Latest revision as of 04:11, 6 February 2020

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

NIA - Exam Security /

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

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

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

Evaluation Method: _~_ _ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant _ _---'--"--__ Simulator Expected Completion Time: 20 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: _ _ _ __ Completion Time: _ _ _ __

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

Comments:

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

NRC 2013 JPM RO COOl May 2013

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

Simulator Simulator Set-up:

1. Initialize Simulator to IC-166

2. Verify the following overrides are set:

a. 5M80A03550 73.00

b. 5M81A03560 75.00

c. 5Ml18A03860 = 76.00

d. 5Ml16A03840 = 68.00

e. 5ARITSIA031000 = 68.00

f. 13MIA042680 69.00

g. 9M53A051270 70.50

3. Take the simulator to Run, and then back to Freeze

4. Verify average DryweU temperature is less than 130°F

5. Verify total Recirc flow is 38 Mlbmlhr

6. Verify FWLC is selected to column 11

7. Tum off PI monitor Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

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

NRC 2013 JPM RO COOl May 2013

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas PasslFail. All steps are sequenced critical unless denoted by a

2. During Evaluated JPM:

Self checking shall be demonstrated.

3. During Training JPM:

Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References:

1. NUREG 1123,2.1.18, RO 3.6

2. Nl-ST-DO Tools and Equipment:

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

Initial Conditions:

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

2. Nl-ST-DO, Daily Checks, is in progress.

3. The provided printout shall be used to determine computer point and PI data.

4. Instructor to ask the operator for any questions.

Initiating cue:

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

I Performance Steps I Standard Grade

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

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

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

NRC 2013 JPM RO COOl May 2013

I Performance Steps I Standard Grade

3. Records section 5.0 readings Records Reactor Recirc Pump Inlet SatlUnsat Temperature readings on Attachment 4 Section 5.0

4. Compare Recirc Pump Inlet Temperature Compares readings and determines readings SatlUnsat readings and determines readings within within 15°P of each other 15°P Checks YES block in Section 5.0, indicating PasslFail the maximum difference in loop temperatures is<15°P

5. Record section 6.0 readings Records RPV water level readings on SatlUnsat Attachment 4 section 6.0 Cue: Another operator has completed the required Independent Verifications.

6. Record Total Recirc Plow Records total recirc flow in the correct box on SatlUnsat Attachment 4 section 6.0

7. Determines average Drywell temperature Observes average Drywell temperature is less SatlUnsatlNA than 125°p Note: Since Yarway level indicator deviation is less than 4 inches, Drywell temperature reading is not necessary for task completion.

8. Analyzes Yarway level indicator deviation Determines Yarway level indicator deviation PasslFail is less than the 6 inch limit Note: This may be evidenced by the lack of a report to the contrary.

9. Analyzes GEMAC level indicator deviation Determines GEMAC level indicator deviation PasslFaii is greater than the 6 inch limit

10. Determines GEMAC level indicators are Checks !NOP option in step 8.4 PasslFaii inoperable

11. Provides completed sections to SRO and Proper communications used (GAP-OPS-Ol) SatlUnsat informs of out of spec readings TERMINATING CUE: Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.

RECORDSTOPTIME_________

NRC 2013 JPM RO COO 1 May 2013

Initial Conditions:

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

2. N1-ST-DO, Daily Checks, is in progress.

3. The provided printout shall be used to determine computer point and PI data.

Initiating cue:

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

NRC 2013 JPM RO COOl May 2013

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

Title:

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

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

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

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

Evaluation Method: Perfonn Evaluation Location: Classroom Expected Completion Time: 15 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: _ _ _ __ Completion Time: _ _ _ __

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

Comments:

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

NRC 2013 JPM RO C002 May 2013

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

Classroom Set-up:

1. Prepare a picture ofRRP 11 suction temperature gauge indicating approximately 535°F.

2. Prepare NI-OP-43A Attachment 18 with the following data:

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

None Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

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

Notes to Instructor I Evaluator:

NRC 2013 JPM RO C002 May 2013

1. Critical steps are identified in grading areas PasslFaii.

2. During Evaluated JPM:

Self checking shall be demonstrated.

3. During Training JPM:

Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References:

1. NUREG 1123,2.1.7, RO 4.4

2. NI-0P-43A Attachment 18 Tools and Equipment:

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

Initial Conditions:

1. A plant startup is in progress.

2. Current time is 1100 on 5/1/13.

3. N 1-0P-43A Attachment 18 is provided with heat-up data for the last hour.

4. All RRP suction temperature readings have been taken from Recirc loop 11.

5. The provided picture shows the current Recirc loop 11 suction temperature indication.

6. Instructor to ask the operator for any questions.

Initiating cue:

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

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

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

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

NRC 2013 JPM RO C002 May 2013

I Performance Steps I Standard Grade

3. Records current RRP suction temperature Records current RRP suction temperature PasslFaii (535°F +/- 10°F)

4. Calculates and records AT115 min for times Calculates and records AT115 min: Sat/Unsat 1030-1100 1030: 470°F - 435°F 35°F 1045: 490°F - 470°F 20°F 1100: 535°F - 490°F 45°F (+/- 10°F)

5. Analyzes and records AT Limits for AT/I5 Analyzes and records AT Limits for AT115 SatlUnsat min min:

1030: UNSAT 1045: SAT 1100: UNSAT

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

7. Analyzes and records Heat-up Rate Limits Analyzes and records Heat-Up Rate Limits:

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

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

RECORDSTOPTIME_________

NRC 2013 JPM RO C002 May 2013

Initial Conditions:

1. A plant startup is in progress.

2. Current time is 1100 on 5/1/13.

3. NI-0P-43A Attachment 18 is provided with heat-up data for the last hour.

4. All RRP suction temperature readings have been taken from Recirc loop 11.

5. The provided picture shows the current Recirc loop 11 suction temperature indication.

Initiating cue:

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

NRC 2013 JPM RO C002 May 2013

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

Title:

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

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

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

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

Evaluation Method: Perform Evaluation Location: Simulator Expected Completion Time: 10 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: _ _ _ __ Completion JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

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

NRC 2013 JPM RO EP May 2013

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

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor! Evaluator:

1. Critical steps are identified as PasslFaii.

2. During Evaluated JPM:

Self-verification shall be demonstrated.

3. During Training JPM:

Self-verification shall be demonstrated.

References:

1. NUREG 1123,2.4.43, RO 3.2

2. EPIP-EPP-18 Tools and Equipment:

None Task Standard: Alert emergency announcement is made.

NRC 2013 JPM RO EP May 2013

Initial Conditions:

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

2. Ask the operator for any questions.

Initiating cue:

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

I Performance Steps I Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTUME _______

2. Place GAI-tronics in MERGE Places GAI-tronics in MERGE by toggling PasslFail MERGE/ISOLATE switch to MERGE

3. Sound the appropriate alarm Sounds the Evacuation Alarm by depressing PasslFaii EV AC pushbutton

4. Stop the alarm Stops the Evacuation Alarm by depressing SatlUnsat OFF pushbutton after approximately 10 seconds

5. Announce checked items Holds GAI-tronics broadcast pushbutton PasslFail while saying:

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

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

I repeat, this is a drill."

Notes:

If Examiner wishes not to broadcast, holding the broadcast pushbutton may be discussed/simulated.

The announcement may differ slightly between Candidates, however the important points must all be covered.

NRC 2013 JPM RO EP -3 May 2013

6. Repeat alarm Sounds the Evacuation Alarm by depressing SatlUnsat EV AC pushbutton

7. Stops alarm Stops the Evacuation Alarm by depressing SatlUnsat OFF pushbutton after approximately 10 seconds

8. Repeat announcement Holds GAI-tronies broadcast pushbutton SatlUnsat while saying:

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

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

I repeat, this is a drill."

Notes:

If Examiner wishes not to broadcast, holding the broadcast pushbutton may be discussed/simulated.

The announcement may differ slightly between Candidates, however the important points must all be covered.

TERMINATING CUE: Alert emergency announcement is made.

RECORDSTOPTIME_________

NRC 2013 JPM RO EP May 2013

Initial Conditions:

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

Initiating cue:

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

NRC 2013 JPM RO EP May 2013

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

Title:

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

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

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

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

Evaluation Method: Perform Evaluation Location: Classroom Expected Completion Time: 30 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: _ _ _ __ Completion Time:._ _ _ __

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

Comments:

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

NRC 2013 JPM RO-SRO EC May 2013

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

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified as PasslFaii.

2. During Evaluated JPM:

Self-verification shall be demonstrated.

3. During Training JPM:

Self-verification shall be demonstrated.

References:

1. NUREG 1123,2.2.41, RO 3.5

2. C-19859-C Sheet 7 Tools and Equipment:

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

NRC 2013 JPM RO-SRO EC May 2013

Initial Conditions:

1. None.

2. Ask the operator for any questions.

Initiating cue:

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

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME ________

2. Obtain a copy ofthe necessary electrical print Obtains the following documents, as needed: SatlUnsati

Drawing Index, if needed NA

Drawing C-19859-C Sheet 7 Note: When the Candidate identifies the correct print, provide them with another copy of the print so that they may mark it up.

3. Using C-19859-C Sheet 7, locates RPS 12 Locates RPS 12 manual scram pushbutton PasslFail manual scram pushbutton (1 S28) on C-19859-C Sheet 7 near drawing coordinate E-6 Note:

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

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

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

NRC 2013 JPM RO-SRO EC May 2013

I Performance Steps I Standard Grade

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

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

Note:

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

6. Using C-19859-C Sheet 7, identifies Locates relays/solenoids 305-139(B) on C PasslFail relays/solenoids 305-139(B) 19859-C Sheet 7 near drawing coordinates F 5/6 through M-5/6 Notes:

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

The candidate does not have to identify all eight solenoids/relays on this sheet, as long as a representative sample is identified and some indication is given that there are multiple solenoids/relays.

7. Describes how depressing the RPS 12 Describes the following: PasslFail manual scram pushbutton on E console

Depressing RPS 12 manual scram results in an RPS half scram pushbutton on E console causes relay 12K55 to de-energize.

Relay 12K55 de-energizing causes contacts 12K55 to open.

Contacts 12K55 opening causes solenoid/relay 305-139(B) to de-energize at each RCU.

Notes:

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

NRC 2013 JPM RO-SRO EC May 2013

Additional SRO Only Cue:

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

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

the Technical Specification impact if the RPS 12 manual scram pushbutton becomes inoperable.

8. SRO Only: Determines the surveillance Determines the surveillance requirement for Pass/Fail requirement for testing the RPS 12 manual testing the RPS 12 manual scram pushbutton scram pushbutton. is weekly.

9. SRO Only: Determines the Technical Determines Technical Specification table Pass/Fail Specification impact if the RPS 12 manual 3.6.2.a item (1) is not met.

scram pushbutton becomes inoperable.

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

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

RECORDSTOPTIME_________

NRC 2013 JPM RO-SRO EC May 2013

Initiating cue:

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

NRC 2013 JPM RO-SRO EC May 2013

Additional SRO Only Cue Determine the following:

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

the Technical Specification impact if the RPS 12 manual scram pushbutton becomes inoperable with the plant at 100% power.

NRC 2013 JPM RO-SRO EC May 2013

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

Title:

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

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

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

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

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

"--"'--- Simulator IClassroom Expected Completion Time: 20 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: _________ Completion Time: _ _ _ __

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

Comments:

Evaluator Signature: ________________________

NRC 2013 JPM SRO COO 1 May 2013

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

Simulator Simulator Set-up:

N/A Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

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

Notes to Instructor I Evaluator:

1. Critical steps are identified in grading areas PasslFail.

2. During Evaluated JPM:

Self checking shall be demonstrated.

3. During Training JPM:

Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References:

1. NUREG 1123,2.1.7, SRO 4.7

2. NI-ST-DO

3. Technical Specifications NRC 2013 JPM SRO COO 1 May 2013

Tools and Equipment:

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

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

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

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

Initial Conditions:

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

2. NI-ST-DO, Daily Checks, is in progress.

3. Operators have completed the RPV water level instrument readings.

4. Instructor to ask the operator for any questions.

Initiating cue:

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

Attachment 4 section 6.0

Step 8.4 When completed, report findings to the Examiner."

NRC 2013 JPM SRO COO 1 May 2013

I Performance Steps I Standard Grade

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

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

2. Obtain a copy of the reference procedure and NI-ST-DO obtained SatlUnsat review/utilize the correct section

3. Review Attachment 4 section 6.0 readings Reviews Attachment 4 section 6.0 readings SatlUnsat and Step 8.4

4. Identifies error in Step 8.4 Identifies that GEMAC Level Column PasslFail Variance is in the !NOP range Cue:

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

5. Determines GEMAC 12 level indicator is Determines GEMAC 12 level indicator is PasslFail inoperable inoperable

6. Determines Technical Specification impact Determines a 15 day LCO applies per PasslFail Technical Specification 3.l.8

7. Provides completed sections to Examiner Proper communications used (GAP-OPS-Ol) SatlUnsat and informs of out of spec readings TERMINATING CUE: Control room RPV water level instrument surveillance per Nl-ST-DO is reviewed. Out of spec results are identified and the appropriate Technical Specification is determined.

RECORDSTOPTIME_________

NRC 2013 JPM SRO COOl May 2013

Initial Conditions:

1. The plant is operating at approximately 670/0 power.

2. Nl-ST-DO, Daily Checks, is in progress.

3. Operators have completed the RPV water level instrument readings.

Initiating cue:

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

Attachment 4 section 6.0

Step 8.4 When completed, report findings to the Examiner."

NRC 2013 JPM SRO COOl May 2013

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

Title:

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

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

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

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

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

Simulator or other location Expected Completion Time: 40 minutes Time Critical Task: No Alternate Path Task: No Start Time: - - - - Stop Time: _ _ _ __ Completion Time: _ _ _ __

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

Comments:

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

NRC 2013 JPM SRO C002 May 2013

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

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

None Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor I Evaluator:

1. Critical steps are identified in grading areas PasslFaii.

2. During Evaluated JPM:

Self checking shall be demonstrated.

3. During Training JPM:

Self checking shall be demonstrated.

Peer checking shall be demonstrated.

4. Verify the references below are available to the candidate.

References:

1. CNG-NL-1.01-1004

2. 10CFR50.72

3. NUREG 1022

4. EAL Matrix

5. EAL Bases NRC 2013 JPM SRO C002 May 2013

Tools and Equipment:

None Task Standard: Determine 10 CFR 50.72 reportability requirements.

Initial Conditions:

1. The plant was operating at 100% power with no equipment out of service.

2. A loss of offsite power Lines 1 and 4 occurred one hour ago.

3. Emergency Diesel Generator (EDG) 102 failed to start and has been declared inoperable.

4. Maintenance reports that repairs to EDG 102 will take several days.

5. Power Control reports Line 1 will be returned to service in approximately 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and Line 4 will be returned to service in approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

6. Instructor to ask Candidate for any questions.

Initiating cue:

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

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

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

These are likely to include the following:

CNG-NL-l.OI-I004

10 CFR 50.72 and 50.73

NUREG 1022

EAL Matrix

EAL Bases

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

NRC 2013 JPM SRO C002 May 2013

I Performance Steps I Standard Grade

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

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Generator.

6. Locate and identify applicability of Identifies reportability per 50.72(b)(3)(v)(D) SatlUnsat 50.72(b)(3)(v)(D) Non-emergency eight hour for an event or condition that could have report. Event or condition that could have prevented fulfillment of a safety function prevented fulfillment of a safety function needed to mitigate the consequences of an needed to mitigate the consequences of an accident (loss of both offsite power lines, accident. failure ofEDG 102), within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Note: This step is deemed non-critical because of the redundancy with other reports and the subjective nature of this call.

TERMINATING CUE: Reportability requirements have been determined.

RECORDSTOPTIME _________

NRC 2013 JPM SRO C002 May 2013

Initial Conditions:

1. The plant was operating at 100% power with no equipment out of service.

2. A loss of offsite power Lines 1 and 4 occurred one hour ago.

3. Emergency Diesel Generator (EDG) 102 failed to start and has been declared inoperable.

4. Maintenance reports that repairs to EDG 102 will take several days.

5. Power Control reports Line 1 will be returned to service in approximately 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and Line 4 will be returned to service in approximately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Initiating cue:

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

NRC 2013 JPM SRO C002 May 2013

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

Title:

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

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

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

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

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

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

Comments:

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

NRC 2013 JPM SRO RC May 2013

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

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas Pass/Fail.

2. During Evaluated JPM:

Self checking shall be demonstrated.

3. During Training JPM:

Self checking shall be demonstrated.

Peer checking shall be demonstrated.

References:

1. ARP Hl-3-8

2. NI-OP-50B

3. ODCM 3.6.14.b and TBL D 3.6.14-2

4. NUREG 1123 KIA 2.3.11 (4.3)

Tools and Equipment:

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

NRC 2013 JPM SRO RC May 2013

Initial Conditions:

1. The plant is operating at 100% power.

2. Annunciator HI-3-8, STACK GAS MONITORING TROUBLE, has alarmed.

3. Computer Point C061, OGESMS RAD MON STATUS - TRBL, is in alarm.

4. OGESMS radiation monitor RN-I OA indicates downscale.

5. Ask the operator for any questions.

Initiating cue:

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

EXAMINER NOTE: Provide Attachment 2.

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

1. Obtain a copy of the reference ARP HI 8 obtained. SatlUnsat procedure and review/utilize the Operator Actions referenced.

correct section.

ODCM obtained.

DLCO 3.6.14 referenced.

Table D 3.6.14-2 referenced.

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

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

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

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

NRC 2013 JPM SRO RC May 2013

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

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

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

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

RECORDSTOPTIME_________

NRC 2013 JPM SRO RC May 2013

Initial Conditions:

1. The plant is operating at 100% power.

2. Annunciator Hl-3-8, STACK GAS MONITORING TROUBLE, has alarmed.

3. Computer Point C061, OGESMS RAD MON STATUS - TRBL, is in alarm.

4. OGESMS radiation monitor RN-l OA indicates downscale.

Initiating cue:

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

NRC 2013 JPM SRO RC May 2013

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

Title:

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

NIA - Exam Security General Supervisor Operations Training (Designee)

" Date General Supervisor Operations (Designee)

Date Configuration Control Date

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

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

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

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

Comments:

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

NRC 2013 JPM SRO EP May 2013

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

Read Before Every JPM Performance:

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor! Evaluator:

1. Critical steps are identified as PasslFaii.

2. During Evaluated lPM:

Self-verification shall be demonstrated.

3. During Training JPM:

Self-verification shall be demonstrated.

No other verification shall be demonstrated.

References:

1. NUREG 1123, 2.4.29, SRO 4.4

2. EPlP-EPP-OI

3. EPlP-EPP-18

4. EPMP-EPP-OIOI Tools and Equipment:

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

2. SMIED Checklist Package Task Standard:

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

NRC 2013 JPM SRO EP May 2013

Initial Conditions:

1. None

2. Instructor to ask the operator for any questions.

Initiating Cue:

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

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME _______

2. Obtain a copy of EPlP-EPP-O 1 attachments 1 EPlP-EPP-Ol attachments 1 and 2, and Shift SatlUnsat and 2, and Shift Manager emergency Manager emergency paperwork is obtained paperwork and review/utilize the correct section

3. Reviews plant conditions and determines if Determines an emergency classification is SatlUnsat emergency classification is warranted. required.

4. Classifies the emergency for 2013 NRC Determines the emergency classification level is PasslFaill Scenario # 1. Alert. NA Examiner Note: The listed EAL is the expected EAL based on scenario validation. If scenario Determines the Emergency Action Level (EAL) PasslFaill deviates from the expected course, examiner designator is 3.1.1. NA discretion will be required to determine the actual classification. EXAMINER NOTE: Time difference below must be 15 minutes or less:

JPM start time: - - - -

Time of Classification: - - - - -

NRC 2013 JPM SRO EP May 2013

I Performance Steps I Standard Grade

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

JPM start time: - - - -

Time of Classification: - - - - -

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

JPM start time: _ _ __

Time of Classification: - - - - -

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

JPM start time: _ _ __

Time of Classification: - - - - -

NRC 2013 JPM SRO EP May 2013

I Performance Steps I Standard Grade

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

JPM start time: - - - -

Time of Classification: - - - - -

TERMINATING CUE: Emergency classification requirement is determined.

RECORDSTOPTIME_________

NRC 2013 JPM SRO EP May 2013

Initiating Cue:

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

NRC 2013 JPM SRO EP May 2013

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

Title:

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

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

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

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

Evaluation Method: _~_ _ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant _ _---"~__ Simulator Expected Completion Time: 20 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: _ _ _ __ Completion Time:._ _ _ __

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

Comments:

Evaluator's Date:_ _ _ _ _ __

NRC 2013 JPM S-l - I - May 2013

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

1. Initialize Simulator to IC-161.

2. Verify RPV water level is above 100 inches.

3. Verify RWCU system isolated with isolation signal clear.

Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor I Evaluator:

1. Critical steps are identified in grading area as Pass/Fail.

2. During Evaluated JPM:

Self verification shall be demonstrated.

3. During Training JPM:

Self verification shall be demonstrated.

Peer verification shall be demonstrated.

References:

1. NUREG 1123,204000, A4.06, RO 3.0, SRO 2.9

2. NI-EOP-HC Tools and Equipment:

None NRC 2013 JPM S-1 May 2013

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

Initial Conditions:

1. RWCU isolated following a low-low RPV water level transient.

2. RPV water level is high.

3. RWCU system is needed to control RPV water level.

4. Another Operator will be controlling RPV pressure using the ERVs and/or ECs.

5. Instructor to ask operator for any questions.

Initiating Cue:

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

Performance Steps Standard Grade

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

2. Obtain a copy of the reference procedure NI-EOP-HC Attachment 12 is obtained SatlUnsat and review/utilize the correct section of the procedure

3. Verify the following:

All Reactor Water Cleanup isolation Observes K3-4-4 clear SatlUnsat signals clear

The cause of the isolation is known Determines cause is known and corrected per SatlUnsat AND corrected initial conditions

4. Verify closed the foHowing valves:

33.1-01B, CLEANUP PCV 11 (LP) Observes 33.l-01B in MAN and output signal SatlUnsat at 0

33-39B, CLEANUP PCV 12 (HP) Places controller PC-33-39 in MAN and dials SatlUnsat to 0

5. Using RMC-33-151, CLEANUP SYS Verifies controller RMC-33-1S1 CLEANUP SatlUnsat SELECTOR, close 33-40 SYS SELECTOR in MAN and dialed to 0 Note: Manipulation of FC-33-169 is inconsequential, but does not satisfy this step.

NRC 2013 JPM S-1 May 2013

Performance Steps Standard Grade

6. Using RMC-33-165, CLEANUP TO Verify controller RMC-33-165C dialed SatlUnsat COND & WASTE FLOW, close 33-165 to °

7. Verify open one of the following using the CLEANUP SELECTOR CONDENSER WASTE control switch:

WASTE (valve 33-10, CLEANUP TO Rotates CLEANUP SELECTOR CONDENS PasslFail WASTE DISPOSAL BV) ER WASTE control switch clockwise to COND position

COND (valve 33-11, CLEANUP TO Observes right-hand set of lights red light ON SatlUnsat CONDENSER BV) and green light OFF, for 33-11 Note: Initiating cue directs the candidate to reject to the condenser

8. Open 33-01R, CU RETURN Rotates33-01R control switch clockwise to PasslFaii ISOLATION VALVE 1 (INSIDE) open Observes red light ON, green light OFF SatlUnsat

9. Open 33-04R, CU SUPPLY ISOLATION Rotates33-04R control switch clockwise to SatlUnsat VALVE 12 (OUTSIDE), for open and uses pull-to-stop function after 3 approximately 3 seconds THEN PULL seconds TO-STOP Observes red light ON, green light ON SatfUnsat Note: Cleanup System Inlet Pressure will rapidly rise in the next step

10. Jog open 33-02R, CU SUPPLY ISOLA Rotates33-02R control switch clockwise to SatfUnsat TION VALVE 11 (INSIDE), using Y2 open and uses pull-to-stop in Y2 second second open signals followed by PULL intervals UNTIL Cleanup system inlet TO-STOP UNTIL Cleanup System Inlet pressure rises and stabilizes at reactor pressure Pressure has stabilized at Reactor Pressure on indicators Observes red light ON, green light ON SatlUnsat Observes cleanup system pressure and reactor SatlUnsat pressure approximately equal

11. Fully open 33-02R Rotates33-02R control switch clockwise to PasslFaii open Observes red light ON, green light OFF SatfUnsat NRC 2013 JPM S-1 May 2013

Performance Steps Standard Grade

12. Fully open the following valves:

33-04 Rotates33-04R control switch clockwise to PasslFail open Observes red light ON, green light OFF SatlUnsat

33-41,AOBLOCKINGVALVE Rotates 33-41 control switch clockwise to PasslFail open Observes red light ON, green light OFF SatlUnsat

13. Simultaneously perfonn the following:

Adjust the in-service PCV to maintain Using controller PC-33-39, dials output signal SatlUnsat Reactor Water Cleanup System to open valve and establish inlet pressure pressure <100 psig below 100 psig Note: Operator may place the PCV in AUTO after pressure is established

Adjust RMC-33-165C, CLEANUP TO Using controller RMC-33-165C, dials output PasslFail COND & WASTE FLOW to control signals to open valve and establish system Reactor Water Level AND maintain reject flow Non-Regenerative Heat Exchanger outlet temperature < 120°F on Maintains parameters to prevent a subsequent PasslFail computer point F359 RWCU system isolation Cue: Another operator will monitor computer point F359.

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

to adjust flow.

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

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

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

RECORD STOP TIME _ _ __

NRC 20 l3 JPM S-1 -5 May 2013

Initial Conditions:

1. R WCU isolated following a low-low RPV water level transient.

2. RPV water level is high.

3. R WCU system is needed to control RPV water level.

4. Another Operator will be controlling RPV pressure using the ERVs and/or ECs.

Initiating Cue:

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

NRC 2013 JPM S-l May 2013

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

Title:

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

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

NIA - Exam Security /

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

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

Evaluation Method: _-'X'-"--__ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant _ _----"X~__ Simulator Expected Completion Time: 15 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Completion Time:._ _ _ __

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

Comments:

Evaluator's NRC 2013 JPM S-2 May 2013

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

1. Initialize Simulator to IC-16I.

2. Verify an RBEVS auto-start signal is locked in.

3. Verify RBEVS 11 is running and RBEVS 12 is secured.

Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor 1 Evaluator:

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

2. During Evaluated JPM:

Self verification shall be demonstrated.

3. During Training JPM:

Self verification shall be demonstrated.

Peer verification shall be demonstrated.

References:

1. NUREG 1123,261000 A4.03 (3.0/3.0)

2. NI-OP-IO Tools and Equipment:

None NRC 2013 JPM 8-2 May 2013

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

Initial Conditions:

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

2. RBEVS auto-initiated on high Reactor Building exhaust radiation level.

3. RBEVS train 11 is in service.

4. RBEVS train 12 is secured.

5. It has been determined that RBEVS train 11 charcoal filter needs to be removed from service and cooled.

6. Another Operator will be controlling Reactor pressure with ERVs and/or ECs.

7. Instructor to ask operator for any questions.

Initiating Cue:

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

Performance Steps Standard Grade

1. Provide repeat back of initiating cue Proper communications used (GAP-OPS-Ol) SatlUnsat Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTT~E ________

2. Obtain a copy of the reference procedure NI-0P-1O obtained, precautions and SatlUnsat and review/utilize the correct section of the limitations reviewed, sections H.3.0 procedure referenced

3. (Step 3.1.1) Verify closed the following valves:

202-47, EM VENTILATION TIE BV Observes 202-47 green light on, red light off SatlUnsat

202-74, EM VENTILATION LOOP 11 Observes 202-74 green light on, red light off SatlUnsat COOLING BV (label contains noun name but no number)

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

202-75, EM VENTILATION LOOP 12 COOLING BV (label contains noun name but no number)

4. (Step 3.l.3.a) Open 202-38, EM Opens 202-38 by rotating control switch CW PasslFail VENTILATION LOOP 12 INLET BV to OPEN

5. (Step 3.1.3.b) Start 202-33, EVS FAN 12 Starts 202-33 by taking control switch out of PasslFail pull-to-Iock Note: 202-33 auto-starts when the control switch is taken out of pull-to-Iock due to Places 202-33 control switch in START SatlUnsat presence of an auto-start signal.

NRC 2013 JPM S-2 May 2013

Performance Steps Standard Grade

6. (Step 3.1.3.c) VerifY open 202-35, EM Observes 202-35 green light off, red light on SatlUnsat VENTILATION EXHAUST FAN 12 OUTLET BV (label contains noun name but no number)

7. (Step 3.1.3 .d) Confirm proper operation of Observes 202-51 green light on, red light on SatlUnsat 202-51, EM VENT EXHAUST FAN 12 INLET FCV, by observing indicating Observes proper RBEVS flow SatiUnsat lights AND flow indication

8. (Step 3.1.3.e) Stop 202-53, EVS FAN 11 Stops 202-53 by rotating control switch CCW PasslFail and pulls to lock Note: RBEVS fan 11 control switch must be placed in pull-to-Iock to stop fan due to presence of an auto-start signal.

9. (Step 3.1.3.f) VerifY closed 202-34, EM Observes 202-34 green light on, red light off SatiUnsat VENT EXHAUST FAN 11 OUTLET BV (label contains noun name but no number)

10. (Step 3.2.2.a) VerifY EVS Train 12 running Observes RBEVS fan 12 green light off, red SatlUnsat light on

11. (Step 3.2.2.b) VerifY 202-53, EVS FAN 11 Observes 202-53 control switch in pull-to SatlUnsat in PULL-TO-LOCK lock

12. (Step 3.2.2.c) NotifY SRO to enter LCO Proper communications used (GAP-OPS-Ol) SatlUnsat 3.4.4.e (7 day plant shutdown LCO when one train of EVS is inoperable)

Role Play: Acknowledge communication as SRO.

13. (Step 3.2.2.d) Open 202-74, EM Opens 202-74 by rotating control switch PasslFan VENTILATION LOOP 11 COOLING BV CCWtoCOOL (label contains noun name but no number), by placing 202-37, EM VENTILATION LOOP 11 INLET BV, control switch to COOL

14. (Step 3.2.2.e) VerifY closed 202-37, EM Observes 202-37 green light on, red light off SatiUnsat VENTILATION LOOP 11 INLET BV

15. (Step 3.2.2.f) Open 202-47, EM Opens 202-47 by rotating control switch CW PasslFaii VENTILATION TIE BV to OPEN Terminating Cue: RBEVS train 12 placed in service and RBEVS train 11 placed in the cooling lineup.

RECORD STOP TIME _ _ __

NRC 2013 JPM S-2 May 2013

Initial Conditions:

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

2. RBEVS auto-initiated on high Reactor Building exhaust radiation level.

3. RBEVS train 11 is in service.

4. RBEVS train 12 is secured.

5. It has been determined that RBEVS train 11 charcoal filter needs to be removed from service and cooled.

6. Another Operator will be controlling Reactor pressure with ERVs and/or ECs.

Initiating Cue:

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

NRC 2013 JPM 8-2 May 2013

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

Title:

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

General Supervisor Date

, . NIA - Exam Security General Supervisor I

Date Operations Training (Designee) Operations (Designee)

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

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

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

"--"---- Simulator Expected Completion Time: 15 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ _ __ Stop Time: _ _ _ __ Completion Time: _ _ _ __

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

Comments:

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

NRC 2013 JPM S-3 May 2013

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

1. Initialize Simulator to IC-162.

2. Verify the Reactor is scrammed with the MSIVs closed.

3. Verify Reactor pressure is approximately 1000 psig and slowly lowering with EC 12 in service.

4. Verify the following malfunctions are inserted:

EC04A, EC Return Valve Fails to Open (IV 39-05)

AD07(A-F), ERV (111-123) Fails Closed (Burned Out Solenoid)

RP06, Reactor Vessel Isolation

5. Verify trigger 1 is set as follows:

Event zdmsisol(I)==1&zdmsisol(2)==I&zdmsisol(3)=I&zdmsisol(4)=1

Command dmf rp06 Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading area as Pass/Fail.

2. During Evaluated JPM:

Self verification shall be demonstrated.

3. During Training JPM:

Self verification shall be demonstrated.

Peer verification shall be demonstrated.

References:

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

NRC 2013 JPM S-3 May 2013

2. N1-EOP-1

3. N1-EOP-HC Tools and Equipment:

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

Initial Conditions:

1. An RPV Blowdown is required.

2. Emergency Condenser 11 has failed to go into service and ERVs have failed to open.

3. MSIV s closed due to a spurious isolation signal.

4. Another Operator has been assigned Reactor water level control.

5. Instructor to ask operator for any questions.

Initiating Cue:

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

Performance Steps Standard Grade

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

2. Obtain a copy of the reference procedure NI-EOP-1 attachment 1 and N1-EOP-HC SatlUnsat and review/utilize the correct section of the attachment 3 obtained procedure

3. Bypass MSIV ISOLATION interlocks by installing the following jumpers at the EOP ISOLATION BYPASS JUMPER SUBPANEL (inside Panel N, between INIA and INIB):

Jumper 15, MSIV ISOLATION BYPASS Inserts EOP jumper 15. PasslFaii RELAY l1K19A TO RELAY 11K73

Jumper 16, MSIV ISOLATION BYPASS Inserts EOP jumper 16. PasslFaii RELAY l1K20A TO RELAY l1K74

Jumper 22, MSIV ISOLATION BYPASS Inserts EOP jumper 22. PasslFaii RELAY 12K19A TO RELAY 12K73

Jumper 23, MSIV ISOLATION BYPASS Inserts EOP jumper 23. PasslFaii RELAY 12K20A TO RELAY l2K74 NRC 2013 JPM S-3 May 2013

Performance Steps Standard Grade

4. Open MSIV 01-03 Opens MSIV 01-03 by rotating control switch PasslFail CWtoOPEN

5. Slowly throttle open MSIV 01-01 utilizing Throttles open MSIV 01-01 by rotating PasslFaii PULL~ TO-STOP control switch CW to OPEN and then pulling control switch out

6. Fully open MSIV 01-01 Opens MSIV 01-01 by rotating control switch PasslFail CW to OPEN

7. Open MSIV 01-04 Opens MSIV 01-04 by rotating control switch PasslFaii CWtoOPEN

8. Slowly throttle open MSIV 01-02 utilizing Throttles open MSlV 01-02 by rotating PasslFaii PULL-TO-STOP control switch CW to OPEN and then pulling control switch out

9. Fully open MSlV 01-02 Opens MSIV 01-02 by rotating control switch PasslFaii CWtoOPEN

10. Opens Turbine Bypass Valve( s) using Rotates BY-PASS OPENING JACK control PasslFaii Bypass Opening Jack (BOJM) switch clockwise to OPEN Terminating Cue: MSIV s re-opened and TBV s open/opening.

RECORD STOP TIME _ _ __

NRC 2013 JPM S-3 May 2013

Initial Conditions:

1. An RPV Blowdown is required.

2. Emergency Condenser 11 has failed to go into service and ERVs have failed to open.

3. MSIVs closed due to a spurious isolation signaL

4. Another Operator has been assigned Reactor water level control.

Initiating Cue:

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

NRC 2013 JPM 8-3 May 2013

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

Title:

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

I ,

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

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

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

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

Comments:

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

NRC 2013 JPM S-4 May 2013

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

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

1. Initialize Simulator to IC-162.

2. VerifY Torus water level raised to ~11.3' per NI-EOP-l Attachment 18.

Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before EveI)' JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor I Evaluator:

1. Critical steps are identified in grading areas PasslFaii.

2. During Evaluated JPM:

Self verification shall be demonstrated.

3. During Training JPM:

Self verification shall be demonstrated.

No other verification shall be demonstrated.

References:

1. NI-EOP-l, Attachment 15

2. NUREG 1123295029 EAl.03 (2.9/3.0)

Tools and Equipment:

None NRC 2013 JPM S-4 May 2013

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

Initial Conditions:

1. Torus water level is 11.3 feet and rising slowly.

2. N1-EOP-4 has been entered.

3. Containment Spray pumps are in pull-to-Iock.

4. Another Operator will control Reactor pressure using ECs and/or ERVs.

5. Another Operator will control Reactor water level using CondensatelFeedwater and CRD.

Initiating Cues:

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

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORD START TIME

2. Obtain a copy of the reference procedure NI-EOP-1 Attachment 15 obtained SatlUnsat and review/utilize the correct section ofthe procedure

3. NotifY Radwaste of intent to pump down Proper communications used SatlUnsat Torus to Waste Collector Tank (GAP-OPS-O 1)

Role Play: Acknowledge report

4. Close 80-45, Cont Spray Bypass BV 122 Closes 80-45 by rotating control switch CCW PasslFaii to CLOSE

5. Open 80-118, Cont Spray Test to Torus Opens80-118 by rotating control switch CW PasslFail FCV to OPEN Note: 80-118 is a throttlable valve, and must be held in the open position until fully open

6. VerifY closed 80-16, Cont Spray Discharge Closes 80-16 by rotating control switch CCW PasslFail IV III to CLOSE

7. VerifY open 80-40, Cont Spray Bypass BV Observes 80-40 green light off, red light on SatlUnsat 111

8. Start Containment Spray Raw Water Pump Starts Containment Spray Raw Water Pump PassiFail 111 111 by rotating control switch CW to START NRC 2013 JPM 8-4 May 2013

Perfonnance Steps Standard Grade

9. Start Containment Spray Pump 111 Starts Containment Spray Pump 111 by PasslFaii rotating control switch CW to START

10. Open 80-115, Cont Spray to Radwaste IV Opens80-115 by rotating control switch CW PasslFaii 12 to OPEN

11. Open 80-114, Cont Spray to Radwaste IV Opens80-114 by rotating control switch CW PasslFaii 11 to OPEN

12. Throttle 80-118, Cont Spray Test to Torus Throttles closed 80-118 by rotating control SatlUnsat FCV as required to control flow to Waste switch CCW as required Collector Tank Role Play: If requested, infonn that Radwaste has indication of sufficient flow

13. Monitor 58-05A and 58-06A TORUS H 2O Observes TORUS H20 LEVEL indicators 58 SatlUnsat LEVEL indicators for level response 05A and 58-06A monitored for level response

14. Inform SRO that flow to the Waste Proper communications used SatlUnsat Collector Tank has been established using (GAP-OPS-Ol)

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

RECORD STOP TIME _ _ __

NRC 2013 JPM S-4 May 2013

Initial Conditions:

1. Torus water level is 11.3 feet and rising slowly.

2. N1-EOP-4 has been entered.

3. Containment Spray pumps are in pull-to-Iock.

4. Another Operator will control Reactor pressure using ECs and/or ERVs.

5. Another Operator will control Reactor water level using CondensatelFeedwater and CRD.

Initiating Cues:

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

NRC 2013 JPM S-4 - I - May 2013

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

Title:

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

r ~

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

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

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

Simulator Expected Completion Time: 15 Minutes Time Critical Task: No Alternate Path Task: Yes Start Time: _ _ __ Stop Time: _ _ _ __ Completion Time: _ _ _ __

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

Comments:

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

NRC 2013 JPM S-5 May 2013

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

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

1) Initialize Simulator to IC-163.

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

3) Insert malfunction ED26 to cause Powerboard 11 to fail to fast transfer.

4) Insert malfunctions MS13A (50%) and MS13C (100%) to fail MSIVs 01-01 and 01-03 to close.

5) Insert trigger 2 to allow MSIV 01-01 to close using the control switch:

Event - zdmsiivc( 1)== 1

Command - dmfms13a

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

Event - zdmsoivc( 1)== I

Command - dmf ms 13c Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas Pass/Fail.

2. During Evaluated JPM:

Self verification shall be demonstrated.

3. During Training JPM:

Self verification shall be demonstrated.

No other verification shall be demonstrated.

NRC 2013 JPM S-5 May 2013

References:

1. Nl-SOP-21.2

2. Nl-SOP-l

3. Nl-S0P-30.1

4. NUREG 1123295016 AA1.01 (3.8/3.9)

Tools and Equipment:

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

Initial Conditions:

1. The plant is operating at approximately 100% power.

2. The Shift Manager has determined that a Control Room Evacuation is required due to a fire in the Auxiliary Control Room.

3. The fire is still small and no smoke has yet entered the Control Room.

4. Time permits completing all required actions ofNI-SOP-21.2, Control Room Evacuation, before leaving the Control Room.

S. Ask the operator for any questions.

Initiating Cues:

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

Performance Steps Standard Grade

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

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

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

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

NRC 2013 JPM S-5 May 2013

Performance Steps Standard Grade

3. Verify ALL Control Rods inserted Observes control rods failed to insert SatlUnsat May depress RPS pushbuttons SatlUnsat Depresses MANUAL ARI pushbutton Pass/Fail Observes control rods insert SatlUnsat

4. Place BOTH VESSEL ISOLATION Rotates both VESSEL ISOLATION switches Pass/FaiJ switches to ISOLATE CCW to ISOLATION

5. Verify ALL MSIVs close Observes green light on, red light off, for SatiUnsat MSNs 01-02 and 01-04 Observes MSIV 01-01 green light on, red SatlUnsat light on Observes MSN 01-03 green light off, red SatlUnsat light on Closes at least one MSN in steam line by: PasslFaii

Rotates MSN 01-01 control switch counterclockwise to CLOSE AND/OR

Rotates MSN 01-03 control switch counterclockwise to CLOSE Cue:

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

NRC 2013 JPM S-5 May 2013

Performance Steps Standard Grade

6. IF time permits, verify the following:

House service loads transfer Observes PB 12 energized (voltmeters show SatlUnsat

~4160V, breakers re-align)

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

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

Rotates Rill control switch clockwise to SatlUnsat CLOSE

Rotates RI14 control switch clockwise to SatlUnsat CLOSE

7. IF time permits, verify the foHowing:

Turbine/Generator trip Observes Turbine trip and Generator lockout SatlUnsat (TSVs indicate closed, 86G1I2 lockouts roll)

HPCI Initiation Observes FW pumps II and 12 start / inject SatlUnsat (green lights off, red lights on, amps, flow)

FW Pump 13 clutch disengaged Observes FW pump 13 clutch disengaged SatlUnsat (green light off, red light off, speed lowers)

7. IF time permits, sound the station alarm Depresses STA pushbutton on GAltronics SatlUnsat AND announce Control Room evacuation Depresses OFF pushbutton on GAItronics SatlUnsat Announces Control Room evacuation Sat/Unsat NRC 2013 JPM S-5 - 1 May 2013

Performance Steps Standard Grade

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

Cue: You have obtained radios and keys.

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

Cue: Task complete.

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

RECORD STOP TIME _ _ __

NRC 2013 JPM S-5 May 2013

Initial Conditions:

1. The plant is operating at approximately 1000/0 power.

2. The Shift Manager has determined that a Control Room Evacuation is required due to a fire in the Auxiliary Control Room.

3. The fire is still small and no smoke has yet entered the Control Room.

4. Time permits completing all required actions ofN1-S0P-21.2, Control Room Evacuation, before leaving the Control Room.

Initiating Cues:

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

NRC 2013 JPM S-5 May 2013

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

Title:

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

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

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

Evaluation Method: _~_ _ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant __---"-x-"--__ Simulator Expected Completion Time: 20 minutes Time Critical Task: No Alternate Path Task: Yes Start Time: _ _ __ Stop Time: _ _ _ __ Completion Time: _ _ _ __

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

Comments:

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

NRC 2013 JPM S-6 - 1* May 2013

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

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

1. Initialize Simulator to IC-I63.

2. Verify EC 11 is removed from service per NI-OP-13 section H.8.0.

3. Verify EC 11 steam pressure has been vented to near 0 psig.

4. Verify malfunction EC06A is set at 25% with a IS second delay time on trigger 1.

5. Verify trigger I is set to initiate when valve 39-09R red light goes on (hzlecmovr(1)==I).

Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas PasslFail.

2. During Evaluated JPM:

Self verification shall be demonstrated.

3. During Training JPM:

Self verification shall be demonstrated.

Peer verification shall be demonstrated.

References:

1. NUREG 1123, KIA 207000 A4.05 (3.5/3.7)

2. NI-OP-13 Tools and Equipment:

I. None NRC 2013 JPM S-6 May 2013

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

Initial Conditions:

1. Emergency Condenser (EC) 11 is out of service per NI-OP-13 section H.8.1 following corrective maintenance.

2. Work is complete and EC 11 is ready to be returned to service.

3. Non-Destructive Evaluation (NDE) has determined EC stearn leg level to be 6 ft 11 inches.

4. Instructor to ask operator for any questions.

Initiating Cues:

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

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction ifnecessary.

RECORD START TIME _______

2. Obtain a copy of the reference procedure NI-OP-13 is obtained, precautions & SatlUnsat and review/utilize the correct section ofthe limitations reviewed, section H.8.3 utilized procedure

3. VerifY proper keepfullievel as follows:

Contact Engineering Programs - NDE to Determines level is 6' 11" per initial SatlUnsat perform UT ofEC stearn leg for level conditions determination

IF EC stearn leg level is greater than 6' Proceeds to step 8.3.2 SatlUnsat 10" THEN proceed to step 8.3.2

4. VerifY open the following valves:

05-11, EMERG COND VENT Opens 05-11 by rotating control switch CW to PasslFail ISOLATION VALVE 112 OPEN

05-01R, EMERG COND VENT Opens 05-0 lR by rotating control switch CW PasslFail ISOLATION VALVE 111 to OPEN NRC 2013 JPM S-6 May 2013

Perfonnance Steps Standard Grade

5. WHEN system pressure has returned to nonnal, open the following valves:

39-11R, EMERG CONDSR STM Opens39-11R by rotating control switch CW PasslFaii SUPPLY DRAIN IV 111 to OPEN

39-12R, EMERG CONDSR STM Opens39-12R by rotating control switch CW PasslFaii SUPPLY DRAIN IV 112 to OPEN

6. Open 39-07R, EC STM ISOLAnON Opens39-07R by rotating control switch CW PasslFaii VALVE 112 to OPEN Note: The candidate may throttle open 39-07R using the pull-to-stop feature, rather than open it in one continuous motion. However, it must be fully opened by the end of the manipulation.

7. Throttle open 39-09R, EC STM Opens39-09R by rotating control switch CW PasslFaii ISOLAnON VALVE 111 and monitor to OPEN system parameters during heatup AND repressurization Stops39-09R by pulling control switch out to SatlUnsat STOP Monitors system temperature and pressures SatlUnsat Fully opens39-09R by rotating control switch SatlUnsati CWtoOPEN NA Note: The alternate path begins when 39-09R red light comes on. This causes an EC tube leak to be initiated.

8. Responds to alann KI-I-2 Acknowledges and reports alann SatlUnsat

9. Confinn alann on computer printout Observes computer points E478 and E480 in SatlUnsat alann

10. Confinn radiation levels on J Panel and Observes E CONDSR VENT RAD MON 111 SatlUnsat contact RP to check dose rates above (RE-RN04A-3) and E CONDSR VENT RAD elevation 340 MON 112 (RE-RN04A-4) reading on J Panel and detennines readings indicate alann condition Role Play: Acknowledge direction as RP. Directs RP to check dose rates above SatlUnsat elevation 340 NRC 2013 JPM S-6 May 2013

Performance Steps Standard Grade

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

2:100F:

Direct Shift Chemistry Technician to Directs Chemistry Tech to assess for possible SatlUnsati assess the possible unmonitored unmonitored release per EPIP-EPP-08 NA radiological release using Attachment 4A of EPIP-EPP-08 SatlUnsatl

Direct Shift Radiation Protection Directs RP Tech to perform downwind survey NA Technician to perform a downwind site at site boundary boundary radiological survey Role Play: Acknowledge direction as RPIChemistry.

12. IF High Rad Alarm is confirmed, (BOTH Note: This step is NI A if shell temperature is RE-RN04A-3 AND RE-RN04A-4 in alarm > 100°F.

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

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

NRC 2013 JPM S-6 May 2013

Performance Steps Standard Grade

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

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

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

RECORD STOP TIME _ _ __

NRC 2013 JPM 8-6 May 2013

Initial Conditions:

1. Emergency Condenser (EC) 11 is out of service per NI-0P-13 section H.8.1 following corrective maintenance.

2. Work is complete and EC 11 is ready to be returned to service.

3. Non-Destructive Evaluation (NDE) has determined EC steam leg level to be 6 ft 11 inches.

Initiating Cues:

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

NRC 2013 JPM S-6 May 2013

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

Title:

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

Task Number: NIA Approvals:

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

NIA - Exam Security /

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

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

Evaluation Method: _~_ _ Perfonn - - - - - - Simulate Evaluation Location: _ _ _ _ Plant _ _---'-"--__ Simulator Expected Completion Time: 20 Minutes Time Critical Task: No Alternate Path Task: Yes Start Time: - - - - Stop Completion Time: _ _ _ __

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

Comments:

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

NRC 2013 JPM S-7 May 2013

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

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

1. Initialize Simulator to IC-164.

2. Verify PB 103 is supplied by EDG 103 per NI-OP-45 section E.3 .0.

3. Verify CRD Pump 11 in service.

4. Verify the Annunciator Ll-4-S is overridden to "Fail Off', to simulate alternate SFP pump in service.

5. Verify malfunction RD35B is inserted as "TRUE", to simulate prevent start of 12 CRD pump.

6. Verify override SDS267L02348 is inserted as "OFF", to simulate prevent start of 12 CRD pump.

7. Verify malfunction DGOSB is inserted as "TRUE" for failure of EDG 103 to stop.

Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas PasslFail.

2. During Evaluated JPM:

Self verification shall be demonstrated.

3. During Training JPM:

Self verification shall be demonstrated.

No other verification shall be demonstrated.

References:

1. NUREG 1123,264000, A4.04, RO 3.7, SRO 3.7

2. NI-OP-4S NRC 2013 JPM S-7 May 2013

Tools and Equipment:

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

Initial Conditions:

1. EDG 103 is supplying PB 103 due to maintenance on breaker RlO13.

2. EDG 103 has been at minimum load for the past hour and at 700 KW for the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3. 115 KV power is stable.

4. N1-0P-45 section G.2 is complete through step 2.6.

5. Instructor to ask operator for any questions.

Initiating Cues:

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

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME ________

2. Obtain a copy of the reference procedure N1-0P-45 obtained SatlUnsat and review/utilize the correct section of the Precautions & limitations reviewed procedure Section G.2 referenced

3. Verify GREEN flagged R1013, PB 103 Rotates R1013 control switch CW from PTL PasslFaii Normal Power Supply Breaker to neutral

4. Place and HOLD in TRIP position R1032, Rotates R1032 control switch CCW and holds PasslFaii Diesel Generator 103 Output Breaker in trip position

5. When 3 to 5 seconds has elapsed, close Rotates RlO13 control switch CW, observes PasslFaii RlO13 red light on, green light off

6. Confirm normal voltage on PB 103 and PB Observes ~4160 VAC on PB 103 voltmeter, SatlUnsat 17B and observes ~600 V AC on PB 17B voltmeter

7. Return R1 032 to Neutral Position Releases RI032 to the neutral position PasslFaii NRC 2013 JPM S-7 May 2013

Performance Steps Standard Grade

8. Reset Lockout 86-17 device Rotates 86-17 control switch CW to reset PasslFaill position NA Note: Lockout device may not need to be reset if R 1013 is closed closer to 3 seconds than 5 seconds (Step 5 above)

9. Install Close fuse for CRD pump 12 Proper communications used SatlUnsat (GAP-OPS-Ol)

Cue: Field operators will install fuse.

Note: Delete malfunction RD35B &

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

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

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

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

Cue: EDG 103 Raw Water Cooling Pump has started.

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

Cue: Another operator will restore PB 17B loads.

13. IF EDG has run idle for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR Determines step is NIA based on initial SatlUnsat operated less than 500 KW for 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , conditions THEN shutdown EDG per Section G, Recovery after Light Load Operation Note: This step is NI A based on initial conditions.

14. VerifY Speed Droop set to zero Proper communications used SatlUnsat (GAP-OPS-Ol)

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

Performance Steps Standard Grade

15. Adjust Governor to achieve greater than or equal to 60.1 Hz synchronous speed AND the Governor high speed light lit as follows.

a. Adjust speed until governor yellow Raises EDG 103 speed as necessary by SatlUnsat high speed light is lit rotating governor control switch CCW, observes yellow high speed light lit

b. Adjust speed to achieve greater than Raises EDG 103 speed as necessary by SatlUnsat or equal to 60.1 Hz with a maximum rotating governor control switch CCW, and of60.2 Hz. observes EDG 103 frequency of 60.1-60.2 Hz Note: This step may be N/A based on EDG speed.

16. Independently verify speed greater than or Proper communications used SatlUnsat equal to 60.1 HZ (max 60.2 Hz) (GAP-OPS-Ol)

Cue: Speed is as you adjusted it.

17. Adjust voltage to 4200 V using VOLT Raises EDG 103 voltage as necessary by SatlUnsat ADJ RHEO GEN 103 rotating voltage regulator control switch CCW, and observes voltage ~4200V

18. Place DIESEL GEN 103 control switch in Rotates EDG 103 control switch CCW to PasslFaii STOP STOP position, observes EDG 103 output voltage lower

19. When approximately 3 minute cooldown Recognizes that EDG did not stop as it should SatlUnsat has elapsed, verify EDG 103 stopped have Cue: Time compression is in effect, 4 minutes have elapsed.

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

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

NRC 2013 JPM S-7 May 2013

Perfonnance Steps Standard Grade

22. IF loss of 125 VDC power is lost due to Detennines 125 VDC power is available SatlUnsat loss of Battery Board 11, THEN enter N 1 based on various control room indications SOP-47A.l to restore 125 VDC power Note: This step is N/A, 125 VDC is available.

23. Place DIESEL GEN control switch to EM Rotates EDG 103 control switch CCW to EM Pass/Fail STOP STOP position, observes EDG 103 frequency lower Note: It is expected that the candidate will stop the EDG from the Control Room and not attempt to have a field operator to shutdown the EDG locally.

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

RECORD STOP TIME _ _ __

NRC 2013 JPM S-7 May 2013

Initial Conditions:

1. EDG 103 is supplying PB 103 due to maintenance on breaker RIO 13.

2. EDG 103 has been at minimum load for the past hour and at 700 KW for the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3. 115 KV power is stable.

4. NI-0P-45 section G.2 is complete through step 2.6.

Initiating Cues:

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

NRC 2013 JPM S-7 May 2013

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

Title:

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

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

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

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

Evaluation Method: _--"X-",-__ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant _ _~-"--__ Simulator Expected Completion Time: 10 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: _ _ _ __ Completion Time: _ _ _ __

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

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

NRC 2013 JPM S-8 May 2013

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

1. Initialize Simulator to IC-165.

2. Verify a Reactor scram is inserted and NOT yet reset.

3. Verify all automatic scram signals are clear, with the exception ofSDV high level.

4. Verify all NI-SOP-l steps are completed up to bypassing SDV high level trip.

5. Markup N l-SOP-I to the conditional step to bypass SDV high level trip.

6. Set trigger 1 event as "zcrprest== 1".

7. Set trigger 1 command as "set rdlsdv = 390".

Directions to the InstructorlEvaluator:

None Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor 1Evaluator:

1. Critical steps are identified in grading area as PasslFaii.

2. During Evaluated JPM:

Self verification shall be demonstrated.

3. During Training JPM:

Self verification shall be demonstrated.

Peer verification shall be demonstrated.

References:

1. NUREG 1123,295006 AAl.07 (4.1/4.1)

2. NI-SOP-l Tools and Equipment: None NRC 2013 JPM S-8 May 2013

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

Initial Conditions:

1. A manual Reactor scram was initiated 5 minutes ago due to high Turbine vibrations.

2. NI-S0P-I, Reactor Scram, is being executed.

3. Instructor to ask operator for any questions.

Initiating Cue:

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

Performance Steps Standard Grade

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

2. Obtain a copy ofthe reference procedure NI-S0P-l obtained SatlUnsat and review/utilize the correct section ofthe procedure

3. If ALL rod motion has stopped, then place Rotates SCRAM DISCHARGE VOL HIGH PassfFaii both SCRAM DISCHARGE VOLUME LEVEL BYPASS CH 11-1/12-1 switch CW HIGH LEVEL BYPASS switches in to BYPASS BYPASS Rotates SCRAM DISCHARGE VOL HIGH PassfFaii LEVEL BYPASS CH 11-2112-2 switch CW to BYPASS

4. If auto-initiated scram signals have cleared Observes all auto-initiated scram signals have SatlUnsat on CH 11 or CH 12, then: cleared or been bypassed (SDV high level)

5. Verify at least 1 CRD pump in service Observes CRD pump green light off, red light SatlUnsat on, amps

6. Reset Reactor Scram Depresses REACTOR TRIP RESET PassfFaii pushbutton

7. Verify ALL control rods inserted to Observes all control rods are inserted to SatlUnsat position 04 OR beyond by observing one position 00 OR more of the following:

Full Core Display

Demand new OD-7 Option 2 (Control Rod Notch Positions)

KI04A&B Red LED lights LIT (1 S20 AuxCR)

All RODS IN Light Illuminated (Remote Shutdown Panel)

NRC 2013 JPM 8-8 May 2013

Performance Steps Standard Grade

8. ConfIrm the following valves open:

44.2-15 AND 44.2-16, CONTROL Observes 44.2-15 green light off, red light on SatlUnsat ROD DRIVE DUMP VOL VENT VALVE Observes 44.2-16 green light off, red light on SatlUnsat

44.2-17 AND 44.2-18, CONTROL Observes 44.2-17 green light off, red light on SatlUnsat ROD DUMP VOL DRAIN IV Observes 44.2-18 green light off, red light on SatlUnsat

9. Confirm F3-2-4, CRD DRAIN - VENT Observes F3-2-4 NOT lit SatiUnsat VALVE CLOSED, clear.

10. If:

F3-1-4, CONT ROD DRIVE SCRAM Observes F3-1-4 NOT lit SatlUnsat DUMP VOLUME WTR LVL HIGH, clears AND

F 1-1-8, RPS CH 11 SCRAM DUMP Observes F 1-1-8 NOT lit SatlUnsat VOL WTR LVL HIGH, clears AND

F4-1-1, RPS CH 12 SCRAM DUMP Observes F4-1-1 NOT lit SatlUnsat VOL WTR LVL HIGH, clears then:

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

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

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

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

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

RECORD STOP TIME _ _ __

NRC 2013 JPM 8-8 May 2013

Initial Conditions:

1. A manual Reactor scram was initiated 5 minutes ago due to high Turbine vibrations.

2. NI-SOP-I, Reactor Scram, is being executed.

Initiating Cue:

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

NRC 2013 JPM 8-8 May 2013

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

Title:

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

NIA - Exam Security /

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

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

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

Evaluation Method: _ _ _ _ Perform _ _~-"-__ Simulate Evaluation Location: ------__ Plant _ _ _ _ _ _ Simulator Expected Completion Time: 15 minutes Time Critical Task: No Alternate Path Task: Yes Start Time: - - - - Stop Time: _ _ _ __ Completion Time: _ _ _ __

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

Comments:

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

NRC 2013 JPM P-l May20l3

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

Turbine Building elevation 261 '

Simulator Set-up (if required):

None Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas Pass/Fail. All steps are sequenced critical unless denoted by a "e".

2. During Evaluated JPM:

Self verification shall be demonstrated.

3. During Training JPM:

Self verification shall be demonstrated.

References:

1. NUREG 1123,207000, A2.08, RO 3.8, SRO 3.8

2. NI-0P-13 Tools and Equipment:

None NRC 2013 JPM P-1 May 2013

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

Initial Conditions:

1. The Reactor has failed to scram and NI-EOP-3 has been entered.

2. The Emergency Condenser Condensate Return Valves have failed to open.

3. NI-0P-13 section H.2 is complete through step 2.3.

4. Instructor to ask operator for any questions.

Initiating Cues:

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

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME _______

2. Obtain a copy of the reference procedure NI-0P-13 obtained, precautions & limitations SatlUnsat and review/utilize the correct section of the reviewed & section H.2 referenced procedure

3. Close 113-529, BV-IA Manifold Supply to 113-529 handwheel rotated fully CW PasslFaii

-A-22110-C SH. 14.

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

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

Note: A wrench is hanging below the air pipe.

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

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

NRC 2013 JPM P-l May 2013

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

6. Close 113-532, BV-IA MANIFOLD 113-532 handwheel rotated fully CW Pass/Fail SUPPLY TO - A-221 1O-C SH.14 Cue: The indicated handwheel is rotated fully in the direction indicated.

7. Using wrench, remove cap from 113-533, Cap removed from 113-533 by rotating CCW Pass/Fail Vent-IA Manifold Cue: The cap is removed.

Note: A wrench is hanging below the air pipe.

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

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

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

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

RECORD STOP TIME _ _ __

NRC 2013 JPM P-I May 2013

Initial Conditions:

1. The Reactor has failed to scram and NI-EOP-3 has been entered.

2. The Emergency Condenser Condensate Return Valves have failed to open.

3. NI-OP-I3 section H.2 is complete through step 2.3.

Initiating Cues:

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

NRC 2013 JPM P-l May 2013

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

Title:

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

General Supervisor

, Date NIA - Exam Security General Supervisor I

Date Operations Training (Designee) Operations (Designee)

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

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

Evaluation Method: _ _ _ _ Perform _ _---"-=---_ _ Simulate Evaluation Location: ~~__ Plant - - - - - - Simulator Expected Completion Time: 15 minutes Time Critical Task: No Alternate Path Task: Yes Start Time: _ _ __ Stop Time: _ _ _ __ Completion JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of un sat or individual competency area unsat requires a comment.

Comments:

Evaluators Date:_ _ _ _ _ __

NRC 2013 JPM P-2 May 2013

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

Turbine Building elevation 261 '

Simulator Set-up (if required):

None Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas PasslFail.

2. During Evaluated JPM:

Self verification shall be demonstrated.

3. During Training JPM:

Self verification shall be demonstrated.

References:

1. NUREG 1123,295018, AA2.04 (2.9/2.9)

2. ARP HI-4-4 Tools and Equipment:

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

NRC 2013 JPM P-2 May 2013

Initial Conditions:

1. The Control Room has received annunciator Hl-4-4, CLOSED LOOP COOL MAKEUP TANK LEVEL HIGH-LOW.

2. Computer point Bl15, CLC MU TK LVL - HIGH, is in alarm.

3. Control Room indications show CLC Makeup tank level is 7' and rising.

4. Annunciator Hl-4-5, LQ PROCESS RAD MON, is NOT in alarm.

5. Instructor to ask operator for any questions.

Initiating Cues:

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

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME ________

2. Obtain a copy of the reference procedure ARP Hl-4-4 obtained SatlUnsat and review/utilize the correct section of the procedure Note: All valves listed in this JPM are located on Turbine Building elevation 351'. The candidate may also do a visual inspection of a level control valve on Turbine Building elevation 261'.

3. Check status of annunciator H 1-4-5 AND Determines from initial conditions that Hl SatlUnsat if in alarm, perform applicable actions of 5 is NOT in alarm Ann. Hl-4-5 AND continue with actions below

4. Close 71-229, BV-CLC MAKE-UP Closes71-229 by rotating handwheel fully PasslFaii TANK INLET FROM MAKE-UP LCV CW Cue: The indicated handwheel is rotated fully in the indicated direction.

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

NRC 2013 JPM P-2 May 2013

Performance Steps Standard Grade

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

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

7. IF level is steady, THEN reopen 71-229 Observes CLC Makeup tank level SatlUnsat and monitor operation Does NOT reopen 71-229 SatlUnsat Cue: CLC Makeup tank level indicates 7' and slowly rising.

8. IF level continues to rise, THEN throttle Opens71-224 by rotating handwheel CCW Pass/Fail 71-224, CLC MU TANK DRAIN as necessary and notifY SM Cue: The indicated handwheel is rotated in the direction indicated.

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

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

RECORD STOP TIME _ _ __

NRC 2013 JPM P-2 May 2013

Initial Conditions:

1. The Control Room has received annunciator HI-4-4, CLOSED LOOP COOL MAKEUP TANK LEVEL HIGH-LOW.

2. Computer point B115, CLC MU TK LVL - HIGH, is in alarm.

3. Control Room indications show CLC Makeup tank level is 7' and rising.

4. Annunciator HI-4-5, LQ PROCESS RAD MON, is NOT in alann.

Initiating Cues:

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

NRC 2013 JPM P-2 May 2013

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

Title:

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

General Supervisor I

Date ShJc2 NIA - Exam Security General Supervisor I

Date Operations Training (Designee) Operations (Designee)

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

TrainerlEvaluator:

Evaluation Method: _______ Perform ___--"-"'-___ Simulate Evaluation Location: _~__ Plant __________ Simulator Expected Completion Time: 15 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: _________ Completion Time:.______

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

Comments:

Evaluators Signature: _________________________

NRC 2013 JPM P-3 May 2013

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

NMP Unit 1 Turbine Building Elevation 261' Simulator Set-up (if required):

None Directions to the Instructor/Evaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas PasslFail.

2. During Evaluated JPM:

Self verification shall be demonstrated.

3. During Training JPM:

Self verification shall be demonstrated.

No other verification shall be demonstrated.

References:

1. NUREG 1123 KA 295031 EA1.08, RO 3.8, SRO 3.9

2. Nl-S0P-21.2, Attachment 4 Tools and Equipment:

1. None NRC 2013 JPM P-3 May 2013

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

1. The Control Room has been evacuated due to a fire.

2. Nl-SOP-2L2 has been entered.

3. Instructor to ask for any questions.

Initiating Cues:

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

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

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

2. Obtain a copy of the reference procedure Nl-SOP-2L2, Attachment 4 obtained SatiUnsat and review/utilize the correct section of the procedure.

3. Verity locked closed the following valves (TB 261 '):

29-07, FIRE WATER TO FEED 29-07 verified closed by ensuring handwheel SatiUnsat WATER AFTER SPOOL PIECE (FS in fully CW position and locking device

62) installed

100-33, FIRE WATER FEED 100-33 verified closed by ensuring handwheel SatiUnsat WATER SPOOL PIECE INLET (FS in fully CW position and locking device

63) installed Cue: Valves 29-07 and 100-33 are LOCKED closed.

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

NRC 2013 JPM P-3 May 2013

Performance Steps Standard Grade

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

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

Attachment 4 steps 2-4 have been verified complete.

S. Unlock the following valves:

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

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

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

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

6. Supply the fire header by performing one of the following:

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

NRC 2013 JPM P-3 May 2013

Performance Steps Standard Grade

7. When directed by the CRS/SM, open the Determines direction has already been given following valves to begin injection into in initiating cue RPV:

29-07, FIRE WATER TO FEED 29-07 opened by turning handwheel fully PasslFail WATER AFTER SPOOL PIECE CCW

100-33, FIRE WATER TO FEED 100-33 opened by turning handwheel fully PasslFaii WATER SPOOL PIECE INLET CCW Cue: Valves 29-07 and 100-33 are open and injection to the RPV has commenced

8. Verify no leakage at spool piece Verifies by visual inspection that there is no SatlUnsat connections leakage at the spool piece connections Cue: There is no leakage from the spool piece connections

9. Notifies CRS/SM that fire water is Proper communications used SatlUnsat being injected to the RPV (GAP-OPS-Ol)

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

NRC 2013 JPM P-3 May 2013

Initial Conditions:

1. The Control Room has been evacuated due to a fire.

2. NI-SOP-21.2 has been entered.

Initiating Cues:

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

NRC 2013 JPM P*3 May 2013

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

SUMMARY

Length: 60 minutes Initial Power Level: Approximately 95%

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

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

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

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

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

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

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

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

1. Malfunctions:

a. CT01 B, CT Pump 112 Trip PRESET

b. FW02A, FEEDWATER BOOSTER PUMP TRIP 11 TRG 1

c. ED04, PB 11 Electrical Fault TRG2

d. EC01, Steam Supply Line Break in PC, FV=11 % TRG3

e. FW06, SHAFT DRIVEN FEEDWATER PUMP CLUTCH FAILS

- DISENGAGES, Delay=20 seconds TRG23

f. PC10A, BV 68-01 Fails Open, Delay=2:00 TRG23

g. PC10C, BV 68-03 Fails Open, Delay=2:00 TRG23

h. FW28A, HPCI MODE FAILURE TO INITIATE 11 PRESET

i. FW28B, HPCI MODE FAILURE TO INITIATE 12 PRESET

j. CS07, CS Injection Valves Failure to Auto Open PRESET

k. CT01A, CT Pump 111 Trip PRESET

2. Remotes:

a. None

3. Overrides:

a. 7S43D14116, POS_3 4H17/51-02A C FRM B, FV=off (FWBP 13 auto-start failure) PRESET

b. 11 S33D15423, SET 1010 RPS CH.11 BYPASS SW, FV=on (Partial primary containment isolation failure) PRESET

c. 11S34D15424, SET 1010 RPS CH.12 BYPASS SW, FV=on (Partial primary containment isolation failure) PRESET

4. Annunciators:

a. None

5. Triggers:

a. TRG 23 - Initiates when the mode switch is taken to SHUTDOWN

i. Event Action: zdrpstdn==1 ii. Command: imf ec01 (O 0) 30 4:00 11

b. TRG 24 - Initiates when Containment Spray flow is initiated

i. Event Action: ctfdw> 100 ii. Command: imf ec01 (0 0) 45 1:00 30

C. Equipment Out of Service

1. Containment Spray pump 112 in PTL with yellow tag

2. Containment Spray suction valve 112 closed with yellow tag

3. Steam Packing Exhauster 12 green-flagged with yellow tag D. Support Documentation

1. RMI for Recirculation pump stop E. Miscellaneous

1. Note the failure of Core Spray to automatically inject is required to make the manual establishment of preferred and alternate injection sources a critical task when HPCI fails to automatically initiate.

2. Ensure Drywell cooling fan 11 is secured with control switch in neutral.

3. Ensure Service Water pump 11 is running and Service Water pump 12 is secured.

4. Protect the following equipment: EDG 103, PB 103, PB 12

5. Update Divisional Status Board

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

Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE)

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

Shift Manager Log (SM, CRS, STA)

Shift Turnover Checklist (ALL)

RO Log (RO)

LCO Status (SM, CRS, STA)

Lit Control Room Annunciators

Computer Alarm Summary (RO)

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

Reactor power is approximately 95%.

Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO per TS 3.3.7.b).

Steam Packing Exhauster 12 is caution tagged due to high vibrations.

PART III: Remarks/Planned Evolutions:

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

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

Review new Clearances (SM)

Test Control Annunciators (CRE)

Shift Crew Composition (SM/CRS)

TITLE NAME TITLE NAME SRO ATCRO BOPRO

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

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

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

Parameter crp H

Initial conditions to be verified prior to initiation of step:

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

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

Critical parameters to be monitored DURING Step:

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

Mlbm/hr IRMI evaluated against approved power profile:

N/A D. I IOther Comments:

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

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

Critical Tasks:

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

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

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

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

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

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

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

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

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

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

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

Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Secure Recirculation Pump 12 While Maintaining Reactor Power SRO

Directs securing Recirculation pump 12 per N1-0P-1 Section H.1.0

Provides oversight for evolution

Determines Technical Specification 3.1.7.e allows Reactor power up to 100% with idled Recirculation loop

Determines Core Operating Limits Report (COLR) requires APLHGR penalty BOP

Reviews N1-0P-1 Section H.1.0

Determines Recirculation pump 12 is NOT in local lock

Places RRECIRC PUMP 12 SPEED CONTROL in BAL AND nulls out Deviation Meter (top meter)

Places RRECIRC PUMP 12 SPEED CONTROL AUTO/BAllMAN switch to MAN

Verifies open REACTOR R PUMP 12 BYPASS VALVE

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 1 continued BOP continued

IF desired by the Shift Manager to maintain the plant close to present power level, THEN perform next two steps alternately using up to 1.0 x 106 Ibm/hr increments UNTIL Reactor Recirc Pump 12 flow is 6 to 8 x 106 Ibm/hr:

Reduces Recirculation pump 12 flow up to 1 x 106 Ibm/hr

Coordinates with ATC to maintain initial power level ATe

Monitors plant parameters

Raises Total Recirc flow using the Master Recirc Controller to initial power level as required based on BOP actions

Monitors APRMs, core flow, CTP, and Feedwater response BOP

Closes REACTOR R PUMP 12 DISCHARGE VALVE

WHEN Discharge Valve is closed, places REACTOR RP MOTOR 12 MG SET switch to STOP

Holds in OPEN position for 2 to 3 seconds, REACTOR R PUMP 12 DISCHARGE VALVE

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 1 continued BOP continued

IF MG set is to be out of service for greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , THEN verifies Electrical Maintenance notified to lift brushes off the Generator AN D Exciter slip rings

Refers to N1-0P-1 Section H.2.0 for 4 loop operations

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

Acknowledge/report annunciator H3 When directed by lead examiner, insert 1-6 REACTOR FW BOOSTER P11 malfunction: TRIP

Diagnose trip of Feedwater Booster FW02A, FEEDWATER BOOSTER PUMP TRIP 11 Pump 11 TRG 1 The following override prevents Feedwater Booster Pump 12 from Auto Starting on low header discharge pressure:

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

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

Acknowledges report

If BOP does not manually start FWBP 12, directs starting FWBP 12

Enters Tech Spec 3.1.B.b

Determines redundant component inoperable in HPCI train 11, thus 15 day LCO applies

Initiates surveillance requirement 4.1.B.c for redundant component operability verification

Notifies WECIWWM

Notifies Ops Management

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 2 continued ATe

Monitors plant parameters

May perform Emergency Power Reduction per N 1-S0P-1.1 as required to maintain RPV water level BOP Role Play: When dispatched as Operator to

Report alarm and respond per H3-1-6 investigate, wait 2 minutes, then report:

Confirms alarm on computer (E049

FWBP 11 breaker tripped on overcurrent RX FW BOOST PMP 11 TRIP)

No abnormal indications at FWBP 12 breaker

Recognizes/diagnoses failure of the

No abnormal indications at FWBP 11 or 12. standby pump to automatically start

Manually starts FWBP 12 Role Play: When dispatched as Operator to swap

Notifies crew of failure of FWBP 12 to HWC, wait 5 minutes and report that HWC injection auto start has been transferred from FWBP 11 to FWBP 12.

Dispatches operators to shift Hydrogen Water Chemistry injection from FWBP 11 to FWBP 12

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

Diagnose/report loss of PB 11 malfunction:

Recognize/report loss of:

Reactor Recirculation Pump 11 ED04, PB 11 Electrical Fault

Drywell Fans 14, 15, 16 TRG2

Condensate Pump 11

Circulating Water Pump 11 Reactor power lowers due to RRP trips

Service Water Pump 11 Reactor water level rises due to RRP trips

RBClC Pump 11 Expected Annunciators:

TBClC Pump 11 A4-1-1, PB 11 R113 TRIP

lAC 11 A4-4-2, POWER BD 16 LOW BUS VOLTAGE

Reactor Building Exhaust Fan 11 L 1-3-4, REACT BLDG/ATM DIFF PRESS

Recognize/report drop in Reactor Also the following equipment trips:

power Reactor Recirculation Pump 11

Recognize/report lowering condenser Drywell Fans 14, 15, 16 vacuum Condensate Pump 11

Recognize/report loss of Reactor Circulating Water Pump 11 Building D/P Service Water Pump 11 RBCLC Pump 11 TBCLC Pump 11 lAC 11 Reactor Building Exhaust Fan 11 SRO

Acknowledges reports from crew

Directs entry into N 1-S0P-30.1

Directs Emergency Power Reduction per N 1-S0P-1.1 to stabilize condenser vacuum, as necessary

Provides oversight for reactivity manipulation

Directs entry into N1-S0P-1.3, Recirculation Pump Trip

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 3 continued SRO continued

Directs RO to re-energize Powerboards 16A and 13A-15A

May enter N1-EOP-5, Secondary Containment Control, on loss of Reactor Building DIP

Directs restoration of Reactor Building DIP with either RBVS or RBEVS

May direct entry into N1-S0P-6.1 for loss of Spent Fuel Pool Cooling, as time permits

Reviews Technical Specifications

Acknowledges that the APRMs are inoperable while the RRP discharge Note: On the loss of Powerboard 11, Recirc pump valves are still open 11 trips. The APRMs are inoperable due to

Determines Technical Specification reverse flow through the tripped Recirc loop. The 3.1.7.e limits Reactor power to 90% in APRMs will be declared operable once the 3 loop operation discharge valve is closed.

Determines Core Operating Limits Report (COLR) requires APLHGR and MCPR penalties

Determines Technical Specification 3.1.8.b is entered again for loss of power to Feedwater pump 11 and Condensate pump 11

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued ATC

Acknowledges direction from SRO

Confirms plant is stable by verifying:

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

Executes N1-S0P-1.1, Emergency Power Reduction, to lower recirc flow and/or insert CRAM rods to stabilize condenser vacuum, as required

Determines plant operating point on the 3-loop power to flow curves Role Play: BOP If dispatched to investigate Powerboard 11, wait 2

Executes N1-S0P-30.1, loss of minutes then report that the normal supply breaker Power Board 11 (R113) tripped on overcurrent.

Starts Service Water pump 12 If dispatched to investigate Powerboard 16A, wait 2

Coordinates with ATC to monitor minutes then report that there are no problems APRMs and lPRMs evident at Powerboard 16. Report that electrical

Verifies TBClC pump 12 running maintenance has also looked at the Powerboard

Verifies lAC 12 and/or 13 running and concurs with re-energizing it.

Verifies RBClC pump 12 running

Verifies Steam Packing Exhauster 12 Role Play: running If dispatched to lineup Steam Packing Exhauster

Answers "Are A4-4-6, A4-4-7, A4-1-3 12, wait 4 minutes, then insert remote:

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

Determines Power Board 11 is faulted Then report task completion.

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

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

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued

Restores power to Powerboard 16A as follows:

Opens R1041

Closes R 1042

Verifies Power Board 16B amps

<962 Role Play: As operator when directed to energize

Dispatches operator to re-energize Powerboards 13A-15A, acknowledge order. If Power Boards 13A, 14A, and 15A asked about status during remainder of scenario,

Notifies SRO that APRMs are report that you are being briefed by the WECo inoperable

Closes Recirc pump 11 discharge valve

Holds open for 2-3 seconds Recirc pump 11 discharge valve

Records time when Recirc pump 11 discharge valve is cracked open

Executes N1-S0P-1.3, Recirc Pump Trip, as time permits Role Play: As operator when directed to restore

Dispatches operator to restore Offgas Offgas vacuum pump, acknowledge order. If called Vacuum Pump for a status on actions, report that you are being briefed by the WECo

Enters N1-S0P-6.1 for loss of Spent Fuel Pool Cooling, as time permits Role Play: As operator when directed to

Dispatches operator to investigate loss of Spent Fuel Pool Cooling, as time investigate Spent Fuel Pool Cooling, wait 3 minutes permits and then report that SFPC pump 11 has tripped.

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued

Respond to either annunciator (or as directed by CRS) and restore RB D/P:

L 1-1-5, RB VENT EXH FAN 11-12 TRIP-VIB o Verifies closed Reactor Building Exhaust Fan 11 outlet damper o Starts Reactor Building Exhaust Fan 12

L 1-3-4, REACT BLDG/ATM DIFF PRESS o Starts RBEVS per OP-1 0 Possible actions in OP-10 Section H.1.0 to start RBEVS

Verifies open 202-36, EM VENTILATION FROM REACTOR BLDG BV

Verifies closed the following valves:

202-47, EM VENTILATION TIE BV

202-74, EM VENTILATION LOOP 11 COOL! NG BV

202-75, EM VENTILATION LOOP 12 COOL! NG BV

Places 202-37(38), EM VENTILATION LOOP 11(12) INLET BV control switch to OPEN

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued

Verifies open 202-37(38), EM VENTILATION LOOP 11(12) INLET BV

Starts 202-53(33), EVS FAN 11 (12)

Verifies open 202-34(35), EM VENT EXHAUST FAN 11 (12) OUTLET BV

Confirms proper operation of 202 50(51), EM VENT EXHAUST FAN 11(12) INLET FCV, by observing indicating lights and flow indication Role Play: As RP, acknowledge report that

Notifies Rad Protection that the RBEVS is in service and RBVS is secured. Reactor Building Emergency Ventilation system is in service

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

Diagnose/report degrading Open. Failure of HPCI to Auto-Initiate. Partial containment parameters Primary Containment Isolation Failure. and Trip

Acknowledge/report annunciators of Containment Spray Pump 111

Diagnose failure of HPCI to When directed by the lead examiner, insert automatically initiate malfunction:

Diagnose partial failure of primary containment isolation EC01, Steam Supply Line Break in PC, FV=11

Diagnose the trip of Containment TRG3 Spray pump 111 Drywell humidity, pressure and temperature rise Drywellieakage rises Expected annunciators:

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

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

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

INSTRUCTOR ACTIONS!

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

Acknowledges reports Verify the following malfunctions automatically

Directs manual scram insert when the mode switch is taken to

Acknowledges scram report SHUTDOWN:

Enters N1-EOP-2 on low RPV water FW06, SHAFT DRIVEN FEEDWATER PUMP level CLUTCH FAILS - DISENGAGES, Delay=20

Directs N1-S0P-1 actions seconds

Directs RPV water level controlled 53 EC01, Steam Supply Line Break in PC, IV=11, 95" with Condensate/FW and CRD RT=4:00, FV=30

When notified of the failure of HPCI PC10A, BV 68*01 Fails Open, Delay=2:00 to initiate, directs manual control of PC10C, BV 68-03 Fails Open, Delay=2:00 Feedwater (preferred and alternate TRG23 injection systems)

Containment conditions further degrade CT*1 Feedwater pump 13 disengages

Directs RPV pressure controlled 800 Reactor water level remains low 1000 psig with Turbine Bypass Valves Two Torus-to-Drywell vacuum breakers indicate or Emergency Condensers open

May direct closure of MSIVs to limit Expected annunciator:

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

Enters N1-EOP-4 due to high drywell pressure and temperature o Direct lockout of Containment Verify the following overrides are PRESET to Spray pumps cause partial primary containment isolation failure:

Re-enters N1-EOP-2 due to high 11S33D15423, SET 1010 RPS drywell pressure CH.11 BYPASS

Directs execution of N1-S0P-40.2 for SW, FV=on isolation verification 11 S34DI5424 SET 1010 RPS

Acknowledges partial failure of primary CH.12 BYPASS containment isolation SW, FV=on

Directs/acknowledges manual closure of primary containment isolation valves Verify the following malfunction automatically inserts when Containment Spray flow is initiated to the Drywell:

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

INSTRUCTOR ACTIONS!

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

When Torus pressure exceeds 13 Events 4,5,6, 7 & 8 continued psig or Drywell temperature approaches 300°F:

Answers "Selow the Containment Spray Initiation Limit?" - Yes

Verifies all Recirc pumps tripped

Directs trip of all Drywell cooling fans

Directs operation of Containment Spray per N1-EOP-1 attachment 17

Evaluates/monitors position on Pressure Suppression Pressure curve

Acknowledges report of Containment Spray pump 111 trip

May direct rapid depressurization with ECs in anticipation of RPV Slowdown

Determines Torus pressure cannot be maintained within Pressure Suppression Pressure limit

Enters N1-EOP-8, RPV Slowdown CT-2

Answers "Are all control rods inserted to at least 04?" YES

Answers "Drywell pressure?" At or above 3.5 psig

May direct prevention of Core Spray injection per N1-EOP-1 Note: Core Spray injection will only be prevented if attachment 4 not needed for core cooling. If the crew has not yet

Directs EC initiation re-established RPV injection when this step is

Answers "Torus water level?"

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

Directs open 4 ERVs continuous guidance for this consideration.

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

Monitors plant parameters

When directed, places Mode Switch in Shutdown

Provides scram report

Performs N1-S0P-1, Reactor Scram, scram verification actions

Places I RMs on range 9

Inserts IRM and SRM detectors

Down-ranges IRMs as necessary to monitor power decrease

If recirc pumps have not yet tripped, reduces recirc flow to 25 43 Mlbm/hr

Maintains RPV pressure below 1080 psig and in assigned band

Executes N1-S0P-40.2

Recognizes/reports failure of multiple primary containment isolation valves to automatically close

Manually closes the following valves:

Note:

201.7-01 & 02, 201.2-110 &

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

(11 H202)

201.2-23 & 24, 201.2-29 & 30 (12 H202)

201.7-08 & 09,201.7-10 & 11 (Drywell CAM)

Reports primary containment isolation valves have been manually closed

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

Monitors/reports degrading Containment parameters

Performs RPV water level control actions of N1-S0P-1, Reactor Scram:

Restores RPV level to 53-95" by controlling injection and rejecting through RWCU

Determines #13 FWP was running

Determines RPV water level is Note: Feedwater level control actions will vary recovering depending on when the operator diagnoses the

Terminates 13 FWP injection as failure of HPCI to automatically control injection follows:

through Feedwater flow control valves 11 and 12.

Closes 13 FWP VALVE CONTROL

Disengages 13 FWP

Closes 29-10, Feedwater Pump 13 Blocking Valve

Verifies RPV water level above 53"

Verifies 11112 FWP controllers in MANUAL and set to zero output

Places FWP BYPASS Valve 11 or 12 in AUTO, sets to 65-70 inches

If RPV level reaches 85 inches and rising, then:

Verifies off all FW Pumps

Secures CRD Pumps not required

Diagnoses failure of HPCI to automatically initiate

Notifies SRO/Crew of HPCI failure

Manually controls RPV injection to restore and maintain level CT-1

INSTRUCTOR ACTIONS!

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

Places Containment Spray pumps in PTL

Closes MSIVs, as directed

Reports when Torus pressure exceeds 13 psig or Drywell temperature approaches 300°F

Verifies Recirc pumps tripped

Trips Drywell cooling fans

Initiates Containment Spray per N1 EOP-1 attachment 17

Diagnoses/reports Containment Spray pump 111 trip

Verifies started Containment Spray pumps 121 and 122

If 80-118 is open for Torus Cooling:

Opens 80-35

Closes80-118 Note: Core Spray pumps may be placed in PTL if

Verifies open 80-40 and 80-45 needed before EOP-1 attachment 4 jumpers can

Prevents Core Spray injection be installed due to scenario progression and installing N1-EOP-1 attachment 4 resource limitations. If Core Spray pumps are jumpers (17, 18, 19,24,25,26), if placed in PTL, at least one Core Spray pump directed should be restarted after jumper installation for App

Initiates both ECs J water seal. Core Spray may also be used as an

Opens 4 ERVs alternate injection source.

CT-2 Terminating Cues:

RPV water level controlled in assigned band

RPV Slowdown in progress

Primary Containment pressure maintained per N1-EOP-4

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

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

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

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

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

SCENARIO

SUMMARY

Length: 50 minutes Initial Power Level: Approximately 55%

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

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

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

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

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

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

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

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

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

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

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

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

1. Malfunctions:

a. CT01 B, CT Pump 112 Trip PRESET

b. NM36A, RECIRC FLOW CONVERTER CHANNEL 11 FAILURE- UPSCALE TRG 1

c. EC03B, EC RETURN VALVE FAILS OPEN(IV 39-06) TRG2

d. CW17, Intake Traveling Screens Blockage, FV=65%, RT=10:00 TRG3

e. FW14C, Feedwater Master Controller - Fail As Is TRG3

f. EC02, Steam Supply Line Break in RB, FV=20% TRG4

g. EC07A, Emergency Condenser 11 Fails to Isolate PRESET

h. EC08A, EC LOOP 11 STM IV FAIL TO CLOSE 111 , FV=50% PRESET

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

2. Remotes:

a. FW24 , REMOVAL OF HPCI FUSES FU8/FU9, FV=pulled TRG24

3. Overrides:

a. 13S70014674, POS_1 1E67 REAC. SW.-RUN, FV=on (Mode switch fails to scram) PRESET

b. 13S70014675, POS_2 1E67 REAC. SW.-SHUTOOWN, FV=off (Mode switch fails to scram) PRESET

c. 1A2S701176, POS_2 TC BOJ CLOSE, FV=off (BO.. IM fails to open TBVs) PRESET

4. Annunciators:

a. None

5. Triggers:

a. Trigger 29 - After scram, allows Mode Switch logic to reposition to prevent MSIV closure on low pressure.

i. Event Action: rd:rpscm(1)==1 ii. Command: dor 13S70014674

b. Trigger 30 - After scram, allows Mode Switch logic to reposition to prevent MSIV closure on low pressure.

i. Event Action: rd:rpscm(1)==1 ii. Command: dor 13S70014674

C. Equipment Out of Service

1. Containment Spray pump 112 in PTL with yellow tag

2. Containment Spray suction valve 112 closed with yellow tag

3. Steam Packing Exhauster 12 green-flagged with yellow tag D. Support Documentation

1. RMI for power ascension with Recirculation flow E. Miscellaneous

1. Ensure Drywell cooling fan 11 is secured with control switch in neutral.

2. Ensure the Main Generator is supplying approximately 100 MVARs to the grid with the voltage regulator in automatic.

3. Markup N1-0P-43B Section F.3.0 to the appropriate steps for 55% power level.

4. Protect the following equipment: EDG 103, PB 103

5. Update Divisional Status Board

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

Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE)

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

Shift Manager Log (SM, CRS, STA)

Shift Turnover Checklist (ALL)

RO Log (RO)

LCO Status (SM, CRS, STA)

Lit Control Room Annunciators

Computer Alarm Summary (RO)

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

Reactor power is approximately 50%.

Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO perTS 3.3.7.b).

Steam Packing Exhauster 12 is caution tagged due to high vibrations.

Circulating Water pump 11 was returned to service following waterbox cleaning earlier in the shift.

PART III: Remarks/Planned Evolutions:

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

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

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

Review new Clearances (SM)

Test Control Annunciators (CRE)

Shift Crew Composition (SM/CRS)

TITLE NAME TITLE NAME SRO ATCRO BOPRO

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

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

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

Initial conditions to be verified prior to initiation of step:

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

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

Critical parameters to be monitored DURING Step:

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

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

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

IRMI evaluated against approved power profile:

N/A D. I IOther Comments:

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

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

Critical Tasks:

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

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

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

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

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

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

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

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

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

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

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

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

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

Measurable Performance Indicators: The crew will manually open ERVs.

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

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

Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Power Ascension With Recirculation SRO

Directs power ascension with Recirculation flow lAW N1-0P-438 and the Reactivity Maneuver Instruction (RMI)

Provides oversight of reactivity maneuver Note: ATC N1-0P-438 includes the following power-to-flow

Acknowledges direction from SRO map restrictions:

Raises Recirculation flow with master

PRIOR to exceeding 65% flow, verify greater Recirculation flow controller than 50% Rod Line OR that RIP region will

Monitors APRMs NOT be entered.

Monitors Recirculation flow

PRIOR to 100% rodline raise recirc flow to

Monitors Feedwater flow and RPV greater than 59% flow (approximately 40 x 106 water level Ib/hr) to avoid the flow biased control rod block

Observes power-to-flow map line. restrictions BOP Note:

Monitors individual RRPs for response Recommend initiating the next event when Reactor

Individual MIA-Speed Control power is between 55-60% power to achieve the stations trending uniformly desired response in Event 6.

Individual RRP indications trending normally for speed increase

Monitors Feedwater controls for proper response

FWP 13 FCV responding to power change

RPV water level remains within program band (65" - 83")

INSTRUCTOR ACTIONS/

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

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

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

Expected Annunciators:

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

Acknowledges reports from crew

Directs response with ARP F2-2-6

Consults Tech Spec Tables 3.6.2.a and 3.6.2.g

Declares APRMs 11-14 inoperable for the upscale scram and rod block functions

Determines a half scram must be placed on RPS channel 11 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

Contacts I&C Department for troubleshooting

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 2 continued ATe

Verifies proper power to flow ratio on Power Flow Map on E Panel BOP

Executes ARP F2-2-6

Confirms alarm by observing the following:

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

INSTRUCTOR ACTIONS/

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

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

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

SRO Role Play:

Acknowledges report from crew If informed as Shift Manager, GSO, Operations

Directs raising Main Generator Manager or CENG Generation Dispatch, reactive load by 100 MVARs per N 1 acknowledge report and concur with actions to OP-32 section F raise MVARs as needed.

BOP

Executes N1-0P-32 section F

Adjusts VOLTAGE REG ADJUSTMENT switch at E console to raise 100 MVARS

Adjusts EXCITER RHEOSTAT switch at E console to establish AND maintain between 10 AND 20 Volts Boost on the VOLTAGE REG AMPLIDYNE meter

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

Recognizelreport Emergency When directed by lead examiner, insert Condenser 12 initiation malfunction:

Recognize/report Reactor power and water level rising EC03B, EC RETURN VALVE FAILS OPEN (IV 39-

Recognize/report no valid Emergency

06) Condenser initiation signal TRG2 EC 12 Condensate Return Valve (39-06) opens Reactor power rises Reactor water level initially rises Expected Annunciators:

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

Acknowledges reports from crew

Directs response with ARP K1-1-5 Role Play:

Directs securing Emergency If dispatched to investigate 39-06, wait 2 minutes Condenser 12 and then report that there is a significant air leak on

Declares Emergency Condenser 12 the air supply line to 39-06. inoperable but available

Enters a 7 day LCO per Tech Spec 3.1.3.b BOP The next event should NOT be inserted until

Executes ARP K1-1-5 Reactor water level has stabilized from this event.

Closes:

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

INSTRUCTOR ACTIONS!

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

Recognize/report annunciator malfunction:

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

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

The malfunction for Event 6 is inserted with Event

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

SRO Booth Operator:

Acknowledges reports When one Circulating Water pump is tripped,

Directs entry into N 1-S0P-18. 1, modify malfunction CW17 to 40% over 1 minute. Service Water Failure / Low Intake Level

Directs emergency power reduction per N1-S0P-1.1 as needed

Provides oversight for reactivity manipulation

Acknowledges improving intake level

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 5 continued BOP

Executes N1-S0P-18.1, Service Role Plays: Water Failure / Low Intake Level If requested as Operator in field to investigate, wait

Updates crew on override 2 minutes, then report: requirements to trip a Circulating

A large amount of lake grass is coming in the Water pump and perform an intake and accumulating on the traveling emergency power reduction screens.

Trips one Circulating Water pump

The traveling screens are operating properly CT-1 but not keeping up with the influx of grass.

Monitors intake level

Report intake level as indicated by simulator

Monitors condenser vacuum, (use screen CW04, Secondary Forebay water Circulating Water temperatures, and level - CWL(4>>. Feedwater response during power reduction Subsequent reports may be given with no delay.

Determines/reports intake level improves following Circulating Water Once one Circulating Water pump is tripped and pump trip intake level is improving, report that the traveling screens are catching up and intake level is improving.

ATC

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

as needed for single Circ Water pump operation

Observes APRMs, CTP, and Recirculation flow

INSTRUCTOR ACTIONS!

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

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

Recognize/report Feedwater FCV 13 and/or Feedwater master controller is FW14C, FW14C, Feedwater Master Controller not responding properly Fail As Is TRG3 Reactor water level deviates from setpoint Feedwater FCV 13 does NOT change position Feedwater flow remains constant Expected Annunciators:

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

Acknowledges reports If crew does not respond to the malfunction, a

Directs entry into N 1-S0P-16.1 ,

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

Directs placing FW FCV 13 in manual ATC

Monitors RPV water level

Monitors plant parameters BOP

Enters N 1-S0P-16.1, Feedwater System Failures

Answers "Problem with FWLC, FW Pumps OR FW heating?" FWLC

Answers "FCV lockup?" NO

Answers "FWLC malfunction?" YES

Places FW FCV 13 controller in MAN

Controls RPV water level in manual

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

Acknowledge/report annunciators Condenser 11 Fails To Isolate, Mode Switch

Recognize/report Emergency Fails to Scram, BOJM Fails to Open TBVs Condenser 11 steam leak When directed by the lead examiner, insert

Recognize/report failure of Emergency malfunction: Condenser 11 to isolate

Recognize/report failure of Mode EC02, Steam Supply Line Break in RB, FV=20% Switch TRG 4

May recognize/report failure of BOJM Reactor Building D/P lowers Rising temperatures, pressures and radiation levels in the Secondary Containment RBEVS auto-starts RBVS isolates Expected Annunciators:

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

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

INSTRUCTOR ACTIONS!

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

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

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

Emergency Condenser 11 fails to iso/ate.

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

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

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

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

SHUTDOWN

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

Acknowledges reports

Enters N 1-EOP-5 on high Reactor Building Vent rad levels, high Reactor Building area temperatures I rad levels, and/or loss of RB DIP

Directs manual isolation of Emergency Condenser 11

Directs Reactor Building evacuation

Acknowledges manual isolation failure

Directs dispatching of an operator and RP tech to obtain general area temperatures and radiation levels in the Reactor Building

When Reactor Building Ventilation exhaust radiation exceeds 5 mRlhr, directs verification of RB Vent isolation and RBEVS initiation

Determines area temperatures and/or radiation levels are above setpoints in Tables T and R, and transitions to N1 EOP-5 circle 27

Determines a primary system is discharging into the Reactor Building and the discharge cannot be isolated, and transitions to N1-EOP-5 circle 28

When any area temperature or radiation level approaches or reaches 135°F or 8 Rlhr, respectively:

Note:

Directs manual Reactor scram If the Reactor scrammed due to an earlier event, CT-2 CT-2 will be N/A.

Acknowledges scram report

Enters N1-EOP-2, RPV Control, on low RPV water level

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

Answers "Are all control rods inserted to at least position 04?" YES

Directs entry into N1-S0P-1, Reactor Scram

Directs RPV water level control 53-95" using Feedwater/Condensate and CRD

Directs RPV pressure maintained

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

May direct anticipatory blowdown with directed from N1-EOP-2 once one Reactor Building TBVs and/or Emergency Condenser General Area temperature is above 135°F with a 12 with cooldown in excess of second temperature trending towards 135°F. 100oF/hr

Acknowledge failure of BOJM, if reported Note:

May direct opening TBVs using Emergency Condenser 12 is available even though MPR it was isolated earlier due to inadvertent initiation.

Acknowledges reports of Reactor The crew may decide not to use Emergency Building temperatures and radiation Condenser 12 due to actuation of Annunciator K1 levels 4-5, EMER COOLING SYSTEM 12 STEAM LEAK

When report is received that 2 General AREA T HI. Areas temperatures are above 1350 F, enters N1-EOP-8, RPV Blowdown

Answers "Are all control rods inserted to at least position 04" YES

Answers "Drywell pressure?" <3.5 psig

May direct initiation of Emergency Condenser 12

Answers "Torus water level?" >8 ft

Directs open 4 ERVs CT-3

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

Monitors plant parameters Note: Prior to the scram, the ATC may also

Makes evacuation announcements perform response actions for BOP since Feedwater due to steam leak level control is in manual.

Places Reactor Mode Switch to SHUTDOWN

Recognizes/reports failure of Mode Switch to scram

Depresses RPS manual scram push buttons and/or manually initiates ARI

Provides scram report

Performs scram verification actions of N1-S0P-1, Reactor Scram:

Confirms all rods inserted

Observes Reactor power lowering

Places IRMs on range 9

Inserts IRM and SRM detectors

Down-ranges IRMs as necessary

Reduces Recirc Master flow to 25-43 x 106 lbm/hr

Verifies main turbine and generator tripped

Controls RPV pressure as directed using TBVs and/or Emergency Condenser 12

May recognize/report failure of BOJM and open TBVs using MPR

INSTRUCTOR ACTIONS!

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

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

the Reactor Building to monitor area temperatures.

39-07R, EC STM ISOLATION The timeline of field reports may be adjusted by VALVE 112 examiner as necessary for evaluation purposes.

39-09R, EC STM ISOLATION VALVE 111 Role Play: When directed as Operator and RP

39-05, EMERG CNDSR COND tech to obtain General Area temperatures and RET ISOLATION VALVE 11 radiation levels in the Reactor Building:

39-11 R, EMERG CNDSR STM SUPPLY DRAIN IV 111 Wait 4 minutes and report RB 318' west side

39-12R, EMERG CNDSR STM temperature is 125°F and rising, radiation level is 2 SUPPLY DRAIN IV 112 mr/hr and rising. Also report that you see steam

05-01 R, EMERG COND VENT coming from the area of the EC steam IV room. ISOLATION VALVE 111

05-11, EMERG COND VENT Note: When one general area temperature is ISOLATION VALVE 112 reported above 135°F and a second general

Reports failure of 39-07R and 39-09R area temperature is reported as approaching to close 135°F, the crew is likely to perform an

Dispatches operator and RP tech to anticipatory blowdown per EOP-2.

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

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

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

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

Performs RPV water level control actions of N1-S0P-1, Reactor Scram:

Restores RPV level to 53-95" by controlling injection and rejecting through RWCU

Determines #13 FWP was running

Determines RPV water level is recovering

Terminates 13 FWP injection as follows:

Closes 13 FWP VALVE CONTROL

Disengages 13 FWP

Closes 29-10, Feedwater Pump 13 Blocking Valve

Verifies RPV water level above 53"

Verifies 11/12 FWP controllers in MANUAL and set to zero output

Places FWP BYPASS Valve 11 or 12 in AUTO, sets to 65-70 inches

If RPV level reaches 85 inches and rising, then:

Verifies off all FW Pumps

Secures CRD Pumps not required

May initiate Emergency Condenser 12

Opens 4 ERVs CT-3 Terminating Cues:

RPV water level controlled in assigned band

RPV Blowdown in progress

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

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

SUMMARY

Length: 60 minutes Initial Power Level: Approximately 100%

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

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

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

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

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

The CRS will determine the Tech Spec impact.

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

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

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

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

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

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

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

1. Malfunctions:

a. CT01 B, CT Pump 112 Trip PRESET

b. RP01A, REACTOR TRIP BUS MOTOR GENERATOR TRIPS 131 TRG 1

c. RP16B, RPV PT 36-07B FAILED LOW TRG2

d. RD36A, CRD FCV 44-151 FAILURE - CLOSED TRG3

e. TC08, MECHANICAL PRES. REGULATOR FAILS - LOW TRG20

f. RD33A, CONTROL ROD BANK BLOCKED BANK 1, FV=8 PRESET

g. RD33B, CONTROL ROD BANK BLOCKED BANK 2, FV=8 PRESET

h. RD33C, CONTROL ROD BANK BLOCKED BANK 3, FV=18 PRESET

i. RD33D, CONTROL ROD BANK BLOCKED BANK 4, FV=8 PRESET

j. RD33E, CONTROL ROD BANK BLOCKED BANK 5, FV=8 PRESET

k. LP01A, Liquid Poison Pump 11 Trip, DT=5 TRG 11 I. LP01 B, Liquid Poison Pump 12 Trip, DT=5 TRG12

m. RD35B, CRD Hydraulic Pump 12 Trip TRG5

2. Remotes:

a. RP01, RX TRIP BUS 131 PWR SOURCE, FV=maint TRG29

b. MS01, HP FW HTR 115 RESET, FV=reset TRG30

c. MS03, HP FW HTR 135 RESET, FV=reset TRG30

d. MS04, FW HTR STRING 11 RESET, FV=reset TRG30

e. MS06, FW HTR STRING 13 RESET, FV=reset TRG30

f. RD05, CRD FLOW CONTROL VALVE ISOL, FV=nc30b TRG 21

g. FW24 , REMOVAL OF HPCI FUSES FU8/FU9, FV=pulled TRG24

3. Overrides:

a. 13S73D146713, POS_2 'I E70 TC MPR POS C, FV=on (MPR setpoint drifts low) TRG4

4. Annunciators:

a. None

5. Triggers:

a. TRG 11 -Initiates when Liquid Poison pump keylock switch is taken to SYS 11 position.

i. Event Action: zdlpsys2==1

ii. Command: None

b. TRG 12 - Initiates when Liquid Poison pump keylock switch is taken to SYS 12 position.

i. Event Action: zdlpsys1 ==1 ii. Command: None

c. TRG 20 - Initiates when the Mode Switch is taken to SHUTDOWN

i. Event Action: zdrpstdn==1 ii. Command: dor 13s73di46713

d. TRG 21 -Initiates when the CRD FCV selector switch is re-positioned

i. Event Action: zdrdfcvb==1 ii. Command: None C. Equipment Out of Service

1. Containment Spray pump 112 in PTL with yellow tag

2. Containment Spray suction valve 112 closed with yellow tag

3. Steam Packing Exhauster 12 green-flagged with yellow tag D. Support Documentation

1. None.

E. Miscellaneous

1. Ensure Drywell cooling fan 11 is secured with control switch in neutral.

2. Ensure CRD pump B is running and CRD pump A is in standby.

3. Protect the following equipment: EDG 103, PB 103

4. Update Divisional Status Board

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

Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE)

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

Shift Manager Log (SM, CRS, STA)

Shift Turnover Checklist (ALL)

RO Log (RO)

LCO Status (SM, CRS, STA)

Lit Control Room Annunciators

Computer Alarm Summary {RO}

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

Reactor power is approximately 100%.

Containment Spray pump 112 is out of service for maintenance (Day 1 of planned 2 day window; 15 day LCO per TS 3.3.7.b).

Steam Packing Exhauster 12 is caution tagged due to high vibrations.

PART III: Remarks/Planned Evolutions:

Maintain operation at rated power.

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

Review new Clearances (SM)

Test Control Annunciators (CRE)

Shift Crew Composition (SM/CRS)

TITLE NAME TITLE NAME SRO ATCRO BOPRO

Critical Tasks:

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

Tripping Reactor Recirculation pumps, and/or

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

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

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

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

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

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

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

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

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

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

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

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

Recognize/report RPS 11 half scram malfunction:

Diagnose trip of RPS MG set 131 RP01 A, REACTOR TRI P BUS MOTOR GENERATOR TRIPS 131 TRG 1 Scram solenoid lights for RPS 11 de-energize Feedwater temperature slowly lowers Reactor power slowly rises Expected annunciators:

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 execution of ARP F1-3-7

Directs entry into N1-0P-48 H.4.D

Directs entry into N1-S0P-16.1 for loss of Feedwater heating

May direct emergency power reduction per N1-S0P-1.1 if needed to control Feedwater temperatures or Reactor power

Provides oversight of reactivity changes

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 1 continued ATC

Monitors plant parameters Role Play: When dispatched as operator to

Lowers power per N1-S0P-1.1 as investigate problem with MG Set 131, wait two required to control Feedwater minutes then report that you can smell burnt temperatures or Reactor power insulation in the vicinity of MG Set 131 motor.

Resets half scram Report that the drive motor breaker tripped on overcurrent. If asked, report no overvoltage trip BOP occurred.

Executes ARP F1-3-7

Dispatches an operator to investigate MG Set 131

Determines I&C Bus 130A is available

Obtains SRO permission to perform Role Play: When dispatched as operator to dead bus transfer of Reactor Trip Bus transfer Reactor Trip Bus 131 to I&C Bus 130A, 131 wait 2 minutes and insert remote:

Dispatches an operator to perform RP01, RP01, RX TRIP BUS 131 PWR SOURCE, dead bus transfer of Reactor Trip Bus FV=maint 131 per N1-0P-48 section H.4.0 TRG 29

Enters N1-S0P-16.1 due to loss of Then report Reactor Trip Bus 131 has been re Feedwater heating energized from I&C Bus 130A, and that half scram

Monitors Feedwater temperatures and Feedwater heaters can be reset.

Acknowledges that Reactor Trip Bus 131 is re-energized Role Play: When dispatched as operator to

Coordinates with ATC to reset half reset Feedwater heaters, wait 2 minutes and insert scram remotes:

Dispatches operator to reset MS01, HP FW HTR 115 RESET, FV=reset Feedwater heaters MS03, HP FW HTR 135 RESET, FV=reset MS04, FW HTR STRING 11 RESET, FV=reset MS06, FW HTR STRING 13 RESET, FV=reset TRG 30 Then report Feedwater heaters have been reset.

INSTRUCTOR ACTIONS!

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

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

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

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

Acknowledges reports from crew

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

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

Executes ARPs F4-4-2 and F4-4-7

Dispatches operator to investigate indications at ATS Cabinet

INSTRUCTOR ACTIONS!

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

Acknowledgelreport Annunciator F3-1 malfunction: S

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

F3-1-5 CRD CHARGING WTR PRESS HIILO SRO

Directs execution of ARP F3-1-S

Directs entry into N1-S0P-S.1

Directs shifting CRD FCVs per N 1 OP-S, Sect. F.S.O

Determines Technical Specification 3.1.6.c applies for a loss of CRD injection flow

Acknowledges report that CRD FCV 12 is in service

After CRD FCV 12 is in service, exits TS 3.1.6 ATC

Monitors plant parameters

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP

Executes ARP F3-1-5

Determines CRD FCV is failed closed

Enters N1-S0P-5.1

Determines standby FCV is to be placed in service per N 1-0P-5 section Role Play: If requested to investigate CRD FCV F.5.0 failure, wait 2 minutes and report that CRD FCV 11

Establishes communications between (44-151) appears to have failed closed. Control Room and CRD Flow Control Valves

Places FIC 44-146B, CRD FLOW CONTROL, MIA station in MANUAL

Directs operator to open the following Role Play: When requested to open 44-148 and valves:

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

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

position following countdown perform countdown and report RB Air Transfer

Places CRD FLOW CONTROL Switch is in the Up position.

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

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

swapped:

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

Confirms CRD Flow between 64-66 FV=nc30b gpm TRG 21

Places FIC 44-146B, CRD FLOW CONTROL, MIA Station in AUTO Role Play: When requested to close 44-150 and 44-153 (step F.5.3.3), wait 1 minute and report valves are closed.

INSTRUCTOR ACTIONS!

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

Recognize/report MPR taking control CRD Pump Trips

Recognize/report lowering Reactor When directed by lead examiner, insert override: pressure

Recognize/report Turbine Bypass 13S73D146713, POS_21E70 TC MPR POS C, valves opening FV=on TRG4

Later:

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

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

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

Liquid Poison pumps trip

INSTRUCTOR ACTIONS!

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

Acknowledges reports

Directs entry into N1-S0P-31.2, as time permits

Directs manual Reactor scram per N1 Note: SOP-1 When the Mode Switch is taken to SHUTDOWN,

Acknowledges failure to scram verify TRG 20 automatically:

Enters N1-EOP-2 due to Reactor

Inserts malfunction TCOS, MECHANICAL power above 6% when scram required PRES. REGULATOR FAILS - LOW

Answers "All rods in to at least 04" NO

Deletes override 135730146713, POS_2 1E70

Answers "Will the reactor stay TC MPR POS C, FV=on shutdown without boron" NO This fails the MPR completely.

Exits N1-EOP-2, enters N1-EOP-3

Directs ADS bypassed

Directs prevention of Core Spray Note:

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

Directs bypass of the low-low RPV RD35B, CRD Hydraulic Pump 12 Trip water level MSIV isolation per N1 TRG5 EOP-1 Att 2 CRD pump 12 trips

Determines Reactor power is above 6% and RPV water level is above -41 inches

Directs terminate and prevent of all injection except boron and CRD per N1-EOP-1 Att 24 CT-1

Directs RPV water level lowered to at least -41 inches

INSTRUCTOR ACTIONS!

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

If an ERV is cycling:

Directs initiation of Emergency Condensers

Directs open ERVs to lower RPV pressure to less than 965 psig

Directs RPV pressure controlled below 1080 psig using Turbine Bypass valves, Emergency Condensers, and ERVs

Monitors Figure M, Heat Capacity Temperature Limit N1-EOP-3 Power Leg Actions

Directs initiation of ARI

Answers "Turbine Generator on-line?"

NO

Answers "Reactor power?" Above 6%

Verifies Recirc Pumps tripped CT-1

Directs execution of N1-EOP-3.1 CT-2

Acknowledges trip of CRD pump 12

May enter N 1-S0P-5.1

Directs start of CRD pump 11

If power oscillates more than 25% or before Torus water temperature reaches 110°F:

Records Liquid Poison tank level

Directs Liquid Poison injection

Acknowledges trip of Liquid Poison pumps

Directs alternate boron injection per N1-EOP-3.2

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

Acknowleqges RPV water level below

-41 inches

If Torus temperature is above 110°F, then directs level lowered until:

Power drops below 6%, OR

Level drops to -84 inches (TAF)

Records final actual level

Directs RPV injection with Condensate/Feedwater and CRD ATC

Places Mode Switch in SHUTDOWN

Depresses manual scram pushbuttons

Provides scram report

Bypasses Core Spray IV interlocks per N1-EOP-1 Att 4 by installing six jumpers inside Panel N (17, 18, 19, 24,25,26)

Bypass low-low MSIV isolation per N1 EOP-1 Att 2 by installing four jumpers inside Panel N (1,2,8, 9)

When directed, performs N1-EOP 3.1 (See actions below)

CT-2

Reports when APRMs <6%

Reports status of control rod insertion

Recognizes/reports trip of CRD pump 12

Starts CRD pump 11

Injects Liquid Poison, if directed

Recognizes/reports trip of Liquid Poison pumps

INSTRUCTOR ACTIONS/

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

Verifies a CRD Pump running

Places Reactor Mode Switch in REFUEL

Places ARI OVERRIDE switch in OVERRIDE

Installs RPS jumpers (5, 6, 12, 13)

Resets the scram

Inserts rods to 00 using EMER ROD IN starting with high power regions of core (use LPRM indications)

CT-2

If more drive pressure is required, then perform one or more of the following:

Fully open CRD Flow Control Valve (F panel)

Close 44-04, Control Rod Drive Water Cont V (F Panel)

Close 44-167, Charging Water Header Blocking Valve (RB 237')

Possible N1-EOP-3.1 Section 4 Actions:

Places ARI OVERRIDE switch in OVERRIDE

Installs RPS jumpers (5, 6, 12, 13)

Resets the scram

Verify open 44-167, Charging Water Header Blocking Valve (RB 237')

When the SDV is drained, then initiate a manual scram

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

Manually initiates ARI

Bypasses ADS

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

CT-1

Closes both Feedwater Isolation Valves 11 and 12 OR places Feedwater pumps 11 and 12 in PTL

Selects Manual on 11, 12 and 13 FWP Valve Control selector switches

Closes 11, 12 and 13 Feedwater FCV (Knurled Knob) full counterclockwise Role Play:

Places FW LVL SETPOINT When directed to pull HPCI fuses, wait one minute, SETDOWN to OVERRI DE then insert remote:

Directs operator to remove fuses FW24, REMOVAL OF HPCI FUSES FU8/FU9, FU-8 and FU-9 from Panel IS34 in FV=pulled the Aux Control Room TRG24

Verifies closed, FEEDWATER Then report task completion.

PUMP 13 BLOCKING VALVE

Verifies in MAN, FWP 11 BYPASS VALVE, AND set to zero output

Verifies in MAN, FWP 12 BYPASS VALVE, AND set to zero output

May re-open Feedwater Isolation Valve

Informs SRO when RPV water level reaches -41 inches

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

If any ERV is cycling:

Initiates Emergency Condensers

Manually opens ERVs to lower RPV pressure <965 psig

Controls RPV pressure below 1080 psig with Turbine Bypass Valves, Emergency Condensers and ERVs

Closes MSIVs, as directed

Initiates ARI

Verifies all Recirc pumps tripped CT-1

Initiates Liquid Poison as directed

Reports initial tank level

Attempts to start Liquid Poison pump 11 and/or 12

Determines/reports Liquid Poison pump(s) trip

Acknowledges direction to re-establish RPV injection with Condensate/Feedwater and CRD

Re-injects with Condensate/Feedwater per N1-EOP-1 Att 24:

Reopens at least one Feedwater Isolation Valve 11 and I or 12, if closed

Controls injection with Feedwater flow control valves Terminating Cues:

RPV water level controlled in assigned band

RPV pressure controlled in assigned band

Control rod insertion in progress or complete

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

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

SUMMARY

Length: 75 minutes Initial Power Level: Approximately 5%

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

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

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

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

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

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

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

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

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

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

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

1. Malfunctions:

a. ED02A, 115 kV Line 1 (South Oswego) Loss of Offsite Power TRG 2

b. MC01, MAIN CONDENSER AIR INLEAKAGE, FV=18 TRG 3

c. ED01A, 115 kV Line 4 (JAF) Loss of Offsite Power, Delay=1 :30 TRG 4

d. DG04A, DG 102 FAILURE TO AUTO START PRESET

e. EC04A, EC RETURN VALVE FAILS TO OPEN(IV 39-05) PRESET

f. EC04B, EC RETURN VALVE FAILS TO OPEN(IV 39-06) PRESET

g. EC03A, EC RETURN VALVE FAILS OPEN(IV 39-05) TRG 17

h. EC03B, EC RETURN VALVE FAILS OPEN(IV 39-06) TRG 18

i. RR29, RR Loop Rupture on Pump 15 Suction Line (LOCA), FV=17 TRG 5

j. CS06, CS Pumps Failure to Auto Start PRESET

2. Remotes:

a. RP21, RPS UPS 162 TROUBLE ANN RESET, FV=reset TRG 28

b. RP22, RPS UPS 172 TROUBLE ANN RESET, FV=reset, DT=10 TRG 28

c. ED40A, I&C Bus 130 NC Supply Breaker from PB 13B, FV=open TRG 29

d. ED40B, I&C Bus 130 NO Supply Breaker from PB 167A, FV=close, DT=5 TRG 29

e. FP04, FIRE WTR TO FW BLOCKING VLVS, FV=100 TRG 21

f. CT03A, CT Raw Water Pump 111 Disch. Throttle Valve 93-14, FV=10 TRG 22

g. FW25 , MANUAL OPER. FW FCV-11, FV=O TRG 23

h. FW26 , MANUAL OPER. FW FCV-12, FV=O TRG 24

i. FW27 , MANUAL OPER. FW FCV-13, FV=O TRG 25

3. Overrides:

a. None

4. Annunciators:

a. None

5. Triggers:

a. TRG 4 - Causes loss of Line 4 after the Mode Switch is taken to shutdown

i. Event Action: zdrpstdn==1 ii. Command: None

b. TRG 5 - Causes the LOCA to begin when Powerboard 16 is crosstied

i. Event Action: zded602c==1 ii. Command: None

c. TRG 10- Makes Condenser vacuum degrade faster once the Turbine is tripped

i. Event Action: tc:trip==1 ii. Command: imf mc01 (0 0) 50 C. Equipment Out of Service

1. Steam Packing Exhauster 12 green-flagged with yellow tag.

D. Support Documentation

1. N1-0P-43A marked up to appropriate point for startup.

2. Startup control rod sequence marked up to current rod (06-31 from 04 to 08).

E. Miscellaneous

1. None

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

Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE)

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

Shift Manager Log (SM, CRS, STA)

Shift Turnover Checklist (ALL)

RO Log (RO)

LCO Status (SM, CRS, STA)

Lit Control Room Annunciators

Computer Alarm Summary (RO)

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

Reactor power is approximately 5% with a startup in progress.

Steam Packing Exhauster 12 is caution tagged due to high vibrations.

PART III: Remarks/Planned Evolutions:

1. Withdraw control rods per the startup sequence. The next control rod to be moved is 06-31 from 04 to 08. Use notch control rod withdrawal. Withdraw the first four rods in the current group, then perform next planned evolution.

2. Place the Mode Switch in RUN per N1-0P-43A steps 4.4 through 4.7.

3. Withdraw the IRMs per N1-0P-43A step 4.10.

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

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

Review new Clearances (SM)

Test Control Annunciators (CRE)

Shift Crew Composition (SM/CRS)

TITLE NAME TITLE NAME SRO ATCRO BOPRO

Critical Tasks:

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Raise Reactor Power with Control Rods SRO

Directs A TC to withdraw rods per Startup Rod Sequence and N 1-0P-5 section F.1.0

Provides oversight for reactivity manipulation ATC

Withdraws control rods per the rod sequence sheet

Verifies Control Rod Power is On

Depresses Rod Select pushbutton for control rod

Places 4S 1 Control Rod Movement switch to the rod out notch position o Observes SRM and period response o Observes RMCS, RPIS and CRD indications

Informs SRO when the first four rods of the current control rod group are withdrawn BOP

Monitors plant parameters

INSTRUCTOR ACTIONS!

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

Acknowledges first four rods of the current control rod group are withdrawn

Directs placing Mode Switch in RUN and withdrawing IRMs per N1-0P-43A

Provides oversight for evolution ATC

Monitors plant parameters BOP

Acknowledges direction from the SRO

Confirms APRMs indicate greater than 5% power AND confirm APRM downscale alarms clear, E panel

Confirm the following annunciators clear - F1-4-? and F4-4-2

Place Mode Switch to RUN

Confirm Computer Point COS?, MODE SWITCH RUN - YES

Confirm annunciator F3-4-S, RPS REACTOR PRESS LOW BY-PASS clear

Transfer recorder indication to APRM channels

Depress the FULL OUT button for each IRM

WHEN the IRM detectors indicate full out, THEN range down the individual IRM Range switches to Range 2 OR UNTI L the respective IRM Downscale AND Upscale lights are out on E Console

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 - Loss of Line 1 CREW When directed by lead examiner, insert

Recognize/report loss of Line 1 malfunction:

ED02A, 115 kV Line 1 (South Oswego) Loss of Offsite Power TRG2 Breaker R10 opens Expected Annunciators:

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

Acknowledges reports

Directs execution of ARPs

Reviews Technical Specification 3.6.3

Determines Line 1 is inoperable

Determines a 7 day LCO applies per Technical Specification 3.6.3.b ATC

Monitors plant parameters BOP

Executes ARPs

Dispatches an operator to the Aux.

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

Role Play: o 1D1 OSWEGO NINE MILE POINT If dispatched to Auxiliary Control Room, wait 2 1 minutes, then report an undervoltage target is in on o 1D2 115 KV RESERVE BUS &

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

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP continued

Observes 86TN relay on Panel 8A to see if it has tripped

Observes back of Panel 88 in the Control Room for flags AND targets

Records time of trip AND targets

Performs N1-0P-33A Section H., Loss 115 kV Line 1:

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

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

INSTRUCTOR ACTIONS!

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

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

Acknowledge/report annunciators:

FV=18

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

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

Acknowledges reports

Directs execution of N1-S0P-25.1, Unplanned Loss of Condenser Vacuum

Determines condenser vacuum can NOT be maintained above 22.1" Hgv

Directs Turbine trip

Determines condenser vacuum can NOT be maintained above 10" Hgv

Directs a Reactor Scram

Acknowledges scram report

Directs entry into N1-S0P-1, Reactor Scram Note:

Directs Reactor water level controlled Initial Reactor pressure control may be on the 53-95" with Condensate, Feedwater, Turbine Bypass Valves, but will transition soon and CRD after the scram to the Emergency Condensers as

Directs Reactor pressure controlled Main Condenser vacuum degrades.

800-1000 psig with Emergency Condensers

When vacuum approaches 10" Hgv, directs trip of Vacuum Trip 2 Note:

When vacuum approaches 7.0" Hgv, May close MSIVs earlier to control cooldown rate.

directs closing the MSIVs

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Event 4 continued ATC

Monitors plant parameters

Assists BOP with Turbine trip

Places Reactor Mode Switch to SHUTDOWN

Provides scram report

Performs scram verification actions of N1-S0P-1, Reactor Scram:

Confirms all rods inserted

Observes Reactor power lowering

Places IRMs on range 9

Inserts IRM and SRM detectors Note:

Down-ranges IRMs as necessary Initial Reactor pressure control may be on the

Verifies main turbine and generator Turbine Bypass Valves, but will transition soon tripped after the scram to the Emergency Condensers as

Controls RPV pressure as directed Main Condenser vacuum degrades.

using Emergency Condensers BOP

Executes N1-S0P-2S.1, Unplanned Loss of Condenser Vacuum

Verifies proper operation of the following:

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

Dispatches operator to check for condenser leakage

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 4 continued BOP continued

Coordinates with A TC to trip Turbine:

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

FV=50 o Depresses UNIT EMERGENCY Main Condenser vacuum lowers quicker TRIP pushbutton AND executes N 1-S0P-31.1, Turbine Trip o Releases FEEDWATER RETURN TO NORMAL AFTER HPCI CH 11 and 12 push buttons

Enters N1-S0P-1

Controls Reactor water level 53-95" using Condensate, Feedwater, and CRD

When directed, trips Vacuum Trip 2 and verifies Turbine Bypass Valves closed

When directed, closes MSIVs

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 5 & 6 - Loss of Line 4 and EDG 102 Fails CREW to Auto-Start

Recognize/report loss of Line 4 Verify the following malfunction automatically

Recognize/report start of EDG 103 inserts when the Mode Switch is taken to

Recognize/report failure of EDG 102 SHUTDOWN: to auto-start ED01A, 115 kV Line 4 (JAF) Loss of Offsite Power, Delay=1 :30 TRG4 Breaker R40 opens Control Room lights go out Emergency Diesel Generator 103 starts Power is lost to the following major loads:

Recirc pumps

Condensate and Feedwater pumps

Circulating Water pumps

Service Water pumps Expected Annunciators:

A8-1-3, 115 KV. BUS LOW VOL TAGE A8-1-7, NMP - FITZ 4 R40 TRIP A8-1-8, NMP - FITZ 4 LINE RELAY TRIP Verify the following malfunction is preset: SRO DG04A, DG 102 FAILURE TO AUTO START

Acknowledges reports from the crew Emergency Diesel Generator 102 fails to auto-start

Directs execution of N 1-S0P-33A 1

Directs start of EDG 102

Directs Reactor water level controlled 53-95" using CRD

Enters N1-EOP-5, Secondary Containment Control, on low Reactor Building D/P

Exits N1-EOP-5 when Reactor Building D/P is restored

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP

Executes N1-S0P-33A.1 Note:

May dispatch operator to field to The crew may perform an alternate leg of N1-S0P investigate EDG 102 failure 33A. 1 if they wait for a field report before starting

Manually starts EDG 102 EDG 102. The crew will perform the scripted leg to

Verifies start of both Emergency N 1-S0P-33A.1 once EDG 102 is started. Diesel Generators AND confirms the following has occurred:

Role Play: o EDG 102 SUPPLY BKR R-1022 If dispatched to investigate EDG 102 auto-start has closed failure, wait 2 minutes, then report that you see no o Powerboards 102 AND 16B are problems with either EDG 102 or Powerboard 102. energized Report that EDG 102 appears to be in a normal o EDG 103 SUPPLY BKR R-1032 standby condition with no apparent reason for a has closed start failure. o Powerboards 103 AND 17B are energized

Answers "Are PB 11 AND 12 energized?" No

Answers "Is any EDG running?" Yes

Verifies the following:

o PB 16A-B Tie Bkr R-1 042 is tripped o PB 17A-B Tie Bkr R-1052 is tripped o Inst. Air Compo (lAC) 11 and 12 in PTL

Continues at Page 4, Arrow B

Monitors EDG 102 AND 103 KW loading

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP continued Note:

IF EDG KW exceeds 2300 KW (PB The EDG load override in N1-S0P-33A.1 will not 102 or 103 Loading), THEN:

be applicable initially, but may be executed later o Verifies the following:

during the LOCA.

Trips all Containment Spray Raw Water Pumps that are running

R-1042 tripped, PB 16 A-B Tie Bkr

R-1052 tripped, PB 17 A-B Tie Bkr

Verifies Lockouts 86-16 and 86-17 reset

Places CRD Pump 11 AND 12 in PTL

RBCLC Pump 11,12 AND 13 secured

ESW Pump 11 AND 12 secured o Place Core Spray and CSTP 111 OR 112 in PTL o Place Core Spray and CSTP 121 OR 122 in PTL o Operate Containment Sprays as required per N1-EOP-4 o Equalize Containment Spray Raw Water Pump KW load (-450 KW) as required AND continue at next Role Play: step When dispatched for load reductions, wait 4

WHILE continuing, sends operator to minutes, then report Attachment 2, Section 1 load perform load reductions of Attachment reductions are complete. 2, Section 1

Verifies Lockouts 86-16 AND 86-17 reset

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP continued

Verifies RBClC Pump 13 started, if available

Verifies RBClC Pump 12 started, if required Role Play:

Starts ESW PUMP 11 AND 12 AND When dispatched to check UPS 162 and 172, wait monitors equipment temperature listed two minutes, then insert remotes: in N1-S0P-18.1, Tables 18.1 and 18.2

Verifies the following:

RP21, RPS UPS 162 TROUBLE ANN RESET, o CRD Pumps 11 AND 12 started, if FV=reset required, UNLESS secured per RP22, RPS UPS 172 TROUBLE ANN RESET, override above FV=reset, DT=10 o MG Set 167 transfers back to AC TRG28 drive Then report that UPS 162 and 172 have o UPS 162 AND 172 re-energizes transferred back to AC input and you have reset o SBC 161 AND 171 re-energizes alarms.

Re-establishes Rx Bldg. differential pressure as follows:

o Verifies RB Supply AND Exhaust Role Play: Fans tripped When dispatched to restore power to I&C Bus 130, o Closes RB Supply AND Exhaust wait two minutes, then insert remotes: Isolation Valves o Verifies RBEV Train 12 initiated, ED40A, IC Bus 130 NC Supply Breaker From PB secures RBEV Train 11 13B,FV=open

Dispatches operator to restore power ED40B, IC Bus 130 NO Supply Breaker From PB to I&C Bus 130 167A, DT=5, FV=close

Places FEEDWATER PUMP 11 AND TRG 29 12 in PTl Then report that I&C Bus 130 is re-energized from

Verifies RBClC Pump 12 in PTl the maintenance supply.

Verifies ESW Pump 12 in PTl

Verifies lAC 11 in PTl

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 5 & 6 continued ATC/BOP continued

Verifies one CRD Pump running as follows UNLESS secured per override above o CRD Pump 12 running o CRD Pump 11 in PTL

Verifies load reductions of Attachment 2 Section 1 complete

Restores power to PB 16A as follows:

o Trips R-1041, PB 16A Supply Bkr o Closes R-1042, PB 16A-B Tie Bkr

Verifies RBCLC Pumps 11 OR 13 running

IF TSC Power is required, AND PB 16B load is less than 900 amps, THEN Places in ON, NDS-1 disconnect switch (TSC Emergency Power)

Restores power to PB 17A as follows:

o Trips R-1051, PB 17A Supply Bkr o Closes R-1052 PB 17A-B Tie Bkr

Verifies lAC 12 started

Follows N1-0P-6 for recovery of Spent Fuel Pool cooling requirements

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 7. 8 & 9 - Loss of Coolant Accident. CREW Core Spray Fails to Auto-Start, ECs Fail to

Recognize/report degrading Primary Operate from Control Room Containment parameters Verify the following malfunction automatically

Recognize/report lowering Reactor inserts when Powerboard 16 is crosstied: water level and pressure RR29, RR Loop Rupture on Pump 15 Suction Line, FV=17 TRG5 Drywel/leakage, humidity, temperature and pressure rise Reactor water level and pressure lower Expected Annunciators:

H2-4-7, Drywel/ Water Leak Detection Sys K2-4-3, Drywel/ Pressure High-Low F1-1-5, RPS Ch 11 Drywel/ Press High F4-1-4, RPS Ch 12 Drywel/ Press High Verify the following malfunctions are preset: SRO CS06, CS Pumps Failure to Auto Start

Acknowledges reports EC04A, EC RETURN VALVE FAILS TO OPEN(lV

Enters N1-EOP-4 due to high Drywell 39-05) pressure and temperature EC04B, EC RETURN VALVE FAILS TO OPEN(IV

Enters N1-EOP-2 due to high Drywell 39-06) pressure and low Reactor water level Core Spray pumps do NOT auto-start

Directs Containment Spray pumps EC Condensate Return Valves will not open locked out

Acknowledges failure of Core Spray to auto-start

Directs start of Core Spray pumps

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 7, 8, & 9 continued SRO continued

When Torus pressure exceeds 13 psig or Drywell temperature approaches 300°F:

Answers "Below the Containment Spray Initiation Limit?" - Yes

Verifies all Recirc pumps are tripped

Directs trip of all Drywell cooling fans

Directs operation of Containment Spray per N1-EOP 1 attachment 17 CT-1

Evaluates/monitors position on Pressure Suppression Pressure curve

Directs Reactor water level control

-84" to 95" with CRD and Liquid Poison

Transitions to alternate level control leg of N1-EOP-2

Directs ADS bypassed

Directs verification of EC initiation

Acknowledges EC initiation failure

May direct local EC initiation

Answers "Are 2 or more Subsystems available?" - Yes (Both loops of Core Spray available)

Waits until Reactor water level drops to -84"

Answers "Is any Subsystem lined up with a pump running?" - Yes (Both loops of Core Spray running)

Answers "Is any injection source lined up with a pump running?" - Yes

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 7.8. & 9 continued SRO continued

Enters N1-EOP-8, RPV Slowdown:

Answers "Are all control rods inserted to at least position 04?"

Yes

Answers "Drywell pressure?" - At or above 3.5 psig

May direct EC initiation

Answers "Torus water level?"

Above 8.0 ft

Directs open 4 ERVs CT-2

Verifies injection of entire contents of Liquid Poison tank

Directs injection with available systems to restore and maintain Reactor water level above -84 inches CT-3

Directs installation of Core Spray jumpers (N1-EOP-1 attachment 4) to allow control of Core Spray IVs

Transitions back to normal level control leg of N1-EOP-2

Directs restoration of Reactor water level to 53-95" ATC/BOP

Updates crew on Reactor and containment parameters

Locks out Containment Spray pumps

Recognizes/reports failure of Core Spray to auto-start

Starts Core Spray pumps

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 7. 8. & 9 continued ATC/BOP continued

Maximizes RPV injection with CRD and Liquid Poison

When Torus pressure exceeds 13 psig or drywell temperature approaches 300°F:

Verifies all Recirc pump are tripped

Trips all Drywell cooling fans

Initiates Containment Spray per N1-EOP-1 attachment 17:

CT-1

Verifies started two Containment Spray pumps (111 or 122 preferred)

May start additional Containment Spray and Containment Spray Raw Water Role Play: pumps as necessary If directed to open 39-05 in the field, wait 2

Bypasses ADS minutes, then delete malfunction EC04A, then

Verifies EC initiation insert malfunction:

Recognizes/reports failure of 39 EC03A, EC RETURN VALVE FAILS OPEN(IV 39 05 and 39-06 to open 05)

May direct operator to open 39-05 TRG 17 and/or 39-06 in field Then report task completion.

May secure ECs for pressure control Role Play:

When Reactor water level drops below If directed to open 39-05 in the field, wait 2

-84":

minutes, then delete malfunction EC04B, then

May initiates ECs insert malfunction:

Opens 4 ERVs EC03B, EC RETURN VALVE FAILS OPEN(IV 39 CT-2 06)

TRG 18 Then report task completion.

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 7, 8, & 9 continued ATC/BOP continued

Verifies Liquid Poison injection to Role Plays: inject entire contents of Liquid Poison If requested to lineup Firewater to Feedwater, wait tank five minutes, then insert remote:

Injects with available systems to FP04, FIRE WTR TO FW BLOCKING VLVS, restore and maintain Reactor water FV=100 level above -84" TRG21 CT-3 Then report Firewater is lined up to Feedwater.

Bypasses Core Spray IV interlocks per Modify the remote as requested to throttle flow. N1-EOP-1 Att 4 by installing six jumpers (17, 18, 19,24,25,26) inside If requested to throttle Containment Spray Raw PanelN Water 111 discharge valve, wait 3 minutes, then

Throttles Core Spray IVs as necessary insert remote: to control Reactor water level CT03A, CT Raw Water Pump 111 Disch. Throttle

Restores Reactor water level to 53-95" Valve 93-14, FV=10 TRG 22 Then report the valve is 5 turns open. Modify the remote as requested to throttle flow.

If requested to take local manual control of a Feedwater FCV, then wait 5 minutes and insert the appropriate remote:

FW25, MANUAL OPER. FW FCV-11, FV=O TRG23 FW26, MANUAL OPER. FW FCV-12, FV=O TRG24 FW27, MANUAL OPER. FW FCV-i3, FV=O TRG25 Then report the appropriate FCV is pinned and fully closed. Modify the remote as requested to throttle flow.

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Terminating Cues:

RPV Slowdown in progress

Reactor water level controlled above top of active fuel

Containment pressure and temperature controlled in accordance with N1-EOP-4

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

ML13154A270: Difference between revisions

Latest revision as of 04:11, 6 February 2020

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