ML103640349: Difference between revisions
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| author name = | | author name = | ||
| author affiliation = Constellation Energy Nuclear Group, LLC | | author affiliation = Constellation Energy Nuclear Group, LLC | ||
| addressee name = Fish T | | addressee name = Fish T | ||
| addressee affiliation = NRC/RGN-I/DRS/OB | | addressee affiliation = NRC/RGN-I/DRS/OB | ||
| docket = 05000410 | | docket = 05000410 |
Revision as of 01:10, 11 July 2019
ML103640349 | |
Person / Time | |
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Site: | Nine Mile Point ![]() |
Issue date: | 10/27/2010 |
From: | Constellation Energy Nuclear Group |
To: | Todd Fish Operations Branch I |
Hansell S | |
Shared Package | |
ML101900599 | List: |
References | |
TAC U01790 | |
Download: ML103640349 (203) | |
Text
NRC JPM SRO C001 Constellation Energy NMP UNIT OPERATOR JOB PERFORMANCE Title: Review Daily Checks Log lAW N2-0SP-LOG-D001 Revision:
NRC 2010 Task Number: NA Approvals:
NA Exam Security I General Supervisor Date Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
____________(SRO) Trainer/Evaluator:
_________ Evaluation Method: Perform Evaluation Location:
Simulator or Other Designated Location Expected Completion Time: 45 minutes Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop Time: Completion Time: ____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluator Signature:
_____________
_ Date:______ NRC 2010 Admin SRO/JPM C001 November 2010 Recommended Start Location: (Completion time based on the start location)
Any appropriate location with the required Reference Material.
Simulator Set-up: None Directions to the Instructor/Evaluator:
To be performed as an administrative JPM. Directions to Operators:
Read Before Every JPM For the performance of this JPM, I will function as the SM, CRO, and Plant Prior to providing direction to perform this task, I will provide you with the initial and answer any questions.
During task performance, I will identify the steps to simulated, or discuss and provide cues as Read Before Each Evaluated JPM This evaluated JPM is a measure of your ability to perform this task independently. Control Room Supervisor has determined that a verifier is not available and that I concurrent verification will not be provided; therefore it should not be Read Before Each Training JPM During this Training JPM, applicable methods of verification are expected to be Therefore, either another individual or I will act as the additional I concurrent Notes to Instructor I Critical steps are identified as Pass/Fail.
All steps are sequenced critical unless denoted by a "e". During Evaluated e Self-verification shall be During Training JPM: Self-verification shall be demonstrated.
- No other verification shall be N2-0SP-LOG-D001, Daily Checks Log OD-7 -100% power KIA 2.1.18(3.0)
Ability to make accurate, clear and concise logs, records, status boards, and reports. Tools and Equipment:
- 1.
Task N2-0SP-LOG-D001, Attachment 2 review completed and deSignated errors documented in the Remarks Section of N2-0SP-LOG-D001.
NRC 2010 Admin C001 November 2010 Initial Conditions: The plant is operating at 100% power. N2-0SP-LOG-0001 for the daily checks log has been completed and submitted for CRS/SM review. Ask the operator for any questions.
Initiating "(Operator's name), Perform a review of N2-0SP-LOG-0001, Attachment 2 and document results and required compensatory actions, if any, in Remarks Section on page 11 of N2-0SP-LOG-0001.
Attachment reviews for Item #'s 27,30 and 31 will be performed by another Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary EVALUATOR to provide copy of N2-0SP-LOG-D001 to candidate for review. RECORD START TIME __ .Obtain a copy of the reference procedure and review/utilize the correct section. Proper communications used for Sat/Unsat repeat back (GAP-OPS-01)
N2-0SP-LOG-0001 obtained.
SaUUnsat Attachment 2 referenced.
NRC 2010 Admin SROfJPM C001 November 2010 Initial Conditions: The plant is operating at 100% power. N2-0SP-LOG-0001 for the daily checks log has been completed and submitted for CRS/SM review. Initiating Cue: "(Operator's name), Perform a review of N2-0SP-LOG-0001, Attachment 2 and document results and required compensatory actions, if any, in the Remarks Section on page 11 of N2-0SP-LOG-0001.
Attachment reviews for Item #'s 27, 30 and 31 will be performed by another operator." NRC 201 Admin SRO/JPM C001 November 2010 NRC JPM SRO C002 Constellation Energy OPERATOR JOB PERFORMANCE Title: SRO Actions for Exceeding CDI Conductivity Action Level 3 Revision:
NRC 2010 Task Number: NA Approvals:
NA Exam Security I General Supervi or General Supervisor Date Operations Trai ing (Designee)
Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
_________(SRO) Trainer/Evaluator:
_______ Evaluation Method: Perform Evaluation Location:
Simulator or Other Designated Area Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop Time: Completion Time: ____ J PM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluator Signature:
_____________
_ Date:______ NRC 2010 Admin SROI ..IPM C002 1 November 2010 Recommended Start Location: (Completion time based on the start location)
N/A Simulator Set-up: N/A Directions to the Instructor/Evaluator:
To be performed as an administrative JPM. Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
This evaluated .JPM is a measure of your ability to perform this task independently.
The Control Room Supervisor has determined that a verifier is not available and that additional!
concurrent verification will not be provided; therefore it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional I concurrent verifier.
Notes to Instructor I Evaluator: Critical steps are identified as Pass/Fail.
All steps are sequenced critical unless denoted by During Evaluated JPM: Self-verification shall be demonstrated. During Training JPM: Self-verification shall be demonstrated. No other verification shall be demonstrated.
References:
GAP-CHE-01 REVISION 14 KIA 2.1.25 (4.2), Ability to obtain and interpret station reference materials such as graphs and tables which contain performance data. KIA 2.1.34 (3.5) Ability to maintain the primary and secondary plant chemistry allowable Tools and NRC 2010 Admin SRO/JPM C002 November 2010 Task Determine plant shutdown and cooldown are required for COl value above Action Level 3 NRC 2010 Admin SRO/JPM C002 3 November 2010 Initial Conditions: The reactor is operating at 20% power You have just been told by the Chemistry Technician that Condensate Conductivity (COl) is reading 1.221 JJS/cm @ 25C and rising slowly. The source of the conductivity rise is indeterminate. A Biocide chemical addition to the system is ongoing. Ask the operator for any questions.
Initiating cue: "(Operator's name), determine and direct the applicable action(s), if any, for the given value of COl" Provide repeat back of Proper communications used for initiating cue. Evaluator repeat back Acknowledge repeat providing correction RECORD START TIME .Obtain a copy of the GAP-CHE-01 is obtained and SaUUnsat l reference procedure and Enclosure 2 is review/utilize the .Determines Action Level Using the supplied value of COl and 3 has been exceeded.
Enclosure
- Determines that the given value of COl is above Action Level 3 IJS/cm). -Enters Section 3.2.3 of Notifies the following personnel that GAP-CHE-01.
COl has exceeded Action Level NRC 2010 Admin SRO/JPM C002 November 2010 Performance SteDs -Initiates an orderly shutdown. .Initiates a cooldown to <200F NOTE: May also identify that a PORC review of corrective actions is performed prior to any restart. Standard SM General Supervisor Chemistry Operations Manager Plant General Manager Vessel & Internals Program Mitigation Engineer Initiate an orderly shutdown as quickly as plant constraints permit. Initiate a cooldown to <200F as quickly as plant constraints permit. Grade Comments TERMINATING CUE:. Determine plant shutdown and cooldown are required for COl value above Action Level 3 RECORD STOP TIME____ NRC 2010 Admin SRO/JPM C002 November 2010 Initial Conditions: The reactor is operating at 20% power You have just been told by the Chemistry Technician that Condensate Conductivity (COl) is reading 1.221IJS/cm
@ 25C and rising slowly. The source of the conductivity rise is indeterminate. A Biocide chemical addition to the system is ongoing. Initiating Cue: "(Operator's name), determine and direct the applicable action(s), if any, for the given value of COl" NRC 2010 Admin SRO/JPM C002 November 2010 SRO Admin JPM EC Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Review and Approval of Completed Surveillance Test, Revision:
NRC 2010 N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test. Task Number: NA Approvals:
NA Exam Security I Date General Supervisor Date Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
_____________(SRO) Trainer/Evaluator:
____________
_ Evaluation Method: L Perform ___Simulate Evaluation Location:
_Plant Expected Completion Time: 25 min. Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop Time: Completion Time: ____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluators Signature:
_____________
_ Date:______ NRC 2010 Admin SRO/JPM EC November 2010 Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up (if required):
None Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM I CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM / CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this ..IPM, I will function as the SM, CRO, and Plant Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently.
The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor
/ Evaluator: Critical steps are identified in grading areas as Pass/Fail.
All steps are sequenced critical unless denoted by a "e". During Evaluated JPM: Self verification shall be demonstrated. During Training JPM: Self verification shall be demonstrated. No other verification shall be demonstrated.
References:
N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test NUREG KIA General Knowledges and Abilities 2.2.12 (4.1) NRC 2010 Admin SRO/JPM EC November 2010 Tools and Equipment: Copy of N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test, completed through Step 10.1 Task Standard:
Given a copy of N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test, the candidate will review the results, identify the discrepancies, and record the results in sections 10.1 and 10.2. NRC 2010 Admin SRO/JPM EC November 2010 Initial Conditions: The Plant is operating at 100% power. N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test, has just been completed.
Initiating Cues: "(Operator's name), this is a copy of N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test. Review the test results and complete Section 10.1 and 10.2." Performance Steps Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME ____ Review/utilize the correct section of the procedure.
Evaluator is to provide the marked up copy of N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test, to the candidate. Determines status of the completed surveillance.
NOTE: May inform examiner verbally of issues Standard Proper communications used for repeat back (GAP-OPS-011)
Grade SatlUnsat Reviews General Test Methods, References/Commitments and the Precaution and Limitation Sections.
SatlUnsat Reviews N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test and identifies the following in the remarks section: SatlUnsat
- 1. At Step 8.1.3 -the incorrect closing time was entered. The initial stroke time of 3.5 seconds should have been entered. lAW precaution and limitation 6.2.1. Pass/Fail The initial stroke time is noted in the remarks section 10.2 (1. -3.5 seconds) 2. At step 8.5.8, the closing stroke time exceeds the TS limit and the SAT block is checked. The UNSAT block should be checked. Pass/Fail
- 3. The valve at Step 8.5.8 was stroked a second time which is not permitted per P&L 6.2.2. SatlUnsat NRC 2010 Admin SRO/JPM EC November 2010 Performance Steps 4. Notify appropriate Plant Management. Acknowledge the information presented.
Standard 4. TS 3.6.1.3.A.1 must be entered -for valve at step 8.5.8. -Isolate the affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. There is an additional TS action to verify the isolated penetration every 31 days however that is NOT Critical.
The ONLY part of this step that is critical is the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> action. Notifies EXAMINER/Ops MGR or designee of issues identified.
Grade Pass/Fail SatlUnsat Terminating Cue: Determination of the status of this surveillance has been made. RECORD STOP TIME ____ NRC 2010 Admin SRO/JPM EC November 2010 Initial Conditions: The Plant is operating at 100% power. N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test, has just been completed through Section 10.1. Initiating Cues: "(Operator's name), this is a copy of N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test. Review the test results and complete Section 10.1 and 10.2." NRC 2010 Admin SRO/JPM EC November 2010 NRC JPM SRO RC Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Generate and approve an Emergency Exposure Authorization Revision:
NRC 2010 Task Number: N/A Approvals:
N/A Exam Security I General Supervisor Date Operations (Designee)
N/A -Exam Security I Configuration Control Date Performer:
_________(SRO) Trainer/Evaluator:
_______ Evaluation Method: Perform Evaluation Location:
Classroom Expected Completion Time: 25 minutes Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop Time: Completion Time: ____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluator Signature:
_____________
_ Date:______ NRC 2010 SRO ADMIN JPM RC November 2010 Recommended Start Location:
Classroom Simulator Set-up: None Directions to the Instructor/Evaluator:
None Directions to Operators:
Read Before Every JPM For the performance of this JPM, I will function as the Radiation Protection, CRO, and Operators.
Prior to providing direction to perform this task, I will provide you with the conditions and answer any questions.
During task performance, I will identify the steps to simulated, or discuss and provide cues as Read Before Each Evaluated JPM This evaluated JPM is a measure of your ability to perform this task independently.
The Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore it should not be requested.
Read Before Each Training JPM During this Training JPM, applicable methods of verification are expected to be used.
either another individual or I will act as the additional I concurrent Notes to Instructor I Evaluator:
- 1. Critical steps are identified as Pass/Fail.
- 2. During evaluated JPM:
- Self-verification shall be demonstrated.
- 3. During training JPM:
- Self-verification shall be demonstrated.
- No other verification shall be demonstrated.
References:
- 1. NUREG 1123, 2.3.4, SRO 3.7 2. EPIP-EPP-15 Tools and Equipment:
- 1. Calculator Task Standard:
Generate and approve an Emergency Exposure Authorization Form and estimate exposure.
NRC 2010 SRO ADIVIIN JPM RC November 2010 Initial Conditions: A Site Area Emergency is in progress. You have assumed the responsibilities of the Shift Manager/Emergency Director. A RCIC steam leak into the Reactor Building cannot be isolated without manually shutting ICS*MOV121. Entry to the Reactor Building is required to manually close valve ICS*MOV121 to stop a release to the environment. Time to complete the task for an experienced Licensed Reactor Operator will be approximately 24 minutes. Time to complete the task for a new Licensed Reactor Operator will be approximately Radiation levels at the valve are approximately 15 Rlhr. Four (4) individuals are available to perform the task: Worker A is a volunteer who is an experienced Licensed Reactor Operator, has previously received a planned special exposure at another facility, and has received a dose of 150 mR this year (TLO Badge No. 11111, SSN 111-11-1111). Worker B is a volunteer who is an experienced Licensed Reactor Operator and is a declared pregnant worker and has received a dose of 15 mR this year (TLO Badge No. 22222, SSN 222-22-2222). Worker C is a volunteer who is an experienced Licensed Reactor Operator and has received a dose of 1800 mR this year (TLO Badge No. 33333, SSN 333-33-3333). Worker 0 is a volunteer who is a new Licensed Reactor Operator that has received a dose of 500 mR this year (TLO Badge No. 44444, SSN 444-44-4444). Ask the operator for any questions.
Initiating Cue: "(Operator's name), choose an individual to close valve ICS*MOV121, state the reason why that worker was chosen, estimate the expected radiation exposure and document your authorization for an Emergency Exposure." Provide repeat back of initiating cue Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME ____ Obtain a copy of the reference procedure and review/utilize the correct section. Determine the expected exposure for the task NRC 2010 SRO ADMIN JPM RC Proper communications used for repeat back (GAP-OPS-01) EPIP-EPP-15 is obtained and Attachments 1 and 1-1 are referenced For an experienced worker Calculates that a 24 minute exposure in a 15 Rlhr field will cause a dose of 6R For a new worker -Calculates that a 30 minute exposure in a 15 Rlhr field will cause a dose of 7.5 R SatlUnsat SatlUnsat SatlUnsat November 2010 I Performance Steps I I Grade Select the best worker to perform the task Note: The following rationale supports worker selection: Worker A should NOT be chosen due to previously receiving a planned special exposure Worker B should NOT be chosen due to being a declared pregnant worker Worker C should be chosen because both their dose for the emergency exposure (6 R) will be less than that for Worker 0; additionally, the dose to the public will be minimized by the shorter task completion time of this experienced worker Worker D should NOT be chosen because their dose for the emergency exposure (7.5 R) will be greater than that for Worker C State reason for choosing the selected worker Estimate expected exposure Role Play: The Candidate may choose to brief the worker on radiological conditions, potential for steam leakage in the area, planned task, applicable ALARA measures, and contingency measures.
NRC 2010 SRO ADIVIIN JPM RC Determines the best worker for the task:
- Does NOT select Worker A Does NOT select Worker B Selects Worker C Does NOT select Worker D :::J States that Worker C was chosen to minimize dose. 0 States that Worker A was NOT chosen due to a previous planned special exposure.
0 States that Worker B was NOT chosen due to being a declared pregnant worker. 0 States that Worker D was NOT chosen due to higher dose. 0 Determines Worker C will receive an estimated 6 R while completing the task (24 minutes x 15 Rlhr I 60 min/hr) Pass/Fail Pass/Fail Pass/Fail Pass/Fail Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat Sat/Unsat November 2010 Role Play: As Worker C acknowledge the briefing.
Role Play: The Candidate may ask for an RWP to be generated.
Role playas RP and state that an RWP has been generated. Generate an Emergency Exposure
- Candidate obtains a copy of Pass/Fail Authorization form EPP-15 Attachment 1-1 Candidate completes Section A (see attached key) TERMINATING CUE: Emergency Exposure Authorization Form has been completed.
RECORD STOP TIME____ NRC 2010 SRO ADMIN JPM RC November 2010 Initial Conditions: A Site Area Emergency is in progress. You have assumed the responsibilities of the Shift Manager/Emergency Director. A RCIC steam leak into the Reactor Building cannot be isolated without manually shutting ICS*MOV121. Entry to the Reactor Building is required to manually close ICS*MOV121 to stop a release to the Time to complete the task for an experienced Licensed Reactor Operator will be approximately 24 minutes. Time to complete the task for a new Licensed Reactor Operator will approximately 30 Radiation levels at the valve are approximately 15 R/hr. Four (4) individuals are available to perform the task: Worker A is a volunteer who is an experienced Licensed Reactor Operator, has previously received a planned special exposure at another facility, and has received a dose of 150 mR this year (TLD Badge No. 11111, SSN 111-11-1111). Worker B is a volunteer who is an experienced Licensed Reactor Operator, is a declared pregnant worker and has received a dose of 15 mR this year (TLD Badge No. 22222, SSN 222-22-2222). Worker C is a volunteer who is an experienced Licensed Reactor Operator and has received a dose of 1800 mR this year (TLD Badge No. 33333, SSN 333-33-3333). Worker D is a volunteer who is a new Licensed Reactor Operator that has received a dose of 500 mR this year (TLD Badge No. 44444, SSN 44-4444).
Initiating Cue: U(Operator's name), choose an individual to close valve ICS*MOV121, state the reason why that worker was chosen, estimate the expected radiation exposure and document your authorization for an Emergency Exposure." NRC 2010 SRO ADMIN JPM RC November 2010 NRC SRO ADMIN JPM EP Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Event Classification and Notifications Revision:
NRC 2010 Task Number: N/A Approvals:
NA Exam Security I General Supervisor Date Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
_________(SRO) Trainer/Evaluator:
_____ Evaluation Method: Perform Evaluation Location:
Simulator or Other Designated Area Expected Completion Time: 25 min. Time Critical Task: Yes Alternate Path Task: No Start Time: ____ Stop Time: Completion Time: ____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluator Signature:
______________
_ Date:______ NRC SRO ADMIN JPM EP November 2010 Recommended Start Location: (Completion time based on the start location)
Classroom or Simulator.
Ensure sufficient copies of SM/ED Checklist Package are available Simulator Set-up: None Directions to the Instructor/Evaluator:
To be performed as an administrative JPM. Ideally this JPM should be performed in the Control Room or Simulator to provide adequate procedural resources.
If this JPM cannot be performed in one of these locations, then the complete SM/ED Checklist Package must be provided to the Candidate.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the Unit 1 SM, Security Supervisor, Communication Aid, and other personnel as necessary.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently.
The Control Room Supervisor has determined that a verifier is not available and that additional!
concurrent verification will not be provided; therefore it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional/
concurrent verifier.
Notes to Instructor
/ Evaluator: Critical steps are identified as Pass/Fail.
All steps are sequenced critical unless denoted by a "e". During Evaluated JPM: Self-verification shall be demonstrated. During Training JPM: Self-verification shall be demonstrated. No other verification shall be demonstrated.
References:
EPIP-EPP-02, Classification Of Emergency Conditions at Unit 2 EPIP-EPP-18, Attachment 1 SM/ED Checklist EPIP-EPP-20, Emergency Notifications KIA 2.4.29(4.0), Knowledge of the Emergency Plan. NRC SRO ADMIN JPM EP November 2010 Tools and Equipment:
1.0 EPIP-EPP-02, ATTACHMENT 2, UNIT 2 EAL FLOWCHART 2.0 SM/ED Checklist Package Task Standard:
Classify the event within 15 minutes of the time that indications are available in the Control Room that an EAL has been exceeded and make all appropriate notifications within 15 minutes of the time the event is classified.
Initial Conditions:
- 1. You are the Shift Manager at NMP2. The STA is unavailable.
- 2. Unit 2 had been operating at 100% power. 3. Unit 1 is operating at full power. 4. The following conditions exist:
- Rising drywell pressure caused the crew to insert a manual scram
- MODE Switch failed to trip RPS, (Five) 5 minutes ago.
- Depressing the Manual SCRAM pushbuttons caused all control rods to insert to 00, Four (4) minutes ago.
- RPV has been flooded to the Main Steam Lines.
- Reserve Transformer "Au has faulted and is lost
- No Release is in progress or anticipated Initiating Cue: "(Operator's name), Based on the above conditions determine the event classifications per EPIP-EPP-02 and complete steps 1 through 9.a of EPIP-EPP-18, Attachment 1, SM/ED Checklist".
This is a time critical activity.
Meteorological Data ! Wind Speed (30 ft) 5 mph I Wind Direction (30 ft) 60 0 I *:i Wind Speed (200 ft) 10 mph I Wind Direction (200 ft) 60 0 '.I Stability Class D
- NRC SRO ADMIN JPM EP November 2010 Performance Steps Provide repeat back of initiating cue Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME ____ Obtain a copy of EPIP-EPP-01 attachment 1 and Shift Manager emergency paperwork and review/utilize the correct section Enters EPIP-EPP-18, Attachment 1, SM/ED Checklist and completes Steps 1 through g.a Classifies and declares the emergency If candidate asks how long it has been since Reserve Transformer A was de-energized, report 15 minutes. Completes EPIP-EPP-18 attachment 1, figure 1 flowchart to determine evacuation and accountability requirements Evacuation determination is subjective and mayor may not be performed.
This will determine which path is taken on EPI P-EPP-18 Attachment 1 and which steps are completed on EPIP-EPP-18 Attachment
- 2. Calls the Communications Aides to the Control Rooms Role Play: Acknowledge communication NRC SRO ADMIN JPM EP I Standard Proper communications used for repeat back (GAP-OPS-01)
EPIP-EPP-01 attachment 1 and Shift Manager emergency paperwork is obtained Completes steps 1 thru g.a. of 18, as described in subsequent JPM steps Declares a Site Area Emergency within fifteen minutes of the JPM initial condition sheet being accepted in accordance with EAL 2.1.2 EXAMINER NOTE: Time difference below must be 15 minutes or less: JPM start time: ____ Time of Declaration:
_____ Completes Attachment as shown in KEY Proper communications used 01) I Grade SatlUnsat SatlUnsat SatlUnsat Pass/Fail SatlUnsat SatlUnsat November 2010 I Performance Steps 7. Fills out the ERO Notification System (ERONS) form I Standard Completes Attachment as shown in KEY I Grade SatiUnsat J. Calls Unit 1 SM to inform that ERONS form is coming and to get Unit 1 plant status Proper communications used 01) SatiUnsat Role Play: If asked about the status of Unit 1, report that Unit 1 is still operating at 100% power with no issues 9. Completes EPIP-EPP-18 attachment 2, Emergency Announcement Completes Attachment as shown in KEY SatiUnsat
- 10. Completes EPIP-EPP-20 Part 1 Notification Fact Sheet Completes Attachment as shown in KEY Part 1 Notification Fact Sheet Steps 3 thru 7 are Critical Steps Pass/Fail EXAMINER NOTE: Time difference must be 15 minutes or less: Time of Declaration (from JPM step 4): Time EPIP-EPP-20 Part 1 Notification Fact Sheet is complete:
TERMINATING CUE: Part 1 Notification Fact Sheet completed.
RECORD STOP TIME ____ NRC SRO ADMIN JPM EP November 2010 Initial Conditions:
- 1. You are the Shift Manager at NMP2. The STA is unavailable. Unit 2 had been operating at 100% power. Unit 1 is operating at full power. The following conditions exist: Rising drywell pressure caused the crew to insert a manual scram MODE Switch failed to trip RPS, (Five) 5 minutes ago. Depressing the Manual SCRAM pushbuttons caused all control rods to insert to 00, Four (4) minutes ago. LOCA occurred causing loss of RPV level instrumentation. RPV has been flooded to the Main Steam Lines. Reserve Transformer "A" has faulted and is lost No Release is in progress or anticipated Initiating Cue: "(Operator's name), Based on the above conditions determine the event classifications per EPIP-EPP-02 and complete steps 1 through g.a of EPP-18, Attachment 1, SM/ED Checklist".
This is a time critical activity.
Meteorological Data 5 m h 10 m h Stability D NRC SRO ADMIN JPM EP November 2010 NRC JPM RO C001 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Verification of Active License Status Revision:
NRC 2010 Task Number: N/A Approvals:
NA Exam Security I General Supervisor Date Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
_____________(RO/SRO) Trainer/Evaluator:
___________
_ Evaluation Method: ---=...X"---_
Perform -----Simulate Evaluation Location:
___ Plant __---:....:X'--_
Simulator or Classroom Expected Completion Time: 10 minutes Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop Time: Completion Time: ____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluator Signature:
_____________
_ Date:______ NRC 2010 RO ADMIN JPM C001 November 2010 Recommended Start Location: (Completion time based on the start location)
Classroom Simulator Set-up: None Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM / CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM / CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically Repositioning of devices will be simulated by discussion and acknowledged by my Read Before Each Evaluated
...IPM This evaluated JPM is a measure of your ability to perform this task independently.
The Room Supervisor has determined that a verifier is not available and that additional/
verification will not be provided; therefore, it should not be Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor I Evaluator:
- 1. Critical steps are identified in grading areas Pass/Fail.
- 2. During Evaluated JPM:
- Self verification shall be demonstrated.
- 3. During Training JPM:
- Self verification shall be demonstrated.
References:
- 1. NUREG 1123,2.1.4,3.3
- 2. S-ODP-TQS-0101 Tools and NRC 2010 RO ADMIN JPM C001 November None Task Candidate determines that only RO #1 is qualified to stand the watch using the criteria contained in S-ODP-TQS-0101.
Initial Conditions: The plant is operating at 100% power. Today is January 1, 2011. You are the CRO. You must leave shift. The online Qualification Report is NOT available. Three replacement operators are available. Instructor to ask the operator for any questions.
Initiating cue: "(Operator's name), using the given information, determine which of the three operators, if any, are qualified to relieve you, in accordance with S-ODP-TQS-0101." Document your findings and the reasons for your findings on the given answer sheet." Examiner Note: Provide candidate with JPM attachments A and B. I Performance Steps I Grade Provide repeat back of initiating cue o Proper communications used for SatlUnsat repeat back (GAP-OPS-01)
Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME ____ Obtain a copy of S-ODP-TQS-01 01 and 0 S-ODP-TQS-0101 obtained SatlUnsat review/utilize the correct section Note: See attached answer key Reviews RO #1 data and determines o Reviews RO #1 data SatlUnsat eligibility Determines RO #1 is qualified to Pass/Fail relieve the CRO Reviews RO #2 data and determines o Reviews RO #2 data SatlUnsat eligibility Determines RO #2 has not performed Pass/Fail enough hours in the past quarter as a licensed operator NRC 2010 RO ADMIN JPM November 2010 I Performance Steps I Standard Grade Cl Determines RO #2 is NOT qualified to relieve the CRO 5. Reviews RO #3 data and determines o Reviews RO #3 data SatiUnsat eligibility Cl Determines RO #3 does not have a SCBA Fit Test on file from the last Pass/Fail Cl year Determines RO #3 is NOT qualified to relieve the CRO Pass/Fail TERMINATING CUE: Candidate determines that only RO #1 is qualified to stand the watch using the criteria contained in S-ODP-TQS-01 01. RECORD STOP TIME ____ NRC 2010 RO ADMIN JPM C001 November 2010 Initial Conditions:
- 1. The plant is operating at 100% power. 2. Today is January 1, 2011. 3. You are the eRO. 4. You must leave shift. 5. The online Qualification Report is NOT available.
- 6. Three replacement operators are available.
Initiating cue: "(Operator's name), using the given information, determine which of the three operators, if any, are qualified to relieve you, in accordance with ODP-TQS-0101.
Document your findings and the reasons for your findings on the given answer sheet." NRC 2010 RO ADMIN JPM C001 November 2010
Attachment A -Data Sheet RO#2 10/21/10:
0700 -10/22/10:
0700 -10/23/10:
0700 -11/12/10:
0700 11/13/10:
0700 11/14/10:
0700 -I All requirements of TR-1.01-102 met 2/312010 3/18/2010 7/12/2009 1/27/2010 RO#3 11/2/10: 0630 -1830 11/3/10: 0630 -1830 11/4/10: 0630 -1830 11/5/10: 0630 -1830 12/24/10:
0630 -1830 12/25/10:
0630 -1830 All requirements of NMP-TR-1.01-102 met 8/16/2010 12/14/2009 12/10/2009 10/22/2010 Hours Licensed Duties in Last 10/28/10:
10/29/10:
10/30/10:
11/22/10:
11/23/10: RO#1 0630 -1830 0630 -1830 0630 -1830 0630 -1830 0630 -1830 Status Date of Last Date of Last SCBA Date of Most NRC Form 396 on Date of Most Respiratory on '--------All requirements of TR-1.01-102 2/10/2010 3/14/2010 8/22/2009 7/1/2010 NRC 2010 RO ADMIN JPM C001 November 2010 Attachment B -Answer Sheet i Qualified for Relief? (Yes/No) If No, what requirement is not being met, in accordance with 01? I RO#1 I I RO#2 RO#3 NRC 2010 RO ADMIN JPM C001 7 November 2010 Attachment C -Answer Key I ! Qualified for Relief? (Yes/No) If No, what requirement is not being met, in accordance with S-ODP-TQS-01 01? RO#1 Yes N/A RO#2 No Does not meet the required number of hours performing duties on a licensed operator for the last quarter RO#3 No Does not have an annual SCBA Fit test on file NRC 2010 RO ADMIN C001 November 2010 NRC RO ADMIN JPM C002 Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Determine Core Thermal Power Revision:
NRC 2010 Task Number: NA Approvals:
NA Exam Security I General Superv' General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
______________
{RO) Trainer/Evaluator:
____________
_ Evaluation Method: ----'X"-"--_Perform
---Simulate Evaluation Location:
___Plant ___Simulator X Classroom Expected Completion Time: 15 Min. Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop Time: Completion Time: ____ .JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluators Signature:
____________
_ Date:______ NRC RO ADMIN JPM C002 November 2010 Recommended Start Location: (Completion time based on the start location)
Any appropriate location with the required Reference Material.
Simulator Set-up (if required):
None Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM / CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM I CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this ..JPM, I will function as the SM, CRO, and Plant Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently.
The Control Room Supervisor has determined that a verifier is not available and that additional!
concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor I Evaluator: Critical steps are identified in grading areas as Pass/Fail.
All steps are sequenced critical unless denoted by a U e ". During Evaluated JPM: e Self verification shall be demonstrated. During Training JPM: Self verification shall be demonstrated. {Additional/Concurrent/No other) verification shall be demonstrated.
NRC RO ADMIN .IPM November 2010
References:
N2-REP-11, Independent Methods of Determining Core Thermal Power NUREG KIA General Knowledges and Abilities 2.1.19(3.0)
Tools and Equipment: Calculator
- 2. 00-3, with % Core Thermal Power = Task Core thermal power correctly calculated in accordance with N2-REP-11, Attachment Candidate determines that the calculated power is not within 2% limit specified in procedure and notifies SM and Initial The plant has been operating at steady-state power for greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. MSR reheat steam is NOT optimized. Turbine bypass valves are closed. SM permission has been granted to perform this procedure.
Initiating Cues: "(Operator's name), determine core thermal power using turbine first stage pressure accordance with N2-REP-11.
Any steps requiring an Independent Verification will completed by another operator at the completion of the
! Performance Steps Grade Provide repeat back of initiating cue. CJ Proper communications used for Sat/Unsat Evaluator Acknowledge repeat back repeat back (GAP-OPS-011) providing correction if necessary.
RECORD START TIME ____ Obtain a copy of the reference CJ N2-REP-11 obtained.
procedure and review/utilize the correct
- Precautions
&Limitations Sat/Unsat section of the procedure.
reviewed.
- Attachment 3
Evaluator:
Provide candidate with blank copy of NRC RO ADMIN JPM November 2010 3 Performance Steps Complete Preliminaries Section of 11 r Attachment 3 for the following: Verifying all turbine bypass valves are fully closed. Verifying MSR reheat steam is NOT optimized. Verify reactor is operating in a steady state condition with core power level constant for the current control rod pattern and core flow. Note: Candidate may obtain SM permission; and/or notify the CRO of procedure performance. Record data on N2-REP-11, Attachment
- 3. Evaluator:
Provide candidate a copy of JPM Attachment
- 1. Obtain Plant Process Computer Program OD-3, Option 2 printout.
Evaluator:
Provide candidate a copy of JPM Attachment
- 2. Calculate core thermal power. Indicate if core thermal power values agree within +/- 2%. NRC RO ADMIN JPM C002 Grade Step completed using JPM Initial SatlUnsat Conditions. Step completed using JPM Initial SatlUnsat Conditions. Step completed using JPM Initial SatlUnsat Conditions. Proper communications used SatlUnsat Data correctly entered on Attachment SatlUnsat Obtains value from JPM Attachment SatlUnsat Core thermal power calculations Pass/Fail completed as follows: % Core Thermal Power based computer points = [(.12464 X 700) + 12.6794] X (.98 + .98)/2= 97.929 (97.93) % Core Thermal Power from 3 printout = Determines core thermal power Pass/Fail values do NOT agree within +/- 2% (99.99 -97.93 = 2.06). November 2010 4 Performance Steps Grade Immediately notifies SM and Reactor o SM and Reactor Engineering Pass/Fail Engineering Supervisor that Core Supervisor notified that Core Thermal Thermal Power determined using turbine Power determined using turbine first first stage pressure does NOT agree stage pressure does NOT agree within 2%. within 2%. Terminating Cue: Core thermal power calculated using N2-REP-11, Attachment
- 1. The plant has been operating at steady-state power for greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. 2. MSR reheat steam is NOT optimized
- 3. Turbine bypass valves are closed. 4. SM permission has been granted to perform this procedure.
Initiating Cues: "(Operator's name), determine core thermal power using turbine first stage pressure in accordance with N2-REP-11.
Any steps requiring an Independent Verification will be completed by another operator at the completion of the procedure." NRC RO ADMIN JPIVI C002 November 2010 6 JPM Attachment 1 N2-REP-11 Data Sheet Computer Point Value I Turbine First Stage Pressure 700 pSia i (MSSPA07) i FW A Correction Factor (FWSFE1 02) i 0.98 I ! . FW B Correction Factor (FWSFE103)
I 1 0.98 NRC RO ADMIN JPM C002 November 2010 7 JPM Attachment 2 003 -Option 2 00-3 Core Thermal Power and APRM Calibration TODAY 09:50:02 Nine Mile Point 2 GMWE CMWT WT WTSUB WD WT FLAG IREC ROD LIN 1182.52 3466.66 97.09 97.86 30.54 2.00 0 107.53 I I I I I I I I PR RWL OPCM WFW HFW WO OHS CAEQ CAQA 1034.6 185.54 15.44 14.93 400.8 525.4 22.80 .12 .15 1-A 2-B 3-C 4-0 RAP 100.01 100.04 99.99 100.03 AGAP 1.0 1.0 1.0 1.0 I NRC RO ADMIN JPM C002 November 2010 8 NRCJPM RO EC Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Prepare a Tagout for TBCLCW Pump P1 B Revision:
NRC 2010 Task Number: N/A Approvals:
NA Exam Security I General Supervi r:; General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
______________(RO) Trainer/Evaluator:
___________
_ Evaluation Method: --=...X.:--_
Perform _____ Simulate Evaluation Location:
___ Plant __--.:...!X'--_
Simulator or Classroom Expected Completion Time: 30 minutes Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop Time: Completion Time: ____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluators Signature:
____________
_ Date:______ NRC 2010 RO ADMIN JPM EC November 2010 Recommended Start Location: (Completion time based on the start location)
Classroom Simulator Set-up (if required):
N!A Directions to the I nstructor!Evaluator:
Prior to performance of this JPM, obtain SM ! CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM ! CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically Repositioning of devices will be simulated by discussion and acknowledged by my Read Before Each Evaluated J PM This evaluated JPM is a measure of your ability to perform this task independently.
The Room Supervisor has determined that a verifier is not available and that additional!
verification will not be provided; therefore, it should not be Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor!
Evaluator: Critical steps are identified in grading areas Pass/Fail.
All steps are sequenced critical unless denoted by a".". During Evaluated JPM: Self verification shall be demonstrated. During Training JPM:
- Self verification shall be demonstrated.
References:
NUREG 1123,2.2.13, R04.1 CNG-OP-1.01-1007 P&IDs 14A thru 14F available Electrical Prints -ESK 5CCS01 (02,03), available ELU-14 -Electrical Lineup OR EE-1L (available)
None Task Standard:
Identify the isolations required to tag out TBCLCW Pump 2CCS-P1 B for the pump packing replacement.
Initial Conditions: The plant is operating at 100% power. TBCLCW pumps P1A and P1 C are operating. TBCLCW pump P1 B is secured. Maintenance is required to repack 2CCS-P1 B eSOMs is unavailable.
- 6. Ask the operator for any questions.
Initiating cue: "(Operator's name), identify the components required to tagout TBCLCW Pump P1 B for the pump packing replacement.
Record the required components, tag type, component positions and tagging sequence on the handout provided." Performance Steps Provides repeat back of initiating cue Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME ____ Obtains a copy of the reference procedure and reviews/utilizes the correct section Obtains and references appropriate drawings and/or procedures to determine isolations Records required isolations.
Note: Due to unavailability of eSOMs and other electronic databases, exact component IDs, names, and tagging positions may vary. Examiner Note: The sequence must be electrical first (control switch, fuses), valve isolations second (suction, discharge) and vent and drain third. NRC 2010 RO ADMIN JPM EC Standard Proper communications used for repeat back (GAP-OPS-01) CNG-OP-1.01-1007 obtained as necessary Obtains and references, as required: P&IDs 14A thru 14F EWOs ESK 5CCS01 (02,03) N2-0P-14 ELU-14 or EE-1 L Identifies the following component isolations, tag type, component positions and tagging sequence on the handout PMP 1 B CSS-P1 B, TBCLCW Pump 2CSS-P1B:
- 1. Control Switch in pull-to-Iock
- 2. Reference or Danger Tag -3 Grade SatlUnsat SatlUnsatl NA SatlUnsat SatlUnsat November 2010 I Performance Steps Standard Grade The candidate may # them 1, 2, 3, 4, 5, 6 or 3. Sequence #1 or #2 1,1,2,2,3,3 2NNS-SWG013-8, 2CCS-P1 B Power Pass/Fail Supply Trip Fuses: 1. Trip Fuses pulled 2. Danger Tag 3. Sequence #1 or #2 AND/OR AND/OR 2NNS-SWG013-8 Breaker for Pass/Fail P1B: Breaker Open & Racked out/handle elevated Danger Tag Sequence #1 or #2 2CCSV303B
-TBCLC Pump P'I B Pass/Fail Discharge Stop Check Valve: Closed Danger Tag Sequence #3 or #4 2CCSV1 B -TBCLC Pump P1 B Pass/Fail Suction Isolation Valve: Closed Danger Tag Sequence #3 or #4 2CCSV307B
-TBCLC Pump P1 B Pass/Fail Casing Vent Valve: Uncapped and Open Danger Tag Sequence #5 or #6 2CCSV6B -TBCLC Pump P1 B Pass/Fail Casing Drain Valve: Uncapped and Open Danger Tag Sequence #5 or #6 NRC 2010 RO ADMIN JPM November 2010 Terminating Cue: Isolations for TBCLCW Pump P1 B have been identified and recorded on the handout provided RECORD STOP TIME ____ KEY Component Tag Type Sequence**
Component Description Position/Configuration PMP 1 B CSS-P1 B, TBCLCW Pump 2CSS-Reference or Danger Sequence #1 or #2 Control Switch in P1B: to-lock 2NNS-SWG013-8, Danger Sequence #1 or #2 Trip Fuses 2CCS-P1 B Supply Trip AND/OR AND/OR 2NNS-SWG013-8 Danger Breaker Open Breaker for 2CCS-P1 B: Racked 2CCSV303B
-TBCLC Danger Sequence #3 or #4 Pump P1 B Stop Check 2CCSV1 B -TBCLC I Danger Sequence #3 or #4 Pump P1 B Isolation I i 2CCSV307B
-TBCLC Danger Sequence #5 or #6 Uncapped and Open I Pump P1 B Casing I I 2CCSV6B -TBCLC Danger Sequence #5 or #6 Uncapped and Open i Pump P1 B Drain **Examiner Note: The sequence must be electrical first (control switch, fuses, breaker), valve isolations second (suction, discharge) and vent and drain third. The candidate may # them 1, 2, 3, 4, 5, 6 or 1, 1, 2, 2, 3, 3 NRC 2010 RO ADMIN JPM EC November 2010 Component Tag Type Sequence I Component i Description Position/Configuration
!1. i I 2. i 3. ! I 4. i 5. ! 6. I 8. i 9. 10 . !
- 1. The plant is operating at 100% power. 2. TBCLCW pumps P1 A and P1 C are operating.
- 3. TBCLCW pump P1 B is secured. 4. Maintenance is required to repack 2CCS-P1 B 5. eSOMs is unavailable.
Initiating cue: U(Operator's name), identify the components required to tagout TBCLCW Pump P1 B for the pump packing replacement.
Record the required components, tag type, component positions and tagging sequence on the handout provided." NRC 2010 RO ADMIN JPM EC November 2010 NRC JPM RO EP Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Perform Actions for External Security Threats Revision:
NRC 2010 Task Number: N/A Approvals:
NA Exam Security I General Supervisor General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
______________(RO) Trainer/Evaluator:
___________
_ Evaluation Method:
Perform _____ Simulate Evaluation Location:
___ Plant __--=:....:x'---_
Simulator or Classroom Expected Completion Time: 15 minutes Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop Time: ____ Completion Time: ____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluators Signature:
____________
_ Date:______ NRC 2010 RO ADMIN JPM EP November 2010 Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up (if required):
N/A Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM ! CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM ! CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically Repositioning of devices will be simulated by discussion and acknowledged by my Read Before Each Evaluated JPM This evaluated JPM is a measure of your ability to perform this task independently.
The Room Supervisor has determined that a verifier is not available and that additional!
verification will not be provided; therefore, it should not be Read Before Each Training .JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor I Evaluator:
- 1. Critical steps are identified in grading areas Pass/Fail.
- 2. During Evaluated JPM:
- Self verification shall be demonstrated.
- 3. During Training JPM:
- Self verification shall be demonstrated.
References:
- 1. NUREG 1123, 2.4.28, RO 3.2 2. EPIP-EPP-10 Tools and Equipment:
None NRC 2010 RO ADMIN JPM EP November 2010 Task Standard:
Perform required actions for an external security threat per EPIP-EPP-10, Attachment
- 2. Initial Conditions: The plant is operating at 100% power. You are the CRO. The NRC calls on the ENS line and informs you of the following: NORAD has reported that two US Airways 737 aircraft have been hijacked from Hancock International Airport in Syracuse, New York. One is headed southeast in the direction of the Indian Point site and one is headed north in the direction of the Fitzpatrick and Nine Mile Point site. The event is classified as a credible, probable airborne threat. Instructor to ask the operator for any questions.
Initiating cue: "(Operator's name), perform actions in response to this security threat in accordance with EPP-10 attachment 2." Performance Steps Grade Provides repeat back of initiating cue a Proper communications used for SatlUnsat repeat back (GAP-OPS-01)
Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME ____ Obtains a copy of the reference a EPIP-EPP-10 attachment 2 obtained SatlUnsat procedure and reviews/utilizes the correct section Once the candidate locates EPP-10 attachment 2, the examiner may supply an extra copy to the candidate for use during the remainder of the JPM Notifies Shift Manager of security event a Proper communications used (GAP-Pass/Fail OPS-01) Checks plant parameters o Observes major plant parameters SatlUnsat using control room instrumentation (ex. Reactor power, pressure and level, Containment conditions)
NRC 2010 RO ADMIN JPM EP -3 November 2010 Performance Steps Standard Grade 5. Notifies Security Site Supervisor o Proper communications used Pass/Fail OPS-01) Note: Security Site Supervisor may be contacted by Gaitronics page or by calling x5222 or x2591 6. Initiates any Operating, Special 1:1 Proper communications used (GAP* Sat/Unsat Operating or EOPs required OPS-01) Cue: Inform that other operators are executing the required Operating, Special Operating and Emergency Operating Procedures
- 7. As directed by Shift Manager, makes 0 Makes plant announcement in announcements accordance with EPIP-EPP-10 attachment 6: Cue: As Shift Manager, provide EPP-10 Attachment 6, a. Places GAltronics in Merge Pass/Fail Imminent/Probable Aircraft Attack Announcement ( ..IPM Handout #1) b. Sounds Evacuation Alarm for 5 Pass/Fail seconds Note: If candidate begins to broadcast
- c. Announces:
Pass/Fail an announcement, Examiner should ask candidate not to Attention All Plant Personnel, this broadcast over the speakers and (is a drill I is an actual emergency) just to the examiner.
Aircraft Impact Imminent.
Evacuate the protected area immediately.
Report directly to the Learning Center or P-Building.
I repeat, this (is a drill I is an actual emergency)
- d. Repeats Alarm and Announcement Sat/Unsat
- e. Leaves GAltronics in merge Sat/Unsat NRC 2010 RO ADMIN JPM EP -4 November 2010 Performance Steps When Security Contingency Event no longer exists, makes a termination announcement in accordance with EPP-18 As Shift Manager, report that Security Contingency Event no longer exists and provide 18 attachment 7, Emergency Termination Announcement (JPM Handout #2) NOTE: If candidate begins to broadcast an announcement, Examiner should ask candidate not to broadcast over the speakers and just to the examiner.
Standard Grade o Makes plant announcement in accordance with EPIP-EPP-18 attachment 7: a. Sounds Station Alarm for 10 seconds SatlUnsat
- b. Announces:
SatlUnsat Attention.
Attention all personnel.
The security event at Nine Mile Point Unit 1 and 2 has been terminated.
I repeat, the security event has been terminated
- c. Repeats alarm and announcement SatlUnsat
- d. Removes GAltronics from merge SatlUnsat Terminating Cue: Emergency Termination Announcement has been made. RECORD STOP TIME ____ NRC 2010 RO ADMIN JPM EP -5 November 2010 Initial Conditions:
- 1. The plant is operating at 100% power. You are the CRO. The NRC calls on the ENS line and informs you of the following: NORAD has reported that two US Airways 737 aircraft have been hijacked from Hancock International Airport in Syracuse, New York. One is headed southeast in the direction of the Indian Point site and one is headed north in the direction of the Fitzpatrick and Nine Mile Point site. The event is classified as a credible, probable airborne threat. Initiating cue: "(Operator's name), perform actions in response to this security threat in accordance with EPIP-EPP-10 attachment 2." When making plant announcements, simulate all actions with the GAltronics and provide announcement to the examiner only (i.e. do NOT broadcast over speakers).
NRC 2010 RO ADMIN EP -6 November 2010 ATIACHMENTS Today Date: Now IMMINENTfPROBABLE AIRCRAFT ArrACK ANNOUNCEMENT Instructions:
- 1. Place GAltronics In Merge 2. Sound Evacuation Alarm for 5 Seconds Announce, Attention AU Plant Personnel, this (is a drill IS an actual emergenc Aircraft impact Imminent Evacuate the protecrea area Immediately.
Report directly to the Learning Center or i repeat.. this {is a driif is an actual emergengxp
- 4. Repeat Alarm and Announcement.
- 5. Leave GAltronics in merge for the duration of the event. 6. Upon completion retum this attachment to the EP Dept. Page EPIP-EPP-10 Rev 17 NRC 2010 RO ADMIN JPM EP -November 2010 ACTIVATION AND DIRECTION OF THE EMERGENCY PLANS EPlp*EPp*18 Revision 01900 Page 190121 Page 1 of 1 Attachment 7, Emergency Termination Announcement Date: Today TIme: Now Emergency Termination (As requested by the SM/EO or
- 1. Place GAltronics in Merge Sound Station Alarm for 10 Seconds Announce. "Attention.
Attention all The condition at Nine Mile ).<:2: Unit 1 has been terminated.
);( Unit 2 has been terminated. (Provide further instructions as necessary) J repeat, the ____s_e_,c_u_r_i_t..::.y
____
condition has been terminated. Repeat Alarm and Announcement. Remove GAltronics from merge. Upon completion retum this attachment to the EP Dept. [N0306J NRC 2010 RO ADMIN JPM EP November 2010 NRC JPM Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Initiate Division I H2I02 Monitoring to Monitor Suppression Chamber, Post LOCA Revision:
NRC 2010 Task Number: NA NA Exam Security General Superviso General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
_____________(RO/SRO) Trainer/Evaluator:
___________
_ Evaluation Method:
_____Simulate Evaluation Location:
___Plant __--"-'X'--_Simulator Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop Time: Completion Time: ____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluator's Signature:
____________
_ Date:______ NRC 2010 JPM S-1 November 2010 Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up (if required):
IC-171 Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM / CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM / CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM This evaluated JPM is a measure of your ability to perform this task independently. Control Room Supervisor has determined that a verifier is not available and that concurrent verification will not be provided; therefore, it should not be Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor
/ Evaluator: Critical steps are identified in grading areas as Pass/Fail.
All steps are sequenced critical unless denoted by a".". During Evaluated JPM: Self-verification shall be demonstrated. During Training JPM: Self-verification shall be demonstrated. No other verification shall be demonstrated.
NRC 2010 JPM 8-1 -2 November 2010 i
References:
N2-0P-82, Revision 00601 KIA 223001 A4.04 3.5/3.6, A4.05 3.6/3.6 Tools and Equipment:
Keys Task Standard:
H202 Analyzers ON and sampling from the suppression chamber Initial Conditions:
The plant is shutdown following a LOCA Initiating Cues: Perform a post LOCA restart of 2CMS*CABi0A per N2-0P-82, Section H.i.0, and using Division I CMS H202 Monitor, sample the Suppression Chamber per Section F.1.0. Performance Ste s Grade Provide repeat back of initiating o Proper communications used for SatlUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME Obtain a copy of the reference o N2-0P-82 obtained.
Precautions
& SatlUnsat procedure and review/utilize the Limitations reviewed.
correct section. Obtain SM/CRS permission to o Obtains SM/CRS permission to SatlUnsat restart 2CMS*CAB10A(B) restart 2CMS*CAB 1 OA Give SM/CRS when NRC 2010 JPM 8-1 -November 2010 PRIOR to overriding the LOCA 0 Prior to overriding the LOCA SatlUnsat isolation signal, notify Radiation isolation signal, notifies Radiation Protection of the intent to restart Protection of the intent to restart 2CMS*CAB10A(B)
AND that 2CMS*CAB10A AND that radiological conditions could radiological conditions could change. change. CUE: As RP, acknowledge. Place the following keylock 0 Places the following keylock PASS/FAIL switches to OVERRIDE:
switches to OVERRIDE: ISOL VLV OVERRIDE on
- ISOL VLV OVERRIDE 2CEC*PNL875 At 2CEC*PNL873, open the 0 OPENS the following valves: PASS/FAIL following valves: 2CMS*SOV60A(B),
- 2CMS*SOV62A, CONTMT CONTMT ATM MON DW MON DW OUTBD OUTBD ISOL RETURN At 2CEC*PNL875, open the 0 OPENS the following valves: PASS/FAIL following valves 2CMS*SOV61A(B),
- 2CMS*SOV63A, CONTMT CONTMT ATM MON DW MON DW INBD ISOL INBD ISOL Direct Radiation Protection to 0 Directs Radiation Protection to place Sat/Unsat place 2CMS*CAB10A(B) in 2CMS*CAB10A in service. service. CUE: Inform operator that 2CMS*CAB10A is in service. Verify 2CMS*CAB1 OA(B) is in 0 Verifies 2CMS*CAB10A is in service SatlUnsat service AND notify the SM/CRS. AI\ID notifies the SM/CRS. CUE: As SM/CRS, acknowledge.
NRC 2010 JPM 8-1 November 2010 I Performance I Standard EVALUATOR'S NOTE: Applicant returns to Section F.1.0 to sample from Path 4 (Suppression Chamber) reference.
- 10. Placing H2/02 Analyzer in o Operator reviews the steps. Panel Service: 2CEC*PNL873 will be used. This Subsection is written both divisions with Division components in Actions in this are performed 2CEC*PNL873(875) otherwise Position 4 lines up Suppression sample stream. It is used as directed Performance of Subsection may be by the EOPs. Changes this Subsection renumbering) are required be reviewed by this Control Room indication H2 and 02 will be less 0% if the analyzer is calibration OR condition.
The only to determine if the unit is self-calor in TROUBLE the indicating lights on remote 2CMS*PNL73A(B)
(240 Aux Bay). Control indication will return self-calibration is 30 i Grade SatlUnsat NRC 2010 JPM S-1 November 2010 I Performance Steps I Grade 11. If required defeat LOCA 0 Refers to Section H.2.0 SatiUnsat per Section H.2.0
- 12. If LOCA isolation signal is o Operator notes that this step was Sat/Unsat present, using PA 235 Key, performed earlier in the JPM (step place the following keylock 5) and verifies switches in switches to OVERRIDE:
OVERRIDE ISOL VLV OVERRIDE
- 13. At 2CEC*PNL873(875), place o At 2CEC*PNL873, places the Pass/Fail the Division 1(11) SAMPLE PATH Division I SAMPLE PATH SELECTOR SWITCH in the SELECTOR SWITCH in the RESET position RESET position.
- 14. Return to Section F.1.0 to o Returns to section F.1.0 SatiUnsat H202 Analyzers in service NOTE: IF a LOCA Isolation occurs while the Analyzer is in service, it will cause the analyzer to trip. Placing the H2/02 ANALYZER PMP switch to STANDBY will reset the trip logic. 15. Verify the H2/02 o Verifies the 2CMS*P2A, H2/02 SatiUnsat ANALYZER PMP, in STANDBY. ANALYZER PMP, in STANDBY. Establish a sample flowpath by o Establishes a sample flowpath by PASS/FAIL placing the SAMPLE PATH placing the SAMPLE PATH SELECTOR SWITCH to SELECTOR SWITCH to Position 4 Position 1, 2 or 3 (Drywell)
OR (Suppression Chamber) 4 (Suppression Chamber) as directed by SM/CRS. 17. Verify EITHER a Drywell o Verifies a Suppression Suppression Chamber sample sample flow path flow path exists, as Suppression chamber flow 2CMS*SOV26A(B),
- 2CMS*SOV26A, SAMPLE PASS/FAIL SAMPLE FROM SUPPR FROM SUPPR CHAM CHAM INBOARD ISOL VLV, INBOARD ISOL VLV, Open Open NRC 2010 JPM S-1 November 2010 I Performance Steps 17. (cant) Suppression sample flow 2CMS*SOV26C(D) , SAMPLE FROM SUPPR CHAM OUTBOARD ISOL VLV, Open 2CMS*SOV34A(B), SUPPR CHAM SAMPLE RTN INBOARD ISOL VLV, Open 2CMS*SOV35A(B).
SUPPR CHAM SAMPLE RTN OUTBOARD ISOL VLV, Open 2CMS*SOV64A(B), H2/02 ANALYZER INLET VLV, Open 2CMS*SOV65A{B), H2/02 ANALYZER OUTLET VLV, Open Standard 2CMS*SOV26C, SAMPLE FROM SUPPR CHAM OUTBOARD ISOL VLV, Open 2CMS*SOV34A, SUPPR CHAM SAMPLE RTN INBOARD ISOL VLV, Open 2CMS*SOV35A, SUPPR CHAM SAMPLE RTN OUTBOARD ISOL VLV, Open 2CMS*SOV64A, H2/02 ANALYZER INLET VLV, Open 2CMS*SOV65A, H2/02 ANALYZER OUTLET VLV, Open Alarms for High 02 concentrations are expected for first 20 minutes until analyzer warm up period is complete. Allow 30 minutes for system stabilization after placing the 2CMS*P2A(B), H2I02 ANALYZER PMP to ANALYZE. It takes approximately 6 minutes to receive and accurately read the sample by the H2I02 Analyzer, when changing sample locations.
CUE: Inform candidate that 30 minutes has elapsed. 18. Place the 2CMS*P2A(B), H2/02 ANALYZER PMP switch to ANALYZE. 19. Verify 2CMS*P2A(B), Sample Pump GREEN light goes OUT and RED light is LIT. TERMINATING CUE: RECORD STOP TIME __ NRC 2010 S-1 D Places the 2CMS*P2A, H2/02 ANALYZER PMP switch to ANALYZE. D Verifies 2CMS*P2A, Sample Pump GREEN light goes OUT and RED light is LIT. Analyzer RED light ON. Sampling from the Suppression Chamber. -7 November 2010 Grade PASS/FAIL PASS/FAIL SatlUnsat SatlUnsat SatlUnsat PASS/FAIL SatlUnsat TURNOVER INITIAL The plant is shutdown following a LOCA. CONDITIONS:
INITIATING Perform a post LOCA restart of 2CMS*CAB10A per N2-0P-82, Section H.1.0, and using Division I CMS H202 Monitor, sample the Suppression Chamber per Section F.1.0. NRC 2010 JPM 8 November 2010 NRC JPM 5-2 Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Add Air to a De-Inerted Drywell Revision:
NRC 2010 Task Number: NA Approvals:
NA Exam Security I General Supervisor Date Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
______________(RO/SRO) Trainer/Evaluator:
____________
_ Evaluation Method: ---=X'-!...-_Perform
_____Simulate Evaluation Location:
___Plant __.-;..:X,--_Simulator Expected Completion Time: 20 min_ Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop Completion JPM Overall Rating: Pass Fail A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluator's Signature:
____________
_ NRC 2010 JPM S-2 -1 November 2010 Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up (if required):
IC-172 Remote PC21, CPS-V26 Purge Fan Discharge Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM ! CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM / CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently.
The Control Room Supervisor has determined that a verifier is not available and that additional!
concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor!
Evaluator: Critical steps are identified in grading areas as Pass/Fail.
All steps are sequenced critical unless denoted by aU.". During Evaluated JPM: Self-verification shall be demonstrated. During Training JPM: Self-verification shall be demonstrated. No other verification shall be demonstrated.
NRC 2010 JPM 8-2 November 2010
References:
N2-0P-61A, Revision 01300 KIA 261000 A4.04 3.3/3.4 Tools and Equipment:
None Task Standard:
Suppression Chamber pressure is ::::: 0 psig and the containment purge fan is stopped. Initial Conditions: Drywell is de-inerted. One (1) SBGT System is operable. Containment venting is NOT in progress.
Initiating Cues: Add air to the Drywell per N2-0P-61A, Section H.3.0. I Performance Steps I Grade Provide repeat back of initiating o Proper communications used for SatlUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary.
RECORD START TIME Obtain a copy of the reference o N2-0P -61A obtained.
Precautions SatlUnsat procedure and review/utilize the & Limitations reviewed.
correct section. Verify Containment Venting is o Verifies Containment Venting is SatlUnsat NOT in progress.
NOT in progress. Provided in NRC 2010 JPM S-2 November 2010 Verify the following:
o Verifies GTS*AOV1 01, CONTAINMENT PURGE GTS* AOV1 01 SBGTSISOL VLV closed CONTAINMENT PURGE TO SBGTS ISOL VLV closed At least one Standby Gas treatment subsystem is OPERABLE At least one Standby treatment subsystem GTS*AOV101 is and one subsystem SBGTS is Line up operating air supply to o Lines up operating air supply to 2CPS*AOV106 as follows: 2CPS* AOV1 06 as Open IAS*SOV168,
- Opens IAS*SOV168, PRIMARY CNTMT OUTBD CNTMT OUTBD ISOL VLV ISOL VL V TO DRYWELL at DRYWELL at Open IAS*SOV180,
- Opens IAS*SOV180, PRIMARY CNTMT INBD CNTMT INBD ISOL ISOL VL V TO DRYWELL at DRYWELL at Open 2CPS-DMP1, Contmt 0 Opens 2CPS-DMP1, Contmt Purge Purge FN1 Inlet Damper. FN1 Inlet 2CPS-DMP1, Purge FN1 Inlet Damper Open 2CPS-V26, Contmt Purge 0 Opens 2CPS-V26, Contmt Purge PASS/FAIL FN1 Disch Isol. FN1 Disch Isol. 2CPS-V26 is Open At 2CEC*PNL873, verify closed 0 At 2CEC*PNL873, verifies CPS*AOV105, SUPP CHMBR CPS*AOV105, SUPP PURGE INLET OUTBOARD PURGE INLET OUTBOARD ISOL VLV. At 2CEC*PNL873, open o At 2CEC*PNL873, opens PASS/FAIL CPS*AOV104, DRYWELL CPS*AOV104, DRYWELL PURGE PURGE INLET OUTBOARD INLET OUTBOARD ISOL VLV. ISOL VLV. NRC 2010 JPM S-2 -4 November 2010 I Performance Steps Grade 10. At 2CEC*PNL875, open CPS*AOV106, DRYWELL PURGE INLET INBOARD ISOL VLV. 11. At 2CEC*PNL873, start CPS-FN1, CONTMT PURGE FAN. 12. At approximately 0 psig drywell pressure, (2CMS*PI1A1B on 2CEC*PNL601 OR computer point CMSPA01/02), stop 2CPS-FN1.
- 13. Close the following: 2CPS-DMP1, Contmt Purge FN1 Inlet Damper Cue: 2CPS-DMP1 is closed 2CPS-V26 Contmt Purge FN1 Disch Isol. Cue: 2CPS-V26 is closed 2CPS*AOV106, DRYWELL PURGE INLET INBOARD ISOL VLV. 2CPS*AOV104, DRYWELL PURGE INLET OUTBOARD ISOL VLV. 2IAS*SOV168, PRIMARY CNTMT OUTBD ISOL VLV TO DRYWELL 2IAS*SOV180, PRIIVIARY CNTMT INBD ISOL VLV TO DRYWELL At 2CEC*PNL875, opens PASS/FAIL CPS*AOV106, DRYWELL PURGE INLET INBOARD ISOL VLV. At 2CEC*PNL873, starts CPS-FN1, PASS/FAIL CONTMT PURGE FAN. At 0 psig drywell pressure, PASS/FAIL (2CMS*PI1A1B on 2CEC*PNL601 OR computer point CMSPA01/02), stops 2CPS-FN1. Closes the following: 2CPS-DMP1, Contmt Purge SatiUnsat FN1 Inlet Damper 2CPS-V26 Contmt Purge FN1 SatiUnsat Disch Isol. 2CPS*AOV106, DRYWELL PASS/FAIL PURGE INLET INBOARD ISOL VLV. 2CPS*AOV104, DRYWELL PASS/FAIL PURGE INLET OUTBOARD ISOL VLV. 2IAS*SOV168, PRIMARY PASS/FAIL CNTMT OUTBD ISOL VLV TO DRYWELL 2IAS*SOV180, PRIMARY PASS/FAIL CNTMT INBD ISOL VLV TO DRYWELL TERMINATING Air added to the Drywell per N2-0P-61A, Section H.3.0. RECORD STOP TIME,____ NRC 2010 JPM S-2 -November 2010 TURNOVER SHEET INITIAL 1. Drywell is de-inerted.
CONDITIONS:
- 3. Containment venting is NOT in progress.
INITIATING CUES: Add air to the Drywell per N2-0P-61A, Section H.3.0. NRC 2010 JPM 5-2 November 2010 NRC JPM Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Securing and Restart of Shutdown Revision:
NRC 2010 Cooling Task Number: NA Approvals:
NA Exam Security I General Supervis General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
______________(RO/SRO) Trainer/Evaluator:
___________
_ Evaluation Method: X Perform _____Simulate Evaluation Location:
___Plant ___X:....>-__Simulator Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: Yes Start Time: ____ Stop Time: Completion Time: ____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluator's Signature:
____________
_ Date:______ NMP2 NRC JPM S-3 November 2010 Recommended Start Location: (Completion time based on the start location)
Unit 2 Simulator Simulator Set-up (if required): Place Simulator in IC-172 Shut Down Cooling Set up the following I/Os and Event Triggers I/O Control switch for 2RHS*MOV40B in 'off' (ovr-01a2s145di0469) and trigger the I/O off the red open indication for 2RHS*MOV40B, [hzlrhvs44(2)==11 TRG 8, ovr-18a3ds146101462 on (turns on red light for HVP*AOD4D on P871 to setup conditional trigger to allow subsequent activation of trigger 9) TRG 9, ovr-01a2s145di0469, Open RHR SOC injection valve Off RHS*MOV40B control switch open position to off disabling switch Event trigger #8, hzlrhps3b(1
)==1 .and. hzlrhsvs44(2)==O (activates when RHS*P'I B is stopped, green light on, and RHS*MOV40B is full closed, red light off) Event trigger #9, hzlpc1 bhvp04(2)==1 .and. hzlrhsvs44(2)==1 (activates when HVP*AOD4D red light is on from trigger 8 and RHS*MOV40B starts to open, red light on) Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM / CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM / CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated
..IPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently.
The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training "IPM Performance:
During this Training ..I PM , applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
NMP2 NRC JPM 8-3 November 2010 Notes to Instructor I Evaluator: Critical steps are identified in grading areas as Pass/Fail.
All steps are sequenced critical unless denoted by a".". During Evaluated JPM: Self-verification shall be demonstrated. During Training JPM: Self-verification shall be demonstrated. (Additional/Concurrent/No other) verification shall be demonstrated.
References:
N2-0P-31, Section H.3.0 and H.4.0 N2-ARP-01, Attachment 6, ARP for window 601648 NUREG 1123, 205000 A4.01 3.7/3.7 Shutdown Cooling System (RHR Shutdown Cooling Mode) Tools and Equipment: Stopwatch Task Standard:
RHS*P1 B tripped after insufficient flow 40 seconds after start. Initial Conditions: Plant is in mode 4. SOC has been in service for >1 hr. SOC Loop 'B' must be shut down for 15 minutes for maintenance checks on system piping. RDS Back fill will remain in service. Initiating Cues: Shutdown and when directed restart RHR Loop "B" in Shutdown Cooling per N2-0P-31, Sections H.3.0 and H.4.0. NMP2 NRC JPM 8-3 November 2010 I Performance Steps I Grade Provide repeat back of initiating I.J Proper communications used for Sat/Unsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME Obtain a copy of the reference I.J N2-0P-31 obtained.
Precautions
& Sat/Unsat procedure and review/utilize the Limitations reviewed.
correct section. Securing Shutdown Cooling for Short Periods In lVIodes 3,4, AND 5 irradiated fuel in the pressure vessel shutdown cooling operation, the cooling pump may shutdown for not more 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per eight period. Refer to 3.4.9,3.4.10,3.9.8, or During the period Shutdown Cooling is not service all Specification coolant pressure temperature limits Monitor RPV coolant I.J Monitors RPV coolant temperature Sat/Unsat temperature closely. IF RPV closely. coolant temperature increases the potential exists for a MODE change. Another operator monitoring RPV Close RHS*MOV40B, SOC B I.J Closes RHS*MOV40B, SDC B Pass/Fail RETURN THROTTLE UNTIL RETURN THROTTLE UNTIL pump pump flow is 2000 gpm on E12-flow is 2000 gpm on E12-R603B, R603B, RHR B TOTAL FLOW. RHR B TOTAL FLOW. NMP2 NRC JPM S-3 -November 2010 I Performance Steps I Grade Stop 2RHS*P1 B by placing its o Stops 2RHS*P1 B by placing its Pass/Fail control switch in control switch in PULL-TO-LOCK LOCK AND start the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> AND starts the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> clock. clock. Fully Close 2RHS*MOV40B.
o Fully closes 2RHS*MOV40B.
Pass/Fail Close 2SWP*MOV33B.
o Closes 2SWP*MOV33B.
Pass/Fail 15 minutes have elapsed and maintenance has completed its checks. Restart the 8 RHS pump in Shutdown Cooling Mode. IF RDS Backfill Injection is out of service to one OR more RPV Level Reference Legs in Mode 3, THEN perform the following: N/A, RDS 8ackfillinjection is NOT out of service.
The RHR pump is without minimum flow protection, Minimum flow of 2: 1000 gpm must be established within 40 seconds of pump start. Use of a stop watch is recommended to ensure the pump is tripped within the required time if minimum flow is not achieved.
Do not allow pump to run for> 15 seconds deadheaded.
- 10. Start 2RHS*P1 B. ::J 2RHS*P1 B red running light Pass/Fail illuminated, Control switch in red flag. 11. Throttle open RHS*MOV40B, o Operator attempts to open SatlUnsat SOC B Return Throttle to 1000 2RHS*MOV40B to obtain 1000 gpm gpm and observes DUAL indication.
- 12. If RHS*MOV40B does not begin a RHS*MOV40B will not open to Pass/Fail to open in 15 seconds OR provide flow 1000 gpm. The system flow is NOT 000 gpm operator will then trip RHS*P1 B by 40 seconds after the pump start, placing the control switch to STOP, Place RHS*P1 B control switch then release to Normal-After-Stop to STOP, then release to Normal-After-Stop NMP2 NRC JPM S-3 -5 November 2010
[ Performance Steps [
Grade 13. Report to CRS inability to CJ Report made to CRS of inability to SatlUnsat required minimum flow on obtain satisfactory min-flow and RHS*P1 B and that the pump pump has been tripped. has been tripped. TERMINATING RHS*P1 B tripped and report to CRS made. RECORD STOP TIME ____ NMP2 NRC JPM S-3 November 2010 INITIAL CONDITIONS:
INITIATING CUES: TURNOVER SHEET Plant is in mode 4. SDC has been in service for >1 hr. SDC Loop "8" must be shutdown for 15 minutes for maintenance checks on system piping. RDS Back Fill will remain in service. Shutdown and when directed restart RHS Loop "8" in Shutdown Cooling per N2-0P-31, Sections H.3.0 and H.4.0. NMP2 NRC JPM 5-3 -7 November 2010 NRC JPM S-4 Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Return WCS to Normal Revision:
NRC 2010 Task Number: NA Approvals: ../"2 NA Exam Security I General Supervis General Supervisor Date Operations Training (DeSignee)
Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
_____________(RO/SRO) Trainer/Evaluator:
____________
_ Evaluation Method: ---.:X:...:..-_Perform
_____Simulate Evaluation Location:
---Plant ___X:...!-__Simulator Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: Yes Start Time: ____ Stop Time: Completion Time: ____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluators Signature:
____________
_ NRC 2010 JPM 8-4 November 2010 Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up (if required): IC 176 Place fourth Filter Demin in service -Remote CU03 A,B,C or D Close WCS*MOV404A Appendix "R" Breakers "SHUT" -Remote CU05A1B SHUT Open WCS*MOV1 07 to the Main Condenser and establish 100 gpm reject flow Throttle WCS*MOV200 to obtain FID flows of 165-175 gpm Insert Malfunction CU08, WCS fails to isolate -QUEUED Activate Malfunction CU07 at 80% when closing WCS*MOV107 to secure blowdown flow. Event Trigger 1 (hzlcus2(1)==1 for MOV107 green light on) will trigger CU07. Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM I CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM / CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated.
JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently.
The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor
/ Evaluator: Critical steps are identified in grading areas as Pass/Fail.
All steps are sequenced unless denoted by a During Evaluated JPM: Self-verification shall be demonstrated.
NRC 2010 JPM 5-4 November 2010 During Training JPM: Self-verification shall be demonstrated. No other verification shall be demonstrated.
References:
N2-0P-37, Sect. F.7.0 N2-S0P-83, N2-ARP-01, Annunciators 602320 and 602313 NUREG KIA 204000 A4.03 Tools and Equipment:
None Task Standard:
WCS Pumps are tripped and the WCS Primary Containment Isolation Valves are closed. Initial Conditions: Reactor Startup in progress with power at 25%. Reactor Water Cleanup System ryvCS) is operating with two (2) pumps and four (4) filter/demins to reduce Feedwater Stratification. Reject flow to the Main Condenser is 100 gpm. Initiating Cues: Return the Reactor Water Cleanup System to NORMAL operations and secure reject flow to the Main Condenser in accordance with N2-0P-37, Section F.7.0. I Performance Steps I Grade Provide repeat back of initiating o Proper communications used for SatiUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME Obtain a copy of the reference o N2-0P-37 obtained.
Precautions
& SatiUnsat procedure and review/utilize the limitations reviewed & section F.7.0 correct section. referenced. SLOWLY open o Opens 2WCS*MOV404A Pass/Fail 2WCS*MOV404A, RWCU VALVE. o NRC 2010 JPM S-4 -3 November 2010 i Performance Steps I Grade Another operator is o Monitor WCS differential flow SatiUnsat monitoring differential indications using 2WCS-FI620A
& B flows. on Panels P632 and P642. Role Play: Log has been updated Notify CRO to log TIME and DATE SatiUnsat of valve opening. Secure "REJECT" flow to the o Slowly lower reject flow to zero (0) Pass/Fail Main Condenser from the WCS as indicated on G33-RS02 using System. G33-R606 (2WCS*FC1135), REJECT FLOW CONTROL FV135 MANUAL CONTROL, on P602. Close 2WCS*MOV107, REJECT SatiUnsat TO MAIN CONDENSER. Malfunction CU07, WCS leak outside Primary Containment, at is auto activated when MOV107 starts to close. Malfunction Failure of WCS to Isolate, malfunction is already active as it queued at the beginning of this 5. Responds to Annunciators: Suspends any operational SatiUnsat 851254 PROCESS evolutions which may be causing perturbation in cleanup system AIRBORNE RADN UNTIL this annunciator ACTIVATED. 602320, RWCU DIFF TIMER EXAMINER NOTE: ANN o Prepares to respond to a cleanup 851254 comes in first. ANN isolation per the 602320 comes in shortly sections of Operator actions to the problem are based response to the ANN in the following JPM Reviews N2-0P-37 Table of Contents and, if time allows Reviews N2-0P-37, section H.1 This annunciator indicates that WCS differential flow exceeded its setpoint of 150.5 gpm and E31-RS21A and/or RS21 B (45 second timers) have started timing out. At the end of seconds, if differential flow has not dropped below 150.5 gpm, full WCS isolation SHOULD NRC 2010 JPM S-4 November 2010 i Performance Steps I Grade Responds to Annunciator D Observes 2WCS"'MOV102 AND Pass/Fail 602313, RWCU DIFFERENTIAL 2WCS*MOV112 DID NOT close by FLOW HIGH observing RED lights "ON" and GREEN lights "OFF". D Informs SM that WCS has failed to Sat/Unsat isolate. D Recommends manual isolation of SatlUnsat WCS to SM/CRS. As SM/CRS, concur recommendation to Candidate will either close Isolation Valves based on entry into SOP-83 or Annunciator response for 602313. IF N2-S0P-83 is as the basis for closing the valves, the candidate is expected follow-up in the Annunciator Response Manually closes D Manually closes 2WCS*MOV102 Pass/Fail 2WCS*MOV102 AND/OR AND/OR 2WCS*MOV112 2WCS*MOV112 per N2-S0P-83 (or Annunciator 602313, RWCU DIFFERENTIAL FLOW HIGH response). Obtains KEYS and inserts into keylock switches Rotates keylock switches to CLOSE position. Observes GREEN Lights "ON" and RED light "OFF" when valve is full closed. Candidate is to be graded as "Pass" for the critical step if valve is closed to isolate the leak. The expectation is that valves will be manually NRC 2010 JPM 8-4 November 2010 I Performance Steps Grade i Follow up actions for o Confirms Isolation valves SaUUnsat Annunciator 602313, RWCU 2WCS*MOV102 AND DIFFERENTIAL FLOW HIGH, if 2WCS*MOV112 closed. valves were closed using SOP-83. Verifies 2WCS-P1 A AND SaUUnsat P1 B have tripped. Pump GREEN light "ON", AND Actuation of Annunciator 602314, RWCU PUMP 1A11B AUTO TRIP. If asked what is WCS pump seals, that the Control Rod System is supplying Pump Provide leak path for WCS o Throttles open 2WCS-MOV11 0, Sat/Unsat Pump seal water flow, to avoid CLEANUP DEMIN BYPASS VLV over-pressurizing pump suction THROTTLE.
piping. 10. Report condition of the o Notifies the SM that the WCS SaUUnsat System to SM. System has been manually isolated.
TERMINATING WCS System is isolated, the WCS Pumps are tripped and 2WCS*MOV11 0 is throttled open. RECORD STOP TIME ____ NRC 2010 JPM S-4 November 2010 TURNOVER INITIAL
- Reactor Startup in progress with power at 25%. CONDITIONS: Reactor Water Cleanup System (WCS) is operating with two (2) pumps and four (4) filter/demins to reduce Feedwater Stratification. Reject flow to the Main Condenser is 100 gpm. INITIATING Return the Reactor Water Cleanup System to NORMAL operations and secure reject flow to the Main Condenser in accordance with N2-0P-37, Section F.7.0. NRC 2010
$-4 -7 November 2010 NRC JPM Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Start and Load Division I Diesel Revision:
NRC 2010 Task Number: NA Approvals:
NA Exam Security I General Supervisor Date Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
_____________(RO/SRO) Trainer/Evaluator:
___________
_ Evaluation Method: ----,X ,-,,--_Perform
_____Simulate Evaluation Location:
___Plant __--'-'X'--_Simulator Expected Completion Time: 25 min. Time Critical Task: No Alternate Path Task: Yes Start Time: ____ Stop Time: Completion Time: ____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluators Signature:
____________
_ Date:______ NMP2 NRC JPM 5-5 November 2010 Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up (if required): IC 175 Override 2SWP*MOV66A Control Switch Closed (OVR-05A2S016DI7284-on) on TRG 1 Remote CW24, Loss of Power to 2SWP*MOV66A on TRG 1, active after 45 seconds. Setup automatic event trigger to activate TRG 1 when DG1 KW exceeds 475 kw (variable dgpdgenkw (1>>= 475). Malfunction DG02A on TRG 2 Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM I CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM / CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will provide cues as necessary.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently.
The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor
/ Evaluator: Critical steps are identified in grading areas as Pass/Fail.
All steps are sequenced critical unless denoted by a "e". During Evaluated JPM: Self verification shall be demonstrated. During Training JPM: Self verification shall be demonstrated. Additional/Concurrent verification shall be demonstrated.
References:
N2-0P-100A, Rev.g, "Standby Diesels", Sec. F.4.0, H.1.0 NUREG KIA: 264000 A4.04 (3.7/3.7) ARP-01 852126, Service Water Low Flow Tools and Equipment: Synch Key Stopwatch NMP2 NRC JPM 5-5 November 2010 Task The Division I Diesel Generator is to be started and paralleled with offsite electric power. The engine will be shutdown using normal operating procedures following a closure of Service Water valve 2SWP*MOV66A.
Initial Conditions: All prestart checks (F.2.0) and data required by Attachment 1 have been completed for Division I N2-0P-100A, Standby Diesel Generators, Attachment 1: Run Time Log and Validity Attachment 2: Diesel Generator Loaded Run Operating Log are being used by an stationed in the Division I EDG All other diesels are operable. Grid conditions are stable. Fast loading is not required Instructor to ask operator for any questions.
Initiating Cues: Start and parallel the Division I Diesel with offsite power and perform a normal load to 1100 KW, per N2-0P-100A, Section F.4.0." Performance Steps Grade Provide repeat back of initiating o Proper communications used for SatiUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01).
repeat back providing correction if necessary.
RECORD START TIME ____ -2. Obtain a copy of the reference o N2-0P-100A obtained.
SatiUnsat procedure and review/utilize the Precautions
& limitations correct section of the procedure.
reviewed & section F.4.0 referenced. Verify 2ENS*SWG101-N*l
.. o Observe NEUTRAL BREAKER Sat/Unsat NEUTRAL BREAKER 101-N1, 101-N1 red light is on. closed. Place EMERGENCY DSL GEN 1 o Parallel switch in on. Sat/Unsat PARALLEL switch to ON .. Verify EMERGENCY DSL GEN 1 o VOLTAGE REGULATOR MODE SatiUnsat VOLTAGE REGULATOR.
MODE SELECT switch in AUTO and red light is on.SELECT switch in AUTO. Place DIVISION 1 2EGS*EG1 o Observe the following Engine Pass/Fail START switch to START. start indications: Annunciators 852109 and -Red light on at EG1 Control 852117 are expected to Switch. alarm. -Diesel Speed as indicated on RPM-2EGPS11, RPM, rises to 600 RPM. NMP2 NRC JPM S-5 -3 November 2010 Run 2EGS*EG 1 unloaded for five minutes at rated voltage AND Frequency to warmup Engine. Instructor/Evaluator should time compress and inform operator that 5 minutes has expired. Place SYNCHRONIZE TO BUS 101 switch to ON. Using EMERGENCY DSL GEN 1 VOLTAGE REGULATOR switch, verify voltage control and clean motor operated potentiometer contacts as follows: Using VOLTAGE REGULATOR control switch, lower voltage UNTIL VOLTS indication is 3950 VOLTS. Using VOLTAGE REGULATOR control switch, raise voltage UNTIL VOLTS indication is 4350 ACVOLTS. Using VOLTAGE REGULATOR control switch, lower voltage UNTIL VOLTS indication is 4160 ACVOLTS. Using EMERGENCY DSL GEN 1 GOVERNOR switch, verify governor control by varying SYNCHROSCOPE indication.
NMP2 NRC JPM 5-5 Grade Generator Voltage as indicated on VM-2EGPA09.
VOLTS, rises to 4.16 A-C KI lOVOl TS. Generator Frequency as indicated on FM-2EGPA09, FREQUENCY, rises to 60 HERTZ. SWP*MOV66A, SERVICE WTR OUTLET, opens. Diesel Service Water Flow as indicated on 2SWP*F176A, SERVICE wrR FLOW, is ;::800 GPM. Annunciator 852117, EDG 1 RUNNING, alarms. 2 EGS and EG1 has run unloaded for at least 5 SYNCHRONIZE TO BUS 101 Pass/Fail switch is ON. Voltage control verified by performing the following. Using VOLTAGE REGULATOR SatlUnsat control switch, lower voltage UNTil VOLTS indication is 3950 VOLTS Using VOLTAGE REGULATOR SatlUnsat control switch, raise voltage UNTIL VOLTS indication is 4350 AC VOLTS. Using VOLTAGE REGULATOR SatlUnsat control switch, lower voltage UNTil VOLTS indication is 4160 AC VOLTS. Speed control verified by SatlUnsat observing change in rate of SYCHROSCOPE rotation or FREQUENCY meter readings change. November 2010 Performance Steps Using VOLTAGE REGULATOR switch, match voltages on 4.16KV 2ENS*SWG101 INCOMING VOL TS meter AND 4KV XSR1A 12ABS-X1/2EGS*EG1 RUNNING VOLTS meter. Adjust GOVERNOR switch to establish slow clockwise rotation on SYNCHROSCOPE (slow in fast direction), as indicated by: Meter movement between % to 1 inch per second 12 to 24 seconds for 360 0 meter sweep WHEN SYNCHROSCOPE reaches 5 minutes before 12 o'clock (11 o'clock position), perform the following: Close 2ENS*SWG101-1 Verify Generator picks up load as indicated on WM-2EGPA20, WATTS. Place SYCHRONIZE TO BUS 101 switch to OFF. USing GOVERNOR switch, raise Generator Load to approximately 1100 KW at a rate of about 500 KW per minute. Console Operator:
When Generator Load exceeds 475 KW, confirm override to close 2SWP*MOV66A activates on TRG 1 and MOV power supply trips after 45 seconds. SWP flow on P852 indicator 2SWP*FI76A SERVICE WTR FLOW drops and when below about 450 gpm Annunciator 852126, EDG Service Water Flow Low alarms ALTERNATE PATH NMP2 NRC JPM S-5 Standard Grade 0 Observe voltages matched on INCOMING and RUNNING VOL TS meters. SatiUnsat 0 Observe SYNCHROSCOPE rate approximately 12 to 24 seconds for one 360 0 sweep. SatiUnsat 0 Closes 2 ENS*SWGR101-1 when synchroscope reaches 5 minutes before 12 (-10 minutes to 12 and 12 o'clock) and observes Red light ON, Green light OFF and generator picks up load by positive (upward) indication on WATTS meter. Pass/Fail 0 SYNCHRONIZE TO BUS 101 is OFF SatiUnsat 0 Raises Generator Load to approximately 1100 KW at a rate of about 500 KW per minute. SatiUnsat November 2010 Performance Steps Refers to 852126 alarm response. Verify SWP*MOV66A open. 18. Verify SWP*V941A and V231A open. Note: Candidate may NOT verify 941A and 231A because these are manual valves which are known to be open because flow previously existed. Cue: If sent to determine the position of SWP*V941A and 231A, report both valves are open. Cue: If asked direct candidate to take the appropriate actions. Critical step is to unload the engine such that an automatic trip is avoided. By unloading the engine and tripping the output breaker, the heat generation is limited. Unload EDG1 per N2-0P-100A, Section H.1.0 (preferred) for Emergency Shutdown OR Section F.6.0 for Normal Shutdown At 2CEC*PNL852, using GOVERNOR switch, reduce DIESEL GENERATOR LOAD to 100 KW. NMP2 NRC JPM S-5 Grade 852126 alarm response referred Sat/Unsat to, observes low service water flow <<100 gpm) on SWP*FI76A. Observes and reports SatlUnsat 2SWP*MOV66A is closed and identifies breaker tripped, after trip occurs AND valve failure to open, Green light OFF, Red light OFF. Contacts and directs an SatlUnsatlNA operator to verify SWP*V941 A and V231A are open. Operator contacted and 941 A and 231 A verified open. Refers to N2-0P-100A, Section Pass/Fail H.1.0 to Emergency OR Refers to N2-0P-100A, Section F.6.0 to Normal Generator Load reduced to SatlUnsat 1 OOKW using the GOVERNOR switch. November 2010 Performance Steps !
Grade Using VOLTAGE VARS adjusted between 0 and SatlUnsat* REGULATOR switch, adjust 100 to bus on AC VARS to >0 AND <100 A-C TO BUS meter by KILOVARS TO BUS. voltage Open 2EGS*SWG101*,1, Rotate control switch for Pass/Fail* OUTPUT BREAKER 2ENS*SWG101-10UTPUT BREAKER counter clockwise and observe:
- Green light ON, Red light OFF
- WA TIS goes to 0 Note: Depending on the shutdown method selected shutdown the EDG using one of the following methods. .20. If using N2-0P-100A, Section Observes annunciator 852117 SatlUnsat H.1.0 to Emergency Shutdown EDG 1 RUNNING clears. EDG1 notify operator at Observes Division I 2CES*IPNL406 ENGINE green light CONTROL PANEL to depress EMERGENCY STOP red Instructor Note: If notified perform emergency stop activate malfunction DG02A shutdown EDG1 by depressing Cue: Report as operator from room that the Division I has been OR .21. If using N2-0P-100A, Section At 2CEC*PNL852, place DIVISION I 2EGS"'START control switch F.6.0 to Normal Shutdown STOP and observe engine at 2CEC*PNL852, place DIVISION minute cooldown cycle begins. I 2EGS*START control switch Notify operator in the EDG room to 0 Operator dispatched to SatlUnsat complete the remaining shutdown complete shutdown steps in the steps. EDG room. Report as operator from room that the remaining are in NMP2 NRC JPM S-5 -7 November 2010
- 23. Report Division I 2EGS*EG1 has Report has been made to SM. SatiUnsat been shutdown due to a loss of Cooling Water. TERMINATING CUE: 2EGS*EG1 Division I has been unloaded and shutdown following unsuccessful run. RECORD STOP TIME ____ NMP2 NRC JPM S-5 November 2010 Initial Conditions: All prestart checks (F.2.0) and data required by Attachment 1 have been completed for the Division I EDG. N2-0P-100A, Standby Diesel Generators, Attachment 1: Run Time Log and Validity and Attachment 2: Diesel Generator Loaded Run Operating Log are being used by an Operator stationed in the Division I EDG Room. All other diesels are operable.
- 4. Grid conditions are stable. Fast loading is not required Initiating Cues: "(Operators name) Start and parallel the Division I Diesel with offsite power and perform a normal load to 1100 KW, per N2-0P-100A, Section F.4.0." NMP2 NRC JPM $-5 -9 November 2010
NRC JPM Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Place Main Turbine Shell Warming In Revision:
NRC 2010 Service Task Number: NA Approvals:
NA Exam Security I General Supervisor Date Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
_____________(RO/SRO) Trainer/Evaluator:
___________
_ Evaluation Method: Perform _____Simulate Evaluation Location:
___Plant Simulator Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: No Start Time: Stop Time: Completion Time: ____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluators Signature:
____ ._________ Date:______ NMP2 2010 NRC JPM S-6 November 2010 Recommended Start Location: (Completion time based on the start location)
Simulator Set-up (if IC-157 2. Neck Spray in service Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM / CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM / CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM This evaluated JPM is a measure of your ability to perform this task independently. Control Room Supervisor has determined that a verifier is not available and that additional concurrent verification will not be provided; therefore, it should not be Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor I Evaluator: Critical steps are identified in grading areas as Pass/Fail.
All steps are sequenced critical unless denoted by a tI.". During Evaluated JPM: Self-verification shall be demonstrated. During Training JPM: Self-verification shall be demonstrated.
- No other verification shall be demonstrated.
References:
N2-0P-21, Revision 01100 KIA 241000 A4.18 2.9/2.8 NMP2 2010 NRC JPM 8-6 November 2010 Tools and Equipment:
None Task Standard: Shell warming placed in service. Initial Conditions: Reactor Pressure is 65 psig. Main Turbine Turning Gear is in operation. N2-0P-21 "Main Turbine System" Section E.3.0. is complete through step E.3.1 Initiating Cues: "(Operators name), Place main turbine shell warming in service in accordance with N2-0P-21, Section E.3.0. beginning at step E.3.2." I Performance Steps I Grade Provide repeat back of initiating o Proper communications used for SatlUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME Obtain a copy of the reference o N2-0P-21 obtained.
Precautions
& SatlUnsat procedure and review/utilize the Limitations reviewed.
correct section. Push Turbine RESET o Pushes Turbine RESET pushbutton Pass/Fail pushbutton UNTIL the Turbine UNTIL the Turbine TRIPPED light TRIPPED light goes out AND goes out AND verifies the following:
verify the following:
Examiner Cue: If required, candidate to hold the reset pushbutton down until reset light comes Turbine RESET light lit.
- Turbine RESET light lit. SatlUnsat CONDENSER VACUUM
- CONDENSER VACUUM TRIP SatlUnsat TRIP RESET light lit. RESET light lit. MECHANICAL TRIP RESET
- MECHANICAL TRIP RESET light SatlUnsat light lit. lit. NMP2 2010 NRC JPM S-6 -3 November 2010 Intermediate Stop Valves ISV1 through ISV6 ALL indicate 100% on COMBINED INTERMEDIATE STOP VALVE POSITION indicators. Intercept Valves IV1 through IV6 ALL indicate 0% on COMBINED INTERCEPT VALVE POSITION indicators. Main Stop Valves MSV1 through MSV4 ALL indicate 0% on MAIN STOP VALVE POSITION indicators. Control Valves CV1 through CV4 ALL indicate 0% on CONTROL VALVE POSITION indicators. Verify Master Trip Solenoid Valve (MTSV) MASTER TRIP SOLENOID TEST push buttons TEST TRIP A AND B lights lit. Verify 2MSS-AOV92A, REHEATER 1A STM SUPPLY VLV is CLOSED. Verify 2MSS-AOV92B, REHEATER 1B STM SUPPI_Y VLV is CLOSED. Place TURBINE SHELUCHEST WARMING switch in ON position at 2CEC-PNL824, MAIN REHEAT & AUX ST DR TURB BLDG MISC DR.
- Intermediate Stop Valves ISV1 through ISV6 ALL indicate 100% on COMBINED INTERMEDIATE STOP VALVE POSITION indicators.
SatlUnsat
- Intercept Valves IV1 through IV6 ALL indicate 0% on COMBINED INTERCEPT VALVE POSITION indicators.
SatlUnsat
- Main Stop Valves MSV1 through MSV4 ALL indicate 0% on MAIN STOP VALVE POSITION indicators.
- Control Valves CV1 through CV4 ALL indicate 0% on CONTROL VALVE POSITION indicators.
SatlUnsat Sat/Unsat CJ Verifies Master Trip Solenoid Valve (MTSV) MASTER TRIP SOLENOID TEST push buttons TEST TRIP A AND B lights lit. SatiUnsat CJ Verifies 2MSS-AOV92A, REHEATER 1A STM SUPPLY VLV is CLOSED. Sat/Unsat CJ Verifies 2MSS-AOV92B, REHEATER 1B STM SUPPLY VLV is CLOSED. SatlUnsat CJ Places TURBINE SHELUCHEST WARMING switch in ON position at 2CEC-PNL824, MAIN REHEAT & AUX ST DR TURB BLDG MISC DR. Pass/Fail NMP2 2010 NRC JPM S-6 November 2010 Performance Ste s Standard Grade 8. Close the following valves at D Closes the following valves at 2CEC-PNL824:
- CRS-MOV7 A, COLD
- CRS-MOV7B, COLD
- CRS-MOV8A, COLD
- CRS-MOV8B, COLD
- CRS-MOV9A, COLD
- CRS-MOV9B, COLD
- CRS-MOV18A, COLD
- CRS-MOV18B, COLD
- DSM-MOV79A, MOISTURE
- DSM-MOV79B, MOISTURE
- HRS-MOV1,
- HRS-MOV2,
- ESS-MOV28A, 5 TH POINT
- ESS-MOV28B, 5 TH POINT
- ESS-MOV28C, 5 TH POINT
- ESS-MOV-3A, 6 TH POINT
- ESS-MOV-3B, 6 TH POINT
- ESS-MOV-3C, 6 TH POINT
- ESS-MOV-3C, 6 TH POINT SatlUnsat HEATER C EXTRACTION HEATER C EXTRACTION STM STM ISOL VLV ISOL VLV NMP2 2010 NRC JPM S-6 -5 November 2010 I Performance Steps 2DTM-AOV105, 5 TH PP HTR EXTRACTION LINE INL HDR DRAIN VLV 2DTM-AOV104, 6 TH PP HTR EXTRACTIOI\I LINE INL HDR DRAIN VLV Verify LOAD LIMIT potentiometer set at
- 10. Push FAST pushbutton START UP RATE
- 11. Observe FAST pushbutton lit. 12. Verify LOAD SET indication is 0 Megawatts.
- 13. Push SHELL pushbutton at MAIN STOP VALVE POSITION DEMAND FOR CHEST/SHELL WARMING controls.
- 14. Verify the following indications: SHELL pushbutton lit. Control Valve CV1 through CV3 ALL indicate 100% on CONTROL VALVE POSITION indicators AND CV4 indicates approximately 40 -60% control valve position. Intermediate Stop Valves ISV1 through ISV6 ALL indicate 0% on COMBINED INTERMEDIATE STOP VALVE POSITION indicators. Closed 2DSM-LV78A, 2DSM-TK4A Emergency Drain control Valve, at Panel 2CES-1 PN L204. As field operator report the valve is closed. NIVIP2 2010 NRC JPM S-6 I Standard 2DTM-AOV105, 5 TH PT HTR EXTRACTION LINE INL HDR DRAIN VLV 2DTM-AOV104, 6 TH PT HTR EXTRACTIOI\I LINE INL HDR DRAIN VLV Verifies LOAD LIMIT SET potentiometer set at 8.69 (102.5%). Pushes FAST pushbutton at START UP RATE controls. Observes FAST pushbutton lit. Verifies LOAD SET indication is Pushes SHELL pushbutton at MAIN STOP VALVE POSITION DEMAND FOR CHEST/SHELL WARMING controls. Verifies the following indications: SHELL pushbutton lit. Control Valve CV1 through CV3 ALL indicate 100% on CONTROL VALVE POSITION indicators AND CV4 indicates approximately 40 -60% control valve position. Intermediate Stop Valves ISV1 through ISV6 ALL indicate 0% on COMBINED INTERMEDIATE STOP VALVE POSITION indicators. Contacts field operator to close 2DSM-LV78A,2DSM-TK4A Emergency Drain control Valve, at Panel 2CES-IPI\IL204. Grade Pass/Fail Pass/Fail SatiUnsat SatiUnsat SatiUnsat Sat/Unsat Pass/Fail SatiUnsat SatiUnsat SatiUnsat SatiUnsat November 2010 Closed 2DSM-L V78B, 2DSM-TK4B Emergency Drain control Valve, at Panel 2CES-IPNL204. As field operator report the valve is closed. 15. IF during shell warming Turbine rolls off Turning immediately stop shell by performing the Close 2MSS-MSV1 D, MSV2, by pushing the DECREASE pushbutton UNTIL CHEST/SHELL WARMING DEMAND meter indicates
<0 Percent. 16. Start shell warming preheating crossaround as Procedure Note: The High Pressure Turbine Shell Inner Temperature will be utilized in determining soak time requirements of Attachment
- 1. Record High Pressure Turbine Shell Inner Temperature in Control Room Log, using Computer Point TMITA10 OR TMITA14, OR 2TMI-T JR137, Point 4. When applicant temperature, provide value of 18. Throttle 2MSS-MSV1 D, MSV2 (Turbine Main Stop Valve), by intermittently pushing INCREASE or DECREASE push buttons as necessary at MAIN STOP VALVE POSITION DEMAND FOR CHEST/SHELL WARMING control. NMP2 2010 NRC JPM 8-6 Contacts field operator to close 2DSM-LV78B,2DSM-TK4B Emergency Drain control Valve, at Panel 2CES-IPNL204. Reviews step and continues (J Reviews the note regarding soak time requirements. Records High Pressure Turbine Shell Inner Temperature in Control Room Log, using Computer Point TMITA10 OR TMITA14, OR TJR137, Point 4. Throttles 2MSS-MSV1 D, MSV2 (Turbine Main Stop Valve), by intermittently pushing INCREASE or DECREASE pushbuttons as necessary at MAIN STOP VALVE POSITION DEMAND FOR CHEST/SHELL WARMING control. SatiUnsat SatiUnsat SatiUnsat Pass/Fail November 2010 I Performance I Standard Grade 19. At 2CEC*PNL842, monitor D Monitors Crossaround Piping SatlUnsat Crossaround Piping Temperature on Temperature on TR137/ZDR135, TURBINE TR137/ZDR135, TURBINE TEMP. TEMP. Cue: Temperatures indications are rising Examiner When the candidate is cued regarding Piping Temperature, the JPM may be TERMINATING Shell Warming in service with crossaround temperature being RECORD STOP TIME,____ NMP2 2010 NRC JPM S-6 November 2010 TURNOVER SHEET INITIAL 1. Reactor Pressure is 65 psig. CONDITIONS: Main Turbine Turning Gear is in operation. N2-0P-21 "Main Turbine System" Section E.3.0. is complete through step E.3.1. INITIATING "(Operators name), Place main turbine shell warming in service in accordance with N2-0P-21, Section E.3.0. beginning at step E.3.2." NMP2 2010 NRC JPM S-6 November 2010 NRC JPM Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Downshift Reactor Recirculation Pumps Revision:
NRC Task Number: Approvals:
<) f!1t:.Jt( NA Exam Security I General Supervis r General Supervisor Date Operations Training (Designee)
Operations (Designee)
NA Exam Security Configuration Control Performer:
____________
Trainer/Evaluator:
________Evaluation Method: ------'X'-'--
__Perform _ __
Evaluation Location:
__Plant Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: Start Time: ____ Stop Time: Completion Time: ___,JPM Overall Rating: Pass NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluator Signature:
______________
_ Date:______ NRC 2010 JPM S-7 November 2010 Recommended Start Location:
Simulator Simulator Set-up: Reset to IC-175 Directions to the Instructor!Evaluator:
Prior to performance of this .JPM, obtain SM ! CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM / CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently.
The Control Room Supervisor has determined that a verifier is not available and that additional!
concurrent verification will not be provided; therefore it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional!
concurrent verifier.
Notes to Instructor
/ Evaluator: Critical steps are identified as Pass/Fail.
All steps are sequenced critical unless denoted by a".". During Evaluated JPM: Self-verification shall be demonstrated. During Training JPM: Self-verification shall be demonstrated. No other verification shall be demonstrated.
References:
N2-0P-29 G.1.0 NUREG KIA 202001 A4.01 3.7/3.7 NRC 2010 JPM 8-7 November 2010 Tools and Equipment:
- 1. None Task Standard:
Recirculation pumps 1A and 1 B running in slow speed with their flow control valves full open. NRC 2010 JPM S-7 November 2010 Initial Conditions: The plant is at 41 % power. The Rod line is at 60%. 3. Hydrogen injection has been Initiating "(Operators name), Transfer Recirc Pumps from high speed to low speed per N2-0P-29 section I Performance Steps 1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME Obtain a copy of the reference procedure and review/utilize the correct section. Verify the following: LOW FREQ MG SET DRIVE MOT BRKR 1A1B are open AND control switches in NORMAL. LOW FREQ MG SET GEN BRKR 2A1B are open AND control switches in NORMAL. GENERATOR LOCKOUTS K110A AND K110B are reset and White Lights are illuminated at RECIRC SYSTEM LFMG SET AUXILIARY PANEL B35-P001A(B). (Normal Switchgear EL. 293') Relays at B35-P001A(B) are reset Cue: When asked, report that generator
& pump motor lockout relays are At 2NPS-SWG004 (SWG005), confirm breaker 1, REACTOR RECIRCULATION PUMP MOTOR BRKR -2A(B) 2RCS-M1A(B) is charged as indicated by yellow indicator on lower left of breaker. Cue: Acknowledge request and report that breaker 1 on both NPS-SWG004 and 005 are charged. NRC 2010 JPM 8-7 I Standard Proper communications used for repeat back (GAP-OPS-01) N2-0P-29 obtained.
Precautions Limitations reviewed and section Verifies BRKRs 1 AlB are open Lights ON and Red Lights OFF) control switches in Verifies BRKRs 2A1B are open Lights ON and Red Lights OFF) control switches in Verifies GENERATOR LOCKOUTS K110A AND K11 OB are reset and White Lights are illuminated at RECIRC SYSTEM LFMG SET AUXILIARY PANEL B35-P001A(B). (Normal Switchgear EL. 293') Confirms breaker 1 at 2NPS-SWG004 (SWG005), REACTOR RECIRCULATION PUMP MOTOR BRKR -2A(B) M1A(B), is charged as indicated by yellow indicator on lower left of breaker. November 2010 Grade SatlUnsat SatlUnsat SatlUnsat SatlUnsat Sat/Unsat SatlUnsat Position AND hold BRKR 5A(B) D Rotates BRKR 5A control switch to Pass/Fail RECIRC PMP 1A(B) MOTOR A(B) TRANSFER MG control switch to TRANSFER MG, D Rotates BRKR 5B control switch to Pass/Fail THEN position AND hold BRKR 5B(A) TRANSFER MG RECIRC PMP 1 B(A} MOTOR B(A} D WHEN BRKR 5A and BRKR 5B are Pass/Fail control switch to TRANSFER MG. observed to OPEN, THEN releases BRKR 5A and BRKR 5B control switches to WHEN BRKR 5A and BRKR 5B observed to OPEN, THEN BRKR 5A and BRKR 5B switches to Instructor Note: The following annunciators alarm not requiring action: 603139 "Reactor Water Level 603218 "OPRM Trip 842310 "HWC Trouble" (reflashes) 851456 "Cnst System Trouble Backup Pmp Available 601225 Recirc PmP 1AAuto Low Speed 601226 Recirc PmP 1 B Auto Low Speed Observe the following:
BRKR 1AAND BRKR 1B close. D Observes BRKR 1A red light ON and SatiUnsat* green light OFF Observes BRKR 1 B red light ON and SatiUnsat green light OFF Pump speed lowers to between 460 D Observes speed on B35-R651A and B SatiUnsat* AND 350 lowers to between 460 AND 350 rpm. BRKR 2A AND BRKR 2B close. D Observes BRKR 2A red light ON and SatiUnsat* green light OFF Observes BRKR 2B red light -ON and SatiUnsat green light OFF Pump speed stabilizes at about 445 D Observes speed on B35-651A and B SaUUnsat stabilizes at about 445 rpm rpm. NRC 2010 JPM 5-7 November 2010 I I Performance Steps Standard Grade Using 2RCS-HC1603A RECIRC LOOP o Raises output signals for RECI RC LOOP Pass/Fail A FLOW CONTROL station, raise A and B FLOW CONTROL to 100%. output signal to 100% (about 85% o Observe loop A VALVE POSITION at SatiUnsat VALVE POSITION INDICTED) about 85% o Observe loop B VALVE POSTION at SatiUnsat Using 2RCS-HC1603B RECIRC LOOP about 95% B FLOW CONTROL station, raise output signal to 100% (about 95% VALVE POSITION indicated)
Instructor Note: The following alarms not requiring 603218 "OPRM Trip Enabled" Monitor the following recirculation o Observe about 73 amps on AM-SatiUnsat pump/LFMG parameters:
2RCSA(B)60 About 73 amps on AM-o Observe approximately 450 rpm on B35-SatiUnsat 2RCSA(B)60, RCS-MG1A(B)
R651A(B).
CURRENT. o Dispatches an Auxiliary Operator to report SatiUnsat Recirc pump speed approximately LFMG generator voltage and amperage.
450 rpm on RECIRC PI\t1P 1A(B) At Switchgear Bldg. Penthouse 293"on B35-P001A(B), generator voltage 1250 V, on GENERATOR At Switchgear Bldg. Penthouse 293"on B35-P001A(B), less 100 Amps (continuous load) on GENERATOR Cue: As the Auxiliary Operator, that LFMG 'A' generator 1250 volts and 95 amps. LFMG '8' generator indicates volts and 94 Reports that Recirc pumps have transferred to slow Cue: Acknowledge the report. TERMINATING CUE: Recirc pumps 1A and 1 B running in slow speed. RECORD STOP TIME ____ NRC 2010 JPM S-7 November 2010 TURNOVER SHEET INITIAL 1. The plant is at 41 % power. CONDITIONS:
- 2. The Rod line is at 60%. 3. Hydrogen injection has been secured. INITIATING "(Operators name) Transfer Recirc Pumps from high speed to low speed per N2-0P-29 section G.1.0." NRC 2010 JPM $-7 November 2010 NRC JPM Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Shift RBCLCW and TBCLCW Pumps Revision:
NRC Task Number: NA Exam Security I General Supervisor Date Operations (Designee)
NA Exam Security Configuration Control Performer:
_________
Trainer/Evaluator:
______Evaluation Method:
__Perform _ __
Evaluation Location:
__,Plant Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: Start Time: ----Stop Time: Completion Time: ___JPM Overall Rating: Pass NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluator Signature:
_____________
_ Date:______ NRC 2010 JPM 5-8 November 2010 Recommended Start Location:
Simulator Simulator Set-up: 1. Resetto IC 186 2. Remote malfunction CW-27 set for 102°F on Trigger 1 3. Event trigger1, hzlcw1 ccsa01 (1 )==1, will activate when CCS-P1A stopped (green light on) Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM I CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM / CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently.
The Control Room Supervisor has determined that a verifier is not available and that additional!
concurrent verification will not be provided; therefore it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional I concurrent verifier.
Notes to Instructor I Evaluator: Critical steps are identified as Pass/Fail.
All steps are sequenced critical unless denoted by a "e". During Evaluated e Self-verification shall be During Training JPM:
- Self-verification shall be demonstrated.
- No other verification shall be demonstrated.
References:
- 1. N2-0P-13 2. N2-0P-14 NRC 2010 JPM S-8 November 2010 ARP 601244 4. NUREG KJA 400000 A4.01 Tools and Equipment:
- 1. None Task Standard:
RBCLCW and TBCLCW pumps shifted with TBCLCW temperature being controlled manually Initial Conditions:
- 1. The plant is operating at full power. Initiating Cue: To support Maintenance checks, shift CCP Main Pumps from "A", "B" lineup to "B", lineup, lAW N2-0P-13, Section F.2.0 and Then shift CCS Pumps from "A", "B" lineup to "8", "c" lineup lAW N2-0P-14, Section F.3.0 and FAO. A plant operator is stationed at the pumps to support pump swaps and perform pump checks. I Performance Steps Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME Obtain a copy of the reference procedure and review/utilize the correct section. For the Main CCP pump to be verify the pump casing is free of air Uncap AND throttle open 2CCP-V195 (Vi96, V197), PiA (8,C) VENT. WHEN a steady stream of water is observed, close AND recap 2CCP-Vi95 (Vi96, V197). Cue: Checked by local operator. has been vented and the vent valve been closed and NRC 2010 JPM S-8 I Standard Grade o Proper communications used for repeat back (GAP-OPS-01).
SatlUnsat Cl N2-0P-13 &N2-0P-14 obtained.
Precautions
& limitations reviewed.
SatlUnsat Cl Ensures pump is checked and vented by plant operator.
SatlUnsat November 2010 I Performance Steps I Grade For the Main CCP pump to be started, at o Places control switch for Pass/Fail paneI2CEC*P601, start 2CCP-P1A (B,C), P1 C in red flagged position.
PMP 1A (B,C), by placing control switch in Normal-After-START (red flagged).
Note: The operator may also make a announcement on the page system 2CCP-P1C is being Note: The applicant will check indications for amps and Confirm normal operating indications in o Ensures operating parameters are SatlUnsat accordance with Subsection F.1.0. checked by plant operator.
Cue: Local indications are normal At 2CEC*PNL601, secure 2CCP-P1A (B,C), 0 Places control switch for 2CCP-Pass/Fail PMP 1A (B,C), by placing control switch in P1A in green flagged position.
Normal-After-STOP. (Green flagged) IF required, place 2CCP-P1A (B,C) control Q May request required status of SatlUnsat switch in PULL TO LOCK. pump control switch. CUE: If asked, the pump can be placed in PULL TO LOCK at this time. Confirm normal operating indications in o Ensures operating parameters are SatlUnsat accordance with Subsection F.1.0. checked by plant operator.
Cue: Another operator will check local indications Examiner Note: The applicant will now refer to N2-0P-14 for TBCLCW operations Procedure Note: CCS system flow of greater than gpm requires more than one exchanger in Actions in this Subsection performed at 2CEC*PNL601 otherwise NRC 2010 JPM 8-8 November 2010 I Performance Steps IF time permits, perform the following: Dispatch an Operator to the pump to perform prestart inspection AND observe pump during start. For the pump to be started, close 2CCS-V303A(B,C), TBCLC PUMP 1A(B,C) STOP CHECK. Cue: Pre-start checks are complete and the stop-check valve is CLOSED Start 2CCS-P1A(B,C), PMP 1A(B,C), by placing the control switch to START (red flagged).
Note: The operator may also make a plant announcement on the page system that 2CCS-P1C is being started Slowly open 2CCS-V303A(B,C).
Cue: Valve has been opened 12. Confirm normal operating indications accordance with Subsection Cue: Local indications are normal Procedure Note: Actions in this Subsection are performed at 2CEC*PNL601 unless otherwise specified. CCS Pump runout is 8,500 gpm. If system flow is greater than 8,000 gpm for one pump operations or 16,000 gpm for two pump operations, then starting an additional pump increases the probability of damaging tube vibrations in the CCS heat exchangers.
Three CCS pump operation shall be avoided unless shifting of pumps is required.
I Standard Grade o Dispatched operator or determines SaUUnsat task has been performed.
o Places control switch for P1 C in red flagged position.
Pass/Fail o Directs local operator to open valve. SaUUnsat o Ensures operating parameters are checked by plant operator.
SaUUnsat o Checks indications Sat/Unsat NRC 2010 JPM S-8 November 2010 Confirm the CCS pump is NOT required for CCS System flow as follows: Computer Pt CCSFA01 # of Running TBCLCW PMP SUCTION FLW Pumps 1,000 -8,200 1 8,200 -16,400 2 Cue: A CCS pump is NOT required -flow is normal Procedure Note: 2CCS-V303A (B,C) is o Directs a local operator to close SatlUnsat located at 2CCS-P1A (B,C) on T8 Elev 250 valve Southwest. Close 2CCS-V303A (B,C), TBClC PUMP 1A (B,C) STOP CHECK. Cue: Valve is closed 15. Secure 2CCS-P1A (B,C), PMP 1A (B,C), by placing the control switch in After-STOP. (Green flagged) o Places control switch for P1A in green flagged position Pass/Fail Console Operator:
Ensure Trigger 1 to fail TBClC temperature controller activates when 2CCS-P1A is stopped. (REMOTE 27 set for 102°F) 16. IF required, place 2CCS-P1A (B,C) control switch in PULL TO lOCK. 0 May request required status of pump control switch. SatlUnsat Cue: If asked, the pump can be placed in PUll TO lOCK at this time. Confirm normal operating indications for o Ensures operating parameters are SatlUnsat the running CCS Pump(s) in accordance checked by plant operator.
with Subsection F.1.0. Examiner Note: Applicant will respond to annunciator 601244 (Turbine Bldg Closed loop Cooling Sys Trouble) and Computer Point CCSTC04 for TBClCW HX DISCH TEMP NRC 2010 JPM S-8 November 2010 I Performance Steps I Grade Determines temp controller is failed and (:J Performs either: Sat/Unsat refers to ARP 601244 or SOP-14
- ARP 601244 actions OR Enters SOP-14, Loss or Degraded CCs System Places 2CCS-TIK104 in "M" Manual (:J Places controller in "M" Manual Pass/Fail Manually controls temperature
(:J Adjusts temperature downward to Pass/Fail approximately 85°F TERMINATING CUE: JPM is complete when TBCLCW temperature is being controlled RECORD STOP TIME,___NRC 2010 JPM 8-8 November 2010 TURNOVER INITIAL The plant is operating at full power. CONDITIONS:
INITIATING CUES: To support Maintenance checks, shift CCP Main Pumps from "A", "8" lineup to "8", "C" lineup, lAW N2-0P-13, Section F.2.0 and F.3.0. Then shift CCS Pumps from "A", "8" lineup to "8", "c" lineup lAW N2-0P-14, Section F.3.0 and F.4.0. A plant operator is stationed at the pumps to support pump swaps and perform pump checks. NRC 2010 JPM S-8 November 2010 NRC JPM P-1 Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Start the Diesel Fire Pump Locally Revision:
NRC 2010 Task Number: NA Approvals:
NA Exam Security I General Supervisor Date Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
______________(RO/SRO) Trainer/Evaluator:
___________
_ Evaluation Method: ___Perform __--=-:X'--_Simulate Evaluation Location: __Plant _____Simulator Expected Completion Time: 30 min. Time Critical Task: No Alternate Path Task: No Start Time: ____ Completion Time: ____ JPM Overall Rating: Pass Fail A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluator's Signature:
____________
_ Date:______ NRC 2010 JPM P-1 -1 November 2010 Recommended Start Location: (Completion time based on the start Any Simulator Set-up (if N/A Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM I CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM I CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM This evaluated JPM is a measure of your ability to perform this task independently. Control Room Supervisor has determined that a verifier is not available and that concurrent verification will not be provided; therefore, it should not be Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor I Evaluator: Critical steps are identified in grading areas as Pass/Fail.
All steps are sequenced critical unless denoted by a".". During Evaluated JPM: Self-verification shall be demonstrated. During Training JPM: Self-verification shall be demonstrated. (Additional/Concurrent/No other) verification shall be demonstrated.
NRC 2010 JPM P-1 -2 November 2010
References:
N2-0P-43, Fire Protection Water Tools and Equipment:
None Task Diesel Fire Pump in Initial A start of the Diesel Fire Pump is required for a hydro of the fire Initiating Start Diesel Fire Pump 2FPW-P1 locally at panel 2FPW-PNL234 lAW N2-0P-43 Section I I Performance Steps Standard Grade Provide repeat back of initiating o Proper communications used for SatlUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME Obtain a copy of the reference o N2-0P-43 obtained.
Precautions
& SatlUnsat procedure and review/utilize the Limitations reviewed.
correct section. PRIOR to starting the pump, o Notifies the Fire Brigade Leader SatlUnsat notify the Fire Brigade Leader. prior to starting the pump. Acknowledge as Brigade The following step is performed inside 2FPW-PNL234 in Diesel Fire Pump NRC 2010 JPM P-1 -3 November 2010 I Performance Steps .
Grade IF applicable, locally start 0 Locally start 2FPW-P1, 2FPW-P1, Diesel Engine Driven Engine Driven Fire Pump, Fire Pump, as follows:
Note: Annunciator 849221, DIESEL FIRE PUMP NOT IN AUTO START, will alarm in the next step. Place the SELECTOR switch in MAN Aor B. Start 2FPW-P1 by depressing the START pushbutton. The diesel fire pump failed to crank and is not running IF 2FPW-P1 fails to crank, D perform the following: Briskly turn the SELECTOR switch to the opposite Manual position Start 2FPW-P1 depressing the You hear the pump running Places the SELECTOR switch in MAN Aor B. Starts 2FPW-P1 by depressing the START pushbutton.
Reviews the procedure then performs the following: Briskly turns the SELECTOR switch to the opposite Manual position Starts 2FPW-P1 by depressing the START pushbutton. The following parameters should be monitored at 5 minute intervals during the first 15 minutes of pump operation and then once per hour. NRC 2010 JPM P-1 November 2010 I Performance Steps 6. Confirm proper pump operation as indicated by the following No unusual noise OR vibrations Sat
- NO RED lights lit ON 2FPW-PNL234 Sat System pressure is == 150 psig as indicated on one of the following: Respond that press indicates:: 2FPW-PI108,2FPW-P1 discharge pressure gauge, located at the pump. 2FWP-PI124, FPW System pressure gauge, located on the wall by 2FPW-PNL234. 2FPW-PI215, FIRE HEADER WTR PRESS meter, located on PNL849 Engine speed is == 1950 RPM as indicated on the diesel :: 1950 RPM. Lube oil pressure is 59 -80 psi as indicated on the diesel :: 70 psi. Jacket water temperature is 165 -195°F as indicated on 2FPW-TI1012, DSL ENG COOLANT TEMP gauge, on the diesel :: 180°F.
Grade Confirms proper pump operation as SatiUnsat indicated by the following: Checks for unusual noise OR SatiUnsat vibrations Verifies NO RED lights lit ON SatiUnsat 2FPW-PNL234 Checks that system pressure is SatiUnsat
== 150 psig as indicated on one of the following: (list in left hand column) Checks engine speed is == 1950 SatiUnsat RPM as indicated on the diesel. Checks Lube oil pressure is SatiUnsat 59 -80 psi as indicated on the diesel. Checks Jacket water SatiUnsat temperature is 165 -195°F as indicated on 2FPW-TI1012, DSL ENG COOLANT TEMP gauge, on the diesel. NRC 2010 JPM P-1 November 2010 I Performance Steps Observe 2FPW-PDI211, DIESEL FIRE PUMP DISCHARGE STRAINER DP. Cue: Respond that DP = 6 PSID Reports to Control Room that the pump is in service TERMINATING CUE: RECORD STOP TIME,_____ I Standard Grade CJ Observes 2FPW-PDI211, DIESEL FIRE PUMP DISCHARGE STRAINER DP. Sat/Unsat Notifies CR that pump is running Sat/Unsat This J PM is complete when diesel fire pump is in service. NRC 2010 JPM P-1 November 2010 TURNOVER INITIAL A start of the Diesel Fire Pump is required for a CONDITIONS:
hydro of the fire hoses. INITIATING Start Diesel Fire Pump 2FPW-P1 locally at PNL 2FPW-PNL234 lAW N2-0P-43.E.3.0.
NRC 2010 JPM P-1 -7 November 2010 NRC JPM P-2 Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Hydro Pump Boron Injection Revision:
NRC 2010 Task Number: NA Approvals:
NA Exam Security / General Supervisor Date Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
____________(RO/SRO) Trainer/Evaluator:
Evaluation Method: Perform X Simulate Evaluation Location:
X Plant -----Simulator Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop Completion Time: ____ JPM Overall Rating: Pass Fail A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluator's Signature:
____________
_ Date:______ NRC 2010 JPM P-2 -November 2010 Recommended Start Location: (Completion time based on the start location)
RB 289 Outside CRD Maintenance Room Simulator Set-up (if required):
None Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM I CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM J CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions answer any questions.
During task performance, I will identify the steps to be simulated, discuss and provide cues as With the exception of accessing panels, NO plant equipment will be physically Repositioning of devices will be simulated by discussion and acknowledged by my Read Before Each Evaluated ,JPM This evaluated JPM is a measure of your ability to perform this task independently. Control Room Supervisor has determined that a verifier is not available and that concurrent verification will not be provided; therefore, it should not be Read Before Each Training .JPM Performance:
During this Training ..IPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor
/ Evaluator: Critical steps are identified in grading areas as Pass/Fail.
All steps are sequenced critical unless denoted by a u e ". During Evaluated JPM: Self-verification shall be demonstrated. During Training JPM: Self-verification shall be demonstrated. No other verification shall be demonstrated.
NRC 2010 JPM P-2 November 2010
References:
N2-EOP-6, Att. 15, "SLS Hydro Injection" NUREG 1123: 295037 EA1.10 3.7/3.9 Tools and Equipment:
Breakaway tie-wrap for EOP Box Task Standard:
Using hydro pump and hoses staged, establish a f10wpath from SLS tank to the Reactor Vessel complete with an air supply to the pump and commence Boron injection.
Initial Conditions: Boron injection is required. The Standby Liquid Control pumps will not start. Initiating Cues: Commence boron injection with the hydro pump lined up to 2SLS*P1A piping in accordance with EOP-6, Attachment
- 15.
- Performance Steps I Grade Provide repeat back of initiating CJ Proper communications used for SatlUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME Obtain a copy of the reference CJ N2-EOP-6, Att. 15 obtained.
Section SatlUnsat procedure and review/utilize the 3.1 referenced.
correct section. Locate equipment.
EOP Box CJ At EOP box, open box, remove SatlUnsat Adjacent to SLS Tank, Rx Bldg. equipment, and check to ensure EI. 289 specified equipment contained.
Note: For simulation purposes, actual layout of hoses and to pump or plant equipment is not required.
Identification of hose use along with connection points is all that is NRC 2010 JPM P-2 -3 November 2010 I Performance Steps I Grade 4. Remove plug from 2SLS*V42, a At 2SLS*V42, remove test conn. Pass/Fail 2SLS*P1A SUCTION PRESS plug by rotating plug counter TEST CONN. (Rx Bldg, EL 289, clockwise.
SLS Area) Cue: Simulate plug removed. Using 25 ft hard suction hose o At 2SLS*V42, connect 25' black Pass/Fail (black) with brass couplings suction hose by rotating brass AND the appropriate coupling clockwise into the test connections, connect hose to connection.
2SLS*V42. (Rx Bldg, EL 289, SLS Area) Cue: Simulate hose connected. Using 25 ft hard suction hose a At hydro pump, connect 25' black Pass/Fail (black) with brass couplings suction hose by rotating brass AND the appropriate coupling clockwise onto the suction connections, connect hose to connection. (Located on the bottom suction side of Hydro Pump. (Rx of the pump.) Bldg, EL 289, SLS Area) Cue: Simulate hose connected. Remove cap downstream of a At 2SLS*V35, remove pipe cap by Pass/Fail 2SLS*V35, INJECTION rotating cap counter clockwise.
HEADER DRAIN VLV. (Rx Bldg, EL 289, SLS Area) Cue: Simulate cap removed. Using 25 ft Hydro Hose with Hi a AT 2SLS*V35, connect 25' hydro Pass/Fail Press SS Couplings AND the hose by rotating hose coupling appropriate connections, clockwise onto the drain connection.
connect hose to 2SLS*V35. (Rx Bldg, EL 289, SLS Area) Cue: Simulate hose connected.
NRC 2010 JPM P-2 November 201 0 I Performance Steps
- Standard Grade 9. Using 25 ft Hydro Hose with Hi o At hydro pump, connect 25' hydro Pass/Fail Press SS Couplings AND the hose by inserting hose coupling into appropriate connections, pump discharge disconnect.
connect hose to discharge side (Located middle of hydro unit. of Hydro Pump. Downstream of Relief Valve.) (Rx Bldg, EL 289, SLS Area) Cue: Simulate hose connected.
Sat/Unsat SLC SYSTEM ISOL. (Rx Bldg, EL 289, on top of SLS tank) Cue: 2MWS-V24 is closed. NRC 2010 JPM P-2 November 2010 I Performance Steps I Grade Note to Evaluator:
The evaluator should cue the candidate that the power supply breaker is opened. At the evaluators discretion, the evaluator can ask the candidate to locate 2EHS*MCC102 breaker-17D (North Aux Bay EI 240) at the completion of the JPM while transitioning to perform remaining JPMs. 11. Open 2SLS*MOV1A, STORAGE TANK OUTLETVLV, manually as follows: NOTE: A CAT 60 key may be required for entry at 2EHS*MCC102. Place 2EHS*MCC1 02-170, 2SLS*MOV1A, SLCS STORAGE TANK OUTLET MOV to OFF. (Aux Bay North, EL 240) Open 2SLS*MOV1A, manually (Rx Bldg, EL 289, SLS Area)
- Cue: 2EHS*MCC102-17D is OFF, MOV is OPEN. 12. Open 2SLS*V42, 2SLS*P1A SUCTION PRESS TEST CONN. (Rx Bldg, EL 289, SLS Area) Cue: Simulate 2SLS*V42 open. Manually open SLS*MOV1 A Open supply breaker Manually open MOV by rotating handle counter clockwise. At 2SLS*V42, rotate the valve handwheel counter clockwise until the valve is at the full open position.
Note: Procedure transition to Section 3.3 to establish boron injection.
- 13. Open 2SLS*V35, INJECTION HEADER DRAIN VLV. (Rx Bldg, EL 289, SLS Area) Cue: Simulate 2SLS*V35 open. At 2SLS*V35, rotate the valve handwheel counter clockwise until the valve is in the full open position.
Pass/Fail Pass/Fail NRC 2010 JPM P-2 November 2010 I Performance Steps Grade o 14. Open 2SLS*V34, o At 2SLS*V34, rotate the valve Pass/Fail HEADER DRAIN VLV. (Rx Bldg, handwheel counter clockwise until EL 289, SLS Area) the valve is in the full open position.
Cue: Simulate 2SLS*V34 open. 15. Verify open, EITHER o Contact control room and request Pass/Fail (2CEC*PNL601
): valve position for 2SLS*MOV5A1B. 2SLS*MOV5A OR 2SLS*MOV5B:
Cue: Simulate valve open. Using 50 ft Air Hose, connect o At hydro pump, connect 50 foot air Pass/Fail air hose to Hydro Pump VL V. hose fitting onto hydro pump air line (Rx Bldg, EL 289, SLS Area) quick disconnect fitting. Cue: Simulate hose connected.
- 17. Verify closed, Hydro o At hydro pump Manual Air Inlet Isolation
- Air inlet isolation closed. SatlUnsat tension is backed off air Tension is backed off air SatlUnsat regulator spring .. (Rx Bldg, EL regulator spring. 289, SLS Area) Cue: Isolation valves regulator spring backed 18. Using 50 ft Air Hose, connect air o At 2SAS-V529, connect air hose Pass/Fail hose from Hydro Pump to fitting into service air quick V529, SERVICE AIR disconnect fitting. CONNECTION located behind SLS pump. (Rx Bldg, EL 289, SLS Area) Cue: Simulate hose connected.
NRC 2010 JPM P-2 November 2010 I Performance Steps 19. Open 2SAS-V529. (Rx Bldg, EL 289, SLS Area) Simulate V529 open. 20. OPEN Hydro Pump Manual Air Inlet Isolation. (Rx Bldg, EL 289, SLSArea) 21. Start Hydro Pump by tightening spring tension on Hydro Pump Air Regulator. (Rx Bldg, EL 289, SLSArea) Simulate Hydro Pump is running. TERMINATING CUE: RECORD STOP TIME ____ I Standard Grade o o Opens 2SAS-V529 PasslFail Open air line isolation valve by Pass/Fail rotating T -handle counter clockwise to the in-line position. Adjust spring tension on air Pass/Fail regulator.
Hydro pump running with flowpath established from SLS tank to Reactor Vessel. NRC 2010 JPM P-2 -8 November 2010 TURNOVER SHEET INITIAL CONDITIONS:
- Boron injection is required.
- The Standby Liquid Control pumps will not start. INITIATING CUES: "(Operators name), Commence boron injection with the hydro pump lined up to 2SLS*P1A piping in accordance with EOP-6, Attachment 15." NRC 2010 JPIVI P-2 November 2010 NRC JPM Constellation Energy NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Reset an EPA Breaker Revision:
NRC 2010 Task Number: NA Approvals:
'.;,::';?t!:.J.l<
It' NA Exam Security I General Supervis General Supervisor Date Operations Traini g (Designee)
Operations (Designee)
NA Exam Security I Configuration Control Date Performer:
_____________(RO/SRO) Trainer/Evaluator:
___________
_ Evaluation Method: ___Perform __--'-'X'--_Simulate Evaluation Location:
X Plant _____Simulator Expected Completion Time: 10 min. Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop Time: Completion Time: ____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:
Evaluator's Signature:
____________
_ Date:______ NRC 2010 JPM P-3 November 2010 Recommended Start Location: (Completion time based on the start location)
EPA Breaker 2VBS*ACB2A Simulator Set-up (if required):
None Directions to the Instructor/Evaluator:
Prior to performance of this JPM, obtain SM / CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM / CRO permission.
Directions to Operators:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
With the exception of accessing panels, NO plant equipment will be physically manipulated.
Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently.
The Control Room Supervisor has determined that a verifier is not available and that additional/
concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.
Notes to Instructor
/ Evaluator: Critical steps are identified in grading areas as Pass/Fail.
All steps are sequenced critical unless denoted by a "e". During Evaluated JPM: Self-verification shall be demonstrated. During Training JPM: Self-verification shall be demonstrated. No other verification shall be demonstrated.
NRC 2010 JPM P-3 November 2010
References:
N2-S0P-97, FLOWCHART LEG B NUREG KIA 262001 2.1.23 Bank JPM 2102-PJE264C01 Rev 0 Tools and Equipment:
None Task Standard:
Reset and close EPA Breaker 2VBS*ACB2A.
Initial Conditions: The plant is operating at 100% power. EPA Breaker 2VBS*ACB1A is closed. EPA Breaker 2VBS*ACB2A is tripped. EPA Breaker 2VBS*ACB2A Overvoltage target light is LIT. Initiating Cues: Reset EPA Breaker 2VBS*ACB2A in accordance with N2-S0P-97. Provide repeat back of initiating CJ Proper communications used for SatlUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME Obtain a copy of the reference CJ N2-S0P-97 obtained.
SatlUnsat procedure and review/utilize the FLOWCHART RESETTING correct section. VBS/RPM EPA'S (LEG B) is referenced. Are both EPS's tripped? CJ Determines only EPA 2VBS*ACB2A SatlUnsat is tripped and answers as NO. Cue: At ACB2A -Output power lamp is OFF NRC 2010 JPM P-3 -3 November 2010 I Performance Steps At ACB2A attempt to any tripped relay Cue: Overvoltage target indicates Can all relay trip flags be reset? Overvoltage target indicates Note the relays that Bypassing the protective Cue the Candidate, each step Remove the black plastic cover for the relay that cannot be reset. Open the red knife switch 90 degrees. Reset ACB2A by taking the switch from 'TRIP" to "RESET to "ON", Output power lamp is LIT. NRC 2010 P-3 I Standard Grade o Attempts to reset tripped relay flags. Determines overvoltage relay will not reset. SaUUnsat 0 Determines overvoltage relay will not reset and answers NO. SaUUnsat Q Notes the overvoltage relay is tripped. SaUUnsat Q Performs the following:
- Simulate REMOVING the black plastic tamper proof cover for the OVERVOLTAGE TEST SW, located to the right of the Overvoltage Relay, Simulate BYPASSING the protective function by simulating OPENING the "RED" KNIFE SWITCH 90°. Pass/Fail Pass/Fail 0 Simulate a RESET of EPA Breaker 2VBS*ACB2A.
- Simulate placing the OUTPUT breaker (handle) in the RESET position from TRIP.
- AND THEN simulate placing the OUTPUT breaker (handle) in the ON position.
Pass/Fail Pass/Fail November 2010 I Performance Steps Notify Control Room of EPA status. Acknowledge the Candidate.
TERMINATING CUE: RECORD STOP TIME ____ I Grade Notify the Control Room of status of SatlUnsat 2VBS*ACB2A The EPA 2VBS*ACB2A is (RESET and The RED KNIFE SWITCH OVERVOL TAGE is EPA Breaker 2VBS*ACB2A has been "RESET" and is "ON" with the Overvoltage relay function bypassed using the "red" Knife Switch. NRC 2010 JPM P-3 November 2010 TURNOVER SHEET INITIAL CONDITIONS:
- 1. The plant is operating at 100% power. 2. EPA Breaker 2VBS*ACB1A is closed. 3. EPA Breaker 2VBS*ACB2A is tripped. 4. EPA Breaker 2VBS*ACB2A Overvoltage target light is LIT. INITIATING CUES: Reset EPA Breaker 2VBS*ACB2A in accordance with N2-S0P-97.
NRC 2010 JPM P-3 November 2010 NMP SIMULATOR SCENARIO NRC SCENARIO # 1 REV. 0 No. of Pages: 18 ADD WATER TO THE SUPPRESSION POOL WITH CSH/CSH MIN FLOW FAILS/RBCLCW PUMP TRIP/ECCS DIV 1 SPURIOUS INITIATION//STEAM LINE BREAK DRYWELULOSS OF OFF-SITE POWER! EDG II OUTPUT BKR FAILS TO AUTO PREPARER S. Dennis/J. DATE 7/17/10 DATE 7/20/10 GEN OPS MANAGER UNIT 2 .:...:Ne....;Ao....:E=x=a:..:...:m..:....S=e=c=u::..:..r:.:..ity'---
________ DATE ____
CONTROL
________ DATE ____SCENARIO
SUMMARY
Length: 60 minutes The scenario begins with the plant operating at 95% power. The crew will add water to the Suppression Pool using the High Pressure Core Spray System (CSH) per normal operating procedure N2-0P-33, High Pressure Core Spray. The crew must recognize the failure of the CSH Min flow valve and the Tech Spec implications.
Then, EHC oscillations will occur requiring entry to N2-S0P-23 and a power reduction lAW SOP-101D.
Once power is stabilized at a lower level, one of the running RBCLCW pumps will trip and the standby pump will fail to auto start. The standby pump can be manually started by the operators.
After the standby RBCLCW pump is started, ECCS DIV I spuriously initiates.
The crew will take actions lAW the appropriate alarm response and operating procedures.
The SRO will address Technical Specifications.
Then, a Division 1 bus fault occurs requiring a reactor scram due to a loss of Service Water. EOP-RPV is entered. A steam line break will occur in the drywell which requires entry to EOP-RPV and EOP-PC. Once the operators take initial actions and control RPV level and pressure, a loss of Line 6 will occur. The operators must diagnose that the DIV II EDG output breaker failed to close in on its respective bus and take actions lAW SOP-3 to repower the bus (CRITICAL TASK). Additionally, once power is restored, Drywell spray must be initiated to prevent pressure from exceeding the PSP limits (CRITICAL TASK). The scenario ends when RPV level is restored and containment parameters are under control. Major N2-0P-33, N2-S0P-23, N2-S0P-1 01 D, N2-EOP-RPV, PC, SOP-03. NMP2 2010 NRC Scenario # 1 November 2010 Dynamic Mitigation Strategy PC3, High containment pressure, drywell sprays required, maintain safe region PSP, no Slowdown required Termination Reactor is shutdown with RPV Level and Pressure controlled in the directed band and containment parameters improving.
NMP2 2010 NRC Scenario # 1 November 2010 SIMULATOR SET UP IC Number: IC 173, 95% Reactor Power Presets/Function Key Assignments Malfunctions:
- a. CW16C CCP-P1C FAILS TO PRESET b. CS08 CSH*MOV105 VALVE FAILS TRG 1 c. TC03A EHC PRESS REG FAILURE OSCILLATIONS TRG2 d. RBCLCW PUMP TRIP (P1A) TRG4 e. ECCS INADVERTENTLY INITIATES (DIV I) TRG5 f. 4.16KV EMERGENCY BUS FAUL T (101) TRG6 MS04 STEAM LINE RUPTURE IN PRIMARY CONT. 4 minute delay, 1.5%, 8:00 minute ramp TRG7 ED02B LOSS OF OFF-SITE 115KV LINE 6 TRG7 2 minute delay i. DIESEL GENERATOR NUMBER 1 TRIP TRG8 Remotes: a. TC02 PRESS REGULATOR BIAS "A", TRG3 Overrides: OVR-05A2S030D172311 NAP EMER DIESEL GEN 3 OUTPUT BREAKER 103-14, OFF, 2 minute delay TRG7 Annunciators: None Equipment Out of Service None Support Documentation Working copy of N2-0P-33, H.3.0 for use by crew OR plastic sleeve procedure sections to facilitate placekeeping.
An already place-kept copy of F.1.0 is to be made and provided with turnover sheet, since the scenario assumes this section has already been completed. Miscellaneous Event Triggers TRG 1 "csfhpcs>91".
Activates when CSH flow exceeds 650 gpm (91 Ib/sec). TRG 7 "zdrps1d==1".
Activates when the mode switch is taken to shutdown. TRG 15 "hzldgegsa01(2)==1".
Activates to delete malfunction RH13A when Div I EDG starts (red running light is on). Command: DMF RH13A NMP2 2010 NRC Scenario # 1 November 2010 SHIFT TURNOVER INFORMATION SHIFT: N D DATE: PART I: To be performed by the oncoming Operator before assuming the shift. Control Panel Walkdown (all panels) (SM, ASM, STA, CRO, CRE) PART II: To be reviewed by the oncoming Operator before assuming the shift. Shift Supervisor Log (SM, ASM, STA)
- Shift Turnover Checklist (ALL) CRO Log (CRO)
- LCO Status (SM, ASM, STA) Lit Control Room Annunciators
Information/Equipment Status: Reactor Power = 95%
- Loadline => 100% PART III: Remarks/Planned Evolutions:
Raise Suppression Pool Water level to 200 feet using CSH pump per N2-0P-33.
Establish CSH pump flow rate of 2000 to 3000 gpm. N2-0P-33 F.1.0 Standby Condition Status Checks are com plete. PART IV: To be reviewed/accomplished shortly after assuming the shift: Review new Clearances (SM)
- Test Control Annunciators (CRE) Shift Crew Composition (SM/ASM) NAME TITLE NAME I SM CRS STA Other NMP2 2010 NRC Scenario # 1 November 2010 III. PERFORMANCE OBJECTIVES A. Critical Tasks: CT-1.0 -Restore power to DIV II vital bus by closing the DIV II EDG output breaker IAWSOP-03.
CT-2.0 -Initiate Drywell spray when suppression chamber pressure is >10 psig to prevent exceeding the Pressure Suppression Pressure Limit. NMP2 2010 NRC Scenario # 1 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENT 1 & 2 -Suppression Pool Fill Utilizing CSH Pump With CSH*MOV105 Minimum Flow Valve Failure OPERATOR ACTIONS CREW Complete panel walk SRO conducts pre-shift brief. Crew assumes the shift. SRO Directs Suppression Pool fill per OP-33, H.3.0 Enters Tech Spec 3.5.1 (as directed from N2-0P-33)
Condition Band initiates Required Actions B.1 Verify by administrative means RCIC System is OPERABLE when RCIC is required to be OPERABLE. (Completion Time is Immediately)
AND B.2 Restore HPCS System to OPERABLE status. (Completion Time is 14 days) NMP2 2010 NRC Scenario # 1 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENT 1 & 2 (Continued)
After the CSH pump is started, Suppression Pool Level (SPL) will rise from initial/evel of 199.8 feet. It will take about 5 minutes to raise SPL to 200 feet. NMP2 2010 NRC Scenario # 1 OPERATOR ACTIONS BOP/RO Verify Subsection F.1.0, Standby Condition Status Checks is complete. (Actual performance is NOT required because completion was provided in Shift Turnover information.) Verify SM has declared CSH System inoperable.
CAUTIONS DO NOT ALLOW THE CSH PUMP TO OPERATE IN A RUNOUT FLOW CONDITION OF > 7175 GPM OR PUMP DAMAGE MAY OCCUR. MINIMIZE AMOUNT OF TIIVIE CSH IS OPERATING ON MINIMUM FLOW OR PUMP DAMAGE MAY OCCUR. ************************** Start CSH*P1, HPCS PUMP 1. Verify open CSH*MOV105, MINIMUM FLOW BYPASS VLV. Monitor CST AND Suppression Pool Levels. Raise rate of transferring water from CST to Suppression Pool (2000 to 3000 gpm) by performing the following: Throttle open CSH*MOV111 , TEST RETURN TO SUPPRESSION POOL November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENT 1 & 2 CONSOLE OPERATOR:
Verify TRG automatically activates as CSH flow CSOS CSH*MOV105 VALVE FAILS SHUT 2CSH*MOV105 Min Flow Valve does not automatically open as CSH flow is reduced below 634 gpm. ROLE PLAY: Acknowledge request to locally check CSH*MOV1 05 and breaker for any visible damage. Report back 1 minute later that there is no apparent damage to either CSH*MOV1 05 or its breaker. OPERATOR ACTIONS BOP/RO WHEN CSH System Flow is > 634 gpm, verify closed CSH*MOV105, MINIMUM FLOW BYPASS VLV. WHEN desired Suppression Pool Level is reached, close CSH*MOV111, TEST RETURN TO SUPPRESSION POOL. WHEN HPCS SYSTEM FLOW is less than 634 GPM, verify open CSH*MOV105, MINIMUM FLOW BYPASS VLV. Stop CSH*P1, HPCS PUMP 1. Verify closed CSH*MOV105, MINIMUM FLOW BYPASS VLV. Notify SM that 2CSH*MOV111 is NOT closed. Restore CST Level, as required, per N2-0P-4. SRO May direct plaCing HPCS in PTL Recognizes that TS 3.5.1 must not be exited TS 3.5.1.B.2 Restores HPCS System to OPERABLE status. (Completion Time is 14 days) May notify WEC, Ops Management, and FIN Team May dispatch PO to check status of CSH*MOV105 and breaker. Reportable to the NRC within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> NMP2 2010 NRC Scenario # 1 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENT 3 -EHC Pressure Regulator Failure CONSOLE OPERATOR:
When directed by Lead Evaluator, activate malfunction using TRG 2. TC03A, EHC PRESS REG FAILURE OSCILLATIONS Reactor power oscillates with EHC regulator Expected 851148, 8 PRESS REGULA TOR IN intermittently alarms as "8" regulator attempts take ROLE PLAY: Call the Control Room as operator sent to relay room and report that you are ready to shift from "A" Pressure Regulator to "8" Pressure Regulator When requested state that N2-S0P-23, Detail "A" steps 1, 2, and 3 are complete.
CONSOLE OPERATOR:
When directed by Control Room to shift regulators, activate remote using TRG 3. TC02 PRESS REGULATOR BIAS" A", 8.0 ROLE PLAY: When requested state that "8" Regulator set at 5.90" and N2-S0P-23, Detail "A" step 4 complete.
Reactor pressure lowers by 5 to 10 psig. OPERATOR ACTIONS CREW Identifies power and pressure oscillations Determines oscillations being caused by EHC regulator oscillations. Responds to Annunciator "8" Press Regulator In Control Reports oscillations to SRO. SRO Directs entry into N2-S0P-23 Directs power reduced to 85%, lAW N2-S0P-101 D. Directs a licensed operator to Relay Room to EHC panel (2CEC-PNL843) (Key 16). Directs attempt to stabilize pressure and Shift to the "8" Press. Reg. Contacts RE to assess thermal limits. RO When directed, lowers power to 85% (or value directed by SRO). Lowers power with recirculation flow in accordance with N2-S0P-1 01 D Verbalizes actions and receives confirmation. Monitors Nuclear Instruments as power is reduced. May check Power/Flow Map after power reduction.
BOP Contacts licensed operator in relay room to shift to "8" EHC pressure regulator.
NMP2 2010 NRC Scenario # 1 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE OPERATOR ACTIONS EVENT 3 (Continued)
- Reports "8" regulator is in control by observing annunciator 851148 and "8" REG in control light illuminated and P851. NMP2 2010 NRC Scenario # 1 November 2010 INSTRUCTOR ACTIONS/ PLANT RESPONSE EVENT 4 -RBCLCW Pump P1A trips. Standby Pump Fails to Auto-Start CONSOLE OPERATOR:
When directed by Lead Evaluator, activate malfunction using TRG 4. CW02A RBCLCW PUMP TRIP (P1A) CW16C CCP-P1C FAILS AUTOSTART ROLE PLAY: If field operator and/or electrical is dispatched to check pump and breaker, report an acrid smell at the pump motor. NMP2 2010 NRC Scenario # 1 OPERATOR ACTIONS CREW Responds to RBCLCW Pump P1A trip. Annunciator:
- 601246, RBCLC SYS TROUBLE Recognizes the CCP-P1 C pump fails to auto-start.
Annunciator: 601252, RBCLC PUMP 1A11B/1C AUTO TRIP/FAIL TO START SRO Directs ROs to respond to annunciators and enter N2-S0P-13 May contact the Work Execution Center (WEC) for maintenance followup. May send maintenance and field operator out to investigate pump and breaker May direct placing the control switch for CCP-P1A in PTL. BOP Recognizes failure of standby RBCLCW pump CCP-P1 C to auto start. References annunciator response for pump trip. Starts the standby pump CCP-P1 C. May place control switch for CCP-P1A in PTL RO Monitors reactor power, pressure and level. May announce on plant page entry into N2-S0P-13.
November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENT 5 -ECCS DIV 1 Inadvertently Initiates CONSOLE OPERATOR:
When directed by Lead Evaluator, activate malfunction using TRG 5. RH13A ECCS INADVERTENTLY INITIATES DIV RHS*P1 A auto starts CSL*P1 auto starts Div I lOG auto starts CONSOLE OPERATOR:
Verify malfunction RH 13A is automatically deleted by auto trigger TRG 15, when Div I EDG starts. ROLE PLAY: Call in as I&C 30 seconds after initiation and state that you bumped into a transmitter in the RB and that there is no damage to the transmitter.
If asked what transmitter(s) were bumped state that you will get back to him. Also, if requested, state that there are no trips and trip units indicate normal. CUE: If necessary, direct SRO to secure ECCS pumps if not required.
ROLE PLAY: If requested, perform EG1 operating checks. CONSOLE OPERATOR:
After ECCS pumps are shutdown and when directed by the Lead Evaluator activate malfunction using TRG 8. DG02A, DIESEL GENERATOR NUMBER 1 TRIP OPERATOR ACTIONS CREW Recognize initiation of Div I ECCS Systems and report same to CRS Examine panels for ECCS initiation conditions SRO Determines ECCS initiation conditions do not exist. May direct Div I ECCS reset May direct securing RHS & CS pumps Refers to Tech Specs 3.8.1 CONDITION B, REO. ACTION B.1 and B.2 and B.3.1 or .2 and B.4 restore DG to operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Informs plant management of event and TS shutdown LCO entry May notify WEC, Ops Management, and FIN Team RO May perform standby checks. Monitors power, pressure, and level. BOP As directed, secures RHS & CS pumps. As directed, attempts to reset Div I ECCS per N2-0P-31 Section G.2.0, and N2-0P-32 Section F.2. NMP2 2010 NRC Scenario # 1 November 2010 INSTRUCTOR PLANT RESPONSE OPERATOR EVENT 6 -DIV1 Bus 101 CREW Responds to Annunciator for Bus 101 CONSOLE OPERATOR:
When directed by Lead Evaluator (after ECCS pumps are activate malfunction using TRG 6. ED05A 4.16KV EMERGENCY BUS FAULT (101)
- Directs entry into N2-SOP-03, Loss of AC power 2ENS*SWG101 de-energizes.
Service Water Div /I
- Directs entry into N2-S0P-11, Loss or Non-Essential MOVs close and cannot be re-Degraded SW system opened. A manual scram is required by N2-S0P-* Directs Reactor Scram due to loss of 11 Loss or Degraded Service water Service Water May enter N2-S0P-29, Sudden Reduction In Core Flow after scram Enters EOP-RPV on Reactor scram Directs entry into N2-SOP-1 01 C RO/BOP As directed, enters N2-S0P-29, Sudden Reduction I n Core Flow As directed, places reactor mode switch in shutdown and provides scram report. Enters N2-S0P-03 As time permits, trips the turbine and recirc pumps. NMP2 2010 NRC Scenario # 1 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 7,8 & 9 Loss of Line 6, Failure of Div II EDG output breaker to auto close. Steam Line break in Drywell CONSOLE OPERATOR:
Ensure TRG 7 activates the following when the mode switch was placed in shutdown. ED02B LOSS OF OFF-SITE 115KV LINE 6,2 minute delay OVR-05A2S030D172311 NAP EMER DIESEL GEN 3 OUTPUT BREAKER 14, OFF, 2 minute delay MS04 STEAM LINE RUPTURE IN PRIMARY CONTAINMENT, 4 minute delay, 1.5%, 8:00 minute ramp On a loss of line 6 Div /I EDG automatically starts however the EDG output breaker 103-14 fails to automatically close due to component malfunction.
2ENS*SWG102 and Div 1/ safety related loads remain de-energized until manual operator action to close 103-14 is taken. CREW Recognizes and reports Loss of AC Power. Recognizes SOP and EOP entry Conditions.
SRO Directs entry into N2-S0P-3 for Loss ofAC Directs power restored to DIV II Bus by closing the DIV II EDG output breaker lAW SOP-03 (CT -1.0) Updates crew on EOP-RPV entry. Directs a RPV water level band 200 inches. Directs a RPV pressure band with a target of 800-1000 psig. BOP As directed, enters N2-S0P-3. Restores power to Div II Bus by closing Div II EDG output breaker lAW N2-S0P-3, Detail "A", instructions: Checks listed annunciators Place SYNCHRONIZE TO BUS 103 switch to ON. Closes the EDG output breaker for the DIV II Bus (CT -1.0) RO As directed, maintains RPV level 200 inches. Continues actions lAW N2-S0P-101C NMP2 2010 NRC Scenario # 1 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENT 7, 8 & 9 (Continued)
OPERATOR ACTIONS CREW Responds to rising Drywell Pressure and Temperature SRO Enters EOP-PC when Drywell Pressure exceeds 1.68 psig and Re-enters RPVon High DW pressure. Directs Suppression Chamber Spray lAW EOP-6 Att. 22. when DIV II bus power is restored May direct restart of DW Cooling lAW EOP-6 Att. 24 when DIV II bus power is restored When Suppression Chamber Pressure exceeds 10 psig then continues in PCP leg and directs Orywell Spray. (CT-2.0) Directs ECCS injection prevented before RPV pressure reaches 400 psig Directs a RPV pressure band with a target of 800-1000 psig. May direct clOSing of MSIVs as reactor depressurizes RO Takes action to maintain RPV water level within the directed band of 160 200 inches with FW and Condensate.
NMP2 2010 NRC Scenario # 1 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 7,8 & 9 (Continued)
BOP/RO Takes action to maintain RPV pressure within the directed band. As directed, closes MSIVs to control cooldown. When directed, restores drywell cooling lAW EOP-6 Att. 24: Determines DW temperature
<250°F Overrides drywell unit cooler water LOCA isolation interlocks with keylock switches. Verifies closed drywell unit cooler inlet valves. Restores CCP to drywell by opening containment isolation valves. Restores CCP to drywell unit coolers by opening drywell unit cooler inlet valves. Overrides drywell unit cooler fan interlocks with keylock switches. Restarts drywell unit cooler fans. Places Suppression Chamber Spray in service lAW EOP-6 Att. 22: Opens SWP*MOV90B, RHR H/X SVCE WTR INLET VLV. May be delayed until after sprays are in service. Verify closed RHS*MOV24B, LPCI IN..IECTION VLV Verify running RHS*P1 B PMP Open RHS*MOV33B, OUTLET TO SUPPR POOL SPRAY NMP2 2010 NRC Scenario # 1 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 7,8 & 9 BOP/RO Verify gpm on SUPPR SPRAY HEADER FLOW (2RHS*F/64B) Places RHR in Drywell Spray prior to exceeding the Pressure Suppression pressure limit as follows (CT -2.0): Trips/verifies tripped RCS Pumps. Trips Drywell Unit Coolers. Verifies an initiation signal present. Verifies open SWP*MOV90B, HEAT EXCHANGER 1B SVCE WTR INLET VLV. May be delayed until after sprays are in service. Verifies closed RHS*MOV24B, LPCI B INJECTION VLV Verifies RHS*P1 B running. Verifies closed RHS*FV38B, RETURN TO SUPPR POOL COOLING. Verifies open RHS*MOV4B, PMP 1 B MINIMUM FLOW VLV. Opens RHS*MOV15B, OUTLET TO DRYWELL SPRAY. Opens RHS*MOV25B, OUTLET TO DRYWELL SPRAY. Verifies RHS*MOV48, PIVIP 1 B MINIMUM FLOW VLV, closes. Verifies approximately 7450 gpm on DRYWELL SPRAY HEADER FLOW (2RHS*FI638). Closes RHS*MOV88 after 10 minute time delay from receipt of initiation signal. NMP2 2010 NRC Scenario # 1 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE Event 7,8 & 9 (Continued)
Termination Cue: Containment parameters improving and RPV level 160 to 200 inches. OPERATOR ACTIONS Contacts RP to start SWP*RE238. Throttles open SWP*MOV338 to establish flow not to exceed 7400 gpm -may be required to start 5 th service water pump (post LOCA). RO/BOP Monitors for improving containment parameters. Controls RPV level 160 to 200 inches. NMP2 2010 NRC Scenario # 1 November 2010 NMP SIMULATOR NRC 2010 Scenario #2 REV. 0 No. of Pages: PERFORM MANUAL SCRAM TEST CHANNELAlHPCS SPURIOUS INJECTION/CRD PUMP TRIP/FEEDWATER HEATER TUBE LEAKlFW CTRLR MALFUNCTIOI\I/RECIRC PUMP HI VI BS/ATWS/SLC AUTO INITIATION FAILURE PREPARER S. Dennis/J.
Reid DATE ':"':"':'-'-'---=-
__ VALIDATED DATE ':"':"==-:'-=-
__ GEN SUPERVISOR OPS TRAINING -Z OPERATIONS DATE _____MANAGER NA Exam Security CONFIGURATION CONTROL NA Exam Security DATE SCENARIO
SUMMARY
Length: 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Initial Power Level: 100%, above the 100% Rod Line The scenario begins at 100% reactor power. The crew will perform surveillance test W002 for the "A" Channel only. An RPS indication will fail requiring TS to be addressed.
Following Tech Spec review an inadvertent start of HPCS with injection into the vessel occurs. This requires the crew verify drywell pressure and reactor water level in normal band and place HPCS in P-T-L. Then a CRD will trip requiring actions per the abnormal procedure.
After the pump trip has been addressed, a high pressure feedwater heater tube leak occurs coincident with a feedwater master controller failure. The crew enters and executes the actions of N2-S0P-8 and lowers power to <3467 MWt due to the partial loss of feedwater heating and resulting unplanned power change. The feedwater malfunction requires feedwater to be placed in manual per N2-S0P-6.
One Recirc Pump begins to experience hi vibration and the pump must be removed from service. The SRO will address TS for loop mismatch and then the other recirc pump will trip requiring a reactor scram. When the reactor is manually scrammed all control rods will not fully insert. EOPs RPV, EOP-Failure-To-Scram will be entered. Given a failure of the reactor to SCRAM, with power above 4% or unknown, the crew will terminate and prevent all injection except boron, CRD and RCIC. (CRITICAL TASK). Given a failure of the reactor to scram, the crew will lower power by inserting control rods or injecting boron in accordance with EOP-C5 (Failure to Scram) (CRITICAL TASK). NMP2 2010 NRC Scenario # 2 November 2010 Major Procedures Exercised:
EOP-RPV, PC, C-5, C-4. N2-S0P-6, N2-S0P-8, N2-S0P-30, N2-S0P-1 01 D and N2-S0P-1 01 C. Dynamic Mitigation Strategy AT1, High power ATWS, heat addition to suppression pool requires entry into level power control, RPV level controlled below feedwater spargers, RPV Slowdown not required Termination All rods are fully inserted and RPV level is restored to the normal band. NMP2 2010 NRC Scenario # 2 November 2010 SIMULATOR SET UP A. IC Number: IC-21 or equivalent. Presets/Function Key Assignments Malfunctions: RD17A,B,C,D,E, PARTIAL INSERTION OF RODS, 48 PRESET RD17H,I,J,K,L,M, PARTIAL INSERTION OF RODS, 48 PRESET RP08A, RRCS 98 SECOND TIMER FAILURE DIV I, TRUE PRESET RP08B, RRCS 98 SECOND TIMER FAILURE DIV II, TRUE PRESET CS01B, HPCS INADVERTENT INITIATION K11 TRG2 (REACTOR LEVEL 2), TRUE RD12A, CRD FEED PUMP TRIP (P1A), TRUE TRG3 MS10A, LOSS OF EXT STEAM TO FW HTR (E6A), TRUE TRG4 FW15, FEEDWATER MASTER CONTROLLER TRG4 FAILURE AS -IS, TRUE RR46A, RCS PMP1A VIBRATION (MILS), TRUE TRG5 RR10B, RR PUMP BKR TRIP (4B), TRUE TRG7 RP02, RPS FAILURE TO SCRAM -AUTOMATIC, TRUE TRG 13 RP14A, RRCS ARI FAILUREIDEFEATED (DIV I), TRUE TRG14 RP14B, RRCS ARI FAILURE/DEFEATED (DIV II), TRUE TRG14 Remotes: a. CS 12, CSH*MOV107 600 VOLT BKR STATUS, TRG10 b. CS06. MANUAL OPS CSH*MOV107 (0-1.0), TRG10 c. MS06A, DEFEAT LEVEL 1 ISOL OF MSIV (K148A). DEFEATED TRG 11 d. MS06B, DEFEAT LEVEL 1 ISOL OF MSIV (K148B). DEFEATED TRG 11 e. MS06C. DEFEAT LEVEL 1 ISOL OF MSIV (K148C), DEFEATED TRG 11 MS06D, DEFEAT LEVEL 1 ISOL OF MSIV (K148D). DEFEATED TRG 11 RC10. DEFEAT RCIC/MT TRIP INTLK (EOP-6 ATT2), DEFEATED TRG12 OG03, OFFGAS HI RADIATION ISOL DEFEATED, DEFEATED TRG15 Overrides:
- a. 03A 1 S30D14234, POS_1 REACTOR MAN SCRAM PB SWA 1, ON TRG 1 Annunciators:
- 8. AN603409, RPS B DISCH VOLUME HIGH LEVEL TRIP, OFF TRG16 b. AN6031 09, RPS A DISCH VOLUME HIGH LEVEL TRIP. OFF TRG16 NMP2 2010 NRC Scenario # 2 November 2010 Equipment Out of Service None Support Documentation N2-0SP-RPS-W002, Signed off thru step 8.1 Miscellaneous Event Triggers TRG 1 "zdrps3ar(1)==1".
Activates when Reactor manual scram switch for channel A1 is ARMED. This overrides the switch to ARMED, simulating switch failure. NMP2 2010 NRC Scenario # 2 November 2010 II. SHIFT TURNOVER INFORMATION OFF GOING SHIFT: N ID DATE: 1 PART I: To be performed by the oncoming Operator before assuming the shift. Control Panel Walkdown (all panels) (SM, CRS, STA, CRO, CRE) PART II: To be reviewed by the oncoming Operator before assuming the shift. Shift Supervisor log (SM, CRS, STA)
- Shift Turnover Checklist (All) CRO log (CRO)
- lCO Status (SM, CRS, STA) Lit Control Room Annunciators
- Computer Alarm Summary (CRO) (SM, CRS, STA, CRO, CRE) Evolutions/General Information/Equipment Status: Reactor Power =1 00%
- load line =>100% N2-0SP-RPS-W002, MANUAL SCRAM CHANNEL FUNCTIONAL TEST is in progress.
PART III: Remarks/Planned Evolutions:
- Perform N2-0SP-RPS-W002, MANUAL SCRAM CHANNEL FUNCTIONAL TEST perform PART IV: To be reviewed/accomplished shortly after assuming the shift: Review new Clearances (SM)
- Test Control Annunciators (CRE) Shift Crew Composition (SM/CRS) TITLE NAME I NAME SRO ATCRO BOPRO I NMP2 2010 Scenario #2 November 2010 III. PERFORMANCE OBJECTIVES A. Critical Tasks: CT*1.0 -Given a failure of the reactor to SCRAM, with power above 4% or unknown, the crew will terminate and prevent all injection except boron, CRD and RCIC. CT-2.0 -Given a failure of the reactor to scram, the crew will lower power by inserting control rods or injecting boron in accordance with EOP-C5 (Failure to Scram) NMP2 2010 Scenario #2 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENT 1 -Perform N2-0SP-RPS-W002, MANUAL SCRAM CHANNEL FUNCTIONAL TEST, section 8.2 only CONSOLE OPERATOR:
Verify TRIGGER 1 automatically activates, when REACTOR SCRAM Ai pushbutton collar is ARMED OVR-03A1S30DI4234, POS_1 REACTOR MAN SCRAM PB SWA1, ON Annunciator 603113, RPS A MANUAL SCRAM SWITCH, will not extinguish later in sUNeillance step 8.2. 12 due to switch failure. OPERATOR ACTIONS CREW Crew conducts a pre-brief and walks down the panels. SRO Direct performance of W002 section 8.2 only When informed by operator that alarm at step 8.2.12 did not clear, references TS 3.3.1.1 -Ai and declares "A" RPS Inop -12 hours to place the channel in trip RO Performs N2-0SP-RPS-W002 section 8.2 only as follows: 8.2 Manual SCRAM Channel "A" Test NOTE: All indicators AND controls for this test are located on panel 2CEC*PNL603 unless otherwise specified. 8.2.1 Verify that there is NO half scram on the "8" side. 8.2.2 Notify CRO that a half scram on "A" side will be generated. 8.2.3 Arm the REACTOR SCRAM Ai pushbutton. 8.2.4 Verify annunciator 603113, RPS A MANUAL SCRAM SWITCH ARMED, has alarmed. 8.2.5 Depress AND hold for 2 to 3 seconds the REACTOR SCRAM Ai pushbutton.
NMP2 2010 Scenario #2 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 1 (Continued)
- 8.2.6 Verify the following annunciators have alarmed: ANNUNCIATOR DESCRIPTION
- 603110 RPS A AUTO TRIP
- 603111 RPS A MANUAL TRIP
- 8.2.7 Verify the status of the following CUE: Indicating lights for REACTOR SCRAM TRIP indicating lights: LOGIC A 1 on 2CEC"PNL609 is extinguished.
- REACTOR SCRAM TRIP LOGIC A 1 (Panel 609 is not modeled in simulator) on 2CEC"PNL609 is extinguished.
- PILOT SCRAM VALVE SOLENOIDS A,C,E, AND G are extinguished.
- 8.2.8 Reset the REACTOR SCRAM RESET LOGIC A.
- 8.2.9 Verify the following occurred for the tripped condition:
- a. Verify the following Plant Computer Printouts:
- RPSUC01 RPS A MANUAL TRIP TRIPPED
- RPSUC03 RPS A AUTO TRIP TRIPPED b. Verify the following Sequence Of Events Printouts:
- RPSUC01 RPS A MANUAL TRIP TRIPPED
- RPSUC03 RPS A AUTO TRIP TRIPPED
- 8.2.10 Verify the following alarms AND indications for the reset condition:
- a. Verify the following annunciators have extinguished:
- 603110 RPS A AUTO TRIP *603111 RPS A MANUAL TRIP NMP2 2010 Scenario #2 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENT 1 (Continued)
CUE: REACTOR SCRAM TRIP LOGIC A1 on 2CEC*PI\IL609 is illuminated.
OPERATOR ACTIONS b. Verify the following Plant Computer Printouts:
- RPSUC01 RPS A MANUAL TRIP ALMCLR
- RPSUC03 RPS A AUTO TRIP ALMCLR c. Verify the following Sequence Of Events Printouts:
- RPSUC01 RPS A MANUAL TRIP ALMCLR
- RPSUC03 RPS A AUTO TRIP ALMCLR d. Verify the status of the following indicating lights:
- REACTOR SCRAM TRIP LOGIC A1 on 2CEC*PNL609 is illuminated.
- PILOT SCRAM VALVE SOLENOIDS A,C,E, AND G are illuminated. 8.2.11 Disarm the REACTOR SCRAM A1 pushbutton. 8.2.12 Verify annunciator 603113, RPS A MANUAL SCRAM SWITCH ARMED, is extinguished. Reports to CRS that annunciator 603113, RPS A MANUAL SCRAM SWITCH ARIVIED, remains illuminated NMP2 2010 Scenario #2 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENT 2 -Inadvertent Initiation and Injection of HPCS CONSOLE OPERATOR:
When directed by Lead Evaluator, activate malfunction by depressing TRIGGER 2: CS01 B, HPCS Inadvertent Initiation K11 (Reactor level 2) HPCS automatically starts and injects into the RPV. Reactor pressure lowers and FWS-L V1 0 controllers respond by closing down to maintain RPV level in normal band. The Division 11/ diesel generator starts and runs unloaded in response to HPCS start signal. The following annunciators alarm: 852311 EDG 2 TROUBLE 852317 EDG2 RUNNING 603139 REACTOR WATER NMP2 2010 Scenario OPERATOR ACTIONS CREW Recognizes and reports start of HPCS SRO Repeats back start of HPCS and EGS*EG2. Directs RO/BOP to verify drywell pressure and reactor water level in normal band. Acknowledges report that RPV level and drywell pressure are normal. May direct power monitoring using APRMs Directs BOP to place HPCS control switch in P-T-L. Refers to Tech. Spec. 3.5.1 and performs required actions. Enters condition B and takes required action B.1 to verify by administrative means that RCIC is OPERABLE immediately and action B.2 to restore HPCS to OPERABLE status within 14 days. May identify 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reportable condition requirement of 1 OCFR50.72.b.3.v and 50.73.a.2.v.
for unplanned inoperability. Enters TS 3.6.1.3 for HPCS CSH*MOV107
-Action C.1 -72 hours to verify line is isolated Notifies Operations and Plant management. May contact WEC for assistance and work planning.
November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENT 2 (Continued)
ROLE PLAY: If requested for HPCS trip unit indication, report all trip units are indicating normal and untripped.
FWLC system will respond and no operator actions are expected to occur other than confirming proper FWLC response.
ROLE PLAY: If Plant Operator contacted to manually close CSH*MOV1 07 wait 1 minute then activate TRG 10. eS12, eSH*MOV107 600 VOLT BKR STATUS, OPEN
- eS06, MANUAL OPS CSH*MOV107 (0-1.0), 0 Report back in 5 minutes that CSH*MOV107 is closed. OPERATOR ACTIONS RO Identifies and reports annunciators to SRO. I mplements the actions of ARP 603139 Confirms FWLC system is responding properly to the rise in water level. BOP Recognizes and reports HPCS injecting. Verifies drywell pressure and reactor water level are normal. Places HPCS control switch in P-T-L. Reviews ARPs 852317,601706 and 851311 and 852319. Dispatch an operator to 2CES*IPNL413, 2EGS*EG2 GENERATOR SWITCH BOARD. IF a local alarm is energized, refer to the applicable Alarm Response Procedure.
These are alarm 852317 (OG Panel) actions: Confirm that 2EGS*EG2 is required to be running. IF 2EGS*EG2 is required to be running, operate the diesel generator in accordance with OP-100B, HPCS DIESEL GENERATOR.
NMP2 2010 Scenario #2 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENT 2 (Continued)
EXAMINER NOTE: Crew is likely to have 2EGS*EG2 remain running until additional resources can be obtained.
When HPCS is placed in P-T-L the following occurs: 852311 -EDG 2 TROUBLE clears 603139 -REACTOR WA TER LEVEL HIGH/LOW clears 601706 -HPCS SYSTEM INOPERABLE 852319 -EDG 2 DC CONT POWER FAILURE AMBER Pump Motor BRKR #2 system status light illuminates.
OPERATOR ACTIONS IF 2EGS*EG2 is NOT required to be running, shutdown the diesel generator per N2-0P-100B.
Step G.5.6 by depressing Emergency Stop PB.
- AFTER 2EGS*EG2 is shutdown, confirm the alarm clears. These are alarm 852319 (DG Panel) actions: Using the Process Computer, determine which computer point(s) brought in the alarm. Notify the SM to evaluate the effect on the operability of 2EGS*EG2, DIVISION 3 diesel generator AND 2ENS*SWG102, Division 3 Emergency Switchgear. Dispatch an operator to 2ENS*SWG102 to check for energized amber circuit monitoring lights. Refer to the applicable INOP STATUS LIGHT for response.
NMP2 2010 Scenario #2 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENT 3 -CRD Pump 1A CONSOLE OPERATOR:
When directed by Evaluator, activate malfunction by TRIGGER RD12A, CRD FEED PUMP TRIP The following Annunciators alarm: 603311 -CRD CHARGING PRESSURE 603308 -CRD PUMP 1A11 B AUTO TRIP 603313 -CRD 1A11 B MOTOR ELEC FAULT 603446 -CRD PUMP DISCH HEADER PRESSURE LOW OPERATOR ACTIONS CREW Recognizes and responds to Pump trip in accordance with Responds to Annunciators: 603311 -CRD CHARGII\JG wrR PRESSURE LOW 603308 -CRD PUMP 1A11 B AUTO TRIP 603313 -CRD 1 Al1 B MOTOR ELEC FAULT 603446 -CRD PUMP DISCH HEADER PRESSURE LOW SRO Directs entry and actions in accordance with N2-S0P-30, Control Rod Drive Failures RO Enters N2-S0P-30, Control Rod Drive Failures, to transfer to standby CRD Pump Shifts Flow Controller to Manual Closes FCV to minimum Starts the "S" CRD pump Adjusts FCV to approx. 63 gpm Places Flow Controller in Auto NMP2 2010 Scenario #2 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENT 4 & 5 Extraction Steam Isolation and Feedwater Master Controller Failure. CONSOLE OPERATOR:
When directed by Lead Evaluator, activate malfunctions by depressing TRIGGER 4: MS10A Loss of Extraction Steam to FWH E6A FW15, Feedwater Master Controller Failure As -Is The following Annunciator alarms: 603139 REACTOR WATER LEVEL HIGH/LOW Reactor water level high alarm due to reduced steam flow and failed feedwater controller Core thermal power and APRM power rises. NMP2 2010 Scenario OPERATOR ACTIONS CREW Recognizes and responds to indications of extraction steam isolation and FW controller failure. Thermal power rise RPV water level changing SRO Acknowledges report of Feedwater Master Controller Failure. Directs entry into N2-S0P-6, Feedwater Failures. Assigns reactor water level band. Acknowledges report of power rise. Directs entry into N2-S0P-08 Unplanned Power Changes due to loss of feedwater heating. Directs power reduced to maintain <3467 MWTH in accordance with SOP-1 01 D, Rapid Power Reduction, using Recirc Flow and/or Cram Rods. Notifies plant management and RE. May contact WEC SRO for assistance and work planning.
RO Reports alarms to CRS Recognizes and reports megawatts electric change, thermal power rise and rise in APRM power. Maintains
<3467MWTH in accordance with N2-S0P-1 01 D as directed by CRS. November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENT 4 & 5 (Continued)
ROLE PLAY: IF asked as Operations Management for guidance on any further power reductions or actions for feedwater heaters, inform SRO that further guidance will be provided later. NOTE: When the crew has stabilized reactor power <3467 MWt and FWLC is in manual with RPV level in the normal band then proceed to next event. OPERATOR ACTIONS Monitors and reports RPV water level and identifies that during the downpower the Feedwater Master Controller is not responding. As directed, enters N2-S0P-6, Feedwater Failures, due to FWLC not responding to RPV level changes. Places 2FWS-HIC1600 (Feedwater Master Controller) in manual. Controls water level in manual in assigned band. BOP Enters and performs the actions of N2-S0P-8 for unplanned power changes as directed by the CRS. Monitors Main steam line and offgas radiation monitors for evidence of fuel failure. Verifies feedwater temperatures are within limits of figure 1 of N2-S0P-8. Verifies 2CNM-AOV1 01, LOW PRESS HTR STRING BYPASS VLV, is closed. Verify that 2ESS-MOV3A, 6TH POINT HEATER A EXTRACTION STM ISOL VLV, for the affected Heater is closed. NMP2 2010 Scenario #2 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENTS 6, 7 & 8 -Recirc Pump High ATWS, SLC Auto Initiation CONSOLE OPERATOR:_When directed by Evaluator, activate malfunction by TRIGGER RR46A, RCS PMP1A VIBRATION ROLE PLAY: Report as Plant Operator after minutes that vibration on the motor frame and is 6 CONSOLE IF reactor scrams during the transient on the Recirc Pump trip then DO NOT activate Trigger 7 for "8" Recirc Pump Trip IF reactor remains at power then when directed by Lead Evaluator, activate malfunction by depressing TRIGGER 7: RR10B RR PUMP BKR TRIP (4B) NOTE: A TWS and SLC auto initiation failures are PRESET ROLE PLAY: One minute after the request, report to control room that EOP-6, Att.2 and 10 actions are complete. TRIGGER 11, MSIV LOW WATER LEVEL ISOLATION DEFEATED (EOP-6 ATT 10) TRIGGER 12, DEFEAT RCIC/MT TRIP INTLK (EOP-6 ATT 2) OPERATOR ACTIONS CREW Responds to Annunciator 602219 "Recirc 1A118 vibration Hi" SRO Directs sending field operator to Panel 2 RCS-PNL 100 to investigate vibration alarm Directs Entry to SOP-29.1, Reactor Recirculation Pump Seal Failure When informed that vibration is >6 mils directs tripping the Recirc Pump Enters SOP-29, Sudden Reduction in Core Flow When U8" Recirc Pump trips OR reactor scrams on level directs entry into EOP-RPV When informed of A TWS enters C5, Failure to Scram. Directs Inhibiting ADS. Directs RRCS initiation. May direct Preventing Main Turbine Trip from RCIC injection in accordance with EOP-6 Att. 2. May direct bypassing the MSIV Low Water Level Isolation in accordance with EOP-6 Att.1 0 Directs RPV Level be Terminated and Prevented with Reactor Power >4% (Critical Task 1.0) NMP2 2010 Scenario #2 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENTS 6, 7 & 8 (Continued)
CONSOLE OPERATOR: When RPS is reset and ARI is defeated delete RD 17 malfunctions as required, to allow initial Control Rod Insertion.
ALL control rods may be inserted on the second scram attempt (All RD17 malfunctions deleted). IF time compression is desired to drain SDV then if directed activate TRIGGER 16 to override annunciators OFF to simulate SDV draining below the scram setpoint. AN603409, RPS B DISCH VOLUME HIGH LEVEL TRIP, OFF AN603109, RPS A DISCH VOLUME HIGH LEVEL TRIP, OFF ROLE PLAY: Acknowledge request to implement EOP-6 Att.14 Sections 3.3 and 3.5. Report back 2 to 3 minutes later that field actions have been implemented TRIGGER 13, RPS DEFEATED TRIGGER 14, RRCS DIV. 1 and NMP2 2010 Scenario OPERATOR ACTIONS Directs Pressure band of 800 to 1000 psig. Directs control rod insertion using EOP-6 Att.14 and/or SLC system to lower reactor power (Critical Task 2.0) Directs SLC initiation when informed of auto initiation failure. When informed that RPV level has lowered to 100 inches, directs a new RPV level band between -39 and +100 inches (corrected if on fuel zone) RO/BOP Trips "A" Recirc Pump when directed. As directed, places Mode Switch to Shutdown. Inhibits ADS. Prevents HPCS Injection. If directed, Prevents Main Turbine Trip from RCIC injection in accordance with EOP-6 Att. 2. As directed, bypasses the MSIV Low Water Level Isolation in accordance with EOP-6 Att.1 O. November 2010 INSTRUCTOR PLANT RESPONSE OPERATOR EVENTS 6, 7 & 8 (Continued)
EXAMINER NOTE: SLC fails to auto-inject, the operators must manually inject SLC Termination Criteria:
All control rods inserted and RPV level is restored to normal band. Terminates and Prevents as follows: 603 Panel: Places FW Master controller to full closed, Verifies all LV-10 positions are at "0", LV-55s at "0", LV-137s at "0" Panel: Places CSL *P1 and 2RHS*P1 C in Pull-To-Lock Arms and Depresses LPCI Div I and II Manual Initiation push buttons, then closes and overrides LPCllnjection Valves (Critical Task 1.0) As directed, maintains RPV level band using Condensate/Feedwater. Recognizes failure of SLC to inject and manually starts and injects with SLC Implements EOP-6 Att.14 to allow rod insertion.
Once informed of implementation, resets scram, reinserts a scram signal while continuing to drive in control rods. (Critical Task 2.0) NMP2 2010 Scenario #2 November 2010 NMP SIMULATOR NMP2 2010 NRC SCENARIO 5 REV. 0 No. of Pages: 25 PERFORM OW TO SC VACUUM BKR TEST/CONTINUE STRTUP/IRM UPSCALE/STUCK CONTROL RODITRANSFER MODE SWITCH TO RUN/LOSS OF DIV II SWGRlUNISOLABLE RCIC STEAM LEAK WITH RPV BLOWDOWN/CONDENSATE BOOSTER PUMPS TRIP PREPARER S. Dennis/J.
Reid DATE 7/20/10 VALIDATED P. Amway/B. Hilliker/C.
Darling DATE 7/22110 GEN SUPERVISOR OPS TRAINING OPERATIONS MANAGER NA Exam Security DATE _____ CONFIGURATION CONTROL NA Exam Security DATE _____ SCENARIO
SUMMARY
Length: 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Initial Power Level: 4.5% with Mode Switch in STARTUP The scenario begins at about 4.5% reactor power during plant startup. The crew will perform Drywell to Suppression Chamber Vacuum Breaker surveillance test, N2-0SC-ISC-M@002.
The crew will continue the startup by withdrawing control rods to raise power above 5%. While withdrawing rods an IRM will fail upscale and then a stuck control rod event will occur. Once those issues are addressed the crew will continue rod withdrawal and transfer the Mode Switch to RUN. Next, a loss of offsite power to Div II Switchgear occurs when a bus fault trips open breaker 17-2. The crew will take action per abnormal procedures to stabilize plant parameters, restore Service Water flow and restore drywell fans. The SRO will be required to address TS. Then, the supply breaker for the RCIC inboard steam supply isolation valve will trip. The SRO must address TS. The major transient begins when a RCIC Steam Leak into Reactor Building occurs. Automatic and manual attempts to isolate the RCIC steam line will be unsuccessful.
Entry to EOP-SC is required and the reactor must be manually scrammed (CRITICAL TASK). When Reactor Building temperatures exceed 212°F in two or more areas, an RPV Blowdown is required (CRITICAL TASK). The EHC Pumps trip to disable the Bypass Valves as a means of rapidly reducing RPV pressure.
The Condensate Booster Pumps trip during the RPV Blowdown requiring additional actions to maintain RPV level. Major Procedures Exercised:
EOP-RPV, EOP-SC, EOP-C2, and N2-S0P-3 Dynamic Mitigation Strategy Code: SC1, Primary system leak in SC, exceed max safe level in 2 or more areas, Blowdown required Termination Criteria:
RPV Blowdown is complete and RPV level is maintained above TAF. NMP2 2010 NRC Scenario #5 November 2010 SIMULATOR SET UP IC Number: IC-11 or equivalent (NRC Exam IC-155) RWM Step 17 Reset CSH HI WTR LEVEL SEAL IN Place aIlIRM/APRM Recorders to IRM position Presets/Function Key Assignments Malfunctions: RD07 Control Rod 10-11 STUCK, TRUE PRESET RC11, RCIC Isolation Failure, TRUE PRESET NM06D, IRM CNHL D UPSCALE FAIL, TRUE TRG 1 ED04G 4.16KV NORMAL BUS FAULT SWG 17, TRUE TRG2 RC12, RCIC Steam Leak in RB 215' Elevation 30%, Ramp Time 5 minutes TRG4 TC15A, EHC Pump A Trip, TRUE TRG5 TC15B, EHC Pump B Trip, TRUE TRG5 FW02A, CONDENSATE BOOSTER PUMP TRIP (P2A), TRUE TRG6 FW02B, CONDENSATE BOOSTER PUMP TRIP (P2B), TRUE TRG6 FW02C, CONDENSATE BOOSTER PUMP TRIP (P2C), TRUE TRG6 Remotes: None Overrides: 01A2S042DI0418 OPEN MOV 128 VALVE STEAM SUPPLY PRESET LINE ISLN (INBOARD), ON 01A2S041DI0366 OPEN MOV 121 VALVE STEAM SUPPLY PRESET LINE ISLN (OUTBOARD), ON 01A2S041 DI0365 CLOSE MOV 121 VALVE STEAM SUPPLY PRESET LINE ISLN (OUTBOARD), OFF 01A2S042DI0564 CLOSE MOV 128 VALVE STEAM SUPPLY PRESET LINE ISLN (INBOARD), OFF 01A1S106L00333 STEAM SUPPLY INBD ISOL MOV 128 TRG3 INOPAMBER, ON 01A2DS079L006314 MOV 128 VALVE STEAM SUPPLY LINE PRESET ISLN (INBOARD)
GREEN, OFF 01A2DS080L006315 MOV 128 VALVE STEAM SUPPLY LINE TRG3 ISLN (INBOARD)
RED, OFF NMP2 2010 NRC Scenario #5 November 2010
- 4. Annunciators:
- a. AN601305, RCIC System Inoperable, TRG3 b. AN601319, RCIC Valves Motor Overload, TRG3 Equipment Out of Service NA Support Documentation N2-0P-101A, Plant Startup complete through E.3.3 Rod Pull Sheets initialed to current rod withdrawal step. Attachment 7 of N2-0P-101A complete with NO Exceptions N2-0SP-ISC-M@002, Marked up to begin at step 8.1.2, Steps 8.3 thru 8.5 N/A'd and Steps 8.7 thru 8.9.4 N/A'd. Cues for 8.11 thru 8.14 in script Miscellaneous Event Triggers TRG 5 "thpdome<850".
Activates when RPV pressure is below 850 psia. TRG 6 "hzlc33s4a".
Activates when RPV water level HIGH LEVEL TRIP A RESET amber light on P603 illuminates.
NMP2 2010 NRC Scenario #5 November 2010 SHIFT TURNOVER INFORMATION OFF GOING SHIFT: IN , DATE: PART I: To be performed by the oncoming Operator before assuming the shift. Control Panel Walkdown (all panels) (SM, CRS, STA, CRO, CRE) PART II: To be reviewed by the oncoming Operator before assuming the shift. Shift Supervisor Log (SM, CRS, STA)
- Shift Turnover Checklist (ALL) CRO Log (CRO)
- LCO Status (SM, CRS, STA) Lit Control Room Annunciators
- Computer Alarm Summary (CRO) (SM, CRS, STA, CRO, CRE) Evolutions/General Information/Equipment Status: Reactor Power = 4.5% approx _________*___R__W__M--'S...:..te:..!.p'--17
_________ RPV Pressure 925 psig Bypass Valves are partially open to control RPV pressure Feedwater Pump A in service with FWS-LV55A in AUTO (HIC137) PART III: Remarks/Planned Evolutions: Perform DW to SC Vacuum Breaker test N2-0SP-ISC-M@002 for 2ISC*RV33A 2ISC*RV33B post maintenance Continue plant startup and place the reactor mode switch to RUN between 5% and power in accordance with N2-0P-101A.
Currently at step RWM Step 17 Rods are to be withdrawn using CONTI N UOUS WITH DRAW to 08 single notch withdraw from 08 to 12 per Reactor Chemistry parameters are in compliance with N2-0P-101A Step 3.6 requirements HWC H2 and 02 piping is pressurized per N2-0P-112 APRM Gain Adjustments are satisfactory per Reactor Engineering There are NO MODE 1 restrictions Attachment 7 of N2-0P-101A is complete with NO Exceptions P625 HPCS LEVEL 8 Test Switch is in NORMAL PART IV: To be reviewed/accomplished shortly after assuming the shift: Shift Crew Composition (SM/CRS) NAME TITLE I NAME SRO BOPRO NMP2 2010 NRC Scenario #5 November 2010 III. PERFORMANCE OBJECTIVES A. Critical Tasks: Given an unisolable RCIC steam leak and secondary containment temperature approaching maximum safe values in one area, the crew will enter EOP-RPV and initiate a manual reactor scram Given an unisolable RCIC steam leak and secondary containment temperature above maximum safe values in two or more areas, the crew will perform an RPV Blowdown per EOP-C2. NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENT 1 -N2-0SP-ISC-M@002 NOTE: Ensure crew has marked up copy of procedure EXAMINER NOTE: The Operator at the Back Panel will coordinate with the front panel operator to verify expected alarms and computer points during the surveillance test NMP2 2010 NRC Scenario OPERATOR ACTIONS CREW Crew conducts a pre-brief, walks down the panels. SRO Directs performance of M@002 for vacuum breakers 2ISC*RV33A
& 2ISC*RV33B BOP Performs N2-0SP-ISC-M@002 for vacuum breakers 2ISC*RV33A
& 2ISC*RV33B as follows: Initial Steps: Open 21AS*SOV167, PRIMARY CNTMT OUTBD ISOL VLV TO DRYWELL, at 2CEC*PNL851. Open 2IAS*SOV185, PRIMARY CNTMT INBD ISOL VLVTO DRYWELL, at 2CEC*PNL851.
Steps For 2ISC*RV33A: Open 2ISC*RV33A, VACUUM BREAKER INBOARD, by depressing AND holding VACUUM BREAKER 2ISC*RV33A INBOARD TEST pushbutton.
Verifies the following: Position indication lights for 2ISC*RV33A indicate open. (Green Extinguished, Red Illuminated)
November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 1 (Continued) Annunciator 601556 DRYWELL VACUUM BRKR INBOARD DISC OPEN alarms on 2CEC*PNL601. Computer pt. ISCBC37, RV33A134A OW VAC BRKR IN is generated in the OPEN condition. Position indication lights for 2ISC*RV33B indicate closed. (Green illuminated, Red extinguished) Close 2ISC*RV33A, by releasing VACUUM BREAKER 2ISC*RV33A INBOARD TEST pushbutton.
Verifies the following: Position indication lights for 2ISC*RV33A indicate closed. (Green Illuminated, Red Extinguished) Annunciator 601556 DRYWELL VACUUM BRKR INBOARD DISC OPEN clear on 2CEC*PNL601. Computer pt. ISCBC37, RV33A134A DWVAC BRKR IN is generated in the CLOSED condition.
Steps For 2ISC*RV33B: Open 2ISC*RV33B, VACUUM BREAKER OUTBOARD, by depressing AND holding VACUUM BREAKER 2ISC*RV33B OUTBOARD TEST pushbutton.
Verifies the following: Position indication lights for 2ISC*RV33B indicate open. (Green Extinguished, Red Illuminated)
NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENT 1 (Continued)
ROLE PLAY: When contacted by control room to perform field actions, acknowledge the request and report back 1 minute later that they are complete and have been independently verified.
OPERATOR ACTIONS Annunciator 601557 DRYWELL VACUUM BRKR OUTBOARD DISC OPEN alarms on 2CEC*PNL601. Computer pt. ISCBC39, RV33B/34B DW VAC BRKR IN is generated in the OPEN condition. Position indication lights for 2ISC*RV33A indicate closed. (Green illuminated, Red extinguished) Close 2ISC*RV33B, by releasing VACUUM BREAKER 2ISC*RV33B OUTBOARD TEST pushbutton.
Verifies the following: Position indication lights for 2ISC*RV33B indicate closed. (Green Illuminated, Red Extinguished) Annunciator 601557 DRYWELL VACUUM BRKR OUTBOARD DISC OPEN clear on 2CEC*PNL601. Computer pt. ISCBC39, RV33B/34B DW VAC BRKR OUT is generated in the CLOSED condition.
Final Steps Close 2IAS*SOV167, PRIMARY CNTMT OUTBD ISOL VLV TO DRYWELL, at 2CEC*PNL851.
NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENT 1 (Continued)
OPERATOR ACTIONS NOTE: the next four steps are performed locally Remove pipe cap downstream of 21AS*V511 t *SOV167 LLRT TEST CONNECTION. Slowly open 21AS*V511 AND 2IAS*V199, PENETRATION Z19A TEST CONNECTION, to vent off Drywell Vacuum Breaker supply line inside the Drywell.. WHEN Drywell Vacuum Breaker supply line is depressurized, close 21AS*V199 AND 2IAS*V511. Replace pipe cap downstream of 2IAS*V511.
Final Step in Control Room Close 2IAS*SOV185, PRIMARY CNTMT INBD ISOL VLVTO DRYWELL, at 2CEC*PNL851.
NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENTS 2 and 3 -Continue Startup and IRM 0 Fails Upscale CONSOLE OPERATOR:
After the first control rod is moved and when directed by Lead Evaluator, activate malfunction by depressing TRIGGER 1 NM06D IRM CHNL D FAILURE UPSCALE OPERATOR ACTIONS SRO Directs plant startup continued at 101A Step E.3.3, RSCS Group 6, RWM step 17, Control Rod 50-51 from 00 to 12 RO RO selects control rod 50-51 and begins to withdraw from 00 to 12. RO/CREW Diagnoses IRM "0" Upscale indications: 603207, IRM UPSCALE 603301, RPS TRI P SYTEM B UPSCALEII NOPERABLE 603402, RPS B NMS TRIP 603410, RPS B AUTO TRIP 603442, CONTROL ROD OUT BLOCK SRO Directs actions in accordance with the ARP to bypass the affected I RM and to reset RPS RO In accordance with N2-0P-92 Step H.2.0, bypasses IRM "0" by placing the joystick to BYPASS. Verifies the BYPASS light is lit. NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONS/ PLANT RESPONSE EVENTS 2 and 3 (Continued)
OPERATOR ACTIONS In accordance with ARP, resets the1/2 scram per N2-0P-97 Step H.2.0 as follows: Places Reactor Scram Reset Logic B and Reactor Scram Reset LogiC D switches to RESET. Verifies PILOT SCRAM VALVE SOLENOID white lights are lit for B,D, F and H. SRO Directs RO to continue startup and rod withdrawal.
RO Continues to withdraw control rods. BOP Monitors BOP equipment.
NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENT 4 -Stuck Control Rod 10-11 Malfunction is PRESET: R007 Control Rod 10-11 CONSOLE OPERATOR:
Delete malfunction RD07 after Drive Water pressure has been raised 50 psig. EXAMINER NOTE: The malfunction will be removed and control rod movement will occur after drive pressure has been raised 50 psig. OPERATOR ACTIONS RO Diagnoses Stuck Control Rod 10-11 and informs CRS. SRO Directs actions to unstuck control rod in accordance with N2-0P-30 Section H.1.0 RO Takes the following steps to move stuck control rod in accordance with N2-0P-30 Simultaneously depresses AND holds CONTINUOUS INSERT AND WITHDRAW push buttons on 2CEC*PNL603. Raises drive water pressure in 50 psig increments by throttling closed PV101, DRIVE WrR PRESS CONTROL MOV and attempts to move the rod. WHEN indication of inward control rod motion is received, quickly release CONTINUOUS INSERT pushbutton and depress CONTINUOUS WITHDRAW pushbutton while continuing to hold WITHDRAW pushbutton. Restores drive water pressure to normal value after successful control rod motion. NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 5 -Mode switch to SRO Directs continuing startup and placing mode switch to RUN in accordance with N2-0P-101A.
RO Continues pulling control rods. Verifies APRMs are reading >5% by placing the IRM/APRM recorder select switch to APRM. In each RPS division, leaves one IRM/APRM recorder select switch in the APRM position. Checks with SRO to confirm chemistry parameters, HWC is pressurized and the APRM gain adjustments are SAT. Verifies the following: Steamline pressure greater than 766 psig. Annunciator 603127 "DIVISION I MN STEAM LINE LOW PRESSURE" is clear. Annunciator 603427 "DIVISION II MN STEAM LINE LOW PRESSURE" is clear APRMs on scale between 5% AND 12%. MSIVs are open. Condenser vacuum greater than 25" Hg. No Mode 1 restrictions exist. Attachment 7 has been completed AND any exceptions listed. Places Mode Switch to RUN. NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENT 6 -Loss of Div II Switchgear CONSOLE OPERATOR:
After the page announcement is made that MODE 1 has been entered or when directed by Lead Evaluator, activate malfunction by depressing TRIGGER 2 ED04G 4.16KV NORMAL BUS FAULT SWG 17 (TRUE) OPERATOR ACTIONS CREW Recognizes trip of BKR 17-2 SRO Enters and Directs actions in accordance with N2-S0P-3, Loss of AC Power Verify affected SW Non-Essential Valves Close Verify One SW pump starts in affected division Directs opening all SW Non-Essential Valves Directs throttling the SW 74 valves as required to <1 Okgpm Directs starting a 3 rd service water pump in non affected division. Directs verifying proper EDG operation Directs restoring DW Pneumatics Directs restores DW cooling by starting the unit coolers at Back Panel 873 Enters Tech Spec LCO 3.8.1 Condition A Required Action A.1 to complete SR 3.8.1.1 with 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> completion time AND A.3 to restore required off site circuit to operable with 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time. NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 6 BOP/RO Verifies affected SW Non-Essential Valves Close Verifies One SW pump starts in affected division OPENS all SW Non-Essential Valves Throttles the SW 74 valves as required to <1 Okgpm As directed, Starts a 3 rd service water pump in non affected division Verifies proper EOG operation Restores OW Pneumatics by opening SOV 184 and SOV 165 Restores OW cooling by starting the unit coolers at Back Panel 873 EXAMINER NOTE: May proceed to next event once OW cooling is restored.
NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENT 7 -SRO Tech Spec, 2ICS*MOV128 Breaker Trip, Containment Isolation Valve Failed Open CONSOLE OPERATOR:
When directed by the Lead Evaluator, insert the following overrides for ICS*MOV128 breaker trip, by depressing TRIGGER 3 01A1S106L00333 STEAM SUPPLY INBD ISOL MOV 128 INOP AMBER, ON 01 A2DS080L006315 MOV 128 VALVE STEAM SUPPLY LINE ISLN (INBOARD)
RED,OFF AN601305, RCIC System Inoperable ON AN601319, RCIC Valve Motor Overload ON ROLE PLAY: When dispatched by the BOP/RO to status power supply to MOV128 wait two (2) minutes and report breaker in the tripped condition.
No cause is apparent.
OPERATOR ACTIONS CREW Recognizes and reports RCIC Inboard Isolation Valve failure. Report condition to CRS. BOP/RO At 2CEC*PNL601, determine IF any INOP Status Lights are energized. IF any INOP Status Lights are energized, refer to their applicable Alarm Response Procedure. Determines INOP status light lit for TURB STM SPLY INBD ISOL VLV ICS*MOV128. IF power is NOT available, dispatch an operator to 2EHS*MCC302 to confirm 2EHS*MCC302 14A, 2ICS*MOV128 Power Supply, is ON. SRO Acknowledges BOP/RO report. Refers to T.S. 3.6.1.3, Primary Containment Isolation failure. From Bases 8.3.6.1.3
-The power operated automatic isolation valves are required to have isolation times within limits and actuate on an automatic isolation signal. The valves covered by this LCO are listed with their associated stroke times in Ref. 1. (TRM) NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENT 7 (Continued)
OPERATOR ACTIONS CONDITION A: One or more penetration flow paths with one PCIV inoperable except due to leakage not within limit. REQUIRED ACTION: A.1: Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured. COMPLETION TIME (for A.1): 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> except for main steam line. (Determines penetration must be isolated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.) AND REQUIRED ACTION A.2: Verify the affected penetration flow path is isolated.
COMPLETION TIME (for A.2): Once per 31 days for isolation devices outside primary containment. Refer to TRM If necessary TRM 3.6.1 Primary Containment Isolation Valves The Primary Containment Isolation Valves and, if applicable, valve groups, isolation signals, and isolation times are listed in Table T3.6.1-2.
NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENT 7 (Continued)
OPERATOR ACTIONS * *
- May enter Tech. Spec. 3.5.3 for RCtC inoperable.
Notifies Operations and Plant Management May contact WEC SRO for assistance and work planning
- Conducts post event brief NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR PLANT RESPONSE OPERATOR EVENT 8 -Unisolable RCIC Steam Leak Responds to Annunciator 851254, CONSOLE OPERATOR:
When directed by Lead PROCESS AIRBORNE RADN MON Evaluator, insert the following malfunction by ACTIVATED depressing TRIGGER 4: Diagnoses issue by checking DRMS RC12, RCIC Steam Leak in Reactor Building, CRT Display to determine RB 30% over 5 minute ramp HVR*RE229 alarming.
The following annunciator alarms: SRO 851254 PROCESS AIRBORNE RADN MON On High Radiation Level: ACTIVATED Verify Automatic Response has occurred, as applicable. (NOTE: SBGT is already in service from previous event) Identify area affected and verify level reading. Refers to N2-EOP-SC Enters and directs actions per SC when HVR Exhaust radiation is above an isolation setpoint (HVR*RE229 exceed DRMS Red setpoint) IF any area temperature is above the Annunciator 601157 Reactor Building General isolation setpoint THEN GO to 28 Areas Temperature High is received and RCIC (Step SC-2) Steam Line should isolate as temperature rises Isolate all discharges into affected above 135°F. WCS system isolates.
areas except systems needed for fire fighting or other EOP actions (Step SC-4) Directs BOP/RO to manually isolate RCIC Steam Line. MOV*128 has no power and MOV*121 does not close. NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 8 (Continued)
- IF "primary system" is discharging into the Reactor Building (YES RCIC, RCtC steam line pressure stays up and Conditional Step SC-4) THEN GO to temperatures in the area are still rising. 29 (Step SC-7) Thus, no isolation of the RCIC Steam Line has occurred.
Fire panel 849107 FIRE DETECTED PNL 1 03 SE QUAD 215 alarms as a result of steam discharging into the area. BEFORE any area temperature reaches Maximum Safe Value (Detail S; 212°F) (Step SC-7 and 8) .... ENTER RPV Control, while continuing in EOP-SC (CT -2.0) These actions are directed by the SRO from EOP-RPV ENTER SCRAM PROCEDURE SOP-101C, while continuing in EOP-RPV (Step 3) and Directs a Reactor Scram (Critical Task 1.0) Executes LEVEL and PRESSURE legs concurrently.
LEVEL ACTIONS DIRECTED BY SRO Restore and maintain RPV water level between 159.3 inches and 202.3 inches using one or more Preferred Injection Systems (Detail E1) Step 3. SRO should direct control between 160 to 200 inches. IF level cannot be restored and maintained above 159.3 inches .... THEN maintain level above -14 inches (Fig Z) NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENT 8 (Continued)
OPERATOR ACTIONS OK to augment with Alternate Injection systems if needed (Detail E2) (Use of these is NOT expected)
PRESSURE ACTIONS DIRECTED BY SRO IF RPV Blowdown (EOP-C2) is anticipated
..... THEN Rapidly depressurize the RPV using the Main Turbine Bypass Valves. OK to exceed 100°F/hr cooldown. (Step P-1 Override). (This is an expected action because EOP-C2 will be necessary due to rising Reactor Building temperatures). Is any SRV Cycling? NO (Step P-2) Stabilize RPV Pressure below 1052 psig using Main Turbine Bypass Valves. (Step P-4). SRO should direct control between 800 to 1000 psig with BPVs. Use Alternate Pressure Control Systems, if needed. Restore pneumatics to drywell, if necessary. WAIT until shutdown cooling pressure interlock clears 128 psig (Step P-7) BEFORE proceeding to Step P-8. While in Step P-7 orsooner, the SRO will likely return to EOP-SC actions and be waiting for 2 areas to reach 212°F NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONS! PLANT RESPONSE EVENT 8 (Continued)
At back panel LOS Temperature Monitoring Panels P632 and P642 the first area in alarm and to reach 212 OF E31-N619A and N620A E31-N619B and N620B If "anticipating" RPV Blowdown, aI/ 5 BPVs are opened. RPV pressure lowers. When RPV pressure drops to about 850 psig, the following malfunction automatically activates from TRIGGER 5: TC15A, EHC Pump A Trip, TRUE TC15B, EHC Pump B Trip, TRUE EHC Pumps trip and as EHC pressure lowers, the BPVs will close due to loss of fluid pressure.
NMP2 2010 NRC Scenario OPERATOR ACTIONS These actions are directed by SRO when returning to EOP-SC WAIT until 2 or more areas are above Maximum Safe Value for the same parameter (Step SC-9), THEN proceed to SC-10 to enter EOP-C2. BOP/RO Recognize and reports increasing area temperatures and in the Reactor Building. Uses EOP-6 Attachment 28 to monitor and report temperature conditions. Confirms WCS and RHR isolation. Reports failure of RCIC to automatically isolate. Attempts to manually isolate the RCIC Steam Line by closing MOV*121 using keylock switch. l\IIonitors back panels for trending area temperatures and radiation levels.
- Reports levels and trends to the SRO. IF directed to rapidly depressurize the RPV using the Main Turbine Bypass Valves, opens all 5 BPVs using the BYPASS JACK INCREASE pushbutton.
OK to exceed 100°F/hr cooldown. (Step P-1 Override). (This is an expected action because C2 will be necessary due to rising Reactor Building temperatures). Reports trip of EHC pumps and loss of BPVs, if used for rapid depressurization.
November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 8 RO These are N2-S0P-1 01 C Scram Actions: IF Automatic Scram is anticipated AND time permits ...... THEN Reduce Recirc Flow to 55 mlbm/hr per SOP-101D. (NA, at 4% power) IF Mode switch is NOT in REFUEL position..... THEN Place MODE Switch to SHUTDOWN position. (Critical Task 1.0) Provides Scram report to SRO Verify automatic responses. All rods full in Rx power lowering Turbine trippedlTSVs
& TCVs shut Generator tripped and house loads transferred SDV V&D valves closed RCS pumps downshift RPV pressure on TBVs OR SRVs FWLC controlling level> 159.3" Performs LEVEL control actions as directed by SRO from EOPs Performs PRESSURE control actions as directed by SRO from EOPs WHILE continuing, perform the following as time permits: Fully insert IRMs AND SRMs. Energize 2WCS-MOV107 MCC008-2E). If required, secure makeup to the Cooling Tower. NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR PLANT RESPONSE OPERATOR EVENT 8 (continued) At 2CEC-PNL842, shutdown HWC. IF WCS is in one pump three filter lineup .... THEN Throttle close 2WCS*MOV200 (AND if required, throttle open 2WCS-MOV11
- 0) to obtain approximately 225 gpm wcsnow. Second area temperature reaches 212'F N601 E and N601 F). RPV Blowdown is required.
BOP/RO Report second area temperature reaching 212°F. If required, restore pneumatics to drywell. At P851 IAS*SOV166 and 184. At P601 lAS *SOV164 and 165. When directed, opens seven (7) ADS/SRVs by using keylock switch EXAMINER NOTE: ADS may be initiated from for EACH ADS valve at control 601 panel if Suppression Pool Cooling had room back panel P628 and P631. been placed in service. (Critical Task -2.0) These actions are directed by the SRO from EOP-C2 Will the reactor stay shutdown without boron? YES all rods are fully inserted (Step 2) NMP2 2010 NRC Scenario #5 November 2010 INSTRUCTOR ACTIONSI PLANT RESPONSE EVENT 8 (Continued)
In accordance with N2-EOP-HC Attachment 5, with no RHS pumps running, opening the 7 ADS valves is performed by placing individual keylock switch for EACH ADS valve to open at control room back panel P628 and P631. EVENT 9 -Condensate Booster Pumps Trip CONSOLE OPERATOR:
When RPV water level HIGH LEVEL TRIP A RESET amber light on P603 illuminates after the ADS Blowdown, confirm TRIGGER 6 automatically activates malfunctions: FW02A, CONDENSATE BOOSTER PUMP TRIP (P2A), TRUE FW02B, CONDENSATE BOOSTER PUMP TRIP (P2B), TRUE FW02C, CONDENSATE BOOSTER PUMP TRIP (P2C), TRUE The operators will be required to restore RPV level using EOP-RPV Table E1 and E2 Systems TERMINATION CRITERIA RPV Slowdown is complete and RPV level is maintained above TAF. NMP2 2010 NRC Scenario OPERATOR ACTIONS Drywell Pressure?
Below 1.68 psig (Step 9, then bypass step
- 10) Suppression Pool Level? Above EI 192 ft (Step 11) Open all 7 ADS Valves (Step 12) (Critical Task-2.0) OK to exceed 100°F/hr Restore pneumatics to drywell if necessary Can all 7 ADS Valves be opened? YES (Step 13) WAIT until shutdown cooling pressure interlock clears 128 psig (Step 16) BEFORE proceeding to Step 17. BOP/RO Maintains level as directed by CRS using EOP*RPV Table E1 and E2 Systems. November 2010