ML103500290

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Final Operating Exam (Sections a, B, and C) (Folder 3)
ML103500290
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 10/27/2010
From: Todd Fish
Operations Branch I
To: Dean R
Constellation Energy Nuclear Group
Hansell S
Shared Package
ML101900588 List:
References
TAC U01797
Download: ML103500290 (220)
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NRC JPM RO C001 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Perform Nl-ST-DO DAILY CHECKS (Partial) Revision: NRC 20 I 0 Task Number: N/A Approvals:

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

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

Trainer/Evaluator:

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

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

Comments:

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

NRC 2010 JPM RO COOl November 2010

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

Simulator Simulator Set-up:

1. Initialize Simulator to IC-160
2. Verify the following overrides are set:
a. 5M80A03SS0 == 73.00
b. 5M81A03560 == 7S.00
c. 5Ml18A03860 = 76.00
d. SM116A03840 68.00
e. SARI TS IA031 000 = 68.00
f. 13MIA042680 == 69.00
g. 9MS3AOS1270 = 70.S0
3. Take the simulator to Run, and then back to Freeze
4. Verify average Drywell temperature is less than 130°F S. Verify total Recirc flow is 38 Mlbmlhr
6. Verify FWLC is selected to column 11
7. Turn off PI monitor Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

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

Notes to Instructor / Evaluator:

NRC 2010 JPM RO COOl November 2010

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

References:

1. NUREG 1123,2.1.18, RO 2.9
2. Nl-ST-DO Tools and Equipment:

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

Initial Conditions:

1. The plant is operating at approximately 67% power.
2. Nl-ST-DO, Daily Checks, is in progress.
3. The provided printout shall be used to determine computer point and PI data.
4. Instructor to ask the operator for any questions.

Initiating cue:

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

I Performance Steps I Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTIME _______

2. Obtain a copy of the reference procedure N-ST-DO obtained, sections 5.0 and 6.0 SatfUnsat and review/utilize the correct section referenced Note: Completed N1-ST-DO is attached as JPM key. Small differences in recorded values may occur due to instrument interpolation.

NRC 2010 JPM RO COOl November 2010

I Performance Steps I Standard Grade

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

RECORDSTOPTlME_________

NRC 2010 JPM RO COOl November 2010

Initial Conditions:

1. The plant is operating at approximately 67% power.
2. Nl-ST-DO, Daily Checks, is in progress.
3. The provided printout shall be used to determine computer point and PI data.

Initiating cue:

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

NRC 2010 JPM RO COOl November 2010

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

Title:

DWFDT I DWEDT Leak Rate Detennination and Evaluation Revision: NRC 2010 Task Number: NIA Approvals:

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

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

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

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

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

NRC 2010 RO ADMIN JPM C002 November 2010

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

Classroom Simulator Set-up (if required):

N/A Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

During this Training JPM, 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 PasslFail.
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.

References:

1. NUREG 1123,2.1.7, RO 4.4
2. NI-0P-8; Attachment 6
3. Unit 1 Technical Specifications, Section 3.2.5 Tools and Equipment
1. Calculator NRC 2010 RO ADMIN JPM C002 November 2010

Task Standard: Determine DWFDT, DWEDT, and total leak rates and recognize Technical Specification limits are being exceeded.

Initial Conditions:

1. The plant is operating at 100% power.
2. The Drywell Leak Detection System is out of service.
3. The following information is available for the Drywell Floor Drain Tank (DWFDT):
  • Leak rate has been constant at 0.92 gpm for the past week.
  • Previous pump down at 21:00 today.
  • Most recent pump down at 21 :25 today.
  • Pump down volume = 140 gallons.
4. The following information is available for the Drywell Equipment Drain Tank (DWEDT):
  • Leak rate has been constant at 0.50 gpm for the past week.
  • Previous pump down at 12:00 today.
  • Most recent pump down at 22:00 today.
  • Pump down volume = 430 gallons.
5. Technical Specification (TS) limits are:
  • 2 gpm increase in unidentified leakage within any period of24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> or less.
  • 25 gpm total leakage averaged over any 24-hour period.
6. Instructor to ask the operator for any questions.

Initiating cue:

"(Operator's name), determine DWFDT, DWEDT, and total leak rates and determine if they are within the Technical Specification limits or not. Record your findings on the attached worksheet."

Performance Steps Standard Grade

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

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

2. Obtain a copy of the reference procedure and Nl-OP-8, Attachment 6 obtained as necessary SatlUnsati review/utilize the correct section NA
3. Determines DWFDTleak rate (140 gallons/25 minutes) = 5.6 gpm PasslFail
4. Evaluates DWFDTleak rate Identifies DWFDT (unidentified leakage) rate PasslFaii is ABOVE the limit (5 gpm)

Identifies DWFDT (unidentified leakage) rate PasslFail is ABOVE the limit for increase in a 24-hour period (2gpm) (5.6 gpm - 0.92 gpm) =4.68 gpm increase (plus or minus 0.02 gpm)

NRC 2010 RO ADMIN JPM C002 November 2010

Performance Steps Standard Grade

5. Determines D WEDT leak rate 10 hours0.417 days <br />0.0595 weeks <br />0.0137 months <br /> = 600 minutes PasslFail (430 gallons/600 minutes) = 0.72 gpm (plus or minus 0.02 gpm)
6. Evaluates TOTAL leak rate Determines total leak rate is 6.32 gpm (plus or PasslFail minus 0.04 gpm) (0.72 gpm + 5.6 gpm = 6.32 gpm)

Note: This may be evidenced by lack of a report Determines total leak rate is within the limit PasslFail to the contrary. (25 gpm)

Terminating Cue: DWFDT, DWEDT, and total leak rates are determined and evaluated against Technical Specification criteria.

RECORD STOP TIME _ _ __

NRC 20lO RO ADMIN JPM C002 November 2010

Initial Conditions:

1. The plant is operating at 100% power.
2. The Drywell Leak Detection System is out of service.
3. The following information is available for the Drywell Floor Drain Tank (DWFDT):
  • Leak rate has been constant at 0.92 gpm for the past week.
  • Previous pump down at 21:00 today.
  • Most recent pump down at 21 :25 today.
  • Pump down volume = 140 gallons.
4. The following information is available for the Drywell Equipment Drain Tank (DWEDT):
  • Leak rate has been constant at 0.50 gpm for the past week.
  • Previous pump down at 12:00 today.
  • Most recent pump down at 22:00 today.
  • Pump down volume = 430 gallons.
5. Technical Specification (TS) limits are:
  • 2 gpm increase in unidentified leakage within any period of 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> or less.
  • 25 gpm total leakage averaged over any 24-hour period.

Initiating cue:

"(Operator's name), determine DWFDT, DWEDT, and total leak rates and determine if they are within the Technical Specification limits or not. Record your findings on the attached worksheet."

NRC 2010 RO ADMIN JPM C002 November 2010

Candidate Worksheet i

Within Technical Calculated Leak Rate Value Specification Limit?

(gpm)

DWFDT Leak Rate DWEDT Leak Rate Total Leak Rate i

NRC 2010 RO ADMIN JPM C002 November 2010

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

Title:

Prepare a tagout for RBCLC pump 13 Revision: NRC 2010 Task Number: N/A Approvals:

~~~'~~(~~~~~~~~~~-LL4~~V NIA - Exam Security I General Supervisor General Supervisor Date Operations Training (Designee) Operations (Designee)

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

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

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

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

Comments:

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 InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

I. 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 1123,2.2.13, RO 4.1
2. CNG-OP-l.Ol-1007
3. P&ID C-18022-C sheet 2
4. EWDs C-19436-C sheets 1 and 3
5. NI-OP-II NRC 2010 RO ADMIN JPM EC November 2010

Tools and Equipment:

None Task Standard: Identify the components required be tagged to tagout RBCLC pump 13for a shaft seal replacement.

Initial Conditions:

1. The plant is operating at 100% power.
2. RBCLC pumps 11 and 12 are operating.
3. RBCLC pump 13 is secured.
4. Maintenance is required to replace RBCLC pump 13 shaft seal.
5. eSOMs is unavailable.
6. Ask the operator for any questions.

Initiating cue:

"(Operator's name), identify the components required to be tagged to tagout RBCLC pump 13 for the shaft seal replacement. Record the required components and their tagged positions using CNG-OP-1.0I-l 007 attachment 8."

Performance Steps Standard Grade

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

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

2. Obtains a copy of the reference procedure eNG-OP-I.O 1-1 007 obtained as necessary SatlUnsatl and reviews/utilizes the correct section NA
3. Obtains and references appropriate drawings Obtains and references, as required: SatlUnsat and/or procedures to determine isolations
  • P&ID C-18022-C sheet 2
  • EWDs C-19436-C sheets 1 and 3
  • NI-OP-ll
4. Records required isolations. Identifies the following isolations on CNG OP-l.Ol-I007 attachment 8:

Note: Due to unavailability of eSOMs and other electronic databases, exact component IDs, names, and tagging positions may vary.

70-03, Reactor Building Closed Loop Cooling SatlUnsat Pump 13, Control Switch in pull-to-Iock 70-03, Reactor Building Closed Loop Cooling SatlUnsat Pump 13, Motor Breaker Trip Fuses pulled or installed in OFF NRC 2010 RO ADMIN JPM EC November 2010

Performance Steps Standard Grade 70-03, Reactor Building Closed Loop Cooling SatlUnsat Pump l3, Motor Breaker Close Fuses pulled or installed in OFF 70-03, Reactor Building Closed Loop Cooling PasslFail Pump 13, Motor Breaker racked out or disconnected 70-09, BV - 13 RBCLC Pump Discharge, PasslFaii closed 70-141, BV 13 RBCLC Pump Suction, PasslFail closed 70-500, Drain 13 RBCLC Pump, open SatlUnsat 70-501, Vent 13 RBCLC Pump, open and SatiUnsat uncapped Terminating Cue: Isolations for RBCLC pump l3 have been identified and recorded on CNG-OP-l.Ol 1007 attachment 8.

RECORD STOP TIME _ _ __

NRC 2010 RO ADMIN JPM EC November 2010

Initial Conditions:

1. The plant is operating at 100% power.
2. RBCLC pumps 11 and 12 are operating.
3. RBCLC pump 13 is secured.
4. Maintenance is required to replace RBCLC pump 13 shaft seal.
5. eSOMs is unavailable.

Initiating cue:

"(Operator's name), identify the components required to be tagged to tagout RBCLC pump 13 for the shaft seal replacement. Record the required components and their tagged positions using CNG-OP-1.0I-1007 attachment 8."

NRC 2010 RO ADMIN JPM EC November 2010

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

Title:

Perform Actions for External Security Threats Revision: NRC 20 I 0 Task Number: N/A Approvals:

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

NIA - Exam Security I Configuration Control Date TrainerlEvaluator:_ _ _ _ _ _ _ _ _ _ _ __

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

Comments:

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 InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

References:

1. NUREG 1123,2.4.28, RO 3.2
2. EPIP-EPP-IO 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 ofthe Indian Point site and one is headed north in the direction ofthe 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-l 0 attachment 2."

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTTTIME _______

2. Obtains a copy of the reference procedure EPIP-EPP-IO attachment 2 obtained SatlUnsat and reviews/utilizes the correct section Note: Once the candidate locates EPIP-EPP-IO 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 Proper communications used (GAP-OPS-Ol) PasslFail
4. Checks plant parameters Observes major plant parameters using SatlUnsat control room instrumentation (ex. Reactor power, pressure and level, Containment conditions)
5. Notifies Security Site Supervisor Proper communications used (GAP-OPS-Ol) PasslFail Note: Security Site Supervisor may be contacted by Gaitronics page or by calling x5222 or x2591 NRC 2010 RO ADMIN JPM EP November 2010

Performance Steps Standard Grade

6. Initiates any Operating, Special Operating or Proper communications used (GAP-OPS-Ol) SatlUnsat EOPs required Cue: Inform that other operators are executing the required Operating, Special Operating and Emergency Operating Procedures
7. As directed by Shift Manager, makes Makes plant announcement in accordance announcements with EPIP-EPP-I 0 attachment 6:

Cue: As Shift Manager, provide EPIP-EPP-l 0 a. Places GAItronics in Merge PasslFaii attachment 6, ImminentlProbable Aircraft Attack Announcement (JPM b. Sounds Evacuation Alarm for 5 PasslFail page 6) seconds Note: If candidate begins to broadcast c. Announces: PasslFail announcement over speakers, examiner should direct the candidate to not Attention All Plant Personnel, this (is broadcast over speakers and direct the a drill / is an actual emergency) announcement to the examiner only. Aircraft Impact Imminent. Evacuate the protected area immediately.

Report directly to the Learning Center or P-Building. I repeat, this (is a drill

/ is an actual emergency)

d. Repeats Alarm and Announcement SatlUnsat
e. Leaves GAItronics in merge SatlUnsat
8. When Security Contingency Event no longer Makes plant announcement in accordance exists, makes a termination announcement in with EPIP-EPP-18 attachment 7:

accordance with EPIP-EPP-18

a. Sounds Station Alarm for 10 seconds SatlUnsat Cue: As Shift Manager, report that Security Contingency Event no longer exists and b. Announces: SatlUnsat provide EPIP-EPP-18 attachment 7, Emergency Termination Announcement Attention. Attention all personneL (JPM page 7) The security event at Nine Mile Point Unit 1 and 2 has been terminated. I Note: If candidate begins to broadcast repeat, the security event has been announcement over speakers, examiner terminated should direct the candidate to not broadcast over speakers and direct the c. Repeats alarm and announcement SatlUnsat announcement to the examiner only_
d. Removes GAItronics 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-IO attachment 2."

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

NRC 2010 RO ADMIN JPM EP November 2010

ATTACHMENT 6 Date: Today Tune: Now IMMINENT/PROBABLE AIRCRAFT ATTACK ANNOUNCEMENT Instructions:

1. Place GAltrooics in Merge
2. Sound Evacuation Alarm for 5 Seconds

~'1Attention All Plant Personnei, this (is a driH~an actual emerge, 3.

Aircraft Impact imminent. Evacuate the~~tfRllmmediateIY_ Report directly to the Learning Center or P-BuiJding I repeat this (is a drill actual emerge, Repeat Alarm and Announcement.

Leave GAJtronics in merge for the duration of the event.

Upon comptetion retum this attachment to the EP Dept.

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

ACTIVATION AND DIRECnON OF THE EMERGENCY PLANS EPiP-EPP*18 Revision 01900 Page 19 of 21 Page 1 of 1 Attad1ment 7, Emergency Tennination Announcement Date: 0 ay nme! Now Emergencev Termination Announcement (As requested by the SM/EO or EDIRM)

Instructions:

1. Place GAltronk:s in Merge
2. Sound Station Alarm for 10 Seconds
3. Announce, I
a. "AttentiOn. Attention all personnel.

The security ~mergencycondltionat Nine Mile Point )! 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_ _ _ _ _~em&rg&ncy condition has been terminated.
4. Repeat Alarm and Announcement
5. Remove GAUronics from merge.
6. Upon completion retum this attachment to the EP Dept. [N0306]

NRC 2010 RO ADMIN JPM EP November 2010

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

Title:

Determine Thermal Limits with Inoperable Pressure Regulator Revision: NRC 2010 Task Number: N/A Approvals:

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

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

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

Evaluation Method: _--"X-"----__ Perform ________ Simulate Evaluation Location: _ _ _ _ Plant ___--"X~__ Simulator or other location 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 un sat or individual competency area unsat requires a comment.

Comments:

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

NRC 2010 SRO ADMIN JPM COOl November 2010

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

Classroom Simulator Set-up: NIA Directions to the InstructorlEvaluator:

Applicant is to be provided with Nl-RESP-l for recording data. Applicant must have access to Core Operating Limits Report, Tech Specs, 3D Monicore printout data and NI-OP-3l.

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor I Evaluator:

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

References:

1. NUREG 1123,2.1.19, SRO 3.8
2. Core Operating Limits Report (COLR)
3. Nl-RESP-l Daily Thermal Limit Surveillance
4. Tech Spec 3.1.7 Tools and Equipment:
1. Calculator NRC 2010 SRO ADMIN JPM COO I November 2010

Task Standard: Complete Nl-RESP-l, Daily Thennal Limit Surveillance. Detennine and evaluate adjusted thennallimits with an inoperable pressure regulator. Identify COLR MCPR limit is exceeded and Tech Spec 3.1.7 actions are required.

Initial Conditions:

1. The plant is operating at power with 5 recirc loops in service.
2. Feedwater Pump 13 is in operation.
3. The plant is at Beginning of Cycle (BOC).
4. Reactor Engineering reports the value of Tau is 1.0.
5. Scoop Tube setting is 102.5%.
6. Current core thennal power and flow are indicated on the given 3D Monicore printout.
7. Core thennal power has not changed since the last 3D Monicore printout.
8. The Mechanical Pressure Regulator is out of service for repairs.
9. The MPR linkage is disconnected at the Front Standard.
10. Instructor to ask operator for any questions.

Initiating cue:

"(Operator's name), using the 3D Monicore printout provided, complete Nl-RESP-l, Daily Thennal Limit Surveillance section 9.2, up to and including step 9.2.14. Report the results in the space below."

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTT~ ________

2. Obtain a copy of the any of the reference Reference materials obtained SatlUnsat documents
3. Record data in Nl-RESP-l by obtaining Records Core Thennal Power in step 9.2.2 as SatlUnsat infonnation from 3D Monicore printout 1591 MWth and 86.0%

Records Total Core Flow in step 9.2.3 as SatlUnsat 48.023 Mlbmlhr and 71.1 %

Records step 9.2.4 as NA, since all RRPs are SatlUnsat operating Records MAPRAT and location in step 9.2.5 SatlUnsat as 0.775 and 41-38-4 Records step 9.2.6 as NA, since all RRPs are SatlUnsat operating NRC 2010 SRO ADMIN JPM COOl November 2010

I i Performance Steps I Standard Grade

4. Determine "Adjusted MCPR limit" value for Determines adjusted value to be 1.797, from SatlUnsat step 9.2.7, with pressure regulator out of COLR Section 2.1 and Figures 2a, 2e, and service and thermal power between 45% and 2f, as follows:

90% from the COLR For 70% :::; P < 90% MCPR Limit = (Rated Note: Uses COLR Figure 2a. 2e and 2f, to OLMCPR)IFRTP determine calculation information.

Rated OLMCPR= MCPRlim*Kf 1.52*1.017 = 1.545 (1.535-1.581 acceptable)

MCPRLimit 1.545/.860 = 1.797 (1.785-1.838 acceptable)

Enters 1.797 (1.785-1.83 8 acceptable) SatlUnsat as "Adjusted MCPR limit" value for step 9.2.7

5. Determine "Actual MCPR Value" from 3D Determines actual MCPR value to be 1.708, SatlUnsat Monicore printout from printout Enters 1.708 as "Actual MCPR Value" for SatlUnsat step 9.2.7
6. Determine COLR thermal limit restriction Evaluates actual MCPR value to be less than PasslFail for MCPR is not met adjusted limit and that the MCPR thermal limit is NOT met Role Play: Candidate may make notifications regarding violated thermal limit.

Acknowledge report, direct the Candidate to identifY the required action and then complete the rest of the surveillance.

e7. Enter Tech Spec 3.1.7.c Recognize entry into Tech Spec 3.1.7.c PasslFail Identifies "action shall be initiated within 15 SatlUnsat minutes to restore operation to the prescribed limit. If all operating MCPRs are not returned within 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br />, reactor power reductions shall be initiated at a rate not less than 10% per hour until MCPR is within the prescribed limit".

NRC 2010 SRO ADMIN JPM COOl November 2010

Performance Steps I Standard Grade

8. Record data in Nl-RESP-l by obtaining Records MFLCPR and location in step 9.2.8 SatlUnsat information from 3D Monicore printout as 0.905 and 29-14 Note: If candidate recognizes that 0.905 is an Records step 9.2.9 as NA, since all RRPs are SatlUnsat incorrect value based on operation operating without the backup pressure regulator, it is acceptable to calculate a correct value and record in step 9.2.9. This value would be calculated as 1.797/1.708::::

1.052 (1.045-1.076 acceptable).

Cue: If candidate does not want to proceed through step 9.2.8 due to incorrect MFLCPR values, report that the step deletion process has been completed to delete step 9.2.8. Continue at step 9.2.9.

Records Power to Flow Ratio (PFR) in step SatlUnsat 9.2.10 as 0.933

9. Determine "Adjusted LHGR limit" value for Determines adjusted value to be 0.860, from PasslFail step 9.2.11, with pressure regulator out of COLR Section 3.1 and Figure 3, as follows:

service and thermal power between 45% and 90% from the COLR For 70% ::; P < 90% MFLPD Limit = FRTP

= 159111850 = 0.86 Enters 0.86 as "Adjusted LHGR limit" value SatlUnsat for step 9.2.11 Note: This value may be 0.02 if Candidate interpolates from graph rather than calculates

10. Determine "Actual MFLPD Value" from 3D Determines actual MFLPD value to be PasslFaii Monicore printout 0.735, from printout Enters 0.735 as "Current value" for step SatlUnsat 9.2.11
11. Determine COLR thermal limit restriction Evaluates actual MFLPD value to be less PasslFail for MFLPD is met than adjusted limit and that the MFLPD thermal limit is met Note: Successful completion ofthis step may be evidenced by the lack of a report to the contrary.

NRC 20 I0 SRO ADMIN JPM COO I November 2010

I Performance Steps I Standard Grade

12. Record data in Nl-RESP-l by obtaining Records MFLPD and location in step 9.2.12 SatlUnsat information from 3D Monicore printout as 0.735 and 41-38-4 Records FPAPDR in step 9.2.13 as 0.855 SatlUnsat from printout Records step 9.2.14 as NA, since FPAPDR is SatlUnsat

< 1.0 TERMINATING CUE: Nl-RESP-I, Daily Thermal Limit Surveillance completed through step 9.2.14.

Adjusted thermal limits for an inoperable pressure regulator are determined. Violation of MCPR limit and required Tech Spec actions are identified.

RECORDSTOPTlltlE_________

NRC 2010 SRO ADMIN JPM COOl November 2010

Initial Conditions:

1. The plant is operating at power with 5 recirc loops in service.
2. Feedwater Pump 13 is in operation.
3. The plant is at Beginning of Cycle (BOC).
4. Reactor Engineering reports the value of Tau is 1.0.
5. Scoop Tube setting is 102.5%.
6. Current core thermal power and flow are indicated on the given 3D Monicore printout.
7. Core thermal power has not changed since the last 3D Monicore printout.
8. The Mechanical Pressure Regulator is out of service for repairs.
9. The lVlPR linkage is disconnected at the Front Standard.

Initiating cue:

"(Operator's name), using the 3D Monicore printout provided, complete N1-RESP 1, Daily Thermal Limit Surveillance section 9.2, up to and including step 9.2.14.

Report the results in the space below."

NRC 2010 SRO ADMIN JPM COO 1 November 2010

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

Title:

Assess Reportability Requirements Revision: NRC 2010 Task Number: N/A Approvals:

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

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

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

Evaluation Method: _--=X-=---__ Perform _______ Simulate Evaluation Location: _ _ _ _ Plant ___-----'X'-"-__ Simulator or other location Expected Completion Time: 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 un sat or individual competency area unsat requires a comment.

Comments:

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

NRC 2010 SRO ADMIN JPM C002 November 2010

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

Classroom Simulator Set-up: NIA Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

References:

1. NUREG 1123,2.1.18, SRO 3.8
2. CNG-NL-1.01-1004
3. 10CFR50.72
4. NUREG 1022
5. EAL Matrix
6. EPIP-EPP-20 NRC 2010 SRO ADMIN JPM C002 November 2010

Tools and Equipment:

None Task Standard: Determine 10 CFR 50.72 reportability requirements.

Initial Conditions:

1. The plant was operating at 100% power with no equipment out of service.
2. A failure of the Feedwater Level Control System has occurred.
3. The plant was manually scrammed in anticipation of an automatic Reactor scram.
4. High Pressure Coolant Injection (HPCI) automatically initiated on low Reactor water level.
5. Reactor water level was restored above the HPCI low level setpoint, and the HPCI initiation signal was reset.
6. Instructor to ask operator for any questions.

Initiating cue:

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

I Performance Steps I Standard Grade

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

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

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

These are likely to include the following:

  • CNG-NL-1.01-1004
  • EPIP-EPP-20 attachment 6A
3. Locate and identify applicability of 10 CFR Determines no emergency classification is SatlUnsat 50.72(a)(1 ) required Note: This step may be evaluated by the absence of a one hour emergency report
4. Locate and identify applicability of 10 CFR Identifies reportability per 10 CFR PasslFail 50.72(b)(2)(iv)(B) 50.72(b)(2)(iv)(B), for a valid RPS actuation while the Reactor is critical NRC 2010 SRO ADMIN JPM C002 November 2010

I Performance Steps I Standard Grade Determines 10 CFR 50.72(b)(2)(iv)(B) PasslFail requires notification within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br />

5. Locate and identifY applicability of 10 CFR Identifies reportability per 10 CFR PasslFail 50.72(b)(3)(iv)(A) 50.72(b)(3)(iv)(A), for a valid actuation of HPCI Note: May alternately refer to 10CFR 50.72(b)(3)(iv)(B)(5) for this Determines 10 CFR 50. 72(b)(3)(iv)(A) PasslFail reportability requirement. requires notification within 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> Note: Candidate may report that the HPCI notification is due within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> to coincide with the RPS actuation notification. This satisfies the requirement for notification within 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br />.

Terminating Cue: Reportability requirements have been determined.

RECORDSTOPT~E ________

NRC 2010 SRO ADMIN JPM C002 November 2010

Initial Conditions:

1. The plant was operating at 100% power with no equipment out of service.
2. A failure of the Feedwater Level Control System has occurred.
3. The plant was manually scrammed in anticipation of an automatic Reactor scram.
4. High Pressure Coolant Injection (HPCI) automatically initiated on low Reactor water level.
5. Reactor water level was restored above the HPCI low level setpoint, and the HPCI initiation signal was reset.

Initiating cue:

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

NRC 2010 SRO ADMIN JPM C002 November 2010

Attachment 1 JPM Scorecard KEY Identify the applicable 10 CFR 50.72 reportability requirements, the reason that they apply and the associated time limitations for reporting under that category Reportability Requirement and Reason Time Limit 10 CFR 50.72(b)(2)(iv)(B) Within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> Valid Reactor Protection System (RPS) actuation while the Reactor is critical 10 CFR 50.72(b)(3)(iv)(A) Within 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> Valid actuation of High Pressure Coolant Injection System (HPCI) Note: Candidate may report that the HPCI notification is due Note: May alternately refer to 10CFR within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> to coincide 50.72(b)(3)(iv)(B)(5) for this reportability with the RPS actuation requirement. notification. This satisfies the requirement for notification within 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> .

NRC 2010 SRO ADMIN JPM C002 November 2010

Attachment 2 JPM Scorecard for Applicant Use Identify the applicable 10 CFR 50.72 reportability requirements, the reason that they apply and the associated time limitations for reporting under that category Reportability Requirement and Reason Time Limit I

NRC 20 I 0 SRO ADMIN JPM C002 November 2010

Attachment 3 Actual Plant Event Used as Basis for JPM Power Reactor Event Number: 61005 Facility: NINE MILE POINT Notification Date: Today's Date Region: 1 State: NY Notification Time: Today's Time [ETJ Unit: [1] [ ] [ ] Event Date: Today's Date RX Type: [1] GE-2,[2] GE-5 Event Time: 11:58 [EDT]

NRC Notified By: Name Last Update Date: Today's Date HQ OPS Officer: Name Emergency Class: NON EMERGENCY Person (Organization):

10 CFR Section: Name (R1DO)

SO.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL SO.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION SCRAM Initial Current Unit Code RX CRIT PWR Initial RX Mode PWR Current RX Mode 1 M/R Y 100 Power Operation 0 Hot Shutdown Event Text MANUAL SCRAM AND HIGH PRESSURE COOLANT INJECTION FOLLOWING A LOSS OF FEEDWATER LEVEL CONTROL "At 1158 on Monday, October 5,2009, Nine Mile Point Unit One was manually scrammed from approximately 100% rated power due to failure of the Feedwater Level Control System, in anticipation of a reactor scram. Following the manual scram insertion at 11:58, High Pressure Coolant Injection (HPCI)

System automatically initiated on low Reactor Vessel (RPV) level. At 11:59, RPV level was restored above the HPCI System low level actuation setpoint, and the HPCI System initiation signal was reset. At Nine Mile Point Unit One, a HPCI System actuation signal on low RPV level is normally received following a reactor scram, due to level shrink.

"Unit 1 has commenced cooldown, in preparation for the forced outage to commence repairs. Reactor water level is being controlled in the normal operating band; reactor temperature is 4S0?F and reactor pressure is approximately 500 psig.

"10 CFR 50.72(b)(2)(iv)(B) requires reporting within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> when any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical.

"10 CFR SO.72(b)(3)(iv)(A) requires reporting within 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> when a valid actuation ofthe High Pressure Coolant Injection System occurs. n All control rods fully inserted. All systems functioned as required following the reactor scram. The reactor is currently stable in Mode 3. HPCI has been secured. Makeup water is being provided by the Reactor Feedwater System and decay heat removal is through the bypass valves to the condenser. There was no impact on Unit 2 and the plant is in a normal post-scram electrical lineup.

The licensee notified the NRC Resident Inspector.

NRC 2010 SRO ADMIN JPM C002 November 2010

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

Title:

Review ofNl-ST-MlA, Liquid Poison Pump 11 Operability Test Revision: NRC 20 I 0 Task Number: NIA Approvals:

NIA - Exam Security /

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

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

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

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

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

Comments:

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

NRC 2010 SRO 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 InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional 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 PassIFail. All steps are sequenced critical unless denoted by a
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Selfverification shall be demonstrated.

References:

1. NUREG 1123,2.2.12, SRO 4.1
2. NI-ST-MIA
3. Technical Specification 3.1.2 NRC 2010 SRO ADMIN JPM EC November 2010

Tools and Equipment:

1. Marked up copy ofNI-ST-MlA with flow rate calculation of27.5 gpm.

Task Standard: Complete review of Nl-ST-MIA. Identify Liquid Poison pump 11 is inoperable and identify the required actions.

Initial Conditions:

1. The plant is operating at 100% power.
2. NI-ST-MIA, Liquid Poison Pump 11 Operability Test, has been completed and requires Operations and Shift Manager review.
3. Instructor to ask the operator for any questions.

Initiating Cue:

"(Operator's name), using the completed surveillance provided, complete Section 10.1, Operations Review and Section 10.2, SM Review. Record the results of your review and any required actions in the space below."

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTT~ _______

2. Obtain a copy of the reference procedure Copy of completed surveillance will be and review/utilize the correct section ofthe provided to the performer procedure
3. Completes section 10.1, Operations Determines Liquid Poison pump 11 discharge SatlUnsat Review, references procedure sections as pressure is SAT applicable to verify the required data, and evaluates the data Determines Liquid Poison pump 11 flow rate PasslFaii is UNSAT SatlUnsat Determines Liquid Poison pump 11 motor current is SAT PasslFail Determines NI-ST-MIA results are UNSAT Note: ACRs are no longer generated as a SatlUnsati standalone document. Generation of a CR Determines ACR to be initiated NA leads to generation of the required work order, which covers this requirement NRC 2010 SRO ADMIN JPM EC November 2010

Performance Steps Standard Grade Informs Operations Manager SatlUnsat Determines ESL entry is required for Liquid SatlUnsat Poison pump 11 Determines 7 day LCO applies per Tech Spec PasslFail 3.1.2 Determines entry into Control Room Log is SatlUnsat required Note: May also refer to yellow clearance tag as Determines yellow clearance tag required for SatlUnsat a caution tag. Liquid Poison pump 11 Determines CR to be written SatlUnsat Terminating Cue: Operations and Shift Manager Review ofNl-ST-MlA is complete. Required actions and notifications are identified.

RECORD STOP TIME _ _ __

NRC 2010 SRO ADMIN JPM EC November 2010

Initial Conditions:

1. The plant is operating at 100% power.
2. N1-ST-M1A, Liquid Poison Pump 11 Operability Test, has been completed and requires Operations and Shift Manager review.

Initiating Cue:

"(Operator's name), using the completed surveillance provided, complete Section 10.1, Operations Review and Section 10.2, SM Review. Record the results of your review and any required actions in the space below."

NRC 2010 SRO ADMIN JPM EC November 2010

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

Title:

Generate and approve an Emergency Exposure Authorization Revision: NRC 2010 Task Number: NIA Approvals:

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

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

TrainerlEvaluator:_ _ _ _ _ _ __

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

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating 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 NRC 2010 SRO ADMIN JPM RC November 2010

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

Read Before Every JPM Performance:

For the performance of this JPM, I will function as the 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! concurrent verification will not be provided; therefore it should not be requested.

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified as PasslFail.
2. During evaluated JPM:
  • Self-verification shall be demonstrated.
3. During training JPM:
  • Self-verification shall be demonstrated.
  • 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 ADMIN JPM RC November 2010

Initial Conditions:

1. A Site Area Emergency is in progress.
2. You have assumed the responsibilities of the Shift ManagerlEmergency Director.
3. An Emergency Condenser 11 steam leak into the Reactor Building cannot be isolated without manually shutting Condensate Return Valve 39-05.
4. Entry to the Reactor Building is required to manually close valve 39-05 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 (TLD 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 (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).
9. Ask the operator for any questions.

Initiating Cue:

"(Operator's name), choose an individual to close valve 39-05, state the reason why that worker was chosen, estimate the expected radiation exposure and document your authorization for an Emergency Exposure."

I Performance Steps I Standard Grade

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

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

2. Obtain a copy of the reference procedure EPIP-EPP-lS is obtained and Attachments 1 Sat/Unsat and review/utilize the correct section and 1-1 are referenced
3. Determine the expected exposure for the F or an experienced worker - Calculates that a SatlUnsat task 24 minute exposure in a 15 Rlhr field will cause a dose of 6 R For a new worker - Calculates that a 30 minute exposure in a 15 Rlhr field will cause a dose of7.5 R NRC 2010 SRO ADMIN JPM RC November 2010

I Performance Steps I Standard Grade

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

Note: The following rationale supports worker Does NOT select Worker A PasslFail selection:

Does NOT select Worker B PasslFail

  • Worker A should NOT be chosen due to previously receiving a Selects Worker C PasslFail planned special exposure
  • Worker B should NOT be chosen Does NOT select Worker D PasslFaii 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 D; 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 States that Worker C was chosen to minimize SatlUnsat worker dose States that Worker A was NOT chosen due to Sat/Unsat a previous planned special exposure States that Worker B was NOT chosen due to Sat/Unsat being a declared pregnant worker States that Worker D was NOT chosen due to SatlUnsat higher dose
6. Estimate expected exposure Determines Worker C will receive an SatlUnsat estimated 6 R while completing the task (24 minutes x 15 Rlhr 160 minlhr)

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. Role play as Worker C and acknowledge the briefing.

NRC 2010 SRO ADMIN JPM RC -4 November 2010

i Peiformance Steps I Standard Grade Role Play: The Candidate may ask for an RWP to be generated. Role play as RP and state that an RWP has been generated.

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

TERMINATING CUE: Emergency Exposure Authorization Form has been completed.

RECORDSTOP~ _________

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 ManagerlEmergency Director.
3. An Emergency Condenser 11 steam leak into the Reactor Building cannot be isolated without manually shutting Condensate Return Valve 39-05.
4. Entry to the Reactor Building is required to manually close valve 39-05 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 (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:

"(Operator's name), choose an individual to close valve 39-05, 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 20 I 0

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

Title:

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

/

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

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

TrainerlEvaluator:_ _ _ _ _ _ _ _ __

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

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

Comments:

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

NRC 2010 SRO ADMIN JPM EP November 2010

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

Read Before Every JPM Performance:

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

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional/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.
2. During Evaluated JPM:
  • Self-verification shall be demonstrated.
3. During Training JPM:
  • Self-verification shall be demonstrated.
  • No other verification shall be demonstrated.

References:

1. NUREG 1123,2.4.41, SRO 4.6
2. EPIP-EPP-Ol
3. EPIP-EPP-18
4. EPIP-EPP-20
5. EPMP-EPP-OI0l Tools and Equipment:

1.0 EPIP-EPP-Ol, ATTACHMENT 1, UNIT 1 EAL FLOWCHART 2.0 SM/ED Checklist Package NRC 2010 SRO ADMIN JPM EP November 2010

Task Standard:

Classify and declare the emergency event within 15 minutes of the time that indications are available to the Candidate that an EAL has been exceeded. Make notifications to New York State and Oswego County within 15 minutes of the time the event is declared.

Initial Conditions:

1. You are the Unit 1 Shift Manager.
2. Unit 1 was operating at 100% power.
3. Unit 2 is operating at 100% power.
4. The following conditions have occurred:
  • A leak in the Drywell results in rising Drywell pressure.
  • EOP-8, RPV Blowdown, is entered due to low RPV water level.
  • RPV water level momentarily lowers below Top of Active Fuel (TAF), but is quickly recovered to the normal band using Core Spray.
  • Reactor Building DIP is -0.25" H20.
  • Stack radiation monitors read at normal background levels.
5. The time of shutdown is 10 minutes ago.
6. Instructor to ask the operator for any questions.

Initiating Cue:

"(Operator's name), based on the above conditions, determine the event classification per EPIP-EPP-Ol and complete steps 1 through 9.a of EPIP-EPP-18, Attachment 1, SM/ED Checklist. This is a time critical task."

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

Evaluator acknowledge repeat back providing correction if necessary RECORDSTARTT~ ________

2. Obtain a copy of EPIP-EPP-O1 attachments 1 EPIP-EPP-O 1 attachments 1 and 2, and Shift SatlUnsat and 2, and Shift Manager emergency Manager emergency paperwork is obtained paperwork and review/utilize the correct section NRC 2010 SRO ADMIN JPM EP November 2010

I Performance Steps I Standard Grade

3. Enters EPIP-EPP-18, Attachment 1, SMIED Completes steps 1 thm 9.a of EPIP-EPP-18, as SatlUnsat Checklist and completes Steps 1 through 9.a described in subsequent JPM steps
4. Classifies and declares the emergency Declares an Alert within fifteen minutes of the PasslFail JPM initial condition sheet being accepted in accordance with EAL 3.1.1 EXAMINER NOTE: Time difference below must be 15 minutes or less:

JPM start time: _ __

Time of Declaration: - - - - -

5. Completes EPIP-EPP-18 attachment 1, figure Completes Attachment as shown in KEY SatlUnsat 1 flowchart to determine evacuation and accountability requirements
6. Calls the Communications Aides to the Proper communications used (GAP-OPS-O 1) SatlUnsat Control Rooms Role Play: Acknowledge communication
7. Fills out the ERO Notification System Completes Attachment as shown in KEY SatlUnsat (ERONS) form
8. Calls Unit 2 SM to inform that ERONS form Proper communications used (GAP-OPS-Ol) SatlUnsat is coming and to get Unit 2 plant status Role Play: If asked about the status of Unit 2, report that Unit 2 is still operating at 100% power with no issues
9. Completes EPlP-EPP-18 attachment 2, Completes Attachment as shown in KEY SatlUnsat Emergency Announcement NRC 2010 SRO ADMIN JPM EP November 2010

I Performance Steps I Standard Grade

10. Completes EPIP-EPP-20 Part 1 Notification Completes Attachment as shown in KEY PasslFail Fact Sheet Part 1 Notification Fact Sheet Steps 3 tbru 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: ERONS Fonn, Emergency Announcement Fonn, and Part 1 Notification Fact Sheet completed. Task completion reported to examiner.

RECORDSTOP~E _________

NRC 2010 SRO ADMIN JPM EP November 2010

Initial Conditions:

1. You are the Unit 1 Shift Manager.
2. Unit 1 was operating at lOO% power.
3. Unit 2 is operating at 100% power.
4. The following conditions have occurred:
  • A leak. in the Drywell results in rising Drywell pressure.
  • EOP-8, RPV Blowdown, is entered due to low RPV water level.
  • RPV water level momentarily lowers below Top of Active Fuel (TAF), but is quickly recovered to the normal band using Core Spray.
  • Reactor Building DIP is -0.25" H20.
  • Stack radiation monitors read at normal background levels.
5. The time of shutdown is lO minutes ago.

Initiating Cue:

"(Operator's name), based on the above conditions, determine the event classification per EPIP-EPP-Ol and complete steps 1 through 9.a ofEPIP-EPP-18, Attachment 1, SMIED Checklist. This is a time critical task."

Meteorological Data 30ft 200 ft Wind Speed 5 mph 10 mph Wind Direction I 60 0 60 0 I Stability Class D NRC 2010 SRO ADMIN JPM EP November 2010

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

Title:

Respond to a Loss of Service Water (PRA) (Alternate Path) Revision: NRC 2010 Task Number: N/A Approvals:

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

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

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

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

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

Comments:

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

NRC 2010 JPM 8-1 November 2010

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

Simulator Simulator Set-up (if required):

1. Initialize Simulator to IC 161
2. VerifY Service Water pump 11 is red flagged and Service Water pump 12 is green flagged
3. VerifY malfunction CW02B is on trigger 1 with a 15 second time delay
4. VerifY trigger 1 command is set to zdcwpstr(4)=1 (Service Water pump 12 control switch in start)
5. VerifY malfunction CW02A is active Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor! Evaluator:

1. Critical steps are identified in grading area as PasslFail.
2. During Evaluated IPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.
  • No other verification shall be demonstrated.

References:

1. NUREG 1123,295018, AA1.01, RO 3.3, SRO 3.4
2. Nl-SOP-I8.1 NRC 2010 JPM S-1 November 2010

Tools and Equipment:

None Task Standard: Nl*SOP-18.1 actions are complete through the override step for a sequential loss of Service Water pumps.

Initial Conditions:

1. The plant is operating at approximately 100% power.
2. Service Water pump 11 has tripped on overcurrent.
3. Instructor to ask operator for any questions.

Initiating Cue:

"(Operator's name), enter and execute NI-SOP-18.1 for Service Water Failure."

Performance Steps Standard Grade

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

Evaluator Acknowledge repeat back providing correction if necessary RECORDSTARTT~ ______________

2. Obtain a copy of the reference procedure and NI-SOP-IS.10btained SatiUnsat review/utilize the correct section ofthe procedure
3. Start standby Service Water pump by placing Rotates Service Water pump 12 control switch PasslFail control switch on Panel H to START CW to start, observes red light on, green light off, proper pump amps Note: Service Water pump 12 will trip after a 15 second time delay, requiring an alternate path to execute the override for loss of both Service Water pumps
4. Identifies trip of Service Water pump 12 Observes Service Water pump 12 green light SatiUnsat on, red light off, pump amps drop to zero, annunciator Hl-2-2 alarms
5. If neither Service Water pump can be started Enters override ofNI-SOP-I8J SatiUnsat OR Service Water Header pressure can NOT be restored to greater than 60 psig, then performs the following steps:

NRC 2010 JPM S*1 November 2010

Performance Steps Standard Grade

6. Start Emergency Service Water pumps Rotates ESW pump 11 control switch CW to PasslFail start, observes red light on, green light off, proper pump amps Rotates ESW pump 12 control switch CW to PasslFail start, observes red light on, green light off, proper pump amps
7. SCRAM the Reactor AND concurrently Rotates the Reactor Mode Switch CW to PasslFail execute NI-S0P-l Shutdown Cue: Another operator will perform SOP-I actions. Continue in SOP-18.1.
8. Initiate Emergency Condensers Rotates 39-05 control switch CW to open PasslFail and/or rotates 39-06 control switch CW to Cue: Another operator will maintain Reactor open pressure per EOP-2.
9. Close MSIV s Rotates 01-01 control switch CCW to close PasslFail Rotates 01-02 control switch CCW to close PasslFail Rotates 01-03 control switch CCW to close PasslFail Rotates 01-04 control switch CCW to close PasslFail
10. Trip all Rx Recirculation Pumps Rotates RRP 11 control switch CCW to stop PasslFail Rotates RRP 12 control switch CCW to stop PasslFail Cue: Another operator will monitor RBCLC Rotates RRP 13 control switch CCW to stop PasslFail and TBCLC temperatures.

Rotates RRP 14 control switch CCW to stop PasslFail Rotates RRP 15 control switch CCW to stop PasslFail Terminating Cue: Nl-SOP-lS.1 actions are completed through the override step for a sequential loss of Service Water pumps.

RECORDSTOPT~ ________

NRC 2010 JPM S-1 November 2010

Initial Conditions:

1. The plant is operating at approximately 1000/0 power.
2. Service Water pump 11 has tripped on overcurrent.

Initiating Cue:

"(Operator's name), enter and execute NI-SOP-I8.1 for Service Water Failure."

NRC 2010 JPM S-1 November 2010

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

Title:

Bypass LPRM Input To APRM Revision: NRC 2010 Task Number: NIA Approvals:

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

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

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

Evaluation Method: _....::X-"--__ Perform - - - - - - Simulate Evaluation Location: _ _ _ _ Plant X Simulator Expected Completion Time: 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's Signature:_ _ _ _ _ _ _ _ _ _ _ _ _ __ Date:_ _ _ _ _ __

NRC 2010 JPM S-2 November 2010

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

Simulator Simulator Set-up (if required):

1. Initialize Simulator to IC-162 (shared with JPM S-8)
2. Verify LPRM 20-25A failed downscale (malfunction NM29R20C25A active)
3. Verify LPRM 20-25A Power Supply, NPWRS-RJOIC-L, on backpanel is selected to Position 1 Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before EveI)' JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor I Evaluator:

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

References:

1. NUREG 1123,215005, A4.04, RO 3.2, SRO 3.2
2. NI-OP-38C NRC 2010 JPM S-2 November 2010

Tools and Equipment:

None Task Standard: LPRM 20-25A input to APRM 13 is bypassed per NI-0P-38C and APRM 13 is unbypassed.

Initial Conditions:

1. LPRM 20-2SA failed downscale.
2. There are no other LPRMs inoperable or bypassed.
3. No APRMs are bypassed.
4. A review of Control Room logs has been performed by the CRS to verifY APRMs are operable.
5. The CRS has reviewed Technical Specifications and verified that the associated APRM can be bypassed.
6. The CRS has completed NI-OP-38C, Attachment 5, and determined that the LPRM 20-2SA input to its associated ARPM can be bypassed.
7. Instructor to ask operator for any questions.

Initiating Cue:

"(Operator's name), bypass LPRM 20-2SA input to its associated APRM per NI-OP-38C, and then return the APRM to operable. You are NOT required to bypass the LPRM alarm function."

Performance Steps Standard Grade

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

Evaluator Acknowledge repeat back providing correction if necessary RECORDSTARTTUME _______

2. Obtain a copy of the reference procedure and NI-OP-38C obtained, precautions & SatlUnsat review/utilize the correct section of the limitations reviewed & section H.3.0 procedure referenced
3. Confirm LPRM can be bypassed Determines step complete per initial SatlUnsat per Technical Specifications, using conditions Attachment 5
4. Bypass selected APRM which includes the DeterminesLPRM 20-25A is assigned to SatlUnsat associated LPRM that is to be bypassed APRM 13 (back panel or Att. 50fOP-38C)

Note: Candidate may use OP-38C section H.l.0 Positions APRM 11-12-13-14 BYPASS PasslFail to bypass the APRM. joystick to CH 13 Checks E-panellight, computer, then checks SatlUnsat back panel light to verifY APRM bypassed

5. Position LPRM to be bypassed to readout on At APRM 13 drawer, positions INPUT SatlUnsat APRM module drawer selector switch, S9, to position 4 Note: APRM 12 and APRM 13 share the same Observes meter indication SatlUnsat drawer.

NRC 2010 JPM S-2 November 2010

Performance Steps Standard Grade

6. Position LPRM to readout on its power Positions Power Supply selector switch for SatJUnsat supply module NPWRS-RJ01C-L to Position 4 Observes meter indication (0 on 0-125 scale)
7. Slide APRM drawer open to expose red APRM drawer pulled out to expose red SatJUnsat LPRM bypass knurled knobs knurled knobs Note: Switches used to bypass the specific LPRM signal to its APRM averaging circuit are located in the related APRM module. Withdrawing this module exposes knurled knobs, which are numbered to correspond with the LPRMs on the faceplate.
8. Rotate appropriate LPRM red knob counter Rotates LPRM red knurled knob S4 counter PasslFail clockwise to bypass LPRM clockwise 114 turn Note: The bypass switch is a two-position switch and will only rotate 1/4 turn
9. Confirm LPRM reading on APRM drawer Observes PERCENT POWER meter at 0% SatJUnsat reads zero with APRM 13 INPUT selector switch, S9, in position 4
10. Confirm LPRM reading on power supply Observes LPRM reading on power supply SatJUnsat module remains the same module did not change (remains 0)
11. Place APRM drawer counts switch to Positions APRM 13 drawer counts switch to SatJUnsat COUNT COUNT
12. Confirm LPRM count rate on APRM Determines that there are 7 operable LPRM SatJUnsat module drawer reflects the number of non inputs to APRM 13 bypassed LPRMs assigned to that APRM channel Determines that LPRM count rate on APRM SatJUnsat 13 should indicate 70%

Note: When in COUNT, the APRM drawer meter indicates the number of available Observes PERCENT POWER meter for SatJUnsat LPRMs times 10% (in this case, 7 x 10% APRM 13 indicates 70%

= 70%).

13. Verify APRM drawer switch is in Average Positions APRM 13 drawer switch to SatJUnsat AVERAGE NRC 2010 JPM S-2 November 2010

Performance Steps Standard Grade

14. NotifY the Reactor Engineering (RE) depart Notifies RE that LPRM 20-25A input to SatlUnsat ment that an LPRM has been bypassed APRM 13 is bypassed Cue: As RE, acknowledge the report that LPRM 20-25A input to APRM 13 is bypassed.

Cue: Inform the operator that RE will perform the APRM GAIN ADJUSTMENTS per Nl-REP-12.

15. Perform APRM gain adjustment per Nl Acknowledges report from RE that the APRM SatlUnsat OP43A Attachment, APRM GAIN GAIN ADJUSTMENTperN1-REP-12 is ADJUSTMENT, orNI-REP-12, APRM complete GAIN ADJUSTMENT Note: Booth Operator - Perform an AGAF once the LPRM is bypassed.

Cue: As RE, report to the reactor operator that the APRM GAIN ADJUSTMENT per Nl-REP-12 is complete.

16. Remove selected APRM from bypass Positions APRM 11-12-13-14 BYPASS Pass/Fail joystick to NEUTRAL position Note: Candidate may use OP-38C section H.2.0 to un-bypass the APRM. Checks E-panellight, computer, then checks SatlUnsat back panel light to verifY APRM un-bypassed
17. Ensure an ESL entry is made for the Informs the SM/CRS that an ESL entry is SatlUnsat bypassed LPRM required for the bypassed LPRM Cue: As the SM/CRS, report that the bypassed LPRM has been entered into the ESL log.
18. Ensure a CRC Book Entry is made in the Informs the SM/CRS that a CRC Book entry SatlUnsat LPRM bypass status sheet section for the is required for the bypassed LPRM bypassed LPRM Cue: As the SM/CRS, report that the CRC Book has been updated for the bypassed LPRM.

Terminating Cue: LPRM 20-25A input to APRM 13 is bypassed per NI-OP-38C and APRM 13 is unbypassed.

RECORD STOP TIME _ _ __

NRC 2010 JPM 8-2 November 2010

Initial Conditions:

1.LPRM 20-25A failed downscale.
2. There are no other LPRMs inoperable or bypassed.
3. No APRMs are bypassed.
4. A review of Control Room logs has been performed by the CRS to verify APRMs are operable.
5. The CRS has reviewed Technical Specifications and verified that the associated APRM can be bypassed.
6. The CRS has completed NI-OP-38C, Attachment 5, and determined that the LPRM 20-25A input to its associated ARPM can be bypassed.

Initiating Cue:

"(Operator's name), bypassLPRM 20-25A input to its associated APRM per NI-OP 38C, and then return the APRM to operable. You are NOT required to bypass the LPRM alarm function."

NRC 2010 JPM 8-2 November 2010

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

Title:

Synchronize Main Generator to Grid, Main Generator Locks Out Revision: NRC 2010 Task Number: NI A Approvals:

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

Configuration Control Date Performer:_ _ _ _ _ _ _ _ _ _ _ _ _ _(ROISRO)

Evaluation Method: _-'X'-"'--__ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant _ _----"'-"--__ Simulator Expected Completion Time: 30 minutes Time Critical Task: No Alternate Path Task: Yes Start Time: _ _ __ Stop Time: _ _ _ __ Completion Time: _ _ _ __

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

Comments:

Evaluator's Date:_ _ _ _ _ __

NRC 2010 JPM S-3 November 2010

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

Simulator Simulator Set-up (if required):

1. Initialize Simulator to IC-163.
2. Generator ready to be synchronized.
3. Complete NI-OP-32 through Step E.3.1. Candidate will start JPM with Step E.3.2.
4. Verify malfunction TCOI is set on Trigger 1 with a 10 second delay time.
5. Verify remote EGlO is set on Trigger 2 with a fmal value of"greenf'.
6. Verify remote EG12 is set on Trigger 2 with a final value of "redf' and a 2 second delay time.
7. Verify Trigger 1 is set to activate on "hzleglOc=l&zdeglOSO=O".

Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor I Evaluator:

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

NRC 20 I 0 JPM S-3 November 2010

References:

1. NUREG 1123,245000, A4.02, RO 3.1, SRO 2.9
2. N1-0P-32
3. N1-ARP-A7
4. Nl-SOP-31.1 Tools and Equipment:

None Task Standard: Main Generator synchronized to the grid, and then Turbine trip responded to in accordance with N1-S0P-31.1.

Initial Conditions:

1. A plant startup is in progress.
2. Reactor power is approximately 18%.
3. NI-OP-43A step E.S.9 is in progress to synchronize and load the turbine and generator.
4. The Main Generator is ready to be synchronized to the grid.
5. NI-0P-32 is completed through step E.3.1.
6. Nine Mile Point Unit 2 Lines 5 and 6 are in-service.
7. Instructor to ask operator for any questions.

Initiating Cue:

"(Operator's name), complete synchronizing the Main Generator to the grid by starting at step E.3.2 of N 1-0P-32. Load the Generator until all turbine bypass valves are closed. Then, complete the remainder of section E.3.0."

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back prOViding correction ifnecessary RECORDSTARTTUME _______

2. Obtain a copy of the reference procedure N 1-0P-32 obtained and section E.3.0 entered SatlUnsat and review/utilize the correct section ofthe procedure
3. Verify open R91S and R925 Verifies R915 and R925 indicate open by SatlUnsat verifying red lights off, green lights on Note: There is a short time delay before movement ofMOD-18 results in indicating light change and clearing of annunciator A 7-1-5 "Generator Switch 18 Open".
4. Close switch SW-18 Places SW 18 Generator 1 switch to close and PasslFail NRC 2010 JPM S-3 November 2010

Per{sJrmance Stees Standard Grade verifies green light goes out and red light is on

5. Insert Sync Key into R915 (R925) Inserts Sync Key into R915 (R925) PasslFail SYNCHRONIZING Switch, AND place SYNCHRONIZING Switch, AND places R915 (R925) SYNCHRONIZING Switch R915 (R92S) SYNCHRONIZING Switch to to ON ON
6. Verifies INCOMING and RUNNING Adjusts voltage as needed using the Exciter SatlUnsat voltages are matched Rheostat
7. Adjust GOVERNOR Switch UNTIL Adjusts generator frequency using by adjusting SatlUnsat synchroscope is rotating slowly in the the GOVERNOR Switch FAST direction
8. When INCOMING and RUNNING When synchroscope indicates 3 to 5 degrees PasslFail voltages are matched, AND synchroscope lead time, places control switch for R915 is indicating 3 to 5 degrees lead time, close (R925) in the CLOSE position R915 (R925)
9. Immediately load the generator to 15-60 Places governor control switch in the RAISE SatlUnsat MWe OR UNTIL all Turbine Bypass position until all turbine bypass valves are Valves Close closed (as observed on panel AI, all Turbine BV indicating lights "green")
10. Place R915 (R925) SYNCHRONIZING R915 (R925) SYNCHRONIZING Switch SatlUnsat Switch to OFF and remove key placed in OFF and key removed Note: When the SYNCHRONIZING Switch is placed in OFF, a trigger with a 10 second time delay will cause a Turbine trip. This initiates the alternate path.
11. Executes alarm response procedures or Observes annunciators, determines the SatlUnsat Nl-SOP-31.l Turbine and Generator have tripped and enters NI-SOP-31.1 Cue: If candidate requests guidance, tell them to respond using the procedure for a Turbine trip.
12. Verify the following: Visually observes the following:
  • Turbine Stop valves closed Turbine Stop Valves closed (green lights on) SatlUnsat
  • Turbine Control valves closed Turbine Control Valves closed (green lights SatlUnsat on)
  • Turbine Reheat Stop Valves closed Combined Reheat Valves closed (green lights SatlUnsat on)
  • Bypass valves maintaining Reactor pressure (red lights on for several valves) pressure as necessary NRC 2010 JPM S-3 November 2010

Perfgrmance Stell.S Standard Grade

13. Verify the following Electrical Visually observes the following:

Distribution system conditions:

  • 345 Kv Breakers R915, R925 TRIPPED 345Kv Breakers R915, R925 TRIPPED Sat/Unsat (Green light on)
  • MOD 18 OPEN MOD 18 OPEN (Green light on) Sat/Unsat
  • PB 11, PBl2 supplied from Reserve PB 11, PBl2 supplied from Reserve Power Sat/Unsat Power (R123 and Rl12 CLOSED, Red lights on)

Cue: Another Operator will control RPV water level and pressure. Continue with the actions ofSOP-31.1.

14. Perform the following:
  • VerifY ON, Aux. Oil pumps Rotates Aux. Oil Pump switches (2) clockwise, observes red lights illuminate, SatlUnsat green lights extinguish Resets 86 relays by rotating control switches PasslFail
  • Reset Generator 86 relays clockwise Dispatches operator to restart Stator Water PasslFail

Rotates Bearing lift pump switches (5) Sat/Unsat

  • Start bearing lift pumps clockwise, observes red lights illuminate, green lights extinguish
15. Shutdown turbine per NI-OP-31 Proper communications used (GAP-OPS-Ol) Sat/Unsat Cue: Inform candidate that another operator will be tasked with Turbine shutdown.
16. Verify ATS Gross Failure Lights are OFF Observes ATS Gross Failure Lights are OFF SatlUnsat
17. Contact Structural Engineering to perform Proper communications used (GAP-OPS-Ol) Sat/Unsat walkdown of System 03 piping and support for damage Terminating Cue: Main Turbine tripped, TCVs, TSVs and Combined Reheat Valves closed, plus Generator 86s reset, Stator Water Cooling on, Auxiliary Oil pumps on, and Bearing Lift pumps on.

RECORD STOP TIME _ _ __

NRC 2010 JPM S-3 November 2010

Initial Conditions:

1. A plant startup is in progress.
2. Reactor power is approximately 18%.
3. N1-0P-43A step E.S.9 is in progress to synchronize and load the turbine and generator.
4. The Main Generator is ready to be synchronized to the grid.

S. N1-0P-32 is completed through step E.3.l.

6. Nine Mile Point Unit 2 Lines S and 6 are in-service.

Initiating Cue:

"(Operator's name), complete synchronizing the Main Generator to the grid by starting at step E.3.2 ofN1-0P-32. Load the Generator until all turbine bypass valves are closed. Then, complete the remainder of section E.3.0."

NRC 2010 JPM S-3 November 2010

NRCJPM 8-4 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Rapid RWCU System Restoration for Level Control Revision: NRC 2010 Task Number: NIA Approvals:

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

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

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

Evaluation Method: __~_ _ Perform ___________ Simulate Evaluation Location: _ _ _ _ Plant ____--"-"'--___ Simulator Expected Completion Time: 20 minutes Time Critical Task: No Alternate Path Task: 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 8-4 November 2010

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

1. Initialize Simulator to IC-164
2. Verify RPV water level is above 100 inches
3. Verify RWCU system isolated with isolation signal clear Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor I Evaluator:

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

References:

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

None NRC 2010 JPM S-4 November 2010

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

Initial Conditions:

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

Initiating Cue:

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

Performance Steps Standard Grade

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

Evaluator Acknowledge repeat back providing correction if necessary RECORDSTARTT~ ________

2. Obtain a copy of the reference procedure N1-EOP-HC Attachment 12 is obtained SatlUnsat and review/utilize the correct section of the procedure
3. Verify the following:
  • The cause of the isolation is known Determines cause is known and corrected per SatlUnsat AND corrected initial conditions
4. Verify closed the following valves:
  • 33.1-01B, CLEANUP PCV 11 (LP) Observes 33.1-0 IB in MAN and output signal SatlUnsat atO
  • 33-39B, CLEANUP PCV 12 (HP) Places controller PC-33-39 in MAN and dials SatlUnsat to 0
5. Using RMC-33-151, CLEANUP SYS Verifies controller RMC-33-15I CLEANUP SatlUnsat SELECTOR, close 33-40 SYS SELECTOR in MAN and dialed to 0 Note: Manipulation ofFC-33-169 is inconsequential, but does not satisfy this step.

NRC 2010 JPM S-4 November 2010

Performance Steps Standard Grade

6. Using RMC-33-165, CLEANUP TO VerifY controller RMC-33-165C dialed SatlUnsat COND & WASTE FLOW, close 33-165 to 0
7. VerifY open one of the following using the CLEANUP SELECTOR CONDENSER WASTE control switch:
  • WASTE (valve 33-10, CLEANUP TO Rotates CLEANUP SELECTOR CONDENS PasslFail WASTE DISPOSAL BV) ER WASTE control switch clockwise to COND position
  • COND (valve 33-11, CLEANUP TO Observes right hand set of lights red light ON SatlUnsat CONDENSER BV) and green light OFF, for 33-11 valve to condenser Note: Initiating cue directs the candidate to reject to the condenser
8. Open 33-01R, CU RETURN Rotates33-01R control switch clockwise to PasslFaii ISOLATION VALVE 1 (INSIDE) open Observes red light ON, green light OFF SatlUnsat
9. Open 33-04R, CU SUPPLY ISOLATION Rotates33-04R control switch clockwise to SatlUnsat VALVE 12 (OUTSIDE), for open and uses pull-to-stop function after 3 approximately 3 seconds THEN PULL seconds TO-STOP Observes red light ON, green light ON SatlUnsat Note: Cleanup System Inlet Pressure will rapidly rise in the next step
10. Jog open 33-02R, CU SUPPLY ISOLA Rotates33-02R control switch clockwise to SatlUnsat TION VALVE 11 (INSIDE), using ~ open and uses pull-to-stop in Yz second second open signals followed by PULL intervals UNTIL Cleanup system inlet TO-STOP UNTIL Cleanup System Inlet pressure rises and stabilizes at reactor pressure Pressure has stabilized at Reactor Pressure on indicators Observes red light ON, green light ON SatlUnsat Observes cleanup system pressure and reactor SatlUnsat pressure approximately equal
11. Fully open 33-02R Rotates33-02R control switch clockwise to PasslFail open Observes red light ON, green light OFF SatlUnsat NRC 2010 JPM S-4 November 20lO

Pertormance Steps Standard Grade

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

Note: 33-165 controller must be greater than 20% before the valve will open, then may be lowered below 20% to adjust flow.

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

Cue: Another operator will continue with N 1 OP-3 H.10.0.

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

RECORD STOP TIME _ _ __

NRC 2010 JPM S-4 November 2010

Initial Conditions:

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

Initiating Cue:

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

NRC 20 I 0 JPM S-4 November 2010

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

Title:

Start the Emergency Ventilation System (Loop 11) Revision: NRC 2010 Task Number: NIA Approvals:

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

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

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

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

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

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

Comments:

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

NRC 2010 JPM S-5 November 2010

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

Simulator Simulator Set-up (if required):

1. Initialize Simulator to IC-165 (100% power, shared with JPM S-6).
2. VerifY RB Ventilation Exhaust fan 11 is running and Supply fan 12 is running, with other fans secured.
3. VerifY Drywell vent lineup is in service, with valves 201-31 and 201-32 open or throttled open.
4. Take simulator out of freeze.

Directions to the InstructorlEvaluator:

Prior to performance of this JPM, obtain SM/CRO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM 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 area as PasslFail.
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.

References:

1. NUREG 1123,288000, A4.01, RO 3.1, SRO 2.9
2. NI-OP-IO Tools and Equipment:

NRC 2010 JPM S-5 November 2010

None Task Standard: Emergency Ventilation System (Loop 11) is running, normal Reactor Building Ventilation is isolate, and Drywell venting is isolated.

Initial Conditions:

1. The plant is operating at 100% power.
2. Drywell venting is in progress in preparation for an outage.
3. Fuel was being moved in the SFP in preparation for the outage.
4. An irradiated fuel bundle has been dropped in the SFP.
5. The refuel floor has been evacuated.
6. Refuel floor radiation levels are rising slowly, but not enough to auto initiate RBEVS.
7. Instructor to ask operator for any questions.

Initiating Cue:

"(Operator's name), manually start Reactor Building Emergency Ventilation System Loop 11, isolate normal Reactor Building Ventilation, and isolate Drywell venting, in accordance with NI-0P-1O Section H.l.O."

Performance Steps Standard Grade

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

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

2. Obtain a copy of the reference procedure NI-OP-IO obtained, precautions & limitations SatlUnsat and review/utilize the correct section of the reviewed and section H.l.O referenced procedure
3. Verify open 202-36, EM Ventilation from Observes 202-36 red light on and green light SatlUnsat Reactor Bldg BV off
4. Verify closed the following valves:
  • 202-47, EM VENTILATION TIE BV Observes 202-47 green light on and red light SatlUnsat off
  • 202-74, EM VENTILATION LOOP Observes 202-74 green light on and red light SatlUnsat 11 COOLING BV off
  • 202-75, EM VENTILATION LOOP Observes 202-75 green light on and red light SatlUnsat 12 COOLING BV off
5. Place 202-37, EM VENTILATION LOOP Rotates 202-37 switch CW to open PasslFail 11 INLET BV control switch to OPEN
6. Verify open 202-37, EM VENTILATION Observes 202-37 red light on and green light SatlUnsat LOOP 11 INLET BV off NRC 2010 JPM 8-5 *3- November 2010

Performance Steps Standard Grade

7. Start 202-53, EVS FAN 11 Rotate switch CW to start PasslFaii
8. VerifY open 202-34, EM VENT Observes 202-34 red light on and green light SatlUnsat EXHAUST FAN 11 OUTLET BV off
9. Conftrm proper operation of 202-50, EM Observes 202-50 red and green lights both on SatlUnsat VENT EXHAUST FAN 11 INLET FCV, as valves goes to intermediate position by observing indicating lights and flow indication Observes flow meter 202-49B SatlUnsat
10. VerifY control switches for the following fans are in OFF:
  • 202-01, REACTOR BLDG SUPPLY Observes Reactor Building Supply Fan 11 SatlUnsat FAN 11 control switch in OFF
  • 202-02, REACTOR BLDG SUPPLY Rotates Reactor Building Supply Fan 12 SatlUnsat FAN 12 control switch CCW to OFF
11. VerifY control switches for the following fans are in OFF:
  • 202-05, REACTOR BLDG Rotates Reactor Building Exhaust Fan 11 SatlUnsat EXHAUST FAN 11 control switch CCW to OFF
  • 202-06, REACTOR BLDG Observes Reactor Building Exhaust Fan 12 SatlUnsat EXHAUST FAN 12 control switch in OFF
12. VerifY closed the following valves:
  • 202-32, REACTOR BLDG Rotates control switch for 202-32 and 202-31 PasslFail EXHAUST ISOLATION VALVE 11 CCWtoclose
  • 202-15, REACTOR BLDG SUPPLY Rotates control switch for 202-15 and 202-16 PasslFail ISOLATION VALVE 11 CCWtoclose
  • 202-31, REACTOR BLDG EXHAUST ISOLATION VALVE 12
  • 202-16, REACTOR BLDG SUPPLY ISOLATION VALVE 12 I NRC 2010 JPM S-5 November 2010

Performance Steps Standard Grade

13. VeritY closed the following valves:
  • 202-03, REACTOR BLDG Observes 202-03 green light on and red light SatlUnsat EXHAUST FAN 11 INLET off DAMPER Note: The procedure has the incorrect name for 202-03. It should be REACTOR BLDG SUPPLYFAN 11 INLET DAMPER. If candidate identifies need for procedure enhancement, report that CRS has processed an Immediate Procedure Change, and direct candidate to continue as though the procedure has been corrected.
  • 202-08, REACTOR BLDG Observes 202-08 green light on and red light off SatlUnsat EXHAUST FAN 11 OUTLET DAMPER
  • 202-04, REACTOR BLDG SUPPLY Observe 202-04 green light on and red light SatlUnsat FAN 12 INLET DAMPER off
  • 202-07, REACTOR BLDG Observes 202-07 green light on and red light SatlUnsat EXHAUST FAN 12 OUTLET DAMPER off
14. IF drywell and torus venting was in Proper communications used (GAP-OPS-O 1) SatlUnsat progress, THEN clear personnel from the drywell at the discretion of the Shift Manager after consulting with Radiation Protection Cue: No personnel are in the drywell.
15. VeritY 201-35 drywell and torus vent and Rotates 201-35 control switch counter SatlUnsat purge fan Off clockwise
16. VeritY closed the following valves:
  • 201-22, DRYWELL & TOR VENT & Observes 201-22 green light on and red light SatlUnsat PURGE FAN OUTLET BV off
  • 201-21, DRY WELL & TOR VENT & Observes 201-21 green light on and red light SatlUnsat PURGE FAN INLET BV off Observes 201-16 green light on and red light SatlUnsat
  • 201-16, TORUS N2 VENT & PURGE off ISOLATION VALVE 11 Observes 201-17 green light on and red light SatlUnsat
  • 201-17, TORUS N2 VENT & PURGE off ISOLATION VALVE 12 NRC 20lO JPM 8-5 -5 November 2010

Performance Steps Standard Grade

  • 201-32, DWN2 VENT & PURGE Rotates 201-32 control switch counter PasslFail ISOLATION VALVE 11 clockwise
  • 201-31,DWN2VENT&PURGE Rotates 201-31 control switch counter PasslFail ISOLATION VALVE 12 clockwise
17. Monitor RX BLDG/ATM DP and EM Observes Lll' and flow meters on L Panel SatlUnsat VENT DIS FLOW CFM meters on panel L (normal flow approximately 1600 CFM)

Note: Reactor Building DIP and RBEVS flow may take a short period of time to stabilize at normal levels.

Cue: If candidate recognizes low Reactor Building DIP and/or low RBEVS flow, state that the parameters are improving and direct them to allow them to stabilize.

18. Notify RP and CRS/SM that EVS loop 11 Proper communications used (GAP-OPS-Ol) SatlUnsat has been placed in service Terminating Cue: Emergency Ventilation System (Loop 11) is running and normal Reactor Building ventilation is isolated.

RECORD STOP TIME _ _ __

NRC 2010 JPM S-5 November 2010

Initial Conditions:

1. The plant is operating at 100% power.
2. Drywell venting is in progress in preparation for an outage.
3. Fuel was being moved in the SFP in preparation for the outage.
4. An irradiated fuel bundle has been dropped in the SFP.
5. The refuel floor has been evacuated.
6. Refuel floor radiation levels are rising slowly, but not enough to auto initiate RBEVS.

Initiating Cue:

"(Operator's name), manually start Reactor Building Emergency Ventilation System Loop 11, isolate normal Reactor Building Ventilation, and isolate Drywell venting, in accordance with NI-OP-l 0 Section H.I.O."

NRC 2010 JPM S-5 November 2010

NRC ...'PM 8-6 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

MSIV Stroke Test and Limit Switch Test (NI-ST-Q26) Revision: NRC 2010 Task Number: N/A Approvals:

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

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

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

Evaluation Method: _~_ _ Perform _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant _ _- . : 2 ' - - _ Simulator Expected Completion Time: 15 minutes Time Critical Task: No Alternate Path Task: No Start Time: _ _ __ Stop Time: _ _ __ Completion Time: _ _ _ __

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

Comments:

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

NRC 2010 JPM S-6 November 2010

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

Simulator Simulator Set-up (if required):

1. Initialize the simulator to IC-16S.
2. Take the simulator out of freeze.

Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional 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 area 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 1123,239001, A4.01, RO 4.2, SRO 4.1
2. NI-ST-Q26 NRC 2010 JPM 8-6 November 2010

Tools and Equipment:

None Task Standard: N l-ST-Q26 completed for Main Steam Isolation Valve 112.

Initial Conditions:

1. The plant is operating at 100% power.
2. All prerequisites for N1-ST-Q26 are complete.
3. Instructor to ask operator for any questions.

Initiating Cue:

"(Operator's name), test Main Steam Line Isolation Valve 112 in accordance with Nl-ST-Q26, Section 8.2."

Performance Steps Standard Grade

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

Evaluator Acknowledge repeat back providing correction if necessary RECORDSTARTTTIME __________

2. Obtain a copy of the reference procedure Nl-ST-Q26 obtained, precautions & SatlUnsat and review/utilize the correct section ofthe limitations reviewed procedure
3. Prepare to initiate a Half-Scram on CHANNEL 11:
  • Verify NO RPS Half-Scram signals Observes all scram solenoid lights energized SatlUnsat exist
  • Notify CRO that the following steps Proper communications used (GAP-OPS-OI) SatlUnsat will initiate a Half-Scram
4. Place Main Steam Isolation Valve 7% Test Test switch is rotated to the 112 position PasslFaii Switch to the 112 position
5. Confirm 01-03 MSN 112 white test light White test light for MSN 112 is verified SatlUnsat ON energized
6. Confirm 01-03 MSN 112 yellow test light Yellow test light for MSN 112 is verified de- SatlUnsat OFF energized NRC 2010 JPM S-6 -3 November 2010

Performance Steps Standard Grade Note: JPM steps 7 to 11 will occur in rapid sequence; expect annunciators F 1-1-7 and Fl-2-1.

Cue: Notify the candidate that you will be monitoring the valve mimic board for MSIV 112.

7. Momentarily place 01-03 MSIV -112 Rotates control switch for MSIV 112 PassfFail control switch to CLOSE position momentarily CCW to CLOSE, then releases
8. Confrrm RPS Channel 11 Half-Scram Observes the following:

indications

  • CHANNEL 11 SCRAM SOLENOID SatlUnsat GROUPS 1, 2, 3, 4, white light off
  • CHANNEL 11 B.U. SCRAM S.D.V. SatlUnsat VENT & DRAIN VALVE red light off Cue: If F 1-1-7 is cleared before candidate SatlUnsat completes verification, report that F 1-1-7
9. Confirm 01-03, MSIV-112 automatic Observes the following:

partial closure indications

  • 01-03 MSIV-112 Green Light ON SatlUnsat momentarily SatlUnsat
  • 01-03 MSIV-112 Red Light ON Cue: The MSIV 112 mimic light came on and SatlUnsat went off as expected.
  • 01-03 MSIV-112 Mimic Light ON momentarily
10. Confirm 01-03 MSIV-112 yellow light Observes 01-03 MSIV 112 yellow test light SatlUnsat illuminated BRIGHT ON brightly
11. Confirm 01-03 MSIV-112 automatic Observes the following:

opening indications

  • 01-03 MSIV-112 Green Light OFF SatlUnsat
  • 01-03 MSIV -112 Red Light ON SatlUnsat
  • 01-03 MSIV-112 Mimic Light OFF SatlUnsat
12. Place MSIV 7% Test Switch to the OFF Rotates Test Switch to OFF PassfFaii position NRC 2010 JPM 8-6 November 2010

Performance Steps Standard Grade Cue: Inform candidate that another operator has completed the Independent Verification.

13. Confmn 01-03 MSIV 112 White Test Observes White Test Light for MSIV-112 is SatlUnsat Light OFF OFF
14. Confirm 01-03 MSIV 112 Yellow Test Observes Yellow Test Light for MSIV -112 is SatlUnsat Light OFF OFF
15. Depress REACTOR TRIP RESET at Depresses Rx Trip RESET Button on E PasslFaii Panel E Console Note: Fl-2-1 clears
16. Confirm RPS Channel 11 Half-Scram Observes the following:

indications clear

  • CHANNEL 11 SCRAM SOLENOID SatlUnsat Groups 1,2,3,4 White Light ON
  • CHANNEL 11 BACKUP SCRAM SatlUnsat VALVE S.D.V. VENTNDDRAIN VALVE Red Light ON

RECORD STOP TIME _ _ __

NRC 2010 JPM 8-6 November 2010

Initial Conditions:

1. The plant is operating at 100% power.
2. All prerequisites for NI-ST-Q26 are complete.

Initiating Cue:

"(Operator's name), test Main Steam Line Isolation Valve 112 in accordance with Nl ST-Q26, Section 8.2."

NRC 2010 JPM S-6 November 2010

NRC JPM 8-7 Constellation Energy Nuclear Group NINE MILE POINT UNIT 1 OPERATOR JOB PERFORMANCE MEASURE

Title:

Perform a Rod Block Withdrawal Test IA W NI-ST-R4 Revision: NRC 20 I 0 Task Number: NIA Approvals:

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

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

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

Evaluation Method: _~_ _ Perform _ _ _ _ _ _ Simulate Evaluation Location: _ _ _ _ Plant ___x~__ Simulator Expected Completion Time: 25 minutes Time Critical Task: No Alternate Path Task: Yes Start Time: _ _ __ Stop Completion Time:._ _ _ __

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

Comments:

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

NRC 2010 JPM S-7 November 2010

Simulator Simulator Set-up (if required):

1. Initialize Simulator to IC-167.
2. Verify malfunction RDOSR18S1 is active.
3. Verify Trigger 1 command is set to "zdrdin=1&&rdvposd(12S>> 767".
4. Verify Trigger 1 event action is set to "dmfrdOSr18S1".

S. Provide a copy of NI-ST-R4 marked up to step 8.1.6. Mark the procedure with control rods 18-51 and 34-03 selected for steps 8.1.4 and 8.1.9, respectively.

Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional 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 area as PasslFail.
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.
  • No other verification shall be demonstrated.

NRC 2010 JPM S-7 November 2010

References:

1. NUREG 1123,201003, A2.02, RO 3.7, SRO 3.8
2. Nl-ST-R4
3. NI-0P-5 Tools and Equipment:

None Task Standard: Control Rod 18-51 re-coupled and Nl-ST-R4 section 8.1 successfully performed.

Initial Conditions:

1. The plant is shut down.
2. NI-ST-R4 is complete up to step 8.1.6 for the Rod Blocks Withdrawal Test.
3. Reactor Engineering has directed using control rod 18-51 for the first rod withdrawal, and control rod 34-03 for the second attempted rod withdrawal.
4. Reactor Engineering has directed continuous rod withdrawal for control rod 18-51 and single notch withdrawal for control rod 34-03.
5. The instructor to ask operator for any questions.

Initiating Cue:

"(Operator's name), perform Nl-ST-R4 Section 8.1, Rod Blocks Withdrawal Test, withdrawing control rod 18-51."

Performance Steps Standard Grade

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

Evaluator acknowledge repeat back providing correction ifnecessary RECORDSTARTTUME ____________

2. Obtain a copy of the reference procedure Nl-ST-R4 obtained, section 8.1 referenced SatlUnsat and review/utilize the correct section of the procedure
3. Withdraw selected control rod to position Obtains NI-0P-5, references section F.l.0 SatlUnsat 48 in accordance with NI-OP-5, Control Rod Drive System
4. Verify Control Rod Power is ON Rotates Control Rod Power switch CW to ON PasslFaii
5. Depress Rod Select pushbutton for control Depresses Control Rod 18-51 select button PasslFaii rod to be withdrawn on Rod Map Display atE Panel NRC 2010 JPM S-7 November 201 0

Performance Steps Standard Grade

6. Confirm the following:
  • Rod Select pushbutton back lighted on Observes Control Rod 18-51 select button LIT SatlUnsat Rod Map Display
7. Verify no other control rods indicate Observes no other Control Rod select lights SatlUnsat Selected at Rod Map Display, OR F Panel LIT on Control Rod select matrix and Full Core Display
8. Place and hold (4S3), Control Rod N Rotates Control Rod N Override Switch CW SatlUnsat Override Switch to NOTCH OVERRIDE and holds during Control Rod movement position and while still holding, place and hold (4S1), Control Rod Movement Rotates Control Rod Movement Switch CW SatlUnsat switch to the ROD OUT NOTCH position and hold during Control Rod movement Control Rod 18-51 withdrawn to position 48 PasslFail Note: The uncoupled control rod will become apparent when the rod travels beyond position 48 during the coupling check.

This cues the candidate to the alternate path.

9. IF the target position is 48, WHEN the control rod reaches 48, perform the following:
a. CRD coupling check as follows:
  • Position 48 illuminates with red backlighting AND remains Observes Rod Position Indication for Control SatlUnsat illuminated for selected rod at F Rod 18-51 illuminate 48 and then go blank Panel
  • Computer Point BO 12, CRD Observes Computer Point B012 in alarm SatlUnsat OVERTRAVEL does NOT alarm
b. Release 4S1, Control Rod Movement Switch AND 4S3, Control Rod N Releases 4S1, Control Rod Movement Switch SatlUnsat Override Switch. AND 4S3, Control Rod N Override Switch
10. Goes to OP-5 Sect. H.l8. Obtains OP-5 and goes to section H.l8 SatlUnsat NRC 2010 JPM S-7 November 2010

Performance Steps Standard Grade

11. Insert Control Rod 18-51 to position 44 Rotates Control Rod Movement Switch CCW PasslFail to move Control Rod 18-51 to position 44 Note: When Control Rod 18-51 is inserted to position 44, verifY Trigger 1 activates and deletes the rod uncoupling malfunction.
12. ConfIrm Annunciator F3-1-6 CONTROL Observes Annunciator F3-1-6 clear SatiUnsat ROD OVERTRAVEL, clear
13. Withdraw control rod 18-51 to position 48 Rotates Control Rod Movement Switch CW SatiUnsat to move Control Rod 18-51 to position 48 (may also rotate Control Rod N Override Switch CW to achieve continuous rod motion)
14. Perform rod over-travel check in Rotates Control Rod N Override Switch CW SatiUnsat accordance with NI-0P-5 and holds during coupling check Rotates Control Rod Movement Switch CW SatiUnsat and hold during coupling check Observes Rod Position Indication for Control SatiUnsat Rod 18-51 illuminate and remain at 48 Observes F3-1-6 does NOT alarm SatiUnsat Observes Computer Point B012 does NOT SatlUnsat alarm Releases 4S1, Control Rod Movement Switch SatiUnsat AND 4S3, Control Rod N Override Switch
15. Confrrm the following: Proper communications used (GAP-OPS-Ol) SatlUnsat
  • ALL RODS IN light off at RSP 11
  • ALL RODS IN light off at RSP 12 Cue: The ALL RODS IN lights are off at the RSPs.

NRC 2010 JPM 8-7 November 2010

Performance Steps Standard Grade

16. Attempt withdrawal of a second rod as follows:
a. Select AND record rod ID Observes Control Rod 34-03 has been pre SatJUnsat recorded Note: Control Rod 34-03 should be selected per the initial conditions, but any Control Rod other Depresses a Control Rod select button other PasslFail than 18-51 will allow for successful surveillance than 18-51 completion.
b. Attempt to withdraw rod Rotates Control Rod Movement Switch CW PasslFaii
c. ConfIrm the following:
  • Selected rod did NOT move Observes selected Control Rod does not move SatJUnsat
  • Rod Block Monitor REFUEL Observes Rod Block Monitor REFUEL ONE SatJUnsat ONE ROD PERMIT light -lit ROD PERMIT light -lit
17. Select control rod 18-51 AND insert fully Depresses Control Rod 18-51 select button PasslFaii Rotates Control Rod Movement Switch CCW PasslFaii and holds until Control Rod 18-51 is fully inserted
18. VerifY rod at position 00 Observes Control Rod 18-51 indicates 00 SatJUnsat
19. ConfIrm the following:
  • Rod Block Monitor REFUEL ONE Observes Rod Block Monitor REFUEL ONE SatJUnsat ROD PERMIT light off ROD PERMIT light OFF
  • ALL RODS IN light lit on RSP 11 Proper communications used (GAP-OPS-Ol) SatJUnsat
  • ALL RODS IN light lit on RSP 12 Cue: The ALL RODS IN lights are lit at the RSPs.

Terminating Cue: Control Rod 18-51 re-coupled and Nl-ST-R4 section 8.1 successfully performed.

RECORD STOP TIME _ _ __

NRC 2010 JPM 8-7 November 2010

Initial Conditions:

1. The plant is shut down.
2. NI-ST-R4 is complete up to step 8.1.6 for the Rod Blocks Withdrawal Test.
3. Reactor Engineering has directed using control rod 18-51 for the first rod withdrawal, and control rod 34-03 for the second attempted rod withdrawal.
4. Reactor Engineering has directed continuous rod withdrawal for control rod 18-51 and single notch withdrawal for control rod 34-03.

Initiating Cue:

"(Operator's name), perform NI-ST-R4 Section 8.1, Rod Blocks Withdrawal Test, withdrawing control rod 18-51."

NRC 2010 JPM S-7 November 2010

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

Title:

Vent the DryweU Prior to Personnel Entry Per NI-OP-9 Revision: NRC 2010 Task Number: NIA Approvals:

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

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

TrainerlEvaluator:_ _ _ _ _ __

Evaluation Method: X Perform _ _ _ Simulate Evaluation Location: ___ Plant X Simulator Expected Completion Time: 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's Signature:_ _ _ _ _ _ _ __ Date:_ _ _ __

NRC 2010 JPM 8-8 November 2010

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

Simulator Simulator Set-up (if required):

1. Initialize Simulator to IC-162 (shared with JPM S-2).
2. Verify Torus pressure is 0 psig.

Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified in grading area as PasslFail.
2. During Evaluated JPM:
  • Self verification shall be demonstrated.
3. During Training JPM:
  • Self verification shall be demonstrated.
  • No other verification shall be demonstrated.

NRC 20 I0 JPM 8-8 November 2010

References:

1. NUREG 1123,223001, A4.03, RO 3.4, SRO 3.4
2. NI-OP-9 Tools and Equipment:

None Task Standard: Drywell vented to atmospheric pressure in accordance with N1-0P-9.

Initial Conditions:

1. The plant is operating at 100% power.
2. Preparations are underway for a plant shutdown.
3. The Torus has already been vented.
4. NI-OP-9 is completed through Step G.1.11.3.
5. Instructor to ask operator for any questions.

Initiating Cue:

"(Operator's name), vent the Drywell and secure the lineup when Drywell pressure is below 0 psig in accordance with N 1-0P-9, starting at step G .1.12."

Performance Steps Standard Grade

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

Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME

2. Obtain a copy of the reference procedure and NI-0P-9 obtained, precautions and limitation SatlUnsat review/utilize the correct section ofthe reviewed, section G.1.0 referenced procedure
3. Open 201-32, DW N2 VENT & PURGE Rotates 201-32 control switch CW PasslFail ISOLAnON VALVE 11
4. Start 201-35, DRYWELL & TORUS VENT Rotates 201-35 control switch CW PassIFail

& PURGE

5. Verify open the following valves:
  • 201-21, DRYWELL & TOR VENT & Observes 201-21 red light on, green light off SatlUnsat PURGE FAN INLET BV
  • 201-22, DRYWELL & TOR VENT & Observes 201-22 red light on, green light off SatlUnsat PURGE FAN OUTLET BV NRC 2010 JPM 8-8 November 2010

Performance Steps Standard Grade

6. Throttle open 201-31, DWN2 VENT & Rotates 201-31 control switch CW PasslFail PURGE ISOLATION VALVE 12 Throttles 201-31 by using pull-to-stop feature SatJUnsat Cue: After the low drywell pressure alann clears of control switch (K2-4-3), report drywell pressure is below opsig for purposes of this JPM (time compression used).
7. When drywell pressures drops BELOW 0 Observes Drywell pressure and when pressure SatJUnsat psig, perfonn the following steps: lowers below 0 psig continues the JPM
8. Stop 201-35 DRY WELL & TORUS VENT Rotates 201-35 control switch CCW PasslFail

& PURGE FAN

9. Verify closed the following valves:
  • 201-21, DRYWELL & TOR VENT & Observes 201-21 green light on, red light off SatJUnsat PURGE FAN INLET BV
  • 201-22, DRYWELL & TOR VENT & Observes 201-22 green light on, red light off SatJUnsat PURGE FAN OUTLET BV
10. Verify closed the following valves:
  • 201-32, DWN2 VENT & PURGE Rotates 201-32 control switch CCW PasslFaii ISOLATION VALVE 11
  • 201-31, DWN2 VENT & PURGE Rotates 201-31 control switch CCW PasslFail ISOLATION VALVE 12 Cue: Another operator will complete this procedure.

Terminating Cue: Drywell vented to atmospheric pressure in accordance with NI-0P-9 and lineup returned to nonna!.

RECORD STOP TIME _ _

NRC 2010 JPM 5-8 November 2010

Initial Conditions:

1. The plant is operating at 100% power.
2. Preparations are underway for a plant shutdown.
3. The Torus has already been vented.
4. NI-OP-9 is completed through Step G.I.II.3.

Initiating Cue:

"(Operator's name), vent the Drywell and secure the lineup when Drywell pressure is below 0 psig in accordance with NI-OP-9, starting at step G.1.12."

NRC 2010 JPM S-8 November 2010

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

Title:

Lineup Lake Water to Supply the EC Makeup Tanks Revision: NRC 2010 Using the Electric Fire Pump Task Number: NIA Approvals:

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

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

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

Evaluation Method: _ _ _ _ Perform __-----'x'-"--__ Simulate Evaluation Location: ~~__ Plant _ _ _ _ _ _ Simulator Expected Completion Time: 25 minutes Time Critical Task: No Alternate Path Task: Yes Start Time: _ _ __ Stop Time: _ _ _ __ Completion Time: _ _ _ __

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

Comments:

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

NRC 2010 JPM P-l November 2010

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

Screenhouse Simulator Set-up (if required):

None Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

I. Critical steps are identified in grading areas PasslFaiL

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

References:

1. NUREG 1123, 207000, A2.0S, RO 4.0, SRO 4.0
2. NI-SOP-21.2, Attachment 5
3. NI-0P-21A Tools and Equipment:

None NRC 2010 JPM P-1 November 2010

Task Standard: Emergency Condenser Makeup Tanks filled to 10 feet using the Electric Fire Pump.

Initial Conditions:

1. The plant was operating at 100% power.
2. A control room evacuation has occurred.
3. Emergency Condenser Makeup Tank levels are low at 6 feet.
4. Emergency Condenser Makeup cross-connect valve, 60-13, has failed closed.
5. Instructor to ask operator for any questions.

Initiating cue:

"(Operator's name), raise Emergency Condenser Makeup Tank levels to 10 feet using the Diesel Fire Pump, in accordance with NI-SOP-21.2, Attachment 5."

Performance Steps Standard Grade

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

Evaluator Acknowledge repeat back providing correction if necessary RECORDSTARTTlldE _______

2. Obtain a copy of the reference procedure N I-S0P-21.2, Attachment 5 obtained SatlUnsat and review/utilize the correct section ofthe procedure
3. Start at least one ofthe following Fire Attempts to starts the Diesel Fire Pump by one SatlUnsat Pumps (Screenhouse): of the following means:
  • Diesel Fire Pump (Preferred)
  • Rotates control switch counterclockwise to TEST position
  • Electric Fire Pump
  • Rotates control switch clockwise to the Note: If the candidate requests an additional MAN 1 position and depresses the start procedure to perform the Diesel Fire Pump start, pushbutton give them NI-OP-21A sections H.l.0 and H.2.0.

The candidate will then perform additional pre

  • Rotates control switch clockwise to the and post-start actions beyond those listed in the MAN 2 position and depresses the start standard, but listed below: pushbutton
  • Verify Diesel Fire Pump lubricant level is at Full mark.
  • Verify Diesel Fire Pump gearcase lubricant level full.
  • Verify the following:
  • Engine coolant full
  • Day tank level 150 gallons or greater
  • Air tank pressures 11 and 12 > 80 psig
  • Engine water temperature> 100°F NRC 2010 JPM P-I November 2010

Performance Steps Standard Grade Cue: Report that the Diesel Fire Pump failed to start and is now damaged.

Starts the Electric Fire Pump by rotating PasslFaii Role Play: If candidate asks for direction how control switch clockwise to START to proceed, direct them to take appropriate action to raise Emergency Condenser Makeup Tank levels to 10 feet.

Note: If the candidate requests an additional procedure to perform the Electric Fire Pump start, give them NI-OP-21A sections H.l.O and H.2.0. The candidate will then perform additional pre- and post-start actions beyond those listed in the standard, but listed below:

  • Verify lubricant levels of Electric Fire Pump is at STANDSTILL LEVEL in top and bottom Bull's Eyes
  • Verify Electric Fire Pump oil reservoir full Cue: When Electric Fire Pump control switch is taken to START, inform the candidate that the Electric Fire Pump started.

Cue: If requested, Electric Fire Pump indications are:

  • Motor current 40 amps
  • Discharge pressure 140 psig
  • Strainer DIP = 1.5 psid
  • Annunciator 2 2-2 Electric Fire Pump # 1 started is alarming on Main Fire Panel 2 Note: The candidate will proceed to TB 369' for the remaining steps.

NRC 2010 JPM P-l November 2010

Performance Steps Standard Grade

4. Unlock and throttle open the following valves to maintain level in Emergency Condenser Makeup Tanks:
  • 100-68, BV - FIRE WATER TO Unlocks 100-68 and removes chain from PasslFail EMERG COND MIU TANK 12 valve handwheel Rotates 100-68 handwheel CCW to open PasslFail valve Cue: Once candidate has opened 100-68, report Observes Makeup tank level SatlUnsat that EC MIU Tank 12 level is 10 feet Proper communications used for repeat back SatlUnsat (GAP-OPS-Ol)

Rotates 100-68 handwheel CW to close the SatiUnsat valve

  • 100-69, BV -FIRE WATER TO Unlocks 100-69 and removes chain from PasslFail EMERG COND MIU TANK 11 valve handwheel Rotates 100-69 handwheel CCW to open PasslFaii valve Cue: Once candidate has opened 100-69, report Observes Makeup tank level SatlUnsat that EC MIU Tank 11 level is 10 feet Proper communications used for repeat back SatlUnsat (GAP-OPS-O 1)

Rotates 100-69 handwheel CW to close the SatlUnsat valve Terminating Cue: Emergency Condenser Makeup Tanks filled to 10 feet using the Electric Fire Pump.

RECORD STOP TIME _ _ __

NRC 2010 JPM P-I November 2010

Initial Conditions:

1. The plant was operating at 100% power.
2. A control room evacuation has occurred.
3. Emergency Condenser Makeup Tank levels are low at 6 feet.
4. Emergency Condenser Makeup cross-connect valve, 60-13, has failed closed.

Initiating Cue:

"(Operator's name), raise Emergency Condenser Makeup Tank levels to 10 feet using the Diesel Fire Pump, in accordance with N1-S0P-21.2, Attachment 5."

NRC 2010 JPM P-I November 2010

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

Title:

Transfer UPS Loads from UPS 162A to 162B Revision: NRC 2010 Task Number: N/A Approvals:

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

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

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

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

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

Comments:

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

NRC 2010 JPM P-2 November 2010

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

TB 261' between EDG Room and Aux Control Room Simulator Set-up (if required):

None Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each ~!!.!:.!:!~~ JPM Performance:

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

Read Before Each Training JPM Performance:

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

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

Notes to Instructor / Evaluator:

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

References:

1. NUREG 1123,212000, AZ.02, RO 3.7, SRO 3.9
2. NI-OP-40 Tools and Equipment:

None NRC 2010 JPM P-2 November 20 I 0

Task Standard: RPS Bus 11 transferred from UPS 162A to UPS 162B, and then to I&C Bus 130A.

Initial Conditions:

1. The plant is operating at 100% power.
2. UPS 162A is in service supplying RPS Bus 11.
3. UPS 162B is in standby.
4. The Electrical Safety requirements for the upcoming job have been determined to be as follows:
  • Leather gloves
  • Safety glasses or goggles
  • 100% cotton long sleeve shirt and pants, OR 100% cotton short sleeve shirt and pants under flame resistant lab coat
5. Instructor to ask operator for any questions.

Initiating Cues:

"(Operator's name), transfer RPS Bus 11 from UPS 162A to UPS 162B per NI-0P-40 section F.l.O."

Performance Steps Standard Grade

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

Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME

2. Obtain a copy of the reference procedure NI-OP-40 obtained, precautions & limitations SatfUnsat and review/utilize the correct section ofthe reviewed & section F.1.0 referenced procedure
3. Notify Control Room that RPS Bus 11 Proper communications used for repeat back SatfUnsat will be transferred from UPS 162A to (GAP-OPS-Ol)

UPS 162B

4. At UPS 162B, verify UPS 162B in At UPS 162B, verify UPS 162B in standby by standby by observing the following: observing the following:
  • Battery DC Input (AI) 0 amps
  • Battery DC input on Inverter Bay 2 SatfUnsat reading 0 amp
  • Inverter Voltage (V2) ~ 120 VAC
  • Inverter output on Inverter Bay 3 SatfUnsat reads 120 VAC
  • Static Switch Output (V202) ~ 120
  • Static Switch Output on Static Bay 4 SatfUnsat VAC reads 120 VAC NRC 2010 lPM P-2 November 2010

Performance Steps Standard Grade Cue: Provide the following parameter values to the candidate:

  • A404 = 40 amps
  • Al = 0 amps
  • V2 = I20VAC
  • V202 = 120 VAC
5. Place Synchroscope Control (S701) in ON On Manual Transfer Cabinet, places PasslFail position and confirm the following: Synchroscope Control toggle switch in ON Cue: S701 is not on the switch labeL When the candidate locates the switch, if there is any confusion, state that this is the S701 switch.
  • UPS A Volts To Synchroscope Observes UPS A Volts to left of sync switch SatlUnsat V701 approximately 120 VAC
  • UPS B Volts To Synchroscope Observes UPS B Volts to right of sync switch SatlUnsat V702 approximately 120 VAC Cue: UPS A Volts = l20VAC UPS B Volts = 120 VAC Note: There is not expected to be a frequency or phase difference between UPS A and UPS B. Therefore, the operator should expect the synchroscope to be at the 12 o'clock position.

Cue: Synchroscope is at the 12 o'clock position

6. If synchroscope is NOT within 10 degrees Observes synchroscope on Manual Transfer SatlUnsat ofthe 12 o'clock position, then contact Cabinet Electrical Maintenance to perform adjustment. Marks step NIA SatlUnsat
7. When needle of synchroscope is within 10 Observes synchroscope SatlUnsat degrees of 12 o'clock position, then place Manual Transfer Switch (S702) to the Firmly rotates switch counterclockwise to the PasslFail UPS B Supplying Load position. UPS B Supplying Load protection Cue: S702 is not on the switch labeL When the candidate locates the switch, if there is any confusion, state that this is the S702 switch.

Note: Operation of the manual transfer switch is a two handed operation NRC 2010 JPM P-2 -4 November 2010

Performance Steps Standard Grade

8. Confirm load transfer by observing the At the Manual Transfer Cabinet, observes the following: following:
  • UPS A Supplying Load Light OFF
  • UPS A Supply Load Light extinguished SatlUnsati NA AND/OR
  • On Static Switch Bay 4 for UPS, Static SatlUnsati
  • UPS 162A Static Switch Output (A202) oamps Switch Output ammeter for UPS 162A at 0 NA amps Cue: UPS A Supply Light is extinguished, A202 on UPS 162A = 0 amps
  • UPS B Supplying Load Light ON
  • Observe UPS B Supply Load Light SatlUnsati extinguished NA AND/OR
  • Observe Static Switch Output ammeter SatlUnsati
  • UPS 162B Static Switch Output (A202) NA approximately 80-90 amps for UPS 162B at 0 amps Cue: UPS B Supplying Load Light is extinguished, A202 on UPS 162B = 0 amps. The control room has reported a loss of RPS Bus 11. The control room has directed you to re-energized RPS Bus 11 from I&C Bus 130A in accordance with NI-0P-40 section H.1.0.

Note: The Examiner is to provide the candidate with a copy ofNI-0P-40 section H.1.0 at this point.

9. Verify I&C Bus 130A is available to carry Proper communications used (GAP-OPS-Ol) SatlUnsat RPS loads.

Cue: I&C Bus 130A is available to carry RPS loads.

10. Notify CRO that dead bus transfer is to be Proper communications used (GAP-OPS-Ol) SatlUnsat performed.

Role Play: Acknowledge communication.

11. Review list of affected systems in N 1 Proper communications used (GAP-OPS-OI) SatlUnsat SOP-40.1, Loss ofRPS Bus, for the RPS channel to be de-energized.

Cue: The control room has reviewed affected systems and directs you to continue.

NRC 2010 JPM P-2 -5 November 2010

Performance Steps Standard Grade

12. Review Attachment 6 AND current plant Proper communication used (GAP-OPS-Ol) SatlUnsat conditions for possible Technical Specification impact.

Cue: The control room has reviewed Attachment 6 and directs you to continue.

13. Confirm NO 112 scram signals are present Proper communication used (GAP-OPS-O!) SatlUnsat OR anticipated due to testing on the opposite RPS Bus AND notify CRO that performance of the following step will initiate a 112 scram.

Role Play: Acknowledge and report that no Y2 scram signals are present on RPS Bus 12.

14. IF RPS BUS #12 to be de-energize AND Marks step as NIA SatlUnsat SDC isolation is NOT desired, THEN perform section H.6.0.

Note: The following breakers are at the Protective Relaying Cabinet near the UPS.

15. Open RPS BUS #11 (12) NORMAL Pushes RPS BUS # 11 NORMAL SUPPLY PasslFaii SUPPLY FROM UPS 162 (172). FROM UPS 162 breaker handle up.
16. Close RPS BUS #11 (12) Pushes RPS BUS # 11 MAINTENANCE Pass/Fail MAINTENANCE SUPPLY FROM I&C SUPPL Y FROM I&C BUS # BOA breaker BUS # BOA. handle down.

Cue: All remaining actions will be completed by other operators.

Terminating Cue: Transfer ofRPS Bus 11 from UPS 162A to UPS 162B, and then to I&C Bus BOA, is complete.

RECORD STOP TIME _ _ __

NRC 2010 JPM P-2 November 2010

Initial Conditions:

1. The plant is operating at 100% power.
2. UPS 162A is in service supplying RPS Bus 11.
3. UPS 162B is in standby.
4. The Electrical Safety requirements for the upcoming job have been determined to be as follows:
  • Leather gloves
  • Safety glasses or goggles
  • 100% cotton long sleeve shirt and pants, OR 1000/0 cotton short sleeve shirt and pants under flame-resistant lab coat Initiating Cues:

"(Operator's name), transfer RPS Bus 11 from UPS 162A to UPS 162B per NI-0P-40 section F.l.O."

NRC 2010 JPM P-2 November 2010

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

Title:

Inject Boron Into the Reactor Using the Hydro Pump Revision: NRC 2010 Task Number: N/A Approvals:

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

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

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

Evaluation Method: Simulate Evaluation Location: Plant 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:

Evaluators Signature:_________________________ Date:__________

NRC 2010 JPM P-3 November 2010

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

Reactor Building Elev. 281 Simulator Set-up (if required):

None Directions to the InstructorlEvaluator:

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

Directions to Operators:

Read Before Every JPM Performance:

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

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

Read Before Each Evaluated JPM Performance:

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

Read Before Each Training JPM Performance:

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

Notes to Instructor / Evaluator:

1. Critical steps are identified as PasslFaii. 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.
  • (IndependentlPeerlNo other) verification shall be demonstrated.

References:

1. NUREG 1123,295037, EA1.10, RO 3.7, SRO 3.9
2. NI-EOP-3
3. NI-EOP-3.2, Attachment 1 Tools and Equipment:

None Task Standard: Boron is being pumped into the Reactor vessel using the Hydro pump.

NRC 2010 JPM P-3 November 2010

Initial Conditions:

I. N l-EOP-3 has been entered due to a failure to scram.

2. An RO has tried to initiate Liquid Poison from the Control Room but the pumps will not start.
3. RWCU has isolated.
4. Radiation Protection is providing continuous monitoring of your activities.
5. Instructor to ask operator for any questions.

Initiating Cues:

"(Operator's name), lineup and inject boron using the Hydro Pump per NI-EOP-3.2, Alternate Boron Injection, Attachment 1."

Performance Steps Standard Grade

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

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

2. Obtain a copy of the reference procedure NI-EOP-3.2 obtained, Attachment 1 SatlUnsat and review/utilize the correct section of the referenced procedure
3. Verify RWCU system is isolated Determines RWCU system is isolated per SatlUnsat initial conditions
4. Notify Rad Protection to provide continuous Determines Rad Protection is providing SatlUnsat monitoring continuous monitoring per initial conditions Cue: Once EOP Box 2 is located, prompt candidate to simulate opening the box and describe the equipment to be used.
5. Connect air supply hose from 95-157, BV Indicates location of 95-157 PasslFail HSA to Alternate Boron Injection System (in overhead above Hydro Pump area), to Attaches one end of air supply hose to Hydro PasslFail the Hydro pump pump air inlet line Note: 95-157 is in the overhead above a small platform. It is not desired for the candidate to access the valve, since this would require RP coverage for work above 6 feet. Successful completion of this JPM step will be for the candidate to indicate the general location of the valve.

Cue: Once candidate indicates location of 95-157, report that the air supply hose is connected to 95-157 NRC 2010 JPM P-3 -3 November 2010

Perfonnance Steps Standard Grade

6. Connect high-pressure hose to discharge of Connects one end of hose to discharge of Pass/Fail Hydro pump Hydro pump
7. Connect 2" hose from hose connection Connects one end of hose to hose connection Pass/Fail downstream of 89-20, Drain - Liquid downstream of 89-20 Poison Tank, to suction of Hydro pump Connects other end of hose to suction of Pass/Fail Hydro pump
8. Unlock and verifY closed 89-21, Drain - LP 89-21 is unlocked Pass/Fail Tank to 55 Gal Drum 89-21 is closed by rotating handwheel fully Pass/Fail clockwise
9. Unlock and close 42-13, BV-LP Squibb Vlv 42-13 (LP-Il) is closed by unlocking and Sat/Unsat 11 Outlet turning handwheel fully clockwise (RB Elev.

298')

10. Unlock and close 42-14, BV-LP Squibb Vlv 42-14 (LP-IO) is closed by unlocking and Sat/Unsat 12 Outlet turning handwheel fully clockwise (RB Elev.

298')

11. Unlock and open 41-04, Drain Liquid 41-04 (LP-701) is opened by unlocking and Pass/Fail Poison Tank turning handwheel fully counter-clockwise
12. Unlock and open 89-20, Drain - Liquid 89-20 is opened by unlocking and turning Pass/Fail Poison Tank handwheel fully counter-clockwise
13. VerifY Hydro Pump Air inlet Valve closed Hydro pump air inlet valve is closed by Sat/Unsat verifYing handwheel is rotated fully clockwise (at Hydro pump)
14. Adjust regulator fully clockwise Rotates regulator fully clockwise Pass/Fail
15. Depress outer collar of adjusting knob Depresses outer collar of adjusting knob Sat/Unsat downward to lock pressure setting downward
16. Connect high pressure hose (from Hydro Connects other end of hose previously Pass/Fail pump discharge) to hose connection attached to Hydro pump discharge to hose upstream of 42-1 0, Drain - LP Sys Hdr connection upstream of 42-1 0 Before Ck Vlvs - 2nd
17. Unlock and open valve 42-10, Drain LP 42-10 (LP-708) is opened by unlocking and Pass/Fail SYS HDR BEFORE CK VLVS - 2ND. turning handwheel fully counter-clockwise (RB Elev. 281)
18. Unlock and open valve 42-09, Drain - LP 42-09 (LP-707) is opened by unlocking and PasslFail SYS HDR BEFORE CK VLVS - 1ST. turning handwheel fully counter-clockwise (RB Elev. 281)

NRC 2010 JPM P-3 November 2010

Perfonnance Steps Standard Grade

19. Open 95-157, BV-HSA to Alt Boron Proper communications used (GAP-OPS-Ol) PasslFail Injection System Note: 95-157 is in the overhead above a small platfonn. It is not desired for the candidate to access the valve, since this would require RP coverage for work above 6 feet.

Cue: Report that 95-157 has been opened by another operator

20. Open hydro pump Air Inlet BV Air inlet valve is opened by turning PasslFail handwheel counter-clockwise Cue: Hydro pump is running and indicating proper discharge pressure
21. Notifies Control Room liquid poison being Proper communications used (GAP-OPS-Ol) SatJUnsat injected with the Hydro Pump.

RECORD STOP TIME _ _ __

NRC 2010 JPM P-3 November 2010

Initial Conditions:

I. NI-EOP-3 has been entered due to a failure to scram.

2. An RO has tried to initiate Liquid Poison from the Control Room but the pumps will not start.
3. RWCU has isolated.
4. Radiation Protection is providing continuous monitoring of your activities.

Initiating Cues:

"(Operator's name), lineup and inject boron using the Hydro Pump per NI-EOP-3.2, Alternate Boron Injection, Attachment I."

NRC 2010 JPM P-3 November 2010

NMP SIMULATOR SCENARIO NRC Scenario 1 REV. 0 No. of Pages: 24 EPR Oscillation, Loss of P8 102, 168 and 16A, Seismic Event with Steam Leak and Torus Leak PREPARER DATE /0;'1)/10

~~;:Z4tg VALIDATED DATE 7/20/10 GEN SUPERVISOR OPS TRAINING DATE 1t)/~k/~

OPERATIONS MANAGER N/A - Exam Security DATE CONFIGURATION CONTROL N/A - Exam Security DATE SCENARIO

SUMMARY

Length: 90 minutes Initial Power Level: Approximately 85%

The scenario begins at 85% power following a rod pattern adjustment. APRM 14 is bypassed for a gain adjustment. The crew is to place APRM 14 back in service per N1-0P-38C. The crew will then raise power using recirculation flow in accordance with a Reactivity Maneuver Instruction.

Then, the EPR will begin to slowly oscillate, requiring the crew to enter N1-S0P-31.2 and place the MPR in service. The CRS will address the thermal limit implications of loss of the backup pressure regulator. Next, Powerboard 102 will develop a fault. The crew will take actions to investigate the loss of the powerboard and to reenergize Powerboard 168 from Powerboard 16A and restore loads. When Powerboard 16A is reenergized, a fault will develop on the powerboard. This will result in a loss of three Drywell cooling fans. The crew will start an additional Drywell cooling fan to address rising Containment temperatures. The CRS must assess the impact of the equipment that is lost and enter Technical Specifications.

Next, the seismic event annunciator alarms. The crew responds using the alarm response procedure and N1-S0P-28. Simultaneously with the seismic monitor alarm, a line break will occur in the Drywell causing slowly rising Drywell pressure, temperature and humidity.

Deteriorating Drywell conditions will require a manual scram. The crew will enter N1-EOP-2, RPV Control, and N1-EOP-4, Primary Containment Control. The crew will initiate Containment Spray when Torus pressure exceeds 13 psig (Critical Task).

NRC Scenario 1 1 November 2010

Once Containment Spray is initiated, an aftershock will cause a break in the Torus. The crew must diagnose that Torus water level is lowering. The crew may attempt to add water to the Torus. Makeup to the Torus will be unavailable due to plant conditions. If Containment Spray Raw Water pump 121 is lined up for Torus makeup, it will trip after a time delay. As Torus level lowers, the crew must enter N1-EOP-8, RPV Blowdown, and RPV pressure must be lowered using ERVs or alternate Blowdown systems (Critical Task).

Major Procedures: N1-S0P-31.2, N1-S0P-1.1, N1-S0P-1, N1-EOP-1, N1-EOP-2, N1-EOP-4, and N1-EOP-8 Dynamic Mitigation Strategy Code: PC2, RPV Blowdown due to Low Torus Water Level EAL Classification: Alert EAL 3.1.1 - High Drywell Pressure Alert EAL 8,4,4 - Earthquake> 0.075g (If given report from Unit 2 seismic instrumentation. )

(Based on Emergency Director judgement, Site Area Emergency EAL 9.1.6

- Loss of Primary Containment Integrity with Loss of Rx Coolant Pressure Boundary if possible)

Termination Criteria: RPV water level controlled in assigned band, RPV Blowdown in progress, Primary Containment pressure maintained per EOP-4 NRC Scenario 1 2 November 2010

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

1. Malfunctions:
a. R035A, CRO Hydraulic Pump 11 Trip PRESET
b. TC06, Electrical Pres. Regulator Fails - Oscillates TRG 1
c. E007, PB 102 Electrical Fault TRG2
d. E012A, PB 16A Electrical Fault, OT=30 TRG3
e. PC05, Seismic Event Triggered TRG4
f. EC01, Steam Supply Line Break in PC, OT=3:00, FV=12 TRG4
g. PC04, Torus Water Leak, OT=10, FV=25 TRG5
h. CT02C, CT Raw Water Pump 121 Trip, OT=45 TRG23
i. A007A, ERV 111 Fails Closed PRESET
2. Remotes:
a. None
3. Overrides:
a. None
4. Annunciators:
a. None
5. Triggers:
a. TRG 3 -Inserts fault on PB 16A when R1042 is taken to close position
i. Event Action: zded602c==1 ii. Command: None
b. TRG 5 - Inserts second seismic event and Torus leak when Containment Spray flow is initiated
i. Event Action: ctfdw>300 ii. Command: None
c. TRG 20 - Raises severity level of steam leak after the mode switch is taken to shutdown
i. Event Action: zdrpstdn==1 it Command: imf ec01 (0 0) 30 4:00 12
d. TRG 21 - Runs batch file to setup second seismic event when Orywell pressure exceeds 12.5 psig
i. Event Action: dwpgas>27.2 NRC Scenario 1 3 November 2010

ii. Command: bat n10scen1trg21.bat

e. TRG 22 -Adjusts Torus leak rate once Torus water level lowers below 10.4 feet
i. Event Action: trlevel<10.4 ii. Command: imf pc04 (0 0) 10
f. TRG 23 - Trips Containment Spray Raw Water pump 121 4S seconds after it is started iii. Event Action: hzlctpmp(14)==1 iv. Command: None C. Equipment Out of Service
1. CRD pump 11 in PTL with yellow tag
2. APRM 14 bypassed with no tag D. Support Documentation
1. RMI for power ascension with recirculation flow E. Miscellaneous
1. Ensure Drywell cooling fan 11 is secured with control switch in neutral
2. Ensure batch file "n1 Oscen1trg21.bat" is in the root batch file directory with the following commands:
a. dmf pcOS
b. irf pc16 (0 0) reset
c. imf pcOS (S 10) true
3. Protect the following equipment: CRD pump 12 control switch, R-10S3, R-10S2
4. Update Divisional Status Board NRC Scenario 1 4 November 2010

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

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

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

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

  • Reactor Power is approximately 85%
  • CRD pump 11 is out of service for repairs (Day 1 of planned 2 day window; 7 day LCO per TS 3.1.6.b)
  • APRM 14 is bypassed, gain adjustments have just been completed PART III: Remarks/Planned Evolutions:

1 Return APRM 14 to service using N1-0P-38C, Sect. H.2.0.

2. Increase Reactor power with recirculation flow per RMI.

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

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

TITLE NAME TITLE NAME SRO ATCRO BOPRO NRC Scenario 1 5 November 2010

ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver: Power Ascension to Rated Step: 1 I INITIAL CONDITIONS/STEP DESCRIPTION I

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

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

Initial conditions to be verified prior to initiation of step:

I~ter Expected Range Actual Parameter Expected Range Actual CTP 1550 - 1590 MWth Description of Step:

1. Raise reactor power to 98% CTP with recirculation flow (1800 - 1813 MWth) over 30 minutes.
2. Raise reactor power to rated (98% to 100%) over one hour.

Critical parameters to be monitored DURING Step:

Critical parameters not used must be deleted OR marked N/A Critical Parameter Limit Owner Frequency Contingency CTP 1850 MWth RO Continuous Lower recirculation flow II RMI evaluated against approved power profile:. N/A O.

I Other Comments:

I Step Prepared by: ~~ I~ Step Reviewed fjr:Ick 0<fJer:m -~

RE/STA Date RElSTAISRO Date Approval to perform Step c.;;!bhn .&.artJn I ~ Step Completed Shift Manager Date SRO Date NRC Scenario 1 6 November 2010

Critical Tasks:

CT-1.0 Given a LOCA in the Drywell, the crew will initiate Containment Sprays prior to exceeding the Pressure Suppression Pressure limit, in accordance with N 1-EOP-4.

CT-2.0 Given a lowering Torus water level, the crew will execute N1-EOP-8, RPV Blowdown, when it is determined Torus water level cannot be maintained above eight (8) feet, in accordance with N1-EOP-4.

NRC Scenario 1 7 November 2010

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

  • Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Place APRM 14 in Service SRO
  • Directs restoration of APRM 14 per OP-38C, Sect H.2.0
  • Provides oversight for evolution RO
  • Verifies no trip signals present
  • Places APRM BYPASS switch in neutral position
  • Confirms APRM BYPASS light is OFF on Panel E
  • Confirms computer printout "APRM_ _BYPASS NO"
  • Confirms APRM BYPASS light is OFF on the LPRM-APRM drawer BOP
  • Monitors plant parameters NRC Scenario 1 8 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 2 - Raise Power with Recirculation Flow SRO

  • Directs power ascension with recirculation flow in accordance with OP-438 and the Reactivity Maneuver Instruction (RMI)
  • Provides oversight of reactivity maneuver Note: In order for event 3 to result in a thermal RO limit penalty, the EPR oscillation must be inserted
  • Acknowledges direction from SRO below 90% power.
  • Raises recirculation flow with master recirculation flow controller
  • Monitors recirculation flow
  • Monitors individual RRPs for response
  • Individual MIA-Speed Control stations trending uniformly
  • Individual RRP indications trending normally for speed increase
  • Monitors Feedwater controls for proper response
  • RPV water level remains within program band (65" - 83")

NRC Scenario 1 9 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 - EPR Oscillations When directed by lead examiner, insert CREW malfunction:

  • Acknowledges I reports annunciator TC06, Electrical Pres. Regulator Fails A2-4-4 Oscillates
  • Observes Reactor power and TRG 1 pressure oscillations EPR servo stroke oscillates
  • Diagnoses EPR oscillations Reactor power and pressure oscillate Expected Annunciator:

A2-4-4, Turbine Mechanical Press. Reg. In Control SRO

  • Acknowledges report from crew
  • Directs execution of SOP-31.2, Pressure Regulator Malfunctions
  • References COLR restrictions for operation without a backup pressure regulator Role Play:
  • Determines thermal limit penalty must If contacted as Reactor Engineering, acknowledge be applied to MCPR and LHGR limits request to analyze thermal limits for operation with power between 45% and 90%

without a backup pressure regulator.

  • Announce or brief crew on the change to MCPR and LHGR limits.

RO

  • Executes SOP-31.2, Pressure Regulator Malfunctions
  • Determines EPR was originally in control
  • Determines pressure is oscillating
  • May lower MPR set point until MPR is in control NRC Scenario 1 10 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued RO continued

  • Raises the EPR setpoint to 1010 psig
  • Works with BOP to return Reactor pressure to pre-transient value by adjusting MPR setpoint, as time permits BOP
  • Monitors plant parameters
  • Works with RO to return Reactor pressure to pre-transient value, as time permits NRC Scenario 1 11 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 4 - Power Board 102 Electrical Fault When directed by lead examiner, insert CREW malfunction:

  • Diagnose/report loss of PB 102 and ED07, PB 102 Electrical Fault 16B TRG2 Powerboard 102 and 16B voltage lower to zero EDG 102 starts but does not close on bus Major expected annunciators:

A4-1-6, PB 102 Bus Voltage Low A4-1-8, Trans 101N Aux Fdr 102 R1012 Trip A 4-4-2, PB 16 Low Bus Voltage K3-4-3, PB 16 Bkr Lockout Relay 86-16 SRO

  • Acknowledges reports
  • Directs shutdown of EDG 102
  • Reviews Technical Specifications
  • Determines limiting Technical Specifications are:
  • TS 3.1.5, 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> shutdown LCO for ADS
  • TS 3.2.7, 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> shutdown LCO for Coolant Isolation Valves NRC Scenario 1 12 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 4 continued RO

  • Monitors plant parameters BOP
  • Determines PB 102 cannot be re Role Play: If dispatched as operator to PB 102, energized wait 3 minutes and report R1012 tripped on
  • Places breaker R1012 in PTL overcurrent.
  • Places EDG 102 control switch in emergency stop Role Play: If dispatched to check PB 16B, wait 2
  • Verifies CRD pump 12 running minutes and report that Maintenance reports PB
  • Verifies RBCLC header pressure >40 16B appears free of faults. psig (May start additional RBCLC pump)

Role Play: If directed to verify EDG 102 shutdown

  • Resets 86-16 wait 2 minutes and report EDG 102 is shutdown
  • Verifies open R1043 with no apparent damage.
  • Closes R1042 Note: Scenario continues automatically with Event 5 when R1042 control switch is taken to close. If crew does not crosstie PB 16, examiner may direct manual insertion of TRG 3.

NRC Scenario 1 13 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 5 - Power Board 16A Electrical Fault CREW The following malfunction is automatically

  • Diagnose/report loss of PB 16A and inserted when R1042 control switch is taken to 168 close (or manually inserted as directed by lead
  • Diagnose/report loss of three Drywell examiner): cooling fans ED12A, PB 16A Electrical Fault, DT=30
  • Diagnoselreport rising Containment TRG3 temperature and pressure Powerboard 16A and 16B voltage lower to zero Three Drywel/ cooling fans trip Containment temperature and pressure slowly rise Major expected annunciators:

A4-3-1, Power Bd 16 R1041 Trip A4-4-2, Power Bd 16 Low Bus Voltage L 1-4-4, Drywell- Torus Temp High L4-3-6, Drywell Cooling Fan Trip- Vib SRO

  • Acknowledges reports
  • Directs execution of ARPs
  • If Drywell average temperature exceeds 150°F, enters EOP-4
  • Directs lockout of Containment Spray pumps Note: If RBClC pump 12 was not started in the
  • May direct emergency power last event, RBClC flow will be lost in this event. reduction per SOP-1.1 This will lead to a RWCU isolation.
  • May direct start of RBClC pump 12
  • Directs start of Drywell cooling fan 11 Note: Procedural guidance for starting Drywell
  • Reviews Technical Specifications, cooling fan 11 may come from either OP-8 via the determines loss of EDG 102 ARPs, or directly from EOP-4. auxiliaries, lP pump 11, and ESW pump 11 all lead to less restrictive LeOs than those of event 4
  • May enter N1-S0P-6.1, loss of SFP/RX Cavity level/Decay Heat Removal NRC Scenario 1 14 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 5 continued RO

  • Monitors plant parameters
  • lowers power using Recirc flow per N1-S0P-1.1, as required BOP Role Play: If dispatched as operator to PB 16,
  • Executes ARPs wait 2 minutes and report R1041 tripped on
  • Determines Powerboards 16A and overcurrent. 16B cannot be re-energized
  • May start RBClC pump 12
  • Starts Drywell cooling fan 11
  • Green flags Drywell cooling fan 13, 14, and 15 control switches to clear l4-3-6.
  • Starts RBClC Pump
  • Reports Containment pressure and temperature
  • Starts Condensate Transfer Pump 12
  • May enter N1-S0P-6.1, loss of Role Play: If dispatched as operator to SFP/RX Cavity level/Decay Heat investigate/restore SFP Cooling, acknowledge Removal and direct an operator to order but delay any action. investigate SFP Cooling.

NRC Scenario 1 15 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 6 - Seismic Event and Steam Leak Requiring a Scram on Rising Drywell Pressure When directed by the lead examiner, insert CREW malfunctions:

  • Diagnose/report seismic annunciator PCOS, Seismic Event Triggered
  • Diagnose/report leak in the EC01, Steam Supply Line Break in PC, DT=3:00, Containment FV=12 TRG4 Drywel/ pressure, temperature, humidity and leak rate increase Expected Annunciators:

H2-1-6, Seismic Detection Equipment Event K2-4-3, Drywel/ Pressure High-Low F1-1-5, RPS Ch 11 Drywel/ Press High F4-1-4, RPS Ch 12 DrywelJ Press High SRO

  • Acknowledges report of seismic event
  • Directs execution of SOP-28, Seismic Event
  • Acknowledges report of degrading Containment parameters
  • Directs Crew to monitor containment parameters
  • May direct emergency power Note: The Reactor may automatically scram on reduction per SOP-1.1 Drywell High Pressure.
  • Acknowledges scram report NRC Scenario 1 16 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 6 continued SRO continued Note: Verify the following malfunction is

  • Enters EOP-2, RPV Control on low automatically adjusted when the mode switch is RPV water level and high Drywell taken to SHUTDOWN: pressure/temperature EC01, Steam Supply Line Break in PC, RT=4:00,
  • Answers "Are all control rods inserted IV=12, FV=30 to at least position 04?" YES
  • Directs entry into SOP-1, Reactor Scram
  • Directs RPV water level control 53-95" using Feedwater/Condensate and CRD
  • Directs RPV pressure control, as required
  • May direct MSIVs closed to minimize cooldown rate Note: May not prevent Core Spray injection until
  • Directs lockout of Containment Spray can be installed due to scenario progression and pumps resource limitations. If Core Spray pumps are
  • May direct preventing Core Spray placed in PTL, at least one Core Spray pump injection not needed for core cooling should be restarted after jumper installation for App per EOP-1 attachment 4 J water seal.
  • When Torus pressure exceeds 13 psig or as Drywell temperature Note: When Drywell pressure exceeds 12.5 psig, approaches 300°F:

verify the following are automatically loaded:

  • Answers "Below the Containment Remote PC16, Seismic Mon Pnl Event Light Spray Initiation Limit?" YES Reset, FV=reset
  • Directs verification of Recirc Malfunction PC05, Seismic Event Triggered, pumps tripped DT=10, on TRG 5
  • Directs Drywell cooling fans tripped NRC Scenario 1 17 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 6 continued SRO continued

  • Monitors Pressure Suppression Pressure limit RO
  • When directed, lowers reactor power using recirc flow per SOP-1.1
  • Places Reactor Mode Switch to SHUTDOWN
  • Performs scram verification actions of N1-S0P-1, Reactor Scram:
  • Confirms all rods inserted
  • Observes Reactor power lowering
  • Places IRMs on range 9
  • Down-ranges IRMs as necessary
  • Reduces Recirc Master flow to 25-43 6

x 10 1bm/hr

  • Executes SOP-28, Seismic Event
  • May confirm seismic event indicator on J panel NRC Scenario 1 18 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 6 continued BOP continued

  • May:

Role Play: If contacted as Unit 2 or JAF, report

  • Contacts Unit 2 and JAF to that you have also experienced a seismic event confirm seismic event and that you have confirmed the seismic event with
  • Notifies I&C to interpret seismic JAF or Unit 2 (as appropriate). Report that Unit 2 data seismic recorders indicated 0.09g.
  • Dispatches operators to inspect plant equipment for damage
  • Monitors Drywell instrumentation
  • Performs RPV water level control actions of SOP-1 :
  • Restores RPV water level to 53 95" by controlling injection and rejecting through RWCU, as necessary
  • Determines #13 FWP was running
  • Determines RPV water level is recovering
  • Verifies at least one Electric FW Pump running
  • Terminates 13 FWP injection as follows:
  • Places FWP 13 FCV in manual and closes
  • Disengages 13 FWP
  • Gives 29-10, FEEDWATER PUMP 13 BLOCKING VALVE a CLOSE signal
  • Verifies RPV water level above 53"
  • Verifies 11/12 FWP controllers in MANUAL and set to zero output
  • Resets HPCI signal NRC Scenario 1 19 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 6 continued BOP continued

  • Places 11 or 12 FWP BYPASS Valve in AUTO, sets to 65-70"
  • If RPV level reaches 85 inches and rising, then:
  • Secures CRD Pumps not required
  • Maximizes RWCU reject flow
  • Maintains RPV water level in aSSigned band RO/BOP
  • Reports when Torus pressure exceeds 13 psig or Drywell temperature approaches 300°F
  • Verifies Recirc pumps tripped
  • Trips Drywell cooling fans
  • Verifies started Containment Spray unavailable due to loss of Powerboard 102 pumps 121 and 122 (CT-1.0)
  • Reports Drywell pressure lowering NRC Scenario 1 20 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 7, 8 and 9 - Second Seismic Event and Torus Leak, Trip of Containment Spray Raw Water Pump 121, ERV 111 Fails to Open Verify the following malfunctions are CREW automatically inserted when Containment Spray

  • Diagnose/report second seismic event flow is initiated:
  • Diagnose/report Torus water level is pe05, Seismic Event Triggered, OT=10 lowering PC04, Torus Water Leak, OT=10, FV=25 TRG5 Torus water level slowly lowers Torus room water level slowly rises Expected Annunciators:

K3-3-1, Torus Water Level High - Low H2-2-1, RBldgFIDrSumps 11-16 Area WtrLvl Level High Verify the following malfunction is preset:

A007A, ERV 111 Fails Closed (Burned Out Solenoid)

ERV 111 fails to open Verify the following malfunction is automatically inserted if Containment Spray Raw Water pump 121 is started:

CT02C, CT Raw Water Pump 121 Trip, OT=45 TRG23 Containment Spray Raw Water pump 121 trips after 45 seconds if started NRC Scenario 1 21 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 7! 8 and 9 continued SRO

  • Acknowledges reports
  • Re-enters EOP-4 on low Torus water Note: Torus makeup will be unavailable. EOP-1 level attachment 6 (low capacity makeup from Core
  • May enter EOP-5 on Hi Sump Level Spray Keep-Fill) is unavailable because Core
  • Evaluates ability to add water to the Spray is running due to high Drywell pressure. Torus per EOP-1 attachments 6 & 18 EOP-1 attachment 18 (high capacity makeup from
  • Determines Torus makeup is Containment Spray Raw Water) is unavailable due unavailable due to plant conditions to earlier electrical power losses and the trip of
  • May direct rapid depressurization of Containment Spray Raw Water pump 121. RPV with ECs andlor TSVs in Additionally, the crew may determine based on the anticipation RPV Slowdown rate of Torus water level lowering, that makeup will
  • Sefore Torus water level drops to 8 not be able to reverse the trend and immediately feet, re-enters EOP-2, RPV Control proceed to RPV Slowdown.
  • Determines Torus water level cannot be maintained above 8 feet Note: Verify the following malfunction is
  • Enters EOP-8, RPV Blowdown (CT automatically adjusted when Torus water level 2.0) lowers below 10.4 feet:
  • Answers "Are all control rods PC04, Torus Water Leak, FV=10 inserted to at least position 04?"

YES

  • Answers "Drywell pressure?" At or above 3.5 psig
  • Directs prevention of Core Spray injection not needed for core cooling per EOP-1 attachment 4, if not previously performed
  • Directs EC initiation
  • If Torus water level is above 8 Note: If MSIVs have been previously closed to feet, directs open 3 ERVs limit cooldown rate, they may be reopened in order
  • If Torus water level is at or below to use TSVs as an alternate Slowdown system 8 feet, directs rapid RPV depressurization using Slowdown Systems (Detail 0)

NRC Scenario 1 22 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 7! 8 and 9 continued RO/BOP

  • May evaluate ability to add water to the Torus per EOP-1 attachments 6 and/or 18
  • If operating, secures Containment Role Play: If directed to investigate the Torus Spray Raw Water pump 121 leak, wait 2 minutes then report no water in the
  • Closes 80-16 Corner Rooms, but can hear leak inside the Torus
  • Closes 80-45 Room.
  • Places CONT SPRAY RAW WTR 121 INTERTIE control switch to CNT SPR 111
  • Diagnoses pump trip after time delay
  • Determines Torus makeup is unavailable due to plant conditions
  • Reports Torus water level approaching 8 feet
  • May rapidly depressurize RPV with ECs and/or TBVs in anticipation of RPV Blowdown
  • Prevents Core Spray injection not needed for core cooling per EOP-1 attachment 4
  • Installs EOP jumpers 17, 18, 19, 24,25 and 26
  • Throttles Core Spray IVs as necessary NRC Scenario 1 23 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 7! 8 and 9 continued RO/BOP continued

  • Initiates ECs (CT-2.0)
  • Verifies open the following valves:
  • 39-05, EMERG CNDSR COND RET ISOLATION VALVE 11
  • 39-06, EMERG CNDSR COND RET ISOLATION VALVE 12
  • If Torus water level is above 8 feet, opens 3 ERVs (CT-2.0)
  • Recognizes/reports ERV 111 fails to open
  • Opens additional ERVs as necessary to achieve 3 open
  • If Torus water level is at or below 8 feet, rapidly depressurizes RPV with Blowdown Systems (CT-2.0)
  • Emergency Condensers
  • Reactor head vent valves
  • Emergency Condenser vents
  • Offgas mixing jet
  • RPV water level controlled in assigned band
  • RPV Blowdown in progress

NMP SIMULATOR SCENARIO NRC Scenario 2 REV. 0 No. of Pages: 25 EDG Failure, Power Reduction, Recirc Pump Failures, RPS MG Set Trip, Instrument Air Leak, A TWS, Feedwater Isolation Valves Stick PREPARER DATE '(j/I.q/t~

VALIDATED DATE 7/20/10 GEN SUPERVISOR OPS TRAINING DATE JC/(;kvo OPERATIONS MANAGER NIA Exam Security DATE CONFIGURATION CONTROL NIA Exam Security DATE SCENARIO

SUMMARY

Length: 90 minutes Initial Power Level: Approximately 100%

The crew will perform N 1-ST-M4A, a monthly surveillance on the Emergency Diesel Generator (EDG). During performance of this surveillance, the EDG governor will fail high. With the EDG exceeding the KW limit in the surveillance, the crew will trip the EDG. The SRO will address Technical Specifications for the inoperable EDG. Then, the crew will lower power to approximately 95% in preparation for Control Rod Pattern Exchange to adjust the margins to Unit 1 thermal limits.

Next the Recirculation pump 12 controller output signal fails high. This results in rising recirculation flow and rising Reactor power. The crew will perform a power reduction to restore and maintain Reactor power below rated. Recirculation pump 12 trips following a time delay.

The crew will enter SOP-1.3 for the tripped pump. The pump discharge valve will fail to close.

The crew will take alternate action to close the pump suction valve. The SRO must address Technical Specifications to determine the resulting Reactor power limit and required actions.

Then, RPS MG set 141 will trip. The crew will enter SOP-16.1 due to the resulting partial loss of Feedwater heating. The crew must recover the RPS trip bus by shifting to its alternate supply. Next, an Instrument Air leak will occur in the piping to the CRD system. The crew will insert a manual Reactor scram as CRD air pressure lowers below 60 psig (Critical Task).

When the scram occurs the control rods will not fully insert. The crew must terminate and prevent injection (Critical Task). When the operator attempts to close Feedwater Isolation Valves 11 and 12, the valves will fail to isolate Feedwater flow. The crew must diagnose the NRC Scenario 2 1 November 2010

failure and place the Feedwater pumps in Pull-To-Lock to terminate feeding the RPV. The crew will lower Reactor power by inserting control rods per EOP-3.1 and/or using Liquid Poison (Critical Task).

Major Procedures: N1-ST-M4A, N1-0P-43B, N1-S0P-1.3, N1-0P-48, N1-S0P-16.1, N1-S0P 20.1, N1-S0P-1, N1-EOP-1, N1-EOP-3, N1-EOP-3.1 Dynamic Mitigation Strategy Code: AT1, ATWS requiring RPV water level to be lowered, no Blowdown EAL Classification: Site Area Emergency per EAL 2.2.2, Failure of Automatic and Manual Scrams with Reactor Power> 6%

Termination Criteria: RPV water level controlled in assigned band, Reactor power < 6%,

Control rod insertion in progress or complete NRC Scenario 2 2 November 2010

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

1. Malfunctions:
a. RD35A, CRD Hydraulic Pump 11 Trip Preset
b. RR68B, RR Pump 12 M/A Station Failure - High TRG2
c. RR01 B, RR Pump 12 Drive Breaker Trip, DT=4:00 TRG2
d. RP01 B, Reactor Trip Bus Motor Generator Trips 141 TRG3
e. RD34, Loss of CRD Instrument Air Pres., RT=5:00, FV=20 TRG4
f. IA01, Loss of Instrument Air, RT=5:00, FV=40 TRG4
g. RD33A, Control Rod Bank Blocked Bank 1, FV=12 Preset
h. RD33B, Control Rod Bank Blocked Bank 2, FV=12 Preset
i. RD33C, Control Rod Bank Blocked Bank 3, FV=18 Preset
j. RD33D, Control Rod Bank Blocked Bank 4, FV=12 Preset
k. RD33E, Control Rod Bank Blocked Bank 5, FV=12 Preset
2. Remotes:
a. DG01, DG 102 Governor Speed Droop, FV=ON Preset
b. RP02, Rx Trip Bus 141 Pwr Source, FV=maint TRG29
c. MS05, FW Htr String 12 Reset, FV=reset TRG30
d. MS02, HP FW Htr 125 Reset, FV=reset TRG 30
e. FW24 , Removal of HPCI Fuses FU8/FU9, FV=pulled TRG24
3. Overrides:
a. 1A4S18D11149, POS_1 DG#102 GOVCS-RAISE, FV=on TRG 1
b. 5S66DI3813 POS_1 2F29/NG03A-A POS A, FV=OFF Preset
c. 5S6D13011, POS-21F10/31-03A POS A, FV=OFF Preset
d. 5S5D1308, POS-2 1F10/31-03A POS A, FV=OFF Preset
3. Annunciators:
a. None
4. Triggers:
a. TRG 1 - Fails EDG 102 governor control switch to RAISE when EDG 102 power is above 2600 KW
i. Event Action: dgemvr>2600 ii. Command: None NRC Scenario 2 3 November 2010
b. TRG 21 - Runs a batch file which deletes override on EDG 102 governor control switch RAISE position and fails off the EDG 102 governor control switch LOWER position, when EDG 102 power is above 2950 KW
i. Event Action: dgemvr>2950 ii. Command: bat n1 Oscen2trg21.bat
c. TRG 26 - Activates when ARI is overridden, RPS has been reset and SDV has drained to allow a manual scram to achieve full inward rod movement
i. Event Action: hzlrp12g1 ==1 &&Zdrrarov==1 &&anxstat2(177)==0 ii. Command: bat n10scen2trg26.bat C. Equipment Out of Service
1. CRD pump 11 in PTL with yellow tag D. Support Documentation
1. N1-ST-M4A, Emergency Diesel Generator 102 and PB102 Operability Test, completed up to step 8.1.15
2. Flag the required control room switches per Attachment 8 of OP-45 for the EDG 102 surveillance.
3. RMI for power reduction with recirculation flow E. Miscellaneous
1. Protect the following: CRD pump 12, PB 17, PB 103, Line 1, Line 4, LP pump 12, Core Spray Loops 112 and 122, EDG 103, Containment Spray Loops 121 and 122, RBEVS Loop 12, CREVS 12, Battery Charger 171A or 171B, Battery 12
2. Update Divisional Status Board
3. Ensure two stopwatches are available for EDG surveillance timing
4. Ensure batch file "n1 Oscen2trg21.bat" is in the root batch file directory with the following commands:
a. dor 1a4s18di1149
b. ior 1a4s18di11410 (0 0) false
5. Ensure batch file "n10scen2trg26.bat" is in the root batch file directory with the following commands:
a. dmf rd33a
b. dmf rd33b
c. dmf rd33c
d. dmf rd33d
e. dmf rd33e NRC Scenario 2 4 November 2010

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

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

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

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

Reactor is at approximately 100% power N1-ST-M4A, EDG 102 monthly surveillance test completed through step 8.1.14.

pump 11 is out maintenance PART III: Remarks/Planned Evolutions:

1. Perform N1-ST-M4A, starting at step 8.1.15.
2. Lower power to 95% in preparation for a Control Rod Pattern Exchange to adjust the margins to thermal limits.

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

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

TITLE NAME TITLE NAME SRO ATCRO BOPRO NRC Scenario 2 5 November 2010

ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver: Power Reduction from Rated Step: 1 I INITIAL CONDITIONS/STEP DESCRIPTION I

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

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

Initial conditions to be verified prior to initiation of step:

Parameter Expected Range Actual Parameter Expected Range Actual CTP 1840-1850 MWth Description of Step:

Lower power to 95% with recirculation flow (1745 - 1770 MWth)

Critical parameters to be monitored DURING Step:

Critical parameters not used must be deleted OR marked N/A Critical Parameter Limit Owner Frequen"CYT Contingency RM Ievaluated against approved power profile:

  • N/A 0, I IOther Comments:

I Step Prepared by: AIcz~ /z;;,@Jz Step Reviewed by: derek C<J)t!crfI Iz;;,~

RE/STA Date RE/STAISRO Date Approval to perform Step c;;John Aan7l1 I ~ Step Completed by: I Shift Manager Date SRO Date NRC Scenario 2 6 November 2010

Critical Tasks:

CT-1.0 Given lowering CRD system air pressure, the crew will insert a manual reactor scram before control rods begin drifting, in accordance with N1-ARP-F3 and/or N1 SOP-20.1.

CT-2.0 Given a failure of the reactor to scram with power above 6% and RPV water level above -41 inches, the crew will terminate and prevent all injection except boron and CRD, in accordance with N1-EOP-3.

CT-3.0 Given a failure of the reactor to scram with power above 6%, the crew will lower reactor power by inserting control rods or injecting boron, in accordance with N1 EOP-3.

NRC Scenario 2 7 November 2010

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

  • Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Events 1 and 2 - EDG 102 Surveillance Test and SRO Governor Failure
  • Directs performance of N1-ST-M4A, starting at step 8.1.15
  • Provides oversight for evolution
  • Directs tripping EDG 102 when KW limit is exceeded

RO

  • Monitors plant parameters
  • Assist in timing of EDG 102 start BOP
  • Performs N1-ST-M4A, starting at step 8.1.15
  • Places EDG 102 control switch to START
  • Records time to reach running frequency and voltage
  • Adjusts speed to 60 Hz using DIESEL GOV control switch
  • Inserts Sync Key in R1022 SYN and places to ON
  • Adjusts EDG to establish a slow clockwise rotation on the synchroscope NRC Scenario 2 8 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 1 and 2 continued BOP continued

  • When sync scope is 5 minutes before Expected alarm A4-2-3, DG Gen 102 Start 12 o'clock, closes R1022
  • Adjusts DIESEL GOV control to establish at least 100 KW
  • Adjusts VOLT ADJ RHEO GEN 102 switch to establish reactive load between 300 and 800 KVARs to the When EDG load is raised above 2600 KW, verify bus the following override is automatically inserted:
  • Adjusts DIESEL GOV control switch 1A4S18DI1149, POS_1 DG #102 GOV CS-RAISE to raise load to at least 2650-2750 TRG 1 KW EDG load rises to approximately 2900 KW
  • Recognizes/reports EDG 102 governor malfunction When EDG load rises above 2900 KW, verify TRG
  • Recognizes/reports EDG 102 load is 21 activates, the above override is deleted, and above the 2845 KW trip criteria of N 1 the following override is inserted: ST-M4A step 8.1.13 1A4S180111410, POS_2 DG #102 GOV CS
  • Places Diesel Generator 102 Control LOWER Switch to Emergency Stop EDG load stabilizes above the surveillance test trip
  • Verifies R 1022 open criteria Role Play: If contacted as an operator at the EDG, report that the EDG is shutdown with no abnormal indications.

Role Play: If contacted as Ops Management or as directed by lead examiner to facilitate next event, inform crew that a team has been dispatched to investigate the EDG 102 failure. Direct the crew to stop all actions in N1-ST-M4A and continue with the Reactor power reduction.

NRC Scenario 2 9 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 - Lower Power with Recirculation Flow SRO

  • Directs power reduction with recirculation flow in accordance with OP-438 and the Reactivity Maneuver Instruction (RMI)
  • Provides oversight of reactivity maneuver RO
  • Acknowledges direction from SRO
  • Lowers recirculation flow with master recirculation flow controller
  • Monitors recirculation flow
  • Monitors individual RRP for response
  • Individual MIA-Speed Control stations trending uniformly
  • Individual RRP indications trending normally for speed increase
  • Monitors Feedwater controls for proper response
  • RPV water level remains within program band (65" - 83")

NRC Scenario 2 10 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 4 and 5 - Recirculation Pump MA Station Fails High with Delayed Pump Trip and CREW Recirculation Pump Discharge Valve Fails to

  • Recognize/report rising Reactor Close power When directed by lead examiner, insert
  • Diagnose RRP 12 flow high malfunctions:

RR68B, RR Pump 12 MIA Failure - High RR01B, RR Pump 12 Drive Breaker Trip, DT=4:00 rRG2 Initial Response:

RRP 12 flow rises Reactor power rises Delayed Response (after 4 minutes if pump not tripped earlier):

RRP 12 trips and flow lowers Reactor power lowers Expected Annunciators:

F2-2-2, REACT RECIRC M-G SET 12 F2-3-5, REACT RECIRC PUMP M-G SET LOCKOUTREL86BLOCKED Note: When RRP 12 trips, RPV water level may exceed the high level alarm briefly.

NRC Scenario 2 11 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 4 and 5 continued SRO

  • Acknowledges reports Note: N1-0P-1 Precaution and Limitation states:
  • May direct entry into SOP-1.5 for Observe the following individual RRP 11 (12, 13, unplanned power change 14, 15) limits:
  • May direct entry into SOP-1.1 to
  • Generator MW O. 790 restore and maintain power less than
  • Generator Amps 240 1850 MWth, as required 6
  • RRP Flow 16.8 x 10 Ibmlhr continuous
  • May direct taking RRP 12 MIA station
  • Generator Frequency 11.5 Hz to 56 Hz to MAN SRO may direct tripping the pump due to
  • May direct taking RRP 12 to local lock exceeding these limits for current and flow.
  • May direct tripping RRP 12
  • Directs entry into SOP-1.3 for RRP 12 trip
  • Acknowledges failure of RRP 12 discharge valve to close
  • Provides oversight of reactivity manipulation while closing suction valve
  • Reviews Tech Specs for impact of removal of pump from service and failure of discharge valve to close Role Play: When contacted as Reactor
  • TS 3.1.7.e applies for partial loop Engineering, acknowledge request to verify operation; limits power to 90.5% until thermal limits. RRP 12 suction, discharge and discharge bypass valves are closed with motor breakers locked open, and RRP 12 motor breaker is opened and racked out
  • Contacts Reactor Engineering to verify thermal limits NRC Scenario 2 12 November 2010

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

  • Monitors plant parameters
  • Lowers power as directed per SOP 1.1
  • Monitors Reactor power and recirculation flow during closure of RRP suction valve
  • Verifies position on four loop P/F map BOP
  • May take RRP 12 M/A station to MAN Role Play: If dispatched as operator to take RRP
  • May dispatch operator to take RRP 12 to local lock, wait 1 minute, then report to the 12 to local lock control room that you cannot take local control of
  • May trip RRP 12 RRMG set 12 because the Operating Lever will not
  • Enters SOP-1.3 for RRP trip move.
  • Verifies proximity to restricted zone on four loop Power to Flow Map
  • Attempts to close RRP 12 discharge valve
  • Recognizes/reports that RRP 12 discharge valve will not close
  • Informs crew that reactor power must be monitored and maintained less than 90%

Note: Expected annunciator F2-1-2 comes in

  • Closes RRP 12 suction valve when RRP 12 suction valve is fully closed. This
  • Opens RRP 12 suction valve for 2-3 annunciator clears when the suction valve is re seconds opened.

NRC Scenario 2 13 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 4 and 5 continued BOP continued

  • Green flags RRP 12 control switch
  • Places RRP 12 MIA station to MAN NRC Scenario 2 14 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 6 - RPS MG Set 141 Trip CREW When directed by the examiner, insert

F4-3-2, RX. TRIP BUS M-G SET 141 TROUBLE F4-3-8, RPS CH 12 MAN REACTOR TRIP F4-2-8, RPS CH 12 AUTO REACTOR TRIP SRO

  • Acknowledges reports
  • Directs entry into OP-48, H.5
  • Directs entry into SOP-16.1 for loss of Feedwater heating
  • May direct emergency power reduction per SOP-1.1 if needed to control Feedwater temperatures or Reactor power
  • Provides oversight of reactivity changes RO
  • Monitors plant parameters
  • Lowers power per SOP-1.1 as required to control Feedwater temperatures or Reactor power

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 6 continued BOP

  • Executes ARP F4-3-2 Role Play: When dispatched as operator to
  • Dispatches an operator to investigate investigate problem with MG Set 141, wait two MG Set 141 minutes then report that you can smell burnt
  • Determines I & C Bus 130A is insulation in the vicinity of MG Set 141 motor. available Report that the drive motor breaker tripped on
  • Obtains SRO permission to perform overcurrent. If asked, report no overvoltage trip dead bus transfer of Reactor Trip Bus occurred. 141
  • Dispatches an operator to perform dead bus transfer of Reactor Trip Bus 141 per OP-48 section H.5.0
  • Enters SOP-16.1 due to loss of Role Play: When dispatched as operator to Feedwater heating transfer Reactor Trip Bus 141 to I&C Bus 130A,
  • Monitors Feedwater temperatures wait 2 minutes and insert remote:
  • Acknowledges that Reactor Trip Bus RP02, Rx Trip Bus 141 Pwr Source, FV=maint 141 is re-energized TRG 29
  • Dispatches operator to reset and Feedwater heaters can be reset. Feedwater heaters Role Play: When dispatched as operator to reset Feedwater heaters, wait 2 minutes and insert remotes:

MS05, FW Htr String 12 Reset, FV=reset MS02, HP FW Htr 125 Reset, FV=reset TRG30 Then report 12 Feedwater heaters have been reset.

NRC Scenario 2 16 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 7 - Instrument Air Leak CREW When directed by lead examiner, insert

  • Recognizes/reports lowering malfunctions: instrument air pressure RD34, Loss of CRD Instrument Air Pres,
  • Observes start of standby lAC RT=5:00, FV=20 IA01, Loss of Instrument Air, RT=5:00, FV=40 TRG4 Instrument air pressure lowers Backup Instrument Air Compressor (lAC) loads Standby Instrument Air Compressor (lAC) starts CRD air pressure lowers Expected Annunciators:

L1-4-7, INST AIR BACK-UP VALVE OPEN F3-3-2, CRD CONTROL AIR PRESSURE HI-LO SRO

  • Acknowledges reports
  • May direct entry into SOP-20.1
  • Acknowledges CRD air pressure is less than 60 psig
  • Monitors plant parameters
  • Places the Mode Switch in SHUTDOWN (CT -1.0)
  • Provides scram report NRC Scenario 2 17 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 7 continued BOP

  • Executes ARP F3-3-2 Role Play: When directed as operator check for
  • If directed executes ARP L 1-4-7 air leaks, acknowledge order. Wait 2 minutes and
  • Dispatches Operator to check for air report air leakage on Reactor Building 237' West, leaks near the HCUs.
  • Monitors CRD air pressure
  • Reports when CRD air pressure lowers below 60 psig NRC Scenario 2 18 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 8 and 9 - ATWS with Failure of FW CREW Isolation Valves to Isolate

  • Diagnose failure of control rods to Verify the following malfunctions are preset: insert R033A, Control Rod Bank Blocked Bank 1,
  • Diagnose Reactor power above 6%

FV=12 R033B, Control Rod Bank Blocked Bank 2, FV=12 R033C, Control Rod Bank Blocked Bank 3, FV=18 R0330, Control Rod Bank Blocked Bank 4, FV=12 R033E, Control Rod Bank Blocked Bank 5, FV=12 Control rods partially insert Reactor power remains> 6%

NRC Scenario 2 19 November 2010

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

  • Enters EOP-2, RPV Control, due to Reactor power above 6% when scram required
  • Answers "Are all rods inserted to at least position 04?" NO
  • Answers "Will the reactor stay shutdown without boron?" NO
  • Directs ADS bypassed
  • May enter EOP-4 on high torus temperature
  • Directs bypass of low-low RPV water level MSIV isolation per EOP-1 att 2
  • Determines Reactor power is above 6% and RPV water level is above 41 inches
  • Directs terminate and prevent of all RPV injection except boron and CRD per EOP-1 att 24 (CT-2.0)
  • Acknowledges failure of FW Isolation Valves 11 and 12
  • Directs placing FW Pumps in PTL
  • Directs RPV level lowered to at least

-41 inches NRC Scenario 2 20 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 8 and 9 continued SRO continued

  • Directs RPV water level controlled

-109 to -41 inches with Condensate/FW and CRD EOP-3 Pressure Leg Actions:

  • If any ERV is cycling:
  • Directs initiation of Emergency Condensers
  • Directs ERVs opened to lower RPV pressure to less than 965 psig
  • Directs RPV pressure controlled below 1080 psig using TBVs, ECs and/or ERVs
  • Monitors Figure M, Heat Capacity Temperature Limit EOP-3 Power Leg Actions:
  • Directs initiation of ARI
  • Answers "Is the Turbine Generator On-line?" NO
  • Answers "Reactor power?" Above 6%
  • Directs Recirc pumps verified tripped
  • Directs execution of EOP-3.1, Alternate Rod Insertion (CT-3.0)
  • If power is oscillating more than 25%

or before Torus temperature reaches 110°F:

  • Records Liquid Poison tank level
  • Directs Liquid Poison injection (CT-3.0)

NRC Scenario 2 21 November 2010

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

  • Acknowledges first Liquid Poison pump injecting RO
  • Depresses RPS push buttons
  • Bypasses Core Spray IV interlocks per N1-EOP-1 Att 4 by installing six jumpers (17, 18, 19,24,25,26) inside Panel N
  • Bypasses low-low RPV water level MSIV isolation per EOP-1 att 2 by installing four jumpers (1, 2, 8, 9) inside Panel N
  • Controls IRM recorders and range switches as required to monitor power
  • Reports when APRMs are < 6%
  • Reports status of control rod insertion NRC Scenario 2 22 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 8 and 9 continued RO continued Possible EOP-3.1 Section 3 Actions:

  • Verify a CRD Pump running
  • Place Reactor Mode Switch in REFUEL
  • Place ARI OVERRIDE switch in OVERRIDE
  • Installed RPS jumpers (5, 6, 12, 13)
  • Insert rods to 00 using EMER ROD RMCS. IN starting with high power regions of core (use LPRM Note: RO will likely have to fully open the CRD indications) (CT -3.0) flow control valve and/or close 44-04 in order to
  • If more drive pressure is required, achieve rod movement via RMCS; these methods then perform one of more of the are preferential to closing 44-167 due to ability to following:

perform from the control room and not preventing

  • Fully open CRD Flow Control further scram attempts by blocking the charging Valve (F panel) water header.
  • Close 44-167, Charging Water Header Blocking Valve (RB 237')

Possible EOP-3.1 Section 4 Actions:

  • Place ARI OVERRIDE switch in OVERRIDE Note: When ARI is overridden, the scram is reset,
  • Reset the scram activate. Verify this occurs and the R033
  • Verify open 44-167, Charging Water malfunctions all delete. This allows all control Header Blocking Valve (RB 237')

rods to insert on the next manual scram attempt.

NRC Scenario 2 23 November 2010

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Events 8 and 9 continued BOP

  • Terminates and prevents all injection except boron and CRD per N1-EOP-1 Att 24 (CT-2.0):
  • Closes both FEEDWATER ISOLATION Valves 11 and 12
  • Diagnoses failure of ISOLATION Valves 11 and 12 to close
  • Selects Manual on 11, 12 and 13 FWP Valve Control selector switches Role Play: When directed as NAO to pull HPCI
  • Closes 11, 12 and 13 Feedwater fuses FU-8 and FU-9, wait one minute and insert FCV (Knurled Knob) full remote:

counterclockwise FW24, Removal of HPCI Fuses FU8/FU9,

  • Directs NAO to remove fuses FU FV=pulled 8 and FU-9 from Panel IS34 in TRG24 the Aux Control Room
  • Verifies closed, FEEDWATER Then report that HPCI fuses FU-8 and FU-9 have PUMP 13 BLOCKING VALVE been pulled
  • Verifies in MAN, FWP 11 BYPASS VALVE, AND set to zero output
  • Verifies in MAN, FWP 12 BYPASS VALVE, AND set to zero output
  • Informs SRO when RPV water level reaches -41 inches NRC Scenario 2 24 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 8 and 9 continued BOP continued

  • If any ERV is cycling:
  • Initiates Emergency Condensers
  • IF initiating EC Loop 11, places 39-05, EMERG CNDSR COND RET ISOLATION VALVE 11 control switch in OPEN
  • IF initiating EC Loop 12, places 39-06, EMERG CNDSR COND RET ISOLATION VALVE 12 control switch in OPEN
  • Subsequently controls EC valves per EOP-HC att 9
  • Manually opens ERVs to lower RPV pressure to 965 psig
  • Controls RPV pressure below 1080 psig with TBVs, ECs and/or ERVs
  • Verifies all Recirc Pumps tripped
  • Initiates Liquid Poison as directed
  • Reports initial tank level
  • Starts Liquid Poison pump 11 or 12
  • Verifies RWCU isolated Terminating Cues:
  • RPV water level controlled in assigned band
  • Reactor power < 6%
  • Control rod insertion in progress or complete NRC Scenario 2 25 November 2010

NMP SIMULATOR SCENARIO NRC Scenario 3 REV. 0 No. of Pages: 24 Powerboard 101 Fault. RBCLC TCV Failure, ERV Inadvertently Opens, Degraded 345 KV Grid, Coolant Leak in Drywell. Feedwater Pump Trip PREPARER VALIDATED Mazuroski, Alfieri, Revelle DATE _.:..:.71=20=/...:..;10=--_

GEN SUPERVISOR ~\~ \

OPS TRAINING ~~ .k.'1xVW1~~ DATE OPERATIONS MANAGER N/A - Exam Security DATE _ _ _ __

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

SCENARIO

SUMMARY

Length: 90 minutes Initial Power Level: Approximately 100%

The crew assumes the shift at approximately 100% power with Feedwater pump 11 out of service. They are directed to transfer the Powerboard 101 supply from the normal breaker, R1014, to the alternate breaker, R1011. Once this evolution is complete, a fault will occur causing a loss of Powerboard 101. The crew will respond to a loss of RRP 13 per SOP-1.3.

Additional lost loads include Condensate Pump 12, Feedwater Booster Pump 12 and the Electric Fire Pump. After the loss of PB 101, the Reactor Building Closed Loop Cooling (RBCLC) Temperature Controller will fail such that RBCLC temperatures rise. This failure will require placing the RBCLC controller in manual and restoring the effected equipment to normal temperatures.

Next, ERV 111 opens inadvertently. The crew will enter SOP-1.4. Power will be reduced to approximately 85% power, and fuses will be pulled. This will close the ERV (Critical Task).

The SRO will enter TS 3.1.5.a, requiring a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> shutdown LCO.

Next, a grid disturbance will result in lowering frequency and voltage on the 345KV power lines.

The crew will enter SOP-33B.1 and monitor grid frequency to determine action times for tripping the turbine. As the grid continues to degrade, the crew will scram the Reactor.

A coolant leak in the Drywell will develop following the scram. The crew will enter EOP-4 and re-enter EOP-2. The crew will initiate Containment Sprays to prevent exceeding Pressure Suppression Pressure, in accordance with EOP-4 (Critical Task). The remaining high pressure Feedwater pump will trip. causing RPV water level to lower to the top of active fuel (TAF). With NRC Scenario 3 1 November 2010

the degraded high pressure injection capability, the crew will enter RPV Slowdown before RPV water level drops below -109 inches, in accordance with EOP-2 (Critical Task).

Major Procedures: N1-0P-30, N1-S0P-1.3, N1-S0P-11.1, N1-S0P-1.4, N1-S0P-1.1, N1 SOP-33S.1, N1-S0P-1, N1-EOP-2, N1-EOP-4, N1-EOP-1, N1-EOP-8 Dynamic Mitigation Strategy Code: RL2, LOCA Results in RPV Water Level Selow TAF, Slowdown and Recover Level with Low Pressure Systems EAL Classification: Alert per EAL 3.1.1, Drywell Pressure> 3.5 psig Termination Criteria: RPV water level controlled in assigned band, RPV Slowdown in progress, Primary Containment pressure maintained per EOP-4 NRC Scenario 3 2 November 2010

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

1. Malfunctions:
a. FW03A, Feedwater Pump Trip 11 Preset
b. ED06, PB 101 Electrical Fault, DT=15 TRG 1
c. CW19, RBCLC Temperature Controller Failure, FV=minimum co- TRG 2
d. AD05, ERV 111 Failure - Opens Inadvertently TRG 3
e. EG11, 345 KV Power Grid Transient, RT=7:00, IV=355*, FV=345 TRG 4
f. RR29, RR Loop Rupture on Pump 15 Suction Line, DT=3:00, RT=7:00, FV=17 TRG5
g. FW03B, Feedwater Pump Trip 12, DT=6:00 TRG5
2. Remotes:
a. AD01A, ERV 111 Fuses, FV=puiled TRG 27
b. AD07, Acoustic Monitor Alarm Reset, FV=reset TRG 28
c. FW24, Removal of HPCI Fuses FU8/FU9, FV=puiled TRG24
3. Overrides:
a. None
3. Annunciators:
a. None
4. Triggers:
a. TRG 1 - Triggers the PB 101 fault when R1011 control switch is taken to CLOSE
i. Event Action: zded551 c==1 ii. Command: None
b. TRG 5 - Triggers the LOCA and the trip of Feedwater pump 12 when the mode switch is taken to SHUTDOWN
i. Event Action: zdrpstdn==1 ii. Command: None C. Equipment Out of Service
1. Feedwater pump 11 control switch is in pull-to-Iock with a yellow clearance tag applied.
2. Feedwater pump 11 block valve is closed with a yellow clearance tag applied.

D. Support Documentation

1. N1-0P-30 section H.B marked up through H.B.1.

NRC Scenario 3 3 November 2010

2. Flag protected equipment for FWP 11 out of service (FWP 12, FWBP 13, CP 13, EDG 103, PB 103, PB 12).
3. Update Divisional Status Board.
  • Displays current value until triggered NRC Scenario 3 4 November 2010

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

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

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

(SM, CRS, STA, RO, CRE)

Evolutions/Generallnformation/Equipment Status:

Preparing to transfer Powerboard 101 supply from R1014 to R1011. Previous shift has completed step H.8.1 of N1-0P-30.

Feedwater pump 11 is out of service for maintenance (Day 1 of planned 3 day window, TS 3.1.8, 15 day LCO applies).

PART III: Remarks/Planned Evolutions:

Transfer Powerboard 101 supply from R1014 to R1011 in accordance with N1-0P-30 section H.8.0.

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

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

TITLE NAME TITLE NAME SRO ATCRO BOPRO NRC Scenario 3 5 November 2010

Critical Tasks:

CT-1.0 Given an inadvertently open ERV at power, the crew will close the ERV or insert a manual scram prior to torus temperature exceeding 110°F, in accordance with N 1 SOP-1.4.

CT-2.0 Given a LOCA in the Drywell, the crew will initiate Containment Sprays prior to exceeding the Pressure Suppression Pressure limit, in accordance with N1-EOP-4.

CT-3.0 Given a LOCA with degraded high pressure injection capability, the crew will depressurize the RPV and inject with Preferred and Alternate Injection Systems to restore and maintain RPV water level above -84 inches, in accordance with N1 EOP-2.

NRC Scenario 3 6 November 2010

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

  • Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Transfer PB 101 from R1014 to R1011 SRO
  • Directs transfer of PB 101 from R1014 to R1011 per OP-30, starting at step H.8.2
  • Provides oversight for evolution RO
  • Monitors plant parameters BOP
  • Acknowledges direction to perform N1-0P-30 section H.8, starting at step H.8.2 Note: Annunciator A5-2-1 is expected while
  • Places PB1 01 SUPPLY BREAKER PB101 SUPPLY BREAKER INTERLOCK BY-PASS INTERLOCK BY-PASS SWITCH in SWITCH is in BYPASS BYPASS
  • Inserts Sync. Key in Breaker R1011
  • Turns Sync. Key ON
  • Confirms incoming AND running voltage NORMAL
  • Closes Breaker R 1011
  • Turns Sync. Key OFF
  • Removes Sync. Key
  • Opens Breaker R1014 NRC Scenario 3 7 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 2 - PB 101 Fault CREW Verify the following malfunction automatically

  • Diagnose/report loss of PB 101 inserts when R1011 control switch is taken to
  • Diagnose/report the trip of RRP 13 CLOSE:

E006, PB 101 Electrical Fault, OT=15 TRG 1 Loss or voltage on PB 101 Lowering Reactor power Lowering Recirc flow Expected Annunciators:

A4-1-7, POWER BOARD 101 R1011 TRIP A4-2-7, POWER BOARD 101 LOCKOUT B6BT F2-2-3, React Recirc M-G Set 13 F2-3-5, React Recirc Pump M-G Set Lockout ReI B6 Blocked SRO

  • Acknowledges reports
  • Directs entry into SOP-1.3 for RRP trip
  • Provides oversight of reactivity change during closure of RRP 13 Note: The next event should be inserted when the discharge valve crew closes the RRP 13 Discharge Valve.
  • Reviews Powerboard 101 loads
  • Reviews TS 3.1.7.e and determines Reactor power may be raised to 100%
  • Determines thermal limits penalty NRC Scenario 3 8 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 2 continued RO

  • Monitors plant parameters
  • Monitors Reactor power and recirculation flow during closure of RRP suction valve
  • Verifies position on four loop P/F map BOP
  • Monitors RPV water level response to Role Play: If dispatched to PB 101, wait 2 minutes transient to report R 1011 tripped on overcurrent and that
  • Enters SOP-1.3 for RRP trip Electrical Maintenance is at the PB investigating.
  • Verifies proximity to restricted zone on four loop Power to Flow Map
  • Closes RRP 13 discharge valve
  • Opens RRP 13 discharge valve for 2-3 seconds
  • Green flags RRP 13 control switch
  • Places RRP 13 MIA station to MAN NRC Scenario 3 9 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 3 - RBCLC Temperature Controller CREW Failure

  • Recognize/report rising RBCLC When directed by lead examiner, insert temperatures malfunction:
  • Diagnose failure of RBCLC automatic CW19, RBCLC Temperature Controller Failure, temperature control FV=minimum co TRG2 TGV 70-137 closes and bypass opens RBGLG water temperature rises Temperatures of components cooled by RBGLG rise Expected Annunciator:

H1-4-1, R BUILDING GOOLING WATER PRESS TEMP MAKEUP FLOW SRO

  • Acknowledges report of RBCLC TCV failure
  • Directs execution of ARP H 1-4-1
  • May direct entry into SOP-11.1 ,

RBCLC Failure

  • Directs manual control of RBCLC temperature RO
  • Monitor plant parameters
  • Monitor RRPs and other components cooled by RBCLC NRC Scenario 3 10 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP

  • Executes ARP H 1-4-1
  • May enter SOP-11.1, RBCLC Failure
  • Monitors equipment cooled by RBCLC
  • Places RBCLC Temperature Controller 70-23B in manual (OP-11, Section H.13 may be referenced)
  • Depress the AIM Button until red LED is illuminated next to "M"
  • Turns knurled knob as required to open/close RBCLC TCV
  • Manually adjust RBCLC Temperature Controller to maintain RBCLC temp between srF and 9s o F NRC Scenario 3 11 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 4 - ERV 111 Opens Inadvertently CREW When directed by lead examiner, insert

  • Diagnoses ERV 111 has inadvertently AD05, ERV 111 Failure - Opens Inadvertently opened TRG3 ERV 111 opens Reactor pressure lowers Slightly Reactor power lowers and then rises slightly Torus temperature rises Torus level rises Expected annunciators:

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

  • Acknowledges reports
  • Directs entry into SOP-1.4, Stuck Open ERV
  • Directs emergency power reduction to approximately 85% power
  • Provides oversight for reactivity manipulation
  • Determines that ERV 111 is inoperable per TS 3.1.5.a, requiring a 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> shutdown
  • Directs taking action to close ERV 111 or directs a manual scram prior to Torus temperature exceeding 11 OOF, in accordance with SOP-1.4 (CT-1.0)

NRC Scenario 3 12 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 4 continued SRO continued

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

NRC Scenario 3 13 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 4 continued BOP

  • Enters SOP-1.4
  • Determines ERV 111 is open using:

- Valve indicating lights on F panel

- Red ERV flow indicating light on F Role Play: When directed as operator to go to panel Auxiliary Control Room and verify ERV 111 is

  • Sends an operator to the Aux Control open, wait one minute and report ERV 111 is open; Room to verify ERV open using subsequent reports on acoustic monitor status may Acoustic Monitor be given immediately, with close attention paid to
  • May send an operator to RB 237' to the actual status of the ERV. standby for pulling local ERV fuses
  • Attempts to close ERV 111 by performing one or all of the following:
  • Depresses ADS Timer Reset pushbuttons Note: Safety glasses and gloves are required for
  • Cycles Control Switch for ERV pulling fuses in F panel 111
  • Pulls control power fuses F15 and F30 in F panel (ERV 111)

Role Play: If the operator is directed to pull fuses (CT-1.0) in the RB wait 3 minutes and insert remote: OR AD01A, ERV 111 Fuses, FV=pulled

  • Directs operator to pull ERV 111 TRG27 fuses on RB 237' (CT -1.0)

Report fuses are pulled.

  • Checks with operator in Aux Control Room to see if ERV is still open
  • Determineslverifies ERV closes Role Play: When directed as operator to reset the
  • Directs reset of acoustic monitor acoustic monitor, wait 1 minute and insert remote:
  • Notifies crew that ERV 111 has closed AD07, Acoustic Monitor Alarm Reset, FV=reset
  • Monitors Torus temperature TRG 28
  • Reports if/when Torus temperature Report acoustic monitor is reset. exceeds 85°F or Torus level exceeds 11.25'

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 4 continued BOP continued

  • Places Torus cooling in service when directed, per SOP-1.4, att 2 or EOP-1 att 16:
  • Close CONT SPRAY BYPASS BV(s) for selected loop
  • Verifies closed 80-115
  • Verifies closed 80-114
  • Verifies closed Cont Spray Discharge IV for selected loop
  • Verifies open CO NT SPRAY BYPASS BV for selected loop

INSTRUCTOR ACTIONS/

PLANT RESPONSE OPERATOR ACTIONS Event 5 - Degraded 345KV Grid Conditions CREW When directed by lead examiner, insert

A6-3-3, 345 KV Sys Frequency High - Low (first)

A8-1-3, 115 KV Bus Low Voltage (second)

A6-2-6, 345 KV Bus Voltage High-Low (later)

SRO

  • Acknowledges reports
  • Directs execution of ARPs
  • Directs entry into SOP-33B.1, Major 345 KV Grid Disturbances Note: Turbine operational time limit changes as
  • Directs entry into SOP-33A3, Major grid conditions continue to degrade: 115 KV Grid Disturbances Variation from 60 Hz Operation Time
  • Acknowledges report that turbine

+/- 0.6 Hz Unlimited operational time limit is exceeded for

+/- 0.6 Hz to 1.4 Hz 90 minutes current frequency variation

+/- 1.4 Hz to 1.9 Hz 12 minutes

> +/- 1.9 Hz o minutes

  • Acknowledges scram report
  • Directs SOP-1 actions
  • Directs RPV water level controlled 53 95" with Condensate/FW and CRD
  • Directs RPV pressure controlled 800 1000 psig with Turbine Bypass Valves or Emergency Condensers NRC Scenario 3 16 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 5 continued RO

  • Monitors plant parameters
  • When directed, places Mode Switch in Shutdown
  • Performs SOP-1, Reactor Scram, scram verification actions
  • Places I RMs on range 9
  • Inserts IRM and SRM detectors Role Play: [f contacted as operator to check for
  • Downranges IRMs as necessary abnormal indications (pump operation, Aux Control to monitor power decrease Room panels, breaker targets, etc.) due to the grid
  • Reduces Recirc Master flow to 25 disturbance, wait 2 minutes and report there are no 43 x 106 Ib/hr abnormal indications.
  • Maintains RPV pressure below 1080 psig and in aSSigned band BOP
  • Executes ARPs Role Play: If contacted as Power Control
  • May execute SOP-33A.3 regarding grid voltage or frequency, give current
  • Executes SOP-33B.1 values based on the simulator instructor station.
  • Monitors 345 KV grid frequency and determines magnitude of frequency Role Play: [f contacted as Power Control variation regarding status of offsite power, inform that
  • Contacts Power Control and obtains thunderstorms have caused a loss of some 345 KV line frequency generation and you do not currently have an
  • Updates crew on turbine operational estimated time for restoration. time limit as grid frequency lowers
  • May notify Power Control of turbine Role Play: If contacted as Power Control operational time limit regarding the low voltage post contingency alarm,
  • Places Turbine Vibration chart inform that the low voltage post contingency alarm recorder in fast speed is NOT alarming.

NRC Scenario 3 17 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 5 continued BOP continued

  • When grid frequency lowers to 58.1 Note: If the crew fails to insert a manual reactor Hz, notifies crew that turbine must be scram for a prolonged period of time following grid tripped and Reactor must be frequency lowering below 58.1 Hz, the lead scrammed examiner may choose to force the scenario
  • Performs SOP-1, Reactor Scram, progression by inserting malfunction: level control actions:

TC01, Main Turbine Trip

  • Restores RPV level to 53-95" by contrOlling injection and rejecting through RWCU, as necessary
  • Determines #13 FWP was running
  • Determines RPV water level is recovering
  • Verifies at least one Electric FW Pump running
  • Terminates 13 FWP injection as follows:
  • Places 13 FWP VALVE CONTROL in MANUAL and closes
  • Disengages 13 FWP
  • Gives 29-10, FEEDWATER PUMP 13 BLOCKING VALVE a CLOSE signal
  • Verifies RPV water level above 53"
  • Verifies 11/12 FWP controllers in MANUAL and set to zero output
  • Resets HPCI signal, if required
  • Places 12 FWP BYPASS Valve in AUTO, sets to 65-70 inches NRC Scenario 3 18 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 5 continued BOP continued

  • If RPV level reaches 85 inches and rising, then:
  • Secures CRD Pumps not required
  • Maximizes RWCU reject flow
  • Maintains RPV water level in assigned band NRC Scenario 3 19 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 6 and 7 - Coolant Leak in the Drywell CREW with a Trip of the Operating FW Pump

  • Diagnose/report degrading Verify the following malfunctions are containment parameters automatically inserted when the mode switch is taken to SHUTDOWN:

RR29, RR Loop Rupture on Pump 15 Suction Line, DT=3:00, RT=7:00, FV=17 FW03B, Feedwater Pump Trip 12, DT=6:00 TRG5 Initial response:

Drywell humidity, pressure and temperature rise Drywellleakage rises RPV level and pressure lower Expected annunciators:

H2-4-7, Drywell Water Leak Detection Sys K2-4-3, Drywell Pressure High-Low F1-1-5, RPS Ch 11 Drywell Press High F4-1-4, RPS Ch 12 Drywell Press High Delayed response:

Feedwater Pump 12 trips Expected annunciators:

H3-2-7, Reactor FW Pump 12 Trip Overload Suction Hi-Level H3-2-8, Reactor FW Pump 12 Aux System NRC Scenario 3 20 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 6 and 7 continued SRO

  • Acknowledges reports
  • Enters EOP-4 due to high drywell pressure and temperature
  • Re-enters EOP-2 due to high drywell pressure and low RPV level
  • When torus pressure exceeds 13 psig or drywell temperature approaches 300°F:
  • Verifies all Recirc pumps are tripped
  • Directs trip of all Drywell cooling fans Note: If Torus cooling is in service candidate will
  • Evaluates/monitors position on Pressure Suppression Pressure curve
  • Directs RPV injection with CRD and Liquid Poison
  • May direct closure of MSIVs and pressure control using Emergency Condensers
  • Transitions to alternate level control leg of EOP-2 NRC Scenario 3 21 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 6 and 7 continued SRO continued

  • Directs ADS bypassed
  • Directs verification of EC initiation
  • Answers "Are 2 or more Subsystems available?" - Yes (Both loops of Core Spray available)
  • Waits until RPV water level drops to 84 inches
  • Answers "Is any Subsystem lined up with a pump running?" - Yes (Both loops of Core Spray running)
  • Answers "Is any injection source lined up with a pump running?" - Yes
  • Answers "Are all control rods inserted to at least position 04?"

-Yes

  • Answers "Drywell pressure?" - At or above 3.5 psig
  • Directs EC initiation
  • Answers "Torus water level?"

Above 8.0 ft

  • Directs open 3 ERVs (CT-3.0)
  • Verifies injection of entire contents of Liquid Poison tank
  • Directs injection with available Note: Most likely injection sources are Core systems to restore and maintain Spray, Condensate/Feedwater, CRD and/or Liquid Poison. RPV water level above -84 inches (CT-3.0)
  • Directs installation of Core Spray jumpers (EOP-1 attachment 4) to allow control of Core Spray IVs NRC Scenario 3 22 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Events 6 and 7 continued SRO continued

  • Transitions back to normal level control leg of EOP-2
  • Directs restoration of RPV level to 53-95 inches RO/BOP
  • Updates crew on reactor and containment parameters
  • Maximizes RPV injection with CRD and Liquid Poison
  • When torus pressure exceeds 13 psig or drywell temperature approaches 300°F:
  • Verifies all Recirc pump are tripped
  • Trips all Drywell cooling fans Note: If Torus cooling is in service candidate will
  • Verifies EC initiation
  • Verifies 39-05 and 39-06 open or previously open NRC Scenario 3 23 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 6 and 7 continued RO/BOP continued

  • May secure ECs for pressure control
  • If RPV water level is above 5",

then closes 39-05 and/or 39-06

  • If RPV water level is below 5",

then closes EC steam IVs

  • When RPV water level drops below 84 inches:
  • Initiates ECs
  • Verifies open 39-05
  • Verifies open 39-06
  • Opens 3 ERVs (CT-3.0)
  • Verifies Liquid Poison injection to inject entire contents of Liquid Poison tank Note: Available injection systems include:
  • Injects with available systems to
  • Condensate/FW restore and maintain RPV water
  • CRD level above -84 inches (CT -3.0)
  • Fire Water inside Panel N
  • Liquid Poison
  • Restores RPV water level to 53-95 inches Terminating Cues:
  • RPV water level controlled in assigned band
  • RPV Blowdown in progress

NMP SIMULATOR SCENARIO NRC Scenario 4 REV. 0 No. of Pages: 25 Generator Voltage Regulator Failure, RRP Seal Failure, FWLC Instrument Failure, Un-Isolable RWCU Break in Reactor Building, TBVs Fail Closed PREPARER DATE _1(j_~_I_'9'_!t_o_

VALIDATED Mazuroski, Alfieri, Revelle DATE 7/21/10 GEN SUPERVISOR OPS TRAINING ~,.--;:~~ J DATE 1/1 (W;'2o/e;)

OPERATIONS MANAGER N/A -- Exam Security DATE CONFIGURATION CONTROL N/A - Exam Security DATE SCENARIO

SUMMARY

Length: 90 minutes Initial Power Level: Approximately 85%

The crew assumes the shift at approximately 85% power. They are directed to remove Condensate Pump 13 from service immediately for maintenance due to a motor oil leak.

After the pump has been removed from service, the crew will conduct a rod pattern exchange.

During the rod pattern exchange, the Main Generator Auto Voltage Regulator will fail. The crew will diagnose the failure and take manual control of generator voltage and restore the correct generator output. Following the Main Generator Auto Voltage Regulator malfunction, the inner seal will fail on Reactor Recirculation Pump 11. A few minutes later, the outer seal will fail, affecting drywell leakage. The crew will remove the pump from service and isolate it. The SRO will review Technical Specifications for dryweilleakage and partial loop operation.

Next, a Reactor pressure transmitter will fail low. This will affect Feedwater level control. The crew will be required to shift to manual Feedwater level control. The crew may then shift reactor pressure/level columns and return to automatic Feedwater level control. Technical SpeCifications must be addressed due to the affect on the HPCI mode of Feedwater.

A Reactor Water Cleanup system line break will occur in the Secondary Containment downstream of the Supply Isolation Valves. Reactor Water Cleanup will fail to isolate on high area temperature. The crew will attempt to isolate the system, but the valves will fail to fully close. This break will require a scram (Critical Task) and RPV blowdown (Critical Task) due to exceeding the Maximum Safe Value for general area temperatures. The Turbine Bypass NRC Scenario 4 1 November 2010

Valves will fail to open throughout the transient, complicating pressure control and limiting anticipatory blowdown.

Major Procedures: N1-0P-15A, N1-0P-5, N1-ARP-A7, N1-S0P-1.2, N1-S0P-16.1, N1 EOP-5, N1-EOP-2, and N1-EOP-8 Dynamic Mitigation Strategy Code: SC1, Primary System Leak in Secondary Containment, Blowdown Required EAL Classification: Site Area Emergency per EALs 3.4.1 (RWCU Isolation Failure and Release Outside Primary Containment) and/or 4.1.1 (Primary System Discharging Outside Primary Containment, >135°F in Two General Areas)

Termination Criteria: RPV water level controlled in assigned band, RPV Blowdown in progress NRC Scenario 4 2 November 2010

I. SIMULATOR SET UP A. IC Number: IC-154 B. Presets/Function Key Assignments

1. Malfunctions:
a. CT01D, CT Pump 122 Trip Preset
b. EG02, Generator Auto Voltage Regulator Fails -Increase TRG 1
c. RR06A, RR Pump 11 Lower (Inner) Seal Failure, RT=3:00, FV=75 TRG2
d. RR07A, RR Pump 11 Upper (Outer) Seal Failure, DT=4:00, RT=5:00, FV=60 TRG2
e. RR92, Rx Vesl Pres Xmr 36-31 (Local-FW Control) Fails Low TRG3
f. CU11, CU Coolant Leak Outside of Drywell, FV=45 TRG4
g. CU14, CU Isolation Valves Stuck Open Preset
h. TC12, All Bypass Valves Fail-- Closed, FV=100 TRG5
2. Remotes:
a. FW01C, Condensate Pump 13 Discharge Valve 50-12, FV=close TRG30
3. Overrides:
a. None
4. Annunciators:
a. None
5. Triggers:
a. TRG 11 - Re-inserts RRP 11 seal failure at 10% when RRP 11 suction and discharge green light are energized
i. Event Action: hzlrrv02c( 1)== 1&&hzlrrv03c( 1)== 1 ii. Command: imf rr06a (0 0) 10
b. TRG 12 -- Re-inserts RRP 11 seal failure at 10% when RRP 11 suction and discharge green light are energized
i. Event Action: hzlrrv02c(1 )==1 &&hzlrrv03c(1 )==1 it Command: imf rr07a (00) 10
c. TRG 21 - Energizes RWCU IV 33-01 green light when control switch is taken to close
i. Event Action: zdcu301 c==1 it Command: ior 9ds51 1051912 (00) true
d. TRG 22 -- Energizes RWCU IV 33-02 green light when control switch is taken to close NRC Scenario 4 3 November 2010
i. Event Action: zdcu302c==1 it Command: ior 9ds531051914 (0 0) true
e. TRG 23 - Energizes RWCU IV 33-04 green light when control switch is taken to close
i. Event Action: zdcu304c==1 ii. Command: ior 9ds55105200 (00) true C. Equipment Out of Service
1. Containment Spray pump 122 control switch in PTL with yellow tag
2. Containment Spray pump 122 suction valve closed with yellow tag D. Support Documentation
1. N1-0P-15A section H.9.0, completed through step 9.2
2. RMI and Rod Movement Sheets for sequence exchange E. Miscellaneous
1. Ensure FWLC is selected to column 11
2. Protect the following equipment: Containment Spray Pumps 111, 112, 121, EDG 102, PB 102
3. Update Divisional Status Board NRC Scenario 4 4 November 2010

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

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

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

(SM, CRS, STA, RO, CRE)

Evolutions/General Information/Equipment Status:

Reactor power is approximately 85%

Containment Spray Pump 122 is out of service for maintenance (Day 1 of planned 4 day window, TS 3.3.7.b 15 day LCO applies)

Condensate pump 13 motor has an oil leak PART III: Remarks/Planned Evolutions:

1. Shutdown Condensate pump 13 per OP-15A section H.9.O.
2. Perform Control Rod Sequence Exchange per RMI.

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

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

TITLE NAIVIE TITLE NAME SRO ATCRO BOPRO NRC Scenario 4 5 November 2010

ATTACHMENT 2: REACTIVITY MANEUVER INSTRUCTION Reactivity Maneuver: Rod Sequence Exchange Step: 1 INITIAL CONDITIONS/STEP DESCRIPTION RE presence required in the Control Room? Yes_ No ./

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

Initial conditions to be verified prior to initiation of step:

Parameter Expected Range Actual Parameter Expected Range Actual Recirc Flow 56 60 Mlbm/hr 57 Mlbm/hr Description of Step:

Complete attached rod movement sheets.

Critical parameters to be monitored DURING Step:

Critical parameters not used must be deleted OR marked N/A Critical Parameter Limit Owner Frequency CTP 1850 MWth RO Continuous RMI evaluated against approved power profile:. N/A O.

Other Comments:

Power may rise to as high as 95% on highest reading APRM by the end of the rod withdrawals.

Step Prepared by: ~&:?ccd I ~1l2 Step Reviewed by: cYck~ I~

RE/STA Date RE/STAISRO Date Approval to perform Step c;'blm Aamn I 'Vqdqp Step Completed Shift Manager Date SRO Date NRC Scenario 4 6 November 2010

NMP1 ROD MOVEMENT SHEET Insert Step: .1 o.....

o FROM: 48 TO: 10 N Initials

.8 Control Rod Move NI Check Coupling FulOut E

From TR.H I 5D To Complete (as Expected) Check Light Comments z

~

14-27 48 08 TRH ,/ NlA N/A 38-27 48 08 TRH ,/ NlA N/A t-Additional Qualified Ul Ub lU 14 lU I I 20 JU J4 jij 42 40 ~U ndividual confirms rod 51 51 position by reselecting rods mH 47 47

[or by using 00-7 printout 43 43 39 39 35 35 31 31 27 1 2 27 23 23 19 19 ""'o" 15 15 .r:::

ns 11 11 r:::

Prepared by ,& t&.tJ Dale ~ 07 07 en 8

03 03 ()

Veriledby.4.)J_,£,.,

_ _ _ _ _ _ _ _ __ Date ~ 02 06 10 14 18 22 26 30 34 38 42 46 50 0::

Z

NMP1 ROD MOVEMENT SHEET Withdrawal Step: 1 o..

o FROM: 04 TO: 08 N

~

t...

Control Rod Inlials I Move NI Check Coupling FulOut E

~

From Comments Complete (as Expected) Check Light To z 14-35 04 08 NlA N/A 38-35 04 08 NlA N/A 38-19 04 08 NlA NIA 14-19 04 08 NlA N/A Q)

Alkiitional QUalified UL Ub 10 14 18 .22 26 3D 34 38 42 46 5U ndividual confirms rod 51 51 position by reselecting rods 47 47 lor by using 00-7 printout 43 43 39 39 35 1 2 35 31 31 27 27 23 23 19 4 3 19 v

o 15 15 "C

((I 11 11 C Prepel\'!d by .& £d Date ~ 01 07 ~

C/)

03 03

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~ri~by1)J~&M~___________________ Date ~ 02 06 10 14 18 22 26 30 34 38 42 46 50 0::

Z

Critical Tasks:

CT-1.0 Given an un-isolable RWCU leak outside primary containment and one general area temperature above the maximum safe limit, the crew will insert a manual reactor scram, in accordance with N1-EOP-S.

CT-2.0 Given an un-isolable RWCU leak outside primary containment and two general area temperatures above the maximum safe limit, the crew will execute N 1-EOP-8, RPV Blowd own , in accordance with N1-EOP-S.

NRC Scenario 4 9 November 2010

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

  • Conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown. panels, assumes the shift Event 1 - Shutdown Condensate Pump 13 SRO
  • Directs shutdown of Condensate pump 13 per OP-15A, Section H.9.0
  • Provides oversight for evolution
  • Enters T.S. 3.1.8.b for removal of a redundant HPCI component from service, 15 day LCD RO
  • Monitors plant parameters BOP
  • Acknowledges direction to shutdown Condensate pump 13
  • Monitors Feedwater Booster pump suction pressure (computer point 0454 - 123 psig)

Role Play: When directed to slowly close 50-12,

  • Directs operator in field to slowly close acknowledge order, wait approximately 1 minute 50-12, BV - COND PMP 13 and insert remote: DISCHARGE FW01C, Condensate Pump 13 Discharge Valve
  • WHEN the Condensate Pump 13 50-12, FV=close discharge valve is 90% closed, places TRG30 the pump control switch in PTL Then report 50-12 is 90% closed.

NRC Scenario 4 10 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 1 continued BOP continued

  • Verifies:
  • Maximum Condensate pump motor current s 135 amps
  • Minimum FW Booster pump Role Play: If contacted as operator to report local suction pressure within the FW pump suction pressure, immediately report FW acceptable range of curve shown pump suction pressure based on simulator value of in OP-15C attachment 4 (minimum FWBP discharge pressure minus 50 psig (-300 pressure at 85% flow (-S mlbs/hr) psi). is 72 psig)
  • Minimum FW pump suction Role Play: When directed to fully close 50-12, pressure;:::: 200 psig acknowledge order, wait approximately 15 seconds
  • Directs operator in field to fully close and report valve is fully closed. 50-12, BV - COND PMP 13 DISCHARGE
  • Verifies no abnormal Main Condenser air in-leakage is occurring NRC Scenario 4 11 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 2 - Rod Sequence Exchange SRO Note: Lead examiner may move to the next event

  • Directs performance of Control Rod once sufficient action is observed on the reactivity Sequence Exchange per RMI and manipulation. OP-5
  • Provides oversight for reactivity manipulation RO
  • Acknowledges direction from SRO Note: RMI includes rods 14-35, 38-35, 38-19, and
  • Obtains copy of RIVII 14-19
  • Selects rod
  • Monitors Feedwater controls for proper response
  • RPV water level remains within program band (65" - 83")

NRC Scenario 4 12 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 3 - Generator Auto Voltage Regulator CREW Fails High

  • Recognize/diagnose Auto Voltage When directed by lead examiner, insert Regulator Failure malfunction:

EG02, Generator Auto Voltage Regulator Fails Increase TRG 1 Amplidyne output meter indication rises Exciter output voltage rises Generator field current rises Expected Annunciators:

A3-1-1, TURB GEN EXC. TRANS. 1 TEMP RECORDER (first)

A7-2-6, GEN VOL T REGULA TOR TRIP (second)

SRO

  • Acknowledges reports
  • Directs ARP response
  • Directs adjustment of generator reactive load RO
  • Monitors plant parameters
  • Places VOLTAGE REG TRANSFER switch to OFF
  • Adjusts generator reactive load using exciter field rheostat to 60 MVARS to the bus (OP-32)

NRC Scenario 4 13 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 3 continued BOP

  • Executes ARP A7-2-6 for voltage Role Play: When contacted as Power Control, regulator trip acknowledge the voltage regulator is in manual
  • Confirms computer point FOgg and request NMP1 supply 100 MVARS to the bus
  • Monitors generator output voltage while in manual voltage control.
  • Coordinates with RO to place VOLTAGE REG TRANSFER switch to OFF
  • Notifies Power Control that voltage Role Play: If directed to investigate the voltage regulator is in manual regulator failure, wait 3 minutes and report no
  • May refer to S-ODP-OPS-0112, Off visible problems at the exciter or breaker cabinet. Site Power Operations and Interface, attachment 4
  • Coordinates with RO to adjust generator reactive load
  • Enter OP-32, Sect H.5, raise Vars using Exciter Rheostat to 100 Mvars to the bus.

NRC Scenario 4 14 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 4 - RRP 11 Seal Failures CREW When directed by lead examiner, insert

  • Diagnoses/reports RRP 11 inner seal malfunctions: failure RR06A, RR Pump 11 Lower (Inner) Seal Failure,
  • Diagnoses/reports RRP 11 outer seal RT=3:00, FV=75 failure (later)

RR07A, RR Pump 11 Upper (Outer) Seal Failure,

  • Recognizes/reports degrading Primary DT=4:00, RT=5:00, FV=60 Containment parameters (later)

TRG2 Initial response:

RRP 11 LP seal pressure rises Delayed response:

RRP 11 HP seal pressure lowers RRP 11 LP seal pressure lowers OW temp, pres and humidity slowly rise DW leakage rises Expected annunciators: SRO F2-1-1, REACT RECIRC PUMP-MOTOR 11

  • Acknowledges reports H2-4-7, Drywel/ Water Leak Detection Sys
  • Directs entry into SOP-1.2, RRP Seal Failure Note: Verify TRG 11 and TRG 12 automatically
  • Reviews Technical Specifications re-insert malfunctions RR06A and RR07A at
  • Determines Drywelileakage rates are 10% when RRP 11 suction and discharge valve affected in Tech Spec 3.2.5 green lights energize.

90.5% until the pump isolation is complete

  • Verifies power < 90.5%
  • Provide oversight of reactivity change during evolution NRC Scenario 4 15 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 4 continued RO

  • Monitors plant parameters
  • Monitor total recirculation flow and APRM power levels while RRP 11 is being shutdown and isolated
  • Verifies position on four loop Power to Flow Map BOP
  • Enters SOP-1.2, RRP Seal Failure
  • Initially answers "Did both seals fail on a single Recirc pump?" NO
  • Monitors OW equipment drain tank level
  • Contacts Engineering for evaluation
  • Monitors RRP 11 seal indications for signs of degradation nd
  • Determines 2 seal is failing Note: SOP-1.2 defines a seal failure as
  • Re-enters SOP-1.2 catastrophic if it results in a noticeable rise in OW
  • Answers "Did both seals fail on a pressure or floor drain leakage. single Recirc pump?" YES
  • Answers "Is failure catastrophic?" YES Note: Closing RRP suction and discharges valves
  • Places RRP 11 control switch to during this event is an approved two-handed STOP manipulation.
  • Closes RRP 11 bypass valve
  • Simultaneously closes RRP suction Note: Allow Reactor water level to recover to and discharge valves normal value before moving to next event in order
  • Verifies proximity to restricted zone to avoid a high level Turbine trip. Also allow the using four loop Power to Flow Map crew to isolate RRP 11 to prevent the seal leak
  • Monitors containment parameters from causing a high drywell pressure scram.

NRC Scenario 4 16 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 5 - RPV Pressure Transmitter Failure CREW Resulting in FWLC Deviation

  • Diagnoses/reports failure of pressure When directed by lead examiner, insert instrument malfunction:
  • Diagnoses/reports failure of FWLC RR92. Rx Vesl Pres Xmtr 36-31 (Local-FW Pressure/Level Column Control) Fails - Low TRG3 RPV pressure instrument indicates downscale Controlling RPV water level instrument indicates lower than actual Feedwater flow rises RPV water level rises Expected Annunciator:

F2-3-3, REACT VESSEL LEVEL HIGH-LOW Note: This event may cause a turbine trip and subsequent reactor scram on high RPV water level if Feedwater flow is not controlled properly. In the event of a scram, TRG 4 should be immediately inserted and the scenario will continue in event 6.

SRO

  • Acknowledges reports
  • Directs entry into SOP-16.1 for failure ofFWLC
  • Directs placing FWLC in manual
  • Directs shifting Reactor Pressure/Level Columns per OP-16, section F.10.0 Note: N1-ST-DO contains acceptance criteria for
  • Reviews Tech Spec 3.1.8 for affect of GEMAC level instrument deviation with regards to level instrument deviation on HPCI HPCloperability. operability, as time permits NRC Scenario 4 17 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 5 continued RO

  • Monitor plant parameters
  • If directed to shift FWLC Note: Switching level columns may result in pressure/level columns:

Annunciator F2-3-3, REACT VESSEL LEVEL

  • Verifies Feedwater lineup HIGH-LOW, due to circuit interruption.
  • Verifies BOP has manual control of FWLC Note: The same channel of level and pressure
  • Shifts reactor pressure and level should be selected columns using the key lock switches on the E Panel
  • Coordinates with BOP to return FWLC to auto:
  • Places FEEDWATER MASTER CONTROL M/A station mode switch in MAN
  • Nulls FWP 13 VALVE CONTROL by adjusting the FEEDWATER MASTER CONTROL station output with the manual knob until the deviation meter indicates 50%

on FWP 13 VALVE CONTROL GEMAC

  • Directs BOP to place FWP 13 FCV M/A Station in BAL
  • Controls RPV water level with the manual knob at the FEEDWATER MASTER CONTROL
  • Nulls FEEDWATER MASTER CONTROL setpoint error by adjusting SP ADJUST knob to null the deviation meter (upper, vertical) at midpoint NRC Scenario 4 18 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 5 continued RO continued

  • Places FEEDWATER MASTER CONTROL MIA station mode switch in AUTO or SAL
  • Confirms system response by adjusting the SP ADJUST knob on FEEDWATER MASTER CONTROL to maintain RPV water level BOP
  • Enters SOP-16.1 due to failure of FWLC
  • Manually restores RPV water level to normal band
  • If directed to shift FWLC pressurellevel columns:
  • Coordinates with RO to return Note: Once the FWP 13 VALVE CONTROL MIA FWLC to auto:

STATION mode switch is in SAL, manual FWLC is

  • Places FWP 13 VALVE shifted to the RO at E-panel CONTROL MIA STATION mode switch in SAL NRC Scenario 4 19 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Events 6. 7 and 8 - RWCU Leak in the CREW Secondary Containment. Failure of the RWCU

  • Diagnoses/reports RWCU failed to malfunction: isolate CU11, CU Coolant Leak Outside of Orywell

H1-4-8, AREA RADIATION MONITORS L 1-4-3, REACT BLDG VENT RAD MONITOR OFF NORMAL L1-3(4)-6, EMER VENT SYS CHANNEL 11(12)

RELA Y OPERA TE K3-3-4, CLEAN-UP SYS LEAK AREA T HI L 1-3-3, CONTINUOUS AIR RAD MONITOR Later Reactor Building DIP goes to Zero Verify the following malfunctions are preset:

CU14, CU Isolation Valves Stuck Open TC12, All Bypasss Va.lves Fail - Closed, FV=100%

NRC Scenario 4 20 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 6, 7 and 8 continued SRO

  • Acknowledges reports
  • Enters EOP-S, Secondary Containment Control, on high Reactor Building Vent rad levels, high Reactor Building area temperatures loss of DIP and rad levels
  • Directs RWCU system isolation
  • Directs Reactor Building evacuation
  • Acknowledges report that RWCU failed to isolate both automatically and manually
  • Directs dispatching of an operator and RP tech to obtain general area temperatures and radiation levels in the Reactor Building
  • Determines area temperatures and radiation levels are above setpoints in Tables T and R, and transitions to EOP-S circle 27
  • Determines a primary system is discharging into the Reactor Building and the discharge cannot be isolated, and transitions to EOP-S circle 28
  • Before any area temperature or radiation level reaches 13SoF or 8 Rlhr, respectively:
  • Acknowledges scram report NRC Scenario 4 21 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 6, 7 and 8 continued SRO continued

  • Answers "Are all control rods inserted to at least position 04?" YES
  • Directs entry into SOP-1, Reactor Scram
  • Directs RPV pressure maintained pressure control due to a malfunction <1080 psig using Emergency Condensers Note: AntiCipatory blowdown is likely to be
  • May direct anticipatory blowdown with directed from EOP-2 once one Reactor Building Emergency Condensers with General Area temperature is above 135°F with a cooldown in excess of 100°FIhr second temperature trending towards 135°F.
  • Acknowledges reports of Reactor Building temperatures and radiation levels
  • When report is received that 2 General Areas temperatures are above 135°F, enters EOP-8, RPV Blowdown
  • Answers "Are all control rods inserted to at least position 04" YES
  • Answers "Drywell pressure?" <3.5 psig
  • Directs initiation of Emergency Condensers
  • Answers "Torus water level?" >8 ft
  • Directs open 3 ERVs (CT-2.0)

NRC Scenario 4 22 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 6, 7 and 8 continued RO

  • Makes evacuation announcements due to steam leak
  • Places Reactor Mode Switch to SHUTDOWN
  • Performs scram verification actions of N1-S0P-1, Reactor Scram:
  • Confirms all rods inserted
  • Observes Reactor power lowering
  • Places IRMs on range 9
  • Down-ranges IRMs as necessary
  • Reduces Recirc Master flow to 25-43 x 106 lbm/hr
  • Controls RPV pressure as directed using Emergency Condensers BOP
  • Attempts to isolate RWCU by closing 33-01 R,33-02R and 33-04R
  • Recognizes/reports failure of RWCU IVs (33-01 R,33-02R and 33-04R) to close Note: No General Area temperature information is
  • Dispatches operator and RP tech to available until an operator has been dispatched to obtain Reactor Building General Area the Reactor Building to monitor area temperatures. temperatures and radiation levels The timeline of field reports may be adjusted by
  • Notifies crew of reports on General examiner as necessary for evaluation purposes. Area temperatures and radiation levels NRC Scenario 4 23 November 2010

INSTRUCTOR ACTIONSI PLANT RESPONSE OPERATOR ACTIONS Event 6, 7 and 8 continued BOP continued

  • Performs RPV water level control actions of SOP-1 :

Role Play: When directed as operator and RP

  • Restores RPV water level to 53-95" by tech to obtain General Area temperatures and controlling injection and rejecting radiation levels in the Reactor Building: through RWCU, as necessary
  • Determines #13 FWP was running Wait 4 minutes and report RB 261' east side
  • Determines RPV water level is temperature is 125°F and rising, radiation level is recovering 100 mr/hr and rising. Also report that you see
  • Verifies at least one Electric FW steam coming from the area of the RWCU rooms. Pump running
  • Terminates 13 FWP injection as Note: When one general area temperature is follows:

reported above 135°F and a second general

  • Places FWP 13 FCV in manual area temperature is reported as approaching and closes 135°F, the crew is likely to perform an
  • Disengages 13 FWP anticipatory blowdown per EOP-2.
  • Gives 29-10, FEEDWATER PUMP 13 BLOCKING VALVE a CLOSE Wait 2 more minutes and report RB 261' east side signal temperature is 137°F and rising, radiation level is
  • Verifies RPV water level above 53" 150 mr/hr and rising. Report RB 261' west side
  • Verifies 11/12 FWP controllers in temperature is 123°F and rising, radiation level is MAN UAL and set to zero output 35 mr/hr and riSing.
  • Places 11 or 12 FWP BYPASS Valve Wait 3 more minutes and report RB 261' east side in AUTO, sets to 65-70" temperature is 145°F and rising. radiation level is
  • If RPV level reaches 85 inches and 175 mr/hr and rising. Report RB 261' west side rising, then:

temperature is 136°F and rising, radiation level is

  • Verifies off all Feedwater Pumps 45 mr/hr and rising.
  • Secures CRD Pumps not required
  • Maintains RPV water level in assigned band NRC Scenario 4 24 November 2010

INSTRUCTOR ACTIONS!

PLANT RESPONSE OPERATOR ACTIONS Event 6, 7 and 8 continued BOP continued

  • Notifies crew of reports on General Area temperatures and radiation levels
  • Verifies Emergency Condensers in service
  • Verifies open 39-05
  • Verifies open 39-06

Terminating Cues:

  • RPV water level controlled in assigned band
  • RPV Slowdown in progress NRC Scenario 4 25 November 2010
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