Revision as of 18:46, 28 April 2019

Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML13154A270
Person / Time
Site:	Nine Mile Point
Issue date:	05/08/2013
From:	; Nine Mile Point
To:	Fish T H; Operations Branch I
	Jackson D E
Shared Package
ML12356A123	List: IR 05000220/2013301; ML13003A171; ML13134A234; ML13154A119; ML13154A257; ML13154A262; ML13154A270; ML13158A156; ML13158A162; ML13158A172; ML13158A175; ML13158A179; ML13182A494;
References
	TAC U01861
	Download: ML13154A270 (196)
	v • d • e

NRC JPM RO C001 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE 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:

_______________

TrainerlEvaluator:

____________Evaluation Method: __Perform ______

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 of this JPM, obtain SM I CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM ! CRO permission.

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and 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 Therefore, either another individual or I will act as the independent verifier or peer NRC 2013 JPM RO COOl May 2013 Notes to Instructor

/ Evaluator: Critical steps are identified in grading areas PasslFail.

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.

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.

Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.

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.

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 I Standard Grade Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)

Evaluator acknowledge repeat back providing correction if necessary

________ 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

5.0 readings

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

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°P of each other Checks YES block in Section 5.0, indicating the maximum difference in loop temperatures is<15°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°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)

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.

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 NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Perfonn Heat-Up Rate Detennination Revision:

NRC 2013 Task Number: N/A Approvals:

I 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 Recommended Start Location: (Completion time based on the start 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 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:

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 This evaluated JPM is a measure of your ability to perform this task independently.

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

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.

References:

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

Calculator Task 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: 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.

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)

Evaluator acknowledge repeat back providing correction if necessary

_______ 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.

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°F +/- Calculates and records AT 115 min: 1030: 470°F -435°F 1045: 490°F -470°F 1100: 535°F -490°F 45°F (+/- Analyzes and records AT Limits for AT 115 min: 1030: 1045: 1100: Calculates ATs: 1030: 470°F -380°F 1045: 490 0 p -400°F 1100: 535°F -415°F Analyzes and records Heat-Up Rate Limits: 1030: SAT 1045: SAT 1100: UNSAT Proper communications used (GAP-OPS-Ol)

Grade PasslFaii Sat/Unsat SatlUnsat SatlUnsatlNA Pass/Fail Pass/Fail Pass/Fail SatlUnsat 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: 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: "(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:

NRC 2013 Task Number: NI A Approvals:

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

Operations (Designee)

NIA -Exam Security Configuration Control Date Performer:

__________TrainerlEvaluator:

____________Evaluation Method: Evaluation Location:

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:

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 This evaluated JPM is a measure of your ability to perform this task independently.

The Control Supervisor has determined that a verifier is not available and that additional!

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!

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.

Tools and Task Standard:

Alert emergency announcement is 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 1. Provide repeat back of initiating cue Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTUME

_______ 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)

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.

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 between Candidates, however important points must all be NRC 2013 JPM RO EP PasslFail PasslFaii SatlUnsat PasslFail May 2013

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.

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: 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 NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE 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: NI A 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: 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

________ 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)

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.

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.

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.

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.

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 May 2013

NRC JPM SRO C001 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Review NI-ST-DO DAILY CHECKS (Partial)

Revision:

NRC 2013 Task Number: N/A Approvals:

N/A -Exam Security I General Supervisor' 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 Simulator 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 This evaluated JPM is a measure of your ability to perform this task independently.

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:

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: Attachment 4 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 I Standard Grade Provide repeat back of initiating cue Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)

Evaluator acknowledge repeat back providing correction if necessary

________ 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.

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 "(Operator's name), perform SRO review of the following section

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:

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:

_______________TrainerlEvaluator:

____________Evaluation Method: _----'X'-"--

__ Perform ______

Evaluation Location:

____ 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:

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.

either another individual or I will act as the independent verifier or peer Notes to Instructor I

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 2 Tools and Equipment:

None Task Standard:

Determine 10 CFR 50.72 reportability requirements.

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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and Line 4 will be returned to service in approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . 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." 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

____________

_____ Obtain a copy of the any ofthe reference Reference materials obtained as necessary.

documents related to regulatory These are likely to include the

CNG-NL-l.OI-I004

10 CFR 50.72 and 50.73

NUREG 1022

EAL Matrix

EAL Bases 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 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).

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)

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.

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 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . 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 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Grade SatlUnsat Pass/Fail Pass/Fail SatlUnsat TERMINATING CUE: Reportability requirements have been determined.

RECORDSTOPTIME

_________ 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and Line 4 will be returned to service in approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . 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 -1 May 2013

NRC JPM SRO RC Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE 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 With the exception of accessing panels, NO plant equipment will be physically manipulated.

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.

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.

either another individual or I will act as the independent verifier or peer Notes to Instructor

/

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: 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.

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. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary

_______ 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.

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 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Post-Scenario Emergency Event Classification Revision:

NRC Task Number: NI NIA -Exam General Supervisor " Date General Supervisor Operations Training (Designee)

Operations Configuration Control Date ,__________TrainerlEvaluator:

__________Evaluation Method: Evaluation Location:

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:

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 For the performance of this JPM, I will function as the Unit 2 SM, Security Supervisor, Communication and other personnel as necessary.

Prior to providing direction to perform this task, I will provide you with initial conditions and answer any questions.

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.

The Control 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 During this Training lPM, applicable methods of verification are expected to be used. Therefore, another individual or I will act as the additional!

concurrent 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 2.

3.

4.

Tools and

1. EPlP-EPP-OI, ATTACHMENT 1, UNIT 1 EAL

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

Initial Conditions: None 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." Provide repeat back of initiating cue Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME

_______ 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.

If scenario deviates from the expected course, examiner discretion will be required to determine the actual classification.

Proper communications used for repeat back (GAP-OPS-Ol)

EPlP-EPP-Ol attachments 1 and 2, and Shift Manager emergency paperwork is obtained Determines an emergency classification is required.

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

I Performance Steps Classifies the emergency for 2013 Scenario Examiner Note: The listed EAL is the expected EAL based on scenario validation.

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.

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.

If scenario deviates from the expected course, examiner discretion will be required to determine the actual classification.

I Standard Determines the emergency classification level is Site Area Emergency.

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.

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.

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.

If scenario deviates from the expected course, examiner discretion will be required to determine the actual classification.

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:

Grade 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 NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE 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 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. 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.

of devices will be simulated by discussion and acknowledged by my Read Before Each Evaluated JPM This evaluated JPM is a measure of your ability to perform this task independently.

The 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.

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: 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.

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 ° 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 Rotates33-01R control switch clockwise to open PasslFaii Observes red light ON, green light OFF SatlUnsat Rotates33-04R control switch clockwise to open and uses pull-to-stop function after 3 seconds SatlUnsat Observes red light ON, green light ON SatfUnsat Rotates33-02R 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 Rotates33-02R 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

< 120°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 Rotates33-04R 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)

Proper communications used (GAP-OPS-Ol)

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:

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 NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE 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:.

_______________

TrainerlEvaluator:.

____________Evaluation Method: _-'X'-"--__ Perform ______

Evaluation Location:

____ Plant __

__

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:

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. 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.

of devices will be simulated by discussion and acknowledged by my Read Before Each Evaluated JPM This evaluated JPM is a measure of your ability to perform this task independently.

The 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.

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: A steam leak in the Reactor Building occurred approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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)

SatlUnsat Evaluator acknowledge repeat back providing correction if necessary

________ 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)

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)

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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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

NRC JPM Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Re-Open MSIV s with Reactor Pressurized and Lower Pressure Revision:

NRC 2013 Task Number: N/A Approvals:

NIA -Exam Security , . I General Supervisor Date General Supervisor 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.

3.

Tools and Task Standard:

MSIV s re-opened and Reactor pressure lowering on Turbine Bypass Initial

1. An RPV Blowdown is

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

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)

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):

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 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.

RECORD STOP TIME ____ NRC 2013 JPM S-3 -4 May 2013 Initial Conditions:

1. An RPV Blowdown is required.

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:

NRC 2013 Containment Spray Loop 111 Task Number: NI A Approvals: I , NIA -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 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 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 This evaluated JPM is a measure of your ability to perform this task independently.

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.

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 2. NUREG 1123295029 EAl.03 Tools and 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 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)

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 Opens80-118 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 Opens80-115 by rotating control switch CW to OPEN PasslFaii PasslFaii Opens80-114 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

NRC ..IPM Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE 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:

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

Operations (Designee)

Configuration 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 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 2) Insert malfunctions RP05A and RP05B to cause failure to 3) Insert malfunction ED26 to cause Powerboard 11 to fail to fast

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

Event -zdmsiivc( 1 )== 1

Command -

6) Insert trigger 3 to allow MSIV 01-03 to close using the control

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:

Nl-SOP-21.2 Nl-SOP-l Nl-S0P-30.1 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: 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.

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)

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.

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:

House service loads transfer Note: The candidate may request guidance on how to deal with PB 11 failure to fast transfer.

Direct candidate to make a recommendation and then carry out that recommendation.

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.

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)

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)

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)

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: 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:

NRC 2013 Task Number: NtA Approvals:

NtA -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 This evaluated JPM is a measure of your ability to perform this task independently.

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.

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: 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.

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)

NI-OP-13 is obtained, precautions

& 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. Opens39-11R by rotating control switch CW to OPEN Opens39-12R by rotating control switch CW to OPEN Opens39-07R by rotating control switch CW to OPEN Opens39-09R by rotating control switch CW to OPEN Stops39-09R by pulling control switch out to STOP Monitors system temperature and pressures Fully opens39-09R 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.

Standard Note: These steps are NI A if shell temperature is <100°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°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 Closes39-07R by rotating control switch CCWtoCLOSE Closes39-09R by rotating control switch CCWtoCLOSE Observes 39-05 green light on, red light off Closes39-11R by rotating control switch CCWtoCLOSE Closes39-12R 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

NRC JPM Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: EDG 103 SID-PB 103 Return to Nonnal Power Revision:

NRC 2013 (Alternate Path) Task Number: NI A Approvals:

General Supervisor

'" Date N/A Exam Security General Supervisor I 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 This evaluated JPM is a measure of your ability to perform this task independently.

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.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . 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 Grade Provide repeat back of initiating cue Proper communications used SatlUnsat (GAP-OPS-01)

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME

________ 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 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

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.

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 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR operated less than 500 KW for 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , 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)

SatlUnsat Observes CRD pump 12 green light on SatlUnsat Proper communications used (GAP-OPS-Ol)

SatlUnsat Proper communications used (GAP-OPS-O

1) SatlUnsat Determines step is NI A based on initial conditions SatlUnsat Proper communications used (GAP-OPS-Ol)

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.

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)

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.

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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . 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:

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 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 This evaluated JPM is a measure of your ability to perform this task independently.

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.

Notes to Instructor 1 Evaluator:

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 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.

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

_______ 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)

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

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.

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 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE 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 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 This evaluated JPM is a measure of your ability to perform this task independently.

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.

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 Grade 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

_______ 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 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.

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.

Air flow is heard. Role If contacted as Control Room, report that Emergency Condenser 12 has gone into service. 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 Constellation Energy Nuclear NINE MILE POINT UNIT OPERATOR JOB PERFORMANCE Title: Respond to RBCLC Makeup Tank Level Alarm Revision:

NRC 2013 Task Number: N/A Approvals:

NIA -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: ____ 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 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 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 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 This evaluated JPM is a measure of your ability to perform this task independently.

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.

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 Tools and Task Standard:

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.

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)

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 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. Open 71-224, DRAIN -CLC MAKE-UP Opens71-224 by rotating handwheel CCW PasslFaii TANK The indicated handwheel is rotated in the direction indicated.

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 Closes71-224 by rotating handwheel fully Pass/Fail the direction indicated.

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 Opens71-224 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.

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: 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

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:

NRC 2013 Task Number: N/A Approvals:

I ShJc2 NIA -Exam Security I General Supervisor Date General Supervisor Date Operations Training (Designee)

Operations (Designee)

NIA -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 This evaluated JPM is a measure of your ability to perform this task independently.

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.

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: The Control Room has been evacuated due to a fire. 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." 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)

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.

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.

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)

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

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)

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:

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

\) " 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 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:

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:

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> 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:

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)

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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . 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 NAME ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver:

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:

N/A D. I I Other Comments:

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.

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. 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 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 Take the simulator out of freeze before the crew enters for the pre-shift walkdown and briefing.

Allow no more than 5 minutes for panel walkdown.

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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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:

FW02A, FEEDWATER BOOSTER PUMP TRIP 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 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:

ED04, PB 11 Electrical Fault TRG2 Reactor power lowers due to RRP trips Reactor water level rises due to RRP trips Expected Annunciators:

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

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:

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.

Partial Primary Containment Isolation Failure. and Trip of Containment Spray Pump 111 When directed by the lead examiner, insert malfunction:

EC01, Steam Supply Line Break in PC, FV=11 TRG3 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 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:

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°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 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

& 111, 201.2-109

& 112 (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 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

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.

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°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 Closes80-118 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.

Intake Grassing.

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

Mode Switch Fails. BOJMFails PREPARER DATE ij'ld,/t3 VALIDATED Grapes, Lavallee.

M. O'Brien DATE 12/19/12 GEN OPS TRAINING t:s = DATE So *"'"

MANAGER N/A -Exam Security DATE ____

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 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 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 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°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

-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:

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:

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)

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: 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)

Test Control Annunciators (CRE) Shift Crew Composition (SM/CRS) NAME TITLE NAME ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver:

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.

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:

N/A D. I I Other Comments:

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:

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 Take the simulator out of freeze before the crew enters for the pre-shift walkdown and briefing.

Allow no more than 5 minutes for panel walkdown.

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")

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

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

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 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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

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.

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:

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 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.

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:

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 Reactor water level deviation from setpoint

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:

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:

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.

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°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°F with a second temperature trending towards 135°F. Note: Emergency Condenser 12 is available even though it was isolated earlier due to inadvertent initiation.

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

<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

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 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.

The timeline of field reports may be adjusted by examiner as necessary for evaluation purposes.

Role Play: When directed as Operator and RP tech to obtain General Area temperatures and radiation levels in the Reactor Building:

Wait 4 minutes and report RB 318' west side temperature is 125°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°F and a second general area temperature is reported as approaching 135°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°F and rising, radiation level is 4 mr/hr and rising. Report RB 318' east side 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. 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

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

'L3D,A3 VALIDATED Grapes. Lavallee.

M. O'Brien DATE 12119/12 GEN SUPERVISOR

() OPSTRAINING C ...

DATE s: ..... S 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 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, 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>

110°F) Termination Criteria:

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:

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:

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:

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)

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) 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:

Tripping Reactor Recirculation pumps, and/or

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 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 Take the simulator out of freeze before the crew enters for the pre-shift walkdown and briefing.

Allow no more than 5 minutes for panel walkdown.

Event 1 -RPS MG Set 131 Trip When directed by lead examiner, insert malfunction:

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 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.

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:

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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) 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

Acknowledgelreport Annunciator 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 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.

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.

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 Later: TRG4

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:

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.

Note: Once 2-3 control rods have been inserted by the ATC and directed by lead examiner, insert malfunction:

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°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°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)

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

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.

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 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 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

< 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

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. 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

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)

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: 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. 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.

PART IV: To be reviewed/accomplished shortly after assuming the shift: Review new Clearances (SM)

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.

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 Take the simulator out of freeze before the crew enters for the pre-shift walkdown and briefing.

Allow no more than 5 minutes for panel walkdown.

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:

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

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: 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

= 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:

MC01, MAIN CONDENSER AIR INLEAKAGE, FV=18 TRG 3 Main Condenser vacuum lowers Offgas flow rate rises Expected Annunciator:

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:

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

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.

Core Spray Fails to Auto-Start, ECs Fail to Operate from Control Room Verify the following malfunction automatically inserts when Powerboard 16 is crosstied:

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 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°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

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.

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.

OPERATOR ACTIONS 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 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.

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

v t e Letter Sequence Other
TAC:U01861, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML13154A119, ML13154A257, ML13154A262, ML13154A270, ML13182A494
MONTHYEAR2013-05-03 [Table View]

ML13154A270: Difference between revisions

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3.6.3 Determines

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ML13154A270: Difference between revisions

Revision as of 18:46, 28 April 2019

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3.6.3 Determines

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