ML13158A179

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Draft Operating Exam (Sections a, B, and C) (Folder 2)
ML13158A179
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 03/22/2013
From: Todd Fish
Operations Branch I
To:
Nine Mile Point
Jackson D
Shared Package
ML12356A123 List:
References
TAC U01861
Download: ML13158A179 (221)
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NRC JPM RO C001 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

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

t s/I/P NtA - Exam Security t General Supervisor " Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NtA - Exam Se<:urity /

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

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

Evaluation Method: _---"X~__ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant - - - - =X= - - 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 "'.E'...."......_ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:

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. SM80A035S0 = 73.00
b. 5M81A03560 75.00
c. 5M118A03860 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 Drywell temperature is less than 130°F S. Verify total Recirc flow is 38 Mlbmlhr
6. Verify FWLC is selected to column 11
7. Tum off PI monitor Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Plant Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

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

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

NRC 2013 JPM RO COOl May 2013

Notes to Instructor / Evaluator:

I. Critical steps are identified in grading areas PasslFaii. All steps are sequenced critical unless denoted by a

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

References:

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

None Task Standard: Control room RPV water level readings are taken for Nl-ST-DO. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.

Initial Conditions:

I. The plant is operating at approximately 15% power.

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

Initiating cue:

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

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

Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME _ _ __

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

NRC 2013 JPM RO COOl May 2013

I Performance Steps I Standard Grade

3. Records section 5.0 readings Records Reactor Recirc Pump Inlet SatlUnsat Temperature readings on Attachment 4 Section 5.0
4. Compare Recirc Pump Inlet Temperature Compares readings and determines readings SatlUnsat readings and determines readings within within 15°P of each other 15°P Checks YES block in Section 5.0, indicating PassIFaii the maximum difference in loop temperatures is < 15°P
5. Record section 6.0 readings Records RPV water level readings on SatlUnsat Attachment 4 section 6.0 Cue: Another operator has completed the required Independent Verifications.
6. Record Total Recirc Plow Records total recirc flow in the correct box on SatlUnsat Attachment 4 section 6.0
7. Determines average Drywell temperature Observes average Drywell temperature is less SatlUnsatlNA than 125°F Note: Since Yarway level indicator deviation is less than 4 inches, Drywell temperature reading is not necessary for task completion.
8. Analyzes Yarway level indicator deviation Determines Yarway level indicator deviation PassIFaii is less than the 6 inch limit Note: This may be evidenced by the lack of a report to the contrary.
9. Analyzes GEMAC level indicator deviation Determines GEMAC level indicator deviation PassIFaii is greater than the 6 inch limit
10. Determines GEMAC level indicators are Checks !NOP option in step 8.4 PassIFaii inoperable
11. Provides completed sections to SRO and Proper communications used (GAP-OPS-O 1) SatlUnsat informs of out of spec readings TERMINATING CUE: Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.

RECORDSTOPTIME_________

NRC 2013 JPM RO COO 1 May 2013

Initial Conditions:

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

Initiating cue:

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

NRC 2013 JPM RO COOl May 2013

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

Title:

Perform Heat-Up Rate Determination Revision: NRC 2013 Task Number: N/A Approvals:

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

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

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

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

Comments:

Evaluator Signature:_ _ _ _ _ _~_ _ _ _ _ _ __ Date:

NRC 2013 JPM RO C002 May 2013

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

Classroom Set-up:

1. Prepare a picture ofRRP 11 suction temperature gauge indicating approximately 535°F.
2. Prepare N1-0P-43A Attachment 18 with the following data:

Date/Time RRP Suction Temp DTIl5 min DT115 min Limits Heatup Rate Limits 511/13 0900 350 N/A N/A N/A 5111130915 370 20 SAT N/A 5/1/13 0930 380 10 SAT N/A 5111130945 400 20 SAT N/A 511113 1000 415 15 SAT SAT 511113 1015 435 20 SAT SAT 5/1/13 1030 470 5/1113 1045 490 5/1/13 1100 Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Plant Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional/concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

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

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

Notes to Instructor / Evaluator:

NRC 2013 JPM RO C002 May 2013

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, RO 4.4
2. NI-OP-43A Attachment 18 Tools and Equipment:

Calculator Task Standard: Current plant heat-up data taken per NI-0P-43A Attachment 18. Current and past heat-up rates calculated. Out of spec heat-up rate is identified to SRO.

Initial Conditions:

1. A plant startup is in progress.
2. Currenttime is 1100 on 5/1/13.
3. NI-0P-43A Attachment 18 is provided with heat-up data for the last hour.
4. All RRP suction temperature readings have been taken from Recirc loop l1.
5. The provided picture shows the current Recirc loop 11 suction temperature indication.
6. Instructor to ask the operator for any questions.

Initiating cue:

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

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME _______

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

NRC 2013 JPM RO C002 -3 May 2013

3. Records current RRP suction temperature Records current RRP suction temperature PasslFail (535°F +/- 10°F)
4. Calculates and records ~T115 min for times Calculates and records ~T115 min: SatlUnsat 1030-1100 1030: 470°F - 435°F = 35°F 1045: 490°F - 470°F == 20°F 1100: 535°F - 490°F = 45°F (::I: 10°F)
5. Analyzes and records ~T Limits for ~T115 Analyzes and records ~T Limits for ~T/15 SatlUnsat min min:

1030: UNSAT 1045: SAT 1100: UNSAT

6. Calculates hourly ~Ts for times 1030-1100 Calculates ~Ts: SatlUnsatlNA Note: There is no column on NI-OP-43A to 1030: 470°F - 380°F = 90°F record this step. It is provided to document an 1045: 490°F - 400°F == 90°F intermediate step taken to arrive at JPM Step #7. 1100: 535°F - 415°F = 120°F If the candidate does not provide these intermediate values, the JPM step may be graded "NA".
7. Analyzes and records Heat-up Rate Limits Analyzes and records Heat-Up Rate Limits:

1030: SAT PasslFail 1045: SAT PasslFaii 1100: UNSAT PasslFail

8. Provides completed sections to SRO and Proper communications used (GAP-OPS-O 1) SatlUnsat informs of out of spec readings TERMINATING CUE: Control room reading taken. Heat-up rates are calculated. Results are provided to SRO.

RECORDSTOP~E _________

NRC 2013 JPM RO C002 May 2013

Initial Conditions:

1. A plant startup is in progress.
2. Current time is 1100 on 511113.
3. NI-0P-43A Attachment 18 is provided with heat-up data for the last hour.
4. All RRP suction temperature readings have been taken from Recire loop 11.
5. The provided picture shows the current Recirc loop 11 suction temperature indication.

Initiating cue:

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

NRC 2013 JPM RO C002 May 2013

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

Title:

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

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

N/A - 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 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-SRO EC May 2013

Recommended Start Location: Classroom Simulator Set-up: N/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/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 PasslFail.
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 identity the surveillance requirements for testing the RPS 12 manual scram pushbutton and the Technical Specification impact ifthe pushbutton becomes inoperable.

NRC 2013 JPM RO-SRO EC May 2013

Initial Conditions:

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

Initiating cue:

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

I Performance Steps I Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME ________

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

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

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

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

NRC 2013 JPM RO-SRO EC May 2013

I Performance Steps I Standard Grade

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

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

Note:

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

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

Notes:

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

NRC 2013 JPM RO-SRO EC May 2013

Additional SRO Only Cue:

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

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

scram pushbutton becomes inoperable.

Determines Technical Specification 3 .6.2.a.(1) requires control rods to be inserted.

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

RECORDSTOPTIME_________

NRC 2013 JPM RO-SRO EC May 2013

Initiating cue:

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

NRC 2013 JPM RO-SRO EC May 2013

Additional SRO Only Cue Determine the following:

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

NRC 2013 JPM RO-SRO EC May 2013

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

Title:

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

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

N/A - Exam Security Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _(RO)

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

Evaluation Method: Perform Evaluation Location: Simulator Expected Completion Time: 10 minutes Time Critical Task: No Alternate Path Task: No Start Time: - - - - Stop Time: _________ Completion 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:

Evaluator Signature: _______________________________ Date:_____________

NRC 2013 JPM RO EP May 2013

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

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

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Plant Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identifY the steps to be simulated, or discuss and provide cues as necessary.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional 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 I concurrent verifier.

Notes to Instructor I Evaluator:

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

References:

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

None Task Standard: Alert emergency announcement is made.

NRC 2013 JPM RO EP May 2013

Initial Conditions:

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

Initiating cue:

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

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

Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME _ _ __

2. Place GAI-tronics in MERGE Places GAI-tronics in MERGE by toggling Pass/FaiJ MERGE/ISOLATE switch to MERGE
3. Sound the appropriate alarm Sounds the Evacuation Alarm by depressing PasslFaii EVAC pushbutton
4. Stop the alarm Stops the Evacuation Alarm by depressing SatlUnsat OFF pushbutton after approximately 10 seconds
5. Announce checked items Holds GAI-tronics broadcast pushbutton PasslFaii 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 is protective clothing should leave the area removing PCs as indicated at the step off pad.

I repeat, this is a drill."

Notes:

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

NRC 2013 JPM RO EP -3 May 2013

I Perfonnance Steps I Standard Grade

6. Repeat alann Sounds the Evacuation Alann by depressing SatlUnsat EVAC pushbutton
7. Stops alann Stops the Evacuation Alann by depressing SatlUnsat OFF pushbutton after approximately 10 seconds
8. Repeat announcement Holds GAI-tronics broadcast pushbutton SatlUnsat while saying:

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

All personnel not assigned emergency response duties shall evacuate the Protected Area and report to the P-Building. Remain at this location until further notice. Personnel is 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.

RECORDSTOPT~ _________

NRC 2013 JPM RO EP May 2013

Initial Conditions:

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

Initiating cue:

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

NRC 2013 JPM RO EP May 2013

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

Title:

Review N I-ST-DO DAILY CHECKS (Partial) Revision: NRC 2013 Task Number: NIA Approvals:

NI 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: _--=-=-_ _ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant __----"x.!!c.-__ 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:_ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:

NRC 2013 JPM SRO COOl -I - May 2013

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

Simulator Simulator Set-up:

N/A Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Plant Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional! concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

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

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

Notes to Instructor! Evaluator:

1. Critical steps are identified in grading areas 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 NRC 2013 JPM SRO COO 1 May 2013

Tools and Equipment:

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

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

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

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

Initial Conditions:

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

Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME ________

2. Obtain a copy of the reference procedure and NI-ST-DO obtained SatfUnsat review/utilize the correct section
3. Review Attachment 4 section 6.0 readings Reviews Attachment 4 section 6.0 readings SatfUnsat and Step 8.4 Note:

If Candidate asks for prior readings for comparison, report that prior readings were consistent with the current readings.

4. Identifies error in Step 8.4 Identifies that GEMAC Level Column Pass/Fail Variance is in the INOP range
5. Determines a GEMAC level indicator is Determines a GEMAC level indicator is Pass/Fail inoperable inoperable
6. Determines Technical Specification impact Determines a 15 day LCO applies per Pass/Fail Technical Specification 3.1.8
7. Provides completed sections to Examiner Proper communications used (GAP-OPS-O 1) SatfUnsat 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 67% power.
2. Nl-ST-DO, Daily Checks, is in progress.
3. Operators have completed the RPV water level instrument readings.

Initiating cue:

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

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

Title:

Assess Reportability Requirements Revision: NRC 20 l3 Task Number: NIA Approvals:

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

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

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

Evaluation Method: _-'X'-"--__ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant _ _--"'X-"'--__ Simulator or other location Expected Completion Time: 40 minutes Time Critical Task: No Alternate Path Task: No Start Time: - - - - Stop Time: _ _ _ __ Completion Time: _ _ _ __

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade ofunsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:_ _ _ _ _ __

NRC 2013 JPM SRO C002 May 2013

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

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

None Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Plant Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identifY the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

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

Notes to Instructor I Evaluator:

1. Critical steps are identified in grading areas PasslFail.
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-l.OI-I004
2. 10CFRSO.72
3. NUREG 1022
4. EAL Matrix NRC 2013 JPM SRO C002 May 2013

Tools and Equipment:

None Task Standard: Determine 10 CFR 50.72 reportability requirements.

Initial Conditions:

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

Initiating cue:

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

1. Provide repeat back of initiating cue. Proper communications used for repeat back SatlUnsat Evaluator Acknowledge repeat back (GAP-OPS-Ol) providing correction if necessary RECORD START TIME _ _ __

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

These are likely to include the following:

  • CNG-NL-1.01-1004
3. Locate and identify applicability of 10 CFR Identifies plant conditions require Emergency SatlUnsat 50.72(a)(I) Classification per Alert EAL 6.1.3 Note: Candidate must recognize that a loss of Identifies reportability per 50. 72(a)(1), for Pass/Fail 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 May 2013

I Performance Steps I Standard Grade

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

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

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

TERMINATING CUE: Reportability requirements have been determined.

RECORD STOP TIME _________

NRC 2013 JPM SRO C002 May 2013

Initial Conditions:

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

Initiating cue:

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

NRC 2013 JPM SRO C002 -I - May 2013

Attachment 1 JPM Scorecard KEY Note: Critical items bolded. Exact wording may vary.

Identify the applicable 10 CFR 50.72 reportability requirements, the reason that they apply and the associated time limitations for reporting under that category Reportability Requirement and Reason Time Limit 50.72(a)(I). Declaration of any of the Emergency Classes. Within one hour.

  • Alert EAL 6.1.3 for Emergency Bus AC power reduced to only EDG 103 for greater than 15 minutes 50.72(b)(2)(i). Initiation of a plant shutdown required by Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, if not previously Tech Specs. reported.
  • Tech Spec 3.6.3.e(l) requires initiation of shutdown within one hour and cold shutdown within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 50.72(b)(3)(iv)(A). Event or condition results in valid Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, if not previously actuation of Emergency Diesel Generator. reported.
  • Loss of offsite power resulting in automatic start of EDG 103
  • May alternately reference 50.72(b)(3)(iv)(B)(8) 50.72(b)(3)(v)(D). Event or condition that could have Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, if not previously prevented fulfillment of a safety function needed to mitigate reported.

the consequences of an accident.

  • Loss of both offsite power lines

Attachment 2 JPM Scorecard For Applicant Use IdentifY the applicable 10 CFR 50.72 reportability requirements, the reason that they apply and the associated time limitations for reporting under that category Reportability Requirement and Reason Time Limit NRC 2013 JPM SRO C002 May 2013

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

Title:

Determine Actions for Inoperable Stack Radiation Monitor Revision: NRC 2013 Task Number: NIA Approvals:

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

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

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

Evaluation Method: Perform Evaluation Location: Classroom Expected Completion Time: 25 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Completion Time: _________

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature: ___________________ 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 EveI)' JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Plant Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional/concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

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

Notes to Instructor I Evaluator:

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

References:

1. ARP HI-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 HI-3-8 and ODCM in response to stack radiation monitor downscale condition.

NRC 2013 JPM SRO RC May 2013

Initial Conditions:

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

Initiating cue:

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

EXAMINER NOTE: Provide Attachment 2.

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

I. Obtain a copy of the reference ARP Hl-3-8 obtained. SatlUnsat procedure and review/utilize the Operator Actions referenced.

correct section.

ODCM obtained.

DLCO 3.6.14 referenced.

Table D 3.6.14-2 referenced.

2. Detennines actions per ARP Hl-3-8. Detennines Chemistry should PasslFaii implement N1-CSP-V309, Stack Monitor Alann Response.

Detennines the 8 Drywell and Torus PasslFaiI Vent and Purge valves must be verified CLOSED and a Caution Clearance Section must be applied.

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

Detennines ODCM Table D 3.6.l4-2 SatlUnsat Instruments l.a.(l) have one less than the minimum number of functional channels.

NRC 2013 JPM SRO RC May 2013

I Performance Steps I Standard Grade Determines ODCM Table D 3.6.14-2 PasslFaii note (a)(l) applies - With the number of channels functional I less than required by the minimum channels functional requirement, effluent releases via this pathway may continue provided:

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

Determines DLCO 3.6.l4.b requires PasslFaii Restore the instruments to functional status within 30 days or outline in the next Radioactive Effluent Release Report the cause ofthe non-functionality and how the instruments were or will be restored to functional status.

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

RECORDSTOPTIME_________

NRC 2013 JPM SRO RC May 2013

Initial Conditions:

I. The plant is operating at 100% power.

2. Annunciator HI-3-8, STACK GAS MONITORING TROUBLE, has alarmed.
3. Computer Point C061, OGESMS RAD MON STATUS ,- TRBL, is in alarm.
4. OGESMS radiation monitor RN-I OA indicates downscale.

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 May20l3

Attachment 1 ANSWER KEY Detennine the appropriate actions in response to these conditions.

Action Required By (Document)

Chemistry should implement NI-CSP-V309, Stack Monitor ARP Hl-3-8 Alann Response.

The 8 Drywell and Torus Vent and Purge valves must be verified CLOSED and a Caution Clearance Section must be applied.

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

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

DLCO 3.6.14.b requires - Restore the instruments to ODCM DLCO 3.6.14.b 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.

NRC 2013 JPM SRO RC May 2013

Attachment 2 JPM Scorecard For Applicant Use Determine the appropriate actions in response to these conditions.

Action Required By (Document)

NRC 2013 JPM SRO RC May 2013

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

Title:

Post-Scenario Emergency Event Classification Revision: NRC 2013 Task Number: N/A Approvals:

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

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

Trainer/Evaluator:- - - - - - - - - - -

Evaluation Method: Perform Evaluation Location: Simulator Expected Completion Time: 15 minutes Time Critical Task: Yes Alternate Path Task: No Start Time: _______ Stop Tirne: _ _ _ __ Completion Time: _________

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature: _ _ _ _ _ _ _ _ _ _ _ _ _ __

NRC 2013 JPM SRO EP May 2013

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

Read Before JPM Performance:

For the performance of this JPM, I will function as the Unit 2 SM, Security Supervisor, Communication Aid, and other personnel as necessary. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure 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 I Evaluator:

1. Critical steps are identified as 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 1123,2.4.29, SRO 4.4
2. EPIP-EPP-O 1
3. EPIP-EPP-18
4. EPMP-EPP-OIOI Tools and Equipment:
1. EPIP-EPP-Ol, ATTACHMENT I, UNIT 1 EAL FLOWCHART
2. SMIED Checklist Package Task Standard:

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

NRC 2013 JPM SRO EP May 2013

Initial Conditions:

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

Initiating Cue:

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

I Performance Steps I Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME _ _ __

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

JPM start time: _ _ __

Time of Classification: - - - - - -

NRC 2013 JPM SRO EP May 2013

I Performance Steps I Standard Grade

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

JPM start time: - - - -

Time of Classification:

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

JPM start time: - - - -

Time of Classification:

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

JPM start time: _ __

Time of Classification:

NRC 2013 JPM SRO EP May 2013

I Performance Steps I Standard Grade

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

JPM start time: - - -

Time of Classification:

TERMINATING CUE: Emergency classification requirement is determined.

RECORDSTOPT~E _________

NRC 2013 JPM SRO EP May 2013

Initiating Cue:

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

NRC 2013 JPM SRO EP May 2013

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

Title:

Rapid RWCU System Restoration for Level Control Revision: NRC 2013 Task Number: NIA Approvals:

General SupervIsor Operations Training (Designee)

Date General Supervisor Operations (Designee)

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

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

Evaluation Method: __---"X'-"--__ Perform - - - - - - Simulate Evaluation Location: _____ Plant _ _----"-"--__ Simulator Expected Completion Time: 20 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: _ _ _ __ Completion JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator's Signature: ____________________

NRC 2013 JPM S-1 May 2013

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

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

Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before Every JPM Performance:

For the performance ofthis JPM, I will function as the SM, CRO, and Plant Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each ~~~~ JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional/concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.

Notes to Instructor I Evaluator:

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

References:

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

None NRC 2013 JPM S-1 May 2013

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

Initial Conditions:

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

Initiating Cue:

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

Performance Steps Standard Grade

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

NRC 2013 JPM S-I May 2013

Performance Steps Standard Grade

6. Using RMC-33-l65, CLEANUP TO Verify controller RMC-33-*165C dialed SatlUnsat COND & WASTE FLOW, close 33-165 to 0
7. Verify open one ofthe following using the CLEANUP SELECTOR CONDENSER WASTE control switch:
  • WASTE (valve 33-10, CLEANUP TO Rotates CLEANUP SELECTOR CONDENS PasslFail WASTE DISPOSAL BV) ER WASTE control switch clockwise to COND position
  • COND (valve 33-11, CLEANUP TO Observes right-hand set of lights red light ON SatlUnsat CONDENSER BV) and green light OFF, for 33-11 Note: Initiating cue directs the candidate to reject to the condenser
8. Open 33-01R, CU RETURN Rotates33-01R control switch clockwise to PasslFail ISOLATION VALVE I (INSIDE) open Observes red light ON, green light OFF SatlUnsat
9. Open 33-04R, CU SUPPLY ISOLATION Rotates33-04R control switch clockwise to SatlUnsat VALVE 12 (OUTSIDE), for open and uses pull-to-stop function after 3 approximately 3 seconds THEN PULL seconds TO-STOP Observes red light ON, green light ON SatlUnsat Note: Cleanup System Inlet Pressure will rapidly rise in the next step
10. Jog open 33-02R, CU SUPPLY ISOLA Rotates33-02R control switch clockwise to SatlUnsat TION VALVE 11 (INSIDE), using Y:z open and uses pull-to-stop in Y:z second second open signals followed by PULL intervals UNTIL Cleanup system inlet TO-STOP UNTIL Cleanup System Inlet pressure rises and stabilizes at reactor pressure Pressure has stabilized at Reactor Pressure on indicators Observes red light ON, green light ON SatlUnsat Observes cleanup system pressure and reactor SatlUnsat pressure approximately equal
11. Fully open 33-02R Rotates33-02R control switch clockwise to PasslFail open Observes red light ON, green light OFF SatlUnsat NRC 2013 JPM S-l May 2013

Performance Steps Standard Grade

12. Fully open the following valves:
  • 33-04 Rotates33-04R control switch clockwise to PasslFaii open Observes red light ON, green light OFF SatlUnsat
  • 33-41, AO BLOCKING VALVE Rotates 33-41 control switch clockwise to PasslFail open Observes red light ON, green light OFF SatlUnsat
13. Simultaneously perform the following:
  • Adjust the in-service PCV to maintain Using controller PC-33-39, dials output signal SatlUnsat Reactor Water Cleanup System to open valve and establish inlet pressure pressure <100 psig below 100 psig Note: Operator may place the PCV in AUTO after pressure is established
  • Adjust RMC-33-l65C, CLEANUP TO Using controller RMC-33-165C, dials output PasslFail COND & WASTE FLOW to control signals to open valve and establish system Reactor Water Level AND maintain reject flow Non-Regenerative Heat Exchanger outlet temperature < 120°F on Maintains parameters to prevent a subsequent PasslFaii computer point F359 RWCU system isolation Cue: Another operator will monitor computer point F359.

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

to adjust flow.

14. As time permits, continue with NI-OP-3, Proper communications used (GAP-OPS-01) SatlUnsat H.10.0.

Cue: Another operator will continue with Nl OP-3 H.lO.O.

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

RECORD STOP TIME _ _ __

NRC 2013 JPM S-l -5 May 2013

Initial Conditions:

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

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-1 May 2013

NRC JPM 8-2 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

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

1>~

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

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

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

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 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 8-2 May 2013

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

1. Initialize Simulator to IC-161.
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 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, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.

Notes to Instructor I Evaluator:

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

References:

1. NUREG 1123,261000 A4.03 (3.013.0)
2. NI-OP-IO Tools and Equipment:

None NRC 2013 JPM S-2 May 2013

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

Initial Conditions:

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

Initiating Cue:

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

Performance Steps Standard Grade

1. Provide repeat back of initiating cue Proper communications used (GAP-OPS-Ol) SatlUnsat Evaluator acknowledge repeat back providing correction ifnecessary RECORD START TIME _ _ __
2. Obtain a copy of the reference procedure NI-0P-1O obtained, precautions and SatlUnsat and review/utilize the correct section ofthe limitations reviewed, sections H.3.0 procedure referenced
3. 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 COOLINGBV
  • 202-75, EM VENTILATION LOOP 12 Observes 202-75 green light on, red light off SatlUnsat COOLINGBV
4. Open 202-38, EM VENTILATION LOOP Opens 202-38 by rotating control switch CW PasslFail 12 INLETBV to OPEN
5. Start 202-33, EVS FAN 12 Starts 202-33 by rotating control switch CW PasslFaii to START
6. VerifY open 202-35, EM VENTILATION Observes 202-35 green light off, red light on SatlUnsat EXHAUST FAN 12 OUTLET BV NRC 2013 JPM S-2 May 2013

Performance Steps Standard Grade

7. Confinn proper operation of202-51, EM Observes 202-51 green light on, red light on SatlUnsat VENT EXHAUST FAN 12 INLET FCV, by observing indicating lights AND flow Observes proper RBEVS flow SatlUnsat indication
8. Stop 202-53, EVS FAN 11 Stops 202-53 by rotating control switch CCW PasslFaii and pulls to lock Note: RBEVS fan 11 control switch must be placed in pull-to-Iock to stop fan due to presence of an auto-start signaL
9. Verify closed 202-34, EM VENT Observes 202-34 green light on, red light off SatlUnsat EXHAUST FAN 11 OUTLET BV
10. Verify EVS Train 12 running Observes RBEVS fan 12 green light off, red SatlUnsat light on
11. Verify 202-53, EVS FAN 11 in PULL Observes 202-53 control switch in pull-to- SatlUnsat TO-LOCK lock
12. Notify SRO to enter LCO 3.4.4.e (7 day Proper communications used (GAP-OPS-Ol) SatlUnsat plant shutdown LCO when one train of EVS is inoperable)

Role Play: Acknowledge communication as SRO.

13. Open 202-74, EM VENTILATION LOOP Opens 202-74 by rotating control switch PasslFaii 11 COOLING BV, by placing 202-37, EM CCWtoCOOL VENTILATION LOOP 11 INLET BV, control switch to COOL
14. Verify closed 202-37, EM Observes 202-37 green light on, red light off SatlUnsat VENTILATION LOOP 11 INLET BV
15. Open 202-47, EM VENTILATION TIE Opens 202-47 by rotating control switch CW PasslFail BV to OPEN Terminating Cne: RBEVS train 12 placed in service and RBEVS train 11 placed in the cooling lineup.

RECORD STOP TIME _ _ __

NRC 2013 JPM S-2 May 2013

Initial Conditions:

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

Initiating Cue:

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

NRC 2013 JPM S-2 May 2013

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

Title:

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

N/A - Exam Security /

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

N/A - Exam Security /

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

Trainer/Evaluator: - - - - - - - - - - - - - - - - - - - - - - - - - - -

Evaluation Method: _---"X~__ Perform _______ Simulate Evaluation Location: _ _ _ _ Plant X 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-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 MSIV s closed.
3. Verify MSIV automatic closure signals are clear.

Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before 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 wil1 be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional 1concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.

Notes to Instructor 1 Evaluator:

1. 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 1123,239001 A4.01 (4.2/4.0)
2. NI-EOP-HC Tools and Equipment:

None NRC 2013 JPM S-3 May 2013

Task Standard: MSIV s re-opened.

Initial Conditions:

1. A Reactor scram occurred 5 minutes ago due to low Reactor water level following trip of Feedwater pump 13.
2. MSIVs closed due to Lo-Lo Reactor water level.
3. Another Operator will control Reactor pressure using ECs and/or ERVs.
4. Another Operator will control Reactor water level using CondensatelFeedwater and CRD.
5. Instructor to ask operator for any questions.

Initiating Cue:

"(Operator's name), re-open the MSIVs per Nl-EOP-HC attachment 3."

Performance Steps Standard Grade

1. Provide repeat back of initiating cue Proper communications used (GAP-OPS-O I) SatlUnsat Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME _ _ __
2. Obtain a copy of the reference procedure NI-EOP-HC attachment 3 obtained SatlUnsat and review/utilize the correct section ofthe procedure
3. Open MSIV 01-03 Opens MSIV 01-03 by rotating control switch PasslFail CWtoOPEN
4. Slowly throttle open MSIV 01-01 utilizing Throttles open MSIV 01-01 by rotating PasslFaii PULL-TO-STOP control switch CW to OPEN and then pulling control switch out
5. Fully open MSIV 01-01 Opens MSIV 01-01 by rotating control switch PasslFail CWtoOPEN
6. Open MSIV 01-04 Opens MSIV 01-04 by rotating control switch PasslFail CW to OPEN
7. Slowly throttle open MSIV 01-02 utilizing Throttles open MSIV 01-02 by rotating PasslFail PULL-TO-STOP control switch CW to OPEN and then pulling control switch out
8. Fully open MSIV 01-02 Opens MSIV 01-02 by rotating control switch PasslFail CWtoOPEN Terminating Cue: MSIVs re-opened.

RECORD STOP TIME _ _ __

NRC 2013 JPM 8-3 May 2013

Initial Conditions:

1. A Reactor scram occurred 5 minutes ago due to low Reactor water level following trip of Feedwater pump 13.
2. MSIVs closed due to Lo-Lo Reactor water level.
3. Another Operator will control Reactor pressure using ECs and/or ERVs.
4. Another Operator will control Reactor water level using CondensatelFeedwater and CRD.

Initiating Cue:

"(Operator's name), re-open the MSIVs per NI-EOP-HC attachment 3."

NRC 2013 JPM S-3 May 2013

NRC ..IPM 5-4 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Transfer Torus Water to the Waste Collector Tank Using Revision: NRC 2013 Containment Spray Loop III Task Number: NI A Approvals:

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

NI A - 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 ofunsat or individual competency area unsat requires a comment.

Comments:

Evaluators Signature: _____________________________ Date:____________

NRC 2013 JPM S-4 May 2013

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

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

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

Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before 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 ""-"-'== 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 PasslFaii.
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.
  • No other verification shall be demonstrated.

References:

1. NI-EOP-l, Attachment 15
2. NUREG 1123295029 EA1.03 (2.9/3.0)

Tools and Equipment:

None NRC 2013 JPM S-4 May 2013

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

Initial Conditions:

1. Torus water level is 1].3 feet and rising slowly.
2. N I-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-I Attachment 15."

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME

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

Role Play: Acknowledge report

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

Performance Steps Standard Grade

9. Start Containment Spray Pump 111 Starts Containment Spray Pump 111 by PasslFaii rotating control switch CW to START
10. Open 80-115, Cont Spray to Radwaste IV Opens80-115 by rotating control switch CW PasslFaii 12 to OPEN
11. Open 80-114, Cont Spray to Radwaste IV Opens80-114 by rotating control switch CW PasslFaii 11 to OPEN
12. Throttle 80-118, Cont Spray Test to Torus Throttles closed 80-118 by rotating control SatlUnsat FCV as required to control flow to Waste switch CCW as required Collector Tank Role Play: If requested, inform that Radwaste has indication of sufficient flow
13. Monitor 58-05A and 58-06A TORUS H 2O Observes TORUS H 20 LEVEL indicators 58 SatlUnsat LEVEL indicators for level response 05A and 58-06A monitored for level response
14. Inform SRO that flow to the Waste Proper communications used SatlUnsat Collector Tank has been established using (GAP-OPS-Ol)

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

RECORD STOP TIME _ _ __

NRC 2013 JPM S-4 May 2013

Initial Conditions:

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

Initiating Cues:

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

NRC 2013 JPM S-4 May 2013

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

Title:

Control Room Evacuation, Manual Scram Fails, ARI Works Revision: NRC 2013 Task Number: N/A Approvals:

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

'" Date General Supervisor Operations (Designee)

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

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

Evaluation Method: __--'X'-=--__ Perform ___________ Simulate Evaluation Location: _____ Plant X

==---- Simulator Expected Completion Time: 10 Minutes Time Critical Task: No Alternate Path Task: Yes Start Time: _ _ __ Stop Time: ________ Completion Tirne: ________

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:

Evaluators Signature: _____________________________ Date:

NRC 2013 JPM S-5 May 2013

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

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

I. Initialize Simulator to IC-163.

2. Insert malfunctions RP05A and RP05B to cause failure to scram.

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 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-S0P-21.2
2. NI-SOP-1
3. NUREG 1123 295016 AA1.01 (3.8/3.9)

Tools and Equipment:

None NRC 2013 JPM S-5 May 2013

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

Initial Conditions:

1. The plant is operating at approximately 100% power.
2. The Shift Manager has determined that a Control Room Evacuation is required due to a fire in the Auxiliary Control Room.
3. Time permits completing all required actions ofNl-SOP-21.2, Control Room Evacuation, before leaving the Control Room.
4. 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."

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

Evaluator acknowledge repeat back providing correction ifnecessary RECORDSTARTTIME ________

2. Place Reactor Mode Switch in Rotates Reactor Mode Switch CW to PasslFail 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 ARI.

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

3. Verify ALL Control Rods inserted Observes control rods failed to insert SatlUnsat May depress RPS push buttons SatlUnsat Depresses MANUAL ARt pushbutton PasslFaii Observes control rods insert SatlUnsat
4. Place BOTH VESSEL ISOLATION Rotates both VESSEL ISOLATION switches PasslFaii switches to ISOLATE CCW to ISOLATION NRC 2013 JPM S-5 May 2013

Performance Steps Standard Grade

5. Verify ALL MSIV s close Observes green light on, red light off, for all SatlUnsat four MSIVs
6. IF time permits, verify the following:
  • House service loads transfer Observes PB 11 and PB 12 energized SatlUnsat (voltmeters show ~4160V, breakers re-align)
  • Turbine/Generator trip Observes Turbine trip and Generator lockout SatlUnsat (TSV s indicate closed, 86G 112 lockouts roll)
  • HPCI Initiation Observes FW pumps 11 and 12 start / inject SatlUnsat (green lights off, red lights on, amps, flow)
  • FW Pump 13 clutch disengaged Observes FW pump 13 clutch disengaged SatlUnsat (green light off, red light off, speed lowers)
7. IF time permits, sound the station alarm Depresses STA pushbutton on GAItronics SatlUnsat AND announce Control Room evacuation Depresses OFF pushbutton on GAItronics SatlUnsat Announces Control Room evacuation SatlUnsat
8. Obtain two sets ofRSP keys (VA-I, GE Proper communications used SatlUnsat 75, PA-235) AND obtain radios (GAP-OPS-Ol)

Cue: You have obtained radios and keys.

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

Cue: Task complete.

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

RECORD STOP TIME _ _ __

NRC 2013 JPM S-5 May 2013

Initial Conditions:

1. The plant is operating at approximately 100% power.
2. The Shift Manager has determined that a Control Room Evacuation is required due to a fire in the Auxiliary Control Room.
3. Time permits completing all required actions ofNI-S0P-21.2, Control Room Evacuation, before leaving the Control Room.

Initiating Cues:

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

NRC 2013 JPM S-5 May 2013

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

Title:

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

NIA - Exam Security I General SuperviSOf' 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: 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:_ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:_ _ _ _ _ __

NRC 2013 JPM S-6 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-163.
2. VerifY EC II is removed from service per NI-OP-13 section H.8.O.
3. VerifY EC 11 steam pressure has been vented to near 0 psig.
4. VerifY malfunction EC06A is set at 25% with a 15 second delay time on trigger 1.
5. VerifY trigger 1 is set to initiate when valve 39-09R red light goes on (hzlecmovr(I)==l).

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.
  • Peer verification shall be demonstrated.

References:

1. NUREG 1123, KIA 207000 A4.05 (3.5/3.7)
2. NI-0P-13 Tools and Equipment:
1. None NRC 2013 JPM 8-6 May 2013

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

Initial Conditions:

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

Initiating Cues:

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

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary.

RECORDSTARTTIME ________

2. Obtain a copy of the reference procedure NI-0P-13 is obtained, precautions & SatlUnsat and review/utilize the correct section of the limitations reviewed, section H.8.3 utilized procedure
3. Verify proper keepfullievel as follows:
  • Contact Engineering Programs - NRC to Determines level is 6' 11" per initial SatlUnsat perform UT of EC steam leg for level conditions determination
  • IF EC steam leg level is greater than 6' Proceeds to step 8.3.2 SatlUnsat 10" THEN proceed to step 8.3.2
4. Verify open the following valves:
  • 05-11, EMERG COND VENT Opens 05-11 by rotating control switch CW to PasslFaii ISOLATION VALVE 112 OPEN
  • OS-OiR, EMERG COND VENT Opens05-01R by rotating control switch CW PasslFaii ISOLA TION VALVE 111 to OPEN NRC 2013 JPM S-6 May 2013
5. WHEN system pressure has returned to normal, open the following valves:
  • 39-11 R, EMERG CONDSR STM Opens 39-11 R by rotating control switch CW Pass/Fail SUPPLY DRAIN IV 111 to OPEN
  • 39-12R, EMERG CONDSR STM Opens39-12R by rotating control switch CW PassIFail SUPPLY DRAIN IV 112 to OPEN
6. Open 39-07R, EC STM ISOLATION Opens39-07R by rotating control switch CW PassIFail VALVE 112 to OPEN Note: The candidate may throttle open 39-07R using the pull-to-stop feature, rather than open it in one continuous motion. However, it must be fully opened by the end ofthe manipulation.
7. Throttle open 39-09R, EC STM Opens39-09R by rotating control switch CW PassIFail ISOLATION VALVE 111 and monitor to OPEN system parameters during heatup AND repressurization Stops39-09R by pulling control switch out to SatJUnsat STOP Monitors system temperature and pressures SatlUnsat Fully opens39-09R by rotating control switch SatlUnsati CWtoOPEN NA Note: The alternate path begins when 39-09R red light comes on. This causes an EC tube leak to be initiated.
8. Responds to alarm Kl-1-2 Acknowledges and reports alarm SatlUnsat
9. Confirm alarm on computer printout Observes computer points E478 and E480 in SatiUnsat alarm
10. Confirm radiation levels on J Panel and Observes RE-RN04A-3 and RE-RN04A-4 SatlUnsat contact RP to check dose rates above reading on J Panel and determines readings elevation 340 indicate alarm condition Role Play: Acknowledge direction as RP. Directs RP to check dose rates above SatlUnsat elevation 340 NRC 2013 JPM S-6 May 2013
11. IF High Rad Alarm is confirmed, (BOTH RE-RN04A-3 AND RE-RN04A-4 in alarm OR one in alarm with the other Note: These steps are NIA if shell inoperable), AND shell side temperature temperature is <100°F.

?:lOOF:

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

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

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

NRC 2013 JPM 8-6 May 2013

Perfonnance Steps Standard Grade

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

a 39-07R, EC STM ISOLATION Closes39-07R by rotating control switch PasslFaii VALVE 112 CCWtoCLOSE a 39-09R, EC STM ISOLATION Closes39-09R by rotating control switch PasslFaii VALVE 111 CCWtoCLOSE a 39-05, EMERG CNDSR COND RET Observes 39-05 green light on, red light off Sat/Unsat ISOLATION VALVE 11 a 39-11 R, EMERG CNDSR STM Closes 39-11 R by rotating control switch PasslFaii SUPPLY DRAIN IV 111 CCWtoCLOSE a 39-12R, EMERG CNDSR STM Closes39-12R by rotating control switch PasslFail SUPPLY DRAIN IV 112 CCWtoCLOSE a 05-0IR, EMERG COND VENT Closes OS-OIR by rotating control switch PasslFaii ISOLATION VALVE 111 CCWtoCLOSE a 05-11, EMERG COND VENT Closes 05-11 by rotating control switch CCW PasslFaii ISOLATION VALVE 112 to CLOSE Role Play: As SM, provide concurrence for isolating EC 11.

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

RECORD STOP TIME _ _ __

NRC 2013 JPM S-6 May 2013

Initial Conditions:

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

Initiating Cues:

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

NRC 2013 JPM S-6 May 2013

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

Title:

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

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: 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 N 1-0P-4S 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 5DS267L02348 is inserted as "OFF", to simulate prevent start of 12 CRD pump.
7. Verify malfunction DG05B 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, Twill 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.

References:

1. NUREG 1123,264000, A4.04, RO 3.7, SRO 3.7
2. NI-OP-45 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 RIO 13.
2. EDG 103 has been at minimum load for the past hour and at 700 KW for the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3. 115 KV power is stable.
4. NI-0P-45 section G.2 is complete through step 2.6.
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 NI-0P-45, beginning at step G.2.7."

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME _ _ __

2. Obtain a copy of the reference procedure NI-0P-45 obtained SatlUnsat and review/utilize the correct section of the Precautions & limitations reviewed procedure Section G.2 referenced
3. Verify GREEN flagged RI013, PB 103 Rotates RIOl3 control switch CW from PTL PasslFail Normal Power Supply Breaker to neutral
4. Place and HOLD in TRIP position RI032, Rotates RI 032 control switch CCW and holds PasslFail Diesel Generator 103 Output Breaker in trip position
5. When 3 to 5 seconds has elapsed, close Rotates RI013 control switch CW, observes PasslFail RI013 red light on, green light off
6. Confirm normal voltage on PB 103 and PB Observes ~4160 V AC on PB 103 voltmeter, SatlUnsat 17B and observes ~600 V AC on PB 17B voltmeter
7. Return Rl 032 to Neutral Position Releases R1032 to the neutral position PasslFail NRC 2013 JPM S-7 May 2013

Performance Steps Standard Grade

8. Reset Lockout 86-17 device Rotates 86-17 control switch CW to reset Pass/Faill position NA Note: Lockout device may not need to be reset ifRI 013 is closed closer to 3 seconds than 5 seconds (Step 5 above)
9. Install Close fuse for CRD pump 12 Proper communications used SatlUnsat (GAP-OPS-Ol)

Cue: Field operators will install fuse.

Note: Delete malfunction RD35B &

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

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

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

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

Cue: EDG 103 Raw Water Cooling Pump has started.

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

Cue: Another operator will restore PB 17B loads.

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

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

Performance Steps Standard Grade

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

Cue: Speed is as you adjusted it.

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

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

20. If the EDG did not shutdown, refer to Refers to NI-OP-45 section G.8.0, Emergency SatlUnsat Section G.B.O, Emergency Shutdown Shutdown
21. If offsite power is not available, THEN Determines offsite power is available per Sat/Unsat verify RI012 OR 1013 in Pull-To-Lock initial conditions Note: This step is NIA, Offsite power is available per the initial conditions.

NRC 2013 JPM S-7 May 2013

Perfonnance Steps Standard Grade

22. IF loss of 125 VDC power is lost due to Detennines 125 VDC power is available SatlUnsat loss of Battery Board 11, THEN enter N 1 based on various control room indications SOP-47A.l to restore 125 VDC power Note: This step is N/A, 125 VDC is available.
23. Place DIESEL GEN control switch to EM Rotates EDG 103 control switch CCW to EM PasslFail STOP STOP position, observes EDG 103 frequency lower Role Play: If contacted to shutdown EDG locally, report that communications have failed and no one can be dispatched to shutdown the EDG locally Terminating Cue: EDG 103 stopped and PB 103 energized.

RECORD STOP TIME _ _ __

NRC 2013 JPM S-7 May 2013

Initial Conditions:

1. EDG 103 is supplying PB 103 due to maintenance on breaker RIOI3.
2. EDG 103 has been at minimum load for the past hour and at 700 KW for the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3. 115 KV power is stable.
4. NI-0P-45 section G.2 is complete through step 2.6.

Initiating Cues:

"(Operator's name), shutdown EDG 103 and return PB 103 to normal power in accordance with NI-0P-4S, beginning at step G.2.7."

NRC 2013 JPM S-7 May 2013

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

Title:

Reset Reactor Scram Revision: NRC 2013 Task Number: NIA 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: _-"'-"-_ _ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant _ _---"=-_ _ Simulator Expected Completion Time: 10 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: _ _ _ __ Completion JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade ofunsat or individual competency area unsat requires a comment.

Comments:

Evaluator's Date: _ _ _ _ __

NRC 2013 JPM S-8 May 2013

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

1. Initialize Simulator to IC-16S.
2. Verify a Reactor scram is inserted and NOT yet reset.
3. Verify all automatic scram signals are clear, with the exception of SOV high level.
4. Verify all N I-S0P-l steps are completed up to bypassing SDV high level trip.
5. Markup NI-SOP-l to the conditional step to bypass SDV high level trip.
6. Set trigger 1 event as "zcrprest==l".
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 ofthis JPM, I will function as the SM, CRO, and Plant Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional/concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.

Notes to Instructor / Evaluator:

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

References:

1. NUREG 1123,295006 AAl.07 (4.114.1)
2. NI-SOP-I Tools and Equipment: None NRC 2013 JPM S-8 May 2013

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

Initial Conditions:

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

Initiating Cue:

"(Operator's name), reset the Reactor scram, verify all control rods are at position 00, and un-bypass the SDV high level trip, perNI-S0P-1."

Performance Steps Standard Grade

1. Provide repeat back of initiating cue Proper communications used (GAP-OPS-Ol) SatlUnsat Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME _ _ __
2. Obtain a copy of the reference procedure NI-SOP-! obtained SatlUnsat and review/utilize the correct section of the procedure
3. If ALL rod motion has stopped, then place Rotates SCRAM DISCHARGE VOL HIGH Pass/Fail both SCRAM DISCHARGE VOLUME LEVEL BYPASS CH 11-1112-1 switch CW HIGH LEVEL BYPASS switches in to BYPASS BYPASS Rotates SCRAM DISCHARGE VOL HIGH Pass/Fail LEVEL BYPASS CH 11-2112-2 switch CW to BYPASS
4. If auto-initiated scram signals have cleared Observes all auto-initiated scram signals have SatlUnsat on CH 11 or CH 12, then: cleared or been bypassed (SDV high level)
5. Verify at least 1 CRD pump in service Observes CRD pump green light off, red light SatlUnsat on, amps
6. Reset Reactor Scram Depresses REACTOR TRIP RESET Pass/Fail pushbutton
7. Verify ALL control rods inserted to Observes all control rods are inserted to SatlUnsat position 04 OR beyond by observing one position 00 OR more of the following:
  • Full Core Display
  • KI04A&B Red LED lights LIT (1S20 AuxCR)

NRC 2013 JPM 8-8 May 2013

Performance Steps Standard Grade

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

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

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

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

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

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

RECORD STOP TIME _ _ __

NRC 2013 JPM S-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 SOV high level trip, per NI-SOP-I."

NRC 2013 JPM S-8 May 2013

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

Title:

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

NIA - Exam Security 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 __---"'x""--__ 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 unsat or individual competency area unsat requires a comment.

Comments:

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

NRC 2013 JPM P-l May 2013

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

Turbine Building elevation 261 '

Simulator Set-up (if required):

None Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Plant Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional! concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas Pass/Fail. All steps are sequenced critical unless denoted by a
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-OP*13 Tools and Equipment:

None NRC 2013 JPM P*l -2* 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-OP-13 section H.2 is complete through step 2.3.
4. Instructor to ask operator for any questions.

Initiating Cues:

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

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME _ _ __

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

- A-22110-C SH. 14.

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

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

Note: A wrench is hanging below the air pipe.

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

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

NRC 2013 JPM P-I May 2013

Perfonnance Steps Standard Grade Role Play: If contacted as Control Room on how to proceed, direct initiation of Emergency Condenser 12 locally.

6. Close 113-532, BV-IA MANIFOLD 113-532 handwheel rotated fully CW PasslFail SUPPLY TO - A-2211 O-C SH.14 Cue: The indicated handwheel is rotated fully in the direction indicated.
7. Using wrench, remove cap from 113-533, Cap removed from 113-533 by rotating CCW PasslFaii Vent-IA Manifold Cue: The cap is removed.

Note: A wrench is hanging below the air pipe.

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

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

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

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

RECORD STOP TIME _ _ __

NRC 2013 JPM P-l 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-I May 2013

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

Title:

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

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 ___X,,-,,-__ Simulate Evaluation Location: ---'X'-"--__ Plant - - - - - Simulator Expected Completion Time: 15 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 unsat or individual competency area unsat requires a comment.

Comments:

Evaluators ..,,:::...u *.u ...,,_ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:

NRC 2013 JPM P-2 May 2013

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

Turbine Building elevation 261 '

Simulator Set-up (if required):

None Directions to the InstructorlEvaluator:

Prior to performance of this JPM, obtain SM 1 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 1 CRO permission.

Directions to Operators:

Read Before JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Plant Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional 1concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.

Notes to Instructor 1 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 Hl-4-4 Tools and Equipment:

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

NRC 2013 JPM P-2 May 2013

Initial Conditions:

1. The Control Room has received annunciator Hl-4-4, CLOSED LOOP COOL MAKEUP TANK LEVEL HIGH-LOW.
2. Computer point B 115, CLC MU TK LVL - HIGH, is in alarm.
3. Control Room indications show CLC Makeup tank level is 7' and rising.
4. Annunciator Hl-4-5, LQ PROCESS RAD MON, is NOT in alarm.

S. 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 Hl-4-4."

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction ifnecessary RECORDSTARTTIME _______

2. Obtain a copy of the reference procedure ARP H 1-4-4 obtained SatlUnsat and review/utilize the correct section of the procedure
3. Check status of annunciator Hl-4-S AND Determines from initial conditions that Hl-4 SatlUnsat if in alarm, perform applicable actions of S is NOT in alarm Ann. HI-4-S AND continue with actions below
4. Close 71-229, BV-CLC MAKE-UP Closes71-229 by rotating handwheel fully PasslFaii TANK INLET FROM MAKE-UP LCV CW Cue: The indicated handwheel is rotated fully in the indicated direction.

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

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

Cue: The indicated handwheel is rotated fully in Closes71-224 by rotating handwheel fully PasslFaii the direction indicated. CW NRC 2013 JPM P-2 -3 May 2013

Perfonnance Steps Standard Grade

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

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

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

RECORD STOP TIME _ _ __

NRC 2013 JPM P-2 May2013

Initial Conditions:

1. The Control Room has received annunciator HI-4-4, CLOSED LOOP COOL MAKEUP TANK LEVEL HIGH-LOW.
2. Computer point B 115, CLC MU TK LVL HIGH, is in alarm.
3. Control Room indications show CLC Makeup tank level is 7' and rising.
4. Annunciator Hl-4-5, LQ PROCESS RAD MON, is NOT in alarm.

Initiating Cues:

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

NRC 2013 JPM P-2 May20l3

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

Title:

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

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

NtA - Exam Security /

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

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

Evaluation Method: _ _ _ _ Perform __--"x'-"--__ 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 ofunsat or individual competency area unsat requires a comment.

Comments:

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

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 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 ofthis JPM, I will function as the SM, CRO, and Plant Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional/concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the independent/peer verifier.

Notes to Instructor / 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. NUREG 1123 KA 295031 EAl.08, RO 3.8, SRO 3.9
2. N I-SOP-2 1.2, Attachment 4 Tools and Equipment:

I. None NRC 2013 JPM P-3 May 2013

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

1. The Control Room has been evacuated due to a fire.
2. Nl-S0P-21.2 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."

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME ________

2. Obtain a copy of the reference procedure N I-SOP-21.2, Attachment 4 obtained SatlUnsat and review/utilize the correct section of the procedure.
3. Verify locked closed the following valves (TB 261 '):
  • 29-07, FIRE WATER TO FEED 29-07 verified closed by ensuring handwheel SatlUnsat WATER AFTER SPOOL PIECE (FS- in fully CW position and locking device
62) installed
  • 100-33, FIRE WATER FEED 100-33 verified closed by ensuring handwheel SatlUnsat WATER SPOOL PIECE INLET (FS- in fully CW position and locking device
63) installed Cue: Valves 29-07 and 100-33 are LOCKED closed.

Note: Have applicant show where the Locates spool piece and tools PasslFail 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 I" on the floor beneath the spool piece) and where spool piece is to be installed. The EOP tool box should not be entered.

Cue: The spool piece has been installed Proper communications used SatlUnsat by a Damage Control Team. N I-S0P-21.2 (GAP-OPS-Ol)

Attachment 4 steps 2-4 have been verified complete.

NRC 2013 JPM P-3 May 2013

Performance Steps Standard Grade

7. Unlock the following valves:
  • 100-33, FIRE WATER TO FEED Lock and restraint removed from 100-33 PasslFail WATER SPOOL PIECE INLET (FS 63)
  • 29-07, FIRE WATER TO FEED Lock and restraint removed from 29-07 PasslFail WATER AFTER SPOOL PIECE (FS 62)

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

8. Supply the ftre header by performing one of the following:
  • Start Diesel Fire Pump. Examinee utilizes Diesel F ire Pump option SatlUnsat per initial conditions Cue: Once Candidate addresses the need to start the Diesel Fire Pump, report that Proper communications used SatlUnsat another Operator in the screenhouse has (GAP-OPS-Ot) started the Diesel Fire Pump.
9. When directed by the CRS/SM, open the Determines direction has already been given following valves to begin injection into in initiating cue RPV:
  • 29-07, FIRE WATER TO FEED 29-07 opened by turning handwheel fully PasslFail WATER AFTER SPOOL PIECE CCW
  • 100-33, FIRE WATER TO FEED 100-33 opened by turning handwheel fully PasslFail WATER SPOOL PIECE INLET CCW Cue: Valves 29-07 and 100-33 are open and injection to the RPV has commenced
10. Verify no leakage at spool piece Veriftes by visual inspection that there is no SatlUnsat connections leakage at the spool piece connections Cue: There is no leakage from the spool piece connections
11. Notiftes CRS/SM that ftre water is Proper communications used SatlUnsat being injected to the RPV (GAP-OPS-Ol)

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

NRC 2013 JPM P-3 May 2013

Initial Conditions:

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

Initiating Cues:

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

NRC 2013 JPM P-3 May 2013

NMP SIMULATOR SCENARIO NRC Scenario 1 REV. 0 No. of Pages: 24 PREPARER DATE 'Y"/'3, VALIDATED Grapes, Lavallee, M. O'Brien DATE 12119/12 GEN SUPERVISOR OPS TRAINING G;~~ IA--~An.,.+--

.... ' . . . s DATE

'3 *b "3 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 N1-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). Two Torus-to-Drywell vacuum breakers will fail open, resulting in some steam escaping from the Drywell directly into the Torus airspace. When the crew initiates Containment Spray, Containment Spray pump 111 will trip. These failures will further degrade Primary Containment pressure control. The Pressure Suppression Pressure (PSP) will be exceeded.

The crew will blowdown the Reactor per N1-EOP-8 (Critical Task).

Major Procedures: N1-0P-1, N1-S0P-16.1, N1-S0P-30.1, N1-S0P-1.3, N1-S0P-1.1, N1-S0P 1, N1-EOP-1, N1-EOP-2, N1-EOP-4, and N1-EOP-8 Dynamic Mitigation Strategy Code: PC4, RPV Slowdown due to PSP EAL Classification: Alert EAL 3.1.1 - High Drywell Pressure Termination Criteria: RPV water level controlled in assigned band, RPV Slowdown 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. 7S43DI4116, POS_3 4H17/51-02A C FRM B, FV=off (FWBP 13 auto-start 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 (00) 304:00 11
b. TRG 24 -Initiates when Containment Spray flow is initiated
i. Event Action: ctfdw> 100 ii. Command: imf ec01 (0 0) 45 1:00 30 C. Equipment Out of Service
1. Containment Spray pump 112 in PTL with yellow tag
2. Containment Spray suction valve 112 closed with yellow tClg
3. Steam Packing Exhauster 12 green-flagged with yellow tag

D. Support Documentation

1. RMI for Recirculation pump stop E. Miscellaneous
1. Note the failure of Core Spray to automatically inject is required to make the manual establishment of preferred and alternate injection sources a critical task when HPCI fails to automatically initiate.
2. Ensure Drywell cooling fan 11 is secured with control switch in neutral.
3. Ensure Service Water pump 11 is running and Service Water pump 12 is secured.
4. Protect the following equipment: EDG 103, PB 103, PB 12
5. Update Divisional Status Board

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

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

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

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

  • Reactor power is approximately 95%.
  • 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.

PART III: Remarks/Planned Evolutions:

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

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

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

TITLE NAME TITLE NAME SRO ATCRO BOPRO

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

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

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

Initial conditions to be verified prior to initiation of step:

Parameter Expected Range Actual Parameter Expected Range Actual CTP 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 the pump is secured.

Critical parameters to be monitored DURING Step:

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

Mlbm/hr IRMI evaluated against approved power profile:. N/A D. I IOther Comments:

I Step Prepared by: AIm: &;'(;1M I '0t1d~ Step Reviewed by~ cldck ciCYean / '0t1~

RE/STA Date RE/STAISRO Date Approval to perform Step ,--bhn Admn I rr::;;~ Step Completed by: I Shift Manager Date SRO Date

Critical Tasks:

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

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

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

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

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

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

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

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

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

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

INSTRUCTOR ACTIONS!

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

  • Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Secure Recirculation Pump 12 While Maintaining Reactor Power SRO
  • Directs securing Recirculation pump 12 per N1-OP-1 Section H.1.O
  • Provides oversight for evolution
  • Determines Core Operating Limits Report (COLR) requires APLHGR penalty BOP
  • Reviews N1-OP-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/BAUMAN switch to MAN
  • Verifies open REACTOR R PUMP 12 BYPASS VALVE

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 1 continued BOP continued

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

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 1 continued BOP continued

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

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

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

OVR-7S43D14116 POS_3 4H17/S1-02A C FRM B, FV=off PRESET RPV water level lowers Feedwater Booster Pump header pressure lowers Expected Annunciators:

H3-1-6, REACTOR FW BOOSTER P11 TRIP H3-3-7, REACTOR FW PUMP 13 SUCTION SRO

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

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 2 continued ATC

  • Monitors plant parameters
  • May perform Emergency Power Reduction per N1-S0P-1.1 as required to maintain RPV water level BOP Role Play: When dispatched as Operator to
  • Report alarm and respond per H3-1-6 investigate, wait 2 minutes, then report:
  • Confirms alarm on computer (E049
  • FWBP 11 breaker tripped on overcurrent RX FW BOOST PMP 11 TRIP)
  • No abnormal indications at FWBP 12 breaker
  • Recognizes/diagnoses failure of the
  • No abnormal indications at FWBP 11 or 12. standby pump to automatically start
  • Manually starts FWBP 12 Role Play: When dispatched as Operator to swap
  • Notifies crew of failure of FWBP 12 to HWC, wait 5 minutes and report that HWC injection auto start has been transferred from FWBP 11 to FWBP 12.
  • Dispatches operators to shift Hydrogen Water Chemistry injection from FWBP 11 to FWBP 12

INSTRUCTOR ACTIONS!

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

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

power Reactor Recirculation Pump 11

  • Recognize/report lowering condenser Drywell Fans 14, 15, 16 vacuum Condensate Pump 11
  • Recognize/report loss of Reactor Circulating Water Pump 11 Building DJP Service Water Pump 11 RBCLC Pump 11 TBCLC Pump 11 lAC 11 Reactor Building Exhaust Fan 11 SRO
  • Acknowledges reports from crew
  • Directs entry into N1-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 ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued SRO continued

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

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Event 3 continued ATC

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

No thermal hydraulic Instability 3 Recire 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 Role Play: BOP If dispatched to investigate Powerboard 11, wait 2
  • Executes N 1-S0P-30.1, Loss of minutes then report that the normal supply breaker Power Board 11 (R113) tripped on overcurrent.
  • Starts Service Water pump 12 If dispatched to investigate Powerboard 16A, wait 2
  • Coordinates with ATC to monitor minutes then report that there are no problems APRMs and LPRMs evident at Powerboard 16. Report that electrical
  • Verifies TBCLC pump 12 running maintenance has also looked at the Powerboard
  • Verifies lAC 12 and/or 13 running and concurs with re-energizing it.
  • Verifies RBCLC pump 12 running
  • Verifies Steam Packing Exhauster 12 Role Play: running If dispatched to lineup Steam Packing Exhauster
  • Answers "Are A4-4-6, A4-4-7, A4-1-3 12, wait 4 minutes, then insert remote:

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

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

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

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

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued

  • Restores power to Powerboard 16A as follows:
  • Opens R1041
  • Closes R1042
  • Verifies Power Board 16B amps

<962 Role Play: As operator when directed to energize

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

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued

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

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued

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

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4.5.6. & 7 - Steam Leak Inside Primary CREW Containment. Vacuum Breaker Fails Open.

  • Diagnose/report degrading Failure of HPCI to Auto-Initiate and Trip of containment parameters Containment Spray Pump 111
  • Diagnose failure of HPCI to malfunction: automatically initiate
  • Diagnose the trip of Containment EC01, Steam Supply Line Break in PC, FV=11 Spray pump 111 TRG3 Drywell humidity, pressure and temperature rise Drywellleakage 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 CT01A, CT Pump 111 Trip CS07, CS Injection Valves Failure to Auto Open Feedwater pump 12 running but not injecting RPV water level slowly lowering Containment Spray pump 111 red light off, green light on and amps go to zero Core Spray IVs do NOT open at 365 psig Expected annunciator:

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

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

  • Acknowledges reports Verify the following malfunctions automatically
  • Directs manual scram insert when the mode switch is taken to
  • Acknowledges scram report SHUTDOWN:
  • Enters N1-EOP-2 on low RPV water FW06, SHAFT DRIVEN FEEDWATER PUMP level CLUTCH FAILS - DISENGAGES, Delay=20
  • Directs N 1-S0P-1 actions seconds
  • Directs RPV water level controlled 53 EC01, Steam Supply Line Break in PC, IV=11, 95" with Condensate/FW and CRD RT=4:00, FV=30
  • When notified of the failure of HPCI PC10A, BV 68-01 Fails Open, Delay=2:00 to initiate, directs manual control of PCi0C, BV 68-03 Fails Open, Delay=2:00 Feedwater (preferred and alternate TRG 23 injection systems)

Containment conditions further degrade CT-1 Feedwater pump 13 disengages

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

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

  • Enters N1-EOP-4 due to high drywell pressure and temperature o Direct lockout of Containment Spray pumps
  • Re-enters N1-EOP-2 due to high drywell pressure Verify the following malfunction automatically inserts when Containment Spray flow is initiated to the Drywell:

EC01, Steam Supply Line Break in PC, IV=30, RT=1 :00, FV=45

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4. 5. 6. & 7 continued SRO continued

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

continuous guidance for this consideration.

Above 8.0 ft

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

  • Monitors plant parameters
  • When directed, places Mode Switch in Shutdown
  • Performs N1-S0P-1, Reactor Scram, scram verification actions
  • Places IRMs on range 9
  • Down-ranges IRMs as necessary to monitor power decrease
  • If recirc pumps have not yet tripped, reduces recirc flow to 25 43 Mlbm/hr
  • Maintains RPV pressure below 1080 psig and in assigned band

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 4.5.6. & 7 continued BOP

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

through Feedwater flow control valves 11 and 12.

  • Closes 13 FWP VALVE CONTROL
  • Disengages 13 FWP
  • Closes 29-10, Feedwater Pump 13 Blocking Valve
  • Verifies RPV water level above 53"
  • Verifies 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
  • 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 ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4,5,6, & 7 continued ATC/BOP

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

CT-2 Terminating Cues:

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

NMP SIMULATOR SCENARIO NRC Scenario 2 REV. 0 No. of Pages: 22 Recirc Flow Unit Failure, Emergency MVAR Support, Inadvertent EC Initiation, Intake Grassing, FWLC Fails As-Is Un-Isolable EC Steam Leak in Seconda Containment PREPARER

~-- 7~ __

DATE '3/7/15

~I VALIDATED Grapes. Lavallee, M. O'Brien DATE 12/19/12 GEN SUPERVISOR ,

OPS TRAINING C)..~~ {Pc a ~k,....

" -SO OPERATIONS MANAGER NIA - Exam Security DATE _ _ _ __

CONFIGURATION CONTROL NIA - Exam Security DATE SCENARIO

SUMMARY

Length: 60 minutes Initial Power Level: Approximately 50%

The scenario begins at approximately 50% power. Containment Spray pump 112 is out of service for maintenance. Steam Packing Exhauster 12 is caution tagged due to high vibrations.

Circulating Water pump 11 is out of service following maintenance. The crew will start Circulating Water pump 11, then raise Reactor power with recirculation flow.

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

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

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

An in-flux of grass will lead to clogging of the intake structure. The crew will enter N1-S0P 18.1, trip one Circulating Water pump, and lower Reactor power. During the power reduction, Feedwater Level Control will fail as-is in automatic. The crew will enter N1-S0P-16.1 and take manual control of Feedwater to restore Reactor water level. Once the Circulating Water pump is secured (Critical Task), intake conditions will improve.

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

The crew will scram the Reactor (Critical Task) and execute N1-EOP-2, RPV Control, and N1 EOP-5, Secondary Containment Control. Two General Areas of the Reactor Building will exceed the maximum safe temperatures. The crew will blowdown the Reactor per N1-EOP-8 (Critical Task).

Major Procedures: N1-0P-19, N1-0P-32, N1-S0P-18.1, N1-S0P-1.1, N1-S0P-16.1, N1-S0P 1, N1-EOP-2, N1-EOP-5, and N1-EOP-8 Dynamic Mitigation Strategy Code: SC1, Primary System Leak in Secondary Containment, Blowdown Required EAL Classification: Site Area Emergency per EALs 3.4.1 (Emergency Condenser Isolation Failure and Release Outside Primary Containment) and/or 4.1.1 (Primary System Discharging Outside Primary Containment, >135°F in Two General Areas)

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

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

1. Malfunctions:
a. CT018, CT Pump 112 Trip PRESET
b. NM36A, RECIRC FLOW CONVERTER CHANNEL 11 FAILURE- UPSCALE TRG 1
c. EC038, EC RETURN VALVE FAILS OPEN(IV 39-06) TRG2
d. CW17, Intake Traveling Screens Blockage, FV=65%, RT=10:00 TRG3
e. FW14C, Feedwater Master Controller - Fail As Is TRG3
f. EC02, Steam Supply Line Break in R8, FV=20% TRG4
g. ECO?A, Emergency Condenser 11 Fails to Isolate PRESET
h. EC08A, EC LOOP 11 STM IV FAIL TO CLOSE 111 , FV=50% PRESET
i. EC088, EC LOOP 11 STM IV FAIL TO CLOSE 112 , FV=50% PRESET
2. Remotes:
a. FW24 , REMOVAL OF HPCI FUSES FU8/FU9, FV=pulled TRG24
3. Overrides:
a. None
4. Annunciators:
a. None
5. Triggers:
a. None C. Equipment Out of Service
1. Containment Spray pump 112 in PTL with yellow tag
2. Containment Spray suction valve 112 closed with yellow tag
3. Steam Packing Exhauster 12 green-flagged with yellow tag
4. Circulating Water pump 11 secured with control switch green-flagged and no tag D. Support Documentation
1. RMI for power ascension with Recirculation flow E. Miscellaneous
1. Ensure Drywell cooling fan 11 is secured with control switch in neutral.
2. Ensure the Main Generator is supplying approximately 100 MVARs to the grid with the voltage regulator in automatic.
3. Markup N1-0P-19 Section E.2.0 up to step E.2.7.
4. Markup N 1-0P-438 Section F.3.0 to the appropriate steps for 50% power level.
5. Protect the following equipment: EDG 103, PB 103, PB 12, eire Water pump 12
6. Update Divisional Status Board

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

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

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

(SM, CRS, STA, RO, CRE)

Evolutions/Generallnformation/Equipment Status:

  • Reactor power is approximately 50%.
  • Steam Packing Exhauster 12 is caution tagged due to high vibrations.

PART III: Remarks/Planned Evolutions:

1. Start Circulating Water pump 11 per N1-0P-19 Section E.2.0. The section is complete up to step E.2.7. In step E.2.11, it is desired to stop both Circulating Water Priming pumps
2. Raise Reactor power with Recirculation flow per the provided RMI and N1-0P-43B.

N1-0P-438 Section F.3.0 is in progress.

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

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

I TITLE NAME TITLE NAME I SRO I ATCRO II BOPRO II

ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver: Power Ascension from 50% Step: 1 I INITIAL CONDITIONS/STEP DESCRIPTION I

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

If YES above, RE presence not required for steps_.

Initial conditions to be verified prior to initiation of step:

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

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

Critical parameters to be monitored DURING Step:

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

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

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

IRMI evaluated against approved power profile:. N/A D. I IOther Comments:

I Step Prepared by: Alex (3(ceri I '0l1d~ Step Reviewed f'Yctck~ '0t1dtw RE/STA Date RE/STAISRO Date Approval to perform Step ...dohn Aarem I rcdd~ Step Completed I Shift Manager Date SRO Date

Critical Tasks:

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

Safety 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. N1-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-S.

Safety 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-S provides direction to scram the Reactor.

Measurable Performance Indicators: Rotation of the Mode Switch to SHUTDOWN or depressing the manual scram push buttons 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 Slowdown, in accordance with N1-EOP-S.

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

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

Measurable Performance Indicators: The crew will manually open ERVs.

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

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

  • Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Start Circulating Water Pump 11 SRO
  • Directs starting Circulating Water pump 11 per N1-0P-19 Section E.2.0
  • Provides oversight for evolution BOP
  • Reviews N1-0P-19 Section E.2.0
  • Verifies running CRD Pump flow greater than 60 GPM Role Play:
  • Starts 74-01, CONDSR When requested, report a good start on Circulating CIRCULATING WATER PUMP 11 Water pump 11.
  • Closes 74-.20, FISH SCREEN DRAIN VALVE 11
  • Contacts Operator to confirm normal Role Play: circulating water pump discharge When requested, report normal circulating water pressure in Screen House pump discharge pressure in Screen House.
  • Verifies the following pumps are stopped per SM direction:
  • 75-09, CONDo WATER BOX Role Play: PRIMING PUMP NO. 11 If asked as Shift Manager, direct securing both
  • 75-08, CONDo WATER BOX Water Box Priming pumps.

PRIMING PUMP NO. 12 ATe

  • Monitors plant parameters

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 2 - Power Ascension With Recirculation SRO

  • Directs power ascension with Recirculation flow in accordance with N1-0P-438 and the Reactivity Maneuver Instruction (RMI)
  • Provides oversight of reactivity maneuver ATC Note:
  • Acknowledges direction from SRO N1-0P-438 includes the following power-to-flow
  • Raises Recirculation flow with master map restrictions: Recirculation flow controller
  • PRIOR to exceeding 65% flow, verify greater
  • Monitors APRMs than 50% Rod Line OR that RIP region will
  • Monitors Recirculation flow NOT be entered.
  • PRIOR to 100% rodline raise recirc flow to water level greater than 59% flow (approximately 40 x 106
  • Observes power-to-flow map Ib/hr) to avoid the flow biased control rod block restrictions line.

BOP Note:

  • Monitors individual RRPs for response Recommend initiating the next event when Reactor
  • Individual MIA-Speed Control power is between 55-60% power to achieve the stations trending uniformly desired response in Event 6.
  • Individual RRP indications trending normally for speed increase
  • Monitors Feedwater controls for proper response
  • RPV water level remains within program band (65" - 83")

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 - Recirculation Flow Unit Fails Upscale CREW When directed by lead examiner, insert

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

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

Expected Annunciators:

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

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

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 3 continued ATC

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

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

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Event 4 - Power Control Requests Emergency CREW MVAR Support

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

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

SRO Role Play:

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

BOP

  • Executes 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 5 - Emergency Condenser 12 Inadvertent CREW Initiation

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

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

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

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

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 6 - Intake Grassing CREW When directed by lead examiner, insert

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

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

The malfunction for Event 6 is inserted with Event

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

SRO Booth Operator:

  • Acknowledges reports When one Circulating Water pump is tripped,
  • Directs entry into N1-S0P-18.1, modify malfunction CW17 to 40% over 1 minute. Service Water Failure / Low Intake Level
  • Directs emergency power reduction per N1-S0P-1.1 as needed
  • Provides oversight for reactivity manipulation
  • Acknowledges improving intake level

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 6 continued BOP

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

ATC

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

as needed for single Circ Water pump operation

  • Observes APRMs, CTP, and Recirculation flow

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 7 - Feedwater Level Control Fails As-is In CREW Automatic

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

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

  • Acknowledges reports If crew does not respond to the malfunction, a
  • Monitors RPV water level
  • Monitors plant parameters BOP
  • Enters N1-S0P-16.1, Feedwater System Failures
  • Answers "FCV lockup?" NO
  • Answers "FWLC malfunction?" YES
  • Places FW FCV 13 controller in MAN
  • Controls RPV water level in manual

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 8 & 9

  • Emergency Condenser 11 Steam CREW Leak In Reactor Building. Emergency
  • Acknowledge/report annunciators Condenser 11 Fails To Isolate
  • Recognize/report Emergency When directed by the lead examiner, insert Condenser 11 steam leak malfunction:
  • Recognize/report failure of Emergency Condenser 11 to isolate EC02, Steam Supply Line Break in RB, FV=20%

TRG4 Reactor Building DIP lowers Rising temperatures, pressures and radiation levels in the Secondary Containment RBEVS auto-starts RB VS isolates Expected Annunciators:

L 1-3-4, REACT. BLDGIA TM 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 RADIA TlON MONITORS

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

EC07 A, Emergency Condenser 11 Fails to Isolate EC08A, EC LOOP 11 STM IV FAIL TO CLOSE 111 , FV=50%

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

Emergency Condenser 11 fails to isolate.

SRO

  • Acknowledges reports
  • Enters N1-EOP-5 on high Reactor Building Vent rad levels, high Reactor Building area temperatures I rad levels, and/or loss of RB DIP
  • Directs manual isolation of Emergency Condenser 11
  • Directs Reactor Building evacuation
  • Acknowledges manual isolation failure
  • Directs dispatching of an operator and RP tech to obtain general area temperatures and radiation levels in the Reactor Building
  • Determines area temperatures andlor radiation levels are above setpoints in Tables T and R, and transitions to N1 EOP-5 circle 27

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

  • 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:
  • Acknowledges scram report
  • Enters N1-EOP-2, RPV Control, on low RPV water level

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

  • Answers "Are all control rods inserted to at least position 04?" YES
  • Directs entry into N1-S0P-1, Reactor Note: Scram If the Reactor scrammed due to an earlier event,
  • Directs RPV water level control 53-95" CT-2 will be N/A. 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 1000 F/hr Note: Anticipatory blowdown is likely to be
  • Acknowleqges reports of Reactor directed from N1-EOP-2 once one Reactor Building Building temperatures and radiation General Area temperature is above 135°F with a levels second temperature trending towards 135°F.
  • When report is received that 2 General Areas temperatures are above 135°F, enters N 1-EOP-8, RPV Blowdown Note:
  • Answers "Are all control rods inserted Emergency Condenser 12 is available even though to at least position 04" YES it was isolated earlier due to inadvertent initiation.
  • Answers "Drywell pressure?" <3.5 psig The crew may decide not to use Emergency
  • May direct initiation of Emergency Condenser 12 due to actuation of Annunciator K 1 Condenser 12 4-5, EMER COOLING SYSTEM 12 STEAM LEAK
  • Answers "Torus water level?" >8 ft AREA T HI.
  • 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
  • Performs scram verification actions of N1-S0P-1, Reactor Scram:
  • Confirms all rods inserted
  • Observes Reactor power lowering
  • Places IRMs on range 9
  • Down-ranges IRMs as necessary
  • Reduces Recirc Master flow to 25-43 x 106 lbm/hr
  • Controls RPV pressure as directed using TBVs and/or Emergency Condenser 12

INSTRUCTOR ACTIONS/

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

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

the Reactor Building to monitor area temperatures.

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

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

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

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

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 8 & 9 continued BOP

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

NMP SIMULATOR SCENARIO NRC Scenario 3 REV. 0 No. of Pages: 18 RPS MG Set Trip, CRD FCV Fails Closed, MPR Failure, Failure to Scram, Liquid Poison Pumps PREPARER ~~:p:~ DATE ?L~3 VALIDATED Grapes, Lavallee, M. O'Brien DATE 12119/12 DATE 'lIlies OPERATIONS MANAGER N/A - Exam Security DATE _ _ _ __

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

SCENARIO

SUMMARY

Length: 60 minutes Initial Power Level: Approximately 100%

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

Shortly after the crew assumes the shift, RPS MG Set 131 will trip. This will result in a half*

scram and loss of two strings of Feedwater heating. The crew will enter N 1-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 N 1-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. Soth Liquid Poison pumps will trip shortly after being started.

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

Major Procedures: N1-ST-W15, N1-S0P-16.1, N1-S0P-1.1, N1-0P-48, N1-S0P-5.1, N1-S0P 31.2, N1-S0P-1, N1-EOP-3, N1-EOP-3.1, N1-S0P-5.1 Dynamic Mitigation Strategy Code: AT1, High power A TWS, RPV level controlled below feedwater spargers, RPV Slowdown not required EAL Classification: Site Area Emergency per EAL 2.2.2 (Any RPS scram setpoint has been exceeded AND automatic and manual scrams fail to result in a control rod pattern which assures reactor shutdown under all conditions without boron AND either: Reactor power> 6% OR Torus temperature> 11 QOF)

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

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

1. Malfunctions:
a. CT01 B, CT Pump 112 Trip PRESET
b. RP01A, REACTOR TRIP BUS MOTOR GENERATOR TRIPS 131 TRG 1
c. RP16B, RPV PT 36-07B FAILED LOW TRG2
d. RD36A, CRD FCV 44-151 FAILURE - CLOSED TRG3
e. TC08, MECHANICAL PRES. REGULATOR FAILS - LOW TRG20
f. RD33A, CONTROL ROD BANK BLOCKED BANK 1, FV=8 PRESET
g. RD33B, CONTROL ROD BANK BLOCKED BANK 2, FV=8 PRESET
h. RD33C, CONTROL ROD BANK BLOCKED BANK 3, FV=18 PRESET
i. RD33D, CONTROL ROD BANK BLOCKED BANK 4, FV=8 PRESET
j. RD33E, CONTROL ROD BANK BLOCKED BANK 5, FV=8 PRESET
k. LP01A, Liquid Poison Pump 11 Trip, DT=5 TRG 11 I. LP01 B, Liquid Poison Pump 12 Trip, DT=5 TRG 12
m. RD35B, CRD Hydraulic Pump 12 Trip TRG5
2. Remotes:
a. RP01, RX TRIP BUS 131 PWR SOURCE, FV=maint TRG29
b. MS01, HP FW HTR 115 RESET, FV=reset TRG30
c. MS03, HP FW HTR 135 RESET, FV=reset TRG30
d. MS04, FW HTR STRING 11 RESET, FV=reset TRG30
e. MS06, FW HTR STRING 13 RESET, FV=reset TRG30
f. RD05, CRD FLOW CONTROL VALVE ISOL, FV=nc30b TRG21
g. FW24, REMOVAL OF HPCI FUSES FU8/FU9, FV=pulled TRG24
3. Overrides:
a. 13S73D146713, POS_2 1E70 TC MPR POS C, FV=on (MPR setpoint drifts low) TRG4
4. Annunciators:
a. None
5. Triggers:
a. TRG 11 -Initiates when Liquid Poison pump keylock switch is taken to SYS 11 position.
i. Event Action: zdlpsys2==1

ii. Command: None

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

E. Miscellaneous

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

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

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

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

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

  • Reactor power is approximately 100%.
  • 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.

PART III: Remarks/Planned Evolutions:

Maintain operation at rated power.

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

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

TITLE NAME TITLE NAME SRO ATCRO BOPRO

Critical Tasks:

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

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

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

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

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

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

CT-2.0 Given a failure of the Reactor to scram, insert control rods, in accordance with N1 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 ACTIONS!

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

  • Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - RPS MG Set 131 Trip CREW When directed by lead examiner, insert

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

  • Acknowledges reports
  • Directs entry into N1-0P-48 H.4.0
  • Directs entry into N1-S0P-16.1 for loss of Feedwater heating
  • May direct emergency power reduction per N1-S0P-1.1 if needed to control Feedwater temperatures or Reactor power
  • Provides oversight of reactivity changes

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 1 continued ATC

  • Monitors plant parameters Role Play: When dispatched as operator to
  • Lowers power per N1-S0P-1.1 as investigate problem with MG Set 131, wait two required to control Feedwater minutes then report that you can smell burnt temperatures or Reactor power insulation in the vicinity of MG Set 131 motor.
  • Resets half scram Report that the drive motor breaker tripped on overcurrent. If asked, report no overvoltage trip BOP occurred.
  • Dispatches an operator to investigate MG Set 131
  • Determines I&C Bus 130A is available
  • Obtains SRO permission to perform Role Play: When dispatched as operator to dead bus transfer of Reactor Trip Bus transfer Reactor Trip Bus 131 to I&C Bus 130A, 131 wait 2 minutes and insert remote:
  • Dispatches an operator to perform RP01, RP01, RX TRIP BUS 131 PWR SOURCE, dead bus transfer of Reactor Trip Bus FV=maint 131 per N1-0P-48 section H.4.0 TRG29
  • Acknowledges that Reactor Trip Bus 131 is re-energized Role Play: When dispatched as operator to
  • Coordinates with ATC to reset half reset Feedwater heaters, wait 2 minutes and insert scram remotes:
  • Dispatches operator to reset MS01, HP FW HTR 115 RESET, FV=reset Feedwater heaters MS03, HP FW HTR 135 RESET, FV=reset MS04, FW HTR STRING 11 RESET, FV=reset MS06, FW HTR STRING 13 RESET, FV=reset TRG30 Then report Feedwater heaters have been reset.

INSTRUCTOR ACTIONS!

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

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

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

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

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

ATC Role Play: When directed as Operator to check

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

BOP

  • Dispatches operator to investigate indications at ATS Cabinet

INSTRUCTOR ACTIONS!

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

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

F3-1-5 CRD CHARGING WTR PRESS HIILO SRO

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

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP

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

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

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

position following countdown perform countdown and report RB Air Transfer

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

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

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

swapped:

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

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

INSTRUCTOR ACTIONS/

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

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

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

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

LP01A, Liquid Poison Pump 11 Trip, DT=5 TRG 11 LP01 B, Liquid Poison Pump 12 Trip, DT=5 TRG 12 Control rods partially insert Reactor power remains> 6%

Liquid Poison pumps trip

INSTRUCTOR ACTIONS!

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

  • Acknowledges reports
  • Directs entry into N1-S0P-31.2, as time permits
  • Enters N1-EOP-2 due to Reactor
  • Inserts malfunction Te08, MECHANICAL power above 6% when scram required PRES. REGULATOR FAILS - LOW
  • Answers "All rods in to at least 04" NO
  • Deletes override 13S73D146713, POS_21E70
  • Answers "Will the reactor stay TC MPR POS C, FV=on shutdown without boron" NO This fails the MPR completely.
  • Exits N1-EOP-2, enters N1-EOP-3
  • Directs ADS bypassed
  • Directs prevention of Core Spray injection per N 1-EOP-1 Att 4 Once 2-3 control rods have been inserted by the ATC and directed by lead examiner, insert N1-EOP-3 Level Leg Actions (Initial) malfunction:
  • Directs bypass of the low-low RPV RD35B, CRD Hydraulic Pump 12 Trip water level MSIV isolation per N1 TRG5 EOP-1 Att 2 CRD pump 12 trips
  • Determines Reactor power is above 6% and RPV water level is above -41 inches
  • Directs terminate and prevent of all injection except boron and CRD per N1-EOP-1 Att 24 CT-1
  • Directs RPV water level lowered to at least -41 inches

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4, 5, 6 and 7 continued SRO continued N 1-EOP-3 Pressure Leg Actions

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

NO

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

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

  • Acknowledges RPV water level below

-41 inches

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

CT-2

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

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 4. 5. 6 and 7 continued ATC continued Possible N1-EOP-3.1 Section 3 Actions:

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

CT*2

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

Possible N 1-EOP-3.1 Section 4 Actions:

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

INSTRUCTOR ACTIONS!

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

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

CT-1

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

PUMP 13 BLOCKING VALVE

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

INSTRUCTOR ACTIONS/

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

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

NMP SIMULATOR SCENARIO NRC Scenario 4 REV. 0 No. of Pages: 22 ERV Inadvertently Opens, Powerboard 16A Fault. loss of All RBClC, loss of High Pressure Feedwater, Coolant leak Inside Primary Containment, RPV Flooding PREPARER M~ ZjH""" DATE y~3 VALIDATED Grapes, lavallee, M. O'Brien DATE 12121/12 GEN SUPERVISOR OPS TRAINING CJ.~D..... .h......fA- oJ Atxn\b.s OPERATIONS MANAGER NIA - 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.

The crew will remove Line 4 from service for maintenance. The CRS will determine the Tech Spec impact.

Next, ERV 111 will inadvertently open. The crew will enter N1-S0P-1.4, Stuck Open ERV. The crew will perform an emergency power reduction to approximately 85% power, then take actions to close ERV 111 (Critical Task). These actions will close the ERV, but leave it inoperable.

The CRS will determine the Tech Spec impact.

Next, Powerboard 16A will develop an electrical fault. This will cause a loss of power to three Drywell cooling fans. The crew will start an additional Drywell cooling fan to stabilize Drywell temperature and pressure. The electrical loss will also affect EDG 103 auxiliary equipment.

The CRS will determine the Tech Spec impact.

Next, the running RBClC pumps will trip. The standby RBClC pump will trip upon being started. The crew will enter N1-S0P-11.1, RBClC Failure. The crew will scram the Reactor, trip Recirculation pumps, initiate Emergency Condensers, and shut the MSIVs. The high pressure Feedwater pumps will trip on the scram, complicating Reactor water level control.

Once the crew stabilizes the plant after the scram, a coolant leak will develop inside the Primary Containment. The crew will re-enter N!-EOP-2, RPV Control, and N1-EOP-4, Primary

Containment Control. Containment parameters will degrade and the crew will initiate Containment Sprays (Critical Task). The elevated Containment temperature will cause the Fuel Zone level indicators to flash. With all other Reactor water level indicators downscale, the crew will execute N1-EOP-7, RPV Flooding, to lower Reactor pressure and flood the Reactor to the Main Steam lines (Critical Task).

Major Procedures: N1-0P-33A, N1-S0P-1.4, N1-S0P-1.1, N1-S0P-11.1, N1-S0P-1, N1-EOP 2, N1-EOP-4, N1-EOP-1, N1-EOP-7 Dynamic Mitigation Strategy Code: RL4, loss of all RPV level indication (non-ATWS), RPV Slowdown, RPV Flooding EAL Classification: Site Area Emergency per EAL 2.1.2, RPV water level CANNOT SE RESTORED AND MAINTAINED >-84 in. (TAF) OR RPV Flooding is required Termination Criteria: RPV Flooding in progress, Reactor water level on scale or upscale, Containment pressure and temperature controlled in accordance with N1 EOP-4

I. SIMULATOR SET UP A. IC Number: IC-1S4 B. Presets/Function Key Assignments

1. Malfunctions:
a. CT01 B, CT Pump 112 Trip PRESET
b. ADOS, ERV 111 Failure - Opens Inadvertently TRG 1
c. ED12A, PB 16A Electrical Fault TRG3
d. CW04A, RBCLC Pump 11 Trip TRG4
e. CW04B, RBCLC Pump 12 Trip TRG4
f. CW04C, RBCLC Pump 13 Trip TRG4
g. FW03A, FEEDWATER PUMP TRIP 11 TRGS
h. FW03B, FEEDWATER PUMP TRIP 12 TRGS
i. FW06, SHAFT DRIVEN FEEDWATER PUMP CLUTCH FAILS DISENGAGES TRGS
j. CU01, CU COOLANT LEAK INSIDE OF DRYWELL, FV=70, RT=S:OO TRG6
k. EC01, Steam Supply Line Break in PC, FV=S, RT=S:OO TRG6 I. RR87, FUEL ZONE LEVEL INSTRUMENT FLASHING TRG7
2. Remotes:
a. AD01A, ERV 111 Fuses, FV=pulled TRG27
b. AD07, Acoustic Monitor Alarm Reset, FV=reset TRG28
3. Overrides:
a. None
4. Annunciators:
a. None S. Triggers:
a. TRG S - Activates on Reactor scram to insert loss of Feedwater
i. Event Action: zdrpstdn==1 ii. Command: None
b. TRG 7 - Activates on DWtemp >200oF, LLL level below -20", and Containment Spray flow to Drywell >100 gpm to insert Fuel Zone flashing
i. Event Action: hzarrI19<0. 07 S&&hzarrI20<0. 07 S&&pctdw8> 200&&ctfdw> 100 ii. Command: None C. Equipment Out of Service
1. Containment Spray pump 112 in PTL with yellow tag
2. Containment Spray suction valve 112 closed with yellow tag
3. Steam Packing Exhauster 12 green flagged with yellow tag D. Support Documentation
1. N1-0P-33A Section H.12 marked up to Step H.12.9.

E. Miscellaneous

1. Ensure Drywell cooling fan 11 is secured with control switch in neutral.
2. Protect the following equipment: EDG102, EDG 103, PB 102, PB 103, Line 1, MOD 8106.
3. Update Divisional Status Board.

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

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

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

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

  • Reactor power is approximately 100%.
  • 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.

PART III: Remarks/Planned Evolutions:

Remove Line 4 from service per N1-0P-33A Section H.12 to support National Grid maintenance. The procedure has been completed up to Step H.12.9.

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

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

TITLE NAME TITLE NAME II SRO  !

ATCRO BOPRO

Critical Tasks:

CT-1 Given an inadvertently open ERV at power, close the ERV or insert a manual scram prior to Torus temperature exceeding 110°F, in accordance with N1-S0P-1.4.

Safety Significance: A manual Reactor scram is required before Torus temperature exceeds 110°F. This reduces the rate of energy production and thus heat input to the Torus. Additionally, this allows evaluating the success of the Reactor scram before boron injection would be required due to Torus temperature in the event of a failure to scram. Closing the ERV prior to the need for the scram avoids the need for these more substantial actions, prevents challenging the plant with a scram, and stops heat input to the Torus.

Cueing: ERV position, ERV acoustic monitors, ERV tailpipe temperature, Torus temperature, Reactor pressure, and steam flow indicate an open ERV. N1-S0P 1.4 provides direction to close the ERV or scram the Reactor.

Measurable Performance Indicators: Pulling ERV fuses, directing an operator to pull ERV fuses in the field, rotating the Mode Switch to SHUTDOWN, and/or depressing the manual scram pushbuttons will provide observable actions for the evaluation team.

Performance Feedback: ERV position, ERV acoustic monitors, ERV tailpipe temperature, Torus temperature, Reactor pressure, and steam flow will provide performance feedback regarding success of crew actions to close the ERV.

Control rod position and Reactor power will provide performance feedback regarding success of crew actions to scram the Reactor.

CT-2 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 initiate Containment Sprays.

CT-3 Given the plant with RPV water level unknown, execute N1-EOP-7, RPV Flooding, in accordance with N1-EOP-2.

Safety Significance: With Reactor water level unknown, the status of core cooling is unknown. RPV flooding is required to establish conditions to cool the core. This protects the fuel cladding integrity.

Cueing: Multiple Reactor water level indications will indicate either downscale or invalid. N1-EOP-2 provides direction to implement N1-EOP-7, RPV Flooding.

Measurable Performance Indicators: Manipulation of ERVs, MSIVs, ECIVs, and injection system controls provide observable actions for the evaluation team.

Performance Feedback: ERV, MSIV, and ECIV position indications, Reactor pressure, ERV tailpipe temperatures, and ERV acoustic monitors provide performance feedback regarding success of RPV flooding actions.

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

  • Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Remove Line 4 From Service SRO
  • Directs removing Line 4 from service per N1-0P-33A Section H.12
  • Provides oversight for evolution

BOP

  • Reviews N1-0P-33A Section H.12
  • Verifies Auto Reclosure for R-40 breaker is OFF Role Play:
  • Opens breaker R-40 When asked as Operator to confirm R40 position,
  • Dispatches Operator to confirm R-40 immediately report all three phases of R-40 are open locally on ALL 3 phases open.
  • Notifies SM to review TS for appropriate LCO applicability
  • Continues at Section H.9.0, Loss of 115 KV Line 4 ATC
  • Monitors plant parameters

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 2 - ERV 111 Inadvertently Opens CREW When directed by lead examiner, insert

  • Diagnoses ERV 111 has inadvertently opened ADOS, ERV 111 Failure - Opens Inadvertently TRG 1 ERV 111 opens Reactor pressure lowers slightly Reactor power lowers and then rises slightly Torus temperature rises Torus level rises Expected annunciators:

F1-4-8, STEAM LINE DETECTION SYS FLOW OFF NORM F2-4-1, MAIN STM LINE ELECTROMA TIC RELIEF VALVE OPEN H3-4-5, PRESS SAFETY/RELIEF VALVES FLOW SRO

  • Acknowledges reports
  • Directs entry into N1-S0P-1.4, Stuck Open ERV
  • Directs emergency power reduction to approximately 85% power
  • Provides oversight for reactivity manipulation
  • Determines that ERV 111 is inoperable per TS 3.1.5.a, requiring a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> shutdown
  • Directs taking action to close ERV 111 or directs a manual scram prior to Torus temperature exceeding 110°F, in accordance with N1-S0P 1.4 CT-1

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 2 continued SRO continued

  • Acknowledges that ERV 111 has closed
  • Enters N1-EOP-4 if Torus temp rises above 85°F or Torus level rises above 11.25'
  • May direct initiation of Torus Cooling per N1-EOP-1 att 16 or N1-S0P-1.4 ATC
  • Performs emergency power reduction per N1-S0P-1.1
  • Reduces Recirculation master controller to lower power to approximately 85%
  • Monitors Recirculation flow
  • Monitors position on power to flow map

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 2 continued BOP

  • Enters N1-S0P-1.4
  • Determines ERV 111 is open using:

- Valve indicating lights on F panel Role Play: - Red ERV flow indicating light on F When directed as Operator to go to Auxiliary panel Control Room and verify ERV 111 is open, wait

  • Sends an operator to the Aux Control one minute and report ERV 111 is open. Room to verify ERV open using Subsequent reports on acoustic monitor status may Acoustic Monitor be given immediately, with close attention paid to
  • May send an operator to RB 237' to the actual status of the ERV. standby for pulling local ERV fuses
  • Attempts to close ERV 111 by performing one or all of the following:

Note:

  • Depresses ADS Timer Reset Safety glasses and gloves are required for pulling pushbuttons fuses in F panel.
  • Cycles Control Switch for ERV 111
  • Pulls control power fuses F15 and F30 in F panel (ERV 111)

Role Play:

OR If the Operator is directed to pull fuses in the RB

  • Directs operator to pull ERV 111 wait 3 minutes and insert remote:

fuses on RB 237' AD01A, ERV 111 Fuses, FV=pulled CT-1 TRG 27

  • Checks with operator in Aux Control Report fuses are pulled. Room to see if ERV is still open
  • Determines/verifies ERV closes
  • Directs reset of acoustic monitor Role Play:
  • Notifies crew that ERV 111 has closed When directed as operator to reset the acoustic
  • Monitors Torus temperature monitor, wait 1 minute and insert remote:
  • Reports if/when Torus temperature exceeds 85°F or Torus level exceeds AD07, Acoustic Monitor Alarm Reset, FV=reset 11.25' TRG28

in PTL if directed

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 2 continued BOP continued

  • Places Torus cooling in service when directed, per N1-S0P-1.4, att 2 or N1 EOP-1 att16:
  • Close CONT SPRAY BYPASS BV(s) for selected loop
  • Verifies closed 80-115
  • Verifies closed 80-114
  • Verifies closed Cont Spray Discharge IV for selected loop
  • Verifies open CONT SPRAY BYPASS BV for selected loop

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 - Powerboard 16A Electrical Fault CREW When directed by lead examiner, insert

  • Recognize/report loss of Powerboard malfunction: 1SA
  • Recognize/report trip of three Drywell ED12A, PB 16A Electrical Fault cooling fans TRG 3
  • Recognize/report trip of RBCLC pump Three Drywell cooling fans de-energize 11 Drywell pressure and temperature rise
  • Recognize/report Spent Fuel Pool Spent Fuel Pool Cooling pump 11 trips trouble alarm RBCLC pump 11 trips Expected Annunciators:

L4-3-6, DRYWELL COOLING FAN TRIP-VIB A4-3-1, POWER BD. 16 R1041 TRIP A4-4-2, POWER BD. 16 LOWBUS VOLTAGE L 1-4-5, FUEL POOL ANNUNCIATOR SRO

  • Directs execution of ARPs
  • Directs start of Drywell cooling fan 11
  • May direct lowering RBCLC temperature
  • May direct Reactor power reduction per N1-S0P-1.1
  • If Drywell average temperature exceeds 150oF, enters N1-EOP-4
  • Directs entry into N1-S0P-S.1, Loss of SFP/Rx Cavity LevellDecay Heat Removal
  • May direct start of RBCLC pump 12

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued ATC

  • Monitors plant parameters
  • If directed, lowers Reactor power per N1-S0P-1.1 BOP
  • Dispatches operator/maintenance to investigate Powerboard 16A Role Play:
  • Dispatches operator to investigate If requested to investigate Powerboard 16A, wait 2 Spent Fuel Pool alarm minutes, then report the feeder breaker is tripped
  • Acknowledges/reports Powerboard and there is an acrid odor in the area. Electrical 16A is faulted Maintenance does NOT recommend re-energizing
  • Starts Drywell cooling fan 11 Powerboard 16A.
  • Green flags Drywell cooling fans 14, 15, and 16 Role Play:
  • May start RBClC pump 12 If requested to investigate SFPC trouble, wait 2
  • May green flag RBClC pump 11 minutes, then report SFPC pump 11 tripped. If
  • If directed, lowers RBClC temperature directed to restore SFPC, acknowledge order, but per N1-0P-11:

delay any action for rest of scenario.

o Places RBClC TCV in manual:

o Depresses the AIM Button UNTil red lED is illuminated next to "M" o Verifies 70-23BV is displayed in the lED readout o IF 70-23BV is NOT displayed, THEN depresses the "0" button UNTil the display shows70-23B.V o Adjusts RBClC temperature as desired o May lower RBClC TCV automatic setpoint per N1-0P-11 Section H.24.0

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued o May place RBCLC TCV back in automatic:

o Depresses the AIM Button UNTIL green LED is illuminated next to "A" o Verifies70-23B.P is displayed in the LED readout o IF 70-23B.P is NOT displayed, THEN depresses the "0" button UNTIL the display shows70-23B.P o Verifies TCV-70-137 is responding properly to automatic control

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Events 4 and 5 - All RBCLC Pumps Trip. CREW Feedwater Pumps Trip

  • Recognize/report trip of all RBCLC When directed by lead examiner, insert pumps malfunction:
  • Later:

CW04A, RBCLC Pump 11 Trip o Recognize/report Feedwater pump CW04B, RBCLC Pump 12 Trip 11 and 12 trips CW04C, RBCLC Pump 13 Trip o Recognize/report Feedwater pump TRG4 13 disengages RBCLC pumps trip o Recognize/report low Reactor RBCLC pressure lowers water level RBCLC temperature Expected Annunciators:

H1-1-1, REACTOR BLDG COOL PUMP 11 TRIP V-SUCT H1-2-1, REACTOR BLDG COOL PUMP 12 TRIP V-SUCT H1-3-1, REACTOR BLDG COOL PUMP 13 TRIP V-SUCT H1-4-1, R BUILDING COOLING WATER PRESS TEMP MAKEUP FLOW K2-4-3, DRYWELL PRESSURE HIGH-LOW K3-4-4, CLEAN-UP SYSTEM ISOLA TlON

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4 and 5 continued SRO

  • Acknowledges reports Verify the following malfunctions are
  • Directs entry into N1-S0P-11.1 automatically inserted when the Reactor scrams:
  • Directs execution of override, PUMP CLUTCH FAILS - DISENGAGES including:

TRG5 o Manual Reactor scram Feedwater pumps 11 and 12 trip immediately after o Trip Recirculation pumps starting, Feedwater pump 13 disengages o Initiate Emergency Condensers Reactor water level remains lower than normal o Close MSIVs Expected Annunciators: o Trip RWCU pump H3-1-7, REACTOR FWPUMP 11 TRIP

  • Acknowledges scram report OVERLOAD SUCTION HI-LEVEL
  • Enters N1-EOP-2, RPV Control, on H3-2-7, REACTOR FWPUMP 12 TRIP low RPV water level OVERLOAD SUCTION HI-LEVEL
  • Answers "Are all control rods inserted H3-4-8, REACTOR FW SHAFT P13 CLUTCH to at least position 041" YES TROUBLE
  • Directs entry into N1-S0P-1, Reactor F2-3-3, REACT VESSEL LEVEL HIGH-LOW Scram
  • Acknowledges trip of Feedwater Note: Expected initial RPV water level control pumps band is narrower (ex. 0" to 95").
  • Directs RPV water level controlled between -84" and 95" using CRD and/or Liquid Poison
  • Directs RPV cooldown <10QoF/hr using Emergency Condensers

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 4 and 5 continued ATe

  • Places Reactor Mode Switch to SHUTDOWN
  • Performs scram verification actions of N 1-S0P-1, Reactor Scram:
  • Confirms all rods inserted
  • Observes Reactor power lowering
  • Places IRMs on range 9
  • Down-ranges IRMs as necessary
  • Controls RPV pressure as directed using Emergency Condensers BOP
  • Executes N 1-S0P-11. 1
  • Attempts to start standby RBCLC pump
  • Informs crew of need to execute Note: override Depending on timing, Lo-Lo Reactor water level
  • Enters N 1-S0P-1 may trip Recirculation pumps, initiate Emergency
  • Informs crew of Feedwater pump trips Condensers, and close MSIVs before operator and low Reactor water level action.
  • Trips Recirculation pumps
  • Initiates Emergency Condensers Note:
  • Closes MSIVs RWCU will likely trip on high temperature before
  • Verifies RWCU pump tripped operator action.
  • May maximize CRD flow by starting second CRD pump and/or taking FCV to manual and opening further
  • May start Liquid Poison

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 6 and 7 - Coolant Leak Inside Primary CREW Containment and Fuel Zone Level Instrument

  • Recognize/report degrading Flashing Containment parameters When directed by lead examiner, insert malfunctions:

CU01, CU Coolant Leak Inside of Orywell, RT=5:00, FV=70 EC01, Steam Supply Line Break in PC, RT=5:00, FV=5 TRG6 Containment parameters degrade RPV water level lowers Expected annunciators:

H2-4-7, DRYWELL WA TER LEAK DETECTION SYS K2-4-3, DRYWELL PRESSURE HIGH-LOW L 1-4-4, DRYWELL - TORUS TEMP HIGH F1-1-5, RPS CH 11 DRYWELL PRESS HIGH F4-1-4, RPS CH 12 DRYWELL PRESS HIGH F1-2-3, RPS CH 11 REACTOR LEVEL LOW-LOW F4-2-6, RPS CH 12 REACTOR LEVEL LOW-LOW F1-3-3, RPS CH 11 REACTOR LEVEL LOW-LOW LOW F4-3-6, RPS CH 12 REACTOR LEVEL LOW-LOW LOW SRO

  • Acknowledges reports from the crew
  • Re-enters N1-EOP-4 on high Orywell pressure
  • Re-enters N1-EOP-2 on high Orywell pressure

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 6 and 7 continued SRO continued Note: Due to an already low RPV water level

  • Transitions to Alternate Level Control when Drywell pressure reaches 3.5 psig, leg of N1-EOP-2 Containment Spray may auto-start before the crew
  • Direct ADS bypassed can prevent it. In accordance with the EOPs, the
  • Verifies EC initiation crew will then verify proper operation per N1-EOP
  • If either Dryweli temperature 1 attachment 17. In this case, Critical Task 2 shall approaches 300°F or Torus pressure be evaluated as "Not Applicable". exceeds 13 psig:

o Answers "Below the Containment Spray Initiation Limit?" Yes o Verifies all Recirc pumps tripped Verify the following malfunction is automatically o Directs trip of all Drywell cooling inserted when OW temp is above 200°F, LLL level fans indicates below -20", and Containment Spray has o Direct Containment Sprays per been initiated: N1-EOP-1 attachment 17 CT-2 RR87, FUEL ZONE LEVEL INSTRUMENT

  • Monitors location on Pressure FLASHING Suppression Pressure curve TRG 7
  • Acknowledges flashing of Fuel Zones
  • Acknowledges RPV water level is Fuel Zone indications blink on and off with sporadic unknown numbers
  • Exits N1-EOP-2, enters N1-EOP-7, All other RPV water level instruments are either RPV Flooding downscale or below minimum usable levels CT-3
  • Answers "Are all control rods inserted to at least position 04?" Yes
  • Answers "Torus water level?" Above 8.0ft

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 6 and 7 continued SRO continued

  • Answers "Can any ERV be opened?"

Yes

  • Directs MSIVs and EC steam IVs verified closed
  • Acknowledges RPV water level rising ATC/BOP
  • Verifies EC initiation
  • Monitors Containment parameters
  • Reports if either Drywell temperature approaches 300°F or Torus pressure exceeds 13 psig
  • Verifies all Recirc pumps tripped
  • Trips all Drywell cooling fans

CT-2

  • Reports Containment pressure and temperature lowering

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 6 and 7 continued A TC/BOP Continued

  • Recognizes/reports flashing of Fuel Zones
  • Recognizes/reports RPV water level is unknown
  • Verifies MSIVs and EC steam IVs closed
  • Monitors for indications of successful flooding
  • Reports RPV water level rising Terminating Cues:
  • RPV Flooding in progress
  • Reactor water level on scale or upscale
  • Containment pressure and temperature controlled in accordance with N1-EOP-4

NMP SIMULATOR SCENARIO NRC Scenario 5 REV. 0 No. of Pages: 27 Startup. APRM Fails Upscale, Sequential Loss of 115 KV Lines, Loss of Vacuum, Loss of Coolant Accident. Core Spray Fails to Auto-Start PREPARER A/~VL *7 ISHIt"'. DATE 3/~/l3

}~

VALIDATED Grapes, Lavallee, M. O'Brien DATE 12121/12 GEN SUPERVISOR OPSTRAINING ~37: .. I A-o 4"""'"'Ab DATE a/r/J'

" ....s 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 JRMs.

APRM 12 then fails upscale. The crew will bypass the APRM. The CRS will determine the Tech Spec impact.

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 Joss 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. Powerboards 102 and 103 will be powered by the Emergency Diesel Generators. Powerboards 11, 12, and 101 will de-energize. This results in a loss of all Feedwater. The crew will enter N1-S0P-33A.1, Loss of 115 KV.

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

The crew will enter N1-EOP-2, RPV Control, and N1-EOP-4, Primary Containment Control. The crew will initiate Containment Spray as Primary Containment conditions degrade (Critical Task). The leak will be beyond the capacity of available high pressure injection sources and

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

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

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

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

1. Malfunctions:
a. NM19B, APRM CHANNEL 12 FAILURE - UPSCALE TRG 1
b. ED02A, 115 kV Line 1 (South Oswego) Loss of Offsite Power TRG 2
c. MC01, MAIN CONDENSER AIR INLEAKAGE, FV=18 TRG 3
d. ED01 A, 115 kV Line 4 (JAF) Loss of Offsite Power, Delay=1 :30 TRG 4
e. RR29, RR Loop Rupture on Pump 15 Suction Line (LOCA), FV=17 TRG 5
f. CS06, CS Pumps Failure to Auto Start PRESET
2. Remotes:
a. RP21, RPS UPS 162 TROUBLE ANN RESET, FV=reset TRG 28
b. RP22, RPS UPS 172 TROUBLE ANN RESET, FV=reset, DT=10 TRG 28
c. ED40A, I&C Bus 130 NC Supply Breaker from PB 13B, FV=open TRG 29
d. ED40B, I&C Bus 130 NO Supply Breaker from PB 167A, FV=close, DT=5 TRG 29
e. FP04, FIRE WrR TO FW BLOCKING VLVS, FV=100 TRG 21
f. CT03A, CT Raw Water Pump 111 Disch. Throttle Valve 93-14, FV=10 TRG 22
g. FW25, MANUAL OPER. FW FCV-11, FV=O TRG 23
h. FW26, MANUAL OPER. FW FCV-12, FV=O TRG 24
i. FW27 , MANUAL OPER. FW FCV-13, FV=O TRG 25
3. Overrides:
a. None
4. Annunciators:
a. None
5. Triggers:
a. TRG 4 - Causes loss of Line 4 after the Mode Switch is taken to shutdown
i. Event Action: zdrpstdn==1 ii. Command: None
b. TRG 5 - Causes the LOCA to begin when Powerboard 16 is crosstied
i. Event Action: zded602c==1 ii. Command: None
c. TRG 10 - Makes Condenser vacuum degrade faster once the Turbine is tripped
i. Event Action: tc:trip==1 ii. Command: imf mc01 (0 0) 50 C. Equipment Out of Service
1. Steam Packing Exhauster 12 green-flagged with yellow tag.

D. Support Documentation

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

E. Miscellaneous

1. None

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

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

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

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

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

PART III: Remarks/Planned Evolutions:

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

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

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

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

TITLE NAME TITLE NAME SRO ATCRO BOPRO

Critical Tasks:

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

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

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

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

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

CT-2 Given Reactor water level below the top of active fuel and Reactor pressure above the capacity of available low pressure injection systems, perform an emergency depressurization of the Reactor, in accordance with N 1-EOP-2 and N 1-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 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.

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

  • Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Raise Reactor Power with Control Rods SRO
  • Directs ATC to withdraw rods per Startup Rod Sequence and N1-0P-5 section F.'1. 0
  • Provides oversight for reactivity manipulation ATC
  • Places 4S1 Control Rod Movement switch to the rod out notch position o Observes SRM and period response o Observes RMCS, RPIS and CRD indications
  • Informs SRO when the first four rods of the current control rod group are withdrawn BOP
  • Monitors plant parameters

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 2 - Place Mode Switch in RUN and SRO Withdraw IRMs

  • Acknowledges first four rods of the current control rod group are withdrawn
  • Directs placing Mode Switch in RUN and withdrawing IRMs per N1-0P-43A
  • Provides oversight for evolution ATe
  • 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 C05?, MODE SWITCH RUN - YES
  • Transfer recorder indication to APRM channels
  • Depress the FULL OUT button for each IRM
  • WHEN the IRM detectors indicate full out, THEN range down the individual IRM Range switches to Range 2 OR UNTIL the respective IRM Downscale AND Upscale lights are out on E Console

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 - APRM 12 Fails Upscale CREW When directed by lead examiner, insert

  • Recognize/report APRM 12 upscale malfunction:

F1-1-1, RPS CH 11 REACT NEUTRON MONITOR F1-2-1, RPS CH 11 AUTO REACTOR TRIP F2-1-6, APRM 11-14 F3-4-4, ROD BLOCK SRO

  • Acknowledges reports from crew
  • Directs response per ARPs
  • Directs bypass of APRM 12
  • Monitors plant parameters BOP
  • Observes E Panel and determines APRM 12 UPSCALE HI and UPSCALE HI-HI lights are lit

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued

  • Observes G Panel to determine if any APRM INOP lights are lit on respective LPRM-APRM AUXILIARIES drawer
  • Monitors APRM recorder for power level
  • Verifies proper power to flow ratio on Power Flow Operation Map in E Panel
  • Notifies SRO to verify Technical Specifications
  • Refers to N 1-0P-38C to bypass APRM 12
  • Places APRM 12 bypass switch to BYPASS
  • Confirms APRM BYPASS light is lit on PanelE
  • Confirms computer printout "APRM 12 BYPASS YES"
  • Confirms APRM BYPASS light is lit on the LPRM-APRM auxiliaries drawer

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 4 - Loss of Line 1 CREW When directed by lead examiner, insert

  • Recognize/report loss of Line 1 malfunction:

ED02A, 115 kV Line 1 (South Oswego) Loss of Offsite Power TRG2 Breaker R1 0 opens Expected Annunciators:

A8-1-1, OSW-NMP 1 R10 TRIP A8-1-2, OSW-NMP 1 LINE RELAY TRIP SRO

  • Acknowledges reports
  • Directs execution of ARPs
  • Monitors plant parameters BOP
  • Dispatches an operator to the Aux.

Control Room to observe the following Panels for flags AND targets:

Role Play: o 1D1 OSWEGO NINE MILE POINT If dispatched to Auxiliary Control Room, wait 2 1 minutes, then report an undervoltage target is in on o 1D2115 KV RESERVE BUS &

panel 1D1 OSWEGO NINE MILE POINT 1. BREAKER R10-R40 If dispatched to switchyard, wait 4 minutes, then o 1D3 NINE MILE POINT report R10 is open with no abnormal indications. LIGHTHOUSE HILL 4

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 4 continued BOP continued

  • Observes 86TN relay on Panel 8A to see if it has tripped
  • Observes back of Panel 88 in the Control Room for flags AND targets
  • Records time of trip AND targets
  • Performs N1-0P-33A Section H., Loss 115 kV Line 1:

o Places computer points F432, Role Play: F433, AND F434 on a special log If contacted as Power Control, report that you are computer printout with a one dispatching a crew to investigate loss of line 1 and minute scanning interval (Interval =

you have no reason for the loss yet. If asked to run 4) per N1-0P-42 AND monitors a Load Flow, wait 3 minutes, then call back and o Contacts System Power Control report that the Low Contingency Voltage Alarm is AND makes notification of the low NOT in alarm. voltage alarm AND to run a Load Flow o Contacts JAF Control Room in an expeditious manner AND informs them of the loss of 115 kV Line 1

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 5 - Loss of Condenser Vacuum CREW When directed by lead examiner, insert

  • Recognize/report lowering main malfunction: condenser vacuum MC01, MAIN CONDENSER AIR INLEAKAGE,

FV=18

  • A1-3-4, CONDENSER VACUUM TRG 3 BELOW 24" HG Main Condenser vacuum lowers Offgas flow rate rises Expected Annunciator:

A 1-3-4, CONDENSER VACUUM BELOW 24" HG SRO

  • Acknowledges reports
  • Determines condenser vacuum can NOT be maintained above 22.1" Hgv
  • Determines condenser vacuum can NOT be maintained above 10" Hgv
  • Acknowledges scram report
  • Directs entry into N1-S0P-1, Reactor Scram Note:
  • Directs Reactor water level controlled Initial Reactor pressure control may be on the 53-95" with Condensate, Feedwater, Turbine Bypass Valves, but will transition soon and CRD after the scram to the Emergency Condensers as

800-1000 psig with Emergency Condensers

  • When vacuum approaches 10" Hgv, directs trip of Vacuum Trip 2 Note:
  • When vacuum approaches 7.0" Hgv, May close MSIVs earlier to control cooldown rate.

directs closing the MSIVs

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 5 continued ATC

  • Monitors plant parameters
  • Places Reactor Mode Switch to SHUTDOWN
  • Performs scram verification actions of N1-S0P-1, Reactor Scram:
  • Confirms all rods inserted
  • Observes Reactor power lowering
  • Places IRMs on range 9
  • Inserts IRM and SRM detectors Note:
  • Down-ranges IRMs as necessary Initial Reactor pressure control may be on the

using Emergency Condensers BOP

  • Verifies proper operation of the following:

o Circ Water System o SJAEs o Off Gas System o Condensate System o Turbine Gland Seal System

  • Dispatches operator to check for condenser leakage

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 5 continued BOP continued

  • Coordinates with ATC to trip Turbine:

Note: o Depresses AND holds down When the Turbine is tripped, verify TRG 10 FEEDWATER RETURN TO automatically inserts: NORMAL AFTER HPCI CH 11 MC01, MAIN CONDENSER AIR INLEAKAGE, and 12 pushbuttons.

FV=50 o Depresses UNIT EMERGENCY Main Condenser vacuum lowers quicker TRIP pushbutton AND executes N1-S0P-31.1, Turbine Trip o Releases FEEDWATER RETURN TO NORMAL AFTER HPCI CH 11 and 12 push buttons

  • Enters N 1-S0P-1
  • Controls Reactor water level 53-95" using Condensate, Feedwater, and CRD
  • When directed, closes MSIVs

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 6 - Loss of Line 4 CREW Verify the following malfunction automatically

  • Recognize/report loss of Line 4 inserts when the Mode Switch is taken to
  • Recognize/report start of EDGs SHUTDOWN:

ED01 A, 115 kV Line 4 (JAF) Loss of Offsite Power, Delay=1 :30 TRG4 Breaker R40 opens Control Room lights go out Both Emergency Diesel Generators (ED G) start Power is lost to the following major loads:

  • Recirc pumps
  • Circulating Water pumps

A8-1-3, 115 KV. BUS LOW VOLTAGE A8-1-7, NMP- FITZ 4 R40 TRIP A8-1-8, NMP - FITZ 4 LINE RELAY TRIP SRO

  • Acknowledges reports from the crew
  • Directs execution of N1-S0P-33A.1
  • Directs Reactor water level controlled 53-95" using CRD
  • Exits N1-EOP-5 when Reactor Building D/P is restored

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Event 6 continued ATC/BOP

  • Executes N 1-S0P-33A.1

o EDG 102 SUPPLY BKR R-1022 has closed o Powerboards 102 AND 16B are energized o EDG 103 SUPPLY BKR R-1032 has closed o Powerboards 103 AND 17B are energized

  • Answers "Are PB 11 AND 12 energized?" No
  • Answers "Is any EDG running?" Yes
  • Verifies the following:

o PB 16A-B Tie Bkr R-1042 is tripped o PB 17A-B Tie Bkr R-1052 is tripped o Inst. Air Camp. (lAC) 11 and 12 in PTL

  • Continues at Page 4, Arrow B
  • Monitors EDG 102 AND 103 KW loading

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 6 continued ATe/BOP continued

  • IF EDG KW exceeds 2300 KW (PB Note: 102 or 103 Loading), THEN:

The EDG load override in N 1-S0P-33A.1 will not o Verifies the following:

be applicable initially, but may be executed later

  • R-1042 tripped, PB 16 A-B Tie Bkr
  • R-1052 tripped, PB 17 A-B Tie Bkr
  • Verifies Lockouts 86-16 and 86-17 reset
  • Places CRD Pump 11 AND 12 in PTL
  • RBCLC Pump 11, 12 AND 13 secured
  • WHILE continuing, sends operator to When dispatched for load reductions, wait 4 perform load reductions of Attachment minutes, then report Attachment 2, Section 1 load 2, Section 1 reductions are complete.
  • Verifies Lockouts 86-16 AND 86-17 reset

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 6 continued ATC/BOP continued

  • Verifies RBCLC Pump 13 started, if available
  • Verifies RBCLC Pump 12 started, if required
  • Starts ESW PUMP 11 AND 12 AND Role Play: monitors equipment temperature listed When dispatched to check UPS 162 and 172, wait in N1-S0P-18.1, Tables 18.1 and 18.2 two minutes, then insert remotes:
  • Verifies the following:

o CRD Pumps 11 AND 12 started, if RP21, RPS UPS 162 TROUBLE ANN RESET, required, UNLESS secured per FV=reset override above RP22, RPS UPS 172 TROUBLE ANN RESET, 0 MG Set 167 transfers back to AC FV=reset, OT=10 drive TRG 28 0 UPS 162 AND 172 re-energizes Then report that UPS 162 and 172 have 0 SBC 161 AND 171 re-energizes transferred back to AC input and you have reset

  • Re-establishes Rx Bldg. differential alarms. pressure as follows:

o Verifies RB Supply AND Exhaust Fans tripped Role Play: o Closes RB Supply AND Exhaust When dispatched to restore power to I&C Bus 130, Isolation Valves wait two minutes, then insert remotes: o Verifies RBEV Train 12 initiated, secures RBEV Train 11 E040A, IC Bus 130 NC Supply Breaker From PB

  • Dispatches operator to restore power 13B, FV=open to I&C Bus 130 E040B, IC Bus 130 NO Supply Breaker From PB
  • Verifies RBCLC Pump 12 in PTL Then report that I&C Bus 130 is re-energized from
  • Verifies ESW Pump 12 in PTL the maintenance supply.
  • Verifies lAC 11 in PTL

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 6 continued ATC/BOP continued

  • Verifies one CRD Pump running as follows UNLESS secured per override above o CRD Pump 12 running o CRD Pump 11 in PTL
  • Verifies load reductions of Attachment 2 Section 1 complete
  • Restores power to PB 16A as follows:

o Trips R-1041, PB 16A Supply Bkr o Closes R-1042, PB 16A-B Tie Bkr

  • Verifies RBCLC Pumps 11 OR 13 running
  • IF TSC Power is required, AND PB 16B load is less than 900 amps, THEN Places in ON, NDS-1 disconnect switch (TSC Emergency Power)
  • Restores power to PB 17A as follows:

o Trips R-1 051, PB 17A Supply Bkr o Closes R-1052 PB 17A-B Tie Bkr

  • Verifies lAC 12 started
  • Follows N 1-0P-6 for recovery of Spent Fuel Pool cooling requirements

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 7 & 8 - Loss of Coolant Accident and CREW Core Spray Fails to Auto-Start

  • Recognize/report degrading Primary Verify the following malfunction automatically Containment parameters inserts when Powerboard 16 is crosstied:
  • Recognize/report lowering Reactor RR29, RR Loop Rupture on Pump 15 Suction water level and pressure Line, FV=17 TRG5 Drywellleakage, humidity, temperature and pressure rise Reactor water level and pressure lower Expected Annunciators:

H2-4-7, Drywell Water Leak Detection Sys K2-4-3, Drywell Pressure High-Low F1-1-5, RPS Ch 11 Drywell Press High F4-1-4, RPS Ch 12 Drywell Press High Verify the following malfunction is preset:

CS06, CS Pumps Failure to Auto Start Core Spray pumps do NO T auto-start 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

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 7 & 8 continued SRO continued

  • When Torus pressure exceeds 13 psig or Drywell temperature approaches 300°F:
  • Verifies all Recirc pumps are tripped
  • Directs trip of all Drywell cooling fans
  • Evaluates/monitors position on Pressure Suppression Pressure curve
  • Directs Reactor water level control

-84" to 95" with CRD and Liquid Poison

  • Transitions to alternate level control leg of N1-EOP-2
  • Directs ADS bypassed
  • Directs verification of EC initiation
  • 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 continued SRO continued

  • Enters N1-EOP-8, RPV Slowdown:
  • Answers "Are all control rods inserted to at least position 04?"

Yes

  • Answers "Drywell pressure?" - At or above 3.5 psig
  • Directs EC initiation
  • Answers "Torus water level?"

Above 8.0 ft

  • Directs open 4 ERVs CT-2
  • Verifies injection of entire contents of Liquid Poison tank
  • Directs injection with available systems to restore and maintain Reactor water level above -84 inches CT-3
  • Directs installation of Core Spray jumpers (N1-EOP-1 attachment 4) to allow control of Core Spray IVs
  • Transitions back to normal level control leg of N1-EOP-2
  • Directs restoration of Reactor water level to 53-95" ATC/BOP
  • Updates crew on Reactor and containment parameters
  • Recognizes/reports failure of Core Spray to auto-start

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Events 7 & 8 continued ATC/BOP continued

  • Maximizes RPV injection with CRD and Liquid Poison
  • When Torus pressure exceeds 13 psig or drywell temperature approaches 300°F:
  • Verifies all Recirc pump are tripped
  • Trips all Drywell cooling fans

CT-1

  • Verifies EC initiation
  • Verifies 39-05 and 39-06 open or previously open
  • May secure ECs for pressure control
  • If RPV water level is above 5",

then closes 39-05 and/or 39-06

  • If RPV water level is below 5", then closes EC steam IVs
  • When Reactor water level drops below

-84":

  • Initiates ECs
  • Verifies open 39-05
  • Verifies open 39-06

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 7 & 8 continued ATC/BOP continued

  • Verifies Liquid Poison injection to Role Plays: inject entire contents of Liquid Poison If requested to lineup Firewater to Feedwater, wait tank five minutes, then insert remote:
  • Injects with available systems to FP04, FIRE WTR TO FW BLOCKING VLVS, restore and maintain Reactor water FV=100 level above -84" TRG 21 CT-3 Then report Firewater is lined up to Feedwater.
  • Bypasses Core Spray IV interlocks per Modify the remote as requested to throttle flow. N 1-EOP-1 Att 4 by installing six jumpers (17, 18, 19,24,25,26) inside If requested to throttle Containment Spray Raw PanelN Water 111 discharge valve, wait 3 minutes, then
  • Throttles Core Spray IVs as necessary insert remote: to control Reactor water level CT03A, CT Raw Water Pump 111 Disch. Throttle
  • Restores Reactor water level to 53-95" Valve 93-14, FV=10 TRG22 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 TRG 23 FW26, MANUAL OPER. FW FCV-12, FV=O TRG24 FW27, MANUAL OPER. FW FCV-13, FV=O TRG25 Then report the appropriate FCV is pinned and fully closed. Modify the remote as requested to throttle flow.

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Terminating Cues:

  • RPV Slowdown in progress
  • Reactor water level controlled above top of active fuel
  • Containment pressure and temperature controlled in accordance with N1-EOP-4
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