ML103640349

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Final Operating Exam (Sections a, B, and C) (Folder 3)
ML103640349
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 10/27/2010
From:
Constellation Energy Nuclear Group
To: Todd Fish
Operations Branch I
Hansell S
Shared Package
ML101900599 List:
References
TAC U01790
Download: ML103640349 (203)
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Text

NRC JPM SRO C001 Constellation Energy Group NMP UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Review Daily Checks Log lAW N2-0SP-LOG-D001 Revision: NRC 2010 Task Number: NA Approvals:

NA Exam Security I General Supervisor Date Operations (Designee)

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

Trainer/Evaluator:_ _ _ _ _ _ _ __

Evaluation Method: Perform Evaluation Location: Simulator or Other Designated Location Expected Completion Time: 45 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: Completion Time: _ _ __

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

Comments:

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

NRC 2010 Admin SRO/JPM C001 November 2010

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

Any appropriate location with the required Reference Material.

Simulator Set-up:

None Directions to the Instructor/Evaluator:

To be performed as an administrative JPM.

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Plant Operators.

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used.

Therefore, either another individual or I will act as the additional I concurrent verifier.

Notes to Instructor I Evaluator:

1. Critical steps are identified as Pass/Fail. All steps are sequenced critical unless denoted by a "e".
2. During Evaluated JPM:

e Self-verification shall be demonstrated.

3. During Training JPM:
  • Self-verification shall be demonstrated.
  • No other verification shall be demonstrated.

References:

1. N2-0SP-LOG-D001, Daily Checks Log
2. OD-7 -100% power
3. KIA 2.1.18(3.0) Ability to make accurate, clear and concise logs, records, status boards, and reports.

Tools and Equipment:

1. Calculator Task Standard:

N2-0SP-LOG-D001, Attachment 2 review completed and deSignated errors documented in the Remarks Section of N2-0SP-LOG-D001.

NRC 2010 Admin SRO/~IPM C001 2 November 2010

Initial Conditions:

1. The plant is operating at 100% power.
2. N2-0SP-LOG-0001 for the daily checks log has been completed and submitted for CRS/SM review.
3. Ask the operator for any questions.

Initiating cue:

"(Operator's name), Perform a review of N2-0SP-LOG-0001, Attachment 2 and document results and required compensatory actions, if any, in the Remarks Section on page 11 of N2-0SP-LOG-0001. Attachment reviews for Item #'s 27,30 and 31 will be performed by another operator."

1. Provide repeat back of Proper communications used for Sat/Unsat initiating cue. Evaluator repeat back (GAP-OPS-01)

Acknowledge repeat back providing correction if necessary EVALUATOR to provide copy of N2-0SP-LOG-D001 to candidate for review.

RECORD START TIME _ _

2. .Obtain a copy of the N2-0SP-LOG-0001 obtained. SaUUnsat reference procedure and Attachment 2 referenced.

review/utilize the correct section.

NRC 2010 Admin SROfJPM C001 3 November 2010

Initial Conditions:

1. The plant is operating at 100% power.
2. N2-0SP-LOG-0001 for the daily checks log has been completed and submitted for CRS/SM review.

Initiating Cue:

"(Operator's name), Perform a review of N2-0SP-LOG-0001, Attachment 2 and document results and required compensatory actions, if any, in the Remarks Section on page 11 of N2-0SP-LOG-0001. Attachment reviews for Item #'s 27, 30 and 31 will be performed by another operator."

NRC 201 Admin SRO/JPM C001 6 November 2010

NRC JPM SRO C002 Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE

Title:

SRO Actions for Exceeding CDI Conductivity Action Level 3 Revision: NRC 2010 Task Number: NA Approvals:

NA Exam Security I General Supervi or General Supervisor Date Operations Trai ing (Designee) Operations (Designee)

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

Trainer/Evaluator:_ _ _ _ _ __

Evaluation Method: Perform Evaluation Location: Simulator or Other Designated Area Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: Completion Time: _ _ __

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

Comments:

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

NRC 2010 Admin SROI..IPM C002 1 November 2010

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

N/A Simulator Set-up:

N/A Directions to the Instructor/Evaluator:

To be performed as an administrative JPM.

Directions to Operators:

Read Before Every JPM Performance:

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used.

Therefore, either another individual or I will act as the additional I concurrent verifier.

Notes to Instructor I Evaluator:

1. Critical steps are identified as Pass/Fail. All steps are sequenced critical unless denoted by
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. GAP-CHE-01 REVISION 14
2. KIA 2.1.25 (4.2), Ability to obtain and interpret station reference materials such as graphs and tables which contain performance data.
3. KIA 2.1.34 (3.5) Ability to maintain the primary and secondary plant chemistry within allowable limits.

Tools and Equipment:

None NRC 2010 Admin SRO/JPM C002 2 November 2010

Task Standard:

Determine plant shutdown and cooldown are required for COl value above Action Level 3 limit.

NRC 2010 Admin SRO/JPM C002 3 November 2010

Initial Conditions:

1. The reactor is operating at 20% power
2. You have just been told by the Chemistry Technician that Condensate Conductivity (COl) is reading 1.221 JJS/cm @ 25C and rising slowly.
3. The source of the conductivity rise is indeterminate.
4. A Biocide chemical addition to the system is ongoing.
5. Ask the operator for any questions.

Initiating cue:

"(Operator's name), determine and direct the applicable action(s), if any, for the given value of COl"

1. Provide repeat back of Proper communications used for Sat/Unsat initiating cue. Evaluator repeat back (GAP-OPS-01)

Acknowledge repeat back providing correction if necessary l

RECORD START TIME

2. .Obtain a copy of the GAP-CHE-01 is obtained and SaUUnsat reference procedure and Enclosure 2 is referenced.

review/utilize the correct section.

3. .Determines Action Level Using the supplied value of COl and Pass/Fail 3 has been exceeded. Enclosure 2;
  • Determines that the given value of COl is above Action Level 3 (~1.0 IJS/cm).
4. -Enters Section 3.2.3 of Notifies the following personnel that Pass/Fail GAP-CHE-01. COl has exceeded Action Level 3; NRC 2010 Admin SRO/JPM C002 4 November 2010

Performance SteDs Standard Grade Comments

  • General Supervisor Chemistry
  • Operations Manager
  • Plant General Manager
  • Vessel & Internals Program Mitigation Engineer
5. -Initiates an orderly Initiate an orderly shutdown as Pass/Fail shutdown. quickly as plant constraints permit.
6. .Initiates a cooldown to Initiate a cooldown to <200F as Pass/Fail

<200F quickly as plant constraints permit.

NOTE: May also identify that a PORC review of corrective actions is performed prior to any restart.

TERMINATING CUE:. Determine plant shutdown and cooldown are required for COl value above Action Level 3 RECORD STOP TIME_ _ __

NRC 2010 Admin SRO/JPM C002 5 November 2010

Initial Conditions:

1. The reactor is operating at 20% power
2. You have just been told by the Chemistry Technician that Condensate Conductivity (COl) is reading 1.221IJS/cm @ 25C and rising slowly.
3. The source of the conductivity rise is indeterminate.
4. A Biocide chemical addition to the system is ongoing.

Initiating Cue:

"(Operator's name), determine and direct the applicable action(s), if any, for the given value of COl" NRC 2010 Admin SRO/JPM C002 6 November 2010

SRO Admin JPM EC Constellation Energy Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Review and Approval of Completed Surveillance Test, Revision: NRC 2010 N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test.

Task Number: NA Approvals:

NA Exam Security I Date General Supervisor Date Operations (Designee)

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

Trainer/Evaluator:_____________

Evaluation Method: L Perform ___Simulate Evaluation Location: _Plant ~Simulator Expected Completion Time: 25 min. Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: Completion Time: _ _ __

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

Comments:

Evaluators Signature: ______________ Date:_ _ _ _ __

NRC 2010 Admin SRO/JPM EC 1 November 2010

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

Simulator Simulator Set-up (if required):

None Directions to the Instructor/Evaluator:

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

Operability, operational status, or the effects are unknown, obtain specific SM / CRO permission.

Directions to Operators:

Read Before Every JPM Performance:

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

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas as 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.
  • No other verification shall be demonstrated.

References:

1. N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test
2. NUREG KIA General Knowledges and Abilities 2.2.12 (4.1)

NRC 2010 Admin SRO/JPM EC 2 November 2010

Tools and Equipment:

1. Copy of N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test, completed through Step 10.1 Task Standard:

Given a copy of N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test, the candidate will review the results, identify the discrepancies, and record the results in sections 10.1 and 10.2.

NRC 2010 Admin SRO/JPM EC 3 November 2010

Initial Conditions:

1. The Plant is operating at 100% power.
2. N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test, has just been completed.

Initiating Cues:

"(Operator's name), this is a copy of N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test. Review the test results and complete Section 10.1 and 10.2."

Performance Steps Standard Grade

1. Provide repeat back of initiating cue. Proper communications used for repeat SatlUnsat Evaluator Acknowledge repeat back back (GAP-OPS-011) providing correction if necessary RECORD START TIME _ _ __
2. Review/utilize the correct section of the Reviews General Test Methods, SatlUnsat procedure. References/Commitments and the Precaution and Limitation Sections.

Evaluator is to provide the marked up copy of N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test, to the candidate.

3. Determines status of the completed Reviews N2-0SP-CPS-Q001, Primary SatlUnsat surveillance. Containment Purge System Valve Operability Test and identifies the following in the remarks section:
1. At Step 8.1.3 - the incorrect closing Pass/Fail time was entered. The initial stroke time of 3.5 seconds should have been entered.

NOTE: May inform examiner verbally of lAW precaution and limitation 6.2.1.

issues The initial stroke time is noted in the remarks section 10.2 (1. - 3.5 seconds)

2. At step 8.5.8, the closing stroke time Pass/Fail exceeds the TS limit and the SAT block is checked. The UNSAT block should be checked.
3. The valve at Step 8.5.8 was stroked a SatlUnsat second time which is not permitted per P&L 6.2.2.

NRC 2010 Admin SRO/JPM EC 4 November 2010

Performance Steps Standard Grade

4. TS 3.6.1.3.A.1 must be entered - for Pass/Fail valve at step 8.5.8. - Isolate the affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

There is an additional TS action to verify the isolated penetration every 31 days however that is NOT Critical.

The ONLY part of this step that is critical is the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> action.

4. Notify appropriate Plant Management. Notifies EXAMINER/Ops MGR or SatlUnsat designee of issues identified.

CUE: Acknowledge the information presented.

Terminating Cue: Determination of the status of this surveillance has been made.

RECORD STOP TIME _ _ __

NRC 2010 Admin SRO/JPM EC 5 November 2010

Initial Conditions:

1. The Plant is operating at 100% power.
2. N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test, has just been completed through Section 10.1.

Initiating Cues:

"(Operator's name), this is a copy of N2-0SP-CPS-Q001, Primary Containment Purge System Valve Operability Test. Review the test results and complete Section 10.1 and 10.2."

NRC 2010 Admin SRO/JPM EC 6 November 2010

NRC JPM SRO RC Constellation Energy Nuclear Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Generate and approve an Emergency Exposure Authorization Revision: NRC 2010 Task Number: N/A Approvals:

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

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

Trainer/Evaluator:_ _ _ _ _ __

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

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

Comments:

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

NRC 2010 SRO ADMIN JPM RC November 2010

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

Read Before Every JPM Performance:

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor I Evaluator:

1. Critical steps are identified as Pass/Fail.
2. During evaluated JPM:
  • Self-verification shall be demonstrated.
3. During training JPM:
  • Self-verification shall be demonstrated.
  • No other verification shall be demonstrated.

References:

1. NUREG 1123, 2.3.4, SRO 3.7
2. EPIP-EPP-15 Tools and Equipment:
1. Calculator Task Standard: Generate and approve an Emergency Exposure Authorization Form and estimate exposure.

NRC 2010 SRO ADIVIIN JPM RC November 2010

Initial Conditions:

1. A Site Area Emergency is in progress.
2. You have assumed the responsibilities of the Shift Manager/Emergency Director.
3. A RCIC steam leak into the Reactor Building cannot be isolated without manually shutting ICS*MOV121.
4. Entry to the Reactor Building is required to manually close valve ICS*MOV121 to stop a release to the environment.
5. Time to complete the task for an experienced Licensed Reactor Operator will be approximately 24 minutes.
6. Time to complete the task for a new Licensed Reactor Operator will be approximately 30 minutes.
7. Radiation levels at the valve are approximately 15 Rlhr.
8. Four (4) individuals are available to perform the task:
  • Worker A is a volunteer who is an experienced Licensed Reactor Operator, has previously received a planned special exposure at another facility, and has received a dose of 150 mR this year (TLO Badge No. 11111, SSN 111-11-1111).
  • Worker B is a volunteer who is an experienced Licensed Reactor Operator and is a declared pregnant worker and has received a dose of 15 mR this year (TLO Badge No. 22222, SSN 222-22-2222).
  • Worker C is a volunteer who is an experienced Licensed Reactor Operator and has received a dose of 1800 mR this year (TLO Badge No. 33333, SSN 333-33-3333).
  • Worker 0 is a volunteer who is a new Licensed Reactor Operator that has received a dose of 500 mR this year (TLO Badge No. 44444, SSN 444-44-4444).
9. Ask the operator for any questions.

Initiating Cue:

"(Operator's name), choose an individual to close valve ICS*MOV121, state the reason why that worker was chosen, estimate the expected radiation exposure and document your authorization for an Emergency Exposure."

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

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

2. Obtain a copy of the reference (J EPIP-EPP-15 is obtained and SatlUnsat procedure and review/utilize the correct Attachments 1 and 1-1 are referenced section.
3. Determine the expected exposure for o For an experienced worker SatlUnsat the task Calculates that a 24 minute exposure in a 15 Rlhr field will cause a dose of 6R For a new worker - Calculates that a 30 minute exposure in a 15 Rlhr field will cause a dose of 7.5 R NRC 2010 SRO ADMIN JPM RC -3 November 2010

I Performance Steps I Standard I Grade

4. Select the best worker to perform the o Determines the best worker for the task task:

Note: The following rationale supports

  • Does NOT select Worker A Pass/Fail worker selection:
  • Does NOT select Worker B Pass/Fail
  • Worker A should NOT be chosen due to previously receiving a
  • Selects Worker C Pass/Fail planned special exposure
  • Worker B should NOT be chosen
  • Does NOT select Worker D Pass/Fail due to being a declared pregnant worker
  • Worker C should be chosen because both their dose for the emergency exposure (6 R) will be less than that for Worker 0; additionally, the dose to the public will be minimized by the shorter task completion time of this experienced worker
  • Worker D should NOT be chosen because their dose for the emergency exposure (7.5 R) will be greater than that for Worker C
5. State reason for choosing the selected  :::J States that Worker C was chosen to Sat/Unsat worker minimize dose.

0 States that Worker A was NOT Sat/Unsat chosen due to a previous planned special exposure.

Sat/Unsat 0 States that Worker B was NOT chosen due to being a declared pregnant worker. Sat/Unsat 0 States that Worker D was NOT chosen due to higher dose.

6. Estimate expected exposure 0 Determines Worker C will receive an Sat/Unsat estimated 6 R while completing the task (24 minutes x 15 Rlhr I 60 min/hr)

Role Play: The Candidate may choose to brief the worker on radiological conditions, potential for steam leakage in the area, planned task, applicable ALARA measures, and contingency measures.

NRC 2010 SRO ADIVIIN JPM RC ~4~ November 2010

Role Play: As Worker C acknowledge the briefing.

Role Play: The Candidate may ask for an RWP to be generated. Role playas RP and state that an RWP has been generated.

7. Generate an Emergency Exposure
  • Candidate obtains a copy of EPIP Pass/Fail Authorization form EPP-15 Attachment 1-1
  • Candidate completes Section A (see attached key)

TERMINATING CUE: Emergency Exposure Authorization Form has been completed.

RECORD STOP TIME_ _ __

NRC 2010 SRO ADMIN JPM RC November 2010

Initial Conditions:

1. A Site Area Emergency is in progress.
2. You have assumed the responsibilities of the Shift Manager/Emergency Director.
3. A RCIC steam leak into the Reactor Building cannot be isolated without manually shutting ICS*MOV121.
4. Entry to the Reactor Building is required to manually close valve ICS*MOV121 to stop a release to the environment.
5. Time to complete the task for an experienced Licensed Reactor Operator will be approximately 24 minutes.
6. Time to complete the task for a new Licensed Reactor Operator will be approximately 30 minutes.
7. Radiation levels at the valve are approximately 15 R/hr.
8. Four (4) individuals are available to perform the task:
  • Worker A is a volunteer who is an experienced Licensed Reactor Operator, has previously received a planned special exposure at another facility, and has received a dose of 150 mR this year (TLD Badge No.

11111, SSN 111-11-1111).

  • Worker B is a volunteer who is an experienced Licensed Reactor Operator, is a declared pregnant worker and has received a dose of 15 mR this year (TLD Badge No. 22222, SSN 222-22-2222).
  • Worker C is a volunteer who is an experienced Licensed Reactor Operator and has received a dose of 1800 mR this year (TLD Badge No.

33333, SSN 333-33-3333).

  • Worker D is a volunteer who is a new Licensed Reactor Operator that has received a dose of 500 mR this year (TLD Badge No. 44444, SSN 444 44-4444).

Initiating Cue:

U(Operator's name), choose an individual to close valve ICS*MOV121, state the reason why that worker was chosen, estimate the expected radiation exposure and document your authorization for an Emergency Exposure."

NRC 2010 SRO ADMIN JPM RC November 2010

NRC SRO ADMIN JPM EP Constellation Energy Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Event Classification and Notifications Revision: NRC 2010 Task Number: N/A Approvals:

NA Exam Security I General Supervisor Date Operations (Designee)

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

Trainer/Evaluator:_ _ _ __

Evaluation Method: Perform Evaluation Location: Simulator or Other Designated Area Expected Completion Time: 25 min. Time Critical Task: Yes Alternate Path Task: No Start Time: _ _ __ Stop Time: Completion Time: _ _ __

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

Comments:

Evaluator Signature: _______________ Date:_ _ _ _ __

NRC SRO ADMIN JPM EP November 2010

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

Classroom or Simulator. Ensure sufficient copies of SM/ED Checklist Package are available Simulator Set-up:

None Directions to the Instructor/Evaluator:

To be performed as an administrative JPM. Ideally this JPM should be performed in the Control Room or Simulator to provide adequate procedural resources. If this JPM cannot be performed in one of these locations, then the complete SM/ED Checklist Package must be provided to the Candidate.

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the Unit 1 SM, Security Supervisor, Communication Aid, and other personnel as necessary. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

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

Read Before Each Evaluated JPM Performance:

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

concurrent verification will not be provided; therefore it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used.

Therefore, either another individual or I will act as the additional/ concurrent verifier.

Notes to Instructor / Evaluator:

1. Critical steps are identified as 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.
  • No other verification shall be demonstrated.

References:

1. EPIP-EPP-02, Classification Of Emergency Conditions at Unit 2
2. EPIP-EPP-18, Attachment 1 SM/ED Checklist
3. EPIP-EPP-20, Emergency Notifications
4. KIA 2.4.29(4.0), Knowledge of the Emergency Plan.

NRC SRO ADMIN JPM EP November 2010

Tools and Equipment:

1.0 EPIP-EPP-02, ATTACHMENT 2, UNIT 2 EAL FLOWCHART 2.0 SM/ED Checklist Package Task Standard:

Classify the event within 15 minutes of the time that indications are available in the Control Room that an EAL has been exceeded and make all appropriate notifications within 15 minutes of the time the event is classified.

Initial Conditions:

1. You are the Shift Manager at NMP2. The STA is unavailable.
2. Unit 2 had been operating at 100% power.
3. Unit 1 is operating at full power.
4. The following conditions exist:
  • Rising drywell pressure caused the crew to insert a manual scram
  • MODE Switch failed to trip RPS, (Five) 5 minutes ago.
  • LOCA occurred causing loss of RPV level instrumentation.
  • Reserve Transformer "Au has faulted and is lost
  • No Release is in progress or anticipated Initiating Cue:

"(Operator's name), Based on the above conditions determine the event classifications per EPIP-EPP-02 and complete steps 1 through 9.a of EPIP-EPP-18, Attachment 1, SM/ED Checklist".

This is a time critical activity.

Meteorological Data

! Wind Speed (30 ft) 5 mph I Wind Direction (30 ft) 600 I *:i Wind Speed (200 ft) 10 mph I Wind Direction (200 ft) 600 I

Stability Class

Performance Steps I Standard I Grade

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

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

2. Obtain a copy of EPIP-EPP-01 EPIP-EPP-01 attachment 1 and Shift SatlUnsat attachment 1 and Shift Manager Manager emergency paperwork is emergency paperwork and review/utilize obtained the correct section
3. Enters EPIP-EPP-18, Attachment 1, Completes steps 1 thru g.a. of EPIP-EPP SatlUnsat SM/ED Checklist and completes Steps 1 18, as described in subsequent JPM steps through g.a
4. Classifies and declares the emergency Declares a Site Area Emergency within Pass/Fail fifteen minutes of the JPM initial condition Cue: If candidate asks how long it has sheet being accepted in accordance with been since Reserve Transformer A EAL 2.1.2 was de-energized, report 15 minutes.

EXAMINER NOTE: Time difference below must be 15 minutes or less:

JPM start time: _ _ __

Time of Declaration: _ _ _ __

5. Completes EPIP-EPP-18 attachment 1, Completes Attachment as shown in KEY SatlUnsat figure 1 flowchart to determine evacuation and accountability requirements Note: Evacuation determination is subjective and mayor may not be performed. This will determine which path is taken on EPI P-EPP-18 Attachment 1 and which steps are completed on EPIP-EPP-18 Attachment 2.
6. Calls the Communications Aides to the Proper communications used (GAP-OPS SatlUnsat Control Rooms 01)

Role Play: Acknowledge communication NRC SRO ADMIN JPM EP -4 November 2010

I Performance Steps I Standard I Grade

7. Fills out the ERO Notification System Completes Attachment as shown in KEY SatiUnsat (ERONS) form J. Calls Unit 1 SM to inform that ERONS Proper communications used (GAP-OPS SatiUnsat form is coming and to get Unit 1 plant 01) status Role Play: If asked about the status of Unit 1, report that Unit 1 is still operating at 100% power with no issues
9. Completes EPIP-EPP-18 attachment 2, Completes Attachment as shown in KEY SatiUnsat Emergency Announcement
10. Completes EPIP-EPP-20 Part 1 Completes Attachment as shown in KEY Pass/Fail Notification Fact Sheet Part 1 Notification Fact Sheet Steps 3 thru 7 are Critical Steps EXAMINER NOTE: Time difference must be 15 minutes or less:

Time of Declaration (from JPM step 4):

Time EPIP-EPP-20 Part 1 Notification Fact Sheet is complete:

TERMINATING CUE: Part 1 Notification Fact Sheet completed.

RECORD STOP TIME _ _ __

NRC SRO ADMIN JPM EP November 2010

Initial Conditions:

1. You are the Shift Manager at NMP2. The STA is unavailable.
2. Unit 2 had been operating at 100 % power.
3. Unit 1 is operating at full power.
4. The following conditions exist:
  • Rising drywell pressure caused the crew to insert a manual scram
  • MODE Switch failed to trip RPS, (Five) 5 minutes ago.
  • LOCA occurred causing loss of RPV level instrumentation.
  • Reserve Transformer "A" has faulted and is lost
  • No Release is in progress or anticipated Initiating Cue:

"(Operator's name), Based on the above conditions determine the event classifications per EPIP-EPP-02 and complete steps 1 through g.a of EPIP EPP-18, Attachment 1, SM/ED Checklist".

This is a time critical activity.

Meteorological Data 5m h 10 m h Stability Class D NRC SRO ADMIN JPM EP November 2010

NRC JPM RO C001 Constellation Energy Nuclear Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Verification of Active License Status Revision: NRC 2010 Task Number: N/A Approvals:

NA Exam Security I General Supervisor Date Operations (Designee)

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

Trainer/Evaluator:_ _ _ _ _ _ _ _ _ _ __

Evaluation Method: ---=...X"---_ Perform - - - - - Simulate Evaluation Location: _ _ _ Plant _ _---:....:X'--_ Simulator or Classroom Expected Completion Time: 10 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: Completion Time: _ _ __

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

Comments:

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

NRC 2010 RO ADMIN JPM C001 November 2010

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

Classroom Simulator Set-up:

None Directions to the Instructor/Evaluator:

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

Operability, operational status, or the effects are unknown, obtain specific SM / CRO permission.

Directions to Operators:

Read Before Every JPM Performance:

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

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated ...IPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional/ 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 Pass/Fail.
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.

References:

1. NUREG 1123,2.1.4,3.3
2. S-ODP-TQS-0101 Tools and Equipment:

NRC 2010 RO ADMIN JPM C001 November 2010

None Task Standard: Candidate determines that only RO #1 is qualified to stand the watch using the criteria contained in S-ODP-TQS-0101.

Initial Conditions:

1. The plant is operating at 100% power.
2. Today is January 1, 2011.
3. You are the CRO.
4. You must leave shift.
5. The online Qualification Report is NOT available.
6. Three replacement operators are available.
7. Instructor to ask the operator for any questions.

Initiating cue:

"(Operator's name), using the given information, determine which of the three operators, if any, are qualified to relieve you, in accordance with S-ODP-TQS-0101." Document your findings and the reasons for your findings on the given answer sheet."

Examiner Note: Provide candidate with JPM attachments A and B.

I Performance Steps I Standard Grade

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

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

2. Obtain a copy of S-ODP-TQS-01 01 and 0 S-ODP-TQS-0101 obtained SatlUnsat review/utilize the correct section Note: See attached answer key
3. Reviews RO #1 data and determines o Reviews RO #1 data SatlUnsat eligibility o Determines RO #1 is qualified to Pass/Fail relieve the CRO
4. Reviews RO #2 data and determines o Reviews RO #2 data SatlUnsat eligibility o Determines RO #2 has not performed Pass/Fail enough hours in the past quarter as a licensed operator NRC 2010 RO ADMIN JPM C001 November 2010

I Performance Steps I Standard Grade Cl Determines RO #2 is NOT qualified to relieve the CRO

5. Reviews RO #3 data and determines o Reviews RO #3 data SatiUnsat eligibility Cl Determines RO #3 does not have a Pass/Fail SCBA Fit Test on file from the last year Pass/Fail Cl Determines RO #3 is NOT qualified to relieve the CRO TERMINATING CUE: Candidate determines that only RO #1 is qualified to stand the watch using the criteria contained in S-ODP-TQS-01 01.

RECORD STOP TIME_ _ __

NRC 2010 RO ADMIN JPM C001 November 2010

Initial Conditions:

1. The plant is operating at 100 % power.
2. Today is January 1, 2011.
3. You are the eRO.
4. You must leave shift.
5. The online Qualification Report is NOT available.
6. Three replacement operators are available.

Initiating cue:

"(Operator's name), using the given information, determine which of the three operators, if any, are qualified to relieve you, in accordance with S ODP-TQS-0101. Document your findings and the reasons for your findings on the given answer sheet."

NRC 2010 RO ADMIN JPM C001 November 2010

Attachment A - Data Sheet RO#1 RO#2 RO#3

~ ---------- ----------

10/21/10: 0700 - 1600 11/2/10: 0630 - 1830 10/28/10: 0630 -1830 10/22/10: 0700 - 1600 11/3/10: 0630 - 1830 Hours Performing 10/29/10: 0630 - 1830 10/23/10: 0700 - 1600 11/4/10: 0630 - 1830 Licensed Operator 10/30/10: 0630 - 1830 11/12/10: 0700 -1600 11/5/10: 0630 - 1830 Duties in Last Quarter 11/22/10: 0630 - 1830 11/13/10: 0700 1600 12/24/10: 0630 - 1830 11/23/10: 0630 - 1830 11/14/10: 0700 - 1600 12/25/10: 0630 - 1830 I

---~---

Status of All requirements of NMP All requirements of NMP All requirements of Requalification TR-1.01-102 met TR-1.01-102 met NMP-TR-1.01-102 met Training Date of Last SCBA 2/10/2010 2/312010 8/16/2010 Training Date of Last SCBA Fit 3/14/2010 3/18/2010 12/14/2009 Test Date of Most Recent 8/22/2009 7/12/2009 12/10/2009 NRC Form 396 on File Date of Most Recent Respiratory Physical 7/1/2010 1/27/2010 10/22/2010 on File NRC 2010 RO ADMIN JPM C001 November 2010

Attachment B - Answer Sheet i If No, what requirement is not Qualified for Relief? (Yes/No) being met, in accordance with I S~ODP~TQS~01 01?

RO#1 I

I RO#2 RO#3 NRC 2010 RO ADMIN JPM C001 ~ 7~ November 2010

Attachment C - Answer Key If No, what requirement is not I Qualified for Relief? (Yes/No) being met, in accordance with S-ODP-TQS-01 01?

RO#1 Yes N/A Does not meet the required number of hours performing RO#2 No duties on a licensed operator for the last quarter Does not have an annual RO#3 No SCBA Fit test on file NRC 2010 RO ADMIN ~IPM C001 November 2010

NRC RO ADMIN JPM C002 Constellation Energy Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Determine Core Thermal Power Revision: NRC 2010 Task Number: NA Approvals:

NA Exam Security I General Superv' General Supervisor Date Operations Training (Designee) Operations (Designee)

NA Exam Security I Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _{RO)

Trainer/Evaluator:_ _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: ----'X"-"--_Perform - - -Simulate Evaluation Location: _ _ _Plant ___Simulator X Classroom Expected Completion Time: 15 Min. Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: Completion Time: _ _ __

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

Comments:

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

NRC RO ADMIN JPM C002 November 2010

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

Any appropriate location with the required Reference Material.

Simulator Set-up (if required):

None Directions to the Instructor/Evaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

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

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

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used.

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

Notes to Instructor I Evaluator:

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

U

2. During Evaluated JPM:

e Self verification shall be demonstrated.

3. During Training JPM:
  • Self verification shall be demonstrated.
  • {Additional/Concurrent/No other) verification shall be demonstrated.

NRC RO ADMIN .IPM C002 November 2010 2

References:

1. N2-REP-11, Independent Methods of Determining Core Thermal Power
2. NUREG KIA General Knowledges and Abilities 2.1.19(3.0) 2.1.20(4.3) 2.1.25(2.8)

Tools and Equipment:

1. Calculator
2. 00-3, with % Core Thermal Power = 99.54%

Task Standard:

Core thermal power correctly calculated in accordance with N2-REP-11, Attachment 3.

Candidate determines that the calculated power is not within 2% limit specified in the procedure and notifies SM and RE.

Initial Conditions:

1. The plant has been operating at steady-state power for greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
2. MSR reheat steam is NOT optimized.
3. Turbine bypass valves are closed.
4. SM permission has been granted to perform this procedure.

Initiating Cues:

"(Operator's name), determine core thermal power using turbine first stage pressure in accordance with N2-REP-11. Any steps requiring an Independent Verification will be completed by another operator at the completion of the procedure."

! Performance Steps Standard Grade

1. Provide repeat back of initiating cue. CJ Proper communications used for Sat/Unsat Evaluator Acknowledge repeat back repeat back (GAP-OPS-011) providing correction if necessary.

RECORD START TIME _ _ __

2. Obtain a copy of the reference CJ N2-REP-11 obtained.

procedure and review/utilize the correct

  • Precautions & Limitations Sat/Unsat section of the procedure. reviewed.
  • Attachment 3 referenced.

Evaluator: Provide candidate with a blank copy of N2-REP-11.

NRC RO ADMIN JPM C002 November 2010 3

Performance Steps Standard Grade

3. Complete Preliminaries Section of REP 11 r Attachment 3 for the following:
  • Verifying MSR reheat steam is NOT o Step completed using JPM Initial SatlUnsat optimized. Conditions.
  • Verify reactor is operating in a steady o Step completed using JPM Initial SatlUnsat state condition with core power level Conditions.

constant for the current control rod pattern and core flow.

Note: Candidate may obtain SM o Proper communications used SatlUnsat permission; and/or notify the CRO of procedure performance.

4. Record data on N2-REP-11, Attachment o Data correctly entered on Attachment
3. 3. SatlUnsat Evaluator: Provide candidate a copy of JPM Attachment 1.
5. Obtain Plant Process Computer o Obtains value from JPM Attachment Program OD-3, Option 2 printout. 1. SatlUnsat Evaluator: Provide candidate a copy of JPM Attachment 2.
6. Calculate core thermal power. o Core thermal power calculations Pass/Fail completed as follows:
  • % Core Thermal Power based on computer points = 97.93

[(.12464 X 700) + 12.6794] X (.98

+ .98)/2= 97.929 (97.93)

  • % Core Thermal Power from OD 3 printout = 99.99
7. Indicate if core thermal power values o Determines core thermal power Pass/Fail agree within +/- 2%. values do NOT agree within +/- 2%

(99.99 - 97.93 = 2.06).

NRC RO ADMIN JPM C002 November 2010 4

Performance Steps Standard Grade

8. Immediately notifies SM and Reactor o SM and Reactor Engineering Pass/Fail Engineering Supervisor that Core Supervisor notified that Core Thermal Thermal Power determined using turbine Power determined using turbine first first stage pressure does NOT agree stage pressure does NOT agree within 2%. within 2%.

Terminating Cue: Core thermal power calculated using N2-REP-11, Attachment 3.

RECORD STOP TIME _ _ __

NRC RO ADMIN JPM C002 November 2010 5

Initial Conditions:

1. The plant has been operating at steady-state power for greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
2. MSR reheat steam is NOT optimized
3. Turbine bypass valves are closed.
4. SM permission has been granted to perform this procedure.

Initiating Cues:

"(Operator's name), determine core thermal power using turbine first stage pressure in accordance with N2-REP-11. Any steps requiring an Independent Verification will be completed by another operator at the completion of the procedure."

NRC RO ADMIN JPIVI C002 November 2010 6

JPM Attachment 1 N2-REP-11 Data Sheet Computer Point Value I

Turbine First Stage Pressure 700 pSia i (MSSPA07) i I

FW A Correction Factor (FWSFE1 02) i 0.98  !

. FW B Correction Factor (FWSFE103) 1 0 .98 I

NRC RO ADMIN JPM C002 November 2010 7

JPM Attachment 2 003 - Option 2 00-3 Core Thermal Power and APRM Calibration TODAY 09:50:02 Nine Mile Point 2 GMWE CMWT WT WTSUB WD WT FLAG IREC ROD LIN 1182.52 3466.66 97.09 97.86 30.54 2.00 0 107.53 I I I I I I I I PR RWL OPCM WFW HFW WO OHS CAEQ CAQA 1034.6 185.54 15.44 14.93 400.8 525.4 22.80 .12 .15 1-A 2-B 3-C 4-0 RAP 100.01 100.04 99.99 100.03 AGAP 1.0 1.0 1.0 1.0 I

NRC RO ADMIN JPM C002 November 2010 8

NRCJPM RO EC Constellation Energy Nuclear Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Prepare a Tagout for TBCLCW Pump P1 B Revision: NRC 2010 Task Number: N/A Approvals:

NA Exam Security I General Supervi r:; General Supervisor Date Operations Training (Designee) Operations (Designee)

NA Exam Security I Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _(RO)

Trainer/Evaluator:_ _ _ _ _ _ _ _ _ _ __

Evaluation Method: --=...X.:--_ Perform _ _ _ _ _ Simulate Evaluation Location: _ _ _ Plant _ _--.:...!X'--_ Simulator or Classroom Expected Completion Time: 30 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: Completion Time: _ _ __

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

Comments:

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

NRC 2010 RO ADMIN JPM EC November 2010

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

Classroom Simulator Set-up (if required):

N!A Directions to the Instructor!Evaluator:

Prior to performance of this JPM, obtain SM ! CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec.

Operability, operational status, or the effects are unknown, obtain specific SM ! CRO permission.

Directions to Operators:

Read Before Every JPM Performance:

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

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated J PM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor! Evaluator:

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

References:

1. NUREG 1123,2.2.13, R04.1
2. CNG-OP-1.01-1007
3. P&IDs 14A thru 14F available
4. Electrical Prints - ESK 5CCS01 (02,03), available
5. ELU Electrical Lineup OR EE-1L (available)
6. N2-0P-14 NRC 2010 RO ADMIN JPM EC November 2010

Tools and Equipment: None Task Standard: Identify the isolations required to tag out TBCLCW Pump 2CCS-P1 B for the pump packing replacement.

Initial Conditions:

1. The plant is operating at 100% power.
2. TBCLCW pumps P1A and P1 C are operating.
3. TBCLCW pump P1 B is secured.
4. Maintenance is required to repack 2CCS-P1 B
5. eSOMs is unavailable.
6. Ask the operator for any questions.

Initiating cue:

"(Operator's name), identify the components required to tagout TBCLCW Pump P1 B for the pump packing replacement. Record the required components, tag type, component positions and tagging sequence on the handout provided."

Performance Steps Standard Grade

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

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

2. Obtains a copy of the reference Q CNG-OP-1.01-1007 obtained as SatlUnsatl procedure and reviews/utilizes the necessary NA correct section
3. Obtains and references appropriate Q Obtains and references, as required: SatlUnsat drawings and/or procedures to determine isolations
  • EWOs ESK 5CCS01 (02,03)
  • N2-0P-14
  • ELU-14 or EE-1 L
4. Records required isolations. Q Identifies the following component isolations, tag type, component Note: Due to unavailability of eSOMs and positions and tagging sequence on other electronic databases, exact the handout component IDs, names, and tagging positions may vary.

Examiner Note: The sequence must be Q PMP 1 B CSS-P1 B, TBCLCW Pump SatlUnsat electrical first (control switch, fuses), valve 2CSS-P1B:

isolations second (suction, discharge) and vent and drain third. 1. Control Switch in pull-to-Iock

2. Reference or Danger Tag NRC 2010 RO ADMIN JPM EC -3 November 2010

I Performance Steps Standard Grade The candidate may # them 1, 2, 3, 4, 5, 6 or 3. Sequence #1 or #2 1,1,2,2,3,3 a 2NNS-SWG013-8, 2CCS-P1 B Power Pass/Fail Supply Trip Fuses:

1. Trip Fuses pulled
2. Danger Tag
3. Sequence #1 or #2 AND/OR AND/OR o 2NNS-SWG013-8 Breaker for 2CCS Pass/Fail P1B:
1. Breaker Open & Racked out/handle elevated
2. Danger Tag
3. Sequence #1 or #2 a 2CCSV303B - TBCLC Pump P'I B Pass/Fail Discharge Stop Check Valve:
1. Closed
2. Danger Tag
3. Sequence #3 or #4 o 2CCSV1 B - TBCLC Pump P1 B Pass/Fail Suction Isolation Valve:
1. Closed
2. Danger Tag
3. Sequence #3 or #4 o 2CCSV307B - TBCLC Pump P1 B Pass/Fail Casing Vent Valve:
1. Uncapped and Open
2. Danger Tag
3. Sequence #5 or #6 a 2CCSV6B - TBCLC Pump P1 B Pass/Fail Casing Drain Valve:
1. Uncapped and Open
2. Danger Tag
3. Sequence #5 or #6 NRC 2010 RO ADMIN JPM EC November 2010

Terminating Cue: Isolations for TBCLCW Pump P1 B have been identified and recorded on the handout provided RECORD STOP TIME _ _ __

KEY Component Tag Type Sequence** Component Description Position/Configuration PMP 1B CSS-P1 B, TBCLCW Pump 2CSS- Reference or Danger Sequence #1 or #2 Control Switch in pull P1B: to-lock 2NNS-SWG013-8, Danger Sequence #1 or #2 Trip Fuses pulled 2CCS-P1 B Power Supply Trip Fuses:

AND/OR AND/OR 2NNS-SWG013-8 Danger Breaker Open &

Breaker for 2CCS-P1 B: Racked ouVhandle elevated 2CCSV303B - TBCLC Danger Sequence #3 or #4 Closed Pump P1 B Discharge Stop Check Valve:

2CCSV1 B - TBCLC I Danger Sequence #3 or #4 Closed Pump P1 B Suction Isolation Valve:

I i 2CCSV307B - TBCLC Danger Sequence #5 or #6 Uncapped and Open I Pump P1 B Casing Vent Valve:

I I 2CCSV6B - TBCLC Danger i Sequence #5 or #6 Uncapped and Open Pump P1 B Casing Drain Valve:

    • Examiner Note: The sequence must be electrical first (control switch, fuses, breaker), valve isolations second (suction, discharge) and vent and drain third.

The candidate may # them 1, 2, 3, 4, 5, 6 or 1, 1, 2, 2, 3, 3 NRC 2010 RO ADMIN JPM EC November 2010

HANDOUT Component i Tag Type Sequence I Component Description Position/Configuration

1. i  !

I 2.

i

3.  !

I

4. i
5.  !

6.

I

7.  !

8.

i 9.

10 .

! 11 i i

12.

I 13.

14. i i

15.

16.  !

I i I NRC 2010 RO ADMIN JPM EC November 2010

Initial Conditions:

1. The plant is operating at 100% power.
2. TBCLCW pumps P1 A and P1 C are operating.
3. TBCLCW pump P1 B is secured.
4. Maintenance is required to repack 2CCS-P1 B
5. eSOMs is unavailable.

Initiating cue:

U(Operator's name), identify the components required to tagout TBCLCW Pump P1 B for the pump packing replacement. Record the required components, tag type, component positions and tagging sequence on the handout provided."

NRC 2010 RO ADMIN JPM EC November 2010

NRC JPM RO EP Constellation Energy Nuclear Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Perform Actions for External Security Threats Revision: NRC 2010 Task Number: N/A Approvals:

NA Exam Security I General Supervisor General Supervisor Date Operations Training (Designee) Operations (Designee)

NA Exam Security I Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _(RO)

Trainer/Evaluator:_ _ _ _ _ _ _ _ _ _ __

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

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

Comments:

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

NRC 2010 RO ADMIN JPM EP November 2010

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

Simulator Simulator Set-up (if required):

N/A Directions to the Instructor/Evaluator:

Prior to performance of this JPM, obtain SM ! CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec.

Operability, operational status, or the effects are unknown, obtain specific SM ! CRO permission.

Directions to Operators:

Read Before Every JPM Performance:

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

With the exception of accessing panels, NO plant equipment will be physically 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 Pass/Fail.
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.

References:

1. NUREG 1123, 2.4.28, RO 3.2
2. EPIP-EPP-10 Tools and Equipment:

None NRC 2010 RO ADMIN JPM EP November 2010

Task Standard: Perform required actions for an external security threat per EPIP-EPP-10, Attachment 2.

Initial Conditions:

1. The plant is operating at 100% power.
2. You are the CRO.
3. The NRC calls on the ENS line and informs you of the following:
  • NORAD has reported that two US Airways 737 aircraft have been hijacked from Hancock International Airport in Syracuse, New York.
  • One is headed southeast in the direction of the Indian Point site and one is headed north in the direction of the Fitzpatrick and Nine Mile Point site.
  • The event is classified as a credible, probable airborne threat.
4. Instructor to ask the operator for any questions.

Initiating cue:

"(Operator's name), perform actions in response to this security threat in accordance with EPIP EPP-10 attachment 2."

Performance Steps Standard Grade

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

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

2. Obtains a copy of the reference a EPIP-EPP-10 attachment 2 obtained SatlUnsat procedure and reviews/utilizes the correct section Note: Once the candidate locates EPIP EPP-10 attachment 2, the examiner may supply an extra copy to the candidate for use during the remainder of the JPM
3. Notifies Shift Manager of security event a Proper communications used (GAP- Pass/Fail OPS-01)
4. Checks plant parameters o Observes major plant parameters SatlUnsat using control room instrumentation (ex. Reactor power, pressure and level, Containment conditions)

NRC 2010 RO ADMIN JPM EP November 2010

Performance Steps Standard Grade

5. Notifies Security Site Supervisor o Proper communications used (GAP Pass/Fail OPS-01)

Note: Security Site Supervisor may be contacted by Gaitronics page or by calling x5222 or x2591

6. Initiates any Operating, Special 1:1 Proper communications used (GAP* Sat/Unsat Operating or EOPs required OPS-01)

Cue: Inform that other operators are executing the required Operating, Special Operating and Emergency Operating Procedures

7. As directed by Shift Manager, makes 0 Makes plant announcement in announcements accordance with EPIP-EPP-10 attachment 6:

Cue: As Shift Manager, provide EPIP EPP-10 Attachment 6, a. Places GAltronics in Merge Pass/Fail Imminent/Probable Aircraft Attack Announcement (..IPM Handout #1) b. Sounds Evacuation Alarm for 5 Pass/Fail seconds Note: If candidate begins to broadcast c. Announces: Pass/Fail an announcement, Examiner should ask candidate not to Attention All Plant Personnel, this broadcast over the speakers and (is a drill I is an actual emergency) just to the examiner. Aircraft Impact Imminent.

Evacuate the protected area immediately. Report directly to the Learning Center or P-Building. I repeat, this (is a drill I is an actual emergency)

d. Repeats Alarm and Announcement Sat/Unsat
e. Leaves GAltronics in merge Sat/Unsat NRC 2010 RO ADMIN JPM EP -4 November 2010

Performance Steps Standard Grade

8. When Security Contingency Event no o Makes plant announcement in longer exists, makes a termination accordance with EPIP-EPP-18 announcement in accordance with EPIP attachment 7:

EPP-18

a. Sounds Station Alarm for 10 SatlUnsat Cue: As Shift Manager, report that seconds Security Contingency Event no longer exists and provide EPIP-EPP b. Announces: SatlUnsat 18 attachment 7, Emergency Termination Announcement (JPM Attention. Attention all personnel.

Handout #2) The security event at Nine Mile Point Unit 1 and 2 has been NOTE: If candidate begins to broadcast terminated. I repeat, the security an announcement, Examiner event has been terminated should ask candidate not to broadcast over the speakers and c. Repeats alarm and announcement SatlUnsat just to the examiner.

d. Removes GAltronics from merge SatlUnsat Terminating Cue: Emergency Termination Announcement has been made.

RECORD STOP TIME _ _ __

NRC 2010 RO ADMIN JPM EP November 2010

Initial Conditions:

1. The plant is operating at 100% power.
2. You are the CRO.
3. The NRC calls on the ENS line and informs you of the following:
  • NORAD has reported that two US Airways 737 aircraft have been hijacked from Hancock International Airport in Syracuse, New York.
  • One is headed southeast in the direction of the Indian Point site and one is headed north in the direction of the Fitzpatrick and Nine Mile Point site.
  • The event is classified as a credible, probable airborne threat.

Initiating cue:

"(Operator's name), perform actions in response to this security threat in accordance with EPIP-EPP-10 attachment 2."

Note: When making plant announcements, simulate all actions with the GAltronics and provide announcement to the examiner only (i.e. do NOT broadcast over speakers).

NRC 2010 RO ADMIN ~IPM EP November 2010

ATIACHMENTS Date: Today Time: Now IMMINENTfPROBABLE AIRCRAFT ArrACK ANNOUNCEMENT Instructions:

1. Place GAltronics In Merge
2. Sound Evacuation Alarm for 5 Seconds
3. Announce, Attention AU Plant Personnel, this (is a drill IS an actual emergenc Aircraft impact Imminent Evacuate the protecrea area Immediately. Report directly to the Learning Center or P-BUlldi'1G~

i repeat.. this {is a driif is an actual emergengxp

4. Repeat Alarm and Announcement.
5. Leave GAltronics in merge for the duration of the event.
6. Upon completion retum this attachment to the EP Dept.

Page 19 EPIP-EPP-10 Rev 17 NRC 2010 RO ADMIN JPM EP November 2010

ACTIVATION AND DIRECTION OF THE EMERGENCY PLANS EPlp*EPp*18 Revision 01900 Page 190121 Page 1 of 1 Attachment 7, Emergency Termination Announcement Date: Today TIme: Now Emergency Termination Announcement (As requested by the SM/EO or ED/RM)

Instructions:

1. Place GAltronics in Merge
2. Sound Station Alarm for 10 Seconds
3. Announce.
a. "Attention. Attention all personnel.

The security ~mergency condition at Nine Mile Point ).<:2: Unit 1 has been terminated.

);( Unit 2 has been terminated.

b. (Provide further instructions as necessary)
c. Jrepeat, the _ _ _ _s_e_,c_u_r_i_t..::.y_ _ _ _---'0....,~~!Jemergency condition has been terminated.
4. Repeat Alarm and Announcement.
5. Remove GAltronics from merge.
6. Upon completion retum this attachment to the EP Dept. [N0306J NRC 2010 RO ADMIN JPM EP November 2010

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

Title:

Initiate Division I H2I02 Monitoring to Revision: NRC 2010 Monitor Suppression Chamber, Post LOCA Task Number: NA Approvals:

~~~ccr~{~~~~~~~~c=~~~~~n. NA Exam Security I General Superviso General Supervisor Date Operations Training (Designee) Operations (Designee)

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

Trainer/Evaluator:_ _ _ _ _ _ _ _ _ _ __

Evaluation Method: ---,X~_Perform _ _ _ _ _Simulate Evaluation Location: _ _ _Plant _ _--"-'X'--_Simulator Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: Completion Time: _ _ __

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

Comments:

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

NRC 2010 JPM S-1 November 2010

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

Simulator Simulator Set-up (if required):

IC-171 Directions to the Instructor/Evaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.

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

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM 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 as Pass/Fail. All steps are sequenced critical unless denoted by a".".
2. During Evaluated JPM:
  • Self-verification shall be demonstrated.
3. During Training JPM:
  • Self-verification shall be demonstrated.
  • No other verification shall be demonstrated.

NRC 2010 JPM 8-1 November 2010

References:

N2-0P-82, Revision 00601 KIA 223001 A4.04 3.5/3.6, A4.05 3.6/3.6 Tools and Equipment:

Keys Task Standard:

H202 Analyzers ON and sampling from the suppression chamber Initial Conditions:

The plant is shutdown following a LOCA Initiating Cues:

Perform a post LOCA restart of 2CMS*CABi0A per N2-0P-82, Section H.i.0, and using Division I CMS H202 Monitor, sample the Suppression Chamber per Section F.1.0.

i Performance Ste s Standard Grade

1. Provide repeat back of initiating o Proper communications used for SatlUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
2. Obtain a copy of the reference o N2-0P-82 obtained. Precautions & SatlUnsat procedure and review/utilize the Limitations reviewed.

correct section.

3. Obtain SM/CRS permission to o Obtains SM/CRS permission to SatlUnsat restart 2CMS*CAB10A(B) restart 2CMS*CAB 1OA CUE: Give SM/CRS permission when asked.

NRC 2010 JPM 8-1 November 2010

4. PRIOR to overriding the LOCA 0 Prior to overriding the LOCA SatlUnsat isolation signal, notify Radiation isolation signal, notifies Radiation Protection of the intent to restart Protection of the intent to restart 2CMS*CAB10A(B) AND that 2CMS*CAB10A AND that radiological conditions could radiological conditions could change. change.

CUE: As RP, acknowledge.

5. Place the following keylock 0 Places the following keylock PASS/FAIL switches to OVERRIDE: switches to OVERRIDE:
  • ISOL VLV OVERRIDE on
  • ISOL VLV OVERRIDE on 2CEC*PNL873 2CEC*PNL873
  • ISOL VLV OVERRIDE on
  • ISOL VLV OVERRIDE on 2CEC*PNL875 2CEC*PNL875
6. At 2CEC*PNL873, open the 0 OPENS the following valves: PASS/FAIL following valves:
  • 2CMS*SOV60A(B),
  • 2CMS*SOV60A, CONTMT ATM CONTMT ATM MON DW MON DW OUTBD ISOL OUTBD ISOL SUPPLY SUPPLY
  • 2CMS*SOV62A(B) ,
  • 2CMS*SOV62A, CONTMT ATM CONTMT ATM MON DW MON DW OUTBD ISOL OUTBD ISOL RETURN RETURN
7. At 2CEC*PNL875, open the 0 OPENS the following valves: PASS/FAIL following valves
  • 2CMS*SOV61A(B),
  • 2CMS*SOV61A, CONTMT CONTMT ATM MON DW ATM MON DW INBD ISOL INBD ISOL SUPPLY SUPPLY
  • 2CMS*SOV63A(B),
  • 2CMS*SOV63A, CONTMT ATM CONTMT ATM MON DW MON DW INBD ISOL RETURN INBD ISOL RETURN
8. Direct Radiation Protection to 0 Directs Radiation Protection to place Sat/Unsat place 2CMS*CAB10A(B) in 2CMS*CAB10A in service.

service.

CUE: Inform operator that 2CMS*CAB10A is in service.

9. Verify 2CMS*CAB1 OA(B) is in 0 Verifies 2CMS*CAB10A is in service SatlUnsat service AND notify the SM/CRS. AI\ID notifies the SM/CRS.

CUE: As SM/CRS, acknowledge.

NRC 2010 JPM 8-1 November 2010

I Performance Steps I Standard i Grade EVALUATOR'S NOTE: Applicant returns to Section F.1.0 to sample from Path 4 (Suppression Chamber) reference.

10. Placing H2/02 Analyzer in o Operator reviews the steps. Panel SatlUnsat Service: 2CEC*PNL873 will be used.
  • This Subsection is written for both divisions with Division II components in parentheses.
  • Actions in this Subsection are performed at 2CEC*PNL873(875) unless otherwise specified.
  • Position 4 lines up the Suppression Chamber sample stream. It is only used as directed by procedure.
  • Performance of this Subsection may be required by the EOPs. Changes to this Subsection (including renumbering) are required to be reviewed by this EOP Coordinator.
  • Control Room indication for H2 and 02 will be less than 0% if the analyzer is self.

calibration OR TROUBLE condition. The only location to determine if the unit is in self-calor in TROUBLE is the indicating lights on the remote panel 2CMS*PNL73A(B) (240 EI.

Aux Bay). Control Room indication will return when self-calibration is complete, 30 minutes.

NRC 2010 JPM S-1 November 2010

I Performance Steps I Standard Grade

11. If required defeat LOCA isolation 0 Refers to Section H.2.0 SatiUnsat per Section H.2.0
12. If LOCA isolation signal is o Operator notes that this step was Sat/Unsat present, using PA 235 Key, performed earlier in the JPM (step place the following keylock 5) and verifies switches in switches to OVERRIDE: OVERRIDE
  • ISOL VLV OVERRIDE on 2EC*PNL873(875)
13. At 2CEC*PNL873(875), place o At 2CEC*PNL873, places the Pass/Fail the Division 1(11) SAMPLE PATH Division I SAMPLE PATH SELECTOR SWITCH in the SELECTOR SWITCH in the RESET position RESET position.
14. Return to Section F.1.0 to place o Returns to section F.1.0 SatiUnsat H202 Analyzers in service NOTE: IF a LOCA Isolation occurs while the Analyzer is in service, it will cause the analyzer to trip. Placing the H2/02 ANALYZER PMP switch to STANDBY will reset the trip logic.
15. Verify the 2CI\t1S*P2A(B), H2/02 o Verifies the 2CMS*P2A, H2/02 SatiUnsat ANALYZER PMP, in STANDBY. ANALYZER PMP, in STANDBY.
16. Establish a sample flowpath by o Establishes a sample flowpath by PASS/FAIL placing the SAMPLE PATH placing the SAMPLE PATH SELECTOR SWITCH to SELECTOR SWITCH to Position 4 Position 1, 2 or 3 (Drywell) OR (Suppression Chamber) 4 (Suppression Chamber) as directed by SM/CRS.
17. Verify EITHER a Drywell OR o Verifies a Suppression Chamber Suppression Chamber sample sample flow path exists.

flow path exists, as follows:

Suppression chamber sample flow path:

  • 2CMS*SOV26A(B),
  • 2CMS*SOV26A, SAMPLE PASS/FAIL SAMPLE FROM SUPPR FROM SUPPR CHAM CHAM INBOARD ISOL VLV, INBOARD ISOL VLV, Open Open NRC 2010 JPM S-1 November 2010

I Performance Steps Standard Grade

17. (cant) Suppression chamber sample flow path:
  • 2CMS*SOV26C(D) ,
  • 2CMS*SOV26C, SAMPLE PASS/FAIL SAMPLE FROM SUPPR FROM SUPPR CHAM CHAM OUTBOARD ISOL OUTBOARD ISOL VLV, Open VLV, Open
  • 2CMS*SOV34A(B), SUPPR
  • 2CMS*SOV34A, SUPPR CHAM PASS/FAIL CHAM SAMPLE RTN SAMPLE RTN INBOARD ISOL INBOARD ISOL VLV, Open VLV, Open
  • 2CMS*SOV35A(B). SUPPR
  • 2CMS*SOV35A, SUPPR CHAM SatlUnsat CHAM SAMPLE RTN SAMPLE RTN OUTBOARD OUTBOARD ISOL VLV, ISOL VLV, Open Open
  • 2CMS*SOV64A(B), H2/02
  • 2CMS*SOV64A, H2/02 SatlUnsat ANALYZER INLET VLV, ANALYZER INLET VLV, Open Open
  • 2CMS*SOV65A{B), H2/02
  • 2CMS*SOV65A, H2/02 SatlUnsat ANALYZER OUTLET VLV, ANALYZER OUTLET VLV, Open Open NOTES:. Alarms for High 02 concentrations are expected for first 20 minutes until analyzer warm up period is complete.
  • Allow 30 minutes for system stabilization after placing the 2CMS*P2A(B), H2I02 ANALYZER PMP to ANALYZE. It takes approximately 6 minutes to receive and accurately read the sample by the H2I02 Analyzer, when changing sample locations.

CUE: Inform candidate that 30 minutes has elapsed.

18. Place the 2CMS*P2A(B), H2/02 D Places the 2CMS*P2A, H2/02 PASS/FAIL ANALYZER PMP switch to ANALYZER PMP switch to ANALYZE. ANALYZE.
19. Verify 2CMS*P2A(B), Sample D Verifies 2CMS*P2A, Sample Pump SatlUnsat Pump GREEN light goes OUT GREEN light goes OUT and RED and RED light is LIT. light is LIT.

TERMINATING CUE: Analyzer RED light ON. Sampling from the Suppression Chamber.

RECORD STOP TIME_ _

NRC 2010 ~IPM S-1 November 2010

TURNOVER SHEET INITIAL The plant is shutdown following a LOCA.

CONDITIONS:

INITIATING CUES: Perform a post LOCA restart of 2CMS*CAB10A per N2-0P-82, Section H.1.0, and using Division I CMS H202 Monitor, sample the Suppression Chamber per Section F.1.0.

NRC 2010 JPM S~1 ~ 8~ November 2010

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

Title:

Add Air to a De-Inerted Drywell Revision: NRC 2010 Task Number: NA Approvals:

NA Exam Security I General Supervisor Date Operations (Designee)

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

Trainer/Evaluator:_____________

Evaluation Method: ---=X'-!...-_Perform _ _ _ _ _Simulate Evaluation Location: _ _ _Plant _ _.-;..:X,--_Simulator Expected Completion Time: 20 min_ Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: Completion JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

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

NRC 2010 JPM S-2 November 2010

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

Simulator Simulator Set-up (if required):

IC-172 Remote PC21, CPS-V26 Purge Fan Discharge Directions to the Instructor/Evaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.

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

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

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

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

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used.

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

Notes to Instructor! Evaluator:

1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by aU.".
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 2010 JPM 8-2 November 2010

References:

N2-0P-61A, Revision 01300 KIA 261000 A4.04 3.3/3.4 Tools and Equipment:

None Task Standard:

Suppression Chamber pressure is ::::: 0 psig and the containment purge fan is stopped.

Initial Conditions:

1. Drywell is de-inerted.
2. One (1) SBGT System is operable.
3. Containment venting is NOT in progress.

Initiating Cues:

Add air to the Drywell per N2-0P-61A, Section H.3.0.

I Performance Steps I Standard Grade

1. Provide repeat back of initiating o Proper communications used for SatlUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary.

RECORD START TIME

2. Obtain a copy of the reference o N2-0P -61A obtained. Precautions SatlUnsat procedure and review/utilize the & Limitations reviewed.

correct section.

3. Verify Containment Venting is o Verifies Containment Venting is SatlUnsat NOT in progress. NOT in progress.

Cue: Provided in Initial Conditions.

NRC 2010 JPM S-2 November 2010

4. Verify the following: o Verifies GTS*AOV1 01, SatlUnsat
  • GTS*AOV1 01 , CONTAINMENT PURGE TO CONTAINMENT PURGE TO SBGTSISOL VLV closed AND SBGTS ISOL VLV closed At least one Standby Gas treatment AND subsystem is OPERABLE
  • At least one Standby Gas treatment subsystem is OPERABLE Cue: GTS*AOV101 is closed and one subsystem of SBGTS is operable
5. Line up operating air supply to o Lines up operating air supply to PASS/FAIL 2CPS*AOV106 as follows: 2CPS*AOV1 06 as follows:
  • Open IAS*SOV168,
  • Opens IAS*SOV168, PRIMARY PRIMARY CNTMT OUTBD CNTMT OUTBD ISOL VLV TO ISOL VLV TO DRYWELL at DRYWELL at 2CEC*PNL851.

2CEC*PNL851.

  • Open IAS*SOV180,
  • Opens IAS*SOV180, PRIMARY PRIMARY CNTMT INBD CNTMT INBD ISOL VLVTO ISOL VL V TO DRYWELL at DRYWELL at 2CEC*PNL851.

2CEC*PNL851.

6. Open 2CPS-DMP1, Contmt 0 Opens 2CPS-DMP1, Contmt Purge PASS/FAIL Purge FN1 Inlet Damper. FN1 Inlet Damper.

Cue: 2CPS-DMP1, Contmt Purge FN1 Inlet Damper is Open.

7. Open 2CPS-V26, Contmt Purge 0 Opens 2CPS-V26, Contmt Purge PASS/FAIL FN1 Disch Isol. FN1 Disch Isol.

Cue: 2CPS-V26 is Open

8. At 2CEC*PNL873, verify closed 0 At 2CEC*PNL873, verifies SatlUnsat CPS*AOV105, SUPP CHMBR CPS*AOV105, SUPP CHMBR PURGE INLET OUTBOARD PURGE INLET OUTBOARD ISOL ISOL VLV. VLVCLOSED.
9. At 2CEC*PNL873, open o At 2CEC*PNL873, opens PASS/FAIL CPS*AOV104, DRYWELL CPS*AOV104, DRYWELL PURGE PURGE INLET OUTBOARD INLET OUTBOARD ISOL VLV.

ISOL VLV.

NRC 2010 JPM S-2 November 2010

I Performance Steps I Standard Grade

10. At 2CEC*PNL875, open o At 2CEC*PNL875, opens PASS/FAIL CPS*AOV106, DRYWELL CPS*AOV106, DRYWELL PURGE PURGE INLET INBOARD ISOL INLET INBOARD ISOL VLV.

VLV.

11. At 2CEC*PNL873, start o At 2CEC*PNL873, starts CPS-FN1, PASS/FAIL CPS-FN1, CONTMT PURGE CONTMT PURGE FAN.

FAN.

12. At approximately 0 psig drywell o At 0 psig drywell pressure, PASS/FAIL pressure, (2CMS*PI1A1B on (2CMS*PI1A1B on 2CEC*PNL601 2CEC*PNL601 OR computer OR computer point CMSPA01/02),

point CMSPA01/02), stop stops 2CPS-FN1.

2CPS-FN1.

13. Close the following: o Closes the following:
  • 2CPS-V26 Contmt Purge FN1 SatiUnsat FN1 Disch Isol. Disch Isol.

Cue: 2CPS-V26 is closed

  • 2CPS*AOV106, DRYWELL
  • 2CPS*AOV106, DRYWELL PASS/FAIL PURGE INLET INBOARD PURGE INLET INBOARD ISOL ISOL VLV. VLV.
  • 2CPS*AOV104, DRYWELL
  • 2CPS*AOV104, DRYWELL PASS/FAIL PURGE INLET OUTBOARD PURGE INLET OUTBOARD ISOL VLV. ISOL VLV.
  • 2IAS*SOV168, PRIMARY
  • 2IAS*SOV168, PRIMARY PASS/FAIL CNTMT OUTBD ISOL VLV CNTMT OUTBD ISOL VLV TO TO DRYWELL DRYWELL
  • 2IAS*SOV180, PRIIVIARY
  • 2IAS*SOV180, PRIMARY PASS/FAIL CNTMT INBD ISOL VLV TO CNTMT INBD ISOL VLV TO DRYWELL DRYWELL TERMINATING CUE: Air added to the Drywell per N2-0P-61A, Section H.3.0.

RECORD STOP TIME,_ _ __

NRC 2010 JPM S-2 November 2010

TURNOVER SHEET INITIAL 1. Drywell is de-inerted.

CONDITIONS: 2. One (1) SBGT System is operable.

3. Containment venting is NOT in progress.

INITIATING CUES: Add air to the Drywell per N2-0P-61A, Section H.3.0.

NRC 2010 JPM 5-2 November 2010

NRC JPM 8-3 Constellation Energy Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Securing and Restart of Shutdown Revision: NRC 2010 Cooling Task Number: NA Approvals:

NA Exam Security I General Supervis General Supervisor Date Operations Training (Designee) Operations (Designee)

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

Trainer/Evaluator:_ _ _ _ _ _ _ _ _ _ __

Evaluation Method: X Perform _ _ _ _ _Simulate Evaluation Location: _ _ _Plant ___X:....>-__Simulator Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: Yes Start Time: _ _ __ Stop Time: Completion Time: _ _ __

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

Comments:

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

NMP2 NRC JPM S-3 November 2010

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

Unit 2 Simulator Simulator Set-up (if required):

1. Place Simulator in IC-172 Shut Down Cooling
2. Set up the following I/Os and Event Triggers
a. I/O Control switch for 2RHS*MOV40B in 'off' (ovr-01a2s145di0469) and trigger the I/O off the red open indication for 2RHS*MOV40B, [hzlrhvs44(2)==11
b. TRG 8, ovr-18a3ds146101462 on (turns on red light for HVP*AOD4D on P871 to setup conditional trigger to allow subsequent activation of trigger 9)
c. TRG 9, ovr-01a2s145di0469, Open RHR SOC injection valve Off (overrides RHS*MOV40B control switch open position to off disabling switch contact)
d. Event trigger #8, hzlrhps3b(1 )==1 .and. hzlrhsvs44(2)==O (activates when RHS*P'I B is stopped, green light on, and RHS*MOV40B is full closed, red light off)
e. Event trigger #9, hzlpc1 bhvp04(2)==1 .and. hzlrhsvs44(2)==1 (activates when HVP*AOD4D red light is on from trigger 8 and RHS*MOV40B starts to open, red light on)

Directions to the Instructor/Evaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.

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

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated ..IPM Performance:

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

Read Before Each Training "IPM Performance:

During this Training ..IPM , applicable methods of verification are expected to be used.

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

NMP2 NRC JPM 8-3 November 2010

Notes to Instructor I Evaluator:

1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a".".
2. During Evaluated JPM:
  • Self-verification shall be demonstrated.
3. During Training JPM:
  • Self-verification shall be demonstrated.
  • (Additional/Concurrent/No other) verification shall be demonstrated.

References:

1. N2-0P-31, Section H.3.0 and H.4.0
2. N2-ARP-01, Attachment 6, ARP for window 601648
3. NUREG 1123, 205000 A4.01 3.7/3.7 Shutdown Cooling System (RHR Shutdown Cooling Mode)

Tools and Equipment:

1. Stopwatch Task Standard:

RHS*P1 B tripped after insufficient flow 40 seconds after start.

Initial Conditions:

  • Plant is in mode 4.
  • SOC has been in service for >1 hr.
  • SOC Loop 'B' must be shut down for 15 minutes for maintenance checks on system piping.
  • RDS Back fill will remain in service.

Initiating Cues:

  • Shutdown and when directed restart RHR Loop "B" in Shutdown Cooling per N2-0P-31, Sections H.3.0 and H.4.0.

NMP2 NRC JPM 8-3 -3 November 2010

I Performance Steps I Standard Grade

1. Provide repeat back of initiating I.J Proper communications used for Sat/Unsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
2. Obtain a copy of the reference I.J N2-0P-31 obtained. Precautions & Sat/Unsat procedure and review/utilize the Limitations reviewed.

correct section.

3. Securing Shutdown Cooling for NA Short Periods NOTE:
  • In lVIodes 3,4, AND 5 with irradiated fuel in the reactor pressure vessel AND shutdown cooling in operation, the shutdown cooling pump may be shutdown for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per eight hour period. Refer to LCO's 3.4.9,3.4.10,3.9.8, or 3.9.9.
4. Monitor RPV coolant I.J Monitors RPV coolant temperature Sat/Unsat temperature closely. IF RPV closely.

coolant temperature increases the potential exists for a MODE change.

Cue: Another operator is monitoring RPV coolant temperatures

5. Close RHS*MOV40B, SOC B I.J Closes RHS*MOV40B, SDC B Pass/Fail RETURN THROTTLE UNTIL RETURN THROTTLE UNTIL pump pump flow is 2000 gpm on E12- flow is 2000 gpm on E12-R603B, R603B, RHR B TOTAL FLOW. RHR B TOTAL FLOW.

NMP2 NRC JPM S-3 November 2010

I Performance Steps I Standard Grade

6. Stop 2RHS*P1 B by placing its o Stops 2RHS*P1 B by placing its Pass/Fail control switch in PULL-TO control switch in PULL-TO-LOCK LOCK AND start the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> AND starts the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> clock.

clock.

7. Fully Close 2RHS*MOV40B. o Fully closes 2RHS*MOV40B. Pass/Fail
8. Close 2SWP*MOV33B. o Closes 2SWP*MOV33B. Pass/Fail Cue: 15 minutes have elapsed and maintenance has completed its checks.

Restart the 8 RHS pump in Shutdown Cooling Mode.

9. IF RDS Backfill Injection is out of service to one OR more RPV Level Reference Legs in Mode 3, THEN perform the following:

Cue: N/A, RDS 8ackfillinjection is NOT out of service.

Caution: The RHR pump is without minimum flow protection, Minimum flow of 2: 1000 gpm must be established within 40 seconds of pump start. Use of a stop watch is recommended to ensure the pump is tripped within the required time if minimum flow is not achieved. Do not allow pump to run for> 15 seconds deadheaded.

10. Start 2RHS*P1 B.  ::J 2RHS*P1 B red running light Pass/Fail illuminated, Control switch in red flag.
11. Throttle open RHS*MOV40B, o Operator attempts to open SatlUnsat SOC B Return Throttle to ~ 1000 2RHS*MOV40B to obtain ~ 1000 gpm gpm and observes DUAL indication.
12. If RHS*MOV40B does not begin a RHS*MOV40B will not open to Pass/Fail to open in 15 seconds OR provide flow ~ 1000 gpm. The system flow is NOT ~1 000 gpm operator will then trip RHS*P1 B by 40 seconds after the pump start, placing the control switch to STOP, Place RHS*P1 B control switch then release to Normal-After-Stop to STOP, then release to Normal-After-Stop NMP2 NRC JPM S-3 November 2010

[ Performance Steps [ Standard Grade

13. Report to CRS inability to obtain CJ Report made to CRS of inability to SatlUnsat required minimum flow on obtain satisfactory min-flow and RHS*P1 B and that the pump pump has been tripped.

has been tripped.

TERMINATING CUE: RHS*P1 B tripped and report to CRS made.

RECORD STOP TIME _ _ __

NMP2 NRC JPM S-3 November 2010

TURNOVER SHEET INITIAL

  • Plant is in mode 4.

CONDITIONS:

  • SDC has been in service for >1 hr.
  • SDC Loop "8" must be shutdown for 15 minutes for maintenance checks on system piping.
  • RDS Back Fill will remain in service.

INITIATING CUES:

  • Shutdown and when directed restart RHS Loop "8" in Shutdown Cooling per N2-0P-31, Sections H.3.0 and H.4.0.

NMP2 NRC JPM 5-3 November 2010

NRC JPM S-4 Constellation Energy Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Return WCS to Normal Revision: NRC 2010 Task Number: NA Approvals:

~7 . / "2 NA Exam Security

~~r~~~~~~~~~~~~~~~,/i? I General Supervis General Supervisor Date Operations Training (DeSignee) Operations (Designee)

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

Trainer/Evaluator:_ _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: ---.:X:...:..-_Perform _ _ _ _ _Simulate Evaluation Location: - - -Plant ___X:...!-__Simulator Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: Yes Start Time: _ _ __ Stop Time: Completion Time: _ _ __

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

Comments:

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

NRC 2010 JPM 8-4 November 2010

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

Simulator Simulator Set-up (if required):

1. IC 176
2. Place fourth Filter Demin in service - Remote CU03 A,B,C or D
3. Close WCS*MOV404A
4. Appendix "R" Breakers "SHUT" - Remote CU05A1B SHUT
5. Open WCS*MOV1 07 to the Main Condenser and establish 100 gpm reject flow
6. Throttle WCS*MOV200 to obtain FID flows of 165-175 gpm
7. Insert Malfunction CU08, WCS fails to isolate - QUEUED
8. Activate Malfunction CU07 at 80% when closing WCS*MOV107 to secure blowdown flow. Event Trigger 1 (hzlcus2(1)==1 for MOV107 green light on) will trigger CU07.

Directions to the Instructor/Evaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.

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

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated. JPM Performance:

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

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used.

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

Notes to Instructor / Evaluator:

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

NRC 2010 JPM 5-4 2- November 2010

3. During Training JPM:
  • Self-verification shall be demonstrated.
  • No other verification shall be demonstrated.

References:

N2-0P-37, Sect. F.7.0 N2-S0P-83, N2-ARP-01, Annunciators 602320 and 602313 NUREG KIA 204000 A4.03 Tools and Equipment:

None Task Standard:

WCS Pumps are tripped and the WCS Primary Containment Isolation Valves are closed.

Initial Conditions:

  • Reactor Startup in progress with power at 25%.

Initiating Cues:

Return the Reactor Water Cleanup System to NORMAL operations and secure reject flow to the Main Condenser in accordance with N2-0P-37, Section F.7.0.

I Performance Steps I Standard Grade

1. Provide repeat back of initiating o Proper communications used for SatiUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
2. Obtain a copy of the reference o N2-0P-37 obtained. Precautions & SatiUnsat procedure and review/utilize the limitations reviewed & section F.7.0 correct section. referenced.
3. SLOWLY open o Opens 2WCS*MOV404A Pass/Fail 2WCS*MOV404A, RWCU VALVE.

o NRC 2010 JPM S-4 November 2010

i Performance Steps I Standard Grade Cue: Another operator is o Monitor WCS differential flow SatiUnsat monitoring differential indications using 2WCS-FI620A & B flows. on Panels P632 and P642.

Role Play: Log has been updated o Notify CRO to log TIME and DATE SatiUnsat of valve opening.

4. Secure "REJECT" flow to the o Slowly lower reject flow to zero (0) Pass/Fail Main Condenser from the WCS as indicated on G33-RS02 using System. G33-R606 (2WCS*FC1135),

REJECT FLOW CONTROL FV135 MANUAL CONTROL, on P602.

o Close 2WCS*MOV107, REJECT SatiUnsat TO MAIN CONDENSER.

Note: Malfunction CU07, WCS leak outside Primary Containment, at 80%

is auto activated when MOV107 starts to close. Malfunction CU08, Failure of WCS to Isolate, malfunction is already active as it was queued at the beginning of this JPM.

5. Responds to Annunciators: o Suspends any operational SatiUnsat
  • 851254 PROCESS evolutions which may be causing a AIRBORNE RADN MON perturbation in cleanup system flow ACTIVATED. UNTIL this annunciator clears.
  • 602320, RWCU DIFF FLOW TIMER BYPASS.

EXAMINER NOTE: ANN o Prepares to respond to a cleanup SatiUnsat 851254 comes in first. ANN isolation per the appropriate 602320 comes in shortly sections of N2-0P-37.

thereafter.

Operator actions to mitigate the problem are based on response to the ANN S02313, in the following JPM step.

  • Reviews N2-0P-37 Table of Contents and, if time allows

RS21 B (45 second timers) have started timing out. At the end of 45 seconds, if differential flow has not dropped below 150.5 gpm, a full WCS isolation SHOULD occur.

NRC 2010 JPM S-4 November 2010

i Performance Steps I Standard Grade

6. Responds to Annunciator D Observes 2WCS"'MOV102 AND Pass/Fail 602313, RWCU DIFFERENTIAL 2WCS*MOV112 DID NOT close by FLOW HIGH observing RED lights "ON" and GREEN lights "OFF".

D Informs SM that WCS has failed to Sat/Unsat isolate.

D Recommends manual isolation of SatlUnsat WCS to SM/CRS.

Cue: As SM/CRS, concur with recommendation to isolate WCS.

Note: Candidate will either close Isolation Valves based on entry into N2 SOP-83 or Annunciator response for 602313. IF N2-S0P-83 is used as the basis for closing the valves, the candidate is expected to follow-up in the Annunciator Response Procedure.

7. Manually closes D Manually closes 2WCS*MOV102 Pass/Fail 2WCS*MOV102 AND/OR AND/OR 2WCS*MOV112 2WCS*MOV112 per N2-S0P-83 (or Annunciator 602313, RWCU DIFFERENTIAL FLOW HIGH response).
  • Obtains KEYS and inserts into keylock switches
  • Rotates keylock switches to CLOSE position.
  • Observes GREEN Lights "ON" and RED light "OFF" when valve is full closed.

Note: Candidate is to be graded as "Pass" for the critical step if either valve is closed to isolate the leak. The expectation is that both valves will be manually closed.

NRC 2010 JPM 8-4 November 2010

I Performance Steps i Standard Grade

8. Follow up actions for o Confirms Isolation valves SaUUnsat Annunciator 602313, RWCU 2WCS*MOV102 AND DIFFERENTIAL FLOW HIGH, if 2WCS*MOV112 closed.

valves were closed using N2 SOP-83.

o Verifies 2WCS-P1 A AND 2WCS SaUUnsat P1 B have tripped.

  • Pump GREEN light "ON", AND

Cue: If asked what is supplying WCS pump seals, reply that the Control Rod Drive System is supplying WCS Pump seals.

9. Provide leak path for WCS o Throttles open 2WCS-MOV11 0, Sat/Unsat Pump seal water flow, to avoid CLEANUP DEMIN BYPASS VLV over-pressurizing pump suction THROTTLE.

piping.

10. Report condition of the WCS o Notifies the SM that the WCS SaUUnsat System to SM. System has been manually isolated.

TERMINATING CUE: WCS System is isolated, the WCS Pumps are tripped and 2WCS*MOV11 0 is throttled open.

RECORD STOP TIME_ _ __

NRC 2010 JPM S-4 November 2010

TURNOVER SHEET INITIAL

  • Reactor Startup in progress with power at 25%.

CONDITIONS:

INITIATING CUES: Return the Reactor Water Cleanup System to NORMAL operations and secure reject flow to the Main Condenser in accordance with N2-0P-37, Section F.7.0.

NRC 2010 ~IPM $-4 November 2010

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

Title:

Start and Load Division I Diesel Revision: NRC 2010 Task Number: NA Approvals:

NA Exam Security I General Supervisor Date Operations (Designee)

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

Trainer/Evaluator:_ _ _ _ _ _ _ _ _ _ __

Evaluation Method: ----,X

, -,,--_Perform _ _ _ _ _Simulate Evaluation Location: _ _ _Plant _ _--'-'X'--_Simulator Expected Completion Time: 25 min. Time Critical Task: No Alternate Path Task: Yes Start Time: _ _ __ Stop Time: Completion Time: _ _ __

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

Comments:

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

NMP2 NRC JPM 5-5 November 2010

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

Simulator Simulator Set-up (if required):

1. IC 175
2. Override 2SWP*MOV66A Control Switch Closed (OVR-05A2S016DI7284-on) on TRG 1
3. Remote CW24, Loss of Power to 2SWP*MOV66A on TRG 1, active after 45 seconds.
4. Setup automatic event trigger to activate TRG 1 when DG1 KW exceeds 475 kw (variable dgpdgenkw (1>>= 475).
5. Malfunction DG02A on TRG 2 Directions to the Instructor/Evaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas as 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.
  • Additional/Concurrent verification shall be demonstrated.

References:

1. N2-0P-100A, Rev.g, "Standby Diesels", Sec. F.4.0, H.1.0
2. NUREG KIA: 264000 A4.04 (3.7/3.7)
3. ARP-01 852126, Service Water Low Flow Tools and Equipment:
1. Synch Key
2. Stopwatch NMP2 NRC JPM 5-5 November 2010

Task Standard: The Division I Diesel Generator is to be started and paralleled with offsite electric power. The engine will be shutdown using normal operating procedures following a closure of Service Water valve 2SWP*MOV66A.

Initial Conditions:

1. All prestart checks (F.2.0) and data required by Attachment 1 have been completed for the Division I EDG.
2. N2-0P-100A, Standby Diesel Generators, Attachment 1: Run Time Log and Validity and Attachment 2: Diesel Generator Loaded Run Operating Log are being used by an Operator stationed in the Division I EDG Room.
3. All other diesels are operable.
4. Grid conditions are stable.
5. Fast loading is not required
6. Instructor to ask operator for any questions.

Initiating Cues:

Start and parallel the Division I Diesel with offsite power and perform a normal load to 1100 KW, per N2-0P-100A, Section F.4.0."

Performance Steps Standard Grade

1. Provide repeat back of initiating o Proper communications used for SatiUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01).

repeat back providing correction if necessary.

RECORD START TIME _ _ __

-2. Obtain a copy of the reference o N2-0P-100A obtained. SatiUnsat procedure and review/utilize the Precautions & limitations correct section of the procedure. reviewed & section F.4.0 referenced.

3. Verify 2ENS*SWG101-N*l . o Observe NEUTRAL BREAKER Sat/Unsat NEUTRAL BREAKER 101-N1, 101-N1 red light is on.

closed.

4. Place EMERGENCY DSL GEN 1 o Parallel switch in on. Sat/Unsat PARALLEL switch to ON .
5. Verify EMERGENCY DSL GEN 1 o VOLTAGE REGULATOR MODE SatiUnsat VOLTAGE REGULATOR. MODE SELECT switch in AUTO and red SELECT switch in AUTO. light is on.
6. Place DIVISION 1 2EGS*EG1 o Observe the following Engine Pass/Fail START switch to START. start indications:

Note: Annunciators 852109 and - Red light on at EG1 Control 852117 are expected to Switch.

alarm. - Diesel Speed as indicated on RPM-2EGPS11, RPM, rises to 600 RPM.

NMP2 NRC JPM S-5 November 2010

Standard Grade

  • Generator Voltage as indicated on VM-2EGPA09. VOLTS, rises to 4.16 A-C KI lOVOlTS.
  • Generator Frequency as indicated on FM-2EGPA09, FREQUENCY, rises to 60 HERTZ.
  • SWP*MOV66A, SERVICE WTR OUTLET, opens.
  • Diesel Service Water Flow as indicated on 2SWP*F176A, SERVICE wrR FLOW, is ;::800 GPM.
7. Run 2EGS*EG 1 unloaded for five o 2 EGS and EG1 has run SatlUnsat minutes at rated voltage AND unloaded for at least 5 minutes.

Frequency to warmup Engine.

Cue: Instructor/Evaluator should time compress and inform operator that 5 minutes has expired.

8. Place SYNCHRONIZE TO BUS o SYNCHRONIZE TO BUS 101 Pass/Fail 101 switch to ON. switch is ON.
9. Using EMERGENCY DSL GEN 1 o Voltage control verified by VOLTAGE REGULATOR switch, performing the following.

verify voltage control and clean motor operated potentiometer contacts as follows:

  • Using VOLTAGE REGULATOR
  • Using VOLTAGE REGULATOR SatlUnsat control switch, lower voltage control switch, lower voltage UNTIL VOLTS indication is 3950 UNTil VOLTS indication is 3950 VOLTS. VOLTS
  • Using VOLTAGE REGULATOR
  • Using VOLTAGE REGULATOR SatlUnsat control switch, raise voltage control switch, raise voltage UNTIL VOLTS indication is 4350 UNTIL VOLTS indication is 4350 ACVOLTS. AC VOLTS.
  • Using VOLTAGE REGULATOR
  • Using VOLTAGE REGULATOR SatlUnsat control switch, lower voltage control switch, lower voltage UNTIL VOLTS indication is 4160 UNTil VOLTS indication is 4160 ACVOLTS. AC VOLTS.
10. Using EMERGENCY DSL GEN 1 o Speed control verified by SatlUnsat GOVERNOR switch, verify observing change in rate of governor control by varying SYCHROSCOPE rotation or SYNCHROSCOPE indication. FREQUENCY meter readings change.

NMP2 NRC JPM 5-5 November 2010

Performance Steps Standard Grade

11. Using VOLTAGE REGULATOR 0 Observe voltages matched on SatiUnsat switch, match voltages on 4.16KV INCOMING and RUNNING 2ENS*SWG101 INCOMING VOLTS meters.

VOLTS meter AND 4KV RTX XSR1A 12ABS-X1/2EGS*EG1 RUNNING VOLTS meter.

12. Adjust GOVERNOR switch to 0 Observe SYNCHROSCOPE SatiUnsat establish slow clockwise rotation rate approximately 12 to 24 on SYNCHROSCOPE (slow in fast seconds for one 360 0 sweep.

direction), as indicated by:

  • Meter movement between % to 1 inch per second
  • 12 to 24 seconds for 360 0 meter sweep
13. WHEN SYNCHROSCOPE 0 Closes 2 ENS*SWGR101-1 Pass/Fail reaches 5 minutes before 12 when synchroscope reaches 5 o'clock (11 o'clock position), minutes before 12 (- 10 minutes perform the following: to 12 and 12 o'clock) and
  • Close 2ENS*SWG101-1 observes Red light ON, Green
  • Verify Generator picks up load light OFF and generator picks as indicated on WM-2EGPA20, up load by positive (upward)

WATTS. indication on WATTS meter.

14. Place SYCHRONIZE TO BUS 101 0 SYNCHRONIZE TO BUS 101 is SatiUnsat switch to OFF. OFF
15. USing GOVERNOR switch, raise 0 Raises Generator Load to SatiUnsat Generator Load to approximately approximately 1100 KW at a 1100 KW at a rate of about 500 rate of about 500 KW per KW per minute. minute.

Console Operator: When Generator Load exceeds 475 KW, confirm override to close 2SWP*MOV66A activates on TRG 1 and MOV power supply trips after 45 seconds.

SWP flow on P852 indicator 2SWP*FI76A SERVICE WTR FLOW drops and when below about 450 gpm Annunciator 852126, EDG Service Water Flow Low alarms ALTERNATE PATH NMP2 NRC JPM S-5 November 2010

Performance Steps Standard Grade

16. Refers to 852126 alarm response. o 852126 alarm response referred Sat/Unsat to, observes low service water flow <<100 gpm) on SWP*FI76A.
17. Verify SWP*MOV66A open. o Observes and reports SatlUnsat 2SWP*MOV66A is closed and identifies breaker tripped, after trip occurs AND valve failure to open, Green light OFF, Red light OFF.
18. Verify SWP*V941A and V231A o Contacts and directs an SatlUnsatlNA open. operator to verify SWP*V941 A and V231A are open. Operator contacted and 941 A and 231 A Note: Candidate may NOT verify verified open.

941A and 231A because these are manual valves which are known to be open because flow previously existed.

Cue: If sent to determine the position of SWP*V941A and 231A, report both valves are open.

Cue: If asked direct candidate to take the appropriate actions.

Note: Critical step is to unload the engine such that an automatic trip is avoided. By unloading the engine and tripping the output breaker, the heat generation is limited.

19. Unload EDG1 per N2-0P-100A, o Refers to N2-0P-100A, Section Pass/Fail Section H.1.0 (preferred) for H.1.0 to Emergency Shutdown Emergency Shutdown OR Section EDG1.

F.6.0 for Normal Shutdown OR o Refers to N2-0P-100A, Section F.6.0 to Normal Shutdown EDG1.

  • At 2CEC*PNL852, using o Generator Load reduced to SatlUnsat GOVERNOR switch, reduce 1OOKW using the GOVERNOR DIESEL GENERATOR LOAD switch.

to 100 KW.

NMP2 NRC JPM S-5 November 2010

Performance Steps  ! Standard Grade

  • Using VOLTAGE 0 VARS adjusted between 0 and SatlUnsat REGULATOR switch, adjust 100 to bus on AC KILOVARS VARS to >0 AND <100 A-C TO BUS meter by lowering KILOVARS TO BUS. voltage regulator.
  • Open 2EGS*SWG101*,1, 0 Rotate control switch for Pass/Fail OUTPUT BREAKER 101-1 2ENS*SWG101-10UTPUT BREAKER counter clockwise and observe:
  • Green light ON, Red light OFF
  • WATIS goes to 0 Note: Depending on the shutdown method selected shutdown the EDG using one of the following methods.

.20. If using N2-0P-100A, Section 0 Observes annunciator 852117 SatlUnsat H.1.0 to Emergency Shutdown EDG 1 RUNNING clears.

EDG1 notify operator at Observes Division I 2EGS*EG1 2CES*IPNL406 ENGINE green light on.

CONTROL PANEL to depress the EMERGENCY STOP red STOP pushbutton.

Instructor Note: If notified to perform emergency stop then activate malfunction DG02A to shutdown EDG1 by depressing TRG 2

Cue: Report as operator from EDG room that the Division I EDG has been shutdown.

OR

.21. If using N2-0P-100A, Section 0 At 2CEC*PNL852, place DIVISION SatlUnsat F.6.0 to Normal Shutdown EDG1 I 2EGS"'START control switch to at 2CEC*PNL852, place DIVISION STOP and observe engine 5 I 2EGS*START control switch to minute cooldown cycle begins.

STOP.

22. Notify operator in the EDG room to 0 Operator dispatched to SatlUnsat complete the remaining shutdown complete shutdown steps in the steps. EDG room.

Cue: Report as operator from EDG room that the remaining steps are in progress.

NMP2 NRC JPM S-5 November 2010

23. Report Division I 2EGS*EG1 has Report has been made to SM. SatiUnsat been shutdown due to a loss of Cooling Water.

TERMINATING CUE: 2EGS*EG1 Division I has been unloaded and shutdown following unsuccessful run.

RECORD STOP TIME _ _ __

NMP2 NRC JPM S-5 November 2010

Initial Conditions:

1. All prestart checks (F.2.0) and data required by Attachment 1 have been completed for the Division I EDG.
2. N2-0P-100A, Standby Diesel Generators, Attachment 1: Run Time Log and Validity and Attachment 2: Diesel Generator Loaded Run Operating Log are being used by an Operator stationed in the Division I EDG Room.
3. All other diesels are operable.
4. Grid conditions are stable.

S. Fast loading is not required Initiating Cues:

"(Operators name) Start and parallel the Division I Diesel with offsite power and perform a normal load to 1100 KW, per N2-0P-100A, Section F.4.0."

NMP2 NRC JPM $-5 November 2010

NRC JPM 5-6 Constellation Energy Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE IVIEASURE

Title:

Place Main Turbine Shell Warming In Revision: NRC 2010 Service Task Number: NA Approvals:

NA Exam Security I General Supervisor Date Operations (Designee)

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

Trainer/Evaluator: _ _ _ _ _ _ _ _ _ _ __

Evaluation Method: - - -Perform _ _ _ _ _Simulate Evaluation Location: _ _ _Plant - - - - -Simulator Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: No Start Time: - - - - Stop Time: Completion Time: _ _ __

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

Comments:

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

NMP2 2010 NRC JPM S-6 November 2010

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

Simulator Simulator Set-up (if required):

1. IC-157
2. Neck Spray in service Directions to the Instructor/Evaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.

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

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used.

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

Notes to Instructor I Evaluator:

1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a tI.".
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. N2-0P-21, Revision 01100
2. KIA 241000 A4.18 2.9/2.8 NMP2 2010 NRC JPM 8-6 November 2010

Tools and Equipment:

None Task Standard:

1. Shell warming placed in service.

Initial Conditions:

1. Reactor Pressure is 65 psig.
2. Main Turbine Turning Gear is in operation.
3. N2-0P-21 "Main Turbine System" Section E.3.0. is complete through step E.3.1 Initiating Cues:

"(Operators name), Place main turbine shell warming in service in accordance with N2-0P-21, Section E.3.0. beginning at step E.3.2."

I Performance Steps I Standard Grade

1. Provide repeat back of initiating o Proper communications used for SatlUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
2. Obtain a copy of the reference o N2-0P-21 obtained. Precautions & SatlUnsat procedure and review/utilize the Limitations reviewed.

correct section.

3. Push Turbine RESET o Pushes Turbine RESET pushbutton Pass/Fail pushbutton UNTIL the Turbine UNTIL the Turbine TRIPPED light TRIPPED light goes out AND goes out AND verifies the following:

verify the following:

Examiner Cue: If required, tell candidate to hold the turbine reset pushbutton down until the reset light comes on.

  • Turbine RESET light lit.
  • Turbine RESET light lit. SatlUnsat
  • CONDENSER VACUUM
  • CONDENSER VACUUM TRIP SatlUnsat TRIP RESET light lit. RESET light lit.
  • MECHANICAL TRIP RESET
  • MECHANICAL TRIP RESET light SatlUnsat light lit. lit.

NMP2 2010 NRC JPM S-6 November 2010

  • Intermediate Stop Valves
  • Intermediate Stop Valves ISV1 SatlUnsat ISV1 through ISV6 ALL through ISV6 ALL indicate 100%

indicate 100% on on COMBINED INTERMEDIATE COMBINED STOP VALVE POSITION INTERMEDIATE STOP indicators.

VALVE POSITION indicators.

  • Intercept Valves IV1 through
  • Intercept Valves IV1 through IV6 SatlUnsat IV6 ALL indicate 0% on ALL indicate 0% on COMBINED COMBINED INTERCEPT INTERCEPT VALVE POSITION VALVE POSITION indicators.

indicators.

  • Main Stop Valves MSV1
  • Main Stop Valves MSV1 through SatlUnsat through MSV4 ALL indicate MSV4 ALL indicate 0% on MAIN 0% on MAIN STOP VALVE STOP VALVE POSITION POSITION indicators. indicators.
  • Control Valves CV1 through
  • Control Valves CV1 through CV4 Sat/Unsat CV4 ALL indicate 0% on ALL indicate 0% on CONTROL CONTROL VALVE VALVE POSITION indicators.

POSITION indicators.

4. Verify Master Trip Solenoid CJ Verifies Master Trip Solenoid Valve SatiUnsat Valve (MTSV) MASTER TRIP (MTSV) MASTER TRIP SOLENOID SOLENOID TEST push buttons TEST push buttons TEST TRIP A TEST TRIP A AND B lights lit. AND B lights lit.
5. Verify 2MSS-AOV92A, CJ Verifies 2MSS-AOV92A, Sat/Unsat REHEATER 1A STM SUPPLY REHEATER 1A STM SUPPLY VLV VLV is CLOSED. is CLOSED.
6. Verify 2MSS-AOV92B, CJ Verifies 2MSS-AOV92B, SatlUnsat REHEATER 1B STM SUPPI_Y REHEATER 1B STM SUPPLY VLV VLV is CLOSED. is CLOSED.
7. Place TURBINE SHELUCHEST CJ Places TURBINE SHELUCHEST Pass/Fail WARMING switch in ON position WARMING switch in ON position at at 2CEC-PNL824, MAIN 2CEC-PNL824, MAIN REHEAT &

REHEAT & AUX ST DR TURB AUX ST DR TURB BLDG MISC DR.

BLDG MISC DR.

NMP2 2010 NRC JPM S-6 -4 November 2010

Performance Ste s Standard Grade

8. Close the following valves at D Closes the following valves at 2CEC-PNL824: 2CEC-PNL824:
  • CRS-MOV7A, COLD
  • CRS-MOV7A, COLD REHEAT Pass/Fail REHEAT STM DRAIN VLV STM DRAIN VLV
  • CRS-MOV7B, COLD
  • CRS-MOV7B, COLD REHEAT Pass/Fail REHEAT STM DRAIN VLV STM DRAIN VLV
  • CRS-MOV8A, COLD
  • CRS-MOV8A, COLD REHEAT Pass/Fail REHEAT STM DRAIN VLV STM ORAl N VLV
  • CRS-MOV8B, COLD
  • CRS-MOV8B, COLD REHEAT Pass/Fail REHEAT STM DRAIN VLV STM DRAIN VLV
  • CRS-MOV9A, COLD
  • CRS-MOV9A, COLD REHEAT Pass/Fail REHEAT STM DRAIN VLV STM DRAIN VLV
  • CRS-MOV9B, COLD
  • CRS-MOV9B, COLD REHEAT Pass/Fail REHEAT STM DRAIN VLV STM DRAIN VLV
  • CRS-MOV18A, COLD
  • CRS-MOV18A, COLD REHEAT Pass/Fail REHEAT STM DRAIN VLV STM DRAIN VLV
  • CRS-MOV18B, COLD
  • CRS-MOV18B, COLD REHEAT Pass/Fail REHEAT STM DRAIN VLV STM DRAIN VLV
  • DSM-MOV79A, MOISTURE
  • DSM-MOV79A, MOISTURE Pass/Fail SEPARATOR A DRAIN VLV SEPARATOR A DRAIN VLV
  • DSM-MOV79B, MOISTURE
  • DSM-M0V79B, MOISTURE Pass/Fail SEPARATOR B DRAIN VLV SEPARATOR B DRAIN VLV
  • HRS-MOV1,
  • HRS-MOV1, CROSSAROUND Pass/Fail CROSSAROUND PIPING PIPING DRAIN VLV DRAIN VLV
  • HRS-MOV2,
  • HRS-MOV2, CROSSAROUND Pass/Fail CROSSAROUND PIPING PIPING DRAIN VLV DRAIN VLV TH
  • ESS-MOV28A, 5TH POINT
  • ESS-MOV28A, 5 POINT SatlUnsat HEATER A EXTRACTION HEATER A EXTRACTION STM STM ISOL VLV ISOL VLV TH
  • ESS-MOV28B, 5TH POINT
  • ESS-MOV28B, 5 POINT SatlUnsat HEATER B EXTRACTION HEATER B EXTRACTION STM STM ISOL VLV ISOL VLV TH
  • ESS-MOV28C, 5TH POINT
  • ESS-MOV28C, 5 POINT SatlUnsat HEATER C EXTRACTION HEATER C EXTRACTION STM STM ISOL VLV ISOL VLV TH
  • ESS-MOV-3A, 6TH POINT
  • ESS-MOV-3A, 6 POINT SatlUnsat HEATER A EXTRACTION HEATER A EXTRACTION STM STM ISOL VLV ISOL VLV TH
  • ESS-MOV-3B, 6TH POINT
  • ESS-MOV-3B, 6 POINT SatlUnsat HEATER B EXTRACTION HEATER B EXTRACTION STM STM ISOL VLV ISOL VLV TH
  • ESS-MOV-3C, 6TH POINT
  • ESS-MOV-3C, 6 POINT SatlUnsat HEATER C EXTRACTION HEATER C EXTRACTION STM STM ISOL VLV ISOL VLV NMP2 2010 NRC JPM S-6 -5 November 2010

I Performance Steps I Standard Grade TH

9. Verify LOAD LIMIT SET o Verifies LOAD LIMIT SET SatiUnsat potentiometer set at 8.69 potentiometer set at 8.69 (102.5%).

(102.5%).

10. Push FAST pushbutton at o Pushes FAST pushbutton at START SatiUnsat START UP RATE controls. UP RATE controls.
11. Observe FAST pushbutton lit. o Observes FAST pushbutton lit. SatiUnsat
12. Verify LOAD SET indication is 0 o Verifies LOAD SET indication is 0 Sat/Unsat Megawatts. Megawatts.
13. Push SHELL pushbutton at o Pushes SHELL pushbutton at MAIN Pass/Fail MAIN STOP VALVE POSITION STOP VALVE POSITION DEMAND DEMAND FOR CHEST/SHELL FOR CHEST/SHELL WARMING WARMING controls. controls.
14. Verify the following indications: o Verifies the following indications:
  • SHELL pushbutton lit.
  • SHELL pushbutton lit. SatiUnsat
  • Control Valve CV1 through
  • Control Valve CV1 through CV3 SatiUnsat CV3 ALL indicate 100% on ALL indicate 100% on CONTROL VALVE CONTROL VALVE POSITION POSITION indicators AND indicators AND CV4 indicates CV4 indicates approximately approximately 40 - 60% control 40 - 60% control valve valve position.

position.

  • Intermediate Stop Valves
  • Intermediate Stop Valves ISV1 SatiUnsat ISV1 through ISV6 ALL through ISV6 ALL indicate 0%

indicate 0% on COMBINED on COMBINED INTERMEDIATE INTERMEDIATE STOP STOP VALVE POSITION VALVE POSITION indicators.

indicators.

  • Contacts field operator to close SatiUnsat 2DSM-TK4A Emergency 2DSM-LV78A,2DSM-TK4A Drain control Valve, at Panel Emergency Drain control Valve, 2CES-1 PN L204. at Panel 2CES-IPI\IL204.

Cue: As field operator report the valve is closed.

NIVIP2 2010 NRC JPM S-6 -6 November 2010

Cue: As field operator report the valve is closed.

15. IF during shell warming the (J Reviews step and continues SatiUnsat Turbine rolls off Turning Gear, immediately stop shell warming by performing the following:
  • Close 2MSS-MSV1 D, MSV2, by pushing the DECREASE pushbutton UNTIL CHEST/SHELL WARMING DEMAND meter indicates <0 Percent.
16. Start shell warming by (J Reviews the note regarding soak preheating crossaround piping time requirements.

as follows:

Procedure Note:

The High Pressure Turbine Shell Inner Temperature will be utilized in determining soak time requirements of Attachment 1.

17. Record High Pressure Turbine (J Records High Pressure Turbine SatiUnsat Shell Inner Temperature in Shell Inner Temperature in Control Control Room Log, using Room Log, using Computer Point Computer Point TMITA10 OR TMITA10 OR TMITA14, OR 2TMI TMITA14, OR 2TMI-TJR137, TJR137, Point 4.

Point 4.

Cue: When applicant checks temperature, provide a value of 80°F

18. Throttle 2MSS-MSV1 D, MSV2 (J Throttles 2MSS-MSV1 D, MSV2 Pass/Fail (Turbine Main Stop Valve), by (Turbine Main Stop Valve), by intermittently pushing intermittently pushing INCREASE or INCREASE or DECREASE DECREASE pushbuttons as push buttons as necessary at necessary at MAIN STOP VALVE MAIN STOP VALVE POSITION POSITION DEMAND FOR DEMAND FOR CHEST/SHELL CHEST/SHELL WARMING control.

WARMING control.

NMP2 2010 NRC JPM 8-6 7 November 2010

I Performance Steps I Standard Grade

19. At 2CEC*PNL842, monitor D Monitors Crossaround Piping SatlUnsat Crossaround Piping Temperature on 2TMI Temperature on 2TMI TR137/ZDR135, TURBINE TR137/ZDR135, TURBINE TEMP.

TEMP.

Cue: Temperatures indications are rising Examiner Note: When the candidate is cued regarding Crossaround Piping Temperature, the JPM may be terminated TERMINATING CUE: Shell Warming in service with crossaround piping temperature being monitored.

RECORD STOP TIME,_ _ __

NMP2 2010 NRC JPM S-6 November 2010

TURNOVER SHEET INITIAL 1. Reactor Pressure is 65 psig.

CONDITIONS:

2. Main Turbine Turning Gear is in operation.
3. N2-0P-21 "Main Turbine System" Section E.3.0.

is complete through step E.3.1.

INITIATING CUES: "(Operators name), Place main turbine shell warming in service in accordance with N2-0P-21, Section E.3.0. beginning at step E.3.2."

NMP2 2010 NRC JPM S-6 November 2010

NRC JPM 5-7 Constellation Energy Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Downshift Reactor Recirculation Pumps Revision: NRC 2010 Task Number: NA Approvals:

<) f!1t:.Jt( ~ NA Exam Security I General Supervis r General Supervisor Date Operations Training (Designee) Operations (Designee)

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

Trainer/Evaluator:_ _ _ _ _ _ _ __

Evaluation Method: ------'X'-'--__Perform _ __Simulate Evaluation Location: _ _Plant _-!X~Simulator Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: Completion Time: _ _ __

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

Comments:

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

NRC 2010 JPM S-7 November 2010

Recommended Start Location:

Simulator Simulator Set-up:

Reset to IC-175 Directions to the Instructor!Evaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Auxiliary Operators.

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

Read Before Each Evaluated JPM Performance:

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

concurrent verification will not be provided; therefore it should not be requested.

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used.

Therefore, either another individual or I will act as the additional! concurrent verifier.

Notes to Instructor / Evaluator:

1. Critical steps are identified as Pass/Fail. All steps are sequenced critical unless denoted by a".".
2. During Evaluated JPM:
  • Self-verification shall be demonstrated.
3. During Training JPM:
  • Self-verification shall be demonstrated.
  • No other verification shall be demonstrated.

References:

1. N2-0P-29 G.1.0
2. NUREG KIA 202001 A4.01 3.7/3.7 NRC 2010 JPM 8-7 November 2010

Tools and Equipment:

1. None Task Standard:

Recirculation pumps 1A and 1B running in slow speed with their flow control valves full open.

NRC 2010 JPM S-7 November 2010

Initial Conditions:

1. The plant is at 41 % power.
2. The Rod line is at 60%.
3. Hydrogen injection has been secured.

Initiating cue:

"(Operators name), Transfer Recirc Pumps from high speed to low speed per N2-0P-29 section G.1.0."

I Performance Steps I Standard Grade

1. Provide repeat back of initiating cue. o Proper communications used for repeat SatlUnsat Evaluator Acknowledge repeat back back (GAP-OPS-01) providing correction if necessary RECORD START TIME
2. Obtain a copy of the reference o N2-0P-29 obtained. Precautions & SatlUnsat procedure and review/utilize the correct Limitations reviewed and section G.1.0 section. referenced
3. Verify the following:

o LOW FREQ MG SET DRIVE MOT o Verifies BRKRs 1AlB are open (Green SatlUnsat BRKR 1A1B are open AND control Lights ON and Red Lights OFF) AND switches in NORMAL. control switches in NORMAL o LOW FREQ MG SET GEN BRKR o Verifies BRKRs 2A1B are open (Green SatlUnsat 2A1B are open AND control switches Lights ON and Red Lights OFF) and in NORMAL. control switches in NORMAL o GENERATOR LOCKOUTS K110A o Verifies GENERATOR LOCKOUTS Sat/Unsat AND K110B are reset and White K110A AND K11 OB are reset and White Lights are illuminated at RECIRC Lights are illuminated at RECIRC SYSTEM LFMG SET AUXILIARY SYSTEM LFMG SET AUXILIARY PANEL PANEL B35-P001A(B). (Normal B35-P001A(B). (Normal Switchgear EL.

Switchgear EL. 293') 293')

J Relays at B35-P001A(B) are reset Cue: When asked, report that LFMG generator & pump motor lockout and relays are reset
4. At 2NPS-SWG004 (SWG005), confirm o Confirms breaker 1 at 2NPS-SWG004 SatlUnsat breaker 1, REACTOR (SWG005), REACTOR RECIRCULATION RECIRCULATION PUMP MOTOR PUMP MOTOR BRKR - 2A(B) 2RCS BRKR - 2A(B) 2RCS-M1A(B) is M1A(B), is charged as indicated by yellow charged as indicated by yellow indicator indicator on lower left of breaker.

on lower left of breaker.

Cue: Acknowledge request and report that breaker 1 on both NPS-SWG004 and 005 are charged.

NRC 2010 JPM 8-7 November 2010

5. Position AND hold BRKR 5A(B) D Rotates BRKR 5A control switch to Pass/Fail RECIRC PMP 1A(B) MOTOR A(B) TRANSFER MG control switch to TRANSFER MG, D Rotates BRKR 5B control switch to Pass/Fail THEN position AND hold BRKR 5B(A) TRANSFER MG RECIRC PMP 1B(A} MOTOR B(A} D WHEN BRKR 5A and BRKR 5B are Pass/Fail control switch to TRANSFER MG. observed to OPEN, THEN releases BRKR 5A and BRKR 5B control switches to Normal.

WHEN BRKR 5A and BRKR 5B are observed to OPEN, THEN release BRKR 5A and BRKR 5B control switches to Normal.

Instructor Note:

The following annunciators alarm not requiring action:

  • 603139 "Reactor Water Level High" (in/clear)
  • 603218 "OPRM Trip Enabled" (clears)
  • 842310 "HWC Trouble" (reflashes)
  • 851456 "Cnst System Trouble No Backup Pmp Available (in/clear)
  • 601225 Recirc PmP 1AAuto Trip Low Speed Transfer
  • 601226 Recirc PmP 1B Auto Trip Low Speed Transfer
6. Observe the following:
  • BRKR 1AAND BRKR 1B close. D Observes BRKR 1A red light ON and SatiUnsat green light OFF D Observes BRKR 1B red light ON and SatiUnsat green light OFF
  • Pump speed lowers to between 460 D Observes speed on B35-R651A and B SatiUnsat AND 350 rpm. lowers to between 460 AND 350 rpm.
  • BRKR 2A AND BRKR 2B close. D Observes BRKR 2A red light ON and SatiUnsat green light OFF D Observes BRKR 2B red light - ON and SatiUnsat green light OFF
  • Pump speed stabilizes at about 445 D Observes speed on B35-651A and B SaUUnsat rpm. stabilizes at about 445 rpm NRC 2010 JPM 5-7 November 2010

I Performance Steps I Standard Grade

7. Using 2RCS-HC1603A RECIRC LOOP o Raises output signals for RECI RC LOOP Pass/Fail A FLOW CONTROL station, raise A and B FLOW CONTROL to 100%.

output signal to 100% (about 85% o Observe loop A VALVE POSITION at SatiUnsat VALVE POSITION INDICTED) about 85%

o Observe loop B VALVE POSTION at SatiUnsat Using 2RCS-HC1603B RECIRC LOOP about 95%

B FLOW CONTROL station, raise output signal to 100% (about 95%

VALVE POSITION indicated)

Instructor Note: The following annunciator alarms not requiring action:

  • 603218 "OPRM Trip Enabled"
8. Monitor the following recirculation o Observe about 73 amps on AM- SatiUnsat pump/LFMG parameters: 2RCSA(B)60
  • About 73 amps on AM- o Observe approximately 450 rpm on B35- SatiUnsat 2RCSA(B)60, RCS-MG1A(B) R651A(B).

CURRENT. o Dispatches an Auxiliary Operator to report SatiUnsat

  • Recirc pump speed approximately LFMG generator voltage and amperage.

450 rpm on B35-R651A(B),

RECIRC PI\t1P 1A(B) SPEED.

  • At Switchgear Bldg. Penthouse EI.

293"on B35- P001A(B), LFMG generator voltage 1250 V, on V GENERATOR VOLTS.

  • At Switchgear Bldg. Penthouse EI.

293"on B35- P001A(B), less than 100 Amps (continuous load) on A GENERATOR AMPS.

Cue: As the Auxiliary Operator, report that LFMG 'A' generator indicates 1250 volts and 95 amps. Also, LFMG '8' generator indicates 1250 volts and 94 amps.

9. Reports that Recirc pumps have been transferred to slow speed.

Cue: Acknowledge the report.

TERMINATING CUE: Recirc pumps 1A and 1B running in slow speed.

RECORD STOP TIME _ _ __

NRC 2010 JPM S-7 November 2010

TURNOVER SHEET INITIAL 1. The plant is at 41 % power.

CONDITIONS: 2. The Rod line is at 60%.

3. Hydrogen injection has been secured.

INITIATING CUES: "(Operators name) Transfer Recirc Pumps from high speed to low speed per N2-0P-29 section G.1.0."

NRC 2010 JPM $-7 November 2010

NRC JPM 5-8 Constellation Energy Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Shift RBCLCW and TBCLCW Pumps Revision: NRC 2010 Task Number: NA NA Exam Security I General Supervisor Date Operations (Designee)

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

Trainer/Evaluator:_ _ _ _ _ __

Evaluation Method: ~X,-,--__Perform _ __Simulate Evaluation Location: _ _,Plant _-!X:...:.-Simulator Expected Completion Time: 20 min. Time Critical Task: No Alternate Path Task: 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 Signature: _ _ _ _ _ _ _ _ _ _ _ _ __ Date:_ _ _ _ __

NRC 2010 JPM 5-8 November 2010

Recommended Start Location:

Simulator Simulator Set-up:

1. Resetto IC 186
2. Remote malfunction CW-27 set for 102°F on Trigger 1
3. Event trigger1, hzlcw1 ccsa01 (1 )==1, will activate when CCS-P1A stopped (green light on)

Directions to the Instructor/Evaluator:

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

CRO permission.

Directions to Operators:

Read Before Every JPM Performance:

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor I Evaluator:

1. Critical steps are identified as Pass/Fail. All steps are sequenced critical unless denoted by a "e".
2. During Evaluated "IPM:

e Self-verification shall be demonstrated.

3. During Training JPM:
  • Self-verification shall be demonstrated.
  • No other verification shall be demonstrated.

References:

1. N2-0P-13
2. N2-0P-14 NRC 2010 JPM S-8 November 2010
3. ARP 601244
4. NUREG KJA 400000 A4.01 Tools and Equipment:
1. None Task Standard:

RBCLCW and TBCLCW pumps shifted with TBCLCW temperature being controlled manually Initial Conditions:

1. The plant is operating at full power.

Initiating Cue:

  • To support Maintenance checks, shift CCP Main Pumps from "A", "B" lineup to "B", "C" lineup, lAW N2-0P-13, Section F.2.0 and F.3.0.
  • Then shift CCS Pumps from "A", "B" lineup to "8", "c" lineup lAW N2-0P-14, Section F.3.0 and FAO.
  • A plant operator is stationed at the pumps to support pump swaps and perform pump checks.

I Performance Steps I Standard Grade

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

providing correction if necessary RECORD START TIME

2. Obtain a copy of the reference procedure Cl N2-0P-13 & N2-0P-14 obtained. SatlUnsat and review/utilize the correct section. Precautions & limitations reviewed.
3. For the Main CCP pump to be started, Cl Ensures pump is checked and SatlUnsat verify the pump casing is free of air as vented by plant operator.

follows:

  • Uncap AND throttle open 2CCP-V195 (Vi96, V197), PiA (8,C) VENT. WHEN a steady stream of water is observed, close AND recap 2CCP-Vi95 (Vi96, V197).

Cue: Checked by local operator. Pump has been vented and the vent valve has been closed and capped.

NRC 2010 JPM S-8 3- November 2010

I Performance Steps I Standard Grade

4. For the Main CCP pump to be started, at o Places control switch for 2CCP Pass/Fail paneI2CEC*P601, start 2CCP-P1A (B,C), P1 C in red flagged position.

PMP 1A (B,C), by placing control switch in Normal-After-START (red flagged).

Note: The operator may also make a plant announcement on the page system that 2CCP-P1C is being started.

Note: The applicant will check board indications for amps and discharge pressure.

5. Confirm normal operating indications in o Ensures operating parameters are SatlUnsat accordance with Subsection F.1.0. checked by plant operator.

Cue: Local indications are normal

6. At 2CEC*PNL601, secure 2CCP-P1A (B,C), 0 Places control switch for 2CCP- Pass/Fail PMP 1A (B,C), by placing control switch in P1A in green flagged position.

Normal-After-STOP. (Green flagged)

7. IF required, place 2CCP-P1A (B,C) control Q May request required status of SatlUnsat switch in PULL TO LOCK. pump control switch.

CUE: If asked, the pump can be placed in PULL TO LOCK at this time.

8. Confirm normal operating indications in o Ensures operating parameters are SatlUnsat accordance with Subsection F.1.0. checked by plant operator.

Cue: Another operator will check local indications Examiner Note: The applicant will now refer to N2-0P-14 for TBCLCW operations Procedure Note:

  • CCS system flow of greater than 8000 gpm requires more than one heat exchanger in service.
  • Actions in this Subsection are performed at 2CEC*PNL601 unless otherwise specified.

NRC 2010 JPM 8-8 November 2010

I Performance Steps I Standard Grade

9. IF time permits, perform the following: o Dispatched operator or determines SaUUnsat
  • Dispatch an Operator to the pump to task has been performed.

perform prestart inspection AND observe pump during start.

  • For the pump to be started, close 2CCS-V303A(B,C), TBCLC PUMP 1A(B,C) STOP CHECK.

Cue: Pre-start checks are complete and the stop-check valve is CLOSED

10. Start 2CCS-P1A(B,C), PMP 1A(B,C), by o Places control switch for 2CCS Pass/Fail placing the control switch to Normal-After P1 C in red flagged position.

START (red flagged).

Note: The operator may also make a plant announcement on the page system that 2CCS-P1C is being started

11. Slowly open 2CCS-V303A(B,C). o Directs local operator to open SaUUnsat valve.

Cue: Valve has been opened

12. Confirm normal operating indications in o Ensures operating parameters are SaUUnsat accordance with Subsection 1.0. checked by plant operator.

Cue: Local indications are normal Procedure Note: o Checks indications Sat/Unsat

  • Actions in this Subsection are performed at 2CEC*PNL601 unless otherwise specified.
  • CCS Pump runout is 8,500 gpm. If system flow is greater than 8,000 gpm for one pump operations or 16,000 gpm for two pump operations, then starting an additional pump increases the probability of damaging tube vibrations in the CCS heat exchangers.

Three CCS pump operation shall be avoided unless shifting of pumps is required.

NRC 2010 JPM S-8 November 2010

13. Confirm the CCS pump is NOT required for CCS System flow as follows:

Computer Pt CCSFA01 # of Running TBCLCW PMP SUCTION FLW Pumps 1,000 - 8,200 GPM 1 8,200 - 16,400 GPM 2 Cue: A CCS pump is NOT required - flow is normal Procedure Note: 2CCS-V303A (B,C) is o Directs a local operator to close SatlUnsat located at 2CCS-P1A (B,C) on T8 Elev 250 valve Southwest.

14. Close 2CCS-V303A (B,C), TBClC PUMP 1A (B,C) STOP CHECK.

Cue: Valve is closed

15. Secure 2CCS-P1A (B,C), PMP 1A (B,C), o Places control switch for 2CCS Pass/Fail by placing the control switch in Normal P1A in green flagged position After-STOP. (Green flagged)

Console Operator: Ensure Trigger 1 to fail TBClC temperature controller activates when 2CCS-P1A is stopped. (REMOTE CW 27 set for 102°F)

16. IF required, place 2CCS-P1A (B,C) control 0 May request required status of SatlUnsat switch in PULL TO lOCK. pump control switch.

Cue: If asked, the pump can be placed in PUll TO lOCK at this time.

17. Confirm normal operating indications for o Ensures operating parameters are SatlUnsat the running CCS Pump(s) in accordance checked by plant operator.

with Subsection F.1.0.

Examiner Note: Applicant will respond to annunciator 601244 (Turbine Bldg Closed loop Cooling Sys Trouble) and Computer Point CCSTC04 for TBClCW HX DISCH TEMP NRC 2010 JPM S-8 November 2010

I Performance Steps I Standard Grade

18. Determines temp controller is failed and (:J Performs either: Sat/Unsat refers to ARP 601244 or SOP-14
  • Enters SOP-14, Loss or Degraded CCs System
19. Places 2CCS-TIK104 in "M" Manual (:J Places controller in "M" Manual Pass/Fail
20. Manually controls temperature (:J Adjusts temperature downward to Pass/Fail approximately 85°F TERMINATING CUE: JPM is complete when TBCLCW temperature is being controlled manually.

RECORD STOP TIME,_ _ __

NRC 2010 JPM 8-8 November 2010

TURNOVER SHEET INITIAL The plant is operating at full power.

CONDITIONS:

INITIATING CUES:

  • To support Maintenance checks, shift CCP Main Pumps from "A", "8" lineup to "8", "C" lineup, lAW N2-0P-13, Section F.2.0 and F.3.0.
  • Then shift CCS Pumps from "A", "8" lineup to "8", "c" lineup lAW N2-0P-14, Section F.3.0 and F.4.0.
  • A plant operator is stationed at the pumps to support pump swaps and perform pump checks.

NRC 2010 JPM S-8 November 2010

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

Title:

Start the Diesel Fire Pump Locally Revision: NRC 2010 Task Number: NA Approvals:

NA Exam Security I General Supervisor Date Operations (Designee)

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

Trainer/Evaluator:_ _ _ _ _ _ _ _ _ _ __

Evaluation Method: _ _ _Perform _ _--=-:X'--_Simulate Evaluation Location: -,X~__Plant _ _ _ _ _Simulator Expected Completion Time: 30 min. 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 Signature: _ _ _ _ _ _ _ _ _ _ _ __ Date:_ _ _ _ __

NRC 2010 JPM P-1 November 2010

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

Any location Simulator Set-up (if required):

N/A Directions to the Instructor/Evaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM 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 as Pass/Fail. All steps are sequenced critical unless denoted by a".".
2. During Evaluated JPM:
  • Self-verification shall be demonstrated.
3. During Training JPM:
  • Self-verification shall be demonstrated.
  • (Additional/Concurrent/No other) verification shall be demonstrated.

NRC 2010 JPM P-1 November 2010

References:

N2-0P-43, Fire Protection Water Tools and Equipment:

None Task Standard:

Diesel Fire Pump in service.

Initial Conditions:

A start of the Diesel Fire Pump is required for a hydro of the fire hoses.

Initiating Cues:

Start Diesel Fire Pump 2FPW-P1 locally at panel 2FPW-PNL234 lAW N2-0P-43 Section E.3.0.

I Performance Steps I Standard Grade

1. Provide repeat back of initiating o Proper communications used for SatlUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
2. Obtain a copy of the reference o N2-0P-43 obtained. Precautions & SatlUnsat procedure and review/utilize the Limitations reviewed.

correct section.

3. PRIOR to starting the pump, o Notifies the Fire Brigade Leader SatlUnsat notify the Fire Brigade Leader. prior to starting the pump.

Cue: Acknowledge as Fire Brigade Leader.

Note: The following step is performed inside 2FPW-PNL234 in the Diesel Fire Pump Room.

NRC 2010 JPM P-1 November 2010

I Performance Steps . Standard Grade

4. IF applicable, locally start 0 Locally start 2FPW-P1, Diesel 2FPW-P1, Diesel Engine Driven Engine Driven Fire Pump, as Fire Pump, as follows: follows:

Note: Annunciator 849221, DIESEL FIRE PUMP NOT IN AUTO START, will alarm in the next step.

  • Place the SELECTOR switch
  • Places the SELECTOR switch in SaUUnsat in MAN Aor B. MAN Aor B.
  • Starts 2FPW-P1 by depressing SaUUnsat the START pushbutton. the START pushbutton.

Cue: The diesel fire pump failed to crank and is not running

5. IF 2FPW-P1 fails to crank, D Reviews the procedure then perform the following: performs the following:
  • Briskly turn the SELECTOR
  • Briskly turns the SELECTOR Pass/Fail switch to the opposite switch to the opposite Manual Manual position position
  • Starts 2FPW-P1 by depressing Pass/Fail depressing the START the START pushbutton.

pushbutton.

Cue: You hear the pump running Note: The following parameters should be monitored at 5 minute intervals during the first 15 minutes of pump operation and then once per hour.

NRC 2010 JPM P-1 November 2010

I Performance Steps Standard Grade

6. Confirm proper pump operation 0 Confirms proper pump operation as SatiUnsat as indicated by the following indicated by the following:
  • No unusual noise OR
  • Checks for unusual noise OR SatiUnsat vibrations vibrations Cue: Sat
  • NO RED lights lit ON
  • System pressure is == 150
  • Checks that system pressure is SatiUnsat psig as indicated on one of == 150 psig as indicated on one the following: of the following: (list in left hand column)

Cue: Respond that system press indicates:: 150 psig.

  • Engine speed is == 1950
  • Checks engine speed is == 1950 SatiUnsat RPM as indicated on the RPM as indicated on the diesel.

diesel Cue:  :: 1950 RPM.

  • Checks Lube oil pressure is SatiUnsat psi as indicated on the 59 - 80 psi as indicated on the diesel diesel.

Cue:  :: 70 psi.

  • Jacket water temperature is
  • Checks Jacket water SatiUnsat 165 - 195°F as indicated on temperature is 165 -195°F as 2FPW-TI1012, DSL ENG indicated on 2FPW-TI1012, COOLANT TEMP gauge, DSL ENG COOLANT TEMP on the diesel gauge, on the diesel.

Cue:  :: 180°F.

NRC 2010 JPM P-1 November 2010

I Performance Steps I Standard Grade

7. Observe 2FPW-PDI211, CJ Observes 2FPW-PDI211, DIESEL Sat/Unsat DIESEL FIRE PUMP FIRE PUMP DISCHARGE DISCHARGE STRAINER DP. STRAINER DP.

Cue: Respond that DP = 6 PSID

8. Reports to Control Room that Notifies CR that pump is running Sat/Unsat the pump is in service TERMINATING CUE: This J PM is complete when diesel fire pump is in service.

RECORD STOP TIME,_ _ _ __

NRC 2010 JPM P-1 November 2010

TURNOVER SHEET INITIAL A start of the Diesel Fire Pump is required for a CONDITIONS: hydro of the fire hoses.

INITIATING CUES: Start Diesel Fire Pump 2FPW-P1 locally at PNL 2FPW-PNL234 lAW N2-0P-43.E.3.0.

NRC 2010 JPM P-1 November 2010

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

Title:

Hydro Pump Boron Injection Revision: NRC 2010 Task Number: NA Approvals:

NA Exam Security /

General Supervisor Date Operations (Designee)

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

Trainer/Evaluator:

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

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

Comments:

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

NRC 2010 JPM P-2 -1 November 2010

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

RB 289 Outside CRD Maintenance Room Simulator Set-up (if required):

None Directions to the Instructor/Evaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CRO, and Plant Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions 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 ..IPM, applicable methods of verification are expected to be used.

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

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas as Pass/Fail. All steps are sequenced critical unless denoted by a u e ".
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 2010 JPM P-2 November 2010

References:

N2-EOP-6, Att. 15, "SLS Hydro Injection" NUREG 1123: 295037 EA1.10 3.7/3.9 Tools and Equipment:

Breakaway tie-wrap for EOP Box Task Standard:

Using hydro pump and hoses staged, establish a f10wpath from SLS tank to the Reactor Vessel complete with an air supply to the pump and commence Boron injection.

Initial Conditions:

  • Boron injection is required.

Initiating Cues:

Commence boron injection with the hydro pump lined up to 2SLS*P1A piping in accordance with EOP-6, Attachment 15.

  • Performance Steps I Standard Grade
1. Provide repeat back of initiating CJ Proper communications used for SatlUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
2. Obtain a copy of the reference CJ N2-EOP-6, Att. 15 obtained. Section SatlUnsat procedure and review/utilize the 3.1 referenced.

correct section.

3. Locate equipment. EOP Box CJ At EOP box, open box, remove SatlUnsat Adjacent to SLS Tank, Rx Bldg. equipment, and check to ensure EI. 289 specified equipment contained.

Note: For simulation purposes, actual layout of hoses and connection to pump or plant equipment is not required. Identification of hose and use along with connection points is all that is required.

NRC 2010 JPM P-2 November 2010

I Performance Steps I Standard Grade

4. Remove plug from 2SLS*V42, a At 2SLS*V42, remove test conn. Pass/Fail 2SLS*P1A SUCTION PRESS plug by rotating plug counter TEST CONN. (Rx Bldg, EL 289, clockwise.

SLS Area)

Cue: Simulate plug removed.

5. Using 25 ft hard suction hose o At 2SLS*V42, connect 25' black Pass/Fail (black) with brass couplings suction hose by rotating brass AND the appropriate coupling clockwise into the test connections, connect hose to connection.

2SLS*V42. (Rx Bldg, EL 289, SLS Area)

Cue: Simulate hose connected.

6. Using 25 ft hard suction hose a At hydro pump, connect 25' black Pass/Fail (black) with brass couplings suction hose by rotating brass AND the appropriate coupling clockwise onto the suction connections, connect hose to connection. (Located on the bottom suction side of Hydro Pump. (Rx of the pump.)

Bldg, EL 289, SLS Area)

Cue: Simulate hose connected.

7. Remove cap downstream of a At 2SLS*V35, remove pipe cap by Pass/Fail 2SLS*V35, INJECTION rotating cap counter clockwise.

HEADER DRAIN VLV. (Rx Bldg, EL 289, SLS Area)

Cue: Simulate cap removed.

8. Using 25 ft Hydro Hose with Hi a AT 2SLS*V35, connect 25' hydro Pass/Fail Press SS Couplings AND the hose by rotating hose coupling appropriate connections, clockwise onto the drain connection.

connect hose to 2SLS*V35. (Rx Bldg, EL 289, SLS Area)

Cue: Simulate hose connected.

NRC 2010 JPM P-2 November 201 0

I Performance Steps

  • Standard Grade
9. Using 25 ft Hydro Hose with Hi o At hydro pump, connect 25' hydro Pass/Fail Press SS Couplings AND the hose by inserting hose coupling into appropriate connections, pump discharge disconnect.

connect hose to discharge side (Located middle of hydro unit.

of Hydro Pump. Downstream of Relief Valve.)

(Rx Bldg, EL 289, SLS Area)

Cue: Simulate hose connected.

10. Close 2MWS-V24, MWS TO o Close 2MWS-V24. Sat/Unsat SLC SYSTEM ISOL. (Rx Bldg, EL 289, on top of SLS tank)

Cue: 2MWS-V24 is closed.

NRC 2010 JPM P-2 November 2010

I Performance Steps I Standard Grade Note to Evaluator: The evaluator should cue the candidate that the power supply breaker is opened. At the evaluators discretion, the evaluator can ask the candidate to locate 2EHS*MCC102 breaker-17D (North Aux Bay EI 240) at the completion of the JPM while transitioning to perform remaining JPMs.

11. Open 2SLS*MOV1A, STORAGE o Manually open SLS*MOV1 A TANK OUTLETVLV, manually
  • Open supply breaker to as follows: 2SLS*MOV1A SatlUnsat NOTE: A CAT 60 key may
  • Manually open MOV by rotating be required for entry at handle counter clockwise. Pass/Fail 2EHS*MCC102.
  • Place 2EHS*MCC1 02-170, 2SLS*MOV1A, SLCS STORAGE TANK OUTLET MOV to OFF. (Aux Bay North, EL 240)
  • Open 2SLS*MOV1A, manually (Rx Bldg, EL 289, SLS Area)

Cue: 2EHS*MCC102-17D is OFF, MOV is OPEN.

12. Open 2SLS*V42, 2SLS*P1A o At 2SLS*V42, rotate the valve Pass/Fail SUCTION PRESS TEST CONN. handwheel counter clockwise until (Rx Bldg, EL 289, SLS Area) the valve is at the full open position.

Cue: Simulate 2SLS*V42 open.

Note: Procedure transition to Section 3.3 to establish boron injection.

13. Open 2SLS*V35, INJECTION o At 2SLS*V35, rotate the valve Pass/Fail HEADER DRAIN VLV. (Rx Bldg, handwheel counter clockwise until EL 289, SLS Area) the valve is in the full open position.

Cue: Simulate 2SLS*V35 open.

NRC 2010 JPM P-2 6- November 2010

I Performance Steps Standard Grade o

14. Open 2SLS*V34, INJECTION o At 2SLS*V34, rotate the valve Pass/Fail HEADER DRAIN VLV. (Rx Bldg, handwheel counter clockwise until EL 289, SLS Area) the valve is in the full open position.

Cue: Simulate 2SLS*V34 open.

15. Verify open, EITHER o Contact control room and request Pass/Fail (2CEC*PNL601): valve position for 2SLS*MOV5A1B.
  • 2SLS*MOV5A OR
  • 2SLS*MOV5B:

Cue: Simulate valve open.

16. Using 50 ft Air Hose, connect o At hydro pump, connect 50 foot air Pass/Fail air hose to Hydro Pump VLV. hose fitting onto hydro pump air line (Rx Bldg, EL 289, SLS Area) quick disconnect fitting.

Cue: Simulate hose connected.

17. Verify closed, Hydro Pump o At hydro pump verify:

Manual Air Inlet Isolation and

  • Air inlet isolation closed. SatlUnsat tension is backed off air
  • Tension is backed off air SatlUnsat regulator spring .. (Rx Bldg, EL regulator spring.

289, SLS Area)

Cue: Isolation valves shut, regulator spring tension backed off.

18. Using 50 ft Air Hose, connect air o At 2SAS-V529, connect air hose Pass/Fail hose from Hydro Pump to 2SAS fitting into service air quick V529, SERVICE AIR disconnect fitting.

CONNECTION located behind SLS pump.

(Rx Bldg, EL 289, SLS Area)

Cue: Simulate hose connected.

NRC 2010 JPM P-2 November 2010

I Performance Steps I Standard Grade o

19. Open 2SAS-V529. (Rx Bldg, EL o Opens 2SAS-V529 PasslFail 289, SLS Area)

Cue: Simulate V529 open.

20. OPEN Hydro Pump Manual Air o Open air line isolation valve by Pass/Fail Inlet Isolation. (Rx Bldg, EL 289, rotating T -handle counter clockwise SLSArea) to the in-line position.
21. Start Hydro Pump by tightening o Adjust spring tension on air Pass/Fail spring tension on Hydro Pump regulator.

Air Regulator. (Rx Bldg, EL 289, SLSArea)

Cue: Simulate Hydro Pump is running.

TERMINATING CUE: Hydro pump running with flowpath established from SLS tank to Reactor Vessel.

RECORD STOP TIME _ _ __

NRC 2010 JPM P-2 November 2010

TURNOVER SHEET INITIAL

  • Boron injection is required.

CONDITIONS:

INITIATING CUES: "(Operators name), Commence boron injection with the hydro pump lined up to 2SLS*P1A piping in accordance with EOP-6, Attachment 15."

NRC 2010 JPIVI P-2 November 2010

NRC JPM P-3 Constellation Energy Group NINE MILE POINT UNIT 2 OPERATOR JOB PERFORMANCE MEASURE

Title:

Reset an EPA Breaker Revision: NRC 2010 Task Number: NA Approvals:

'.;,::';?t!:.J.l< !:i..t:!."""""-~I:!:!.t!!:.:J6:::;..+--,L:':::"":":~~::-"~.L.::I.::::::.;,.,i.'...IZ:."" It' NA Exam Security I General Supervis General Supervisor Date Operations Traini g (Designee) Operations (Designee)

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

Trainer/Evaluator:_ _ _ _ _ _ _ _ _ _ __

Evaluation Method: _ _ _Perform _ _--'-'X'--_Simulate Evaluation Location: X Plant _ _ _ _ _Simulator Expected Completion Time: 10 min. Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: Completion Time: _ _ __

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

Comments:

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

NRC 2010 JPM P-3 November 2010

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

EPA Breaker 2VBS*ACB2A Simulator Set-up (if required):

None Directions to the Instructor/Evaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues.

Read Before Each Evaluated JPM Performance:

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

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

Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used.

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

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading areas as 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.
  • No other verification shall be demonstrated.

NRC 2010 JPM P-3 November 2010

References:

1. N2-S0P-97, FLOWCHART LEG B
2. NUREG KIA 262001 2.1.23
3. Bank JPM 2102-PJE264C01 Rev 0 Tools and Equipment:

None Task Standard:

Reset and close EPA Breaker 2VBS*ACB2A.

Initial Conditions:

1. The plant is operating at 100% power.
2. EPA Breaker 2VBS*ACB1A is closed.
3. EPA Breaker 2VBS*ACB2A is tripped.
4. EPA Breaker 2VBS*ACB2A Overvoltage target light is LIT.

Initiating Cues:

Reset EPA Breaker 2VBS*ACB2A in accordance with N2-S0P-97.

1. Provide repeat back of initiating CJ Proper communications used for SatlUnsat cue. Evaluator Acknowledge repeat back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME
2. Obtain a copy of the reference CJ N2-S0P-97 obtained. SatlUnsat procedure and review/utilize the FLOWCHART RESETTING correct section. VBS/RPM EPA'S (LEG B) is referenced.
3. Are both EPS's tripped? CJ Determines only EPA 2VBS*ACB2A SatlUnsat is tripped and answers as NO.

Cue: At ACB2A - Output power lamp is OFF NRC 2010 JPM P-3 November 2010

I Performance Steps I Standard Grade

4. At ACB2A attempt to reset o Attempts to reset tripped relay flags. SaUUnsat any tripped relay flags Determines overvoltage relay will not reset.

Cue: Overvoltage target flag indicates orange

5. Can all relay trip flags be reset? 0 Determines overvoltage relay will SaUUnsat not reset and answers NO.

Cue: Overvoltage target flag indicates orange

6. Note the relays that have Q Notes the overvoltage relay is SaUUnsat tripped. tripped.
7. Bypassing the overvoltage Q Performs the following:

protective relay.

Cue: Cue the Candidate, as each step occurs:

  • Remove the black plastic
  • Simulate REMOVING the black Pass/Fail cover for the relay that plastic tamper proof cover for cannot be reset. the OVERVOLTAGE TEST SW, located to the right of the Overvoltage Relay,
  • Open the red knife switch
  • Simulate BYPASSING the Pass/Fail 90 degrees. protective function by simulating OPENING the "RED" KNIFE SWITCH 90°.

8, Reset ACB2A by taking the 0 Simulate a RESET of EPA Breaker switch from 'TRIP" to "RESET to 2VBS*ACB2A.

"ON",

  • Simulate placing the OUTPUT Pass/Fail breaker (handle) in the RESET position from TRIP.
  • AND THEN simulate placing Pass/Fail the OUTPUT breaker (handle) in the ON position.

Cue: Output power lamp is LIT.

NRC 2010 ~IPM P-3 4- November 2010

I Performance Steps I Standard Grade

9. Notify Control Room of EPA o Notify the Control Room of status of SatlUnsat status. 2VBS*ACB2A
  • The EPA Breaker 2VBS*ACB2A is closed (RESET and ON).
  • The RED KNIFE SWITCH for OVERVOLTAGE is "OPEN".

Cue: Acknowledge the Candidate.

TERMINATING CUE: EPA Breaker 2VBS*ACB2A has been "RESET" and is "ON" with the Overvoltage relay function bypassed using the "red" Knife Switch.

RECORD STOP TIME _ _ __

NRC 2010 JPM P-3 5- November 2010

TURNOVER SHEET INITIAL 1. The plant is operating at 100% power.

CONDITIONS:

2. EPA Breaker 2VBS*ACB1A is closed.
3. EPA Breaker 2VBS*ACB2A is tripped.
4. EPA Breaker 2VBS*ACB2A Overvoltage target light is LIT.

INITIATING CUES: Reset EPA Breaker 2VBS*ACB2A in accordance with N2-S0P-97.

NRC 2010 JPM P-3 November 2010

NMP SIMULATOR SCENARIO NRC SCENARIO # 1 REV. 0 No. of Pages: 18 ADD WATER TO THE SUPPRESSION POOL WITH CSH/CSH MIN FLOW VALVE FAILS/RBCLCW PUMP TRIP/ECCS DIV 1 SPURIOUS INITIATION//STEAM LINE BREAK IN DRYWELULOSS OF OFF-SITE POWER! EDG II OUTPUT BKR FAILS TO AUTO CLOSE PREPARER S. Dennis/J. Reid DATE 7/17/10 VALIDATED DATE 7/20/10 GEN SUPERVISOR OPS TRAINING OPERATIONS MANAGER UNIT 2 .:...:Ne....;Ao....:E=x=a:..:...:m..:....S=e=c=u::..:..r:.:..ity'---_ _ _ _ _ _ __ DATE _ _ _ __

CONFIGURATION CONTROL .:...:N~Ao....:E=x=a:..:...:m-=-=S=ec=u::..:..r:.:..ity'---_ _ _ _ _ _ __ DATE _ _ _ __

SCENARIO

SUMMARY

Length: 60 minutes The scenario begins with the plant operating at 95% power. The crew will add water to the Suppression Pool using the High Pressure Core Spray System (CSH) per normal operating procedure N2-0P-33, High Pressure Core Spray. The crew must recognize the failure of the CSH Min flow valve and the Tech Spec implications.

Then, EHC oscillations will occur requiring entry to N2-S0P-23 and a power reduction lAW N2 SOP-101D. Once power is stabilized at a lower level, one of the running RBCLCW pumps will trip and the standby pump will fail to auto start. The standby pump can be manually started by the operators.

After the standby RBCLCW pump is started, ECCS DIV I spuriously initiates. The crew will take actions lAW the appropriate alarm response and operating procedures. The SRO will address Technical Specifications. Then, a Division 1 bus fault occurs requiring a reactor scram due to a loss of Service Water. EOP-RPV is entered.

A steam line break will occur in the drywell which requires entry to EOP-RPV and EOP-PC.

Once the operators take initial actions and control RPV level and pressure, a loss of Line 6 will occur. The operators must diagnose that the DIV II EDG output breaker failed to close in on its respective bus and take actions lAW SOP-3 to repower the bus (CRITICAL TASK).

Additionally, once power is restored, Drywell spray must be initiated to prevent pressure from exceeding the PSP limits (CRITICAL TASK).

The scenario ends when RPV level is restored and containment parameters are under control.

Major Procedures: N2-0P-33, N2-S0P-23, N2-S0P-1 01 D, N2-EOP-RPV, N2-EOP PC, SOP-03.

NMP2 2010 NRC Scenario # 1 November 2010

Dynamic Mitigation Strategy Code: PC3, High containment pressure, drywell sprays required, maintain safe region PSP, no Slowdown required Termination Criteria: Reactor is shutdown with RPV Level and Pressure controlled in the directed band and containment parameters improving.

NMP2 2010 NRC Scenario # 1 November 2010

I. SIMULATOR SET UP A. IC Number: IC 173, 95% Reactor Power B. Presets/Function Key Assignments

1. Malfunctions:
a. CW16C CCP-P1C FAILS TO AUTOSTART PRESET
b. CS08 CSH*MOV105 VALVE FAILS SHUT TRG 1
c. TC03A EHC PRESS REG FAILURE OSCILLATIONS TRG2
d. CW02A RBCLCW PUMP TRIP (P1A) TRG4
e. RH13A ECCS INADVERTENTLY INITIATES (DIV I) TRG5
f. ED05A 4.16KV EMERGENCY BUS FAULT (101) TRG6
g. MS04 STEAM LINE RUPTURE IN PRIMARY CONT.

4 minute delay, 1.5%, 8:00 minute ramp TRG7

h. ED02B LOSS OF OFF-SITE 115KV LINE 6 TRG7 2 minute delay
i. DG02A DIESEL GENERATOR NUMBER 1 TRIP TRG8
2. Remotes:
a. TC02 PRESS REGULATOR BIAS "A", 8.0 TRG3
3. Overrides:
a. OVR-05A2S030D172311 NAP EMER DIESEL GEN 3 OUTPUT BREAKER 103-14, OFF, 2 minute delay TRG7
4. Annunciators:
a. None C. Equipment Out of Service
1. None D. Support Documentation
1. Working copy of N2-0P-33, H.3.0 for use by crew OR plastic sleeve procedure sections to facilitate placekeeping. An already place-kept copy of F.1.0 is to be made and provided with turnover sheet, since the scenario assumes this section has already been completed.

E. Miscellaneous

1. Event Triggers
a. TRG 1 "csfhpcs>91". Activates when CSH flow exceeds 650 gpm (91 Ib/sec).
b. TRG 7 "zdrps1d==1". Activates when the mode switch is taken to shutdown.
c. TRG 15 "hzldgegsa01(2)==1". Activates to delete malfunction RH13A when Div I EDG starts (red running light is on). Command: DMF RH13A NMP2 2010 NRC Scenario # 1 November 2010

II. SHIFT TURNOVER INFORMATION SHIFT: N D DATE:

PART I: To be performed by the oncoming Operator before assuming the shift.

  • Control Panel Walkdown (all panels) (SM, ASM, STA, CRO, CRE)

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

  • Shift Turnover Checklist (ALL)
  • CRO Log (CRO)
  • Computer Alarm Summary (CRO)

(SM, ASM, STA, CRO, CRE)

Evolutions/General Information/Equipment Status:

  • Reactor Power = 95%
  • Loadline => 100%

PART III: Remarks/Planned Evolutions:

Raise Suppression Pool Water level to 200 feet using CSH pump per N2-0P-33. Establish CSH pump flow rate of 2000 to 3000 gpm. N2-0P-33 F.1.0 Standby Condition Status Checks are com plete.

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

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

TITLE I NAME TITLE NAME SM CRS STA CRO Other NMP2 2010 NRC Scenario # 1 4- November 2010

III. PERFORMANCE OBJECTIVES A. Critical Tasks:

CT-1.0 - Restore power to DIV II vital bus by closing the DIV II EDG output breaker IAWSOP-03.

CT-2.0 - Initiate Drywell spray when suppression chamber pressure is >10 psig to prevent exceeding the Pressure Suppression Pressure Limit.

NMP2 2010 NRC Scenario # 1 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 1 & 2 - Suppression Pool Fill Utilizing CREW CSH Pump With CSH*MOV105 Minimum Flow

  • Complete panel walk Valve Failure
  • SRO conducts pre-shift brief.
  • Crew assumes the shift.

SRO

  • Directs Suppression Pool fill per N2 OP-33, H.3.0
  • Enters Tech Spec 3.5.1 (as directed from N2-0P-33) Condition Band initiates Required Actions
  • B.1 Verify by administrative means RCIC System is OPERABLE when RCIC is required to be OPERABLE. (Completion Time is Immediately)

AND

  • B.2 Restore HPCS System to OPERABLE status. (Completion Time is 14 days)

NMP2 2010 NRC Scenario # 1 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 1 & 2 (Continued) BOP/RO

  • Verify Subsection F.1.0, Standby Condition Status Checks is complete.

(Actual performance is NOT required because completion was provided in Shift Turnover information.)

CAUTIONS DO NOT ALLOW THE CSH PUMP TO OPERATE IN A RUNOUT FLOW CONDITION OF > 7175 GPM OR PUMP DAMAGE MAY OCCUR.

MINIMIZE AMOUNT OF TIIVIE CSH IS OPERATING ON MINIMUM FLOW OR PUMP DAMAGE MAY OCCUR.

  • Start CSH*P1, HPCS PUMP 1.

After the CSH pump is started, Suppression Pool

  • Verify open CSH*MOV105, Level (SPL) will rise from initial/evel of 199.8 feet. MINIMUM FLOW BYPASS VLV.

It will take about 5 minutes to raise SPL to 200 feet.

  • Monitor CST AND Suppression Pool Levels.
  • Raise rate of transferring water from CST to Suppression Pool (2000 to 3000 gpm) by performing the following:
  • Throttle open CSH*MOV111 ,

TEST RETURN TO SUPPRESSION POOL NMP2 2010 NRC Scenario # 1 -7 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 1 & 2 (Continued) BOP/RO CONSOLE OPERATOR: Verify TRG 1

  • WHEN CSH System Flow is > 634 automatically activates as CSH flow rises. gpm, verify closed CSH*MOV105, CSOS CSH*MOV105 VALVE FAILS SHUT MINIMUM FLOW BYPASS VLV.
  • WHEN desired Suppression Pool Level is reached, close CSH*MOV111, TEST RETURN TO SUPPRESSION POOL.

2CSH*MOV105 Min Flow Valve does not

  • WHEN HPCS SYSTEM FLOW is less automatically open as CSH flow is reduced below than 634 GPM, verify open 634 gpm. CSH*MOV105, MINIMUM FLOW BYPASS VLV.
  • Stop CSH*P1, HPCS PUMP 1.
  • Verify closed CSH*MOV105, MINIMUM FLOW BYPASS VLV.
  • Notify SM that 2CSH*MOV111 is NOT closed.
  • Restore CST Level, as required, per N2-0P-4.

ROLE PLAY: Acknowledge request to locally SRO check CSH*MOV1 05 and breaker for any visible

  • May direct plaCing HPCS in PTL damage. Report back 1 minute later that there is
  • Recognizes that TS 3.5.1 must not be no apparent damage to either CSH*MOV1 05 or its exited breaker.

(Completion Time is 14 days)

  • May notify WEC, Ops Management, and FIN Team
  • May dispatch PO to check status of CSH*MOV105 and breaker.
  • Reportable to the NRC within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> NMP2 2010 NRC Scenario # 1 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 3 - EHC Pressure Regulator Failure CREW

  • Identifies power and pressure CONSOLE OPERATOR: When directed by Lead oscillations Evaluator, activate malfunction using TRG 2.
  • Determines oscillations being caused TC03A, EHC PRESS REG FAILURE by EHC regulator oscillations.

OSCILLATIONS

  • Responds to Annunciator 851148 "8" Press Regulator In Control Reactor power oscillates with EHC pressure
  • Reports oscillations to SRO.

regulator failure.

Expected Annunciators: SRO 851148, 8 PRESS REGULA TOR IN CONTROL

  • Directs entry into N2-S0P-23 intermittently alarms as "8" regulator attempts to
  • Directs power reduced to 85%, lAW take control. N2-S0P-101 D.
  • Directs a licensed operator to Relay ROLE PLAY: Call the Control Room as operator Room to EHC panel (2CEC-PNL843) sent to relay room and report that you are ready to (Key 16).

shift from "A" Pressure Regulator to "8" Pressure

  • Directs attempt to stabilize pressure Regulator and Shift to the "8" Press. Reg.

When requested state that N2-S0P-23, Detail "A"

  • Contacts RE to assess thermal limits.

steps 1, 2, and 3 are complete.

RO CONSOLE OPERATOR: When directed by

  • When directed, lowers power to 85%

Control Room to shift regulators, activate remote (or value directed by SRO).

using TRG 3.

  • Lowers power with recirculation flow in TC02 PRESS REGULATOR BIAS"A", 8.0 accordance with N2-S0P-1 01 D
  • Verbalizes actions and receives ROLE PLAY: When requested state that "8" confirmation.

Regulator set at 5.90" and N2-S0P-23, Detail "A"

  • Monitors Nuclear Instruments as step 4 complete.

power is reduced.

  • May check Power/Flow Map after Reactor pressure lowers by 5 to 10 psig. power reduction.

BOP

  • Contacts licensed operator in relay room to shift to "8" EHC pressure regulator.

NMP2 2010 NRC Scenario # 1 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 3 (Continued)

  • Reports "8" regulator is in control by observing annunciator 851148 and "8" REG in control light illuminated and P851.

NMP2 2010 NRC Scenario # 1 November 2010

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS EVENT 4 - RBCLCW Pump P1A trips. Standby CREW Pump Fails to Auto-Start

  • Responds to RBCLCW Pump CCP P1A trip. Annunciator:

CONSOLE OPERATOR: When directed by Lead

  • 601246, RBCLC SYS TROUBLE Evaluator, activate malfunction using TRG 4.
  • Recognizes the CCP-P1 C pump fails
  • CW02A RBCLCW PUMP TRIP (P1A) to auto-start. Annunciator:
  • CW16C CCP-P1C FAILS TO
  • 601252, RBCLC PUMP 1A11B/1C AUTOSTART PRESET AUTO TRIP/FAIL TO START SRO
  • May contact the Work Execution Center (WEC) for maintenance followup.

ROLE PLAY: If field operator and/or electrical is

  • May send maintenance and field dispatched to check pump and breaker, report an operator out to investigate pump and acrid smell at the pump motor. breaker
  • May direct placing the control switch for CCP-P1A in PTL.

BOP

  • Recognizes failure of standby RBCLCW pump CCP-P1 C to auto start.
  • Starts the standby pump CCP-P1 C.
  • May place control switch for CCP-P1A in PTL RO
  • Monitors reactor power, pressure and level.
  • May announce on plant page entry into N2-S0P-13.

NMP2 2010 NRC Scenario # 1 -11 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 5 - ECCS DIV 1 Inadvertently Initiates CREW

  • Recognize initiation of Div I ECCS CONSOLE OPERATOR: When directed by Lead Systems and report same to CRS Evaluator, activate malfunction using TRG 5.
  • Examine panels for ECCS initiation RH13A ECCS INADVERTENTLY INITIATES DIV conditions RHS*P1 A auto starts SRO CSL *P1 auto starts
  • Determines ECCS initiation conditions Div I lOG auto starts do not exist.
  • May direct Div I ECCS reset CONSOLE OPERATOR: Verify malfunction
  • May direct securing RHS & CS pumps RH 13A is automatically deleted by auto trigger
  • Refers to Tech Specs TRG 15, when Div I EDG starts. 3.8.1 CONDITION B, REO.

ACTION B.1 and B.2 and B.3.1 or

.2 and B.4 restore DG to operable ROLE PLAY: Call in as I&C 30 seconds after within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> initiation and state that you bumped into a

  • Informs plant management of event transmitter in the RB and that there is no damage and TS shutdown LCO entry to the transmitter. If asked what transmitter(s)
  • May notify WEC, Ops Management, were bumped state that you will get back to him. and FIN Team Also, if requested, state that there are no trips and trip units indicate normal. RO
  • May perform standby checks.

CUE: If necessary, direct SRO to secure ECCS

  • Monitors power, pressure, and level.

pumps if not required.

BOP ROLE PLAY: If requested, perform EG1 operating

  • As directed, secures RHS & CS checks. pumps.
  • As directed, attempts to reset Div I CONSOLE OPERATOR: After ECCS pumps are ECCS per N2-0P-31 Section G.2.0, shutdown and when directed by the Lead Evaluator and N2-0P-32 Section F.2.

activate malfunction using TRG 8.

DG02A, DIESEL GENERATOR NUMBER 1 TRIP NMP2 2010 NRC Scenario # 1 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 6 - DIV1 Bus 101 Fault CREW

  • Responds to Annunciator for Bus 101 CONSOLE OPERATOR: When directed by Lead Fault.

Evaluator (after ECCS pumps are secured),

activate malfunction using TRG 6. SRO ED05A 4.16KV EMERGENCY BUS FAULT (101)

  • Directs entry into N2- SOP-03, Loss of AC power 2ENS*SWG101 de-energizes. Service Water Div /I
  • Directs entry into N2-S0P-11, Loss or Non-Essential MOVs close and cannot be re- Degraded SW system opened. A manual scram is required by N2-S0P-
  • May enter N2-S0P-29, Sudden Reduction In Core Flow after scram
  • Directs entry into N2- SOP-1 01 C RO/BOP
  • As directed, enters N2-S0P-29, Sudden Reduction In Core Flow
  • As directed, places reactor mode switch in shutdown and provides scram report.
  • Enters N2-S0P-03
  • As time permits, trips the turbine and recirc pumps.

NMP2 2010 NRC Scenario # 1 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 7,8 & 9 CREW Loss of Line 6, Failure of Div II EDG output

  • Recognizes and reports Loss of AC breaker to auto close. Steam Line break in Power.

Drywell

  • Recognizes SOP and EOP entry Conditions.

CONSOLE OPERATOR: Ensure TRG 7 activates the following when the mode switch was placed in SRO shutdown.

  • Directs entry into N2-S0P-3 for Loss
  • ED02B LOSS OF OFF-SITE 115KV LINE ofAC 6,2 minute delay
  • Directs power restored to DIV II Bus
  • OVR-05A2S030D172311 NAP EMER by closing the DIV II EDG output DIESEL GEN 3 OUTPUT BREAKER 103 breaker lAW SOP-03 (CT -1.0) 14, OFF, 2 minute delay
  • MS04 STEAM LINE RUPTURE IN

delay, 1.5%, 8:00 minute ramp

  • Directs a RPV pressure band with a target of 800-1000 psig.

On a loss of line 6 Div /I EDG automatically starts BOP however the EDG output breaker 103-14 fails to

  • As directed, enters N2-S0P-3.

automatically close due to component malfunction.

  • Restores power to Div II Bus by 2ENS*SWG102 and Div 1/ safety related loads closing Div II EDG output breaker remain de-energized until manual operator action lAW N2-S0P-3, Detail "A",

to close 103-14 is taken. instructions:

o Checks listed annunciators o Place SYNCHRONIZE TO BUS 103 switch to ON.

o Closes the EDG output breaker for the DIV II Bus (CT-1.0)

RO

  • As directed, maintains RPV level 160 200 inches.
  • Continues actions lAW N2-S0P-101C NMP2 2010 NRC Scenario # 1 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 7, 8 & 9 (Continued) CREW Responds to rising Drywell Pressure and Temperature SRO

  • Enters EOP-PC when Drywell Pressure exceeds 1.68 psig and Re-enters EOP RPVon High DW pressure.
  • Directs Suppression Chamber Spray lAW EOP-6 Att. 22. when DIV II bus power is restored
  • May direct restart of DW Cooling lAW EOP-6 Att. 24 when DIV II bus power is restored
  • When Suppression Chamber Pressure exceeds 10 psig then continues in PCP leg and directs Orywell Spray. (CT-2.0)
  • Directs ECCS injection prevented before RPV pressure reaches 400 psig
  • Directs a RPV pressure band with a target of 800-1000 psig.
  • May direct clOSing of MSIVs as reactor depressurizes RO
  • Takes action to maintain RPV water level within the directed band of 160 200 inches with FW and Condensate.

NMP2 2010 NRC Scenario # 1 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 7,8 & 9 (Continued) BOP/RO

  • Takes action to maintain RPV pressure within the directed band.
  • As directed, closes MSIVs to control cooldown.
  • When directed, restores drywell cooling lAW EOP-6 Att. 24:

o Determines DW temperature

<250°F o Overrides drywell unit cooler water LOCA isolation interlocks with keylock switches.

o Verifies closed drywell unit cooler inlet valves.

  • Restores CCP to drywell by opening containment isolation valves.

o Restores CCP to drywell unit coolers by opening drywell unit cooler inlet valves.

o Overrides drywell unit cooler fan interlocks with keylock switches.

o Restarts drywell unit cooler fans.

  • Places Suppression Chamber Spray in service lAW EOP-6 Att. 22:

o Opens SWP*MOV90B, RHR H/X SVCE WTR INLET VLV. May be delayed until after sprays are in service.

o Verify closed RHS*MOV24B, LPCI IN..IECTION VLV o Verify running RHS*P1 B PMP o Open RHS*MOV33B, OUTLET TO SUPPR POOL SPRAY NMP2 2010 NRC Scenario # 1 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 7,8 & 9 (Continued) BOP/RO o Verify ~450 gpm on SUPPR SPRAY HEADER FLOW (2RHS*F/64B)

  • Places RHR in Drywell Spray prior to exceeding the Pressure Suppression pressure limit as follows (CT -2.0):

o Trips/verifies tripped RCS Pumps.

o Trips Drywell Unit Coolers.

o Verifies an initiation signal present.

o Verifies open SWP*MOV90B, HEAT EXCHANGER 1B SVCE WTR INLET VLV. May be delayed until after sprays are in service.

o Verifies closed RHS*MOV24B, LPCI B INJECTION VLV o Verifies RHS*P1 B running.

o Verifies closed RHS*FV38B, RETURN TO SUPPR POOL COOLING.

o Verifies open RHS*MOV4B, PMP 1B MINIMUM FLOW VLV.

o Opens RHS*MOV15B, OUTLET TO DRYWELL SPRAY.

o Opens RHS*MOV25B, OUTLET TO DRYWELL SPRAY.

o Verifies RHS*MOV48, PIVIP 1B MINIMUM FLOW VLV, closes.

o Verifies approximately 7450 gpm on DRYWELL SPRAY HEADER FLOW (2RHS*FI638).

o Closes RHS*MOV88 after 10 minute time delay from receipt of initiation signal.

NMP2 2010 NRC Scenario # 1 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 7,8 & 9 (Continued) o Contacts RP to start SWP*RE238.

o Throttles open SWP*MOV338 to establish flow not to exceed 7400 gpm - may be required to start 5th service water pump (post LOCA).

RO/BOP

  • Monitors for improving containment parameters.
  • Controls RPV level 160 to 200 inches.

Termination Cue:

Containment parameters improving and RPV level 160 to 200 inches.

NMP2 2010 NRC Scenario # 1 November 2010

NMP SIMULATOR SCENARIO NRC 2010 Scenario #2 REV. 0 No. of Pages: 18 PERFORM MANUAL SCRAM TEST CHANNELAlHPCS SPURIOUS INJECTION/CRD PUMP TRIP/FEEDWATER HEATER TUBE LEAKlFW CTRLR MALFUNCTIOI\I/RECIRC PUMP HI VI BS/ATWS/SLC AUTO INITIATION FAILURE PREPARER S. Dennis/J. Reid DATE ':"':"':'-'-'---=-_ _

VALIDATED DATE ':"':"==-:'-=-_ _

GEN SUPERVISOR OPS TRAINING -Z==~~~====~~-7~~~~--~

OPERATIONS MANAGER NA Exam Security DATE _ _ _ __

CONFIGURATION CONTROL NA Exam Security DATE SCENARIO

SUMMARY

Length: 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Initial Power Level: 100%, above the 100% Rod Line The scenario begins at 100% reactor power. The crew will perform surveillance test N2-0SP-RPS W002 for the "A" Channel only. An RPS indication will fail requiring TS to be addressed.

Following Tech Spec review an inadvertent start of HPCS with injection into the vessel occurs. This requires the crew verify drywell pressure and reactor water level in normal band and place HPCS in P-T-L. Then a CRD will trip requiring actions per the abnormal procedure.

After the pump trip has been addressed, a high pressure feedwater heater tube leak occurs coincident with a feedwater master controller failure. The crew enters and executes the actions of N2-S0P-8 and lowers power to <3467 MWt due to the partial loss of feedwater heating and resulting unplanned power change. The feedwater malfunction requires feedwater to be placed in manual per N2-S0P-6.

One Recirc Pump begins to experience hi vibration and the pump must be removed from service.

The SRO will address TS for loop mismatch and then the other recirc pump will trip requiring a reactor scram. When the reactor is manually scrammed all control rods will not fully insert. EOPs RPV, EOP-Failure-To-Scram will be entered. Given a failure of the reactor to SCRAM, with power above 4% or unknown, the crew will terminate and prevent all injection except boron, CRD and RCIC. (CRITICAL TASK).

Given a failure of the reactor to scram, the crew will lower power by inserting control rods or injecting boron in accordance with EOP-C5 (Failure to Scram) (CRITICAL TASK).

NMP2 2010 NRC Scenario # 2 November 2010

Major Procedures Exercised: EOP-RPV, PC, C-5, C-4. N2-S0P-6, N2-S0P-8, N2-S0P-30, N2-S0P-1 01 D and N2-S0P-1 01 C.

Dynamic Mitigation Strategy Code:: AT1, High power ATWS, heat addition to suppression pool requires entry into level power control, RPV level controlled below feedwater spargers, RPV Slowdown not required Termination Criteria: All rods are fully inserted and RPV level is restored to the normal band.

NMP2 2010 NRC Scenario # 2 November 2010

I. SIMULATOR SET UP A. IC Number: IC-21 or equivalent.

B. Presets/Function Key Assignments

1. Malfunctions:
8. RD17A,B,C,D,E, PARTIAL INSERTION OF RODS, 48 PRESET
b. RD17H,I,J,K,L,M, PARTIAL INSERTION OF RODS, 48 PRESET
c. RP08A, RRCS 98 SECOND TIMER FAILURE DIV I, TRUE PRESET
d. RP08B, RRCS 98 SECOND TIMER FAILURE DIV II, TRUE PRESET
e. CS01B, HPCS INADVERTENT INITIATION K11 TRG2 (REACTOR LEVEL 2), TRUE
f. RD12A, CRD FEED PUMP TRIP (P1A), TRUE TRG3
g. MS10A, LOSS OF EXT STEAM TO FW HTR (E6A), TRUE TRG4
h. FW15, FEEDWATER MASTER CONTROLLER TRG4 FAILURE AS - IS, TRUE
i. RR46A, RCS PMP1A VIBRATION (MILS), TRUE TRG5
j. RR10B, RR PUMP BKR TRIP (4B), TRUE TRG7
k. RP02, RPS FAILURE TO SCRAM - AUTOMATIC, TRUE TRG 13 I. RP14A, RRCS ARI FAILUREIDEFEATED (DIV I), TRUE TRG14
m. RP14B, RRCS ARI FAILURE/DEFEATED (DIV II), TRUE TRG14
2. Remotes:
a. CS 12, CSH*MOV107 600 VOLT BKR STATUS, OPEN TRG10
b. CS06. MANUAL OPS CSH*MOV107 (0-1.0), 0 TRG10
c. MS06A, DEFEAT LEVEL 1 ISOL OF MSIV (K148A). DEFEATED TRG 11
d. MS06B, DEFEAT LEVEL 1 ISOL OF MSIV (K148B). DEFEATED TRG 11
e. MS06C. DEFEAT LEVEL 1 ISOL OF MSIV (K148C), DEFEATED TRG 11
f. MS06D, DEFEAT LEVEL 1 ISOL OF MSIV (K148D). DEFEATED TRG 11
g. RC10. DEFEAT RCIC/MT TRIP INTLK (EOP-6 ATT2), DEFEATED TRG12
h. OG03, OFFGAS HI RADIATION ISOL DEFEATED, DEFEATED TRG15
3. Overrides:
a. 03A1S30D14234, POS_1 REACTOR MAN SCRAM PB SWA1, ON TRG 1
4. Annunciators:
8. AN603409, RPS B DISCH VOLUME HIGH LEVEL TRIP, OFF TRG16
b. AN6031 09, RPS A DISCH VOLUME HIGH LEVEL TRIP. OFF TRG16 NMP2 2010 NRC Scenario # 2 November 2010

C. Equipment Out of Service

1. None D. Support Documentation
1. N2-0SP-RPS-W002, Signed off thru step 8.1 E. Miscellaneous
1. Event Triggers
a. TRG 1 "zdrps3ar(1)==1". Activates when Reactor manual scram switch for channel A1 is ARMED. This overrides the switch to ARMED, simulating switch failure.

NMP2 2010 NRC Scenario # 2 November 2010

II. SHIFT TURNOVER INFORMATION OFF GOING SHIFT: 1 N ID DATE:

PART I: To be performed by the oncoming Operator before assuming the shift.

  • Control Panel Walkdown (all panels) (SM, CRS, STA, CRO, CRE)

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

  • Shift Turnover Checklist (All)
  • CRO log (CRO)
  • Computer Alarm Summary (CRO)

(SM, CRS, STA, CRO, CRE)

Evolutions/General Information/Equipment Status:

  • Reactor Power =100%
  • loadline =>100%
  • N2-0SP-RPS-W002, MANUAL SCRAM CHANNEL FUNCTIONAL TEST is in progress.

PART III: Remarks/Planned Evolutions:

  • Perform N2-0SP-RPS-W002, MANUAL SCRAM CHANNEL FUNCTIONAL TEST perform PART IV: To be reviewed/accomplished shortly after assuming the shift:
  • Review new Clearances (SM)
  • Shift Crew Composition (SM/CRS)

TITLE NAME I TITLE NAME SRO I ATCRO I BOPRO I I I NMP2 2010 Scenario #2 November 2010

III. PERFORMANCE OBJECTIVES A. Critical Tasks:

CT*1.0 - Given a failure of the reactor to SCRAM, with power above 4% or unknown, the crew will terminate and prevent all injection except boron, CRD and RCIC.

CT-2.0 - Given a failure of the reactor to scram, the crew will lower power by inserting control rods or injecting boron in accordance with EOP-C5 (Failure to Scram)

NMP2 2010 Scenario #2 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 1 - Perform N2-0SP-RPS-W002, CREW MANUAL SCRAM CHANNEL FUNCTIONAL

  • Crew conducts a pre-brief and walks TEST, section 8.2 only down the panels.

SRO

  • Direct performance of N2-0SP-RPS W002 section 8.2 only
  • When informed by operator that alarm at step 8.2.12 did not clear, references TS 3.3.1.1 - Ai and declares "A" RPS Inop -12 hours to place the channel in trip RO Performs N2-0SP-RPS-W002 section 8.2 only as follows:

8.2 Manual SCRAM Channel "A" Test CONSOLE OPERATOR: Verify TRIGGER 1 NOTE: All indicators AND controls for this automatically activates, when REACTOR SCRAM test are located on panel 2CEC*PNL603 Ai pushbutton collar is ARMED unless otherwise specified.

OVR-03A1S30DI4234, POS_1 REACTOR MAN

  • 8.2.1 Verify that there is NO half SCRAM PB SWA1, ON scram on the "8" side.
  • 8.2.2 Notify CRO that a half scram on "A" side will be generated.

Annunciator 603113, RPS A MANUAL SCRAM

  • 8.2.3 Arm the REACTOR SCRAM Ai SWITCH, will not extinguish later in sUNeillance pushbutton.

step 8.2. 12 due to switch failure.

  • 8.2.5 Depress AND hold for 2 to 3 seconds the REACTOR SCRAM Ai pushbutton.

NMP2 2010 Scenario #2 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 1 (Continued)

ANNUNCIATOR DESCRIPTION

  • 603110 RPS A AUTO TRIP
  • 8.2.7 Verify the status of the following CUE: Indicating lights for REACTOR SCRAM TRIP indicating lights:

LOGIC A 1 on 2CEC"PNL609 is extinguished.

  • REACTOR SCRAM TRIP LOGIC A 1 (Panel 609 is not modeled in simulator) on 2CEC"PNL609 is extinguished.
  • PILOT SCRAM VALVE SOLENOIDS A,C,E, AND G are extinguished.
  • 8.2.8 Reset the REACTOR SCRAM RESET LOGIC A.
  • 8.2.9 Verify the following occurred for the tripped condition:
a. Verify the following Plant Computer Printouts:
  • RPSUC03 RPS A AUTO TRIP TRIPPED
b. Verify the following Sequence Of Events Printouts:
  • RPSUC03 RPS A AUTO TRIP TRIPPED
  • 8.2.10 Verify the following alarms AND indications for the reset condition:
a. Verify the following annunciators have extinguished:
  • 603110 RPS A AUTO TRIP

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 1 (Continued) b. Verify the following Plant Computer Printouts:

  • RPSUC03 RPS A AUTO TRIP ALMCLR
c. Verify the following Sequence Of Events Printouts:
  • RPSUC03 RPS A AUTO TRIP ALMCLR CUE: REACTOR SCRAM TRIP LOGIC A1 on d. Verify the status of the following 2CEC*PI\IL609 is illuminated. indicating lights:
  • REACTOR SCRAM TRIP LOGIC A1 on 2CEC*PNL609 is illuminated.
  • PILOT SCRAM VALVE SOLENOIDS A,C,E, AND G are illuminated.
  • 8.2.11 Disarm the REACTOR SCRAM A1 pushbutton.

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 2 - Inadvertent Initiation and Injection of CREW HPCS Recognizes and reports start of HPCS SRO CONSOLE OPERATOR: When directed by Lead Evaluator, activate malfunction by depressing

  • Repeats back start of HPCS and TRIGGER 2: EGS*EG2.

CS01 B, HPCS Inadvertent Initiation K11

  • Directs RO/BOP to verify drywell (Reactor level 2) pressure and reactor water level in normal band.

HPCS automatically starts and injects into the

  • Acknowledges report that RPV level RPV. Reactor pressure lowers and FWS-L V1 0 and drywell pressure are normal.

controllers respond by closing down to maintain

  • May direct power monitoring using RPV level in normal band. The Division 11/ diesel APRMs generator starts and runs unloaded in response to
  • Directs BOP to place HPCS control HPCS start signal. switch in P-T-L.
  • Refers to Tech. Spec. 3.5.1 and The following annunciators alarm: performs required actions.
  • 852311 EDG 2 TROUBLE
  • Enters condition B and takes required
  • 852317 EDG2 RUNNING action B.1 to verify by administrative
  • 603139 REACTOR WATER LEVEL means that RCIC is OPERABLE HIGH/LOW immediately and action B.2 to restore HPCS to OPERABLE status within 14 days.
  • May identify 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reportable condition requirement of 10CFR50.72.b.3.v and 50.73.a.2.v. for unplanned inoperability.
  • Enters TS 3.6.1.3 for HPCS CSH*MOV107 - Action C.1 - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to verify line is isolated
  • Notifies Operations and Plant management.
  • May contact WEC for assistance and work planning.

NMP2 2010 Scenario #2 -10 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 2 (Continued) RO

indication, report all trip units are indicating normal

  • Implements the actions of ARP and untripped. 603139
  • Confirms FWLC system is responding FWLC system will respond and no operator actions properly to the rise in water level.

are expected to occur other than confirming proper FWLC response. BOP

  • Recognizes and reports HPCS injecting.

ROLE PLAY: If Plant Operator contacted to

  • Verifies drywell pressure and reactor manually close CSH*MOV1 07 wait 1 minute then water level are normal.

activate TRG 10.

  • Places HPCS control switch in P-T-L.
  • eS12, eSH*MOV107 600 VOLT BKR
  • Reviews ARPs 852317,601706 and STATUS, OPEN 851311 and 852319.
  • eS06, MANUAL OPS CSH*MOV107 (0-1.0), 0
  • Dispatch an operator to Report back in 5 minutes that CSH*MOV107 is 2CES*IPNL413, 2EGS*EG2 closed. GENERATOR SWITCH BOARD.
  • IF a local alarm is energized, refer to the applicable Alarm Response Procedure.

These are alarm 852317 (OG Panel) actions:

  • Confirm that 2EGS*EG2 is required to be running.
  • IF 2EGS*EG2 is required to be running, operate the diesel generator in accordance with N2 OP-100B, HPCS DIESEL GENERATOR.

NMP2 2010 Scenario #2 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 2 (Continued)

  • IF 2EGS*EG2 is NOT required to be running, shutdown the diesel EXAMINER NOTE: Crew is likely to have generator per N2-0P-100B. Step 2EGS*EG2 remain running until additional G.5.6 by depressing Emergency resources can be obtained. Stop PB.
  • AFTER 2EGS*EG2 is shutdown, confirm the alarm clears.

These are alarm 852319 (DG Panel)

When HPCS is placed in P- T-L the following actions:

occurs:

  • Using the Process Computer,
  • 852311 - EDG 2 TROUBLE clears determine which computer point(s)
  • 603139 - REACTOR WA TER LEVEL brought in the alarm.

HIGH/LOW clears

  • Notify the SM to evaluate the
  • 852319 - EDG 2 DC CONT POWER 2EGS*EG2, DIVISION 3 diesel FAILURE generator AND 2ENS*SWG102,
  • AMBER Pump Motor BRKR #2 system Division 3 Emergency Switchgear.

status light illuminates.

  • Dispatch an operator to 2ENS*SWG102 to check for de energized amber circuit monitoring lights.
  • Refer to the applicable INOP STATUS LIGHT for response.

NMP2 2010 Scenario #2 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 3 - CRD Pump 1A Trip CREW

  • Recognizes and responds to CRD CONSOLE OPERATOR: When directed by Lead Pump trip in accordance with N2 Evaluator, activate malfunction by depressing SOP-30 TRIGGER 3:

RD12A, CRD FEED PUMP TRIP (P1A)

  • 603308 - CRD PUMP 1A11 B
  • 603311 - CRD CHARGING WrR AUTO TRIP PRESSURE LOW
  • 603313 - CRD 1Al1 B MOTOR
  • 603308 - CRD PUMP 1A11 B AUTO TRIP ELEC FAULT
  • 603313 - CRD 1A11 B MOTOR ELEC
  • Directs entry and actions in accordance with N2-S0P-30, Control Rod Drive Failures RO
  • Enters N2-S0P-30, Control Rod Drive Failures, to transfer to standby CRD Pump
  • Shifts Flow Controller to Manual
  • Closes FCV to minimum
  • Starts the "S" CRD pump
  • Adjusts FCV to approx. 63 gpm
  • Places Flow Controller in Auto NMP2 2010 Scenario #2 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 4 & 5 Extraction Steam Isolation and CREW Feedwater Master Controller Failure. Recognizes and responds to indications of extraction steam isolation and FW CONSOLE OPERATOR: When directed by Lead controller failure.

Evaluator, activate malfunctions by depressing

  • Thermal power rise TRIGGER 4:
  • RPV water level changing
  • Acknowledges report of Feedwater Failure As - Is Master Controller Failure.
  • Directs entry into N2-S0P-6, Feedwater Failures.
  • Assigns reactor water level band.

The following Annunciator alarms:

  • Acknowledges report of power rise.

603139 REACTOR WATER LEVEL HIGH/LOW

  • Directs entry into N2-S0P-08 Unplanned Power Changes due to Reactor water level high alarm due to reduced loss of feedwater heating.

steam flow and failed feedwater controller

  • Directs power reduced to maintain

<3467 MWTH in accordance with N2 SOP-1 01 D, Rapid Power Reduction, Core thermal power and APRM power rises.

using Recirc Flow and/or Cram Rods.

  • Notifies plant management and RE.
  • May contact WEC SRO for assistance and work planning.

RO

  • Reports alarms to CRS
  • Recognizes and reports megawatts electric change, thermal power rise and rise in APRM power.
  • Maintains <3467MWTH in accordance with N2-S0P-1 01 D as directed by CRS.

NMP2 2010 Scenario #2 -14 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 4 & 5 (Continued)

  • Monitors and reports RPV water level and identifies that during the downpower the Feedwater Master Controller is not responding.
  • As directed, enters N2-S0P-6, Feedwater Failures, due to FWLC not responding to RPV level changes.
  • Controls water level in manual in assigned band.

BOP

  • Enters and performs the actions of N2-S0P-8 for unplanned power changes as directed by the CRS.
  • Monitors Main steam line and offgas radiation monitors for evidence of fuel ROLE PLAY: IF asked as Operations Management failure.

for guidance on any further power reductions or

  • Verifies feedwater temperatures are actions for feedwater heaters, inform SRO that within limits of figure 1 of N2-S0P-8.

further guidance will be provided later.

  • Verifies 2CNM-AOV1 01, LOW PRESS HTR STRING BYPASS VLV, is NOTE: When the crew has stabilized reactor power closed.

<3467 MWt and FWLC is in manual with RPV level

  • Verify that 2ESS-MOV3A, 6TH POINT in the normal band then proceed to next event.

HEATER A EXTRACTION STM ISOL VLV, for the affected Heater is closed.

NMP2 2010 Scenario #2 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENTS 6, 7 & 8 - Recirc Pump High Vibration, CREW ATWS, SLC Auto Initiation Failure Responds to Annunciator 602219 "Recirc 1A118 vibration Hi" CONSOLE OPERATOR:_When directed by Lead Evaluator, activate malfunction by depressing SRO TRIGGER 5:

  • Directs sending field operator to Panel RR46A, RCS PMP1A VIBRATION (MILS) 2 RCS-PNL 100 to investigate vibration alarm ROLE PLAY: Report as Plant Operator after 2
  • Directs Entry to SOP-29.1, Reactor minutes that vibration on the motor frame and shaft Recirculation Pump Seal Failure is 6 mils.
  • When informed that vibration is >6 mils directs tripping the Recirc Pump CONSOLE OPERATOR:
  • Enters SOP-29, Sudden Reduction in
  • IF reactor scrams during the transient on the Core Flow Recirc Pump trip then DO NOT activate
  • When U8" Recirc Pump trips OR Trigger 7 for "8" Recirc Pump Trip reactor scrams on level directs entry
  • IF reactor remains at power then when directed into EOP-RPV by Lead Evaluator, activate malfunction by

RR10B RR PUMP BKR TRIP (4B)

  • Directs Inhibiting ADS.
  • Directs RRCS initiation.

NOTE: ATWS and SLC auto initiation failures are

ROLE PLAY: One minute after the request, report

  • May direct bypassing the MSIV Low to control room that EOP-6, Att.2 and 10 actions are complete. Water Level Isolation in accordance with EOP-6 Att.1 0
  • Directs RPV Level be Terminated ISOLATION DEFEATED (EOP-6 ATT 10) and Prevented with Reactor Power
  • TRIGGER 12, DEFEAT RCIC/MT TRIP >4% (Critical Task 1.0)

INTLK (EOP-6 ATT 2)

NMP2 2010 Scenario #2 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENTS 6, 7 & 8 (Continued)

  • Directs Pressure band of 800 to 1000 psig.

CONSOLE OPERATOR:

  • When RPS is reset and ARI is defeated delete EOP-6 Att.14 and/or SLC system to RD 17 malfunctions as required, to allow initial lower reactor power (Critical Task Control Rod Insertion. ALL control rods may be 2.0) inserted on the second scram attempt (All
  • Directs SLC initiation when informed RD17 malfunctions deleted).

of auto initiation failure.

  • IF time compression is desired to drain SDV
  • When informed that RPV level has then if directed activate TRIGGER 16 to lowered to 100 inches, directs a new override annunciators OFF to simulate SDV RPV level band between -39 and +100 draining below the scram setpoint.

inches (corrected if on fuel zone)

  • AN603409, RPS B DISCH VOLUME HIGH LEVEL TRIP, OFF
  • AN603109, RPS A DISCH VOLUME HIGH LEVEL TRIP, OFF ROLE PLAY: Acknowledge request to implement EOP-6 Att.14 Sections 3.3 and 3.5. Report back 2 to 3 minutes later that field actions have been implemented
  • TRIGGER 13, RPS DEFEATED RO/BOP
  • TRIGGER 14, RRCS DIV. 1 and 2
  • Trips "A" Recirc Pump when directed.

DEFEATED

  • As directed, places Mode Switch to Shutdown.
  • Prevents HPCS Injection.
  • As directed, bypasses the MSIV Low Water Level Isolation in accordance with EOP-6 Att.1 O.

NMP2 2010 Scenario #2 -17 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENTS 6, 7 & 8 (Continued)

  • Terminates and Prevents as follows:

603 Panel:

  • Places FW Master controller to full closed, Verifies all LV-10 positions are at "0", LV-55s at "0", LV-137s at "0" 601 Panel:
  • Places CSL*P1 and 2RHS*P1 C in Pull-To-Lock
  • Arms and Depresses LPCI Div I and II Manual Initiation push buttons, then closes and overrides LPCllnjection Valves (Critical Task 1.0)
  • As directed, maintains RPV level band using Condensate/Feedwater.

EXAMINER NOTE: SLC fails to auto-inject, the

  • Recognizes failure of SLC to inject operators must manually inject SLC and manually starts and injects with SLC
  • Implements EOP-6 Att.14 to allow rod insertion. Once informed of implementation, resets scram, reinserts a scram signal while continuing to drive in control rods.

(Critical Task 2.0)

Termination Criteria: All control rods inserted and RPV level is restored to normal band.

NMP2 2010 Scenario #2 November 2010

NMP SIMULATOR SCENARIO NMP2 2010 NRC SCENARIO 5 REV. 0 No. of Pages: 25 PERFORM OW TO SC VACUUM BKR TEST/CONTINUE STRTUP/IRM UPSCALE/STUCK CONTROL RODITRANSFER MODE SWITCH TO RUN/LOSS OF DIV II SWGRlUNISOLABLE RCIC STEAM LEAK WITH RPV BLOWDOWN/CONDENSATE BOOSTER PUMPS TRIP PREPARER S. Dennis/J. Reid DATE 7/20/10 VALIDATED P. Amway/B. Hilliker/C. Darling DATE 7/22110 GEN SUPERVISOR OPS TRAINING OPERATIONS MANAGER NA Exam Security DATE _ _ _ __

CONFIGURATION CONTROL NA Exam Security DATE _ _ _ __

SCENARIO

SUMMARY

Length: 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Initial Power Level: 4.5% with Mode Switch in STARTUP The scenario begins at about 4.5% reactor power during plant startup. The crew will perform Drywell to Suppression Chamber Vacuum Breaker surveillance test, N2-0SC-ISC-M@002. The crew will continue the startup by withdrawing control rods to raise power above 5%. While withdrawing rods an IRM will fail upscale and then a stuck control rod event will occur. Once those issues are addressed the crew will continue rod withdrawal and transfer the Mode Switch to RUN.

Next, a loss of offsite power to Div II Switchgear occurs when a bus fault trips open breaker 17-2. The crew will take action per abnormal procedures to stabilize plant parameters, restore Service Water flow and restore drywell fans. The SRO will be required to address TS. Then, the supply breaker for the RCIC inboard steam supply isolation valve will trip. The SRO must address TS.

The major transient begins when a RCIC Steam Leak into Reactor Building occurs. Automatic and manual attempts to isolate the RCIC steam line will be unsuccessful. Entry to EOP-SC is required and the reactor must be manually scrammed (CRITICAL TASK). When Reactor Building temperatures exceed 212°F in two or more areas, an RPV Blowdown is required (CRITICAL TASK). The EHC Pumps trip to disable the Bypass Valves as a means of rapidly reducing RPV pressure. The Condensate Booster Pumps trip during the RPV Blowdown requiring additional actions to maintain RPV level.

Major Procedures Exercised: EOP-RPV, EOP-SC, EOP-C2, and N2-S0P-3 Dynamic Mitigation Strategy Code: SC1, Primary system leak in SC, exceed max safe level in 2 or more areas, Blowdown required Termination Criteria: RPV Blowdown is complete and RPV level is maintained above TAF.

NMP2 2010 NRC Scenario #5 November 2010

I. SIMULATOR SET UP A. IC Number: IC-11 or equivalent (NRC Exam IC-155)

  • Reset CSH HI WTR LEVEL SEAL IN
  • Place aIlIRM/APRM Recorders to IRM position B. Presets/Function Key Assignments
1. Malfunctions:
a. RD07 Control Rod 10-11 STUCK, TRUE PRESET
b. RC11, RCIC Isolation Failure, TRUE PRESET
c. NM06D, IRM CNHL D UPSCALE FAIL, TRUE TRG 1
d. ED04G 4.16KV NORMAL BUS FAULT SWG 17, TRUE TRG2
e. RC12, RCIC Steam Leak in RB 215' Elevation 30%, Ramp Time 5 minutes TRG4
f. TC15A, EHC Pump A Trip, TRUE TRG5
g. TC15B, EHC Pump B Trip, TRUE TRG5
h. FW02A, CONDENSATE BOOSTER PUMP TRIP (P2A), TRUE TRG6
i. FW02B, CONDENSATE BOOSTER PUMP TRIP (P2B), TRUE TRG6
j. FW02C, CONDENSATE BOOSTER PUMP TRIP (P2C), TRUE TRG6
2. Remotes:
a. None
3. Overrides:
a. 01A2S042DI0418 OPEN MOV 128 VALVE STEAM SUPPLY PRESET LINE ISLN (INBOARD), ON
b. 01A2S041DI0366 OPEN MOV 121 VALVE STEAM SUPPLY PRESET LINE ISLN (OUTBOARD), ON
c. 01A2S041 DI0365 CLOSE MOV 121 VALVE STEAM SUPPLY PRESET LINE ISLN (OUTBOARD), OFF
d. 01A2S042DI0564 CLOSE MOV 128 VALVE STEAM SUPPLY PRESET LINE ISLN (INBOARD), OFF
e. 01A1S106L00333 STEAM SUPPLY INBD ISOL MOV 128 TRG3 INOPAMBER, ON
f. 01A2DS079L006314 MOV 128 VALVE STEAM SUPPLY LINE PRESET ISLN (INBOARD) GREEN, OFF
g. 01A2DS080L006315 MOV 128 VALVE STEAM SUPPLY LINE TRG3 ISLN (INBOARD) RED, OFF NMP2 2010 NRC Scenario #5 November 2010
4. Annunciators:
a. AN601305, RCIC System Inoperable, ON TRG3
b. AN601319, RCIC Valves Motor Overload, ON TRG3 C. Equipment Out of Service
1. NA D. Support Documentation
1. N2-0P-101A, Plant Startup complete through E.3.3
2. Rod Pull Sheets initialed to current rod withdrawal step.
3. Attachment 7 of N2-0P-101A complete with NO Exceptions
4. N2-0SP-ISC-M@002, Marked up to begin at step 8.1.2, Steps 8.3 thru 8.5 N/A'd and Steps 8.7 thru 8.9.4 N/A'd. Cues for 8.11 thru 8.14 in script E. Miscellaneous
1. Event Triggers
a. TRG 5 "thpdome<850". Activates when RPV pressure is below 850 psia.
b. TRG 6 "hzlc33s4a". Activates when RPV water level HIGH LEVEL TRIP A RESET amber light on P603 illuminates.

NMP2 2010 NRC Scenario #5 November 2010

II. SHIFT TURNOVER INFORMATION OFF GOING SHIFT: IN , D DATE:

PART I: To be performed by the oncoming Operator before assuming the shift.

  • Control Panel Walkdown (all panels) (SM, CRS, STA, CRO, CRE)

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

  • Shift Turnover Checklist (ALL)
  • CRO Log (CRO)
  • Computer Alarm Summary (CRO)

(SM, CRS, STA, CRO, CRE)

Evolutions/General Information/Equipment Status:

  • Reactor Power = 4.5% approx_________*___ R__

W__M--'S...:..te:..!.p'--17_ _ _ _ _ _ _ __

  • RPV Pressure 925 psig
  • Bypass Valves are partially open to control RPV pressure
  • Feedwater Pump A in service with FWS-LV55A in AUTO (HIC137)

PART III: Remarks/Planned Evolutions:

  • Perform DW to SC Vacuum Breaker test N2-0SP-ISC-M@002 for 2ISC*RV33A &

2ISC*RV33B post maintenance testing.

  • Continue plant startup and place the reactor mode switch to RUN between 5% and 6%

power in accordance with N2-0P-101A. Currently at step E.3.3

  • RWM Step 17 Rods are to be withdrawn using CONTI NUOUS WITH DRAW to 08 then single notch withdraw from 08 to 12 per Reactor Engineering
  • Chemistry parameters are in compliance with N2-0P-101A Step 3.6 requirements
  • HWC H2 and 02 piping is pressurized per N2-0P-112
  • APRM Gain Adjustments are satisfactory per Reactor Engineering
  • There are NO MODE 1 restrictions
  • Attachment 7 of N2-0P-101A is complete with NO Exceptions
  • P625 HPCS LEVEL 8 Test Switch is in NORMAL PART IV: To be reviewed/accomplished shortly after assuming the shift:
  • Shift Crew Composition (SM/CRS)

TITLE NAME TITLE I NAME SRO I ATCRO BOPRO I NMP2 2010 NRC Scenario #5 November 2010

III. PERFORMANCE OBJECTIVES A. Critical Tasks:

CT-1.0 Given an unisolable RCIC steam leak and secondary containment temperature approaching maximum safe values in one area, the crew will enter EOP-RPV and initiate a manual reactor scram CT-2.0 Given an unisolable RCIC steam leak and secondary containment temperature above maximum safe values in two or more areas, the crew will perform an RPV Blowdown per EOP-C2.

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 1 - N2-0SP-ISC-M@002 CREW Crew conducts a pre-brief, walks down NOTE: Ensure crew has marked up copy of the panels.

procedure SRO Directs performance of N2-0SP-ISC M@002 for vacuum breakers 2ISC*RV33A & 2ISC*RV33B BOP Performs N2-0SP-ISC-M@002 for vacuum breakers 2ISC*RV33A &

2ISC*RV33B as follows:

EXAMINER NOTE: The Operator at the Back Initial Steps:

Panel will coordinate with the front panel operator

  • Open 21AS*SOV167, PRIMARY to verify expected alarms and computer points CNTMT OUTBD ISOL VLV TO during the surveillance test DRYWELL, at 2CEC*PNL851.
  • Open 2IAS*SOV185, PRIMARY CNTMT INBD ISOL VLVTO DRYWELL, at 2CEC*PNL851.

Steps For 2ISC*RV33A:

  • Open 2ISC*RV33A, VACUUM BREAKER INBOARD, by depressing AND holding VACUUM BREAKER 2ISC*RV33A INBOARD TEST pushbutton.

Verifies the following:

  • Position indication lights for 2ISC*RV33A indicate open.

(Green Extinguished, Red Illuminated)

NMP2 2010 NRC Scenario #5 -6 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 1 (Continued)

  • Annunciator 601556 DRYWELL VACUUM BRKR INBOARD DISC OPEN alarms on 2CEC*PNL601.
  • Computer pt. ISCBC37, RV33A134A OW VAC BRKR IN is generated in the OPEN condition.
  • Position indication lights for 2ISC*RV33B indicate closed. (Green illuminated, Red extinguished)
  • Close 2ISC*RV33A, by releasing VACUUM BREAKER 2ISC*RV33A INBOARD TEST pushbutton.

Verifies the following:

  • Position indication lights for 2ISC*RV33A indicate closed.

(Green Illuminated, Red Extinguished)

  • Annunciator 601556 DRYWELL VACUUM BRKR INBOARD DISC OPEN clear on 2CEC*PNL601.
  • Computer pt. ISCBC37, RV33A134A DWVAC BRKR IN is generated in the CLOSED condition.

Steps For 2ISC*RV33B:

  • Open 2ISC*RV33B, VACUUM BREAKER OUTBOARD, by depressing AND holding VACUUM BREAKER 2ISC*RV33B OUTBOARD TEST pushbutton.

Verifies the following:

  • Position indication lights for 2ISC*RV33B indicate open.

(Green Extinguished, Red Illuminated)

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 1 (Continued)

  • Annunciator 601557 DRYWELL VACUUM BRKR OUTBOARD DISC OPEN alarms on 2CEC*PNL601.
  • Computer pt. ISCBC39, RV33B/34B DW VAC BRKR IN is generated in the OPEN condition.
  • Position indication lights for 2ISC*RV33A indicate closed. (Green illuminated, Red extinguished)
  • Close 2ISC*RV33B, by releasing VACUUM BREAKER 2ISC*RV33B OUTBOARD TEST pushbutton.

Verifies the following:

  • Position indication lights for 2ISC*RV33B indicate closed.

(Green Illuminated, Red Extinguished)

  • Annunciator 601557 DRYWELL VACUUM BRKR OUTBOARD DISC OPEN clear on 2CEC*PNL601.
  • Computer pt. ISCBC39, RV33B/34B DW VAC BRKR OUT is generated in the CLOSED condition.

Final Steps

  • Close 2IAS*SOV167, PRIMARY ROLE PLAY: When contacted by control room to CNTMT OUTBD ISOL VLV TO perform field actions, acknowledge the request and DRYWELL, at 2CEC*PNL851.

report back 1 minute later that they are complete and have been independently verified.

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 1 (Continued) NOTE: the next four steps are performed locally

  • Remove pipe cap downstream of 21AS*V511 *SOV167 LLRT TEST t

CONNECTION.

  • Slowly open 21AS*V511 AND 2IAS*V199, PENETRATION Z19A TEST CONNECTION, to vent off Drywell Vacuum Breaker supply line inside the Drywell..
  • WHEN Drywell Vacuum Breaker supply line is depressurized, close 21AS*V199 AND 2IAS*V511.
  • Replace pipe cap downstream of 2IAS*V511.

Final Step in Control Room

  • Close 2IAS*SOV185, PRIMARY CNTMT INBD ISOL VLVTO DRYWELL, at 2CEC*PNL851.

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENTS 2 and 3 - Continue Startup and IRM 0 SRO Fails Upscale Directs plant startup continued at N2-0P 101A Step E.3.3, RSCS Group 6, RWM step 17, Control Rod 50-51 from 00 to 12 RO CONSOLE OPERATOR: After the first control rod RO selects control rod 50-51 and begins is moved and when directed by Lead Evaluator, to withdraw from 00 to 12.

activate malfunction by depressing TRIGGER 1 NM06D IRM CHNL D FAILURE UPSCALE RO/CREW Diagnoses IRM "0" Upscale indications:

  • 603207, IRM UPSCALE
  • 603301, RPS TRI P SYTEM B UPSCALEII NOPERABLE
  • 603402, RPS B NMS TRIP
  • 603410, RPS B AUTO TRIP
  • In accordance with N2-0P-92 Step H.2.0, bypasses IRM "0" by placing the joystick to BYPASS.
  • Verifies the BYPASS light is lit.

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS EVENTS 2 and 3 (Continued)

  • In accordance with ARP, resets the1/2 scram per N2-0P-97 Step H.2.0 as follows:
  • Places Reactor Scram Reset Logic B and Reactor Scram Reset LogiC D switches to RESET.
  • Verifies PILOT SCRAM VALVE SOLENOID white lights are lit for B,D, F and H.

SRO Directs RO to continue startup and rod withdrawal.

RO Continues to withdraw control rods.

BOP Monitors BOP equipment.

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 4 - Stuck Control Rod 10-11 RO Diagnoses Stuck Control Rod 10-11 and Malfunction is PRESET: informs CRS.

R007 Control Rod 10-11 SRO CONSOLE OPERATOR: Delete malfunction Directs actions to unstuck control rod in RD07 after Drive Water pressure has been raised accordance with N2-0P-30 Section H.1.0 50 psig.

RO Takes the following steps to move stuck control rod in accordance with N2-0P-30 EXAMINER NOTE: The malfunction will be removed and control rod movement will occur after

  • Simultaneously depresses AND holds CONTINUOUS INSERT AND drive pressure has been raised 50 psig.

WITHDRAW push buttons on 2CEC*PNL603.

  • Raises drive water pressure in 50 psig increments by throttling closed 2RDS PV101, DRIVE WrR PRESS CONTROL MOV and attempts to move the rod.
  • WHEN indication of inward control rod motion is received, quickly release CONTINUOUS INSERT pushbutton and depress CONTINUOUS WITHDRAW pushbutton while continuing to hold WITHDRAW pushbutton.
  • Restores drive water pressure to normal value after successful control rod motion.

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 5 - Mode switch to Run SRO Directs continuing startup and placing mode switch to RUN in accordance with N2-0P-101A.

RO

  • Verifies APRMs are reading >5% by placing the IRM/APRM recorder select switch to APRM.
  • In each RPS division, leaves one IRM/APRM recorder select switch in the APRM position.
  • Checks with SRO to confirm chemistry parameters, HWC is pressurized and the APRM gain adjustments are SAT.
  • Verifies the following:
  • Steamline pressure greater than 766 psig.
  • APRMs on scale between 5% AND 12%.
  • Condenser vacuum greater than 25" Hg.
  • No Mode 1 restrictions exist.
  • Attachment 7 has been completed AND any exceptions listed.
  • Places Mode Switch to RUN.

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 6 - Loss of Div II Switchgear CREW Recognizes trip of BKR 17-2 CONSOLE OPERATOR: After the page announcement is made that MODE 1 has been SRO entered or when directed by Lead Evaluator, Enters and Directs actions in accordance activate malfunction by depressing TRIGGER 2 with N2-S0P-3, Loss of AC Power ED04G 4.16KV NORMAL BUS FAULT SWG 17

  • Verify affected SW Non-Essential (TRUE) Valves Close
  • Verify One SW pump starts in affected division
  • Directs opening all SW Non-Essential Valves
  • Directs throttling the SW 74 valves as required to <1 Okgpm rd
  • Directs starting a 3 service water pump in non affected division.
  • Directs verifying proper EDG operation
  • Directs restoring DW Pneumatics
  • Directs restores DW cooling by starting the unit coolers at Back Panel 873
  • Enters Tech Spec LCO 3.8.1 Condition A Required Action A.1 to complete SR 3.8.1.1 with 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> completion time AND A.3 to restore required off site circuit to operable with 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time.

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 6 (Continued) BOP/RO

  • Verifies affected SW Non-Essential Valves Close
  • Verifies One SW pump starts in affected division
  • OPENS all SW Non-Essential Valves
  • Throttles the SW 74 valves as required to <1 Okgpm rd
  • As directed, Starts a 3 service water pump in non affected division
  • Verifies proper EOG operation
  • Restores OW Pneumatics by opening SOV 184 and SOV 165
  • Restores OW cooling by starting the unit coolers at Back Panel 873 EXAMINER NOTE: May proceed to next event once OW cooling is restored.

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 7 - SRO Tech Spec, 2ICS*MOV128 CREW Breaker Trip, Containment Isolation Valve

  • Recognizes and reports RCIC Inboard Failed Open Isolation Valve failure.
  • Report condition to CRS.

CONSOLE OPERATOR: When directed by the Lead Evaluator, insert the following overrides for BOP/RO ICS*MOV128 breaker trip, by depressing

  • At 2CEC*PNL601, determine IF any TRIGGER 3 INOP Status Lights are energized.
  • 01A1S106L00333 STEAM SUPPLY INBD
  • IF any INOP Status Lights are ISOL MOV 128 INOP AMBER, ON energized, refer to their applicable
  • 01 A2DS080L006315 MOV 128 VALVE Alarm Response Procedure.

STEAM SUPPLY LINE ISLN (INBOARD)

  • Determines INOP status light lit for RED,OFF TURB STM SPLY INBD ISOL VLV
  • AN601319, RCIC Valve Motor Overload
  • IF power is NOT available, dispatch ON an operator to 2EHS*MCC302 to confirm 2EHS*MCC302 14A, 2ICS*MOV128 Power Supply, is ON.

SRO ROLE PLAY: When dispatched by the BOP/RO to

  • Acknowledges BOP/RO report.

status power supply to MOV128 wait two (2)

  • Refers to T.S. 3.6.1.3, Primary minutes and report breaker in the tripped condition. Containment Isolation failure.

No cause is apparent.

  • From Bases 8.3.6.1.3 - The power operated automatic isolation valves are required to have isolation times within limits and actuate on an automatic isolation signal. The valves covered by this LCO are listed with their associated stroke times in Ref. 1.

(TRM)

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 7 (Continued)

  • CONDITION A: One or more penetration flow paths with one PCIV inoperable except due to leakage not within limit.

REQUIRED ACTION:

  • A.1: Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

COMPLETION TIME (for A.1): 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> except for main steam line.

(Determines penetration must be isolated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.) AND REQUIRED ACTION

  • A.2: Verify the affected penetration flow path is isolated.

COMPLETION TIME (for A.2): Once per 31 days for isolation devices outside primary containment.

  • Refer to TRM If necessary
  • The Primary Containment Isolation Valves and, if applicable, valve groups, isolation signals, and isolation times are listed in Table T3.6.1-2.

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 7 (Continued)

  • Notifies Operations and Plant Management
  • May contact WEC SRO for assistance and work planning
  • Conducts post event brief NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 8 - Unisolable RCIC Steam Leak CREW

  • Responds to Annunciator 851254, CONSOLE OPERATOR: When directed by Lead PROCESS AIRBORNE RADN MON Evaluator, insert the following malfunction by ACTIVATED depressing TRIGGER 4:
  • Diagnoses issue by checking DRMS RC12, RCIC Steam Leak in Reactor Building, CRT Display to determine RB 30% over 5 minute ramp HVR*RE229 alarming.

The following annunciator alarms: SRO 851254 PROCESS AIRBORNE RADN MON On High Radiation Level:

ACTIVATED

  • Verify Automatic Response has occurred, as applicable.

(NOTE: SBGT is already in service from previous event)

  • Identify area affected and verify level reading.
  • Refers to N2-EOP-SC
  • Enters and directs actions per EOP SC when HVR Exhaust radiation is above an isolation setpoint (HVR*RE229 exceed DRMS Red setpoint)
  • IF any area temperature is above the Annunciator 601157 Reactor Building General isolation setpoint THEN GO to 28 Areas Temperature High is received and RCIC (Step SC-2)

Steam Line should isolate as temperature rises

  • Isolate all discharges into affected above 135°F. WCS system isolates.

areas except systems needed for fire fighting or other EOP actions (Step SC-4)

  • Directs BOP/RO to manually isolate RCIC Steam Line.

MOV*128 has no power and MOV*121 does not close.

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 8 (Continued)

  • IF "primary system" is discharging into the Reactor Building (YES RCIC, RCtC steam line pressure stays up and Conditional Step SC-4) THEN GO to temperatures in the area are still rising. 29 (Step SC-7)

Thus, no isolation of the RCIC Steam Line has occurred. Fire panel 849107 FIRE DETECTED PNL 103 SE QUAD 215 alarms as a result of steam discharging into the area.

  • BEFORE any area temperature reaches Maximum Safe Value (Detail S; 212°F) (Step SC-7 and SC
8) .... ENTER RPV Control, while continuing in EOP-SC (CT-2.0)

These actions are directed by the SRO from EOP-RPV

  • ENTER SCRAM PROCEDURE N2 SOP-101C, while continuing in EOP-RPV (Step 3) and Directs a Reactor Scram (Critical Task 1.0)
  • Executes LEVEL and PRESSURE legs concurrently.

LEVEL ACTIONS DIRECTED BY SRO

  • Restore and maintain RPV water level between 159.3 inches and 202.3 inches using one or more Preferred Injection Systems (Detail E1) Step L
3. SRO should direct control between 160 to 200 inches.
  • IF level cannot be restored and maintained above 159.3 inches .... THEN maintain level above

-14 inches (Fig Z)

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 8 (Continued)

  • OK to augment with Alternate Injection systems if needed (Detail E2) (Use of these is NOT expected)

PRESSURE ACTIONS DIRECTED BY SRO

  • IF RPV Blowdown (EOP-C2) is anticipated ..... THEN Rapidly depressurize the RPV using the Main Turbine Bypass Valves. OK to exceed 100°F/hr cooldown. (Step P-1 Override). (This is an expected action because EOP-C2 will be necessary due to rising Reactor Building temperatures).
  • Is any SRV Cycling? NO (Step P-2)
  • Use Alternate Pressure Control Systems, if needed.
  • Restore pneumatics to drywell, if necessary.

BEFORE proceeding to Step P-8.

While in Step P-7 orsooner, the SRO will likely return to EOP-SC actions and be waiting for 2 areas to reach 212°F NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 8 (Continued) These actions are directed by SRO when returning to EOP-SC

  • WAIT until 2 or more areas are above Maximum Safe Value for the same parameter (Step SC-9), THEN proceed to SC-10 to enter EOP-C2.

BOP/RO

  • Recognize and reports increasing area temperatures and in the Reactor At back panel LOS Temperature Monitoring Panels Building.

P632 and P642 the first area in alarm and to reach

  • Uses EOP-6 Attachment 28 to monitor 212 OF and report temperature conditions.

E31-N619A and N620A

  • Confirms WCS and RHR isolation.

E31-N619B and N620B

  • Reports failure of RCIC to automatically isolate.
  • Attempts to manually isolate the RCIC Steam Line by closing MOV*121 using If "anticipating" RPV Blowdown, aI/ 5 BPVs are keylock switch.

opened. RPV pressure lowers. When RPV

  • l\IIonitors back panels for trending area pressure drops to about 850 psig, the following temperatures and radiation levels.

malfunction automatically activates from TRIGGER

  • Reports levels and trends to the SRO.

5:

  • IF directed to rapidly depressurize the TC15A, EHC Pump A Trip, TRUE RPV using the Main Turbine Bypass TC15B, EHC Pump B Trip, TRUE Valves, opens all 5 BPVs using the BYPASS JACK INCREASE EHC Pumps trip and as EHC pressure lowers, the pushbutton. OK to exceed 100°F/hr BPVs will close due to loss of fluid pressure.

cooldown. (Step P-1 Override). (This is an expected action because EOP C2 will be necessary due to rising Reactor Building temperatures).

  • Reports trip of EHC pumps and loss of BPVs, if used for rapid depressurization.

NMP2 2010 NRC Scenario #5 -22 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 8 (Continued) RO These are N2-S0P-1 01 C Scram Actions:

  • IF Automatic Scram is anticipated AND time permits ...... THEN Reduce Recirc Flow to 55 mlbm/hr per N2 SOP-101D. (NA, at 4% power)
  • IF Mode switch is NOT in REFUEL position ..... THEN Place MODE Switch to SHUTDOWN position.

(Critical Task 1.0)

  • Verify automatic responses.
  • All rods full in
  • Rx power lowering
  • Turbine trippedlTSVs & TCVs shut
  • Generator tripped and house loads transferred
  • SDV V&D valves closed
  • RCS pumps downshift
  • FWLC controlling level> 159.3"
  • Performs LEVEL control actions as directed by SRO from EOPs
  • Performs PRESSURE control actions as directed by SRO from EOPs
  • WHILE continuing, perform the following as time permits:

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS EVENT 8 (continued)

  • IF WCS is in one pump three filter lineup .... THEN Throttle close 2WCS*MOV200 (AND if required, throttle open 2WCS-MOV11 0) to obtain approximately 225 gpm wcsnow.

Second area temperature reaches 212'F (E31 N601 E and N601 F). RPV Blowdown is required.

BOP/RO

  • Report second area temperature reaching 212°F.
  • If required, restore pneumatics to drywell.
  • At P851 IAS*SOV166 and 184.
  • At P601 lAS *SOV164 and 165.
  • When directed, opens seven (7)

ADS/SRVs by using keylock switch EXAMINER NOTE: ADS may be initiated from for EACH ADS valve at control 601 panel if Suppression Pool Cooling had room back panel P628 and P631.

been placed in service. (Critical Task - 2.0)

These actions are directed by the SRO from EOP-C2

  • Will the reactor stay shutdown without boron? YES all rods are fully inserted (Step 2)

NMP2 2010 NRC Scenario #5 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS EVENT 8 (Continued)

  • Drywell Pressure? Below 1.68 psig (Step 9, then bypass step 10)
  • Suppression Pool Level? Above EI 192 ft (Step 11)

In accordance with N2-EOP-HC Attachment 5, with

  • Open all 7 ADS Valves (Step 12) no RHS pumps running, opening the 7 ADS valves (Critical Task- 2.0) is performed by placing individual keylock switch
  • OK to exceed 100°F/hr for EACH ADS valve to open at control room back
  • Restore pneumatics to drywell if panel P628 and P631. necessary
  • Can all 7 ADS Valves be opened?

YES (Step 13)

EVENT 9 - Condensate Booster Pumps Trip BEFORE proceeding to Step 17.

CONSOLE OPERATOR: When RPV water level BOP/RO HIGH LEVEL TRIP A RESET amber light on P603 Maintains level as directed by CRS using illuminates after the ADS Blowdown, confirm EOP*RPV Table E1 and E2 Systems.

TRIGGER 6 automatically activates malfunctions:

  • FW02A, CONDENSATE BOOSTER PUMP TRIP (P2A), TRUE
  • FW02B, CONDENSATE BOOSTER PUMP TRIP (P2B), TRUE
  • FW02C, CONDENSATE BOOSTER PUMP TRIP (P2C), TRUE The operators will be required to restore RPV level using EOP-RPV Table E1 and E2 Systems TERMINATION CRITERIA RPV Slowdown is complete and RPV level is maintained above TAF.

NMP2 2010 NRC Scenario #5 -25 November 2010

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