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| number = ML13154A270
| number = ML13154A270
| issue date = 05/08/2013
| issue date = 05/08/2013
| title = Nine Mile Point Station, Unit 1 - Final Operating Exam (Sections a, B, and C) (Folder 3)
| title = Final Operating Exam (Sections a, B, and C) (Folder 3)
| author name =  
| author name =  
| author affiliation = Nine Mile Point Nuclear Station, LLC
| author affiliation = Nine Mile Point Nuclear Station, LLC
| addressee name = Fish T H
| addressee name = Fish T
| addressee affiliation = NRC/RGN-I/DRS/OB
| addressee affiliation = NRC/RGN-I/DRS/OB
| docket = 05000220
| docket = 05000220
| license number = DPR-063
| license number = DPR-063
| contact person = Jackson D E
| contact person = Jackson D
| case reference number = TAC U01861
| case reference number = TAC U01861
| package number = ML12356A123
| package number = ML12356A123
| document type = License-Operator, Part 55 Examination Related Material
| document type = License-Operator, Part 55 Examination Related Material
| page count = 196
| page count = 196
| project = TAC:U01861
| stage = Other
}}
}}


=Text=
=Text=
{{#Wiki_filter:NRC JPM RO C001 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Perform NI-ST-DO DAILY CHECKS (Partial)
{{#Wiki_filter:NRC JPM RO C001 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
Revision:
 
NRC 2013 Task Number: NI A Approvals:
==Title:==
NIA -Exam Security / General Supervisor  
Perform NI-ST-DO DAILY CHECKS (Partial)                                           Revision: NRC 2013 Task Number:     NI A Approvals:
'" Date General Supervisor Date Operations Training (Designee)
NIA - Exam Security               /
Operations (Designee)
General Supervisor           '"           Date                       General Supervisor                   Date Operations Training (Designee)                                       Operations (Designee)
Configuration Control Date Performer:
Configuration Control                     Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)
_______________
TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __
TrainerlEvaluator:
Evaluation Method:     _~_ _      Perform          _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant                 _ _---'--"--__ Simulator Expected Completion Time:         20 minutes       Time Critical Task:       No     Alternate Path Task:     No Start Time: _ _ __                Stop Time: _ _ _ __                Completion Time: _ _ _ __
____________Evaluation Method: __Perform ______
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.
Evaluation Location:
Comments:
____ Plant __---'--"--__ Simulator Expected Completion Time: 20 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: _ _ _ _ _ _ _ _ _ _ _ _ _ __
Evaluator Signature:
NRC 2013 JPM RO COOl                                                                                     May 2013
______________
 
_ NRC 2013 JPM RO COOl May 2013 Recommended Start Location: (Completion time based on the start location)
Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up: 1. Initialize Simulator to IC-166 2. Verify the following overrides are set: a. 5M80A03550 73.00 b. 5M81A03560 75.00 c. 5Ml18A03860  
Simulator Simulator Set-up:
= 76.00 d. 5Ml16A03840  
: 1. Initialize Simulator to IC-166
=68.00 e. 5ARITSIA031000  
: 2. Verify the following overrides are set:
= 68.00 f. 13MIA042680 69.00 g. 9M53A051270 70.50 3. Take the simulator to Run, and then back to Freeze 4. Verify average DryweU temperature is less than 130°F 5. Verify total Recirc flow is 38 Mlbmlhr 6. Verify FWLC is selected to column 11 7. Tum off PI monitor Directions to the InstructorlEvaluator:
: a. 5M80A03550 73.00
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.
: b. 5M81A03560 75.00
: c. 5Ml18A03860 = 76.00
: d. 5Ml16A03840 = 68.00
: e. 5ARITSIA031000 = 68.00
: f. 13MIA042680 69.00
: g. 9M53A051270 70.50
: 3. Take the simulator to Run, and then back to Freeze
: 4. Verify average DryweU temperature is less than 130°F
: 5. Verify total Recirc flow is 38 Mlbmlhr
: 6. Verify FWLC is selected to column 11
: 7. Tum off PI monitor Directions to the InstructorlEvaluator:
Prior to performance ofthis 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:
Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
With the exception of accessing panels, NO plant equipment will be physically manipulated.
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.
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:
Read Before Each Training JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are Therefore, either another individual or I will act as the independent verifier or peer NRC 2013 JPM RO COOl May 2013 Notes to Instructor  
During this Training JPM, the use of applicable methods of verification and checking are expected.
/ Evaluator: Critical steps are identified in grading areas PasslFail.
Therefore, either another individual or I will act as the independent verifier or peer checker.
All steps are sequenced critical unless denoted by a ".". During Evaluated JPM: Self checking shall be demonstrated. During Training JPM: Self checking shall be demonstrated.
NRC 2013 JPM RO COOl                                                                                   May 2013
* Peer checking shall be NUREG 1123,2.1.18 , RO 3.6 Nl-ST-DO Tools and Equipment:
 
Calculator Task Control room RPV water level readings are taken for Nl-ST-DO.
Notes to Instructor / Evaluator:
Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.
: 1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a
Initial Conditions: The plant is operating at approximately 15% power. Nl-ST-DO, Daily Checks, is in progress. The provided printout shall be used to determine computer point and PI data. Instructor to ask the operator for any questions.
: 2. During Evaluated JPM:
Initiating cue: "(Operator's name), obtain the instrument readings needed from control room panels to complete Nl-ST-DO Attachment 4 sections 5.0 and 6.0 only, then complete section 8.4 in the body of the procedure.
* Self checking shall be demonstrated.
When completed, report findings and provide completed sections to SRO." I Performance I Standard Grade Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)
: 3. During Training JPM:
Evaluator acknowledge repeat back providing correction if necessary
* Self checking shall be demonstrated.
________ Obtain a copy of the reference procedure and N-ST-DO obtained, sections 5.0 and 6.0 SatlUnsat review/utilize the correct section referenced Completed NI-ST-DO is attached JPM key. Small differences in values may occur due to NRC 2013 JPM RO COOl -3 May 2013 I Performance Steps Records section
* Peer checking shall be demonstrated.


===5.0 readings===
==References:==
Compare Recirc Pump Inlet readings and determines readings Record section 6.0 readings Cue: Another operator has completed required Independent Record Total Recirc Plow Determines average Drywell temperature Since Yarway level indicator deviation is less than 4 inches, Drywell temperature reading is not necessary for task completion. Analyzes Yarway level indicator deviation This may be evidenced by the lack of a report to the contrary. Analyzes GEMAC level indicator deviation
: 1. NUREG 1123,2.1.18, RO 3.6
: 10. Determines GEMAC level indicators Provides completed sections to SRO informs of out of spec I Standard Records Reactor Recirc Pump Temperature readings on Attachment Section Compares readings and determines readings within 15&deg;P of each other Checks YES block in Section 5.0, indicating the maximum difference in loop temperatures is<15&deg;P Records RPV water level readings Attachment 4 section Records total recirc flow in the correct box on Attachment 4 section 6.0 Observes average Drywell temperature is less than 125&deg;p Determines Yarway level indicator deviation is less than the 6 inch limit Determines GEMAC level indicator deviation is greater than the 6 inch limit Checks !NOP option in step 8.4 Proper communications used (GAP-OPS-Ol)
: 2. Nl-ST-DO Tools and Equipment:
Grade SatlUnsat SatlUnsat PasslFail SatlUnsat SatlUnsat SatlUnsatlNA PasslFail PasslFaii PasslFaii SatlUnsat TERMINATING CUE: Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.
Calculator Task Standard: Control room RPV water level readings are taken for Nl-ST-DO. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.
RECORDSTOPTIME
Initial Conditions:
_________ NRC 2013 JPM RO COO 1 May 2013 Initial Conditions:  
: 1.        The plant is operating at approximately 15% power.
: 1. The plant is operating at approximately 15% power. 2. N1-ST-DO, Daily Checks, is in progress.  
: 2.        Nl-ST-DO, Daily Checks, is in progress.
: 3. The provided printout shall be used to determine computer point and PI data. Initiating cue: "(Operator's name), obtain the instrument readings needed from control room panels to complete N1-ST-DO Attachment 4 sections 5.0 and 6.0 only, then complete section 8.4 in the body of the procedure.
: 3.       The provided printout shall be used to determine computer point and PI data.
When completed, report findings and provide completed sections to SRO." NRC 2013 JPM RO COOl May 2013 NRC JPM RO C002 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Perfonn Heat-Up Rate Detennination Revision:
: 4.        Instructor to ask the operator for any questions.
NRC 2013 Task Number: N/A Approvals:
Initiating cue:
I NIA -Exam Security I General Supervisor Date General Supervisor Date Operations Training (Designee)
    "(Operator's name), obtain the instrument readings needed from control room panels to complete Nl-ST-DO Attachment 4 sections 5.0 and 6.0 only, then complete section 8.4 in the body of the procedure. When completed, report findings and provide completed sections to SRO."
Operations (Designee)
I Performance Steps                                    I Standard                                              Grade
NIA -Exam Security I Configuration Control Date Perfonner:
: 1. Provide repeat back of initiating cue              Proper communications used for repeat back          SatlUnsat (GAP-OPS-Ol)
______________
Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTT~E                ________
,(RO/SRO)
: 2. Obtain a copy of the reference procedure and        N-ST-DO obtained, sections 5.0 and 6.0              SatlUnsat review/utilize the correct section                referenced Note:    Completed NI-ST-DO is attached as JPM key. Small differences in recorded values may occur due to instrument interpolation.
TrainerlEvaluator:
NRC 2013 JPM RO COOl                                                                                  May 2013
____________
 
_ Evaluation Method: Perfonn Evaluation Location:
I Performance Steps                              I Standard                                           Grade
Classroom Expected Completion Time: 15 minutes Time Critical Task: No Alternate Path Task:
: 3. Records section 5.0 readings                  Records Reactor Recirc Pump Inlet                SatlUnsat Temperature readings on Attachment 4 Section 5.0
No Start Time: ____ Stop Time: _____ Completion Time: _____ JPM Overall Rating: Pass Fail NOTE: A JPM overall rating offail shall be given if any critical step is graded as fail. Any grade of un sat or individual competency area unsat requires a comment. Comments:
: 4. Compare Recirc Pump Inlet Temperature          Compares readings and determines readings        SatlUnsat readings and determines readings within      within 15&deg;P of each other 15&deg;P Checks YES block in Section 5.0, indicating       PasslFail the maximum difference in loop temperatures is<15&deg;P
Evaluator  
: 5. Record section 6.0 readings                    Records RPV water level readings on              SatlUnsat Attachment 4 section 6.0 Cue: Another operator has completed the required Independent Verifications.
...,.0.11........  
: 6. Record Total Recirc Plow                      Records total recirc flow in the correct box on   SatlUnsat Attachment 4 section 6.0
._______________
: 7. Determines average Drywell temperature        Observes average Drywell temperature is less   SatlUnsatlNA than 125&deg;p Note: Since Yarway level indicator deviation is less than 4 inches, Drywell temperature reading is not necessary for task completion.
_ Date:.______NRC 2013 JPM RO C002 May Recommended Start Location: (Completion time based on the start 1. Prepare a picture ofRRP 11 suction temperature gauge indicating approximately 535&deg;F. 2. Prepare NI-OP-43A Attachment 18 with the following data: DatelTime RRP Suction Temp DT/I5 min DT 115 min Limits Heatup Rate Limits 5111130900 350 N/A N/A N/A 511113 0915 370 20 SAT NIA 5/1113 0930 380 10 SAT N/A 5/1113 0945 400 20 SAT NIA 511113 1000 415 15 SAT SAT 511/13 1015 435 20 SAT SAT 5/1/13 1030 470 5/1/13 1045 490 511113 1100 Directions to the InstructorlEvaluator:
: 8. Analyzes Yarway level indicator deviation      Determines Yarway level indicator deviation       PasslFail is less than the 6 inch limit Note: This may be evidenced by the lack of a report to the contrary.
: 9. Analyzes GEMAC level indicator deviation      Determines GEMAC level indicator deviation       PasslFaii is greater than the 6 inch limit
: 10. Determines GEMAC level indicators are        Checks !NOP option in step 8.4                   PasslFaii inoperable
: 11. Provides completed sections to SRO and        Proper communications used (GAP-OPS-Ol)           SatlUnsat informs of out of spec readings TERMINATING CUE: Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.
RECORDSTOPTIME_________
NRC 2013 JPM RO COO 1                                                                         May 2013
 
Initial Conditions:
: 1.     The plant is operating at approximately 15% power.
: 2.     N1-ST-DO, Daily Checks, is in progress.
: 3.     The provided printout shall be used to determine computer point and PI data.
Initiating cue:
"(Operator's name), obtain the instrument readings needed from control room panels to complete N1-ST-DO Attachment 4 sections 5.0 and 6.0 only, then complete section 8.4 in the body of the procedure. When completed, report findings and provide completed sections to SRO."
NRC 2013 JPM RO COOl                                                         May 2013
 
NRC JPM RO C002 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
Perfonn Heat-Up Rate Detennination                                               Revision: NRC 2013 Task Number:         N/A Approvals:
I   :s/~(t2                NIA - Exam Security               I General Supervisor                       Date                       General Supervisor                   Date Operations Training (Designee)                                       Operations (Designee)
NIA - Exam Security                       I Configuration Control                     Date Perfonner:_ _ _ _ _ _ _ _ _ _ _ _ _ _,(RO/SRO)
TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __
Evaluation Method: Perfonn Evaluation Location: 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 offail shall be given if any critical step is graded as fail. Any grade of un sat or individual competency area unsat requires a comment.
Comments:
Evaluator ...,.0.11........ .________________                                  Date:._ _ _ _ _ __
NRC 2013 JPM RO C002                                                                                   May 2013
 
Recommended Start Location: (Completion time based on the start location)
Classroom Set-up:
: 1. Prepare a picture ofRRP 11 suction temperature gauge indicating approximately 535&deg;F.
: 2. Prepare NI-OP-43A Attachment 18 with the following data:
DatelTime           RRP Suction Temp           DT/I5 min         DT115 min Limits       Heatup Rate Limits 5111130900                   350                   N/A                 N/A                 N/A 511113 0915                   370                   20                   SAT                 NIA 5/1113 0930                   380                   10                 SAT                 N/A 5/1113 0945                   400                   20                 SAT                 NIA 511113 1000                   415                   15                 SAT                 SAT 511/13 1015                   435                   20                   SAT                 SAT 5/1/13 1030                   470 5/1/13 1045                   490 511113 1100 Directions to the InstructorlEvaluator:
None Directions to Operators:
None Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
With the exception of accessing panels, NO plant equipment will be physically manipulated.
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.
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.
Read Before Each Training JPM Performance:
The Control Supervisor has determined that a verifier is not available and that additional I concurrent verification will be provided; therefore, it should not be Read Before Each Training JPM During this Training JPM, the use of applicable methods of verification and checking are Therefore, either another individual or I will act as the independent verifier or peer Notes to Instructor I
During this Training JPM, the use of applicable methods of verification and checking are expected.
NRC 2013 JPM RO C002 May Critical steps are identified in grading areas PasslFaii. During Evaluated JPM: Self checking shall be demonstrated. During Training JPM: Self checking shall be demonstrated. Peer checking shall be demonstrated.  
Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor I Evaluator:
NRC 2013 JPM RO C002                                                                                   May 2013
: 1. Critical steps are identified in grading areas PasslFaii.
: 2. During Evaluated JPM:
* Self checking shall be demonstrated.
: 3. During Training JPM:
* Self checking shall be demonstrated.
* Peer checking shall be demonstrated.


==References:==
==References:==
NUREG 1123,2.1.7, RO 4.4 NI-0P-43A Attachment 18 Tools and Equipment:
: 1. NUREG 1123,2.1.7, RO 4.4
Calculator Task Current plant heat-up data taken per NI-OP-43A Attachment  
: 2. NI-0P-43A Attachment 18 Tools and Equipment:
: 18. Current and past heat-up rates calculated.
Calculator Task Standard: Current plant heat-up data taken per NI-OP-43A Attachment 18. Current and past heat-up rates calculated. Out of spec heat-up rate is identified to SRO.
Out of spec heat-up rate is identified to SRO. Initial Conditions: A plant startup is in progress. Current time is 1100 on 5/1/13. N 1-0P-43A Attachment 18 is provided with heat-up data for the last hour. All RRP suction temperature readings have been taken from Recirc loop 11. The provided picture shows the current Recirc loop 11 suction temperature indication. Instructor to ask the operator for any questions.
Initial Conditions:
Initiating cue: "(Operator's name), obtain the time 1100 reading for NI-0P-43A Attachment 18, then complete the attachment for times 1030, 1045, and 1100. When completed, report findings and provide completed sections to SRO." Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)
: 1.      A plant startup is in progress.
Evaluator acknowledge repeat back providing correction if necessary
: 2.      Current time is 1100 on 5/1/13.
_______ Obtain a copy of the reference procedure and Nl-OP-43A Attachment 18 SatlUnsat review/utilize the correct section Completed NI-OP-43A is attached as JPM key. Small differences in recorded values may occur due to instrument interpolation.
: 3.      N 1-0P-43A Attachment 18 is provided with heat-up data for the last hour.
NRC 2013 JPM RO C002 -3 May 2013 I Performance Steps Records current RRP suction temperature Calculates and records AT 115 min for times 1030-1100 Analyzes and records AT Limits for AT/I5 min Calculates hourly ATs for times 1030-1100 Note: There is no column on NI-0P-43A to record this step. It is provided to document an intennediate step taken to arrive at JPM Step #7. If the candidate does not provide these intermediate values, the JPM step may be graded "NA". Analyzes and records Heat-up Rate Limits Provides completed sections to SRO and infonns of out of spec readings I Standard Records current RRP suction (535&deg;F +/- Calculates and records AT 115 min: 1030: 470&deg;F -435&deg;F 1045: 490&deg;F -470&deg;F 1100: 535&deg;F -490&deg;F 45&deg;F (+/- Analyzes and records AT Limits for AT 115 min: 1030: 1045: 1100: Calculates ATs: 1030: 470&deg;F -380&deg;F 1045: 490 0 p -400&deg;F 1100: 535&deg;F -415&deg;F Analyzes and records Heat-Up Rate Limits: 1030: SAT 1045: SAT 1100: UNSAT Proper communications used (GAP-OPS-Ol)
: 4.      All RRP suction temperature readings have been taken from Recirc loop 11.
Grade PasslFaii Sat/Unsat SatlUnsat SatlUnsatlNA Pass/Fail Pass/Fail Pass/Fail SatlUnsat TERMINATING CUE: Control room reading taken. Heat-up rates are calculated.
: 5.      The provided picture shows the current Recirc loop 11 suction temperature indication.
Results are provided to SRO. RECORDSTOPTIME
: 6.      Instructor to ask the operator for any questions.
_________ NRC 2013 JPM RO C002 May 2013 Initial Conditions: A plant startup is in progress. Current time is 1100 on 5/1/13. NI-0P-43A Attachment 18 is provided with heat-up data for the last hour. All RRP suction temperature readings have been taken from Recirc loop 11. The provided picture shows the current Recirc loop 11 suction temperature indication.
Initiating cue:
Initiating cue: "(Operator's name), obtain the time 1100 reading for NI-0P-43A Attachment 18, then complete the attachment for times 1030, 1045, and 1100. When completed, report findings and provide completed sections to SRO." NRC 2013 JPM RO C002 -5 May 2013 NRCJPM ROEP Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Conduct Alert Emergency Announcement and Revision:
  "(Operator's name), obtain the time 1100 reading for NI-0P-43A Attachment 18, then complete the attachment for times 1030, 1045, and 1100. When completed, report findings and provide completed sections to SRO."
NRC 2013 Task Number: NI A Approvals:
: 1. Provide repeat back of initiating cue             Proper communications used for repeat back     SatlUnsat (GAP-OPS-Ol)
NIA -Exam Security General Supervisor Date General Supervisor Date Operations Training (Designee)
Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTT~E                _______
Operations (Designee)
: 2. Obtain a copy of the reference procedure and     Nl-OP-43A Attachment 18                         SatlUnsat review/utilize the correct section Note:    Completed NI-OP-43A is attached as JPM key. Small differences in recorded values may occur due to instrument interpolation.
NIA -Exam Security Configuration Control Date Performer:
NRC 2013 JPM RO C002                                                                           May 2013
__________TrainerlEvaluator:
 
____________Evaluation Method: Evaluation Location:
I Performance Steps                                 I Standard                                      Grade
Expected Completion Time: 10 minutes Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop Time: _____ 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:
: 3. Records current RRP suction temperature         Records current RRP suction temperature    PasslFaii (535&deg;F +/- 10&deg;F)
Evaluator Signature:
: 4. Calculates and records AT115 min for times      Calculates and records AT115 min:           Sat/Unsat 1030-1100 1030: 470&deg;F - 435&deg;F    35&deg;F 1045: 490&deg;F - 470&deg;F    20&deg;F 1100: 535&deg;F - 490&deg;F   45&deg;F (+/- 10&deg;F)
_______________
: 5. Analyzes and records AT Limits for AT/I5        Analyzes and records AT Limits for AT115    SatlUnsat min                                            min:
_ Date:_______ NRC 2013 JPM RO EP May 2013 Recommended Start Location:
1030: UNSAT 1045: SAT 1100: UNSAT
Simulator Simulator Set-up: N!A Directions to the InstructorlEvaluator:
: 6. Calculates hourly ATs for times 1030-1100        Calculates ATs:                          SatlUnsatlNA Note: There is no column on NI-0P-43A to            1030: 470&deg;F - 380&deg;F   90&deg;F record this step. It is provided to document an    1045: 4900 p - 400&deg;F   90&deg;F intennediate step taken to arrive at JPM Step #7. 1100: 535&deg;F - 415&deg;F   120&deg;F Ifthe candidate does not provide these intermediate values, the JPM step may be graded "NA".
This JPM may be conducted anywhere a GAI-tronics station (with alarms) is located. Directions to Operators:
: 7. Analyzes and records Heat-up Rate Limits        Analyzes and records Heat-Up Rate Limits:
1030: SAT                                   Pass/Fail 1045: SAT                                   Pass/Fail 1100: UNSAT                                 Pass/Fail
: 8. Provides completed sections to SRO and          Proper communications used (GAP-OPS-Ol)     SatlUnsat infonns of out of spec readings TERMINATING CUE: Control room reading taken. Heat-up rates are calculated. Results are provided to SRO.
RECORDSTOPTIME_________
NRC 2013 JPM RO C002                                                                       May 2013
 
Initial Conditions:
: 1.      A plant startup is in progress.
: 2.      Current time is 1100 on 5/1/13.
: 3.      NI-0P-43A Attachment 18 is provided with heat-up data for the last hour.
: 4.      All RRP suction temperature readings have been taken from Recirc loop 11.
: 5.      The provided picture shows the current Recirc loop 11 suction temperature indication.
Initiating cue:
"(Operator's name), obtain the time 1100 reading for NI-0P-43A Attachment 18, then complete the attachment for times 1030, 1045, and 1100. When completed, report findings and provide completed sections to SRO."
NRC 2013 JPM RO C002                                                         May 2013
 
NRCJPM ROEP Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
Conduct Alert Emergency Announcement and Evacuation                                  Revision: NRC 2013 Task Number: NIA Approvals:
NIA - Exam Security General Supervisor             Date                       General Supervisor                         Date Operations Training (Designee)                             Operations (Designee)
NIA - Exam Security Configuration Control           Date Performer:_ _ _ _ _ _ _ _ _ _(RO)
TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __
Evaluation Method: Perform Evaluation Location: Simulator Expected Completion Time:       10 minutes       Time Critical Task:       No     Alternate Path Task:     No Start Time: _ _ __              Stop Time: _ _ _ __                Completion 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 2013 JPM RO EP                                                                                       May 2013
 
Recommended Start Location: Simulator Simulator Set-up: N!A Directions to the InstructorlEvaluator:
This JPM may be conducted anywhere a GAI-tronics station (with alarms) is located.
Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
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.
During task performance, I will identifY the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM This evaluated JPM is a measure of your ability to perform this task independently.
Read Before Each Evaluated JPM Performance:
The Control Supervisor has determined that a verifier is not available and that additional!
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.
concurrent verification 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 used. Therefore, another individual or I will act as the additional!
Read Before Each Training JPM Performance:
concurrent verifier.
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!
Notes to Instructor! Evaluator:
Evaluator:  
: 1.     Critical steps are identified as PasslFaii.
: 1. Critical steps are identified as PasslFaii.  
: 2.     During Evaluated JPM:
: 2. During Evaluated JPM:
* Self-verification shall be demonstrated.
* Self-verification shall be demonstrated.  
: 3.     During Training JPM:
: 3. During Training JPM:
* Self-verification shall be demonstrated.
* Self-verification shall be demonstrated.  


==References:==
==References:==
: 1. NUREG 1123,2.4.43 , RO 3.2 2.
: 1. NUREG 1123,2.4.43, RO 3.2
Tools and Task Standard:
: 2. EPIP-EPP-18 Tools and Equipment:
Alert emergency announcement is NRC 2013 JPM RO EP May 2013 Initial Conditions:  
None Task Standard: Alert emergency announcement is made.
: 1. The Shift Manager has declared an Alert emergency condition due to high Drywell pressure.  
NRC 2013 JPM RO EP                                                                                     May 2013
 
Initial Conditions:
: 1. The Shift Manager has declared an Alert emergency condition due to high Drywell pressure.
: 2. Ask the operator for any questions.
: 2. Ask the operator for any questions.
Initiating cue: "(Operator's name), make the provided EPIP-EPP-18 attachment 2 Emergency Announcement." I Performance Steps 1. Provide repeat back of initiating cue Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTUME
Initiating cue:
_______ Place GAI-tronics in MERGE 3. Sound the appropriate alarm 4. Stop the alarm 5. Announce checked items I Standard Proper communications used for repeat back (GAP-OPS-Ot)
"(Operator's name), make the provided EPIP-EPP-18 attachment 2 Emergency Announcement."
Places GAI-tronics in MERGE by MERGE/ISOLATE switch to Sounds the Evacuation Alarm by depressing EV AC pushbutton Stops the Evacuation Alarm by depressing OFF pushbutton after approximately 10 seconds Holds GAI-tronics broadcast while "Attention, attention, all personneL This is a drilL Nine Mile Point Unit 1 is experiencing an Alert emergency condition due to high Drywell pressure.
I Performance Steps                               I Standard                                          Grade
All Emergency Response Organization personnel are to report to their Emergency Response Facilities and card in. All personnel not assigned emergency response duties shall evacuate the Protected Area and report to the P-Building.
: 1. Provide repeat back of initiating cue         Proper communications used for repeat back      SatlUnsat (GAP-OPS-Ot)
Remain at this location until further notice. Personnel in protective clothing should leave the area removing PCs as indicated at the step off pad. I repeat, this is a drill." Notes: If Examiner wishes not to broadcast, holding the broadcast pushbutton may be discussed/simulated. The announcement may differ between Candidates, however important points must all be NRC 2013 JPM RO EP PasslFail PasslFaii SatlUnsat PasslFail May 2013
Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTUME _______
: 6. Repeat alarm 7. Stops alarm 8. Repeat announcement Sounds the Evacuation Alarm by depressing EV AC pushbutton Stops the Evacuation Alarm by depressing OFF pushbutton after approximately 10 seconds Holds GAI-tronies broadcast pushbutton while saying: "Attention, attention, all personnel.
: 2. Place GAI-tronics in MERGE                     Places GAI-tronics in MERGE by toggling          PasslFail MERGE/ISOLATE switch to MERGE
This is a drill. Nine Mile Point Unit 1 is experiencing an Alert emergency condition due to high Drywell pressure.
: 3. Sound the appropriate alarm                    Sounds the Evacuation Alarm by depressing       PasslFaii EV AC pushbutton
All Emergency Response Organization personnel are to report to their Emergency Response Facilities and card in. All personnel not assigned emergency response duties shall evacuate the Protected Area and report to the P-Building.
: 4. Stop the alarm                                  Stops the Evacuation Alarm by depressing       SatlUnsat OFF pushbutton after approximately 10 seconds
Remain at this location until further notice. Personnel in protective clothing should leave the area removing PCs as indicated at the step off pad. I repeat, this is a drill." Notes: If Examiner wishes not to broadcast, holding the broadcast pushbutton may be discussed/simulated. The announcement may differ slightly between Candidates, however the important points must all be covered.
: 5. Announce checked items                        Holds GAI-tronics broadcast pushbutton          PasslFail while saying:
TERMINATING CUE: Alert emergency announcement is made. RECORDSTOPTIME
                                                    "Attention, attention, all personneL This is a drilL Nine Mile Point Unit 1 is experiencing an Alert emergency condition due to high Drywell pressure. All Emergency Response Organization personnel are to report to their Emergency Response Facilities and card in.
_________ NRC 2013 JPM RO EP May 2013 Initial Conditions: The Shift Manager has declared an Alert emergency condition due to high Drywell pressure.
All personnel not assigned emergency response duties shall evacuate the Protected Area and report to the P-Building. Remain at this location until further notice. Personnel in protective clothing should leave the area removing PCs as indicated at the step off pad.
Initiating cue: "(Operator's name), make the provided EPIP-EPP-18 attachment 2 Emergency Announcement. " NRC 2013 JPM RO EP May 2013 NRC JPM RO-SRO EC Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: RPS Manual Scram Electrical Print Reading Revision:
I repeat, this is a drill."
NRC 2013 Task Number: NtA Approvals:
Notes:
NtA -Exam Security General Supervisor Date General Supervisor Date Operations Training (Designee)
* If Examiner wishes not to broadcast, holding the broadcast pushbutton may be discussed/simulated.
Operations (Designee)
* The announcement may differ slightly between Candidates, however the important points must all be covered.
NtA -Exam Security Configuration Control Date Performer:
NRC 2013 JPM RO EP                                     -3                                            May 2013
__________(RO/SRO) TrainerlEvaluator:.
: 6. Repeat alarm                         Sounds the Evacuation Alarm by depressing       SatlUnsat EV AC pushbutton
____________
: 7. Stops alarm                          Stops the Evacuation Alarm by depressing         SatlUnsat OFF pushbutton after approximately 10 seconds
_ Evaluation Method: Perform Evaluation Location:
: 8. Repeat announcement                  Holds GAI-tronies broadcast pushbutton           SatlUnsat while saying:
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 offail shall be given if any critical step is graded as fail. Any grade ofunsat or individual competency area unsat requires a comment. Comments:
                                        "Attention, attention, all personnel. This is a drill. Nine Mile Point Unit 1 is experiencing an Alert emergency condition due to high Drywell pressure. All Emergency Response Organization personnel are to report to their Emergency Response Facilities and card in.
Evaluator  
All personnel not assigned emergency response duties shall evacuate the Protected Area and report to the P-Building. Remain at this location until further notice. Personnel in protective clothing should leave the area removing PCs as indicated at the step off pad.
..."f",u....... Date:______NRC 2013 JPM RO-SRO EC May 2013 Recommended Start Location:
I repeat, this is a drill."
Classroom Simulator Set-up: NI A Directions to the InstructorlEvaluator:
Notes:
Make available a set of electrical prints. When the Candidate identifies the correct print, provide them with another copy of the print so that they may mark it up. Directions to Operators:
* If Examiner wishes not to broadcast, holding the broadcast pushbutton may be discussed/simulated.
* The announcement may differ slightly between Candidates, however the important points must all be covered.
TERMINATING CUE: Alert emergency announcement is made.
RECORDSTOPTIME_________
NRC 2013 JPM RO EP                                                                     May 2013
 
Initial Conditions:
: 1. The Shift Manager has declared an Alert emergency condition due to high Drywell pressure.
Initiating cue:
"(Operator's name), make the provided EPIP-EPP-18 attachment 2 Emergency Announcement. "
NRC 2013 JPM RO EP                                                         May 2013
 
NRC JPM RO-SRO EC Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
RPS Manual Scram Electrical Print Reading                                       Revision: NRC 2013 Task Number: NtA Approvals:
NtA - Exam Security General Supervisor                 Date                     General Supervisor                         Date Operations Training (Designee)                               Operations (Designee)
NtA - Exam Security Configuration Control               Date Performer:_ _ _ _ _ _ _ _ _ _(RO/SRO)
TrainerlEvaluator:._ _ _ _ _ _ _ _ _ _ _ __
Evaluation Method: Perform Evaluation Location: 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 offail shall be given if any critical step is graded as fail. Any grade ofunsat or individual competency area unsat requires a comment.
Comments:
Evaluator . ." f",u.......                                                       Date:_ _ _ _ _ __
NRC 2013 JPM RO-SRO EC                                                                                     May 2013
 
Recommended Start Location: Classroom Simulator Set-up: NIA Directions to the InstructorlEvaluator:
Make available a set of electrical prints. When the Candidate identifies the correct print, provide them with another copy of the print so that they may mark it up.
Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
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.
During task performance, I will identifY the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
Read Before Each Evaluated JPM Performance:
This evaluated JPM is a measure of your ability to perform this task independently.
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.
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:
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.
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  
Notes to Instructor / Evaluator:
/ Evaluator:  
: 1.     Critical steps are identified as PasslFaii.
: 1. Critical steps are identified as PasslFaii.  
: 2.     During Evaluated JPM:
: 2. During Evaluated JPM:
* Self-verification shall be demonstrated.
* Self-verification shall be demonstrated.  
: 3.     During Training JPM:
: 3. During Training JPM:
* Self-verification shall be demonstrated.
* Self-verification shall be demonstrated.  


==References:==
==References:==
: 1. NUREG 1123,2.2.41 , RO 3.5 2. C-19859-C Sheet 7 Tools and Equipment:
: 1. NUREG 1123,2.2.41, RO 3.5
None Task Standard:
: 2. C-19859-C Sheet 7 Tools and Equipment:
Relays and contacts affected by depressing RPS 12 manual scram pushbutton are identified on station electrical drawings and operation is explained.
None Task Standard: Relays and contacts affected by depressing RPS 12 manual scram pushbutton are identified on station electrical drawings and operation is explained. For SRO candidates, additionally identifY the surveillance requirements for testing the RPS 12 manual scram pushbutton and the Technical Specification impact if the pushbutton becomes inoperable.
For SRO candidates, additionally identifY the surveillance requirements for testing the RPS 12 manual scram pushbutton and the Technical Specification impact if the pushbutton becomes inoperable.
NRC 2013 JPM RO-SRO EC                                                                                   May 2013
NRC 2013 JPM RO-SRO EC May 2013 Initial Conditions: None. Ask the operator for any questions.
 
Initiating cue: "(Operator's name), using station electrical prints, explain how depressing the RPS 12 manual scram pushbutton on E console results in an RPS channel 12 half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action." Provide repeat back of initiating cue Evaluator acknowledge repeat providing correction if RECORDSTARTTIME
Initial Conditions:
________ Obtain a copy ofthe necessary electrical print Note: When the Candidate identifies the correct print, provide them with another copy of the print so that they may mark it up. Using C-19859-C Sheet 7, locates RPS 12 manual scram pushbutton Using C-19859-C Sheet 7, identifies relay 12K55 Proper communications used for repeat back (GAP-OPS-Ol)
: 1. None.
Obtains the following documents, as needed: Drawing Index, if needed Drawing C-19859-C Sheet 7 Locates RPS 12 manual scram pushbutton (1 S28) on C-19859-C Sheet 7 near drawing coordinate E-6 Note: This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet. Locates relay 12K55 on C-19859-C Sheet 7 near drawing coordinate E-7 Note: This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet. PasslFail PasslFail NRC 2013 JPM RO-SRO EC May 2013 I Performance Steps Using C-19859-C Sheet 7, identifies contacts 12K55 Using C-19859-C Sheet 7, identifies relays/solenoids 305-139(B) Describes how depressing the RPS 12 manual scram pushbutton on E console results in an RPS half scram I Standard Locates contact 12K55 on C-19859-C Sheet 7 near drawing coordinates F-2, R-2, J-2, and L-2 Note: This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet. Note: The candidate may also identify the contact near drawing coordinate N-2. This is satisfactory but not required, as the task did not require discussion of the backup scram. Locates relays/solenoids 305-139(B) on 19859-C Sheet 7 near drawing coordinates 5/6 through M-5/6 Notes: This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet. The candidate does not have to identify all eight solenoids/relays on this sheet, as long as a representative sample is identified and some indication is given that there are multiple solenoids/relays.
: 2. Ask the operator for any questions.
Describes the following: Depressing RPS 12 manual pushbutton on E console causes 12K55 to Relay 12K55 de-energizing contacts 12K55 to Contacts 12K55 opening causes solenoid/relay 305-139(B) to de-energize at each RCU. The candidate does not have to match description word-for-word, but must all concepts in their Grade PasslFaii PasslFail PasslFail NRC 2013 JPM RO-SRO EC May 2013 Additional SRO Only Cue: Provide SRO candidates the additional SRO only cue sheet and direct them to determine: the surveillance requirement for testing the RPS 12 manual scram pushbutton and the Technical Specification impact if the RPS 12 manual scram pushbutton becomes inoperable. SRO Only: Determines the surveillance requirement for testing the RPS 12 manual scram pushbutton. SRO Only: Determines the Technical Specification impact if the RPS 12 manual scram pushbutton becomes inoperable.
Initiating cue:
Determines the surveillance requirement for testing the RPS 12 manual scram pushbutton is weekly. Determines Technical Specification table 3.6.2.a item (1) is not met. Determines Technical Specification 3.6.2.a.(l) requires control rods to be inserted OR Determines Technical Specification 3 .6.2.a.( 1) requires placing the manual scram circuitry in a tripped condition.
"(Operator's name), using station electrical prints, explain how depressing the RPS 12 manual scram pushbutton on E console results in an RPS channel 12 half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action."
Pass/Fail Pass/Fail TERMINATING CUE: Relays and contacts affected by depressing RPS 12 manual scram pushbutton are identified on station electrical drawings and operation is explained.
: 1. Provide repeat back of initiating cue             Proper communications used for repeat back      SatlUnsat (GAP-OPS-Ol)
RECORDSTOPTIME
Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME ________
_________ NRC 2013 JPM RO-SRO EC May 2013 Initiating cue: "(Operator's name), using station electrical prints, explain how depressing the RPS 12 manual scram pushbutton on E console results in an RPS channel 12 half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action." NRC 2013 JPM RO-SRO EC May 2013 Additional SRO Only Cue Determine the following: the surveillance requirement for testing the RPS 12 manual scram pushbutton and the Technical Specification impact if the RPS 12 manual scram pushbutton becomes inoperable with the plant at 100% power. NRC 2013 JPM RO-SRO May 2013
: 2. Obtain a copy ofthe necessary electrical print     Obtains the following documents, as needed:    SatlUnsati
--------------------
* Drawing Index, if needed                    NA
----NRC JPM SRO C001 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Review NI-ST-DO DAILY CHECKS (Partial)
* Drawing C-19859-C Sheet 7 Note: When the Candidate identifies the correct print, provide them with another copy of the print so that they may mark it up.
Revision:
: 3. Using C-19859-C Sheet 7, locates RPS 12            Locates RPS 12 manual scram pushbutton         PasslFail manual scram pushbutton                         (1 S28) on C-19859-C Sheet 7 near drawing coordinate E-6 Note:
NRC 2013 Task Number: N/A Approvals:
This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.
N/A -Exam Security I General Supervisor' General Supervisor Date Operations Training (Designee)
: 4. Using C-19859-C Sheet 7, identifies relay          Locates relay 12K55 on C-19859-C Sheet 7       PasslFail 12K55                                            near drawing coordinate E-7 Note:
Operations (Designee)
This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.
NIA -Exam Security I Configuration Control Date Performer:
NRC 2013 JPM RO-SRO EC                                                                             May 2013
_______________(SRO) TrainerlEvaluator:
 
Evaluation Method: _--"X'-"--
I Performance Steps                               I Standard                                          Grade
__ Perform _______ Simulate Evaluation Location:
: 5. Using C-19859-C Sheet 7, identifies contacts   Locates contact 12K55 on C-19859-C Sheet 7       PasslFaii 12K55                                        near drawing coordinates F-2, R-2, J-2, and L-2 Note:
Plant X Simulator IClassroom Expected Completion Time: 20 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:
This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.
Evaluator Signature:
Note:
_______________________
The candidate may also identify the contact near drawing coordinate N-2. This is satisfactory but not required, as the task did not require discussion of the backup scram.
_ NRC 2013 JPM SRO COO 1 May 2013 Recommended Start Location: (Completion time based on the start Simulator N/A Directions to the InstructorlEvaluator:
: 6. Using C-19859-C Sheet 7, identifies            Locates relays/solenoids 305-139(B) on C        PasslFail relays/solenoids 305-139(B)                  19859-C Sheet 7 near drawing coordinates F 5/6 through M-5/6 Notes:
* This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.
* The candidate does not have to identify all eight solenoids/relays on this sheet, as long as a representative sample is identified and some indication is given that there are multiple solenoids/relays.
: 7. Describes how depressing the RPS 12            Describes the following:                         PasslFail manual scram pushbutton on E console
* Depressing RPS 12 manual scram results in an RPS half scram                      pushbutton on E console causes relay 12K55 to de-energize.
* Relay 12K55 de-energizing causes contacts 12K55 to open.
* Contacts 12K55 opening causes solenoid/relay 305-139(B) to de-energize at each RCU.
Notes:
The candidate does not have to match this description word-for-word, but must include all concepts in their description.
NRC 2013 JPM RO-SRO EC                                                                           May 2013
 
Additional SRO Only Cue:
Provide SRO candidates the additional SRO only cue sheet and direct them to determine:
* the surveillance requirement for testing the RPS 12 manual scram pushbutton and
* the Technical Specification impact if the RPS 12 manual scram pushbutton becomes inoperable.
: 8. SRO Only: Determines the surveillance             Determines the surveillance requirement for      Pass/Fail requirement for testing the RPS 12 manual         testing the RPS 12 manual scram pushbutton scram pushbutton.                                is weekly.
: 9. SRO Only: Determines the Technical                Determines Technical Specification table        Pass/Fail Specification impact if the RPS 12 manual         3.6.2.a item (1) is not met.
scram pushbutton becomes inoperable.
Determines Technical Specification 3.6.2.a.(l) requires control rods to be inserted OR Determines Technical Specification 3 .6.2.a.( 1) requires placing the manual scram circuitry in a tripped condition.
TERMINATING CUE: Relays and contacts affected by depressing RPS 12 manual scram pushbutton are identified on station electrical drawings and operation is explained.
RECORDSTOPTIME_________
NRC 2013 JPM RO-SRO EC                                                                               May 2013
 
Initiating cue:
"(Operator's name), using station electrical prints, explain how depressing the RPS 12 manual scram pushbutton on E console results in an RPS channel 12 half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action."
NRC 2013 JPM RO-SRO EC                                                         May 2013
 
Additional SRO Only Cue Determine the following:
* the surveillance requirement for testing the RPS 12 manual scram pushbutton and
* the Technical Specification impact if the RPS 12 manual scram pushbutton becomes inoperable with the plant at 100% power.
NRC 2013 JPM RO-SRO EC                                                        May 2013
 
NRC JPM SRO C001 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
Review NI-ST-DO DAILY CHECKS (Partial)                                           Revision: NRC 2013 Task Number:     N/A Approvals:
N/A - Exam Security               I General S u p e r v i s o r '                                       General Supervisor                   Date Operations Training (Designee)                                       Operations (Designee)
NIA - Exam Security                       I Configuration Control                     Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _(SRO)
TrainerlEvaluator:--------------------
Evaluation Method: _--"X'-"--__ Perform           _______ Simulate Evaluation Location: - - - - Plant                         X
                                                  -----"--"'---    Simulator IClassroom Expected Completion Time:       20 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: ________________________
NRC 2013 JPM SRO COO 1                                                                                 May 2013
 
Recommended Start Location: (Completion time based on the start location)
Simulator Simulator Set-up:
N/A Directions to the InstructorlEvaluator:
None Directions to Operators:
None Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance ofthis JPM, I will function as the SM, CRO, and Plant Operators.
For the performance ofthis 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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
With the exception of accessing panels, NO plant equipment will be physically manipulated.
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.
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.
Read Before Each Training JPM Performance:
The Control Supervisor has determined that a verifier is not available and that additional I concurrent verification will be provided; therefore, it should not be Read Before Each Training JPM During this Training JPM, the use of applicable methods of verification and checking are Therefore, either another individual or I will act as the independent verifier or peer checker. Notes to Instructor I Evaluator:  
During this Training JPM, the use of applicable methods of verification and checking are expected.
: 1. Critical steps are identified in grading areas PasslFail.  
Therefore, either another individual or I will act as the independent verifier or peer checker.
Notes to Instructor I Evaluator:
: 1. Critical steps are identified in grading areas PasslFail.
: 2. During Evaluated JPM:
: 2. During Evaluated JPM:
* Self checking shall be demonstrated.  
* Self checking shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self checking shall be demonstrated.
* Self checking shall be demonstrated.
* Peer checking shall be demonstrated.  
* Peer checking shall be demonstrated.


==References:==
==References:==
: 1. NUREG 1123,2.1.7, SRO 4.7 2. NI-ST-DO 3. Technical Specifications NRC 2013 JPM SRO COO 1 May 2013 Tools and Equipment:
: 1. NUREG 1123,2.1.7, SRO 4.7
Provide copy ofNl-ST-DO with Attachment 4 section 6.0 and step 8.4 completed with the following values: Attachment 4 section 6.0: Low-Low Level Alarms -Checked "NO" Feedwater Level Column -Checked "11" E-Panel Vessel Level Indicator  
: 2. NI-ST-DO
-72" K-Panel Vessel Level Indicator  
: 3. Technical Specifications NRC 2013 JPM SRO COO 1                                                                                 May 2013
-72" K-Panel Flange Level Indicator  
 
-DOWNSCALE Reactor Vessel Level Recorder -71 " Wide Range Level Indicator 7' GEMAC Level Column (Ch 11112) 71" / 79" GEMAC Level Computer Points (Ch 11112) -71.344" / 79.051" Pi Calculated GEMAC level column difference 7.680" RPS Level Column (Ch 11112) 73"/76" Yarway (RPS) Level Column 73.125"/75.763" Pi Calculated Yarway level column difference  
Tools and Equipment:
-2.770" GEMAC variance -8" Computer point variance -7.707" Total Recirc Flow -38.0 Mlbmlhr Step 8.4: Check "Pi-Calculated GEMAC Level Delta" Check "Acceptable Range" Task Standard:
Provide copy ofNl-ST-DO with Attachment 4 section 6.0 and step 8.4 completed with the following values: section 6.0:
Control room RPV water level instrument surveillance per NI-ST-DO is reviewed.
Low-Low Level Alarms - Checked "NO" Feedwater Level Column - Checked "11" E-Panel Vessel Level Indicator - 72" K-Panel Vessel Level Indicator -72" K-Panel Flange Level Indicator - DOWNSCALE Reactor Vessel Level Recorder - 71 "
Out of spec results are identified and the appropriate Technical Specification is determined.
Wide Range Level Indicator 7' GEMAC Level Column (Ch 11112) 71" / 79" GEMAC Level Computer Points (Ch 11112) -71.344" / 79.051" Pi Calculated GEMAC level column difference 7.680" RPS Level Column (Ch 11112) 73"/76" Yarway (RPS) Level Column 73.125"/75.763" Pi Calculated Yarway level column difference - 2.770" GEMAC variance - 8" Computer point variance -7.707" Total Recirc Flow - 38.0 Mlbmlhr Step 8.4:
Check "Pi-Calculated GEMAC Level Delta" Check "Acceptable Range" Task Standard: Control room RPV water level instrument surveillance per NI-ST-DO is reviewed. Out of spec results are identified and the appropriate Technical Specification is determined.
Initial Conditions:
Initial Conditions:
I. The plant is operating at approximately 67% power. 2. NI-ST-DO, Daily Checks, is in progress.  
I.       The plant is operating at approximately 67% power.
: 3. Operators have completed the RPV water level instrument readings.  
: 2.       NI-ST-DO, Daily Checks, is in progress.
: 4. Instructor to ask the operator for any questions.
: 3.       Operators have completed the RPV water level instrument readings.
Initiating cue: "(Operator's name), perform SRO review of the following section ofNl-ST-DO:
: 4.       Instructor to ask the operator for any questions.
Initiating cue:
"(Operator's name), perform SRO review of the following section ofNl-ST-DO:
* Attachment 4 section 6.0
* Attachment 4 section 6.0
* Step 8.4 When completed, report findings to the Examiner." NRC 2013 JPM SRO COO 1 May 2013 I Performance I Standard Grade Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)
* Step 8.4 When completed, report findings to the Examiner."
Evaluator acknowledge repeat back providing correction if necessary
NRC 2013 JPM SRO COO 1                                                                         May 2013
________ Obtain a copy of the reference procedure and NI-ST-DO obtained SatlUnsat review/utilize the correct section Review Attachment 4 section 6.0 readings Reviews Attachment 4 section 6.0 readings SatlUnsat and Step 8.4 Identifies error in Step 8.4 Identifies that GEMAC Level Column PasslFail Variance is in the !NOP range If Candidate asks for prior readings for comparison, or for Engineering evaluation, report that plant data GEMAC 11 is trending normally and GEMAC 12 indicates higher than Determines GEMAC 12 level indicator is Determines GEMAC 12 level indicator is PasslFail inoperable inoperable Determines Technical Specification impact Determines a 15 day LCO applies per PasslFail Technical Specification 3.l.8 Provides completed sections to Examiner Proper communications used (GAP-OPS-Ol)
 
SatlUnsat and informs of out of spec readings TERMINATING CUE: Control room RPV water level instrument surveillance per Nl-ST-DO is reviewed.
I Performance Steps                                  I Standard                                               Grade
Out of spec results are identified and the appropriate Technical Specification is determined.
: 1. Provide repeat back of initiating cue             Proper communications used for repeat back             SatlUnsat (GAP-OPS-Ol)
RECORDSTOPTIME
Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTT~E              ________
_________ NRC 2013 JPM SRO COOl -May 2013 Initial Conditions:  
: 2. Obtain a copy of the reference procedure and     NI-ST-DO obtained                                     SatlUnsat review/utilize the correct section
: 1. The plant is operating at approximately 670/0 power. 2. Nl-ST-DO, Daily Checks, is in progress.  
: 3. Review Attachment 4 section 6.0 readings         Reviews Attachment 4 section 6.0 readings             SatlUnsat and Step 8.4
: 3. Operators have completed the RPV water level instrument readings.
: 4. Identifies error in Step 8.4                     Identifies that GEMAC Level Column                     PasslFail Variance is in the !NOP range Cue:
Initiating "(Operator's name), perform SRO review of the following section
If Candidate asks for prior readings for comparison, or for Engineering evaluation, report that plant data indicates GEMAC 11 is trending normally and GEMAC 12 indicates higher than expected.
: 5. Determines GEMAC 12 level indicator is           Determines GEMAC 12 level indicator is                 PasslFail inoperable                                       inoperable
: 6. Determines Technical Specification impact         Determines a 15 day LCO applies per                   PasslFail Technical Specification 3.l.8
: 7. Provides completed sections to Examiner           Proper communications used (GAP-OPS-Ol)               SatlUnsat and informs of out of spec readings TERMINATING CUE: Control room RPV water level instrument surveillance per Nl-ST-DO is reviewed. Out of spec results are identified and the appropriate Technical Specification is determined.
RECORDSTOPTIME_________
NRC 2013 JPM SRO COOl                                                                                 May 2013
 
Initial Conditions:
: 1.     The plant is operating at approximately 670/0 power.
: 2.     Nl-ST-DO, Daily Checks, is in progress.
: 3.     Operators have completed the RPV water level instrument readings.
Initiating cue:
"(Operator's name), perform SRO review of the following section ofNI-ST-DO:
* Attachment 4 section 6.0
* Attachment 4 section 6.0
* Step 8.4 When completed, report findings to the Examiner." NRC 2013 JPM SRO COOl May 2013 NRC JPM SRO C002 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Assess Reportability Requirements Revision:
* Step 8.4 When completed, report findings to the Examiner."
NRC 2013 Task Number: NtA Approvals:
NRC 2013 JPM SRO COOl                                                   May 2013
NtA -Exam Security General Supervisor Date General Supervisor Date Operations Training (Designee)
 
Operations (Designee)
NRC JPM SRO C002 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
NtA -Exam Security Configuration Control Date Performer:
 
_______________TrainerlEvaluator:
==Title:==
____________Evaluation Method: _----'X'-"--
Assess Reportability Requirements                                           Revision: NRC 2013 Task Number: NtA Approvals:
__ Perform ______
NtA - Exam Security General Supervisor               Date                     General Supervisor                         Date Operations Training (Designee)                             Operations (Designee)
Evaluation Location:
NtA - Exam Security Configuration Control           Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _(SRO)
____ Plant Simulator or other Expected Completion Time: 40 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:
TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __
Evaluator Signature:
Evaluation Method: _----'X'-"--__ Perform         _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant                ----"-"'--
_______________
Simulator or other location Expected Completion Time:       40 minutes       Time Critical Task:       No     Alternate Path Task:     No Start Time: - - - -             Stop Time: _ _ _ __                Completion Time: _ _ _ __
_ Date:_______ NRC 2013 JPM SRO C002 May 2013 Recommended Start Location: (Completion time based on the start location)
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 2013 JPM SRO C002                                                                                   May 2013
 
Recommended Start Location: (Completion time based on the start location)
Classroom Simulator Set-up: N/A Directions to the InstructorlEvaluator:
Classroom Simulator Set-up: N/A Directions to the InstructorlEvaluator:
None Directions to Operators:
None Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
With the exception of accessing panels, NO plant equipment will be physically manipulated.
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.
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:
Read Before Each Training JPM Performance:
During this Training JPM, the use of applicable methods of verification and checking are expected.
During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.
either another individual or I will act as the independent verifier or peer Notes to Instructor I  
Notes to Instructor I Evaluator:
: 1. Critical steps are identified in grading areas PasslFaii.  
: 1. Critical steps are identified in grading areas PasslFaii.
: 2. During Evaluated JPM:
: 2. During Evaluated JPM:
* Self checking shall be demonstrated.  
* Self checking shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self checking shall be demonstrated.
* Self checking shall be demonstrated.
* Peer checking shall be demonstrated.  
* Peer checking shall be demonstrated.
: 4. Verify the references below are available to the candidate.  
: 4. Verify the references below are available to the candidate.


==References:==
==References:==
: 1. CNG-NL-1.01-1004  
: 1. CNG-NL-1.01-1004
: 2. 10CFR50.72  
: 2. 10CFR50.72
: 3. NUREG 1022 4. EAL Matrix 5. EAL Bases NRC 2013 JPM SRO C002 May 2013 2 Tools and Equipment:
: 3. NUREG 1022
None Task Standard:
: 4. EAL Matrix
Determine 10 CFR 50.72 reportability requirements.
: 5. EAL Bases NRC 2013 JPM SRO C002                                                                                   May 2013
Initial Conditions: The plant was operating at 100% power with no equipment out of service. A loss of offsite power Lines 1 and 4 occurred one hour ago. Emergency Diesel Generator (EDG) 102 failed to start and has been declared inoperable. Maintenance reports that repairs to EDG 102 will take several days. Power Control reports Line 1 will be returned to service in approximately 12 hours, and Line 4 will be returned to service in approximately 24 hours. Instructor to ask Candidate for any questions.
 
Initiating cue: "(Operator's name), list the applicable 10 CFR 50.72 reportability requirements, the reason that they apply and the associated time limitations for reporting under that category.
Tools and Equipment:
Record your findings on the sheet provided." Provide repeat back of initiating cue. Proper communications used for repeat back SatlUnsat Evaluator Acknowledge repeat back (GAP-OPS-Ol) providing correction if necessary RECORDSTARTTDdE
None Task Standard: Determine 10 CFR 50.72 reportability requirements.
____________
Initial Conditions:
_____ Obtain a copy of the any ofthe reference Reference materials obtained as necessary.
: 1. The plant was operating at 100% power with no equipment out of service.
documents related to regulatory These are likely to include the
: 2. A loss of offsite power Lines 1 and 4 occurred one hour ago.
: 3. Emergency Diesel Generator (EDG) 102 failed to start and has been declared inoperable.
: 4. Maintenance reports that repairs to EDG 102 will take several days.
: 5. Power Control reports Line 1 will be returned to service in approximately 12 hours, and Line 4 will be returned to service in approximately 24 hours.
: 6. Instructor to ask Candidate for any questions.
Initiating cue:
        "(Operator's name), list the applicable 10 CFR 50.72 reportability requirements, the reason that they apply and the associated time limitations for reporting under that category. Record your findings on the sheet provided."
: 1. Provide repeat back of initiating cue.           Proper communications used for repeat back         SatlUnsat Evaluator Acknowledge repeat back               (GAP-OPS-Ol) providing correction if necessary RECORDSTARTTDdE _________________
2    Obtain a copy of the any ofthe reference         Reference materials obtained as necessary.         SatlUnsat documents related to regulatory notifications.
These are likely to include the following:
* CNG-NL-l.OI-I004
* CNG-NL-l.OI-I004
* 10 CFR 50.72 and 50.73
* 10 CFR 50.72 and 50.73
* NUREG 1022
* NUREG 1022
* EAL Matrix
* EAL Matrix
* EAL Bases Locate and identify applicability of 10 CFR Identifies plant conditions require Emergency SatlUnsat 50.72(a)(I)
* EAL Bases
Classification per Alert EAL 6.1.3 Note: Candidate must recognize that a loss of Identifies reportability per 50.72(a)(I), for PasslFail offsite power with a failure of an EDG to start declaration of any of the Emergency Classes, requires Emergency Classification (Alert EAL within one hour 6.1.3). The exact classification is not critical for the purposes of this JPM. Event classification will be tested in more detail in other exam items. NRC 2013 JPM SRO C002 -1 May 2013 I Performance Steps Locate and identify applicability of 50.72(b)(2)(i).
: 3. Locate and identify applicability of 10 CFR       Identifies plant conditions require Emergency     SatlUnsat 50.72(a)(I)                                     Classification per Alert EAL 6.1.3 Note: Candidate must recognize that a loss of         Identifies reportability per 50.72(a)(I), for     PasslFail offsite power with a failure of an EDG to start       declaration of any ofthe Emergency Classes, requires Emergency Classification (Alert EAL         within one hour 6.1.3). The exact classification is not critical for the purposes ofthis JPM. Event classification will be tested in more detail in other exam items.
Non-emergency four hour report. Initiation of a plant shutdown required by Tech Specs. Locate and identify applicability of 50.72(b)(3)(iv)(A)
NRC 2013 JPM SRO C002                                                                                 May 2013
Non-emergency eight hour report. Event or condition results in valid actuation of Emergency Diesel Generator. Locate and identify applicability of 50.72(b)(3)(v)(D)
 
Non-emergency eight hour report. Event or condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident.
I Performance Steps                                   I Standard                                          Grade
Note: This step is deemed non-critical because of the redundancy with other reports and the subjective nature of this call. I Standard Refers to Tech Spec 3.6.3 .e(1) and determines that with specification not being met, the required action is to initiate a shutdown within one hour and be in cold shutdown within 10 hours. Identifies reportability per 50.72(b)(2)(i), for initiation of a plant shutdown required by Tech Specs, within four hours Identifies reportability per 50. 72(b )(3)(iv)(A) (or may alternately reference 50.72(b)(3)(iv)(B)(8), for valid actuation of Emergency Diesel Generator, within 8 hours Identifies reportability per 50.72(b)(3)(v)(D) for an event or condition that could have prevented fulfillment of a safety function needed to mitigate the consequences of an accident (loss of both offsite power lines, failure ofEDG 102), within 8 hours Grade SatlUnsat Pass/Fail Pass/Fail SatlUnsat TERMINATING CUE: Reportability requirements have been determined.
: 4. Locate and identify applicability of               Refers to Tech Spec 3.6.3 .e(1) and determines  SatlUnsat 50.72(b)(2)(i). Non-emergency four hour           that with specification not being met, the report. Initiation of a plant shutdown required  required action is to initiate a shutdown within by Tech Specs.                                    one hour and be in cold shutdown within 10 hours.
RECORDSTOPTIME
Identifies reportability per 50.72(b)(2)(i), for Pass/Fail initiation of a plant shutdown required by Tech Specs, within four hours
_________ NRC 2013 JPM SRO C002 -1 May 2013 Initial Conditions: The plant was operating at 100% power with no equipment out of service. A loss of offsite power Lines 1 and 4 occurred one hour ago. 3. Emergency Diesel Generator (EDG) 102 failed to start and has been declared inoperable. Maintenance reports that repairs to EDG 102 will take several days. Power Control reports Line 1 will be returned to service in approximately 12 hours, and Line 4 will be returned to service in approximately 24 hours. Initiating cue: "(Operator's name), list the applicable 10 CFR 50.72 reportability requirements, the reason that they apply and the associated time limitations for reporting under that category.
: 5. Locate and identify applicability of              Identifies reportability per 50. 72(b)(3)(iv)(A) Pass/Fail 50.72(b)(3)(iv)(A) Non-emergency eight          (or may alternately reference hour report. Event or condition results in        50.72(b)(3)(iv)(B)(8), for valid actuation of valid actuation of Emergency Diesel              Emergency Diesel Generator, within 8 hours Generator.
Record your findings on the sheet provided." NRC 2013 JPM SRO C002 -1 May 2013
: 6. Locate and identify applicability of              Identifies reportability per 50.72(b)(3)(v)(D)   SatlUnsat 50.72(b)(3)(v)(D) Non-emergency eight hour        for an event or condition that could have report. Event or condition that could have        prevented fulfillment of a safety function prevented fulfillment of a safety function       needed to mitigate the consequences of an needed to mitigate the consequences of an         accident (loss of both offsite power lines, accident.                                        failure ofEDG 102), within 8 hours Note: This step is deemed non-critical because of the redundancy with other reports and the subjective nature of this call.
--------------------
TERMINATING CUE: Reportability requirements have been determined.
NRC JPM SRO RC Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Detennine Actions for Inoperable Stack Radiation Monitor Revision:
RECORDSTOPTIME _________
NRC 2013 Task Number: N/A Approvals:
NRC 2013 JPM SRO C002                                                                             May 2013
NIA -Exam Security General Supervisor Date General Supervisor Date Operations Training (Designee)
 
Operations (Designee)
Initial Conditions:
NIA -Exam Security Configuration Control Date Perfonner:.
: 1. The plant was operating at 100% power with no equipment out of service.
_______________(SRO) TrainerlEvaluator:
: 2. A loss of offsite power Lines 1 and 4 occurred one hour ago.
Evaluation Method: Perfonn Evaluation Location:
: 3. Emergency Diesel Generator (EDG) 102 failed to start and has been declared inoperable.
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 offail shall be given if any critical step is graded as fail. Any grade of un sat or individual competency area unsat requires a comment. Comments:
: 4. Maintenance reports that repairs to EDG 102 will take several days.
Evaluator  
: 5. Power Control reports Line 1 will be returned to service in approximately 12 hours, and Line 4 will be returned to service in approximately 24 hours.
...,.c"...."....,*.-----______________
Initiating cue:
_ Date:_______ NRC 2013 JPM SRO RC May 2013 Recommended Start Location:
        "(Operator's name), list the applicable 10 CFR 50.72 reportability requirements, the reason that they apply and the associated time limitations for reporting under that category. Record your findings on the sheet provided."
Classroom Simulator Set-up: None Directions to the InstructorlEvaluator:
NRC 2013 JPM SRO C002                                                           May 2013
None Directions to Operators:
 
NRC JPM SRO RC Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
Detennine Actions for Inoperable Stack Radiation Monitor                     Revision: NRC 2013 Task Number: N/A Approvals:
NIA - Exam Security General Supervisor                     Date                   General Supervisor                       Date Operations Training (Designee)                               Operations (Designee)
NIA - Exam Security Configuration Control                 Date Perfonner:._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (SRO)
TrainerlEvaluator:--------------------
Evaluation Method: Perfonn 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 offail shall be given if any critical step is graded as fail. Any grade of un sat or individual competency area unsat requires a comment.
Comments:
Evaluator ...,.c"....".... ,*.-----_ _ _ _ _ _ _ _ _ _ _ _ _ __                Date:_ _ _ _ _ __
NRC 2013 JPM SRO RC                                                                                     May 2013
 
Recommended Start Location: Classroom Simulator Set-up: None Directions to the InstructorlEvaluator: None Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identifY the steps to be simulated, or discuss and provide cues as With the exception of accessing panels, NO plant equipment will be physically manipulated.
Read Before Each Evaluated JPM Performance:
Repositioning 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.
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.
The Control Supervisor has determined that a verifier is not available and that additional/concurrent verification will not provided; therefore, it should not be Read Before Each Training JPM During this Training JPM, the use of applicable methods of verification and checking are expected.
Read Before Each Training JPM Performance:
either another individual or I will act as the independent verifier or peer Notes to Instructor  
During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.
/  
Notes to Instructor / Evaluator:
: 1. Critical steps are identified in grading areas Pass/Fail.  
: 1. Critical steps are identified in grading areas Pass/Fail.
: 2. During Evaluated JPM:
: 2. During Evaluated JPM:
* Self checking shall be demonstrated.  
* Self checking shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self checking shall be demonstrated.
* Self checking shall be demonstrated.
* Peer checking shall be demonstrated.  
* Peer checking shall be demonstrated.


==References:==
==References:==
: 1. ARP Hl-3-8 2. NI-OP-50B  
: 1. ARP Hl-3-8
: 3. ODCM 3.6.14.b and TBL D 3.6.14-2 4. NUREG 1123 KIA 2.3.11 (4.3) Tools and Equipment:  
: 2. NI-OP-50B
: 1. None Task Standard:
: 3. ODCM 3.6.14.b and TBL D 3.6.14-2
Determine actions per ARP Hl-3-8 and ODCM in response to stack radiation monitor downscale condition.
: 4. NUREG 1123 KIA 2.3.11 (4.3)
NRC 2013 JPM SRO RC May 2013 Initial Conditions: The plant is operating at 100% power. Annunciator HI-3-8, STACK GAS MONITORING TROUBLE, has alarmed. Computer Point C061, OGESMS RAD MON STATUS -TRBL, is in alarm. OGESMS radiation monitor RN-I OA indicates downscale. Ask the operator for any questions.
Tools and Equipment:
Initiating cue: "(Operator's name), determine the appropriate actions and compensatory measures in response to ARP Hl-3-8. Record your findings on the provided attachment." EXAMINER NOTE: Provide Attachment  
: 1. None Task Standard: Determine actions per ARP Hl-3-8 and ODCM in response to stack radiation monitor downscale condition.
: 2. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary
NRC 2013 JPM SRO RC                                                                                     May 2013
_______ Obtain a copy of the reference procedure and review/utilize the correct section. Determines actions per ARP Hl-3-8. Determines actions per ODCM. Proper communications used repeat back ARP HI 8 Operator Actions ODCM DLCO 3.6.14 Table D 3.6.14-2 Determines Chemistry implement NI-CSP-V309, Monitor Alarm Determines the 8 Drywell and Vent and Purge valves must verified CLOSED and a Clearance Section must be Determines one Stack Monitoring Noble Gas Activity Range Monitor is Determines ODCM Table D Instruments l.a.( 1) have one less the minimum number of SatlUnsat SatlUnsat PasslFaii Pass/Fail SatlUnsat SatlUnsat NRC 2013 JPM SRO RC -3 May 2013 Detennines ODCM Table D 3.6.14-2 note (a)(1) applies -With the number of channels functional 1 less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided: (a) The nonfunctional channel is placed in the tripped (b) Vent and Purge valves are closed and administratively (c) Primary containment integrity is not required.
 
Detennines DLCO 3.6.14.b Restore the instruments to functional status within 30 days or outline in the next Radioactive Effluent Release Report the cause of the non-functionality and how the instruments were or will be restored to functional status. PasslFail PasslFail TERMINATING CUE: Actions have been detennined per ARP Hl-3-8 and ODCM in response to stack radiation monitor downscale condition.
Initial Conditions:
RECORDSTOPTIME
: 1. The plant is operating at 100% power.
_________ NRC 2013 JPM SRO RC May 2013 Initial Conditions:  
: 2. Annunciator HI-3-8, STACK GAS MONITORING TROUBLE, has alarmed.
: 1. The plant is operating at 100% power. 2. Annunciator Hl-3-8, STACK GAS MONITORING TROUBLE, has alarmed. 3. Computer Point C061, OGESMS RAD MON STATUS -TRBL, is in alarm. 4. OGESMS radiation monitor RN-l OA indicates downscale.
: 3. Computer Point C061, OGESMS RAD MON STATUS - TRBL, is in alarm.
Initiating cue: "(Operator's name), determine the appropriate actions and compensatory measures in response to ARP Hl-3-8. Record your findings on the provided attachment." NRC 2013 JPM SRO RC May 2013 NRC ..IPM SRO Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Post-Scenario Emergency Event Classification Revision:
: 4. OGESMS radiation monitor RN-I OA indicates downscale.
NRC Task Number: NI NIA -Exam General Supervisor " Date General Supervisor Operations Training (Designee)
: 5. Ask the operator for any questions.
Operations Configuration Control Date ,__________TrainerlEvaluator:
Initiating cue:
__________Evaluation Method: Evaluation Location:
        "(Operator's name), determine the appropriate actions and compensatory measures in response to ARP Hl-3-8. Record your findings on the provided attachment."
Expected Completion Time: 15 minutes Time Critical Task: Yes 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. Any grade of unsat or individual competency area unsat requires a comment. Comments:
EXAMINER NOTE: Provide Attachment 2.
Evaluator Signature:
: 1. Provide repeat back of initiating cue. Proper communications used for                  SatlUnsat Evaluator Acknowledge repeat back       repeat back (GAP-OPS-Ol) providing correction if necessary RECORDSTARTT~                _______
_______.________ NRC 2013 JPM SRO EP May 2013 Recommended Start Location:
: 1. Obtain a copy of the reference           ARP HI 8 obtained.                          SatlUnsat procedure and review/utilize the         Operator Actions referenced.
Classroom/Simulator Simulator Set-up: None Directions to the InstructorlEvaluator:
correct section.
None Directions to Operators:
ODCM obtained.
Read Before Every JPM For the performance of this JPM, I will function as the Unit 2 SM, Security Supervisor, Communication and other personnel as necessary.
DLCO 3.6.14 referenced.
Prior to providing direction to perform this task, I will provide you with initial conditions and answer any questions.
Table D 3.6.14-2 referenced.
During task performance, I will identify the steps to be 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.
: 2. Determines actions per ARP Hl-3-8.        Determines Chemistry should                    PasslFaii implement NI-CSP-V309, Stack Monitor Alarm Response.
The Control Supervisor has determined that a verifier is not available and that additional!
Determines the 8 Drywell and Torus              Pass/Fail Vent and Purge valves must be verified CLOSED and a Caution Clearance Section must be applied.
concurrent verification will not be provided; therefore it should not be requested.
: 3. Determines actions per ODCM.              Determines one Stack Effluent                  SatlUnsat Monitoring Noble Gas Activity High Range Monitor is inoperable.
Read Before Each Training JPM During this Training lPM, applicable methods of verification are expected to be used. Therefore, another individual or I will act as the additional!
Determines ODCM Table D 3.6.14-2                SatlUnsat Instruments l.a.( 1) have one less than the minimum number of functional channels.
concurrent Notes to Instructor!
NRC 2013 JPM SRO RC                                                                               May 2013
Evaluator:  
 
: 1. Critical steps are identified as PasslFaii.  
Detennines ODCM Table D 3.6.14-2       PasslFail note (a)(1) applies - With the number of channels functional 1 less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided:
(a) The nonfunctional channel is placed in the tripped condition, OR (b) Vent and Purge valves are closed and administratively controlled, OR (c) Primary containment integrity is not required.
Detennines DLCO 3.6.14.b requires        PasslFail Restore the instruments to functional status within 30 days or outline in the next Radioactive Effluent Release Report the cause of the non-functionality and how the instruments were or will be restored to functional status.
TERMINATING CUE: Actions have been detennined per ARP Hl-3-8 and ODCM in response to stack radiation monitor downscale condition.
RECORDSTOPTIME_________
NRC 2013 JPM SRO RC                                                                 May 2013
 
Initial Conditions:
: 1. The plant is operating at 100% power.
: 2. Annunciator Hl-3-8, STACK GAS MONITORING TROUBLE, has alarmed.
: 3. Computer Point C061, OGESMS RAD MON STATUS - TRBL, is in alarm.
: 4. OGESMS radiation monitor RN-l OA indicates downscale.
Initiating cue:
        "(Operator's name), determine the appropriate actions and compensatory measures in response to ARP Hl-3-8. Record your findings on the provided attachment."
NRC 2013 JPM SRO RC                                                         May 2013
 
NRC ..IPM SRO EP Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
Post-Scenario Emergency Event Classification                               Revision: NRC 2013 Task Number: NIA Approvals:
NIA - Exam Security General Supervisor Operations Training (Designee)
                                    "   Date             General Supervisor Operations (Designee)
Date Configuration Control                   Date
            ,_ _ _ _ _ _ _ _ _ _ (SRO)
TrainerlEvaluator:_ _ _ _ _ _ _ _ _ __
Evaluation Method: Perform Evaluation Location: Simulator Expected Completion Time: 15 minutes             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: _ _ _ _ _ _ _._ _ _ _ _ _ __
NRC 2013 JPM SRO EP                                                                                   May 2013
 
Recommended Start Location: Classroom/Simulator Simulator Set-up: None Directions to the InstructorlEvaluator: None Directions to Operators:
Read Before Every JPM Performance:
For the performance ofthis JPM, I will function as the Unit 2 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 ofyour 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 lPM, 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:
: 1. Critical steps are identified as PasslFaii.
: 2. During Evaluated lPM:
: 2. During Evaluated lPM:
* Self-verification shall be demonstrated.  
* Self-verification shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self-verification shall be demonstrated.
* Self-verification shall be demonstrated.
* No other verification shall be demonstrated.  
* No other verification shall be demonstrated.


==References:==
==References:==
: 1. NUREG 1123, 2.4.29, SRO 2.  
: 1. NUREG 1123, 2.4.29, SRO 4.4
: 3.  
: 2. EPlP-EPP-OI
: 4.
: 3. EPlP-EPP-18
Tools and  
: 4. EPMP-EPP-OIOI Tools and Equipment:
: 1. EPlP-EPP-OI, ATTACHMENT 1, UNIT 1 EAL  
: 1. EPlP-EPP-OI, ATTACHMENT 1, UNIT 1 EAL FLOWCHART
: 2. SMIED Checklist Task Classify the emergency event based on the final scenario conditions within 15 minutes of the JPM start NRC 2013 JPM SRO EP May 2013
: 2. SMIED Checklist Package Task Standard:
---------Initial Conditions: None Instructor to ask the operator for any questions.
Classify the emergency event based on the final scenario conditions within 15 minutes of the JPM start time.
Initiating Cue: "(Operator's name), based on the events that have just occurred, determine if the conditions warranted emergency classification.
NRC 2013 JPM SRO EP                                                                                     May 2013
If so, determine the appropriate emergency classification.
 
This is a time critical task. Your time starts now." Provide repeat back of initiating cue Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME
Initial Conditions:
_______ Obtain a copy of EPlP-EPP-O 1 attachments 1 and 2, and Shift Manager emergency paperwork and review/utilize the correct section Reviews plant conditions and determines if emergency classification is warranted. Classifies the emergency for 2013 NRC Scenario # 1. Examiner Note: The listed EAL is the expected EAL based on scenario validation.
: 1. None
If scenario deviates from the expected course, examiner discretion will be required to determine the actual classification.
: 2. Instructor to ask the operator for any questions.
Proper communications used for repeat back (GAP-OPS-Ol)
Initiating Cue:
EPlP-EPP-Ol attachments 1 and 2, and Shift Manager emergency paperwork is obtained Determines an emergency classification is required.
        "(Operator's name), based on the events that have just occurred, determine if the conditions warranted emergency classification. If so, determine the appropriate emergency classification. This is a time critical task. Your time starts now."
Determines the emergency classification level is Alert. Determines the Emergency Action Level (EAL) designator is EXAMINER NOTE: Time difference must be 15 minutes or JPM start Time of SatlUnsat SatlUnsat SatlUnsat NRC 2013 JPM SRO EP May 2013
: 1. Provide repeat back of initiating cue             Proper communications used for repeat back          SatlUnsat (GAP-OPS-Ol)
-------------------I Performance Steps Classifies the emergency for 2013 Scenario Examiner Note: The listed EAL is the expected EAL based on scenario validation.
Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME _______
If scenario deviates from the expected course, examiner discretion will be required to determine the actual classification. Classifies the emergency for 2013 NRC Scenario #3. Examiner Note: The listed EAL is the expected EAL based on scenario validation.
: 2. Obtain a copy of EPlP-EPP-O 1 attachments 1     EPlP-EPP-Ol attachments 1 and 2, and Shift        SatlUnsat and 2, and Shift Manager emergency               Manager emergency paperwork is obtained paperwork and review/utilize the correct section
If scenario deviates from the expected course, examiner discretion will be required to determine the actual classification. Classifies the emergency for 2013 NRC Scenario #4. Examiner Note: The listed EAL is the expected EAL based on scenario validation.
: 3. Reviews plant conditions and determines if       Determines an emergency classification is          SatlUnsat emergency classification is warranted.          required.
If scenario deviates from the expected course, examiner discretion will be required to determine the actual classification.
: 4. Classifies the emergency for 2013 NRC             Determines the emergency classification level is    PasslFaill Scenario # 1.                                   Alert.                                                NA Examiner Note: The listed EAL is the expected EAL based on scenario validation. If scenario       Determines the Emergency Action Level (EAL)        PasslFaill deviates from the expected course, examiner         designator is 3.1.1.                                  NA discretion will be required to determine the actual classification.                               EXAMINER NOTE: Time difference below must be 15 minutes or less:
I Standard Determines the emergency classification level is Site Area Emergency.
JPM start time: - - - -
Determines the Emergency Action Level (EAL) designator is 3.4.1 and/or EXAMINER NOTE: Time difference must be 15 minutes or JPM start Time of Determines the emergency classification level is Site Area Emergency.
Time of Classification: - - - - -
Determines the Emergency Action Level (EAL) designator is EXAMINER NOTE: Time difference must be 15 minutes or JPM start time: ___Time of Determines the emergency classification level is Site Area Emergency.
NRC 2013 JPM SRO EP                                                                                   May 2013
Determines the Emergency Action Level (EAL) designator is EXAMINER NOTE: Time difference must be 15 minutes or JPM start time: ___Time of Grade PasslFaill NA NRC 2013 JPM SRO EP May 2013
 
---------I Performance Steps Classifies the emergency for 2013 Scenario Examiner Note: The listed EAL is the expected EAL based on scenario validation.
I Performance Steps                             I Standard                                          Grade
If scenario deviates from the expected course, examiner discretion will be required to determine the actual classification.
: 5. Classifies the emergency for 2013 NRC        Determines the emergency classification level is PasslFaill Scenario #2.                                Site Area Emergency.                                NA Examiner Note: The listed EAL is the expected   Determines the Emergency Action Level (EAL)      PasslFaill EAL based on scenario validation. If scenario   designator is 3.4.1 and/or 4.1.1.                  NA deviates from the expected course, examiner discretion will be required to determine the   EXAMINER NOTE: Time difference below actual classification.                          must be 15 minutes or less:
I Standard Determines the emergency classification level is Alert. Determines the Emergency Action Level (EAL) designator is EXAMINER NOTE: Time difference must be 15 minutes or JPM start time: Time of Classification:
JPM start time: - - - -
Grade TERMINATING CUE: Emergency classification requirement is determined.
Time of Classification: - - - - -
RECORDSTOPTIME
: 6. Classifies the emergency for 2013 NRC       Determines the emergency classification level is PasslFaill Scenario #3.                               Site Area Emergency.                                NA Examiner Note: The listed EAL is the expected   Determines the Emergency Action Level (EAL)      PasslFaill EAL based on scenario validation. If scenario   designator is 2.2.2.                                NA deviates from the expected course, examiner discretion will be required to determine the   EXAMINER NOTE: Time difference below actual classification.                          must be 15 minutes or less:
_________ NRC 2013 JPM SRO EP May 2013 Initiating Cue: "(Operator's name), based on the events that have just occurred, determine if the conditions warranted emergency classification.
JPM start time: _ _ __
If so, determine the appropriate emergency classification.
Time of Classification: - - - - -
This is a time critical task. Your time starts now." NRC 2013 JPM SRO EP May 2013 NRC JPM 8-1 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Rapid RWCU System Restoration for Level Control Revision:
: 7. Classifies the emergency for 2013 NRC       Determines the emergency classification level is PasslFaiU Scenario #4.                               Site Area Emergency.                                NA Examiner Note: The listed EAL is the expected EAL based on scenario validation. If scenario   Determines the Emergency Action Level (EAL)      PasslFaiU deviates from the expected course, examiner     designator is 2.1.1.                                NA discretion will be required to determine the actual classification.                         EXAMINER NOTE: Time difference below must be 15 minutes or less:
NRC 2013 Task Number: N/A Approvals:
JPM start time: _ _ __
N/ A -Exam Security I General Supervisor  
Time of Classification: - - - - -
-Date General Supervisor Date Operations Training (Designee)
NRC 2013 JPM SRO EP                                                                             May 2013
Operations (Designee)
 
Configuration Control Date Performer:.
I Performance Steps                             I Standard                                          Grade
_______________
: 8. Classifies the emergency for 2013 NRC        Determines the emergency classification level is PasslFaill Scenario #5.                                Alert.                                              NA Examiner Note: The listed EAL is the expected   Determines the Emergency Action Level (EAL)      PasslFaill EAL based on scenario validation. If scenario   designator is 3.1.1.                                NA deviates from the expected course, examiner discretion will be required to determine the   EXAMINER NOTE: Time difference below actual classification.                          must be 15 minutes or less:
(,RO/SRO)
JPM start time: - - - -
TrainerlEvaluator:
Time of Classification: - - - - -
____________
TERMINATING CUE: Emergency classification requirement is determined.
_ Evaluation Method: __Perform ______ Simulate Evaluation Location:
RECORDSTOPTIME_________
____ Plant __
NRC 2013 JPM SRO EP                                                                             May 2013
__ Simulator Expected Completion Time: 20 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 ofunsat or individual competency area unsat requires a comment. Comments:
 
Evaluator's Date:_______ NRC 2013 JPM S-l -I -May 2013 Recommended Start Location:
Initiating Cue:
Simulator Simulator Set-up (if required):  
        "(Operator's name), based on the events that have just occurred, determine if the conditions warranted emergency classification. If so, determine the appropriate emergency classification. This is a time critical task. Your time starts now."
: 1. Initialize Simulator to IC-161. 2. Verify RPV water level is above 100 inches. 3. Verify RWCU system isolated with isolation signal clear. Directions to the InstructorlEvaluator:
NRC 2013 JPM SRO EP                                                             May 2013
 
NRC JPM 8-1 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
Rapid RWCU System Restoration for Level Control                             Revision:   NRC 2013 Task Number:     N/A Approvals:
N/A - Exam Security               I General Supervisor         -           Date                       General Supervisor                   Date Operations Training (Designee)                                     Operations (Designee)
Configuration Control                   Date Performer:._ _ _ _ _ _ _ _ _ _ _ _ _ _ _(,RO/SRO)
TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __
Evaluation Method: _~_ _        Perform          _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant               _ _---"~__ Simulator Expected Completion Time:       20 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 ofunsat or individual competency area unsat requires a comment.
Comments:
Evaluator's                                                                 Date:_ _ _ _ _ __
NRC 2013 JPM S-l                                         - I -                                             May 2013
 
Recommended Start Location: Simulator Simulator Set-up (if required):
: 1. Initialize Simulator to IC-161.
: 2. Verify RPV water level is above 100 inches.
: 3. Verify RWCU system isolated with isolation signal clear.
Directions to the InstructorlEvaluator:
None Directions to Operators:
None Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
For the performance ofthis 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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. task performance, I will identify the steps to be simulated, or discuss and provide cues as With the exception of accessing panels, NO plant equipment will be physically manipulated.
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.
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.
Read Before Each Evaluated JPM Performance:
The Control Supervisor has determined that a verifier is not available and that additional!
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.
concurrent verification will be provided; therefore, it should not be Read Before Each Training JPM During this Training JPM, applicable methods of verification are expected to be used. Therefore, another individual or I will act as the independent/peer verifier.
Read Before Each Training JPM Performance:
Notes to Instructor I Evaluator:  
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.
: 1. Critical steps are identified in grading area as Pass/Fail.  
Notes to Instructor I Evaluator:
: 1. Critical steps are identified in grading area as Pass/Fail.
: 2. During Evaluated JPM:
: 2. During Evaluated JPM:
* Self verification shall be demonstrated.  
* Self verification shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self verification shall be demonstrated.
* Self verification shall be demonstrated.
* Peer verification shall be demonstrated.  
* Peer verification shall be demonstrated.


==References:==
==References:==
: 1. NUREG 1123,204000, A4.06, RO 3.0, SRO 2.9 2. NI-EOP-HC Tools and Equipment:
: 1. NUREG 1123,204000, A4.06, RO 3.0, SRO 2.9
None NRC 2013 JPM S-1 May 2013 Task Standard:
: 2. NI-EOP-HC Tools and Equipment:
RWCU is rejecting to the condenser for level control. Initial Conditions: RWCU isolated following a low-low RPV water level transient. RPV water level is high. RWCU system is needed to control RPV water level. Another Operator will be controlling RPV pressure using the ERVs and/or ECs. 5. Instructor to ask operator for any questions.
None NRC 2013 JPM S-1                                                                                       May 2013
Initiating Cue: "(Operator's name), perform rapid RWCU system restoration for RPV water level control and establish reject flow to the condenser, per NI-EOP-HC Attachment 12." Performance Steps Grade Provide repeat back of initiating cue Proper communications used (GAP-OPS-Ol)
 
SatlUnsat Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME ____ Obtain a copy of the reference procedure NI-EOP-HC Attachment 12 is obtained SatlUnsat and review/utilize the correct section of the procedure Verify the following: All Reactor Water Cleanup isolation Observes K3-4-4 clear SatlUnsat signals clear The cause of the isolation is known Determines cause is known and corrected per SatlUnsat AND corrected initial conditions Verify closed the foHowing valves: 33.1-01B, CLEANUP PCV 11 (LP) Observes 33.l-01B in MAN and output signal SatlUnsat at 0 33-39B, CLEANUP PCV 12 (HP) Places controller PC-33-39 in MAN and dials SatlUnsat to 0 Using RMC-33-151, CLEANUP SYS Verifies controller RMC-33-1S1 CLEANUP SatlUnsat SELECTOR, close 33-40 SYS SELECTOR in MAN and dialed to 0 Note: Manipulation of FC-33-169 is inconsequential, but does not satisfy this step. NRC 2013 JPM S-1 -3 May 2013 Performance Steps Using RMC-33-165, CLEANUP TO COND & WASTE FLOW, close 33-165 Verify open one of the following using the CLEANUP SELECTOR CONDENSER WASTE control switch: WASTE (valve 33-10, CLEANUP TO WASTE DISPOSAL BV) COND (valve 33-11, CLEANUP TO CONDENSER BV) Initiating cue directs the candidate to reject to the condenser Open 33-01R, CU RETURN ISOLATION VALVE 1 (INSIDE) Open 33-04R, CU SUPPL Y ISOLATION VALVE 12 (OUTSIDE), for approximately 3 seconds THEN TO-STOP Cleanup System Inlet Pressure will rapidly rise in the next step Jog open 33-02R, CU SUPPLY TION VALVE 11 (INSIDE), using Y2 second open signals followed by TO-STOP UNTIL Cleanup System Inlet Pressure has stabilized at Reactor Pressure Fully open 33-02R Standard Grade Verify controller RMC-33-165C dialed to &deg; SatlUnsat Rotates CLEANUP SELECTOR ER WASTE control switch clockwise to COND position PasslFail Observes right-hand set of lights red light ON and green light OFF, for 33-11 SatlUnsat Rotates 33-01R control switch clockwise to open PasslFaii Observes red light ON, green light OFF SatlUnsat Rotates 33-04R control switch clockwise to open and uses pull-to-stop function after 3 seconds SatlUnsat Observes red light ON, green light ON SatfUnsat Rotates 33-02R control switch clockwise to open and uses pull-to-stop in Y2 second intervals UNTIL Cleanup system inlet pressure rises and stabilizes at reactor pressure on indicators SatfUnsat Observes red light ON, green light ON SatlUnsat Observes cleanup system pressure and reactor pressure approximately equal SatlUnsat Rotates 33-02R control switch clockwise to open PasslFaii Observes red light ON, green light OFF SatfUnsat NRC 2013 JPM S-1 May 2013 Performance Steps Fully open the following valves: 33-04 33-41,AOBLOCKINGVALVE Simultaneously perfonn the following: Adjust the in-service PCV to maintain Reactor Water Cleanup System pressure <100 psig Operator may place the PCV in AUTO after pressure is established Adjust RMC-33-165C, CLEANUP TO COND & WASTE FLOW to control Reactor Water Level AND maintain Non-Regenerative Heat Exchanger outlet temperature  
Task Standard:         RWCU is rejecting to the condenser for level control.
< 120&deg;F on computer point F359 Another operator will monitor computer point F359. 33-165 controller output signal must be greater than 20% before the valve will open, then may be lowered below 20% to adjust flow. As time pennits, continue with NI-OP-3, H.lO.O. Another operator will continue with N OP-3 H.IO.O. Reports to CRS that RWCU is restored and rejecting to condenser for level control Standard Rotates 33-04R control switch clockwise to open Observes red light ON, green light OFF Rotates 33-41 control switch clockwise to open Observes red light ON, green light OFF Using controller PC-33-39, dials output signal to open valve and establish inlet pressure below 100 psig Using controller RMC-33-165C, dials output signals to open valve and establish system reject flow Maintains parameters to prevent a subsequent RWCU system isolation Proper communications used (GAP-OPS-Ol)
Initial Conditions:
Proper communications used (GAP-OPS-Ol)
: 1. RWCU isolated following a low-low RPV water level transient.
Terminating Cue: RWCU is rejecting to the condenser for level control. RECORD STOP TIME ____ NRC 20 l3 JPM -5 Grade PasslFail SatlUnsat PasslFail SatlUnsat SatlUnsat PasslFail PasslFail SatlUnsat SatlUnsat May 2013 Initial Conditions:  
: 2. RPV water level is high.
: 1. R WCU isolated following a low-low RPV water level transient.  
: 3. RWCU system is needed to control RPV water level.
: 2. RPV water level is high. 3. R WCU system is needed to control RPV water level. 4. Another Operator will be controlling RPV pressure using the ERVs and/or ECs. Initiating Cue: "(Operator's name), perform rapid RWCU system restoration for RPV water level control and establish reject flow to the condenser, per NI-EOP-HC Attachment 12." NRC 2013 JPM S-l May 2013 NRC JPM 5-2 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Cool RBEVS Charcoal Filter Revision:
: 4. Another Operator will be controlling RPV pressure using the ERVs and/or ECs.
NRC 2013 Task Number: N/A Approvals:
: 5. Instructor to ask operator for any questions.
General Supervisor Date General Supervisor Date Operations Training (Designee)
Initiating Cue:
Operations (Designee)
    "(Operator's name), perform rapid RWCU system restoration for RPV water level control and establish reject flow to the condenser, per NI-EOP-HC Attachment 12."
NIA -Exam Security / Configuration Control Date Performer:.
Performance Steps                                     Standard                                    Grade
_______________
: 1. Provide repeat back of initiating cue         Proper communications used (GAP-OPS-Ol)       SatlUnsat Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME _ _ __
TrainerlEvaluator:.
: 2. Obtain a copy of the reference procedure     NI-EOP-HC Attachment 12 is obtained           SatlUnsat and review/utilize the correct section of the procedure
____________Evaluation Method: _-'X'-"--__ Perform ______
: 3. Verify the following:
Evaluation Location:
* All Reactor Water Cleanup isolation     Observes K3-4-4 clear                         SatlUnsat signals clear
____ Plant __
* The cause of the isolation is known     Determines cause is known and corrected per   SatlUnsat AND corrected                           initial conditions
__
: 4. Verify closed the foHowing valves:
Expected Completion Time: 15 minutes Time Critical Task: No Alternate Path Task: Start Time: ____ Stop Completion Time:.____JPM Overall Rating: Pass NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat individual competency area unsat requires a comment. Comments:
* 33.1-01B, CLEANUP PCV 11 (LP)           Observes 33.l-01B in MAN and output signal     SatlUnsat at 0
Evaluator's NRC 2013 JPM S-2 May 2013 Recommended Start Location:
* 33-39B, CLEANUP PCV 12 (HP)             Places controller PC-33-39 in MAN and dials   SatlUnsat to 0
Simulator Simulator Set-up (if required):  
: 5. Using RMC-33-151, CLEANUP SYS                 Verifies controller RMC-33-1S1 CLEANUP         SatlUnsat SELECTOR, close 33-40                       SYS SELECTOR in MAN and dialed to 0 Note: Manipulation of FC-33-169 is inconsequential, but does not satisfy this step.
: 1. Initialize Simulator to IC-16I. 2. Verify an RBEVS auto-start signal is locked in. 3. Verify RBEVS 11 is running and RBEVS 12 is secured. Directions to the InstructorlEvaluator:
NRC 2013 JPM S-1                                                                                 May 2013
 
Performance Steps                                 Standard                                        Grade
: 6. Using RMC-33-165, CLEANUP TO                 Verify controller RMC-33-165C dialed              SatlUnsat COND & WASTE FLOW, close 33-165             to &deg;
: 7. Verify open one of the following using the CLEANUP SELECTOR CONDENSER WASTE control switch:
* WASTE (valve 33-10, CLEANUP TO         Rotates CLEANUP SELECTOR CONDENS                  PasslFail WASTE DISPOSAL BV)                     ER WASTE control switch clockwise to COND position
* COND (valve 33-11, CLEANUP TO           Observes right-hand set of lights red light ON    SatlUnsat CONDENSER BV)                           and green light OFF, for 33-11 Note: Initiating cue directs the candidate to reject to the condenser
: 8. Open 33-01R, CU RETURN                     Rotates 33-01R control switch clockwise to        PasslFaii ISOLATION VALVE 1 (INSIDE)                 open Observes red light ON, green light OFF             SatlUnsat
: 9. Open 33-04R, CU SUPPLY ISOLATION            Rotates 33-04R control switch clockwise to         SatlUnsat VALVE 12 (OUTSIDE), for                      open and uses pull-to-stop function after 3 approximately 3 seconds THEN PULL          seconds TO-STOP Observes red light ON, green light ON             SatfUnsat Note: Cleanup System Inlet Pressure will rapidly rise in the next step
: 10. Jog open 33-02R, CU SUPPLY ISOLA            Rotates 33-02R control switch clockwise to         SatfUnsat TION VALVE 11 (INSIDE), using Y2            open and uses pull-to-stop in Y2 second second open signals followed by PULL        intervals UNTIL Cleanup system inlet TO-STOP UNTIL Cleanup System Inlet          pressure rises and stabilizes at reactor pressure Pressure has stabilized at Reactor Pressure on indicators Observes red light ON, green light ON             SatlUnsat Observes cleanup system pressure and reactor       SatlUnsat pressure approximately equal
: 11. Fully open 33-02R                          Rotates 33-02R control switch clockwise to         PasslFaii open Observes red light ON, green light OFF             SatfUnsat NRC 2013 JPM S-1                                                                                 May 2013
 
Performance Steps                                 Standard                                      Grade
: 12. Fully open the following valves:
* 33-04                                   Rotates 33-04R control switch clockwise to      PasslFail open Observes red light ON, green light OFF          SatlUnsat
* 33-41,AOBLOCKINGVALVE                   Rotates 33-41 control switch clockwise to      PasslFail open Observes red light ON, green light OFF          SatlUnsat
: 13. Simultaneously perfonn the following:
* Adjust the in-service PCV to maintain   Using controller PC-33-39, dials output signal  SatlUnsat Reactor Water Cleanup System           to open valve and establish inlet pressure pressure <100 psig                     below 100 psig Note: Operator may place the PCV in AUTO after pressure is established
* Adjust RMC-33-165C, CLEANUP TO         Using controller RMC-33-165C, dials output      PasslFail COND & WASTE FLOW to control           signals to open valve and establish system Reactor Water Level AND maintain       reject flow Non-Regenerative Heat Exchanger outlet temperature < 120&deg;F on           Maintains parameters to prevent a subsequent    PasslFail computer point F359                     RWCU system isolation Cue:    Another operator will monitor computer point F359.
Note: 33-165 controller output signal must be greater than 20% before the valve will open, then may be lowered below 20%
to adjust flow.
: 14. As time pennits, continue with NI-OP-3,     Proper communications used (GAP-OPS-Ol)        SatlUnsat H.lO.O.
Cue:    Another operator will continue with N 1 OP-3 H.IO.O.
: 15. Reports to CRS that RWCU is restored         Proper communications used (GAP-OPS-Ol)         SatlUnsat and rejecting to condenser for level control Terminating Cue: RWCU is rejecting to the condenser for level control.
RECORD STOP TIME _ _ __
NRC 20 l3 JPM S-1                                    -5                                           May 2013
 
Initial Conditions:
: 1. R WCU isolated following a low-low RPV water level transient.
: 2. RPV water level is high.
: 3. R WCU system is needed to control RPV water level.
: 4. Another Operator will be controlling RPV pressure using the ERVs and/or ECs.
Initiating Cue:
    "(Operator's name), perform rapid RWCU system restoration for RPV water level control and establish reject flow to the condenser, per NI-EOP-HC Attachment 12."
NRC 2013 JPM S-l                                                           May 2013
 
NRC JPM 5-2 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
Cool RBEVS Charcoal Filter                                               Revision:   NRC 2013 Task Number:     N/A Approvals:
General Supervisor                     Date                     General Supervisor                   Date Operations Training (Designee)                                 Operations (Designee)
NIA - Exam Security                   /
Configuration Control                 Date Performer:._ _ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)
TrainerlEvaluator:._ _ _ _ _ _ _ _ _ _ _ __
Evaluation Method: _-'X'-"--__ Perform         _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant             _ _----"X~__ Simulator Expected Completion Time:     15 minutes     Time Critical Task:       No     Alternate Path Task: No Start Time: _ _ __            Stop                             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 NRC 2013 JPM S-2                                                                                   May 2013
 
Recommended Start Location: Simulator Simulator Set-up (if required):
: 1. Initialize Simulator to IC-16I.
: 2. Verify an RBEVS auto-start signal is locked in.
: 3. Verify RBEVS 11 is running and RBEVS 12 is secured.
Directions to the InstructorlEvaluator:
None Directions to Operators:
None Directions to Operators:
Read Before JPM Performance:
Read Before         JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. task performance, I will identify the steps to be simulated, or discuss and provide cues as With the exception of accessing panels, NO plant equipment will be physically manipulated.
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.
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.
Read Before Each Evaluated JPM Performance:
The Control Supervisor has determined that a verifier is not available and that additional 1 concurrent verification will be provided; therefore, it should not be Read Before Each Training JPM During this Training lPM, applicable methods of verification are expected to be used. Therefore, another individual or I will act as the independent/peer verifier.
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 1 concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
During this Training lPM, 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 1 Evaluator:
Notes to Instructor 1 Evaluator:
I. Critical steps are identified in grading area as PasslFail.  
I. Critical steps are identified in grading area as PasslFail.
: 2. During Evaluated JPM:
: 2. During Evaluated JPM:
* Self verification shall be demonstrated.  
* Self verification shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self verification shall be demonstrated.
* Self verification shall be demonstrated.
* Peer verification shall be demonstrated.  
* Peer verification shall be demonstrated.


==References:==
==References:==
: 1. NUREG 1123,261000 A4.03 (3.0/3.0)  
: 1. NUREG 1123,261000 A4.03 (3.0/3.0)
: 2. NI-OP-IO Tools and Equipment:
: 2. NI-OP-IO Tools and Equipment:
None NRC 2013 JPM 8-2 May 2013 Task Standard:
None NRC 2013 JPM 8-2                                                                                         May 2013
RBEVS train 12 placed in service and RBEVS train 11 placed in the cooling lineup. Initial Conditions: A steam leak in the Reactor Building occurred approximately 24 hours ago. RBEVS auto-initiated on high Reactor Building exhaust radiation level. RBEVS train 11 is in service. RBEVS train 12 is secured. It has been determined that RBEVS train 11 charcoal filter needs to be removed from service and cooled. Another Operator will be controlling Reactor pressure with ERVs and/or ECs. Instructor to ask operator for any questions.
 
Initiating Cue: "(Operator's name), place RBEVS train 12 in service and cool the charcoal filter for RBEVS train 11 per OP-IO section H.3.0." Performance Standard Grade 1 Provide repeat back of initiating cue Proper communications used (GAP-OPS-Ol)
Task Standard:         RBEVS train 12 placed in service and RBEVS train 11 placed in the cooling lineup.
SatlUnsat Evaluator acknowledge repeat back providing correction if necessary
Initial Conditions:
________ Obtain a copy of the reference procedure NI-0P-1O obtained, precautions and SatlUnsat and review/utilize the correct section of the limitations reviewed, sections H.3.0 procedure referenced (Step 3.1.1) Verify closed the following valves: 202-47, EM VENTILATION TIE BV Observes 202-47 green light on, red light off SatlUnsat 202-74, EM VENTILATION LOOP 11 Observes 202-74 green light on, red light off SatlUnsat COOLING BV (label contains noun name but no number) Observes 202-75 green light on, red light off SatlUnsat 202-75, EM VENTILATION LOOP COOLING BV (label contains noun but no (Step 3.l.3.a) Open 202-38, EM Opens 202-38 by rotating control switch CW PasslFail VENTILATION LOOP 12 INLET BV to OPEN (Step 3.1.3.b) Start 202-33, EVS FAN 12 Starts 202-33 by taking control switch out of PasslFail pull-to-Iock Note: 202-33 auto-starts when the control switch is taken out of pull-to-Iock due to Places 202-33 control switch in START SatlUnsat presence of an auto-start signal. NRC 2013 JPM S-2 -3 May 2013 Performance Steps (Step 3.1.3.c) VerifY open 202-35, EM VENTILATION EXHAUST FAN 12 OUTLET BV (label contains noun name but no number) (Step 3.1.3 .d) Confirm proper operation of 202-51, EM VENT EXHAUST FAN 12 INLET FCV, by observing indicating lights AND flow indication (Step 3.1.3.e) Stop 202-53, EVS FAN 11 Note: RBEVS fan 11 control switch must be placed in pull-to-Iock to stop fan due to presence of an auto-start signal. (Step 3.1.3.f) VerifY closed 202-34, EM VENT EXHAUST FAN 11 OUTLET BV (label contains noun name but no number) (Step 3.2.2.a) VerifY EVS Train 12 running (Step 3.2.2.b) VerifY 202-53, EVS FAN 11 in PULL-TO-LOCK (Step 3.2.2.c) NotifY SRO to enter LCO 3.4.4.e (7 day plant shutdown LCO when one train of EVS is inoperable)
: 1. A steam leak in the Reactor Building occurred approximately 24 hours ago.
Role Acknowledge communication as SRO. (Step 3.2.2.d) Open 202-74, EM VENTILATION LOOP 11 COOLING BV (label contains noun name but no number), by placing 202-37, EM VENTILATION LOOP 11 INLET BV, control switch to COOL (Step 3.2.2.e) VerifY closed 202-37, EM VENTILA TION LOOP 11 INLET BV (Step 3.2.2.f) Open 202-47, EM VENTILATION TIE BV Standard Observes 202-35 green light off, red light on Observes 202-51 green light on, red light on Observes proper RBEVS flow Stops 202-53 by rotating control switch CCW and pulls to lock Observes 202-34 green light on, red light off Observes RBEVS fan 12 green light off, red light on Observes 202-53 control switch in lock Proper communications used (GAP-OPS-Ol)
: 2. RBEVS auto-initiated on high Reactor Building exhaust radiation level.
Opens 202-74 by rotating control switch CCWtoCOOL Observes 202-37 green light on, red light off Opens 202-47 by rotating control switch CW to OPEN Grade SatiUnsat SatlUnsat SatlUnsat SatlUnsat PasslFan SatiUnsat PasslFaii Terminating Cue: RBEVS train 12 placed in service and RBEVS train 11 placed in the cooling RECORD STOP TIME ___NRC 2013 JPM S-2 May Initial Conditions: A steam leak in the Reactor Building occurred approximately 24 hours ago. RBEVS auto-initiated on high Reactor Building exhaust radiation level. 3. RBEVS train 11 is in service. RBEVS train 12 is secured. It has been determined that RBEVS train 11 charcoal filter needs to be removed from service and cooled. Another Operator will be controlling Reactor pressure with ERVs and/or ECs. Initiating Cue: "(Operator's name), place RBEVS train 12 in service and cool the charcoal filter for RBEVS train 11 per NI-0P-I0 section H.3.0." NRC 2013 JPM 8-2 -5 May 2013
: 3. RBEVS train 11 is in service.
---------------
: 4. RBEVS train 12 is secured.
NRC JPM Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Re-Open MSIV s with Reactor Pressurized and Lower Pressure Revision:
: 5. It has been determined that RBEVS train 11 charcoal filter needs to be removed from service and cooled.
NRC 2013 Task Number: N/A Approvals:
: 6. Another Operator will be controlling Reactor pressure with ERVs and/or ECs.
NIA -Exam Security , . I General Supervisor Date General Supervisor Date Operations Training (Designee)
: 7. Instructor to ask operator for any questions.
Operations (Designee)
Initiating Cue:
NIA -Exam Security I Configuration Control Date Performer:
    "(Operator's name), place RBEVS train 12 in service and cool the charcoal filter for RBEVS train 11 per NI OP-IO section H.3.0."
________________(RO/SRO) TrainerlEvaluator:
Performance Steps                                      Standard                                       Grade
Evaluation Method: _----"X--"--
: 1. Provide repeat back of initiating cue         Proper communications used (GAP-OPS-Ol)           SatlUnsat Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTT~E                  ________
__Perform ______ Simulate Evaluation Location:
: 2.      Obtain a copy of the reference procedure       NI-0P-1O obtained, precautions and               SatlUnsat and review/utilize the correct section of the limitations reviewed, sections H.3.0 procedure                                     referenced
Plant X------------"--"----
: 3.      (Step 3.1.1) Verify closed the following valves:
Simulator 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:
* 202-47, EM VENTILATION TIE BV               Observes 202-47 green light on, red light off     SatlUnsat
Evaluator's Signature:
* 202-74, EM VENTILATION LOOP 11               Observes 202-74 green light on, red light off     SatlUnsat COOLING BV (label contains noun name but no number)
______________
Observes 202-75 green light on, red light off     SatlUnsat
_ Date:_______ NRC 2013 JPM S-3 May 2013 Recommended Start Location:
* 202-75, EM VENTILATION LOOP 12 COOLING BV (label contains noun name but no number)
Simulator Simulator Set-up (if required):  
: 4.      (Step 3.l.3.a) Open 202-38, EM                 Opens 202-38 by rotating control switch CW       PasslFail VENTILATION LOOP 12 INLET BV                   to OPEN
: 1. Initialize Simulator to IC-162. 2. Verify the Reactor is scrammed with the MSIVs closed. 3. Verify Reactor pressure is approximately 1000 psig and slowly lowering with EC 12 in service. 4. Verify the following malfunctions are inserted:
: 5.    (Step 3.1.3.b) Start 202-33, EVS FAN 12       Starts 202-33 by taking control switch out of     PasslFail pull-to-Iock Note: 202-33 auto-starts when the control switch is taken out of pull-to-Iock due to     Places 202-33 control switch in START             SatlUnsat presence of an auto-start signal.
NRC 2013 JPM S-2                                                                                     May 2013
 
Performance Steps                                 Standard                                      Grade
: 6.  (Step 3.1.3.c) VerifY open 202-35, EM       Observes 202-35 green light off, red light on  SatlUnsat VENTILATION EXHAUST FAN 12 OUTLET BV (label contains noun name but no number)
: 7.  (Step 3.1.3 .d) Confirm proper operation of Observes 202-51 green light on, red light on  SatlUnsat 202-51, EM VENT EXHAUST FAN 12 INLET FCV, by observing indicating           Observes proper RBEVS flow                    SatiUnsat lights AND flow indication
: 8.  (Step 3.1.3.e) Stop 202-53, EVS FAN 11       Stops 202-53 by rotating control switch CCW    PasslFail and pulls to lock Note: RBEVS fan 11 control switch must be placed in pull-to-Iock to stop fan due to presence of an auto-start signal.
: 9.  (Step 3.1.3.f) VerifY closed 202-34, EM     Observes 202-34 green light on, red light off  SatiUnsat VENT EXHAUST FAN 11 OUTLET BV (label contains noun name but no number)
: 10.  (Step 3.2.2.a) VerifY EVS Train 12 running   Observes RBEVS fan 12 green light off, red    SatlUnsat light on
: 11. (Step 3.2.2.b) VerifY 202-53, EVS FAN 11     Observes 202-53 control switch in pull-to    SatlUnsat in PULL-TO-LOCK                             lock
: 12.  (Step 3.2.2.c) NotifY SRO to enter LCO       Proper communications used (GAP-OPS-Ol)        SatlUnsat 3.4.4.e (7 day plant shutdown LCO when one train of EVS is inoperable)
Role Play: Acknowledge communication as SRO.
: 13.  (Step 3.2.2.d) Open 202-74, EM               Opens 202-74 by rotating control switch        PasslFan VENTILATION LOOP 11 COOLING BV               CCWtoCOOL (label contains noun name but no number), by placing 202-37, EM VENTILATION LOOP 11 INLET BV, control switch to COOL
: 14. (Step 3.2.2.e) VerifY closed 202-37, EM       Observes 202-37 green light on, red light off  SatiUnsat VENTILATION LOOP 11 INLET BV
: 15.  (Step 3.2.2.f) Open 202-47, EM               Opens 202-47 by rotating control switch CW     PasslFaii VENTILATION TIE BV                          to OPEN Terminating Cue: RBEVS train 12 placed in service and RBEVS train 11 placed in the cooling lineup.
RECORD STOP TIME _ _ __
NRC 2013 JPM S-2                                                                               May 2013
 
Initial Conditions:
: 1. A steam leak in the Reactor Building occurred approximately 24 hours ago.
: 2. RBEVS auto-initiated on high Reactor Building exhaust radiation level.
: 3. RBEVS train 11 is in service.
: 4. RBEVS train 12 is secured.
: 5. It has been determined that RBEVS train 11 charcoal filter needs to be removed from service and cooled.
: 6. Another Operator will be controlling Reactor pressure with ERVs and/or ECs.
Initiating Cue:
    "(Operator's name), place RBEVS train 12 in service and cool the charcoal filter for RBEVS train 11 per NI-0P-I0 section H.3.0."
NRC 2013 JPM 8-2                                                               May 2013
 
NRC JPM 5-3 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
Re-Open MSIV s with Reactor Pressurized and Lower Pressure                   Revision:   NRC 2013 Task Number:     N/A Approvals:
General Supervisor                      Date
                                                ,  .                NIA - Exam Security General Supervisor I
Date Operations Training (Designee)                                     Operations (Designee)
NIA - Exam Security                     I Configuration Control                   Date Performer: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)
TrainerlEvaluator:- - - - - - - - - - - - - - -
Evaluation Method: _----"X--"--__ Perform        _ _ _ _ _ _ Simulate Evaluation Location: - - - - Plant                        X
                                                  --------"--"----   Simulator 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:
Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __                          Date:_ _ _ _ _ __
NRC 2013 JPM S-3                                                                                       May 2013
 
Recommended Start Location: Simulator Simulator Set-up (if required):
: 1. Initialize Simulator to IC-162.
: 2. Verify the Reactor is scrammed with the MSIVs closed.
: 3. Verify Reactor pressure is approximately 1000 psig and slowly lowering with EC 12 in service.
: 4. Verify the following malfunctions are inserted:
* EC04A, EC Return Valve Fails to Open (IV 39-05)
* EC04A, EC Return Valve Fails to Open (IV 39-05)
* AD07(A-F), ERV (111-123)
* AD07(A-F), ERV (111-123) Fails Closed (Burned Out Solenoid)
Fails Closed (Burned Out Solenoid)
* RP06, Reactor Vessel Isolation
* RP06, Reactor Vessel Isolation  
: 5. Verify trigger 1 is set as follows:
: 5. Verify trigger 1 is set as follows:
* Event zdmsisol(I)==1&zdmsisol(2)==I&zdmsisol(3)=I&zdmsisol(4)=1
* Event zdmsisol(I)==1&zdmsisol(2)==I&zdmsisol(3)=I&zdmsisol(4)=1
Line 512: Line 868:
None Directions to Operators:
None Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
With the exception of accessing panels, NO plant equipment will be physically manipulated.
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 1 concurrent verification will not be provided; therefore, it should not be requested.
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 1 concurrent verification will not be provided; therefore, it should not be requested.
Read Before Each Training JPM Performance:
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.
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  
Notes to Instructor / Evaluator:
/ Evaluator:  
: 1. Critical steps are identified in grading area as Pass/Fail.
: 1. Critical steps are identified in grading area as Pass/Fail.  
: 2. During Evaluated JPM:
: 2. During Evaluated JPM:
* Self verification shall be demonstrated.  
* Self verification shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self verification shall be demonstrated.
* Self verification shall be demonstrated.
* Peer verification shall be demonstrated.  
* Peer verification shall be demonstrated.


==References:==
==References:==
: 1. NUREG 1123,239001 A4.01 (4.2/4.0)
: 1. NUREG 1123,239001 A4.01 (4.2/4.0)
NRC 2013 JPM S-3 May 2013
NRC 2013 JPM S-3                                                                                         May 2013
: 2.  
: 2. N1-EOP-1
: 3.
: 3. N1-EOP-HC Tools and Equipment:
Tools and Task Standard:
None Task Standard:         MSIV s re-opened and Reactor pressure lowering on Turbine Bypass Valves.
MSIV s re-opened and Reactor pressure lowering on Turbine Bypass Initial  
Initial Conditions:
: 1. An RPV Blowdown is  
: 1. An RPV Blowdown is required.
: 2. Emergency Condenser 11 has failed to go into service and ERVs have failed to 3. MSIV s closed due to a spurious isolation 4. Another Operator has been assigned Reactor water level  
: 2. Emergency Condenser 11 has failed to go into service and ERVs have failed to open.
: 5. Instructor to ask operator for any Initiating "(Operator's name), install NI-EOP-l attachment 1 jumpers, re-open the MSIVs per NI-EOP-HC attachment 3, and then depressurize the Reactor with Turbine Bypass Valves using the Bypass Opening Jack (BOJM)." Performance Steps Grade Provide repeat back of initiating cue Proper communications used (GAP-OPS-Ol)
: 3. MSIV s closed due to a spurious isolation signal.
SatlUnsat Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME ____ Obtain a copy of the reference procedure NI-EOP-1 attachment 1 and N1-EOP-HC SatlUnsat and review/utilize the correct section of the attachment 3 obtained procedure Bypass MSIV ISOLATION interlocks by installing the following jumpers at the EOP ISOLATION BYPASS JUMPER SUBPANEL (inside Panel N, between INIA and INIB):
: 4. Another Operator has been assigned Reactor water level control.
* Jumper 15, MSIV ISOLATION BYPASS Inserts EOP jumper 15. PasslFaii RELAY l1K19A TO RELAY 11K73
: 5. Instructor to ask operator for any questions.
* Jumper 16, MSIV ISOLATION BYPASS Inserts EOP jumper 16. PasslFaii RELAY l1K20A TO RELAY l1K74
Initiating Cue:
* Jumper 22, MSIV ISOLATION Inserts EOP jumper 22. PasslFaii RELAY 12K19A TO RELAY 12K73 Inserts EOP jumper PasslFaii* Jumper 23, MSIV ISOLATION RELAY 12K20A TO RELAY NRC 2013 JPM S-3 -3 May 2013 Performance Steps Open MSIV 01-03 Slowly throttle open MSIV 01-01 utilizing TO-STOP Fully open MSIV 01-01 Open MSIV 01-04 Slowly throttle open MSIV 01-02 utilizing PULL-TO-STOP Fully open MSlV 01-02 Opens Turbine Bypass Valve( s) using Bypass Opening Jack (BOJM) Standard Grade Opens MSIV 01-03 by rotating control switch CWtoOPEN PasslFail Throttles open MSIV 01-01 by rotating control switch CW to OPEN and then pulling control switch out PasslFaii Opens MSIV 01-01 by rotating control switch CW to OPEN PasslFail Opens MSIV 01-04 by rotating control switch CWtoOPEN PasslFaii Throttles open MSlV 01-02 by rotating control switch CW to OPEN and then pulling control switch out PasslFaii Opens MSIV 01-02 by rotating control switch CWtoOPEN PasslFaii Rotates BY-PASS OPENING JACK control switch clockwise to OPEN PasslFaii Terminating Cue: MSIV s re-opened and TBV s open/opening.
      "(Operator's name), install NI-EOP-l attachment 1 jumpers, re-open the MSIVs per NI-EOP-HC attachment 3, and then depressurize the Reactor with Turbine Bypass Valves using the Bypass Opening Jack (BOJM)."
RECORD STOP TIME ____ NRC 2013 JPM S-3 -4 May 2013 Initial Conditions:  
Performance Steps                                       Standard                                    Grade
: 1. An RPV Blowdown is required.  
: 1. Provide repeat back of initiating cue           Proper communications used (GAP-OPS-Ol)       SatlUnsat Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME _ _ __
: 2. Emergency Condenser 11 has failed to go into service and ERV s have failed to open. 3. MSIVs closed due to a spurious isolation signaL 4. Another Operator has been assigned Reactor water level control. Initiating Cue: "(Operator's name), install NI-EOP-l attachment 1 jumpers, re-open the MSIVs per NI-EOP-HC attachment 3, and then depressurize the Reactor with Turbine Bypass Valves using the Bypass Opening Jack (BOJM)." NRC 2013 JPM 8-3 May 2013 NRC JPM S-4 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Transfer Torus Water to the Waste Collector Tank Using Revision:
: 2.      Obtain a copy of the reference procedure       NI-EOP-1 attachment 1 and N1-EOP-HC           SatlUnsat and review/utilize the correct section of the   attachment 3 obtained procedure
NRC 2013 Containment Spray Loop 111 Task Number: NI A Approvals: I , NIA -Exam Security I General Supervisor  
: 3.      Bypass MSIV ISOLATION interlocks by installing the following jumpers at the EOP ISOLATION BYPASS JUMPER SUBPANEL (inside Panel N, between INIA and INIB):
'" Date General Supervisor Date Operations Training (Designee)
* Jumper 15, MSIV ISOLATION BYPASS                 Inserts EOP jumper 15.                       PasslFaii RELAY l1K19A TO RELAY 11K73
Operations (Designee)
* Jumper 16, MSIV ISOLATION BYPASS                 Inserts EOP jumper 16.                       PasslFaii RELAY l1K20A TO RELAY l1K74
Configuration Control Date Performer:
* Jumper 22, MSIV ISOLATION BYPASS                  Inserts EOP jumper 22.                       PasslFaii RELAY 12K19A TO RELAY 12K73
______________
* Jumper 23, MSIV ISOLATION BYPASS                  Inserts EOP jumper 23.                        PasslFaii RELAY 12K20A TO RELAY l2K74 NRC 2013 JPM S-3                                                                                   May 2013
(,RO/SRO)
 
Evaluation Method: _-=X-=---__ Perform ______ Simulate Evaluation Location:
Performance Steps                             Standard                                    Grade
____ Plant __---''-''--
: 4. Open MSIV 01-03                           Opens MSIV 01-03 by rotating control switch  PasslFail CWtoOPEN
__ Simulator Expected Completion Time: 15 Minutes Time Critical Task: No Alternate Path Task: No Start Time: ____ Stop 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:
: 5. Slowly throttle open MSIV 01-01 utilizing Throttles open MSIV 01-01 by rotating       PasslFaii PULL~ TO-STOP                            control switch CW to OPEN and then pulling control switch out
Evaluators Signature:
: 6. Fully open MSIV 01-01                    Opens MSIV 01-01 by rotating control switch PasslFail CW to OPEN
______________
: 7. Open MSIV 01-04                          Opens MSIV 01-04 by rotating control switch PasslFaii CWtoOPEN
_ Date:______NRC 2013 JPM S-4 May Recommended Start Location: (Completion time based on the start location)
: 8. Slowly throttle open MSIV 01-02 utilizing Throttles open MSlV 01-02 by rotating       PasslFaii PULL-TO-STOP                              control switch CW to OPEN and then pulling control switch out
NMP Unit 1 Simulator Simulator Set-up (if required):  
: 9. Fully open MSlV 01-02                    Opens MSIV 01-02 by rotating control switch PasslFaii CWtoOPEN
: 1. Initialize Simulator to IC-162. 2. VerifY Torus water level raised to per NI-EOP-l Attachment  
: 10. Opens Turbine Bypass Valve( s) using      Rotates BY-PASS OPENING JACK control         PasslFaii Bypass Opening Jack (BOJM)                switch clockwise to OPEN Terminating Cue: MSIV s re-opened and TBV s open/opening.
: 18. Directions to the InstructorlEvaluator:
RECORD STOP TIME _ _ __
NRC 2013 JPM S-3                                                                         May 2013
 
Initial Conditions:
: 1. An RPV Blowdown is required.
: 2. Emergency Condenser 11 has failed to go into service and ERVs have failed to open.
: 3. MSIVs closed due to a spurious isolation signaL
: 4. Another Operator has been assigned Reactor water level control.
Initiating Cue:
    "(Operator's name), install NI-EOP-l attachment 1 jumpers, re-open the MSIVs per NI-EOP-HC attachment 3, and then depressurize the Reactor with Turbine Bypass Valves using the Bypass Opening Jack (BOJM)."
NRC 2013 JPM 8-3                                                             May 2013
 
NRC JPM S-4 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
Transfer Torus Water to the Waste Collector Tank Using                       Revision:   NRC 2013 Containment Spray Loop 111 Task Number: NIA Approvals:
I ,
NI A - Exam Security             I General Supervisor       '"             Date                       General Supervisor                   Date Operations Training (Designee)                                     Operations (Designee)
Configuration Control                   Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _(,RO/SRO)
Evaluation Method: _-=X-=---__ Perform           _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant               _ _---''-''--__ Simulator Expected Completion Time:       15 Minutes       Time Critical Task:       No     Alternate Path Task:     No Start Time: _ _ __              Stop                               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 2013 JPM S-4                                                                                       May 2013
 
Recommended Start Location: (Completion time based on the start location)
NMP Unit 1 Simulator Simulator Set-up (if required):
: 1. Initialize Simulator to IC-162.
: 2. VerifY Torus water level raised to ~11.3' per NI-EOP-l Attachment 18.
Directions to the InstructorlEvaluator:
None Directions to Operators:
None Directions to Operators:
Read Before EveI)' JPM Performance:
Read Before EveI)' JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identifY the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
With the exception of accessing panels, NO plant equipment will be physically manipulated.
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.
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.
Read Before Each Training JPM Performance:
The Control Supervisor has determined that a verifier is not available and that additional/concurrent verification will be provided; therefore, it should not be Read Before Each Training JPM During this Training JPM, applicable methods of verification are expected to be used. Therefore, another individual or I will act as the independent/peer verifier.
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:  
Notes to Instructor I Evaluator:
: 1. Critical steps are identified in grading areas PasslFaii.  
: 1. Critical steps are identified in grading areas PasslFaii.
: 2. During Evaluated JPM:
: 2. During Evaluated JPM:
* Self verification shall be demonstrated.  
* Self verification shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self verification shall be demonstrated.
* Self verification shall be demonstrated.
* No other verification shall be demonstrated.  
* No other verification shall be demonstrated.


==References:==
==References:==
: 1. NI-EOP-l, Attachment 2. NUREG 1123295029 EAl.03 Tools and NRC 2013 JPM S-4 May 2013 Task Standard:
: 1. NI-EOP-l, Attachment 15
Torus water level is being lowered via the Containment Spray System. Initial Conditions:  
: 2. NUREG 1123295029 EAl.03 (2.9/3.0)
: 1. Torus water level is 11.3 feet and rising slowly. 2. N1-EOP-4 has been entered. 3. Containment Spray pumps are in pull-to-Iock.  
Tools and Equipment:
: 4. Another Operator will control Reactor pressure using ECs and/or ERVs. 5. Another Operator will control Reactor water level using CondensatelFeedwater and CRD. Initiating Cues: "(Operator's name), lower Torus water level to 11.0 feet by discharging water to the Waste Collector Tank using Containment Spray Loop 111 in accordance with NI-EOP-1 Attachment 15." 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 of the procedure NotifY Radwaste of intent to pump down Torus to Waste Collector Tank Role Play: Acknowledge report Close 80-45, Cont Spray Bypass BV 122 Open 80-118, Cont Spray Test to Torus FCV Note: 80-118 is a throttlable valve, and must be held in the open position until fully open VerifY closed 80-16, Cont Spray Discharge IV III VerifY open 80-40, Cont Spray Bypass BV 111 Start Containment Spray Raw Water Pump 111 Standard Proper communications used (GAP-OPS-OI)
None NRC 2013 JPM S-4                                                                                     May 2013
Grade SatlUnsat NI-EOP-1 Attachment 15 obtained SatlUnsat Proper communications used (GAP-O PS-O 1 ) SatlUnsat Closes 80-45 by rotating control switch CCW to CLOSE Opens 80-118 by rotating control switch CW to OPEN PasslFaii PasslFail Closes 80-16 by rotating control switch CCW to CLOSE Observes 80-40 green light off, red light on PasslFail SatlUnsat Starts Containment Spray Raw Water Pump 111 by rotating control switch CW to START PassiFail NRC 2013 JPM 8-4 -1 May 2013 Perfonnance Steps Start Containment Spray Pump 111 Open 80-115, Cont Spray to Radwaste IV 12 Open 80-114, Cont Spray to Radwaste IV 11 Throttle 80-118, Cont Spray Test to Torus FCV as required to control flow to Waste Collector Tank Role Play: If requested, infonn that Radwaste has indication of sufficient flow Monitor 58-05A and 58-06A TORUS H 2 O LEVEL indicators for level response Inform SRO that flow to the Waste Collector Tank has been established using Containment Spray Loop 111 Role Play: Acknowledge report Standard Grade Starts Containment Spray Pump 111 by rotating control switch CW to START Opens 80-115 by rotating control switch CW to OPEN PasslFaii PasslFaii Opens 80-114 by rotating control switch CW to OPEN PasslFaii Throttles closed 80-118 by rotating control switch CCW as required SatlUnsat Observes TORUS H 2 0 LEVEL indicators 05A and 58-06A monitored for level response Proper communications used (GAP-OPS-Ol)
 
SatlUnsat SatlUnsat Terminating Cue: Torus water level is being lowered via Containment Spray Loop 111. RECORD STOP TIME ____ NRC 2013 JPM S-4 -1 May 2013 Initial Conditions: Torus water level is 11.3 feet and rising slowly. 2. N1-EOP-4 has been entered. Containment Spray pumps are in pull-to-Iock. Another Operator will control Reactor pressure using ECs and/or ERVs. Another Operator will control Reactor water level using CondensatelFeedwater and CRD. Initiating Cues: "(Operator's name), lower Torus level to 11.0 feet by discharging water to the Waste Collector Tank using Containment Spray Loop 111 in accordance with N1-EOP-1 Attachment 15." NRC 2013 JPM S-4 -I May 2013
Task Standard:       Torus water level is being lowered via the Containment Spray System.
------NRC ..IPM Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Control Room Evacuation, Manual Scram Fails, ARl Works Revision:
Initial Conditions:
NRC 2013 One Main Steam Line Fails to Isolate, Powerboard 11 Fails To Fast Transfer Task Number: N/A Approvals:
: 1. Torus water level is 11.3 feet and rising slowly.
NtA -Exam Security I r General Supervisor Date General Supervisor Date Operations Training (Designee)
: 2. N1-EOP-4 has been entered.
Operations (Designee)
: 3. Containment Spray pumps are in pull-to-Iock.
Configuration Date Performer:
: 4. Another Operator will control Reactor pressure using ECs and/or ERVs.
______________(RO/SRO) Evaluation Method: __Perform Simulate Evaluation Location:
: 5. Another Operator will control Reactor water level using CondensatelFeedwater and CRD.
____ Plant Simulator Expected Completion Time: 15 Minutes 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:
Initiating Cues:
Evaluators Signature:
    "(Operator's name), lower Torus water level to 11.0 feet by discharging water to the Waste Collector Tank using Containment Spray Loop 111 in accordance with NI-EOP-1 Attachment 15."
______________
Performance Steps                                         Standard                                    Grade
_ NRC 2013 JPM May 2013 Recommended Start Location: (Completion time based on the start location)
: l. Provide repeat back of initiating cue           Proper communications used                      SatlUnsat (GAP-OPS-OI)
NMP Unit 1 Simulator Simulator Set-up (if required):  
Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME
: 1) Initialize Simulator to 2) Insert malfunctions RP05A and RP05B to cause failure to 3) Insert malfunction ED26 to cause Powerboard 11 to fail to fast  
: 2. Obtain a copy of the reference procedure       NI-EOP-1 Attachment 15 obtained                  SatlUnsat and review/utilize the correct section ofthe procedure
: 4) Insert malfunctions MS13A (50%) and MS13C (100%) to fail MSIVs 01-01 and 01-03 to 5) Insert trigger 2 to allow MSIV 01-01 to close using the control
: 3. NotifY Radwaste of intent to pump down         Proper communications used                      SatlUnsat Torus to Waste Collector Tank                   (GAP-OPS-O 1)
* Event -zdmsiivc( 1 )== 1
Role Play: Acknowledge report
* Command -
: 4. Close 80-45, Cont Spray Bypass BV 122           Closes 80-45 by rotating control switch CCW      PasslFaii to CLOSE
: 6) Insert trigger 3 to allow MSIV 01-03 to close using the control
: 5. Open 80-118, Cont Spray Test to Torus           Opens 80-118 by rotating control switch CW      PasslFail FCV                                             to OPEN Note: 80-118 is a throttlable valve, and must be held in the open position until fully open
* Event -zdmsoivc( 1 )== I
: 6. VerifY closed 80-16, Cont Spray Discharge       Closes 80-16 by rotating control switch CCW      PasslFail IV III                                         to CLOSE
* Command -dmf ms 13c Directions to the InstructorlEvaluator:
: 7. VerifY open 80-40, Cont Spray Bypass BV         Observes 80-40 green light off, red light on     SatlUnsat 111
: 8. Start Containment Spray Raw Water Pump          Starts Containment Spray Raw Water Pump         PassiFail 111                                            111 by rotating control switch CW to START NRC 2013 JPM 8-4                                                                                   May 2013
 
Perfonnance Steps                                   Standard                                Grade
: 9. Start Containment Spray Pump 111           Starts Containment Spray Pump 111 by        PasslFaii rotating control switch CW to START
: 10. Open 80-115, Cont Spray to Radwaste IV     Opens 80-115 by rotating control switch CW  PasslFaii 12                                         to OPEN
: 11. Open 80-114, Cont Spray to Radwaste IV     Opens 80-114 by rotating control switch CW  PasslFaii 11                                         to OPEN
: 12. Throttle 80-118, Cont Spray Test to Torus   Throttles closed 80-118 by rotating control  SatlUnsat FCV as required to control flow to Waste   switch CCW as required Collector Tank Role Play: If requested, infonn that Radwaste has indication of sufficient flow
: 13. Monitor 58-05A and 58-06A TORUS H 2O        Observes TORUS H20 LEVEL indicators 58      SatlUnsat LEVEL indicators for level response         05A and 58-06A monitored for level response
: 14. Inform SRO that flow to the Waste           Proper communications used                  SatlUnsat Collector Tank has been established using   (GAP-OPS-Ol)
Containment Spray Loop 111 Role Play: Acknowledge report Terminating Cue: Torus water level is being lowered via Containment Spray Loop 111.
RECORD STOP TIME _ _ __
NRC 2013 JPM S-4                                                                         May 2013
 
Initial Conditions:
: 1. Torus water level is 11.3 feet and rising slowly.
: 2. N1-EOP-4 has been entered.
: 3. Containment Spray pumps are in pull-to-Iock.
: 4. Another Operator will control Reactor pressure using ECs and/or ERVs.
: 5. Another Operator will control Reactor water level using CondensatelFeedwater and CRD.
Initiating Cues:
    "(Operator's name), lower Torus level to 11.0 feet by discharging water to the Waste Collector Tank using Containment Spray Loop 111 in accordance with N1-EOP-1 Attachment 15."
NRC 2013 JPM S-4                             - I -                                May 2013
 
NRC ..IPM 8-5 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
Control Room Evacuation, Manual Scram Fails, ARl Works                       Revision:   NRC 2013 One Main Steam Line Fails to Isolate, Powerboard 11 Fails To Fast Transfer Task Number: N/A Approvals:
r  ~
NtA - Exam Security               I General Supervisor                       Date                       General Supervisor                   Date Operations Training (Designee)                                     Operations (Designee)
Configuration Control                    Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)
Evaluation Method: _~_ _      Perform          - - - - - - Simulate Evaluation Location: _ _ _ _ Plant                -----"--"---
Simulator Expected Completion Time:       15 Minutes       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 2013 JPM S-5                                                                                            May 2013
 
Recommended Start Location: (Completion time based on the start location)
NMP Unit 1 Simulator Simulator Set-up (if required):
: 1) Initialize Simulator to IC-163.
: 2) Insert malfunctions RP05A and RP05B to cause failure to scram.
: 3) Insert malfunction ED26 to cause Powerboard 11 to fail to fast transfer.
: 4) Insert malfunctions MS13A (50%) and MS13C (100%) to fail MSIVs 01-01 and 01-03 to close.
: 5) Insert trigger 2 to allow MSIV 01-01 to close using the control switch:
* Event - zdmsiivc( 1)== 1
* Command - dmfms13a
: 6) Insert trigger 3 to allow MSIV 01-03 to close using the control switch:
* Event - zdmsoivc( 1)== I
* Command - dmf ms 13c Directions to the InstructorlEvaluator:
None Directions to Operators:
None Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
With the exception of accessing panels, NO plant equipment will be physically manipulated.
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.
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:
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.
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  
Notes to Instructor / Evaluator:
/ Evaluator:  
: 1. Critical steps are identified in grading areas Pass/Fail.
: 1. Critical steps are identified in grading areas Pass/Fail.  
: 2. During Evaluated JPM:
: 2. During Evaluated JPM:
* Self verification shall be demonstrated.  
* Self verification shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self verification shall be demonstrated.
* Self verification shall be demonstrated.
* No other verification shall be demonstrated.
* No other verification shall be demonstrated.
NRC 2013 JPM S-5 May 2013
NRC 2013 JPM S-5                                                                                     May 2013


==References:==
==References:==
Nl-SOP-21.2 Nl-SOP-l Nl-S0P-30.1 NUREG 1123295016 AA1.01 (3.8/3.9)
: 1. Nl-SOP-21.2
: 2. Nl-SOP-l
: 3. Nl-S0P-30.1
: 4. NUREG 1123295016 AA1.01 (3.8/3.9)
Tools and Equipment:
Tools and Equipment:
None Task Standard:
None Task Standard:       Control Room actions for Control Room Evacuation complete, including compensatory actions for failure of Mode Switch and RPS push buttons, MSIV closure, and Powerboard 11 fast transfer.
Control Room actions for Control Room Evacuation complete, including compensatory actions for failure of Mode Switch and RPS push buttons, MSIV closure, and Powerboard 11 fast transfer.
Initial Conditions:
Initial Conditions: The plant is operating at approximately 100% power. The Shift Manager has determined that a Control Room Evacuation is required due to a fire in the Auxiliary Control Room. The fire is still small and no smoke has yet entered the Control Room. Time permits completing all required actions ofNI-SOP-21.2, Control Room Evacuation, before leaving the Control Room. Ask the operator for any questions.
: 1. The plant is operating at approximately 100% power.
Initiating Cues: "(Operator's name), perform the Control Room actions for a Control Room Evacuation per NI-SOP-21.2." Performance Steps Grade Provide repeat back of initiating cue Proper communications used SatlUnsat (GAP-OPS-Ol)
: 2. The Shift Manager has determined that a Control Room Evacuation is required due to a fire in the Auxiliary Control Room.
Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME ____ Place Reactor Mode Switch in Rotates Reactor Mode Switch CW to PasslFaii SHUTDOWN SHUTDOWN Note: The Mode Switch and the RPS pushbuttons will fail to cause a Reactor scram. The Candidate may use guidance in NI-SOP-l to immediately attempt manual ARl. Role Play: If asked how to proceed with failure to scram, direct the Candidate to perform immediate actions ofN I-SOP-l, Reactor Scram. NRC 2013 JPM S-5 -1 May 2013 Performance Steps Verify ALL Control Rods inserted Place BOTH VESSEL ISOLATION switches to ISOLATE Verify ALL MSIVs close Cue: If required, inform candidate that time still permits completing rest of Control Room actions for NI-S0P-21.2.
: 3. The fire is still small and no smoke has yet entered the Control Room.
Standard Observes control rods failed to insert May depress RPS pushbuttons Depresses MANUAL ARI pushbutton Observes control rods insert Rotates both VESSEL ISOLATION switches CCW to ISOLATION Observes green light on, red light off, for MSNs 01-02 and 01-04 Observes MSIV 01-01 green light on, red light on Observes MSN 01-03 green light off, red light on Closes at least one MSN in steam line by: Rotates MSN 01-01 control switch counterclockwise to CLOSE AND/OR Rotates MSN 01-03 control switch counterclockwise to CLOSE Grade Pass/Fail SatlUnsat Pass/FaiJ SatiUnsat SatlUnsat SatlUnsat PasslFaii NRC 2013 JPM S-5 -1 May 2013 Performance Steps IF time permits, verify the following:
: 4. Time permits completing all required actions ofNI-SOP-21.2, Control Room Evacuation, before leaving the Control Room.
* House service loads transfer Note: The candidate may request guidance on how to deal with PB 11 failure to fast transfer.
S. Ask the operator for any questions.
Direct candidate to make a recommendation and then carry out that recommendation.
Initiating Cues:
Candidate will likely use NI-SOP-30.1 for guidance on how to re-energize PB 11. In this case, the candidate will also verify other things, such as Service Water pump 12 running, prior to energizing PB 11. Cue: If asked for permission to re-energize Powerboard 11, give permission.
    "(Operator's name), perform the Control Room actions for a Control Room Evacuation per NI-SOP-21.2."
Cue: If candidate begins to close Recirc pump discharge valves, inform them that another operator will perform all actions in N 1-SOP-30.1 other than re-energizing the board. IF time permits, verify the foHowing: Turbine/Generator trip HPCI Initiation FW Pump 13 clutch disengaged IF time permits, sound the station alarm AND announce Control Room evacuation NRC 2013 JPM S-5 Standard Observes PB 12 energized (voltmeters show breakers re-align)
Performance Steps                                       Standard                                      Grade
Observes PB II de-energized Enters Nl-SOP-30.l Verifies proper loads running Opens breaker R 113 by rotating control switch counterclockwise to TRIP Inserts Sync Key into RIl2 and rotates clockwise to ON Closes breaker R 112 by rotating control switch clockwise to CLOSE Rotates Sync Key counterclockwise to OFF and removes Restores loads by: Rotates Rill control switch clockwise to CLOSE Rotates RI14 control switch clockwise to CLOSE Observes Turbine trip and Generator lockout (TSVs indicate closed, 86G1I2 lockouts roll) Observes FW pumps II and 12 start / inject (green lights off, red lights on, amps, flow) Observes FW pump 13 clutch disengaged (green light off, red light off, speed lowers) Depresses ST A pushbutton on GAltronics Depresses OFF pushbutton on GAItronics Announces Control Room evacuation -1 Grade SatlUnsat SatlUnsat SatlUnsat SatlUnsat SatlUnsat PasslFaii PasslFaii SatlUnsat SatlUnsat SatlUnsat SatlUnsat SatlUnsat SatlUnsat SatlUnsat SatlUnsat Sat/Unsat May 2013 Performance Steps Standard Grade 8. Obtain two sets of RSP keys (V A-I, GE-Proper communications used SatlUnsat 75, PA-235) AND obtain radios (GAP-OPS-Ol)
: 1. Provide repeat back of initiating cue         Proper communications used                       SatlUnsat (GAP-OPS-Ol)
Cue: You have obtained radios and keys. 9. Evacuate Control Room through Proper communications used SatlUnsat West corridor, south side of Control Room (GAP-OPS-Ol)
Evaluator acknowledge repeat back providing correction ifnecessary RECORD START TIME _ _ __
: 2. Place Reactor Mode Switch in                 Rotates Reactor Mode Switch CW to                 PasslFaii SHUTDOWN                                     SHUTDOWN Note: The Mode Switch and the RPS pushbuttons will fail to cause a Reactor scram. The Candidate may use guidance in NI-SOP-l to immediately attempt manual ARl.
Role Play: If asked how to proceed with failure to scram, direct the Candidate to perform immediate actions ofN I-SOP-l, Reactor Scram.
NRC 2013 JPM S-5                                                                                 May 2013
 
Performance Steps                                 Standard                                Grade
: 3. Verify ALL Control Rods inserted         Observes control rods failed to insert       SatlUnsat May depress RPS pushbuttons                 SatlUnsat Depresses MANUAL ARI pushbutton             Pass/Fail Observes control rods insert                 SatlUnsat
: 4. Place BOTH VESSEL ISOLATION              Rotates both VESSEL ISOLATION switches       Pass/FaiJ switches to ISOLATE                      CCW to ISOLATION
: 5. Verify ALL MSIVs close                    Observes green light on, red light off, for SatiUnsat MSNs 01-02 and 01-04 Observes MSIV 01-01 green light on, red     SatlUnsat light on Observes MSN 01-03 green light off, red     SatlUnsat light on Closes at least one MSN in steam line by:   PasslFaii
* Rotates MSN 01-01 control switch counterclockwise to CLOSE AND/OR
* Rotates MSN 01-03 control switch counterclockwise to CLOSE Cue:
If required, inform candidate that time still permits completing rest of Control Room actions for NI-S0P-21.2.
NRC 2013 JPM S-5                                                                       May 2013
 
Performance Steps                                   Standard                                    Grade
: 6. IF time permits, verify the following:
* House service loads transfer       Observes PB 12 energized (voltmeters show      SatlUnsat
                                                  ~4160V,  breakers re-align)
Note: The candidate may request guidance on how to deal with PB 11 failure to fast transfer. Observes PB II de-energized                    SatlUnsat Direct candidate to make a recommendation and then carry out that recommendation. Candidate     Enters Nl-SOP-30.l                              SatlUnsat will likely use NI-SOP-30.1 for guidance on how to re-energize PB 11. In this case, the       Verifies proper loads running                  SatlUnsat candidate will also verify other things, such as Service Water pump 12 running, prior to re      Opens breaker R 113 by rotating control        SatlUnsat energizing PB 11.                                 switch counterclockwise to TRIP Cue: If asked for permission to re-energize       Inserts Sync Key into RIl2 and rotates          PasslFaii Powerboard 11, give permission.                   clockwise to ON Cue: If candidate begins to close Recirc pump     Closes breaker R 112 by rotating control        PasslFaii discharge valves, inform them that another       switch clockwise to CLOSE operator will perform all actions in N 1-SOP-30.1 other than re-energizing the board.
Rotates Sync Key counterclockwise to OFF       SatlUnsat and removes Restores loads by:
* Rotates Rill control switch clockwise to   SatlUnsat CLOSE
* Rotates RI14 control switch clockwise to   SatlUnsat CLOSE
: 7. IF time permits, verify the foHowing:
* Turbine/Generator trip            Observes Turbine trip and Generator lockout     SatlUnsat (TSVs indicate closed, 86G1I2 lockouts roll)
* HPCI Initiation                    Observes FW pumps II and 12 start / inject     SatlUnsat (green lights off, red lights on, amps, flow)
* FW Pump 13 clutch disengaged      Observes FW pump 13 clutch disengaged           SatlUnsat (green light off, red light off, speed lowers)
: 7. IF time permits, sound the station alarm  Depresses STA pushbutton on GAltronics         SatlUnsat AND announce Control Room evacuation Depresses OFF pushbutton on GAItronics         SatlUnsat Announces Control Room evacuation               Sat/Unsat NRC 2013 JPM S-5                                    - 1                                        May 2013
 
Performance Steps                                   Standard                               Grade
: 8. Obtain two sets of RSP keys (V A-I, GE-     Proper communications used                 SatlUnsat 75, PA-235) AND obtain radios               (GAP-OPS-Ol)
Cue: You have obtained radios and keys.
: 9. Evacuate Control Room through East          Proper communications used                 SatlUnsat West corridor, south side of Control Room   (GAP-OPS-Ol)
Cue: Task complete.
Cue: Task complete.
Terminating Cue: Control Room actions for Control Room Evacuation complete, including compensatory actions for failure of Mode Switch and RPS pushbuttons.
Terminating Cue: Control Room actions for Control Room Evacuation complete, including compensatory actions for failure of Mode Switch and RPS pushbuttons.
RECORD STOP TIME ____ NRC 2013 JPM S-5 May 2013 Initial Conditions: The plant is operating at approximately 1000/0 power. The Shift Manager has determined that a Control Room Evacuation is required due to a fire in the Auxiliary Control Room. 3. The fire is still small and no smoke has yet entered the Control Room. Time permits completing all required actions ofN1-S0P-21.2, Control Room Evacuation, before leaving the Control Room. Initiating Cues: "(Operator's name), perform the Control Room actions for a Control Evacuation per NRC 2013 JPM S-5 -1 May 2013 NRC JPM 5-6 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Restore EC 11 To Service (Alternate Path) Revision:
RECORD STOP TIME _ _ __
NRC 2013 Task Number: NtA Approvals:
NRC 2013 JPM S-5                                                                         May 2013
NtA -Exam Security I General Supervisor Date General Supervisor Date Operations Training (Designee)
 
Operations (Designee)
Initial Conditions:
NtA -Exam Security t Configuration Control Date Performer:
: 1. The plant is operating at approximately 1000/0 power.
______________(RO/SRO) Evaluation Method: __Perform ______ Simulate Evaluation Location:
: 2. The Shift Manager has determined that a Control Room Evacuation is required due to a fire in the Auxiliary Control Room.
____ Plant __---"-x-"--
: 3. The fire is still small and no smoke has yet entered the Control Room.
__ Simulator Expected Completion Time: 20 minutes 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:
: 4. Time permits completing all required actions ofN1-S0P-21.2, Control Room Evacuation, before leaving the Control Room.
Evaluator's Signature:
Initiating Cues:
______________
    "(Operator's name), perform the Control Room actions for a Control Room Evacuation per N1-S0P-21.2."
_ NRC 2013 JPM S-6 -1
NRC 2013 JPM S-5                                                         May 2013
* May 2013 Recommended Start Location: (Completion time based on the start location)
 
Unit 1 Simulator Simulator Set-up (if required):  
NRC JPM 5-6 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
: 1. Initialize Simulator to IC-I63. 2. Verify EC 11 is removed from service per NI-OP-13 section H.8.0. 3. Verify EC 11 steam pressure has been vented to near 0 psig. 4. Verify malfunction EC06A is set at 25% with a IS second delay time on trigger 1. 5. Verify trigger I is set to initiate when valve 39-09R red light goes on (hzlecmovr(1)==I).
 
==Title:==
Restore EC 11 To Service (Alternate Path)                               Revision: NRC 2013 Task Number:     NtA Approvals:
Nt A - Exam Security             I General Supervisor                     Date                     General Supervisor                   Date Operations Training (Designee)                                 Operations (Designee)
NtA - Exam Security                   t Configuration Control                 Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)
Evaluation Method: _~_ _      Perform        _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant             __---"-x-"--__ Simulator Expected Completion Time:     20 minutes     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:_ _ _ _ _ _ _ _ _ _ _ _ _ __
NRC 2013 JPM S-6                                       - 1*                                             May 2013
 
Recommended Start Location: (Completion time based on the start location)
Unit 1 Simulator Simulator Set-up (if required):
: 1. Initialize Simulator to IC-I63.
: 2. Verify EC 11 is removed from service per NI-OP-13 section H.8.0.
: 3. Verify EC 11 steam pressure has been vented to near 0 psig.
: 4. Verify malfunction EC06A is set at 25% with a IS second delay time on trigger 1.
: 5. Verify trigger I is set to initiate when valve 39-09R red light goes on (hzlecmovr(1)==I).
Directions to the InstructorlEvaluator:
Directions to the InstructorlEvaluator:
None Directions to Operators:
None Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
With the exception of accessing panels, NO plant equipment will be physically manipulated.
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.
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.
Read Before Each Training JPM Performance:
The Control Supervisor has determined that a verifier is not available and that additional/concurrent verification will be provided; therefore, it should not be Read Before Each Training JPM During this Training JPM, applicable methods of verification are expected to be used. Therefore, another individual or I will act as the independent/peer verifier.
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  
Notes to Instructor / Evaluator:
/ Evaluator:  
: 1. Critical steps are identified in grading areas PasslFail.
: 1. Critical steps are identified in grading areas PasslFail.  
: 2. During Evaluated JPM:
: 2. During Evaluated JPM:
* Self verification shall be demonstrated.  
* Self verification shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self verification shall be demonstrated.
* Self verification shall be demonstrated.
* Peer verification shall be demonstrated.  
* Peer verification shall be demonstrated.


==References:==
==References:==
: 1. NUREG 1123, KIA 207000 A4.05 (3.5/3.7)  
: 1. NUREG 1123, KIA 207000 A4.05 (3.5/3.7)
: 2. NI-OP-13 Tools and Equipment:
: 2. NI-OP-13 Tools and Equipment:
I. None NRC 2013 JPM S-6 May 2013 Task Standard:
I. None NRC 2013 JPM S-6                                                                                       May 2013
EC 11 is isolated due to tube leakage. Initial Conditions: Emergency Condenser (EC) 11 is out of service per NI-OP-13 section H.8.1 following corrective maintenance. Work is complete and EC 11 is ready to be returned to service. Non-Destructive Evaluation (NDE) has determined EC stearn leg level to be 6 ft 11 inches. Instructor to ask operator for any questions.
 
Initiating Cues: "(Operator's name), return EC 11 to service per NI-OP-13 section H.8.0." Performance Steps Provide repeat back of initiating cue Evaluator acknowledge repeat back providing correction if necessary.
Task Standard:       EC 11 is isolated due to tube leakage.
RECORD START TIME _______ Obtain a copy of the reference procedure and review/utilize the correct section of the procedure VerifY proper keepfullievel as follows: Contact Engineering Programs -NDE to perform UT ofEC stearn leg for level determination IF EC stearn leg level is greater than 6' 10" THEN proceed to step 8.3.2 VerifY open the following valves: 05-11, EMERG COND ISOLATION VALVE 05-01R, EMERG COND ISOLATION VALVE Standard Proper communications used (GAP-OPS-Ol)
Initial Conditions:
NI-OP-13 is obtained, precautions
: 1. Emergency Condenser (EC) 11 is out of service per NI-OP-13 section H.8.1 following corrective maintenance.
& limitations reviewed, section H.8.3 utilized Determines level is 6' 11" per initial conditions Proceeds to step 8.3.2 Opens 05-11 by rotating control switch CW to OPEN Opens 05-0 lR by rotating control switch CW to OPEN Grade SatlUnsat SatlUnsat SatlUnsat SatlUnsat PasslFail PasslFail NRC 2013 JPM S-6 -3 May 2013 Perfonnance Steps Grade WHEN system pressure has returned to nonnal, open the following valves: 39-11R, EMERG CONDSR STM SUPPLY DRAIN IV 111 39-12R, EMERG CONDSR STM SUPPLY DRAIN IV 112 Open 39-07R, EC STM ISOLA nON VALVE 112 Note: The candidate may throttle open 39-07R using the pull-to-stop feature, rather than open it in one continuous motion. However, it must be fully opened by the end of the manipulation. Throttle open 39-09R, EC STM ISOLA nON VALVE 111 and monitor system parameters during heatup AND repressurization Note: The alternate path begins when 39-09R red light comes on. This causes an EC tube leak to be initiated. Responds to alann KI-I-2 Confinn alann on computer printout Confinn radiation levels on J Panel and contact RP to check dose rates above elevation 340 Role Play: Acknowledge direction as RP. Opens 39-11R by rotating control switch CW to OPEN Opens 39-12R by rotating control switch CW to OPEN Opens 39-07R by rotating control switch CW to OPEN Opens 39-09R by rotating control switch CW to OPEN Stops 39-09R by pulling control switch out to STOP Monitors system temperature and pressures Fully opens 39-09R by rotating control switch CWtoOPEN Acknowledges and reports alann Observes computer points E478 and E480 in alann Observes E CONDSR VENT RAD MON 111 (RE-RN04A-3) and E CONDSR VENT RAD MON 112 (RE-RN04A-4) reading on J Panel and detennines readings indicate alann condition Directs RP to check dose rates above elevation 340 PasslFaii PasslFaii PasslFaii PasslFaii SatlUnsat NRC 2013 JPM S-6 May 2013 Performance Steps IF High Rad Alarm is confirmed, (BOTH RE-RN04A-3 AND RE-RN04A-4 in alarm OR one in alarm with the other inoperable), AND shell side temperature 2:100F: Direct Shift Chemistry Technician to assess the possible unmonitored radiological release using Attachment 4A of EPIP-EPP-08 Direct Shift Radiation Protection Technician to perform a downwind site boundary radiological survey Role Play: Acknowledge direction as RP IChemistry. IF High Rad Alarm is confirmed, (BOTH RE-RN04A-3 AND RE-RN04A-4 in alarm OR one in alarm with the other inoperable), AND shell side temperature is <100F, direct the Shift Chemistry Technician to obtain AND evaluate an EC shell side sample Role Play: Acknowledge direction as Chemistry.
: 2. Work is complete and EC 11 is ready to be returned to service.
Standard Note: These steps are NI A if shell temperature is <100&deg;F. Directs Chemistry Tech to assess for possible unmonitored release per EPIP-EPP-08 Directs RP Tech to perform downwind survey at site boundary Note: This step is NI A if shell temperature is >100&deg;F. Directs Chemistry Tech to obtain and evaluate EC 11 shell side sample Grade NRC 2013 JPM S-6 -5 May 2013 Performance Steps IF alarm is valid THEN with SM concurrence, close the following valves: 39-07R, EC STM ISOLATION VALVE 112 39-09R, EC STM ISOLATION VALVE 111 39-05, EMERG CNDSR COND RET ISOLATION VALVE 11 39-11R, EMERG CNDSR STM SUPPLY DRAIN IV 111 39-12R, EMERG CNDSR STM SUPPLY DRAIN IV 112 OS-OlR, EMERG COND VENT ISOLATION VALVE 111 05-11, EMERG COND VENT ISOLATION VALVE 112 Role Play: As SM, inform the candidate that the alarm is valid and provide concurrence for isolating EC 11. Standard Closes 39-07R by rotating control switch CCWtoCLOSE Closes 39-09R by rotating control switch CCWtoCLOSE Observes 39-05 green light on, red light off Closes 39-11R by rotating control switch CCWtoCLOSE Closes 39-12R by rotating control switch CCWtoCLOSE Closes OS-OIR by rotating control switch CCWto CLOSE Closes 05-11 by rotating control switch CCW to CLOSE Grade PasslFail PasslFail Sat/Unsat PasslFail PasslFail PasslFail PasslFaii Terminating Cue: EC 11 is isolated due to tube leak. RECORD STOP TIME ____ NRC 2013 JPM 8-6 -6 May 2013 Initial Conditions: Emergency Condenser (EC) 11 is out of service per NI-0P-13 section H.8.1 following corrective maintenance. Work is complete and EC 11 is ready to be returned to service. 3. Non-Destructive Evaluation (NDE) has determined EC steam leg level to be 6 ft 11 inches. Initiating Cues: "(Operator's name), return EC 11 to service per NI-0P-13 section H.8.0." NRC 2013 JPM S-6 -7 May 2013 
: 3. Non-Destructive Evaluation (NDE) has determined EC stearn leg level to be 6 ft 11 inches.
------NRC JPM Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: EDG 103 SID-PB 103 Return to Nonnal Power Revision:
: 4. Instructor to ask operator for any questions.
NRC 2013 (Alternate Path) Task Number: NI A Approvals:
Initiating Cues:
General Supervisor
    "(Operator's name), return EC 11 to service per NI-OP-13 section H.8.0."
'" Date N/A Exam Security General Supervisor I Date Operations Training (Designee)
Performance Steps                                       Standard                                  Grade
Operations (Designee)
: 1. Provide repeat back of initiating cue         Proper communications used                    SatlUnsat (GAP-OPS-Ol)
NIA -Exam Security / Configuration Control Date Perfonner:
Evaluator acknowledge repeat back providing correction ifnecessary.
______________(RO/SRO) TrainerlEvaluator:
RECORD START TIME _______
____________
: 2. Obtain a copy of the reference procedure       NI-OP-13 is obtained, precautions &          SatlUnsat and review/utilize the correct section ofthe  limitations reviewed, section H.8.3 utilized procedure
_ Evaluation Method: __ Perfonn Simulate Evaluation Location:
: 3. VerifY proper keepfullievel as follows:
____ Plant __---'-"--__ Simulator Expected Completion Time: 20 Minutes Time Critical Task: No Alternate Path Task: Yes Start Time: ----Stop 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 un sat or individual competency area unsat requires a comment. Comments:
* Contact Engineering Programs - NDE to       Determines level is 6' 11" per initial        SatlUnsat perform UT ofEC stearn leg for level         conditions determination
Evaluators Signature:
* IF EC stearn leg level is greater than 6'   Proceeds to step 8.3.2                        SatlUnsat 10" THEN proceed to step 8.3.2
______________
: 4. VerifY open the following valves:
_ Date:_______ NRC 2013 JPM S-7 May 2013 Recommended Start Location: (Completion time based on the start location)
* 05-11, EMERG COND VENT                      Opens 05-11 by rotating control switch CW to  PasslFail ISOLATION VALVE 112                          OPEN
NMP Unit 1 Simulator Simulator Set-up (if required):  
* 05-01R, EMERG COND VENT                      Opens 05-0 lR by rotating control switch CW  PasslFail ISOLATION VALVE 111                          to OPEN NRC 2013 JPM S-6                                                                                May 2013
: 1. Initialize Simulator to IC-164. 2. Verify PB 103 is supplied by EDG 103 per NI-OP-45 section E.3 .0. 3. Verify CRD Pump 11 in service. 4. Verify the Annunciator Ll-4-S is overridden to "Fail Off', to simulate alternate SFP pump in service. 5. Verify malfunction RD35B is inserted as "TRUE", to simulate prevent start of 12 CRD pump. 6. Verify override SDS267L02348 is inserted as "OFF", to simulate prevent start of 12 CRD pump. 7. Verify malfunction DGOSB is inserted as "TRUE" for failure of EDG 103 to stop. Directions to the InstructorlEvaluator:
 
Perfonnance Steps                                      Standard                                  Grade
: 5. WHEN system pressure has returned to nonnal, open the following valves:
* 39-11R, EMERG CONDSR STM                  Opens 39-11R by rotating control switch CW     PasslFaii SUPPLY DRAIN IV 111                        to OPEN
* 39-12R, EMERG CONDSR STM                  Opens 39-12R by rotating control switch CW    PasslFaii SUPPLY DRAIN IV 112                        to OPEN
: 6. Open 39-07R, EC STM ISOLAnON                Opens 39-07R by rotating control switch CW    PasslFaii VALVE 112                                   to OPEN Note: The candidate may throttle open 39-07R using the pull-to-stop feature, rather than open it in one continuous motion. However, it must be fully opened by the end of the manipulation.
: 7. Throttle open 39-09R, EC STM                 Opens 39-09R by rotating control switch CW    PasslFaii ISOLAnON VALVE 111 and monitor               to OPEN system parameters during heatup AND repressurization                             Stops 39-09R by pulling control switch out to  SatlUnsat STOP Monitors system temperature and pressures      SatlUnsat Fully opens 39-09R by rotating control switch  SatlUnsati CWtoOPEN                                          NA Note: The alternate path begins when 39-09R red light comes on. This causes an EC tube leak to be initiated.
: 8. Responds to alann KI-I-2                     Acknowledges and reports alann                 SatlUnsat
: 9. Confinn alann on computer printout           Observes computer points E478 and E480 in      SatlUnsat alann
: 10. Confinn radiation levels on J Panel and     Observes E CONDSR VENT RAD MON 111            SatlUnsat contact RP to check dose rates above         (RE-RN04A-3) and E CONDSR VENT RAD elevation 340                               MON 112 (RE-RN04A-4) reading on J Panel and detennines readings indicate alann condition Role Play: Acknowledge direction as RP.            Directs RP to check dose rates above          SatlUnsat elevation 340 NRC 2013 JPM S-6                                                                                May 2013
 
Performance Steps                                  Standard                                    Grade
: 11. IF High Rad Alarm is confirmed, (BOTH RE-RN04A-3 AND RE-RN04A-4 in alarm OR one in alarm with the other            Note: These steps are NIA if shell inoperable), AND shell side temperature    temperature is <100&deg;F.
2:100F:
* Direct Shift Chemistry Technician to    Directs Chemistry Tech to assess for possible    SatlUnsati assess the possible unmonitored        unmonitored release per EPIP-EPP-08                NA radiological release using Attachment 4A of EPIP-EPP-08 SatlUnsatl
* Direct Shift Radiation Protection        Directs RP Tech to perform downwind survey          NA Technician to perform a downwind site  at site boundary boundary radiological survey Role Play: Acknowledge direction as RPIChemistry.
: 12. IF High Rad Alarm is confirmed, (BOTH     Note: This step is NI A if shell temperature is RE-RN04A-3 AND RE-RN04A-4 in alarm         > 100&deg;F.
OR one in alarm with the other inoperable), AND shell side temperature is
      <100F, direct the Shift Chemistry         Directs Chemistry Tech to obtain and evaluate    SatlUnsati Technician to obtain AND evaluate an EC   EC 11 shell side sample                            NA shell side sample Role Play: Acknowledge direction as Chemistry.
NRC 2013 JPM S-6                                                                              May 2013
 
Performance Steps                                        Standard                                 Grade
: 13. IF alarm is valid THEN with SM concurrence, close the following valves:
o  39-07R, EC STM ISOLATION                  Closes 39-07R by rotating control switch      PasslFail VALVE 112                                  CCWtoCLOSE o  39-09R, EC STM ISOLATION                    Closes 39-09R by rotating control switch      PasslFail VALVE 111                                  CCWtoCLOSE o 39-05, EMERG CNDSR COND RET                  Observes 39-05 green light on, red light off  Sat/Unsat ISOLATION VALVE 11 o 39-11R, EMERG CNDSR STM                      Closes 39-11R by rotating control switch      PasslFail SUPPLY DRAIN IV 111                        CCWtoCLOSE o 39-12R, EMERG CNDSR STM                       Closes 39-12R by rotating control switch      PasslFail SUPPLY DRAIN IV 112                        CCWtoCLOSE o OS-OlR, EMERG COND VENT                      Closes OS-OIR by rotating control switch      PasslFail ISOLATION VALVE 111                         CCWto CLOSE o  05-11, EMERG COND VENT                     Closes 05-11 by rotating control switch CCW  PasslFaii ISOLATION VALVE 112                         to CLOSE Role Play: As SM, inform the candidate that the alarm is valid and provide concurrence for isolating EC 11.
Terminating Cue:          EC 11 is isolated due to tube leak.
RECORD STOP TIME _ _ __
NRC 2013 JPM 8-6                                                                                  May 2013
 
Initial Conditions:
: 1. Emergency Condenser (EC) 11 is out of service per NI-0P-13 section H.8.1 following corrective maintenance.
: 2. Work is complete and EC 11 is ready to be returned to service.
: 3. Non-Destructive Evaluation (NDE) has determined EC steam leg level to be 6 ft 11 inches.
Initiating Cues:
    "(Operator's name), return EC 11 to service per NI-0P-13 section H.8.0."
NRC 2013 JPM S-6                                                          May 2013
 
NRC JPM S-7 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
EDG 103 SID- PB 103 Return to Nonnal Power                                  Revision:   NRC 2013 (Alternate Path)
Task Number: NIA Approvals:
N/A  Exam Security              I General Supervisor      '"             Date                      General Supervisor                  Date Operations Training (Designee)                                      Operations (Designee)
NIA - Exam Security                      /
Configuration Control                    Date Perfonner:_ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)
TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __
Evaluation Method: _~_ _ Perfonn                  - - - - - - Simulate Evaluation Location: _ _ _ _ Plant               _ _---'-"--__ Simulator Expected Completion Time:       20 Minutes       Time Critical Task:       No     Alternate Path Task:     Yes Start Time: - - - -             Stop                               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 un sat or individual competency area unsat requires a comment.
Comments:
Evaluators Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __                            Date:_ _ _ _ _ __
NRC 2013 JPM S-7                                                                                       May 2013
 
Recommended Start Location: (Completion time based on the start location)
NMP Unit 1 Simulator Simulator Set-up (if required):
: 1. Initialize Simulator to IC-164.
: 2. Verify PB 103 is supplied by EDG 103 per NI-OP-45 section E.3 .0.
: 3. Verify CRD Pump 11 in service.
: 4. Verify the Annunciator Ll-4-S is overridden to "Fail Off', to simulate alternate SFP pump in service.
: 5. Verify malfunction RD35B is inserted as "TRUE", to simulate prevent start of 12 CRD pump.
: 6. Verify override SDS267L02348 is inserted as "OFF", to simulate prevent start of 12 CRD pump.
: 7. Verify malfunction DGOSB is inserted as "TRUE" for failure of EDG 103 to stop.
Directions to the InstructorlEvaluator:
None Directions to Operators:
None Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
With the exception of accessing panels, NO plant equipment will be physically manipulated.
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.
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.
Read Before Each Training JPM Performance:
The Control Supervisor has determined that a verifier is not available and that additional/concurrent verification will be provided; therefore, it should not be Read Before Each Training JPM During this Training JPM, applicable methods of verification are expected to be used. Therefore, another individual or I will act as the independent/peer verifier.
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  
Notes to Instructor / Evaluator:
/ Evaluator:  
: 1. Critical steps are identified in grading areas PasslFail.
: 1. Critical steps are identified in grading areas PasslFail.  
: 2. During Evaluated JPM:
: 2. During Evaluated JPM:
* Self verification shall be demonstrated.  
* Self verification shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self verification shall be demonstrated.
* Self verification shall be demonstrated.
* No other verification shall be demonstrated.  
* No other verification shall be demonstrated.


==References:==
==References:==
: 1. NUREG 1123,264000, A4.04, RO 3.7, SRO 3.7 2. NI-OP-4S NRC 2013 JPM S-7 May 2013 Tools and Equipment:  
: 1. NUREG 1123,264000, A4.04, RO 3.7, SRO 3.7
: 1. None Task Standard:
: 2. NI-OP-4S NRC 2013 JPM S-7                                                                                       May 2013
Shutdown EDG 103 and reenergize PB 103. Initial Conditions:  
 
: 1. EDG 103 is supplying PB 103 due to maintenance on breaker RlO13. 2. EDG 103 has been at minimum load for the past hour and at 700 KW for the previous 24 hours. 3. 115 KV power is stable. 4. N1-0P-45 section G.2 is complete through step 2.6. 5. Instructor to ask operator for any questions.
Tools and Equipment:
Initiating Cues: "(Operator's name), shutdown EDG 103 and return PB 103 to normal power in accordance with N1-0P-45, beginning at step G.2.7." Performance Steps Grade Provide repeat back of initiating cue Proper communications used SatlUnsat (GAP-OPS-01)
: 1. None Task Standard: Shutdown EDG 103 and reenergize PB 103.
Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME
Initial Conditions:
________ Obtain a copy of the reference procedure N1-0P-45 obtained SatlUnsat and review/utilize the correct section of the Precautions  
: 1. EDG 103 is supplying PB 103 due to maintenance on breaker RlO13.
& limitations reviewed procedure Section G.2 referenced Verify GREEN flagged R1013, PB 103 Rotates R1013 control switch CW from PTL PasslFaii Normal Power Supply Breaker to neutral Place and HOLD in TRIP position R1032, Rotates R1032 control switch CCW and holds PasslFaii Diesel Generator 103 Output Breaker in trip position When 3 to 5 seconds has elapsed, close Rotates RlO13 control switch CW, observes PasslFaii RlO13 red light on, green light off Confirm normal voltage on PB 103 and PB Observes VAC on PB 103 voltmeter, SatlUnsat 17B and observes V AC on PB 17B voltmeter  
: 2. EDG 103 has been at minimum load for the past hour and at 700 KW for the previous 24 hours.
: 7. Return R1 032 to Neutral Releases RI032 to the neutral position PasslFaii NRC 2013 JPM S-7 -3 May 2013 Performance Steps Reset Lockout 86-17 device Note: Lockout device may not need to be reset if R 10 13 is closed closer to 3 seconds than 5 seconds (Step 5 above) Install Close fuse for CRD pump 12 Field operators will install fuse. Note: Delete malfunction RD35B & override 5DS267L02348, then report close fuse for CRD pump 12 has been installed and independently verified. VerifY Green light ON for CRD pump 12 Note: The green light will not be lit until the instructor note in step 9 above is completed.
: 3. 115 KV power is stable.
Role Play: If informed to exit Technical Specification for CRD pump, acknowledge report. VerifY EDG Raw Water Cooling Pump started Cue: EDG 103 Raw Water Cooling Pump has started. Restore normal loads on PB 17B Cue: Another operator will restore PB 1 7B loads. IF EDG has run idle for 8 hours OR operated less than 500 KW for 4.5 hours, THEN shutdown EDG per Section G, Recovery after Light Load Operation Note: This step is NI A based on initial conditions. VerifY Speed Droop set to zero Cue: EDG 103 Speed Droop set to zero Standard Rotates 86-17 control switch CW to reset position Grade PasslFaill NA Proper communications used (GAP-OPS-Ol)
: 4. N1-0P-45 section G.2 is complete through step 2.6.
SatlUnsat Observes CRD pump 12 green light on SatlUnsat Proper communications used (GAP-OPS-Ol)
: 5. Instructor to ask operator for any questions.
SatlUnsat Proper communications used (GAP-OPS-O
Initiating Cues:
: 1) SatlUnsat Determines step is NI A based on initial conditions SatlUnsat Proper communications used (GAP-OPS-Ol)
          "(Operator's name), shutdown EDG 103 and return PB 103 to normal power in accordance with N1-0P-45, beginning at step G.2.7."
SatlUnsat NRC 2013 JPM S-7 May 2013 Performance Steps Adjust Governor to achieve greater than or equal to 60.1 Hz synchronous speed AND the Governor high speed light lit as follows. Adjust speed until governor yellow high speed light is lit Adjust speed to achieve greater than or equal to 60.1 Hz with a maximum of60.2 Hz. Note: This step may be N/A based on EDG speed. Independently verify speed greater than or equal to 60.1 HZ (max 60.2 Hz) Speed is as you adjusted it. Adjust voltage to 4200 V using VOLT ADJ RHEO GEN 103 Place DIESEL GEN 103 control switch in STOP When approximately 3 minute cooldown has elapsed, verify EDG 103 stopped Time compression is in effect, 4 minutes have elapsed. Note: The applicant should recognize that the EDG should have stopped. If the EDG did not shutdown, refer to Section G.8.0, Emergency Shutdown If offsite power is not available, TIffiN verify R1012 OR 1013 in Pull-To-Lock Note: This step is N/A, Offsite power is available per the initial conditions.
Performance Steps                                       Standard                                Grade
Standard Grade Raises EDG 103 speed as necessary by rotating governor control switch CCW, observes yellow high speed light lit Raises EDG 103 speed as necessary by rotating governor control switch CCW, and observes EDG 103 frequency of 60.1-60.2 Hz SatlUnsat SatlUnsat Proper communications used (GAP-OPS-Ol)
: 1. Provide repeat back of initiating cue         Proper communications used                   SatlUnsat (GAP-OPS-01)
SatlUnsat Raises EDG 103 voltage as necessary by rotating voltage regulator control switch CCW, and observes voltage Rotates EDG 103 control switch CCW to STOP position, observes EDG 103 output voltage lower Recognizes that EDG did not stop as it should have SatlUnsat PasslFaii SatlUnsat Refers to N1-0P-45 section G.8.0, Emergency Shutdown Determines offsite power is available per initial conditions SatlUnsat SatlUnsat NRC 2013 JPM S-7 -5 May 2013 Perfonnance Steps Grade IF loss of 125 VDC power is lost due to loss of Battery Board 11, THEN enter N SOP-47A.l to restore 125 VDC power Note: This step is N/A, 125 VDC is available. Place DIESEL GEN control switch to EM STOP Note: It is expected that the candidate will stop the EDG from the Control Room and not attempt to have a field operator to shutdown the EDG locally. Role Play: If contacted to shutdown EDG locally, report that communications have failed and no one can be dispatched to shutdown the EDG locally Detennines 125 VDC power is available based on various control room indications Rotates EDG 103 control switch CCW to EM STOP position, observes EDG 103 frequency lower SatlUnsat Pass/Fail Terminating Cue: EDG 103 stopped and PB 103 energized.
Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME ________
RECORD STOP TIME ____ NRC 2013 JPM S-7 -6 May 2013 Initial Conditions: EDG 103 is supplying PB 103 due to maintenance on breaker RIO 13. EDG 103 has been at minimum load for the past hour and at 700 KW for the previous 24 hours. 115 KV power is stable. NI-0P-45 section G.2 is complete through step 2.6. Initiating Cues: "(Operator's name), shutdown EDG 103 and return PB 103 to normal power in accordance with NI-0P-45, beginning at step G.2.7." NRC 2013 JPM S-7 -7 May 2013 NRC JPM 8-8 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Reset Reactor Scram Revision:
: 2. Obtain a copy of the reference procedure     N1-0P-45 obtained                             SatlUnsat and review/utilize the correct section of the Precautions & limitations reviewed procedure                                     Section G.2 referenced
NRC 2013 Task Number: N/A Approvals:
: 3. Verify GREEN flagged R1013, PB 103           Rotates R1013 control switch CW from PTL     PasslFaii Normal Power Supply Breaker                   to neutral
N/A -Exam Security I General Supervisor Date General Supervisor Date Operations Training (Designee)
: 4. Place and HOLD in TRIP position R1032,       Rotates R1032 control switch CCW and holds   PasslFaii Diesel Generator 103 Output Breaker           in trip position
Operations (Designee)
: 5. When 3 to 5 seconds has elapsed, close       Rotates RlO13 control switch CW, observes     PasslFaii RlO13                                         red light on, green light off
NtA -Exam Security I Configuration Control Date Performer:
: 6. Confirm normal voltage on PB 103 and PB       Observes ~4160 VAC on PB 103 voltmeter,       SatlUnsat 17B                                         and observes ~600 V AC on PB 17B voltmeter
________________(RO/SRO) TrainerlEvaluator:
: 7. Return R1 032 to Neutral Position            Releases RI032 to the neutral position       PasslFaii NRC 2013 JPM S-7                                                                               May 2013
____________
 
_ Evaluation Method: _--"X-",-__ Perform ______ Simulate Evaluation Location:
Performance Steps                                     Standard                              Grade
____ Plant __
: 8. Reset Lockout 86-17 device                   Rotates 86-17 control switch CW to reset  PasslFaill position                                    NA Note: Lockout device may not need to be reset if R 1013 is closed closer to 3 seconds than 5 seconds (Step 5 above)
__ Simulator 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:
: 9. Install Close fuse for CRD pump 12           Proper communications used                SatlUnsat (GAP-OPS-Ol)
Evaluator's Signature:
Cue: Field operators will install fuse.
______________
Note: Delete malfunction RD35B &
_ Date:______NRC 2013 JPM S-8 May Recommended Start Location:
override 5DS267L02348, then report close fuse for CRD pump 12 has been installed and independently verified.
Simulator Simulator Set-up (if required):  
: 10. VerifY Green light ON for CRD pump 12         Observes CRD pump 12 green light on      SatlUnsat Note: The green light will not be lit until the instructor note in step 9 above is completed.
: 1. Initialize Simulator to IC-165. 2. Verify a Reactor scram is inserted and NOT yet reset. 3. Verify all automatic scram signals are clear, with the exception ofSDV high level. 4. Verify all NI-SOP-l steps are completed up to bypassing SDV high level trip. 5. Markup N l-SOP-I to the conditional step to bypass SDV high level trip. 6. Set trigger 1 event as "zcrprest==
Role Play: If informed to exit Technical Specification for CRD pump, acknowledge report.
1 ". 7. Set trigger 1 command as "set rdlsdv = 390". Directions to the InstructorlEvaluator:
: 11. VerifY EDG Raw Water Cooling Pump             Proper communications used                SatlUnsat started                                       (GAP-OPS-Ol)
Cue: EDG 103 Raw Water Cooling Pump has started.
: 12. Restore normal loads on PB 17B               Proper communications used                SatlUnsat (GAP-OPS-O 1)
Cue: Another operator will restore PB 17B loads.
: 13. IF EDG has run idle for 8 hours OR           Determines step is NIA based on initial  SatlUnsat operated less than 500 KW for 4.5 hours,     conditions THEN shutdown EDG per Section G, Recovery after Light Load Operation Note: This step is NI A based on initial conditions.
: 14. VerifY Speed Droop set to zero               Proper communications used               SatlUnsat (GAP-OPS-Ol)
Cue: EDG 103 Speed Droop set to zero NRC 2013 JPM S-7                                                                          May 2013
 
Performance Steps                                  Standard                                  Grade
: 15. Adjust Governor to achieve greater than or equal to 60.1 Hz synchronous speed AND the Governor high speed light lit as follows.
: a. Adjust speed until governor yellow  Raises EDG 103 speed as necessary by          SatlUnsat high speed light is lit             rotating governor control switch CCW, observes yellow high speed light lit
: b. Adjust speed to achieve greater than Raises EDG 103 speed as necessary by          SatlUnsat or equal to 60.1 Hz with a maximum   rotating governor control switch CCW, and of60.2 Hz.                           observes EDG 103 frequency of 60.1-60.2 Hz Note: This step may be N/A based on EDG speed.
: 16. Independently verify speed greater than or Proper communications used                    SatlUnsat equal to 60.1 HZ (max 60.2 Hz)             (GAP-OPS-Ol)
Cue: Speed is as you adjusted it.
: 17. Adjust voltage to 4200 V using VOLT       Raises EDG 103 voltage as necessary by        SatlUnsat ADJ RHEO GEN 103                           rotating voltage regulator control switch CCW, and observes voltage ~4200V
: 18. Place DIESEL GEN 103 control switch in     Rotates EDG 103 control switch CCW to          PasslFaii STOP                                      STOP position, observes EDG 103 output voltage lower
: 19. When approximately 3 minute cooldown      Recognizes that EDG did not stop as it should  SatlUnsat has elapsed, verify EDG 103 stopped        have Cue: Time compression is in effect, 4 minutes have elapsed.
Note: The applicant should recognize that the EDG should have stopped.
: 20. If the EDG did not shutdown, refer to      Refers to N1-0P-45 section G.8.0, Emergency    SatlUnsat Section G.8.0, Emergency Shutdown          Shutdown 2l. If offsite power is not available, TIffiN  Determines offsite power is available per      SatlUnsat verify R1012 OR 1013 in Pull-To-Lock      initial conditions Note: This step is N/A, Offsite power is available per the initial conditions.
NRC 2013 JPM S-7                                                                            May 2013
 
Perfonnance Steps                                  Standard                                Grade
: 22. IF loss of 125 VDC power is lost due to     Detennines 125 VDC power is available      SatlUnsat loss of Battery Board 11, THEN enter N 1    based on various control room indications SOP-47A.l to restore 125 VDC power Note: This step is N/A, 125 VDC is available.
: 23. Place DIESEL GEN control switch to EM        Rotates EDG 103 control switch CCW to EM  Pass/Fail STOP                                        STOP position, observes EDG 103 frequency lower Note: It is expected that the candidate will stop the EDG from the Control Room and not attempt to have a field operator to shutdown the EDG locally.
Role Play: If contacted to shutdown EDG locally, report that communications have failed and no one can be dispatched to shutdown the EDG locally Terminating Cue: EDG 103 stopped and PB 103 energized.
RECORD STOP TIME _ _ __
NRC 2013 JPM S-7                                                                         May 2013
 
Initial Conditions:
: 1. EDG 103 is supplying PB 103 due to maintenance on breaker RIO 13.
: 2. EDG 103 has been at minimum load for the past hour and at 700 KW for the previous 24 hours.
: 3. 115 KV power is stable.
: 4. NI-0P-45 section G.2 is complete through step 2.6.
Initiating Cues:
        "(Operator's name), shutdown EDG 103 and return PB 103 to normal power in accordance with NI-0P-45, beginning at step G.2.7."
NRC 2013 JPM S-7                                                         May 2013
 
NRC JPM 8-8 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
Reset Reactor Scram                                                         Revision:   NRC 2013 Task Number:     N/A Approvals:
N/A - Exam Security               I General Supervisor ~                    Date                       General Supervisor                   Date Operations Training (Designee)                                     Operations (Designee)
NtA - Exam Security                     I Configuration Control                   Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)
TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __
Evaluation Method: _--"X-",-__ Perform           _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant               _ _~-"--__ Simulator 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's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __                          Date:_ _ _ _ _ __
NRC 2013 JPM S-8                                                                                       May 2013
 
Recommended Start Location: Simulator Simulator Set-up (if required):
: 1. Initialize Simulator to IC-165.
: 2. Verify a Reactor scram is inserted and NOT yet reset.
: 3. Verify all automatic scram signals are clear, with the exception ofSDV high level.
: 4. Verify all NI-SOP-l steps are completed up to bypassing SDV high level trip.
: 5. Markup N l-SOP-I to the conditional step to bypass SDV high level trip.
: 6. Set trigger 1 event as "zcrprest== 1".
: 7. Set trigger 1 command as "set rdlsdv = 390".
Directions to the InstructorlEvaluator:
None Directions to Operators:
None Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
With the exception of accessing panels, NO plant equipment will be physically manipulated.
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 1concurrent verification will not be provided; therefore, it should not be requested.
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.
Read Before Each Training JPM Performance:
The Control Supervisor has determined that a verifier is not available and that additional 1 concurrent verification will be provided; therefore, it should not be Read Before Each Training JPM During this Training JPM, applicable methods of verification are expected to be used. Therefore, another individual or I will act as the independent/peer verifier.
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 1 Evaluator:  
Notes to Instructor 1Evaluator:
: 1. Critical steps are identified in grading area as PasslFaii.  
: 1. Critical steps are identified in grading area as PasslFaii.
: 2. During Evaluated JPM:
: 2. During Evaluated JPM:
* Self verification shall be demonstrated.  
* Self verification shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self verification shall be demonstrated.
* Self verification shall be demonstrated.
* Peer verification shall be demonstrated.  
* Peer verification shall be demonstrated.


==References:==
==References:==
: 1. NUREG 1123,295006 AAl.07 (4.1/4.1)  
: 1. NUREG 1123,295006 AAl.07 (4.1/4.1)
: 2. NI-SOP-l Tools and Equipment:
: 2. NI-SOP-l Tools and Equipment: None NRC 2013 JPM S-8                                                                                       May 2013
None NRC 2013 JPM S-8 May 2013 Task Standard:
 
Reactor scram reset, all control rods verified at position 00, and SDV high level scram Initial A manual Reactor scram was initiated 5 minutes ago due to high Turbine vibrations. NI-S0P-I, Reactor Scram, is being executed. Instructor to ask operator for any questions.
Task Standard:         Reactor scram reset, all control rods verified at position 00, and SDV high level scram un bypassed.
Initiating Cue: "(Operator's name), reset the Reactor scram, verify all control rods are at position 00, and un-bypass the SDV high level trip, per Nl-SOP-I." Performance Steps Provide repeat back of initiating cue Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME
Initial Conditions:
_______ Obtain a copy ofthe reference procedure and review/utilize the correct section of the procedure If ALL rod motion has stopped, then place both SCRAM DISCHARGE VOLUME HIGH LEVEL BYPASS switches in BYPASS If auto-initiated scram signals have cleared on CH 11 or CH 12, then: Verify at least 1 CRD pump in service Reset Reactor Scram Verify ALL control rods inserted to position 04 OR beyond by observing one OR more of the following: Full Core Display Demand new OD-7 Option 2 (Control Rod Notch Positions) KI04A&B Red LED lights LIT (1 S20 AuxCR) All RODS IN Light Illuminated (Remote Shutdown Panel) Standard Proper communications used (GAP-OPS-Ol)
: 1. A manual Reactor scram was initiated 5 minutes ago due to high Turbine vibrations.
NI-S0P-l obtained Rotates SCRAM DISCHARGE VOL HIGH LEVEL BYPASS CH 11-1/12-1 switch CW to BYPASS Rotates SCRAM DISCHARGE VOL HIGH LEVEL BYPASS CH 11-2112-2 switch CW to BYPASS Observes all auto-initiated scram signals have cleared or been bypassed (SDV high level) Observes CRD pump green light off, red light on, amps Depresses REACTOR TRIP RESET pushbutton Observes all control rods are inserted to position 00 Grade SatlUnsat SatlUnsat PassfFaii PassfFaii SatlUnsat SatlUnsat PassfFaii SatlUnsat NRC 2013 JPM 8-8 -3 May 2013 Performance Steps Grade ConfIrm the following valves open: 44.2-15 AND 44.2-16, CONTROL ROD DRIVE DUMP VOL VENT VALVE 44.2-17 AND 44.2-18, CONTROL ROD DUMP VOL DRAIN IV Confirm F3-2-4, CRD DRAIN -VENT VALVE CLOSED, clear. If: F3-1-4, CONT ROD DRIVE SCRAM DUMP VOLUME WTR LVL HIGH, clears AND
: 2. NI-S0P-I, Reactor Scram, is being executed.
* F 1-1-8, RPS CH 11 SCRAM DUMP VOL WTR LVL HIGH, clears AND F4-1-1, RPS CH 12 SCRAM DUMP VOL WTR L VL HIGH, clears then: Note: It will take a few minutes after the scram is reset for these annunciators to clear. Place SCRAM DISCHARGE VOL HIGH LEVEL BYPASS switches to DISCH VOL. ConfIrm F3-3-4, RPS CRD SCRAM DUMP VOL BY-PASS, clears. Observes 44.2-15 green light off, red light on Observes 44.2-16 green light off, red light on Observes 44.2-17 green light off, red light on Observes 44.2-18 green light off, red light on Observes F3-2-4 NOT lit Observes F3-1-4 NOT lit Observes F 1-1-8 NOT lit Observes F4-1-1 NOT lit Rotates SCRAM DISCHARGE VOL HIGH LEVEL BYPASS CH 11-1112-1 switch CCW to DISCH VOL. Rotates SCRAM DISCHARGE VOL HIGH LEVEL BYPASS CH 11-2/12-2 switch CCW to DISCH VOL. Observes F3-3-4 NOT in alarm SatlUnsat SatlUnsat SatlUnsat SatlUnsat SatiUnsat SatlUnsat SatlUnsat SatlUnsat PasslFaii PasslFail SatlUnsat Terminating Cne: Reactor scram reset, all control rods verifIed at position 00, and SDV high level scram bypassed.
: 3. Instructor to ask operator for any questions.
RECORD STOP TIME ___NRC 2013 JPM 8-8 May 2013 Initial Conditions:  
Initiating Cue:
: 1. A manual Reactor scram was initiated 5 minutes ago due to high Turbine vibrations.  
    "(Operator's name), reset the Reactor scram, verify all control rods are at position 00, and un-bypass the SDV high level trip, per Nl-SOP-I."
Performance Steps                                       Standard                                        Grade
: 1. Provide repeat back of initiating cue             Proper communications used (GAP-OPS-Ol)            SatlUnsat Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME _______
: 2. Obtain a copy ofthe reference procedure           NI-S0P-l obtained                                  SatlUnsat and review/utilize the correct section ofthe procedure
: 3. If ALL rod motion has stopped, then place         Rotates SCRAM DISCHARGE VOL HIGH                  PassfFaii both SCRAM DISCHARGE VOLUME                       LEVEL BYPASS CH 11-1/12-1 switch CW HIGH LEVEL BYPASS switches in                     to BYPASS BYPASS Rotates SCRAM DISCHARGE VOL HIGH                  PassfFaii LEVEL BYPASS CH 11-2112-2 switch CW to BYPASS
: 4. If auto-initiated scram signals have cleared     Observes all auto-initiated scram signals have    SatlUnsat on CH 11 or CH 12, then:                         cleared or been bypassed (SDV high level)
: 5. Verify at least 1 CRD pump in service             Observes CRD pump green light off, red light      SatlUnsat on, amps
: 6. Reset Reactor Scram                               Depresses REACTOR TRIP RESET                      PassfFaii pushbutton
: 7. Verify ALL control rods inserted to               Observes all control rods are inserted to          SatlUnsat position 04 OR beyond by observing one           position 00 OR more of the following:
* Full Core Display
* Demand new OD-7 Option 2 (Control Rod Notch Positions)
* KI04A&B Red LED lights LIT (1 S20 AuxCR)
* All RODS IN Light Illuminated (Remote Shutdown Panel)
NRC 2013 JPM 8-8                                                                                         May 2013
 
Performance Steps                                 Standard                                        Grade
: 8. ConfIrm the following valves open:
* 44.2-15 AND 44.2-16, CONTROL           Observes 44.2-15 green light off, red light on      SatlUnsat ROD DRIVE DUMP VOL VENT VALVE                                 Observes 44.2-16 green light off, red light on      SatlUnsat
* 44.2-17 AND 44.2-18, CONTROL           Observes 44.2-17 green light off, red light on      SatlUnsat ROD DUMP VOL DRAIN IV Observes 44.2-18 green light off, red light on    SatlUnsat
: 9. Confirm F3-2-4, CRD DRAIN - VENT           Observes F3-2-4 NOT lit                            SatiUnsat VALVE CLOSED, clear.
: 10. If:
* F3-1-4, CONT ROD DRIVE SCRAM             Observes F3-1-4 NOT lit                            SatlUnsat DUMP VOLUME WTR LVL HIGH, clears AND
* F 1-1-8, RPS CH 11 SCRAM DUMP             Observes F 1-1-8 NOT lit                          SatlUnsat VOL WTR LVL HIGH, clears AND
* F4-1-1, RPS CH 12 SCRAM DUMP             Observes F4-1-1 NOT lit                            SatlUnsat VOL WTR LVL HIGH, clears then:
Note: It will take a few minutes after the scram is reset for these annunciators to clear.
: 11. Place SCRAM DISCHARGE VOL HIGH             Rotates SCRAM DISCHARGE VOL HIGH                  PasslFaii LEVEL BYPASS switches to DISCH             LEVEL BYPASS CH 11-1112-1 switch CCW VOL.                                      to DISCH VOL.
Rotates SCRAM DISCHARGE VOL HIGH                   PasslFail LEVEL BYPASS CH 11-2/12-2 switch CCW to DISCH VOL.
: 12. ConfIrm F3-3-4, RPS CRD SCRAM              Observes F3-3-4 NOT in alarm                       SatlUnsat DUMP VOL BY-PASS, clears.
Terminating Cne: Reactor scram reset, all control rods verifIed at position 00, and SDV high level scram un bypassed.
RECORD STOP TIME _ _ __
NRC 2013 JPM 8-8                                                                                   May 2013
 
Initial Conditions:
: 1. A manual Reactor scram was initiated 5 minutes ago due to high Turbine vibrations.
: 2. NI-SOP-I, Reactor Scram, is being executed.
: 2. NI-SOP-I, Reactor Scram, is being executed.
Initiating Cue: "(Operator's name), reset the Reactor scram, verify all control rods are at position 00, and un-bypass the SDV high level trip, per NI-SOP-I." NRC 2013 JPM 8-8 May 2013 NRC JPM Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Initiating Emergency Cooling System #11 Locally Revision:
Initiating Cue:
NRC 2013 Task Number: N/A Approvals:
    "(Operator's name), reset the Reactor scram, verify all control rods are at position 00, and un-bypass the SDV high level trip, per NI-SOP-I."
NIA -Exam Security / General Supervisor " Date General Supervisor Date Operations Training (Designee)
NRC 2013 JPM 8-8                                                                 May 2013
Operations (Designee)
 
Configuration Control Date Performer:
NRC JPM P-1 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
_______________(RO/SRO) TrainerlEvaluator:
 
____________
==Title:==
_ Evaluation Method: ____Perform ____ Simulate Evaluation Location:  
Initiating Emergency Cooling System #11 Locally                             Revision: NRC 2013 Task Number: N/A Approvals:
----''-''-
NIA - Exam Security               /
__ Plant ______ Simulator Expected Completion Time: 15 minutes 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 un sat or individual competency area unsat requires a comment. Comments:
General Supervisor         "             Date                       General Supervisor                   Date Operations Training (Designee)                                     Operations (Designee)
Evaluators Signature:
Configuration Control                   Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)
______________NRC 2013 JPM P-l Recommended Start Location: (Completion time based on the start location)
TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __
Turbine Building elevation 261 ' Simulator Set-up (if required):
Evaluation Method: _ _ _ _ Perform                _ _~-"-__ Simulate Evaluation Location: ----''-''-__ Plant           _ _ _ _ _ _ Simulator Expected Completion Time:       15 minutes       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 un sat or individual competency area unsat requires a comment.
Comments:
Evaluators Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __
NRC 2013 JPM P-l                                                                                         May20l3
 
Recommended Start Location: (Completion time based on the start location)
Turbine Building elevation 261 '
Simulator Set-up (if required):
None Directions to the InstructorlEvaluator:
None Directions to the InstructorlEvaluator:
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.
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:
Directions to Operators:
Read Before JPM Performance:
Read Before         JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identifY the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
With the exception of accessing panels, NO plant equipment will be physically manipulated.
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.
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.
Read Before Each Training JPM Performance:
The Control Supervisor has determined that a verifier is not available and that additional/concurrent verification will be provided; therefore, it should not be Read Before Each Training JPM During this Training JPM, applicable methods of verification are expected to be used. Therefore, another individual or I will act as the independent/peer verifier.
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  
Notes to Instructor / Evaluator:
/ Evaluator:  
: 1. Critical steps are identified in grading areas Pass/Fail. All steps are sequenced critical unless denoted by a "e".
: 1. Critical steps are identified in grading areas Pass/Fail.
: 2. During Evaluated JPM:
All steps are sequenced critical unless denoted by a "e". 2. During Evaluated JPM:
* Self verification shall be demonstrated.
* Self verification shall be demonstrated.  
: 3. During Training JPM:
: 3. During Training JPM:
* Self verification shall be demonstrated.  
* Self verification shall be demonstrated.


==References:==
==References:==
: 1. NUREG 1123,207000, A2.08, RO 3.8, SRO 3.8 2. NI-0P-13 Tools and Equipment:
: 1. NUREG 1123,207000, A2.08, RO 3.8, SRO 3.8
None NRC 2013 JPM P-1 May 2013 Task Standard:
: 2. NI-0P-13 Tools and Equipment:
Emergency Condenser Loop 12 placed in service locally. Initial Conditions:  
None NRC 2013 JPM P-1                                                                                       May 2013
: 1. The Reactor has failed to scram and NI-EOP-3 has been entered. 2. The Emergency Condenser Condensate Return Valves have failed to open. 3. NI-0P-13 section H.2 is complete through step 2.3. 4. Instructor to ask operator for any questions.
 
Initiating Cues: "(Operator's name), place Emergency Condenser Loop 11 in service by opening the Condensate Return Valve locally in accordance with NI-0P-13 starting at step H.2.4." Performance Steps Grade Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)
Task Standard: Emergency Condenser Loop 12 placed in service locally.
Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME
Initial Conditions:
_______ Obtain a copy of the reference procedure NI-0P-13 obtained, precautions  
: 1. The Reactor has failed to scram and NI-EOP-3 has been entered.
& limitations SatlUnsat and review/utilize the correct section of the reviewed & section H.2 referenced procedure Close 113-529, BV-IA Manifold Supply to 113-529 handwheel rotated fully CW PasslFaii -A-22110-C SH. 14. Cue: The indicated handwheel is rotated fully in the direction indicated. Using wrench, remove cap from 113-530, Cap removed from 113-530 by rotating CCW PasslFaii Vent-IA Manifold The cap is removed. Note: A wrench is hanging below the air pipe. 5. Open 113-530 handwheel rotated fully CCW PasslFaii The indicated handwheel is rotated fully in the direction indicated.
: 2. The Emergency Condenser Condensate Return Valves have failed to open.
No air flow is heard. Role If contacted as Control Room, report that Emergency Condenser 11 has NOT gone into service. NRC 2013 JPM P-l May 2013 Role [f contacted as Control Room on how to proceed, direct initiation of Emergency Condenser 12 locally. Close 113-532, BV-IA MANIFOLD 113-532 handwheel rotated fully CW Pass/Fail SUPPLY TO -A-221 1 O-C SH.14 Cue: The indicated handwheel is rotated fully in the direction indicated. Using wrench, remove cap from 113-533, Cap removed from 113-533 by rotating CCW Pass/Fail Vent-IA Manifold Cue: The cap is Note: A wrench is hanging below the air Open 113-533 113-533 handwheel rotated fully CCW The indicated handwheel is rotated fully in the direction indicated.
: 3. NI-0P-13 section H.2 is complete through step 2.3.
Air flow is heard. Role If contacted as Control Room, report that Emergency Condenser 12 has gone into service. Reports task completion.
: 4. Instructor to ask operator for any questions.
Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)
Initiating Cues:
Terminating Cue: Emergency Condenser Loop 12 placed in service locally. RECORD STOP TIME ____ NRC 2013 JPM P-I May 2013 Initial Conditions:  
    "(Operator's name), place Emergency Condenser Loop 11 in service by opening the Condensate Return Valve locally in accordance with NI-0P-13 starting at step H.2.4."
: 1. The Reactor has failed to scram and NI-EOP-3 has been entered. 2. The Emergency Condenser Condensate Return Valves have failed to open. 3. NI-OP-I3 section H.2 is complete through step 2.3. Initiating Cues: "(Operator's name), place Emergency Condenser Loop 11 in service by opening the Condensate Return Valve locally in accordance with NI-OP-I3 starting at step H.2.4." NRC 2013 JPM P-l May 2013
Performance Steps                                       Standard                                  Grade
------NRC JPM Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Respond to RBCLC Makeup Tank Level Alarm Revision:
: 1. Provide repeat back of initiating cue         Proper communications used for repeat back   SatlUnsat (GAP-OPS-Ol)
NRC 2013 Task Number: N/A Approvals:
Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME _______
NIA -Exam Security I , General Supervisor Date General Supervisor Date Operations Training (Designee)
: 2. Obtain a copy of the reference procedure     NI-0P-13 obtained, precautions & limitations SatlUnsat and review/utilize the correct section of the reviewed & section H.2 referenced procedure
Operations (Designee)
: 3. Close 113-529, BV-IA Manifold Supply to       113-529 handwheel rotated fully CW           PasslFaii
NtA -Exam Security I Configuration Control Date Performer:
      -A-22110-C SH. 14.
_______________
Cue: The indicated handwheel is rotated fully in the direction indicated.
(.RO/SRO)
: 4. Using wrench, remove cap from 113-530,       Cap removed from 113-530 by rotating CCW     PasslFaii Vent-IA Manifold Cue: The cap is removed.
TrainerlEvaluator:
Note: A wrench is hanging below the air pipe.
____________
: 5. Open 113-530                                  113-530 handwheel rotated fully CCW           PasslFaii Cue: The indicated handwheel is rotated fully in the direction indicated. No air flow is heard.
_ Evaluation Method: ____ Perform __---"-=---__ Simulate Evaluation Location: __ Plant Simulator Expected Completion Time: 15 minutes Time Critical Task: No Alternate Path Task: Yes Start Time: ____ Stop Time: _____ Completion 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 un sat or individual competency area unsat requires a comment. Comments:
Role Play: If contacted as Control Room, report that Emergency Condenser 11 has NOT gone into service.
Evaluators Date:______NRC 2013 JPM P-2 May Recommended Start Location: (Completion time based on the start location)
NRC 2013 JPM P-l                                                                               May 2013
Turbine Building elevation 261 ' Simulator Set-up (if required):
 
Role Play: [f contacted as Control Room on how to proceed, direct initiation of Emergency Condenser 12 locally.
: 6. Close 113-532, BV-IA MANIFOLD               113-532 handwheel rotated fully CW         Pass/Fail SUPPLY TO - A-221 1O-C SH.14 Cue: The indicated handwheel is rotated fully in the direction indicated.
: 7. Using wrench, remove cap from 113-533,     Cap removed from 113-533 by rotating CCW   Pass/Fail Vent-IA Manifold Cue: The cap is removed.
Note: A wrench is hanging below the air pipe.
: 8. Open 113-533                               113-533 handwheel rotated fully CCW       Pass/Fail Cue: The indicated handwheel is rotated fully in the direction indicated. Air flow is heard.
Role Play: If contacted as Control Room, report that Emergency Condenser 12 has gone into service.
: 9. Reports task completion.                   Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)
Terminating Cue:         Emergency Condenser Loop 12 placed in service locally.
RECORD STOP TIME _ _ __
NRC 2013 JPM P-I                                                                         May 2013
 
Initial Conditions:
: 1. The Reactor has failed to scram and NI-EOP-3 has been entered.
: 2. The Emergency Condenser Condensate Return Valves have failed to open.
: 3. NI-OP-I3 section H.2 is complete through step 2.3.
Initiating Cues:
    "(Operator's name), place Emergency Condenser Loop 11 in service by opening the Condensate Return Valve locally in accordance with NI-OP-I3 starting at step H.2.4."
NRC 2013 JPM P-l                                                             May 2013
 
NRC JPM P-2 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
Respond to RBCLC Makeup Tank Level Alarm                                     Revision: NRC 2013 Task Number: N/A Approvals:
General Supervisor
                              ,          Date NIA - Exam Security General Supervisor I
Date Operations Training (Designee)                                     Operations (Designee)
NtA - Exam Security                     I Configuration Control                   Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _(.RO/SRO)
TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __
Evaluation Method: _ _ _ _ Perform               _ _---"-=---_ _    Simulate Evaluation Location: ~~__     Plant             - - - - - - Simulator Expected Completion Time:       15 minutes       Time Critical Task:       No     Alternate Path Task:     Yes Start Time: _ _ __              Stop Time: _ _ _ __                Completion 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 un sat or individual competency area unsat requires a comment.
Comments:
Evaluators                                                                   Date:_ _ _ _ _ __
NRC 2013 JPM P-2                                                                                         May 2013
 
Recommended Start Location: (Completion time based on the start location)
Turbine Building elevation 261 '
Simulator Set-up (if required):
None Directions to the InstructorlEvaluator:
None Directions to the InstructorlEvaluator:
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.
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:
Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
For the performance ofthis 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 identity the steps to be simulated, or discuss and provide cues as necessary.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identity the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
With the exception of accessing panels, NO plant equipment will be physically manipulated.
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.
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.
Read Before Each Training JPM Performance:
The Control Supervisor has determined that a verifier is not available and that additional/concurrent verification will be provided; therefore, it should not be Read Before Each Training JPM During this Training JPM, applicable methods of verification are expected to be used. Therefore, another individual or I will act as the independent/peer verifier.
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  
Notes to Instructor / Evaluator:
/ Evaluator:  
: 1. Critical steps are identified in grading areas PasslFail.
: 1. Critical steps are identified in grading areas PasslFail.  
: 2. During Evaluated JPM:
: 2. During Evaluated JPM:
* Self verification shall be demonstrated.  
* Self verification shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self verification shall be demonstrated.  
* Self verification shall be demonstrated.


==References:==
==References:==
: 1. NUREG 1123,295018, AA2.04 (2.9/2.9)  
: 1. NUREG 1123,295018, AA2.04 (2.9/2.9)
: 2. ARP Tools and Task Standard:
: 2. ARP HI-4-4 Tools and Equipment:
CLC makeup tank level restored to normal NRC 2013 JPM P-2 May 2013 Initial Conditions: The Control Room has received annunciator Hl-4-4, CLOSED LOOP COOL MAKEUP TANK LEVEL HIGH-LOW. Computer point Bl15, CLC MU TK LVL -HIGH, is in alarm. Control Room indications show CLC Makeup tank level is 7' and rising. Annunciator Hl-4-5, LQ PROCESS RAD MON, is NOT in alarm. Instructor to ask operator for any questions.
None Task Standard: CLC makeup tank level restored to normal band.
Initiating Cues: "(Operator's name), perform the field actions for the high CLC Makeup tank level per ARP HI-4-4." Performance Steps Grade Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)
NRC 2013 JPM P-2                                                                                       May 2013
Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME
 
________ Obtain a copy of the reference procedure ARP Hl-4-4 obtained SatlUnsat and review/utilize the correct section of the procedure Note: All valves listed in this JPM are located on Turbine Building elevation 351'. The candidate may also do a visual inspection of a level control valve on Turbine Building elevation 261'. Check status of annunciator H 1-4-5 AND Determines from initial conditions that Hl-4-SatlUnsat if in alarm, perform applicable actions of 5 is NOT in alarm Ann. Hl-4-5 AND continue with actions below Close 71-229, BV-CLC MAKE-UP Closes 71-229 by rotating handwheel fully PasslFaii TANK INLET FROM MAKE-UP LCV CW Cue: The indicated handwheel is rotated fully in the indicated direction. Open 71-224, DRAIN -CLC MAKE-UP Opens 71-224 by rotating handwheel CCW PasslFaii TANK The indicated handwheel is rotated in the direction indicated.
Initial Conditions:
NRC 2013 JPM P-2 May 2013 Performance Steps Grade WHEN level is restored to normal range, Observes CLC Makeup tank level SatlUnsat close 71-224, DRAIN -CLC MAKE-UP TANK CLC Makeup tank level indicates 6' and slowly lowering. The indicated handwheel is rotated fully in Closes 71-224 by rotating handwheel fully Pass/Fail the direction indicated.
: 1. The Control Room has received annunciator Hl-4-4, CLOSED LOOP COOL MAKEUP TANK LEVEL HIGH-LOW.
CW IF level is steady, THEN reopen 71-229 Observes CLC Makeup tank level SatlUnsat and monitor operation Does NOT reopen 71-229 SatlUnsat CLC Makeup tank level indicates 7' and slowly rising. IF level continues to rise, THEN throttle Opens 71-224 by rotating handwheel CCW Pass/Fail 71-224, CLC MU TANK DRAIN as necessary and notifY SM The indicated handwheel is rotated in the direction indicated. CLC Makeup tank level indicates 6' and Observes CLC Makeup tank level SatlUnsat stable. Reports task completion.
: 2. Computer point Bl15, CLC MU TK LVL - HIGH, is in alarm.
Proper communications used (GAP-OPS-OI)
: 3. Control Room indications show CLC Makeup tank level is 7' and rising.
SatlUnsat Terminating Cue: CLC makeup tank level restored to normal band. RECORD STOP TIME ____ NRC 2013 JPM P-2 May 2013 Initial Conditions: The Control Room has received annunciator HI-4-4, CLOSED LOOP COOL MAKEUP TANK LEVEL HIGH-LOW. Computer point B115, CLC MU TK L VL -HIGH, is in alarm. Control Room indications show CLC Makeup tank level is 7' and rising. Annunciator HI-4-5, LQ PROCESS RAD MON, is NOT in alann. Initiating Cues: "(Operator's name), perform the field actions for the high CLC Makeup tank level per ARP Hl-4-4." NRC 2013 JPM P-2 May 2013
: 4. Annunciator Hl-4-5, LQ PROCESS RAD MON, is NOT in alarm.
----------------------
: 5. Instructor to ask operator for any questions.
NRC JPM P-3 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Lineup to Flood the Reactor Vessel Using the Diesel Fire Pump Revision:
Initiating Cues:
NRC 2013 Task Number: N/A Approvals:
    "(Operator's name), perform the field actions for the high CLC Makeup tank level per ARP HI-4-4."
I ShJc2 NIA -Exam Security I General Supervisor Date General Supervisor Date Operations Training (Designee)
Performance Steps                                       Standard                                  Grade
Operations (Designee)
: 1. Provide repeat back of initiating cue         Proper communications used for repeat back     SatlUnsat (GAP-OPS-Ol)
NIA -Exam Security I Configuration Control Date Performer:
Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME ________
_______________
: 2. Obtain a copy of the reference procedure       ARP Hl-4-4 obtained                           SatlUnsat and review/utilize the correct section of the procedure Note: All valves listed in this JPM are located on Turbine Building elevation 351'. The candidate may also do a visual inspection of a level control valve on Turbine Building elevation 261'.
(,RO/SRO)
: 3. Check status of annunciator H 1-4-5 AND       Determines from initial conditions that Hl SatlUnsat if in alarm, perform applicable actions of     5 is NOT in alarm Ann. Hl-4-5 AND continue with actions below
: 4. Close 71-229, BV-CLC MAKE-UP                   Closes 71-229 by rotating handwheel fully     PasslFaii TANK INLET FROM MAKE-UP LCV                   CW Cue: The indicated handwheel is rotated fully in the indicated direction.
: 5. Open 71-224, DRAIN - CLC MAKE-UP               Opens 71-224 by rotating handwheel CCW         PasslFaii TANK Cue: The indicated handwheel is rotated in the direction indicated.
NRC 2013 JPM P-2                                                                                   May 2013
 
Performance Steps                                     Standard                              Grade
: 6. WHEN level is restored to normal range,       Observes CLC Makeup tank level             SatlUnsat close 71-224, DRAIN - CLC MAKE-UP TANK Cue: CLC Makeup tank level indicates 6' and slowly lowering.
Cue: The indicated handwheel is rotated fully in   Closes 71-224 by rotating handwheel fully Pass/Fail the direction indicated.                     CW
: 7. IF level is steady, THEN reopen 71-229       Observes CLC Makeup tank level             SatlUnsat and monitor operation Does NOT reopen 71-229                     SatlUnsat Cue: CLC Makeup tank level indicates 7' and slowly rising.
: 8. IF level continues to rise, THEN throttle     Opens 71-224 by rotating handwheel CCW     Pass/Fail 71-224, CLC MU TANK DRAIN as necessary and notifY SM Cue: The indicated handwheel is rotated in the direction indicated.
Cue: CLC Makeup tank level indicates 6' and         Observes CLC Makeup tank level             SatlUnsat stable.
: 9. Reports task completion.                     Proper communications used (GAP-OPS-OI)   SatlUnsat Terminating Cue:         CLC makeup tank level restored to normal band.
RECORD STOP TIME _ _ __
NRC 2013 JPM P-2                                                                           May 2013
 
Initial Conditions:
: 1. The Control Room has received annunciator HI-4-4, CLOSED LOOP COOL MAKEUP TANK LEVEL HIGH-LOW.
: 2. Computer point B115, CLC MU TK LVL - HIGH, is in alarm.
: 3. Control Room indications show CLC Makeup tank level is 7' and rising.
: 4. Annunciator HI-4-5, LQ PROCESS RAD MON, is NOT in alann.
Initiating Cues:
    "(Operator's name), perform the field actions for the high CLC Makeup tank level per ARP Hl-4-4."
NRC 2013 JPM P-2                                                             May 2013
 
NRC JPM P-3 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE
 
==Title:==
Lineup to Flood the Reactor Vessel Using the Diesel Fire Pump                 Revision: NRC 2013 Task Number: N/A Approvals:
General Supervisor I
Date ShJc2                 NIA - Exam Security General Supervisor I
Date Operations Training (Designee)                                     Operations (Designee)
NI A - Exam Security                     I Configuration Control                   Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _(,RO/SRO)
TrainerlEvaluator:
TrainerlEvaluator:
Evaluation Method: _______ Perform ___--"-"'-___ Simulate Evaluation Location: __ Plant __________
Evaluation Method: _______ Perform               ___--"-"'-___ Simulate Evaluation Location: _~__       Plant           __________ Simulator Expected Completion Time:       15 minutes       Time Critical Task:       No     Alternate Path Task:     No Start Time: _ _ __              Stop Time: _________               Completion Time:.______
Simulator 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:
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.
Evaluators Signature:
Comments:
________________________
Evaluators Signature: _________________________
_ NRC 2013 JPM P-3 May 2013 Recommended Start Location: (Completion time based on the start location)
NRC 2013 JPM P-3                                                                                         May 2013
 
Recommended Start Location: (Completion time based on the start location)
NMP Unit 1 Turbine Building Elevation 261' Simulator Set-up (if required):
NMP Unit 1 Turbine Building Elevation 261' Simulator Set-up (if required):
None Directions to the Instructor/Evaluator:
None Directions to the Instructor/Evaluator:
Line 881: Line 1,581:
Directions to Operators:
Directions to Operators:
Read Before Every JPM Performance:
Read Before Every JPM Performance:
For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.
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.
Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.
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.
During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.
Read Before Each Evaluated JPM Performance:
With the exception of accessing panels, NO plant equipment will be physically manipulated.
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.
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.
Read Before Each Training JPM Performance:
The Control Supervisor has determined that a verifier is not available and that additional/concurrent verification will be provided; therefore, it should not be Read Before Each Training JPM During this Training JPM, applicable methods of verification are expected to be used. Therefore, another individual or I will act as the independent/peer verifier.
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  
Notes to Instructor / Evaluator:
/ Evaluator:  
: 1. Critical steps are identified in grading areas PasslFail.
: 1. Critical steps are identified in grading areas PasslFail.  
: 2. During Evaluated JPM:
: 2. During Evaluated JPM:
* Self verification shall be demonstrated.  
* Self verification shall be demonstrated.
: 3. During Training JPM:
: 3. During Training JPM:
* Self verification shall be demonstrated.
* Self verification shall be demonstrated.
* No other verification shall be demonstrated.  
* No other verification shall be demonstrated.


==References:==
==References:==
: 1. NUREG 1123 KA 295031 EA1.08, RO 3.8, SRO 3.9 2. Nl-S0P-21.2, Attachment 4 Tools and Equipment:  
: 1. NUREG 1123 KA 295031 EA1.08, RO 3.8, SRO 3.9
: 1. None NRC 2013 JPM P-3 May 2013 Task Standard: Fire system water entering the RPV through the Feedwater System Initial Conditions: The Control Room has been evacuated due to a fire. Nl-SOP-2L2 has been entered. 3. Instructor to ask for any questions.
: 2. Nl-S0P-21.2, Attachment 4 Tools and Equipment:
Initiating Cues: "(Operator's name), inject water into the RPV in accordance with Nl-S0P-21.2, Attachment 4, using the Diesel Fire Pump." Provide repeat back of initiating cue Evaluator acknowledge repeat back providing correction ifnecessary RECORD START TIME ____ Obtain a copy of the reference procedure and review/utilize the correct section of the procedure. Verity locked closed the following valves (TB 261 '): 29-07, FIRE WATER TO FEED WATER AFTER SPOOL PIECE 62) 100-33, FIRE WATER FEED WATER SPOOL PIECE INLET 63) Valves 29-07 and 100-33 are LOCKED closed. Note: The lock on these valves would require a V A-I key. Proper communications used (GAP-OPS-Ol)
: 1. None NRC 2013 JPM P-3                                                                                       May 2013
SatiUnsat Nl-SOP-2L2, Attachment 4 obtained SatiUnsat 29-07 verified closed by ensuring handwheel in fully CW position and locking device installed 100-33 verified closed by ensuring handwheel in fully CW position and locking device installed SatiUnsat SatiUnsat NRC 2013 JPM P-3 May 2013 Performance Steps Remove drain line from 29-07, Feed System blank flange, Remove blank flanges from Feedwater AND Fire System lines, and Install spoolpiece to intertie Feedwater AND Fire System lines Note: Have applicant show where the spool piece and tools are located (next to entrance of the Demin Recycle Valve Room, TB 261' , and in the gang box labeled "For EOP Use Only, Box 1" on the floor beneath the spool piece) and where spool piece is to be installed.
 
The EOP tool box should not be entered.
Task Standard: Fire system water entering the RPV through the Feedwater System Initial Conditions:
Cue: The spool piece has been installed by a Damage Control Team. N I-SOP-21.2 Attachment 4 steps 2-4 have been verified complete. Unlock the following valves: 100-33, FIRE WATER TO FEED WATER SPOOL PIECE INLET 63) 29-07, FIRE WATER TO FEED WATER AFTER SPOOL PIECE 62) Cue: Valves 100-33 and 29-07 are unlocked.
: 1. The Control Room has been evacuated due to a fire.
Note: The lock on these valves would require a V A-I key. Supply the fire header by performing one of the following: Start Diesel Fire Pump. Once Candidate addresses the need to start the Diesel Fire Pump, report that another Operator in the screenhouse has started the Diesel Fire Pump. Standard Locates spool piece and tools Proper communications used (GAP-OPS-Ol)
: 2. Nl-SOP-2L2 has been entered.
SatlUnsat Lock and restraint removed from 100-33 PasslFail Lock and restraint removed from 29-07 PasslFail Examinee indicates need to start Diesel Fire Pump per initial conditions Proper communications used (GAP-OPS-O
: 3. Instructor to ask for any questions.
: 1) PasslFaii SatlUnsat NRC 2013 JPM P-3 May 2013 Performance Steps When directed by the CRS/SM, open the following valves to begin injection into RPV: 29-07, FIRE WATER TO FEED WATER AFTER SPOOL PIECE 100-33, FIRE WATER TO FEED WATER SPOOL PIECE INLET Cue: Valves 29-07 and 100-33 are open and injection to the RPV has commenced Verify no leakage at spool piece connections Cue: There is no leakage from the spool piece connections Notifies CRS/SM that fire water is being injected to the RPV Role Play: Acknowledge report Standard Determines direction has already been given in initiating cue 29-07 opened by turning handwheel fully CCW 100-33 opened by turning handwheel fully CCW Verifies by visual inspection that there is no leakage at the spool piece connections Proper communications used (GAP-OPS-Ol)
Initiating Cues:
Grade PasslFail PasslFaii SatlUnsat SatlUnsat Terminating Cue: Fire System water entering the RPV through the Feedwater System RECORD STOP TIME ____ NRC 2013 JPM P-3 May 2013 Initial Conditions:  
    "(Operator's name), inject water into the RPV in accordance with Nl-S0P-21.2, Attachment 4, using the Diesel Fire Pump."
: 1. The Control Room has been evacuated due to a fire. 2. NI-SOP-21.2 has been entered. Initiating Cues: "(Operator's name), inject water into the RPV in accordance with NI-SOP-21.2, Attachment 4, using the Diesel Fire Pump." NRC 2013 JPM P*3 May 2013 NMP SIMULATOR NRC Scenario 1 REV. 0 No. of Pages: 24 PREPARER DATE 'lito), sVALIDATED Grapes, Lavallee, M. O'Brien DATE 12/19/12 GEN SUPERVISOR OPS TRAINING  
: 1. Provide repeat back of initiating cue         Proper communications used                    SatiUnsat (GAP-OPS-Ol)
\) " DATE s: .!-z-!n OPERATIONS MANAGER N/A Exam Security DATE CONFIGURATION CONTROL N/A Exam Security DATE SCENARIO  
Evaluator acknowledge repeat back providing correction ifnecessary RECORD START TIME _ _ __
: 2. Obtain a copy of the reference procedure     Nl-SOP-2L2, Attachment 4 obtained              SatiUnsat and review/utilize the correct section of the procedure.
: 3. Verity locked closed the following valves (TB 261 '):
* 29-07, FIRE WATER TO FEED                 29-07 verified closed by ensuring handwheel    SatiUnsat WATER AFTER SPOOL PIECE (FS              in fully CW position and locking device
: 62)                                       installed
* 100-33, FIRE WATER FEED                   100-33 verified closed by ensuring handwheel  SatiUnsat WATER SPOOL PIECE INLET (FS              in fully CW position and locking device
: 63)                                       installed Cue: Valves 29-07 and 100-33 are LOCKED closed.
Note: The lock on these valves would require a VA-I key.
NRC 2013 JPM P-3                                                                                 May 2013
 
Performance Steps                                 Standard                                  Grade
: 4. Remove drain line from 29-07, Feed         Locates spool piece and tools                PasslFail System blank flange, Remove blank flanges from Feedwater AND Fire System lines, and Install spoolpiece to intertie Feedwater AND Fire System lines Note: Have applicant show where the spool piece and tools are located (next to entrance of the Demin Recycle Valve Room, TB 261' , and in the gang box labeled "For EOP Use Only, Box 1" on the floor beneath the spool piece) and where spool piece is to be installed. The EOP tool box should not be entered.
Cue: The spool piece has been installed   Proper communications used                  SatlUnsat by a Damage Control Team. N I-SOP-21.2     (GAP-OPS-Ol)
Attachment 4 steps 2-4 have been verified complete.
S. Unlock the following valves:
* 100-33, FIRE WATER TO FEED           Lock and restraint removed from 100-33      PasslFail WATER SPOOL PIECE INLET (FS 63)
* 29-07, FIRE WATER TO FEED             Lock and restraint removed from 29-07        PasslFail WATER AFTER SPOOL PIECE (FS 62)
Cue: Valves 100-33 and 29-07 are unlocked.
Note: The lock on these valves would require a V A-I key.
: 6. Supply the fire header by performing one of the following:
* Start Diesel Fire Pump.               Examinee indicates need to start Diesel Fire PasslFaii Pump per initial conditions Cue: Once Candidate addresses the need to start the Diesel Fire Pump, report that Proper communications used                  SatlUnsat another Operator in the screenhouse has   (GAP-OPS-O 1) started the Diesel Fire Pump.
NRC 2013 JPM P-3                                                                           May 2013
 
Performance Steps                                 Standard                                    Grade
: 7. When directed by the CRS/SM, open the   Determines direction has already been given following valves to begin injection into in initiating cue RPV:
* 29-07, FIRE WATER TO FEED           29-07 opened by turning handwheel fully        PasslFail WATER AFTER SPOOL PIECE             CCW
* 100-33, FIRE WATER TO FEED         100-33 opened by turning handwheel fully      PasslFaii WATER SPOOL PIECE INLET             CCW Cue: Valves 29-07 and 100-33 are open and injection to the RPV has commenced
: 8. Verify no leakage at spool piece        Verifies by visual inspection that there is no SatlUnsat connections                              leakage at the spool piece connections Cue: There is no leakage from the spool piece connections
: 9. Notifies CRS/SM that fire water is       Proper communications used                    SatlUnsat being injected to the RPV               (GAP-OPS-Ol)
Role Play: Acknowledge report Terminating Cue: Fire System water entering the RPV through the Feedwater System RECORD STOP TIME _ _ __
NRC 2013 JPM P-3                                                                           May 2013
 
Initial Conditions:
: 1. The Control Room has been evacuated due to a fire.
: 2. NI-SOP-21.2 has been entered.
Initiating Cues:
    "(Operator's name), inject water into the RPV in accordance with NI-SOP-21.2, Attachment 4, using the Diesel Fire Pump."
NRC 2013 JPM P*3                                                               May 2013
 
NMP SIMULATOR SCENARIO NRC Scenario 1                                 REV. 0                           No. of Pages: 24 PREPARER                                         ~5H.                        DATE   'lito),, s VALIDATED                        Grapes, Lavallee, M. O'Brien                 DATE       12/19/12 GEN SUPERVISOR OPS TRAINING             C::l.~ \) o~                                        DATE       s: .!-z-!n OPERATIONS MANAGER N/A Exam Security                   DATE CONFIGURATION CONTROL                                 N/A Exam Security                   DATE SCENARIO  


==SUMMARY==
==SUMMARY==
Length: 60 minutes Initial Power Level: Approximately 95% The scenario begins at approximately 95% power. Containment Spray pump 112 is out of service for maintenance.
 
Steam Packing Exhauster 12 is caution tagged due to high vibrations.
Length: 60 minutes Initial Power Level: Approximately 95%
The crew will remove Recirculation pump 12 from service for maintenance while maintaining Reactor power near the initial value. The CRS will determine the appropriate four-loop operating limitations per Tech Specs. Then, Feedwater Booster pump 11 will trip. The standby Feedwater Booster pump will fail to auto-start.
The scenario begins at approximately 95% power. Containment Spray pump 112 is out of service for maintenance. Steam Packing Exhauster 12 is caution tagged due to high vibrations.
The crew will manually start the standby Feedwater Booster pump to restore normal system pressures.
The crew will remove Recirculation pump 12 from service for maintenance while maintaining Reactor power near the initial value. The CRS will determine the appropriate four-loop operating limitations per Tech Specs.
The CRS will determine the Tech Spec impact for loss of a redundant HPCI component.
Then, Feedwater Booster pump 11 will trip. The standby Feedwater Booster pump will fail to auto-start. The crew will manually start the standby Feedwater Booster pump to restore normal system pressures. The CRS will determine the Tech Spec impact for loss of a redundant HPCI component.
Next, Powerboard 11 will de-energize due to an electrical fault. This will cause loss of multiple major loads, including a second Recirculation pump, a Service Water pump, and a Circulating Water pump. The crew will respond per N 1-S0P-30.1.
Next, Powerboard 11 will de-energize due to an electrical fault. This will cause loss of multiple major loads, including a second Recirculation pump, a Service Water pump, and a Circulating Water pump. The crew will respond per N 1-S0P-30.1. This will include lowering Reactor power to restore the plant within single Circulating Water pump operating limitations. The CRS will determine the Tech Spec impact of this power loss.
This will include lowering Reactor power to restore the plant within single Circulating Water pump operating limitations.
Next, a steam leak will develop inside Primary Containment. The crew will scram the Reactor and execute N1-EOP-2, RPV Control, and N1-EOP-4, Primary Containment Control. After the scram, Feedwater pump 13 will dis-engage early and Feedwater will fail to automatically shift to the HPCI flow-control mode on low Reactor water level. At lower Reactor pressure, Core Spray Isolation Valves will also fail to automatically open. The crew will be able to restore and maintain Reactor water level by manually injecting with preferred and alternate systems
The CRS will determine the Tech Spec impact of this power loss. Next, a steam leak will develop inside Primary Containment.
 
The crew will scram the Reactor and execute N1-EOP-2, RPV Control, and N1-EOP-4, Primary Containment Control. After the scram, Feedwater pump 13 will dis-engage early and Feedwater will fail to automatically shift to the HPCI flow-control mode on low Reactor water level. At lower Reactor pressure, Core Spray Isolation Valves will also fail to automatically open. The crew will be able to restore and maintain Reactor water level by manually injecting with preferred and alternate systems (Critical Task). Multiple primary containment isolation valves will fail to close on either manual or automatic containment isolation.
(Critical Task). Multiple primary containment isolation valves will fail to close on either manual or automatic containment isolation. The crew will be able to manually close these valves. Two Torus-to-Drywell vacuum breakers will fail open, resulting in some steam escaping from the Drywell directly into the Torus airspace. When the crew initiates Containment Spray, Containment Spray pump 111 will trip. These failures will further degrade Primary Containment pressure control. The Pressure Suppression Pressure (PSP) will be exceeded. The crew will blowdown the Reactor per N1-EOP-8 (Critical Task).
The crew will be able to manually close these valves. Two Torus-to-Drywell vacuum breakers will fail open, resulting in some steam escaping from the Drywell directly into the Torus airspace.
Major Procedures: N1-0P-1, N1-S0P-16.1, N1-S0P-30.1, N1-S0P-1.3, N1-S0P-1.1, N1-S0P 1, N1-EOP-1, N1-EOP-2, N1-EOP-4, N1-S0P-40.2, and N1-EOP-8 Dynamic Mitigation Strategy Code: PC4, RPV Blowdown due to PSP EAL Classification: Alert EAL 3.1.1 - High Drywell Pressure Termination Criteria: RPV water level controlled in assigned band, RPV Blowdown in progress, Primary Containment pressure maintained per N1-EOP-4
When the crew initiates Containment Spray, Containment Spray pump 111 will trip. These failures will further degrade Primary Containment pressure control. The Pressure Suppression Pressure (PSP) will be exceeded.
 
The crew will blowdown the Reactor per N1-EOP-8 (Critical Task). Major N1-0P-1, N1-S0P-16.1, N1-S0P-30.1, N1-S0P-1.3, N1-S0P-1.1, 1, N1-EOP-1, N1-EOP-2, N1-EOP-4, N1-S0P-40.2, and N1-EOP-8 Dynamic Mitigation Strategy Code: PC4, RPV Blowdown due to PSP EAL Classification:
I. SIMULATOR SET UP A. IC Number:     IC-151 B. Presets/Function Key Assignments
Alert EAL 3.1.1 -High Drywell Pressure Termination RPV water level controlled in assigned band, RPV Blowdown in progress, Primary Containment pressure maintained per N1-EOP-4 I. SIMULATOR SET UP A. IC Number: IC-151 B. Presets/Function Key Assignments  
: 1. Malfunctions:
: 1. Malfunctions:  
: a. CT01 B, CT Pump 112 Trip                                     PRESET
: a. CT01 B, CT Pump 112 Trip PRESET b. FW02A, FEEDWATER BOOSTER PUMP TRIP 11 TRG 1 c. ED04, PB 11 Electrical Fault TRG2 d. EC01, Steam Supply Line Break in PC, FV=11 % TRG3 e. FW06, SHAFT DRIVEN FEEDWATER PUMP CLUTCH FAILS -DISENGAGES, Delay=20 seconds TRG23 f. PC10A, BV 68-01 Fails Open, Delay=2:00 TRG23 g. PC10C, BV 68-03 Fails Open, Delay=2:00 TRG23 h. FW28A, HPCI MODE FAILURE TO INITIATE 11 PRESET i. FW28B, HPCI MODE FAILURE TO INITIATE 12 PRESET j. CS07, CS Injection Valves Failure to Auto Open PRESET k. CT01A, CT Pump 111 Trip PRESET 2. Remotes: a. None 3. Overrides:  
: b. FW02A, FEEDWATER BOOSTER PUMP TRIP 11                       TRG 1
: a. 7S43D14116, POS_3 4H17/51-02A C FRM B, FV=off (FWBP 13 auto-start failure) PRESET b. 11 S33D15423, SET 1010 RPS CH.11 BYPASS SW, FV=on (Partial primary containment isolation failure) PRESET c. 11S34D15424, SET 1010 RPS CH.12 BYPASS SW, FV=on (Partial primary containment isolation failure) PRESET 4. Annunciators:  
: c. ED04, PB 11 Electrical Fault                               TRG2
: a. None 5. Triggers:  
: d. EC01, Steam Supply Line Break in PC, FV=11 %                 TRG3
: a. TRG 23 -Initiates when the mode switch is taken to SHUTDOWN i. Event Action: zdrpstdn==1 ii. Command: imf ec01 (O 0) 30 4:00 11 b. TRG 24 -Initiates when Containment Spray flow is initiated  
: e. FW06, SHAFT DRIVEN FEEDWATER PUMP CLUTCH FAILS
: i. Event Action: ctfdw> 1 00 ii. Command: imf ec01 (0 0) 45 1 :00 30 Equipment Out of Service Containment Spray pump 112 in PTL with yellow tag Containment Spray suction valve 112 closed with yellow tag Steam Packing Exhauster 12 green-flagged with yellow tag Support Documentation RMI for Recirculation pump stop Miscellaneous Note the failure of Core Spray to automatically inject is required to make the manual establishment of preferred and alternate injection sources a critical task when HPCI fails to automatically initiate. Ensure Drywell cooling fan 11 is secured with control switch in neutral. Ensure Service Water pump 11 is running and Service Water pump 12 is secured. Protect the following equipment:
            - DISENGAGES, Delay=20 seconds                               TRG23
EDG 103, PB 103, PB 12 Update Divisional Status Board II. SHIFT TURNOVER INFORMATION OFF GOING SHIFT: [] N DATE: Today 'D PART I: To be performed by the oncoming Operator before assuming the shift. Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE) PART II: To be reviewed by the oncoming Operator before assuming the shift. Shift Manager Log (SM, CRS, STA)
: f. PC10A, BV 68-01 Fails Open, Delay=2:00                     TRG23
* Shift Turnover Checklist (ALL) RO Log (RO)
: g. PC10C, BV 68-03 Fails Open, Delay=2:00                       TRG23
* LCO Status (SM, CRS, STA) Lit Control Room Annunciators
: h. FW28A, HPCI MODE FAILURE TO INITIATE 11                     PRESET
* Computer Alarm Summary (RO) (SM, CRS, STA, RO, CRE) Evolutions/General Information/Equipment Status: Reactor power is approximately 95%. Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO per TS 3.3.7.b). Steam Packing Exhauster 12 is caution tagged due to high vibrations.
: i. FW28B, HPCI MODE FAILURE TO INITIATE 12                     PRESET
PART III: Remarks/Planned Evolutions:
: j. CS07, CS Injection Valves Failure to Auto Open             PRESET
Remove Recirculation pump 12 from service per N1-0P-1 Section H.1.0. Maintain Reactor power near the initial value as Recirculation pump 12 is secured. Recirculation pump 12 will be out of service for greater than 24 hours. PART IV: To be reviewed/accomplished shortly after assuming the shift: Review new Clearances (SM)
: k. CT01A, CT Pump 111 Trip                                     PRESET
* Test Control Annunciators (CRE) Shift Crew Composition (SM/CRS) TITLE NAME NAME ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver:
: 2. Remotes:
Recire Pump Shutdown Step: 1 INITIAL CONDITIONS/STEP DESCRIPTION I RE presence required in the Control Room? Yes_ No If YES above, RE presence not required for steps Initial conditions to be verified prior to initiation of step: Parameter H Range Actual Parameter Expected Range Actual crp 1740-1780 MWth Description of Step: Secure Recirculation pump 12 per N1-0P-1 Section H.1.0. Maintain Reactor power near the initial value as pump is Critical parameters to be monitored DURING Critical parameters not used must be deleted OR marked Critical Parameter Limit Owner Frequency 35-67.5 Recirc Flow RO Continuous Stop evolution and consult RE.Mlbm/hr I RMI evaluated against approved power profile:
: a. None
* N/A D. I I Other Comments:
: 3. Overrides:
I Step Prepared by: Alex <!J.i&d Step Reviewed by: RE/STA Date RE/STAISRO Approval to perform Step ...c!bhn &nJn I Step Completed Shift Manager Date SRO Critical Tasks: Given a LOCA in the Drywell and a failure of HPCI to initiate, inject with preferred and alternate injection systems to restore and maintain RPV water level above -84 inches, in accordance with N1-EOP-2.
: a. 7S43D14116, POS_3 4H17/51-02A C FRM B, FV=off (FWBP 13 auto-start failure)                               PRESET
Safety Significance:
: b. 11 S33D15423, SET 1010 RPS CH.11 BYPASS SW, FV=on (Partial primary containment isolation failure)             PRESET
Maintaining Reactor water level above -84 inches ensures adequate core cooling through the preferred method of core submergence.
: c. 11S34D15424, SET 1010 RPS CH.12 BYPASS SW, FV=on (Partial primary containment isolation failure)             PRESET
This protects the integrity of the fuel cladding.
: 4. Annunciators:
Cueing: Multiple Reactor water level indicators and annunciators will provide indications of lowering Reactor water level. N1-EOP-2 provides multiple procedure steps directing injection with preferred and alternate injection systems. Measurable Performance Indicators:
: a. None
Manipulation of pumps and/or valves in the preferred or alternate injection system(s) will provide observable actions for the evaluation team. Performance Feedback:
: 5. Triggers:
Multiple Reactor water level indicators and annunciators will provide performance feedback regarding the success of injection with preferred and alternate injection systems. Given a LOCA in the Drywell and degraded Containment Spray capability, execute N1-EOP-8, RPV Slowdown, when it is determined Torus pressure cannot be maintained below the Pressure Suppression Pressure limit, in accordance with EOP-4. Safety Significance:
: a. TRG 23 - Initiates when the mode switch is taken to SHUTDOWN
A Slowdown is required to limit further release of energy into the Primary Containment and to ensure that the RPV is depressurized while pressure suppression capability is still available.
: i. Event Action: zdrpstdn==1 ii. Command: imf ec01 (O 0) 30 4:00 11
This protects the integrity of the Primary Containment.
: b. TRG 24 - Initiates when Containment Spray flow is initiated
Cueing: Multiple Primary Containment pressure indicators and annunciators will provide indications.
: i. Event Action: ctfdw> 100 ii. Command: imf ec01 (0 0) 45 1:00 30
N1-EOP-4 provides direction to monitor the Pressure Suppression Pressure limit and blowdown if required.
 
Measurable Performance Indicators:
C. Equipment Out of Service
The crew will manually open valves to initiate Emergency Condensers.
: 1. Containment Spray pump 112 in PTL with yellow tag
The crew will manually open ERVs. Performance Feedback:
: 2. Containment Spray suction valve 112 closed with yellow tag
Emergency Condenser and ERV instrumentation will provide indication that these systems are functioning properly once placed in service. Multiple Reactor pressure indicators and annunciators will provide performance feedback regarding the success of the blowdown.
: 3. Steam Packing Exhauster 12 green-flagged with yellow tag D. Support Documentation
INSTRUCTOR ACTIONSI PLANT RESPONSE Take the simulator out of freeze before the crew enters for the pre-shift walkdown and briefing.
: 1. RMI for Recirculation pump stop E. Miscellaneous
Allow no more than 5 minutes for panel walkdown.
: 1. Note the failure of Core Spray to automatically inject is required to make the manual establishment of preferred and alternate injection sources a critical task when HPCI fails to automatically initiate.
Event 1 -Secure Recirculation Pump 12 While Maintaining Reactor Power OPERATOR ACTIONS CREW Conducts pre-brief, walks down the panels, assumes the shift SRO Directs securing Recirculation pump 12 per N1-0P-1 Section H.1.0 Provides oversight for evolution Determines Technical Specification 3.1.7.e allows Reactor power up to 100% with idled Recirculation loop Determines Core Operating Limits Report (COLR) requires APLHGR penalty BOP Reviews N1-0P-1 Section H.1.0 Determines Recirculation pump 12 is NOT in local lock Places RRECIRC PUMP 12 SPEED CONTROL in BAL AND nulls out Deviation Meter (top meter) Places RRECIRC PUMP 12 SPEED CONTROL AUTO/BAllMAN switch to MAN Verifies open REACTOR R PUMP 12 BYPASS VALVE INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 1 continued BOP continued IF desired by the Shift Manager to maintain the plant close to present power level, THEN perform next two steps alternately using up to 1.0 x 10 6 Ibm/hr increments UNTIL Reactor Recirc Pump 12 flow is 6 to 8 x 10 6 Ibm/hr: Reduces Recirculation pump 12 flow up to 1 x 10 6 Ibm/hr Coordinates with ATC to maintain initial power level ATe Monitors plant parameters Raises Total Recirc flow using the Master Recirc Controller to initial power level as required based on BOP actions Monitors APRMs, core flow, CTP, and Feedwater response BOP Closes REACTOR R PUMP 12 DISCHARGE VALVE WHEN Discharge Valve is closed, places REACTOR RP MOTOR 12 MG SET switch to STOP Holds in OPEN position for 2 to 3 seconds, REACTOR R PUMP 12 DISCHARGE VALVE INSTRUCTOR ACTIONSI PLANT RESPONSE Event 1 continued OPERATOR ACTIONS BOP continued IF MG set is to be out of service for greater than 24 hours, THEN verifies Electrical Maintenance notified to lift brushes off the Generator AN D Exciter slip rings Refers to N1-0P-1 Section H.2.0 for 4 loop operations INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 2 -Feedwater Booster Pump 11 Trips, CREW Standby Pump Fails to Auto-Start When directed by lead examiner, insert malfunction:
: 2. Ensure Drywell cooling fan 11 is secured with control switch in neutral.
FW02A, FEEDWATER BOOSTER PUMP TRIP 11 TRG 1 The following override prevents Feedwater Booster Pump 12 from Auto Starting on low header discharge pressure:
: 3. Ensure Service Water pump 11 is running and Service Water pump 12 is secured.
: 4. Protect the following equipment: EDG 103, PB 103, PB 12
: 5. Update Divisional Status Board
 
II.                           SHIFT TURNOVER INFORMATION OFF GOING SHIFT: [] N         'D                            DATE: Today PART I:         To be performed by the oncoming Operator before assuming the shift.
* Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE)
PART II:       To be reviewed by the oncoming Operator before assuming the shift.
* Shift Manager Log (SM, CRS, STA)
* Shift Turnover Checklist (ALL)
* RO Log (RO)
* LCO Status (SM, CRS, STA)
* Lit Control Room Annunciators
* Computer Alarm Summary (RO)
(SM, CRS, STA, RO, CRE)
Evolutions/General Information/Equipment Status:
* Reactor power is approximately 95%.
* Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO per TS 3.3.7.b).
* Steam Packing Exhauster 12 is caution tagged due to high vibrations.
PART III:       Remarks/Planned Evolutions:
Remove Recirculation pump 12 from service per N1-0P-1 Section H.1.0. Maintain Reactor power near the initial value as Recirculation pump 12 is secured. Recirculation pump 12 will be out of service for greater than 24 hours.
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                     TITLE                    NAME SRO ATCRO BOPRO
 
ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver: Recire Pump Shutdown                                                         Step: 1 I                                    INITIAL CONDITIONS/STEP DESCRIPTION I
RE presence required in the Control Room? Yes_ No ./
If YES above, RE presence not required for steps _ .
Parameter crp H
Initial conditions to be verified prior to initiation of step:
Range 1740-1780 MWth Actual       Parameter         Expected Range       Actual Description of Step:
Secure Recirculation pump 12 per N1-0P-1 Section H.1.0. Maintain Reactor power near the initial value as the pump is secured.
Critical parameters to be monitored DURING Step:
Critical parameters not used must be deleted OR marked N/A Critical Parameter         Limit         Owner           Frequency Contingency 35-67.5 Recirc Flow                             RO         Continuous Stop evolution and consult RE.
Mlbm/hr IRMI evaluated against approved power profile:
* N/A D.                                               I IOther Comments:
I Step Prepared by:         Alex <!J.i&d             I~          Step Reviewed by: d({dt:~            I~~
RE/STA                 Date                           RE/STAISRO           Date Approval to perform Step . .c!bhn &nJn I rcM~ Step Completed                                       I Shift Manager Date                                     SRO             Date
 
Critical Tasks:
CT-1.0      Given a LOCA in the Drywell and a failure of HPCI to initiate, inject with preferred and alternate injection systems to restore and maintain RPV water level above -84 inches, in accordance with N1-EOP-2.
Safety Significance: Maintaining Reactor water level above -84 inches ensures adequate core cooling through the preferred method of core submergence. This protects the integrity of the fuel cladding.
Cueing: Multiple Reactor water level indicators and annunciators will provide indications of lowering Reactor water level. N1-EOP-2 provides multiple procedure steps directing injection with preferred and alternate injection systems.
Measurable Performance Indicators: Manipulation of pumps and/or valves in the preferred or alternate injection system(s) will provide observable actions for the evaluation team.
Performance Feedback: Multiple Reactor water level indicators and annunciators will provide performance feedback regarding the success of injection with preferred and alternate injection systems.
CT-2.0      Given a LOCA in the Drywell and degraded Containment Spray capability, execute N1-EOP-8, RPV Slowdown, when it is determined Torus pressure cannot be maintained below the Pressure Suppression Pressure limit, in accordance with N1 EOP-4.
Safety Significance: A Slowdown is required to limit further release of energy into the Primary Containment and to ensure that the RPV is depressurized while pressure suppression capability is still available. This protects the integrity of the Primary Containment.
Cueing: Multiple Primary Containment pressure indicators and annunciators will provide indications. N1-EOP-4 provides direction to monitor the Pressure Suppression Pressure limit and blowdown if required.
Measurable Performance Indicators: The crew will manually open valves to initiate Emergency Condensers. The crew will manually open ERVs.
Performance Feedback: Emergency Condenser and ERV instrumentation will provide indication that these systems are functioning properly once placed in service. Multiple Reactor pressure indicators and annunciators will provide performance feedback regarding the success of the blowdown.
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                   OPERATOR ACTIONS Take the simulator out of freeze before the crew CREW enters for the pre-shift walkdown and briefing.
* Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Secure Recirculation Pump 12 While Maintaining Reactor Power SRO
* Directs securing Recirculation pump 12 per N1-0P-1 Section H.1.0
* Provides oversight for evolution
* Determines Technical Specification 3.1.7.e allows Reactor power up to 100% with idled Recirculation loop
* Determines Core Operating Limits Report (COLR) requires APLHGR penalty BOP
* Reviews N1-0P-1 Section H.1.0
* Determines Recirculation pump 12 is NOT in local lock
* Places RRECIRC PUMP 12 SPEED CONTROL in BAL AND nulls out Deviation Meter (top meter)
* Places RRECIRC PUMP 12 SPEED CONTROL AUTO/BAllMAN switch to MAN
* Verifies open REACTOR R PUMP 12 BYPASS VALVE
 
INSTRUCTOR ACTIONSI PLANT RESPONSE     OPERATOR ACTIONS Event 1 continued   BOP continued
* IF desired by the Shift Manager to maintain the plant close to present power level, THEN perform next two steps alternately using up to 1.0 x 106 Ibm/hr increments UNTIL Reactor Recirc Pump 12 flow is 6 to 8 x 106 Ibm/hr:
* Reduces Recirculation pump 12 flow up to 1 x 106 Ibm/hr
* Coordinates with ATC to maintain initial power level ATe
* Monitors plant parameters
* Raises Total Recirc flow using the Master Recirc Controller to initial power level as required based on BOP actions
* Monitors APRMs, core flow, CTP, and Feedwater response BOP
* Closes REACTOR R PUMP 12 DISCHARGE VALVE
* WHEN Discharge Valve is closed, places REACTOR RP MOTOR 12 MG SET switch to STOP
* Holds in OPEN position for 2 to 3 seconds, REACTOR R PUMP 12 DISCHARGE VALVE
 
INSTRUCTOR ACTIONSI PLANT RESPONSE     OPERATOR ACTIONS Event 1 continued   BOP continued
* IF MG set is to be out of service for greater than 24 hours, THEN verifies Electrical Maintenance notified to lift brushes off the Generator AN D Exciter slip rings
* Refers to N1-0P-1 Section H.2.0 for 4 loop operations
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                   OPERATOR ACTIONS Event 2 - Feedwater Booster Pump 11 Trips,       CREW Standby Pump Fails to Auto-Start
* Acknowledge/report annunciator H3 When directed by lead examiner, insert             1-6 REACTOR FW BOOSTER P11 malfunction:                                       TRIP
* Diagnose trip of Feedwater Booster FW02A, FEEDWATER BOOSTER PUMP TRIP 11              Pump 11 TRG 1 The following override prevents Feedwater Booster Pump 12 from Auto Starting on low header discharge pressure:
OVR-7S43D14116 POS_3 4H17/51-02A C FRM B, FV=off PRESET RPV water level lowers Feedwater Booster Pump header pressure lowers Expected Annunciators:
OVR-7S43D14116 POS_3 4H17/51-02A C FRM B, FV=off PRESET RPV water level lowers Feedwater Booster Pump header pressure lowers Expected Annunciators:
H3-1-6, REACTOR FWBOOSTER P11 TRIP H3-3-7, REACTOR FWPUMP 13 SUCTION Acknowledge/report annunciator 1-6 REACTOR FW BOOSTER P11 TRIP Diagnose trip of Feedwater Booster Pump 11 SRO Acknowledges report If BOP does not manually start FWBP 12, directs starting FWBP 12 Enters Tech Spec 3.1.B.b Determines redundant component inoperable in HPCI train 11, thus 15 day LCO applies Initiates surveillance requirement 4.1.B.c for redundant component operability verification Notifies WECIWWM Notifies Ops Management INSTRUCTOR ACTIONSI PLANT RESPONSE Event 2 continued Role Play: When dispatched as Operator to investigate, wait 2 minutes, then report: FWBP 11 breaker tripped on overcurrent No abnormal indications at FWBP 12 breaker No abnormal indications at FWBP 11 or 12. Role Play: When dispatched as Operator to swap HWC, wait 5 minutes and report that HWC injection has been transferred from FWBP 11 to FWBP 12. OPERATOR ACTIONS ATe Monitors plant parameters May perform Emergency Power Reduction per N 1-S0P-1.1 as required to maintain RPV water level BOP Report alarm and respond per H3-1-6 Confirms alarm on computer (E049 RX FW BOOST PMP 11 TRIP) Recognizes/diagnoses failure of the standby pump to automatically start Manually starts FWBP 12 Notifies crew of failure of FWBP 12 to auto start Dispatches operators to shift Hydrogen Water Chemistry injection from FWBP 11 to FWBP 12 INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 -Powerboard 11 Electrical Fault CREW When directed by lead examiner, insert malfunction:
H3-1-6, REACTOR FWBOOSTER P11 TRIP H3-3-7, REACTOR FWPUMP 13 SUCTION SRO
ED04, PB 11 Electrical Fault TRG2 Reactor power lowers due to RRP trips Reactor water level rises due to RRP trips Expected Annunciators:
* Acknowledges report
A4-1-1, PB 11 R113 TRIP A 4-4-2, POWER BD 16 LOW BUS VOLTAGE L 1-3-4, REACT BLDG/ATM DIFF PRESS Also the following equipment trips: Reactor Recirculation Pump 11 Drywell Fans 14, 15, 16 Condensate Pump 11 Circulating Water Pump 11 Service Water Pump 11 RBCLC Pump 11 TBCLC Pump 11 lAC 11 Reactor Building Exhaust Fan 11 Diagnose/report loss of PB 11 Recognize/report loss of: Reactor Recirculation Pump 11 Drywell Fans 14, 15, 16 Condensate Pump 11 Circulating Water Pump 11 Service Water Pump 11 RBClC Pump 11 TBClC Pump 11 lAC 11 Reactor Building Exhaust Fan 11 Recognize/report drop in Reactor power Recognize/report lowering condenser vacuum Recognize/report loss of Reactor Building D/P SRO Acknowledges reports from crew Directs entry into N 1-S0P-30.1 Directs Emergency Power Reduction per N 1-S0P-1.1 to stabilize condenser vacuum, as necessary Provides oversight for reactivity manipulation Directs entry into N1-S0P-1.3, Recirculation Pump Trip INSTRUCTOR ACTIONS! PLANT RESPONSE Event 3 continued Note: On the loss of Powerboard 11, Recirc pump 11 trips. The APRMs are inoperable due to reverse flow through the tripped Recirc loop. The APRMs will be declared operable once the discharge valve is closed. OPERATOR ACTIONS SRO continued Directs RO to re-energize Powerboards 16A and 13A-15A May enter N1-EOP-5, Secondary Containment Control, on loss of Reactor Building DIP Directs restoration of Reactor Building DIP with either RBVS or RBEVS May direct entry into N1-S0P-6.1 for loss of Spent Fuel Pool Cooling, as time permits Reviews Technical Specifications Acknowledges that the APRMs are inoperable while the RRP discharge valves are still open Determines Technical Specification 3.1.7.e limits Reactor power to 90% in 3 loop operation Determines Core Operating Limits Report (COLR) requires APLHGR and MCPR penalties Determines Technical Specification 3.1.8.b is entered again for loss of power to Feedwater pump 11 and Condensate pump 11 INSTRUCTOR ACTIONSI PLANT RESPONSE Event 3 continued Role If dispatched to investigate Powerboard 11, wait minutes then report that the normal supply (R113) tripped on If dispatched to investigate Powerboard 16A, wait minutes then report that there are no evident at Powerboard  
* If BOP does not manually start FWBP 12, directs starting FWBP 12
: 16. Report that maintenance has also looked at the and concurs with re-energizing Role If dispatched to lineup Steam Packing 12, wait 4 minutes, then insert MS09, SPE 12 SUCTION VlV, Then report task If asked to also close suction valve to Packing Exhauster, wait 2 minutes, then MS08, SPE 11 SUCTION VLV, Then report task OPERATOR ACTIONS ATC Acknowledges direction from SRO Confirms plant is stable by verifying:
* Enters Tech Spec 3.1.B.b
No thermal hydraulic Instability 3 Recirc pumps running Not operating in the Restricted Zone Executes N 1-S0P-1.1, Emergency Power Reduction, to lower recirc flow and/or insert CRAM rods to stabilize condenser vacuum, as required Determines plant operating point on the 3-loop power to flow curves BOP Executes N1-S0P-30.1, loss of Power Board 11 Starts Service Water pump 12 Coordinates with ATC to monitor APRMs and lPRMs Verifies TBClC pump 12 running Verifies lAC 12 and/or 13 running Verifies RBClC pump 12 running Verifies Steam Packing Exhauster 12 running Answers "Are A4-4-6, A4-4-7, A4-1-3 OR A5-2-8 in alarm" YES Determines Power Board 11 is faulted and cannot be reenergized INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued Role Play: As operator when directed to energize Powerboards 13A-15A, acknowledge order. If asked about status during remainder of scenario, report that you are being briefed by the WECo Role Play: As operator when directed to restore Offgas vacuum pump, acknowledge order. If called for a status on actions, report that you are being briefed by the WECo Role Play: As operator when directed to investigate Spent Fuel Pool Cooling, wait 3 minutes and then report that SFPC pump 11 has tripped. Restores power to Powerboard 16A as follows: Opens R1041 Closes R 1042 Verifies Power Board 16B amps <962 Dispatches operator to re-energize Power Boards 13A, 14A, and 15A Notifies SRO that APRMs are inoperable Closes Recirc pump 11 discharge valve Holds open for 2-3 seconds Recirc pump 11 discharge valve Records time when Recirc pump 11 discharge valve is cracked open Executes N1-S0P-1.3, Recirc Pump Trip, as time permits Dispatches operator to restore Offgas Vacuum Pump Enters N1-S0P-6.1 for loss of Spent Fuel Pool Cooling, as time permits Dispatches operator to investigate loss of Spent Fuel Pool Cooling, as time permits INSTRUCTOR ACTIONSI PLANT RESPONSE Event 3 continued OPERATOR ACTIONS BOP continued Respond to either annunciator (or as directed by CRS) and restore RB D/P: L 1-1-5, RB VENT EXH FAN 11-12 TRIP-VIB Verifies closed Reactor Building Exhaust Fan 11 outlet damper Starts Reactor Building Exhaust Fan 12 L 1-3-4, REACT BLDG/ATM DIFF PRESS Starts RBEVS per OP-1 0 Possible actions in OP-10 Section H.1.0 to start RBEVS Verifies open 202-36, EM VENTILATION FROM REACTOR BLDG BV Verifies closed the following valves: 202-47, EM VENTILATION TIE BV 202-74, EM VENTILATION LOOP 11 COOL! NG BV 202-75, EM VENTILATION LOOP 12 COOL! NG BV Places 202-37(38), EM VENTILATION LOOP 11(12) INLET BV control switch to OPEN INSTRUCTOR ACTIONS! PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued Role Play: As RP, acknowledge report RBEVS is in service and RBVS is Verifies open 202-37(38), EM VENTILATION LOOP 11(12) INLET BV Starts 202-53(33), EVS FAN 11 (12) Verifies open 202-34(35), EM VENT EXHAUST FAN 11 (12) OUTLET BV Confirms proper operation of 50(51), EM VENT EXHAUST FAN 11(12) INLET FCV, by observing indicating lights and flow indication Notifies Rad Protection that the Reactor Building Emergency Ventilation system is in service INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4,5,6, 7 & 8 -Steam Leak Inside CREW Primary Containment, Vacuum Breaker Fails Open. Failure of HPCI to Auto-Initiate.
* Determines redundant component inoperable in HPCI train 11, thus 15 day LCO applies
Partial Primary Containment Isolation Failure. and Trip of Containment Spray Pump 111 When directed by the lead examiner, insert malfunction:
* Initiates surveillance requirement 4.1.B.c for redundant component operability verification
EC01, Steam Supply Line Break in PC, FV=11 TRG3 Drywell humidity, pressure and temperature rise Drywellieakage rises Expected annunciators:
* Notifies WECIWWM
H2-1-1, Drywell Floor Drain Level High H2-4-7, Drywell Water Leak Detection Sys K2-4-3, Drywell Pressure High-Low F1-1-5(4-1-4), RPS Ch 11(12) Drywell Press High Verify the following malfunctions are preset: FW28A, HPCI Mode Failure to Initiate 11 FW28B, HPCI Mode Failure to Initiate 12 CT01 A, CT Pump 111 Trip CS07, CS Injection Valves Failure to Auto Open Feedwater pump 12 running but not injecting RPV water level slowly lowering Containment Spray pump 111 red light off, green light on and amps go to zero Core Spray IVs do NOT open at 365 psig Expected annunciator:
* Notifies Ops Management
K1-1-7, Containment Spray Pump 111 Trip Fail to Run Diagnose/report degrading containment parameters Acknowledge/report annunciators Diagnose failure of HPCI to automatically initiate Diagnose partial failure of primary containment isolation Diagnose the trip of Containment Spray pump 111 INSTRUCTOR ACTIONS! PLANT RESPONSE OPERATOR ACTIONS Events 4, 5, 6, 7 & 8 continued SRO Verify the following malfunctions automatically insert when the mode switch is taken to SHUTDOWN:
 
FW06, SHAFT DRIVEN FEEDWATER PUMP CLUTCH FAILS -DISENGAGES, Delay=20 seconds EC01, Steam Supply Line Break in PC, IV=11, RT=4:00, FV=30 PC10A, BV 68*01 Fails Open, Delay=2:00 PC10C, BV 68-03 Fails Open, Delay=2:00 TRG23 Containment conditions further degrade Feedwater pump 13 disengages Reactor water level remains low Two Torus-to-Drywell vacuum breakers indicate open Expected annunciator:
INSTRUCTOR ACTIONSI PLANT RESPONSE                                   OPERATOR ACTIONS Event 2 continued                                 ATe
K1-4-6, Torus-OW Vac Relief Check Valve Open Verify the following overrides are PRESET to cause partial primary containment isolation failure: 11S33D15423, SET 1010 RPS CH.11 BYPASS SW, FV=on 11 S34DI5424 SET 1010 RPS CH.12 BYPASS SW, FV=on Verify the following malfunction inserts when Containment Spray flow is initiated the EC01, Steam Supply Line Break in PC, Acknowledges reports Directs manual scram Acknowledges scram report Enters N1-EOP-2 on low RPV water level Directs N1-S0P-1 actions Directs RPV water level controlled 95" with Condensate/FW and CRD When notified of the failure of HPCI to initiate, directs manual control of Feedwater (preferred and alternate injection systems) CT*1 Directs RPV pressure controlled 1000 psig with Turbine Bypass Valves or Emergency Condensers May direct closure of MSIVs to limit cooldown rate Enters N1-EOP-4 due to high drywell pressure and temperature Direct lockout of Containment Spray pumps Re-enters N1-EOP-2 due to high drywell pressure Directs execution of N1-S0P-40.2 for isolation verification Acknowledges partial failure of primary containment isolation Directs/acknowledges manual closure of primary containment isolation valves INSTRUCTOR ACTIONS! PLANT RESPONSE OPERATOR ACTIONS RT=1 :00, FV=45 SRO continued Events 4,5,6, 7 & 8 continued Note: Core Spray injection will only be prevented if not needed for core cooling. If the crew has not yet re-established RPV injection when this step is evaluated, the Core Spray jumpers may not be installed until later. EOP-2 step P-1 provides continuous guidance for this consideration. When Torus pressure exceeds 13 psig or Drywell temperature approaches 300&deg;F:
* Monitors plant parameters
* Answers "Selow the Containment Spray Initiation Limit?" -Yes Verifies all Recirc pumps tripped Directs trip of all Drywell cooling fans Directs operation of Containment Spray per N1-EOP-1 attachment 17 Evaluates/monitors position on Pressure Suppression Pressure curve Acknowledges report of Containment Spray pump 111 trip May direct rapid depressurization with ECs in anticipation of RPV Slowdown Determines Torus pressure cannot be maintained within Pressure Suppression Pressure limit Enters N1-EOP-8, RPV Slowdown CT-2 Answers "Are all control rods inserted to at least 04?" YES Answers "Drywell pressure?" At or above 3.5 psig May direct prevention of Core Spray injection per N1-EOP-1 attachment 4 Directs EC initiation Answers "Torus water level?" Above 8.0 ft Directs open 4 ERVs INSTRUCTOR ACTIONSI PLANT RESPONSE Events 4.5,6, 7 & 8 continued The failed primary containment isolation valves controlled by three control OPERATOR ACTIONS ATC Monitors plant parameters When directed, places Mode Switch in Shutdown Provides scram report Performs N1-S0P-1, Reactor Scram, scram verification actions Places I RMs on range 9 Inserts IRM and SRM detectors Down-ranges IRMs as necessary to monitor power decrease If recirc pumps have not yet tripped, reduces recirc flow to 43 Mlbm/hr Maintains RPV pressure below 1080 psig and in assigned band Executes N1-S0P-40.2 Recognizes/reports failure of multiple primary containment isolation valves to automatically close Manually closes the following valves: 201.7-01 & 02, 201.2-110
* May perform Emergency Power Reduction per N 1-S0P-1.1 as required to maintain RPV water level BOP Role Play: When dispatched as Operator to
& 111, 201.2-109
* Report alarm and respond per H3-1-6 investigate, wait 2 minutes, then report:
& 112 (11 H202) 201.2-23 & 24, 201.2-29 & 30 (12 H202) 201.7-08 & 09,201.7-10
* Confirms alarm on computer (E049
& 11 (Drywell CAM) Reports primary containment isolation valves have been manually closed INSTRUCTOR ACTIONSI PLANT RESPONSE Events 4. 5. 6, 7 & 8 continued Note: Feedwater level control actions will vary depending on when the operator diagnoses the failure of HPCI to automatically control injection through Feedwater flow control valves 11 and 12. OPERATOR ACTIONS BOP Monitors/reports degrading Containment parameters Performs RPV water level control actions of N1-S0P-1, Reactor Scram: Restores RPV level to 53-95" by controlling injection and rejecting through RWCU Determines
* FWBP 11 breaker tripped on overcurrent         RX FW BOOST PMP 11 TRIP)
#13 FWP was running Determines RPV water level is recovering Terminates 13 FWP injection as follows: Closes 13 FWP VALVE CONTROL Disengages 13 FWP Closes 29-10, Feedwater Pump 13 Blocking Valve Verifies RPV water level above 53" Verifies 11112 FWP controllers in MANUAL and set to zero output Places FWP BYPASS Valve 11 or 12 in AUTO, sets to 65-70 inches If RPV level reaches 85 inches and rising, then: Verifies off all FW Pumps Secures CRD Pumps not required Diagnoses failure of HPCI to automatically initiate Notifies SRO/Crew of HPCI failure Manually controls RPV injection to restore and maintain level CT-1 INSTRUCTOR ACTIONS! PLANT RESPONSE OPERATOR ACTIONS Events 4, 5, 6, 7 & 8 continued ATC/BOP Note: Core Spray pumps may be placed in PTL if needed before EOP-1 attachment 4 jumpers can be installed due to scenario progression and resource limitations.
* No abnormal indications at FWBP 12 breaker
If Core Spray pumps are placed in PTL, at least one Core Spray pump should be restarted after jumper installation for App J water seal. Core Spray may also be used as an alternate injection source. Terminating Cues: RPV water level controlled in assigned band RPV Slowdown in progress Primary Containment pressure maintained per N1-EOP-4 Places Containment Spray pumps in PTL Closes MSIVs, as directed Reports when Torus pressure exceeds 13 psig or Drywell temperature approaches 300&deg;F Verifies Recirc pumps tripped Trips Drywell cooling fans Initiates Containment Spray per EOP-1 attachment 17 Diagnoses/reports Containment Spray pump 111 trip Verifies started Containment Spray pumps 121 and 122 If 80-118 is open for Opens 80-35 Closes 80-118 Verifies open 80-40 and 80-45 Prevents Core Spray injection installing N1-EOP-1 attachment 4 jumpers (17, 18, 19,24,25,26), if directed Initiates both ECs Opens 4 ERVs CT-2 NMP SIMULATOR NRC Scenario 2 REV. 0 No. of Pages: 22 Recirc Flow Unit Failure, Emergency MVAR Support. Inadvertent EC Initiation.
* Recognizes/diagnoses failure of the
Intake Grassing.
* No abnormal indications at FWBP 11 or 12.       standby pump to automatically start
FWLC Fails As-Is, Un-Isolable EC Steam Leak in Secondary Containment.
* Manually starts FWBP 12 Role Play: When dispatched as Operator to swap
Mode Switch Fails. BOJMFails PREPARER DATE ij'ld,/t3 VALIDATED Grapes, Lavallee.
* Notifies crew of failure of FWBP 12 to HWC, wait 5 minutes and report that HWC injection   auto start has been transferred from FWBP 11 to FWBP 12.
M. O'Brien DATE 12/19/12 GEN OPS TRAINING t:s = DATE So *"'"
* Dispatches operators to shift Hydrogen Water Chemistry injection from FWBP 11 to FWBP 12
* MANAGER N/A -Exam Security DATE ____
 
CONTROL N/A -Exam Security DATE ____SCENARIO
INSTRUCTOR ACTIONSI PLANT RESPONSE                                  OPERATOR ACTIONS Event 3 - Powerboard 11 Electrical Fault        CREW When directed by lead examiner, insert
* Diagnose/report loss of PB 11 malfunction:
* Recognize/report loss of:
* Reactor Recirculation Pump 11 ED04, PB 11 Electrical Fault
* Drywell Fans 14, 15, 16 TRG2
* Condensate Pump 11
* Circulating Water Pump 11 Reactor power lowers due to RRP trips
* Service Water Pump 11 Reactor water level rises due to RRP trips
* RBClC Pump 11 Expected Annunciators:
* TBClC Pump 11 A4-1-1, PB 11 R113 TRIP
* lAC 11 A4-4-2, POWER BD 16 LOW BUS VOLTAGE
* Reactor Building Exhaust Fan 11 L 1-3-4, REACT BLDG/ATM DIFF PRESS
* Recognize/report drop in Reactor Also the following equipment trips:
power Reactor Recirculation Pump 11
* Recognize/report lowering condenser Drywell Fans 14, 15, 16 vacuum Condensate Pump 11
* Recognize/report loss of Reactor Circulating Water Pump 11 Building D/P Service Water Pump 11 RBCLC Pump 11 TBCLC Pump 11 lAC 11 Reactor Building Exhaust Fan 11 SRO
* Acknowledges reports from crew
* Directs entry into N 1-S0P-30.1
* Directs Emergency Power Reduction per N 1-S0P-1.1 to stabilize condenser vacuum, as necessary
* Provides oversight for reactivity manipulation
* Directs entry into N1-S0P-1.3, Recirculation Pump Trip
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                    OPERATOR ACTIONS Event 3 continued                                SRO continued
* Directs RO to re-energize Powerboards 16A and 13A-15A
* May enter N1-EOP-5, Secondary Containment Control, on loss of Reactor Building DIP
* Directs restoration of Reactor Building DIP with either RBVS or RBEVS
* May direct entry into N1-S0P-6.1 for loss of Spent Fuel Pool Cooling, as time permits
* Reviews Technical Specifications
* Acknowledges that the APRMs are inoperable while the RRP discharge Note: On the loss of Powerboard 11, Recirc pump     valves are still open 11 trips. The APRMs are inoperable due to
* Determines Technical Specification reverse flow through the tripped Recirc loop. The   3.1.7.e limits Reactor power to 90% in APRMs will be declared operable once the           3 loop operation discharge valve is closed.
* Determines Core Operating Limits Report (COLR) requires APLHGR and MCPR penalties
* Determines Technical Specification 3.1.8.b is entered again for loss of power to Feedwater pump 11 and Condensate pump 11
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                      OPERATOR ACTIONS Event 3 continued                                  ATC
* Acknowledges direction from SRO
* Confirms plant is stable by verifying:
No thermal hydraulic Instability 3 Recirc pumps running Not operating in the Restricted Zone
* Executes N1-S0P-1.1, Emergency Power Reduction, to lower recirc flow and/or insert CRAM rods to stabilize condenser vacuum, as required
* Determines plant operating point on the 3-loop power to flow curves Role Play:                                          BOP If dispatched to investigate Powerboard 11, wait 2
* Executes N1-S0P-30.1, loss of minutes then report that the normal supply breaker    Power Board 11 (R113) tripped on overcurrent.
* Starts Service Water pump 12 If dispatched to investigate Powerboard 16A, wait 2
* Coordinates with ATC to monitor minutes then report that there are no problems        APRMs and lPRMs evident at Powerboard 16. Report that electrical
* Verifies TBClC pump 12 running maintenance has also looked at the Powerboard
* Verifies lAC 12 and/or 13 running and concurs with re-energizing it.
* Verifies RBClC pump 12 running
* Verifies Steam Packing Exhauster 12 Role Play:                                            running If dispatched to lineup Steam Packing Exhauster
* Answers "Are A4-4-6, A4-4-7, A4-1-3 12, wait 4 minutes, then insert remote:
OR A5-2-8 in alarm" YES MS09, SPE 12 SUCTION VlV, FV=open
* Determines Power Board 11 is faulted Then report task completion.
and cannot be reenergized If asked to also close suction valve to Steam Packing Exhauster, wait 2 minutes, then insert remote:
MS08, SPE 11 SUCTION VLV, FV=close Then report task completion.
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                      OPERATOR ACTIONS Event 3 continued                                  BOP continued
* Restores power to Powerboard 16A as follows:
* Opens R1041
* Closes R 1042
* Verifies Power Board 16B amps
                                                          <962 Role Play: As operator when directed to energize
* Dispatches operator to re-energize Powerboards 13A-15A, acknowledge order. If            Power Boards 13A, 14A, and 15A asked about status during remainder of scenario,
* Notifies SRO that APRMs are report that you are being briefed by the WECo        inoperable
* Closes Recirc pump 11 discharge valve
* Holds open for 2-3 seconds Recirc pump 11 discharge valve
* Records time when Recirc pump 11 discharge valve is cracked open
* Executes N1-S0P-1.3, Recirc Pump Trip, as time permits Role Play: As operator when directed to restore
* Dispatches operator to restore Offgas Offgas vacuum pump, acknowledge order. If called Vacuum Pump for a status on actions, report that you are being briefed by the WECo
* Enters N1-S0P-6.1 for loss of Spent Fuel Pool Cooling, as time permits Role Play: As operator when directed to
* Dispatches operator to investigate loss of Spent Fuel Pool Cooling, as time investigate Spent Fuel Pool Cooling, wait 3 minutes permits and then report that SFPC pump 11 has tripped.
 
INSTRUCTOR ACTIONSI PLANT RESPONSE      OPERATOR ACTIONS Event 3 continued  BOP continued
* Respond to either annunciator (or as directed by CRS) and restore RB D/P:
* L 1-1-5, RB VENT EXH FAN 11-12 TRIP-VIB o  Verifies closed Reactor Building Exhaust Fan 11 outlet damper o  Starts Reactor Building Exhaust Fan 12
* L 1-3-4, REACT BLDG/ATM DIFF PRESS o  Starts RBEVS per OP-1 0 Possible actions in OP-10 Section H.1.0 to start RBEVS
* Verifies open 202-36, EM VENTILATION FROM REACTOR BLDG BV
* Verifies closed the following valves:
* 202-47, EM VENTILATION TIE BV
* 202-74, EM VENTILATION LOOP 11 COOL! NG BV
* 202-75, EM VENTILATION LOOP 12 COOL! NG BV
* Places 202-37(38), EM VENTILATION LOOP 11(12) INLET BV control switch to OPEN
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                            OPERATOR ACTIONS Event 3 continued                        BOP continued
* Verifies open 202-37(38), EM VENTILATION LOOP 11(12) INLET BV
* Starts 202-53(33), EVS FAN 11 (12)
* Verifies open 202-34(35), EM VENT EXHAUST FAN 11 (12) OUTLET BV
* Confirms proper operation of 202 50(51), EM VENT EXHAUST FAN 11(12) INLET FCV, by observing indicating lights and flow indication Role Play: As RP, acknowledge report that
* Notifies Rad Protection that the RBEVS is in service and RBVS is secured. Reactor Building Emergency Ventilation system is in service
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                  OPERATOR ACTIONS Events 4,5,6, 7 & 8 - Steam Leak Inside          CREW Primary Containment, Vacuum Breaker Fails
* Diagnose/report degrading Open. Failure of HPCI to Auto-Initiate. Partial    containment parameters Primary Containment Isolation Failure. and Trip
* Acknowledge/report annunciators of Containment Spray Pump 111
* Diagnose failure of HPCI to When directed by the lead examiner, insert        automatically initiate malfunction:
* Diagnose partial failure of primary containment isolation EC01, Steam Supply Line Break in PC, FV=11
* Diagnose the trip of Containment TRG3  Spray pump 111 Drywell humidity, pressure and temperature rise Drywellieakage rises Expected annunciators:
H2-1-1, Drywell Floor Drain Level High H2-4-7, Drywell Water Leak Detection Sys K2-4-3, Drywell Pressure High-Low F1-1-5(4-1-4), RPS Ch 11(12) Drywell Press High Verify the following malfunctions are preset:
FW28A, HPCI Mode Failure to Initiate 11 FW28B, HPCI Mode Failure to Initiate 12 CT01 A, CT Pump 111 Trip CS07, CS Injection Valves Failure to Auto Open Feedwater pump 12 running but not injecting RPV water level slowly lowering Containment Spray pump 111 red light off, green light on and amps go to zero Core Spray IVs do NOT open at 365 psig Expected annunciator:
K1-1-7, Containment Spray Pump 111 Trip Fail to Run
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                       OPERATOR ACTIONS Events 4, 5, 6, 7 & 8 continued                     SRO
* Acknowledges reports Verify the following malfunctions automatically
* Directs manual scram insert when the mode switch is taken to
* Acknowledges scram report SHUTDOWN:
* Enters N1-EOP-2 on low RPV water FW06, SHAFT DRIVEN FEEDWATER PUMP                     level CLUTCH FAILS - DISENGAGES, Delay=20
* Directs N1-S0P-1 actions seconds
* Directs RPV water level controlled 53 EC01, Steam Supply Line Break in PC, IV=11,           95" with Condensate/FW and CRD RT=4:00, FV=30
* When notified of the failure of HPCI PC10A, BV 68*01 Fails Open, Delay=2:00                 to initiate, directs manual control of PC10C, BV 68-03 Fails Open, Delay=2:00                 Feedwater (preferred and alternate TRG23     injection systems)
Containment conditions further degrade CT*1 Feedwater pump 13 disengages
* Directs RPV pressure controlled 800 Reactor water level remains low 1000 psig with Turbine Bypass Valves Two Torus-to-Drywell vacuum breakers indicate or Emergency Condensers open
* May direct closure of MSIVs to limit Expected annunciator:
cooldown rate K1-4-6, Torus-OW Vac Relief Check Valve Open
* Enters N1-EOP-4 due to high drywell pressure and temperature o  Direct lockout of Containment Verify the following overrides are PRESET to Spray pumps cause partial primary containment isolation failure:
* Re-enters N1-EOP-2 due to high 11S33D15423, SET 1010 RPS drywell pressure CH.11 BYPASS
* Directs execution of N1-S0P-40.2 for SW, FV=on isolation verification 11 S34DI5424 SET 1010 RPS
* Acknowledges partial failure of primary CH.12 BYPASS containment isolation SW, FV=on
* Directs/acknowledges manual closure of primary containment isolation valves Verify the following malfunction automatically inserts when Containment Spray flow is initiated to the Drywell:
EC01, Steam Supply Line Break in PC, IV=30,
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                      OPERATOR ACTIONS RT=1 :00, FV=45                                      SRO continued
* When Torus pressure exceeds 13 Events 4,5,6, 7 & 8 continued                            psig or Drywell temperature approaches 300&deg;F:
* Answers "Selow the Containment Spray Initiation Limit?" - Yes
* Verifies all Recirc pumps tripped
* Directs trip of all Drywell cooling fans
* Directs operation of Containment Spray per N1-EOP-1 attachment 17
* Evaluates/monitors position on Pressure Suppression Pressure curve
* Acknowledges report of Containment Spray pump 111 trip
* May direct rapid depressurization with ECs in anticipation of RPV Slowdown
* Determines Torus pressure cannot be maintained within Pressure Suppression Pressure limit
* Enters N1-EOP-8, RPV Slowdown CT-2
* Answers "Are all control rods inserted to at least 04?" YES
* Answers "Drywell pressure?" At or above 3.5 psig
* May direct prevention of Core Spray injection per N1-EOP-1 Note: Core Spray injection will only be prevented if attachment 4 not needed for core cooling. If the crew has not yet
* Directs EC initiation re-established RPV injection when this step is
* Answers "Torus water level?"
evaluated, the Core Spray jumpers may not be Above 8.0 ft installed until later. EOP-2 step P-1 provides
* Directs open 4 ERVs continuous guidance for this consideration.
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                      OPERATOR ACTIONS Events 4.5,6, 7 & 8 continued                      ATC
* Monitors plant parameters
* When directed, places Mode Switch in Shutdown
* Provides scram report
* Performs N1-S0P-1, Reactor Scram, scram verification actions
* Places I RMs on range 9
* Inserts IRM and SRM detectors
* Down-ranges IRMs as necessary to monitor power decrease
* If recirc pumps have not yet tripped, reduces recirc flow to 25 43 Mlbm/hr
* Maintains RPV pressure below 1080 psig and in assigned band
* Executes N1-S0P-40.2
* Recognizes/reports failure of multiple primary containment isolation valves to automatically close
* Manually closes the following valves:
Note:
* 201.7-01 & 02, 201.2-110 &
The failed primary containment isolation valves are 111, 201.2-109 & 112 controlled by three control switches.
(11 H202)
* 201.2-23 & 24, 201.2-29 & 30 (12 H202)
* 201.7-08 & 09,201.7-10 & 11 (Drywell CAM)
* Reports primary containment isolation valves have been manually closed
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                    OPERATOR ACTIONS Events 4. 5. 6, 7 & 8 continued                    BOP
* Monitors/reports degrading Containment parameters
* Performs RPV water level control actions of N1-S0P-1, Reactor Scram:
* Restores RPV level to 53-95" by controlling injection and rejecting through RWCU
* Determines #13 FWP was running
* Determines RPV water level is Note: Feedwater level control actions will vary          recovering depending on when the operator diagnoses the
* Terminates 13 FWP injection as failure of HPCI to automatically control injection      follows:
through Feedwater flow control valves 11 and 12.
* Closes 13 FWP VALVE CONTROL
* Disengages 13 FWP
* Closes 29-10, Feedwater Pump 13 Blocking Valve
* Verifies RPV water level above 53"
* Verifies 11112 FWP controllers in MANUAL and set to zero output
* Places FWP BYPASS Valve 11 or 12 in AUTO, sets to 65-70 inches
* If RPV level reaches 85 inches and rising, then:
* Verifies off all FW Pumps
* Secures CRD Pumps not required
* Diagnoses failure of HPCI to automatically initiate
* Notifies SRO/Crew of HPCI failure
* Manually controls RPV injection to restore and maintain level CT-1
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                        OPERATOR ACTIONS Events 4, 5, 6, 7 & 8 continued                      ATC/BOP
* Places Containment Spray pumps in PTL
* Closes MSIVs, as directed
* Reports when Torus pressure exceeds 13 psig or Drywell temperature approaches 300&deg;F
* Verifies Recirc pumps tripped
* Trips Drywell cooling fans
* Initiates Containment Spray per N1 EOP-1 attachment 17
* Diagnoses/reports Containment Spray pump 111 trip
* Verifies started Containment Spray pumps 121 and 122
* If 80-118 is open for Torus Cooling:
* Opens 80-35
* Closes 80-118 Note: Core Spray pumps may be placed in PTL if
* Verifies open 80-40 and 80-45 needed before EOP-1 attachment 4 jumpers can
* Prevents Core Spray injection be installed due to scenario progression and installing N1-EOP-1 attachment 4 resource limitations. If Core Spray pumps are jumpers (17, 18, 19,24,25,26), if placed in PTL, at least one Core Spray pump directed should be restarted after jumper installation for App
* Initiates both ECs J water seal. Core Spray may also be used as an
* Opens 4 ERVs alternate injection source.
CT-2 Terminating Cues:
* RPV water level controlled in assigned band
* RPV Slowdown in progress
* Primary Containment pressure maintained per N1-EOP-4
 
NMP SIMULATOR SCENARIO NRC Scenario 2                                  REV. 0                             No. of Pages: 22 Recirc Flow Unit Failure, Emergency MVAR Support. Inadvertent EC Initiation. Intake Grassing.
FWLC Fails As-Is, Un-Isolable EC Steam Leak in Secondary Containment. Mode Switch Fails.
                        ~                    BOJMFails PREPARER                 ~~:n,,1/w1                                          DATE    ij'ld,/t3 VALIDATED                           Grapes, Lavallee. M. O'Brien            DATE      12/19/12 GEN SUPERVISOR OPS TRAINING              ~~      t:s = ,~                                  DATE        So J.rj" OPERATIONS                                        "'"
MANAGER                                N/A - Exam Security                  DATE _ _ _ __
CONFIGURATION CONTROL                                N/A - Exam Security                 DATE _ _ _ __
SCENARIO


==SUMMARY==
==SUMMARY==
Length: 50 minutes Initial Power Level: Approximately 55% The scenario begins at approximately 55% power. Containment Spray pump 112 is out of service for maintenance.
 
Steam Packing Exhauster 12 is caution tagged due to high vibrations.
Length: 50 minutes Initial Power Level: Approximately 55%
The crew will begin by raising Reactor power with recirculation flow. Recirculation flow unit 11 fails upscale. The crew will respond per the alarm response procedure and the CRS will determine the Tech Spec impact. Power Control will call the Control Room and request increased reactive load support to ensure grid voltage is maintained due to loss of generation capacity.
The scenario begins at approximately 55% power. Containment Spray pump 112 is out of service for maintenance. Steam Packing Exhauster 12 is caution tagged due to high vibrations.
The crew will utilize N1-0P-32 and raise MVARs to the grid using the Main Generator automatic voltage regulator.
The crew will begin by raising Reactor power with recirculation flow.
Next, Emergency Condenser 12 will inadvertently initiate.
Recirculation flow unit 11 fails upscale. The crew will respond per the alarm response procedure and the CRS will determine the Tech Spec impact.
The crew will secure Emergency Condenser  
Power Control will call the Control Room and request increased reactive load support to ensure grid voltage is maintained due to loss of generation capacity. The crew will utilize N1-0P-32 and raise MVARs to the grid using the Main Generator automatic voltage regulator.
: 12. This action will make Emergency Condenser 12 inoperable, but available.
Next, Emergency Condenser 12 will inadvertently initiate. The crew will secure Emergency Condenser 12. This action will make Emergency Condenser 12 inoperable, but available. The CRS will determine the Tech Spec impact.
The CRS will determine the Tech Spec impact. An in-flux of grass will lead to clogging of the intake structure.
An in-flux of grass will lead to clogging of the intake structure. The crew will enter N1-S0P 18.1, trip one Circulating Water pump, and lower Reactor power. During the power reduction, Feedwater Level Control will fail as-is in automatic. The crew will enter N1-S0P-15.1 and take manual control of Feedwater to restore Reactor water level. Once the Circulating Water pump is secured (Critical Task), intake conditions will improve.
The crew will enter 18.1, trip one Circulating Water pump, and lower Reactor power. During the power reduction, Feedwater Level Control will fail as-is in automatic.
 
The crew will enter N1-S0P-15.1 and take manual control of Feedwater to restore Reactor water level. Once the Circulating Water pump is secured (Critical Task), intake conditions will improve.
Next, a steam leak will develop from Emergency Condenser 11. The crew will attempt to isolate the leak, however the Emergency Condenser will fail to isolate both automatically and manually.
Next, a steam leak will develop from Emergency Condenser  
The crew will scram the Reactor (Critical Task) and execute N1-EOP-2, RPV Control, and N1 EOP-5, Secondary Containment Control. The Mode Switch will fail to scram the Reactor, however either RPS push buttons or manual ARI actuation will result in successful control rod insertion. The Bypass Opening Jack Motor (BOJM) will fail to open Turbine Bypass Valves if the crew anticipates blowdown, however the MPR is available to open Turbine Bypass Valves.
: 11. The crew will attempt to isolate the leak, however the Emergency Condenser will fail to isolate both automatically and manually.
Two General Areas of the Reactor Building will exceed the maximum safe temperatures. The crew will blowdown the Reactor per N1-EOP-S (Critical Task).
The crew will scram the Reactor (Critical Task) and execute N1-EOP-2, RPV Control, and EOP-5, Secondary Containment Control. The Mode Switch will fail to scram the Reactor, however either RPS push buttons or manual ARI actuation will result in successful control rod insertion.
Major Procedures: N1-0P-19, N1-0P-32, N1-S0P-1S.1, N1-S0P-1.1, N1-S0P-16.1, N1-S0P 1, N1-EOP-2, N1-EOP-5, and N1-EOP-S Dynamic Mitigation Strategy Code: SC1, Primary System Leak in Secondary Containment, Blowdown Required EAL Classification: Site Area Emergency per EALs 3.4.1 (Emergency Condenser Isolation Failure and Release Outside Primary Containment) and/or 4.1.1 (Primary System Discharging Outside Primary Containment, >135&deg;F in Two General Areas)
The Bypass Opening Jack Motor (BOJM) will fail to open Turbine Bypass Valves if the crew anticipates blowdown, however the MPR is available to open Turbine Bypass Valves. Two General Areas of the Reactor Building will exceed the maximum safe temperatures.
Termination Criteria: RPV water level controlled in assigned band, RPV Blowdown in progress
The crew will blowdown the Reactor per N1-EOP-S (Critical Task). Major N1-0P-19, N1-0P-32, N1-S0P-1S.1, N1-S0P-1.1, N1-S0P-16.1, 1, N1-EOP-2, N1-EOP-5, and N1-EOP-S Dynamic Mitigation Strategy SC1, Primary System Leak in Secondary Containment, Blowdown Required EAL Site Area Emergency per EALs 3.4.1 (Emergency Condenser Isolation Failure and Release Outside Primary Containment) and/or 4.1.1 (Primary System Discharging Outside Primary Containment, >135&deg;F in Two General Areas) Termination Criteria:
 
RPV water level controlled in assigned band, RPV Blowdown in progress SIMULATOR SET UP IC Number: IC-152 Presets/Function Key Assignments Malfunctions: CT01 B, CT Pump 112 Trip PRESET NM36A, RECIRC FLOW CONVERTER CHANNEL 11 FAILURE-UPSCALE TRG 1 EC03B, EC RETURN VALVE FAILS OPEN(IV 39-06) TRG2 CW17, Intake Traveling Screens Blockage, FV=65%, RT=10:00 TRG3 FW14C, Feedwater Master Controller  
I. SIMULATOR SET UP A. IC Number:       IC-152 B. Presets/Function Key Assignments
-Fail As Is TRG3 EC02, Steam Supply Line Break in RB, FV=20% TRG4 EC07A, Emergency Condenser 11 Fails to Isolate PRESET EC08A, EC LOOP 11 STM IV FAIL TO CLOSE 111 , FV=50% PRESET EC08B, EC LOOP 11 STM IV FAIL TO CLOSE 112 , FV=50% PRESET Remotes: FW24 , REMOVAL OF HPCI FUSES FU8/FU9, FV=pulled TRG24 Overrides:  
: 1. Malfunctions:
: a. 13S70014674, POS_1 1E67 REAC. SW.-RUN, FV=on (Mode switch fails to scram) PRESET b. 13S70014675, POS_2 1 E67 REAC. SW.-SHUTOOWN, FV=off (Mode switch fails to scram) PRESET c. 1A2S701176, POS_2 TC BOJ CLOSE, FV=off (BO...IM fails to open TBVs) PRESET Annunciators: None Triggers: Trigger 29 -After scram, allows Mode Switch logic to reposition to prevent MSIV closure on low pressure. Event Action: rd:rpscm(1)==1 Command: dor 13S70014674 Trigger 30 -After scram, allows Mode Switch logic to reposition to prevent MSIV closure on low pressure. Event Action: rd:rpscm(1)==1 Command: dor 13S70014674 Equipment Out of Service Containment Spray pump 112 in PTL with yellow tag Containment Spray suction valve 112 closed with yellow tag Steam Packing Exhauster 12 green-flagged with yellow tag Support Documentation RMI for power ascension with Recirculation flow Miscellaneous Ensure Drywell cooling fan 11 is secured with control switch in neutral. Ensure the Main Generator is supplying approximately 100 MVARs to the grid with the voltage regulator in automatic. Markup N1-0P-43B Section F.3.0 to the appropriate steps for 55% power level. Protect the following equipment:
: a. CT01 B, CT Pump 112 Trip                                               PRESET
EDG 103, PB 103 Update Divisional Status Board SHIFT TURNOVER INFORMATION OFF GOING SHIFT: D N DATE: Today PART I: To be performed by the oncoming Operator before assuming the shift. Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE) PART II: To be reviewed by the oncoming Operator before assuming the shift. Shift Manager Log (SM, CRS, STA)
: b. NM36A, RECIRC FLOW CONVERTER CHANNEL 11 FAILURE- UPSCALE                                                     TRG 1
* Shift Turnover Checklist (ALL) RO Log (RO)
: c. EC03B, EC RETURN VALVE FAILS OPEN(IV 39-06)                           TRG2
* LCO Status (SM, CRS, STA) Lit Control Room Annunciators
: d. CW17, Intake Traveling Screens Blockage, FV=65%, RT=10:00             TRG3
* Computer Alarm Summary (RO) (SM, CRS, STA, RO, CRE) Evolutions/General Information/Equipment Status: Reactor power is approximately 50%. Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO perTS 3.3.7.b). Steam Packing Exhauster 12 is caution tagged due to high vibrations. Circulating Water pump 11 was returned to service following waterbox cleaning earlier in the shift. PART III: Remarks/Planned Evolutions: Raise Reactor power with Recirculation flow per the provided RMI and N1-0P-43B.
: e. FW14C, Feedwater Master Controller - Fail As Is                       TRG3
: f. EC02, Steam Supply Line Break in RB, FV=20%                           TRG4
: g. EC07A, Emergency Condenser 11 Fails to Isolate                         PRESET
: h. EC08A, EC LOOP 11 STM IV FAIL TO CLOSE 111 , FV=50%                   PRESET
: i. EC08B, EC LOOP 11 STM IV FAIL TO CLOSE 112 , FV=50%                   PRESET
: 2. Remotes:
: a. FW24 , REMOVAL OF HPCI FUSES FU8/FU9, FV=pulled                       TRG24
: 3. Overrides:
: a. 13S70014674, POS_1 1E67 REAC. SW.-RUN, FV=on (Mode switch fails to scram)                                         PRESET
: b. 13S70014675, POS_2 1E67 REAC. SW.-SHUTOOWN, FV=off (Mode switch fails to scram)                                         PRESET
: c. 1A2S701176, POS_2 TC BOJ CLOSE, FV=off (BO.. IM fails to open TBVs)                                         PRESET
: 4. Annunciators:
: a. None
: 5. Triggers:
: a. Trigger 29 - After scram, allows Mode Switch logic to reposition to prevent MSIV closure on low pressure.
: i. Event Action: rd:rpscm(1)==1 ii. Command: dor 13S70014674
: b. Trigger 30 - After scram, allows Mode Switch logic to reposition to prevent MSIV closure on low pressure.
: i. Event Action: rd:rpscm(1)==1 ii. Command: dor 13S70014674
 
C. Equipment Out of Service
: 1. Containment Spray pump 112 in PTL with yellow tag
: 2. Containment Spray suction valve 112 closed with yellow tag
: 3. Steam Packing Exhauster 12 green-flagged with yellow tag D. Support Documentation
: 1. RMI for power ascension with Recirculation flow E. Miscellaneous
: 1. Ensure Drywell cooling fan 11 is secured with control switch in neutral.
: 2. Ensure the Main Generator is supplying approximately 100 MVARs to the grid with the voltage regulator in automatic.
: 3. Markup N1-0P-43B Section F.3.0 to the appropriate steps for 55% power level.
: 4. Protect the following equipment: EDG 103, PB 103
: 5. Update Divisional Status Board
 
II.                          SHIFT TURNOVER INFORMATION OFF GOING SHIFT: D N         'D                          DATE: Today PART I:         To be performed by the oncoming Operator before assuming the shift.
* Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE)
PART II:       To be reviewed by the oncoming Operator before assuming the shift.
* Shift Manager Log (SM, CRS, STA)
* Shift Turnover Checklist (ALL)
* RO Log (RO)
* LCO Status (SM, CRS, STA)
* Lit Control Room Annunciators
* Computer Alarm Summary (RO)
(SM, CRS, STA, RO, CRE)
Evolutions/General Information/Equipment Status:
* Reactor power is approximately 50%.
* Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO perTS 3.3.7.b).
* Steam Packing Exhauster 12 is caution tagged due to high vibrations.
* Circulating Water pump 11 was returned to service following waterbox cleaning earlier in the shift.
PART III:       Remarks/Planned Evolutions:
: 1. Raise Reactor power with Recirculation flow per the provided RMI and N1-0P-43B.
N1-0P-43B Section F.3.0 is in progress.
N1-0P-43B Section F.3.0 is in progress.
PART IV: To be reviewed/accomplished shortly after assuming the shift: Review new Clearances (SM)
PART IV:       To be reviewed/accomplished shortly after assuming the shift:
* Test Control Annunciators (CRE) Shift Crew Composition (SM/CRS) NAME TITLE NAME ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver:
* Review new Clearances (SM)
Power Ascension from 55% Step: 1 INITIAL CONDITIONS/STEP DESCRIPTION I RE presence required in the Control Room? Yes_ No If YES above, RE presence not required for steps Initial conditions to be verified prior to initiation of step: Parameter Expected Range Actual Parameter Expected Range CTP 900-950 Description of Step: Raise Reactor power to approximately 85% with Recirculation flow per N1-0P-43B.
* Test Control Annunciators (CRE)
Critical parameters to be monitored DURING Critical parameters not used must be deleted OR marked Critical Parameter Limit Owner Frequency 67.5 Recirc Flow RO Continuous Stop evolution and consult RE.Mlbm/hr Lower power to less than 1850 MWth with CTP 1850 MWth RO Continuous Recirculation Rod line 108% RO 15 minutes Stop evolution and consult I RMI evaluated against approved power profile:
* Shift Crew Composition (SM/CRS)
* N/A D. I I Other Comments:
TITLE                  NAME                     TITLE                   NAME SRO ATCRO BOPRO
I Step Prepared by: A!t:z GK.eed I Step Reviewed by: dttck Q;(j)ettll I RE/STA Date RE/STAISRO Approval to perform Step dPhn Attron I 'Codap Step Completed by: Shift Manager Date SRO Critical Tasks: CT-1.0 Given the plant at power with lowering intake water level, remove a Circulating Water pump from service in order to preserve use of the lake as a heat sink, in accordance with N1-S0P-18.1.
 
Safetv Significance:
ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver: Power Ascension from 55%                                                         Step: 1 I                                    INITIAL CONDITIONS/STEP DESCRIPTION I
Circulating Water pumps draw a large volume of water from the cooling water intake. This intake is shared with pumps from safety significant systems such as Emergency Service Water, Containment Spray Raw Water, and Diesel Generator Raw Water. In the event of lowering intake water level with the plant at power, a Circulating Water pump must be removed from service in order to preserve water in the intake for other systems to maintain use of the lake as a heat sink. Cueing: Annunciators will alert the crew to the low intake level. Field reports will provide additional information about lowering intake level. N 1-S0P-18.1 provides direction to remove a Circulating Water pump from service. Measurable Performance Indicators:
RE presence required in the Control Room? Yes_ No ./
Manipulation of a Circulating Water pump control switch will provide the observable action for the evaluation team. Performance Feedback:
If YES above, RE presence not required for steps _ .
Lowering Circulating Water pump amps and indications of rising intake water level will provide performance feedback regarding the success of removing the Circulating Water pump from service. CT-2.0 Given an un-isolable Emergency Condenser leak outside primary containment and one general area temperature above the maximum safe limit, insert a manual reactor scram, in accordance with N1-EOP-5.
Initial conditions to be verified prior to initiation of step:
Safetv Significance:
Parameter           Expected Range                 Actual       Parameter           Expected Range         Actual CTP             900-950 MWth Description of Step:
With an un-isolable primary system discharging outside of Primary Containment resulting in general area temperature above the maximum safe limit, the Reactor must be scrammed.
Raise Reactor power to approximately 85% with Recirculation flow per N1-0P-43B.
This reduces the rate of energy production and thus the heat input, radioactivity release, and break flow into the Secondary Containment.
Critical parameters to be monitored DURING Step:
This also ensures the Reactor is shutdown prior to need for a blowdown.
Critical parameters not used must be deleted OR marked N/A Critical Parameter         Limit         Owner           Frequency   Contingency 67.5 Recirc Flow                             RO         Continuous   Stop evolution and consult RE.
Cueing: Multiple annunciators will provide indications of a primary system discharging into Secondary Containment.
Mlbm/hr Lower power to less than 1850 MWth with CTP           1850 MWth           RO         Continuous Recirculation flow.
Emergency Condenser valve position indicators will provide indication that the system is un-isolable.
Rod line           108%             RO         15 minutes   Stop evolution and consult RE.
Field reports will provide indication that a general area is above the maximum safe temperature limit. N 1-EOP-5 provides direction to scram the Reactor. Measurable Performance Indicators:
IRMI evaluated against approved power profile:
Rotation of the Mode Switch to SHUTDOWN or depressing the manual scram pushbuttons will provide observable actions for the evaluation team.
* N/A D.                                                 I IOther Comments:
Performance Feedback:
I Step Prepared by:         A!t:z GK.eed             I 'Cod~      Step Reviewed by: dttck Q;(j)ettll       I 'Co~
Control rod position and Reactor power indications will provide performance feedback regarding the success of the scram. CT-3.0 Given an un-isolable Emergency Condenser leak outside primary containment and two general area temperatures above the maximum safe limit, execute N1-EOP-8, RPV Blowdown, in accordance with N1-EOP-S.
RE/STA                 Date                             RE/STAISRO             Date Approval to perform Step dPhn Attron I 'Codap Step Completed by:                                     I Shift Manager Date                                       SRO               Date
Safety Significance:
 
An un-isolable primary system discharging outside of Primary Containment resulting in two general area temperatures above the maximum safe limit indicates a wide-spread problem posing a direct and immediate threat to Secondary Containment.
Critical Tasks:
A blowdown minimizes flow through the break, rejects heat to the suppression pool in preference to outside the containment, and places the primary system in the lowest possible energy state. Cueing: Multiple annunciators will provide indications of a primary system discharging into Secondary Containment.
CT-1.0     Given the plant at power with lowering intake water level, remove a Circulating Water pump from service in order to preserve use of the lake as a heat sink, in accordance with N1-S0P-18.1.
Emergency Condenser valve position indicators will provide indication that the system is un-isolable.
Safetv Significance: Circulating Water pumps draw a large volume of water from the cooling water intake. This intake is shared with pumps from safety significant systems such as Emergency Service Water, Containment Spray Raw Water, and Diesel Generator Raw Water. In the event of lowering intake water level with the plant at power, a Circulating Water pump must be removed from service in order to preserve water in the intake for other systems to maintain use of the lake as a heat sink.
Field reports will provide indication that two general areas is above the maximum safe temperature limit. N1-EOP-S provides direction to blowdown the Reactor. Measurable Performance Indicators:
Cueing: Annunciators will alert the crew to the low intake level. Field reports will provide additional information about lowering intake level. N 1-S0P-18.1 provides direction to remove a Circulating Water pump from service.
The crew will manually open ERVs. Performance Feedback:
Measurable Performance Indicators: Manipulation of a Circulating Water pump control switch will provide the observable action for the evaluation team.
ERV instrumentation will provide indication that these valves are functioning properly once placed in service. Multiple Reactor pressure indicators and annunciators will provide performance feedback regarding the success of the blowdown.
Performance Feedback: Lowering Circulating Water pump amps and indications of rising intake water level will provide performance feedback regarding the success of removing the Circulating Water pump from service.
INSTRUCTOR ACTIONSI PLANT RESPONSE Take the simulator out of freeze before the crew enters for the pre-shift walkdown and briefing.
CT-2.0     Given an un-isolable Emergency Condenser leak outside primary containment and one general area temperature above the maximum safe limit, insert a manual reactor scram, in accordance with N1-EOP-5.
Allow no more than 5 minutes for panel walkdown.
Safetv Significance: With an un-isolable primary system discharging outside of Primary Containment resulting in general area temperature above the maximum safe limit, the Reactor must be scrammed. This reduces the rate of energy production and thus the heat input, radioactivity release, and break flow into the Secondary Containment. This also ensures the Reactor is shutdown prior to need for a blowdown.
Event 1 -Power Ascension With Recirculation N1-0P-438 includes the following map PRIOR to exceeding 65% flow, verify greater than 50% Rod Line OR that RIP region will NOT be entered. PRIOR to 100% rodline raise recirc flow to greater than 59% flow (approximately 40 x 106 Ib/hr) to avoid the flow biased control rod block line. Recommend initiating the next event when power is between 55-60% power to achieve desired response in Event OPERATOR ACTIONS CREW Conducts pre-brief, walks down the panels, assumes the shift SRO Directs power ascension with Recirculation flow lAW N1-0P-438 and the Reactivity Maneuver Instruction (RMI) Provides oversight of reactivity maneuver ATC Acknowledges direction from SRO Raises Recirculation flow with master Recirculation flow controller Monitors APRMs Monitors Recirculation flow Monitors Feedwater flow and RPV water level Observes power-to-flow map restrictions BOP Monitors individual RRPs for response Individual MIA-Speed Control stations trending uniformly Individual RRP indications trending normally for speed increase Monitors Feedwater controls for proper response FWP 13 FCV responding to power change RPV water level remains within program band (65" -83")
Cueing: Multiple annunciators will provide indications of a primary system discharging into Secondary Containment. Emergency Condenser valve position indicators will provide indication that the system is un-isolable. Field reports will provide indication that a general area is above the maximum safe temperature limit. N 1-EOP-5 provides direction to scram the Reactor.
INSTRUCTOR ACTIONS/ PLANT RESPONSE OPERATOR ACTIONS Event 2 -Recirculation Flow Unit Fails Upscale CREW When directed by lead examiner, insert malfunction:
Measurable Performance Indicators: Rotation of the Mode Switch to SHUTDOWN or depressing the manual scram pushbuttons will provide observable actions for the evaluation team.
NM36A, RECIRC FLOW CONVERTER CHANNEL 11 FAILURE* UPSCALE TRG 1 Comparator trip occurs resulting in a Rod Block. The "FLOW CaMPARA TOR" lamps on the Rod Block Display (PANEL E) will light. Expected Annunciators:
 
F2-2-6, APRM FLOW UNIT 11 F3-2-1, APRM FLOW UNIT 12 F3-4-4, ROD BLOCK
Performance Feedback: Control rod position and Reactor power indications will provide performance feedback regarding the success of the scram.
* Recognize/report Recirculation now unit 11 failed upscale SRO Acknowledges reports from crew Directs response with ARP F2-2-6 Consults Tech Spec Tables 3.6.2.a and 3.6.2.g Declares APRMs 11-14 inoperable for the upscale scram and rod block functions Determines a half scram must be placed on RPS channel 11 within 1 hour Contacts I&C Department for troubleshooting INSTRUCTOR ACTIONS! PLANT RESPONSE Event 2 continued OPERATOR ACTIONS ATe Verifies proper power to flow ratio on Power Flow Map on E Panel BOP Executes ARP F2-2-6 Confirms alarm by observing the following: Computer Printout APRM Flow Comparator on G Panel LPRM/APRM Trip Auxiliary Panels on G Panel Rod Block Monitor on E Panel INSTRUCTOR ACTIONS/ PLANT RESPONSE Event 3 -Power Control Requests MVAR When directed by lead examiner, call the crew Power Control and make the following "This is Power Control. We are about to some generation capacity on the grid due emergent shutdown of another plant. We Nine Mile Point Unit 1 to supply an 100 MVARs to the grid as soon as possible ensure stable grid Role If informed as Shift Manager, GSO, Manager or CENG Generation acknowledge report and concur with actions raise MVARs as OPERATOR ACTIONS CREW Acknowledge/report Power Control communication SRO Acknowledges report from crew Directs raising Main Generator reactive load by 100 MVARs per N OP-32 section F BOP Executes N 1-0P-32 section F Adjusts VOLTAGE REG ADJUSTMENT switch at E console to raise 100 MVARS Adjusts EXCITER RHEOSTAT switch at E console to establish AND maintain between 10 AND 20 Volts Boost on the VOLTAGE REG AMPLIDYNE meter INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 4 -Emergency Condenser 12 Inadvertent CREW Initiation
CT-3.0 Given an un-isolable Emergency Condenser leak outside primary containment and two general area temperatures above the maximum safe limit, execute N1-EOP-8, RPV Blowdown, in accordance with N1-EOP-S.
* Recognizelreport Emergency When directed by lead examiner, insert Condenser 12 initiation malfunction:
Safety Significance: An un-isolable primary system discharging outside of Primary Containment resulting in two general area temperatures above the maximum safe limit indicates a wide-spread problem posing a direct and immediate threat to Secondary Containment. A blowdown minimizes flow through the break, rejects heat to the suppression pool in preference to outside the containment, and places the primary system in the lowest possible energy state.
* Recognize/report Reactor power and water level rising EC03B, EC RETURN VALVE FAILS OPEN (IV 39-* Recognize/report no valid Emergency  
Cueing: Multiple annunciators will provide indications of a primary system discharging into Secondary Containment. Emergency Condenser valve position indicators will provide indication that the system is un-isolable. Field reports will provide indication that two general areas is above the maximum safe temperature limit. N1-EOP-S provides direction to blowdown the Reactor.
: 06) Condenser initiation signal TRG2 EC 12 Condensate Return Valve (39-06) opens Reactor power rises Reactor water level initially rises Expected Annunciators:
Measurable Performance Indicators: The crew will manually open ERVs.
K1-1-5, EMER COND CONDEN RET ISOL VALVE 12 OPEN SRO Acknowledges reports from crew
Performance Feedback: ERV instrumentation will provide indication that these valves are functioning properly once placed in service. Multiple Reactor pressure indicators and annunciators will provide performance feedback regarding the success of the blowdown.
* Directs response with ARP K1-1-5 Role Play: Directs securing Emergency If dispatched to investigate 39-06, wait 2 minutes Condenser 12 and then report that there is a significant air leak on
 
* Declares Emergency Condenser 12 the air supply line to 39-06. inoperable but available Enters a 7 day LCO per Tech Spec 3.1.3.b BOP The next event should NOT be inserted until
INSTRUCTOR ACTIONSI PLANT RESPONSE                                       OPERATOR ACTIONS Take the simulator out of freeze before the crew     CREW enters for the pre-shift walkdown and briefing.
* Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown.         panels, assumes the shift Event 1 - Power Ascension With Recirculation         SRO
* Directs power ascension with Recirculation flow lAW N1-0P-438 and the Reactivity Maneuver Instruction (RMI)
* Provides oversight of reactivity maneuver Note:                                                ATC N1-0P-438 includes the following power-to-flow
* Acknowledges direction from SRO map restrictions:
* Raises Recirculation flow with master
* PRIOR to exceeding 65% flow, verify greater        Recirculation flow controller than 50% Rod Line OR that RIP region will
* Monitors APRMs NOT be entered.
* Monitors Recirculation flow
* PRIOR to 100% rodline raise recirc flow to
* Monitors Feedwater flow and RPV greater than 59% flow (approximately 40 x 106       water level Ib/hr) to avoid the flow biased control rod block
* Observes power-to-flow map line.                                               restrictions BOP Note:
* Monitors individual RRPs for response Recommend initiating the next event when Reactor
* Individual MIA-Speed Control power is between 55-60% power to achieve the                stations trending uniformly desired response in Event 6.
* Individual RRP indications trending normally for speed increase
* Monitors Feedwater controls for proper response
* FWP 13 FCV responding to power change
* RPV water level remains within program band (65" - 83")
 
INSTRUCTOR ACTIONS/
PLANT RESPONSE                                    OPERATOR ACTIONS Event 2 - Recirculation Flow Unit Fails Upscale    CREW When directed by lead examiner, insert
* Recognize/report Recirculation now malfunction:                                        unit 11 failed upscale NM36A, RECIRC FLOW CONVERTER CHANNEL 11 FAILURE* UPSCALE TRG 1 Comparator trip occurs resulting in a Rod Block.
The "FLOW CaMPARA TOR" lamps on the Rod Block Display (PANEL E) will light.
Expected Annunciators:
F2-2-6, APRM FLOW UNIT 11 F3-2-1, APRM FLOW UNIT 12 F3-4-4, ROD BLOCK SRO
* Acknowledges reports from crew
* Directs response with ARP F2-2-6
* Consults Tech Spec Tables 3.6.2.a and 3.6.2.g
* Declares APRMs 11-14 inoperable for the upscale scram and rod block functions
* Determines a half scram must be placed on RPS channel 11 within 1 hour
* Contacts I&C Department for troubleshooting
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE      OPERATOR ACTIONS Event 2 continued  ATe
* Verifies proper power to flow ratio on Power Flow Map on E Panel BOP
* Executes ARP F2-2-6
* Confirms alarm by observing the following:
o    Computer Printout o    APRM Flow Comparator on G Panel o    LPRM/APRM Trip Auxiliary Panels on G Panel o    Rod Block Monitor on E Panel
 
INSTRUCTOR ACTIONS/
PLANT RESPONSE                                   OPERATOR ACTIONS Event 3 - Power Control Requests Emergency      CREW MVAR Support
* Acknowledge/report Power Control When directed by lead examiner, call the crew as  communication Power Control and make the following report:
"This is Power Control. We are about to lose some generation capacity on the grid due an emergent shutdown of another plant. We need Nine Mile Point Unit 1 to supply an additional 100 MVARs to the grid as soon as possible to ensure stable grid voltage."
SRO Role Play:
* Acknowledges report from crew If informed as Shift Manager, GSO, Operations
* Directs raising Main Generator Manager or CENG Generation Dispatch,              reactive load by 100 MVARs per N 1 acknowledge report and concur with actions to      OP-32 section F raise MVARs as needed.
BOP
* Executes N1-0P-32 section F
* Adjusts VOLTAGE REG ADJUSTMENT switch at E console to raise 100 MVARS
* Adjusts EXCITER RHEOSTAT switch at E console to establish AND maintain between 10 AND 20 Volts Boost on the VOLTAGE REG AMPLIDYNE meter
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                         OPERATOR ACTIONS Event 4 - Emergency Condenser 12 Inadvertent           CREW Initiation
* Recognizelreport Emergency When directed by lead examiner, insert                   Condenser 12 initiation malfunction:
* Recognize/report Reactor power and water level rising EC03B, EC RETURN VALVE FAILS OPEN (IV 39-
* Recognize/report no valid Emergency
: 06)                                                       Condenser initiation signal TRG2 EC 12 Condensate Return Valve (39-06) opens Reactor power rises Reactor water level initially rises Expected Annunciators:
K1-1-5, EMER COND CONDEN RET ISOL VALVE 12 OPEN SRO
* Acknowledges reports from crew
* Directs response with ARP K1-1-5 Role Play:
* Directs securing Emergency If dispatched to investigate 39-06, wait 2 minutes       Condenser 12 and then report that there is a significant air leak on
* Declares Emergency Condenser 12 the air supply line to 39-06.                            inoperable but available
* Enters a 7 day LCO per Tech Spec 3.1.3.b BOP The next event should NOT be inserted until
* Executes ARP K1-1-5 Reactor water level has stabilized from this event.
* Executes ARP K1-1-5 Reactor water level has stabilized from this event.
* Closes: 39-0BR EC STM ISOLATION VALVE 122, and/or 39-10R EC STM ISOLATION VALVE 121 INSTRUCTOR ACTIONS! PLANT RESPONSE OPERATOR ACTIONS Event 5 -Intake Grassing CREW When directed by lead examiner, insert malfunction:
* Closes:
CW17, Intake Traveling Screens Blockage, FV=65%, RT=10:00 TRG3 Traveling screen DIP rises Forebay water level lowers Expected Annunciators:
o  39-0BR EC STM ISOLATION VALVE 122, and/or o  39-10R EC STM ISOLATION VALVE 121
H1-4-3, SCREEN WASH PUMP-SCREEN La VOL T DIFF PRESS H2-1-3, CIRCULATING WATER PUMP INTAKE LEVEL LOW The malfunction for Event 6 is inserted with 5. Event 6 will become evident when the crew initiates a Reactor power reduction.
 
Booth When one Circulating Water pump is modify malfunction CW17 to 40% over 1 Recognize/report annunciator Recognize/report lowering intake level SRO Acknowledges reports Directs entry into N 1-S0P-18. 1 , Service Water Failure / Low Intake Level Directs emergency power reduction per N1-S0P-1.1 as needed Provides oversight for reactivity manipulation Acknowledges improving intake level INSTRUCTOR ACTIONS! PLANT RESPONSE Event 5 Role If requested as Operator in field to investigate, 2 minutes, then A large amount of lake grass is coming in the intake and accumulating on the traveling screens. The traveling screens are operating properly but not keeping up with the influx of grass. Report intake level as indicated by simulator (use screen CW04, Secondary Forebay water level -CWL(4>>. Subsequent reports may be given with no delay. Once one Circulating Water pump is tripped and intake level is improving, report that the traveling screens are catching up and intake level is improving.
INSTRUCTOR ACTIONS!
OPERATOR ACTIONS BOP Executes N1-S0P-18.1, Service Water Failure / Low Intake Level Updates crew on override requirements to trip a Circulating Water pump and perform an emergency power reduction Trips one Circulating Water pump CT-1 Monitors intake level Monitors condenser vacuum, Circulating Water temperatures, and Feedwater response during power reduction Determines/reports intake level improves following Circulating Water pump trip ATC Performs emergency power reduction by lowering Recirculation flow and/or inserting CRAM rods per N 1-S0P-1.1 , as needed for single Circ Water pump operation Observes APRMs, CTP, and Recirculation flow INSTRUCTOR ACTIONS! PLANT RESPONSE OPERATOR ACTIONS Event 6 -Feedwater Level Control Fails As-is In CREW Automatic Verify the following malfunction is inserted along with Event 5: FW14C, FW14C, Feedwater Master Controller Fail As Is TRG3 Reactor water level deviates from set point Feedwater FCV 13 does NOT change position Feedwater flow remains constant Expected Annunciators:
PLANT RESPONSE                                     OPERATOR ACTIONS Event 5 - Intake Grassing                         CREW When directed by lead examiner, insert
F2-3-3, REACT VESSEL LEVEL HIGH-LOW If crew does not respond to the malfunction, Turbine trip / Reactor scram will occur. Continue Event 7 and initiate TRG
* Recognize/report annunciator malfunction:
* Recognize/report Reactor water level deviation from setpoint
* Recognize/report lowering intake level CW17, Intake Traveling Screens Blockage, FV=65%, RT=10:00 TRG3 Traveling screen DIP rises Forebay water level lowers Expected Annunciators:
* Recognize/report Feedwater FCV 13 and/or Feedwater master controller is not responding properly SRO Acknowledges reports Directs entry into N 1-S0P-16.1 , Feedwater System Failures Directs placing FW FCV 13 in manual ATC Monitors RPV water level Monitors plant parameters BOP Enters N 1-S0P-16.1, Feedwater System Failures Answers "Problem with FWLC, FW Pumps OR FW heating?" FWLC Answers "FCV lockup?" NO Answers "FWLC malfunction?" YES Places FW FCV 13 controller in MAN Controls RPV water level in manual INSTRUCTOR ACTIONSI PLANT RESPONSE Events 7, 8, 9, & 10 -Emergency Condenser 11 Steam Leak In Reactor Building, Emergency Condenser 11 Fails To Isolate, Mode Switch Fails to Scram, BOJM Fails to Open TBVs When directed by the lead examiner, insert malfunction:
H1-4-3, SCREEN WASH PUMP-SCREEN TRIP La VOL T DIFF PRESS H2-1-3, CIRCULATING WATER PUMP INTAKE LEVEL LOW Note:
EC02, Steam Supply Line Break in RB, FV=20% TRG 4 Reactor Building D/P lowers Rising temperatures, pressures and radiation levels in the Secondary Containment RBEVS auto-starts RBVS isolates Expected Annunciators:
The malfunction for Event 6 is inserted with Event
L 1-3-4, REACT. BLDG/ATM DIFF PRESS L 1-4-3, REACT BLDG VENT RAD MONITOR OFF NORMAL L 1-3(4)-6, EMER VENT SYS CHANNEL 11(12) RELA Y OPERA TE MFP2 2-1-1-7, REAC BLDG 318 LOCAL PNL NO.7 FIRE K1-4-3, EMER COOLING SYSTEM 11 STEAM LEAK AREA T HI K1-4-5, EMER COOLING SYSTEM 12 STEAM LEAK AREA T HI L 1-3-3, CONTINUOUS AIR RAD MONITOR H1-4-8, AREA RADIATION MONITORS OPERATOR ACTIONS CREW Acknowledge/report annunciators Recognize/report Emergency Condenser 11 steam leak Recognize/report failure of Emergency Condenser 11 to isolate Recognize/report failure of Mode Switch May recognize/report failure of BOJM INSTRUCTOR PLANT RESPONSE OPERATOR Events 8 & 9 Verify the following malfunctions are EC07 A, Emergency Condenser 11 Fails EC08A, EC LOOP 11 STM IV FAIL TO 111 , EC08B, EC LOOP 11 STM IV FAIL TO 112, Emergency Condenser 11 fails to Verify the following overrides are preset to Mode Switch and BOJM 13S70014674, POS_11E67 REAC. 13S70014675, POS_21E67 REAC. SHUTDOWN, 1A2S701176, POS_2 TC BOJ CLOSE, When control rods insert, verify triggers 29 and automatically initiate and delete the 13S70014674, POS_11E67 REAC. 13S70014675, POS_2 1 E67 REAC.
: 5. Event 6 will become evident when the crew initiates a Reactor power reduction.
INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 8 & 9 continued SRO If the Reactor scrammed due to an earlier CT -2 will be Acknowledges reports Enters N 1-EOP-5 on high Reactor Building Vent rad levels, high Reactor Building area temperatures I rad levels, and/or loss of RB DIP Directs manual isolation of Emergency Condenser 11 Directs Reactor Building evacuation Acknowledges manual isolation failure Directs dispatching of an operator and RP tech to obtain general area temperatures and radiation levels in the Reactor Building When Reactor Building Ventilation exhaust radiation exceeds 5 mRlhr, directs verification of RB Vent isolation and RBEVS initiation Determines area temperatures and/or radiation levels are above setpoints in Tables T and R, and transitions to EOP-5 circle 27 Determines a primary system is discharging into the Reactor Building and the discharge cannot be isolated, and transitions to N1-EOP-5 circle 28 When any area temperature or radiation level approaches or reaches 135&deg;F or 8 Rlhr, respectively: Directs manual Reactor scram CT-2 Acknowledges scram report Enters N1-EOP-2, RPV Control, on low RPV water level INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 8 & 9 continued SRO continued Note: Anticipatory blowdown is likely to be directed from N1-EOP-2 once one Reactor Building General Area temperature is above 135&deg;F with a second temperature trending towards 135&deg;F. Note: Emergency Condenser 12 is available even though it was isolated earlier due to inadvertent initiation.
SRO Booth Operator:
The crew may decide not to use Emergency Condenser 12 due to actuation of Annunciator 4-5, EMER COOLING SYSTEM 12 STEAM LEAK AREA T HI. Answers "Are all control rods inserted to at least position 04?" YES Directs entry into N1-S0P-1, Reactor Scram Directs RPV water level control 53-95" using Feedwater/Condensate and CRD Directs RPV pressure maintained
* Acknowledges reports When one Circulating Water pump is tripped,
<1080 psig using TBVs May direct anticipatory blowdown with TBVs and/or Emergency Condenser 12 with cooldown in excess of 100 o F/hr Acknowledge failure of BOJM, if reported May direct opening TBVs using MPR Acknowledges reports of Reactor Building temperatures and radiation levels When report is received that 2 General Areas temperatures are above 135 0 F, enters N1-EOP-8, RPV Blowdown Answers "Are all control rods inserted to at least position 04" YES Answers "Drywell pressure?" <3.5 psig May direct initiation of Emergency Condenser 12 Answers "Torus water level?" >8 ft Directs open 4 ERVs CT-3 INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 8 & 9 continued ATC
* Directs entry into N 1-S0P-18. 1, modify malfunction CW17 to 40% over 1 minute.        Service Water Failure / Low Intake Level
* Directs emergency power reduction per N1-S0P-1.1 as needed
* Provides oversight for reactivity manipulation
* Acknowledges improving intake level
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                         OPERATOR ACTIONS Event 5 continued                                      BOP
* Executes N1-S0P-18.1, Service Role Plays:                                              Water Failure / Low Intake Level If requested as Operator in field to investigate, wait
* Updates crew on override 2 minutes, then report:                                  requirements to trip a Circulating
* A large amount of lake grass is coming in the     Water pump and perform an intake and accumulating on the traveling           emergency power reduction screens.
* Trips one Circulating Water pump
* The traveling screens are operating properly                                           CT-1 but not keeping up with the influx of grass.
* Monitors intake level
* Report intake level as indicated by simulator
* Monitors condenser vacuum, (use screen CW04, Secondary Forebay water           Circulating Water temperatures, and level - CWL(4>>.                                     Feedwater response during power reduction Subsequent reports may be given with no delay.
* Determines/reports intake level improves following Circulating Water Once one Circulating Water pump is tripped and           pump trip intake level is improving, report that the traveling screens are catching up and intake level is improving.
ATC
* Performs emergency power reduction by lowering Recirculation flow and/or inserting CRAM rods per N 1-S0P-1.1 ,
as needed for single Circ Water pump operation
* Observes APRMs, CTP, and Recirculation flow
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                      OPERATOR ACTIONS Event 6 - Feedwater Level Control Fails As-is In    CREW Automatic
* Recognize/report Reactor water level Verify the following malfunction is inserted along    deviation from setpoint with Event 5:
* Recognize/report Feedwater FCV 13 and/or Feedwater master controller is FW14C, FW14C, Feedwater Master Controller              not responding properly Fail As Is TRG3 Reactor water level deviates from setpoint Feedwater FCV 13 does NOT change position Feedwater flow remains constant Expected Annunciators:
F2-3-3, REACT VESSEL LEVEL HIGH-LOW SRO Note:
* Acknowledges reports If crew does not respond to the malfunction, a
* Directs entry into N 1-S0P-16.1 ,
Turbine trip / Reactor scram will occur. Continue to    Feedwater System Failures Event 7 and initiate TRG 5.
* Directs placing FW FCV 13 in manual ATC
* Monitors RPV water level
* Monitors plant parameters BOP
* Enters N 1-S0P-16.1, Feedwater System Failures
* Answers "Problem with FWLC, FW Pumps OR FW heating?" FWLC
* Answers "FCV lockup?" NO
* Answers "FWLC malfunction?" YES
* Places FW FCV 13 controller in MAN
* Controls RPV water level in manual
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                      OPERATOR ACTIONS Events 7, 8, 9, & 10 - Emergency Condenser 11      CREW Steam Leak In Reactor Building, Emergency
* Acknowledge/report annunciators Condenser 11 Fails To Isolate, Mode Switch
* Recognize/report Emergency Fails to Scram, BOJM Fails to Open TBVs              Condenser 11 steam leak When directed by the lead examiner, insert
* Recognize/report failure of Emergency malfunction:                                          Condenser 11 to isolate
* Recognize/report failure of Mode EC02, Steam Supply Line Break in RB, FV=20%          Switch TRG 4
* May recognize/report failure of BOJM Reactor Building D/P lowers Rising temperatures, pressures and radiation levels in the Secondary Containment RBEVS auto-starts RBVS isolates Expected Annunciators:
L 1-3-4, REACT. BLDG/ATM DIFF PRESS L 1-4-3, REACT BLDG VENT RAD MONITOR OFF NORMAL L 1-3(4)-6, EMER VENT SYS CHANNEL 11(12)
RELA Y OPERA TE MFP2 2-1-1-7, REAC BLDG 318 LOCAL PNL NO.7 FIRE K1-4-3, EMER COOLING SYSTEM 11 STEAM LEAK AREA T HI K1-4-5, EMER COOLING SYSTEM 12 STEAM LEAK AREA T HI L 1-3-3, CONTINUOUS AIR RAD MONITOR H1-4-8, AREA RADIATION MONITORS
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                      OPERATOR ACTIONS Events 8 & 9 continued Verify the following malfunctions are preset:
EC07A, Emergency Condenser 11 Fails to Isolate EC08A, EC LOOP 11 STM IV FAIL TO CLOSE 111 , FV=50%
EC08B, EC LOOP 11 STM IV FAIL TO CLOSE 112, FV=50%
Emergency Condenser 11 fails to iso/ate.
Verify the following overrides are preset to cause Mode Switch and BOJM failures:
13S70014674, POS_11E67 REAC. SW.-RUN, FV=on 13S70014675, POS_21E67 REAC. SW.
SHUTDOWN, FV=off 1A2S701176, POS_2 TC BOJ CLOSE, FV=off When control rods insert, verify triggers 29 and 30 automatically initiate and delete the following overrides:
13S70014674, POS_11E67 REAC. SW.-RUN 13S70014675, POS_2 1E67 REAC. SW.
SHUTDOWN
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                   OPERATOR ACTIONS Events 8 & 9 continued                           SRO
* Acknowledges reports
* Enters N 1-EOP-5 on high Reactor Building Vent rad levels, high Reactor Building area temperatures I rad levels, and/or loss of RB DIP
* Directs manual isolation of Emergency Condenser 11
* Directs Reactor Building evacuation
* Acknowledges manual isolation failure
* Directs dispatching of an operator and RP tech to obtain general area temperatures and radiation levels in the Reactor Building
* When Reactor Building Ventilation exhaust radiation exceeds 5 mRlhr, directs verification of RB Vent isolation and RBEVS initiation
* Determines area temperatures and/or radiation levels are above setpoints in Tables T and R, and transitions to N1 EOP-5 circle 27
* Determines a primary system is discharging into the Reactor Building and the discharge cannot be isolated, and transitions to N1-EOP-5 circle 28
* When any area temperature or radiation level approaches or reaches 135&deg;F or 8 Rlhr, respectively:
Note:
* Directs manual Reactor scram If the Reactor scrammed due to an earlier event, CT-2 CT-2 will be N/A.
* Acknowledges scram report
* Enters N1-EOP-2, RPV Control, on low RPV water level
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                         OPERATOR ACTIONS Events 8 & 9 continued                                 SRO continued
* Answers "Are all control rods inserted to at least position 04?" YES
* Directs entry into N1-S0P-1, Reactor Scram
* Directs RPV water level control 53-95" using Feedwater/Condensate and CRD
* Directs RPV pressure maintained
                                                        <1080 psig using TBVs Note: Anticipatory blowdown is likely to be
* May direct anticipatory blowdown with directed from N1-EOP-2 once one Reactor Building        TBVs and/or Emergency Condenser General Area temperature is above 135&deg;F with a          12 with cooldown in excess of second temperature trending towards 135&deg;F.              100oF/hr
* Acknowledge failure of BOJM, if reported Note:
* May direct opening TBVs using Emergency Condenser 12 is available even though              MPR it was isolated earlier due to inadvertent initiation.
* Acknowledges reports of Reactor The crew may decide not to use Emergency                Building temperatures and radiation Condenser 12 due to actuation of Annunciator K1        levels 4-5, EMER COOLING SYSTEM 12 STEAM LEAK
* When report is received that 2 General AREA T HI.                                              Areas temperatures are above 1350 F, enters N1-EOP-8, RPV Blowdown
* Answers "Are all control rods inserted to at least position 04" YES
* Answers "Drywell pressure?" <3.5 psig
* May direct initiation of Emergency Condenser 12
* Answers "Torus water level?" >8 ft
* Directs open 4 ERVs CT-3
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                   OPERATOR ACTIONS Events 8 & 9 continued                           ATC
* Monitors plant parameters Note: Prior to the scram, the ATC may also
* Monitors plant parameters Note: Prior to the scram, the ATC may also
* Makes evacuation announcements perform response actions for BOP since Feedwater due to steam leak level control is in manual.
* Makes evacuation announcements perform response actions for BOP since Feedwater   due to steam leak level control is in manual.
* Places Reactor Mode Switch to SHUTDOWN Recognizes/reports failure of Mode Switch to scram Depresses RPS manual scram push buttons and/or manually initiates ARI Provides scram report Performs scram verification actions of N1-S0P-1, Reactor Scram: Confirms all rods inserted Observes Reactor power lowering Places IRMs on range 9 Inserts IRM and SRM detectors Down-ranges IRMs as necessary Reduces Recirc Master flow to 25-43 x 10 6 lbm/hr Verifies main turbine and generator tripped Controls RPV pressure as directed using TBVs and/or Emergency Condenser 12 May recognize/report failure of BOJM and open TBVs using MPR INSTRUCTOR ACTIONS! PLANT RESPONSE Events 8 & 9 continued Note: No General Area temperature information is available until an Operator has been dispatched to the Reactor Building to monitor area temperatures.
* Places Reactor Mode Switch to SHUTDOWN
The timeline of field reports may be adjusted by examiner as necessary for evaluation purposes.
* Recognizes/reports failure of Mode Switch to scram
Role Play: When directed as Operator and RP tech to obtain General Area temperatures and radiation levels in the Reactor Building:
* Depresses RPS manual scram push buttons and/or manually initiates ARI
Wait 4 minutes and report RB 318' west side temperature is 125&deg;F and rising, radiation level is 2 mr/hr and rising. Also report that you see steam coming from the area of the EC steam IV room. Note: When one general area temperature is reported above 135&deg;F and a second general area temperature is reported as approaching 135&deg;F, the crew is likely to perform an anticipatory blowdown per EOP-2. Wait 2 more minutes and report RB 318' west side temperature is 137&deg;F and rising, radiation level is 4 mr/hr and rising. Report RB 318' east side temperature is 123&deg;F and rising, radiation level is 2 mr/hr and rising. Wait 3 more minutes and report RB 318' west side temperature is 145&deg;F and rising, radiation level is 6 mr/hr and rising. Report RB 318' east side temperature is 136&deg;F and rising, radiation level is 3 mr/hr and rising. OPERATOR ACTIONS BOP/ATe Attempts to isolate Emergency Condenser 1 'I by closing the following valves per ARP K1-4-3: 39-07R, EC STM ISOLATION VALVE 112 39-09R, EC STM ISOLATION VALVE 111 39-05, EMERG CNDSR COND RET ISOLATION VALVE 11 39-11 R, EMERG CNDSR STM SUPPLY DRAIN IV 111 39-12R, EMERG CNDSR STM SUPPLY DRAIN IV 112 05-01 R, EMERG COND VENT ISOLATION VALVE 111 05-11, EMERG COND VENT ISOLATION VALVE 112 Reports failure of 39-07R and 39-09R to close Dispatches operator and RP tech to obtain Reactor Building General Area temperatures and radiation levels Notifies crew of reports on General Area temperatures and radiation levels INSTRUCTOR ACTIONSI PLANT RESPONSE Events 8 & 9 continued Terminating Cues: RPV water level controlled in assigned band RPV Blowdown in progress OPERATOR ACTIONS BOP Performs RPV water level control actions of N1-S0P-1, Reactor Scram: Restores RPV level to 53-95" by controlling injection and rejecting through RWCU Determines  
* Provides scram report
#13 FWP was running Determines RPV water level is recovering Terminates 13 FWP injection as follows: Closes 13 FWP VALVE CONTROL Disengages 13 FWP Closes 29-10, Feedwater Pump 13 Blocking Valve Verifies RPV water level above 53" Verifies 11/12 FWP controllers in MANUAL and set to zero output Places FWP BYPASS Valve 11 or 12 in AUTO, sets to 65-70 inches If RPV level reaches 85 inches and rising, then: Verifies off all FW Pumps Secures CRD Pumps not required May initiate Emergency Condenser 12 Opens 4 ERVs CT-3 NMP SIMULATOR NRC Scenario 3 REV. 0 No. of Pages: 18 RPS MG Set Trip, CRD FCV Fails Closed, MPR Failure. Failure to Scram. Liquid Poison Pumps PREPARER DATE
* Performs scram verification actions of N1-S0P-1, Reactor Scram:
'L3D,A3 VALIDATED Grapes. Lavallee.
* Confirms all rods inserted
M. O'Brien DATE 12119/12 GEN SUPERVISOR  
* Observes Reactor power lowering
() OPSTRAINING C ...
* Places IRMs on range 9
DATE s: ..... S OPERATIONS MANAGER N/A -Exam Security DATE CONFIGURATION CONTROL N/A -Exam Security DATE SCENARIO  
* Inserts IRM and SRM detectors
* Down-ranges IRMs as necessary
* Reduces Recirc Master flow to 25-43 x 106 lbm/hr
* Verifies main turbine and generator tripped
* Controls RPV pressure as directed using TBVs and/or Emergency Condenser 12
* May recognize/report failure of BOJM and open TBVs using MPR
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                       OPERATOR ACTIONS Events 8 & 9 continued                               BOP/ATe
* Attempts to isolate Emergency Note: No General Area temperature information is       Condenser 1'I by closing the following available until an Operator has been dispatched to     valves per ARP K1-4-3:
the Reactor Building to monitor area temperatures.
* 39-07R, EC STM ISOLATION The timeline of field reports may be adjusted by           VALVE 112 examiner as necessary for evaluation purposes.
* 39-09R, EC STM ISOLATION VALVE 111 Role Play: When directed as Operator and RP
* 39-05, EMERG CNDSR COND tech to obtain General Area temperatures and               RET ISOLATION VALVE 11 radiation levels in the Reactor Building:
* 39-11 R, EMERG CNDSR STM SUPPLY DRAIN IV 111 Wait 4 minutes and report RB 318' west side
* 39-12R, EMERG CNDSR STM temperature is 125&deg;F and rising, radiation level is 2       SUPPLY DRAIN IV 112 mr/hr and rising. Also report that you see steam
* 05-01 R, EMERG COND VENT coming from the area of the EC steam IV room.               ISOLATION VALVE 111
* 05-11, EMERG COND VENT Note: When one general area temperature is ISOLATION VALVE 112 reported above 135&deg;F and a second general
* Reports failure of 39-07R and 39-09R area temperature is reported as approaching to close 135&deg;F, the crew is likely to perform an
* Dispatches operator and RP tech to anticipatory blowdown per EOP-2.
obtain Reactor Building General Area temperatures and radiation levels Wait 2 more minutes and report RB 318' west side
* Notifies crew of reports on General temperature is 137&deg;F and rising, radiation level is 4 Area temperatures and radiation mr/hr and rising. Report RB 318' east side levels temperature is 123&deg;F and rising, radiation level is 2 mr/hr and rising.
Wait 3 more minutes and report RB 318' west side temperature is 145&deg;F and rising, radiation level is 6 mr/hr and rising. Report RB 318' east side temperature is 136&deg;F and rising, radiation level is 3 mr/hr and rising.
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                 OPERATOR ACTIONS Events 8 & 9 continued                         BOP
* Performs RPV water level control actions of N1-S0P-1, Reactor Scram:
* Restores RPV level to 53-95" by controlling injection and rejecting through RWCU
* Determines #13 FWP was running
* Determines RPV water level is recovering
* Terminates 13 FWP injection as follows:
* Closes 13 FWP VALVE CONTROL
* Disengages 13 FWP
* Closes 29-10, Feedwater Pump 13 Blocking Valve
* Verifies RPV water level above 53"
* Verifies 11/12 FWP controllers in MANUAL and set to zero output
* Places FWP BYPASS Valve 11 or 12 in AUTO, sets to 65-70 inches
* If RPV level reaches 85 inches and rising, then:
* Verifies off all FW Pumps
* Secures CRD Pumps not required
* May initiate Emergency Condenser 12
* Opens 4 ERVs CT-3 Terminating Cues:
* RPV water level controlled in assigned band
* RPV Blowdown in progress
 
NMP SIMULATOR SCENARIO NRC Scenario 3                                     REV. 0                           No. of Pages: 18 RPS MG Set Trip, CRD FCV Fails Closed, MPR Failure. Failure to Scram. Liquid Poison Pumps PREPARER                 ~/~J;~;:TriP                                          DATE     'L3D,A3 VALIDATED                         Grapes. Lavallee. M. O'Brien                 DATE     12119/12 GEN SUPERVISOR OPSTRAINING               C ... ~(\= ~~,~
()
                                                        /
S DATE       s: b.,to OPERATIONS MANAGER                                   N/A - Exam Security                 DATE CONFIGURATION CONTROL                                   N/A - Exam Security                 DATE SCENARIO  


==SUMMARY==
==SUMMARY==
Length: 60 minutes Initial Power Level: Approximately 100% The scenario begins at approximately 100% power. Containment Spray pump 112 is out of service for maintenance.
 
Steam Packing Exhauster 12 is caution tagged due to high vibrations.
Length: 60 minutes Initial Power Level: Approximately 100%
Shortly after the crew assumes the shift, RPS MG Set 131 will trip. This will result in a scram and loss of two strings of Feedwater heating. The crew will enter N1-S0P-16.1, Feedwater System Failures, and lower power as required to maintain below the license limit. The crew will re-energize RPS trip bus 131 from I&C Bus 130A, and then reset the half-scram and Feedwater heaters. Next, Reactor pressure instrument 36-07B will fail downscale.
The scenario begins at approximately 100% power. Containment Spray pump 112 is out of service for maintenance. Steam Packing Exhauster 12 is caution tagged due to high vibrations.
This failure makes one channel inoperable for the RPS high pressure scram. The CRS will determine the Tech Spec impact. Next, the in-service CRD flow control valve will fail closed.
Shortly after the crew assumes the shift, RPS MG Set 131 will trip. This will result in a half scram and loss of two strings of Feedwater heating. The crew will enter N1-S0P-16.1, Feedwater System Failures, and lower power as required to maintain below the license limit.
The crew will enter N1-S0P-5.1, Loss of Control Rod Drive, and take action to place the standby flow control valve in service. The CRS will determine the Tech Spec impact. Next, the MPR setpoint begins drifting low. This will cause the MPR to take control of and further open Turbine Control/Bypass valves. Reactor pressure will lower until either the crew manually scrams the Reactor, or the Reactor scrams from MSIV closure at 850 psig. The crew will enter N1-S0P-31.2, Pressure Regulator Malfunction, and N1-S0P-1, Reactor Scram. Multiple control rods will fail to fully insert on the scram. The crew will enter N1-EOP-3, Failure to Scram. The crew will lower Reactor power by tripping Reactor Recirculation pumps and/or terminating and preventing all RPV injection except boron and CRD (Critical Task). The crew will also take action to insert control rods (Critical Task). The crew will be challenged by a failure of Liquid Poison to inject. Both Liquid Poison pumps will trip shortly after being started. Once control rod insertion is in progress, the running CRD pump will trip. The crew will be able to start an alternate CRD pump to continue control rod insertion.
The crew will re-energize RPS trip bus 131 from I&C Bus 130A, and then reset the half-scram and Feedwater heaters.
Major Procedures:
Next, Reactor pressure instrument 36-07B will fail downscale. This failure makes one channel inoperable for the RPS high pressure scram. The CRS will determine the Tech Spec impact.
N1-ST-W15, N1-S0P-16.1, N1-S0P-1.1, N1-0P-48, N1-S0P-5.1, 31.2, N1-S0P-1, N1-EOP-3, N1-EOP-3.1, N1-S0P-5.1 Dynamic Mitigation Strategy Code: AT1, High power ATWS, RPV level controlled below feedwater spargers, RPV Blowdown not required EAL Site Area Emergency per EAL 2.2.2 (Any RPS scram setpoint has been exceeded AND automatic and manual scrams fail to result in a control rod pattern which assures reactor shutdown under all conditions without boron AND either: Reactor power> 6% OR Torus temperature>
Next, the in-service CRD flow control valve will fail closed. The crew will enter N1-S0P-5.1, Loss of Control Rod Drive, and take action to place the standby flow control valve in service.
110&deg;F) Termination Criteria:
The CRS will determine the Tech Spec impact.
RPV water level controlled in assigned band, RPV pressure controlled in assigned band, control rod insertion in progress or completed SIMULATOR SET UP IC Number: IC-153 Presets/Function Key Assignments Malfunctions:  
Next, the MPR setpoint begins drifting low. This will cause the MPR to take control of and further open Turbine Control/Bypass valves. Reactor pressure will lower until either the crew manually scrams the Reactor, or the Reactor scrams from MSIV closure at 850 psig. The crew will enter N1-S0P-31.2, Pressure Regulator Malfunction, and N1-S0P-1, Reactor Scram.
: a. CT01 B, CT Pump 112 Trip b. RP01A, REACTOR TRIP BUS MOTOR GENERATOR TRIPS 131 c. RP16B, RPV PT 36-07B FAILED LOW d. RD36A, CRD FCV 44-151 FAILURE -CLOSED e. TC08, MECHANICAL PRES. REGULATOR FAILS -LOW f. RD33A, CONTROL ROD BANK BLOCKED BANK 1, FV=8 g. RD33B, CONTROL ROD BANK BLOCKED BANK 2, FV=8 h. RD33C, CONTROL ROD BANK BLOCKED BANK 3, FV=18 i. RD33D, CONTROL ROD BANK BLOCKED BANK 4, FV=8 j. RD33E, CONTROL ROD BANK BLOCKED BANK 5, FV=8 k. LP01A, Liquid Poison Pump 11 Trip, DT=5 I. LP01 B, Liquid Poison Pump 12 Trip, DT=5 m. RD35B, CRD Hydraulic Pump 12 Trip 2. Remotes: a. RP01, RX TRIP BUS 131 PWR SOURCE, FV=maint b. MS01, HP FW HTR 115 RESET, FV=reset c. MS03, HP FW HTR 135 RESET, FV=reset d. MS04, FW HTR STRING 11 RESET, FV=reset e. MS06, FW HTR STRING 13 RESET, FV=reset f. RD05, CRD FLOW CONTROL VALVE ISOL, FV=nc30b FW24 , REMOVAL OF HPCI FUSES FU8/FU9, FV=pulled Overrides: 13S73D146713, POS_2 'I E70 TC MPR POS C, FV=on (MPR setpoint drifts low) Annunciators: None Triggers:
Multiple control rods will fail to fully insert on the scram. The crew will enter N1-EOP-3, Failure to Scram. The crew will lower Reactor power by tripping Reactor Recirculation pumps and/or terminating and preventing all RPV injection except boron and CRD (Critical Task). The crew
PRESET TRG 1 TRG2 TRG3 TRG20 PRESET PRESET PRESET PRESET PRESET TRG 11 TRG12 TRG5 TRG29 TRG30 TRG30 TRG30 TRG30 TRG 21 TRG24 TRG4 TRG 11 -Initiates when Liquid Poison pump keylock switch is taken to SYS 11 position. Event Action: zdlpsys2==1 Command: None TRG 12 -Initiates when Liquid Poison pump keylock switch is taken to SYS 12 position. Event Action: zdlpsys1 ==1 Command: None TRG 20 -Initiates when the Mode Switch is taken to SHUTDOWN Event Action: zdrpstdn==1 Command: dor 13s73di46713  
 
: d. TRG 21 -Initiates when the CRD FCV selector switch is re-positioned Event Action: zdrdfcvb==1 Command: None Equipment Out of Service Containment Spray pump 112 in PTL with yellow tag Containment Spray suction valve 112 closed with yellow tag Steam Packing Exhauster 12 green-flagged with yellow tag Support Documentation None. Miscellaneous Ensure Drywell cooling fan 11 is secured with control switch in neutral. Ensure CRD pump B is running and CRD pump A is in standby. Protect the following equipment:
will also take action to insert control rods (Critical Task). The crew will be challenged by a failure of Liquid Poison to inject. Both Liquid Poison pumps will trip shortly after being started.
EDG 103, PB 103 Update Divisional Status Board SHIFT TURNOVER INFORMATION OFF GOING SHIFT: 0 N , DATE: Today PART I: To be performed by the oncoming Operator before assuming the shift. Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE) PART II: To be reviewed by the oncoming Operator before assuming the shift. Shift Manager Log (SM, CRS, STA)
Once control rod insertion is in progress, the running CRD pump will trip. The crew will be able to start an alternate CRD pump to continue control rod insertion.
* Shift Turnover Checklist (ALL) RO Log (RO)
Major Procedures: N1-ST-W15, N1-S0P-16.1, N1-S0P-1.1, N1-0P-48, N1-S0P-5.1, N1-S0P 31.2, N1-S0P-1, N1-EOP-3, N1-EOP-3.1, N1-S0P-5.1 Dynamic Mitigation Strategy Code: AT1, High power ATWS, RPV level controlled below feedwater spargers, RPV Blowdown not required EAL Classification: Site Area Emergency per EAL 2.2.2 (Any RPS scram setpoint has been exceeded AND automatic and manual scrams fail to result in a control rod pattern which assures reactor shutdown under all conditions without boron AND either: Reactor power> 6% OR Torus temperature> 110&deg;F)
* LCO Status (SM, CRS, STA) Lit Control Room Annunciators
Termination Criteria: RPV water level controlled in assigned band, RPV pressure controlled in assigned band, control rod insertion in progress or completed
* Computer Alarm Summary {RO} (SM, CRS, STA, RO, CRE) Evolutions/General Information/Equipment Status: Reactor power is approximately 100%. Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO per TS 3.3.7.b). Steam Packing Exhauster 12 is caution tagged due to high vibrations.
 
PART III: Remarks/Planned Evolutions:
I. SIMULATOR SET UP A. IC Number:     IC-153 B. Presets/Function Key Assignments
Maintain operation at rated power. PART IV: To be reviewed/accomplished shortly after assuming the shift: Review new Clearances (SM)
: 1. Malfunctions:
* Test Control Annunciators (CRE) Shift Crew Composition (SM/CRS) NAME TITLE NAME Critical Tasks: CT-1.0 Given a failure of the Reactor to scram with power above 6% or unknown and RPV water level above -41 inches, lower power to below 6% by:
: a. CT01 B, CT Pump 112 Trip                                           PRESET
: b. RP01A, REACTOR TRIP BUS MOTOR GENERATOR TRIPS 131                   TRG 1
: c. RP16B, RPV PT 36-07B FAILED LOW                                   TRG2
: d. RD36A, CRD FCV 44-151 FAILURE - CLOSED                             TRG3
: e. TC08, MECHANICAL PRES. REGULATOR FAILS - LOW                       TRG20
: f. RD33A, CONTROL ROD BANK BLOCKED BANK 1, FV=8                       PRESET
: g. RD33B, CONTROL ROD BANK BLOCKED BANK 2, FV=8                       PRESET
: h. RD33C, CONTROL ROD BANK BLOCKED BANK 3, FV=18                       PRESET
: i. RD33D, CONTROL ROD BANK BLOCKED BANK 4, FV=8                       PRESET
: j. RD33E, CONTROL ROD BANK BLOCKED BANK 5, FV=8                       PRESET
: k. LP01A, Liquid Poison Pump 11 Trip, DT=5                           TRG 11 I. LP01 B, Liquid Poison Pump 12 Trip, DT=5                           TRG12
: m. RD35B, CRD Hydraulic Pump 12 Trip                                   TRG5
: 2. Remotes:
: a. RP01, RX TRIP BUS 131 PWR SOURCE, FV=maint                         TRG29
: b. MS01, HP FW HTR 115 RESET, FV=reset                                 TRG30
: c. MS03, HP FW HTR 135 RESET, FV=reset                               TRG30
: d. MS04, FW HTR STRING 11 RESET, FV=reset                             TRG30
: e. MS06, FW HTR STRING 13 RESET, FV=reset                             TRG30
: f. RD05, CRD FLOW CONTROL VALVE ISOL, FV=nc30b                       TRG 21
: g. FW24 , REMOVAL OF HPCI FUSES FU8/FU9, FV=pulled                     TRG24
: 3. Overrides:
: a. 13S73D146713, POS_2 'I E70 TC MPR POS C, FV=on (MPR setpoint drifts low)                                         TRG4
: 4. Annunciators:
: a. None
: 5. Triggers:
: a. TRG 11 -Initiates when Liquid Poison pump keylock switch is taken to SYS 11 position.
: i. Event Action: zdlpsys2==1
 
ii. Command: None
: b. TRG 12 - Initiates when Liquid Poison pump keylock switch is taken to SYS 12 position.
: i. Event Action: zdlpsys1 ==1 ii. Command: None
: c. TRG 20 - Initiates when the Mode Switch is taken to SHUTDOWN
: i. Event Action: zdrpstdn==1 ii. Command: dor 13s73di46713
: d. TRG 21 -Initiates when the CRD FCV selector switch is re-positioned
: i. Event Action: zdrdfcvb==1 ii. Command: None C. Equipment Out of Service
: 1. Containment Spray pump 112 in PTL with yellow tag
: 2. Containment Spray suction valve 112 closed with yellow tag
: 3. Steam Packing Exhauster 12 green-flagged with yellow tag D. Support Documentation
: 1. None.
E. Miscellaneous
: 1. Ensure Drywell cooling fan 11 is secured with control switch in neutral.
: 2. Ensure CRD pump B is running and CRD pump A is in standby.
: 3. Protect the following equipment: EDG 103, PB 103
: 4. Update Divisional Status Board
 
II.                          SHIFT TURNOVER INFORMATION OFF GOING SHIFT: 0 N         , D                          DATE: Today PART I:         To be performed by the oncoming Operator before assuming the shift.
* Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE)
PART II:       To be reviewed by the oncoming Operator before assuming the shift.
* Shift Manager Log (SM, CRS, STA)
* Shift Turnover Checklist (ALL)
* RO Log (RO)
* LCO Status (SM, CRS, STA)
* Lit Control Room Annunciators
* Computer Alarm Summary {RO}
(SM, CRS, STA, RO, CRE)
Evolutions/General Information/Equipment Status:
* Reactor power is approximately 100%.
* Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO per TS 3.3.7.b).
* Steam Packing Exhauster 12 is caution tagged due to high vibrations.
PART III:       Remarks/Planned Evolutions:
Maintain operation at rated power.
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                   TITLE                   NAME SRO ATCRO BOPRO
 
Critical Tasks:
CT-1.0     Given a failure of the Reactor to scram with power above 6% or unknown and RPV water level above -41 inches, lower power to below 6% by:
* Tripping Reactor Recirculation pumps, and/or
* Tripping Reactor Recirculation pumps, and/or
* Terminating and preventing all injection except boron and CRD, in accordance with N1-EOP-3.
* Terminating and preventing all injection except boron and CRD, in accordance with N1-EOP-3.
Safety Significance:
Safety Significance: High Reactor power after a scram is attempted indicates a challenge to nuclear fuel and to plant heat sinks. In the event of a loss of the normal heat sink, this may result in adding heat to the Torus and challenging the Primary Containment. Lowering Reactor power reduces these challenges.
High Reactor power after a scram is attempted indicates a challenge to nuclear fuel and to plant heat sinks. In the event of a loss of the normal heat sink, this may result in adding heat to the Torus and challenging the Primary Containment.
Cueing: Control rod position and Reactor power indications will indicate a failure to scram with Reactor power above 6%. N1-EOP-3 provides direction to trip Recirculation pumps and terminate and prevent injection based on Reactor power.
Lowering Reactor power reduces these challenges.
Measurable Performance Indicators: Manipulation of Recirculation pump control switches, Feedwater system components, and Core Spray jumpers will provide observable actions for the evaluation team.
Cueing: Control rod position and Reactor power indications will indicate a failure to scram with Reactor power above 6%. N1-EOP-3 provides direction to trip Recirculation pumps and terminate and prevent injection based on Reactor power. Measurable Performance Indicators:
Performance Feedback: Lowering Recirculation flow, Feedwater flow, Reactor water level, and Reactor power will provide performance feedback regarding the success of crew actions.
Manipulation of Recirculation pump control switches, Feedwater system components, and Core Spray jumpers will provide observable actions for the evaluation team. Performance Feedback:
CT-2.0     Given a failure of the Reactor to scram, insert control rods, in accordance with N 1 EOP-3.
Lowering Recirculation flow, Feedwater flow, Reactor water level, and Reactor power will provide performance feedback regarding the success of crew actions. CT-2.0 Given a failure of the Reactor to scram, insert control rods, in accordance with N EOP-3. Safety Significance:
Safety Significance: Inserting control rods lowers Reactor power, which reduces challenges to the plant during a failure to scram. Additionally, inserting control rods ultimately provides a long-term, stable core shutdown. Boron injection alone may not provide a stable shutdown condition.
Inserting control rods lowers Reactor power, which reduces challenges to the plant during a failure to scram. Additionally, inserting control rods ultimately provides a long-term, stable core shutdown.
Cueing: Control rod position and Reactor power indications will indicate a failure to scram. N1-EOP-3 provides direction to insert control rods.
Boron injection alone may not provide a stable shutdown condition.
Measurable Performance Indicators: Manipulation of RPS, CRD, and RMCS controls will provide observable actions for the evaluation team.
Cueing: Control rod position and Reactor power indications will indicate a failure to scram. N1-EOP-3 provides direction to insert control rods. Measurable Performance Indicators:
Performance Feedback: Control rod position and Reactor power will provide performance feedback regarding success of crew actions to insert control rods.
Manipulation of RPS, CRD, and RMCS controls will provide observable actions for the evaluation team. Performance Feedback:
 
Control rod position and Reactor power will provide performance feedback regarding success of crew actions to insert control rods.
INSTRUCTOR ACTIONSI PLANT RESPONSE                                     OPERATOR ACTIONS Take the simulator out of freeze before the crew   CREW enters for the pre-shift walkdown and briefing.
INSTRUCTOR ACTIONSI PLANT RESPONSE Take the simulator out of freeze before the crew enters for the pre-shift walkdown and briefing.
* Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown.     panels, assumes the shift Event 1 - RPS MG Set 131 Trip                       CREW When directed by lead examiner, insert
Allow no more than 5 minutes for panel walkdown.
* Recognize/report RPS 11 half scram malfunction:
Event 1 -RPS MG Set 131 Trip When directed by lead examiner, insert malfunction:
* Diagnose trip of RPS MG set 131 RP01 A, REACTOR TRI P BUS MOTOR GENERATOR TRIPS 131 TRG 1 Scram solenoid lights for RPS 11 de-energize Feedwater temperature slowly lowers Reactor power slowly rises Expected annunciators:
RP01 A, REACTOR TRI P BUS MOTOR GENERATOR TRIPS 131 TRG 1 Scram solenoid lights for RPS 11 de-energize Feedwater temperature slowly lowers Reactor power slowly rises Expected annunciators:
F1-3-7, RX. TRIP BUS M-G SET 131 TROUBLE F1-3-1, RPS CH 11 MAN REACTOR TRIP F1-2-1, RPS CH 11 AUTO REACTOR TRIP SRO
F1-3-7, RX. TRIP BUS M-G SET 131 TROUBLE F1-3-1, RPS CH 11 MAN REACTOR TRIP F1-2-1, RPS CH 11 AUTO REACTOR TRIP OPERATOR ACTIONS CREW Conducts pre-brief, walks down the panels, assumes the shift CREW Recognize/report RPS 11 half scram Diagnose trip of RPS MG set 131 SRO Acknowledges reports Directs execution of ARP F1-3-7 Directs entry into N1-0P-48 H.4.D Directs entry into N1-S0P-16.1 for loss of Feedwater heating May direct emergency power reduction per N1-S0P-1.1 if needed to control Feedwater temperatures or Reactor power Provides oversight of reactivity changes INSTRUCTOR ACTIONSI PLANT RESPONSE Event 1 continued Role Play: When dispatched as operator investigate problem with MG Set 131, wait minutes then report that you can smell insulation in the vicinity of MG Set 131 Report that the drive motor breaker tripped overcurrent.
* Acknowledges reports
If asked, report no overvoltage Role Play: When dispatched as operator transfer Reactor Trip Bus 131 to I &C Bus wait 2 minutes and insert RP01, RP01, RX TRIP BUS 131 PWR TRG 29 Then report Reactor Trip Bus 131 has been energized from I&C Bus 130A, and that half scram and Feedwater heaters can be reset. Role Play: When dispatched as operator to reset Feedwater heaters, wait 2 minutes and insert remotes: MS01, HP FW HTR 115 RESET, FV=reset MS03, HP FW HTR 135 RESET, FV=reset MS04, FW HTR STRING 11 RESET, FV=reset MS06, FW HTR STRING 13 RESET, FV=reset TRG 30 Then report Feedwater heaters have been reset. OPERATOR ACTIONS ATC Monitors plant parameters Lowers power per N1-S0P-1.1 as required to control Feedwater temperatures or Reactor power Resets half scram BOP Executes ARP F1-3-7 Dispatches an operator to investigate MG Set 131 Determines I&C Bus 130A is available Obtains SRO permission to perform dead bus transfer of Reactor Trip Bus 131 Dispatches an operator to perform dead bus transfer of Reactor Trip Bus 131 per N1-0P-48 section H.4.0 Enters N1-S0P-16.1 due to loss of Feedwater heating Monitors Feedwater temperatures Acknowledges that Reactor Trip Bus 131 is re-energized Coordinates with ATC to reset half scram Dispatches operator to reset Feedwater heaters INSTRUCTOR ACTIONS! PLANT RESPONSE Event 2 -Reactor Pressure Instrument Fails Downscale When directed by lead examiner, insert malfunction:
* Directs execution of ARP F1-3-7
* Directs entry into N1-0P-48 H.4.D
* Directs entry into N1-S0P-16.1 for loss of Feedwater heating
* May direct emergency power reduction per N1-S0P-1.1 if needed to control Feedwater temperatures or Reactor power
* Provides oversight of reactivity changes
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                     OPERATOR ACTIONS Event 1 continued                                   ATC
* Monitors plant parameters Role Play: When dispatched as operator to
* Lowers power per N1-S0P-1.1 as investigate problem with MG Set 131, wait two          required to control Feedwater minutes then report that you can smell burnt          temperatures or Reactor power insulation in the vicinity of MG Set 131 motor.
* Resets half scram Report that the drive motor breaker tripped on overcurrent. If asked, report no overvoltage trip  BOP occurred.
* Executes ARP F1-3-7
* Dispatches an operator to investigate MG Set 131
* Determines I&C Bus 130A is available
* Obtains SRO permission to perform Role Play: When dispatched as operator to dead bus transfer of Reactor Trip Bus transfer Reactor Trip Bus 131 to I&C Bus 130A,        131 wait 2 minutes and insert remote:
* Dispatches an operator to perform RP01, RP01, RX TRIP BUS 131 PWR SOURCE, dead bus transfer of Reactor Trip Bus FV=maint 131 per N1-0P-48 section H.4.0 TRG 29
* Enters N1-S0P-16.1 due to loss of Then report Reactor Trip Bus 131 has been re Feedwater heating energized from I&C Bus 130A, and that half scram
* Monitors Feedwater temperatures and Feedwater heaters can be reset.
* Acknowledges that Reactor Trip Bus 131 is re-energized Role Play:     When dispatched as operator to
* Coordinates with ATC to reset half reset Feedwater heaters, wait 2 minutes and insert scram remotes:
* Dispatches operator to reset MS01, HP FW HTR 115 RESET, FV=reset Feedwater heaters MS03, HP FW HTR 135 RESET, FV=reset MS04, FW HTR STRING 11 RESET, FV=reset MS06, FW HTR STRING 13 RESET, FV=reset TRG 30 Then report Feedwater heaters have been reset.
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                     OPERATOR ACTIONS Event 2 - Reactor Pressure Instrument Fails       CREW Downscale
* Recognize/report Reactor pressure When directed by lead examiner, insert               instrument failed downscale malfunction:
RP16B, RPV PT 36-07B FAILED LOW TRG2 RPV pressure instrument indicates downscale Expected Annunciators:
RP16B, RPV PT 36-07B FAILED LOW TRG2 RPV pressure instrument indicates downscale Expected Annunciators:
F4-4-2, RPS CH 12 REACTOR PRESS LOW F4-4-7, RPS CH 12 MAIN STEAM ISOLATION AUTO OPERA TE Role Play: When directed as Operator to check ATS cabinet indication, wait 2 minutes and report that PT 36-078 is downscale with the gross failure light lit. OPERATOR ACTIONS CREW Recognize/report Reactor pressure instrument failed downscale SRO Acknowledges reports from crew Enters T.S. Table 3.6.2.a (0), for pressure transmitter 36-078 (Place RPS Channel 11 in the tripped condition within 12 hours) ATC Monitors plant parameters Observes other Reactor pressure indications stable BOP Executes ARPs F4-4-2 and F4-4-7 Dispatches operator to investigate indications at ATS Cabinet INSTRUCTOR ACTIONS! PLANT RESPONSE OPERATOR ACTIONS Event 3 -CRD Flow Control Valve Fails Closed CREW When directed by lead examiner, insert
F4-4-2, RPS CH 12 REACTOR PRESS LOW F4-4-7, RPS CH 12 MAIN STEAM ISOLATION AUTO OPERA TE SRO
* Acknowledgelreport Annunciator malfunction:
* Acknowledges reports from crew
S Diagnose CRD FCV 11 failed closed RD36A, CRD FCV 44-151 FAILURE -CLOSED TRG3 CRD flow indication indicates low Expected Annunciator:
* Enters T.S. Table 3.6.2.a (0), for pressure transmitter 36-078 (Place RPS Channel 11 in the tripped condition within 12 hours)
F3-1-5 CRD CHARGING WTR PRESS HIILO SRO Directs execution of ARP F3-1-S Directs entry into N1-S0P-S.1 Directs shifting CRD FCVs per N OP-S, Sect. F.S.O Determines Technical Specification 3.1.6.c applies for a loss of CRD injection flow Acknowledges report that CRD FCV 12 is in service After CRD FCV 12 is in service, exits TS 3.1.6 ATC Monitors plant parameters INSTRUCTOR ACTIONS/ PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP Role Play: If requested to investigate CRD FCV failure, wait 2 minutes and report that CRD FCV 11 (44-151) appears to have failed closed. Role Play: When requested to open 44-148 and 44-152 (step F.5.3.1), wait 1 minute and report valves are open. Role Play: When requested to countdown and position RB Air Transfer Switch (step F.5.3.2.a), perform countdown and report RB Air Transfer Switch is in the Up position.
ATC Role Play: When directed as Operator to check
Note: Verify the following remote automatically inserts when the CRD FCV selector switch is swapped: ROOS, CRO FLOW CONTROL VALVE ISOL, FV=nc30b TRG 21 Role Play: When requested to close 44-150 and 44-153 (step F.5.3.3), wait 1 minute and report valves are closed. Executes ARP F3-1-5 Determines CRD FCV is failed closed Enters N1-S0P-5.1 Determines standby FCV is to be placed in service per N 1-0P-5 section F.5.0 Establishes communications between Control Room and CRD Flow Control Valves Places FIC 44-146B, CRD FLOW CONTROL, MIA station in MANUAL Directs operator to open the following valves: o 44-148, CRD FCV 12 INLET o 44-152, CRD FCV 12 OUTLET Directs operator to place 113-297 SEL-CRD FCV Service Selector in Up position following countdown Places CRD FLOW CONTROL VALVE TRANSFER switch in VALVE 12 position Directs operator to close the following valves: o 44-150, CRD FCV 11 INLET o 44-153, CRD FCV 11 OUTLET Confirms CRD Flow between 64-66 gpm Places FIC 44-146B, CRD FLOW CONTROL, MIA Station in AUTO INSTRUCTOR ACTIONS! PLANT RESPONSE OPERATOR ACTIONS Events 4, 5, 6 and 7 -MPR Setpoint Drifts Low, CREW Failure to Scram, Liquid Poison Pumps Trip.
* Monitors plant parameters ATS cabinet indication, wait 2 minutes and report
* Observes other Reactor pressure that PT 36-078 is downscale with the gross failure    indications stable light lit.
BOP
* Executes ARPs F4-4-2 and F4-4-7
* Dispatches operator to investigate indications at ATS Cabinet
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                               OPERATOR ACTIONS Event 3 - CRD Flow Control Valve Fails Closed CREW When directed by lead examiner, insert
* Acknowledgelreport Annunciator F3-1 malfunction:                                   S
* Diagnose CRD FCV 11 failed closed RD36A, CRD FCV 44-151 FAILURE - CLOSED TRG3 CRD flow indication indicates low Expected Annunciator:
F3-1-5 CRD CHARGING WTR PRESS HIILO SRO
* Directs execution of ARP F3-1-S
* Directs entry into N1-S0P-S.1
* Directs shifting CRD FCVs per N 1 OP-S, Sect. F.S.O
* Determines Technical Specification 3.1.6.c applies for a loss of CRD injection flow
* Acknowledges report that CRD FCV 12 is in service
* After CRD FCV 12 is in service, exits TS 3.1.6 ATC
* Monitors plant parameters
 
INSTRUCTOR ACTIONS/
PLANT RESPONSE                                     OPERATOR ACTIONS Event 3 continued                                 BOP
* Executes ARP F3-1-5
* Determines CRD FCV is failed closed
* Enters N1-S0P-5.1
* Determines standby FCV is to be placed in service per N 1-0P-5 section Role Play: If requested to investigate CRD FCV      F.5.0 failure, wait 2 minutes and report that CRD FCV 11
* Establishes communications between (44-151) appears to have failed closed.              Control Room and CRD Flow Control Valves
* Places FIC 44-146B, CRD FLOW CONTROL, MIA station in MANUAL
* Directs operator to open the following Role Play: When requested to open 44-148 and valves:
44-152 (step F.5.3.1), wait 1 minute and report o   44-148, CRD FCV 12 INLET valves are open.                                    o   44-152, CRD FCV 12 OUTLET
* Directs operator to place 113-297 Role Play: When requested to countdown and re SEL-CRD FCV Service Selector in Up position RB Air Transfer Switch (step F.5.3.2.a),
position following countdown perform countdown and report RB Air Transfer
* Places CRD FLOW CONTROL Switch is in the Up position.
VALVE TRANSFER switch in VALVE 12 position Note: Verify the following remote automatically
* Directs operator to close the following inserts when the CRD FCV selector switch is valves:
swapped:
o   44-150, CRD FCV 11 INLET o   44-153, CRD FCV 11 OUTLET ROOS, CRO FLOW CONTROL VALVE ISOL,
* Confirms CRD Flow between 64-66 FV=nc30b gpm TRG 21
* Places FIC 44-146B, CRD FLOW CONTROL, MIA Station in AUTO Role Play: When requested to close 44-150 and 44-153 (step F.5.3.3), wait 1 minute and report valves are closed.
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                   OPERATOR ACTIONS Events 4, 5, 6 and 7 - MPR Setpoint Drifts Low, CREW Failure to Scram, Liquid Poison Pumps Trip.
* Recognize/report MPR taking control CRD Pump Trips
* Recognize/report MPR taking control CRD Pump Trips
* Recognize/report lowering Reactor When directed by lead examiner, insert override:
* Recognize/report lowering Reactor When directed by lead examiner, insert override:   pressure
pressure
* Recognize/report Turbine Bypass 13S73D146713, POS_21E70 TC MPR POS C,             valves opening FV=on TRG4
* Recognize/report Turbine Bypass 13S73D146713, POS_21E70 TC MPR POS C, valves opening FV=on Later: TRG4
* Later:
* o Recognize/report failure to scram Turbine Control Valves open further o Recognize/report trip of Liquid Turbine Bypass Valves being to open Poison pumps Reactor pressure lowers o Recognize/report trip of CRD Expected Annunciators:
Turbine Control Valves open further               o   Recognize/report failure to scram Turbine Bypass Valves being to open               o   Recognize/report trip of Liquid Reactor pressure lowers                                Poison pumps Expected Annunciators:                             o  Recognize/report trip of CRD A2-4-4, TURBINE MECHANICAL PRESS. REG. IN             pump B CONTROL A 1-4-6, TURBINE BY-PASS VALVES OPEN Verify the following malfunctions are preset:
pump B A2-4-4, TURBINE MECHANICAL PRESS. REG. IN CONTROL A 1-4-6, TURBINE BY-PASS VALVES OPEN Verify the following malfunctions are preset: RD33A, CONTROL ROD BANK BLOCKED BANK 1, FV=8 RD33B, CONTROL ROD BANK BLOCKED BANK 2, FV=8 RD33C, CONTROL ROD BANK BLOCKED BANK 3, FV=18 RD33D, CONTROL ROD BANK BLOCKED BANK 4, FV=8 RD33E, CONTROL ROD BANK BLOCKED BANK 5, FV=8 Verify the following malfunctions automatically insert when the respective pump is started: LP01A, Liquid Poison Pump 11 Trip, DT=5 TRG 11 LP01B, Liquid Poison Pump 12 Trip, DT=5 TRG 12 Control rods partially insert Reactor power remains> 6% Liquid Poison pumps trip INSTRUCTOR ACTIONS! PLANT RESPONSE OPERATOR ACTIONS Events 4. 5. 6 and 7 continued SRO When the Mode Switch is taken to verify TRG 20 Inserts malfunction TCOS, MECHANICAL PRES. REGULATOR FAILS -LOW Deletes override 135730146713, POS _2 1 E70 TC MPR POS C, FV=on This fails the MPR completely.
RD33A, CONTROL ROD BANK BLOCKED BANK 1, FV=8 RD33B, CONTROL ROD BANK BLOCKED BANK 2, FV=8 RD33C, CONTROL ROD BANK BLOCKED BANK 3, FV=18 RD33D, CONTROL ROD BANK BLOCKED BANK 4, FV=8 RD33E, CONTROL ROD BANK BLOCKED BANK 5, FV=8 Verify the following malfunctions automatically insert when the respective pump is started:
Note: Once 2-3 control rods have been inserted by the ATC and directed by lead examiner, insert malfunction:
LP01A, Liquid Poison Pump 11 Trip, DT=5 TRG 11 LP01B, Liquid Poison Pump 12 Trip, DT=5 TRG 12 Control rods partially insert Reactor power remains> 6%
RD35B, CRD Hydraulic Pump 12 Trip TRG5 CRD pump 12 trips Acknowledges reports Directs entry into N1-S0P-31.2, as time permits Directs manual Reactor scram per SOP-1 Acknowledges failure to scram Enters N1-EOP-2 due to Reactor power above 6% when scram required Answers "All rods in to at least 04" NO Answers "Will the reactor stay shutdown without boron" NO Exits N1-EOP-2, enters N1-EOP-3 Directs ADS bypassed Directs prevention of Core Spray injection per N1-EOP-1 Att 4 N1-EOP-3 Level Leg Actions (Initial) Directs bypass of the low-low RPV water level MSIV isolation per EOP-1 Att 2 Determines Reactor power is above 6% and RPV water level is above -41 inches Directs terminate and prevent of all injection except boron and CRD per N1-EOP-1 Att 24 CT-1 Directs RPV water level lowered to at least -41 inches INSTRUCTOR ACTIONS! PLANT RESPONSE Events 4,5,6 and 7 continued OPERATOR ACTIONS SRO continued N1-EOP-3 Pressure Leg Actions If an ERV is cycling: Directs initiation of Emergency Condensers Directs open ERVs to lower RPV pressure to less than 965 psig Directs RPV pressure controlled below 1080 psig using Turbine Bypass valves, Emergency Condensers, and ERVs Monitors Figure M, Heat Capacity Temperature Limit N1-EOP-3 Power Leg Actions Directs initiation of ARI Answers "Turbine Generator on-line?" NO Answers "Reactor power?" Above 6% Verifies Recirc Pumps tripped CT-1 Directs execution of N1-EOP-3.1 CT-2 Acknowledges trip of CRD pump 12 May enter N 1-S0P-5.1 Directs start of CRD pump 11 If power oscillates more than 25% or before Torus water temperature reaches 110&deg;F: Records Liquid Poison tank level Directs Liquid Poison injection Acknowledges trip of Liquid Poison pumps Directs alternate boron injection per N1-EOP-3.2 INSTRUCTOR ACTIONSI PLANT RESPONSE Events 4, 5, 6 and 7 continued OPERATOR ACTIONS SRO continued EOP-3 Level Leg Actions (Subsequent) Acknowleqges RPV water level below -41 inches If Torus temperature is above 110&deg;F, then directs level lowered until: Power drops below 6%, OR Level drops to -84 inches (TAF) Records final actual level Directs RPV injection with Condensate/Feedwater and CRD ATC Places Mode Switch in SHUTDOWN Depresses manual scram pushbuttons Provides scram report Bypasses Core Spray IV interlocks per N1-EOP-1 Att 4 by installing six jumpers inside Panel N (17, 18, 19, 24,25,26) Bypass low-low MSIV isolation per EOP-1 Att 2 by installing four jumpers inside Panel N (1,2,8, 9) When directed, performs (See actions below) CT-2 Reports when APRMs <6% Reports status of control rod insertion Recognizes/reports trip of CRD pump 12 Starts CRD pump 11 Injects Liquid Poison, if directed Recognizes/reports trip of Liquid Poison pumps INSTRUCTOR ACTIONS/ PLANT RESPONSE Events 4, 6, 6 and 7 continued OPERATOR ACTIONS ATC continued Possible N1-EOP-3.1 Section 3 Actions: Verifies a CRD Pump running Places Reactor Mode Switch in REFUEL Places ARI OVERRIDE switch in OVERRIDE Installs RPS jumpers (5, 6, 12, 13) Resets the scram Inserts rods to 00 using EMER ROD IN starting with high power regions of core (use LPRM indications)
Liquid Poison pumps trip
CT-2 If more drive pressure is required, then perform one or more of the following: Fully open CRD Flow Control Valve (F panel) Close 44-04, Control Rod Drive Water Cont V (F Panel) Close 44-167, Charging Water Header Blocking Valve (RB 237') Possible N1-EOP-3.1 Section 4 Actions: Places ARI OVERRIDE switch in OVERRIDE Installs RPS jumpers (5, 6, 12, 13) Resets the scram Verify open 44-167, Charging Water Header Blocking Valve (RB 237') When the SDV is drained, then initiate a manual scram INSTRUCTOR ACTIONSI PLANT RESPONSE Events 4, 5, 6 and 7 continued Role Play: When directed to pull HPCI fuses, wait one minute, then insert remote: FW24, REMOVAL OF HPCI FUSES FU8/FU9, FV=pulled TRG24 Then report task completion.
 
OPERATOR ACTIONS BOP Manually initiates ARI Bypasses ADS Terminates and prevents all injection except boron and CRD per N1-EOP-1 Att 24: CT-1 Closes both Feedwater Isolation Valves 11 and 12 OR places Feedwater pumps 11 and 12 in PTL Selects Manual on 11, 12 and 13 FWP Valve Control selector switches Closes 11, 12 and 13 Feedwater FCV (Knurled Knob) full counterclockwise Places FW LVL SETDOWN to OVERRI Directs operator to remove fuses FU-8 and FU-9 from Panel IS34 in the Aux Control Room Verifies closed, FEEDWATER PUMP 13 BLOCKING VALVE Verifies in MAN, FWP 11 BYPASS VALVE, AND set to zero output Verifies in MAN, FWP 12 BYPASS VALVE, AND set to zero output May re-open Feedwater Isolation Valve Informs SRO when RPV water level reaches -41 inches INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4, 5, 6 and 7 continued BOP continued If any ERV is cycling: Initiates Emergency Condensers Manually opens ERVs to lower RPV pressure <965 psig Controls RPV pressure below 1080 psig with Turbine Bypass Valves, Emergency Condensers and ERVs Closes MSIVs, as directed Initiates ARI Verifies all Recirc pumps tripped CT-1 Initiates Liquid Poison as directed Reports initial tank level Attempts to start Liquid Poison pump 11 and/or 12 Determines/reports Liquid Poison pump(s) trip Acknowledges direction to re-establish RPV injection with Condensate/Feedwater and CRD Re-injects with Condensate/Feedwater per N1-EOP-1 Att 24: Reopens at least one Feedwater Isolation Valve 11 and I or 12, if closed Controls injection with Feedwater flow control valves Terminating Cues: RPV water level controlled in assigned band
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                   OPERATOR ACTIONS Events 4. 5. 6 and 7 continued                   SRO
* Acknowledges reports
* Directs entry into N1-S0P-31.2, as time permits
* Directs manual Reactor scram per N1 Note:                                              SOP-1 When the Mode Switch is taken to SHUTDOWN,
* Acknowledges failure to scram verify TRG 20 automatically:
* Enters N1-EOP-2 due to Reactor
* Inserts malfunction TCOS, MECHANICAL            power above 6% when scram required PRES. REGULATOR FAILS - LOW
* Answers "All rods in to at least 04" NO
* Deletes override 135730146713, POS_2 1E70
* Answers "Will the reactor stay TC MPR POS C, FV=on                            shutdown without boron" NO This fails the MPR completely.
* Exits N1-EOP-2, enters N1-EOP-3
* Directs ADS bypassed
* Directs prevention of Core Spray Note:
injection per N1-EOP-1 Att 4 Once 2-3 control rods have been inserted by the ATC and directed by lead examiner, insert N1-EOP-3 Level Leg Actions (Initial) malfunction:
* Directs bypass of the low-low RPV RD35B, CRD Hydraulic Pump 12 Trip water level MSIV isolation per N1 TRG5 EOP-1 Att 2 CRD pump 12 trips
* Determines Reactor power is above 6% and RPV water level is above -41 inches
* Directs terminate and prevent of all injection except boron and CRD per N1-EOP-1 Att 24 CT-1
* Directs RPV water level lowered to at least -41 inches
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE               OPERATOR ACTIONS Events 4,5,6 and 7 continued SRO continued N1-EOP-3 Pressure Leg Actions
* If an ERV is cycling:
* Directs initiation of Emergency Condensers
* Directs open ERVs to lower RPV pressure to less than 965 psig
* Directs RPV pressure controlled below 1080 psig using Turbine Bypass valves, Emergency Condensers, and ERVs
* Monitors Figure M, Heat Capacity Temperature Limit N1-EOP-3 Power Leg Actions
* Directs initiation of ARI
* Answers "Turbine Generator on-line?"
NO
* Answers "Reactor power?" Above 6%
* Verifies Recirc Pumps tripped CT-1
* Directs execution of N1-EOP-3.1 CT-2
* Acknowledges trip of CRD pump 12
* May enter N 1-S0P-5.1
* Directs start of CRD pump 11
* If power oscillates more than 25% or before Torus water temperature reaches 110&deg;F:
* Records Liquid Poison tank level
* Directs Liquid Poison injection
* Acknowledges trip of Liquid Poison pumps
* Directs alternate boron injection per N1-EOP-3.2
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                 OPERATOR ACTIONS Events 4, 5, 6 and 7 continued SRO continued EOP-3 Level Leg Actions (Subsequent)
* Acknowleqges RPV water level below
                                  -41 inches
* If Torus temperature is above 110&deg;F, then directs level lowered until:
* Power drops below 6%, OR
* Level drops to -84 inches (TAF)
* Records final actual level
* Directs RPV injection with Condensate/Feedwater and CRD ATC
* Places Mode Switch in SHUTDOWN
* Depresses manual scram pushbuttons
* Provides scram report
* Bypasses Core Spray IV interlocks per N1-EOP-1 Att 4 by installing six jumpers inside Panel N (17, 18, 19, 24,25,26)
* Bypass low-low MSIV isolation per N1 EOP-1 Att 2 by installing four jumpers inside Panel N (1,2,8, 9)
* When directed, performs N1-EOP 3.1 (See actions below)
CT-2
* Reports when APRMs <6%
* Reports status of control rod insertion
* Recognizes/reports trip of CRD pump 12
* Starts CRD pump 11
* Injects Liquid Poison, if directed
* Recognizes/reports trip of Liquid Poison pumps
 
INSTRUCTOR ACTIONS/
PLANT RESPONSE                 OPERATOR ACTIONS Events 4, 6, 6 and 7 continued ATC continued Possible N1-EOP-3.1 Section 3 Actions:
* Verifies a CRD Pump running
* Places Reactor Mode Switch in REFUEL
* Places ARI OVERRIDE switch in OVERRIDE
* Installs RPS jumpers (5, 6, 12, 13)
* Resets the scram
* Inserts rods to 00 using EMER ROD IN starting with high power regions of core (use LPRM indications)
CT-2
* If more drive pressure is required, then perform one or more of the following:
* Fully open CRD Flow Control Valve (F panel)
* Close 44-04, Control Rod Drive Water Cont V (F Panel)
* Close 44-167, Charging Water Header Blocking Valve (RB 237')
Possible N1-EOP-3.1 Section 4 Actions:
* Places ARI OVERRIDE switch in OVERRIDE
* Installs RPS jumpers (5, 6, 12, 13)
* Resets the scram
* Verify open 44-167, Charging Water Header Blocking Valve (RB 237')
* When the SDV is drained, then initiate a manual scram
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                     OPERATOR ACTIONS Events 4, 5, 6 and 7 continued                     BOP
* Manually initiates ARI
* Bypasses ADS
* Terminates and prevents all injection except boron and CRD per N1-EOP-1 Att 24:
CT-1
* Closes both Feedwater Isolation Valves 11 and 12 OR places Feedwater pumps 11 and 12 in PTL
* Selects Manual on 11, 12 and 13 FWP Valve Control selector switches
* Closes 11, 12 and 13 Feedwater FCV (Knurled Knob) full counterclockwise Role Play:
* Places FW LVL SETPOINT When directed to pull HPCI fuses, wait one minute,      SETDOWN to OVERRI DE then insert remote:
* Directs operator to remove fuses FW24, REMOVAL OF HPCI FUSES FU8/FU9, FU-8 and FU-9 from Panel IS34 in FV=pulled the Aux Control Room TRG24
* Verifies closed, FEEDWATER Then report task completion.
PUMP 13 BLOCKING VALVE
* Verifies in MAN, FWP 11 BYPASS VALVE, AND set to zero output
* Verifies in MAN, FWP 12 BYPASS VALVE, AND set to zero output
* May re-open Feedwater Isolation Valve
* Informs SRO when RPV water level reaches -41 inches
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                  OPERATOR ACTIONS Events 4, 5, 6 and 7 continued                  BOP continued
* If any ERV is cycling:
* Initiates Emergency Condensers
* Manually opens ERVs to lower RPV pressure <965 psig
* Controls RPV pressure below 1080 psig with Turbine Bypass Valves, Emergency Condensers and ERVs
* Closes MSIVs, as directed
* Initiates ARI
* Verifies all Recirc pumps tripped CT-1
* Initiates Liquid Poison as directed
* Reports initial tank level
* Attempts to start Liquid Poison pump 11 and/or 12
* Determines/reports Liquid Poison pump(s) trip
* Acknowledges direction to re-establish RPV injection with Condensate/Feedwater and CRD
* Re-injects with Condensate/Feedwater per N1-EOP-1 Att 24:
* Reopens at least one Feedwater Isolation Valve 11 and I or 12, if closed
* Controls injection with Feedwater flow control valves Terminating Cues:
* RPV water level controlled in assigned band
* RPV pressure controlled in assigned band
* RPV pressure controlled in assigned band
* Control rod insertion in progress or complete NMP SIMULATOR NRC Scenario 5 REV. 0 No. of Pages: 25 Startup. Sequential Loss of 115 KV Lines. Loss of Vacuum, EDG 102 Fails to Auto-Start.
* Control rod insertion in progress or complete
Loss of Coolant Accident.
 
Core Spray Fails to Auto-Start.
NMP SIMULATOR SCENARIO NRC Scenario 5                               REV. 0                             No. of Pages: 25 Startup. Sequential Loss of 115 KV Lines. Loss of Vacuum, EDG 102 Fails to Auto-Start. Loss of Coolant Accident. Core Spray Fails to Auto-Start. Emergency Condensers Fail to Operate from Control Room PREPARER                                                                   DATE   'ljJo/:r VALIDATED                     Grapes, Lavallee, M. O'Brien                 DATE       12121/12 GEN SUPERVISOR OPS TRAINING                                                               DATE       5}2-/''''
Emergency Condensers Fail to Operate from Control Room PREPARER DATE 'ljJo/:r* VALIDATED Grapes, Lavallee, M. O'Brien DATE 12121/12 GEN SUPERVISOR OPS TRAINING DATE 5}2-/''''
OPERATIONS MANAGER                               NIA - Exam Security                   DATE CONFIGURATION CONTROL                               NIA - Exam Security                   DATE SCENARIO  
OPERATIONS MANAGER NIA -Exam Security DATE CONFIGURATION CONTROL NIA -Exam Security DATE SCENARIO  


==SUMMARY==
==SUMMARY==
Length: 75 minutes Initial Power Level: Approximately 5% The scenario begins at approximately 5% power during a plant startup. Steam Packing Exhauster 12 is caution tagged due to high vibrations.
 
The crew will raise Reactor power by withdrawing control rods. The crew will then place the Mode Switch in RUN and withdraw IRMs. Next, 115 KV Line 1 will de-energize.
Length: 75 minutes Initial Power Level: Approximately 5%
The CRS will determine the Tech Spec impact. Then, Main Condenser vacuum will begin to degrade. The crew will enter N 1-S0P-25.1, Unplanned Loss of Condenser Vacuum. The crew will scram the Reactor before vacuum lowers to 10" Hg. The continued loss of vacuum will lead to trip of the Turbine Bypass Valves and closure of the MSIVs. The crew will respond to the scram in accordance with N1-S0P-1, Reactor Scram. The crew will establish pressure control using the Emergency Condensers.
The scenario begins at approximately 5% power during a plant startup. Steam Packing Exhauster 12 is caution tagged due to high vibrations. The crew will raise Reactor power by withdrawing control rods. The crew will then place the Mode Switch in RUN and withdraw IRMs.
Next, 115 KV Line 4 will de-energize.
Next, 115 KV Line 1 will de-energize. The CRS will determine the Tech Spec impact. Then, Main Condenser vacuum will begin to degrade. The crew will enter N 1-S0P-25.1, Unplanned Loss of Condenser Vacuum. The crew will scram the Reactor before vacuum lowers to 10" Hg.
Combined with the earlier loss of Line 1, this will result in a loss of all offsite power. Powerboard 103 will be powered by Emergency Diesel Generator 103. Emergency Diesel Generator 102 will fail to auto-start.
The continued loss of vacuum will lead to trip of the Turbine Bypass Valves and closure of the MSIVs. The crew will respond to the scram in accordance with N1-S0P-1, Reactor Scram. The crew will establish pressure control using the Emergency Condensers.
The crew will manually start Emergency Diesel Generator 102 to re-energize Powerboard 102. Powerboards 11, 12, and 101 will de-energize.
Next, 115 KV Line 4 will de-energize. Combined with the earlier loss of Line 1, this will result in a loss of all offsite power. Powerboard 103 will be powered by Emergency Diesel Generator 103. Emergency Diesel Generator 102 will fail to auto-start. The crew will manually start Emergency Diesel Generator 102 to re-energize Powerboard 102. Powerboards 11, 12, and 101 will de-energize. This results in a loss of all Feedwater. The crew will enter N1-S0P 33A.1, Loss of 115 KV.
This results in a loss of all Feedwater.
Once the crew stabilizes the plant, a coolant leak will develop inside the Primary Containment.
The crew will enter 33A.1, Loss of 115 KV. Once the crew stabilizes the plant, a coolant leak will develop inside the Primary Containment.
The crew will enter N1-EOP-2, RPV Control, and N1-EOP-4, Primary Containment Control.
The crew will enter N1-EOP-2, RPV Control, and N1-EOP-4, Primary Containment Control. Emergency Condensers will fail to operate from the Control Room, but may be initiated from the field. The crew will initiate Containment Spray as Primary Containment conditions degrade (Critical Task). The leak will be beyond the capacity of available high pressure injection sources and Reactor pressure will be above the range of low pressure injection sources. When Reactor water level reaches the top of active fuel, the crew will perform an emergency depressurization per N1-EOP-8, RPV Slowdown (Critical Task). Core Spray will fail to start. The crew will control injection systems to restore and maintain Reactor water level above the top of active fuel (Critical Task). Major N1-0P-5, N1-0P-43A, N1-0P-38C, N1-S0P-25.1, N1-S0P-1, N1-EOP-2, N1-EOP-4, N1-EOP-8, N1-EOP-1 Dynamic Mitigation Strategy RL2, Small break LOCA or loss of high pressure injection, RPV level cannot be maintained above the top of active fuel, RPV Slowdown, recover level above TAF with low pressure systems and I or alternate coolant injection systems. EAL Alert per EAL 3.1.1, Drywell pressure CANNOT SE MAINTAINED  
Emergency Condensers will fail to operate from the Control Room, but may be initiated from the
< 3.5 psig due to coolant leakage Termination RPV Slowdown in progress, Reactor water level controlled above top of active fuel, Containment pressure and temperature controlled in accordance with N1-EOP-4 SIMULATOR SET UP IC Number: IC-155 Presets/Function Key Assignments Malfunctions: ED02A, 115 kV Line 1 (South Oswego) Loss of Offsite Power TRG 2 MC01, MAIN CONDENSER AIR INLEAKAGE, FV=18 TRG 3 ED01A, 115 kV Line 4 (JAF) Loss of Offsite Power, Delay=1 :30 TRG 4 DG04A, DG 102 FAILURE TO AUTO START PRESET EC04A, EC RETURN VALVE FAILS TO OPEN(IV 39-05) PRESET EC04B, EC RETURN VALVE FAILS TO OPEN(IV 39-06) PRESET EC03A, EC RETURN VALVE FAILS OPEN(IV 39-05) TRG 17 EC03B, EC RETURN VALVE FAILS OPEN(IV 39-06) TRG 18 RR29, RR Loop Rupture on Pump 15 Suction Line (LOCA), FV=17 TRG 5 CS06, CS Pumps Failure to Auto Start PRESET Remotes: RP21, RPS UPS 162 TROUBLE ANN RESET, FV=reset TRG 28 RP22, RPS UPS 172 TROUBLE ANN RESET, FV=reset, DT=10 TRG 28 ED40A, I&C Bus 130 NC Supply Breaker from PB 13B, FV=open TRG 29 ED40B, I&C Bus 130 NO Supply Breaker from PB 167 A, FV=close, DT=5 TRG 29 FP04, FIRE WTR TO FW BLOCKING VLVS, FV=100 TRG 21 CT03A, CT Raw Water Pump 111 Disch. Throttle Valve 93-14, FV=10 TRG 22 FW25 , MANUAL OPER. FW FCV-11, FV=O TRG 23 FW26 , MANUAL OPER. FW FCV-12, FV=O TRG 24 FW27 , MANUAL OPER. FW FCV-13, FV=O TRG 25 Overrides: None Annunciators: None Triggers: TRG 4 -Causes loss of Line 4 after the Mode Switch is taken to shutdown Event Action: zdrpstdn==1 Command: None
 
: b. TRG 5 -Causes the LOCA to begin when Powerboard 16 is crosstied  
field. The crew will initiate Containment Spray as Primary Containment conditions degrade (Critical Task). The leak will be beyond the capacity of available high pressure injection sources and Reactor pressure will be above the range of low pressure injection sources. When Reactor water level reaches the top of active fuel, the crew will perform an emergency depressurization per N1-EOP-8, RPV Slowdown (Critical Task). Core Spray will fail to auto start. The crew will control injection systems to restore and maintain Reactor water level above the top of active fuel (Critical Task).
: i. Event Action: zded602c==1 ii. Command: None c. TRG 10-Makes Condenser vacuum degrade faster once the Turbine is tripped i. Event Action: tc:trip==1 ii. Command: imf mc01 (0 0) 50 C. Equipment Out of Service 1. Steam Packing Exhauster 12 green-flagged with yellow tag. D. Support Documentation  
Major Procedures: N1-0P-5, N1-0P-43A, N1-0P-38C, N1-S0P-25.1, N1-S0P-1, N1-EOP-2, N1-EOP-4, N1-EOP-8, N1-EOP-1 Dynamic Mitigation Strategy Code: RL2, Small break LOCA or loss of high pressure injection, RPV level cannot be maintained above the top of active fuel, RPV Slowdown, recover level above TAF with low pressure systems and I or alternate coolant injection systems.
: 1. N 1-0P-43A marked up to appropriate point for startup. 2. Startup control rod sequence marked up to current rod (06-31 from 04 to 08). E. Miscellaneous  
EAL Classification: Alert per EAL 3.1.1, Drywell pressure CANNOT SE MAINTAINED < 3.5 psig due to coolant leakage Termination Criteria: RPV Slowdown in progress, Reactor water level controlled above top of active fuel, Containment pressure and temperature controlled in accordance with N1-EOP-4
: 1. None II. SHIFT TURNOVER INFORMATION OFF GOING SHIFT: [] N DATE: Today'D PART I: To be performed by the oncoming Operator before assuming the shift. Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE) PART II: To be reviewed by the oncoming Operator before assuming the shift. Shift Manager Log (SM, CRS, STA)
 
* Shift Turnover Checklist (ALL) RO Log (RO)
I. SIMULATOR SET UP A. IC Number:     IC-155 B. Presets/Function Key Assignments
* LCO Status (SM, CRS, STA) Lit Control Room Annunciators
: 1. Malfunctions:
* Computer Alarm Summary (RO) (SM, CRS, STA, RO, CRE) Evolutions/General Information/Equipment Status: Reactor power is approximately 5% with a startup in progress. Steam Packing Exhauster 12 is caution tagged due to high vibrations.
: a. ED02A, 115 kV Line 1 (South Oswego) Loss of Offsite Power           TRG 2
PART III: Remarks/Planned Evolutions: Withdraw control rods per the startup sequence.
: b. MC01, MAIN CONDENSER AIR INLEAKAGE, FV=18                           TRG 3
The next control rod to be moved is 06-31 from 04 to 08. Use notch control rod withdrawal.
: c. ED01A, 115 kV Line 4 (JAF) Loss of Offsite Power, Delay=1 :30       TRG 4
Withdraw the first four rods in the current group, then perform next planned evolution. Place the Mode Switch in RUN per N1-0P-43A steps 4.4 through 4.7. Withdraw the IRMs per N1-0P-43A step 4.10. Note: Another group of operators has already been assigned the task of inerting the Containment and will control that evolution.
: d. DG04A, DG 102 FAILURE TO AUTO START                                 PRESET
PART IV: To be reviewed/accomplished shortly after assuming the shift: Review new Clearances (SM)
: e. EC04A, EC RETURN VALVE FAILS TO OPEN(IV 39-05)                       PRESET
* Test Control Annunciators (CRE) Shift Crew Composition (SM/CRS) NAME TITLE NAME Critical Tasks: CT-1 Given a LOCA in the Drywell, initiate Containment Sprays prior to exceeding the Pressure Suppression Pressure limit, in accordance with N1-EOP-4.
: f. EC04B, EC RETURN VALVE FAILS TO OPEN(IV 39-06)                     PRESET
Safety Significance:
: g. EC03A, EC RETURN VALVE FAILS OPEN(IV 39-05)                         TRG 17
Initiating Containment Sprays reduces Primary Containment pressure.
: h. EC03B, EC RETURN VALVE FAILS OPEN(IV 39-06)                         TRG 18
This reduces stresses on the Drywell and Torus, assists in avoiding "chugging" that may cause fatigue failure of the LOCA downcomers, and avoids the need for a blowdown.
: i. RR29, RR Loop Rupture on Pump 15 Suction Line (LOCA), FV=17         TRG 5
These benefits reduce challenges to the fuel cladding, the RPV, and the Primary Containment.
: j. CS06, CS Pumps Failure to Auto Start                                 PRESET
Cueing: Multiple Primary Containment pressure and temperature indications and annunciators will indicate degrading conditions.
: 2. Remotes:
N1-EOP-4 provides direction to initiate Containment Sprays. Measurable Performance Indicators:
: a. RP21, RPS UPS 162 TROUBLE ANN RESET, FV=reset                       TRG 28
Manipulation of Containment Spray pump control switches will provide observable actions for the evaluation team. Performance Feedback:
: b. RP22, RPS UPS 172 TROUBLE ANN RESET, FV=reset, DT=10                 TRG 28
Containment Spray flow and lowering Primary Containment pressure and temperature indications will provide performance feedback regarding success of crew actions to initiated Containment Sprays. CT-2 Given Reactor water level below the top of active fuel and Reactor pressure above the capacity of available low pressure injection systems, perform an emergency depressurization of the Reactor, in accordance with N1-EOP-2 and N1-EOP-8.
: c. ED40A, I&C Bus 130 NC Supply Breaker from PB 13B, FV=open           TRG 29
Safety Significance:
: d. ED40B, I&C Bus 130 NO Supply Breaker from PB 167A, FV=close, DT=5                                                               TRG 29
Reactor water level must be maintained above limits to ensure adequate core cooling. With only low pressure systems available to inject and Reactor pressure above the pressure limits of these systems, Reactor pressure must be quickly lowered to allow injection.
: e. FP04, FIRE WTR TO FW BLOCKING VLVS, FV=100                           TRG 21
This protects the integrity of the fuel cladding.
: f. CT03A, CT Raw Water Pump 111 Disch. Throttle Valve 93-14, FV=10                                                               TRG 22
: g. FW25 , MANUAL OPER. FW FCV-11, FV=O                                 TRG 23
: h. FW26 , MANUAL OPER. FW FCV-12, FV=O                                 TRG 24
: i. FW27 , MANUAL OPER. FW FCV-13, FV=O                                 TRG 25
: 3. Overrides:
: a. None
: 4. Annunciators:
: a. None
: 5. Triggers:
: a. TRG 4 - Causes loss of Line 4 after the Mode Switch is taken to shutdown
: i. Event Action: zdrpstdn==1 ii. Command: None
: b. TRG 5 - Causes the LOCA to begin when Powerboard 16 is crosstied
: i. Event Action: zded602c==1 ii. Command: None
: c. TRG 10- Makes Condenser vacuum degrade faster once the Turbine is tripped
: i. Event Action: tc:trip==1 ii. Command: imf mc01 (0 0) 50 C. Equipment Out of Service
: 1. Steam Packing Exhauster 12 green-flagged with yellow tag.
D. Support Documentation
: 1. N1-0P-43A marked up to appropriate point for startup.
: 2. Startup control rod sequence marked up to current rod (06-31 from 04 to 08).
E. Miscellaneous
: 1. None
 
II.                           SHIFT TURNOVER INFORMATION OFF GOING SHIFT: [] N         'D                          DATE: Today PART I:         To be performed by the oncoming Operator before assuming the shift.
* Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE)
PART II:       To be reviewed by the oncoming Operator before assuming the shift.
* Shift Manager Log (SM, CRS, STA)
* Shift Turnover Checklist (ALL)
* RO Log (RO)
* LCO Status (SM, CRS, STA)
* Lit Control Room Annunciators
* Computer Alarm Summary (RO)
(SM, CRS, STA, RO, CRE)
Evolutions/General Information/Equipment Status:
* Reactor power is approximately 5% with a startup in progress.
* Steam Packing Exhauster 12 is caution tagged due to high vibrations.
PART III:       Remarks/Planned Evolutions:
: 1. Withdraw control rods per the startup sequence. The next control rod to be moved is 06-31 from 04 to 08. Use notch control rod withdrawal. Withdraw the first four rods in the current group, then perform next planned evolution.
: 2. Place the Mode Switch in RUN per N1-0P-43A steps 4.4 through 4.7.
: 3. Withdraw the IRMs per N1-0P-43A step 4.10.
Note: Another group of operators has already been assigned the task of inerting the Containment and will control that evolution.
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                   TITLE                     NAME SRO ATCRO BOPRO
 
Critical Tasks:
CT-1       Given a LOCA in the Drywell, initiate Containment Sprays prior to exceeding the Pressure Suppression Pressure limit, in accordance with N1-EOP-4.
Safety Significance: Initiating Containment Sprays reduces Primary Containment pressure. This reduces stresses on the Drywell and Torus, assists in avoiding "chugging" that may cause fatigue failure of the LOCA downcomers, and avoids the need for a blowdown. These benefits reduce challenges to the fuel cladding, the RPV, and the Primary Containment.
Cueing: Multiple Primary Containment pressure and temperature indications and annunciators will indicate degrading conditions. N1-EOP-4 provides direction to initiate Containment Sprays.
Measurable Performance Indicators: Manipulation of Containment Spray pump control switches will provide observable actions for the evaluation team.
Performance Feedback: Containment Spray flow and lowering Primary Containment pressure and temperature indications will provide performance feedback regarding success of crew actions to initiated Containment Sprays.
CT-2       Given Reactor water level below the top of active fuel and Reactor pressure above the capacity of available low pressure injection systems, perform an emergency depressurization of the Reactor, in accordance with N1-EOP-2 and N1-EOP-8.
Safety Significance: Reactor water level must be maintained above limits to ensure adequate core cooling. With only low pressure systems available to inject and Reactor pressure above the pressure limits of these systems, Reactor pressure must be quickly lowered to allow injection. This protects the integrity of the fuel cladding.
Cueing: Multiple Reactor water level and pressure indications and annunciators will indicate low Reactor water level with Reactor pressure too high for available injection systems to inject. N1-EOP-2 provides direction to initiate a blowdown.
Cueing: Multiple Reactor water level and pressure indications and annunciators will indicate low Reactor water level with Reactor pressure too high for available injection systems to inject. N1-EOP-2 provides direction to initiate a blowdown.
Measurable Performance Indicators:
Measurable Performance Indicators: Manipulation of Emergency Condenser valve and ERV control switches will provide observable actions for the evaluation team.
Manipulation of Emergency Condenser valve and ERV control switches will provide observable actions for the evaluation team. Performance Feedback:
Performance Feedback: Emergency Condenser and ERV instrumentation will provide indication that these systems are functioning properly once placed in service. Multiple Reactor pressure indicators and annunciators will provide performance feedback regarding the success of the blowdown.
Emergency Condenser and ERV instrumentation will provide indication that these systems are functioning properly once placed in service. Multiple Reactor pressure indicators and annunciators will provide performance feedback regarding the success of the blowdown.
 
CT-3 Given a LOCA in the Drywell and Reactor water level below the top of active fuel, inject with Preferred and Alternate Injection Systems to restore and maintain Reactor water level above -84 inches, in accordance with N1-EOP-2.
CT-3 Given a LOCA in the Drywell and Reactor water level below the top of active fuel, inject with Preferred and Alternate Injection Systems to restore and maintain Reactor water level above -84 inches, in accordance with N1-EOP-2.
Safety Significance:
Safety Significance: Maintaining Reactor water level above -84 inches ensures adequate core cooling through the preferred method of core submergence. This protects the integrity of the fuel cladding.
Maintaining Reactor water level above -84 inches ensures adequate core cooling through the preferred method of core submergence.
Cueing: Multiple Reactor water level indicators and annunciators will provide indications of lowering Reactor water level. N1-EOP-2 provides multiple procedure steps directing injection with preferred and alternate injection systems.
This protects the integrity of the fuel cladding.
Measurable Performance Indicators: Manipulation of pumps and/or valves in the preferred or alternate illjection system(s) will provide observable actions for the evaluation team.
Cueing: Multiple Reactor water level indicators and annunciators will provide indications of lowering Reactor water level. N1-EOP-2 provides multiple procedure steps directing injection with preferred and alternate injection systems. Measurable Performance Indicators:
Performance Feedback: Multiple Reactor water level indicators and annunciators will provide performance feedback regarding the success of injection with preferred and alternate injection systems.
Manipulation of pumps and/or valves in the preferred or alternate illjection system(s) will provide observable actions for the evaluation team. Performance Feedback:
 
Multiple Reactor water level indicators and annunciators will provide performance feedback regarding the success of injection with preferred and alternate injection systems.
INSTRUCTOR ACTIONSI PLANT RESPONSE                                   OPERATOR ACTIONS Take the simulator out of freeze before the crew CREW enters for the pre-shift walkdown and briefing.
INSTRUCTOR ACTIONSI PLANT RESPONSE Take the simulator out of freeze before the crew enters for the pre-shift walkdown and briefing.
* Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Raise Reactor Power with Control Rods SRO
Allow no more than 5 minutes for panel walkdown.
* Directs A TC to withdraw rods per Startup Rod Sequence and N 1-0P-5 section F.1.0
Event 1 -Raise Reactor Power with Control Rods OPERATOR ACTIONS CREW Conducts pre-brief, walks down the panels, assumes the shift SRO Directs A TC to withdraw rods per Startup Rod Sequence and N 1-0P-5 section F.1.0 Provides oversight for reactivity manipulation ATC Withdraws control rods per the rod sequence sheet Verifies Control Rod Power is On Depresses Rod Select pushbutton for control rod Places 4S 1 Control Rod Movement switch to the rod out notch position Observes SRM and period response Observes RMCS, RPIS and CRD indications Informs SRO when the first four rods of the current control rod group are withdrawn BOP Monitors plant parameters INSTRUCTOR ACTIONS! PLANT RESPONSE Event 2 -Place Mode Switch in RUN and Withdraw IRMs OPERATOR ACTIONS SRO Acknowledges first four rods of the current control rod group are withdrawn Directs placing Mode Switch in RUN and withdrawing IRMs per N1-0P-43A Provides oversight for evolution ATC Monitors plant parameters BOP Acknowledges direction from the SRO Confirms APRMs indicate greater than 5% power AND confirm APRM downscale alarms clear, E panel Confirm the following annunciators clear -F1-4-? and F4-4-2 Place Mode Switch to RUN Confirm Computer Point COS?, MODE SWITCH RUN -YES Confirm annunciator F3-4-S, RPS REACTOR PRESS LOW BY-PASS clear Transfer recorder indication to APRM channels Depress the FULL OUT button for each IRM WHEN the IRM detectors indicate full out, THEN range down the individual IRM Range switches to Range 2 OR U NTI L the respective I RM Downscale AND Upscale lights are out on E Console INSTRUCTOR ACTIONSI PLANT RESPONSE Event 3 -Loss of Line 1 When directed by lead examiner, insert malfunction:
* Provides oversight for reactivity manipulation ATC
* Withdraws control rods per the rod sequence sheet
* Verifies Control Rod Power is On
* Depresses Rod Select pushbutton for control rod
* Places 4S 1 Control Rod Movement switch to the rod out notch position o    Observes SRM and period response o    Observes RMCS, RPIS and CRD indications
* Informs SRO when the first four rods of the current control rod group are withdrawn BOP
* Monitors plant parameters
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                         OPERATOR ACTIONS Event 2 - Place Mode Switch in RUN and SRO Withdraw IRMs
* Acknowledges first four rods of the current control rod group are withdrawn
* Directs placing Mode Switch in RUN and withdrawing IRMs per N1-0P-43A
* Provides oversight for evolution ATC
* Monitors plant parameters BOP
* Acknowledges direction from the SRO
* Confirms APRMs indicate greater than 5% power AND confirm APRM downscale alarms clear, E panel
* Confirm the following annunciators clear - F1-4-? and F4-4-2
* Place Mode Switch to RUN
* Confirm Computer Point COS?, MODE SWITCH RUN - YES
* Confirm annunciator F3-4-S, RPS REACTOR PRESS LOW BY-PASS clear
* Transfer recorder indication to APRM channels
* Depress the FULL OUT button for each IRM
* WHEN the IRM detectors indicate full out, THEN range down the individual IRM Range switches to Range 2 OR UNTI L the respective IRM Downscale AND Upscale lights are out on E Console
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                       OPERATOR ACTIONS Event 3 - Loss of Line 1                             CREW When directed by lead examiner, insert
* Recognize/report loss of Line 1 malfunction:
ED02A, 115 kV Line 1 (South Oswego) Loss of Offsite Power TRG2 Breaker R10 opens Expected Annunciators:
ED02A, 115 kV Line 1 (South Oswego) Loss of Offsite Power TRG2 Breaker R10 opens Expected Annunciators:
A8-1-1, OSW-NMP 1 R10 TRIP A8-1-2, OSW-NMP 1 LINE RELAY TRIP Role If dispatched to Auxiliary Control Room, wait minutes, then report an undervoltage target is in panel 1 D1 OSWEGO NINE MILE POINT If dispatched to switchyard, wait 4 minutes, report R10 is open with no abnormal OPERATOR ACTIONS CREW Recognize/report loss of Line 1 SRO Acknowledges reports Directs execution of ARPs Reviews Technical Specification
A8-1-1, OSW-NMP 1 R10 TRIP A8-1-2, OSW-NMP 1 LINE RELAY TRIP SRO
* Acknowledges reports
* Directs execution of ARPs
* Reviews Technical Specification 3.6.3
* Determines Line 1 is inoperable
* Determines a 7 day LCO applies per Technical Specification 3.6.3.b ATC
* Monitors plant parameters BOP
* Executes ARPs
* Dispatches an operator to the Aux.
Control Room to observe the following Panels for flags AND targets:
Role Play:                                            o    1D1 OSWEGO NINE MILE POINT If dispatched to Auxiliary Control Room, wait 2            1 minutes, then report an undervoltage target is in on  o    1D2 115 KV RESERVE BUS &
panel 1D1 OSWEGO NINE MILE POINT 1.                        BREAKER R 1O-R40 If dispatched to switchyard, wait 4 minutes, then      o    1D3 NINE MILE POINT report R10 is open with no abnormal indications.            LIGHTHOUSE HILL 4
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                      OPERATOR ACTIONS Event 3 continued                                    BOP continued
* Observes 86TN relay on Panel 8A to see if it has tripped
* Observes back of Panel 88 in the Control Room for flags AND targets
* Records time of trip AND targets
* Performs N1-0P-33A Section H., Loss 115 kV Line 1:
o  Places computer points F432, Role Play:                                                F433, AND F434 on a special log If contacted as Power Control, report that you are        computer printout with a one dispatching a crew to investigate loss of line 1 and      minute scanning interval (Interval =
you have no reason for the loss yet. If asked to run      4) per N1-0P-42 AND monitors a Load Flow, wait 3 minutes, then call back and        o  Contacts System Power Control report that the Low Contingency Voltage Alarm is          AN D makes notification of the low NOT in alarm.                                            voltage alarm AND to run a Load Flow o  Contacts JAF Control Room in an expeditious manner AND informs them of the loss of 115 kV Line 1
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                      OPERATOR ACTIONS Event 4 - Loss of Condenser Vacuum                  CREW When directed by lead examiner, insert
* Recognize/report lowering main malfunction:                                          condenser vacuum MC01, MAIN CONDENSER AIR INLEAKAGE,
* Acknowledge/report annunciators:
FV=18
* A1-3-4, CONDENSER VACUUM TRG 3      BELOW 24" HG Main Condenser vacuum lowers Offgas flow rate rises Expected Annunciator:
A 1-3-4, CONDENSER VACUUM BELOW 24" HG SRO
* Acknowledges reports
* Directs execution of N1-S0P-25.1, Unplanned Loss of Condenser Vacuum
* Determines condenser vacuum can NOT be maintained above 22.1" Hgv
* Directs Turbine trip
* Determines condenser vacuum can NOT be maintained above 10" Hgv
* Directs a Reactor Scram
* Acknowledges scram report
* Directs entry into N1-S0P-1, Reactor Scram Note:
* Directs Reactor water level controlled Initial Reactor pressure control may be on the 53-95" with Condensate, Feedwater, Turbine Bypass Valves, but will transition soon and CRD after the scram to the Emergency Condensers as
* Directs Reactor pressure controlled Main Condenser vacuum degrades.
800-1000 psig with Emergency Condensers
* When vacuum approaches 10" Hgv, directs trip of Vacuum Trip 2 Note:
* When vacuum approaches 7.0" Hgv, May close MSIVs earlier to control cooldown rate.
directs closing the MSIVs
 
INSTRUCTOR ACTIONS/
PLANT RESPONSE                                  OPERATOR ACTIONS Event 4 continued                              ATC
* Monitors plant parameters
* Assists BOP with Turbine trip
* Places Reactor Mode Switch to SHUTDOWN
* Provides scram report
* Performs scram verification actions of N1-S0P-1, Reactor Scram:
* Confirms all rods inserted
* Observes Reactor power lowering
* Places IRMs on range 9
* Inserts IRM and SRM detectors Note:
* Down-ranges IRMs as necessary Initial Reactor pressure control may be on the
* Verifies main turbine and generator Turbine Bypass Valves, but will transition soon tripped after the scram to the Emergency Condensers as
* Controls RPV pressure as directed Main Condenser vacuum degrades.
using Emergency Condensers BOP
* Executes N1-S0P-2S.1, Unplanned Loss of Condenser Vacuum
* Verifies proper operation of the following:
o    Circ Water System o    SJAEs o    Off Gas System o    Condensate System o    Turbine Gland Seal System
* Dispatches operator to check for condenser leakage


====3.6.3 Determines====
INSTRUCTOR ACTIONSI PLANT RESPONSE                            OPERATOR ACTIONS Event 4 continued                          BOP continued
* Coordinates with A TC to trip Turbine:
Note:                                        o  Depresses AND holds down When the Turbine is tripped, verify TRG 10      FEEDWATER RETURN TO automatically inserts:                          NORMAL AFTER HPCI CH 11 MC01, MAIN CONDENSER AIR INLEAKAGE,              and 12 pushbuttons.
FV=50                                        o  Depresses UNIT EMERGENCY Main Condenser vacuum lowers quicker            TRIP pushbutton AND executes N 1-S0P-31.1, Turbine Trip o  Releases FEEDWATER RETURN TO NORMAL AFTER HPCI CH 11 and 12 push buttons
* Enters N1-S0P-1
* Controls Reactor water level 53-95" using Condensate, Feedwater, and CRD
* When directed, trips Vacuum Trip 2 and verifies Turbine Bypass Valves closed
* When directed, closes MSIVs


Line 1 is inoperable Determines a 7 day LCO applies per Technical Specification 3.6.3.b ATC Monitors plant parameters BOP Executes ARPs Dispatches an operator to the Aux. Control Room to observe the following Panels for flags AND targets: 1 D1 OSWEGO NINE MILE POINT 1 1D2 115 KV RESERVE BUS & BREAKER R 1 O-R40 1 D3 NINE MILE LIGHTHOUSE HILL INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued Role Play: If contacted as Power Control, report that you are dispatching a crew to investigate loss of line 1 and you have no reason for the loss yet. If asked to run a Load Flow, wait 3 minutes, then call back and report that the Low Contingency Voltage Alarm is NOT in alarm. Observes 86TN relay on Panel 8A to see if it has tripped Observes back of Panel 88 in the Control Room for flags AND targets Records time of trip AND targets Performs N1-0P-33A Section H., Loss 115 kV Line 1: Places computer points F432, F433, AND F434 on a special log computer printout with a one minute scanning interval (Interval
INSTRUCTOR ACTIONSI PLANT RESPONSE                                     OPERATOR ACTIONS Events 5 & 6 - Loss of Line 4 and EDG 102 Fails   CREW to Auto-Start
= 4) per N1-0P-42 AND monitors Contacts System Power Control AN D makes notification of the low voltage alarm AND to run a Load Flow Contacts JAF Control Room in an expeditious manner AND informs them of the loss of 115 kV Line 1 INSTRUCTOR ACTIONS! PLANT RESPONSE Event 4 -Loss of Condenser Vacuum When directed by lead examiner, insert malfunction:
* Recognize/report loss of Line 4 Verify the following malfunction automatically
MC01, MAIN CONDENSER AIR INLEAKAGE, FV=18 TRG 3 Main Condenser vacuum lowers Offgas flow rate rises Expected Annunciator:
* Recognize/report start of EDG 103 inserts when the Mode Switch is taken to
A 1-3-4, CONDENSER VACUUM BELOW 24" HG Initial Reactor pressure control may be on Turbine Bypass Valves, but will transition after the scram to the Emergency Condensers Main Condenser vacuum May close MSIVs earlier to control cooldown OPERATOR ACTIONS CREW Recognize/report lowering main condenser vacuum Acknowledge/report annunciators: A1-3-4, CONDENSER VACUUM BELOW 24" HG SRO Acknowledges reports Directs execution of N 1-S0P-25.1, Unplanned Loss of Condenser Vacuum Determines condenser vacuum can NOT be maintained above 22.1" Hgv Directs Turbine trip Determines condenser vacuum can NOT be maintained above 10" Hgv Directs a Reactor Scram Acknowledges scram report Directs entry into N1-S0P-1, Reactor Scram Directs Reactor water level controlled 53-95" with Condensate, Feedwater, and CRD Directs Reactor pressure controlled 800-1000 psig with Emergency Condensers When vacuum approaches 10" Hgv, directs trip of Vacuum Trip 2 When vacuum approaches 7.0" Hgv, directs closing the MSIVs INSTRUCTOR ACTIONS/ PLANT RESPONSE OPERATOR ACTIONS Event 4 continued ATC Note: Initial Reactor pressure control may be on the Turbine Bypass Valves, but will transition soon after the scram to the Emergency Condensers as Main Condenser vacuum degrades. Monitors plant parameters Assists BOP with Turbine trip Places Reactor Mode Switch to SHUTDOWN Provides scram report Performs scram verification actions of N1-S0P-1, Reactor Scram: Confirms all rods inserted Observes Reactor power lowering Places IRMs on range 9 Inserts IRM and SRM detectors Down-ranges IRMs as necessary Verifies main turbine and generator tripped Controls RPV pressure as directed using Emergency Condensers BOP Executes N1-S0P-2S.1, Unplanned Loss of Condenser Vacuum Verifies proper operation of the following: Circ Water System SJAEs Off Gas System Condensate System Turbine Gland Seal System Dispatches operator to check for condenser leakage INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 4 continued BOP continued When the Turbine is tripped, verify TRG automatically MC01, MAIN CONDENSER AIR Main Condenser vacuum lowers quicker Coordinates with A TC to trip Turbine: Depresses AND holds down FEEDWATER RETURN TO NORMAL AFTER HPCI CH 11 and 12 pushbuttons. Depresses UNIT EMERGENCY TRIP pushbutton AND executes N 1-S0P-31.1, Turbine Trip Releases FEEDWATER RETURN TO NORMAL AFTER HPCI CH 11 and 12 push buttons Enters N1-S0P-1 Controls Reactor water level 53-95" using Condensate, Feedwater, and CRD When directed, trips Vacuum Trip 2 and verifies Turbine Bypass Valves closed When directed, closes MSIVs INSTRUCTOR ACTIONSI PLANT RESPONSE Events 5 & 6 -Loss of Line 4 and EDG 102 Fails to Auto-Start Verify the following malfunction automatically inserts when the Mode Switch is taken to SHUTDOWN:
* Recognize/report failure of EDG 102 SHUTDOWN:                                           to auto-start ED01A, 115 kV Line 4 (JAF) Loss of Offsite Power, Delay=1 :30 TRG4 Breaker R40 opens Control Room lights go out Emergency Diesel Generator 103 starts Power is lost to the following major loads:
ED01A, 115 kV Line 4 (JAF) Loss of Offsite Power, Delay=1 :30 TRG4 Breaker R40 opens Control Room lights go out Emergency Diesel Generator 103 starts Power is lost to the following major loads: Recirc pumps Condensate and Feedwater pumps Circulating Water pumps
* Recirc pumps
* Condensate and Feedwater pumps
* Circulating Water pumps
* Service Water pumps Expected Annunciators:
* Service Water pumps Expected Annunciators:
A8-1-3, 115 KV. BUS LOW VOL TAGE A8-1-7, NMP -FITZ 4 R40 TRIP A8-1-8, NMP -FITZ 4 LINE RELAY TRIP Verify the following malfunction is preset: DG04A, DG 102 FAILURE TO AUTO START Emergency Diesel Generator 102 fails to auto-start OPERATOR ACTIONS CREW Recognize/report loss of Line 4 Recognize/report start of EDG 103 Recognize/report failure of EDG 102 to auto-start SRO Acknowledges reports from the crew Directs execution of N 1-S0P-33A 1 Directs start of EDG 102 Directs Reactor water level controlled 53-95" using CRD Enters N1-EOP-5, Secondary Containment Control, on low Reactor Building D/P Exits N1-EOP-5 when Reactor Building D/P is restored INSTRUCTOR ACTIONS/ PLANT RESPONSE OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP Note: The crew may perform an alternate leg of 33A. 1 if they wait for a field report before starting EDG 102. The crew will perform the scripted leg to N 1-S0P-33A.1 once EDG 102 is started. Role Play: If dispatched to investigate EDG 102 auto-start failure, wait 2 minutes, then report that you see no problems with either EDG 102 or Powerboard 102. Report that EDG 102 appears to be in a normal standby condition with no apparent reason for a start failure. Executes N1-S0P-33A.1 May dispatch operator to field to investigate EDG 102 failure Manually starts EDG 102 Verifies start of both Emergency Diesel Generators AND confirms the following has occurred: EDG 102 SUPPLY BKR R-1022 has closed Powerboards 102 AND 16B are energized EDG 103 SUPPLY BKR R-1032 has closed Powerboards 103 AND 17B are energized Answers "Are PB 11 AND 12 energized?" No Answers "Is any EDG running?" Yes Verifies the following: PB 16A-B Tie Bkr R-1 042 is tripped PB 17A-B Tie Bkr R-1052 is tripped Inst. Air Compo (lAC) 11 and 12 in PTL Continues at Page 4, Arrow B Monitors EDG 102 AND 103 KW loading INSTRUCTOR ACTIONSI PLANT RESPONSE Events 5 & 6 continued The EDG load override in N1-S0P-33A.1 will be applicable initially, but may be executed during the Role When dispatched for load reductions, wait minutes, then report Attachment 2, Section 1 reductions are OPERATOR ACTIONS ATC/BOP continued IF EDG KW exceeds 2300 KW (PB 102 or 103 Loading), THEN: Verifies the following: Trips all Containment Spray Raw Water Pumps that are running R-1042 tripped, PB 16 A-B Tie Bkr R-1052 tripped, PB 17 A-B Tie Bkr Verifies Lockouts 86-16 and 86-17 reset Places CRD Pump 11 AND 12 in PTL RBCLC Pump 11,12 AND 13 secured ESW Pump 11 AND 12 secured Place Core Spray and CSTP 111 OR 112 in PTL Place Core Spray and CSTP 121 OR 122 in PTL Operate Containment Sprays as required per N1-EOP-4 Equalize Containment Spray Raw Water Pump KW load (-450 KW) as required AND continue at next step WHILE continuing, sends operator to perform load reductions of Attachment 2, Section 1 Verifies Lockouts 86-16 AND 86-17 reset INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP continued Role When dispatched to check UPS 162 and 172, two minutes, then insert RP21, RPS UPS 162 TROUBLE ANN RP22, RPS UPS 172 TROUBLE ANN FV=reset, TRG28 Then report that UPS 162 and 172 have transferred back to AC input and you have reset alarms. Role When dispatched to restore power to I&C Bus wait two minutes, then insert ED40A, IC Bus 130 NC Supply Breaker From ED40B, IC Bus 130 NO Supply Breaker From 167 A, DT=5, TRG 29 Then report that I&C Bus 130 is re-energized from the maintenance supply. Verifies RBClC Pump 13 started, if available Verifies RBClC Pump 12 started, if required Starts ESW PUMP 11 AND 12 AND monitors equipment temperature listed in N1-S0P-18.1, Tables 18.1 and 18.2 Verifies the following: CRD Pumps 11 AND 12 started, if required, UNLESS secured per override above MG Set 167 transfers back to AC drive UPS 162 AND 172 re-energizes SBC 161 AND 171 re-energizes Re-establishes Rx Bldg. differential pressure as follows: Verifies RB Supply AND Exhaust Fans tripped Closes RB Supply AND Exhaust Isolation Valves Verifies RBEV Train 12 initiated, secures RBEV Train 11 Dispatches operator to restore power to I&C Bus 130 Places FEEDWATER PUMP 11 AND 12 in PTl Verifies RBClC Pump 12 in PTl Verifies ESW Pump 12 in PTl Verifies lAC 11 in PTl INSTRUCTOR ACTIONS! PLANT RESPONSE OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP continued Verifies one CRD Pump running as follows UNLESS secured per override above CRD Pump 12 running CRD Pump 11 in PTL Verifies load reductions of Attachment 2 Section 1 complete Restores power to PB 16A as follows: Trips R-1041, PB 16A Supply Bkr Closes R-1042, PB 16A-B Tie Bkr Verifies RBCLC Pumps 11 OR 13 running IF TSC Power is required, AND PB 16B load is less than 900 amps, THEN Places in ON, NDS-1 disconnect switch (TSC Emergency Power) Restores power to PB 17 A as follows: Trips R-1051, PB 17A Supply Bkr Closes R-1052 PB 17A-B Tie Bkr Verifies lAC 12 started Follows N1-0P-6 for recovery of Spent Fuel Pool cooling requirements INSTRUCTOR ACTIONSI PLANT RESPONSE Events 7. 8 & 9 -Loss of Coolant Accident.
A8-1-3, 115 KV. BUS LOW VOL TAGE A8-1-7, NMP - FITZ 4 R40 TRIP A8-1-8, NMP - FITZ 4 LINE RELAY TRIP Verify the following malfunction is preset:       SRO DG04A, DG 102 FAILURE TO AUTO START
Core Spray Fails to Auto-Start, ECs Fail to Operate from Control Room Verify the following malfunction automatically inserts when Powerboard 16 is crosstied:
* Acknowledges reports from the crew Emergency Diesel Generator 102 fails to auto-start
RR29, RR Loop Rupture on Pump 15 Suction Line, FV=17 TRG5 Drywel/leakage, humidity, temperature and pressure rise Reactor water level and pressure lower Expected Annunciators:
* Directs execution of N 1-S0P-33A 1
H2-4-7, Drywel/ Water Leak Detection Sys K2-4-3, Drywel/ Pressure High-Low F1-1-5, RPS Ch 11 Drywel/ Press High F4-1-4, RPS Ch 12 Drywel/ Press High Verify the following malfunctions are CS06, CS Pumps Failure to Auto EC04A, EC RETURN VALVE FAILS TO EC04B, EC RETURN VALVE FAILS TO Core Spray pumps do NOT auto-start EC Condensate Return Valves will not open OPERATOR ACTIONS CREW Recognize/report degrading Primary Containment parameters Recognize/report lowering Reactor water level and pressure SRO Acknowledges reports Enters N1-EOP-4 due to high Drywell pressure and temperature Enters N1-EOP-2 due to high Drywell pressure and low Reactor water level Directs Containment Spray pumps locked out Acknowledges failure of Core Spray to auto-start Directs start of Core Spray pumps INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 7, 8, & 9 continued SRO continued When Torus pressure exceeds 13 psig or Drywell temperature approaches 300&deg;F: Answers "Below the Containment Spray Initiation Limit?" -Yes Verifies all Recirc pumps are tripped Directs trip of all Drywell cooling fans Directs operation of Containment Spray per 1 attachment 17 CT-1 Evaluates/monitors position on Pressure Suppression Pressure curve Directs Reactor water level control -84" to 95" with CRD and Liquid Poison Transitions to alternate level control leg of N1-EOP-2 Directs ADS bypassed Directs verification of EC initiation Acknowledges EC initiation failure May direct local EC initiation Answers "Are 2 or more Subsystems available?" -Yes (Both loops of Core Spray available) Waits until Reactor water level drops to -84" Answers "Is any Subsystem lined up with a pump running?" -Yes (Both loops of Core Spray running) Answers "Is any injection source lined up with a pump running?" -Yes INSTRUCTOR ACTIONS! PLANT RESPONSE OPERATOR ACTIONS Events 7.8. & 9 continued SRO continued Enters N1-EOP-8, RPV Slowdown: Answers "Are all control rods inserted to at least position Yes Answers "Drywell pressure?" -At or above 3.5 psig May direct EC initiation Answers "Torus water level?" Above 8.0 ft Directs open 4 ERVs CT-2 Verifies injection of entire contents of Liquid Poison tank Directs injection with available systems to restore and maintain Reactor water level above -84 inches CT-3 Directs installation of Core Spray jumpers (N1-EOP-1 attachment
* Directs start of EDG 102
: 4) to allow control of Core Spray IVs Transitions back to normal level control leg of N1-EOP-2 Directs restoration of Reactor water level to 53-95" ATC/BOP Updates crew on Reactor and containment parameters Locks out Containment Spray pumps Recognizes/reports failure of Core Spray to auto-start Starts Core Spray pumps INSTRUCTOR ACTIONS! PLANT RESPONSE Events 7. 8. & 9 continued Role If directed to open 39-05 in the field, wait minutes, then delete malfunction EC04A, insert EC03A, EC RETURN VALVE FAILS OPEN(IV TRG 17 Then report task completion.
* Directs Reactor water level controlled 53-95" using CRD
Role If directed to open 39-05 in the field, wait minutes, then delete malfunction EC04B, insert EC03B, EC RETURN VALVE FAILS OPEN(IV TRG 18 Then report task completion.
* Enters N1-EOP-5, Secondary Containment Control, on low Reactor Building D/P
OPERATOR ACTIONS ATC/BOP continued Maximizes RPV injection with CRD and Liquid Poison When Torus pressure exceeds 13 psig or drywell temperature approaches 300&deg;F: Verifies all Recirc pump are tripped Trips all Drywell cooling fans Initiates Containment Spray per N1-EOP-1 attachment 17: CT-1 Verifies started two Containment Spray pumps (111 or 122 preferred) May start additional Containment Spray and Containment Spray Raw Water pumps as necessary Bypasses ADS Verifies EC initiation Recognizes/reports failure of 05 and 39-06 to open May direct operator to open 39-05 and/or 39-06 in field May secure ECs for pressure control When Reactor water level drops below -84": May initiates ECs Opens 4 ERVs CT-2 INSTRUCTOR ACTIONSI PLANT RESPONSE Events 7, 8, & 9 continued Role If requested to lineup Firewater to Feedwater, five minutes, then insert FP04, FIRE WTR TO FW BLOCKING TRG21 Then report Firewater is lined up to Feedwater.
* Exits N1-EOP-5 when Reactor Building D/P is restored
Modify the remote as requested to throttle flow. If requested to throttle Containment Spray Raw Water 111 discharge valve, wait 3 minutes, then insert remote: CT03A, CT Raw Water Pump 111 Disch. Throttle Valve 93-14, FV=10 TRG 22 Then report the valve is 5 turns open. Modify the remote as requested to throttle flow. If requested to take local manual control of a Feedwater FCV, then wait 5 minutes and insert the appropriate remote: FW25, MANUAL OPER. FW FCV-11, FV=O TRG23 FW26, MANUAL OPER. FW FCV-12, FV=O TRG24 FW27, MANUAL OPER. FW FCV-i3, FV=O TRG25 Then report the appropriate FCV is pinned and fully closed. Modify the remote as requested to throttle flow. OPERATOR ACTIONS ATC/BOP continued Verifies Liquid Poison injection to inject entire contents of Liquid Poison tank Injects with available systems to restore and maintain Reactor water level above -84" CT-3 Bypasses Core Spray IV interlocks per N1-EOP-1 Att 4 by installing six jumpers (17, 18, 19,24,25,26) inside PanelN Throttles Core Spray IVs as necessary to control Reactor water level Restores Reactor water level to 53-95" INSTRUCTOR PLANT RESPONSE OPERATOR Terminating Cues: RPV Slowdown in progress Reactor water level controlled above top of active fuel Containment pressure and temperature controlled in accordance with N1-EOP-4}}
 
INSTRUCTOR ACTIONS/
PLANT RESPONSE                                         OPERATOR ACTIONS Events 5 & 6 continued                                 ATC/BOP
* Executes N1-S0P-33A.1 Note:
* May dispatch operator to field to The crew may perform an alternate leg of N1-S0P        investigate EDG 102 failure 33A. 1 if they wait for a field report before starting
* Manually starts EDG 102 EDG 102. The crew will perform the scripted leg to
* Verifies start of both Emergency N 1-S0P-33A.1 once EDG 102 is started.                   Diesel Generators AND confirms the following has occurred:
Role Play:                                              o    EDG 102 SUPPLY BKR R-1022 If dispatched to investigate EDG 102 auto-start               has closed failure, wait 2 minutes, then report that you see no     o    Powerboards 102 AND 16B are problems with either EDG 102 or Powerboard 102.               energized Report that EDG 102 appears to be in a normal           o    EDG 103 SUPPLY BKR R-1032 standby condition with no apparent reason for a               has closed start failure.                                           o    Powerboards 103 AND 17B are energized
* Answers "Are PB 11 AND 12 energized?" No
* Answers "Is any EDG running?" Yes
* Verifies the following:
o    PB 16A-B Tie Bkr R-1 042 is tripped o    PB 17A-B Tie Bkr R-1052 is tripped o    Inst. Air Compo (lAC) 11 and 12 in PTL
* Continues at Page 4, Arrow B
* Monitors EDG 102 AND 103 KW loading
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                    OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP continued Note:
* IF EDG KW exceeds 2300 KW (PB The EDG load override in N1-S0P-33A.1 will not        102 or 103 Loading), THEN:
be applicable initially, but may be executed later  o    Verifies the following:
during the LOCA.
* Trips all Containment Spray Raw Water Pumps that are running
* R-1042 tripped, PB 16 A-B Tie Bkr
* R-1052 tripped, PB 17 A-B Tie Bkr
* Verifies Lockouts 86-16 and 86-17 reset
* Places CRD Pump 11 AND 12 in PTL
* RBCLC Pump 11,12 AND 13 secured
* ESW Pump 11 AND 12 secured o    Place Core Spray and CSTP 111 OR 112 in PTL o    Place Core Spray and CSTP 121 OR 122 in PTL o    Operate Containment Sprays as required per N1-EOP-4 o    Equalize Containment Spray Raw Water Pump KW load (-450 KW) as required AND continue at next Role Play:                                                step When dispatched for load reductions, wait 4
* WHILE continuing, sends operator to minutes, then report Attachment 2, Section 1 load    perform load reductions of Attachment reductions are complete.                              2, Section 1
* Verifies Lockouts 86-16 AND 86-17 reset
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                   OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP continued
* Verifies RBClC Pump 13 started, if available
* Verifies RBClC Pump 12 started, if required Role Play:
* Starts ESW PUMP 11 AND 12 AND When dispatched to check UPS 162 and 172, wait      monitors equipment temperature listed two minutes, then insert remotes:                  in N1-S0P-18.1, Tables 18.1 and 18.2
* Verifies the following:
RP21, RPS UPS 162 TROUBLE ANN RESET,               o    CRD Pumps 11 AND 12 started, if FV=reset                                                required, UNLESS secured per RP22, RPS UPS 172 TROUBLE ANN RESET,                    override above FV=reset, DT=10                                    o    MG Set 167 transfers back to AC TRG28         drive Then report that UPS 162 and 172 have               o    UPS 162 AND 172 re-energizes transferred back to AC input and you have reset     o    SBC 161 AND 171 re-energizes alarms.
* Re-establishes Rx Bldg. differential pressure as follows:
o    Verifies RB Supply AND Exhaust Role Play:                                              Fans tripped When dispatched to restore power to I&C Bus 130,    o    Closes RB Supply AND Exhaust wait two minutes, then insert remotes:                  Isolation Valves o    Verifies RBEV Train 12 initiated, ED40A, IC Bus 130 NC Supply Breaker From PB              secures RBEV Train 11 13B,FV=open
* Dispatches operator to restore power ED40B, IC Bus 130 NO Supply Breaker From PB        to I&C Bus 130 167A, DT=5, FV=close
* Places FEEDWATER PUMP 11 AND TRG 29   12 in PTl Then report that I&C Bus 130 is re-energized from
* Verifies RBClC Pump 12 in PTl the maintenance supply.
* Verifies ESW Pump 12 in PTl
* Verifies lAC 11 in PTl
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE        OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP continued
* Verifies one CRD Pump running as follows UNLESS secured per override above o    CRD Pump 12 running o    CRD Pump 11 in PTL
* Verifies load reductions of Attachment 2 Section 1 complete
* Restores power to PB 16A as follows:
o    Trips R-1041, PB 16A Supply Bkr o    Closes R-1042, PB 16A-B Tie Bkr
* Verifies RBCLC Pumps 11 OR 13 running
* IF TSC Power is required, AND PB 16B load is less than 900 amps, THEN Places in ON, NDS-1 disconnect switch (TSC Emergency Power)
* Restores power to PB 17A as follows:
o    Trips R-1051, PB 17A Supply Bkr o    Closes R-1052 PB 17A-B Tie Bkr
* Verifies lAC 12 started
* Follows N1-0P-6 for recovery of Spent Fuel Pool cooling requirements
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                   OPERATOR ACTIONS Events 7. 8 & 9 - Loss of Coolant Accident.      CREW Core Spray Fails to Auto-Start, ECs Fail to
* Recognize/report degrading Primary Operate from Control Room                          Containment parameters Verify the following malfunction automatically
* Recognize/report lowering Reactor inserts when Powerboard 16 is crosstied:           water level and pressure RR29, RR Loop Rupture on Pump 15 Suction Line, FV=17 TRG5 Drywel/leakage, humidity, temperature and pressure rise Reactor water level and pressure lower Expected Annunciators:
H2-4-7, Drywel/ Water Leak Detection Sys K2-4-3, Drywel/ Pressure High-Low F1-1-5, RPS Ch 11 Drywel/ Press High F4-1-4, RPS Ch 12 Drywel/ Press High Verify the following malfunctions are preset:    SRO CS06, CS Pumps Failure to Auto Start
* Acknowledges reports EC04A, EC RETURN VALVE FAILS TO OPEN(lV
* Enters N1-EOP-4 due to high Drywell 39-05)                                            pressure and temperature EC04B, EC RETURN VALVE FAILS TO OPEN(IV
* Enters N1-EOP-2 due to high Drywell 39-06)                                            pressure and low Reactor water level Core Spray pumps do NOT auto-start
* Directs Containment Spray pumps EC Condensate Return Valves will not open          locked out
* Acknowledges failure of Core Spray to auto-start
* Directs start of Core Spray pumps
 
INSTRUCTOR ACTIONSI PLANT RESPONSE            OPERATOR ACTIONS Events 7, 8, & 9 continued SRO continued
* When Torus pressure exceeds 13 psig or Drywell temperature approaches 300&deg;F:
* Answers "Below the Containment Spray Initiation Limit?" - Yes
* Verifies all Recirc pumps are tripped
* Directs trip of all Drywell cooling fans
* Directs operation of Containment Spray per N1-EOP 1 attachment 17 CT-1
* Evaluates/monitors position on Pressure Suppression Pressure curve
* Directs Reactor water level control
                            -84" to 95" with CRD and Liquid Poison
* Transitions to alternate level control leg of N1-EOP-2
* Directs ADS bypassed
* Directs verification of EC initiation
* Acknowledges EC initiation failure
* May direct local EC initiation
* Answers "Are 2 or more Subsystems available?" - Yes (Both loops of Core Spray available)
* Waits until Reactor water level drops to -84"
* Answers "Is any Subsystem lined up with a pump running?" - Yes (Both loops of Core Spray running)
* Answers "Is any injection source lined up with a pump running?" - Yes
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE           OPERATOR ACTIONS Events 7.8. & 9 continued SRO continued
* Enters N1-EOP-8, RPV Slowdown:
* Answers "Are all control rods inserted to at least position 04?"
Yes
* Answers "Drywell pressure?" - At or above 3.5 psig
* May direct EC initiation
* Answers "Torus water level?"
Above 8.0 ft
* Directs open 4 ERVs CT-2
* Verifies injection of entire contents of Liquid Poison tank
* Directs injection with available systems to restore and maintain Reactor water level above -84 inches CT-3
* Directs installation of Core Spray jumpers (N1-EOP-1 attachment 4) to allow control of Core Spray IVs
* Transitions back to normal level control leg of N1-EOP-2
* Directs restoration of Reactor water level to 53-95" ATC/BOP
* Updates crew on Reactor and containment parameters
* Locks out Containment Spray pumps
* Recognizes/reports failure of Core Spray to auto-start
* Starts Core Spray pumps
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                       OPERATOR ACTIONS Events 7. 8. & 9 continued                           ATC/BOP continued
* Maximizes RPV injection with CRD and Liquid Poison
* When Torus pressure exceeds 13 psig or drywell temperature approaches 300&deg;F:
* Verifies all Recirc pump are tripped
* Trips all Drywell cooling fans
* Initiates Containment Spray per N1-EOP-1 attachment 17:
CT-1
* Verifies started two Containment Spray pumps (111 or 122 preferred)
* May start additional Containment Spray and Containment Spray Raw Water Role Play:                                                      pumps as necessary If directed to open 39-05 in the field, wait 2
* Bypasses ADS minutes, then delete malfunction EC04A, then
* Verifies EC initiation insert malfunction:
* Recognizes/reports failure of 39 EC03A, EC RETURN VALVE FAILS OPEN(IV 39 05 and 39-06 to open 05)
* May direct operator to open 39-05 TRG 17 and/or 39-06 in field Then report task completion.
* May secure ECs for pressure control Role Play:
* When Reactor water level drops below If directed to open 39-05 in the field, wait 2
                                                        -84":
minutes, then delete malfunction EC04B, then
* May initiates ECs insert malfunction:
* Opens 4 ERVs EC03B, EC RETURN VALVE FAILS OPEN(IV 39 CT-2 06)
TRG 18 Then report task completion.
 
INSTRUCTOR ACTIONSI PLANT RESPONSE                                      OPERATOR ACTIONS Events 7, 8, & 9 continued                          ATC/BOP continued
* Verifies Liquid Poison injection to Role Plays:                                          inject entire contents of Liquid Poison If requested to lineup Firewater to Feedwater, wait  tank five minutes, then insert remote:
* Injects with available systems to FP04, FIRE WTR TO FW BLOCKING VLVS,                  restore and maintain Reactor water FV=100                                                level above -84" TRG21                                        CT-3 Then report Firewater is lined up to Feedwater.
* Bypasses Core Spray IV interlocks per Modify the remote as requested to throttle flow.      N1-EOP-1 Att 4 by installing six jumpers (17, 18, 19,24,25,26) inside If requested to throttle Containment Spray Raw        PanelN Water 111 discharge valve, wait 3 minutes, then
* Throttles Core Spray IVs as necessary insert remote:                                        to control Reactor water level CT03A, CT Raw Water Pump 111 Disch. Throttle
* Restores Reactor water level to 53-95" Valve 93-14, FV=10 TRG 22 Then report the valve is 5 turns open. Modify the remote as requested to throttle flow.
If requested to take local manual control of a Feedwater FCV, then wait 5 minutes and insert the appropriate remote:
FW25, MANUAL OPER. FW FCV-11, FV=O TRG23 FW26, MANUAL OPER. FW FCV-12, FV=O TRG24 FW27, MANUAL OPER. FW FCV-i3, FV=O TRG25 Then report the appropriate FCV is pinned and fully closed. Modify the remote as requested to throttle flow.
 
INSTRUCTOR ACTIONS!
PLANT RESPONSE                                OPERATOR ACTIONS Terminating Cues:
* RPV Slowdown in progress
* Reactor water level controlled above top of active fuel
* Containment pressure and temperature controlled in accordance with N1-EOP-4}}

Latest revision as of 04:11, 6 February 2020

Final Operating Exam (Sections a, B, and C) (Folder 3)
ML13154A270
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/08/2013
From:
Nine Mile Point
To: Todd Fish
Operations Branch I
Jackson D
Shared Package
ML12356A123 List:
References
TAC U01861
Download: ML13154A270 (196)
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Text

NRC JPM RO C001 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Perform NI-ST-DO DAILY CHECKS (Partial) Revision: NRC 2013 Task Number: NI A Approvals:

NIA - Exam Security /

General Supervisor '" Date General Supervisor Date Operations Training (Designee) Operations (Designee)

Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)

TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: _~_ _ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant _ _---'--"--__ Simulator Expected Completion Time: 20 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: _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC 2013 JPM RO COOl May 2013

Recommended Start Location: (Completion time based on the start location)

Simulator Simulator Set-up:

1. Initialize Simulator to IC-166
2. Verify the following overrides are set:
a. 5M80A03550 73.00
b. 5M81A03560 75.00
c. 5Ml18A03860 = 76.00
d. 5Ml16A03840 = 68.00
e. 5ARITSIA031000 = 68.00
f. 13MIA042680 69.00
g. 9M53A051270 70.50
3. Take the simulator to Run, and then back to Freeze
4. Verify average DryweU temperature is less than 130°F
5. Verify total Recirc flow is 38 Mlbmlhr
6. Verify FWLC is selected to column 11
7. Tum off PI monitor Directions to the InstructorlEvaluator:

Prior to performance ofthis 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 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, the use of applicable methods of verification and checking are expected.

Therefore, either another individual or I will act as the independent verifier or peer checker.

NRC 2013 JPM RO COOl May 2013

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a
2. During Evaluated JPM:
  • Self checking shall be demonstrated.
3. During Training JPM:
  • Self checking shall be demonstrated.
  • Peer checking shall be demonstrated.

References:

1. NUREG 1123,2.1.18, RO 3.6
2. Nl-ST-DO Tools and Equipment:

Calculator Task Standard: Control room RPV water level readings are taken for Nl-ST-DO. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.

Initial Conditions:

1. The plant is operating at approximately 15% power.
2. Nl-ST-DO, Daily Checks, is in progress.
3. The provided printout shall be used to determine computer point and PI data.
4. Instructor to ask the operator for any questions.

Initiating cue:

"(Operator's name), obtain the instrument readings needed from control room panels to complete Nl-ST-DO Attachment 4 sections 5.0 and 6.0 only, then complete section 8.4 in the body of the procedure. When completed, report findings and provide completed sections to SRO."

I Performance Steps I Standard Grade

1. Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTT~E ________

2. Obtain a copy of the reference procedure and N-ST-DO obtained, sections 5.0 and 6.0 SatlUnsat review/utilize the correct section referenced Note: Completed NI-ST-DO is attached as JPM key. Small differences in recorded values may occur due to instrument interpolation.

NRC 2013 JPM RO COOl May 2013

I Performance Steps I Standard Grade

3. Records section 5.0 readings Records Reactor Recirc Pump Inlet SatlUnsat Temperature readings on Attachment 4 Section 5.0
4. Compare Recirc Pump Inlet Temperature Compares readings and determines readings SatlUnsat readings and determines readings within within 15°P of each other 15°P Checks YES block in Section 5.0, indicating PasslFail the maximum difference in loop temperatures is<15°P
5. Record section 6.0 readings Records RPV water level readings on SatlUnsat Attachment 4 section 6.0 Cue: Another operator has completed the required Independent Verifications.
6. Record Total Recirc Plow Records total recirc flow in the correct box on SatlUnsat Attachment 4 section 6.0
7. Determines average Drywell temperature Observes average Drywell temperature is less SatlUnsatlNA than 125°p Note: Since Yarway level indicator deviation is less than 4 inches, Drywell temperature reading is not necessary for task completion.
8. Analyzes Yarway level indicator deviation Determines Yarway level indicator deviation PasslFail is less than the 6 inch limit Note: This may be evidenced by the lack of a report to the contrary.
9. Analyzes GEMAC level indicator deviation Determines GEMAC level indicator deviation PasslFaii is greater than the 6 inch limit
10. Determines GEMAC level indicators are Checks !NOP option in step 8.4 PasslFaii inoperable
11. Provides completed sections to SRO and Proper communications used (GAP-OPS-Ol) SatlUnsat informs of out of spec readings TERMINATING CUE: Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.

RECORDSTOPTIME_________

NRC 2013 JPM RO COO 1 May 2013

Initial Conditions:

1. The plant is operating at approximately 15% power.
2. N1-ST-DO, Daily Checks, is in progress.
3. The provided printout shall be used to determine computer point and PI data.

Initiating cue:

"(Operator's name), obtain the instrument readings needed from control room panels to complete N1-ST-DO Attachment 4 sections 5.0 and 6.0 only, then complete section 8.4 in the body of the procedure. When completed, report findings and provide completed sections to SRO."

NRC 2013 JPM RO COOl May 2013

NRC JPM RO C002 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Perfonn Heat-Up Rate Detennination Revision: NRC 2013 Task Number: N/A Approvals:

I :s/~(t2 NIA - Exam Security I General Supervisor Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NIA - Exam Security I Configuration Control Date Perfonner:_ _ _ _ _ _ _ _ _ _ _ _ _ _,(RO/SRO)

TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: Perfonn Evaluation Location: 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 offail shall be given if any critical step is graded as fail. Any grade of un sat or individual competency area unsat requires a comment.

Comments:

Evaluator ...,.0.11........ .________________ Date:._ _ _ _ _ __

NRC 2013 JPM RO C002 May 2013

Recommended Start Location: (Completion time based on the start location)

Classroom Set-up:

1. Prepare a picture ofRRP 11 suction temperature gauge indicating approximately 535°F.
2. Prepare NI-OP-43A Attachment 18 with the following data:

DatelTime RRP Suction Temp DT/I5 min DT115 min Limits Heatup Rate Limits 5111130900 350 N/A N/A N/A 511113 0915 370 20 SAT NIA 5/1113 0930 380 10 SAT N/A 5/1113 0945 400 20 SAT NIA 511113 1000 415 15 SAT SAT 511/13 1015 435 20 SAT SAT 5/1/13 1030 470 5/1/13 1045 490 511113 1100 Directions to the InstructorlEvaluator:

None 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 I concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected.

Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor I Evaluator:

NRC 2013 JPM RO C002 May 2013

1. Critical steps are identified in grading areas PasslFaii.
2. During Evaluated JPM:
  • Self checking shall be demonstrated.
3. During Training JPM:
  • Self checking shall be demonstrated.
  • Peer checking shall be demonstrated.

References:

1. NUREG 1123,2.1.7, RO 4.4
2. NI-0P-43A Attachment 18 Tools and Equipment:

Calculator Task Standard: Current plant heat-up data taken per NI-OP-43A Attachment 18. Current and past heat-up rates calculated. Out of spec heat-up rate is identified to SRO.

Initial Conditions:

1. A plant startup is in progress.
2. Current time is 1100 on 5/1/13.
3. N 1-0P-43A Attachment 18 is provided with heat-up data for the last hour.
4. All RRP suction temperature readings have been taken from Recirc loop 11.
5. The provided picture shows the current Recirc loop 11 suction temperature indication.
6. Instructor to ask the operator for any questions.

Initiating cue:

"(Operator's name), obtain the time 1100 reading for NI-0P-43A Attachment 18, then complete the attachment for times 1030, 1045, and 1100. When completed, report findings and provide completed sections to SRO."

1. Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTT~E _______

2. Obtain a copy of the reference procedure and Nl-OP-43A Attachment 18 SatlUnsat review/utilize the correct section Note: Completed NI-OP-43A is attached as JPM key. Small differences in recorded values may occur due to instrument interpolation.

NRC 2013 JPM RO C002 May 2013

I Performance Steps I Standard Grade

3. Records current RRP suction temperature Records current RRP suction temperature PasslFaii (535°F +/- 10°F)
4. Calculates and records AT115 min for times Calculates and records AT115 min: Sat/Unsat 1030-1100 1030: 470°F - 435°F 35°F 1045: 490°F - 470°F 20°F 1100: 535°F - 490°F 45°F (+/- 10°F)
5. Analyzes and records AT Limits for AT/I5 Analyzes and records AT Limits for AT115 SatlUnsat min min:

1030: UNSAT 1045: SAT 1100: UNSAT

6. Calculates hourly ATs for times 1030-1100 Calculates ATs: SatlUnsatlNA Note: There is no column on NI-0P-43A to 1030: 470°F - 380°F 90°F record this step. It is provided to document an 1045: 4900 p - 400°F 90°F intennediate step taken to arrive at JPM Step #7. 1100: 535°F - 415°F 120°F Ifthe candidate does not provide these intermediate values, the JPM step may be graded "NA".
7. Analyzes and records Heat-up Rate Limits Analyzes and records Heat-Up Rate Limits:

1030: SAT Pass/Fail 1045: SAT Pass/Fail 1100: UNSAT Pass/Fail

8. Provides completed sections to SRO and Proper communications used (GAP-OPS-Ol) SatlUnsat infonns of out of spec readings TERMINATING CUE: Control room reading taken. Heat-up rates are calculated. Results are provided to SRO.

RECORDSTOPTIME_________

NRC 2013 JPM RO C002 May 2013

Initial Conditions:

1. A plant startup is in progress.
2. Current time is 1100 on 5/1/13.
3. NI-0P-43A Attachment 18 is provided with heat-up data for the last hour.
4. All RRP suction temperature readings have been taken from Recirc loop 11.
5. The provided picture shows the current Recirc loop 11 suction temperature indication.

Initiating cue:

"(Operator's name), obtain the time 1100 reading for NI-0P-43A Attachment 18, then complete the attachment for times 1030, 1045, and 1100. When completed, report findings and provide completed sections to SRO."

NRC 2013 JPM RO C002 May 2013

NRCJPM ROEP Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Conduct Alert Emergency Announcement and Evacuation Revision: NRC 2013 Task Number: NIA Approvals:

NIA - Exam Security General Supervisor Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NIA - Exam Security Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _(RO)

TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: Perform Evaluation Location: Simulator Expected Completion Time: 10 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: _ _ _ __ Completion 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 2013 JPM RO EP May 2013

Recommended Start Location: Simulator Simulator Set-up: N!A Directions to the InstructorlEvaluator:

This JPM may be conducted anywhere a GAI-tronics station (with alarms) is located.

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.

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:

1. Critical steps are identified as PasslFaii.
2. During Evaluated JPM:
  • Self-verification shall be demonstrated.
3. During Training JPM:
  • Self-verification shall be demonstrated.

References:

1. NUREG 1123,2.4.43, RO 3.2
2. EPIP-EPP-18 Tools and Equipment:

None Task Standard: Alert emergency announcement is made.

NRC 2013 JPM RO EP May 2013

Initial Conditions:

1. The Shift Manager has declared an Alert emergency condition due to high Drywell pressure.
2. Ask the operator for any questions.

Initiating cue:

"(Operator's name), make the provided EPIP-EPP-18 attachment 2 Emergency Announcement."

I Performance Steps I Standard Grade

1. Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ot)

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTUME _______

2. Place GAI-tronics in MERGE Places GAI-tronics in MERGE by toggling PasslFail MERGE/ISOLATE switch to MERGE
3. Sound the appropriate alarm Sounds the Evacuation Alarm by depressing PasslFaii EV AC pushbutton
4. Stop the alarm Stops the Evacuation Alarm by depressing SatlUnsat OFF pushbutton after approximately 10 seconds
5. Announce checked items Holds GAI-tronics broadcast pushbutton PasslFail while saying:

"Attention, attention, all personneL This is a drilL Nine Mile Point Unit 1 is experiencing an Alert emergency condition due to high Drywell pressure. All Emergency Response Organization personnel are to report to their Emergency Response Facilities and card in.

All personnel not assigned emergency response duties shall evacuate the Protected Area and report to the P-Building. Remain at this location until further notice. Personnel in protective clothing should leave the area removing PCs as indicated at the step off pad.

I repeat, this is a drill."

Notes:

  • If Examiner wishes not to broadcast, holding the broadcast pushbutton may be discussed/simulated.
  • The announcement may differ slightly between Candidates, however the important points must all be covered.

NRC 2013 JPM RO EP -3 May 2013

6. Repeat alarm Sounds the Evacuation Alarm by depressing SatlUnsat EV AC pushbutton
7. Stops alarm Stops the Evacuation Alarm by depressing SatlUnsat OFF pushbutton after approximately 10 seconds
8. Repeat announcement Holds GAI-tronies broadcast pushbutton SatlUnsat while saying:

"Attention, attention, all personnel. This is a drill. Nine Mile Point Unit 1 is experiencing an Alert emergency condition due to high Drywell pressure. All Emergency Response Organization personnel are to report to their Emergency Response Facilities and card in.

All personnel not assigned emergency response duties shall evacuate the Protected Area and report to the P-Building. Remain at this location until further notice. Personnel in protective clothing should leave the area removing PCs as indicated at the step off pad.

I repeat, this is a drill."

Notes:

  • If Examiner wishes not to broadcast, holding the broadcast pushbutton may be discussed/simulated.
  • The announcement may differ slightly between Candidates, however the important points must all be covered.

TERMINATING CUE: Alert emergency announcement is made.

RECORDSTOPTIME_________

NRC 2013 JPM RO EP May 2013

Initial Conditions:

1. The Shift Manager has declared an Alert emergency condition due to high Drywell pressure.

Initiating cue:

"(Operator's name), make the provided EPIP-EPP-18 attachment 2 Emergency Announcement. "

NRC 2013 JPM RO EP May 2013

NRC JPM RO-SRO EC Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

RPS Manual Scram Electrical Print Reading Revision: NRC 2013 Task Number: NtA Approvals:

NtA - Exam Security General Supervisor Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NtA - Exam Security Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _(RO/SRO)

TrainerlEvaluator:._ _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: Perform Evaluation Location: 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 offail shall be given if any critical step is graded as fail. Any grade ofunsat or individual competency area unsat requires a comment.

Comments:

Evaluator . ." f",u....... Date:_ _ _ _ _ __

NRC 2013 JPM RO-SRO EC May 2013

Recommended Start Location: Classroom Simulator Set-up: NIA Directions to the InstructorlEvaluator:

Make available a set of electrical prints. When the Candidate identifies the correct print, provide them with another copy of the print so that they may mark it up.

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.

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 additional/concurrent verifier.

Notes to Instructor / Evaluator:

1. Critical steps are identified as PasslFaii.
2. During Evaluated JPM:
  • Self-verification shall be demonstrated.
3. During Training JPM:
  • Self-verification shall be demonstrated.

References:

1. NUREG 1123,2.2.41, RO 3.5
2. C-19859-C Sheet 7 Tools and Equipment:

None Task Standard: Relays and contacts affected by depressing RPS 12 manual scram pushbutton are identified on station electrical drawings and operation is explained. For SRO candidates, additionally identifY the surveillance requirements for testing the RPS 12 manual scram pushbutton and the Technical Specification impact if the pushbutton becomes inoperable.

NRC 2013 JPM RO-SRO EC May 2013

Initial Conditions:

1. None.
2. Ask the operator for any questions.

Initiating cue:

"(Operator's name), using station electrical prints, explain how depressing the RPS 12 manual scram pushbutton on E console results in an RPS channel 12 half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action."

1. Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME ________

2. Obtain a copy ofthe necessary electrical print Obtains the following documents, as needed: SatlUnsati
  • Drawing Index, if needed NA
  • Drawing C-19859-C Sheet 7 Note: When the Candidate identifies the correct print, provide them with another copy of the print so that they may mark it up.
3. Using C-19859-C Sheet 7, locates RPS 12 Locates RPS 12 manual scram pushbutton PasslFail manual scram pushbutton (1 S28) on C-19859-C Sheet 7 near drawing coordinate E-6 Note:

This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.

4. Using C-19859-C Sheet 7, identifies relay Locates relay 12K55 on C-19859-C Sheet 7 PasslFail 12K55 near drawing coordinate E-7 Note:

This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.

NRC 2013 JPM RO-SRO EC May 2013

I Performance Steps I Standard Grade

5. Using C-19859-C Sheet 7, identifies contacts Locates contact 12K55 on C-19859-C Sheet 7 PasslFaii 12K55 near drawing coordinates F-2, R-2, J-2, and L-2 Note:

This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.

Note:

The candidate may also identify the contact near drawing coordinate N-2. This is satisfactory but not required, as the task did not require discussion of the backup scram.

6. Using C-19859-C Sheet 7, identifies Locates relays/solenoids 305-139(B) on C PasslFail relays/solenoids 305-139(B) 19859-C Sheet 7 near drawing coordinates F 5/6 through M-5/6 Notes:
  • This may be identified by either marking on the electrical print or writing the electrical print number and location on the response sheet.
  • The candidate does not have to identify all eight solenoids/relays on this sheet, as long as a representative sample is identified and some indication is given that there are multiple solenoids/relays.
7. Describes how depressing the RPS 12 Describes the following: PasslFail manual scram pushbutton on E console
  • Relay 12K55 de-energizing causes contacts 12K55 to open.
  • Contacts 12K55 opening causes solenoid/relay 305-139(B) to de-energize at each RCU.

Notes:

The candidate does not have to match this description word-for-word, but must include all concepts in their description.

NRC 2013 JPM RO-SRO EC May 2013

Additional SRO Only Cue:

Provide SRO candidates the additional SRO only cue sheet and direct them to determine:

  • the surveillance requirement for testing the RPS 12 manual scram pushbutton and
8. SRO Only: Determines the surveillance Determines the surveillance requirement for Pass/Fail requirement for testing the RPS 12 manual testing the RPS 12 manual scram pushbutton scram pushbutton. is weekly.
9. SRO Only: Determines the Technical Determines Technical Specification table Pass/Fail Specification impact if the RPS 12 manual 3.6.2.a item (1) is not met.

scram pushbutton becomes inoperable.

Determines Technical Specification 3.6.2.a.(l) requires control rods to be inserted OR Determines Technical Specification 3 .6.2.a.( 1) requires placing the manual scram circuitry in a tripped condition.

TERMINATING CUE: Relays and contacts affected by depressing RPS 12 manual scram pushbutton are identified on station electrical drawings and operation is explained.

RECORDSTOPTIME_________

NRC 2013 JPM RO-SRO EC May 2013

Initiating cue:

"(Operator's name), using station electrical prints, explain how depressing the RPS 12 manual scram pushbutton on E console results in an RPS channel 12 half scram. You may mark the provided prints and/or write the explanation on this sheet. Identify the electrical components that accomplish this action."

NRC 2013 JPM RO-SRO EC May 2013

Additional SRO Only Cue Determine the following:

  • the surveillance requirement for testing the RPS 12 manual scram pushbutton and

NRC 2013 JPM RO-SRO EC May 2013

NRC JPM SRO C001 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Review NI-ST-DO DAILY CHECKS (Partial) Revision: NRC 2013 Task Number: N/A Approvals:

N/A - Exam Security I General S u p e r v i s o r ' General Supervisor Date Operations Training (Designee) Operations (Designee)

NIA - Exam Security I Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _(SRO)

TrainerlEvaluator:--------------------

Evaluation Method: _--"X'-"--__ Perform _______ Simulate Evaluation Location: - - - - Plant X

"--"'--- Simulator IClassroom Expected Completion Time: 20 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: ________________________

NRC 2013 JPM SRO COO 1 May 2013

Recommended Start Location: (Completion time based on the start location)

Simulator Simulator Set-up:

N/A Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before Every JPM Performance:

For the performance ofthis 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 I concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected.

Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor I Evaluator:

1. Critical steps are identified in grading areas PasslFail.
2. During Evaluated JPM:
  • Self checking shall be demonstrated.
3. During Training JPM:
  • Self checking shall be demonstrated.
  • Peer checking shall be demonstrated.

References:

1. NUREG 1123,2.1.7, SRO 4.7
2. NI-ST-DO
3. Technical Specifications NRC 2013 JPM SRO COO 1 May 2013

Tools and Equipment:

Provide copy ofNl-ST-DO with Attachment 4 section 6.0 and step 8.4 completed with the following values: section 6.0:

Low-Low Level Alarms - Checked "NO" Feedwater Level Column - Checked "11" E-Panel Vessel Level Indicator - 72" K-Panel Vessel Level Indicator -72" K-Panel Flange Level Indicator - DOWNSCALE Reactor Vessel Level Recorder - 71 "

Wide Range Level Indicator 7' GEMAC Level Column (Ch 11112) 71" / 79" GEMAC Level Computer Points (Ch 11112) -71.344" / 79.051" Pi Calculated GEMAC level column difference 7.680" RPS Level Column (Ch 11112) 73"/76" Yarway (RPS) Level Column 73.125"/75.763" Pi Calculated Yarway level column difference - 2.770" GEMAC variance - 8" Computer point variance -7.707" Total Recirc Flow - 38.0 Mlbmlhr Step 8.4:

Check "Pi-Calculated GEMAC Level Delta" Check "Acceptable Range" Task Standard: Control room RPV water level instrument surveillance per NI-ST-DO is reviewed. Out of spec results are identified and the appropriate Technical Specification is determined.

Initial Conditions:

I. The plant is operating at approximately 67% power.

2. NI-ST-DO, Daily Checks, is in progress.
3. Operators have completed the RPV water level instrument readings.
4. Instructor to ask the operator for any questions.

Initiating cue:

"(Operator's name), perform SRO review of the following section ofNl-ST-DO:

  • Attachment 4 section 6.0
  • Step 8.4 When completed, report findings to the Examiner."

NRC 2013 JPM SRO COO 1 May 2013

I Performance Steps I Standard Grade

1. Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTT~E ________

2. Obtain a copy of the reference procedure and NI-ST-DO obtained SatlUnsat review/utilize the correct section
3. Review Attachment 4 section 6.0 readings Reviews Attachment 4 section 6.0 readings SatlUnsat and Step 8.4
4. Identifies error in Step 8.4 Identifies that GEMAC Level Column PasslFail Variance is in the !NOP range Cue:

If Candidate asks for prior readings for comparison, or for Engineering evaluation, report that plant data indicates GEMAC 11 is trending normally and GEMAC 12 indicates higher than expected.

5. Determines GEMAC 12 level indicator is Determines GEMAC 12 level indicator is PasslFail inoperable inoperable
6. Determines Technical Specification impact Determines a 15 day LCO applies per PasslFail Technical Specification 3.l.8
7. Provides completed sections to Examiner Proper communications used (GAP-OPS-Ol) SatlUnsat and informs of out of spec readings TERMINATING CUE: Control room RPV water level instrument surveillance per Nl-ST-DO is reviewed. Out of spec results are identified and the appropriate Technical Specification is determined.

RECORDSTOPTIME_________

NRC 2013 JPM SRO COOl May 2013

Initial Conditions:

1. The plant is operating at approximately 670/0 power.
2. Nl-ST-DO, Daily Checks, is in progress.
3. Operators have completed the RPV water level instrument readings.

Initiating cue:

"(Operator's name), perform SRO review of the following section ofNI-ST-DO:

  • Attachment 4 section 6.0
  • Step 8.4 When completed, report findings to the Examiner."

NRC 2013 JPM SRO COOl May 2013

NRC JPM SRO C002 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Assess Reportability Requirements Revision: NRC 2013 Task Number: NtA Approvals:

NtA - Exam Security General Supervisor Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NtA - Exam Security Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _(SRO)

TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: _----'X'-"--__ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant ----"-"'--

Simulator or other location Expected Completion Time: 40 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 2013 JPM SRO C002 May 2013

Recommended Start Location: (Completion time based on the start location)

Classroom Simulator Set-up: N/A Directions to the InstructorlEvaluator:

None 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 I concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor I Evaluator:

1. Critical steps are identified in grading areas PasslFaii.
2. During Evaluated JPM:
  • Self checking shall be demonstrated.
3. During Training JPM:
  • Self checking shall be demonstrated.
  • Peer checking shall be demonstrated.
4. Verify the references below are available to the candidate.

References:

1. CNG-NL-1.01-1004
2. 10CFR50.72
3. NUREG 1022
4. EAL Matrix
5. EAL Bases NRC 2013 JPM SRO C002 May 2013

Tools and Equipment:

None Task Standard: Determine 10 CFR 50.72 reportability requirements.

Initial Conditions:

1. The plant was operating at 100% power with no equipment out of service.
2. A loss of offsite power Lines 1 and 4 occurred one hour ago.
3. Emergency Diesel Generator (EDG) 102 failed to start and has been declared inoperable.
4. Maintenance reports that repairs to EDG 102 will take several days.
5. Power Control reports Line 1 will be returned to service in approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and Line 4 will be returned to service in approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
6. Instructor to ask Candidate for any questions.

Initiating cue:

"(Operator's name), list the applicable 10 CFR 50.72 reportability requirements, the reason that they apply and the associated time limitations for reporting under that category. Record your findings on the sheet provided."

1. Provide repeat back of initiating cue. Proper communications used for repeat back SatlUnsat Evaluator Acknowledge repeat back (GAP-OPS-Ol) providing correction if necessary RECORDSTARTTDdE _________________

2 Obtain a copy of the any ofthe reference Reference materials obtained as necessary. SatlUnsat documents related to regulatory notifications.

These are likely to include the following:

  • CNG-NL-l.OI-I004
3. Locate and identify applicability of 10 CFR Identifies plant conditions require Emergency SatlUnsat 50.72(a)(I) Classification per Alert EAL 6.1.3 Note: Candidate must recognize that a loss of Identifies reportability per 50.72(a)(I), for PasslFail offsite power with a failure of an EDG to start declaration of any ofthe Emergency Classes, requires Emergency Classification (Alert EAL within one hour 6.1.3). The exact classification is not critical for the purposes ofthis JPM. Event classification will be tested in more detail in other exam items.

NRC 2013 JPM SRO C002 May 2013

I Performance Steps I Standard Grade

4. Locate and identify applicability of Refers to Tech Spec 3.6.3 .e(1) and determines SatlUnsat 50.72(b)(2)(i). Non-emergency four hour that with specification not being met, the report. Initiation of a plant shutdown required required action is to initiate a shutdown within by Tech Specs. one hour and be in cold shutdown within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

Identifies reportability per 50.72(b)(2)(i), for Pass/Fail initiation of a plant shutdown required by Tech Specs, within four hours

5. Locate and identify applicability of Identifies reportability per 50. 72(b)(3)(iv)(A) Pass/Fail 50.72(b)(3)(iv)(A) Non-emergency eight (or may alternately reference hour report. Event or condition results in 50.72(b)(3)(iv)(B)(8), for valid actuation of valid actuation of Emergency Diesel Emergency Diesel Generator, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Generator.
6. Locate and identify applicability of Identifies reportability per 50.72(b)(3)(v)(D) SatlUnsat 50.72(b)(3)(v)(D) Non-emergency eight hour for an event or condition that could have report. Event or condition that could have prevented fulfillment of a safety function prevented fulfillment of a safety function needed to mitigate the consequences of an needed to mitigate the consequences of an accident (loss of both offsite power lines, accident. failure ofEDG 102), within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Note: This step is deemed non-critical because of the redundancy with other reports and the subjective nature of this call.

TERMINATING CUE: Reportability requirements have been determined.

RECORDSTOPTIME _________

NRC 2013 JPM SRO C002 May 2013

Initial Conditions:

1. The plant was operating at 100% power with no equipment out of service.
2. A loss of offsite power Lines 1 and 4 occurred one hour ago.
3. Emergency Diesel Generator (EDG) 102 failed to start and has been declared inoperable.
4. Maintenance reports that repairs to EDG 102 will take several days.
5. Power Control reports Line 1 will be returned to service in approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and Line 4 will be returned to service in approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Initiating cue:

"(Operator's name), list the applicable 10 CFR 50.72 reportability requirements, the reason that they apply and the associated time limitations for reporting under that category. Record your findings on the sheet provided."

NRC 2013 JPM SRO C002 May 2013

NRC JPM SRO RC Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Detennine Actions for Inoperable Stack Radiation Monitor Revision: NRC 2013 Task Number: N/A Approvals:

NIA - Exam Security General Supervisor Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NIA - Exam Security Configuration Control Date Perfonner:._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (SRO)

TrainerlEvaluator:--------------------

Evaluation Method: Perfonn 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 offail shall be given if any critical step is graded as fail. Any grade of un sat or individual competency area unsat requires a comment.

Comments:

Evaluator ...,.c"....".... ,*.-----_ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:_ _ _ _ _ __

NRC 2013 JPM SRO RC May 2013

Recommended Start Location: Classroom Simulator Set-up: None Directions to the InstructorlEvaluator: None 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, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas Pass/Fail.
2. During Evaluated JPM:
  • Self checking shall be demonstrated.
3. During Training JPM:
  • Self checking shall be demonstrated.
  • Peer checking shall be demonstrated.

References:

1. ARP Hl-3-8
2. NI-OP-50B
3. ODCM 3.6.14.b and TBL D 3.6.14-2
4. NUREG 1123 KIA 2.3.11 (4.3)

Tools and Equipment:

1. None Task Standard: Determine actions per ARP Hl-3-8 and ODCM in response to stack radiation monitor downscale condition.

NRC 2013 JPM SRO RC May 2013

Initial Conditions:

1. The plant is operating at 100% power.
2. Annunciator HI-3-8, STACK GAS MONITORING TROUBLE, has alarmed.
3. Computer Point C061, OGESMS RAD MON STATUS - TRBL, is in alarm.
4. OGESMS radiation monitor RN-I OA indicates downscale.
5. Ask the operator for any questions.

Initiating cue:

"(Operator's name), determine the appropriate actions and compensatory measures in response to ARP Hl-3-8. Record your findings on the provided attachment."

EXAMINER NOTE: Provide Attachment 2.

1. Provide repeat back of initiating cue. Proper communications used for SatlUnsat Evaluator Acknowledge repeat back repeat back (GAP-OPS-Ol) providing correction if necessary RECORDSTARTT~ _______
1. Obtain a copy of the reference ARP HI 8 obtained. SatlUnsat procedure and review/utilize the Operator Actions referenced.

correct section.

ODCM obtained.

DLCO 3.6.14 referenced.

Table D 3.6.14-2 referenced.

2. Determines actions per ARP Hl-3-8. Determines Chemistry should PasslFaii implement NI-CSP-V309, Stack Monitor Alarm Response.

Determines the 8 Drywell and Torus Pass/Fail Vent and Purge valves must be verified CLOSED and a Caution Clearance Section must be applied.

3. Determines actions per ODCM. Determines one Stack Effluent SatlUnsat Monitoring Noble Gas Activity High Range Monitor is inoperable.

Determines ODCM Table D 3.6.14-2 SatlUnsat Instruments l.a.( 1) have one less than the minimum number of functional channels.

NRC 2013 JPM SRO RC May 2013

Detennines ODCM Table D 3.6.14-2 PasslFail note (a)(1) applies - With the number of channels functional 1 less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided:

(a) The nonfunctional channel is placed in the tripped condition, OR (b) Vent and Purge valves are closed and administratively controlled, OR (c) Primary containment integrity is not required.

Detennines DLCO 3.6.14.b requires PasslFail Restore the instruments to functional status within 30 days or outline in the next Radioactive Effluent Release Report the cause of the non-functionality and how the instruments were or will be restored to functional status.

TERMINATING CUE: Actions have been detennined per ARP Hl-3-8 and ODCM in response to stack radiation monitor downscale condition.

RECORDSTOPTIME_________

NRC 2013 JPM SRO RC May 2013

Initial Conditions:

1. The plant is operating at 100% power.
2. Annunciator Hl-3-8, STACK GAS MONITORING TROUBLE, has alarmed.
3. Computer Point C061, OGESMS RAD MON STATUS - TRBL, is in alarm.
4. OGESMS radiation monitor RN-l OA indicates downscale.

Initiating cue:

"(Operator's name), determine the appropriate actions and compensatory measures in response to ARP Hl-3-8. Record your findings on the provided attachment."

NRC 2013 JPM SRO RC May 2013

NRC ..IPM SRO EP Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Post-Scenario Emergency Event Classification Revision: NRC 2013 Task Number: NIA Approvals:

NIA - Exam Security General Supervisor Operations Training (Designee)

" Date General Supervisor Operations (Designee)

Date Configuration Control Date

,_ _ _ _ _ _ _ _ _ _ (SRO)

TrainerlEvaluator:_ _ _ _ _ _ _ _ _ __

Evaluation Method: Perform Evaluation Location: Simulator Expected Completion Time: 15 minutes 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: _ _ _ _ _ _ _._ _ _ _ _ _ __

NRC 2013 JPM SRO EP May 2013

Recommended Start Location: Classroom/Simulator Simulator Set-up: None Directions to the InstructorlEvaluator: None Directions to Operators:

Read Before Every JPM Performance:

For the performance ofthis JPM, I will function as the Unit 2 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 ofyour 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 lPM, 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:

1. Critical steps are identified as PasslFaii.
2. During Evaluated lPM:
  • Self-verification shall be demonstrated.
3. During Training JPM:
  • Self-verification shall be demonstrated.
  • No other verification shall be demonstrated.

References:

1. NUREG 1123, 2.4.29, SRO 4.4
2. EPlP-EPP-OI
3. EPlP-EPP-18
4. EPMP-EPP-OIOI Tools and Equipment:
1. EPlP-EPP-OI, ATTACHMENT 1, UNIT 1 EAL FLOWCHART
2. SMIED Checklist Package Task Standard:

Classify the emergency event based on the final scenario conditions within 15 minutes of the JPM start time.

NRC 2013 JPM SRO EP May 2013

Initial Conditions:

1. None
2. Instructor to ask the operator for any questions.

Initiating Cue:

"(Operator's name), based on the events that have just occurred, determine if the conditions warranted emergency classification. If so, determine the appropriate emergency classification. This is a time critical task. Your time starts now."

1. Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME _______

2. Obtain a copy of EPlP-EPP-O 1 attachments 1 EPlP-EPP-Ol attachments 1 and 2, and Shift SatlUnsat and 2, and Shift Manager emergency Manager emergency paperwork is obtained paperwork and review/utilize the correct section
3. Reviews plant conditions and determines if Determines an emergency classification is SatlUnsat emergency classification is warranted. required.
4. Classifies the emergency for 2013 NRC Determines the emergency classification level is PasslFaill Scenario # 1. Alert. NA Examiner Note: The listed EAL is the expected EAL based on scenario validation. If scenario Determines the Emergency Action Level (EAL) PasslFaill deviates from the expected course, examiner designator is 3.1.1. NA discretion will be required to determine the actual classification. EXAMINER NOTE: Time difference below must be 15 minutes or less:

JPM start time: - - - -

Time of Classification: - - - - -

NRC 2013 JPM SRO EP May 2013

I Performance Steps I Standard Grade

5. Classifies the emergency for 2013 NRC Determines the emergency classification level is PasslFaill Scenario #2. Site Area Emergency. NA Examiner Note: The listed EAL is the expected Determines the Emergency Action Level (EAL) PasslFaill EAL based on scenario validation. If scenario designator is 3.4.1 and/or 4.1.1. NA deviates from the expected course, examiner discretion will be required to determine the EXAMINER NOTE: Time difference below actual classification. must be 15 minutes or less:

JPM start time: - - - -

Time of Classification: - - - - -

6. Classifies the emergency for 2013 NRC Determines the emergency classification level is PasslFaill Scenario #3. Site Area Emergency. NA Examiner Note: The listed EAL is the expected Determines the Emergency Action Level (EAL) PasslFaill EAL based on scenario validation. If scenario designator is 2.2.2. NA deviates from the expected course, examiner discretion will be required to determine the EXAMINER NOTE: Time difference below actual classification. must be 15 minutes or less:

JPM start time: _ _ __

Time of Classification: - - - - -

7. Classifies the emergency for 2013 NRC Determines the emergency classification level is PasslFaiU Scenario #4. Site Area Emergency. NA Examiner Note: The listed EAL is the expected EAL based on scenario validation. If scenario Determines the Emergency Action Level (EAL) PasslFaiU deviates from the expected course, examiner designator is 2.1.1. NA discretion will be required to determine the actual classification. EXAMINER NOTE: Time difference below must be 15 minutes or less:

JPM start time: _ _ __

Time of Classification: - - - - -

NRC 2013 JPM SRO EP May 2013

I Performance Steps I Standard Grade

8. Classifies the emergency for 2013 NRC Determines the emergency classification level is PasslFaill Scenario #5. Alert. NA Examiner Note: The listed EAL is the expected Determines the Emergency Action Level (EAL) PasslFaill EAL based on scenario validation. If scenario designator is 3.1.1. NA deviates from the expected course, examiner discretion will be required to determine the EXAMINER NOTE: Time difference below actual classification. must be 15 minutes or less:

JPM start time: - - - -

Time of Classification: - - - - -

TERMINATING CUE: Emergency classification requirement is determined.

RECORDSTOPTIME_________

NRC 2013 JPM SRO EP May 2013

Initiating Cue:

"(Operator's name), based on the events that have just occurred, determine if the conditions warranted emergency classification. If so, determine the appropriate emergency classification. This is a time critical task. Your time starts now."

NRC 2013 JPM SRO EP May 2013

NRC JPM 8-1 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Rapid RWCU System Restoration for Level Control Revision: NRC 2013 Task Number: N/A Approvals:

N/A - Exam Security I General Supervisor - Date General Supervisor Date Operations Training (Designee) Operations (Designee)

Configuration Control Date Performer:._ _ _ _ _ _ _ _ _ _ _ _ _ _ _(,RO/SRO)

TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: _~_ _ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant _ _---"~__ Simulator Expected Completion Time: 20 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 ofunsat or individual competency area unsat requires a comment.

Comments:

Evaluator's Date:_ _ _ _ _ __

NRC 2013 JPM S-l - I - May 2013

Recommended Start Location: Simulator Simulator Set-up (if required):

1. Initialize Simulator to IC-161.
2. Verify RPV water level is above 100 inches.
3. Verify RWCU system isolated with isolation signal clear.

Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before Every JPM Performance:

For the performance ofthis 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:

1. Critical steps are identified in grading area as Pass/Fail.
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.
  • Peer verification shall be demonstrated.

References:

1. NUREG 1123,204000, A4.06, RO 3.0, SRO 2.9
2. NI-EOP-HC Tools and Equipment:

None NRC 2013 JPM S-1 May 2013

Task Standard: RWCU is rejecting to the condenser for level control.

Initial Conditions:

1. RWCU isolated following a low-low RPV water level transient.
2. RPV water level is high.
3. RWCU system is needed to control RPV water level.
4. Another Operator will be controlling RPV pressure using the ERVs and/or ECs.
5. Instructor to ask operator for any questions.

Initiating Cue:

"(Operator's name), perform rapid RWCU system restoration for RPV water level control and establish reject flow to the condenser, per NI-EOP-HC Attachment 12."

Performance Steps Standard Grade

1. Provide repeat back of initiating cue Proper communications used (GAP-OPS-Ol) SatlUnsat Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME _ _ __
2. Obtain a copy of the reference procedure NI-EOP-HC Attachment 12 is obtained SatlUnsat and review/utilize the correct section of the procedure
3. Verify the following:
  • The cause of the isolation is known Determines cause is known and corrected per SatlUnsat AND corrected initial conditions
4. Verify closed the foHowing valves:
  • 33.1-01B, CLEANUP PCV 11 (LP) Observes 33.l-01B in MAN and output signal SatlUnsat at 0
  • 33-39B, CLEANUP PCV 12 (HP) Places controller PC-33-39 in MAN and dials SatlUnsat to 0
5. Using RMC-33-151, CLEANUP SYS Verifies controller RMC-33-1S1 CLEANUP SatlUnsat SELECTOR, close 33-40 SYS SELECTOR in MAN and dialed to 0 Note: Manipulation of FC-33-169 is inconsequential, but does not satisfy this step.

NRC 2013 JPM S-1 May 2013

Performance Steps Standard Grade

6. Using RMC-33-165, CLEANUP TO Verify controller RMC-33-165C dialed SatlUnsat COND & WASTE FLOW, close 33-165 to °
7. Verify open one of the following using the CLEANUP SELECTOR CONDENSER WASTE control switch:
  • WASTE (valve 33-10, CLEANUP TO Rotates CLEANUP SELECTOR CONDENS PasslFail WASTE DISPOSAL BV) ER WASTE control switch clockwise to COND position
  • COND (valve 33-11, CLEANUP TO Observes right-hand set of lights red light ON SatlUnsat CONDENSER BV) and green light OFF, for 33-11 Note: Initiating cue directs the candidate to reject to the condenser
8. Open 33-01R, CU RETURN Rotates33-01R control switch clockwise to PasslFaii ISOLATION VALVE 1 (INSIDE) open Observes red light ON, green light OFF SatlUnsat
9. Open 33-04R, CU SUPPLY ISOLATION Rotates33-04R control switch clockwise to SatlUnsat VALVE 12 (OUTSIDE), for open and uses pull-to-stop function after 3 approximately 3 seconds THEN PULL seconds TO-STOP Observes red light ON, green light ON SatfUnsat Note: Cleanup System Inlet Pressure will rapidly rise in the next step
10. Jog open 33-02R, CU SUPPLY ISOLA Rotates33-02R control switch clockwise to SatfUnsat TION VALVE 11 (INSIDE), using Y2 open and uses pull-to-stop in Y2 second second open signals followed by PULL intervals UNTIL Cleanup system inlet TO-STOP UNTIL Cleanup System Inlet pressure rises and stabilizes at reactor pressure Pressure has stabilized at Reactor Pressure on indicators Observes red light ON, green light ON SatlUnsat Observes cleanup system pressure and reactor SatlUnsat pressure approximately equal
11. Fully open 33-02R Rotates33-02R control switch clockwise to PasslFaii open Observes red light ON, green light OFF SatfUnsat NRC 2013 JPM S-1 May 2013

Performance Steps Standard Grade

12. Fully open the following valves:
  • 33-04 Rotates33-04R control switch clockwise to PasslFail open Observes red light ON, green light OFF SatlUnsat
  • 33-41,AOBLOCKINGVALVE Rotates 33-41 control switch clockwise to PasslFail open Observes red light ON, green light OFF SatlUnsat
13. Simultaneously perfonn the following:
  • Adjust the in-service PCV to maintain Using controller PC-33-39, dials output signal SatlUnsat Reactor Water Cleanup System to open valve and establish inlet pressure pressure <100 psig below 100 psig Note: Operator may place the PCV in AUTO after pressure is established
  • Adjust RMC-33-165C, CLEANUP TO Using controller RMC-33-165C, dials output PasslFail COND & WASTE FLOW to control signals to open valve and establish system Reactor Water Level AND maintain reject flow Non-Regenerative Heat Exchanger outlet temperature < 120°F on Maintains parameters to prevent a subsequent PasslFail computer point F359 RWCU system isolation Cue: Another operator will monitor computer point F359.

Note: 33-165 controller output signal must be greater than 20% before the valve will open, then may be lowered below 20%

to adjust flow.

14. As time pennits, continue with NI-OP-3, Proper communications used (GAP-OPS-Ol) SatlUnsat H.lO.O.

Cue: Another operator will continue with N 1 OP-3 H.IO.O.

15. Reports to CRS that RWCU is restored Proper communications used (GAP-OPS-Ol) SatlUnsat and rejecting to condenser for level control Terminating Cue: RWCU is rejecting to the condenser for level control.

RECORD STOP TIME _ _ __

NRC 20 l3 JPM S-1 -5 May 2013

Initial Conditions:

1. R WCU isolated following a low-low RPV water level transient.
2. RPV water level is high.
3. R WCU system is needed to control RPV water level.
4. Another Operator will be controlling RPV pressure using the ERVs and/or ECs.

Initiating Cue:

"(Operator's name), perform rapid RWCU system restoration for RPV water level control and establish reject flow to the condenser, per NI-EOP-HC Attachment 12."

NRC 2013 JPM S-l May 2013

NRC JPM 5-2 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Cool RBEVS Charcoal Filter Revision: NRC 2013 Task Number: N/A Approvals:

General Supervisor Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NIA - Exam Security /

Configuration Control Date Performer:._ _ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)

TrainerlEvaluator:._ _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: _-'X'-"--__ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant _ _----"X~__ Simulator Expected Completion Time: 15 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop 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 NRC 2013 JPM S-2 May 2013

Recommended Start Location: Simulator Simulator Set-up (if required):

1. Initialize Simulator to IC-16I.
2. Verify an RBEVS auto-start signal is locked in.
3. Verify RBEVS 11 is running and RBEVS 12 is secured.

Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before 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 1 concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

During this Training lPM, 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 1 Evaluator:

I. Critical steps are identified in grading area as PasslFail.

2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.
  • Peer verification shall be demonstrated.

References:

1. NUREG 1123,261000 A4.03 (3.0/3.0)
2. NI-OP-IO Tools and Equipment:

None NRC 2013 JPM 8-2 May 2013

Task Standard: RBEVS train 12 placed in service and RBEVS train 11 placed in the cooling lineup.

Initial Conditions:

1. A steam leak in the Reactor Building occurred approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago.
2. RBEVS auto-initiated on high Reactor Building exhaust radiation level.
3. RBEVS train 11 is in service.
4. RBEVS train 12 is secured.
5. It has been determined that RBEVS train 11 charcoal filter needs to be removed from service and cooled.
6. Another Operator will be controlling Reactor pressure with ERVs and/or ECs.
7. Instructor to ask operator for any questions.

Initiating Cue:

"(Operator's name), place RBEVS train 12 in service and cool the charcoal filter for RBEVS train 11 per NI OP-IO section H.3.0."

Performance Steps Standard Grade

1. Provide repeat back of initiating cue Proper communications used (GAP-OPS-Ol) SatlUnsat Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTT~E ________
2. Obtain a copy of the reference procedure NI-0P-1O obtained, precautions and SatlUnsat and review/utilize the correct section of the limitations reviewed, sections H.3.0 procedure referenced
3. (Step 3.1.1) Verify closed the following valves:
  • 202-47, EM VENTILATION TIE BV Observes 202-47 green light on, red light off SatlUnsat
  • 202-74, EM VENTILATION LOOP 11 Observes 202-74 green light on, red light off SatlUnsat COOLING BV (label contains noun name but no number)

Observes 202-75 green light on, red light off SatlUnsat

  • 202-75, EM VENTILATION LOOP 12 COOLING BV (label contains noun name but no number)
4. (Step 3.l.3.a) Open 202-38, EM Opens 202-38 by rotating control switch CW PasslFail VENTILATION LOOP 12 INLET BV to OPEN
5. (Step 3.1.3.b) Start 202-33, EVS FAN 12 Starts 202-33 by taking control switch out of PasslFail pull-to-Iock Note: 202-33 auto-starts when the control switch is taken out of pull-to-Iock due to Places 202-33 control switch in START SatlUnsat presence of an auto-start signal.

NRC 2013 JPM S-2 May 2013

Performance Steps Standard Grade

6. (Step 3.1.3.c) VerifY open 202-35, EM Observes 202-35 green light off, red light on SatlUnsat VENTILATION EXHAUST FAN 12 OUTLET BV (label contains noun name but no number)
7. (Step 3.1.3 .d) Confirm proper operation of Observes 202-51 green light on, red light on SatlUnsat 202-51, EM VENT EXHAUST FAN 12 INLET FCV, by observing indicating Observes proper RBEVS flow SatiUnsat lights AND flow indication
8. (Step 3.1.3.e) Stop 202-53, EVS FAN 11 Stops 202-53 by rotating control switch CCW PasslFail and pulls to lock Note: RBEVS fan 11 control switch must be placed in pull-to-Iock to stop fan due to presence of an auto-start signal.
9. (Step 3.1.3.f) VerifY closed 202-34, EM Observes 202-34 green light on, red light off SatiUnsat VENT EXHAUST FAN 11 OUTLET BV (label contains noun name but no number)
10. (Step 3.2.2.a) VerifY EVS Train 12 running Observes RBEVS fan 12 green light off, red SatlUnsat light on
11. (Step 3.2.2.b) VerifY 202-53, EVS FAN 11 Observes 202-53 control switch in pull-to SatlUnsat in PULL-TO-LOCK lock
12. (Step 3.2.2.c) NotifY SRO to enter LCO Proper communications used (GAP-OPS-Ol) SatlUnsat 3.4.4.e (7 day plant shutdown LCO when one train of EVS is inoperable)

Role Play: Acknowledge communication as SRO.

13. (Step 3.2.2.d) Open 202-74, EM Opens 202-74 by rotating control switch PasslFan VENTILATION LOOP 11 COOLING BV CCWtoCOOL (label contains noun name but no number), by placing 202-37, EM VENTILATION LOOP 11 INLET BV, control switch to COOL
14. (Step 3.2.2.e) VerifY closed 202-37, EM Observes 202-37 green light on, red light off SatiUnsat VENTILATION LOOP 11 INLET BV
15. (Step 3.2.2.f) Open 202-47, EM Opens 202-47 by rotating control switch CW PasslFaii VENTILATION TIE BV to OPEN Terminating Cue: RBEVS train 12 placed in service and RBEVS train 11 placed in the cooling lineup.

RECORD STOP TIME _ _ __

NRC 2013 JPM S-2 May 2013

Initial Conditions:

1. A steam leak in the Reactor Building occurred approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago.
2. RBEVS auto-initiated on high Reactor Building exhaust radiation level.
3. RBEVS train 11 is in service.
4. RBEVS train 12 is secured.
5. It has been determined that RBEVS train 11 charcoal filter needs to be removed from service and cooled.
6. Another Operator will be controlling Reactor pressure with ERVs and/or ECs.

Initiating Cue:

"(Operator's name), place RBEVS train 12 in service and cool the charcoal filter for RBEVS train 11 per NI-0P-I0 section H.3.0."

NRC 2013 JPM 8-2 May 2013

NRC JPM 5-3 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Re-Open MSIV s with Reactor Pressurized and Lower Pressure Revision: NRC 2013 Task Number: N/A Approvals:

General Supervisor Date

, . NIA - Exam Security General Supervisor I

Date Operations Training (Designee) Operations (Designee)

NIA - Exam Security I Configuration Control Date Performer: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)

TrainerlEvaluator:- - - - - - - - - - - - - - -

Evaluation Method: _----"X--"--__ Perform _ _ _ _ _ _ Simulate Evaluation Location: - - - - Plant X

"--"---- Simulator 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:

Evaluator's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:_ _ _ _ _ __

NRC 2013 JPM S-3 May 2013

Recommended Start Location: Simulator Simulator Set-up (if required):

1. Initialize Simulator to IC-162.
2. Verify the Reactor is scrammed with the MSIVs closed.
3. Verify Reactor pressure is approximately 1000 psig and slowly lowering with EC 12 in service.
4. Verify the following malfunctions are inserted:
  • EC04A, EC Return Valve Fails to Open (IV 39-05)
  • AD07(A-F), ERV (111-123) Fails Closed (Burned Out Solenoid)
  • RP06, Reactor Vessel Isolation
5. Verify trigger 1 is set as follows:
  • Event zdmsisol(I)==1&zdmsisol(2)==I&zdmsisol(3)=I&zdmsisol(4)=1
  • Command dmf rp06 Directions to the InstructorlEvaluator:

None 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 1 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:

1. Critical steps are identified in grading area as Pass/Fail.
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.
  • Peer verification shall be demonstrated.

References:

1. NUREG 1123,239001 A4.01 (4.2/4.0)

NRC 2013 JPM S-3 May 2013

2. N1-EOP-1
3. N1-EOP-HC Tools and Equipment:

None Task Standard: MSIV s re-opened and Reactor pressure lowering on Turbine Bypass Valves.

Initial Conditions:

1. An RPV Blowdown is required.
2. Emergency Condenser 11 has failed to go into service and ERVs have failed to open.
3. MSIV s closed due to a spurious isolation signal.
4. Another Operator has been assigned Reactor water level control.
5. Instructor to ask operator for any questions.

Initiating Cue:

"(Operator's name), install NI-EOP-l attachment 1 jumpers, re-open the MSIVs per NI-EOP-HC attachment 3, and then depressurize the Reactor with Turbine Bypass Valves using the Bypass Opening Jack (BOJM)."

Performance Steps Standard Grade

1. Provide repeat back of initiating cue Proper communications used (GAP-OPS-Ol) SatlUnsat Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME _ _ __
2. Obtain a copy of the reference procedure NI-EOP-1 attachment 1 and N1-EOP-HC SatlUnsat and review/utilize the correct section of the attachment 3 obtained procedure
3. Bypass MSIV ISOLATION interlocks by installing the following jumpers at the EOP ISOLATION BYPASS JUMPER SUBPANEL (inside Panel N, between INIA and INIB):
  • Jumper 15, MSIV ISOLATION BYPASS Inserts EOP jumper 15. PasslFaii RELAY l1K19A TO RELAY 11K73
  • Jumper 16, MSIV ISOLATION BYPASS Inserts EOP jumper 16. PasslFaii RELAY l1K20A TO RELAY l1K74
  • Jumper 22, MSIV ISOLATION BYPASS Inserts EOP jumper 22. PasslFaii RELAY 12K19A TO RELAY 12K73
  • Jumper 23, MSIV ISOLATION BYPASS Inserts EOP jumper 23. PasslFaii RELAY 12K20A TO RELAY l2K74 NRC 2013 JPM S-3 May 2013

Performance Steps Standard Grade

4. Open MSIV 01-03 Opens MSIV 01-03 by rotating control switch PasslFail CWtoOPEN
5. Slowly throttle open MSIV 01-01 utilizing Throttles open MSIV 01-01 by rotating PasslFaii PULL~ TO-STOP control switch CW to OPEN and then pulling control switch out
6. Fully open MSIV 01-01 Opens MSIV 01-01 by rotating control switch PasslFail CW to OPEN
7. Open MSIV 01-04 Opens MSIV 01-04 by rotating control switch PasslFaii CWtoOPEN
8. Slowly throttle open MSIV 01-02 utilizing Throttles open MSlV 01-02 by rotating PasslFaii PULL-TO-STOP control switch CW to OPEN and then pulling control switch out
9. Fully open MSlV 01-02 Opens MSIV 01-02 by rotating control switch PasslFaii CWtoOPEN
10. Opens Turbine Bypass Valve( s) using Rotates BY-PASS OPENING JACK control PasslFaii Bypass Opening Jack (BOJM) switch clockwise to OPEN Terminating Cue: MSIV s re-opened and TBV s open/opening.

RECORD STOP TIME _ _ __

NRC 2013 JPM S-3 May 2013

Initial Conditions:

1. An RPV Blowdown is required.
2. Emergency Condenser 11 has failed to go into service and ERVs have failed to open.
3. MSIVs closed due to a spurious isolation signaL
4. Another Operator has been assigned Reactor water level control.

Initiating Cue:

"(Operator's name), install NI-EOP-l attachment 1 jumpers, re-open the MSIVs per NI-EOP-HC attachment 3, and then depressurize the Reactor with Turbine Bypass Valves using the Bypass Opening Jack (BOJM)."

NRC 2013 JPM 8-3 May 2013

NRC JPM S-4 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Transfer Torus Water to the Waste Collector Tank Using Revision: NRC 2013 Containment Spray Loop 111 Task Number: NIA Approvals:

I ,

NI A - Exam Security I General Supervisor '" Date General Supervisor Date Operations Training (Designee) Operations (Designee)

Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _(,RO/SRO)

Evaluation Method: _-=X-=---__ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant _ _------__ Simulator Expected Completion Time: 15 Minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop 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 2013 JPM S-4 May 2013

Recommended Start Location: (Completion time based on the start location)

NMP Unit 1 Simulator Simulator Set-up (if required):

1. Initialize Simulator to IC-162.
2. VerifY Torus water level raised to ~11.3' per NI-EOP-l Attachment 18.

Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before EveI)' 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:

1. Critical steps are identified in grading areas PasslFaii.
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. NI-EOP-l, Attachment 15
2. NUREG 1123295029 EAl.03 (2.9/3.0)

Tools and Equipment:

None NRC 2013 JPM S-4 May 2013

Task Standard: Torus water level is being lowered via the Containment Spray System.

Initial Conditions:

1. Torus water level is 11.3 feet and rising slowly.
2. N1-EOP-4 has been entered.
3. Containment Spray pumps are in pull-to-Iock.
4. Another Operator will control Reactor pressure using ECs and/or ERVs.
5. Another Operator will control Reactor water level using CondensatelFeedwater and CRD.

Initiating Cues:

"(Operator's name), lower Torus water level to 11.0 feet by discharging water to the Waste Collector Tank using Containment Spray Loop 111 in accordance with NI-EOP-1 Attachment 15."

Performance Steps Standard Grade

l. Provide repeat back of initiating cue Proper communications used SatlUnsat (GAP-OPS-OI)

Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME

2. Obtain a copy of the reference procedure NI-EOP-1 Attachment 15 obtained SatlUnsat and review/utilize the correct section ofthe procedure
3. NotifY Radwaste of intent to pump down Proper communications used SatlUnsat Torus to Waste Collector Tank (GAP-OPS-O 1)

Role Play: Acknowledge report

4. Close 80-45, Cont Spray Bypass BV 122 Closes 80-45 by rotating control switch CCW PasslFaii to CLOSE
5. Open 80-118, Cont Spray Test to Torus Opens80-118 by rotating control switch CW PasslFail FCV to OPEN Note: 80-118 is a throttlable valve, and must be held in the open position until fully open
6. VerifY closed 80-16, Cont Spray Discharge Closes 80-16 by rotating control switch CCW PasslFail IV III to CLOSE
7. VerifY open 80-40, Cont Spray Bypass BV Observes 80-40 green light off, red light on SatlUnsat 111
8. Start Containment Spray Raw Water Pump Starts Containment Spray Raw Water Pump PassiFail 111 111 by rotating control switch CW to START NRC 2013 JPM 8-4 May 2013

Perfonnance Steps Standard Grade

9. Start Containment Spray Pump 111 Starts Containment Spray Pump 111 by PasslFaii rotating control switch CW to START
10. Open 80-115, Cont Spray to Radwaste IV Opens80-115 by rotating control switch CW PasslFaii 12 to OPEN
11. Open 80-114, Cont Spray to Radwaste IV Opens80-114 by rotating control switch CW PasslFaii 11 to OPEN
12. Throttle 80-118, Cont Spray Test to Torus Throttles closed 80-118 by rotating control SatlUnsat FCV as required to control flow to Waste switch CCW as required Collector Tank Role Play: If requested, infonn that Radwaste has indication of sufficient flow
13. Monitor 58-05A and 58-06A TORUS H 2O Observes TORUS H20 LEVEL indicators 58 SatlUnsat LEVEL indicators for level response 05A and 58-06A monitored for level response
14. Inform SRO that flow to the Waste Proper communications used SatlUnsat Collector Tank has been established using (GAP-OPS-Ol)

Containment Spray Loop 111 Role Play: Acknowledge report Terminating Cue: Torus water level is being lowered via Containment Spray Loop 111.

RECORD STOP TIME _ _ __

NRC 2013 JPM S-4 May 2013

Initial Conditions:

1. Torus water level is 11.3 feet and rising slowly.
2. N1-EOP-4 has been entered.
3. Containment Spray pumps are in pull-to-Iock.
4. Another Operator will control Reactor pressure using ECs and/or ERVs.
5. Another Operator will control Reactor water level using CondensatelFeedwater and CRD.

Initiating Cues:

"(Operator's name), lower Torus level to 11.0 feet by discharging water to the Waste Collector Tank using Containment Spray Loop 111 in accordance with N1-EOP-1 Attachment 15."

NRC 2013 JPM S-4 - I - May 2013

NRC ..IPM 8-5 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Control Room Evacuation, Manual Scram Fails, ARl Works Revision: NRC 2013 One Main Steam Line Fails to Isolate, Powerboard 11 Fails To Fast Transfer Task Number: N/A Approvals:

r ~

NtA - Exam Security I General Supervisor Date General Supervisor Date Operations Training (Designee) Operations (Designee)

Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)

Evaluation Method: _~_ _ Perform - - - - - - Simulate Evaluation Location: _ _ _ _ Plant -----"--"---

Simulator Expected Completion Time: 15 Minutes 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 2013 JPM S-5 May 2013

Recommended Start Location: (Completion time based on the start location)

NMP Unit 1 Simulator Simulator Set-up (if required):

1) Initialize Simulator to IC-163.
2) Insert malfunctions RP05A and RP05B to cause failure to scram.
3) Insert malfunction ED26 to cause Powerboard 11 to fail to fast transfer.
4) Insert malfunctions MS13A (50%) and MS13C (100%) to fail MSIVs 01-01 and 01-03 to close.
5) Insert trigger 2 to allow MSIV 01-01 to close using the control switch:
  • Event - zdmsiivc( 1)== 1
  • Command - dmfms13a
6) Insert trigger 3 to allow MSIV 01-03 to close using the control switch:
  • Event - zdmsoivc( 1)== I
  • Command - dmf ms 13c Directions to the InstructorlEvaluator:

None 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:

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.
  • No other verification shall be demonstrated.

NRC 2013 JPM S-5 May 2013

References:

1. Nl-SOP-21.2
2. Nl-SOP-l
3. Nl-S0P-30.1
4. NUREG 1123295016 AA1.01 (3.8/3.9)

Tools and Equipment:

None Task Standard: Control Room actions for Control Room Evacuation complete, including compensatory actions for failure of Mode Switch and RPS push buttons, MSIV closure, and Powerboard 11 fast transfer.

Initial Conditions:

1. The plant is operating at approximately 100% power.
2. The Shift Manager has determined that a Control Room Evacuation is required due to a fire in the Auxiliary Control Room.
3. The fire is still small and no smoke has yet entered the Control Room.
4. Time permits completing all required actions ofNI-SOP-21.2, Control Room Evacuation, before leaving the Control Room.

S. Ask the operator for any questions.

Initiating Cues:

"(Operator's name), perform the Control Room actions for a Control Room Evacuation per NI-SOP-21.2."

Performance Steps Standard Grade

1. Provide repeat back of initiating cue Proper communications used SatlUnsat (GAP-OPS-Ol)

Evaluator acknowledge repeat back providing correction ifnecessary RECORD START TIME _ _ __

2. Place Reactor Mode Switch in Rotates Reactor Mode Switch CW to PasslFaii SHUTDOWN SHUTDOWN Note: The Mode Switch and the RPS pushbuttons will fail to cause a Reactor scram. The Candidate may use guidance in NI-SOP-l to immediately attempt manual ARl.

Role Play: If asked how to proceed with failure to scram, direct the Candidate to perform immediate actions ofN I-SOP-l, Reactor Scram.

NRC 2013 JPM S-5 May 2013

Performance Steps Standard Grade

3. Verify ALL Control Rods inserted Observes control rods failed to insert SatlUnsat May depress RPS pushbuttons SatlUnsat Depresses MANUAL ARI pushbutton Pass/Fail Observes control rods insert SatlUnsat
4. Place BOTH VESSEL ISOLATION Rotates both VESSEL ISOLATION switches Pass/FaiJ switches to ISOLATE CCW to ISOLATION
5. Verify ALL MSIVs close Observes green light on, red light off, for SatiUnsat MSNs 01-02 and 01-04 Observes MSIV 01-01 green light on, red SatlUnsat light on Observes MSN 01-03 green light off, red SatlUnsat light on Closes at least one MSN in steam line by: PasslFaii
  • Rotates MSN 01-01 control switch counterclockwise to CLOSE AND/OR
  • Rotates MSN 01-03 control switch counterclockwise to CLOSE Cue:

If required, inform candidate that time still permits completing rest of Control Room actions for NI-S0P-21.2.

NRC 2013 JPM S-5 May 2013

Performance Steps Standard Grade

6. IF time permits, verify the following:
  • House service loads transfer Observes PB 12 energized (voltmeters show SatlUnsat

~4160V, breakers re-align)

Note: The candidate may request guidance on how to deal with PB 11 failure to fast transfer. Observes PB II de-energized SatlUnsat Direct candidate to make a recommendation and then carry out that recommendation. Candidate Enters Nl-SOP-30.l SatlUnsat will likely use NI-SOP-30.1 for guidance on how to re-energize PB 11. In this case, the Verifies proper loads running SatlUnsat candidate will also verify other things, such as Service Water pump 12 running, prior to re Opens breaker R 113 by rotating control SatlUnsat energizing PB 11. switch counterclockwise to TRIP Cue: If asked for permission to re-energize Inserts Sync Key into RIl2 and rotates PasslFaii Powerboard 11, give permission. clockwise to ON Cue: If candidate begins to close Recirc pump Closes breaker R 112 by rotating control PasslFaii discharge valves, inform them that another switch clockwise to CLOSE operator will perform all actions in N 1-SOP-30.1 other than re-energizing the board.

Rotates Sync Key counterclockwise to OFF SatlUnsat and removes Restores loads by:

  • Rotates Rill control switch clockwise to SatlUnsat CLOSE
  • Rotates RI14 control switch clockwise to SatlUnsat CLOSE
7. IF time permits, verify the foHowing:
  • Turbine/Generator trip Observes Turbine trip and Generator lockout SatlUnsat (TSVs indicate closed, 86G1I2 lockouts roll)
  • HPCI Initiation Observes FW pumps II and 12 start / inject SatlUnsat (green lights off, red lights on, amps, flow)
  • FW Pump 13 clutch disengaged Observes FW pump 13 clutch disengaged SatlUnsat (green light off, red light off, speed lowers)
7. IF time permits, sound the station alarm Depresses STA pushbutton on GAltronics SatlUnsat AND announce Control Room evacuation Depresses OFF pushbutton on GAItronics SatlUnsat Announces Control Room evacuation Sat/Unsat NRC 2013 JPM S-5 - 1 May 2013

Performance Steps Standard Grade

8. Obtain two sets of RSP keys (V A-I, GE- Proper communications used SatlUnsat 75, PA-235) AND obtain radios (GAP-OPS-Ol)

Cue: You have obtained radios and keys.

9. Evacuate Control Room through East Proper communications used SatlUnsat West corridor, south side of Control Room (GAP-OPS-Ol)

Cue: Task complete.

Terminating Cue: Control Room actions for Control Room Evacuation complete, including compensatory actions for failure of Mode Switch and RPS pushbuttons.

RECORD STOP TIME _ _ __

NRC 2013 JPM S-5 May 2013

Initial Conditions:

1. The plant is operating at approximately 1000/0 power.
2. The Shift Manager has determined that a Control Room Evacuation is required due to a fire in the Auxiliary Control Room.
3. The fire is still small and no smoke has yet entered the Control Room.
4. Time permits completing all required actions ofN1-S0P-21.2, Control Room Evacuation, before leaving the Control Room.

Initiating Cues:

"(Operator's name), perform the Control Room actions for a Control Room Evacuation per N1-S0P-21.2."

NRC 2013 JPM S-5 May 2013

NRC JPM 5-6 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Restore EC 11 To Service (Alternate Path) Revision: NRC 2013 Task Number: NtA Approvals:

Nt A - Exam Security I General Supervisor Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NtA - Exam Security t Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)

Evaluation Method: _~_ _ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant __---"-x-"--__ Simulator Expected Completion Time: 20 minutes 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:_ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC 2013 JPM S-6 - 1* May 2013

Recommended Start Location: (Completion time based on the start location)

Unit 1 Simulator Simulator Set-up (if required):

1. Initialize Simulator to IC-I63.
2. Verify EC 11 is removed from service per NI-OP-13 section H.8.0.
3. Verify EC 11 steam pressure has been vented to near 0 psig.
4. Verify malfunction EC06A is set at 25% with a IS second delay time on trigger 1.
5. Verify trigger I is set to initiate when valve 39-09R red light goes on (hzlecmovr(1)==I).

Directions to the InstructorlEvaluator:

None 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:

1. Critical steps are identified in grading areas PasslFail.
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.
  • Peer verification shall be demonstrated.

References:

1. NUREG 1123, KIA 207000 A4.05 (3.5/3.7)
2. NI-OP-13 Tools and Equipment:

I. None NRC 2013 JPM S-6 May 2013

Task Standard: EC 11 is isolated due to tube leakage.

Initial Conditions:

1. Emergency Condenser (EC) 11 is out of service per NI-OP-13 section H.8.1 following corrective maintenance.
2. Work is complete and EC 11 is ready to be returned to service.
3. Non-Destructive Evaluation (NDE) has determined EC stearn leg level to be 6 ft 11 inches.
4. Instructor to ask operator for any questions.

Initiating Cues:

"(Operator's name), return EC 11 to service per NI-OP-13 section H.8.0."

Performance Steps Standard Grade

1. Provide repeat back of initiating cue Proper communications used SatlUnsat (GAP-OPS-Ol)

Evaluator acknowledge repeat back providing correction ifnecessary.

RECORD START TIME _______

2. Obtain a copy of the reference procedure NI-OP-13 is obtained, precautions & SatlUnsat and review/utilize the correct section ofthe limitations reviewed, section H.8.3 utilized procedure
3. VerifY proper keepfullievel as follows:
  • Contact Engineering Programs - NDE to Determines level is 6' 11" per initial SatlUnsat perform UT ofEC stearn leg for level conditions determination
  • IF EC stearn leg level is greater than 6' Proceeds to step 8.3.2 SatlUnsat 10" THEN proceed to step 8.3.2
4. VerifY open the following valves:
  • 05-11, EMERG COND VENT Opens 05-11 by rotating control switch CW to PasslFail ISOLATION VALVE 112 OPEN
  • 05-01R, EMERG COND VENT Opens 05-0 lR by rotating control switch CW PasslFail ISOLATION VALVE 111 to OPEN NRC 2013 JPM S-6 May 2013

Perfonnance Steps Standard Grade

5. WHEN system pressure has returned to nonnal, open the following valves:
  • 39-11R, EMERG CONDSR STM Opens39-11R by rotating control switch CW PasslFaii SUPPLY DRAIN IV 111 to OPEN
  • 39-12R, EMERG CONDSR STM Opens39-12R by rotating control switch CW PasslFaii SUPPLY DRAIN IV 112 to OPEN
6. Open 39-07R, EC STM ISOLAnON Opens39-07R by rotating control switch CW PasslFaii VALVE 112 to OPEN Note: The candidate may throttle open 39-07R using the pull-to-stop feature, rather than open it in one continuous motion. However, it must be fully opened by the end of the manipulation.
7. Throttle open 39-09R, EC STM Opens39-09R by rotating control switch CW PasslFaii ISOLAnON VALVE 111 and monitor to OPEN system parameters during heatup AND repressurization Stops39-09R by pulling control switch out to SatlUnsat STOP Monitors system temperature and pressures SatlUnsat Fully opens39-09R by rotating control switch SatlUnsati CWtoOPEN NA Note: The alternate path begins when 39-09R red light comes on. This causes an EC tube leak to be initiated.
8. Responds to alann KI-I-2 Acknowledges and reports alann SatlUnsat
9. Confinn alann on computer printout Observes computer points E478 and E480 in SatlUnsat alann
10. Confinn radiation levels on J Panel and Observes E CONDSR VENT RAD MON 111 SatlUnsat contact RP to check dose rates above (RE-RN04A-3) and E CONDSR VENT RAD elevation 340 MON 112 (RE-RN04A-4) reading on J Panel and detennines readings indicate alann condition Role Play: Acknowledge direction as RP. Directs RP to check dose rates above SatlUnsat elevation 340 NRC 2013 JPM S-6 May 2013

Performance Steps Standard Grade

11. IF High Rad Alarm is confirmed, (BOTH RE-RN04A-3 AND RE-RN04A-4 in alarm OR one in alarm with the other Note: These steps are NIA if shell inoperable), AND shell side temperature temperature is <100°F.

2:100F:

  • Direct Shift Chemistry Technician to Directs Chemistry Tech to assess for possible SatlUnsati assess the possible unmonitored unmonitored release per EPIP-EPP-08 NA radiological release using Attachment 4A of EPIP-EPP-08 SatlUnsatl
  • Direct Shift Radiation Protection Directs RP Tech to perform downwind survey NA Technician to perform a downwind site at site boundary boundary radiological survey Role Play: Acknowledge direction as RPIChemistry.
12. IF High Rad Alarm is confirmed, (BOTH Note: This step is NI A if shell temperature is RE-RN04A-3 AND RE-RN04A-4 in alarm > 100°F.

OR one in alarm with the other inoperable), AND shell side temperature is

<100F, direct the Shift Chemistry Directs Chemistry Tech to obtain and evaluate SatlUnsati Technician to obtain AND evaluate an EC EC 11 shell side sample NA shell side sample Role Play: Acknowledge direction as Chemistry.

NRC 2013 JPM S-6 May 2013

Performance Steps Standard Grade

13. IF alarm is valid THEN with SM concurrence, close the following valves:

o 39-07R, EC STM ISOLATION Closes39-07R by rotating control switch PasslFail VALVE 112 CCWtoCLOSE o 39-09R, EC STM ISOLATION Closes39-09R by rotating control switch PasslFail VALVE 111 CCWtoCLOSE o 39-05, EMERG CNDSR COND RET Observes 39-05 green light on, red light off Sat/Unsat ISOLATION VALVE 11 o 39-11R, EMERG CNDSR STM Closes39-11R by rotating control switch PasslFail SUPPLY DRAIN IV 111 CCWtoCLOSE o 39-12R, EMERG CNDSR STM Closes39-12R by rotating control switch PasslFail SUPPLY DRAIN IV 112 CCWtoCLOSE o OS-OlR, EMERG COND VENT Closes OS-OIR by rotating control switch PasslFail ISOLATION VALVE 111 CCWto CLOSE o 05-11, EMERG COND VENT Closes 05-11 by rotating control switch CCW PasslFaii ISOLATION VALVE 112 to CLOSE Role Play: As SM, inform the candidate that the alarm is valid and provide concurrence for isolating EC 11.

Terminating Cue: EC 11 is isolated due to tube leak.

RECORD STOP TIME _ _ __

NRC 2013 JPM 8-6 May 2013

Initial Conditions:

1. Emergency Condenser (EC) 11 is out of service per NI-0P-13 section H.8.1 following corrective maintenance.
2. Work is complete and EC 11 is ready to be returned to service.
3. Non-Destructive Evaluation (NDE) has determined EC steam leg level to be 6 ft 11 inches.

Initiating Cues:

"(Operator's name), return EC 11 to service per NI-0P-13 section H.8.0."

NRC 2013 JPM S-6 May 2013

NRC JPM S-7 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

EDG 103 SID- PB 103 Return to Nonnal Power Revision: NRC 2013 (Alternate Path)

Task Number: NIA Approvals:

N/A Exam Security I General Supervisor '" Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NIA - Exam Security /

Configuration Control Date Perfonner:_ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)

TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: _~_ _ Perfonn - - - - - - Simulate Evaluation Location: _ _ _ _ Plant _ _---'-"--__ Simulator Expected Completion Time: 20 Minutes Time Critical Task: No Alternate Path Task: Yes Start Time: - - - - Stop 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 un sat or individual competency area unsat requires a comment.

Comments:

Evaluators Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:_ _ _ _ _ __

NRC 2013 JPM S-7 May 2013

Recommended Start Location: (Completion time based on the start location)

NMP Unit 1 Simulator Simulator Set-up (if required):

1. Initialize Simulator to IC-164.
2. Verify PB 103 is supplied by EDG 103 per NI-OP-45 section E.3 .0.
3. Verify CRD Pump 11 in service.
4. Verify the Annunciator Ll-4-S is overridden to "Fail Off', to simulate alternate SFP pump in service.
5. Verify malfunction RD35B is inserted as "TRUE", to simulate prevent start of 12 CRD pump.
6. Verify override SDS267L02348 is inserted as "OFF", to simulate prevent start of 12 CRD pump.
7. Verify malfunction DGOSB is inserted as "TRUE" for failure of EDG 103 to stop.

Directions to the InstructorlEvaluator:

None 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:

1. Critical steps are identified in grading areas PasslFail.
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 1123,264000, A4.04, RO 3.7, SRO 3.7
2. NI-OP-4S NRC 2013 JPM S-7 May 2013

Tools and Equipment:

1. None Task Standard: Shutdown EDG 103 and reenergize PB 103.

Initial Conditions:

1. EDG 103 is supplying PB 103 due to maintenance on breaker RlO13.
2. EDG 103 has been at minimum load for the past hour and at 700 KW for the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3. 115 KV power is stable.
4. N1-0P-45 section G.2 is complete through step 2.6.
5. Instructor to ask operator for any questions.

Initiating Cues:

"(Operator's name), shutdown EDG 103 and return PB 103 to normal power in accordance with N1-0P-45, beginning at step G.2.7."

Performance Steps Standard Grade

1. Provide repeat back of initiating cue Proper communications used SatlUnsat (GAP-OPS-01)

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME ________

2. Obtain a copy of the reference procedure N1-0P-45 obtained SatlUnsat and review/utilize the correct section of the Precautions & limitations reviewed procedure Section G.2 referenced
3. Verify GREEN flagged R1013, PB 103 Rotates R1013 control switch CW from PTL PasslFaii Normal Power Supply Breaker to neutral
4. Place and HOLD in TRIP position R1032, Rotates R1032 control switch CCW and holds PasslFaii Diesel Generator 103 Output Breaker in trip position
5. When 3 to 5 seconds has elapsed, close Rotates RlO13 control switch CW, observes PasslFaii RlO13 red light on, green light off
6. Confirm normal voltage on PB 103 and PB Observes ~4160 VAC on PB 103 voltmeter, SatlUnsat 17B and observes ~600 V AC on PB 17B voltmeter
7. Return R1 032 to Neutral Position Releases RI032 to the neutral position PasslFaii NRC 2013 JPM S-7 May 2013

Performance Steps Standard Grade

8. Reset Lockout 86-17 device Rotates 86-17 control switch CW to reset PasslFaill position NA Note: Lockout device may not need to be reset if R 1013 is closed closer to 3 seconds than 5 seconds (Step 5 above)
9. Install Close fuse for CRD pump 12 Proper communications used SatlUnsat (GAP-OPS-Ol)

Cue: Field operators will install fuse.

Note: Delete malfunction RD35B &

override 5DS267L02348, then report close fuse for CRD pump 12 has been installed and independently verified.

10. VerifY Green light ON for CRD pump 12 Observes CRD pump 12 green light on SatlUnsat Note: The green light will not be lit until the instructor note in step 9 above is completed.

Role Play: If informed to exit Technical Specification for CRD pump, acknowledge report.

11. VerifY EDG Raw Water Cooling Pump Proper communications used SatlUnsat started (GAP-OPS-Ol)

Cue: EDG 103 Raw Water Cooling Pump has started.

12. Restore normal loads on PB 17B Proper communications used SatlUnsat (GAP-OPS-O 1)

Cue: Another operator will restore PB 17B loads.

13. IF EDG has run idle for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> OR Determines step is NIA based on initial SatlUnsat operated less than 500 KW for 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, conditions THEN shutdown EDG per Section G, Recovery after Light Load Operation Note: This step is NI A based on initial conditions.
14. VerifY Speed Droop set to zero Proper communications used SatlUnsat (GAP-OPS-Ol)

Cue: EDG 103 Speed Droop set to zero NRC 2013 JPM S-7 May 2013

Performance Steps Standard Grade

15. Adjust Governor to achieve greater than or equal to 60.1 Hz synchronous speed AND the Governor high speed light lit as follows.
a. Adjust speed until governor yellow Raises EDG 103 speed as necessary by SatlUnsat high speed light is lit rotating governor control switch CCW, observes yellow high speed light lit
b. Adjust speed to achieve greater than Raises EDG 103 speed as necessary by SatlUnsat or equal to 60.1 Hz with a maximum rotating governor control switch CCW, and of60.2 Hz. observes EDG 103 frequency of 60.1-60.2 Hz Note: This step may be N/A based on EDG speed.
16. Independently verify speed greater than or Proper communications used SatlUnsat equal to 60.1 HZ (max 60.2 Hz) (GAP-OPS-Ol)

Cue: Speed is as you adjusted it.

17. Adjust voltage to 4200 V using VOLT Raises EDG 103 voltage as necessary by SatlUnsat ADJ RHEO GEN 103 rotating voltage regulator control switch CCW, and observes voltage ~4200V
18. Place DIESEL GEN 103 control switch in Rotates EDG 103 control switch CCW to PasslFaii STOP STOP position, observes EDG 103 output voltage lower
19. When approximately 3 minute cooldown Recognizes that EDG did not stop as it should SatlUnsat has elapsed, verify EDG 103 stopped have Cue: Time compression is in effect, 4 minutes have elapsed.

Note: The applicant should recognize that the EDG should have stopped.

20. If the EDG did not shutdown, refer to Refers to N1-0P-45 section G.8.0, Emergency SatlUnsat Section G.8.0, Emergency Shutdown Shutdown 2l. If offsite power is not available, TIffiN Determines offsite power is available per SatlUnsat verify R1012 OR 1013 in Pull-To-Lock initial conditions Note: This step is N/A, Offsite power is available per the initial conditions.

NRC 2013 JPM S-7 May 2013

Perfonnance Steps Standard Grade

22. IF loss of 125 VDC power is lost due to Detennines 125 VDC power is available SatlUnsat loss of Battery Board 11, THEN enter N 1 based on various control room indications SOP-47A.l to restore 125 VDC power Note: This step is N/A, 125 VDC is available.
23. Place DIESEL GEN control switch to EM Rotates EDG 103 control switch CCW to EM Pass/Fail STOP STOP position, observes EDG 103 frequency lower Note: It is expected that the candidate will stop the EDG from the Control Room and not attempt to have a field operator to shutdown the EDG locally.

Role Play: If contacted to shutdown EDG locally, report that communications have failed and no one can be dispatched to shutdown the EDG locally Terminating Cue: EDG 103 stopped and PB 103 energized.

RECORD STOP TIME _ _ __

NRC 2013 JPM S-7 May 2013

Initial Conditions:

1. EDG 103 is supplying PB 103 due to maintenance on breaker RIO 13.
2. EDG 103 has been at minimum load for the past hour and at 700 KW for the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3. 115 KV power is stable.
4. NI-0P-45 section G.2 is complete through step 2.6.

Initiating Cues:

"(Operator's name), shutdown EDG 103 and return PB 103 to normal power in accordance with NI-0P-45, beginning at step G.2.7."

NRC 2013 JPM S-7 May 2013

NRC JPM 8-8 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Reset Reactor Scram Revision: NRC 2013 Task Number: N/A Approvals:

N/A - Exam Security I General Supervisor ~ Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NtA - Exam Security I Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)

TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: _--"X-",-__ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant _ _~-"--__ Simulator 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's Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:_ _ _ _ _ __

NRC 2013 JPM S-8 May 2013

Recommended Start Location: Simulator Simulator Set-up (if required):

1. Initialize Simulator to IC-165.
2. Verify a Reactor scram is inserted and NOT yet reset.
3. Verify all automatic scram signals are clear, with the exception ofSDV high level.
4. Verify all NI-SOP-l steps are completed up to bypassing SDV high level trip.
5. Markup N l-SOP-I to the conditional step to bypass SDV high level trip.
6. Set trigger 1 event as "zcrprest== 1".
7. Set trigger 1 command as "set rdlsdv = 390".

Directions to the InstructorlEvaluator:

None 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 1concurrent 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 1Evaluator:

1. Critical steps are identified in grading area as PasslFaii.
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.
  • Peer verification shall be demonstrated.

References:

1. NUREG 1123,295006 AAl.07 (4.1/4.1)
2. NI-SOP-l Tools and Equipment: None NRC 2013 JPM S-8 May 2013

Task Standard: Reactor scram reset, all control rods verified at position 00, and SDV high level scram un bypassed.

Initial Conditions:

1. A manual Reactor scram was initiated 5 minutes ago due to high Turbine vibrations.
2. NI-S0P-I, Reactor Scram, is being executed.
3. Instructor to ask operator for any questions.

Initiating Cue:

"(Operator's name), reset the Reactor scram, verify all control rods are at position 00, and un-bypass the SDV high level trip, per Nl-SOP-I."

Performance Steps Standard Grade

1. Provide repeat back of initiating cue Proper communications used (GAP-OPS-Ol) SatlUnsat Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME _______
2. Obtain a copy ofthe reference procedure NI-S0P-l obtained SatlUnsat and review/utilize the correct section ofthe procedure
3. If ALL rod motion has stopped, then place Rotates SCRAM DISCHARGE VOL HIGH PassfFaii both SCRAM DISCHARGE VOLUME LEVEL BYPASS CH 11-1/12-1 switch CW HIGH LEVEL BYPASS switches in to BYPASS BYPASS Rotates SCRAM DISCHARGE VOL HIGH PassfFaii LEVEL BYPASS CH 11-2112-2 switch CW to BYPASS
4. If auto-initiated scram signals have cleared Observes all auto-initiated scram signals have SatlUnsat on CH 11 or CH 12, then: cleared or been bypassed (SDV high level)
5. Verify at least 1 CRD pump in service Observes CRD pump green light off, red light SatlUnsat on, amps
6. Reset Reactor Scram Depresses REACTOR TRIP RESET PassfFaii pushbutton
7. Verify ALL control rods inserted to Observes all control rods are inserted to SatlUnsat position 04 OR beyond by observing one position 00 OR more of the following:
  • Full Core Display
  • KI04A&B Red LED lights LIT (1 S20 AuxCR)

NRC 2013 JPM 8-8 May 2013

Performance Steps Standard Grade

8. ConfIrm the following valves open:
  • 44.2-15 AND 44.2-16, CONTROL Observes 44.2-15 green light off, red light on SatlUnsat ROD DRIVE DUMP VOL VENT VALVE Observes 44.2-16 green light off, red light on SatlUnsat
  • 44.2-17 AND 44.2-18, CONTROL Observes 44.2-17 green light off, red light on SatlUnsat ROD DUMP VOL DRAIN IV Observes 44.2-18 green light off, red light on SatlUnsat
9. Confirm F3-2-4, CRD DRAIN - VENT Observes F3-2-4 NOT lit SatiUnsat VALVE CLOSED, clear.
10. If:
  • F3-1-4, CONT ROD DRIVE SCRAM Observes F3-1-4 NOT lit SatlUnsat DUMP VOLUME WTR LVL HIGH, clears AND
  • F 1-1-8, RPS CH 11 SCRAM DUMP Observes F 1-1-8 NOT lit SatlUnsat VOL WTR LVL HIGH, clears AND
  • F4-1-1, RPS CH 12 SCRAM DUMP Observes F4-1-1 NOT lit SatlUnsat VOL WTR LVL HIGH, clears then:

Note: It will take a few minutes after the scram is reset for these annunciators to clear.

11. Place SCRAM DISCHARGE VOL HIGH Rotates SCRAM DISCHARGE VOL HIGH PasslFaii LEVEL BYPASS switches to DISCH LEVEL BYPASS CH 11-1112-1 switch CCW VOL. to DISCH VOL.

Rotates SCRAM DISCHARGE VOL HIGH PasslFail LEVEL BYPASS CH 11-2/12-2 switch CCW to DISCH VOL.

12. ConfIrm F3-3-4, RPS CRD SCRAM Observes F3-3-4 NOT in alarm SatlUnsat DUMP VOL BY-PASS, clears.

Terminating Cne: Reactor scram reset, all control rods verifIed at position 00, and SDV high level scram un bypassed.

RECORD STOP TIME _ _ __

NRC 2013 JPM 8-8 May 2013

Initial Conditions:

1. A manual Reactor scram was initiated 5 minutes ago due to high Turbine vibrations.
2. NI-SOP-I, Reactor Scram, is being executed.

Initiating Cue:

"(Operator's name), reset the Reactor scram, verify all control rods are at position 00, and un-bypass the SDV high level trip, per NI-SOP-I."

NRC 2013 JPM 8-8 May 2013

NRC JPM P-1 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Initiating Emergency Cooling System #11 Locally Revision: NRC 2013 Task Number: N/A Approvals:

NIA - Exam Security /

General Supervisor " Date General Supervisor Date Operations Training (Designee) Operations (Designee)

Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _(RO/SRO)

TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: _ _ _ _ Perform _ _~-"-__ Simulate Evaluation Location: ------__ Plant _ _ _ _ _ _ Simulator Expected Completion Time: 15 minutes 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 un sat or individual competency area unsat requires a comment.

Comments:

Evaluators Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC 2013 JPM P-l May20l3

Recommended Start Location: (Completion time based on the start location)

Turbine Building elevation 261 '

Simulator Set-up (if required):

None Directions to the InstructorlEvaluator:

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 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:

1. Critical steps are identified in grading areas Pass/Fail. All steps are sequenced critical unless denoted by a "e".
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.

References:

1. NUREG 1123,207000, A2.08, RO 3.8, SRO 3.8
2. NI-0P-13 Tools and Equipment:

None NRC 2013 JPM P-1 May 2013

Task Standard: Emergency Condenser Loop 12 placed in service locally.

Initial Conditions:

1. The Reactor has failed to scram and NI-EOP-3 has been entered.
2. The Emergency Condenser Condensate Return Valves have failed to open.
3. NI-0P-13 section H.2 is complete through step 2.3.
4. Instructor to ask operator for any questions.

Initiating Cues:

"(Operator's name), place Emergency Condenser Loop 11 in service by opening the Condensate Return Valve locally in accordance with NI-0P-13 starting at step H.2.4."

Performance Steps Standard Grade

1. Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME _______

2. Obtain a copy of the reference procedure NI-0P-13 obtained, precautions & limitations SatlUnsat and review/utilize the correct section of the reviewed & section H.2 referenced procedure
3. Close 113-529, BV-IA Manifold Supply to 113-529 handwheel rotated fully CW PasslFaii

-A-22110-C SH. 14.

Cue: The indicated handwheel is rotated fully in the direction indicated.

4. Using wrench, remove cap from 113-530, Cap removed from 113-530 by rotating CCW PasslFaii Vent-IA Manifold Cue: The cap is removed.

Note: A wrench is hanging below the air pipe.

5. Open 113-530 113-530 handwheel rotated fully CCW PasslFaii Cue: The indicated handwheel is rotated fully in the direction indicated. No air flow is heard.

Role Play: If contacted as Control Room, report that Emergency Condenser 11 has NOT gone into service.

NRC 2013 JPM P-l May 2013

Role Play: [f contacted as Control Room on how to proceed, direct initiation of Emergency Condenser 12 locally.

6. Close 113-532, BV-IA MANIFOLD 113-532 handwheel rotated fully CW Pass/Fail SUPPLY TO - A-221 1O-C SH.14 Cue: The indicated handwheel is rotated fully in the direction indicated.
7. Using wrench, remove cap from 113-533, Cap removed from 113-533 by rotating CCW Pass/Fail Vent-IA Manifold Cue: The cap is removed.

Note: A wrench is hanging below the air pipe.

8. Open 113-533 113-533 handwheel rotated fully CCW Pass/Fail Cue: The indicated handwheel is rotated fully in the direction indicated. Air flow is heard.

Role Play: If contacted as Control Room, report that Emergency Condenser 12 has gone into service.

9. Reports task completion. Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)

Terminating Cue: Emergency Condenser Loop 12 placed in service locally.

RECORD STOP TIME _ _ __

NRC 2013 JPM P-I May 2013

Initial Conditions:

1. The Reactor has failed to scram and NI-EOP-3 has been entered.
2. The Emergency Condenser Condensate Return Valves have failed to open.
3. NI-OP-I3 section H.2 is complete through step 2.3.

Initiating Cues:

"(Operator's name), place Emergency Condenser Loop 11 in service by opening the Condensate Return Valve locally in accordance with NI-OP-I3 starting at step H.2.4."

NRC 2013 JPM P-l May 2013

NRC JPM P-2 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Respond to RBCLC Makeup Tank Level Alarm Revision: NRC 2013 Task Number: N/A Approvals:

General Supervisor

, Date NIA - Exam Security General Supervisor I

Date Operations Training (Designee) Operations (Designee)

NtA - Exam Security I Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _(.RO/SRO)

TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: _ _ _ _ Perform _ _---"-=---_ _ Simulate Evaluation Location: ~~__ Plant - - - - - - Simulator Expected Completion Time: 15 minutes Time Critical Task: No Alternate Path Task: Yes Start Time: _ _ __ Stop Time: _ _ _ __ Completion 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 un sat or individual competency area unsat requires a comment.

Comments:

Evaluators Date:_ _ _ _ _ __

NRC 2013 JPM P-2 May 2013

Recommended Start Location: (Completion time based on the start location)

Turbine Building elevation 261 '

Simulator Set-up (if required):

None Directions to the InstructorlEvaluator:

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 ofthis 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 identity 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:

1. Critical steps are identified in grading areas PasslFail.
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.

References:

1. NUREG 1123,295018, AA2.04 (2.9/2.9)
2. ARP HI-4-4 Tools and Equipment:

None Task Standard: CLC makeup tank level restored to normal band.

NRC 2013 JPM P-2 May 2013

Initial Conditions:

1. The Control Room has received annunciator Hl-4-4, CLOSED LOOP COOL MAKEUP TANK LEVEL HIGH-LOW.
2. Computer point Bl15, CLC MU TK LVL - HIGH, is in alarm.
3. Control Room indications show CLC Makeup tank level is 7' and rising.
4. Annunciator Hl-4-5, LQ PROCESS RAD MON, is NOT in alarm.
5. Instructor to ask operator for any questions.

Initiating Cues:

"(Operator's name), perform the field actions for the high CLC Makeup tank level per ARP HI-4-4."

Performance Steps Standard Grade

1. Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME ________

2. Obtain a copy of the reference procedure ARP Hl-4-4 obtained SatlUnsat and review/utilize the correct section of the procedure Note: All valves listed in this JPM are located on Turbine Building elevation 351'. The candidate may also do a visual inspection of a level control valve on Turbine Building elevation 261'.
3. Check status of annunciator H 1-4-5 AND Determines from initial conditions that Hl SatlUnsat if in alarm, perform applicable actions of 5 is NOT in alarm Ann. Hl-4-5 AND continue with actions below
4. Close 71-229, BV-CLC MAKE-UP Closes71-229 by rotating handwheel fully PasslFaii TANK INLET FROM MAKE-UP LCV CW Cue: The indicated handwheel is rotated fully in the indicated direction.
5. Open 71-224, DRAIN - CLC MAKE-UP Opens71-224 by rotating handwheel CCW PasslFaii TANK Cue: The indicated handwheel is rotated in the direction indicated.

NRC 2013 JPM P-2 May 2013

Performance Steps Standard Grade

6. WHEN level is restored to normal range, Observes CLC Makeup tank level SatlUnsat close 71-224, DRAIN - CLC MAKE-UP TANK Cue: CLC Makeup tank level indicates 6' and slowly lowering.

Cue: The indicated handwheel is rotated fully in Closes71-224 by rotating handwheel fully Pass/Fail the direction indicated. CW

7. IF level is steady, THEN reopen 71-229 Observes CLC Makeup tank level SatlUnsat and monitor operation Does NOT reopen 71-229 SatlUnsat Cue: CLC Makeup tank level indicates 7' and slowly rising.
8. IF level continues to rise, THEN throttle Opens71-224 by rotating handwheel CCW Pass/Fail 71-224, CLC MU TANK DRAIN as necessary and notifY SM Cue: The indicated handwheel is rotated in the direction indicated.

Cue: CLC Makeup tank level indicates 6' and Observes CLC Makeup tank level SatlUnsat stable.

9. Reports task completion. Proper communications used (GAP-OPS-OI) SatlUnsat Terminating Cue: CLC makeup tank level restored to normal band.

RECORD STOP TIME _ _ __

NRC 2013 JPM P-2 May 2013

Initial Conditions:

1. The Control Room has received annunciator HI-4-4, CLOSED LOOP COOL MAKEUP TANK LEVEL HIGH-LOW.
2. Computer point B115, CLC MU TK LVL - HIGH, is in alarm.
3. Control Room indications show CLC Makeup tank level is 7' and rising.
4. Annunciator HI-4-5, LQ PROCESS RAD MON, is NOT in alann.

Initiating Cues:

"(Operator's name), perform the field actions for the high CLC Makeup tank level per ARP Hl-4-4."

NRC 2013 JPM P-2 May 2013

NRC JPM P-3 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Lineup to Flood the Reactor Vessel Using the Diesel Fire Pump Revision: NRC 2013 Task Number: N/A Approvals:

General Supervisor I

Date ShJc2 NIA - Exam Security General Supervisor I

Date Operations Training (Designee) Operations (Designee)

NI A - Exam Security I Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _(,RO/SRO)

TrainerlEvaluator:

Evaluation Method: _______ Perform ___--"-"'-___ Simulate Evaluation Location: _~__ Plant __________ Simulator 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: _________________________

NRC 2013 JPM P-3 May 2013

Recommended Start Location: (Completion time based on the start location)

NMP Unit 1 Turbine Building Elevation 261' 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 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 / Evaluator:

1. Critical steps are identified in grading areas PasslFail.
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 KA 295031 EA1.08, RO 3.8, SRO 3.9
2. Nl-S0P-21.2, Attachment 4 Tools and Equipment:
1. None NRC 2013 JPM P-3 May 2013

Task Standard: Fire system water entering the RPV through the Feedwater System Initial Conditions:

1. The Control Room has been evacuated due to a fire.
2. Nl-SOP-2L2 has been entered.
3. Instructor to ask for any questions.

Initiating Cues:

"(Operator's name), inject water into the RPV in accordance with Nl-S0P-21.2, Attachment 4, using the Diesel Fire Pump."

1. Provide repeat back of initiating cue Proper communications used SatiUnsat (GAP-OPS-Ol)

Evaluator acknowledge repeat back providing correction ifnecessary RECORD START TIME _ _ __

2. Obtain a copy of the reference procedure Nl-SOP-2L2, Attachment 4 obtained SatiUnsat and review/utilize the correct section of the procedure.
3. Verity locked closed the following valves (TB 261 '):
  • 29-07, FIRE WATER TO FEED 29-07 verified closed by ensuring handwheel SatiUnsat WATER AFTER SPOOL PIECE (FS in fully CW position and locking device
62) installed
  • 100-33, FIRE WATER FEED 100-33 verified closed by ensuring handwheel SatiUnsat WATER SPOOL PIECE INLET (FS in fully CW position and locking device
63) installed Cue: Valves 29-07 and 100-33 are LOCKED closed.

Note: The lock on these valves would require a VA-I key.

NRC 2013 JPM P-3 May 2013

Performance Steps Standard Grade

4. Remove drain line from 29-07, Feed Locates spool piece and tools PasslFail System blank flange, Remove blank flanges from Feedwater AND Fire System lines, and Install spoolpiece to intertie Feedwater AND Fire System lines Note: Have applicant show where the spool piece and tools are located (next to entrance of the Demin Recycle Valve Room, TB 261' , and in the gang box labeled "For EOP Use Only, Box 1" on the floor beneath the spool piece) and where spool piece is to be installed. The EOP tool box should not be entered.

Cue: The spool piece has been installed Proper communications used SatlUnsat by a Damage Control Team. N I-SOP-21.2 (GAP-OPS-Ol)

Attachment 4 steps 2-4 have been verified complete.

S. Unlock the following valves:

  • 100-33, FIRE WATER TO FEED Lock and restraint removed from 100-33 PasslFail WATER SPOOL PIECE INLET (FS 63)
  • 29-07, FIRE WATER TO FEED Lock and restraint removed from 29-07 PasslFail WATER AFTER SPOOL PIECE (FS 62)

Cue: Valves 100-33 and 29-07 are unlocked.

Note: The lock on these valves would require a V A-I key.

6. Supply the fire header by performing one of the following:
  • Start Diesel Fire Pump. Examinee indicates need to start Diesel Fire PasslFaii Pump per initial conditions Cue: Once Candidate addresses the need to start the Diesel Fire Pump, report that Proper communications used SatlUnsat another Operator in the screenhouse has (GAP-OPS-O 1) started the Diesel Fire Pump.

NRC 2013 JPM P-3 May 2013

Performance Steps Standard Grade

7. When directed by the CRS/SM, open the Determines direction has already been given following valves to begin injection into in initiating cue RPV:
  • 29-07, FIRE WATER TO FEED 29-07 opened by turning handwheel fully PasslFail WATER AFTER SPOOL PIECE CCW
  • 100-33, FIRE WATER TO FEED 100-33 opened by turning handwheel fully PasslFaii WATER SPOOL PIECE INLET CCW Cue: Valves 29-07 and 100-33 are open and injection to the RPV has commenced
8. Verify no leakage at spool piece Verifies by visual inspection that there is no SatlUnsat connections leakage at the spool piece connections Cue: There is no leakage from the spool piece connections
9. Notifies CRS/SM that fire water is Proper communications used SatlUnsat being injected to the RPV (GAP-OPS-Ol)

Role Play: Acknowledge report Terminating Cue: Fire System water entering the RPV through the Feedwater System RECORD STOP TIME _ _ __

NRC 2013 JPM P-3 May 2013

Initial Conditions:

1. The Control Room has been evacuated due to a fire.
2. NI-SOP-21.2 has been entered.

Initiating Cues:

"(Operator's name), inject water into the RPV in accordance with NI-SOP-21.2, Attachment 4, using the Diesel Fire Pump."

NRC 2013 JPM P*3 May 2013

NMP SIMULATOR SCENARIO NRC Scenario 1 REV. 0 No. of Pages: 24 PREPARER ~5H. DATE 'lito),, s VALIDATED Grapes, Lavallee, M. O'Brien DATE 12/19/12 GEN SUPERVISOR OPS TRAINING C::l.~ \) o~ DATE s: .!-z-!n OPERATIONS MANAGER N/A Exam Security DATE CONFIGURATION CONTROL N/A Exam Security DATE SCENARIO

SUMMARY

Length: 60 minutes Initial Power Level: Approximately 95%

The scenario begins at approximately 95% power. Containment Spray pump 112 is out of service for maintenance. Steam Packing Exhauster 12 is caution tagged due to high vibrations.

The crew will remove Recirculation pump 12 from service for maintenance while maintaining Reactor power near the initial value. The CRS will determine the appropriate four-loop operating limitations per Tech Specs.

Then, Feedwater Booster pump 11 will trip. The standby Feedwater Booster pump will fail to auto-start. The crew will manually start the standby Feedwater Booster pump to restore normal system pressures. The CRS will determine the Tech Spec impact for loss of a redundant HPCI component.

Next, Powerboard 11 will de-energize due to an electrical fault. This will cause loss of multiple major loads, including a second Recirculation pump, a Service Water pump, and a Circulating Water pump. The crew will respond per N 1-S0P-30.1. This will include lowering Reactor power to restore the plant within single Circulating Water pump operating limitations. The CRS will determine the Tech Spec impact of this power loss.

Next, a steam leak will develop inside Primary Containment. The crew will scram the Reactor and execute N1-EOP-2, RPV Control, and N1-EOP-4, Primary Containment Control. After the scram, Feedwater pump 13 will dis-engage early and Feedwater will fail to automatically shift to the HPCI flow-control mode on low Reactor water level. At lower Reactor pressure, Core Spray Isolation Valves will also fail to automatically open. The crew will be able to restore and maintain Reactor water level by manually injecting with preferred and alternate systems

(Critical Task). Multiple primary containment isolation valves will fail to close on either manual or automatic containment isolation. The crew will be able to manually close these valves. Two Torus-to-Drywell vacuum breakers will fail open, resulting in some steam escaping from the Drywell directly into the Torus airspace. When the crew initiates Containment Spray, Containment Spray pump 111 will trip. These failures will further degrade Primary Containment pressure control. The Pressure Suppression Pressure (PSP) will be exceeded. The crew will blowdown the Reactor per N1-EOP-8 (Critical Task).

Major Procedures: N1-0P-1, N1-S0P-16.1, N1-S0P-30.1, N1-S0P-1.3, N1-S0P-1.1, N1-S0P 1, N1-EOP-1, N1-EOP-2, N1-EOP-4, N1-S0P-40.2, and N1-EOP-8 Dynamic Mitigation Strategy Code: PC4, RPV Blowdown due to PSP EAL Classification: Alert EAL 3.1.1 - High Drywell Pressure Termination Criteria: RPV water level controlled in assigned band, RPV Blowdown in progress, Primary Containment pressure maintained per N1-EOP-4

I. SIMULATOR SET UP A. IC Number: IC-151 B. Presets/Function Key Assignments

1. Malfunctions:
a. CT01 B, CT Pump 112 Trip PRESET
b. FW02A, FEEDWATER BOOSTER PUMP TRIP 11 TRG 1
c. ED04, PB 11 Electrical Fault TRG2
d. EC01, Steam Supply Line Break in PC, FV=11 % TRG3
e. FW06, SHAFT DRIVEN FEEDWATER PUMP CLUTCH FAILS

- DISENGAGES, Delay=20 seconds TRG23

f. PC10A, BV 68-01 Fails Open, Delay=2:00 TRG23
g. PC10C, BV 68-03 Fails Open, Delay=2:00 TRG23
h. FW28A, HPCI MODE FAILURE TO INITIATE 11 PRESET
i. FW28B, HPCI MODE FAILURE TO INITIATE 12 PRESET
j. CS07, CS Injection Valves Failure to Auto Open PRESET
k. CT01A, CT Pump 111 Trip PRESET
2. Remotes:
a. None
3. Overrides:
a. 7S43D14116, POS_3 4H17/51-02A C FRM B, FV=off (FWBP 13 auto-start failure) PRESET
b. 11 S33D15423, SET 1010 RPS CH.11 BYPASS SW, FV=on (Partial primary containment isolation failure) PRESET
c. 11S34D15424, SET 1010 RPS CH.12 BYPASS SW, FV=on (Partial primary containment isolation failure) PRESET
4. Annunciators:
a. None
5. Triggers:
a. TRG 23 - Initiates when the mode switch is taken to SHUTDOWN
i. Event Action: zdrpstdn==1 ii. Command: imf ec01 (O 0) 30 4:00 11
b. TRG 24 - Initiates when Containment Spray flow is initiated
i. Event Action: ctfdw> 100 ii. Command: imf ec01 (0 0) 45 1:00 30

C. Equipment Out of Service

1. Containment Spray pump 112 in PTL with yellow tag
2. Containment Spray suction valve 112 closed with yellow tag
3. Steam Packing Exhauster 12 green-flagged with yellow tag D. Support Documentation
1. RMI for Recirculation pump stop E. Miscellaneous
1. Note the failure of Core Spray to automatically inject is required to make the manual establishment of preferred and alternate injection sources a critical task when HPCI fails to automatically initiate.
2. Ensure Drywell cooling fan 11 is secured with control switch in neutral.
3. Ensure Service Water pump 11 is running and Service Water pump 12 is secured.
4. Protect the following equipment: EDG 103, PB 103, PB 12
5. Update Divisional Status Board

II. SHIFT TURNOVER INFORMATION OFF GOING SHIFT: [] N 'D DATE: Today PART I: To be performed by the oncoming Operator before assuming the shift.

PART II: To be reviewed by the oncoming Operator before assuming the shift.

  • Shift Turnover Checklist (ALL)
  • Computer Alarm Summary (RO)

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

  • Reactor power is approximately 95%.
  • Steam Packing Exhauster 12 is caution tagged due to high vibrations.

PART III: Remarks/Planned Evolutions:

Remove Recirculation pump 12 from service per N1-0P-1 Section H.1.0. Maintain Reactor power near the initial value as Recirculation pump 12 is secured. Recirculation pump 12 will be out of service for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

PART IV: To be reviewed/accomplished shortly after assuming the shift:

  • Review new Clearances (SM)
  • Shift Crew Composition (SM/CRS)

TITLE NAME TITLE NAME SRO ATCRO BOPRO

ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver: Recire Pump Shutdown Step: 1 I INITIAL CONDITIONS/STEP DESCRIPTION I

RE presence required in the Control Room? Yes_ No ./

If YES above, RE presence not required for steps _ .

Parameter crp H

Initial conditions to be verified prior to initiation of step:

Range 1740-1780 MWth Actual Parameter Expected Range Actual Description of Step:

Secure Recirculation pump 12 per N1-0P-1 Section H.1.0. Maintain Reactor power near the initial value as the pump is secured.

Critical parameters to be monitored DURING Step:

Critical parameters not used must be deleted OR marked N/A Critical Parameter Limit Owner Frequency Contingency 35-67.5 Recirc Flow RO Continuous Stop evolution and consult RE.

Mlbm/hr IRMI evaluated against approved power profile:

  • N/A D. I IOther Comments:

I Step Prepared by: Alex <!J.i&d I~ Step Reviewed by: d({dt:~ I~~

RE/STA Date RE/STAISRO Date Approval to perform Step . .c!bhn &nJn I rcM~ Step Completed I Shift Manager Date SRO Date

Critical Tasks:

CT-1.0 Given a LOCA in the Drywell and a failure of HPCI to initiate, inject with preferred and alternate injection systems to restore and maintain RPV water level above -84 inches, in accordance with N1-EOP-2.

Safety Significance: Maintaining Reactor water level above -84 inches ensures adequate core cooling through the preferred method of core submergence. This protects the integrity of the fuel cladding.

Cueing: Multiple Reactor water level indicators and annunciators will provide indications of lowering Reactor water level. N1-EOP-2 provides multiple procedure steps directing injection with preferred and alternate injection systems.

Measurable Performance Indicators: Manipulation of pumps and/or valves in the preferred or alternate injection system(s) will provide observable actions for the evaluation team.

Performance Feedback: Multiple Reactor water level indicators and annunciators will provide performance feedback regarding the success of injection with preferred and alternate injection systems.

CT-2.0 Given a LOCA in the Drywell and degraded Containment Spray capability, execute N1-EOP-8, RPV Slowdown, when it is determined Torus pressure cannot be maintained below the Pressure Suppression Pressure limit, in accordance with N1 EOP-4.

Safety Significance: A Slowdown is required to limit further release of energy into the Primary Containment and to ensure that the RPV is depressurized while pressure suppression capability is still available. This protects the integrity of the Primary Containment.

Cueing: Multiple Primary Containment pressure indicators and annunciators will provide indications. N1-EOP-4 provides direction to monitor the Pressure Suppression Pressure limit and blowdown if required.

Measurable Performance Indicators: The crew will manually open valves to initiate Emergency Condensers. The crew will manually open ERVs.

Performance Feedback: Emergency Condenser and ERV instrumentation will provide indication that these systems are functioning properly once placed in service. Multiple Reactor pressure indicators and annunciators will provide performance feedback regarding the success of the blowdown.

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Take the simulator out of freeze before the crew CREW enters for the pre-shift walkdown and briefing.

  • Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Secure Recirculation Pump 12 While Maintaining Reactor Power SRO
  • Directs securing Recirculation pump 12 per N1-0P-1 Section H.1.0
  • Provides oversight for evolution
  • Determines Core Operating Limits Report (COLR) requires APLHGR penalty BOP
  • Reviews N1-0P-1 Section H.1.0
  • Determines Recirculation pump 12 is NOT in local lock
  • Places RRECIRC PUMP 12 SPEED CONTROL in BAL AND nulls out Deviation Meter (top meter)
  • Places RRECIRC PUMP 12 SPEED CONTROL AUTO/BAllMAN switch to MAN
  • Verifies open REACTOR R PUMP 12 BYPASS VALVE

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 1 continued BOP continued

  • IF desired by the Shift Manager to maintain the plant close to present power level, THEN perform next two steps alternately using up to 1.0 x 106 Ibm/hr increments UNTIL Reactor Recirc Pump 12 flow is 6 to 8 x 106 Ibm/hr:
  • Reduces Recirculation pump 12 flow up to 1 x 106 Ibm/hr
  • Coordinates with ATC to maintain initial power level ATe
  • Monitors plant parameters
  • Raises Total Recirc flow using the Master Recirc Controller to initial power level as required based on BOP actions
  • Closes REACTOR R PUMP 12 DISCHARGE VALVE
  • WHEN Discharge Valve is closed, places REACTOR RP MOTOR 12 MG SET switch to STOP
  • Holds in OPEN position for 2 to 3 seconds, REACTOR R PUMP 12 DISCHARGE VALVE

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 1 continued BOP continued

  • IF MG set is to be out of service for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, THEN verifies Electrical Maintenance notified to lift brushes off the Generator AN D Exciter slip rings
  • Refers to N1-0P-1 Section H.2.0 for 4 loop operations

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 2 - Feedwater Booster Pump 11 Trips, CREW Standby Pump Fails to Auto-Start

  • Acknowledge/report annunciator H3 When directed by lead examiner, insert 1-6 REACTOR FW BOOSTER P11 malfunction: TRIP
  • Diagnose trip of Feedwater Booster FW02A, FEEDWATER BOOSTER PUMP TRIP 11 Pump 11 TRG 1 The following override prevents Feedwater Booster Pump 12 from Auto Starting on low header discharge pressure:

OVR-7S43D14116 POS_3 4H17/51-02A C FRM B, FV=off PRESET RPV water level lowers Feedwater Booster Pump header pressure lowers Expected Annunciators:

H3-1-6, REACTOR FWBOOSTER P11 TRIP H3-3-7, REACTOR FWPUMP 13 SUCTION SRO

  • Acknowledges report
  • If BOP does not manually start FWBP 12, directs starting FWBP 12
  • Determines redundant component inoperable in HPCI train 11, thus 15 day LCO applies
  • Notifies WECIWWM
  • Notifies Ops Management

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 2 continued ATe

  • Monitors plant parameters
  • May perform Emergency Power Reduction per N 1-S0P-1.1 as required to maintain RPV water level BOP Role Play: When dispatched as Operator to
  • Report alarm and respond per H3-1-6 investigate, wait 2 minutes, then report:
  • Confirms alarm on computer (E049
  • FWBP 11 breaker tripped on overcurrent RX FW BOOST PMP 11 TRIP)
  • No abnormal indications at FWBP 12 breaker
  • Recognizes/diagnoses failure of the
  • No abnormal indications at FWBP 11 or 12. standby pump to automatically start
  • Manually starts FWBP 12 Role Play: When dispatched as Operator to swap
  • Notifies crew of failure of FWBP 12 to HWC, wait 5 minutes and report that HWC injection auto start has been transferred from FWBP 11 to FWBP 12.
  • Dispatches operators to shift Hydrogen Water Chemistry injection from FWBP 11 to FWBP 12

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 - Powerboard 11 Electrical Fault CREW When directed by lead examiner, insert

  • Diagnose/report loss of PB 11 malfunction:
  • Recognize/report loss of:
  • Drywell Fans 14, 15, 16 TRG2
  • Condensate Pump 11
  • Circulating Water Pump 11 Reactor power lowers due to RRP trips
  • TBClC Pump 11 A4-1-1, PB 11 R113 TRIP
  • lAC 11 A4-4-2, POWER BD 16 LOW BUS VOLTAGE
  • Reactor Building Exhaust Fan 11 L 1-3-4, REACT BLDG/ATM DIFF PRESS
  • Recognize/report drop in Reactor Also the following equipment trips:

power Reactor Recirculation Pump 11

  • Recognize/report lowering condenser Drywell Fans 14, 15, 16 vacuum Condensate Pump 11
  • Recognize/report loss of Reactor Circulating Water Pump 11 Building D/P Service Water Pump 11 RBCLC Pump 11 TBCLC Pump 11 lAC 11 Reactor Building Exhaust Fan 11 SRO
  • Acknowledges reports from crew
  • Directs entry into N 1-S0P-30.1
  • Directs Emergency Power Reduction per N 1-S0P-1.1 to stabilize condenser vacuum, as necessary
  • Provides oversight for reactivity manipulation
  • Directs entry into N1-S0P-1.3, Recirculation Pump Trip

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 3 continued SRO continued

  • Directs RO to re-energize Powerboards 16A and 13A-15A
  • Directs restoration of Reactor Building DIP with either RBVS or RBEVS
  • May direct entry into N1-S0P-6.1 for loss of Spent Fuel Pool Cooling, as time permits
  • Reviews Technical Specifications
  • Acknowledges that the APRMs are inoperable while the RRP discharge Note: On the loss of Powerboard 11, Recirc pump valves are still open 11 trips. The APRMs are inoperable due to
  • Determines Technical Specification reverse flow through the tripped Recirc loop. The 3.1.7.e limits Reactor power to 90% in APRMs will be declared operable once the 3 loop operation discharge valve is closed.
  • Determines Core Operating Limits Report (COLR) requires APLHGR and MCPR penalties

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued ATC

  • Acknowledges direction from SRO
  • Confirms plant is stable by verifying:

No thermal hydraulic Instability 3 Recirc pumps running Not operating in the Restricted Zone

  • Executes N1-S0P-1.1, Emergency Power Reduction, to lower recirc flow and/or insert CRAM rods to stabilize condenser vacuum, as required
  • Determines plant operating point on the 3-loop power to flow curves Role Play: BOP If dispatched to investigate Powerboard 11, wait 2
  • Executes N1-S0P-30.1, loss of minutes then report that the normal supply breaker Power Board 11 (R113) tripped on overcurrent.
  • Starts Service Water pump 12 If dispatched to investigate Powerboard 16A, wait 2
  • Coordinates with ATC to monitor minutes then report that there are no problems APRMs and lPRMs evident at Powerboard 16. Report that electrical
  • Verifies TBClC pump 12 running maintenance has also looked at the Powerboard
  • Verifies lAC 12 and/or 13 running and concurs with re-energizing it.
  • Verifies RBClC pump 12 running
  • Verifies Steam Packing Exhauster 12 Role Play: running If dispatched to lineup Steam Packing Exhauster
  • Answers "Are A4-4-6, A4-4-7, A4-1-3 12, wait 4 minutes, then insert remote:

OR A5-2-8 in alarm" YES MS09, SPE 12 SUCTION VlV, FV=open

  • Determines Power Board 11 is faulted Then report task completion.

and cannot be reenergized If asked to also close suction valve to Steam Packing Exhauster, wait 2 minutes, then insert remote:

MS08, SPE 11 SUCTION VLV, FV=close Then report task completion.

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued

  • Restores power to Powerboard 16A as follows:
  • Opens R1041
  • Closes R 1042
  • Verifies Power Board 16B amps

<962 Role Play: As operator when directed to energize

  • Dispatches operator to re-energize Powerboards 13A-15A, acknowledge order. If Power Boards 13A, 14A, and 15A asked about status during remainder of scenario,
  • Closes Recirc pump 11 discharge valve
  • Holds open for 2-3 seconds Recirc pump 11 discharge valve
  • Records time when Recirc pump 11 discharge valve is cracked open
  • Executes N1-S0P-1.3, Recirc Pump Trip, as time permits Role Play: As operator when directed to restore
  • Dispatches operator to restore Offgas Offgas vacuum pump, acknowledge order. If called Vacuum Pump for a status on actions, report that you are being briefed by the WECo
  • Enters N1-S0P-6.1 for loss of Spent Fuel Pool Cooling, as time permits Role Play: As operator when directed to
  • Dispatches operator to investigate loss of Spent Fuel Pool Cooling, as time investigate Spent Fuel Pool Cooling, wait 3 minutes permits and then report that SFPC pump 11 has tripped.

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued

  • L 1-1-5, RB VENT EXH FAN 11-12 TRIP-VIB o Verifies closed Reactor Building Exhaust Fan 11 outlet damper o Starts Reactor Building Exhaust Fan 12
  • L 1-3-4, REACT BLDG/ATM DIFF PRESS o Starts RBEVS per OP-1 0 Possible actions in OP-10 Section H.1.0 to start RBEVS
  • Verifies open 202-36, EM VENTILATION FROM REACTOR BLDG BV
  • Verifies closed the following valves:
  • 202-47, EM VENTILATION TIE BV
  • 202-74, EM VENTILATION LOOP 11 COOL! NG BV
  • 202-75, EM VENTILATION LOOP 12 COOL! NG BV
  • Places 202-37(38), EM VENTILATION LOOP 11(12) INLET BV control switch to OPEN

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued

  • Verifies open 202-37(38), EM VENTILATION LOOP 11(12) INLET BV
  • Starts 202-53(33), EVS FAN 11 (12)
  • Verifies open 202-34(35), EM VENT EXHAUST FAN 11 (12) OUTLET BV
  • Confirms proper operation of 202 50(51), EM VENT EXHAUST FAN 11(12) INLET FCV, by observing indicating lights and flow indication Role Play: As RP, acknowledge report that
  • Notifies Rad Protection that the RBEVS is in service and RBVS is secured. Reactor Building Emergency Ventilation system is in service

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4,5,6, 7 & 8 - Steam Leak Inside CREW Primary Containment, Vacuum Breaker Fails

  • Diagnose/report degrading Open. Failure of HPCI to Auto-Initiate. Partial containment parameters Primary Containment Isolation Failure. and Trip
  • Diagnose failure of HPCI to When directed by the lead examiner, insert automatically initiate malfunction:
  • Diagnose partial failure of primary containment isolation EC01, Steam Supply Line Break in PC, FV=11
  • Diagnose the trip of Containment TRG3 Spray pump 111 Drywell humidity, pressure and temperature rise Drywellieakage rises Expected annunciators:

H2-1-1, Drywell Floor Drain Level High H2-4-7, Drywell Water Leak Detection Sys K2-4-3, Drywell Pressure High-Low F1-1-5(4-1-4), RPS Ch 11(12) Drywell Press High Verify the following malfunctions are preset:

FW28A, HPCI Mode Failure to Initiate 11 FW28B, HPCI Mode Failure to Initiate 12 CT01 A, CT Pump 111 Trip CS07, CS Injection Valves Failure to Auto Open Feedwater pump 12 running but not injecting RPV water level slowly lowering Containment Spray pump 111 red light off, green light on and amps go to zero Core Spray IVs do NOT open at 365 psig Expected annunciator:

K1-1-7, Containment Spray Pump 111 Trip Fail to Run

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 4, 5, 6, 7 & 8 continued SRO

  • Acknowledges reports Verify the following malfunctions automatically
  • Directs manual scram insert when the mode switch is taken to
  • Acknowledges scram report SHUTDOWN:
  • Enters N1-EOP-2 on low RPV water FW06, SHAFT DRIVEN FEEDWATER PUMP level CLUTCH FAILS - DISENGAGES, Delay=20
  • Directs N1-S0P-1 actions seconds
  • Directs RPV water level controlled 53 EC01, Steam Supply Line Break in PC, IV=11, 95" with Condensate/FW and CRD RT=4:00, FV=30
  • When notified of the failure of HPCI PC10A, BV 68*01 Fails Open, Delay=2:00 to initiate, directs manual control of PC10C, BV 68-03 Fails Open, Delay=2:00 Feedwater (preferred and alternate TRG23 injection systems)

Containment conditions further degrade CT*1 Feedwater pump 13 disengages

  • Directs RPV pressure controlled 800 Reactor water level remains low 1000 psig with Turbine Bypass Valves Two Torus-to-Drywell vacuum breakers indicate or Emergency Condensers open
  • May direct closure of MSIVs to limit Expected annunciator:

cooldown rate K1-4-6, Torus-OW Vac Relief Check Valve Open

  • Enters N1-EOP-4 due to high drywell pressure and temperature o Direct lockout of Containment Verify the following overrides are PRESET to Spray pumps cause partial primary containment isolation failure:
  • Re-enters N1-EOP-2 due to high 11S33D15423, SET 1010 RPS drywell pressure CH.11 BYPASS
  • Directs execution of N1-S0P-40.2 for SW, FV=on isolation verification 11 S34DI5424 SET 1010 RPS
  • Acknowledges partial failure of primary CH.12 BYPASS containment isolation SW, FV=on
  • Directs/acknowledges manual closure of primary containment isolation valves Verify the following malfunction automatically inserts when Containment Spray flow is initiated to the Drywell:

EC01, Steam Supply Line Break in PC, IV=30,

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS RT=1 :00, FV=45 SRO continued

  • When Torus pressure exceeds 13 Events 4,5,6, 7 & 8 continued psig or Drywell temperature approaches 300°F:
  • Verifies all Recirc pumps tripped
  • Directs trip of all Drywell cooling fans
  • Evaluates/monitors position on Pressure Suppression Pressure curve
  • May direct rapid depressurization with ECs in anticipation of RPV Slowdown
  • Determines Torus pressure cannot be maintained within Pressure Suppression Pressure limit
  • Enters N1-EOP-8, RPV Slowdown CT-2
  • Answers "Drywell pressure?" At or above 3.5 psig
  • May direct prevention of Core Spray injection per N1-EOP-1 Note: Core Spray injection will only be prevented if attachment 4 not needed for core cooling. If the crew has not yet
  • Directs EC initiation re-established RPV injection when this step is
  • Answers "Torus water level?"

evaluated, the Core Spray jumpers may not be Above 8.0 ft installed until later. EOP-2 step P-1 provides

  • Directs open 4 ERVs continuous guidance for this consideration.

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4.5,6, 7 & 8 continued ATC

  • Monitors plant parameters
  • When directed, places Mode Switch in Shutdown
  • Performs N1-S0P-1, Reactor Scram, scram verification actions
  • Places I RMs on range 9
  • Down-ranges IRMs as necessary to monitor power decrease
  • If recirc pumps have not yet tripped, reduces recirc flow to 25 43 Mlbm/hr
  • Maintains RPV pressure below 1080 psig and in assigned band
  • Executes N1-S0P-40.2
  • Recognizes/reports failure of multiple primary containment isolation valves to automatically close
  • Manually closes the following valves:

Note:

  • 201.7-01 & 02, 201.2-110 &

The failed primary containment isolation valves are 111, 201.2-109 & 112 controlled by three control switches.

(11 H202)

  • 201.2-23 & 24, 201.2-29 & 30 (12 H202)
  • 201.7-08 & 09,201.7-10 & 11 (Drywell CAM)

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4. 5. 6, 7 & 8 continued BOP

  • Monitors/reports degrading Containment parameters
  • Performs RPV water level control actions of N1-S0P-1, Reactor Scram:
  • Restores RPV level to 53-95" by controlling injection and rejecting through RWCU
  • Determines #13 FWP was running
  • Determines RPV water level is Note: Feedwater level control actions will vary recovering depending on when the operator diagnoses the
  • Terminates 13 FWP injection as failure of HPCI to automatically control injection follows:

through Feedwater flow control valves 11 and 12.

  • Closes 13 FWP VALVE CONTROL
  • Disengages 13 FWP
  • Closes 29-10, Feedwater Pump 13 Blocking Valve
  • Verifies RPV water level above 53"
  • Verifies 11112 FWP controllers in MANUAL and set to zero output
  • Places FWP BYPASS Valve 11 or 12 in AUTO, sets to 65-70 inches
  • If RPV level reaches 85 inches and rising, then:
  • Verifies off all FW Pumps
  • Secures CRD Pumps not required
  • Diagnoses failure of HPCI to automatically initiate
  • Notifies SRO/Crew of HPCI failure
  • Manually controls RPV injection to restore and maintain level CT-1

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 4, 5, 6, 7 & 8 continued ATC/BOP

  • Closes MSIVs, as directed
  • Reports when Torus pressure exceeds 13 psig or Drywell temperature approaches 300°F
  • Verifies Recirc pumps tripped
  • Trips Drywell cooling fans
  • If 80-118 is open for Torus Cooling:
  • Opens 80-35
  • Verifies open 80-40 and 80-45 needed before EOP-1 attachment 4 jumpers can
  • Prevents Core Spray injection be installed due to scenario progression and installing N1-EOP-1 attachment 4 resource limitations. If Core Spray pumps are jumpers (17, 18, 19,24,25,26), if placed in PTL, at least one Core Spray pump directed should be restarted after jumper installation for App
  • Initiates both ECs J water seal. Core Spray may also be used as an
  • Opens 4 ERVs alternate injection source.

CT-2 Terminating Cues:

  • RPV water level controlled in assigned band
  • RPV Slowdown in progress

NMP SIMULATOR SCENARIO NRC Scenario 2 REV. 0 No. of Pages: 22 Recirc Flow Unit Failure, Emergency MVAR Support. Inadvertent EC Initiation. Intake Grassing.

FWLC Fails As-Is, Un-Isolable EC Steam Leak in Secondary Containment. Mode Switch Fails.

~ BOJMFails PREPARER ~~:n,,1/w1 DATE ij'ld,/t3 VALIDATED Grapes, Lavallee. M. O'Brien DATE 12/19/12 GEN SUPERVISOR OPS TRAINING ~~ t:s = ,~ DATE So J.rj" OPERATIONS "'"

MANAGER N/A - Exam Security DATE _ _ _ __

CONFIGURATION CONTROL N/A - Exam Security DATE _ _ _ __

SCENARIO

SUMMARY

Length: 50 minutes Initial Power Level: Approximately 55%

The scenario begins at approximately 55% power. Containment Spray pump 112 is out of service for maintenance. Steam Packing Exhauster 12 is caution tagged due to high vibrations.

The crew will begin by raising Reactor power with recirculation flow.

Recirculation flow unit 11 fails upscale. The crew will respond per the alarm response procedure and the CRS will determine the Tech Spec impact.

Power Control will call the Control Room and request increased reactive load support to ensure grid voltage is maintained due to loss of generation capacity. The crew will utilize N1-0P-32 and raise MVARs to the grid using the Main Generator automatic voltage regulator.

Next, Emergency Condenser 12 will inadvertently initiate. The crew will secure Emergency Condenser 12. This action will make Emergency Condenser 12 inoperable, but available. The CRS will determine the Tech Spec impact.

An in-flux of grass will lead to clogging of the intake structure. The crew will enter N1-S0P 18.1, trip one Circulating Water pump, and lower Reactor power. During the power reduction, Feedwater Level Control will fail as-is in automatic. The crew will enter N1-S0P-15.1 and take manual control of Feedwater to restore Reactor water level. Once the Circulating Water pump is secured (Critical Task), intake conditions will improve.

Next, a steam leak will develop from Emergency Condenser 11. The crew will attempt to isolate the leak, however the Emergency Condenser will fail to isolate both automatically and manually.

The crew will scram the Reactor (Critical Task) and execute N1-EOP-2, RPV Control, and N1 EOP-5, Secondary Containment Control. The Mode Switch will fail to scram the Reactor, however either RPS push buttons or manual ARI actuation will result in successful control rod insertion. The Bypass Opening Jack Motor (BOJM) will fail to open Turbine Bypass Valves if the crew anticipates blowdown, however the MPR is available to open Turbine Bypass Valves.

Two General Areas of the Reactor Building will exceed the maximum safe temperatures. The crew will blowdown the Reactor per N1-EOP-S (Critical Task).

Major Procedures: N1-0P-19, N1-0P-32, N1-S0P-1S.1, N1-S0P-1.1, N1-S0P-16.1, N1-S0P 1, N1-EOP-2, N1-EOP-5, and N1-EOP-S Dynamic Mitigation Strategy Code: SC1, Primary System Leak in Secondary Containment, Blowdown Required EAL Classification: Site Area Emergency per EALs 3.4.1 (Emergency Condenser Isolation Failure and Release Outside Primary Containment) and/or 4.1.1 (Primary System Discharging Outside Primary Containment, >135°F in Two General Areas)

Termination Criteria: RPV water level controlled in assigned band, RPV Blowdown in progress

I. SIMULATOR SET UP A. IC Number: IC-152 B. Presets/Function Key Assignments

1. Malfunctions:
a. CT01 B, CT Pump 112 Trip PRESET
b. NM36A, RECIRC FLOW CONVERTER CHANNEL 11 FAILURE- UPSCALE TRG 1
c. EC03B, EC RETURN VALVE FAILS OPEN(IV 39-06) TRG2
d. CW17, Intake Traveling Screens Blockage, FV=65%, RT=10:00 TRG3
e. FW14C, Feedwater Master Controller - Fail As Is TRG3
f. EC02, Steam Supply Line Break in RB, FV=20% TRG4
g. EC07A, Emergency Condenser 11 Fails to Isolate PRESET
h. EC08A, EC LOOP 11 STM IV FAIL TO CLOSE 111 , FV=50% PRESET
i. EC08B, EC LOOP 11 STM IV FAIL TO CLOSE 112 , FV=50% PRESET
2. Remotes:
a. FW24 , REMOVAL OF HPCI FUSES FU8/FU9, FV=pulled TRG24
3. Overrides:
a. 13S70014674, POS_1 1E67 REAC. SW.-RUN, FV=on (Mode switch fails to scram) PRESET
b. 13S70014675, POS_2 1E67 REAC. SW.-SHUTOOWN, FV=off (Mode switch fails to scram) PRESET
c. 1A2S701176, POS_2 TC BOJ CLOSE, FV=off (BO.. IM fails to open TBVs) PRESET
4. Annunciators:
a. None
5. Triggers:
a. Trigger 29 - After scram, allows Mode Switch logic to reposition to prevent MSIV closure on low pressure.
i. Event Action: rd:rpscm(1)==1 ii. Command: dor 13S70014674
b. Trigger 30 - After scram, allows Mode Switch logic to reposition to prevent MSIV closure on low pressure.
i. Event Action: rd:rpscm(1)==1 ii. Command: dor 13S70014674

C. Equipment Out of Service

1. Containment Spray pump 112 in PTL with yellow tag
2. Containment Spray suction valve 112 closed with yellow tag
3. Steam Packing Exhauster 12 green-flagged with yellow tag D. Support Documentation
1. RMI for power ascension with Recirculation flow E. Miscellaneous
1. Ensure Drywell cooling fan 11 is secured with control switch in neutral.
2. Ensure the Main Generator is supplying approximately 100 MVARs to the grid with the voltage regulator in automatic.
3. Markup N1-0P-43B Section F.3.0 to the appropriate steps for 55% power level.
4. Protect the following equipment: EDG 103, PB 103
5. Update Divisional Status Board

II. SHIFT TURNOVER INFORMATION OFF GOING SHIFT: D N 'D DATE: Today PART I: To be performed by the oncoming Operator before assuming the shift.

PART II: To be reviewed by the oncoming Operator before assuming the shift.

  • Shift Turnover Checklist (ALL)
  • Computer Alarm Summary (RO)

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

  • Reactor power is approximately 50%.
  • Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO perTS 3.3.7.b).
  • Steam Packing Exhauster 12 is caution tagged due to high vibrations.
  • Circulating Water pump 11 was returned to service following waterbox cleaning earlier in the shift.

PART III: Remarks/Planned Evolutions:

1. Raise Reactor power with Recirculation flow per the provided RMI and N1-0P-43B.

N1-0P-43B Section F.3.0 is in progress.

PART IV: To be reviewed/accomplished shortly after assuming the shift:

  • Review new Clearances (SM)
  • Shift Crew Composition (SM/CRS)

TITLE NAME TITLE NAME SRO ATCRO BOPRO

ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver: Power Ascension from 55% Step: 1 I INITIAL CONDITIONS/STEP DESCRIPTION I

RE presence required in the Control Room? Yes_ No ./

If YES above, RE presence not required for steps _ .

Initial conditions to be verified prior to initiation of step:

Parameter Expected Range Actual Parameter Expected Range Actual CTP 900-950 MWth Description of Step:

Raise Reactor power to approximately 85% with Recirculation flow per N1-0P-43B.

Critical parameters to be monitored DURING Step:

Critical parameters not used must be deleted OR marked N/A Critical Parameter Limit Owner Frequency Contingency 67.5 Recirc Flow RO Continuous Stop evolution and consult RE.

Mlbm/hr Lower power to less than 1850 MWth with CTP 1850 MWth RO Continuous Recirculation flow.

Rod line 108% RO 15 minutes Stop evolution and consult RE.

IRMI evaluated against approved power profile:

  • N/A D. I IOther Comments:

I Step Prepared by: A!t:z GK.eed I 'Cod~ Step Reviewed by: dttck Q;(j)ettll I 'Co~

RE/STA Date RE/STAISRO Date Approval to perform Step dPhn Attron I 'Codap Step Completed by: I Shift Manager Date SRO Date

Critical Tasks:

CT-1.0 Given the plant at power with lowering intake water level, remove a Circulating Water pump from service in order to preserve use of the lake as a heat sink, in accordance with N1-S0P-18.1.

Safetv Significance: Circulating Water pumps draw a large volume of water from the cooling water intake. This intake is shared with pumps from safety significant systems such as Emergency Service Water, Containment Spray Raw Water, and Diesel Generator Raw Water. In the event of lowering intake water level with the plant at power, a Circulating Water pump must be removed from service in order to preserve water in the intake for other systems to maintain use of the lake as a heat sink.

Cueing: Annunciators will alert the crew to the low intake level. Field reports will provide additional information about lowering intake level. N 1-S0P-18.1 provides direction to remove a Circulating Water pump from service.

Measurable Performance Indicators: Manipulation of a Circulating Water pump control switch will provide the observable action for the evaluation team.

Performance Feedback: Lowering Circulating Water pump amps and indications of rising intake water level will provide performance feedback regarding the success of removing the Circulating Water pump from service.

CT-2.0 Given an un-isolable Emergency Condenser leak outside primary containment and one general area temperature above the maximum safe limit, insert a manual reactor scram, in accordance with N1-EOP-5.

Safetv Significance: With an un-isolable primary system discharging outside of Primary Containment resulting in general area temperature above the maximum safe limit, the Reactor must be scrammed. This reduces the rate of energy production and thus the heat input, radioactivity release, and break flow into the Secondary Containment. This also ensures the Reactor is shutdown prior to need for a blowdown.

Cueing: Multiple annunciators will provide indications of a primary system discharging into Secondary Containment. Emergency Condenser valve position indicators will provide indication that the system is un-isolable. Field reports will provide indication that a general area is above the maximum safe temperature limit. N 1-EOP-5 provides direction to scram the Reactor.

Measurable Performance Indicators: Rotation of the Mode Switch to SHUTDOWN or depressing the manual scram pushbuttons will provide observable actions for the evaluation team.

Performance Feedback: Control rod position and Reactor power indications will provide performance feedback regarding the success of the scram.

CT-3.0 Given an un-isolable Emergency Condenser leak outside primary containment and two general area temperatures above the maximum safe limit, execute N1-EOP-8, RPV Blowdown, in accordance with N1-EOP-S.

Safety Significance: An un-isolable primary system discharging outside of Primary Containment resulting in two general area temperatures above the maximum safe limit indicates a wide-spread problem posing a direct and immediate threat to Secondary Containment. A blowdown minimizes flow through the break, rejects heat to the suppression pool in preference to outside the containment, and places the primary system in the lowest possible energy state.

Cueing: Multiple annunciators will provide indications of a primary system discharging into Secondary Containment. Emergency Condenser valve position indicators will provide indication that the system is un-isolable. Field reports will provide indication that two general areas is above the maximum safe temperature limit. N1-EOP-S provides direction to blowdown the Reactor.

Measurable Performance Indicators: The crew will manually open ERVs.

Performance Feedback: ERV instrumentation will provide indication that these valves are functioning properly once placed in service. Multiple Reactor pressure indicators and annunciators will provide performance feedback regarding the success of the blowdown.

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Take the simulator out of freeze before the crew CREW enters for the pre-shift walkdown and briefing.

  • Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Power Ascension With Recirculation SRO
  • Directs power ascension with Recirculation flow lAW N1-0P-438 and the Reactivity Maneuver Instruction (RMI)
  • Provides oversight of reactivity maneuver Note: ATC N1-0P-438 includes the following power-to-flow
  • Acknowledges direction from SRO map restrictions:
  • Raises Recirculation flow with master
  • PRIOR to exceeding 65% flow, verify greater Recirculation flow controller than 50% Rod Line OR that RIP region will
  • Monitors APRMs NOT be entered.
  • Monitors Recirculation flow
  • PRIOR to 100% rodline raise recirc flow to
  • Monitors Feedwater flow and RPV greater than 59% flow (approximately 40 x 106 water level Ib/hr) to avoid the flow biased control rod block
  • Observes power-to-flow map line. restrictions BOP Note:
  • Monitors individual RRPs for response Recommend initiating the next event when Reactor
  • Individual MIA-Speed Control power is between 55-60% power to achieve the stations trending uniformly desired response in Event 6.
  • Individual RRP indications trending normally for speed increase
  • Monitors Feedwater controls for proper response
  • RPV water level remains within program band (65" - 83")

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Event 2 - Recirculation Flow Unit Fails Upscale CREW When directed by lead examiner, insert

  • Recognize/report Recirculation now malfunction: unit 11 failed upscale NM36A, RECIRC FLOW CONVERTER CHANNEL 11 FAILURE* UPSCALE TRG 1 Comparator trip occurs resulting in a Rod Block.

The "FLOW CaMPARA TOR" lamps on the Rod Block Display (PANEL E) will light.

Expected Annunciators:

F2-2-6, APRM FLOW UNIT 11 F3-2-1, APRM FLOW UNIT 12 F3-4-4, ROD BLOCK SRO

  • Acknowledges reports from crew
  • Consults Tech Spec Tables 3.6.2.a and 3.6.2.g
  • Determines a half scram must be placed on RPS channel 11 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
  • Contacts I&C Department for troubleshooting

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 2 continued ATe

  • Verifies proper power to flow ratio on Power Flow Map on E Panel BOP
  • Confirms alarm by observing the following:

o Computer Printout o APRM Flow Comparator on G Panel o LPRM/APRM Trip Auxiliary Panels on G Panel o Rod Block Monitor on E Panel

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Event 3 - Power Control Requests Emergency CREW MVAR Support

  • Acknowledge/report Power Control When directed by lead examiner, call the crew as communication Power Control and make the following report:

"This is Power Control. We are about to lose some generation capacity on the grid due an emergent shutdown of another plant. We need Nine Mile Point Unit 1 to supply an additional 100 MVARs to the grid as soon as possible to ensure stable grid voltage."

SRO Role Play:

  • Acknowledges report from crew If informed as Shift Manager, GSO, Operations
  • Directs raising Main Generator Manager or CENG Generation Dispatch, reactive load by 100 MVARs per N 1 acknowledge report and concur with actions to OP-32 section F raise MVARs as needed.

BOP

  • Executes N1-0P-32 section F
  • Adjusts VOLTAGE REG ADJUSTMENT switch at E console to raise 100 MVARS
  • Adjusts EXCITER RHEOSTAT switch at E console to establish AND maintain between 10 AND 20 Volts Boost on the VOLTAGE REG AMPLIDYNE meter

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 4 - Emergency Condenser 12 Inadvertent CREW Initiation

  • Recognizelreport Emergency When directed by lead examiner, insert Condenser 12 initiation malfunction:
  • Recognize/report Reactor power and water level rising EC03B, EC RETURN VALVE FAILS OPEN (IV 39-
  • Recognize/report no valid Emergency
06) Condenser initiation signal TRG2 EC 12 Condensate Return Valve (39-06) opens Reactor power rises Reactor water level initially rises Expected Annunciators:

K1-1-5, EMER COND CONDEN RET ISOL VALVE 12 OPEN SRO

  • Acknowledges reports from crew
  • Directs securing Emergency If dispatched to investigate 39-06, wait 2 minutes Condenser 12 and then report that there is a significant air leak on
  • Declares Emergency Condenser 12 the air supply line to 39-06. inoperable but available
  • Executes ARP K1-1-5 Reactor water level has stabilized from this event.
  • Closes:

o 39-0BR EC STM ISOLATION VALVE 122, and/or o 39-10R EC STM ISOLATION VALVE 121

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 5 - Intake Grassing CREW When directed by lead examiner, insert

  • Recognize/report lowering intake level CW17, Intake Traveling Screens Blockage, FV=65%, RT=10:00 TRG3 Traveling screen DIP rises Forebay water level lowers Expected Annunciators:

H1-4-3, SCREEN WASH PUMP-SCREEN TRIP La VOL T DIFF PRESS H2-1-3, CIRCULATING WATER PUMP INTAKE LEVEL LOW Note:

The malfunction for Event 6 is inserted with Event

5. Event 6 will become evident when the crew initiates a Reactor power reduction.

SRO Booth Operator:

  • Acknowledges reports When one Circulating Water pump is tripped,
  • Directs entry into N 1-S0P-18. 1, modify malfunction CW17 to 40% over 1 minute. Service Water Failure / Low Intake Level
  • Directs emergency power reduction per N1-S0P-1.1 as needed
  • Provides oversight for reactivity manipulation
  • Acknowledges improving intake level

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 5 continued BOP

  • Executes N1-S0P-18.1, Service Role Plays: Water Failure / Low Intake Level If requested as Operator in field to investigate, wait
  • Updates crew on override 2 minutes, then report: requirements to trip a Circulating
  • A large amount of lake grass is coming in the Water pump and perform an intake and accumulating on the traveling emergency power reduction screens.
  • Trips one Circulating Water pump
  • The traveling screens are operating properly CT-1 but not keeping up with the influx of grass.
  • Monitors intake level
  • Report intake level as indicated by simulator
  • Monitors condenser vacuum, (use screen CW04, Secondary Forebay water Circulating Water temperatures, and level - CWL(4>>. Feedwater response during power reduction Subsequent reports may be given with no delay.
  • Determines/reports intake level improves following Circulating Water Once one Circulating Water pump is tripped and pump trip intake level is improving, report that the traveling screens are catching up and intake level is improving.

ATC

  • Performs emergency power reduction by lowering Recirculation flow and/or inserting CRAM rods per N 1-S0P-1.1 ,

as needed for single Circ Water pump operation

  • Observes APRMs, CTP, and Recirculation flow

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 6 - Feedwater Level Control Fails As-is In CREW Automatic

  • Recognize/report Reactor water level Verify the following malfunction is inserted along deviation from setpoint with Event 5:

F2-3-3, REACT VESSEL LEVEL HIGH-LOW SRO Note:

  • Acknowledges reports If crew does not respond to the malfunction, a
  • Directs entry into N 1-S0P-16.1 ,

Turbine trip / Reactor scram will occur. Continue to Feedwater System Failures Event 7 and initiate TRG 5.

  • Monitors RPV water level
  • Monitors plant parameters BOP
  • Enters N 1-S0P-16.1, Feedwater System Failures
  • Answers "FCV lockup?" NO
  • Answers "FWLC malfunction?" YES
  • Places FW FCV 13 controller in MAN
  • Controls RPV water level in manual

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 7, 8, 9, & 10 - Emergency Condenser 11 CREW Steam Leak In Reactor Building, Emergency

  • Acknowledge/report annunciators Condenser 11 Fails To Isolate, Mode Switch
  • Recognize/report Emergency Fails to Scram, BOJM Fails to Open TBVs Condenser 11 steam leak When directed by the lead examiner, insert
  • Recognize/report failure of Emergency malfunction: Condenser 11 to isolate
  • Recognize/report failure of Mode EC02, Steam Supply Line Break in RB, FV=20% Switch TRG 4
  • May recognize/report failure of BOJM Reactor Building D/P lowers Rising temperatures, pressures and radiation levels in the Secondary Containment RBEVS auto-starts RBVS isolates Expected Annunciators:

L 1-3-4, REACT. BLDG/ATM DIFF PRESS L 1-4-3, REACT BLDG VENT RAD MONITOR OFF NORMAL L 1-3(4)-6, EMER VENT SYS CHANNEL 11(12)

RELA Y OPERA TE MFP2 2-1-1-7, REAC BLDG 318 LOCAL PNL NO.7 FIRE K1-4-3, EMER COOLING SYSTEM 11 STEAM LEAK AREA T HI K1-4-5, EMER COOLING SYSTEM 12 STEAM LEAK AREA T HI L 1-3-3, CONTINUOUS AIR RAD MONITOR H1-4-8, AREA RADIATION MONITORS

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 8 & 9 continued Verify the following malfunctions are preset:

EC07A, Emergency Condenser 11 Fails to Isolate EC08A, EC LOOP 11 STM IV FAIL TO CLOSE 111 , FV=50%

EC08B, EC LOOP 11 STM IV FAIL TO CLOSE 112, FV=50%

Emergency Condenser 11 fails to iso/ate.

Verify the following overrides are preset to cause Mode Switch and BOJM failures:

13S70014674, POS_11E67 REAC. SW.-RUN, FV=on 13S70014675, POS_21E67 REAC. SW.

SHUTDOWN, FV=off 1A2S701176, POS_2 TC BOJ CLOSE, FV=off When control rods insert, verify triggers 29 and 30 automatically initiate and delete the following overrides:

13S70014674, POS_11E67 REAC. SW.-RUN 13S70014675, POS_2 1E67 REAC. SW.

SHUTDOWN

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 8 & 9 continued SRO

  • Acknowledges reports
  • Enters N 1-EOP-5 on high Reactor Building Vent rad levels, high Reactor Building area temperatures I rad levels, and/or loss of RB DIP
  • Directs manual isolation of Emergency Condenser 11
  • Directs Reactor Building evacuation
  • Acknowledges manual isolation failure
  • Directs dispatching of an operator and RP tech to obtain general area temperatures and radiation levels in the Reactor Building
  • Determines area temperatures and/or radiation levels are above setpoints in Tables T and R, and transitions to N1 EOP-5 circle 27
  • Determines a primary system is discharging into the Reactor Building and the discharge cannot be isolated, and transitions to N1-EOP-5 circle 28
  • When any area temperature or radiation level approaches or reaches 135°F or 8 Rlhr, respectively:

Note:

  • Directs manual Reactor scram If the Reactor scrammed due to an earlier event, CT-2 CT-2 will be N/A.
  • Acknowledges scram report
  • Enters N1-EOP-2, RPV Control, on low RPV water level

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 8 & 9 continued SRO continued

  • Answers "Are all control rods inserted to at least position 04?" YES
  • Directs entry into N1-S0P-1, Reactor Scram
  • Directs RPV water level control 53-95" using Feedwater/Condensate and CRD
  • Directs RPV pressure maintained

<1080 psig using TBVs Note: Anticipatory blowdown is likely to be

  • May direct anticipatory blowdown with directed from N1-EOP-2 once one Reactor Building TBVs and/or Emergency Condenser General Area temperature is above 135°F with a 12 with cooldown in excess of second temperature trending towards 135°F. 100oF/hr
  • Acknowledge failure of BOJM, if reported Note:
  • May direct opening TBVs using Emergency Condenser 12 is available even though MPR it was isolated earlier due to inadvertent initiation.
  • Acknowledges reports of Reactor The crew may decide not to use Emergency Building temperatures and radiation Condenser 12 due to actuation of Annunciator K1 levels 4-5, EMER COOLING SYSTEM 12 STEAM LEAK
  • When report is received that 2 General AREA T HI. Areas temperatures are above 1350 F, enters N1-EOP-8, RPV Blowdown
  • Answers "Are all control rods inserted to at least position 04" YES
  • Answers "Drywell pressure?" <3.5 psig
  • May direct initiation of Emergency Condenser 12
  • Answers "Torus water level?" >8 ft
  • Directs open 4 ERVs CT-3

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 8 & 9 continued ATC

  • Monitors plant parameters Note: Prior to the scram, the ATC may also
  • Makes evacuation announcements perform response actions for BOP since Feedwater due to steam leak level control is in manual.
  • Places Reactor Mode Switch to SHUTDOWN
  • Recognizes/reports failure of Mode Switch to scram
  • Performs scram verification actions of N1-S0P-1, Reactor Scram:
  • Confirms all rods inserted
  • Observes Reactor power lowering
  • Places IRMs on range 9
  • Down-ranges IRMs as necessary
  • Reduces Recirc Master flow to 25-43 x 106 lbm/hr
  • Controls RPV pressure as directed using TBVs and/or Emergency Condenser 12
  • May recognize/report failure of BOJM and open TBVs using MPR

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 8 & 9 continued BOP/ATe

  • Attempts to isolate Emergency Note: No General Area temperature information is Condenser 1'I by closing the following available until an Operator has been dispatched to valves per ARP K1-4-3:

the Reactor Building to monitor area temperatures.

  • 39-07R, EC STM ISOLATION The timeline of field reports may be adjusted by VALVE 112 examiner as necessary for evaluation purposes.
  • 39-09R, EC STM ISOLATION VALVE 111 Role Play: When directed as Operator and RP
  • 39-05, EMERG CNDSR COND tech to obtain General Area temperatures and RET ISOLATION VALVE 11 radiation levels in the Reactor Building:
  • 39-11 R, EMERG CNDSR STM SUPPLY DRAIN IV 111 Wait 4 minutes and report RB 318' west side
  • 39-12R, EMERG CNDSR STM temperature is 125°F and rising, radiation level is 2 SUPPLY DRAIN IV 112 mr/hr and rising. Also report that you see steam
  • 05-01 R, EMERG COND VENT coming from the area of the EC steam IV room. ISOLATION VALVE 111
  • 05-11, EMERG COND VENT Note: When one general area temperature is ISOLATION VALVE 112 reported above 135°F and a second general
  • Reports failure of 39-07R and 39-09R area temperature is reported as approaching to close 135°F, the crew is likely to perform an
  • Dispatches operator and RP tech to anticipatory blowdown per EOP-2.

obtain Reactor Building General Area temperatures and radiation levels Wait 2 more minutes and report RB 318' west side

  • Notifies crew of reports on General temperature is 137°F and rising, radiation level is 4 Area temperatures and radiation mr/hr and rising. Report RB 318' east side levels temperature is 123°F and rising, radiation level is 2 mr/hr and rising.

Wait 3 more minutes and report RB 318' west side temperature is 145°F and rising, radiation level is 6 mr/hr and rising. Report RB 318' east side temperature is 136°F and rising, radiation level is 3 mr/hr and rising.

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 8 & 9 continued BOP

  • Performs RPV water level control actions of N1-S0P-1, Reactor Scram:
  • Restores RPV level to 53-95" by controlling injection and rejecting through RWCU
  • Determines #13 FWP was running
  • Determines RPV water level is recovering
  • Terminates 13 FWP injection as follows:
  • Closes 13 FWP VALVE CONTROL
  • Disengages 13 FWP
  • Closes 29-10, Feedwater Pump 13 Blocking Valve
  • Verifies RPV water level above 53"
  • Verifies 11/12 FWP controllers in MANUAL and set to zero output
  • Places FWP BYPASS Valve 11 or 12 in AUTO, sets to 65-70 inches
  • If RPV level reaches 85 inches and rising, then:
  • Verifies off all FW Pumps
  • Secures CRD Pumps not required
  • May initiate Emergency Condenser 12
  • Opens 4 ERVs CT-3 Terminating Cues:
  • RPV water level controlled in assigned band
  • RPV Blowdown in progress

NMP SIMULATOR SCENARIO NRC Scenario 3 REV. 0 No. of Pages: 18 RPS MG Set Trip, CRD FCV Fails Closed, MPR Failure. Failure to Scram. Liquid Poison Pumps PREPARER ~/~J;~;:TriP DATE 'L3D,A3 VALIDATED Grapes. Lavallee. M. O'Brien DATE 12119/12 GEN SUPERVISOR OPSTRAINING C ... ~(\= ~~,~

()

/

S DATE s: b.,to OPERATIONS MANAGER N/A - Exam Security DATE CONFIGURATION CONTROL N/A - Exam Security DATE SCENARIO

SUMMARY

Length: 60 minutes Initial Power Level: Approximately 100%

The scenario begins at approximately 100% power. Containment Spray pump 112 is out of service for maintenance. Steam Packing Exhauster 12 is caution tagged due to high vibrations.

Shortly after the crew assumes the shift, RPS MG Set 131 will trip. This will result in a half scram and loss of two strings of Feedwater heating. The crew will enter N1-S0P-16.1, Feedwater System Failures, and lower power as required to maintain below the license limit.

The crew will re-energize RPS trip bus 131 from I&C Bus 130A, and then reset the half-scram and Feedwater heaters.

Next, Reactor pressure instrument 36-07B will fail downscale. This failure makes one channel inoperable for the RPS high pressure scram. The CRS will determine the Tech Spec impact.

Next, the in-service CRD flow control valve will fail closed. The crew will enter N1-S0P-5.1, Loss of Control Rod Drive, and take action to place the standby flow control valve in service.

The CRS will determine the Tech Spec impact.

Next, the MPR setpoint begins drifting low. This will cause the MPR to take control of and further open Turbine Control/Bypass valves. Reactor pressure will lower until either the crew manually scrams the Reactor, or the Reactor scrams from MSIV closure at 850 psig. The crew will enter N1-S0P-31.2, Pressure Regulator Malfunction, and N1-S0P-1, Reactor Scram.

Multiple control rods will fail to fully insert on the scram. The crew will enter N1-EOP-3, Failure to Scram. The crew will lower Reactor power by tripping Reactor Recirculation pumps and/or terminating and preventing all RPV injection except boron and CRD (Critical Task). The crew

will also take action to insert control rods (Critical Task). The crew will be challenged by a failure of Liquid Poison to inject. Both Liquid Poison pumps will trip shortly after being started.

Once control rod insertion is in progress, the running CRD pump will trip. The crew will be able to start an alternate CRD pump to continue control rod insertion.

Major Procedures: N1-ST-W15, N1-S0P-16.1, N1-S0P-1.1, N1-0P-48, N1-S0P-5.1, N1-S0P 31.2, N1-S0P-1, N1-EOP-3, N1-EOP-3.1, N1-S0P-5.1 Dynamic Mitigation Strategy Code: AT1, High power ATWS, RPV level controlled below feedwater spargers, RPV Blowdown not required EAL Classification: Site Area Emergency per EAL 2.2.2 (Any RPS scram setpoint has been exceeded AND automatic and manual scrams fail to result in a control rod pattern which assures reactor shutdown under all conditions without boron AND either: Reactor power> 6% OR Torus temperature> 110°F)

Termination Criteria: RPV water level controlled in assigned band, RPV pressure controlled in assigned band, control rod insertion in progress or completed

I. SIMULATOR SET UP A. IC Number: IC-153 B. Presets/Function Key Assignments

1. Malfunctions:
a. CT01 B, CT Pump 112 Trip PRESET
b. RP01A, REACTOR TRIP BUS MOTOR GENERATOR TRIPS 131 TRG 1
c. RP16B, RPV PT 36-07B FAILED LOW TRG2
d. RD36A, CRD FCV 44-151 FAILURE - CLOSED TRG3
e. TC08, MECHANICAL PRES. REGULATOR FAILS - LOW TRG20
f. RD33A, CONTROL ROD BANK BLOCKED BANK 1, FV=8 PRESET
g. RD33B, CONTROL ROD BANK BLOCKED BANK 2, FV=8 PRESET
h. RD33C, CONTROL ROD BANK BLOCKED BANK 3, FV=18 PRESET
i. RD33D, CONTROL ROD BANK BLOCKED BANK 4, FV=8 PRESET
j. RD33E, CONTROL ROD BANK BLOCKED BANK 5, FV=8 PRESET
k. LP01A, Liquid Poison Pump 11 Trip, DT=5 TRG 11 I. LP01 B, Liquid Poison Pump 12 Trip, DT=5 TRG12
m. RD35B, CRD Hydraulic Pump 12 Trip TRG5
2. Remotes:
a. RP01, RX TRIP BUS 131 PWR SOURCE, FV=maint TRG29
b. MS01, HP FW HTR 115 RESET, FV=reset TRG30
c. MS03, HP FW HTR 135 RESET, FV=reset TRG30
d. MS04, FW HTR STRING 11 RESET, FV=reset TRG30
e. MS06, FW HTR STRING 13 RESET, FV=reset TRG30
f. RD05, CRD FLOW CONTROL VALVE ISOL, FV=nc30b TRG 21
g. FW24 , REMOVAL OF HPCI FUSES FU8/FU9, FV=pulled TRG24
3. Overrides:
a. 13S73D146713, POS_2 'I E70 TC MPR POS C, FV=on (MPR setpoint drifts low) TRG4
4. Annunciators:
a. None
5. Triggers:
a. TRG 11 -Initiates when Liquid Poison pump keylock switch is taken to SYS 11 position.
i. Event Action: zdlpsys2==1

ii. Command: None

b. TRG 12 - Initiates when Liquid Poison pump keylock switch is taken to SYS 12 position.
i. Event Action: zdlpsys1 ==1 ii. Command: None
c. TRG 20 - Initiates when the Mode Switch is taken to SHUTDOWN
i. Event Action: zdrpstdn==1 ii. Command: dor 13s73di46713
d. TRG 21 -Initiates when the CRD FCV selector switch is re-positioned
i. Event Action: zdrdfcvb==1 ii. Command: None C. Equipment Out of Service
1. Containment Spray pump 112 in PTL with yellow tag
2. Containment Spray suction valve 112 closed with yellow tag
3. Steam Packing Exhauster 12 green-flagged with yellow tag D. Support Documentation
1. None.

E. Miscellaneous

1. Ensure Drywell cooling fan 11 is secured with control switch in neutral.
2. Ensure CRD pump B is running and CRD pump A is in standby.
3. Protect the following equipment: EDG 103, PB 103
4. Update Divisional Status Board

II. SHIFT TURNOVER INFORMATION OFF GOING SHIFT: 0 N , D DATE: Today PART I: To be performed by the oncoming Operator before assuming the shift.

PART II: To be reviewed by the oncoming Operator before assuming the shift.

  • Shift Turnover Checklist (ALL)
  • Computer Alarm Summary {RO}

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

  • Reactor power is approximately 100%.
  • Steam Packing Exhauster 12 is caution tagged due to high vibrations.

PART III: Remarks/Planned Evolutions:

Maintain operation at rated power.

PART IV: To be reviewed/accomplished shortly after assuming the shift:

  • Review new Clearances (SM)
  • Shift Crew Composition (SM/CRS)

TITLE NAME TITLE NAME SRO ATCRO BOPRO

Critical Tasks:

CT-1.0 Given a failure of the Reactor to scram with power above 6% or unknown and RPV water level above -41 inches, lower power to below 6% by:

  • Terminating and preventing all injection except boron and CRD, in accordance with N1-EOP-3.

Safety Significance: High Reactor power after a scram is attempted indicates a challenge to nuclear fuel and to plant heat sinks. In the event of a loss of the normal heat sink, this may result in adding heat to the Torus and challenging the Primary Containment. Lowering Reactor power reduces these challenges.

Cueing: Control rod position and Reactor power indications will indicate a failure to scram with Reactor power above 6%. N1-EOP-3 provides direction to trip Recirculation pumps and terminate and prevent injection based on Reactor power.

Measurable Performance Indicators: Manipulation of Recirculation pump control switches, Feedwater system components, and Core Spray jumpers will provide observable actions for the evaluation team.

Performance Feedback: Lowering Recirculation flow, Feedwater flow, Reactor water level, and Reactor power will provide performance feedback regarding the success of crew actions.

CT-2.0 Given a failure of the Reactor to scram, insert control rods, in accordance with N 1 EOP-3.

Safety Significance: Inserting control rods lowers Reactor power, which reduces challenges to the plant during a failure to scram. Additionally, inserting control rods ultimately provides a long-term, stable core shutdown. Boron injection alone may not provide a stable shutdown condition.

Cueing: Control rod position and Reactor power indications will indicate a failure to scram. N1-EOP-3 provides direction to insert control rods.

Measurable Performance Indicators: Manipulation of RPS, CRD, and RMCS controls will provide observable actions for the evaluation team.

Performance Feedback: Control rod position and Reactor power will provide performance feedback regarding success of crew actions to insert control rods.

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Take the simulator out of freeze before the crew CREW enters for the pre-shift walkdown and briefing.

  • Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - RPS MG Set 131 Trip CREW When directed by lead examiner, insert
  • Diagnose trip of RPS MG set 131 RP01 A, REACTOR TRI P BUS MOTOR GENERATOR TRIPS 131 TRG 1 Scram solenoid lights for RPS 11 de-energize Feedwater temperature slowly lowers Reactor power slowly rises Expected annunciators:

F1-3-7, RX. TRIP BUS M-G SET 131 TROUBLE F1-3-1, RPS CH 11 MAN REACTOR TRIP F1-2-1, RPS CH 11 AUTO REACTOR TRIP SRO

  • Acknowledges reports
  • Directs entry into N1-0P-48 H.4.D
  • Directs entry into N1-S0P-16.1 for loss of Feedwater heating
  • May direct emergency power reduction per N1-S0P-1.1 if needed to control Feedwater temperatures or Reactor power
  • Provides oversight of reactivity changes

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 1 continued ATC

  • Monitors plant parameters Role Play: When dispatched as operator to
  • Lowers power per N1-S0P-1.1 as investigate problem with MG Set 131, wait two required to control Feedwater minutes then report that you can smell burnt temperatures or Reactor power insulation in the vicinity of MG Set 131 motor.
  • Resets half scram Report that the drive motor breaker tripped on overcurrent. If asked, report no overvoltage trip BOP occurred.
  • Dispatches an operator to investigate MG Set 131
  • Determines I&C Bus 130A is available
  • Obtains SRO permission to perform Role Play: When dispatched as operator to dead bus transfer of Reactor Trip Bus transfer Reactor Trip Bus 131 to I&C Bus 130A, 131 wait 2 minutes and insert remote:
  • Dispatches an operator to perform RP01, RP01, RX TRIP BUS 131 PWR SOURCE, dead bus transfer of Reactor Trip Bus FV=maint 131 per N1-0P-48 section H.4.0 TRG 29
  • Acknowledges that Reactor Trip Bus 131 is re-energized Role Play: When dispatched as operator to
  • Dispatches operator to reset MS01, HP FW HTR 115 RESET, FV=reset Feedwater heaters MS03, HP FW HTR 135 RESET, FV=reset MS04, FW HTR STRING 11 RESET, FV=reset MS06, FW HTR STRING 13 RESET, FV=reset TRG 30 Then report Feedwater heaters have been reset.

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 2 - Reactor Pressure Instrument Fails CREW Downscale

  • Recognize/report Reactor pressure When directed by lead examiner, insert instrument failed downscale malfunction:

RP16B, RPV PT 36-07B FAILED LOW TRG2 RPV pressure instrument indicates downscale Expected Annunciators:

F4-4-2, RPS CH 12 REACTOR PRESS LOW F4-4-7, RPS CH 12 MAIN STEAM ISOLATION AUTO OPERA TE SRO

  • Acknowledges reports from crew
  • Enters T.S. Table 3.6.2.a (0), for pressure transmitter 36-078 (Place RPS Channel 11 in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)

ATC Role Play: When directed as Operator to check

  • Monitors plant parameters ATS cabinet indication, wait 2 minutes and report
  • Observes other Reactor pressure that PT 36-078 is downscale with the gross failure indications stable light lit.

BOP

  • Dispatches operator to investigate indications at ATS Cabinet

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 3 - CRD Flow Control Valve Fails Closed CREW When directed by lead examiner, insert

  • Diagnose CRD FCV 11 failed closed RD36A, CRD FCV 44-151 FAILURE - CLOSED TRG3 CRD flow indication indicates low Expected Annunciator:

F3-1-5 CRD CHARGING WTR PRESS HIILO SRO

  • Directs execution of ARP F3-1-S
  • Directs entry into N1-S0P-S.1
  • Directs shifting CRD FCVs per N 1 OP-S, Sect. F.S.O
  • Acknowledges report that CRD FCV 12 is in service
  • Monitors plant parameters

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP

  • Determines CRD FCV is failed closed
  • Enters N1-S0P-5.1
  • Determines standby FCV is to be placed in service per N 1-0P-5 section Role Play: If requested to investigate CRD FCV F.5.0 failure, wait 2 minutes and report that CRD FCV 11
  • Establishes communications between (44-151) appears to have failed closed. Control Room and CRD Flow Control Valves
  • Places FIC 44-146B, CRD FLOW CONTROL, MIA station in MANUAL
  • Directs operator to open the following Role Play: When requested to open 44-148 and valves:

44-152 (step F.5.3.1), wait 1 minute and report o 44-148, CRD FCV 12 INLET valves are open. o 44-152, CRD FCV 12 OUTLET

  • Directs operator to place 113-297 Role Play: When requested to countdown and re SEL-CRD FCV Service Selector in Up position RB Air Transfer Switch (step F.5.3.2.a),

position following countdown perform countdown and report RB Air Transfer

  • Places CRD FLOW CONTROL Switch is in the Up position.

VALVE TRANSFER switch in VALVE 12 position Note: Verify the following remote automatically

  • Directs operator to close the following inserts when the CRD FCV selector switch is valves:

swapped:

o 44-150, CRD FCV 11 INLET o 44-153, CRD FCV 11 OUTLET ROOS, CRO FLOW CONTROL VALVE ISOL,

  • Confirms CRD Flow between 64-66 FV=nc30b gpm TRG 21
  • Places FIC 44-146B, CRD FLOW CONTROL, MIA Station in AUTO Role Play: When requested to close 44-150 and 44-153 (step F.5.3.3), wait 1 minute and report valves are closed.

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 4, 5, 6 and 7 - MPR Setpoint Drifts Low, CREW Failure to Scram, Liquid Poison Pumps Trip.

  • Recognize/report MPR taking control CRD Pump Trips
  • Recognize/report lowering Reactor When directed by lead examiner, insert override: pressure
  • Recognize/report Turbine Bypass 13S73D146713, POS_21E70 TC MPR POS C, valves opening FV=on TRG4
  • Later:

Turbine Control Valves open further o Recognize/report failure to scram Turbine Bypass Valves being to open o Recognize/report trip of Liquid Reactor pressure lowers Poison pumps Expected Annunciators: o Recognize/report trip of CRD A2-4-4, TURBINE MECHANICAL PRESS. REG. IN pump B CONTROL A 1-4-6, TURBINE BY-PASS VALVES OPEN Verify the following malfunctions are preset:

RD33A, CONTROL ROD BANK BLOCKED BANK 1, FV=8 RD33B, CONTROL ROD BANK BLOCKED BANK 2, FV=8 RD33C, CONTROL ROD BANK BLOCKED BANK 3, FV=18 RD33D, CONTROL ROD BANK BLOCKED BANK 4, FV=8 RD33E, CONTROL ROD BANK BLOCKED BANK 5, FV=8 Verify the following malfunctions automatically insert when the respective pump is started:

LP01A, Liquid Poison Pump 11 Trip, DT=5 TRG 11 LP01B, Liquid Poison Pump 12 Trip, DT=5 TRG 12 Control rods partially insert Reactor power remains> 6%

Liquid Poison pumps trip

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 4. 5. 6 and 7 continued SRO

  • Acknowledges reports
  • Directs entry into N1-S0P-31.2, as time permits
  • Enters N1-EOP-2 due to Reactor
  • Inserts malfunction TCOS, MECHANICAL power above 6% when scram required PRES. REGULATOR FAILS - LOW
  • Answers "All rods in to at least 04" NO
  • Deletes override 135730146713, POS_2 1E70
  • Answers "Will the reactor stay TC MPR POS C, FV=on shutdown without boron" NO This fails the MPR completely.
  • Exits N1-EOP-2, enters N1-EOP-3
  • Directs ADS bypassed

injection per N1-EOP-1 Att 4 Once 2-3 control rods have been inserted by the ATC and directed by lead examiner, insert N1-EOP-3 Level Leg Actions (Initial) malfunction:

  • Directs bypass of the low-low RPV RD35B, CRD Hydraulic Pump 12 Trip water level MSIV isolation per N1 TRG5 EOP-1 Att 2 CRD pump 12 trips
  • Determines Reactor power is above 6% and RPV water level is above -41 inches
  • Directs terminate and prevent of all injection except boron and CRD per N1-EOP-1 Att 24 CT-1
  • Directs RPV water level lowered to at least -41 inches

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 4,5,6 and 7 continued SRO continued N1-EOP-3 Pressure Leg Actions

  • If an ERV is cycling:
  • Directs initiation of Emergency Condensers
  • Directs open ERVs to lower RPV pressure to less than 965 psig
  • Monitors Figure M, Heat Capacity Temperature Limit N1-EOP-3 Power Leg Actions
  • Directs initiation of ARI
  • Answers "Turbine Generator on-line?"

NO

  • Answers "Reactor power?" Above 6%
  • Verifies Recirc Pumps tripped CT-1
  • Directs execution of N1-EOP-3.1 CT-2
  • Acknowledges trip of CRD pump 12
  • May enter N 1-S0P-5.1
  • Directs start of CRD pump 11
  • If power oscillates more than 25% or before Torus water temperature reaches 110°F:
  • Records Liquid Poison tank level
  • Directs Liquid Poison injection
  • Acknowledges trip of Liquid Poison pumps
  • Directs alternate boron injection per N1-EOP-3.2

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4, 5, 6 and 7 continued SRO continued EOP-3 Level Leg Actions (Subsequent)

  • Acknowleqges RPV water level below

-41 inches

  • If Torus temperature is above 110°F, then directs level lowered until:
  • Power drops below 6%, OR
  • Level drops to -84 inches (TAF)
  • Records final actual level
  • Directs RPV injection with Condensate/Feedwater and CRD ATC
  • Places Mode Switch in SHUTDOWN
  • Bypasses Core Spray IV interlocks per N1-EOP-1 Att 4 by installing six jumpers inside Panel N (17, 18, 19, 24,25,26)
  • Bypass low-low MSIV isolation per N1 EOP-1 Att 2 by installing four jumpers inside Panel N (1,2,8, 9)
  • When directed, performs N1-EOP 3.1 (See actions below)

CT-2

  • Recognizes/reports trip of CRD pump 12
  • Starts CRD pump 11
  • Injects Liquid Poison, if directed
  • Recognizes/reports trip of Liquid Poison pumps

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Events 4, 6, 6 and 7 continued ATC continued Possible N1-EOP-3.1 Section 3 Actions:

  • Verifies a CRD Pump running
  • Places Reactor Mode Switch in REFUEL
  • Places ARI OVERRIDE switch in OVERRIDE
  • Installs RPS jumpers (5, 6, 12, 13)
  • Inserts rods to 00 using EMER ROD IN starting with high power regions of core (use LPRM indications)

CT-2

  • If more drive pressure is required, then perform one or more of the following:
  • Fully open CRD Flow Control Valve (F panel)
  • Close 44-167, Charging Water Header Blocking Valve (RB 237')

Possible N1-EOP-3.1 Section 4 Actions:

  • Places ARI OVERRIDE switch in OVERRIDE
  • Installs RPS jumpers (5, 6, 12, 13)
  • Verify open 44-167, Charging Water Header Blocking Valve (RB 237')
  • When the SDV is drained, then initiate a manual scram

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4, 5, 6 and 7 continued BOP

  • Manually initiates ARI
  • Terminates and prevents all injection except boron and CRD per N1-EOP-1 Att 24:

CT-1

  • Selects Manual on 11, 12 and 13 FWP Valve Control selector switches
  • Closes 11, 12 and 13 Feedwater FCV (Knurled Knob) full counterclockwise Role Play:
  • Places FW LVL SETPOINT When directed to pull HPCI fuses, wait one minute, SETDOWN to OVERRI DE then insert remote:
  • Directs operator to remove fuses FW24, REMOVAL OF HPCI FUSES FU8/FU9, FU-8 and FU-9 from Panel IS34 in FV=pulled the Aux Control Room TRG24
  • Verifies closed, FEEDWATER Then report task completion.

PUMP 13 BLOCKING VALVE

  • Verifies in MAN, FWP 11 BYPASS VALVE, AND set to zero output
  • Verifies in MAN, FWP 12 BYPASS VALVE, AND set to zero output
  • Informs SRO when RPV water level reaches -41 inches

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4, 5, 6 and 7 continued BOP continued

  • If any ERV is cycling:
  • Initiates Emergency Condensers
  • Manually opens ERVs to lower RPV pressure <965 psig
  • Closes MSIVs, as directed
  • Verifies all Recirc pumps tripped CT-1
  • Initiates Liquid Poison as directed
  • Reports initial tank level
  • Attempts to start Liquid Poison pump 11 and/or 12
  • Determines/reports Liquid Poison pump(s) trip
  • Acknowledges direction to re-establish RPV injection with Condensate/Feedwater and CRD
  • Re-injects with Condensate/Feedwater per N1-EOP-1 Att 24:
  • Reopens at least one Feedwater Isolation Valve 11 and I or 12, if closed
  • Controls injection with Feedwater flow control valves Terminating Cues:
  • RPV water level controlled in assigned band
  • RPV pressure controlled in assigned band

NMP SIMULATOR SCENARIO NRC Scenario 5 REV. 0 No. of Pages: 25 Startup. Sequential Loss of 115 KV Lines. Loss of Vacuum, EDG 102 Fails to Auto-Start. Loss of Coolant Accident. Core Spray Fails to Auto-Start. Emergency Condensers Fail to Operate from Control Room PREPARER DATE 'ljJo/:r VALIDATED Grapes, Lavallee, M. O'Brien DATE 12121/12 GEN SUPERVISOR OPS TRAINING DATE 5}2-/'

OPERATIONS MANAGER NIA - Exam Security DATE CONFIGURATION CONTROL NIA - Exam Security DATE SCENARIO

SUMMARY

Length: 75 minutes Initial Power Level: Approximately 5%

The scenario begins at approximately 5% power during a plant startup. Steam Packing Exhauster 12 is caution tagged due to high vibrations. The crew will raise Reactor power by withdrawing control rods. The crew will then place the Mode Switch in RUN and withdraw IRMs.

Next, 115 KV Line 1 will de-energize. The CRS will determine the Tech Spec impact. Then, Main Condenser vacuum will begin to degrade. The crew will enter N 1-S0P-25.1, Unplanned Loss of Condenser Vacuum. The crew will scram the Reactor before vacuum lowers to 10" Hg.

The continued loss of vacuum will lead to trip of the Turbine Bypass Valves and closure of the MSIVs. The crew will respond to the scram in accordance with N1-S0P-1, Reactor Scram. The crew will establish pressure control using the Emergency Condensers.

Next, 115 KV Line 4 will de-energize. Combined with the earlier loss of Line 1, this will result in a loss of all offsite power. Powerboard 103 will be powered by Emergency Diesel Generator 103. Emergency Diesel Generator 102 will fail to auto-start. The crew will manually start Emergency Diesel Generator 102 to re-energize Powerboard 102. Powerboards 11, 12, and 101 will de-energize. This results in a loss of all Feedwater. The crew will enter N1-S0P 33A.1, Loss of 115 KV.

Once the crew stabilizes the plant, a coolant leak will develop inside the Primary Containment.

The crew will enter N1-EOP-2, RPV Control, and N1-EOP-4, Primary Containment Control.

Emergency Condensers will fail to operate from the Control Room, but may be initiated from the

field. The crew will initiate Containment Spray as Primary Containment conditions degrade (Critical Task). The leak will be beyond the capacity of available high pressure injection sources and Reactor pressure will be above the range of low pressure injection sources. When Reactor water level reaches the top of active fuel, the crew will perform an emergency depressurization per N1-EOP-8, RPV Slowdown (Critical Task). Core Spray will fail to auto start. The crew will control injection systems to restore and maintain Reactor water level above the top of active fuel (Critical Task).

Major Procedures: N1-0P-5, N1-0P-43A, N1-0P-38C, N1-S0P-25.1, N1-S0P-1, N1-EOP-2, N1-EOP-4, N1-EOP-8, N1-EOP-1 Dynamic Mitigation Strategy Code: RL2, Small break LOCA or loss of high pressure injection, RPV level cannot be maintained above the top of active fuel, RPV Slowdown, recover level above TAF with low pressure systems and I or alternate coolant injection systems.

EAL Classification: Alert per EAL 3.1.1, Drywell pressure CANNOT SE MAINTAINED < 3.5 psig due to coolant leakage Termination Criteria: RPV Slowdown in progress, Reactor water level controlled above top of active fuel, Containment pressure and temperature controlled in accordance with N1-EOP-4

I. SIMULATOR SET UP A. IC Number: IC-155 B. Presets/Function Key Assignments

1. Malfunctions:
a. ED02A, 115 kV Line 1 (South Oswego) Loss of Offsite Power TRG 2
b. MC01, MAIN CONDENSER AIR INLEAKAGE, FV=18 TRG 3
c. ED01A, 115 kV Line 4 (JAF) Loss of Offsite Power, Delay=1 :30 TRG 4
d. DG04A, DG 102 FAILURE TO AUTO START PRESET
e. EC04A, EC RETURN VALVE FAILS TO OPEN(IV 39-05) PRESET
f. EC04B, EC RETURN VALVE FAILS TO OPEN(IV 39-06) PRESET
g. EC03A, EC RETURN VALVE FAILS OPEN(IV 39-05) TRG 17
h. EC03B, EC RETURN VALVE FAILS OPEN(IV 39-06) TRG 18
i. RR29, RR Loop Rupture on Pump 15 Suction Line (LOCA), FV=17 TRG 5
j. CS06, CS Pumps Failure to Auto Start PRESET
2. Remotes:
a. RP21, RPS UPS 162 TROUBLE ANN RESET, FV=reset TRG 28
b. RP22, RPS UPS 172 TROUBLE ANN RESET, FV=reset, DT=10 TRG 28
c. ED40A, I&C Bus 130 NC Supply Breaker from PB 13B, FV=open TRG 29
d. ED40B, I&C Bus 130 NO Supply Breaker from PB 167A, FV=close, DT=5 TRG 29
e. FP04, FIRE WTR TO FW BLOCKING VLVS, FV=100 TRG 21
f. CT03A, CT Raw Water Pump 111 Disch. Throttle Valve 93-14, FV=10 TRG 22
g. FW25 , MANUAL OPER. FW FCV-11, FV=O TRG 23
h. FW26 , MANUAL OPER. FW FCV-12, FV=O TRG 24
i. FW27 , MANUAL OPER. FW FCV-13, FV=O TRG 25
3. Overrides:
a. None
4. Annunciators:
a. None
5. Triggers:
a. TRG 4 - Causes loss of Line 4 after the Mode Switch is taken to shutdown
i. Event Action: zdrpstdn==1 ii. Command: None
b. TRG 5 - Causes the LOCA to begin when Powerboard 16 is crosstied
i. Event Action: zded602c==1 ii. Command: None
c. TRG 10- Makes Condenser vacuum degrade faster once the Turbine is tripped
i. Event Action: tc:trip==1 ii. Command: imf mc01 (0 0) 50 C. Equipment Out of Service
1. Steam Packing Exhauster 12 green-flagged with yellow tag.

D. Support Documentation

1. N1-0P-43A marked up to appropriate point for startup.
2. Startup control rod sequence marked up to current rod (06-31 from 04 to 08).

E. Miscellaneous

1. None

II. SHIFT TURNOVER INFORMATION OFF GOING SHIFT: [] N 'D DATE: Today PART I: To be performed by the oncoming Operator before assuming the shift.

PART II: To be reviewed by the oncoming Operator before assuming the shift.

  • Shift Turnover Checklist (ALL)
  • Computer Alarm Summary (RO)

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

  • Reactor power is approximately 5% with a startup in progress.
  • Steam Packing Exhauster 12 is caution tagged due to high vibrations.

PART III: Remarks/Planned Evolutions:

1. Withdraw control rods per the startup sequence. The next control rod to be moved is 06-31 from 04 to 08. Use notch control rod withdrawal. Withdraw the first four rods in the current group, then perform next planned evolution.
2. Place the Mode Switch in RUN per N1-0P-43A steps 4.4 through 4.7.
3. Withdraw the IRMs per N1-0P-43A step 4.10.

Note: Another group of operators has already been assigned the task of inerting the Containment and will control that evolution.

PART IV: To be reviewed/accomplished shortly after assuming the shift:

  • Review new Clearances (SM)
  • Shift Crew Composition (SM/CRS)

TITLE NAME TITLE NAME SRO ATCRO BOPRO

Critical Tasks:

CT-1 Given a LOCA in the Drywell, initiate Containment Sprays prior to exceeding the Pressure Suppression Pressure limit, in accordance with N1-EOP-4.

Safety Significance: Initiating Containment Sprays reduces Primary Containment pressure. This reduces stresses on the Drywell and Torus, assists in avoiding "chugging" that may cause fatigue failure of the LOCA downcomers, and avoids the need for a blowdown. These benefits reduce challenges to the fuel cladding, the RPV, and the Primary Containment.

Cueing: Multiple Primary Containment pressure and temperature indications and annunciators will indicate degrading conditions. N1-EOP-4 provides direction to initiate Containment Sprays.

Measurable Performance Indicators: Manipulation of Containment Spray pump control switches will provide observable actions for the evaluation team.

Performance Feedback: Containment Spray flow and lowering Primary Containment pressure and temperature indications will provide performance feedback regarding success of crew actions to initiated Containment Sprays.

CT-2 Given Reactor water level below the top of active fuel and Reactor pressure above the capacity of available low pressure injection systems, perform an emergency depressurization of the Reactor, in accordance with N1-EOP-2 and N1-EOP-8.

Safety Significance: Reactor water level must be maintained above limits to ensure adequate core cooling. With only low pressure systems available to inject and Reactor pressure above the pressure limits of these systems, Reactor pressure must be quickly lowered to allow injection. This protects the integrity of the fuel cladding.

Cueing: Multiple Reactor water level and pressure indications and annunciators will indicate low Reactor water level with Reactor pressure too high for available injection systems to inject. N1-EOP-2 provides direction to initiate a blowdown.

Measurable Performance Indicators: Manipulation of Emergency Condenser valve and ERV control switches will provide observable actions for the evaluation team.

Performance Feedback: Emergency Condenser and ERV instrumentation will provide indication that these systems are functioning properly once placed in service. Multiple Reactor pressure indicators and annunciators will provide performance feedback regarding the success of the blowdown.

CT-3 Given a LOCA in the Drywell and Reactor water level below the top of active fuel, inject with Preferred and Alternate Injection Systems to restore and maintain Reactor water level above -84 inches, in accordance with N1-EOP-2.

Safety Significance: Maintaining Reactor water level above -84 inches ensures adequate core cooling through the preferred method of core submergence. This protects the integrity of the fuel cladding.

Cueing: Multiple Reactor water level indicators and annunciators will provide indications of lowering Reactor water level. N1-EOP-2 provides multiple procedure steps directing injection with preferred and alternate injection systems.

Measurable Performance Indicators: Manipulation of pumps and/or valves in the preferred or alternate illjection system(s) will provide observable actions for the evaluation team.

Performance Feedback: Multiple Reactor water level indicators and annunciators will provide performance feedback regarding the success of injection with preferred and alternate injection systems.

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Take the simulator out of freeze before the crew CREW enters for the pre-shift walkdown and briefing.

  • Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Raise Reactor Power with Control Rods SRO
  • Directs A TC to withdraw rods per Startup Rod Sequence and N 1-0P-5 section F.1.0
  • Provides oversight for reactivity manipulation ATC
  • Places 4S 1 Control Rod Movement switch to the rod out notch position o Observes SRM and period response o Observes RMCS, RPIS and CRD indications
  • Informs SRO when the first four rods of the current control rod group are withdrawn BOP
  • Monitors plant parameters

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 2 - Place Mode Switch in RUN and SRO Withdraw IRMs

  • Acknowledges first four rods of the current control rod group are withdrawn
  • Directs placing Mode Switch in RUN and withdrawing IRMs per N1-0P-43A
  • Provides oversight for evolution ATC
  • Monitors plant parameters BOP
  • Acknowledges direction from the SRO
  • Confirms APRMs indicate greater than 5% power AND confirm APRM downscale alarms clear, E panel
  • Confirm the following annunciators clear - F1-4-? and F4-4-2
  • Place Mode Switch to RUN
  • Confirm Computer Point COS?, MODE SWITCH RUN - YES
  • Transfer recorder indication to APRM channels
  • Depress the FULL OUT button for each IRM
  • WHEN the IRM detectors indicate full out, THEN range down the individual IRM Range switches to Range 2 OR UNTI L the respective IRM Downscale AND Upscale lights are out on E Console

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 - Loss of Line 1 CREW When directed by lead examiner, insert

  • Recognize/report loss of Line 1 malfunction:

ED02A, 115 kV Line 1 (South Oswego) Loss of Offsite Power TRG2 Breaker R10 opens Expected Annunciators:

A8-1-1, OSW-NMP 1 R10 TRIP A8-1-2, OSW-NMP 1 LINE RELAY TRIP SRO

  • Acknowledges reports
  • Directs execution of ARPs
  • Monitors plant parameters BOP
  • Dispatches an operator to the Aux.

Control Room to observe the following Panels for flags AND targets:

Role Play: o 1D1 OSWEGO NINE MILE POINT If dispatched to Auxiliary Control Room, wait 2 1 minutes, then report an undervoltage target is in on o 1D2 115 KV RESERVE BUS &

panel 1D1 OSWEGO NINE MILE POINT 1. BREAKER R 1O-R40 If dispatched to switchyard, wait 4 minutes, then o 1D3 NINE MILE POINT report R10 is open with no abnormal indications. LIGHTHOUSE HILL 4

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued

  • Observes 86TN relay on Panel 8A to see if it has tripped
  • Observes back of Panel 88 in the Control Room for flags AND targets
  • Records time of trip AND targets
  • Performs N1-0P-33A Section H., Loss 115 kV Line 1:

o Places computer points F432, Role Play: F433, AND F434 on a special log If contacted as Power Control, report that you are computer printout with a one dispatching a crew to investigate loss of line 1 and minute scanning interval (Interval =

you have no reason for the loss yet. If asked to run 4) per N1-0P-42 AND monitors a Load Flow, wait 3 minutes, then call back and o Contacts System Power Control report that the Low Contingency Voltage Alarm is AN D makes notification of the low NOT in alarm. voltage alarm AND to run a Load Flow o Contacts JAF Control Room in an expeditious manner AND informs them of the loss of 115 kV Line 1

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 4 - Loss of Condenser Vacuum CREW When directed by lead examiner, insert

  • Recognize/report lowering main malfunction: condenser vacuum MC01, MAIN CONDENSER AIR INLEAKAGE,

FV=18

  • A1-3-4, CONDENSER VACUUM TRG 3 BELOW 24" HG Main Condenser vacuum lowers Offgas flow rate rises Expected Annunciator:

A 1-3-4, CONDENSER VACUUM BELOW 24" HG SRO

  • Acknowledges reports
  • Determines condenser vacuum can NOT be maintained above 22.1" Hgv
  • Determines condenser vacuum can NOT be maintained above 10" Hgv
  • Acknowledges scram report
  • Directs entry into N1-S0P-1, Reactor Scram Note:
  • Directs Reactor water level controlled Initial Reactor pressure control may be on the 53-95" with Condensate, Feedwater, Turbine Bypass Valves, but will transition soon and CRD after the scram to the Emergency Condensers as

800-1000 psig with Emergency Condensers

  • When vacuum approaches 10" Hgv, directs trip of Vacuum Trip 2 Note:
  • When vacuum approaches 7.0" Hgv, May close MSIVs earlier to control cooldown rate.

directs closing the MSIVs

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Event 4 continued ATC

  • Monitors plant parameters
  • Places Reactor Mode Switch to SHUTDOWN
  • Performs scram verification actions of N1-S0P-1, Reactor Scram:
  • Confirms all rods inserted
  • Observes Reactor power lowering
  • Places IRMs on range 9
  • Inserts IRM and SRM detectors Note:
  • Down-ranges IRMs as necessary Initial Reactor pressure control may be on the

using Emergency Condensers BOP

  • Verifies proper operation of the following:

o Circ Water System o SJAEs o Off Gas System o Condensate System o Turbine Gland Seal System

  • Dispatches operator to check for condenser leakage

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 4 continued BOP continued

  • Coordinates with A TC to trip Turbine:

Note: o Depresses AND holds down When the Turbine is tripped, verify TRG 10 FEEDWATER RETURN TO automatically inserts: NORMAL AFTER HPCI CH 11 MC01, MAIN CONDENSER AIR INLEAKAGE, and 12 pushbuttons.

FV=50 o Depresses UNIT EMERGENCY Main Condenser vacuum lowers quicker TRIP pushbutton AND executes N 1-S0P-31.1, Turbine Trip o Releases FEEDWATER RETURN TO NORMAL AFTER HPCI CH 11 and 12 push buttons

  • Enters N1-S0P-1
  • Controls Reactor water level 53-95" using Condensate, Feedwater, and CRD
  • When directed, closes MSIVs

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 5 & 6 - Loss of Line 4 and EDG 102 Fails CREW to Auto-Start

  • Recognize/report loss of Line 4 Verify the following malfunction automatically
  • Recognize/report start of EDG 103 inserts when the Mode Switch is taken to
  • Recognize/report failure of EDG 102 SHUTDOWN: to auto-start ED01A, 115 kV Line 4 (JAF) Loss of Offsite Power, Delay=1 :30 TRG4 Breaker R40 opens Control Room lights go out Emergency Diesel Generator 103 starts Power is lost to the following major loads:
  • Recirc pumps
  • Circulating Water pumps

A8-1-3, 115 KV. BUS LOW VOL TAGE A8-1-7, NMP - FITZ 4 R40 TRIP A8-1-8, NMP - FITZ 4 LINE RELAY TRIP Verify the following malfunction is preset: SRO DG04A, DG 102 FAILURE TO AUTO START

  • Directs execution of N 1-S0P-33A 1
  • Directs start of EDG 102
  • Directs Reactor water level controlled 53-95" using CRD
  • Exits N1-EOP-5 when Reactor Building D/P is restored

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP

  • Executes N1-S0P-33A.1 Note:
  • May dispatch operator to field to The crew may perform an alternate leg of N1-S0P investigate EDG 102 failure 33A. 1 if they wait for a field report before starting
  • Manually starts EDG 102 EDG 102. The crew will perform the scripted leg to
  • Verifies start of both Emergency N 1-S0P-33A.1 once EDG 102 is started. Diesel Generators AND confirms the following has occurred:

Role Play: o EDG 102 SUPPLY BKR R-1022 If dispatched to investigate EDG 102 auto-start has closed failure, wait 2 minutes, then report that you see no o Powerboards 102 AND 16B are problems with either EDG 102 or Powerboard 102. energized Report that EDG 102 appears to be in a normal o EDG 103 SUPPLY BKR R-1032 standby condition with no apparent reason for a has closed start failure. o Powerboards 103 AND 17B are energized

  • Answers "Are PB 11 AND 12 energized?" No
  • Answers "Is any EDG running?" Yes
  • Verifies the following:

o PB 16A-B Tie Bkr R-1 042 is tripped o PB 17A-B Tie Bkr R-1052 is tripped o Inst. Air Compo (lAC) 11 and 12 in PTL

  • Continues at Page 4, Arrow B
  • Monitors EDG 102 AND 103 KW loading

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP continued Note:

  • IF EDG KW exceeds 2300 KW (PB The EDG load override in N1-S0P-33A.1 will not 102 or 103 Loading), THEN:

be applicable initially, but may be executed later o Verifies the following:

during the LOCA.

  • R-1042 tripped, PB 16 A-B Tie Bkr
  • R-1052 tripped, PB 17 A-B Tie Bkr
  • Verifies Lockouts 86-16 and 86-17 reset
  • Places CRD Pump 11 AND 12 in PTL
  • RBCLC Pump 11,12 AND 13 secured
  • WHILE continuing, sends operator to minutes, then report Attachment 2, Section 1 load perform load reductions of Attachment reductions are complete. 2, Section 1
  • Verifies Lockouts 86-16 AND 86-17 reset

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP continued

  • Verifies RBClC Pump 13 started, if available
  • Verifies RBClC Pump 12 started, if required Role Play:
  • Starts ESW PUMP 11 AND 12 AND When dispatched to check UPS 162 and 172, wait monitors equipment temperature listed two minutes, then insert remotes: in N1-S0P-18.1, Tables 18.1 and 18.2
  • Verifies the following:

RP21, RPS UPS 162 TROUBLE ANN RESET, o CRD Pumps 11 AND 12 started, if FV=reset required, UNLESS secured per RP22, RPS UPS 172 TROUBLE ANN RESET, override above FV=reset, DT=10 o MG Set 167 transfers back to AC TRG28 drive Then report that UPS 162 and 172 have o UPS 162 AND 172 re-energizes transferred back to AC input and you have reset o SBC 161 AND 171 re-energizes alarms.

  • Re-establishes Rx Bldg. differential pressure as follows:

o Verifies RB Supply AND Exhaust Role Play: Fans tripped When dispatched to restore power to I&C Bus 130, o Closes RB Supply AND Exhaust wait two minutes, then insert remotes: Isolation Valves o Verifies RBEV Train 12 initiated, ED40A, IC Bus 130 NC Supply Breaker From PB secures RBEV Train 11 13B,FV=open

  • Dispatches operator to restore power ED40B, IC Bus 130 NO Supply Breaker From PB to I&C Bus 130 167A, DT=5, FV=close
  • Places FEEDWATER PUMP 11 AND TRG 29 12 in PTl Then report that I&C Bus 130 is re-energized from
  • Verifies RBClC Pump 12 in PTl the maintenance supply.
  • Verifies ESW Pump 12 in PTl
  • Verifies lAC 11 in PTl

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP continued

  • Verifies one CRD Pump running as follows UNLESS secured per override above o CRD Pump 12 running o CRD Pump 11 in PTL
  • Verifies load reductions of Attachment 2 Section 1 complete
  • Restores power to PB 16A as follows:

o Trips R-1041, PB 16A Supply Bkr o Closes R-1042, PB 16A-B Tie Bkr

  • Verifies RBCLC Pumps 11 OR 13 running
  • IF TSC Power is required, AND PB 16B load is less than 900 amps, THEN Places in ON, NDS-1 disconnect switch (TSC Emergency Power)
  • Restores power to PB 17A as follows:

o Trips R-1051, PB 17A Supply Bkr o Closes R-1052 PB 17A-B Tie Bkr

  • Verifies lAC 12 started
  • Follows N1-0P-6 for recovery of Spent Fuel Pool cooling requirements

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 7. 8 & 9 - Loss of Coolant Accident. CREW Core Spray Fails to Auto-Start, ECs Fail to

  • Recognize/report degrading Primary Operate from Control Room Containment parameters Verify the following malfunction automatically
  • Recognize/report lowering Reactor inserts when Powerboard 16 is crosstied: water level and pressure RR29, RR Loop Rupture on Pump 15 Suction Line, FV=17 TRG5 Drywel/leakage, humidity, temperature and pressure rise Reactor water level and pressure lower Expected Annunciators:

H2-4-7, Drywel/ Water Leak Detection Sys K2-4-3, Drywel/ Pressure High-Low F1-1-5, RPS Ch 11 Drywel/ Press High F4-1-4, RPS Ch 12 Drywel/ Press High Verify the following malfunctions are preset: SRO CS06, CS Pumps Failure to Auto Start

  • Acknowledges reports EC04A, EC RETURN VALVE FAILS TO OPEN(lV
  • Enters N1-EOP-4 due to high Drywell 39-05) pressure and temperature EC04B, EC RETURN VALVE FAILS TO OPEN(IV
  • Enters N1-EOP-2 due to high Drywell 39-06) pressure and low Reactor water level Core Spray pumps do NOT auto-start

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 7, 8, & 9 continued SRO continued

  • When Torus pressure exceeds 13 psig or Drywell temperature approaches 300°F:
  • Verifies all Recirc pumps are tripped
  • Directs trip of all Drywell cooling fans
  • Evaluates/monitors position on Pressure Suppression Pressure curve
  • Directs Reactor water level control

-84" to 95" with CRD and Liquid Poison

  • Transitions to alternate level control leg of N1-EOP-2
  • Directs ADS bypassed
  • Directs verification of EC initiation
  • Acknowledges EC initiation failure
  • May direct local EC initiation
  • Answers "Are 2 or more Subsystems available?" - Yes (Both loops of Core Spray available)
  • Waits until Reactor water level drops to -84"
  • Answers "Is any Subsystem lined up with a pump running?" - Yes (Both loops of Core Spray running)
  • Answers "Is any injection source lined up with a pump running?" - Yes

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 7.8. & 9 continued SRO continued

  • Enters N1-EOP-8, RPV Slowdown:
  • Answers "Are all control rods inserted to at least position 04?"

Yes

  • Answers "Drywell pressure?" - At or above 3.5 psig
  • May direct EC initiation
  • Answers "Torus water level?"

Above 8.0 ft

  • Directs open 4 ERVs CT-2
  • Verifies injection of entire contents of Liquid Poison tank
  • Directs injection with available systems to restore and maintain Reactor water level above -84 inches CT-3
  • Directs installation of Core Spray jumpers (N1-EOP-1 attachment 4) to allow control of Core Spray IVs
  • Transitions back to normal level control leg of N1-EOP-2
  • Directs restoration of Reactor water level to 53-95" ATC/BOP
  • Updates crew on Reactor and containment parameters
  • Recognizes/reports failure of Core Spray to auto-start

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 7. 8. & 9 continued ATC/BOP continued

  • Maximizes RPV injection with CRD and Liquid Poison
  • When Torus pressure exceeds 13 psig or drywell temperature approaches 300°F:
  • Verifies all Recirc pump are tripped
  • Trips all Drywell cooling fans

CT-1

  • Bypasses ADS minutes, then delete malfunction EC04A, then
  • Verifies EC initiation insert malfunction:
  • Recognizes/reports failure of 39 EC03A, EC RETURN VALVE FAILS OPEN(IV 39 05 and 39-06 to open 05)
  • May direct operator to open 39-05 TRG 17 and/or 39-06 in field Then report task completion.
  • May secure ECs for pressure control Role Play:
  • When Reactor water level drops below If directed to open 39-05 in the field, wait 2

-84":

minutes, then delete malfunction EC04B, then

  • May initiates ECs insert malfunction:
  • Opens 4 ERVs EC03B, EC RETURN VALVE FAILS OPEN(IV 39 CT-2 06)

TRG 18 Then report task completion.

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 7, 8, & 9 continued ATC/BOP continued

  • Verifies Liquid Poison injection to Role Plays: inject entire contents of Liquid Poison If requested to lineup Firewater to Feedwater, wait tank five minutes, then insert remote:
  • Injects with available systems to FP04, FIRE WTR TO FW BLOCKING VLVS, restore and maintain Reactor water FV=100 level above -84" TRG21 CT-3 Then report Firewater is lined up to Feedwater.
  • Bypasses Core Spray IV interlocks per Modify the remote as requested to throttle flow. N1-EOP-1 Att 4 by installing six jumpers (17, 18, 19,24,25,26) inside If requested to throttle Containment Spray Raw PanelN Water 111 discharge valve, wait 3 minutes, then
  • Throttles Core Spray IVs as necessary insert remote: to control Reactor water level CT03A, CT Raw Water Pump 111 Disch. Throttle
  • Restores Reactor water level to 53-95" Valve 93-14, FV=10 TRG 22 Then report the valve is 5 turns open. Modify the remote as requested to throttle flow.

If requested to take local manual control of a Feedwater FCV, then wait 5 minutes and insert the appropriate remote:

FW25, MANUAL OPER. FW FCV-11, FV=O TRG23 FW26, MANUAL OPER. FW FCV-12, FV=O TRG24 FW27, MANUAL OPER. FW FCV-i3, FV=O TRG25 Then report the appropriate FCV is pinned and fully closed. Modify the remote as requested to throttle flow.

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Terminating Cues:

  • RPV Slowdown in progress
  • Reactor water level controlled above top of active fuel
  • Containment pressure and temperature controlled in accordance with N1-EOP-4
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