOP Checks Chimney Gas Monitors for trends SIMOP ROLE PLAY: Acknowledge directives as necessary if notified as Rad Protection and Chemistry personnel.
SRO/BOP Notifies Rad Protection to perform surveys SRO/BOP Notifies Chemistry to monitor CAMS BOP Responds to Annunciator DRYWELL HIGH RAD CONC and notifies the Unit Supervisor SRO/BOP (Continuous) Monitor Drywell Radiation Levels BOP Confirms rising rad levels on RIS 1-2419 A& B at Panel 901-55 & 56 Event 7 continued Quad Cities 2016 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 7-8 Page 1 of 5 Event
Description:
Fuel failure and HPCI steam line break. Crew enters QGA 300 and transitions to QGA 500-1 when two areas exceed Max Safe radiation levels.
Time Position Applicants Actions or Behavior BOP Monitors Containment H2 and O2 levels per QCOP 2400-01 SRO/BOP Notifies Radiation Protection ATC Responds to Annunciator GROUP 2 ISOL CH TRIP and CONTROL ROOM VENT ISOLATED and informs the Unit Supervisor SRO May direct verification of Group 2 and CR Vent isolation ATC/BOP As directed, verifies the Group 2 and CR Vent isolations BOP Responds to Annunciator OFF GAS HIGH HIGH RADIATION BOP Verifies Offgas 15-Minute Timer has started (at 901-10)
SRO When Offgas activity cannot be reduced < the Offgas HI HI Rad Alarm, directs actions to shutdown the reactor and isolate the release ATC Manually scrams the reactor (See Page 3 of this event)
CT 1 SRO Directs closing of AO 1-5406 Offgas Discharge to Stack CT 1 BOP Closes AO 1-5406 BOP As directed, verifies that AO 1-5408A and AO 1-5408B close CT 1 BOP Manually initiates a Group 1 Isolation / Closes MSIVs and MSIV Drain valves SRO Directs actions QCGP 2-3 ATC Places RX MODE switch to SHUTDOWN position ATC Verifies the SDV vent and drain valves are closed ATC Verifies that all Control Rods have fully inserted ATC Makes scram report including entry into QGA 100 on RPV Water Level
< 0 inches ATC Attempts to maintain RPV level 0 to +48 with preferred injection systems:
- Verifies DFWLC in Single Element
- May isolate Feed Water Reg Valve(s)
- May place Low Flow Feed Reg Valve in Service
- May secure unnecessary Feed and Condensate Pumps Event 7 continued Quad Cities 2016 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 7-8 Page 1 of 5 Event
Description:
Fuel failure and HPCI steam line break. Crew enters QGA 300 and transitions to QGA 500-1 when two areas exceed Max Safe radiation levels.
Time Position Applicants Actions or Behavior ATC (CONTINUOUS) Monitors RPV water level and pressure EVALUATOR NOTE: The SRMs and IRMs will not automatically insert. This is Event 8.
SIM OP NOTE: Pay close attention to when the ATC depresses the DRIVE IN pushbutton for the SRM/IRM. This can be done by visual observation via camera, or by monitoring the event triggers. When Event Trigger 5 goes TRUE (turns RED) the button has been depressed.
When the button is depressed run batch file d:\delsrmirm from the CAEP. (Expert: bat d:\delsrmirm)
ATC Manually inserts SRMs AND IRMs by depressing the SRM/IRM DETECTOR POSITION display switch and then the DRIVE IN switch.
ATC Verifies both Recirc Pumps running at minimum speed in Manual ATC Reports when all rods are fully inserted SRO Enters and directs actions of QGA 100 SRO Directs ATC/BOP to verify 0 isolations and auto-starts ATC/BOP Stabilize RPV Pressure < 1060 psig with Relief Valves ATC/BOP Verifies Group 2 and 3 Isolations, RB vent isolation and SBGT start ATC Verifies Main Turbine trips, all SVs, CVs, ISVs, IVs and extraction steam check valves close ATC Verifies Main Generator Output Breakers tripped after 30 seconds and places control switches in PTL ATC Verifies Main Generator Field and Exciter Field Breakers ATC Verifies all 4 KV buses powered from T-12 ATC Verifies both Recirc Pumps running at minimum speed in Manual ATC Starts the Control Room AFU Booster Fan within 40 minutes ATC Dispatches EO to reset the Generator 86 Relays SIMOP NOTE: When the Main Turbine trips, verify trigger 1 goes true inserting the HPCI steam leak and gross fuel failure using malfunction CR02:
imf hp13(1) 100 30: (100% Severity on a 30 minute ramp) imf cr02(1) 2 30: (Gross Fuel Failure at 2% Severity, 30 minute ramp)
Quad Cities 2016 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 7-8 Page 1 of 5 Event
Description:
Fuel failure and HPCI steam line break. Crew enters QGA 300 and transitions to QGA 500-1 when two areas exceed Max Safe radiation levels.
Time Position Applicants Actions or Behavior Key Parameter Response: Increasing Radiation levels and Temperature in the HPCI Room Expected Annunciator(s):
901-3 A-1, RX BLDG HI RADIATION (in approximately 1.5 minutes) 901-3 H-2, AREA HI TEMP STM LEAK DETECT (in approximately 2.5 minutes)
Automatic Actions: None (Malfunctions for HPCI Steam Supply Valve binding)
BOP Responds to annunciators and informs the Unit Supervisor Event 7 continued BOP Responds to a Annunciator RX BLDG HI RADIATION and informs the Unit Supervisor SRO Enters and directs applicable actions of QGA 300 BOP Monitors Area Radiation levels from the 901-2 and 901-10 panels and reports QGA 300 Entry Conditions EVALUATOR NOTE:
The HPCI Room ARM exceeds its Max Safe Value approximately 4 minutes after the turbine trip.
The Torus Area ARM will also be approaching its Max Normal (Alarm) value.
SIMOP NOTE: If the fire alarm sounds, silence the alarm with the command: bat fireout Cue the Evaluator to role play as the Unit 2 Operator and inform the BOP that the alarm is from the Unit 1 HPCI room, (high temoerature).
BOP Reports HPCI Room Radiation levels are > Max Normal and increasing BOP/ATC Monitors Reactor Bldg Temperatures at Panel 901-21 (TR 1-1290)
SIMOP ROLE PLAY: When requested to investigate breakers for HPCI 4 & 5, wait 2 minutes and as EO report: The thermals are tripped.
If asked to reset them, reply: They will NOT reset BOP/ATC Recognizes and reports when the HPCI Room exceeds its Max Safe value of 155°F BOP Reports HPCI Room Radiation levels are > Max Safe value of 3000 mr SRO Re-enters and directs applicable actions of QGA 100 BOP Attempts to isolate HPCI Steam Lines Quad Cities 2016 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 7-8 Page 1 of 5 Event
Description:
Fuel failure and HPCI steam line break. Crew enters QGA 300 and transitions to QGA 500-1 when two areas exceed Max Safe radiation levels.
Time Position Applicants Actions or Behavior BOP Directs EO to investigate breakers for HPCI 4 & 5 valves BOP Directs EO with Rad Prot. support to investigate source of leak Event 7 continued SIMOP ROLE-PLAY: As EO, report:
The HPCI room is filled with steam and entry is impossible.
ATC/BOP Dispatches EO to start the U-1 EDG cooling water pump and monitor RB Basement water levels SIMOP ROLE PLAY: If dispatched as EO, wait 2 minutes and start the Unit 1 EDG CWP:
mrf sw10r run SRO/BOP Announces evacuation of Unit 1 Reactor Bldg. over plant page SIMOP NOTE: Verify the Torus Area ARM exceeds its Max Safe Value (3000 mr/hr) approximately 11 minutes after the Mode Switch is taken to Shutdown. If necessary, use the following malfunction to ramp the ARM:
rm0115 60 15:
Key Parameter Response: Increasing Radiation levels in the Torus Area on ARM 15 Expected Annunciator(s): 901-3 A-1, RX BLDG HI RADIATION (Re-Alarming)
Automatic Actions: None BOP Monitors Reactor Bldg ARMs on Panel 901-11 BOP Recognizes and reports that ARM 15 TORUS AREA is trending higher BOP Recognizes and reports when the second area, the Torus Area, has exceeded its Max Safe Radiation level (3000 MR)
SRO When 2 areas (HPCI Room and Torus Area) exceed Max Safe radiation levels, enter and direct QGA 500-1 SRO Verifies all rods in BOP Reports Drywell pressure < 2.5 psig and Torus level above 5 ft.
CT 2 SRO Orders all 5 ADS valves opened and leave switches in Manual Quad Cities 2016 NRC EXAM Scenario 3 Appendix D Required Operator Actions Form ES-D-2 Quad Cities Scenario No.: 3 Event No.: 7-8 Page 1 of 5 Event
Description:
Fuel failure and HPCI steam line break. Crew enters QGA 300 and transitions to QGA 500-1 when two areas exceed Max Safe radiation levels.
Time Position Applicants Actions or Behavior CT2 BOP Opens all 5 ADS valves and leaves all switches in the MAN position Event 7 continued BOP Verifies ADS valve positions at the 901-21 panel ATC/BOP Starts cooldown to cold shutdown per QCOP 1000-05 ATC Monitors and controls RPV water level SIMOP NOTE: When the RPV is depressurized per QGA 500-1 guidance, the ATC has driven in the SRMs and IRMs, and/or at the discretion of the Lead Examiner, place the simulator in FREEZE.
FINAL Quad Cities 2016 NRC EXAM Scenario 4 Exelon Nuclear 2016 NRC Exam Scenario Scenario Number:
NRC Scenario 4 Revision Number: 00 Date: 11/02/2015 Developed By:
Instructor Date Validated By:
SME or Instructor Date Reviewed By:
Operations Representative Date Approved By:
Training Department Date Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2016 NRC Scenario 4 Op-Test No. ILT 14-1 Examiners: ________________________ Operators:_____________________________
Initial Conditions:
The plant is currently at 75% power and holding load per Generation Dispatch.
Turnover: Perform the Core Spray Monthly surveillance for the 1B Core Spray pump, and QCOS 1600-04, Weekly Primary Containment Oxygen Concentration from the 901-56 panel.
Event Malf. No. Event Event No. Type* Description 1 None BOP Perform Core Spray Monthly Surveillance (1B Core N Spray pump) 2 DIHS124AS6B BOP Failure of 1B CAM to start for surveillance. TS C
3 FW17C ATC 1C Condensate Pump trip w/failure of standby pump DIHS13302 to auto-start.
C 4 None SRO SSMP Room Cooler inoperable. TS 5 DIHS156041A BOP 1A Gland Exhauster trip.
LOHS156041A C 6 MC08 ATC Loss of Main Condenser vacuum / Emergency Power Reduction R
7 RP02 ATC Electric ATWS (ARI inserts control rods) QGA 101.
RP03 C 8 MS04B CREW Main Steam Line break inside the Drywell. QGA 100 M and QGA 200.
9 DIHS11001S17B CREW Failure of Drywell Sprays (S-17B and RHR 23A RH19AR valve). Blowdown QGA 500-1 C
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:
Total Malfunctions (5-8): 7 BOP Normal: E1 Malfunction(s) after EOP (1-2): E8 & 9 ATC Reactivity (1 per set): E6 Abnormal Events (2-4): E2, 3, 5, 6 BOP I/C (4 per set): E2 & 5 Major Transient(s) /E-Plan entry (1-2): E8 ATC I/C (4 per set): E3 & 7 EOPs (1-2): QGA 100, 200 SRO-I I/C (4 per set inc 2 as ATC): E2,3,5,7 EOP Contingencies (0-2): QGA 500-1 SRO Tech Spec (2 per set): E2 & 4 Critical Tasks (2-3): 2 ALL Major Transients (2 per set) E8 Quad Cities 2016 NRC EXAM Scenario 4
SUMMARY
- Initial Conditions:
o The plant is operating at 75%.
- Event 1: The BOP performs QCOS 1400-04, Core Spray Pump Operability Test for the 1B Core Spray Pump.
- Event 2: The BOP is directed to perform QCOS 1600-04, Weekly Primary Containment Oxygen Test, however, the 1B CAM (901-56 panel) will fail to start. The SRO will enter TLCO 3.3.b. Condition A, for one inoperable channel (Table 3.3.b-1 function 5&6).
- Event 3: The 1C Condensate/Condensate Booster Pump will trip due to a motor short causing an overcurrent condition sensed at the breaker. The standby pump (1A) will fail to autostart requiring a manual start by the ATC operator. EOs will be dispatched to the breaker and running pumps. The EO will report an overcurrent target up at Bus 14 cubicle 8 and EMs will be notified to investigate.
- Event 4: The BOP will dispatch an EO to the SSMP Room in response to the 912-8 A-8, Safe Shutdown System Trouble alarm. The EO will report that the Compressor Trip light is lit on the Room Cooler. The EO will attempt a reset as directed by the BOP, however, it will be unsuccessful. The SRO will declare the SSMP inoperable due to an inoperable room cooler and enter TS 3.7.9 and a 14 Day Safe Shutdown Analysis Administrative Technical Requirement, (SSA ATR) for both Units.
- Event 5: The running Gland Seal Exhauster will trip. The BOP will start the standby Exhauster and adjust Gland Exhaust pressure.
- Event 6: An air leak will result in lowering Main Condenser vacuum. The crew performs QOA 3300-02 and Emergency Power Reduction. All efforts to mitigate the loss of Main Condenser vacuum will be unsuccessful and a manual scram will be inserted as backpressure approaches 7.5 in Hg.
- Event 7: Control rods do not insert due to an Electric ATWS. The SRO will transition to QGA 101 and manual initiation of the ARI system will insert all control rods. The SRO will exit QGA 101 and re-enter QGA 100.
- Event 8: A leak in the B Main Steam Line inside the Drywell will develop resulting in a QGA 200 entry. The crew will attempt to spray the Drywell, however, Div I DW sprays are not available because the RHR 23A valve breaker will trip and not reset. DIV II DW sprays will also not be available due to an S17 switch problem. The crew will enter QGA 500-1, RPV Blowdown in order to avoid exceeding the Pressure Suppression Pressure (PSP) limit.
Approximate Run Time: 1.5 Hours Quad Cities 2016 NRC EXAM Scenario 4 CRITICAL TASKS:
Critical Task #1: With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron (prior to exceeding 110°F Torus temperature) and/or inserting control rods, to prevent exceeding primary containment design limits. (BWROG RPV-6.1 ATWS PWR/LVL S/D REACTOR)
Critical Task #2: When DW temperature CANNOT be maintained <280 F OR Torus pressure CANNOT be maintained LESS THAN the Pressure Suppression Limit (PSP),
INITATE an Emergency Depressurization.
Quad Cities 2016 NRC EXAM Scenario 4 EXERCISE PERFORMANCE OBJECTIVES SR-1400-K20 (Freq: LIC=B) Given a system operating mode and various plant conditions, EVALUATE the following system indications and DETERMINE if the indications are expected and normal:
- a. Core Spray (1) Pump run/trip status (2) Valve position (3) Pump suction and discharge pressures SR-2400-K32 (Freq: LIC=B) Given CAM operability status OR key parameter indications, various plant conditions and a copy of Tech Specs, DETERMINE Tech Spec compliance and required actions, if any.
SR-2400-K21 SR-2400-K21 (Freq: LIC=B) Given a CAM operating mode and various plant conditions, PREDICT how CAM / plant parameters will respond to manipulation of the following CAM local/remote controls:
- b. H2-O2 Mon Inlet Valve Selector Switch
- c. CAM Power Control Switch SR-3200-K22 (Freq: LIC=B) Given a Condensate/Feedwater System operating mode and various plant conditions, PREDICT how key Condensate/Feedwater System/
plant parameters will respond to the following Condensate/Feedwater System component or controller failures:
- a. Condensate/condensate booster pump trip SR-2900-K32 (Freq: LIC=B) Given SSMP System operability status OR key parameter indications, various plant conditions and a copy of Tech Specs, DETERMINE Tech Spec compliance and required actions, if any.
SR-5600-K22 (Freq: LIC=B) Given a Main Turbine and Auxiliary Systems operating mode and various plant conditions, PREDICT how system/plant parameters will respond to the following Main Turbine and Auxiliary Systems component or controller failures:
- f. Gland Steam Exhauster trip SR-3300-P09 (Freq: LIC=B) Given a reactor plant at power with a loss of condenser vacuum, take action to attempt to locate and correct the cause for lowering vacuum in accordance with QOA 3300-02 and/or QOA 5450-05. (PRA Initiating Event %TC - Loss of Vacuum accounts for 7.65% of total CDF and initiates 4 of the top 100 Core Damage Sequences)
SR-0002-P03 (Freq: LIC=A) Given a reactor plant at power with a reactor scram, place the plant into a stable condition in accordance with QCGP 2-3.
SR-1000-P02 (Freq: LIC=A) Given a reactor plant in an accident condition (QGA), operate torus sprays in accordance with QCOP 1000-30 and appropriate QGA.
(Important PRA Operator Action - starting containment sprays has a RAW value of 82.5)
Quad Cities 2016 NRC EXAM Scenario 4 EXERCISE PERFORMANCE OBJECTIVES SR-0001-P11 (Freq: LIC=B) Given a reactor plant with an ATWS, take action to reduce heat input into the containment in accordance with QGA 101. (SOER 83-8 r11) (ATWS is a key event in 1 of the 100 most probable PRA Core Damage Sequences)
SR-0001-P26 (Freq: LIC=B) Given a reactor plant with rising drywell temperature due to a LOCA or steam leak and RHR is not needed for core cooling, verify parameters are in the safe region of the Drywell Spray Initiation Limit (QGA Figure K), verify tripped or trip recirc pumps and drywell coolers, and attempt to initiate drywell sprays before drywell temperature reaches 338 degrees in accordance with QGA 200.
SR-0001-P23 (Freq: LIC=A) Given a reactor plant with rising containment pressure and temperature due to a LOCA or steam leak, initiate an emergency depressurization when torus pressure cannot be maintained below the Pressure Suppression Pressure (QGA Figure L) or when drywell temperature cannot be restored and held below 338 degrees in accordance with QGA 200 and QGA 500-1. (Important PRA Operator Action - emergency depressurization terminates 19 of top 100 Core Damage Sequences)
SR-0001-P45 (Freq: LIC=A) Given a reactor plant in a QGA condition, verify the proper actuation of containment isolations and ECCS and emergency DG starts in accordance with QGA 100 or QGA 101.
Quad Cities 2016 NRC EXAM Scenario 4 Simulator Setup:
- 1. Reset to IC-20 (Approximately 75% power).
- 2. Go to RUN.
- 3. Verify the following RWM Sequence is loaded:4 PHESD (or current shut down sequence)
(The following commands to be utilized for this scenario are contained in the CAEP file:
2016 NRC Scenario 4.cae)
- 5. Insert Commands for setup:
- ior dihs11001s17b off (override the B Loop S-17 switch to OFF)
- ior dihs124as6b off (override the 1B CAM power switch to OFF on the 901-56 panel)
- ior dihs13302 p2a_off (override the Condensate Pump Selector Switch to OFF)
- ior lohs13302a4 on (override the 1A Condensate Pump Standby light ON)
- trgset 1 zdihs13302a(5) (Set trigger 1 true when the 1A Condensate Pump control switch is taken to Start)
- trgset 2 zdihs13302a(5) (Set trigger 2 true when the 1A Condensate Pump control switch is taken to Start)
- trg 2 dor dihs13302 (Delete the override on the Condensate Pump Selector Switch when trigger 1 goes true)
- trg 1 dor lohs13302a4 (Delete the override on the 1A Condensate Pump Standby light when trigger 1 goes true)
- ior dihs156041a (3) trip (On trigger 3, override the1A Gland Exhauster handswitch to TRIP)
- ior lohs156041a4 (3) on (On trigger 3, override the 1A Gland Exhauster Amber Trip light ON)
- imf ser0986(3) on (On trigger 3, set annunciator 912-7 E-12 in alarm)
- trgset 5 zdihs1100123a(2) (Set trigger 5 true when the RHR 23A valve control switch is taken to OPEN)
- trg 5 irf rh19ar open (On trigger 5, open the breaker for the RHR 23A valve)
- imf rp03a (Manual Scram Circuit Failure Channel A)
- imf rp03b (Manual Scram Circuit Failure Channel B)
- imf rp02a (Auto Scram Circuit Failure Channel A1)
- imf rp02b (Auto Scram Circuit Failure Channel B1)
- imf rp02c (Auto Scram Circuit Failure Channel A2)
- imf rp02d (Auto Scram Circuit Failure Channel B2)
- 6. Verify the following commands for scenario performance:
- irf pc11r ackn (reset alarms at 901-64A panel in Cable Spreading Room for A CAM)
- imf fw17c (trip the 1C Condensate/Condensate Booster Pump)
- imf ano9128a8 on (override alarm 912-8 A-8, Safe Shutdown System Trouble, on)
- trg! 3 (trip the 1A Gland Seal Steam Exhauster using trigger 3)
- imf mc08 100 25: (Set Main Condenser air in-leakage to 100% ramped over 25 minutes)
Quad Cities 2016 NRC EXAM Scenario 4
- irf cu9r out (Isolate the 1A RWCU Demin)
- irf cu10r out (Isolate the 1B RWCU Demin)
- imf ms04b 0.5 10: (B Main Steam Line break in Drywell at 0.5% severity over 10 min)
- 7. Take the following components Out of Service:
- None
- 8. Provide a current revision of the following procedures, signed off as specified:
- Provide a copy of QCOS 1400 -04 marked up as a partial surveillance to test the 1B Core Spray Pump and a stopwatch.
- Provide a SDTC for the 1B Core Spray Pump inoperable.
- Provide a copy of QCOS 1600-04 with both the Weekly Containment O2 Concentration and the Monthly Channel Check required. Marked up to start at step H.2.
- 9. Provide a Load Drop REMA signed off to be at 75% power.
- 10. Perform the applicable Post Simulator Exam Security Actions of TQ-QC-201-0113 Simulator Exam Security Actions Checklist.
Quad Cities 2016 NRC EXAM Scenario 4 LIST OF POTENTIAL PROCEDURES Annunciator Procedures o 901(2)-3 A-4, CORE SPRAY PUMP RUNNING, Rev. 4 o 901(2)-3 A-14, TORUS HIGH/LOW LEVEL, Rev. 9 o 901(2)-3 A-16, PRI CNMT HIGH PRESSURE, Rev. 16 o 901(2)-3 D-2, OFF GAS HI RADIATION, Rev.15 o 901(2)-5 D-11, PRIMARY CNMT HIGH PRESS, Rev. 12 o 901(2)-5 D-10/15, RPS CHANNEL A/ B REACTOR SCRAM, Rev. 6 o 901(2)-5 A-10/15, RPS CHANNEL A/B MANUAL SCRAM, Rev. 6 o 901(2)-5 F-5, CONDENSER VACUUM LO, Rev. 8 o 901(2)-6 A-6, COND PUMP DISCHARGE LOW PRESSURE, Rev. 9 o 901(2)-6 F-5, CONDENSATE BOOSTER PUMP AUTO TRIP, Rev. 10 o 900-7 E-12, GLAND STM EXH MOTOR TRIP, Rev. 3 o 901(2)-7 H-3, CONDENSER LO VACUUM 24 IN. HG, Rev. 9 o 912-8 A-8, SAFE SHUTDOWN SYSTEM TROUBLE, Rev. 5 o 900-54 C-7, NORMAL PROCESS FLOW HI/LO, Rev. 3 o 900-55 B-5, H/2 & O/2 MON SYSTEM CMN FAIL, Rev. 4 QCGP 2-3, REACTOR SCRAM, Rev. 84 QCGP 3-1, REACTOR POWER OPERATIONS, Rev. 79 QGA 100, RPV CONTROL, Rev. 10 QGA 200, PRIMARY CONTAINMENT CONTROL, Rev. 10 QGA 500-1, RPV BLOWDOWN, Rev. 14 QCOA 0201-01, INCREASING DRYWELL PRESSURE, Rev. 27 QCOA 3300-01, LOSS OF CONDENSATE PUMP, Rev. 22 QOA 3300-02, LOSS OF CONDENSER VACUUM, Rev. 40 QCOP 1000-30, POST-ACCIDENT RHR OPERATION, Rev. 31 QCOP 2900-01, SAFE SHUTDOWN MAKEUP PUMP SYSTEM PREPARATION FOR STANDBY OPERATION, Rev. 36 QOP 5600-01, GLAND STEAM STSTEM, Rev. 22 QCOP 5750-19, DRYWELL COOLER OPERATION, Rev. 10 QCOS 1400-04, CORE SPRAY PUMP OPERABILITY TEST, Rev. 16 QCOS 1600-04, WEEKLY PRIMARY CONTAINMENT OXYGEN CONCENTRATION, Rev. 31 QCAP 0200-10, EMERGENCY OPERATING PROCEDURE (QGA) EXECUTION STANDARDS, Rev. 49 QCAP 1500-02, ADMINISTRATIVE TECHNICAL REQUIREMENTS FOR NON-FUNCTIONAL SAFE SHUTDOWN EQUIPMENT, Rev. 32 Quad Cities 2016 NRC EXAM Scenario 4 CREW TURNOVER 1.) Plant Conditions:
a.) Unit 1 is at 75% Power, holding load for Generation Dispatch.
b.) Unit 2 is at 100% Power.
c.) Technical Specification limitations:
(1) Unit 1: None (2) Unit 2: None d.) On Line Risk is GREEN.
e.) Fire Risk is GREEN.
f.) Protected Equipment:
(1) RBCCW (2) Fuel Pool Cooling 2.) Significant problems/abnormalities:
None.
3.) Evolutions/maintenance for the oncoming shift:
a.) Perform QCOS 1400-04, Core Spray Pump Operability Test for the 1B Core Spray Pump.
b.) After the Core Spray monthly is complete, then perform QCOS 1600-04, Weekly Primary Containment Oxygen Test using the 1B CAM (901-56 panel) system.
The critical due date for this surveillance is today.
Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 1 Page 1 of 1 Event
Description:
Perform QCOS 1400-04 for the 1B Core Spray Pump Time Position Applicants Actions or Behavior Directs the BOP to perform QCOS 1400-04, Core Spray Pump SRO Operability Test for the 1B Core Spray Pump.
Starts the 1B Core Spray Pump and verifies the MO 1-1402-38B, CS BOP Min Flow valve opens.
BOP Notifies the SRO of entry time for B Core Spray loop inoperability.
SRO Enters a Short Duration Time Clock for 1B Core Spray Pump inoperable. (TS LCO 3.5.1 Condition B)
BOP Throttles open MO 1-1402-4B, CS BYP AND TEST VLV to establish flow rate of > 4500 gpm at > 216 psig.
BOP Contacts the EO at the pump to report pump suction pressure on PI 1-1402-40B.
SIMOP ROLE PLAY: When contacted, as EO report:
The 1B Core Spray pump suction pressure is 4 psig as indicated on PI 1-1402-40B.
BOP Verifies pump suction pressure is > 3 psig and records pump discharge pressure and flow rate.
BOP Closes and times MO 1-1402-4B.
BOP Verifies MO 1-1402-38B opens as system flow decreases.
BOP Stops the 1B Core Spray Pump.
BOP Closes MO 1-1402-38B valve.
BOP Notifies the SRO to exit the LCO for B Core Spray loop inoperable.
BOP Performs standby lineup verification for B loop Core Spray valves.
BOP Signs off surveillance as satisfactory and returns it to the SRO for approval signature.
ATC Continuously monitors RPV power, pressure, and water level.
End of Event 1 Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 2 Page 1 of 1 Event
Description:
Failure of 1B CAM (901-56 panel) to start for surveillance.
Time Position Applicants Actions or Behavior SRO Directs BOP to perform QCOS 1600-04, Weekly Primary Containment Oxygen Concentration.
BOP Records position of the H2 % O2 MON INLET VLV SELECT switch for each CAM.
BOP Momentarily places the 1B CAM PWR CONT switch to ON at the 901-56 panel and reports the B CAM did NOT start and the sample valves did NOT open.
SRO/BOP Contacts Instrument Maintenance and requests assistance.
SIM OP ROLE PLAY: If contacted, as IM Supervisor, acknowledge the report and then state that you:
Will prepare a troubleshooting package, brief the Techs and then report to the control room.
SRO Enters TLCO 3.3.b, Post Accident Monitoring (PAM) Instrumentation, Condition A, for one required channel inoperable. (Table T3.3.b-1 Function 5 & 6). TS BOP Momentarily places the 1A CAM PWR CONT switch to ON at the 901-55 panel and acknowledges alarms.
BOP Places the H2 & O2 MON INLT SELECT switch for the A Train to the DW position and verifies the sample valves swap from Torus to Drywell.
BOP Dispatches an EO to the Cable Spreading Room to locally reset the 901-55 B-5 alarm.
SIM OP ROLE PLAY: If dispatched to the 901-64A/B panels in the Cable Spreading Room, as EO reset the alarms for the A CAM (901-55 panel) using the following command:
irf pc11r ackn ATC Continuously monitors RPV power, pressure, and water level.
End of Event 2 Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 3 Page 1 of 2 Event
Description:
1C Condensate/Condensate Booster Pump trip with failure of Standby Pump to auto-start.
Time Position Applicants Actions or Behavior SIMOP: At the Lead Evaluators direction, trip the 1C Condensate/Condensate Booster Pump using malfunction FW17C:
imf fw17c Key Parameter Response: 1C Condensate/Condensate Booster Pump trips with failure of Standby Pump to auto-start.
Expected Annunciator(s):
901-6 A-6, COND PUMP DISCHARGE LOW PRESSURE 901-6 F-5, CONDENSATE BOOSTER PUMP AUTO TRIP Automatic Actions: None ( Standby Pump auto-start is defeated)
BOP Reports 1C Condensate/Condensate Booster Pump has tripped and the Standby Pump has failed to autostart.
BOP Manually starts the 1A Condensate/Condensate Booster Pump.
ATC Reports RPV water level is +30 inches and stable.
BOP Refers to QCAN 901-6 F-6 and verifies:
PI 1-3340-48, COND PMP DISCH HDR PRESS, indicates > 104 psig.
1-3240-73, RFP SUCT HDR PRESS, indicates > 145 psig.
US Directs actions of QCOA 3300-01, Loss of Condensate Pump.
BOP Notifies Generation Dispatch of plant status.
SIM OP ROLE PLAY: If contacted, as Generation Dispatch, acknowledge the report of the tripped pump.
BOP Places the COND PMP SELECTOR switch to the OFF position.
ATC/BOP Verifies proper operation of the Feed Water Reg Valves.
BOP Verifies Bus 14 current and voltage are in normal range.
BOP Dispatches EO to Bus 14 to check for any red targets on the breaker compartment or the Bus Auxiliary compartment.
Event 3 Continued Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 3 Page 2 of 2 Event
Description:
1C Condensate/Condensate Booster Pump trip with failure of Standby Pump to auto-start.
Time Position Applicants Actions or Behavior BOP Dispatches EO to check operation of running Condensate/Condensate Booster Pumps and to perform step D.12 of QCOA 3300-01:
- Secure Hydrogen injection on the 1C Cond/Cond Booster Pump
- Valve in Hydrogen injection on the 1A Cond/Cond Booster Pump SIM OP ROLE PLAY: As the EO dispatched to Bus 14, wait 1 minute, then report:
There is an overcurrent target up on Bus 14 cubicle 8, for the 1C Cond/Cond Booster Pump. No other targets are up on any of the compartments.
SIM OP ROLE PLAY: As the EO dispatched to the Condensate Pumps, wait 2 minutes, then report:
The 1A, 1B, and 1D Condensate Pumps are operating normally. Step D.12 of QCOA 3300-01 is complete. Hydrogen injection is valved into the 1A Condensate pump and secured on the 1C Condensate pump.
End of Event 3 Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 4 Page 1 of 1 Event
Description:
SSMP Room Cooler inoperable.
Time Position Applicants Actions or Behavior SIMOP ROLE PLAY: When directed by the Lead Examiner, actuate annunciator 912-8 A-8 using the following command: imf ano9128a8 on Key Parameter Response: None.
Expected Annunciator(s):
912-8 A-8, SAFE SHUTDOWN SYSTEM TROUBLE Automatic Actions: None.
BOP Reports annunciator 912-8 A-8, Safe Shutdown System Trouble is in alarm and refers to annunciator procedure.
BOP Dispatches an EO to the Safe Shutdown Makeup Pump Room to investigate.
SIM OP ROLE PLAY: As the EO, wait 1 minute, then report back that:
The COMPRESSOR TRIP INDICATING LIGHT is lit on the side of the SSMP Room Cooler.
BOP Reports condition to the SRO and directs the EO to attempt a reset per QCOP 2900-01 step F.17.
SIM OP ROLE PLAY: As the EO, wait 4 minutes, then call back and report that you have:
Performed QCOP 2900-01 step F.17 and the COMPRESSOR TRIP INDICATING LIGHT will NOT reset. The light is still lit and the compressor is NOT running.
BOP Reports to the SRO that the SSMP Room Cooler compressor is tripped and will not reset.
BOP Contacts Mechanical Maintenance for assistance.
ATC Continuously monitors RPV power, pressure, and water level.
SRO Declares SSMP inoperable due to an inoperable Room Cooler. Enters the following administrative actions for Units 1 and 2:
TS 3.7.9, Condition A, SSMP inoperable.
SIM OP ROLE PLAY: If contacted, as Maintenance Supervisor, state that you will:
Prepare a troubleshooting package and dispatch a crew to investigate the SSMP Room Cooler Compressor.
End of Event 4 Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 5 Page 1 of 2 Event
Description:
1A Gland Steam Exhauster Trip Time Position Applicants Actions or Behavior SIM OP: When directed by the Lead Examiner, trip the 1A Gland Exhauster by manually initiating trigger 3 trg! 3 Verify the following commands go active:
imf ser0986 (3) on ior dihs156041a (3) trip ior lohs156041a4 (3) on Key Parameter Response: 1A Exhauster Amber Trip light on and Red Running light off:
Lowering Vacuum on Gland Seal Exhaust Vacuum indication, 1-5140-70 Expected Annunciator(s):
901-7 E-12, GLAND STM EXH MOTOR TRIP Automatic Actions: MO 1-5400-E1, A CNDSR EXH ISOL VLV E1 closes when the GSE Motor breaker trips.
BOP Acknowledges annunciator 901-7 E-12, and reports the 1A Gland Steam Exhauster has tripped.
SRO Directs BOP to perform the actions of QCAN 901-7 E-12.
BOP Starts the 1B Gland Steam Exhauster.
BOP Throttles open MO 1-5405B, B CNDSR EXH DISCH VLV D-2.
BOP On the tripped Gland Steam Exhauster, throttles closed MO 1-5405A, A CNDSR EXH DISCH VLV D-1.
BOP On the tripped Gland Steam Exhauster, verifies MO 1-5400-E1, A CNDSR EXH ISOL VLV E1 automatically closes.
BOP Refers to QOP 5600-01, step F.2 BOP Verifies NO valid level alarms on Gland Condenser Hotwell or Shell.
ATC Continuously monitors RPV power, pressure, and RPV water level.
Event 5 Continued Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 5 Page 2 of 2 Event
Description:
1A Gland Steam Exhauster Trip Time Position Applicants Actions or Behavior BOP Throttles the MO 1-5405B to obtain 10 inches to 15 inches of vacuum as indicated on the 1-5140-70, GLAND SEAL EXH VACU.
BOP Verifies GLAND SEAL SPLY PRESS is between 2.5 and 5.0 psig.
BOP Dispatches an EO to MCC 15-1 to investigate the tripped breaker.
SIM OP ROLE PLAY: As the EO, wait 2 minutes after being dispatched to MCC 15-1 and call back to report:
The breaker for the Gland Steam Exhauster Motor at MCC 15-1 cubicle B2 is tripped.
There is no obvious problem at the breaker and you have contacted EMD to investigate.
End of Event 5 Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 6 Page 1 of 2 Event
Description:
Loss of Main Condenser vacuum (Emergency Power Reduction)
Time Position Applicants Actions or Behavior SIM OP: When directed by the Lead Examiner, initiate a 100% loss of Main Condenser vacuum ramped over 25 minutes using malfunction MC08:
imf mc08 100 25:
Key Parameter Response: Main Condenser backpressure rising on PR 1-5640-79; Generator MW(e) lowering, Off gas flow to Main Chimney rising on FI 1-5440-7.
Expected Annunciator(s):
901-3 D-2, OFF GAS HI RADIATION 901-7 H-3, CONDENSER LO VACUUM 24 IN HG 901-5 F-5, CONDENSER VACUUM LO 901-54 C-7, NORMAL PROCESS FLOW HI/LO Automatic Actions: Reactor Scram and Turbine trip BOP Acknowledges 901-3 D-2 alarm and refers to the QCAN.
SRO Directs that reactor power be held constant until the cause of the high radiation is determined.
BOP Monitors SJAE and Main Steam Line radiation levels.
ATC/BOP Report Off Gas Flow as indicated on FI 1-5440-7, OFF GAS FLOW TO MN CHIMNEY, is rising.
ATC/BOP Report Main Condenser backpressure rising.
SRO Enters and directs actions of QOA 3300-02, Loss of Condenser Vacuum.
SRO Directs an Emergency Power Reduction to control Condenser backpressure < 6 in. Hg.
ATC Reduces Recirc Pump speed(s) using the Master/Individual Controllers OR the Manual Runback pushbuttons.
ATC Inserts CRAM rods to maintain FCL within the MELLLA boundary.
BOP Dispatches EOs to verify Condenser vacuum breaker water seal is intact and loop seal are full.
SRO Sets scram criteria at 7.5 in Hg.
BOP Verifies Off-Gas and SJAE suction valves are open.
BOP Verifies Circulating Water System is operating normally.
BOP Verifies Main Condenser Hotwell level is normal.
Event 6 Continued Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 6 Page 2 of 2 Event
Description:
Loss of Main Condenser vacuum (Emergency Power Reduction)
Time Position Applicants Actions or Behavior BOP Acknowledges and reports annunciator 901-7 H-3, CONDENSER LO VACUUM 24 IN. HG, is in alarm.
BOP Notifies Chemistry that Condenser vacuum has been lost and to align Unit 1 Reactor Building Sample Panel drains per CY-QC-110-608.
SRO Directs ATC to insert a manual reactor scram on loss of Main Condenser vacuum.
ATC Inserts a manual reactor scram by depressing both RX SCRAM pushbuttons AND placing the RX MODE SELECT switch to SHUTDOWN.
End of Event 6 Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 7 Page 1 of 3 Event
Description:
Electric ATWS (Manual ARI inserts rods)
Time Position Applicants Actions or Behavior Key Parameter Response: No control rod movement when manual scram is inserted. All 8 RPS SCRAM SOLENOID GROUP indicating lights on 901-5 panel remain lit.
Expected Annunciator(s):
901-5 C-5, ATWS CHANNEL A OR B MANUAL PB ARMED (when ARI system is initiated) 901-5 A-1, SCRAM VALVE AIR SUPPLY LOW PRESSURE (when ARI system is initiated) 901-5 A-10/15, CHANNEL A/B MANUAL SCRAM Automatic Actions: None ATC Reports control rods did NOT insert SRO Enters QGA 100, RPV Control and transitions to QGA 101 on failure to scram when above 5% power.
CT1 ATC Arms and depresses ARI pushbuttons.
ATC Injects SBLC by placing the SBLC PUMP SELECT to either SYS 1 or SYS 2. (if control rod motion has not been observed yet)
ATC Runs both Recirc Pump speeds to minimum (32%).
SRO Directs BOP to inhibit ADS.
BOP Inhibits ADS by placing AUTO BLOWDOWN INHIBIT switch to INHIBIT.
SRO Directs Core Spray Pumps placed in P-T-L.
BOP Places both Core Spray Pump control switches in P-T-L.
ATC Reports ALL control rods are inserted.
SRO Directs ATC to terminate Boron injection.
ATC Places SBLC switch to OFF. (if system was injecting)
SRO Directs BOP to return AUTO BLOWDOWN INHIBIT switch to the NORMAL position and take Core Spray pump control switches out of P-T-L.
BOP Places AUTO BLOWDOWN INHIBIT switch to the NORMAL and takes both Core Spray pump control switches out of P-T-L.
SRO Exits QGA 101 and re-enters QGA 100.
SRO Directs ATC to enter and perform actions per QCGP 2-3, Reactor Scram.
Event 7 continued Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 7 Page 2 of 3 Event
Description:
Electric ATWS (Manual ARI inserts rods)
Time Position Applicants Actions or Behavior ATC Performs post scram actions per QCGP 2-3, Attachment A.
SRO Directs ATC/BOP to verify auto actions/isolations for 0 inches RPV water level.
ATC/BOP Report all Group II and Group III isolations are verified SRO Directs ATC to control RPV water level in a band of 0 to +48 in. with the Condensate and Feedwater system.
ATC Controls RPV water level in 0 to +48 in. band using the Condensate/Feed System.
BOP Starts up RWCU system in reject mode per QCOP 1200-07 Attach. A (Hard Card)
- Verifies RBCCW system is in operation at the 912-1 panel.
- Resets Group III isolation with the ISOL VLV RESET switch at the 901-5 panel.
- Cracks open MO 1-1201-80, RETURN ISOL VLV.
- Starts 1A/B RWCU pump throttling open MO 1-1201-80 valve as necessary to clear alarm 901-4 H-12, RWCU SYSTEM PUMPS LOW FLOW.
- Throttles MO 1-1201-80 to establish pump discharge pressure 100 to 200 psig > Reactor pressure.
- Opens MO 1-1201-78, CU REJECT TO CONDENSER SV.
- Removes Filter Demins from operation per QCOP 1200-03.
BOP Dispatches EO to the RWCU Demin Panel 2201-61.
Event 7 continued Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 7 Page 2 of 3 Event
Description:
Electric ATWS (Manual ARI inserts rods)
Time Position Applicants Actions or Behavior SIM OP ROLE PLAY: If dispatched as EO to isolate the RWCU Demins, wait 2 minutes, then call back and remove the 1A and 1B Demins respectively, using the commands below.
Note: (the BOP will throttle open MO 1-1201-133, DEMIN BYPASS VLV as each one is taken off line.)
irf cu13r 0 :30 irf cu09r out irf cu14r 0 :30 irf cu10r out SRO Directs the BOP to initiate an RPV cooldown using ADS valves at
< 100°F/hr.
ATC/BOP Initiate an RPV cooldown using ADS valves.
End of Event 7 Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 8-9 Page 1 of 5 Event
Description:
Main Steam Line break inside the Drywell / Blowdown Time Position Applicants Actions or Behavior SIM OP: When the plant is stabilized and at the direction of the Lead Examiner, insert a .5%
break in the B Main Steam Line ramped over 10 minutes using malfunction MS04B:
imf ms04b .5 10:
Key Parameter Response: Drywell /Torus pressure and temperature rising Expected Annunciator(s): (Not a complete list) 901-3 A-16 PRIMARY CONTAINMENT HIGH PRESSURE 901-5 D-11 PRIMARY CNMT HIGH PRESS Automatic Actions: Group 2 Isolation, CR and RB Vents isolate, SBGTS starts, ECCS systems initiate, EDGs start, LOCA Load Shed, LPCI Loop Select BOP Acknowledges and reports annunciator 901-3 A-16, PRI CNMT HIGH PRESSURE, is in alarm.
BOP Monitors and reports rising Drywell pressure.
SRO Directs BOP to take actions per QCOA 0201-01.
BOP Makes an announcement to evacuate the Reactor Building.
BOP Notifies Radiation Protection of elevated drywell pressure and directs them to control access to the Reactor Building.
ATC/BOP Investigate cause of increasing Drywell pressure.
BOP Reports Drywell pressure at 2.5 psig and rising.
SRO Enters QGA 100 and 200 on 2.5 psig Drywell pressure.
SRO Directs ATC/BOP to verify auto actions for 2.5 psig Drywell pressure.
SRO Verifies HPCI is not needed for core cooling and directs ATC/BOP to trip-latch HPCI.
ATC/BOP Places HPCI turbine Trip pushbutton in trip-latch.
ATC/BOP Verify isolations and actuations per QCAP 0200-10 Attach. O.
SRO Directs BOP to restart RBCCW and Drywell Coolers.
BOP Restarts RBCCW and Drywell Coolers per QCOP 5750-19, Hard Card.
Event 8-9 continued Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 8-9 Page 2 of 5 Event
Description:
Main Steam line break inside Drywell / Blowdown Time Position Applicants Actions or Behavior SRO Directs BOP to initiate and maximize Torus Cooling.
BOP Maintains the following during Post-Accident RHR Operation:
- RHR Service Water Pressure 15-20 psig > RHR Pressure
- RHR Service Water flow <3600 gpm/pump
Verifies RHR Pumps running.
Places LOOP A/B CONTAINMENT COOLING PERMISSIVE Switch 17 to ON.
Places LOOP A/B RHR SW START PERMISSIVE Switch 19 to MANUAL OVERRIDE.
BOP Starts an RHR Service Water on both loops.
Opens MO 1-1001-5A/B to approximately 40%.
Throttles MO 1-1001-5A/B as necessary.
Closes MO 1-1001-16A/B valves.
BOP Starts 2nd RHR Service Water pump on both loops.
Opens MO 1-1001-5A/B to achieve approximately 140 psig RHR Service Water pressure.
Throttles MO 1-1001-5A/B as necessary to maintain flow
<7200 gpm and discharge pressure <350 psig.
Event 8-9 continued Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 8-9 Page 3 of 5 Event
Description:
Main Steam line break inside Drywell / Blowdown Time Position Applicants Actions or Behavior BOP Opens MO 1-1001-34A.
BOP Throttles open MO-1-1001-36A and maintains RHR discharge pressure in a 100-250 psig band.
BOP Attempts to open MO 1-1001-34B and reports the valve will NOT open.
Determines a possible problem with the S-17B switch (RHR Loop B CONTAINMENT Clg permissive) and contacts EM for assistance.
SIM OP ROLE PLAY: If directed as EMD or IMD to troubleshoot LOOP B CONTAINMENT COOLING PERMISSIVE Switch 17, inform the operator you will locate your supervisor, start a troubleshooting package, and then report to the control room (No EMD or IMD personnel will enter the simulator).
SRO Verifies Torus level <27 ft.
SRO Before Torus Pressure reaches 5 psig, directs BOP to start Torus Sprays.
BOP As directed, initiates Torus Sprays on A Loop.
Opens MO 1-1001-34A.
Opens MO 1-1001-37A and reports Torus Sprays initiated.
BOP Throttles MO 1-1001-36A as necessary to maintain RHR Discharge Pressure.
SRO Directs BOP to secure Torus Sprays before Torus Pressure drops to 0 psig.
BOP Reports Torus pressure >5 psig.
SRO Verifies Torus level <17 ft.
SRO Verifies containment parameters (DW temperature and pressure) are within the DW Spray Initiation Limit Curve.
SRO Verifies Recirc pumps are tripped and directs Drywell coolers tripped if restarted.
BOP Trips drywell coolers. (if required)
Event 8-9 Continued Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 8-9 Page 4 of 5 Event
Description:
Main Steam line break inside Drywell / Blowdown Time Position Applicants Actions or Behavior SRO Directs BOP to initiate DW Sprays.
BOP Reports the RHR 23A valve breaker tripped and dispatches an EO to MCC 18-1B.
SIM OP ROLE PLAY: As EO dispatched to investigate the RHR 23A valve breaker, wait 4 minutes, then report back:
The RHR 23A valve breaker is tripped and will not reset.
BOP Dispatches EOs to manually open the RHR 23A valve.
SIMOP ROLE PLAY: If asked for status of opening the DW spray valves state that you are:
Having trouble moving the handwheel and have requested assistance from Mechanical Maintenance.
SRO May direct actions to start all available drywell cooling.
ATC/BOP Restarts DW coolers if directed.
CT2 SRO Enters and directs actions of QGA 500-1 to blowdown the vessel when it is determined Drywell temperature cannot be restored below 280ºF or Torus pressure cannot be maintained within PSP limits.
ATC/BOP Prevents injection from Core Spray and LPCI not needed for Core Cooling by diverting LPCI flow to Torus cooling and/or placing pumps in PTL.
SRO Verifies Torus level > 5 feet.
CT2 BOP Opens all 5 ADS valves and leaves switches in MAN.
BOP Verifies all ADS valves open by acoustic monitor indication on the 901-21 panel.
Event 8-9 continued Quad Cities 2016 NRC EXAM Scenario 4 Appendix D Required Operator Actions Form ES-D-2 Quad Cities 2016 NRC Scenario No. 4 Event No. 8-9 Page 5 of 5 Event
Description:
Main Steam line break inside Drywell / Blowdown Time Position Applicants Actions or Behavior ATC Verifies or trips RFPs due to level exceeding +48 inches from swell.
ATC/BOP Monitors RPV water level instruments for indications of saturation.
SIM OP NOTE: When RPV pressure is a or below 100 psig, RPV water level is stabilized, and at the direction of the Lead Evaluator, freeze the Simulator.
End of Scenario