Text

2013 Perry Nuclear Power Plant Initial License Examination Proposed JPMs
	ML13179A088
Person / Time
Site:	Perry
Issue date:	03/14/2013
From:	; NRC/RGN-III
To:	; FirstEnergy Nuclear Operating Co
	Bielby, M.
Shared Package
ML11354A275	List: L-12-446, 2013 Perry Nuclear Power Plant Initial License Examination Proposed Exam Files; ML13175A088; ML13179A087; ML13179A088; ML13179A089; ML13179A104;
References
	OT-3701-ADM_027_RO, Rev 0
	Download: ML13179A088 (149)
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OT-3701-ADM_027_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: Conduct of Operations Validated Time: 23 Minutes

References:

NOP-OP-1002 Rev 7, SOI-N35 Rev 19, SOI-C11(CRDH) Rev 21, IOI-3 Rev 47, and TS 3.4.1 Required Material: None Task: 299-687-03-01 Report Abnormal Parameters or Conditions Task Standard: Identify system/component discrepancies during hourly walkdown K/A Data: 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. Importance: SRO 3.6 SRO 3.8

1. Setup Instructions: Reset to IC 98. Run Schedule file NRC JPM ADM-027_RO.sch.

Acknowledge all alarms. Place simulator in FREEZE

2. Location / Method: Simulator / Performance

3. Initial Condition: Plant conditions are as found.

4. Initiating Cue: As the Operator ATC, perform your hourly Control Area walkdown IAW NOP-OP-1002, Conduct of Operations.

Start: Stop:

Candidate:

OT-3701-ADM_027_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 NOP-OP-1002, Conduct of Operations 4.5 Operator Professionalism, Monitoring, and Control Room Performance 4.5.2 Standards

13. During steady state conditions, the RO ATC should perform an hourly panel walk-down within the Controls Area.

Standard: Candidate walks-down horseshoe panels for discrepancies and trends.

Instructor Cue: None Notes: If the Candidate identifies items other than the 4 out of spec items for this JPM, advise him that the item will be adjusted after walkdown is complete and to continue with walkdown.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_027_RO Rev 0 Step 2 Observe discrepancy - CRD Drive Pressure Critical Step: Candidate observes CRD Drive pressure at 350 psid.

Instructor Cue: Will adjust after walkdown complete. Continue with walkdown.

Notes: Normal CRD Drive pressure should be 250-275 psid.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 Observe discrepancy - Reactor Recirc Loop Flow mismatch Critical Step: Candidate observes Reactor Recirc Loop flow mismatch > 5%.

Instructor Cue: Will adjust after walkdown complete. Continue with walkdown.

Notes: Normal Loop Flow mismatch should be < 5%.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_027_RO Rev 0 Step 4 Observe discrepancy - Load Set Critical Step: Candidate observes Load Set only slightly > load.

Instructor Cue: Will adjust after walkdown complete. Continue with walkdown.

Notes: Normal Load Set should be set at 120 MWe > load. (Normally set @

1450 when at 100% power)

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 Observe discrepancy - Generator Hydrogen Purity Critical Step: Candidate observes Generator H2 purity in red zone of meter.

Instructor Cue: Will dispatch NLO after walkdown complete. Continue with walkdown.

Notes: Normal Hydrogen Purity should be at 90% but >70%.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Horseshoe walkdown is complete and discrepancies have been correctly identified.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-ADM_027_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS: Plant conditions are as found.

INITIATING CUE: As the Operator ATC, perform your hourly Control Area walkdown IAW NOP-OP-1002, Conduct of Operations.

OT-3701-ADM_019-RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: Conduct of Operations Validated Time: 25 Minutes

References:

ONI-E12-2 Rev 29, PDB-A019 Rev 8, PDB-A017 Rev 11, & PDB-A016 Rev 12 Required Material: ONI-E12-2, Loss of Decay Heat Removal PDB-A019, Time to Core Uncovery Curves PDB-A017, Pool Heatup Curves PDB-A016, Decay Heat Curve Task: 299-827-01-01 Demonstrate the Use of PDB Entries in Tabs A, B, C, D, E, F, G, H, and T Task Standard: Determine Time to Boil and Time to Core Uncovery.

K/A: 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. Importance: RO 3.9 SRO 4.2

1. Setup: Provide copies of PDB-A-16, -017, & 019 and ONI-E12-2

2. Location / Method: Class Room / Administrative performance.

3. Initial Condition: It is day 25 of Refueling Outage 14. Reactor vessel reassembly is in progress after refueling was completed. Current Reactor level is being maintained near the vessel flange for setting the vessel head. The backup decay heat removal system is unavailable. Thirty minutes ago RHR B tripped with Reactor water temperature of 90°F.

Operations and Maintenance personnel are attempting to determine cause. No decay heat removal systems are in service or currently available.

4. Initiating Cue: The Shift Manager directs you to calculate Time to Boil per ONI-E12-2 Loss OF Decay Heat Removal Step 4.4.7. Additionally, determine Time to Core Uncovery, Start: Stop:

Candidate:

OT-3701-ADM_019-RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 ONI-E12-2, Loss of Decay Heat Removal 4.0 SUPPLEMENTAL ACTIONS 4.4 IF a loss of reactor decay heat removal has occurred, THEN PERFORM the following:

4.4.7 IF in MODE 5 or At All Times, THEN REFER TO the Perry Work Implementation Schedule (PWIS) OR PDB-A0017 and DETERMINE estimated time to boil.

Standard: Obtains and reviews PDB-A0017.

Instructor Cue: If asked, the PWIS is not available.

Notes: When Candidate identifies the correct PDB, provide him with a copy.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2 Determine PDB-A0016 and PDB-A0019 are also needed.

Standard: Determines that PDB-A0016 and PDB-A0019 are also needed.

Instructor Cue: None Notes: When Candidate identifies the correct PDBs, provide him with a copy.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_019-RO Rev 0 Step 3 Determine Time to Boil.

Critical Step: Using PDB-A016 p 5 and PDB-A017 p 9 Candidate determines Time To Boil is approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 Determine Time To Core Uncovery.

Critical Step: Using PDB-A016 p 5 and PDB-A019 p 9 Candidate determines Time To Core Uncovery is approximately 43 hours4.976852e-4 days 0.0119 hours 7.109788e-5 weeks 1.63615e-5 months .

Instructor Cue: None Notes: Due to readability of the graph, 42.5-44 hours is acceptable.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Determines Time to Boil and Time to Core Uncovery.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-ADM_019-RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

It is day 25 of Refueling Outage 14.

Reactor vessel reassembly is in progress after refueling was completed.

Current Reactor level is being maintained near the vessel flange for setting the vessel head.

The backup decay heat removal system is unavailable.

Thirty minutes ago RHR B tripped with Reactor water temperature of 90°F.

Operations and Maintenance personnel are attempting to determine cause.

No decay heat removal systems are in service or currently available.

INITIATING CUE: The Shift Manager directs you to calculate Time to Boil per ONI-E12-2 Loss OF Decay Heat Removal Step 4.4.7. Additionally, determine Time to Core Uncovery,

OT-3701-ADM_026_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: P54, Fire Protection System - Water Time Critical: No Alternate Path: No Applicability: SRO only, RO/SRO Safety Function: Administrative Validated Time: 10 Minutes

References:

SOI-P54 (WTR) Rev 16, PAP-1910 Rev 27, & Dwg 914-001 Rev NN Required Material: SOI-P54 & Dwg 914-001 Task: 286-505-01-01 Analyze System Problems 286-506-03-01 Inform Unit Supervisor of Inoperable Fire Protection Task Standard: Identify boundary for leaking fire protection system component K/A Data: 2.2.41 - Ability to obtain and interpret station electrical and mechanical drawings. Importance: RO 3.5 SRO 3.9

1. Setup Instructions: None

2. Location / Method: Simulator / Classroom - Administrative Performance

3. Initial Condition: Reports from the field indicate that P54-F3554, Motor to Diesel Fire Pump Xconn Supply to Ring has a thru wall pipe rupture. The Unit Supervisor has ordered all Fire Pumps shutdown to secured status per SOI-P54 Water.

4. Initiating Cue: The Unit Supervisor directs you to determine how P54-F3554 can be isolated.

Start: Stop:

Candidate:

OT-3701-ADM_026_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 Evaluate Leak Isolation, Drawing 914-0001-0000 Rev LL, Fire Service Yard Area Critical Step: Candidate obtains drawing and determines that closing P54-F3552 is necessary to isolate P54F3554.

Instructor Cue: When the Candidate determines the correct 914 drawing to use, then provide the drawing to the Candidate if required.

Notes: JPM Steps 1, 2, & 3 can be performed in any order.

P54-F3554 coordinates are F-4 and P54-F3552 coordinates are H-2.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_026_RO Rev 0 Step 2 Evaluate Leak Isolation, Drawing 914-0001-0000 Rev LL, Fire Service Yard Area Critical Step: Candidate obtains drawing and determines that closing P54-F6371 is necessary to isolate P54F3554.

Instructor Cue: None Notes: JPM Steps 1, 2, & 3 can be performed in any order.

P54-F3554 coordinates are F-4 and P54-F6371 coordinates are C-3.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 Evaluate Leak Isolation, Drawing 914-0001-0000 Rev LL, Fire Service Yard Area Critical Step: Candidate obtains drawing and determines that closing P54-F3555 is necessary to isolate P54F3554.

Instructor Cue: None Notes: JPM Steps 1, 2, & 3 can be performed in any order.

P54-F3554 coordinates are F-4 and P54-F3555 coordinates are F-4.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: The valves needed to isolate the leak have been correctly identified.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-ADM_026_RO x Rev 0 Answer Key Isolation valve Leaking valve Isolation valve Drawing 914-0001 Rev NN

OT-3701-ADM_026_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS: Reports from the field indicate that P54-F3554, Motor to Diesel Fire Pump Xconn Supply to Ring has a thru wall pipe rupture. The Unit Supervisor has ordered all Fire Pumps shutdown to secured status per SOI-P54 Water.

INITIATING CUE: Unit Supervisor directs you to determine how P54-F3554 can be isolated.

OT-3701-ADM_018-RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Applicability: RO/ SRO Safety Function: Radiation Control Validated Time: 14 Minutes

References:

Dwg 304-625 Rev J VSDS IB-599 Survey Map Required Material: IB-599 Survey Map, Calculator Task: 299-502-03-01 Maintain Radiation Exposure as Low as Reasonably Achievable (ALARA) 299-848-01-01 Comply with the Administrative Requirements for the Perry Plant Radiation Dose Control Program Task Standard: Determine radiological conditions and calculate dose.

K/A: 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. Importance: RO 3.5 SRO 3.6

1. Simulator Setup: N/A

2. Location / Method: Class Room / Administrative performance.

3. Initial Condition: While investigating a leak in the FPCC Heat Exchanger Room. An NLO (Roberts) became incapacitated against the east wall near the A HX. He is unable to move. Another NLO (Webb) was unable to move him, but stated that he is directly below the P42-F440 valve. Roberts has suffered unknown injuries. You and Fire Brigade member Bill Smith have volunteered to rescue NLO Roberts.

4. Initiating Cue: Review the survey map for the FPCC HX Room and determine the following:

1. What is the highest contamination level?

2. What is the highest contact radiation level?

3. What is the highest general area dose rate level?

4 What is the estimated dose if it takes you 8 minutes to stabilize and prepare to remove NLO Roberts? (Disregard dose for traveling to and from door to Roberts.)

Start: Stop:

Candidate:

OT-3701-ADM_018-RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 Determine the highest contamination level.

Critical Step: Determines the highest contamination level is 5000 DPM/100 cm2 at smear location 3.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2 Determine the highest contact radiation level.

Critical Step: Determines the highest contact radiation level is 1100 mr/hr at DR-23.

Instructor Cue: None Notes: Some of the contact dose readings are lower than the 30 cm readings due to the 30 cm reading being taken closer to the HX.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_018-RO Rev 0 Step 3 Determine the highest general area dose rate level.

Critical Step: Determines the highest general area dose rate level is 3100 mr/hr at DR-21.

Instructor Cue: None None Notes:

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 Determine the estimated dose to stabilize and prepare to remove NLO Roberts.

Critical Step: Calculates the dose to stabilize and prepare to remove NLO Roberts to be Instructor Cue: None Notes: Dose 30 cm from P42-F440 is 100 mr/hr @ 8 min = 13.3 mr each.

(13 to 14 mr is acceptable)

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Determines highest contamination level, contact dose rate, general area dose, and dose received.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-ADM_018-RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS: While investigating a leak in the FPCC Heat Exchanger Room. An NLO (Roberts) became incapacitated against the east wall near the A HX. He is unable to move. Another NLO (Webb) was unable to move him, but stated that he is directly below the P42-F440 valve.

Roberts has suffered unknown injuries. You and Fire Brigade member Bill Smith have volunteered to rescue NLO Roberts.

INITIATING CUE: Review the survey map for the FPCC HX Room and determine the following:

1. What is the highest contamination level?

2. What is the highest contact radiation level?

3. What is the highest general area dose rate level?

4 What is the estimated dose if it takes you 8 minutes to stabilize and prepare to remove NLO Roberts? (Disregard dose for traveling to and from door to Roberts.)

OT-3701-ADM_320SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: Yes Alternate Path: No Applicability: SRO only Safety Function: N/A Validated Time: 20 Minutes

References:

PAP-1604 Rev 24 Required Material: PAP-1604, Reports Management Task: 341-640-03-02 Evaluate each Event or Condition under the Notification Requirements specified in Attachment 1 of PAP-1604 for Reportability Task Standard: Perform a reportability evaluation of an RPS actuation K/A: 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. Importance SRO 3.8

1. Setup Instructions: None

2. Location / Method: Classroom / Administrative Performance

3. Initial Condition: Plant shutdown for a refuel outage was in progress. The shutdown schedule called for power to be reduced to 20% and then a manual reactor scram was to be inserted.

Thirty minutes ago while shifting reactor feed pumps, a problem with Digital Feedwater Control System resulted in an excessive feed rate and a rising RPV level. The ATC inserted a manual reactor scram prior to reaching Level 8. Reactor power at the time of the scram was 30%. Manual control of DFWCS was regained following the scram and plant conditions are now stable.

4. Initiating Cue: As the Shift Manager, evaluate this event for reportability per PAP-1604, Reports Management.

This JPM is Time Critical Start: Stop:

Candidate:

OT-3701-ADM_320SRO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 PAP-1604, Reports Management 4.2 Immediate Notifications 4.2.1 Shift Manager

1. Ensure that each event or condition is evaluated under the notification requirements specified in Attachment 1.

Critical Step: Evaluate PAP-1604, Attachment 1, and determines that a Four Hour (10CFR50.72 Non-Emergency) Notification is required due to the RPS actuation (when the reactor is critical).

Instructor Cue: After Candidate determines that a Four Hour Notification is necessary tell him to perform any required notifications to the NRC Operations Center.

Notes: The Candidate must determine that the manual reactor scram was not part of the pre-planned shutdown sequence.

The 4-hour Notifications should be documented on the form.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_320SRO Rev 0 Step 2

2. Ensure that the required notifications are made within the specified time requirements to the NRC Operations Center via the Emergency Notification System (ENS) unless otherwise specified in Attachment 1.

Critical Step: Determine that the notification is due four hours from the time of the manual reactor scram.

Instructor Cue: What is the latest time the Notification can be made?

Notes: The limiting Notification is the 4-hour Notification SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3

3. Ensure that information provided to the NRC is recorded on an Event Notification form PNPP No. 6912 including any additional information requested by the NRC Duty Officer.

Critical Step: Fill in Form PNPP No. 6912, Initial Notification.

Instructor Cue: If asked, inform the Candidate that the Condition Report (CR) has not yet been written.

Notes: Only the RPS Actuation and System Actuation boxes are critical steps for the completion of the form.

See attached copy of completed Form PNPP No. 6912, Event Notification, in order to verify proper completion of the Form.

When Candidate identifies the need for Form PNPP No. 6912 and where he can obtain it, hand the Candidate a blank form.

The Candidate is only required to complete Form PNPP No. 6912 through the completion of the Description block.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_320SRO Rev 0 Terminating Cue: Form PNPP No. 6912, Event Notification, is properly filled out through the completion of the Description block.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-ADM_320SRO Rev 0

OT-3701-ADM_320SRO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

Plant shutdown for a refuel outage was in progress.

The shutdown schedule called for power to be reduced to 20%

and then a manual reactor scram was to be inserted.

Thirty minutes ago while shifting reactor feed pumps, a problem with Digital Feedwater Control System resulted in an excessive feed rate and rising RPV level.

The ATC inserted a manual reactor scram prior to reaching Level

8. Reactor power at the time of the scram was 30%.

Manual control of DFWCS was regained following the scram and plant conditions are now stable.

INITIATING CUE: As the Shift Manager, evaluate this event for reportability per PAP-1604, Reports Management.

This JPM is Time Critical

OT-3701-ADM_017SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: SRO Safety Function: Conduct Of Operations Setting: Classroom / Simulator Validated: 15 minutes

References:

SOI-F15 Rev. 16 Required Material SOI-F15 - Refueling And 360 Platforms Tasks: 234-521-04-02 Operate the Refueling Platform In Interlock Override 046-550-04-04 Respond to Alarms Associated With the Refuel Bridge and Fuel Handling Bridge Task Standard: Determine actions required for Refuel Bridge PLC failure with fuel suspended and identify the safe location for the fuel.

K/A Data: 2.1.36 Knowledge of procedures and limitations involved in core alterations.

Importance Rating: SRO 4.1 2.1.42 Knowledge of new and spent fuel movement procedures.

Importance Rating: SRO 3.4

1. Instructions: Ensure Required Material available at JPM site.

2. Location / Method: Simulator or Control Room / Administrative performance.

3. Initial Condition: Plant is in Mode 5 with refueling operations in progress. A new fuel bundle is being moved from IFTS to Reactor location 17-38. IFTS carriage is now located in the FHB. A Refuel Platform PLC failure occurs and the Refuel Platform has stopped in the Cattle Chute.

4. Initiating Cue: As the Refueling Supervisor, determine the following:

The actions required to move the Refuel Platform and whose authorization is required for the required actions, and Where can the New Fuel bundle be placed?

Start Time End Time Candidate

OT-3701-ADM_017SRO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 Determine the actions are required to move the Refuel Platform and authorization.

SOI-F15, Refueling And 360 Platforms 7.15 Operating The Refueling Platform In Interlock Override NOTE Except for testing, the Interlock Override Key Switch shall only be used in the event of a PLC failure to move the bridge and grappled components. The Interlock Override Key Switch shall only be used as directed by the Refueling Supervisor or Control Room Supervisor.

Critical Step: Operator determines that SOI-F15 Section 7.15 Operating The Refueling Platform In Interlock Override is appropriate. And the Refueling Supervisor or the Unit Supervisor must authorize override.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_017SRO Rev 0 Step 2 Determine where the new fuel bundle can be placed.

7.15 Operating The Refueling Platform In Interlock Override NOTE The following conditions of the Fuel or Core Components are defined as safe for the purposes of this instruction:

Properly seated in the reactor vessel (only if all refueling interlocks are available).

Properly seated in a designated storage location.

Properly seated in the IFTS carriage with the carriage at the AT CONTAINMENT position with the Upender inclined.

Properly seated in the IFTS carriage with the carriage at the AT FUEL BUILDING position with the Upender inclined.

Fuel bundles in the Fuel Preparation Machines to their full down position.

7.15.3 IF a fuel bundle OR any other core component is hoisted, THEN PLACE the hoisted component to a safe condition as directed by the Refueling Supervisor.

Critical Step: Operator determines that the fuel bundle must be properly seated in a designated storage location (RP-1)

Instructor Cue: None Notes: When the Operator has identified the correct SOI Section, authorization requirements, and proper storage location, terminate the JPM SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Operator determines that SOI-F15 section 7.15 has the steps to perform the movement and the Refueling Supervisor or Control Room Unit Supervisor can authorize the override and the bundle can be place in RP-1 or designated storage location.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-ADM_017SRO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

Plant is in Mode 5, refueling operations are in progress.

A new fuel bundle is being moved from IFTS to Reactor location 17-38.

IFTS carriage is now located in the FHB.

A Refuel Platform PLC failure occurs and the Refuel Platform has stopped in the Cattle Chute.

INITIATING CUE: As the Refueling Supervisor, determine the following:

The actions required to move the Refuel Platform and whose authorization is required for the required actions, and

Where can the New Fuel bundle be placed?

OT-3701-ADM_026_SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: P54, Fire Protection System - Water Time Critical: No Alternate Path: No Applicability: SRO only, RO/SRO Safety Function: Administrative Validated Time: 22 Minutes

References:

SOI-P54 (WTR) Rev 16, PAP-1910 Rev 27, & Dwg 914-001 Rev NN Required Material: SOI-P54 & Dwg 914-001 Task: 286-505-01-01 Analyze System Problems 286-506-03-01 Inform Unit Supervisor of Inoperable Fire Protection 343-684-03-02 Determine Required Actions for an Unplanned Fire Impairment / Barrier Removal When the P54 RSE is not Available Task Standard: Identify boundary for leaking fire protection system component and determine Required Actions for an Unplanned Fire Impairment.

K/A Data: 2.2.41 - Ability to obtain and interpret station electrical and mechanical drawings. Importance SRO 3.9 2.2.38 - Knowledge of conditions and limitations in the facility license.

lImportance SRO 4.5

1. Setup Instructions: None

2. Location / Method: Simulator / Classroom - Administrative Performance

3. Initial Condition: Reports from the field indicate that P54-F3554, Motor to Diesel Fire Pump Xconn Supply to Ring has a thru wall pipe rupture. The Unit Supervisor has ordered all Fire Pumps shutdown to secured status per SOI-P54 Water.

4. Initiating Cue: As the Unit Supervisor, determine:

1) How P54-F3554 can be isolated.

2) What Fire Protection Functional Specification(s) is the plant currently in per PAP-1910?

Start: Stop:

Candidate:

OT-3701-ADM_026_SRO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 Evaluate Leak Isolation, Drawing 914-0001-0000 Rev LL, Fire Service Yard Area Critical Step: Candidate obtains drawing and determines that closing P54-F3552 is necessary to isolate P54F3554.

Instructor Cue: When the Candidate determines the correct 914 drawing to use, then provide the drawing to the Candidate if required Notes: JPM Steps 1, 2, & 3 can be performed in any order.

P54-F3554 coordinates are F-4 and P54-F3552 coordinates are H-2.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_026_SRO Rev 0 Step 2 Evaluate Leak Isolation, Drawing 914-0001-0000 Rev LL, Fire Service Yard Area Critical Step: Candidate obtains drawing and determines that closing P54-F6371 is necessary to isolate P54F3554.

Instructor Cue: None Notes: JPM Steps 1, 2, & 3 can be performed in any order.

P54-F3554 coordinates are F-4 and P54-F6371 coordinates are C-3.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 Evaluate Leak Isolation, Drawing 914-0001-0000 Rev LL, Fire Service Yard Area Critical Step: Candidate obtains drawing and determines that closing P54-F3555 is necessary to isolate P54F3554.

Instructor Cue: None Notes: JPM Steps 1, 2, & 3 can be performed in any order.

P54-F3554 coordinates are F-4 and P54-F3555 coordinates are F-4.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_026_SRO Rev 0 Step 4 PAP-1910 Fire Protection Program , Section 3.A Fire Suppression Water Supply Determine Fire Protection Functional Specifications: Current Specification, prior to isolation and restoration:

Critical Step: Candidate determines that both fire pumps are not functional and determines Actions for Not Functional are:

D.2).a.(1) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to establish backup system or D.2)a.(2) Enter LCO 3.0.3.

Instructor Cue: Plant is in Mode 1 Notes: PAP 1910 page 67, with both pumps in secured status, pumps are not capable of auto starting, therefore, not functional.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_026_SRO Rev 0 Step 5 , Section 4.A Fire Mains and Headers Determine Fire Protection Functional Specifications: Current Specification, prior to isolation and restoration:

Standard: Candidate determines that Fire Mains and Headers are not functional and determines Actions for Not Functional are:

D.1).a. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months -Verify at least one functional flow path exists, or D.1).b. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months - Establish back up system fire suppression supply.

Instructor Cue: Fire Marshall is working on the necessary compensation for each individual system per the note on page 71.

Notes: PAP-1910, Fire Pump spec is more limiting.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: The valves needed to isolate the leak have been correctly identified and the correct Functional Specifications for the loss of Fire Suppression Equipment have been identified.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-ADM_026_SRO Rev 0 Answer Key Isolation valve Leaking valve Isolation valve Drawing 914-0001 Rev NN

OT-3701-ADM_026_SRO Rev 0 JPM CUE SHEET INITIAL CONDITIONS: Reports from the field indicate that P54-F3554, Motor to Diesel Fire Pump Xconn Supply to Ring has a thru wall pipe rupture. The Unit Supervisor has ordered all Fire Pumps shutdown to secured status per SOI-P54 Water.

INITIATING CUE: As the Unit Supervisor, determine:

1) How P54-F3554 can be isolated.

2) What Fire Protection Functional Specification(s) is the plant currently in per PAP-1910?

OT-3701-ADM_018SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Applicability: SRO only Safety Function: Radiation Control Validated Time: 15 Minutes

References:

HPI-B0003 Rev 27 Form 10136 Rev 7/26/01 Required Material: HPI-B0003, Processing of Personnel Dosimetry Form PNPP 10136, Emergency Dose Authorization Task: 344-511-05-03 Request and Authorize increased exposure limits for emergency responders during emergency events.

451-656-05-50 Discuss TSC or CR EC responsibilities for authorization plans personnel to receive dose in excess of 10CFR20 limits under emergency situations.

Task Standard: Determine if an Operator can perform an emergency evolution due to radiation levels and complete an Emergency Dose Authorization if evolution can be performed.

K/A: 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. Importance: SRO 3.7

OT-3701-ADM_018SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET Cont

1. Setup: Ensure Required Material available at JPM site.

2. Location / Method: Class Room / Administrative performance.

3. Initial Condition: The plant is in an Unusual Event due to lowering Spent Fuel Pool level.

No facilities are currently activated and Emergency Coordinator duties remain in the Control Room. While investigating a leak in the FPCC Heat Exchanger Room. An NLO (Roberts) became pinned against the east wall near the A HX when a scaffold supporting lead blankets collapsed. Due to the weight of the blankets he is unable to move, but is shielded. He has suffered potentially life threatening injuries. You must assign two operators to rescue NLO Roberts. RP Supervision informs you that travel path dose rates are 3 REM/hr to NLO Roberts and 60 REM/hr where NLO Roberts is located.

It is estimated that total travel time to and from NLO Roberts is 5 minutes (2&1/2 minutes each way) and it will take 30 minutes to move the blankets and rescue NLO Roberts.

The three operators available for this assignment are Bob Smith, Bill Johnson, and Ray Jones.

Bob Smith is 52 years old and has a life time dose of 7.2 Rem. Bob has a year to date dose of 20 mrem. Bob has not volunteered for this assignment.

Bill Johnson is 34 years old and has a life time dose of 16.5 Rem. Bill has a year to date dose of 200 mrem. Bill has volunteered for this assignment.

Ray Jones is 28 years old and has a life time dose of 700 mrem. Ray has a year to date dose of 100 mrem. Ray has volunteered for this assignment.

4. Initiating Cue: Assign two of these operators to rescue the NLO Roberts and complete and approve the Perry Emergency Dose Authorization form PNPP 10136.

Start: Stop:

Candidate:

OT-3701-ADM_018SRO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 Determine the radiation dose that will be received.

Critical Step: Determine dose to be received by the rescue operators.

Instructor Cue: None Notes: 3 REM/60 min*5 min=0.25 REM.

60 REM/60 min* 30 min =30 REM Total dose = 30.25 REM per rescuer SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2 Determine that the rescuers may receive greater than 25 REM for lifesaving if he is a volunteer.

Critical Step: Determines that Bill Johnson and Ray Jones will rescue the NLO Roberts.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_018SRO Rev 0 Step 3 Complete Emergency Dose Authorization (Form # - PNPP 10136)

Critical Step: Fill in NAME, CURRENT YEAR DOSE, LIFETIME DOSE, & LEVEL APPROVED on form PNPP 10136.

Approve the Emergency Dose Authorization Instructor Cue: If asked, Jones SSN is 555-55-5551 and Johnsons SSN is 555-55-5552 If asked, acting as Jones & Johnson, sign for Jones & Johnson.

Notes: Level approved needs to be 30.25 Rem.

No signatures are required in the REQUEST block, but if requested, sign as RP supervisor.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 Approve Emergency Dose Authorization (Form # - PNPP 10136) as Shift Manager acting as Emergency Coordinator.

Critical Step: Approve the Emergency Dose Authorization form PNPP 10136 in the APPROVAL Section Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Assigns Ray Jones & Bill Johnson to rescue the NLO ROBERTS and approve the Emergency Dose Authorization.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-ADM_018SRO Answer Key Rev 0 EMERGENCY DOSE AUTHORIZATION PNPP No. 10136 Rev. 7/26/01 HPI B-0003 INCREASE IS REQUIRED TO SUPPORT THE FOLLOWING EMERGENCY OPERATIONS:

Rescue NLO Roberts from FPCC HX Room Name SSN Current Lifetime Signature Level Year - All required to Required to exceed 5 rem Approved exceed 5 Facilities rem R Ray Jones 555-55-5551 100 700 () 30.25 E mRem mRem Rem Q Bill Johnson 555-55-5552 200 16.5 () 30.25 U mRem Rem Rem E

S T

OSC Support Supervisor/Operations Shift Manager:

N/A Print / Signature Date Health Physics Support Supervisor/Shift Health Physics Supervisor:

N/A Print / Signature Date LIMITS TEDE:

10CFR20 - 5 rem Services - 5 rem Valuable Property - 10 rem Large Pop. or Lifesaving - 25 rem*

If persons have volunteered to perform lifesaving activities or protect large populations and are fully aware of the risks involved the above dose limits may be exceeded. Doses should be limited to the lowest practicable.

Operations Shift Manager and Shift Health Physics Supervisor should submit Emergency Dose Authorizations prior to OSC activation.

TSC Operations Manager/Operations Shift Manager:

A P

P Print / Signature Date R

O Radiation Protection Coordinator/Supervision, RP:

V A

L Print / Signature Date Operations Shift Manager and Supervision, RP should approve Emergency Dose Authorizations prior to TSC activation.

OT-3701-ADM_018SRO Rev 0 JPM CUE SHEET INITIAL CONDITIONS: The plant is in an Unusual Event due to lowering Spent Fuel Pool level. No facilities are currently activated and Emergency Coordinator duties remain in the Control Room. While investigating a leak in the FPCC Heat Exchanger Room. An NLO (Roberts) became pinned against the east wall near the A HX when a scaffold supporting lead blankets collapsed. Due to the weight of the blankets he is unable to move, but is shielded. He has suffered potentially life threatening injuries. You must assign two operators to rescue NLO Roberts. RP Supervision informs you that travel path dose rates are 3 REM/hr to NLO Roberts and 60 REM/hr where NLO Roberts is located. It is estimated that total travel time to and from NLO Roberts is 5 minutes (2&1/2 minutes each way) and it will take 30 minutes to move the blankets and rescue NLO Roberts.

The three operators available for this assignment are Bob Smith, Bill Johnson, and Ray Jones.

Bob Smith is 52 years old and has a life time dose of 7.2 Rem. Bob has a year to date dose of 20 mrem. Bob has not volunteered for this assignment.

Bill Johnson is 34 years old and has a life time dose of 16.5 Rem. Bill has a year to date dose of 200 mrem. Bill has volunteered for this assignment.

Ray Jones is 28 years old and has a life time dose of 700 mrem. Ray has a year to date dose of 100 mrem. Ray has volunteered for this assignment.

INITIATING CUE: Assign two of these operators to rescue the NLO Roberts and complete and approve the Perry Emergency Dose Authorization form PNPP 10136.

OT-3701-ADM_018SRO Rev 0 EMERGENCY DOSE AUTHORIZATION PNPP No. 10136 Rev. 7/26/01 HPI B-0003 INCREASE IS REQUIRED TO SUPPORT THE FOLLOWING EMERGENCY OPERATIONS:

Name SSN Current Lifetime Signature Level Year - All required to Required to exceed 5 rem Approved exceed 5 Facilities rem R

E Q

U E

S T

OSC Support Supervisor/Operations Shift Manager:

Print / Signature Date Health Physics Support Supervisor/Shift Health Physics Supervisor:

Print / Signature Date LIMITS TEDE:

10CFR20 - 5 rem Services - 5 rem Valuable Property - 10 rem Large Pop. or Lifesaving - 25 rem*

If persons have volunteered to perform lifesaving activities or protect large populations and are fully aware of the risks involved the above dose limits may be exceeded. Doses should be limited to the lowest practicable.

Operations Shift Manager and Shift Health Physics Supervisor should submit Emergency Dose Authorizations prior to OSC activation.

TSC Operations Manager/Operations Shift Manager:

A P

P Print / Signature Date R

O Radiation Protection Coordinator/Supervision, RP:

V A

L Print / Signature Date Operations Shift Manager and Supervision, RP should approve Emergency Dose Authorizations prior to TSC activation.

NOTE: Normally, planned doses during an emergency should be controlled to within <10CFR20> limits. However, under emergency circumstances these limits may be waived by TSC Operations Manager along with the Radiation Protection Coordinator, or the Operations Shift Manager, acting as Emergency Coordinator, if the TSC is not activated, to allow personnel to perform valuable emergency actions. Due to the urgent nature of emergency dose requirements, completion of the Emergency Dose Authorization can be accomplished subsequent to receiving dose if situations warrant. The doses received should be voluntary and commensurate with the significance of the objective and held to the lowest practicable level that the emergency permits.

OT-3701-ADM_315SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: Yes Applicability: SRO Safety Function: Emergency Procedures / Plan Setting: Classroom / Simulator Validated: 15 minutes

References:

EPI-A1 Rev. 25, EPI-A2 Rev. 17, EPI-B1 Rev. 23, & EPI-B8 Rev. 14 Required Material EPI-A1 - Emergency Action Levels EPI-A2 - Emergency Actions Based On Event Classification EPI-B1 - Emergency Notification System EPI-B8, Protective Actions And Guides Tasks: 344-532-05-02 Prepare Emergency Plan Initial Notification Form Task Standard: Classify the emergency and complete Initial Notifications IAW appropriate E-plan procedures.

K/A Data: 295017 AK3.03 Implementation of site emergency plan.

Importance: SRO 4.5 295038 EK3.01 Implementation of site emergency plan.

Importance: SRO 4.5 2.4.41 Knowledge of the emergency action level thresholds and classifications. Importance: SRO 4.6

1. Setup Instructions: None

2. Location / Method: Simulator / Classroom

3. Initial Condition: The plant was operating at rated power. A Containment Isolation occurred due to high Aux Building Steam Tunnel Temperatures. A successful scram was initiated. Currently, RPV Water Level is (minus) -10 and stable. While verifying Isolations and Actuations, 1B21-F016 and 1B21-F019 were found open. Neither valve will shut from the control room. The Steam Tunnel Temperature is 198° F and stable.

4. Initiating Cue: As the Shift Manager, with the information provided, declare the Emergency Action Level and complete Initial Notifications and other required actions.

Task is Time Critical Start Time: End Time:

Name:

OT-3701-ADM_315SRO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 EPI-A1, Emergency Action Levels 5.1 Event Assessment and Event Classification 5.1 Classify the emergency as follows:

1. Using Initiating Condition Index (PNPP No. 8852, Attachment 1), identify the emergency by event category and determine the most appropriate Initiating Condition

2. Refer to Attachment 2 for the applicable Initiating Condition(s) to determine whether the criteria are met for the operating mode(s) listed.

3. Declare an emergency class when all the conditions listed in at least one EAL column have been met, and implement <EPI-A2>.

a. When several Initiating Conditions are met, declare the most severe emergency class.

OT-3701-ADM_315SRO Rev 0 FISSION PRODUCT BARRIER MATRIX REACTOR PRESSURE VESSEL LEVEL INSTRUCTIONS INITIATING CONDITIONS Entry into SAG-1, Primary Containment 1. For each of the three UNUSUAL EVENT LOSS Flooding.3 barriers, determine if AU3 Any loss or challenge to any LOSS or CRITERIA the Containment FUEL CLAD CHALLENGE criteria barrier.

BARRIER have been met. Modes: 1 2 3 RPV level is less RPV level CHALLENGE

2. Compare the barrier ALERT than 0 inches. 2 CANNOT be determined. LOSS(es) and AA1 Any loss or challenge to CRITERIA CHALLENGE(s) to Fuel Clad barrier.

the initiating Modes: 1 2 3 conditions listed, and make the appropriate AA2 Any loss or challenge to event declaration. the Reactor Coolant REACTOR PRESSURE System barrier.

VESSEL LEVEL Modes: 1 2 3 RPV level is less REACTOR COOLANT SYSTEM LOSS than 0 inches. 2 SITE AREA EMERGENCY AS2 Either a challenge or CRITERIA loss of both the Fuel Clad barrier AND Reactor Coolant BARRIER System barrier.

Modes: 1 2 3 CHALLENGE NOT APPLICABLE AS3 Challenge to either the Fuel Clad barrier OR CRITERIA Reactor Coolant System barrier, AND the loss of any additional barrier.

Modes: 1 2 3 CONTAINMENT ISOLATION GENERAL EMERGENCY AG1 Loss of two barriers, Containment penetration AND a loss or does NOT isolate on a challenge to the third valid closure signal. barrier.

LOSS Immediate Operator actions in the Modes: 1 2 3 Control Room are NOT successful CONTAINMENT CRITERIA in isolating affected penetration.

Pathway to the BARRIER environment exists via penetration.

CHALLENGE NOT APPLICABLE CRITERIA

OT-3701-ADM_315SRO Rev 0 Critical Step: Candidate determines: FC Barrier challenge on RPV level < 0 , RCS Barrier loss on RPV level < 0, and Containment Barrier loss on Containment Isolation occurred and classifies event as AG-1 (Loss of two barriers, AND a loss or challenge to the third barrier), 15 minutes to classify.

Instructor Cue: Notify the operator that time critical action starts after the first read of initial conditions and he is given initiating cue.

Notes: Based on conditions in Initiating Cue, AG-1 conditions are met.

Start Time ________ Classification Time __________

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2

4. Complete the EVENT CLASSIFICATION CHECKLIST (PNPP No. 7983A),

contained in <EPI-A2>.

Standard: Operator uses Event Classification Checklist to assist with required actions.

Instructor Cue: Give Operator E-Plan Packet, when he identifies where to obtain.

I&C has been contacted and is en route.

Notes: Checklist completed through line A.6.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_315SRO Rev 0 Step 3 EPI-A2, Emergency Actions Based On Event Classification - Event Classification Checklist Note: For a General Emergency, ensure that PAR is included using EPI-B8, Attachment 1 Par Decision Flow Chart

4. Complete an Initial Notification form (PNPP No. 7794) and forward to communicators within 10 minutes of decision to classify event Critical Step: Initial Notification Completed within 15 minutes of classification.

Block 3.a is checked for General Emergency AG-1. Blocks 5.a and 6.a are also checked.

Instructor Cue: If asked, the wind is from 182° Notes: Time Given to Communicator ________

The goal is to get the Initial Notification to the I&C Communicator within 10 minutes of classification.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4

6. Complete the Pager Messages form (PNPP No. 9100), approve, and forward to the SAS within 10 minutes of decision to classify event or revise PARs.

Standard: Pager Message completed, Scenario ID No. 4 Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_315SRO Rev 0 Step 5 EPI-B8, Protective Actions and Guides 5.1.3 Emergency Coordinator

1. DETERMINE if the appropriate method was used to determine the PAR using the PAR Decision Flow Chart (Attachment 1).

2. APPROVE PARs for the general public developed utilizing Attachment 1 and ensure that the State of Ohio, local counties, and the NRC are notified per <EPI-B1>.

IF a dose projection cannot be completed within 10 minutes of the declaration of the General Emergency, THEN use the PAR decision flowchart using the UNKNOWN decision path per Attachment 1.

Critical Step: Determine Subareas 1 and Lake to be evacuated.

Instructor Cue: If asked, the wind is from 182° If asked, a dose projection cannot be completed within 10 minutes.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Event Classified within 15 minutes and Initial Notification given to communicator 5 minutes prior to notification due time.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-ADM_315SRO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

The plant was operating at rated power.

A Containment Isolation occurred due to high Aux Building Steam Tunnel Temperatures.

A successful scram was initiated.

Currently, RPV Water Level is (minus) -10 and stable.

While verifying Isolations and Actuations, 1B21-F016 and 1B21-F019 were found open.

Neither valve will shut from the control room. The Steam Tunnel Temperature is 198° F and stable.

INITIATING CUE: As the Shift Manager, with the information provided, declare the emergency action level, complete initial notifications and other required actions.

Task is Time Critical

OT-3701-C11_513_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: C11 CRDH Time Critical: No Alternate Path: Yes Applicability: RO/SRO Safety Function: 1. Reactivity Control Validated Time: 17 Minutes

References:

SOI-C11(CRDH) Rev 21 & SOI-C11(RCIS) Rev 28 Required Material: SOI-C11(CRDH) & SOI-C11(RCIS)

Task: 214-510-01-01 Withdraw a Control Rod 214-519-04-01 Respond to an Inability to Move Control Rods Task Standard: Withdraw control rod using double clutching method of Alternate Control Methods Rod Initially at Position 00 per SOI-C11(RCIS)

K/A: 201003 - A2.01 Ability to (a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Stuck rod.

Importance: RO 3.4 SRO 3.6

1. Simulator Setup Instructions: Reset simulator to a reactor startup IC 94. Insert Schedule file JPM C11-513. Verify Schedule file JPM-C11-Del.sch and Event File JPM-C11-Del.evt auto load. Verify clean pull sheet (no asterisks).

2. Location / Method: Simulator / performance

3. Initial Condition: Start up is in progress after a reactor scram. Reactor Power is approximately 2%.. Beginning of Life pull sheets at Step 12. Unit Supervisor is operating per IOI-1 Cold Startup Section 4.6 Heat up to 940 psig. Drive water pressure is at 300 psid per SOI-C11(RCIS).

4. Initiating Cue: Unit Supervisor directs you to continue power ascension until reactor pressure is 940 psig.

Start Time End Time Operator

OT-3701-C11_513_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 Continue Power Ascension:

Operator obtains Beginning of Life pull sheets and verifies step and position.

Standard: Operator verifies step and position on Beginning of Life pull sheets.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_513_RO Rev 0 Step 2 SOI-C11(RCIS) 7.4 Notch Withdrawal for Single Rod or Gang NOTES

The REACTOR MODE SWITCH must be in STARTUP/STANDBY, REFUEL or RUN for individual rod motion or in STARTUP/STANDBY or RUN for Gang Rod motion.

The Rod Pattern Controller rod sequence constraints are enforced even when withdrawing a control rod under the One-Rod-Out interlock (i.e., with the REACTOR MODE SWITCH in REFUEL).

Rod or gang withdrawal is allowed if both the WITHDRAW BLOCK and WITHDRAW INHIBIT lights are off.

A red WITHDRAW BLOCK light in conjunction with a red WITHDRAW INHIBIT light indicates rod motion is disallowed by the RPC.

A WITHDRAW BLOCK light by itself indicates a rod block signal due to plant status or nuclear instrumentation not associated with RPC constraints.

7.4.1 BEFORE withdrawing control rods in Modes 2, 3, 4, and 5, VERIFY Attachment 2, Single Control Rod Withdrawal Checklist, is complete.

Standard: Verifies Attachment 2 complete if section 7.4 of SOI-C11 (RCIS) is referenced.

Instructor Cue: Inform operator Attachment 2 is complete.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_513_RO Rev 0 Step 3 NOTES

RAW DATA and alternating data mode (i.e., dual channel) should be selected when moving control rods.

Gang mode of rod withdrawal is not allowed with a rod drive transponder bypassed at the RGDC due to the possibility of the bypassed rod moving with the gang.

7.4.2 SELECT the single rod OR rod gang.

Critical Step: Operator selects correct rod.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_513_RO Rev 0 Step 4 7.4.3 MOMENTARILY DEPRESS WITHDRAW.

7.4.4 OBSERVE the following:

The IN light comes on momentarily AND goes off.

The OUT light comes on AND goes off after approximately 2 seconds.

The RDM indicates the new rod position(s).

The SETTLE light comes on for approximately 6 seconds AND goes off.

Expected changes occur in Nuclear Instrumentation.

IF in gang withdrawal, THEN the new position is displayed in the GANG POSITION subsection of the RDM AND the green STABLE status LED will be on.

Critical Step: Operator withdraws correct control rods Instructor Cue: None Notes: After Rod is off Zero if he depresses INSERT, JPM would be a failure.

Three rods in the gang will work correctly, the fourth rod, rod 26-51 is stuck.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_513_RO Rev 0 Step 5 NOTE Failure to achieve a green STABLE status LED is indicative of a gang misalignment condition AND will be indicated by the red MISALIGNED status LED.

7.4.5 IF the SETTLE light goes off before the RDM indicates the new rod position, THEN perform the following:

Standard: Step is N/A Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 6 7.4.6 In Modes 3, 4, OR 5 Standard: Step is N/A Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_513_RO Rev 0 Step 7 7.4.2 SELECT the single rod OR rod gang. (possible repeat of steps)

Critical Step: Operator selects correct rod 26-51 and attempts withdraw. Operator may attempt a couple of withdraws.

Instructor Cue: Use alternate controls Notes: Operator may select single rod 26-51 and attempt to withdraw. No Rod Movement, ROD at position 00.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 9 7.24 Alternate Control Methods Rod Initially at Position 00 NOTES

The upper limit of the normal drive water pressure band may be increased to 300 psid during the Start-Up following a Reactor Scram.

The following methods will be performed in the sequence listed until a successful notch-out is achieved.

7.24.1 IF NOT using a Control Rod Movement Sheet, THEN PERFORM the following:

Standard: Step 7.24.1 is N/A Instructor Cue: None Notes: Prior to double clutching simulator driver deletes stuck rod failure -

malfunction RD01R1455.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_513_RO Rev 0 Step 10 7.24.2 ATTEMPT to withdraw the rod by double clutching as follows:

7.24.2.a DEPRESS AND HOLD the IN TIMER SKIP for several seconds.

7.24.2.b VERIFY the FULL IN light is on in the rod status display.

7.24.2.c IMMEDIATELY OPERATE the CRD in Continuous Withdraw Mode.

Critical Step: Operator moves rod by double clutching. Operator withdraws control rod Instructor Cue: None Notes: Prior to double clutching simulator driver deletes stuck rod failure.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 11 NOTE The drive water header pressure control valve is paralleled with an inline relief valve. Manual adjustment of drive water pressure must be below the relief valve setting (approx. 550 psig).

7.24.3 IF the double-clutching method at the normal Drive Water pressure failed to move the rod, THEN ATTEMPT to move the rod using High Drive Water Pressure method as follows:

Standard: Step 7.24.3 is NA Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-C11_513_RO Rev 0 Step 12 7.24.4 IF moving the rod has NOT been successful, THEN PERFORM the following:

7.24.5 Rod withdrawal was NOT successful Drive water pressure is 500 psid THEN PERFORM the following:

7.24.6 IF moving control rods in accordance with Tech Spec 3.10.6, THEN RETURN Drive Water Pressure to normal as directed by the US/SS.

7.24.7 IF NOT moving control rods in accordance with Tech Spec 3.10.6, THEN RETURN Drive Water Pressure to normal WHEN any one of the following condition is met:

The rod is at the withdrawal limit

Rod movement is suspended

The US/SO determine the elevated pressure is no longer needed

Another Control Rod is to be selected Standard: 7.24.4, 7.24.5, 7.24.6, and 7.24.7 are N/A.

Instructor Cue: Terminate JPM Notes: Terminate JPM SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Rods that were attempted to be withdrawn are at withdraw limit.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-C11_513_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS: Start up is in progress after a reactor scram. Reactor Power is approximately 5%. Turbine warm up is in progress. Beginning of Life pull sheets at Step 26. Unit Supervisor is operating per IOI-1 Cold Startup Section 4.6 Heat up to 940 psig. Drive water pressure is at 300 psid per SOI-C11(RCIS).

INITIATING CUE: Unit Supervisor directs you to continue power ascension until reactor pressure is 940 psig.

OT-3701-E51_006 Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: E51, Reactor Core Isolation Cooling Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: 2 - Reactor Water Inventory Control Validated: 17 minutes

References:

EOP-SPI 6.6 Rev 0 Required Material EOP-SPI 6.6, RCIC Injection And Pressure Control Tasks: 217-565-04-01 Control RPV Level with RCIC Operating in the Injection Mode Task Standard: Lineup RCIC to control RPV level per EOP-SPI 6.6 K/A Data: 217000 K3.01 Knowledge of the effect that a loss or malfunction of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) will have on following: Reactor water level. Importance: RO 3.7 / SRO 3.7 A4.05 Ability to manually operate and/or monitor in the control room: Reactor water level. Importance: RO 4.1 / SRO 4.1

1. Setup Instructions:

Reset simulator to IC-95.

Place yellow switch caps on HPCS Pump and Injection valve.

2. Location / Method: Simulator / Perform

3. Initial Condition: The unit is scrammed and is operating IAW EOP-1A. HPCS is tagged out for maintenance. Feedwater has been lost. RPV level band is 150 to 219. RPV water level is lowering due to SRV operation.

4. Initiating Cue: The Unit Supervisor directs you restore and maintain RPV level IAW EOP-SPI 6.6, RCIC Injection and Pressure Control. An I&C tech is standby to assist you.

Start Time: End Time:

Candidate:

OT-3701-E51_006 Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 EOP-SPI 6.6, RCIC Injection and Pressure Control 1.0 IF the RCIC system is isolated OR an isolation may occur, THEN BYPASS isolations signals as follows::

1.1 AT H13-P629, Card File E21A-Z3-1, REMOVE trip unit RX PRESS.

E31-N685A 1.2 AT H13-P618, Card File E12A-Z6-1, REMOVE trip unit RX PRESS.

E31-N685B Standard: Candidate goes to H13-P629 & P618 to remove trip units Instructor Cue: After Candidate locates each trip unit, inform him that the I&C Tech will remove the trip unit.

The trip units E31-N685A & B are removed Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E51_006 Rev 0 Step 2 1.3 AT H13-P642, VERIFY the following keylock switches in BYPASS:

RCIC LD ISOLATION BYPASS. E31A-S2B

RHR LD ISOL BYPASS FOR RHR AND RCIC. E31A-S4B 1.4 AT H13-P632, VERIFY the following keylock switches in BYPASS:

RCIC LD ISOLATION BYPASS. E31A-S2A

RHR LD ISOL BYPASS FOR RHR AND RCIC. E31A-S4A Critical Step: Candidate places keylock switches in BYPASS Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 1.5 AT H13-P601, DEPRESS the following pushbuttons:

RCIC DIVISION 1 ISOLATION RESET E51A-S16

RCIC DIVISION 2 ISOLATION RESET E51A-S25 Critical Step: Candidate depresses isolation reset pushbuttons.

Instructor Cue: None Notes: Only S25 shows isolation SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E51_006 Rev 0 Step 4 1.6 AT H13-P601, VERIFY the following valves are OPEN:

1.6.1 RCIC ST SUPP WARMUP ISOL. E51-F076 1.6.2 RCIC ST SUPP INBD ISOL. E51-F063 1.6.3 RCIC ST SUPP OTBD ISOL. E51-F064 1.6.4 RCIC TURB EXHAUST SHUTOFF. E51-F068 Critical Step: Candidate opens E51-F076 & F063.

Instructor Cue: None Notes: Candidate verifies valves E51-F064 & F068 are open.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 2.0 AT H13-P629, Card File E21A-Z6-1, REMOVE the following trip units to defeat the RCIC High Suppression Pool Level suction transfer:

SUPR PL LVL. E51-N636A

SUPR PL LVL. E51-N636E Standard: Candidate goes to H13-P629 to remove trip units Instructor Cue: After Candidate locates each trip unit, inform him that the I&C Tech will remove the trip unit.

The trip units E51-N636A & B are removed Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E51_006 Rev 0 Step 6 3.0 IF RPV level will be below 130 inches (Level 2), THEN AT H13-P629, Card File E21A-Z2-1, REMOVE the following trip units to defeat the RCIC Automatic Initiation:

RX Level. 1B21-N692A

RX Level. 1B21-N692E Standard: Candidate goes to H13-P629 to remove trip units Instructor Cue: If asked, and RPV level not yet below L2, respond, RPV level is lowering The I&C Tech will remove the trip units.

The trip units E51-N636A & B are removed Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E51_006 Rev 0 Step 7 NOTE The control switch for RCIC PUMP SUPR PL SUCT ISOL, 1E51-F031, must be placed in CLOSE prior to RCIC PUMP CST SUCTION VALVE, 1E51-F010, reaching full open or the CST/Supr Pool suction interlock will cause RCIC PUMP CST SUCTION VALVE, 1E51-F010, to close automatically.

4.0 The CST is available RCIC PUMP SUPR PL SUCT ISOL, 1E51-F031 is OPEN THEN PLACE RCIC suction on the CST as follows:

4.1 TAKE RCIC PUMP CST SUCTION VALVE to OPEN. 1E51-F010 4.2 TAKE RCIC PUMP SUPR PL SUCT ISOL to CLOSE. 1E51-F031 Standard: Candidate observes RCIC suction on the CST.

Instructor Cue: None Notes: Step 4 is N/A SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 8 5.0 DEPRESS the RCIC INIT - MN & FDW TB TRIP - SEAL IN RESET pushbutton.

1E51A-S18 6.0 CONFIRM the RCIC INIT - MN & FDW TB TRIP - SEAL IN RESET white seal in light is OFF. 1E51A-S18 Standard: Candidate Depresses pushbutton and confirms white light off.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E51_006 Rev 0 Step 9 7.0 IF ESW PUMP A is available AND is NOT running, THEN TAKE ESW A PUMP control switch to START. 1P45-C001A 8.0 IF ECC PUMP A is available AND is NOT running, THEN TAKE ECC A PUMP control switch to START. 1P42-C001A Standard: Candidate verifies ESW and ECC pumps started.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 10 9.0 IF RCIC gland seal compressor is available, THEN VERIFY the RCIC gland seal compressor is running. E51-C004 Standard: Candidate starts gland seal compressor.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E51_006 Rev 0 Step 11 10.0 INITIATE an evacuation from the following:

Reactor Building Annulus.

Containment Building.

Standard: Candidate announces evacuation over PA.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 12 11.0 VERIFY the following:

RCIC SECOND TEST VALVE TO CST is OPEN. 1E51-F059

RCIC pump flow controller, in Auto set between 350 to 700 GPM. 1E51-R600

RCIC TURBINE TRIP THRT V LATCH is OPEN. 1E51-F510

RCIC TURBINE TRIP THRT V POSITION is OPEN. 1E51-F510 Critical Step: Candidate Opens 1E51-F059 and takes 1E51-F510 to close to latch the valve and opens 1E51-F510.

Instructor Cue: If asked, pressure band is 600-1000 paig.

Notes: Candidate verifies 1E51-R600 set at 350 to 700 GPM (not critical step).

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E51_006 Rev 0 Step 12 12.0 PERFORM Steps 13.0 and 14.0 as needed to maintain RPV Level and RPV pressure within directed bands.

Standard: Candidate verifies the above.

Instructor Cue: None Notes: Step 13.0 is not used now - using RCIC for level control. However, will need to use Step 13.0 when RPV level is in band to stop level rise.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 13 14.0 WHEN desired to operate RCIC in the Level Control Mode as follows, THEN PERFORM the following:

14.1 VERIFY RCIC STEAM SHUTOFF is OPEN. 1E51-F045 Critical Step: Candidate opens E51-F045.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E51_006 Rev 0 Step 14 14.2 IF the RCIC INJECTION VALVE is CLOSED, THEN THROTTLE the RCIC FIRST TEST VALVE TO CST UNTIL RCIC pump discharge pressure is 100 to 200 psig below RPV pressure. 1E51-F022 Critical Step: Candidate throttles open E51-F022.

Instructor Cue: None Notes: SOI-E51 P&L warns against operating RCIC on min flow.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 15 14.3 TAKE RCIC INJECTION VALVE to OPEN. 1E51-F013 Critical Step: Candidate opens E51-F013.

Instructor Cue: None Notes: Candidate needs to control RPV level in band of 150 to 219.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E51_006 Rev 0 Step 16 14.4 VERIFY RCIC FIRST TEST VALVE TO CST is CLOSED. 1E51-F022 14.5 MAINTAIN RCIC flow between 350 GPM and 700 GPM. 1E51-R600 Standard: Candidate closes E51-F022 and maintains RCIC flow in band.

Instructor Cue: None Notes: If level rise is slow and candidate controls level in band, terminate the JPM. Otherwise continue to JPM step 17 SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 17 13.0 WHEN desired to operate RCIC in the Pressure Control Mode as follows, then perform the following:

13.1 VERFIY RCIC INJECTION VALVE to CLOSED. 1E51-F013 13.2 VERIFY RCIC STEAM SHUTOFF is OPEN. 1E51-F045 13.3 MAINTAIN RCIC flow between 350 GPM and 700 GPM. 1E51-R600 13.4 THROTTLE RCIC FIRST TEST VALVE TO CST to maintain desired RPV pressure.

. 1E51-F022 Standard: Candidate closes E51-F022 and maintains RCIC flow in band.

Instructor Cue: None Notes: When level is stable and in band, terminate the JPM.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: RCIC is injecting into the RPV and controlling level in band.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-E51_006 Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

The unit is scrammed and is operating IAW EOP-1A. HPCS is tagged out for maintenance.

Feedwater has been lost.

RPV level band is 150 to 219.

RPV water level is lowering due to SRV operation.

INITIATING CUE: The Unit Supervisor directs you restore and maintain RPV level IAW EOP-SPI 6.6, RCIC Injection and Pressure Control. An I&C tech is standby to assist you.

OT-3701-B21_009 Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: B21, Main Steam Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: 3 - Reactor Pressure Control Validated Time: 15 minutes

References:

EOP-SPI 9.2 Rev 1 Required Material EOP-SPI 9.2, Opening MSIVs Tasks: 239-527-01-01 Open MSIV's from H13-P601 Task Standard: Reopen MSIVs to control RPV pressure per EOP-SPI 9.2 K/A Data: 239001 K3.08 Knowledge of the effect that a loss or malfunction of the Main And Reheat Steam System will have on following: Decay heat removal.

Importance: RO 3.4 / SRO 3.5 A2.03 Ability to (a) predict the impacts of the following on the Main And Reheat Steam System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

MSIV closure. Importance: RO 4.0 / SRO 4.2

1. Setup Instructions:

Reset simulator to IC-95.

Driver will need to control RPV pressure using SRVs until MSL drains are opened.

(control in 940 to 1000 psig band)

Do not go to RUN until SPDS falls through

2. Location / Method: Simulator / Perform

3. Initial Condition: The unit is scrammed and is operating IAW EOP-1A. MSIV's closed due to a Mode Switch malfunction which has been corrected.

4. Initiating Cue: The Unit Supervisor directs you reopen the MSIV's IAW EOP-SPI 9.2, Opening MSIV's.

Start Time: End Time:

Candidate:

Note: Run this JPM then E51-006 in sequence.

OT-3701-B21_009 Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 EOP-SPI 9.2, OPENING MSIV's 1.0 DEFEAT MSIV low RPV level isolation as follows:

AT H13-P694, VERIFY MSIV ISOL LO LEVEL BYPASS CH D keylock

switch in BYP. B21H-S76D

AT H13-P691, VERIFY MSIV ISOL LO LEVEL BYPASS CH A keylock

switch in BYP. B21H-S76A

AT H13-P692, VERIFY MSIV ISOL LO LEVEL BYPASS CH B keylock

switch in BYP. B21H-S76B

AT H13-P693, VERIFY MSIV ISOL LO LEVEL BYPASS CH C keylock

switch in BYP. B21H-S76C Critical Step: Candidate verifies (places) keylock switches in BYPASS Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-B21_009 Rev 0 Step 2 2.0 VERIFY the following control switches are in CLOSE:

MSL B OTBD MSIV. B21-F028B

MSL D OTBD MSIV. B21-F028D

MSL A OTBD MSIV. B21-F028A

MSL C OTBD MSIV. B21-F028C

MSL B INBD MSIV. B21-F022B

MSL D INBD MSIV. B21-F022D

MSL A INBD MSIV. B21-F022A

MSL C INBD MSIV. B21-F022C Critical Step: Candidate places MSIV control switches in CLOSE.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 3.0 AT Panel P680, VERIFY all Turbine Bypass Valves are CLOSED.

Standard: Candidate observes Turbine Bypass Valves are CLOSED.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-B21_009 Rev 0 Step 4 4.0 AT Panel P601, VERIFY the following drain valves are CLOSED:

MSL Low Point DRN Shutoff. 1B21-F015

Shutoff Vlv Before Seat Norm DRN. 1N22-F450

Shutoff Vlv Before Seat Warmup DRN. 1N22-F455

INBD MSIV Before Seat Normal Drain. 1B21-F033.

Critical Step: Candidate places drain valve control switches in CLOSE.

Instructor Cue: None Notes: N22-F455 already closed - not critical step.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 5.0 AT Panel P870, VERIFY MST To RFPT A & B Supply Valve is CLOSED.

1N11-F100 Critical Step: Candidate places 1N11-F100 valve control switches in CLOSE.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-B21_009 Rev 0 Step 6 6.0 IF Main Turb Stop Valves Before Seat DRN valves are OPEN, THEN AT 1N22-F340A Panel P870, 1N22-F340B LATCH controller 1N22-R235, Main Turb Stop Valves Before 1N22-F340C Seat DRN Valve controller as follows: 1N22-F340D 6.1 VERIFY Main Turb Stop Valves Before Seat DRN Valve 1N22-R235 controller at 100%.

6.2 WHEN controller Main Turb Stop Valves Before Seat DRN Valve 1N22-R235 has been at 100% for at least 10 seconds, THEN VERIFY Main Turb Stop Valves Before Seat DRN Valve controller at 0%.

6.3 IF 1N22-F340A-D are still open (controller does not latch), THEN 1N22-K032 AT 1H13-P866 Bay D, RELEASE latching relay by manually pulling Release tab, located on top right of relay.

Critical Step: Candidate performs steps 6.1 and 6.2 to close drain valves.

Instructor Cue: None Notes: Step 6.3 is N/A SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-B21_009 Rev 0 Step 7 7.0 WHEN the following alarms have cleared,

MSL ISOL MAIN STEAM LINE FLOW HIGH. (H13-P601-19A-A3)

MSL ISOL TURBINE AREA TEMP HIGH. (H13-P601-19A-B3)

MSL & RWCU ISOL STEAM TUNNEL TEMP HIGH. (H13-P601-19A-B4)

THEN DEPRESS the following pushbuttons:

MSL & NS4 INBD ISOL SEAL IN RESET. 1B21H-S33

MSL & NS4 OTBD ISOL SEAL IN RESET. 1B21H-S32 Critical Step: Candidate Depresses 1B21H-S33 and 1B21H-S32 to clear isolation signal.

Instructor Cue: None Notes: Alarm H13-P601-19A-A1 will clear.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 8 8.0 VERIFY the following valves are OPEN:

MSL DRN & MSIV BYP INBD ISOL. B21-F016

MSL DRN & MSIV BYP OTBD ISOL. B21-F019

MSIV BYP VLV For MST Line Warm Up. 1B21-F020

INBD MSIV Before Seat Warmup Drain. 1B21-F021 Critical Step: Candidate opens the above listed valves.

Instructor Cue: None Notes: When drain valves are opened, RPV pressure will start to lower. Pressure control on SRVs no longer required.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-B21_009 Rev 0 Step 9 9.0 Instrument Air is isolated to the Drywell NO known air leak is present in Containment NO known air leak is present in Drywell THEN RESTORE Instrument Air to Containment and Drywell as follows:

9.1 VERIFY INST AIR DRYWELL ISOL valve is OPEN. P52-F646 9.2 VERIFY INST AIR CNTMT ISOL valve is OPEN. P52-F200 Standard: Candidate verifies opens the air isolation valves.

Instructor Cue: If asked, there are no known air leaks in containment or drywell Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-B21_009 Rev 0 Step 10 10.0 SELECT an available MSL to OPEN. MSL B MSL D MSL A MSL C 11.0 PLACE the SELECTED MSL OTBD MSIV control switch in Auto, to B21-F028B open the outboard MSIV. B21-F028D B21-F028A B21-F028C 12.0 PLACE the SELECTED MSL INBD MSIV control switch in Auto, to B21-F022B open the outboard MSIV. B21-F022D B21-F022A B21-F022C Critical Step: Candidate selects and opens the isolation valves for one main steam line.

Instructor Cue: None Notes: Opening the first MSL causes an RPV level perturbation.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-B21_009 Rev 0 Step 11 14.0 VERIFY the following control switches are in AUTO:

MSL B OTBD MSIV. B21-F028B

MSL D OTBD MSIV. B21-F028D

MSL A OTBD MSIV. B21-F028A

MSL C OTBD MSIV. B21-F028C

MSL B INBD MSIV. B21-F022B

MSL D INBD MSIV. B21-F022D

MSL A INBD MSIV. B21-F022A

MSL C INBD MSIV. B21-F022C Standard: Candidate places control switches for remaining MSIVs in AUTO.

Instructor Cue: None Notes: Step 13 is N/A Terminate the JPM SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: MSIVs are open.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-B21_009 Rev 0 JPM CUE SHEET INITIAL CONDITIONS: The unit is scrammed and is operating IAW EOP-1A.

MSIV's closed due to a Mode Switch malfunction which has been corrected.

INITIATING CUE: The Unit Supervisor directs you reopen the MSIV's IAW EOP-SPI 9.2, Opening MSIV's.

OT-3701-E12_506_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: E12, Residual Heat Removal Time Critical: No Alternate Path: Yes Applicability: RO Safety Function: 1 - Reactivity Control Setting: Simulator Validated: 36 minutes

References:

SOI-E12 Rev. 57 & ONI-E12-2 Rev 29 Required Material SOI-E12 - Residual Heat Removal System Tasks: 205-535-01-01 Warmup and Initiate Shutdown Cooling from Standby Readiness Task Standard: Initiate SDC in Alternate Return Path mode prior to exceeding 200° F in vessel.

K/A Data: 205000 Ability to (a) predict the impacts of the following on the Shutdown Cooling System (RHR Shutdown Cooling Mode) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:: A2.06 SDC/RHR pump trips.

Importance RO 3.4 / SRO 3.5. A2.10 R Valve operation. Importance: RO 2.9 SRO 2.9 Ability to manually operate and/or monitor in the control room: A4.01 SDC/RHR pumps Importance RO 3.7 / SRO 3.7. A4.03 SDC/RHR discharge valves Importance RO 3.6 / SRO 3.5. A4.09 System flow. Importance RO 3.1 / SRO 3.1

OT-3701-E12_506_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET contd.

1. Simulator Setup Instructions: Reset simulator to IC 96 (RPV temperature ~ 120°F). Run schedule file JPM-E12-506 (malfunction mv06_1e12f0053a & remote Function RH07 for RHR B pump breaker control power loss). Maintain reactor vessel level between 250 and 260 using Low Flow Control for feedwater and G33 blowdown. Simulator driver to control vessel level. Verify Low Flow Control screen up on DFWCS. Provide marked-up copy of SOI-E12. Place simulator in run after reading Initial Conditions to Operator.

2. Location / Method: Simulator / performance

3. Initial Condition: The plant shutdown due to scram yesterday. Currently in Mode 4. and the Unit Supervisor is operating in IOI-12 Maintaining Cold Shutdown. RHR B was operating in Shutdown Cooling when the pump tripped. The Unit Supervisor has entered ONI-E12-2 Loss of Decay Heat Removal. No Reactor Recirculation pumps are in operation. Reactor temperature band is 110 to 120 degrees F. RPV temperature was 115 degrees F prior to trip. The RO shifting SDC loops became ill.

4. Initiating Cue: The Unit Supervisor directs you, the Reactor Operator, to continue shifting Shutdown Cooling loops from B to A using RHR A through the Normal Return Path. Section 4.7 Shutdown Cooling Startup for RHR A is complete through Step 4.7.14.

Monitor Reactor Temperature per IOI-12.

Start Time: End Time:

Operator:

OT-3701-E12_506_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 SOI-E12, RESIDUAL HEAT REMOVAL SYSTEM 2.0 Precautions And Limitations 2.2 Observe the following limitations during the operation of the RHR pumps:

Do not operate the RHR pump against a shutoff head for greater than 8 seconds.

2.6 Operation of the LPCI mode of RHR with injection flow to the vessel shall only be done in an accident condition, a plant emergency condition, or an approved test condition of short duration. ONI-E12-2, Loss of Decay Heat Removal, and IOI-11, Shutdown From Outside Control Room, direct the use of the LPCI injection lines as Alternate Shutdown Cooling flow paths. Use of this flow path is still subject to reportability (as described in PAP-1604) when used for Alternate Shutdown Cooling.

4.7 Shutdown Cooling Startup for RHR A(B)

Operator reviews place-kept copy of SOI-E12 including Precautions and Limitations and panel H13-P601.

Standard: The Operator reviews place-kept copy of SOI-E12 Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 2 4.7.15 Hold the Oncoming RJR HXS BYPASS VALVE in CLOSE for 59-62 seconds.

1E12-F048A Critical Step: The Operator closes 1E12F048A for 59-62 seconds.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 4.7.16 Hold the Oncoming RJR HXS OUTLET VALVE in CLOSE until closed.

1E12-F003A Critical Step: The Operator closes 1E12F003A.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 4 4.7.17 It is desired to establish the Normal 1E12- 1E12-Return Path F053A F053B RHR Upper Pool Cooling Isol is closed 1E12- 1E12-F037A F037B LPCI Injection Valve is closed 1E12- 1E12-F042A F042B THEN PERFORM the following:

4.7.17.a IF the Feedwater System is shutdown, THEN VERIFY the Oncoming RHR loop FDW HDR SHUTOFF is closed, to prevent flow to the feedwater system.

1B21-F065A 1B21-F065B Standard: The Operator observes that feedwater is not shutdown and the B21F065s are open.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 5 CAUTIONS

The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.

Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.

Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.

4.7.17.a INITIATE flow through the SHUTDOWN COOLING TO FDW SHUTOFF as follows: 1E12-F053A 1E12-F053B 4.7.17.b.1 PERFORM the following simultaneously:

HOLD the SHUTDOWN COOLING TO FDW SHUTOFF in OPEN, UNTIL open. 1E12-F053A

TAKE the RHR PUMP to START. 1E12-C002A 4.7.17.b.2 WITHIN 8 seconds, THROTTLE RHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.

Critical Step: The Operator starts to open 1E12F053A and starts RHR A pump.

Instructor Cue: After report of valve failure, if pump was started, direct operator to shutdown RHR A pump while deciding on a course of action.

Direct Operator to establish shutdown cooling, this is an emergency.

Notes: Operator may or may not start pump if he notices failure of 1E12-F053A.

1E12-F053A is failed closed and will lose indication simulating blown fuse. If Operator started pump, the Minimum Flow Valve was down-powered per step 4.7.10.c and the pump will not have minimum flow protection SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 6 4.7.18 It is desired to establish the Refuel 1E12- 1E12-Return Path F037A F037B Operator determines that this step is N/A.

Standard: This Step is N/A. The Operator cannot use Refuel Mode Path.

Instructor Cue: None Notes: Plant not in Mode 5, Vessel Head installed.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 7 CAUTION

Operation of the RHR Loop with Vessel Injection via the LPCI Injection Line has the potential to result in fatigue failure of incore instrument tubes and burnishing of fuel channels.

The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.

Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.

Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.

4.7.19 It is desired to establish the Alternate 1E12- 1E12-Return Path F042A F042B Normal Shutdown Cooling return path 1E12- 1E12-is unavailable F053A F053B Refuel Shutdown Cooling return path is 1E12- 1E12-unavailable F037A F037B THEN PERFORM the following:

4.7.19.a REFER TO Alternate Shutdown Cooling Data (Attachment 42) and TAKE Pre-Start Data.

Standard: The Operator requests/obtains Attachment 42.

Instructor Cue: This is an Emergency. Establish Shutdown Cooling. Another Reactor Operator has taken prestart data on Attachment 42.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 8 CAUTIONS

The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.

Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.

Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.

4.7.19.b INITIATE flow through the LPCI INJECTION VALVE as follows:

1E12-F042A 4.7.19.b.1 PERFORM the following simultaneously:

TAKE the LPCI INJECTION VALVE to OPEN. 1E12-F042A

TAKE the RHR PUMP to START. 1E12-C002A Critical Step: The Operator starts to open 1E12F042A and starts RHR A pump.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 9 4.7.19.b.2 WITHIN 8 seconds, THROTTLE RHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.

1E12- F048A 1E12-R603A 4.7.19.c JOG OPEN the RHR HXS BYPASS VALVE in 1000-2000 gpm increments, UNTIL RHR PUMP FLOW is 2575-7100 gpm.

1E12- F048A 1E12-R603A Critical Step: Within 8 seconds the Operator opens 1E12F048A until flow is > 2575 gpm then controls flow within directed band.

Instructor Cue: Flow band is 4000 to 5000 gpm.

Reactor coolant temperature band is 110 to 120 deg F Notes: Reactor coolant temperature should be between 140 and 150 degrees if Operator establishes flow with some urgency. If Operator delays and spends time reviewing the procedure, Reactor temperature could be as high as 180 degrees. Initial flow will be 3500 gpm. Temperature indication will be RHR out on SPDS or Point 5 on recorder with E12F003A closed.

If SPDS RPV Temperature Trend is displayed, RPV temp will initially rise once flow is established, then lower as cooling is established.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 10 4.7.19.d NOTIFY the following of the use of the Shutdown Cooling return flow to the Vessel via LPCI INJECTION VALVE so the required fuel inspection may be scheduled:

Reactor Engineering.

Outage Planning.

4.7.19.e INITIATE a special report to the NRC in accordance with PAP-1604.

4.7.19.f GO TO RHR Shutdown Cooling Operations for RHR A(B).

Standard: The Operator will proceed to Section 7.6, RHR Shutdown Cooling Operations for RHR A(B).

Instructor Cue: Steps 4.7.19.d & e are being performed by the Shift Manager.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 11 7.6 RHR Shutdown Cooling Operations for RHR A(B)

NOTES

Normal Design parameters for Shutdown Cooling/Test Mode operation:

- RHR Pump Flow 7000-7100 gpm.

- RHR Pump Amps95-110 Amps.

- RHR A Head Spray Flow 0 - 500 gpm.

- RHR Suction Pressure Less than 135 psig.

- RHR HX ESW Outlet Temps Less than 108oF.

- RHR Pump Suct Temp Less than 100oF (Refuel Mode).

- RHR HXS RHR Outlet Temp Less than 86oF (Refuel Mode).

The following actions can be performed in any logical order or repeated to support current plant conditions.

OT-3701-E12_506_RO Rev 0 Step 11 - Continued 7.6.1 OBSERVE the following limitations when in Shutdown Cooling:

MAINTAIN cooldown rate less than 100oF in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period.

DO NOT allow any RHR piping which has been inadvertently drained to be refilled with water from the Reactor Vessel.

MAINTAIN Vessel temperature below 190oF while in Shutdown Cooling.

WHEN using the alternate return path, THEN MONITOR the following additional items: 1E12-F042A

MAINTAIN RHR FLOW in the band 2575-7100 gpm.

1E12-F042A 1E12-F042B

MAINTAIN RHR H2O DISCH temperature greater than 65oF.

1E12-R601 Pt 5 (magenta) 1E12-R601 Pt 6 (orange)

Standard: The Operator establishes flow of 4000 to 5000 gpm.

Instructor Cue: Establish a cooldown to restore Reactor temperature to band of 135 to 145 deg F. Flow band is 4000 to 5000 gpm.

Notes: Reactor temperature will increase steadily if cooling is not established.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 12 7.6.2 PERFORM the following as needed to maintain desired cooldown rate AND RHR Pump flow 7000-7100 (alternate return path 2575-7100):

1E12-R603A 1E12-R603B:

THROTTLE RHR HXS OUTLET VALVE. 1E12-F003A

THROTTLE RHR HXS BYPASS VALVE. 1E12-F048A Critical Step: The Operator throttles opens 1E12F003A and 1E12F048A is throttled close to establish a cooldown.

Instructor Cue: Establish a cooldown to restore temperature within band of 135 to 145 degrees. Flow Band is 4000 to 5000 gpm.

Notes: Exceeding 200 degrees Reactor Water temperature would be a failure.

200 degrees is a MODE change.

Operator can establish full cooling and not have a problem with 100 degrees per hour.

Terminate JPM once satisfied with cooldown rate.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Shutdown Cooling Flow established through Alternate Return path, a cooldown rate has been established and Reactor Water Temperature is maintained less than 200 degrees.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-E12_506_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

The plant shutdown due to scram yesterday.

Currently in Mode 4. and the Unit Supervisor is operating in IOI-12 Maintaining Cold Shutdown.

RHR B was operating in Shutdown Cooling when the pump tripped.

The Unit Supervisor has entered ONI-E12-2 Loss of Decay Heat Removal.

No Reactor Recirculation pumps are in operation.

Reactor temperature band is 135 to 145 degrees F.

RPV temperature was 140 degrees F prior to trip.

The RO shifting SDC loops became ill.

INITIATING CUE:

The Unit Supervisor directs you, the Reactor Operator, to continue shifting Shutdown Cooling loops from B to A using RHR A through the Normal Return Path. Section 4.7

Shutdown Cooling Startup for RHR A is complete through Step 4.7.14.

Monitor Reactor Temperature per IOI-12.

OT-3701-R43_501 Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: R43, Division 1 And 2 Diesel Generator Time Critical: No Alternate Path: Yes Applicability: RO/SRO Safety Function: 6 - Electrical Setting: Simulator Validated: 28 minutes

References:

SOI-R43 Rev 42 Required Material: SOI-R43 - Division 1 And 2 Diesel Generator System Tasks: 264-506-01-01 Shutdown the SBDG to Standby Readiness (Remote)

Task Standard: Shutdown Div 2 DG to Standby Readiness from Control Room then place in PTL.

K/A Data: 264000 Ability to manually operate and/or monitor in the control room:

A4.04 Manual start, loading, and stopping of emergency generator: Plant-Specific. Importance RO 3.7 / SRO 3.7.

1. Simulator Setup Instructions: Reset Simulator to IC 94. - Insert Schedule file JPM-R43-501 and verify Event file JPM R43 auto loads.

2. Location / Method: Simulator / performance

3. Initial Condition: The Div 2 DG has completed a four-hour maintenance run. It has been disconnected from EH12 and is ready to be shutdown. PPO is standing by at the diesel to assist.

4. Initiating Cue: The Unit Supervisor directs you as the Reactor Operator to shutdown Div 2 DG to standby readiness in accordance with SOI-R43 section 6.1 Remote Shutdown to Standby Readiness.

Start Time: End Time:

Candidate:

OT-3701-R43_501 Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 SOI-R43 - Division 1 And 2 Diesel Generator System 6.1 Remote - Shutdown to Standby Readiness NOTES

If the voltage and speed are not adjusted on DG shutdown, the DG will need to be started and shutdown per this SOI to adjust speed and voltage prior to operability.

Emergency stop is accomplished by performing Emergency Shutdown.

6.1.1 IF diesel unloading was NOT within the unloading limits listed in the Precautions and Limitations THEN OPEN the Diesel Turbo Prelube Oil Valve.

1R47-F544B Standard: Step 6.1.1 is N/A The Operator may ask examiner for unloading rate.

Instructor Cue: If asked, the diesel unloading was within limits Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R43_501 Rev 0 Step 2 6.1.2 VERIFY the DIESEL GENERATOR in AUTO at 1H13-P877. Div 2 6.1.3 VERIFY the DIESEL GENERATOR CONTROL TRANSFER is in CONT RM at the Generator Control Panel. 1H51-P055B Standard: The Operator verifies DG is in AUTO at P877 and calls Plant Operator (PPO) to verify transfer switch in CONT RM at P055B.

Instructor Cue: Transfer switch in CONT RM at P055B Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 6.1.4 PERFORM the following at 1H13-P877:

6.1.4.a VERIFY the DIESEL GEN OUT OF SERVICE is in NORM. Div 2 6.1.4.b CONFIRM the DIESEL GEN BRKR green light is on EH1201 6.1.4.c IF the PREFERRED SOURCE BRKR is closed EH1212, THEN PLACE the SYNC SEL SWITCH in TH1.

Standard: The Operator verifies DG Out Of Service switch in NORM and confirms EH1201 green light on.

Instructor Cue: None Notes: Step 6.1.4.c is N/A SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R43_501 Rev 0 Step 4 6.1.4.d IF the ALTN PREFERRED SOURCE EH1213 BRKR is closed, THEN PLACE the SYNC SEL SWITCH in TH21.

6.1.4.e ADJUST the DIESEL GEN GOVERNOR so the SYNCHROSCOPE is moving slow in the FAST direction. 1R43-R032B 6.1.4.f PLACE the SYNC SEL SWITCH in OFF.

Critical Step: The Operator places Synch Select Switch in TH21 and adjusts governor so synchroscope is moving slow in Fast direction. Then places the SYNC SEL SWITCH in OFF.

Instructor Cue: None Notes: Speed is set so synchroscope is moving slow in the SLOW direction. Will need to raise diesel speed.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 6.1.4.g ADJUST the DIESEL GEN VOLTAGE RGLTR to read 4100 to 4200 Volts on DIESEL GEN A-B VOLTS. 1R43-R027B Critical Step: The Operator adjusts voltage regulator to obtain 4100 to 4200 volts on 1R43R027B.

Instructor Cue: None Notes: Voltage set @ 4000V - will need to adjust voltage up.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R43_501 Rev 0 Step 6 6.1.5 The DIESEL GENERATOR FIELD 1H51- 1H51-BREAKER CLOSED amber light is off at P055A P055B Generator Control Panel The bulb is good.

THEN PERFORM the following:

6.1.5.a INITIATE a Notification 6.1.5.b INFORM the Unit Supervisor.

Standard: The Operator Contacts PPO to confirm Amber light status.

Instructor Cue: PPO reports, Amber light on.

Notes: Steps 6.1.5.a & b are N/A.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R43_501 Rev 0 Step 7 NOTE The Diesel Generator is Inoperable for Manual starts for 2 - 3 minutes, until the Unit Avail Emergency Status light is illuminated.

6.1.6 RECORD appropriate Maintenance Rule status in Plant Narrative Log.

6.1.7 TAKE the DIESEL GENERATOR to STOP at 1H13-P877.

Critical Step: The Operator Stops Div 2 DG.

Instructor Cue: Another Operator will log Maintenance Rule status in Plant Narrative Log.

Notes: Step 6.1.6 is not critical.

Driver: Ensure Event 2 is activated upon shutdown.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 8 6.1.8 Observe the DIESEL GENERATOR FIELD BREAKER CLOSED light is de-energized.

Standard: The Operator Contacts PPO to confirm Amber light status.

Instructor Cue: PPO reports, Amber light off.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R43_501 Rev 0 Step 9 6.1.9 IF the DIESEL GENERATOR FIELD BREAKER CLOSED light is energized, THEN PERFORM the following:

Standard: Step 6.1.9 is N/A.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R43_501 Rev 0 Step 10 6.1.10 IF annunciator DG TRIP* PROTECT RELAY LOCKOUT (1H13-P877-1, E2) is in alarm, THEN PERFORM the following:

NOTE When operating the Diesel Generator control switch (from PULL-TO-LOCK to AUTO, or from AUTO to PULL-TO-LOCK), a deliberate pause in the STOP position is required in order to ensure proper operation of the associated circuitry.

6.1.10.a PLACE DIESEL GENERATOR in PULL-TO-LOCK 6.1.10.b PLACE the MODE SELECT keylock in INOP. 1H51-P054B Critical Step: The Operator places Div 2 DG in PULL-TO-LOCK and Directs NLO to place Mode Select switch in INOP.

Instructor Cue: Relay 86G and 86 G/1 are tripped.

When Event 3 is activated, keylock in INOP at 1H51P054B.

Notes: Driver: When directed to place the mode select keylock in INOP, activate Event 3.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R43_501 Rev 0 Step 11 6.1.10.c Refer to SVI-R10-T5227 and Perform actions for T.S. 3.8.1 Condition B.

6.1.10.d RECORD appropriate Maintenance Rule status in Plant Narrative Log 6.1.10.e INITIATE a Notification 6.1.10.f INFORM the Unit Supervisor.

Standard: The Operator notifies Unit Supervisor 86G is tripped and places DIESEL GEN OUT OF SERVICE switch to INOP.

Instructor Cue: Another Operator is performing Steps 6.1.10.c, d and e.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 12 6.1.11 IF annunciator DG TRIP DIFF RELAY LOCKOUT (1H13-P877-1, E4) is in alarm, THEN PERFORM the following:

6.1.12 IF Diesel Turbo Prelube Valve is open, THEN CLOSE the Diesel Turbo Prelube Valve. 1R47-F544B Standard: Steps 6.1.11 and 6.1.12 are N/A.

Instructor Cue: If asked for Step 6.1.12, Turbo Prelube Valve is closed.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R43_501 Rev 0 Step 13 6.1.13 WHEN the control system is reset, as evidenced by Unit Avail Emergency Status light illuminated approximately 2 minutes after shutdown, THEN PERFORM the following:

6.1.13.a CONFIRM that the following indicate approximately zero:

Gen Field Amps 1R43-R112B

Gen Field Volts 1R43-R113B Standard: Operator request PPO report above readings.

Instructor Cue: PPO reports, 1R43-R112B is 105 amps and 1R43-R113B is 40 vdc.

Notes: The Operator has same indications on P877, R43R020B and R43R021B of 105 Amps and 40 Volts.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 14 6.1.13.b IF the field is still energized, THEN PERFORM the following:

6.1.13.b.1 INFORM the Unit Supervisor.

6.1.13.b.2 OPEN the following disconnect for the offgoing generator:

GENERATOR (FIELD FLASH) CONTROL PNL, 1H51-P055B ED1B06 Disc 27 Critical Step: The Operator Directs the PPO to open Disc 27 at ED1B06.

Instructor Cue: Relay 86G and 86 G/1 are tripped.

When Event 4 is activated report, Disc 27 at ED1B06 at is open.

Notes: Driver: When directed to open Disc 27 at ED1B06, activate Event 4.

Terminate JPM when directed to open disc 27 at ED1B06.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R43_501 Rev 0 Terminating Cue: Division 2 DG is in Pull to Lock and ED1B06 Disc 27 is open.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-R43_501 Rev 0 JPM CUE SHEET INITIAL CONDITIONS: The Div 2 DG has completed a four-hour maintenance run. It has been disconnected from EH12 and is ready to be shutdown. PPO is standing by at the diesel to assist.

INITIATING CUE: The Unit Supervisor directs you as the Reactor Operator to shutdown Div 2 DG to standby readiness in accordance with SOI-R43 section 6.1 Remote Shutdown to Standby Readiness.

OT-3701-D17-001 Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: D17B Airborne Radiation Monitoring Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: 7 - Instrumentation Validated: xx Minutes

References:

SOI-D17B Rev. 14 Required Material: SOI-D17B, Airborne Radiation Monitoring System Process Tasks: 088-517-01-01 Assist Startup of Drywell Atmosphere Monitor 1D17-K670 Task Standard: Startup Drywell Atmosphere Monitor 1D17-K670 per SOI-D17B K/A Data: 272000 A1.01 Ability to predict and/or monitor changes in parameters associated with operating the RADIATION MONITORING SYSTEM controls including:

Lights, alarms, and indications associated with normal operations. Importance: RO 3.2 / SRO 3.2.

1. Setup Instructions: None

2. Location / Method: Control Room / Simulation

3. Initial Condition: Plant conditions are as is. The DW Radiation Monitor 1D17-K670 was shutdown to secured status for an RPS Bus transfer, which is now complete.

4. Initiating Cue: Unit Supervisor directs you the Reactor Operator to Startup the DW Radiation Monitor 1D17-K670 from secured status.

Start Time: End Time:

Candidate:

OT-3701-D17-001 Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc.

before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 SOI-D17B, Airborne Radiation Monitoring System Process 4.2 Drywell Atmosphere Monitor 1D17-K670, Startup From Secured Status 4.2.1 PERFORM the following in the Control Room (at 1H13-P804):

4.2.1.a VERIFY the FUNCTION switches on the Readout Modules are in the OPER position.

Gas Module 1D17-K676

Iodine Module 1D17-K677

Particulate Module 1D17-K678 Standard: Candidate identifies each module and verifies switches in OPER position Instructor Cue: Switches are as found.

Notes: Switches should already be in OPER.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-D17-001 Rev 0 Step 2 4.2.1.b MOMENTARILY DEPRESS the FAIL/RESET button for each of the following readout modules to reset any locked in rad monitor alarms:

Gas Module 1D17-K676

Iodine Module 1D17-K677

Particulate Module 1D17-K678 Standard: Candidate identifies FAIL/RESET pushbutton for each module and simulates depressing them.

Instructor Cue: None Notes: No alarms are present if RED and AMBER lights are off.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 NOTE This step will not apply power to the moving filter. Power is applied when it is turned on at the sample enclosure in a following step.

4.2.1.c PLACE the MOVING FILTER POWER SWITCH in ON. 1D17-K679 Critical Step: Candidate simulates placing the Moving Filter Power Switch to ON.

Instructor Cue: Initially: Moving Filter Power Switch is OFF After candidate turns switch, Moving Filter Power Switch is ON Notes: Moving Filter Power Switch is taken to OFF during shutdown.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-D17-001 Rev 0 Step 4 4.2.1.d VERIFY the PAPER CONTROL SWITCH is in NORM. 1D17-K679 Standard: Candidate identifies Paper Control Switch and verifies it is in NORM.

Instructor Cue: Switch is as found.

Notes: Switch should already be in NORM..

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 4.2.2 OPEN the following (at 1H13-P881):

DW RAD MON OTBD SUCT ISOL 1D17-F071A

DW RAD MON OTBD DISCH ISOL 1D17-F079A Critical Step: Candidate simulates opening the valves.

Instructor Cue: Initially: Valves are closed After candidate turns switch, Valves are open Notes: Valves are closed during shutdown.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-D17-001 Rev 0 Step 6 4.2.3 OPEN the following (at 1H13-P882):

DW RAD MON INBD SUCT ISOL 1D17-F071B

DW RAD MON INBD DISCH ISOL 1D17-F079B Critical Step: Candidate simulates opening the valves.

Instructor Cue: Initially: Valves are closed After candidate turns switch, Valves are open Notes: Valves are closed during shutdown.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 7 Candidate contacts Radiation Protection to perform steps 4.2.4 and 4.2.5.

Standard: Candidate contacts Radiation Protection to perform steps 4.2.4 and 4.2.5.

Instructor Cue: As RP Tech, I will perform SOI-D17B steps 4.2.4 and 4.2.5 for startup of DW rad monitor.

Report back after a moment, SOI-D17B steps 4.2.4 for startup of DW rad monitor are complete. Do you have any alarms?

Notes: Steps 4.2.4 and 4.2.5 are performed by Radiation Protection Personnel SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-D17-001 Rev 0 Step 8 4.2.6 PERFORM independent verification of required components.

Standard: Candidate identifies Independent verification is required.

Instructor Cue: RP Tech will provide IV.

Notes: Terminate the JPM SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: The Drywell Airborne rad monitor is started up from secured status.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-D17-001 Rev 0 JPM CUE SHEET INITIAL CONDITIONS: Plant conditions are as is. The DW Radiation Monitor 1D17-K670 was shutdown to secured status for an RPS Bus transfer, which is now complete.

Unit Supervisor directs you the Reactor Operator to Startup the DW Radiation Monitor 1D17-K670 from secured status.

INITIATING CUE: Unit Supervisor directs you the Reactor Operator to Startup the DW Radiation Monitor 1D17-K670 from secured status.

OT-3701-P41-001 Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: P41 - Service Water Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: 8 - Plant Service Systems Validated: 10 Minutes

References:

SOI-P40/41 Rev. 9 Required Material: SOI-P40/41, Service Water And Service Water Screen Wash Tasks: 276-505-02-01 Shift Service Water Pumps Task Standard: Shift Service Water Pumps from B to D per SOI-P40/41 K/A Data: 400000 A4.01 Ability to manually operate and / or monitor in the control room:

CCW indications and control. Importance: RO 3.1 / SRO 3.0.

1. Setup Instructions: Reset simulator to any IC. (IC-94 for ILO Exam) Verify SW pump B is running and SW pump D is in standby.

2. Location / Method: Simulator / Performance

3. Initial Condition: Plant conditions are as is.

4. Initiating Cue: Unit Supervisor directs you the Reactor Operator to perform the weekly Service water pump shift to equalize run time. Shift from SW Pump B to D running.

Start Time: End Time:

Candidate:

OT-3701-P41-001 Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc.

before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 SOI-P41, Service Water And Service Water Screen Wash 7.1 Shifting Service Water Pumps 7.1.1 START the oncoming Service Water Pump as follows:

7.1.1.1.a THROTTLE, as necessary, the SW 0P41- 0P41- 0P41- 0P41-Pump Lube Water Supply valve to F546A F546B F546C F546D maintain the oncoming Service Water 0P41- 0P41- 0P41- 0P41-Pump seal flow between 3 and 5 gpm. N150A N150B N150C N150D Standard: Candidate contacts NLO to perform step 7.1.2 Instructor Cue: SW Pump D seal water flow is 4.0 gpm.

If asked, all other SW pumps seal flows are also in band.

If asked, oil level is in band.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P41-001 Rev 0 Step 2 7.1.1.b TAKE the SW PUMP DISCH VLV to P41- P41- P41- P41-OPEN. F040A F040B F040C F040D 7.1.1.c WHEN the blue light comes on, THEN PRESS the STOP button.

7.1.1.d TAKE the SW PUMP to START. P41- P41- P41- P41-C001A C001B C001C C001D Critical Step: Candidate takes SW Pump D discharge valve to OPEN, presses the STOP button when the blue light comes on, then takes SW Pump D to start.

Instructor Cue: None Notes: Candidate should announce start of SW pump D over PA system SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 7.1.1.e WHEN the oncoming SW PUMP P41- P41- P41- P41-AMPS stabilize, F040A F040B F040C F040D THEN TAKE the oncoming SW PUMP DISCH VLV to OPEN.

Critical Step: Candidate takes SW Pump D discharge valve to OPEN.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P41-001 Rev 0 Step 4 CAUTION Operation of a Service Water Pump with its discharge valve at less than the minimum flow position (blue light) may result in pump damage.

7.1.2 SHUTDOWN the Offgoing Service Water Pump as follows:

7.1.2.a PERFORM the following steps concurrently:

7.1.2.a.1 TAKE the SW PUMP DISCH VLV to P41- P41- P41- P41-CLOSE. F040A F040B F040C F040D 7.1.2.a.2 WHEN either of the following occur,

The applicable blue light comes on

SW Pump Discharge valve P41- P41- P41- P41-indicates full closed F040A F040B F040C F040D THEN TAKE the SW PUMP to STOP. P41- P41- P41- P41-C001A C001B C001C C001D Critical Step: Candidate takes SW Pump B discharge valve to CLOSE and stops SW Pump B when blue light comes on or when Discharge Valve indicates full closed.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P41-001 Rev 0 Step 5 NOTE In the following step, 55-60 psig is the normal range for SW pump discharge pressure.

Discharge pressure outside of this range is permissible provided pressure is maintained between 46 and 64 psig.

7.1.2.b THROTTLE the NCC HX SW BYPASS VLV to achieve the desired operating pump discharge pressures. P41-F400 P41- P41- P41- P41-R051A R051B R051C R051D 7.1.2.c VERIFY the applicable SW PUMP P41- P41- P41- P41-DISCH VLV indicates CLOSED. F040A F040B F040C F040D 7.1.3 DIRECT Chemistry to place the Service Water Chlorination AND Dechlorination System in operation in accordance with SOI-P48/84B.

Standard: Candidate should not need to throttle P41-F400.

Candidate will close P41-F040B if not previously done.

Candidate calls Chemistry about chlorination.

Instructor Cue: None Notes: Terminate the JPM SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Service Water pumps have been shifted from B to D running.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-P41-001 Rev 0 JPM CUE SHEET INITIAL CONDITIONS: Plant conditions are as is.

INITIATING CUE: Unit Supervisor directs you the Reactor Operator to perform the weekly Service water pump shift to equalize run time. Shift from SW Pump B to D running.

OT-3701-M25_501 Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: M25/M26 Control Room Ventilation and Emergency Recirc System Time Critical: No Alternate Path: Yes Applicability: RO/SRO Safety Function: 9 - Radioactivity Release Validated Time: 12 Minutes

References:

SOI-M25/26 Rev. 22 & ARI-H13-P904-0001 Rev 10, Cyc-14 T/O EPY-M25-005 Required Material: SOI-M25/26, Control Room HVAC And Emergency Recirculating System Task: 037-531-01-01 Shift to (Manual) Emerg Rcirc from Smoke Clear or Norm 037-534-04-01 Operate System Using Individual Fan Control Switches Task Standard: Shift Control Room HVAC to Emergency Recirc using individual control switches.

K/A: 290003 - A2.03 Ability to (a) predict the impacts of the following on the CONTROL ROOM HVAC ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Initiation/reconfiguration failure. Importance: RO 3.4 SRO 3.6

1. Setup Instructions: Reset simulator to IC 95 Insert Schedule file JPM-M25-506.sch. Place a Yellow Switch Caps on M25 A Supply Fan and M26 A Emergency Recirc Fan.

2. Location / Method: Simulator / Performance

3. Initial Condition: Plant conditions are as is. CR HVAC Supply Fan A is tagged out to replace a broken belt. The Security Shift Supervisor reports that a tanker truck carrying anhydrous ammonia overturned on Parmly Rd. near the contractors gate and is leaking its contents. Lake County Hazmat has been called. The wind is blowing out of the south at 10 mph.

4. Initiating Cue: The Unit Supervisor directs you, the Reactor Operator, to shift Control Room Ventilation to Emergency Recirc.

Start Time: Stop Time:

Candidate:

OT-3701-M25_501 Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 SOI-M25/26, Control Room HVAC And Emergency Recirculating System 7.5 Shifting From NORM Or SMOKE CLEAR To EMERG RCIRC:

7.5.1 PLACE both of the following in EMERG RCIRC:

CONT RM HVAC TRAIN A MODE SELECT M25-S7

CONT RM HVAC TRAIN B MODE SELECT M25-S8 Critical Step: Operator places both switches in EMERG RCIRC.

Instructor Cue: None Notes: When M25-S8 taken to ER, the Return Fan will lose power causing a TRAIN TRIP. (Annunciator H13-P904-01-C6)

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-M25_501 Rev 0 Step 2 ARI-H13-P904-0001-C6 1.0 CAUSE OF ALARM 1.1 Loss of power to or low flow sensed on:

CONT RM HVAC RETURN FAN B, M25-C002B Standard: Operator reviews ARI and suggests course of action.

Instructor Cue: If Candidate does not suggest a course of action, ask what they recommend.

Remind him that toxic gas is moving toward the plant.

Notes: The Alarm Response Instruction is not helpful in this instance.

The Candidate should refer to the SOI and use Individual Control Switches to start B train in ER.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-M25_501 Rev 0 Step 3 SOI-M25/26, Control Room HVAC And Emergency Recirculating System 2.0 Precautions and Limitations 2.3 A train trip signal is generated by any of the following:

Loss of power to any of the respective trains fans

Loss of control power to any of the respective trains fans

Low flow on any running fan in the respective train Upon receipt of a train trip signal, all of the fans in the train will stop. An automatic Emergency Recirculation initiation signal bypasses the train trip signal and will start the appropriate fans. Any other operation of the fans with a train trip signal must be by individual control switches. Following a train trip, the trip signal may be reset by performance of the section Shifting Trains (Any Mode, Manual Initiation) to place the alternate train in operation and the tripped train in standby.

2.14 Fan operation using Individual Fan Control Switches defeats the train trip logic. Verification of system lineup and frequent monitoring of the system is required to preclude an adverse system condition.

7.13 Shifting Trains/Operating Modes While Operating Using Individual Fan Control Switches 7.13.1 REFER TO the appropriate section to shutdown the operating train to Standby Readiness Using Individual Fan Control Switches.

NOTE When possible, the startup should be in accordance with the normal startup methods which utilize the CONT RM HVAC TRAIN CONT switches.

7.13.2 IF the train can NOT be started in accordance with normal startup methods using CONT RM HVAC TRAIN CONT, THEN REFER TO the appropriate section and STARTUP the oncoming train Using Individual Fan Control Switches.

Critical Step: Operator reviews SOI and determines using Individual Fan Control Switches is required.

Instructor Cue: If asked, shutdown the B train to Standby Readiness Using Individual Fan Control Switches is not required since it tripped.

Notes: The Candidate can proceed to Section 7.12.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-M25_501 Rev 0 Step 4 7.12 Startup To EMERG RCIRC Using Individual Fan Controls 7.12.1 VERIFY both of the following in EMRG RCIRC:

CONT RM HVAC TRAIN A MODE SELECT M25-S7

CONT RM HVAC TRAIN B MODE SELECT M25-S8 Standard: Operator verifies both switches are in ER Instructor Cue: None Notes: The switches should have been previously placed in ER.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 5 7.12.2 PLACE the following fans in ON:

CONT RM HVAC SUPP FAN M25-C001B

CONT RM EMG RCIRC FAN M26-C001B Critical Step: Operator places both fans in ON.

Instructor Cue: None Notes: Starting M25-C001B allows M26-C001B to auto start. It is still required to place Control Switch for M26-C001B to Start.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-M25_501 Rev 0 Step 6 7.12.3 CONFIRM components are in the proper configuration in accordance with the appropriate attachment:

Train B in Operation and Train A Shutdown (Attachment 6)

Standard: Operator confirms component positions using Attachment 6.

Instructor Cue: None N0otes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 7 7.12.4 IF the train is being started due to an emergency condition, THEN TAKE the following to CLOSE:

CONT RM HVAC A INBD SUPP DMPR M25-F020B

CONT RM HVAC B INBD SUPP DMPR M25-F020A Standard: Candidate takes dampers to Close.

Instructor Cue: If asked, M24-F051A & B are both closed.

Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-M25_501 Rev 0 Step 8 NOTE Relative humidity of 70% is determined by an alarm on the computer points M26-BC003 or M26-BC004.

7.12.5 Control Room Control Room relative humidity relative humidity is 70% is unknown TAKE the CONT RM EMG RCIRC M26- M26-ELEC HTG CONT to START. D001A D001B Standard: Candidate checks humidity.

Instructor Cue: None Notes: Humidity should be < 70%

Terminate the JPM SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Terminating Cue: B Train of Control Room Ventilation is running in Emergency Recirc.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-M25_501 Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

Plant conditions are as is.

CR HVAC Supply Fan A is tagged out to replace a broken belt.

The Security Shift Supervisor reports that a tanker truck carrying anhydrous ammonia overturned on Parmly Rd. near the contractors gate and is leaking its contents.

Lake County Hazmat has been called.

The wind is blowing out of the south at 10 mph.

INITIATING CUE: The Unit Supervisor directs you, the Reactor Operator, to shift Control Room Ventilation to Emergency Recirc.

OT-3701-P54_502_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Fire Protection Time Critical: No Alternate path: Yes Applicability: RO/SRO Safety Function: 8 - Plant Service Systems Setting: Plant (Non-RRA)

Validated: 29 minutes

References:

SOI-P54 (WTR) Rev 16 Task Standard: Start the Motor Fire Service Pump per SOI-P54(WTR)

Task #: 286-566-05-04 Perform Motor Fire Pump Emergency Run 341-651-01-02 Maintain Fire Protection Systems Operable Required Material: SOI-P54 (WTR), Fire Protection System - Water Sections 4.2 & 7.4 K / A Data: 286000 A2.08 Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required Importance: RO 3.2 / SRO 3.3 A4.05 Ability to operate and/or monitor in the control room: Fire pump. Importance: RO 3.3 / SRO 3.3

1. Setup Instructions: JPM starts in Control Room, then moves to ESW pumphouse.

Provide SOI-P54(WTR), Section 7.4 after STEP 2, when asked.

2. Location / Method: Plant / Simulation

3. Initial Condition: The Plant entered ONI-P54 Fire, The Motor Fire Service pump failed to start at 120 psig and fire main pressure is lowering. The Diesel Fire pump is out of service.

4. Initiating Cue: The Unit Supervisor directs you as the Field Supervisor to start the Motor Fire Service Pump.

Start Time: End Time:

Candidate:

OT-3701-P54_502_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 SOI-P54(WTR), FIRE PROTECTION SYSTEM - WATER 4.2 Fire Service Pumps Manual Startup CAUTION Extended run time for the Motor Fire Service Pump or Diesel Fire Service Pump under a minimum flow condition can be detrimental to the component health and should be kept to a minimum.

NOTE The following pumps may be started individually or any order as desired.

4.2.2 IF starting the Motor Fire Service Pump, THEN PERFORM one of the following:

DEPRESS the MOTOR FIRE SERVICE PUMP START push-button on H13-P970. P54-C002

DEPRESS the Motor Fire Service Pump START push-button on H51-P102. P54-C002 Critical Step: Operator simulates depressing the start push button on H13-P970.

Instructor Cue: 1. SAS reports start of the Motor Fire Service Pump

2. SAS reports Motor Fire Pump no longer running

3. Both lights have extinguished for Motor Fire Service Pump.

4. Start Motor Fire Service Pump Notes: Wait 10 seconds betweens Cues 1 and 2 SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P54_502_RO Rev 0 Step 2 4.2.2 IF starting the Motor Fire Service Pump, THEN PERFORM one of the following:

DEPRESS the MOTOR FIRE SERVICE PUMP START push-button on H13-P970. P54-C002

DEPRESS the Motor Fire Service Pump START push-button on H51-P102. P54-C002 Standard: Operator simulates depressing the START push button on H51-P102.

Instructor Cue:

Motor Fire Service Pump failed to start.

Start Motor Fire Service Pump Notes: Operator may try a start from H51-P102 or go directly to Step 3 of JPM SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 7.4 Emergency Run of the Motor Fire Service Pump 7.4.1 DEPRESS AND TURN the EMERGENCY RUN push-button on H51-P102 to Start the Motor Fire Service Pump. P54-C002 Critical Step: Operator simulates depressing and turning the EMERGENCY RUN push button at H51-P102.

Instructor Cue: Motor Fire Service Pump starts Notes: JPM may be terminated at this point SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-P54_502_RO Rev 0 Step 4 Operator reports status of Motor Fire Service Pump Standard: Operator reports to the Unit Supervisor that the Motor Fire Service Pump is running.

Instructor Cue: None Notes: Terminate JPM SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: The Motor Fire Service Pump is operating per SOI-P54 section 7.4.

Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-P54_502_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS: The Plant entered ONI-P54 Fire, The Motor Fire Service pump failed to start at 120 psig and fire main pressure is lowering. The Diesel Fire pump is out of service.

INITIATING CUE: The Unit Supervisor directs you as the Field Supervisor to start the Motor Fire Service Pump.

OT-3701-T23_004_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: T23 - Containment Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: 5 - Containment Integrity Validated Time: 38 Minutes

References:

ONI-ZZZ-7 Rev 7 Required Material ONI-ZZZ Contingency Plans Task: 223-511-04-01 Perform Containment/Fuel Handling Building Closure in Accordance with ONI-ZZZ-7, Attachment 5 Task Standard: Perform Containment Building Closure in Accordance with ONI-ZZZ-7, Attachment 5 K/A: 290001 - A2.06 Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Auxiliary building isolation: BWR-6 Importance: RO 3.7 SRO 4.0

1. Simulator Setup Instructions: None

2. Location / Method: Plant / Simulation

3. Initial Condition: Plant is in Mode 4 at the start of a Refuel Outage. Due to equipment failures and plant conditions, the Shift Manager has entered ONI-ZZZ-7, Contingency Plans.

4. Initiating Cue: The Unit Supervisor directs you as an extra Reactor Operator to perform Steps 4.2 and 4.3 of Attachment 5 of ONI-ZZZ-7 Contingency Plans.

Start Time End Time Operator

OT-3701-T23_004_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 ONI-ZZZ Contingency Plans Attachment 5 - Containment/Fuel Handling Building Closure 4.2 Airlock Closure NOTE The following sequence of steps must be performed for each open containment air lock (i.e.,

both the upper and lower air lock must be closed).

4.2.1 CLEAR all lines in accordance with the directions on the Information Tags.

4.2.2 REMOVE any sheathing installed on the functional door OR its seals.

4.2.3 REMOVE any objects that interfere with closing the functional door.

4.2.4 CLOSE the functional air lock door.

4.2.5 WHEN the functional door has been closed THEN NOTIFY the control room.

Critical Step: Operator verifies all four containment airlock doors closed or simulates closing.

Instructor Cue: Door are as found. If necessary operator simulates above actions to close doors.

Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-T23_004_RO Rev 0 Step 2 4.3 Door Closure 4.3.1 VERIFY the following doors are closed:

IB318 interior access door at 620 IB J/07.

IB315 exterior access door at 620 IB C/10.

IB316 exterior access door at 620 IB N/10.

IB317 FHB rollup railroad door.

RB101 Unit 2 annulus access door at IB M/08.

IB319 interior access door at 620 IB G/07.

AX412 annulus access door at 620 AX E/08.

Critical Step: Operator simulates closing and verifies above doors closed.

Instructor Cue: Door are as found. Door closed.

Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 4 4.3.2 VERIFY the following floor hatches are in place:

Concrete floor plug at 620 IB G/08 (adjacent to Unit 1 equip hatch).

FPCC Surge Tank cover at 620 IB G/07.

Concrete floor plug at 620 IB J/08 (adjacent to Unit 2 equip hatch).

FPCC Surge Tank Cover at 620 IB J/07.

Critical Step Operator verifies the above floor hatches are in place.

Instructor Cue: As Found Notes: If floor hatch removed operator informs Unit Supervisor.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

OT-3701-T23_004_RO Rev 0 Step 5 4.3.3 VERIFY at least seven shield blocks are installed adjacent to the Unit 2 shield building.

Critical Step Operator verifies seven shield blocks are installed.

Instructor Cue: As found Notes: Terminate JPM when shield blocks are verified.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Terminating Cue: ONI-ZZZ-7 attachment 5 steps 4.2 and 4.3 complete Evaluation Results: SAT_____ UNSAT_____

End Time

OT-3701-T23_004_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS: Plant is in Mode 4 at the start of a Refuel Outage. Due to equipment failures and plant conditions, the Shift Manager has entered ONI-ZZZ-7, Contingency Plans.

INITIATING CUE: The Unit Supervisor directs you as an extra Reactor Operator to perform Steps 4.2 and 4.3 of Attachment 5 of ONI-ZZZ-7 Contingency Plans.

OT-3701-R10_303_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: R10 - Station Electrical Time Critical: Yes Alternate Path: No Applicability: RO/SRO Safety Function: 6 - Electrical Setting: Plant (Non-RRA)

Validated: 26 minutes

References:

ONI-SPI D-2 Rev 4 Tasks: 066-508-04-01 Respond to Loss of Off Site Power 262-554-04-01 Maintain System Availability 263-510-04-01 Remove Non-Essential DC Loads Task Standard: Extend battery life by shedding nonessential DC loads per ONI-SPI D-2 for Divisional buses.

Required Material: ONI-SPI D-2, Nonessential DC Loads & pictures of V-1-A K / A Data: 295003 AK2.01 Knowledge of the interrelations between partial or complete loss of A.C. POWER and the following: Station batteries.

RO 3.2 / SRO 3.3 AA1.04 Ability to operate and/or monitor the following as they apply to partial or complete loss of A.C. power: D.C. electrical distribution system. RO 3.6 / SRO 3.7

1. Setup Instructions: This JPM has a 3-hour Time Critical Limit as directed from ONI-R10.

2. Location / Method: Plant / Simulation

3. Initial Condition: A Station Blackout has occurred. The plant is operating IAW ONI-R10, Loss Of AC Power. Div 1 DG is damaged and will not be restored. Preparations are underway to restore Div 2 DG to service. Div 3 DG is carrying EH13 bus. Non-Divisional DC Loads are being removed per ONI-SPI D-2, by another Plant Operator.

4. Initiating Cue: The Unit Supervisor directs you, as a Plant Operator, to perform ONI-SPI D2, Non Essential DC Loads, and shed all non-essential loads for Divisional buses.

This JPM is Time Critical Start Time: End Time:

Candidate:

OT-3701-R10_303_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 ONI-SPI D-2, NONESSENTIAL DC LOADS NOTES One non-licensed operator should be assigned to perform the following actions.

A Radiation Protection Technician may be required to perform Steps 1.9 thru 1.13.

and Steps 2.6 thru 2.10.

Steps and sub-steps may be performed in any order.

1.0 Remove Nonessential DC Loads as follows:

NOTE Neutron Flux indication at panels 1H13-P669 and P671 is lost when DIV 1 ATWS UPS, 1R14-S012, is shutdown.

1.1 AT Distribution Panel ED1A06 (CC 638), VERIFY the following disconnects OPEN:

ECCS BENCHBOARD, 1H13-P601 Disc 1

DIV 1 RPS INST AND AUX RELAY PANEL, 1H13-P691 Disc 2

RRCS PANEL (CH A), 1C22-P001 Disc 14

RRCS PANEL (CH B), 1C22-P001 Disc 16

DIV 1 ATWS UPS, 1R14-S012 Disc 22

RCIRC PUMP BRKRS 3A & 3B CONTROL POWER Disc 26

OT-3701-R10_303_RO Rev 0 Critical Step: Operator simulates opening disconnects 1, 2, 14, 16, 22, and 26 at ED1A06 Instructor Cue: Disconnects are open Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2 1.2 IF it has been determined that the Div. 1 Diesel Generator CANNOT be made operational. THEN AT Distribution Panel ED1A06 (CC 638), VERIFY the following disconnects OPEN:

GENERATOR CONTROL PANEL, 1H51-P055A Disc 9

ENGINE (START) CONTROL PANEL, 1H51-P054A Disc 11

ENGINE (RDN START) CONTROL PANEL, H51-P054A Disc 12

GENERATOR (FIELD FLASH) CONTROL PANEL, 1H51-P055A Disc 28 Critical Step: Operator simulates opening disconnects 9, 11, 12, and 28 at ED1A06 Instructor Cue: Disconnects are open Notes: Initiating Cue gave Div 1 DG will not be restored.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R10_303_RO Rev 0 Step 3 NOTE The Maintenance and Calibration System (R52) can be used to augment the plant radios for communication.

1.3 AT 120V AC Vital Distribution Panel V-1-A (CC 638 Behind Unit 1 Computer Room), VERIFY the following disconnects OPEN:

ERIS DIGITAL INPUTS PANEL, 1H22-P110A-1 Disc 1

OSCILLOGRAPH/B.A.T PANEL, H13-P910 Disc 3

ANALOG LOOP A INSTRUMENT PANEL, 1H13-P865 Disc 9

ERIS POWER MONITOR INPUT Disc 11

STEAM BYPASS AND PRESSURE REGULATOR CABINET, 1H13-P637 Disc 14

MAINTENANCE AND CALIBRATION SYSTEM Disc 20 Standard: Operator determines Step 1.3 is N/A Instructor Cue: None Notes: Initial Conditions state that the Non-Divisional DC Loads are being removed by another Plant Operator. However, operator may choose to coordinate with other operator and perform this step.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R10_303_RO Rev 0 Step 4 1.4 AT Distribution Panel ED1B06 (CC 638), VERIFY the RCIRC PUMP BRKRS 4A & 4B CONTROL POWER disconnect OPEN. Disc 26 Critical Step: Operator simulates opening disconnect 26 at ED1B06 Instructor Cue: Disconnect is open Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 1.5 IF it has been determined that the Div. 2 Diesel Generator CANNOT be made operational THEN AT Distribution Panel ED1B06 (CC 638), VERIFY the following disconnects OPEN:

Standard: Step 1.5 is N/A.

Instructor Cue: None Notes: The Initiating Cue gave that Div 2 DG will be restored SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R10_303_RO Rev 0 Step 6 NOTE Neutron Flux indication at panels 1H13-P670 and P672 is lost when DIV 2 ATWS UPS, 1R14-S013, is shutdown.

1.6 AT Distribution Panel ED1B08 (CC 638), VERIFY the following disconnects OPEN:

ECCS BENCHBOARD, 1H13-P601 Disc 1

CH B RPS INST AND AUX RELAY PANEL, 1H13-P692 Disc 2

RRCS PANEL (CH A), 1C22-P002 Disc 14

RRCS PANEL (CH B), 1C22-P002 Disc 16

DIV 2 ATWS UPS, 1R14-S013 Disc 26 Critical Step: Operator simulates opening disconnects 1, 2, 14, 16, and 26 at ED1B08 Instructor Cue: Disconnects are open Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 7 1.7 AT Bus ED-1-C (DG 620 Inside 1E22-P002), VERIFY the ECCS BENCHBOARD, 1H13-P601 Brkr OPEN: 1CB17 Critical Step: Operator simulates opening breaker 1CB17.

Instructor Cue: Breaker is open Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-R10_303_RO Rev 0 Step 8 1.8 IF it has been determined that the Div. 3 Diesel Generator CANNOT be made operational THEN AT Bus ED-1-C (DG 620 Inside 1E22-P002), VERIFY the following Brkrs OPEN:

Standard: Step 1.8 is N/A.

Instructor Cue: None Notes: The Initiating Cue gave that Div 3 DG is running Terminate the JPM.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: DC Load shed complete for Divisional buses.

Evaluation Results: SAT_____ UNSAT_____

End Time:

OT-3701-R10_303_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

A Station Blackout has occurred.

The plant is operating IAW ONI-R10, Los of AC Power.

Div 1 DG is damaged and will not be restored.

Preparations are underway to restore Div 2 DG to service.

Div 3 DG is carrying EH13 bus.

Non-Divisional DC Loads are being removed per ONI-SPI D-2, by another Plant Operator.

INITIATING CUE: The Unit Supervisor directs you, as a Plant Operator, to perform ONI-SPI D2, Non Essential DC Loads, and shed all non-essential loads for Divisional buses.

OT-3701-R10_303_RO Rev 0

ML13179A088

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ML13179A088

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