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| {{#Wiki_filter:LaSalle County Station LICENSED OPERATOR EVALUATED SCENARIO GUIDE 19-1 NRC Exam Scenario 1 Rev. 00 | | {{#Wiki_filter:}} |
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| 19-1 NRC Exam Scenario 1 Revision 00 Facility: LaSalle County Generating Station Scenario #: 19-1 NRC Exam Scenario 1 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.
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| ==SUMMARY==
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| OF EVENTS
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| : 1. The crew with perform LOS-HP-Q1.
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| : 2. With HPCS running, the pump breaker will trip requiring the crew to place HPCS in a shutdown lineup and enter TS 3.5.1.
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| : 3. Gland seal steam PCV will fail requiring the crew to place main steam on gland sealing steam.
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| : 4. With a minor leak on 1B steam jet air ejector, the crew will lower power to recover backpressure.
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| : 5. An oil leak on 1A TDRFP will require the crew to trip the 1A TDRFP and verify operation of the MDRFP.
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| : 6. The 1B RR FCV will fail closed and the FCV lockup pushbutton will also fail. This will require the crew to take action per LOA-RR-101 and enter TS 3.4.1.
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| : 7. The SJAE leak will increase, requiring a manual scram.
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| : 8. A hydraulic ATWS will occur requiring the crew to enter LGA-010.
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| : 9. The crew will take action to initiate SBLC to combat the ATWS, the first SBLC pump discharge relief valve will fail open, requiring the crew to swap SBLC pumps.
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| Critical Tasks
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| : 1. After failure of ARI and with the reactor power still above 3%, inject boron using SBLC after determining the FIRST SBLC pump has failed, within 16 minutes.
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| : 2. With a reactor scram required and insufficient control rod worth inserted to maintain the reactor shutdown under all conditions without boron, inhibit ADS prior to ADS auto initiation to prevent an uncontrolled RPV depressurization, causing a significant power excursion.
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| : 3. During an ATWS with reactor power above 3%, rapidly lower RPV water level to at least -60 inches within 16 minutes and not to go below -150 inches as indicated on WR level indication.
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| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 2 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 TRAINING REQUESTS (if applicable)
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| : 1. None OPEX (if applicable)
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| : 1. None Operator Fundamentals
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| : 1. Monitoring plant indications and conditions closely
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| : 2. Controlling plant evolutions precisely
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| : 3. Operating the plant with a conservative bias
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| : 4. Working effectively as a team
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| : 5. Having a solid understanding of plant design, engineering principles, and sciences SOER 10-2
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| : 1. Supervisory oversight role
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| : 2. Recognition and mitigation of risk
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| : 3. Worker performance
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| : 4. Tolerance of repetitive/long standing issues and degradation of standards
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| : 5. Operating Experience Record of Revisions (Summary)
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| Rev. 0 Developed new for the ILT 19-1 NRC Exam SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 3 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 INITIAL SIMULATOR SETUP/ REQUIRED DOCUMENTATION
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| : 1. Recall a full power IC 151
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| : 2. Place simulator in RUN
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| : 3. Load and run the SmartScenario file NRC 19-1 Scenario 1.ssf
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| : 4. Have a marked-up copy of LOS-HP-Q1 up to step A.9.
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| : 5. Flag annunciators, 1H13-P601-A204, -A405, -A406
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| : 6. Load HPCS Motor Screen to PPC Overhead C.
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| : 7. VERIFY the Tech Spec Timeclock Sheet as follows:
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| TS/TRM/ODCM System/ Required REQUIRED ACTION Completion Expiration Component Action Description Time Date/Time FP/0B Diesel Restore equipment to 3.7.j A.1 7 days 6 days FP OPERABLE status
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| : 8. Perform the pre-scenario checklist (TQ-LA-150-0308)
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| SCENARIO OUTLINE (NRC Evaluations Only)
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| Event Malf. Event Event No. No. Type* Description 1 None N (BOP) Perform HPCS full flow test IAW LOS-HP-Q1 C (BOP) HPCS breaker overcurrent, secure HPCS IAW LOP-HP-04. SRO enters 2 MES033 T (SRO) TS 3.5.1 Condition B Lowering Gland Seal Steam Pressure; Manual recovery of Seal Steam 3 K5H03JC1 C (BOP)
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| Pressure Minor condenser leak on 1B Steam Jet Air Ejector, reduce reactor 4 MCN002 R (ATC) power IAW LGP-3-1 1A TDRFP lube oil leak; Start MDRFP and manually trip the 1A 5 R1041 C (ATC)
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| TDRFP C (ATC) 1B Recirc Pump FCV slowly drifting shut, lock 1B FCV. SRO 6 K2L12P1L T (SRO) evaluates TS 3.4.1 for applicability Condenser leak increases in size, requiring manual scram IAW LGP 7 MCN002 M (ALL) 2 MRD277 8 M (ALL) Hydraulic ATWS MRD278 Initiate second train of SBLC IAW LGA-SC-101, first train of SBLC fails 9 MSL001/2 C (ATC) on discharge relief valve stuck open
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| * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specification SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 4 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 APPROXIMATE SCENARIO RUN TIME 90 Minutes GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE)
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| During performance of tasks, dynamic learning activities, or formal evaluations, 769.00.01 demonstrate applicable Human Performance behaviors IAW the appropriate procedures.
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| Given an operating experience document, paraphrase the lessons learned and 762.04.00 methods to prevent recurrence at LaSalle Station, as described in the training material.
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| During performance of tasks, apply the administrative requirements of PROCEDURE 614.010 USE AND ADHERENCE EXPECTATIONS, IAW station procedures.
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| TASKS RO - ATC Provided initial conditions, Respond to a Reactor Recirc Flow Control System failure to minimum 23.003 demand, IAW station procedures.
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| 23.006 Provided initial conditions, respond to Reactor Recirc FCV Runback.
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| Given Unit Supervisor authorization, perform Control Room actions to respond to a RFP trip, IAW 77.045 station procedures.
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| Given Unit Supervisor authorization, respond to a Loss of Condenser Vacuum, IAW station 111.002 procedures.
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| 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 413.000 59.5 IAW LGA-001 Given entry in LGA-10, Failure to Scram, evaluate plant conditions and shutdown the reactor, IAW 431.000 station procedures.
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| Given entry in LGA-10, Failure to Scram, evaluate plant conditions and insert control rods, IAW 431.010 station procedures.
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| Given entry in LGA-010, Failure to Scram, evaluate plant conditions and perform SBLC injection, 431.020 IAW station procedures.
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| Given entry in LGA-10, Failure to Scram, and power level, evaluate plant conditions and maintain 433.000 RPV water level, IAW station procedures.
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| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 5 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 RO - BOP/ASSIST Given Unit Supervisor authorization, 0erform Control Room actions for HPCS System Inservice 61.009 test, IAW station procedures.
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| Given Unit Supervisor authorization, preform Control Room actions to transfer between Gland 71.035 Seal Steam supplies, IAW station procedures.
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| Given Unit Supervisor authorization, respond to a Loss of Condenser Vacuum, IAW station 111.002 procedures.
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| SRO - UNIT SUPERVISOR Provided initial conditions, Respond to a Reactor Recirc Flow Control System failure to minimum 23.003 demand, IAW station procedures.
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| 23.006 Provided initial conditions, respond to Reactor Recirc FCV Runback.
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| Given Unit Supervisor authorization, 0erform Control Room actions for HPCS System Inservice 61.009 test, IAW station procedures.
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| Given Unit Supervisor authorization, preform Control Room actions to transfer between Gland 71.035 Seal Steam supplies, IAW station procedures.
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| Given Unit Supervisor authorization, perform Control Room actions to respond to a RFP trip, IAW 77.045 station procedures.
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| 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures Given entry in LGA-10, Failure to Scram, evaluate plant conditions and shutdown the reactor, IAW 431.000 station procedures.
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| Given entry in LGA-10, Failure to Scram, evaluate plant conditions and insert control rods, IAW 431.010 station procedures.
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| Given entry in LGA-010, Failure to Scram, evaluate plant conditions and perform SBLC injection, 431.020 IAW station procedures.
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| Given entry in LGA-10, Failure to Scram, and power level, evaluate plant conditions and maintain 433.000 RPV water level, IAW station procedures.
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| Given a set of plant conditions, identify and prepare the Technical Specification required actions 201.011 IAW Tech Specs.
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| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 6 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 1
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| == Description:==
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| Perform HPCS full flow test IAW LOS-HP-Q1 Initiation: Following the crew assuming the shift Cues: Turnover Task/
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| Position EXPECTED OPERATOR RESPONSE Obj.
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| * Monitor plant parameters and update the crew as required ATC
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| * Provide peer checks as required Per LOS-HP-Q1
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| * At Control Room Panel 1H13-P601, START HPCS Pump 1E22-C001
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| * VERIFY 1E22-F012, HPCS Min Flow Vlv, OPENS 61.009 BOP
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| * THROTTLE OPEN 1E22-F023, HPCS Test to SP Vlv to establish a flow rate of 6300 gpm as indicated on 1E22-R603, HPCS Pmp Flow
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| * VERIFY 1E22-F012, HPCS Min Flow Vlv, CLOSES
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| * At Panel 1H13-P601, VERIFY 1B Diesel Gen Cooling Wtr Pmp, 1E22-C002 ON 61.009 US
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| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 7 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 1
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| == Description:==
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| Perform HPCS full flow test IAW LOS-HP-Q1 Simulator Operator Actions none Simulator Operator Role Play As the EO in the field when asked, report, HPCS water leg pump discharge pressure is 45 psig and stable (A.15.1)
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| As the EO in the field when asked, report, 1VY02C is ON. (A.17)
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| As the EO in the field when asked, report, 1PDI-VY008 indicates 2 inches of H2O (A.17)
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| As the EO in the field when asked, report, 1PDI-VY026 indicates 2 inches of H2O (A.17)
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| Respond as required.
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| Floor Instructor Notes/OPEX/TRs Terminus: When the HPCS is running at 6300 gpm and at the discretion of the Lead Evaluator.
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| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 8 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 2
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| == Description:==
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| HPCS breaker overcurrent Initiation: Following the completion of event 1 Cues:
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| Automatic Actions: HPCS Pump trips Expected Annunciator: 1H13-P601-A105, HPCS Pump BKR Trip Key Parameter Response: HPCS flow lowers to zero Task/
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| Position EXPECTED OPERATOR RESPONSE Obj.
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| * Monitor plant condtions and update the crew as required ATC
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| * Provide peer checks as required Per LOR-1H13-P601-A105
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| * Dispatch operator to switchgear MCC 143 and HPCS conrener room to determine cause of trip 61.009 BOP Per LOS-HP-Q1 or LOP-HP-04
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| * CLOSE 1E22-F023, HPCS Test to SP Vlv
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| * VERIFY 1E22-F012, HPCS Min Flow Vlv, CLOSES
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| * SHUTDOWN the HPCS Diesel Generator Cooling Water Pump 61.009
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| * Direct above actions 201.001 US
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| * Enter 3.5.1, condition B, RA B.1 and B.2 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 9 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 2
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| == Description:==
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| HPCS breaker overcurrent Simulator Operator Actions When directed by the Lead Release Event 2 Evaluator Simulator Operator Role Play As the EO in the field when asked, report, the HPCS pump breaker tripped on overcurrent.
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| Respond as required Floor Instructor Notes/OPEX/TRs NOTE: Ensure a verifiable action has been performed to shutdown the HPCS system before moving on.
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| Terminus: When the Tech Spec call has been made and per the Lead Evaluator.
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| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 10 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 3
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| == Description:==
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| Lowering Gland Seal Steam Pressure; Manual recovery of Seal Steam Pressure Initiation: Per Lead Evaluator Cues:
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| Automatic Actions: none Expected Annunciator: 1PM02J-A205, U1 Gland Steam Seal Header Pressure Low Key Parameter Response: lowering gland seal pressure Task/
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| Position EXPECTED OPERATOR RESPONSE Obj.
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| * Monitor plant condtions and update the crew as required ATC
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| * Provide peer checks as required
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| * Per LOR- 1PM02J-A205/ LOA-GS-101
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| * CHECK Gland Seal Steam Header Pressure is equal to or less than alarm setpoint
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| * CONTROL Gland Seal Steam Header Pressure at 3-6 psig (4 psig is preferred) using 1GS-S2, Gland Seal Steam Regulator Bypass Valve, at 1PM02J 71.035 BOP
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| * DISPATCH operator to EL. 768' in Turbine Building to INSPECT Gland Seal Steam Control Panel 1PL81J and Gland Seal Steam Evaporator Control Panel 1PA80J for proper operation
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| * REFER to procedure LOA-GS-101, Unit 1 Turbine Gland Seal Steam System Abnormal 71.035 US
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| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 11 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 3
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| == Description:==
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| Lowering Gland Seal Steam Pressure; Manual recovery of Seal Steam Pressure Simulator Operator Actions When directed by the Lead Release Event 3 Evaluator Simulator Operator Role Play As the EO sent to investigate the gland seal, report, the PCV has failed closed.
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| Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When gland seal steam is on the bypass and at the discretion of the Lead Evaluator.
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| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 12 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 4
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| == Description:==
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| Minor condenser leak on 1B Steam Jet Air Ejector Initiation: Per Lead Evaluator Cues:
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| Automatic Actions: none Expected Annunciator:
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| 1N62-P600-A504, SJAE Inter Condenser Pressure A/B High/Low 1N62-P600-B506, Off Gas Charcoal Adsorber Train Differential Pressure High 1N62-P600-B204, Off Gas Outlet Flow Abnormal Key Parameter Response: degrading condenser backpressure Task/
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| Position EXPECTED OPERATOR RESPONSE Obj.
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| Per LOA-OG-101
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| * REDUCE load as necessary per LGP-3-1, to maintain condenser vacuum below trip setpoint OR Per LOR-1N62-P600-B204
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| * If Main Condenser vacuum starts to decrease, refer to LOR-1PM03J-B511 for actions to control vacuum 111.002 ATC
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| * Per LOR-1PM03J-B511
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| * Monitor Condenser Vacuum Indication
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| * VERIFY SJAE are operating properly per LOP-OG-07, Startup of Off Gas System
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| * VERIFY Circulating Water System is operating properly per LOP-CW-03, Startup of Circulating Water System
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| * If Condenser Vacuum continues to decrease, REDUCE Reactor Power per LGP 1, as necessary, to a point at which Condenser Vacuum has stabilized. If vacuum cannot be stabilized and Turbine Trip is imminent, MANUALLY Scram reactor per LGP-3-2, Reactor Scram.
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| * Monitor plant parameters and update the crew as required BOP
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| * Provide peer checks as required
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| * Direct above actions 111.002 US
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| * Set manual scram criteria for condenser backpressure SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 13 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 4
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| == Description:==
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| Minor condenser leak on 1B Steam Jet Air Ejector Simulator Operator Actions When directed by the Lead Release Event 4 Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note: none Terminus: When sufficient reactor power has been reduced and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 14 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 5
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| == Description:==
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| 1A TDRFP lube oil leak Initiation: Per Lead Evaluator Cues:
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| Automatic Actions: none Expected Annunciator: 1PM03J-A104, Turbine Driven Reactor Feedwater Pump Bearing Oil Pressure Low (R1041)
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| Key Parameter Response: lowering TDRFP oil pressure Task/
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| Position EXPECTED OPERATOR RESPONSE Obj.
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| Per LOR-1PM03J-A104
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| * DETERMINE which Turbine Driven Reactor Feedwater Pump (TDRFP) has Low Bearing Oil Pressure
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| * If entire Turbine Oil System is failing, immediately REDUCE power per LGP-3-1 and/or LGP-2-1 to within capacity of MDRFP
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| * PLACE an idle Reactor Feedwater Pump in service per procedure LOP-FW-03, Startup of Motor Driven Reactor Feed Pumps (MDRFP), or LOP-FW-04, Startup of a Turbine Driven Reactor Feed Pump (TDRFP)
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| * SHUTDOWN affected TDRFP per procedure LOP-FW-05, Shutdown of Turbine Driven Reactor Feed Pump 77.035 23.006 ATC OR
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| * MANUALLY Trip 1A TDRFP and VERIFY proper operation on MDRFP Per LOA-RR-101 o If OPRM inop or in or near Regions 1 or 2, PERFORM Subsection B.1, Thermal Hydraulic Instability
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| * CHECK both 1A and 1B FCVs have Run-Back properly
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| * CHECK FCVs - none are Locked-Up o PRESS RAISE/LOWER pushbuttons to adjust Recirc flow to obtain balanced Recirc loop flow o At 1DS001, initiate TADS by DEPRESSING TDR icon
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| * Monitor plant parameters and update the crew as required BOP
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| * Provide peer checks as required 77.035 23.006 US
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| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 15 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 5
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| == Description:==
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| 1A TDRFP lube oil leak Simulator Operator Actions When directed by the Lead Release Event 5 Evaluator Simulator Operator Role Play If asked to investigate the 1A TDRFP as an EO, wait 3 minutes and report, the 1A TDRFP has oil spraying from it and I cant get close enough to isolate it.
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| Respond as required Floor Instructor Notes/OPEX/TRs Note: This event is intended for the ATC.
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| Terminus: The 1A TDRFP tripped and MDRFP running and at the discretion of the Lead Evaluator.
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| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 16 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 6
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| == Description:==
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| 1B Recirc Pump FCV slowly drifting shut Initiation: Per Lead Evaluator Cues:
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| Automatic Actions: None Expected Annunciator: None Key Parameter Response: Lowering Reactor Power and Flow Task/
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| Position EXPECTED OPERATOR RESPONSE Obj.
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| Per LOA-RR-101
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| * CHECK FCV position STABLE.
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| * Lock up FCV o PRESS 1B HPU TRIP pushbutton o Lockup solenoid valve at 1DS001 23.003 ATC o Stop HPU Pump at 1DS001
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| * CHECK recirculation loop jet pump flows -LESS THAN TECH SPEC MISMATCH
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| * At 1DS001, initiate TADS by DEPRESSING TDR icon
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| * Within 1 hour restoer flow mismatch
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| * EVALUATE core performance
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| * Monitor plant parameters and update the crew as required BOP
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| * Provide peer checks as required 23.003
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| * Direct above actions 201.011 US
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| * Enter Tech Spec 3.4.1, condition B, RA B.1 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 17 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 6
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| == Description:==
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| 1B Recirc Pump FCV slowly drifting shut Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note:
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| TECH SPEC MISMATCH.
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| * Within 5.425 Mlb/hr as read from 1B21-R611A/B, if core flow is greater than or equal to 75.95 Mlbm/hr.
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| * Within 10.85 Mlb/hr as read from 1B21-R611A/B, if core flow is less than 75.95 Mlbm/hr.
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| Terminus: Following Tech Spec Call and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 18 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 7
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| == Description:==
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| Condenser leak increases in size, requiring manual scram IAW LGP-3-2 Initiation: Per Lead Evaluator Cues:
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| Automatic Actions: None Expected Annunciator: 1PM03J-B511, Condenser Vacuum Low Key Parameter Response: Degrading Condenser Backpressure Task/
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| Position EXPECTED OPERATOR RESPONSE Obj.
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| Per LOR-1PM03J-B511
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| * Monitor Condenser Vacuum Indication
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| * If Condenser Vacuum continues to decrease, REDUCE Reactor Power per LGP 1, as necessary, to a point at which Condenser Vacuum has stabilized. If vacuum cannot be stabilized and Turbine Trip is imminent, MANUALLY Scram reactor per LGP-3-2, Reactor Scram.
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| 111.002 ATC Performs Reactor Scram and LGP 3-2 on US direction.
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| * ARM and DEPRESS Scram Pushbuttons
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| * PLACE Reactor Mode Switch in SHUTDOWN
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| * INSERT IRMs and SRMs
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| * CHECK Control Rods INSERTED and Power Decreasing
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| * INFORM Unit Supervisor of Control Rod Status and Reactor Power
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| * Recognize that all rods did not insert and notify US (Hydraulic ATWS)
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| Per LOR-1PM03J-B511 BOP
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| * Monitor Condenser Vacuum Indication
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| * Direct above actions 111.002 US
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| * Set manual scram criteria for condenser backpressure SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 19 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 7
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| == Description:==
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| Condenser leak increases in size, requiring manual scram IAW LGP-3-2 Simulator Operator Actions When directed by the Lead Release Event 7 Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 20 of 26
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| 19-1 NRC Exam Scenario 1 Revision 00 Event - 8
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| == Description:==
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| Hydraulic ATWS Initiation: Continued Cues:
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| Automatic Actions: none Expected Annunciator: Multiple Key Parameter Response: Reactor power NOT zero and multiple rods NOT full in Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Per the POWER Leg of LGA-010
| |
| * If control rods remain out:
| |
| * Initiate ARI
| |
| * If power is above 3%, initiate SBLC (CT)
| |
| * Insert Control rods per LGA-NB-01
| |
| * Method 3 Single Rod Insert 304.010
| |
| * Bypass RWM 431.000
| |
| * Place CRD Drive Flow Trip Circuit in BYPASS 431.010 ATC
| |
| * Insert control rods using Continuous Insert or Insert Button 431.020 Per the Level Leg of LGA-010 433.000
| |
| * If reactor power > 3% or unknown then Rapidly LOWER Level to at least -60 inches (minimizes Feedwater injection) (CT) and use only preferred systems to hold level between -100 and -60 inches. (CT)
| |
| * RUNBACK Reactor Recirculation flow to minimum
| |
| * If power is >3% then TRIP RR Pumps
| |
| * Method 4 Reset Scram/Drain SDV/Re-Scram
| |
| * Reset Scram/Drain SDV/Re-Scram Per LGA-010
| |
| * Inhibit ADS (CT)
| |
| * Prevent injection from HPCS, LPCS and LPCI BOP Per the PRESSURE Leg
| |
| * STABILIZE pressure <1059 psig using main turbine bypass valves
| |
| * VERIFY required automatic actions occur
| |
| * Directs Inhibit ADS (CT) 304.010
| |
| * Directs rapidly lowering vessel level to -60.(CT) 431.000
| |
| * Directs controlling level -100 to -60.(CT) 431.010 US
| |
| * Directs start of SBLC and/or insert control rods.(CT) 431.020
| |
| * Directs method of control rod insertion per LGA-NB-01 433.000 o May direct Method 3 for Single Rod Insertion o May direct Method 4 Reset Scram/Drain SDV/Re-Scram SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 21 of 26
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| | |
| 19-1 NRC Exam Scenario 1 Revision 00 Event - 8
| |
| | |
| == Description:==
| |
| Hydraulic ATWS Simulator Operator Actions When directed by the Lead Release LGA jumpers and keys Evaluator Simulator Operator Role Play When each LGA action is complete, report the completion to the crew.
| |
| Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 22 of 26
| |
| | |
| 19-1 NRC Exam Scenario 1 Revision 00 Event - 9
| |
| | |
| == Description:==
| |
| Initiate second train of SBLC IAW LGA-SC-101, first train of SBLC fails on discharge relief valve stuck open Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: None Expected Annunciator: None Key Parameter Response: SBLC pump discharge pressure less than reactor pressure Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Determine the first SBLC Pump has failed
| |
| * Start the standby SBLC Pump (CT)
| |
| * Update the crew 431.020 ATC Per LGA-NB-01
| |
| * Reset the scram o When SDV is drained, depress RPS scram pushbuttons
| |
| * Monitor plant parameters and update the crew as required BOP
| |
| * Provide peer checks as required
| |
| * Direct above actions 431.020 US
| |
| * Directs starting standby SBLC Pump (CT)
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 23 of 26
| |
| | |
| 19-1 NRC Exam Scenario 1 Revision 00 Event - 9
| |
| | |
| == Description:==
| |
| Initiate second train of SBLC IAW LGA-SC-101, first train of SBLC fails on discharge relief valve stuck open Simulator Operator Actions When directed by the Lead Release Event 9 Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When RPS has been reset and at the discretion of the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 24 of 26
| |
| | |
| 19-1 NRC Exam Scenario 1 Revision 00 REFERENCES Procedure Rev Title
| |
| : 1. INPO 15-004 Operations Fundamentals
| |
| : 2. SOER 10-2 Engaged, Thinking Organizations
| |
| : 3. LOR-1H13-P601- 3 HPCS Pump BKR Trip A105
| |
| : 4. LOR-1PM02J-A205 3 U1 Gland Steam Seal Header Pressure Low
| |
| : 5. LOR-1PM03J-B511 6 Condenser Vacuum Low
| |
| : 6. LOR-1PM03J-A104 1 Turbine Driven Reactor Feedwater Pump Bearing Oil Pressure Low
| |
| : 7. LOR-1N62-P600- 2 SJAE Inter Condenser Pressure A/B High/Low A504
| |
| : 8. LOR-1N62-P600- 1 Off Gas Charcoal Adsorber Train Differential Pressure High B506
| |
| : 9. LOR-1N62-P600- 9 Off Gas Outlet Flow Abnormal B204
| |
| : 10. LOA-GS-101 8 Gland Seal Steam System Abnormal
| |
| : 11. LOA-RR-101 43 Reactor Recirc System Trouble
| |
| : 12. LOA-OG-101 25 Off Gas System Abnormal
| |
| : 13. LOS-HP-Q1 76 HPCS Inservice Test
| |
| : 14. LOP-FW-05 Shutdown of Turbine Driven Reactor Feedwater Pump
| |
| : 15. LOP-HP-04 13 Shutdown of the High Pressure Core Spray System after an automatic initiation
| |
| : 16. LOP-RR-07 Operation of the Reactor Recirc Flow Control System
| |
| : 17. LGP-3-2 75 Reactor Scram
| |
| : 18. LGP-3-1 70 Power Changes
| |
| : 19. LGA-001 18A RPV Control
| |
| : 20. LGA-010 18 Failure to Scram
| |
| : 21. LGA-NB-01 19 Alternate Rod Insertion
| |
| : 22. LGA-MS-101 4 Using the Main Condenser as a Heat Sink during an ATWS
| |
| : 23. LGA-RH-101 5 Alternate Vessel Injection using Shutdown Cooling return
| |
| : 24. OP-LA-101-111-1002 81 LaSalle Operations Philosophy Handbook.
| |
| : 25. OP-LA-103-102-1002 21 Strategies for Successful Transient Mitigation SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 25 of 26
| |
| | |
| 19-1 NRC Exam Scenario 1 Revision 00 U1 SUPERVISOR TURNOVER Shift: Days Date: Today Mode: 1 OLR: Green Work Week: Div 3 Unit 1 power level Unit 2 power level
| |
| * 100 % Power
| |
| * 100 % Power U1 Thermal Limit Issues /Power Evolutions U2 Thermal Limit Issues /Power Evolutions
| |
| * None
| |
| * None Existing LCOs, date of next surveillance Existing LCOs, date of next surveillance
| |
| * TRM 3.7.j Required Action A.1
| |
| * None LOSs in progress or major maintenance LOSs in progress or major maintenance
| |
| * LOS-HP-Q1
| |
| * None Equipment removed from service or currently unavailable
| |
| * None
| |
| * None Grid Status is Green Comments, evolutions, problems, etc. Comments, evolutions, problems, etc.
| |
| * 0B Diesel Fire Pump is OOS for
| |
| * Non-Div Workweek. OLR is Green Maintenance, scheduled to be returned in 24 hours
| |
| * Perform LOS-HP-Q1 starting at step A.9 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 26 of 26
| |
| | |
| LaSalle County Station LICENSED OPERATOR EVALUATED SCENARIO GUIDE 19-1 NRC Exam Scenario 2 Rev. 00
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Facility: LaSalle County Generating Station Scenario #: 19-1 NRC Exam Scenario 2 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.
| |
| | |
| ==SUMMARY==
| |
| OF EVENTS
| |
| : 1. The crew will withdraw all IRMs as directed per the turnover and LGP-1-1.
| |
| : 2. When withdrawing IRMs, the F IRM will stick and require the crew to bypass the stuck IRM IAW LOA-NR-101.
| |
| : 3. The crew will withdraw control rods per LGP-1-1 and LOP-RM-01 until 1 1/2 bypass valves are open.
| |
| : 4. The 1A VT Exhaust Fan will trip, requiring the crew to start the 1C VT Exhaust Fan
| |
| : 5. A control rod will drift out, requiring the crew to take action per LOA-RD-101, to insert the control rod and enter Tech Specs.
| |
| : 6. RCIC will spuriously initiate, requiring the crew to secure RCIC and enter Tech Specs.
| |
| : 7. A leak will occur in the RCIC system that will require and isolation. The isolations will fail both manually and automatically requiring a scram per LGA-002. With two areas above max safe, blowdown per LGA-004 will be required.
| |
| : 8. With ADS initiated, only 3 SRVs will open requiring the crew to manually open 4 SRVs.
| |
| Critical Tasks
| |
| : 1. With a steam leak in the RCIC Room and the temperature and radiation levels trending toward the max safe values, the crew will scram the reactor IAW LGA-002 before reaching any area radiation/temperature max safe value.
| |
| : 2. With a steam leak in the RCIC Room, temperature and radiation levels will reach the max safe values in the RCIC Room and LPCS Ventilation. The crew will wait until two or more areas are above the max safe value of the same parameter (in the RCIC Room and LPCS Ventilation) to transition to LGA-004 to blowdown within 20 minutes.
| |
| : 3. With blowdown required by LGA-002, the crew will initiate blowdown per LGA-004. When the BOP manually initiates ADS, only 3 of the required 7 ADS valves will open. The BOP will manually open SRVs, one at a time, until 7 SRVs are open within 10 minutes of manually initiating ADS.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 2 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 TRAINING REQUESTS (if applicable)
| |
| : 1. None OPEX (if applicable)
| |
| : 1. None Operator Fundamentals
| |
| : 1. Monitoring plant indications and conditions closely
| |
| : 2. Controlling plant evolutions precisely
| |
| : 3. Operating the plant with a conservative bias
| |
| : 4. Working effectively as a team
| |
| : 5. Having a solid understanding of plant design, engineering principles, and sciences SOER 10-2
| |
| : 1. Supervisory oversight role
| |
| : 2. Recognition and mitigation of risk
| |
| : 3. Worker performance
| |
| : 4. Tolerance of repetitive/long standing issues and degradation of standards
| |
| : 5. Operating Experience Record of Revisions (Summary)
| |
| Rev. 0 Developed new for the ILT 19-1 NRC Exam SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 3 of 24
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| | |
| 19-1 NRC Exam Scenario 2 Revision 00 INITIAL SIMULATOR SETUP/ REQUIRED DOCUMENTATION
| |
| : 1. Recall a full power IC 201 Password 0201
| |
| : 2. Place simulator in RUN
| |
| : 3. Load and run the SmartScenario file NRC 19-1 Scenario 2.ssf
| |
| : 4. Update the Tech Spec Timeclock Sheet as follows:
| |
| TS/TRM/ODCM System/ Required REQUIRED ACTION Completion Expiration Component Action Description Time Date/Time N/A N/A N/A N/A N/A N/A
| |
| : 5. Perform the pre-scenario checklist (TQ-LA-150-0308)
| |
| SCENARIO OUTLINE (NRC Evaluations Only)
| |
| Event Malf. Event Event No. No. Type* Description 1 none N (ATC) Withdraw IRM detectors per LOP-NR-02, Intermediate Range Monitor Operation (IRM)
| |
| IRM F becomes stuck in the core when being withdrawn per 2 MNI047 I (ATC)
| |
| LOP-NR-02 Withdraw control rods until at least 1 1/2 TBVs are open, continue 3 none R (ATC) through step E.7.3 4 R1479 C (BOP) 1A Turbine Building Exhaust Fan trip, manually start idle fan C (ATC) Control rod drifts out, insert rod to position 00. SRO enters TS 5 MRD093 T (SRO) 3.1.3 Condition C C (BOP) Inadvertent RCIC actuation, secure RCIC IAW LOP-RI-03. SRO 6 MNB080 T (US) enters TS 3.5.3 Condition A Increase leak to a major unisolable steam leak at pipe weld 7 MES019 M (ALL) upstream of MOV-F008. Two areas (RCIC equipment room, LPCS Vent) reach Max Safe Temperature/ RPV Blowdown ISRVFUSE ADS initiation opens only 3 ADS Valves, manually open SRVs 8 14/16/17/1 C (BOP) 8 until 7 are open
| |
| * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specification APPROXIMATE SCENARIO RUN TIME 90 Minutes SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 4 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE)
| |
| During performance of tasks, dynamic learning activities, or formal evaluations, 769.00.01 demonstrate applicable Human Performance behaviors IAW the appropriate procedures.
| |
| Given an operating experience document, paraphrase the lessons learned and 762.04.00 methods to prevent recurrence at LaSalle Station, as described in the training material.
| |
| During performance of tasks, apply the administrative requirements of PROCEDURE 614.010 USE AND ADHERENCE EXPECTATIONS, IAW station procedures.
| |
| TASKS RO - ATC Given plant conditions, Perform Control Room actions for a RCIC System steam Line break, IAW 32.019 Station Procedures.
| |
| Given Unit Supervisor authorization, perform Control Room actions for an Intermediate Range or 42.001 Source Range Monitor Insert/Withdraw failure, IAW station procedures.
| |
| Given Unit Supervisor authorization, perform a continuous Control Rod Insertion, IAW station 47.004 procedures.
| |
| Given Unit Supervisor authorization, Reduce power from 100% to 60 % power, IAW station 303.020 procedures.
| |
| 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 413.000 59.5 IAW LGA-001 Given entry conditions, evaluate plant conditions and isolate all primary systems discharging 427.000 outside primary and secondary containment not required for other LGA actions, IAW Station Procedures.
| |
| With a blowdown required, evaluate plant conditions and rapidly depressurize the RPV using 428.000 SRVs via the ADS system, IAW Station procedures.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 5 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 RO - BOP/ASSIST Given plant conditions, Perform Control Room actions for a RCIC System steam Line break, 32.019 IAW Station Procedures.
| |
| Given Unit Supervisor authorization, respond to a Turbine Building abnormal condition, IAW 119.015 station procedures.
| |
| Given entry conditions, evaluate plant conditions and isolate all primary systems discharging 427.000 outside primary and secondary containment not required for other LGA actions, IAW Station Procedures.
| |
| With a blowdown required, evaluate plant conditions and rapidly depressurize the RPV using 428.000 SRVs via the ADS system, IAW Station procedures.
| |
| SRO - UNIT SUPERVISOR Given plant conditions, Perform Control Room actions for a RCIC System steam Line break, IAW 32.019 Station Procedures.
| |
| Given Unit Supervisor authorization, perform Control Room actions for an Intermediate Range or 42.001 Source Range Monitor Insert/Withdraw failure, IAW station procedures.
| |
| Given Unit Supervisor authorization, perform Control Room actions to operate the Intermediate 42.004 Range Monitors, IAW station procedures.
| |
| Given Unit Supervisor authorization, perform a continuous Control Rod Insertion, IAW station 47.004 procedures.
| |
| Given Unit Supervisor authorization, respond to a Turbine Building abnormal condition, IAW 119.015 station procedures.
| |
| 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 413.000 59.5 IAW LGA-001 Given entry conditions, evaluate plant conditions and isolate all primary systems discharging 427.000 outside primary and secondary containment not required for other LGA actions, IAW Station Procedures.
| |
| With a blowdown required, evaluate plant conditions and rapidly depressurize the RPV using 428.000 SRVs via the ADS system, IAW Station procedures.
| |
| Given a set of plant conditions, identify and prepare the Technical Specification required actions 201.011 IAW Tech Specs.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 6 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 1
| |
| | |
| == Description:==
| |
| Withdraw IRM detectors per LOP-NR-02, Intermediate Range Monitor Operation (IRM)
| |
| Initiation: Following turnover Cues:
| |
| Automatic Actions: none Expected Annunciator: none Key Parameter Response: IRM Full-in lights extinguish and Full-out light illuminate Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Per LOP-NR-02
| |
| * When in the RUN mode, DEPRESS all inserted IRM select buttons, DEPRESS the Drive-Out button, and HOLD until all IRM detectors are out of the core and all IRM 42.001 ATC OUT lights are illuminate
| |
| * Once IRMs are fully withdrawn, RANGE IRMs as necessary to maintain upscale and downscale trip lights clear
| |
| * Monitor plant parameters and update the crew as required BOP
| |
| * Provide peer checks as required 42.001 US
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 7 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 1
| |
| | |
| == Description:==
| |
| Withdraw IRM detectors per LOP-NR-02, Intermediate Range Monitor Operation (IRM)
| |
| Simulator Operator Actions None Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note: This event is intended for the ATC.
| |
| Terminus: Continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 8 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 2
| |
| | |
| == Description:==
| |
| IRM F becomes stuck in the core when being withdrawn per LOP-NR-02 Initiation: Automatic Cues:
| |
| Automatic Actions: none Expected Annunciator: none Key Parameter Response: F IRM Full-in light does not extinguish Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Per LOA-NR-101
| |
| * STOP all control rod motion/power change
| |
| * VERIFY Detector Drive and Position Indication POWER ON light -ILLUMINATED 42.004 ATC
| |
| * VERIFY desired detectors SELECTED
| |
| * CHECK selected detectors MOVE
| |
| * BYPASS affected channel
| |
| * Monitor plant parameters and update the crew as required BOP
| |
| * Provide peer checks as required 42.004 US
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 9 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 2
| |
| | |
| == Description:==
| |
| IRM F becomes stuck in the core when being withdrawn per LOP-NR-02 Simulator Operator Actions When directed by the Lead Evaluator if the crew does As Shift Manager, call Unit Supervisor with report below not continue with the startup Simulator Operator Role Play When requested to replace fuses, as IMD, report, Well develop a trouble shooting package for the stuck IRM.
| |
| As Shift Manager, inform the Unit Supervisor, Continue with the Startup per LGP-1-1.
| |
| Respond as required Floor Instructor Notes/OPEX/TRs Note: This event is intended for the ATC.
| |
| Terminus: and at the discretion of the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 10 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 3
| |
| | |
| == Description:==
| |
| Withdraw control rods until at least 1 1/2 TBVs are open Initiation: Following the crew assuming the shift Cues: Turnover Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Per LGP-1-1
| |
| * CONTINUE control rod withdrawal until at least 11/2 Bypass Valves are open for initial generator loading Per LOP-RM-01
| |
| * VERIFY CRD Drive Flow Trip Circuit Bypass Switch is in the BYPASS position
| |
| * VERIFY CRD Drive Flow Trip Circuit Test Switch is in the NORMAL position
| |
| * Simultaneously DEPRESS and HOLD both CONTINUOUS WITHDRAW and WITHDRAW push-button. Selected rod will continuously withdraw until one (1) 47.004 ATC push-button is released
| |
| * CHECK the following:
| |
| * Rod Withdraw Sequence begins
| |
| * CONTINUOUS WITHDRAW indication appears as long as both pushbuttons are depressed
| |
| * OBSERVE changes in nuclear instrumentation indications
| |
| * Wheneither push-button is released, Rod SETTLE indication is lit for approximately 2 seconds
| |
| * New rod position will be indicated on the ROD SELECT Display, STATUS Display and CORE MAP Display
| |
| * Monitor plant parameters and update the crew as required BOP
| |
| * Provide peer checks as required 47.004 US
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 11 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 3
| |
| | |
| == Description:==
| |
| Withdraw control rods until at least 1 1/2 TBVs are open Simulator Operator Actions none Simulator Operator Role Play Respond as required.
| |
| Floor Instructor Notes/OPEX/TRs Terminus: When sufficient power increase has been performed per the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 12 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 4
| |
| | |
| == Description:==
| |
| 1A Turbine Building Exhaust Fan trip Initiation: As directed by the Lead Evaluator Cues:
| |
| Automatic Actions: 1A VT Exhaust Fan Trips Expected Annunciator: 1PM06J-B402, Turbine Building Ventilation Exhaust Fan 1VT02CA Automatic Trip Key Parameter Response: None Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Monitor plant condtions and update the crew as required ATC
| |
| * Provide peer checks as required Per LOR-1PM06J-B402
| |
| * START idle Turbine Building Ventilation Exhaust Fan
| |
| * ENTER LOA-VT-101, Unit 1 Turbine Building Ventilation Abnormal 119.015 BOP
| |
| * REFER to LOP-VT-01, Turbine Building Ventilation System Startup for follow-up actions
| |
| * DETERMINE cause of TRIP 119.015 US
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 13 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 4
| |
| | |
| == Description:==
| |
| 1A Turbine Building Exhaust Fan trip Simulator Operator Actions When directed by the Lead Release Event 4 Evaluator Simulator Operator Role Play As the EO in the field when asked, report, the 1A VT Exhaust Fan tripped on overcurrent.
| |
| Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When the 1C VT Exhaust Fan is running and per the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 14 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 5
| |
| | |
| == Description:==
| |
| Control rod drifts out (Rod 06-39)
| |
| Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: none Expected Annunciator: 1H13-P603-A504, Control Rod Drive Drift Alarm Key Parameter Response: Rod 06-39 drifting out Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Per LOA-RD-101
| |
| * CONTINUALLY CHECK control rods status
| |
| * CHECK Control Rods -No control rod currently moving
| |
| * SELECT drifting control rod
| |
| * VERIFY insertblock indication OFF at ROD SELECT or STATUS Display
| |
| * PLACE the RWM Select switch to BYPASS
| |
| * INSERT control rod to position 00 44.002 ATC
| |
| * PLACE CRD DRIVE FLOW TRIP CIRCUIT BYPASSSwitch to BYPASS
| |
| * CHECK control rod remains at position 04 or less
| |
| * If control rod will NOT remain at position 04 or less and manpower allows, DEPRESS AND HOLD Insert push-button while continuing here
| |
| * If desired:
| |
| o PLACE control rod OOS on RCMS o DISARM control rod electrically on RCMS
| |
| * ENTER Mispositioned Control Rod(s)subsection while continuing here
| |
| * Monitor plant condtions and update the crew as required BOP
| |
| * Provide peer checks as required
| |
| * Direct above actions
| |
| * Give manual scram criteria of no more than 1 rod moving or rods drifted full in
| |
| * Enter Tech Spec 3.1.3 Condition C
| |
| * Required Action C.1 and C.2 44.002 201.001 US
| |
| * Enter Tech Spec 3.3.2.1. Condition C
| |
| * Required Action C.1 or
| |
| * Required Action C.2.1.1 or C.2.1.2, and C.2.2 o Refer to Tech Spec 3.1.6 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 15 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 5
| |
| | |
| == Description:==
| |
| Control rod drifts out Simulator Operator Actions When directed by the Lead Release Event 5 Evaluator Simulator Operator Role Play As the EO sent to investigate the HCU, report, there is nothing abnormal at the HCU.
| |
| Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When the control rod is full in with weighted device on insert button and the Tech Spec call has been made and at the discretion of the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 16 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 6
| |
| | |
| == Description:==
| |
| Inadvertent RCIC actuation Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: RCIC starts Expected Annunciator: 1H13-P601-D406, Reactor Core Isolation Cooling Running Key Parameter Response: Rising Reactor level Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Monitor plant parameters and update the crew as required ATC
| |
| * Provide peer checks as required Per LOR-1H13-P601-D406
| |
| * If RCIC injection is inadvertent or NOT desired, PERFORM the following:
| |
| BOP
| |
| * TRIP RCIC Turbine
| |
| * SHUTDOWN RCIC per LOP-RI-03
| |
| * Direct above actions
| |
| * Enter Tech Spec 3.3.5.3
| |
| * Condition A, RA A.1 201.001 US
| |
| * Condition B, RA B.1 and B.2
| |
| * Tech Spec 3.5.3
| |
| * Condition A, RA A.1 and A.2 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 17 of 24
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| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 6
| |
| | |
| == Description:==
| |
| Inadvertent RCIC actuation Simulator Operator Actions When directed by the Lead Release Event 6 Evaluator Simulator Operator Role Play After call to investigate, wait 3 minutes and report, The RCIC level 2 trip unit has failed Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When RCIC has been secured and Tech Spec call made and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 18 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 7
| |
| | |
| == Description:==
| |
| Major unisolable steam leak at pipe weld upstream of MOV-F008. Two areas reach Max Safe Temperature/ RPV Blowdown Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: none Expected Annunciator: 1H13-P601-B110, Reactor Building Radiation High Key Parameter Response: Rising secondary containment temperatures and rad levels Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Performs Reactor Scram and LGP 3-2
| |
| * ARM and DEPRESS Scram Pushbuttons (CT)
| |
| * PLACE Reactor Mode Switch in SHUTDOWN (CT)
| |
| * INSERT SRMs
| |
| * CHECK Control Rods INSERTED and Power Decreasing 32.019
| |
| * INFORM Unit Supervisor of Control Rod Status and Reactor Power 304.010 413.000 ATC
| |
| * Operate Feedwater and/or ECCS as necessary to maintain RPV Water Level 20" to 427.000 50" or as specified by Unit Supervisor
| |
| * Place LFFRV in AUTO
| |
| * REPORT to the Unit Supervisor the status of RPV Level and Pressure
| |
| * If needed for level control:
| |
| * Place the FRV in AUTO
| |
| * STABILIZE Reactor Pressure <1020 psig
| |
| * Monitor plant parameters and update the crew as required
| |
| * Collect LGA-002 data Per LGA-002 BOP
| |
| * Isolate all discharges into the affecetd areas except systems needed for damge control and LGA actions
| |
| * Attempt to CLOSE 1E51-F008 and 1E51-F063 (FAIL)
| |
| * Montior radiation release for potential entry into LGA-009 32.019
| |
| * Direct above actions 304.010 413.000 US
| |
| * Enter LGA-002 427.000
| |
| * Direct scram prior to MAX Safe (CT)
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 19 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 7
| |
| | |
| == Description:==
| |
| Major unisolable steam leak at pipe weld upstream of MOV-F008. Two areas reach Max Safe Temperature/ RPV Blowdown Simulator Operator Actions When directed by the Lead Release Event 7 Evaluator Simulator Operator Role Play As an EO, if asked to investigate the RCIC leak, wait 1 minute and report, A large amount of steam is coming from the RCIC corner room.
| |
| Respond as required Floor Instructor Notes/OPEX/TRs Note: The reactor scram must occur prior to 212 degrees as indicated in the RCIC Equipment Room and RCIC/LPCS Room Vent Temps.
| |
| Terminus: Continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 20 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 8
| |
| | |
| == Description:==
| |
| ADS initiation opens only 3 ADS Valves, manually open SRVs until 7 are open Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: 3 SRVs open Expected Annunciator: multiple Key Parameter Response: the open indicated on 3 SRVs illuminate Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Monitor plant parameters and update the crew as required ATC
| |
| * Provide peer checks as required Per LGA-004
| |
| * Prevent LPCS and LPCI injection not needed for core cooling
| |
| * CHECK suppression pool level above -18 feet 428.000 BOP
| |
| * Initate ADS
| |
| * VERIFY 7 ADS valves open (CT)
| |
| * Open other SRVs until a total of 7 are open (CT)
| |
| * Leave SRVs open. Allow RPV to depressurize
| |
| * Direct entry into LGA-004 428.000 US
| |
| * Direct initation of ADS (CT)
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 21 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 Event - 8
| |
| | |
| == Description:==
| |
| ADS initiation opens only 3 ADS Valves, manually open SRVs until 7 are open Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When a total of 7 SRVs are open, RPV is depressurized, and the crew has established RPV level control in the normal shutdown level band and at the discretion of the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 22 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 REFERENCES Procedure Rev Title
| |
| : 1. INPO 15-004 Operations Fundamentals
| |
| : 2. SOER 10-2 Engaged, Thinking Organizations
| |
| : 3. LOR-1H13-P603- 4 Control Rod Drive Drift Alarm A504
| |
| : 4. LOR-1PM06J-B402 2 Turbine Building Ventilation Exhaust Fan 1VT02CA Automatic Trip
| |
| : 5. LOR-1H13-P601- 5 Reactor Core Isolation Cooling Running D406
| |
| : 6. LOR-1H13-P601- 3 RCIC Turbine Trip D104
| |
| : 7. LOR-1H13-P601- 1 Reactor Building Radiation High B110
| |
| : 8. LOA-AR-101 5 Area Radiation Monitoring System Abnormal
| |
| : 9. LOA-NR-101 20 Neutron Monitoring Trouble
| |
| : 10. LOA-RD-101 21 Control Rod Drive Abnormal
| |
| : 11. LOA-VT-101 4 Unit 1 Turbine Building Ventilation System Abnormal
| |
| : 12. LOP-NR-02 21 Intermediate Range Monitor Operation
| |
| : 13. LOP-VT-01 24 Turbine Building Ventilation System Startup
| |
| : 14. LGP-3-2 75 Reactor Scram
| |
| : 15. LGP-3-1 70 Power Changes
| |
| : 16. LGP-1-1 126 Normal Reactor Startup
| |
| : 17. LGA-VQ-101 1 Unit 1 Containment Vent
| |
| : 18. LGA-001 18A RPV Control
| |
| : 19. LGA-002 10 Secondary Containment Control
| |
| : 20. LGA-004 9 RPV Blowdown
| |
| : 21. OP-LA-101-111-1002 81 LaSalle Operations Philosophy Handbook.
| |
| : 22. OP-LA-103-102-1002 21 Strategies for Successful Transient Mitigation SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 23 of 24
| |
| | |
| 19-1 NRC Exam Scenario 2 Revision 00 U1 SUPERVISOR TURNOVER Shift: Days Date: Today Mode: 1 OLR: Green Work Week: Div 2 Unit 1 power level Unit 2 power level
| |
| * 8 % Power
| |
| * 100 % Power
| |
| * LGP-1-1 Startup In-progress
| |
| * U1 Thermal Limit Issues /Power Evolutions U2 Thermal Limit Issues /Power Evolutions
| |
| * None
| |
| * None Existing LCOs, date of next surveillance Existing LCOs, date of next surveillance
| |
| * None
| |
| * None LOSs in progress or major maintenance LOSs in progress or major maintenance
| |
| * None
| |
| * None Equipment removed from service or currently unavailable
| |
| * None
| |
| * None Grid Status is Green Comments, evolutions, problems, etc. Comments, evolutions, problems, etc.
| |
| * Withdraw IRMs per LGP-1-1 step E.6.18
| |
| * Non-Div Workweek. OLR is Green IAW LOP-NR-02 step E.2.1.8
| |
| * Step E.6.19 is COMPLETE
| |
| * Raise reactor power per LGP-1-1 step E.7.1 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 24 of 24
| |
| | |
| LaSalle County Station LICENSED OPERATOR EVALUATED SCENARIO GUIDE 19-1 NRC Exam Scenario 3 Rev. 00
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Facility: LaSalle County Generating Station Scenario #: 19-1 NRC Exam Scenario 3 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.
| |
| | |
| ==SUMMARY==
| |
| OF EVENTS
| |
| : 1. The crew will synchronize the main generator to the grid per LOP-TG-02.
| |
| : 2. The crew will raise reactor power per the turnover using control rods per LGP-1-1 step E.7.6.
| |
| : 3. Due to a failure of the manual initiation logic, the SBGT system to auto start. Once started, the primary fan will indicate a low flow condition and require a system shutdown and Tech Specs to be entered.
| |
| : 4. A loss of A RCMS Interface will occur, causing the crew to take actions to reset per LOA-RM-101.
| |
| : 5. A VC Rad Monitor will fail, causing the Unit Supervisor to enter Tech Specs.
| |
| : 6. The MDRFP flow instrument will fail upscale requiring the crew to take manual control and open the min flow valve.
| |
| : 7. Main Turbine vibrations will rise, causing the crew to initiate a turbine trip. With a turbine/generator trip, OCB 10-11 will fail to auto trip and must be manually tripped.
| |
| : 8. A leak will develop in the A MSL to the MST causing LGA-002 entry and scram.
| |
| : 9. With a leak from A MSL the crew will attempt to isolate the leak by closing MSIVs and drains. Both A line MSIVs will fail to close.
| |
| : 10. With a high offsite release due to a failure of 1VT79A/B/C, the crew will perform an RPV blowdown per LGA-004.
| |
| Critical Tasks
| |
| : 1. Scram the reactor prior to one reactor building designated area (MSL Tunnel) temperature reaching its Maximum Safe value.
| |
| : 2. With a primary system discharging outside primary and secondary containment, manually scram the reactor if a reactor scram has not yet been initiated, enter LGA-001, and INITIATE emergency depressurization before offsite release rate reaches the General Emergency level.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 2 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 TRAINING REQUESTS (if applicable)
| |
| : 1. None OPEX (if applicable)
| |
| : 1. None Operator Fundamentals
| |
| : 1. Monitoring plant indications and conditions closely
| |
| : 2. Controlling plant evolutions precisely
| |
| : 3. Operating the plant with a conservative bias
| |
| : 4. Working effectively as a team
| |
| : 5. Having a solid understanding of plant design, engineering principles, and sciences SOER 10-2
| |
| : 1. Supervisory oversight role
| |
| : 2. Recognition and mitigation of risk
| |
| : 3. Worker performance
| |
| : 4. Tolerance of repetitive/long standing issues and degradation of standards
| |
| : 5. Operating Experience Record of Revisions (Summary)
| |
| Rev. 0 Developed new for the ILT 19-1 NRC Exam SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 3 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 INITIAL SIMULATOR SETUP/ REQUIRED DOCUMENTATION
| |
| : 1. Recall a full power IC 201 Password 0201
| |
| : 2. Place simulator in RUN
| |
| : 3. Load and run the SmartScenario file NRC 19-1 Scenario 3.ssf
| |
| : 4. Update the Tech Spec Timeclock Sheet as follows:
| |
| TS/TRM/ODCM System/ Required REQUIRED ACTION Completion Expiration Component Action Description Time Date/Time N/A N/A N/A N/A N/A N/A
| |
| : 5. Perform the pre-scenario checklist (TQ-LA-150-0308)
| |
| SCENARIO OUTLINE (NRC Evaluations Only)
| |
| Event Malf. Event Event No. No. Type* Description Synchronize to the grid IAW LGP 1-1, step E.7.4 and LOP-TG-02, step 1 none N (BOP)
| |
| E.24 2 none R (ATC) Raise power with control rods to 15% power IAW LGP 1-1, step E.7.6 KDD01PE V C (BOP) SBGTS Low Flow after Autostart on a failure of the manual initiation 3 KDD01BO T (SRO) logic - SRO enters TS 3.6.4.3 condition A V
| |
| 4 MRD343 I (ATC) Loss of A Rod Control Management System Interface Control Room Ventilation Radiation Monitor Fails. SRO Enters TS 5 MRM039 T (SRO) 3.3.7.1 Condition A 6 MCF074 I (ATC) Upscale failure of the MDRFP Flow Instrument 1C34-R612 MMS056 High Vibrations on Main Turbine Bearings Requiring Manual Trip of 7 C (BOP)
| |
| MEE065 Turbine; One Output Breaker Fails to Open MNB106 Large steam leak in Main Steam Tunnel resulting in significant fuel 8 M (ALL)
| |
| MNB103 failure and entry into LGA-002 on high MST temperature MNB109 9 C (ALL) Close MSIVs to stop the leak but both A loop MSIVs fail open MNB113 Turbine building dampers 1VT79YA/B/C Fail OPEN, High Off-site 10 MVT001 M (ALL)
| |
| Release/ RPV Blowdown
| |
| * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specification APPROXIMATE SCENARIO RUN TIME 90 Minutes SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 4 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE)
| |
| During performance of tasks, dynamic learning activities, or formal evaluations, 769.00.01 demonstrate applicable Human Performance behaviors IAW the appropriate procedures.
| |
| Given an operating experience document, paraphrase the lessons learned and 762.04.00 methods to prevent recurrence at LaSalle Station, as described in the training material.
| |
| During performance of tasks, apply the administrative requirements of PROCEDURE 614.010 USE AND ADHERENCE EXPECTATIONS, IAW station procedures.
| |
| TASKS RO - ATC Given Unit Supervisor authorization, complete the control room actions associated with RWLCS 31.013 Trouble alarm, IAW station procedures.
| |
| 47.004 Provided initial indications, perform continuous Control Rod Withdrawal, IAW station procedures.
| |
| Provided initial indications, perform the Main Control Room actions associated with Rod Control 47.013 Management System Alarms, IAW station procedures.
| |
| 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 413.000 59.5 IAW LGA-001 Given entry conditions, evaluate plant conditions and isolate all primary systems discharging 427.000 outside primary and secondary containment not required for other LGA actions, IAW Station Procedures.
| |
| With a blowdown required, evaluate plant conditions and rapidly depressurize the RPV using 428.000 SRVs via the ADS system, IAW Station procedures.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 5 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 RO - BOP/ASSIST Given Unit Supervisor authorization, Perform actions for Main Turbine startup and 71.010 synchronization, IAW station procedures.
| |
| Provided initial conditions, perform Control Room actions for Main Turbine Generator trip (load 71.028
| |
| < 25%), IAW station procedures.
| |
| Provided initial conditions, perform Control Room actions for Main Turbine Generator high 71.030 vibration or noise, IAW station procedures.
| |
| Provided initial indications, respond to VC/VE system abnormalities (i.e. hi rad, smoke, etc.),
| |
| 117.016 IAW station procedures.
| |
| Given LGA-009, Radioactivity Release Control, in progress, evaluate plant conditions and 426.000 establish a monitored release path, IAW station procedures.
| |
| Given entry conditions, evaluate plant conditions and isolate all primary systems discharging 427.000 outside primary and secondary containment not required for other LGA actions, IAW Station Procedures.
| |
| With a blowdown required, evaluate plant conditions and rapidly depressurize the RPV using 428.000 SRVs via the ADS system, IAW Station procedures.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 6 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 SRO - UNIT SUPERVISOR Given Unit Supervisor authorization, complete the control room actions associated with RWLCS 31.013 Trouble alarm, IAW station procedures.
| |
| 47.004 Provided initial indications, perform continuous Control Rod Withdrawal, IAW station procedures.
| |
| Provided initial indications, perform the Main Control Room actions associated with Rod Control 47.013 Management System Alarms, IAW station procedures.
| |
| Given Unit Supervisor authorization, Perform actions for Main Turbine startup and 71.010 synchronization, IAW station procedures.
| |
| Provided initial conditions, perform Control Room actions for Main Turbine Generator trip (load <
| |
| 71.028 25%), IAW station procedures.
| |
| Provided initial conditions, perform Control Room actions for Main Turbine Generator high 71.030 vibration or noise, IAW station procedures.
| |
| Provided initial indications, respond to VC/VE system abnormalities (i.e. hi rad, smoke, etc.), IAW 117.016 station procedures.
| |
| 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 413.000 59.5 IAW LGA-001 421.010 Given plant conditions, cool the Suppression Pool, IAW Station Procedures.
| |
| Given LGA-009, Radioactivity Release Control, in progress, evaluate plant conditions and 426.000 establish a monitored release path, IAW station procedures.
| |
| Given entry conditions, evaluate plant conditions and isolate all primary systems discharging 427.000 outside primary and secondary containment not required for other LGA actions, IAW Station Procedures.
| |
| With a blowdown required, evaluate plant conditions and rapidly depressurize the RPV using 428.000 SRVs via the ADS system, IAW Station procedures.
| |
| Given a set of plant conditions, identify and prepare the Technical Specification required actions 201.011 IAW Tech Specs.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 7 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 1
| |
| | |
| == Description:==
| |
| Synchronize to the grid IAW LGP 1-1 Initiation: Following the crew assuming the shift Cues: Turnover Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Monitor plant condtions and update the crew as required ATC
| |
| * Provide peer checks as required Per LOP-TG-02
| |
| * VERIFY GENERATOR FIELD VOLTS ADJUST at minimum position as indicated by LOWER LIMIT light on
| |
| * VERIFY U1 GENERATOR REGULATOR MODE TRANSFER in MANUA
| |
| * VERIFY U1 GENERATOR VOLTMETER SELECTOR is NOT OFF
| |
| * CLOSE U1 GENERATOR FIELD BREAKER and OBSERVE the following:
| |
| * 1EI-MP002, U1 GENERATOR FIELD VOLTS indication rises.
| |
| * 1EI-MP021, U1 GENERATOR KILOVOLTS indication rises.
| |
| * VERIFY 1EI-MP021, U1 GENERATOR KILOVOLTS indicates 18 KV to 22 KV.
| |
| * Using GENERATOR FIELD VOLTS ADJUST, RAISE 1EI-MP021, U1 GENERATOR KILOVOLTS to 23.5 KV to 24.0 KV
| |
| * CHECK all three phases of generator voltage approximately 23.7 KV using U1 GENERATOR VOLTMETER SELECTOR
| |
| * VERIFY Main Power Transformer Trouble alarms are clear at Panel 1PM01J windows A203 and A204
| |
| * PLACE Generator control in automatic as follows:
| |
| * ADJUST U1 GENERATOR TERMINAL VOLTS ADJUST until 1EI-MP003, U1 GEN REGULATOR TRANSFER VOLTS indicates zero
| |
| * PLACE U1 GENERATOR REGULATOR MODE TRANSFER in AUTO
| |
| * VERIFY proper operation of the Main Generator Voltage Regulator in Auto by lowering and raising the voltage using the GENERATOR TERMINAL VOLTS ADJUST by 1 KV 71.010 BOP
| |
| * At Panel 0PM11J VERIFY OCB 9-10 Auto Recloser is OFF
| |
| * VERIFY the following control switches are NOT in PULL-TO-LOCK: 9-10 and 10-11
| |
| * Place one of the following in ON: 9-10 or 10-11
| |
| * Manually ADJUST Generator speed using Load Raise/Lower pushbuttons so generator output frequency is slightly higher than grid frequency, U1 GENERATOR SYNCHROSCOPE, meter on 1PM01J rotates slowly in the FAST direction
| |
| * Adjust Main Generator output voltage to make incoming slightly higher than running
| |
| * Just prior to U1 GENERATOR SYNCHROSCOPE, meter reaching 12 o'clock position CLOSE OCB 9-10 or 10-11
| |
| * At 1PM02J EHC Workstation, RAISE Load Set Stpt to 105.0 % using either the Load Set Manual Adj.
| |
| Raise pushbutton or by entering a target Load Set Setpoint and Ramp Rate
| |
| * Turn the SYNC scope OFF for the beaker just CLOSED and ON for the next breaker to be CLOSED
| |
| * VERIFY U1 GENERATOR SYNCHROSCOPE, meter in 12 o'clock position
| |
| * U1 GENERATOR INCOMING VOLTS, and U1 GENERATOR RUNNING VOLTS are approximately equal
| |
| * CLOSE the selected OCB and CHECK the breaker closes and turn the SYNC scope OFF
| |
| * If the Generator voltage regulator is in MANUAL and it is desired to transfer to AUTO
| |
| * ADJUST U1 GENERATOR TERMINAL VOLTS ADJUST until 1EI-MP003, U1 GEN REGULATOR TRANSFER VOLTS indicates zero
| |
| * PLACE U1 GENERATOR REGULATOR MODE TRANSFER in AUTO
| |
| * PLACE OCBs 9-10 and 10-11 in NAC on the 1PM11J
| |
| * Inform TSO 71.010 US
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 8 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 1
| |
| | |
| == Description:==
| |
| Synchronize to the grid IAW LGP 1-1 Simulator Operator Actions none Simulator Operator Role Play Respond as required.
| |
| Floor Instructor Notes/OPEX/TRs Terminus: When the Main Generator synced to the grid with the voltage regulator in AUTO and at the discretion of the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 9 of 29
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| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 2
| |
| | |
| == Description:==
| |
| Raise power with control rods to 15% power IAW LGP 1-1 Initiation: Following the completion of event 1 Cues: turnover Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Per LGP-1-1 and LOP-RM-01
| |
| * CONTINUE control rod withdrawal until at least 11/2 Bypass Valves are open for initial generator loading Per LOP-RM-01
| |
| * VERIFY CRD Drive Flow Trip Circuit Bypass Switch is in the BYPASS position
| |
| * VERIFY CRD Drive Flow Trip Circuit Test Switch is in the NORMAL position
| |
| * Simultaneously DEPRESS and HOLD both CONTINUOUS WITHDRAW and WITHDRAW push-button. Selected rod will continuously withdraw until one (1) 47.004 ATC push-button is released
| |
| * CHECK the following:
| |
| * Rod Withdraw Sequence begins
| |
| * CONTINUOUS WITHDRAW indication appears as long as both pushbuttons are depressed
| |
| * OBSERVE changes in nuclear instrumentation indications
| |
| * When either push-button is released, Rod SETTLE indication is lit for approximately 2 seconds
| |
| * New rod position will be indicated on the ROD SELECT Display, STATUS Display and CORE MAP Display
| |
| * Monitor plant condtions and update the crew as required BOP
| |
| * Provide peer checks as required 47.004 US
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 10 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 2
| |
| | |
| == Description:==
| |
| Raise power with control rods to 15% power IAW LGP 1-1 Simulator Operator Actions None Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When a sufficient power increase has been observed per the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 11 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 3
| |
| | |
| == Description:==
| |
| SBGTS Low Flow after Auto-start Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: SBGT starts Expected Annunciator: 1PM07J-A301, Standby Gas Treatment System Manual Initiation 1PM07J-A401, Standby Gas Treatment System Primary Fan Flow High-Low Key Parameter Response: Reactor Building D/P fluctuates Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Monitor plant condtions and update the crew as required ATC
| |
| * Provide peer checks as required Per LOR-1PM07J-A401
| |
| * VERIFY SBGT Primary Fan 1VG01C is running
| |
| * VERIFY following dampers are Open:
| |
| * 1VG001, SBGT Suction from Reactor Building, or 1VQ041, SBGT Suction from Return Air Riser
| |
| * 1VG003, SBGT Train Outlet
| |
| * 1VG05Y, SBGT Primary Fan Gravity Damper
| |
| * VERIFY SBGT Flow Control Damper 1VG002 is modulating to control flow
| |
| * If unable to obtain proper flow and SBGT is required for accident conditions, manually initiate the other SBGT system BOP
| |
| * Per LOP-VG-02
| |
| * STOP 1VG01C, Standby Gas Treatment Primary Fan by placing Control Switch to PULL TO LOCK
| |
| * VERIFY 1VG02C, Standby Gas Treatment Cooling Fan AUTO starts
| |
| * VERIFY 1VG01A, SBGT Air Heater shuts off as flow decreases through the Train
| |
| * VERIFY 1VG003, Standby Gas Treatment Outlet Damper closes, then RE-OPENS
| |
| * PULL Pistol Grip for 1VG001, Standby Gas Treatment Suction from Reactor Building Atmosphere out
| |
| * CLOSE 1VG001, Standby Gas Treatment Suction from Reactor Building Atmosphere
| |
| * Direct above actions 201.011 US
| |
| * Enter Tech Spec 3.6.4.3, condition A, RA A.1 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 12 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 3
| |
| | |
| == Description:==
| |
| SBGTS Low Flow after Auto-start Simulator Operator Actions When directed by the Lead Release Event 3 Evaluator Simulator Operator Role Play As IMD, if asked to investigate the SBGT initiation, report, that we report to the control room.
| |
| Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When SBGT is secured and Tech Spec call has been made and at the discretion of the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 13 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 4
| |
| | |
| == Description:==
| |
| Loss of A Rod Control Management System Interface Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: none Expected Annunciator: 1H13-P603-A511, RWLCS Key Parameter Response: loss of transponder power Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Per LOA-RM-101
| |
| * CHECK Core Map, Rod Select Display and Status Display all indicate NO DATA AVAILABLE
| |
| * EXIT to LOP-RM-03
| |
| * Per LOP-RM-03
| |
| * At the MAINTENANCE Display, panel 1H13-P659, PLACE the SYSTEM SELECT Switch as follows: BYPASS A to bypass RCMS Interface Unit A 47.013 ATC
| |
| * If Transponder Power has been turned OFF, PERFORM the following:
| |
| * At the ROD SELECT Display, or STATUS Display, whichever is in CONTROL Mode, NAVIGATE to the SET CHAN PARAMETERS screen
| |
| * SELECT the desired Transponder Power, LEFT CORE HALF (L1) or RIGHT CORE HALF (R1) using the UP/DOWN arrows.
| |
| * SELECT ON using the RIGHT/LEFT arrows
| |
| * PRESS ACCEPT to change transponder power to ON
| |
| * ACKNOWLEDGE any screen message
| |
| * Monitor plant parameters and update the crew as required BOP
| |
| * Provide peer checks as required 47.013 US
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 14 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 4
| |
| | |
| == Description:==
| |
| Loss of A Rod Control Management System Interface Simulator Operator Actions When directed by the Lead Release Event 4 Evaluator When directed by the crew to take Bypass A to bypass Release BYPASS A RCMS Interface RCMS Interface Unit A Simulator Operator Role Play As the EO sent to AEER, when ordered to Bypass A RCMS Interface, wait 2minutes, preform the above action and report back, RCMS Interface Unit A is in Bypass A.
| |
| Respond as required Floor Instructor Notes/OPEX/TRs Note: none Terminus: When transponder power has been restored and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 15 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 5
| |
| | |
| == Description:==
| |
| Control Room Ventilation Radiation Monitor Fails Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: none Expected Annunciator: 1PM13J-B401, Control Room HVAC or Radwaste Reboiler Steam Outlet High Radiation or Instrument Failure (r1387)
| |
| Key Parameter Response:
| |
| Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Monitor plant parameters and update the crew as required 117.016 ATC
| |
| * Provide peer checks as required Per LOR-1PM13J-B401
| |
| * CHECK alarm typer printout to determine if alarm is due to Control Room HVAC High Radiation, Reboiler High Radiation, or Rad Instrument Failure BOP
| |
| * If alarm is due to a failed instrument:
| |
| * VERIFY affected instrument is energized per LOP-PR-01E
| |
| * SEE LOA-PR-101, Unit 1 Process Radiation Monitoring System Abnormal 117.016
| |
| * Direct above actions 201.011 US
| |
| * Enter Tech Spec 3.3.7.1, condition A, RA A.1 and A.2 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 16 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 5
| |
| | |
| == Description:==
| |
| Control Room Ventilation Radiation Monitor Fails Simulator Operator Actions When directed by the Lead Release Event 5 Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Note: The Control Room Air Intake RadiationHigh Function consists of eight independent monitors, with four monitors associated with one CRAF subsystem and the other four monitors associated with the other CRAF subsystem. Each of the four monitors associated with a CRAF subsystem are arranged in two trip systems, with each trip system containing two radiation monitors.
| |
| Terminus: When the Tech Spec call has been made and at the discretion of the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 17 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 6
| |
| | |
| == Description:==
| |
| Upscale failure of the MDRFP Flow Instrument Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: None Expected Annunciator: 1H13-P603-A511, RWLCS Trouble Key Parameter Response: Lowering Reactor Level Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Per LOR-1H13-P603-A511
| |
| * At the 1DS001 Operation Station Event List, Check alarm message
| |
| * If alarm message is "Dev Header/Pump Flow" then CHECK for failing reactor feed pump discharge flow signal
| |
| * If a Reactor feed pump discharge flow signal has failed:
| |
| * VERIFY the corresponding reactor feed pump minflow M/A station is in manual
| |
| * POSITION the corresponding reactor feed pump minflow as required for plant conditions 31.013 ATC
| |
| * REFER to LOP-FW-16 to determine cause of alarm and required actions OR Per LOP-FW-16
| |
| * If a feedwater pump discharge flow indicator has failed
| |
| * VERIFY the affected feedwater pump minflow valve is in Manual control
| |
| * VERIFY affected minflow valve is positioned properly for plant conditions
| |
| * Monitor plant parameters and update the crew as required BOP
| |
| * Provide peer checks as required
| |
| * Direct above actions 31.013 US
| |
| * Set manual scram criteria RPV level is 20 to 50 and/or IN CONTROL SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 18 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 6
| |
| | |
| == Description:==
| |
| Upscale failure of the MDRFP Flow Instrument Simulator Operator Actions When directed by the Lead Release Event 6 Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When level is stable and MDRFP Min Flow Valve M/A station is in manual and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 19 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 7
| |
| | |
| == Description:==
| |
| High Vibrations on Main Turbine Bearings Requiring Manual Trip of Turbine; One Output Breaker Fails to Open Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: None Expected Annunciator: 1PM02J-A401, U1 Turbine Generator Vibration High 1PM02J-B405, U1 Turbine Generator Vibration Hi Hi Key Parameter Response: Rising Turbine Vibes Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Monitor plant parameters and update the crew as required ATC
| |
| * Provide peer checks as required Per LOA-TG-101
| |
| * CHECK Vibration levels - REFER to the limits identified in Attachment A
| |
| * At direction of Unit Supervisor REDUCE Reactor power
| |
| * If bearing vibration limits exceed Attachment A then MANUALLY trip the main turbine
| |
| * CHECK Turbine Bypass Valves - controlling Reactor pressure 71.028 71.030 BOP
| |
| * CHECK Turbine - TRIPPED
| |
| * START 1TG09P, Emer Brg Oil Pmp
| |
| * At either EHC Workstation on Speed-Load screen, from control menu, CHECK Speed Cmd - CLOSE VALVES
| |
| * CHECK Generator OCBs 9-10 and 10 OPEN
| |
| * CHECK Generator field breaker - OPEN 71.028 71.030 US
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 20 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 7
| |
| | |
| == Description:==
| |
| High Vibrations on Main Turbine Bearings Requiring Manual Trip of Turbine; One Output Breaker Fails to Open Simulator Operator Actions When directed by the Lead Release Event 7 Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 21 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 8
| |
| | |
| == Description:==
| |
| Large steam leak in Main Steam Tunnel with fuel failure Initiation: Continued Cues:
| |
| Automatic Actions: none Expected Annunciator: Multiple Key Parameter Response: Rising secondary containment radiation levels and temperatures Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Performs Reactor Scram and LGP 3-2 (CT)
| |
| * ARM and DEPRESS Scram Pushbuttons
| |
| * PLACE Reactor Mode Switch in SHUTDOWN
| |
| * INSERT SRMs
| |
| * CHECK Control Rods INSERTED and Power Decreasing 304.010
| |
| * INFORM Unit Supervisor of Control Rod Status and Reactor Power 413.000 ATC
| |
| * Operate Feedwater and/or ECCS as necessary to maintain RPV Water Level 427.000 20" to 50" or as specified by Unit Supervisor
| |
| * Place LFFRV in AUTO
| |
| * REPORT to the Unit Supervisor the status of RPV Level and Pressure
| |
| * If needed for level control:
| |
| * Place the FRV in AUTO
| |
| * STABILIZE Reactor Pressure <1020 psig
| |
| * Collect LGA-002 data 427.000 BOP
| |
| * Update the crew of changing secondary containment conditions
| |
| * Enter LGA-002 304.010
| |
| * Direct manual scram on 1 area aproaching Max Safe level and not able to be 413.000 US 427.000 isolated at power (CT)
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 22 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 8
| |
| | |
| == Description:==
| |
| Large steam leak in Main Steam Tunnel with fuel failure Simulator Operator Actions When directed by the Lead Release Event 8 Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 23 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 9
| |
| | |
| == Description:==
| |
| Close MSIVs to stop the leak but both A loop MSIVs fail open Initiation: Continued Cues:
| |
| Automatic Actions: none Expected Annunciator: Multiple Key Parameter Response: Rising secondary containment radiation levels and temperatures Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Monitor plant parameters and update the crew as required 427.000 ATC
| |
| * Provide peer checks as required
| |
| * Maintain reactor water level per LGA-001 Per LGA-002
| |
| * Reactor Building Vent. isolated or should have isolated on Reactor Building Hi-Hi radiation
| |
| * Isolate all discharges into affected areas except systems needed for:
| |
| 427.000 BOP
| |
| * Damage control
| |
| * LGA actions
| |
| * Monitor radiation release limits for potential entry into LGA-009, Radioactivity Release Control
| |
| * Direct above actions 427.000 US
| |
| * Direct LGA-002 actions
| |
| * Direct leak isolation SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 24 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 9
| |
| | |
| == Description:==
| |
| Close MSIVs to stop the leak but both A loop MSIVs fail open Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 25 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 10
| |
| | |
| == Description:==
| |
| Turbine building dampers 1VT79YA/B/C Fail OPEN, High Off-site Release/ RPV Blowdown Initiation: Continued Cues:
| |
| Automatic Actions: none Expected Annunciator: Multiple Key Parameter Response: Rising WRGM release rates Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Monitor plant parameters and update the crew as required ATC
| |
| * Provide peer checks as required
| |
| * Maintain reactor water level per LGA-001 Per LGA-009
| |
| * Isolate all primary system discharges outside primary and secondary containments except systems needed for other LGA actions
| |
| * DETERMINE Offsite release rate trending toward GSEP General Emergency level 426.000 BOP Per LGA-004 428.000
| |
| * Prevent LPCS and LPCI injection not needed for core cooling
| |
| * CHECK suppression pool level above -18 feet
| |
| * Initate ADS
| |
| * VERIFY 7 ADS valves open
| |
| * Leave SRVs open. Allow RPV to depressurize 426.000
| |
| * Direct above actions 428.000 US
| |
| * Anounce entry into LGA-009 and LGA-004 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 26 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 Event - 10
| |
| | |
| == Description:==
| |
| Turbine building dampers 1VT79YA/B/C Fail OPEN, High Off-site Release/ RPV Blowdown Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Reactor is depressurized and RPV level controlled in the normal shutdown RPV Level band SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 27 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 REFERENCES Procedure Rev Title
| |
| : 1. INPO 15-004 Operations Fundamentals
| |
| : 2. SOER 10-2 Engaged, Thinking Organizations
| |
| : 3. LOR-1PM07J-A301 3 Standby Gas Treatment System Manual Initiation
| |
| : 4. LOR-1PM07J-A401 3 Standby Gas Treatment System Primary Fan Flow High-Low
| |
| : 5. LOR-1PM13J-B401 9 Control Room HVAC or Radwaste Reboiler Steam Outlet High Radiation or Instrument Failure
| |
| : 6. LOR-1H13-P603- 2 RWLCS A511
| |
| : 7. LOR-1PM02J-A401 2 U1 Turbine Generator Vibration High
| |
| : 8. LOA-AR-101 5 Area Radiation Monitoring System Abnormal
| |
| : 9. LOA-RM-101 23 Unit 1 RCMS Abnormal Situations
| |
| : 10. LOA-TG-101 22 Unit 1 Turbine Generator
| |
| : 11. LOP-FW-16 37 1 and 2DS001 Operator Station Alarm Message Interpretation
| |
| : 12. LOP-RL-01 26 Operation of the Reactor Level Control System
| |
| : 13. LOP-RM-05 7 RCMS Power Supplies and Transfers
| |
| : 14. LOP-TG-02 84 Turbine Generator Startup
| |
| : 15. LGP-3-2 75 Reactor Scram
| |
| : 16. LGP-3-1 70 Power Changes
| |
| : 17. LGP-1-1 126 Normal Unit Startup
| |
| : 18. LGA-001 18A RPV Control
| |
| : 19. LGA-002 9 Secondary Containment Control
| |
| : 20. LGA-004 9 RPV Blowdown
| |
| : 21. LGA-009 8 Radioactive Release Control
| |
| : 22. OP-LA-101-111-1002 81 LaSalle Operations Philosophy Handbook.
| |
| : 23. OP-LA-103-102-1002 21 Strategies for Successful Transient Mitigation SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 28 of 29
| |
| | |
| 19-1 NRC Exam Scenario 3 Revision 00 U1 SUPERVISOR TURNOVER Shift: Days Date: Today Mode: 1 OLR: Green Work Week: Div 2 Unit 1 power level Unit 2 power level
| |
| * 10 % Power
| |
| * 100 % Power
| |
| * LGP-1-1 Startup In-progress
| |
| * U1 Thermal Limit Issues /Power Evolutions U2 Thermal Limit Issues /Power Evolutions
| |
| * None
| |
| * None Existing LCOs, date of next surveillance Existing LCOs, date of next surveillance
| |
| * None
| |
| * None LOSs in progress or major maintenance LOSs in progress or major maintenance
| |
| * None
| |
| * None Equipment removed from service or currently unavailable
| |
| * None
| |
| * None Grid Status is Green Comments, evolutions, problems, etc. Comments, evolutions, problems, etc.
| |
| * Perform LGP-1-1, step E.7.4 IAW LOP-TG-
| |
| * Non-Div Workweek. OLR is Green 02, step E.24
| |
| * Raise reactor power to 15% per LGP-1-1, step E.7.6 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 29 of 29
| |
| | |
| LaSalle County Station LICENSED OPERATOR EVALUATED SCENARIO GUIDE 19-1 NRC Exam Scenario 4 Rev. 00
| |
| | |
| 19-1 NRC Exam Scenario 4 Revision 00 Facility: LaSalle County Generating Station Scenario #: 19-1 NRC Exam Scenario 4 PURPOSE Examine the ILT candidates ability to operate the plant in normal, abnormal, and emergency conditions.
| |
| | |
| ==SUMMARY==
| |
| OF EVENTS
| |
| : 1. The crew will swap from 1B WT pump to 1A WT pump per LOP-WT-02.
| |
| : 2. The 1A RT Pump will trip requiring the crew perform a 5 minute flush and start the 1B RT pump per LOA-RT-101 and LOP-RT-02.
| |
| : 3. HPCS will spuriously start due to a failure of the Level 2 instrumentation and the crew will secure HPCS and enter Tech Specs.
| |
| : 4. A loss bus 138 due to a contractor knocking the breaker, the crew will re-energize bus 138.
| |
| : 5. A failure of the level instrumentation will cause the 16A heater to isolate and the crew to reduce power per LOA-HD-101.
| |
| : 6. A leak in the motor of the 1A RR pump will require the crew to trip the RR pump and enter Tech Specs.
| |
| : 7. A large break in the feedwater system inside the drywell with a bypass path will cause the crew to scram and take action per LGA-001 and LGA-003.
| |
| : 8. With a scram required, RPS B will fail, requiring the crew to insert rods using ARI.
| |
| : 9. With ECCS signals present, LPCS will fail to auto start, requiring the crew to manually start LPCS to maintain RPV level.
| |
| Critical Tasks
| |
| : 1. In LGA-003, Primary Containment Control, with suppression chamber pressure above 12 psig, containment flood level below 722 feet, and drywell parameters below the Drywell Spray Initiation Limit; trip all recirculation pumps and start drywell sprays using RHR pumps not needed for adequate core cooling prior to 60 psig drywell pressure.
| |
| : 2. With a Scram signal present and the reactor not shutdown, commence inserting control rods (ARI) prior to Suppression Pool temperature exceeding 110 degrees F.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 2 of 27
| |
| | |
| 19-1 NRC Exam Scenario 4 Revision 00 TRAINING REQUESTS (if applicable)
| |
| : 1. None OPEX (if applicable)
| |
| : 1. None Operator Fundamentals
| |
| : 1. Monitoring plant indications and conditions closely
| |
| : 2. Controlling plant evolutions precisely
| |
| : 3. Operating the plant with a conservative bias
| |
| : 4. Working effectively as a team
| |
| : 5. Having a solid understanding of plant design, engineering principles, and sciences SOER 10-2
| |
| : 1. Supervisory oversight role
| |
| : 2. Recognition and mitigation of risk
| |
| : 3. Worker performance
| |
| : 4. Tolerance of repetitive/long standing issues and degradation of standards
| |
| : 5. Operating Experience Record of Revisions (Summary)
| |
| Rev. 0 Developed new for the ILT 19-1 NRC Exam SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 3 of 27
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| 19-1 NRC Exam Scenario 4 Revision 00 INITIAL SIMULATOR SETUP/ REQUIRED DOCUMENTATION
| |
| : 1. Recall a full power IC 201 Password 0201
| |
| : 2. Place simulator in RUN
| |
| : 3. Load and run the SmartScenario file NRC 19-1 Scenario 4.ssf
| |
| : 4. Update the Tech Spec Timeclock Sheet as follows:
| |
| TS/TRM/ODCM System/ Required REQUIRED ACTION Completion Expiration Component Action Description Time Date/Time N/A N/A N/A N/A N/A N/A
| |
| : 5. Perform the pre-scenario checklist (TQ-LA-150-0308)
| |
| SCENARIO OUTLINE (NRC Evaluations Only)
| |
| Event Malf. Event Event No. No. Type* Description Shift running Turbine Building Closed Cooling Water (TBCCW) 1 None N (BOP) from the B Pump to the A Pump 1A RWCU Recirc Pump Auto Trip (Instantaneous overcurrent) 2 MRW001 C (ATC) and Startup of 1B RT Recirc Pump I (BOP) HPCS Spurious Initiation; SRO enters TS 3.5.1, Condition B and 3 MNB078 T (SRO) TS 3.3.5.1 Conditions A and B 4 K6L09JT8 C (BOP) Loss of Bus 138 VRHT59A Emergency Power Reduction due to a Loss of Feedwater Heating 5 D R (ATC) 16A Heater High Level Switch Failure R0591 C (ATC) Motor Cooler Leak on 1A RR Pump Results in the Crew Manually 6 R0593 T (SRO) Tripping the Pump; SRO enters TS 3.4.1, Condition C Unisolable Feedwater Rupture Inside Primary Containment.
| |
| Rupture will be large enough to de-pressurize the RPV and lower 7 MCF034 M (ALL) level. A suppression chamber to drywell bypass pathway will occur.
| |
| 8 MRP018 C (ATC) Electrical ATWS, ARI Successful 9 MES039 C (BOP) Low Pressure Core Spray Fails to Auto Actuate
| |
| * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (T)echnical Specification APPROXIMATE SCENARIO RUN TIME 90 Minutes SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 4 of 27
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| 19-1 NRC Exam Scenario 4 Revision 00 GENERAL OBJECTIVE: (USED THROUGHOUT THIS EXERCISE)
| |
| During performance of tasks, dynamic learning activities, or formal evaluations, 769.00.01 demonstrate applicable Human Performance behaviors IAW the appropriate procedures.
| |
| Given an operating experience document, paraphrase the lessons learned and 762.04.00 methods to prevent recurrence at LaSalle Station, as described in the training material.
| |
| During performance of tasks, apply the administrative requirements of PROCEDURE 614.010 USE AND ADHERENCE EXPECTATIONS, IAW station procedures.
| |
| TASKS RO - ATC Given Unit Supervisor authorization, perform the Control Room actions to respond to a loss of one 22.015 or both RR pumps, IAW station procedures.
| |
| Given Unit Supervisor authorization, respond to a heater Hi/Lo Level alarm, IAW station 079.017 procedures.
| |
| Provided initial conditions, respond to an automatic heater string isolation at power, IAW station 079.020 procedures.
| |
| 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 413.000 59.5 IAW LGA-001 Given entry in LGA-010, Failure to Scram, evaluate plant conditions and shutdown the reactor, 431.000 IAW station procedures.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 5 of 27
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| | |
| 19-1 NRC Exam Scenario 4 Revision 00 RO - BOP/ASSIST 4.009 Provided initial conditions, Respond to a loss of a 480 VAC ESS bus, IAW station procedures.
| |
| Given Unit Supervisor authorization, Perform the Main Control Room actions to Warm Up, 27.001 Flush and Startup the Reactor Water Cleanup (RWCU) System, IAW station procedures.
| |
| Given Unit Supervisor authorization, perform Control Room actions to shutdown HPCS after an 61.006 Auto Initiation, IAW station procedures.
| |
| Given Unit Supervisor authorization, respond to a heater Hi/Lo Level alarm, IAW station 079.017 procedures.
| |
| Provided initial conditions, respond to an automatic heater string isolation at power, IAW station 079.020 procedures.
| |
| Given Unit Supervisor authorization, perform the Main Control Room actions to swap Turbine 113.004 Building Closed Cooling Water (TBCCW) Pumps, IAW station procedures.
| |
| Given LGA-003, Primary Containment Control in progress, spray the Suppression Pool, IAW 419.020 station procedures.
| |
| Given LGA-003, Primary Containment Control in progress, spray the Drywell, IAW station 419.030 procedures.
| |
| 421.010 Given plant conditions, cool the Suppression Pool, IAW Station Procedures.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 6 of 27
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| | |
| 19-1 NRC Exam Scenario 4 Revision 00 SRO - UNIT SUPERVISOR 4.009 Provided initial conditions, Respond to a loss of a 480 VAC ESS bus, IAW station procedures.
| |
| Given Unit Supervisor authorization, perform the Control Room actions to respond to a loss of one 22.015 or both RR pumps, IAW station procedures.
| |
| Given Unit Supervisor authorization, Perform the Main Control Room actions to Warm Up, Flush 27.001 and Startup the Reactor Water Cleanup (RWCU) System, IAW station procedures.
| |
| Given Unit Supervisor authorization, perform Control Room actions to shutdown HPCS after an 61.006 Auto Initiation, IAW station procedures.
| |
| Given Unit Supervisor authorization, respond to a heater Hi/Lo Level alarm, IAW station 079.017 procedures.
| |
| Provided initial conditions, respond to an automatic heater string isolation at power, IAW station 079.020 procedures.
| |
| Given Unit Supervisor authorization, perform the Main Control Room actions to swap Turbine 113.004 Building Closed Cooling Water (TBCCW) Pumps, IAW station procedures.
| |
| 304.010 Given Unit Supervisor authorization, perform actions for a reactor scram IAW station procedures Given LGA-01, RPV Control, in progress, evaluate plant conditions and control RPV level +11 to 413.000 59.5 IAW LGA-001 Given LGA-003, Primary Containment Control in progress, spray the Suppression Pool, IAW 419.020 station procedures.
| |
| Given LGA-003, Primary Containment Control in progress, spray the Drywell, IAW station 419.030 procedures.
| |
| 421.010 Given plant conditions, cool the Suppression Pool, IAW Station Procedures.
| |
| Given entry in LGA-010, Failure to Scram, evaluate plant conditions and shutdown the reactor, 431.000 IAW station procedures.
| |
| Given a set of plant conditions, identify and prepare the Technical Specification required actions 201.011 IAW Tech Specs.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 7 of 27
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| | |
| 19-1 NRC Exam Scenario 4 Revision 00 Event - 1
| |
| | |
| == Description:==
| |
| Shift running Turbine Building Closed Cooling Water (TBCCW) from the B Pump to the A Pump Initiation: Following the crew assuming the shift Cues: Turnover Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Monitor plant condtions and update the crew as required ATC
| |
| * Provide peer checks as required Per LOP-TG-02
| |
| * START idle A Turbine Building Closed Cooling Water Pump, 1WT01PA.
| |
| * At panel 1PM10J, OBSERVE pressure increase on TBCCW Pump discharge 119.014 BOP pressure indicator 1PI-WT008
| |
| * STOP B Turbine Building Closed Cooling Water Pump, 1WT01PB
| |
| * OBSERVE TBCCW Pump discharge pressure returns to approximately same pressure prior to pump shifting 119.014 US
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 8 of 27
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| | |
| 19-1 NRC Exam Scenario 4 Revision 00 Event - 1
| |
| | |
| == Description:==
| |
| Shift running Turbine Building Closed Cooling Water (TBCCW) from the B Pump to the A Pump Simulator Operator Actions none Simulator Operator Role Play As the EO in the field, when ordered to vent the 1A WT pump, report the 1A WT pump has been vented. (E.2.2)
| |
| As the EO in the field, when ordered to ensure cooling of all running SACs, wait 1 minute and report, All SACs are being properly cooled. (E.2.6)
| |
| Respond as required.
| |
| Floor Instructor Notes/OPEX/TRs Terminus: When 1A WT pump is running with 1B WT pump secured and at the discretion of the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 9 of 27
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| | |
| 19-1 NRC Exam Scenario 4 Revision 00 Event - 2
| |
| | |
| == Description:==
| |
| 1A RWCU Recirc Pump Auto Trip (Instantaneous overcurrent) and Startup of 1B RT Recirc Pump Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: 1A RT Pump Trips Expected Annunciator:
| |
| 1H13-P602-A206, Reactor Water Cleanup Recirculation Pumps 1G33-C001A/B Flow Low 1H13-P602-B103, Reactor Water Cleanup Filter Demineralizer Trouble 1H13-P602-A106, Reactor Water Cleanup Recirculation Pump 1G33-C001A Automatic Trip Key Parameter Response: Lowering RT flow Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Per LOA-RT-101
| |
| * CHECK RWCU -NOT ISOLATED
| |
| * FLUSH system piping to the Main Condenser as follows:
| |
| * CLOSE 1G33-F042, RWCU Return Upstrm Isol Vlv
| |
| * OPEN 1G33-F034, RWCU Reject to Main Condenser Vlv
| |
| * OPEN 1G33-F033, RWCU Reject Flow Control Valve to establish 100 -150 gpm flow
| |
| * After 5 minutes of flow to the Main Condenser, thenCLOSE 1G33-F033, RWCU 303.020 ATC Reject Flow Control Valve
| |
| * CLOSE 1G33-F034, RWCU Reject to Main Condenser Vlv
| |
| * START Standby RWCU Pump per LOP-RT-02 Per LOP-RT-02
| |
| * VERIFY RBCCW valved in to RWCU pump heat exchanger
| |
| * SEND an operator to the RWCU pump rooms to VERIFY the following and standby for pump start
| |
| * START the standby RWCU Recirc pump, 1G33-C001B
| |
| * Monitor plant condtions and update the crew as required 303.020 BOP
| |
| * Provide peer checks as required 303.020 US
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 10 of 27
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| 19-1 NRC Exam Scenario 4 Revision 00 Event - 2
| |
| | |
| == Description:==
| |
| 1A RWCU Recirc Pump Auto Trip (Instantaneous overcurrent) and Startup of 1B RT Recirc Pump Simulator Operator Actions When directed by the Lead Release Event 2 Evaluator Simulator Operator Role Play If asked as the Ops Director, if B RT pump is authorized per LOP-RT-02, report, B RT pump is not an FME concern and is authorized. (E.3.1)
| |
| As the EO in the field, if asked if WR is lined up to B RT Pump, report, WR is lined up to 1B RT pump. (E.3.2)
| |
| As the EO in the field, if asked if B RT Pump is lined up, report, 1B RT Pump is lined up for operation per LOP-RT-02 step E.3.2.
| |
| As the EO in the field, if asked what casing temperature is, report, 1B RT pump casing temperature is 450 degrees. (E.3.3)
| |
| As the EO in the field, if asked the status of post start checks, report, post start checks are SAT.
| |
| Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When 1B RT pump is running and per the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 11 of 27
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| | |
| 19-1 NRC Exam Scenario 4 Revision 00 Event - 3
| |
| | |
| == Description:==
| |
| HPCS Spurious Initiation Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: HPCS Pump and 1B Diesel Generator start Expected Annunciator:
| |
| 1H13-P601-A201, HPCS Diesel Generator 1B Engine Running 1H13-P601-A205, HPCS System Actuated 1H13-P601-A208, Reactor Vessel Water Level 2 Lo-Lo 1H13-P601-A308, Reactor Vessel Water Level 2 Lo-Lo Key Parameter Response: Rising Reactor Water Level Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Per LOA-PWR-101
| |
| * CHECK RPS setpoints NOT exceeded
| |
| * CHECK Reactor Power is < 100% RTP (3546 MWt)
| |
| * REDUCE Power to < 100% RTP by using RR FCVs or Control Rods
| |
| * CHECK Reactor Pressure is LESS than 1005 psig ATC
| |
| * CHECK Reactor Power and core flow - OUTSIDE REGIONs 1 & 2 of the Power to Flow Map
| |
| * CHECK FCL is LESS than MELLLA (113.2% FCL) on the Power to Flow Map (Attachment A in LOA-RR-101)
| |
| * RUN OD-20
| |
| * CHECK the following rad indications NORMAL
| |
| * NOTIFY Chemistry to sample reactor coolant for iodine activity Per LOR-1H13-P601-A205/208/308
| |
| * CHECK Reactor Vessel Water Level indication on panels 1H13-P601 and 1H13-P603
| |
| * If Shutdown of HPCS after Auto Initiation is required, REFER to LOP-HP-04 Per LOR-1H13-P601-A201
| |
| * DETERMINE cause for start of Diesel Generator 1B o If appropriate, SHUTDOWN Diesel Generator 1B per LOP-DG-03, Diesel Generator Shutdown 61.006 BOP Per LOA-PWR-101
| |
| * If there is a spurious HPCS injection, IMMEDIATELY SHUTDOWN HPCS
| |
| * VERIFY lineup of HPCS with LOP-HP-04, Shutdown of HPCS After an Automatic Initiation Per LOP-HP-04
| |
| * CLOSE 1E22-F004, HPCS Injection Line Isolation
| |
| * VERIFY CLOSED 1E22-F012, HPCS Pump Minimum Flow Stop o When plant conditions permit, PLACE the HPCS system in standby per LOP-HP-03
| |
| * Direct above actions
| |
| * Enter Tech Spec 3.3.5.1 61.006
| |
| * Condition A, RA A.1 201.011 US
| |
| * Condition B, RA B.2 and B.3 o Enter Tech Spec 3.5.1 o Condition B, RA B.1 and B.2 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 12 of 27
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| | |
| 19-1 NRC Exam Scenario 4 Revision 00 Event - 3
| |
| | |
| == Description:==
| |
| HPCS Spurious Initiation Simulator Operator Actions When directed by the Lead Release Event 3 Evaluator Simulator Operator Role Play As the EO sent to investigate the instrument racks for HPCS, wait 2 minutes and report, All level 2 instruments look like they tripped.
| |
| Respond as required Floor Instructor Notes/OPEX/TRs NOTE: Per Tech Spec 3.3.5.1, required action B.2, HPCS must be declared INOP within 1 hour.
| |
| This means that Tech Spec 3.5.1 does not have to be entered until the 1 hour time clock is complete but may be declared prior.
| |
| Terminus: When SBGT is secured and Tech Spec call has been made and at the discretion of the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 13 of 27
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| | |
| 19-1 NRC Exam Scenario 4 Revision 00 Event - 4
| |
| | |
| == Description:==
| |
| Loss of Bus 138 Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: Bus 138 de-energizes Expected Annunciator: 1PM01J-B505, 480V Bus 132X/Y 134X/Y 138 Undervoltage (R0943 480V Bus 138 Voltage Lo)
| |
| Key Parameter Response: None Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Monitor plant parameters and update the crew as required ATC
| |
| * Provide peer checks as required Per LOR-1PM01J-B505
| |
| * DETERMINE which Bus has undervoltage condition by checking alarm typer 5.009 BOP
| |
| * DISPATCH operator to INVESTIGATE cause of alarm
| |
| * CORRECT cause of alarm and REENERGIZE Bus if possible 5.009 US
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 14 of 27
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| | |
| 19-1 NRC Exam Scenario 4 Revision 00 Event - 4
| |
| | |
| == Description:==
| |
| Loss of Bus 138 Simulator Operator Actions When directed by the Lead Release Event 4 Evaluator Simulator Operator Role Play As the EO sent to investigate the loss of bus 138, wait 2 minutes and report, A contractor says they bumped the breaker, there is no damage to the bus.
| |
| Respond as required Floor Instructor Notes/OPEX/TRs Note: none Terminus: When bus 138 is re-energized and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 15 of 27
| |
| | |
| 19-1 NRC Exam Scenario 4 Revision 00 Event - 5
| |
| | |
| == Description:==
| |
| Loss of Feedwater Heating 16A Heater High Level Switch Failure Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: 16A Heater Isolates Expected Annunciator:
| |
| 1PM03J-B101, High Pressure Heater 16A/B Level High 1PM03J-B201, High Pressure Heater 16 Spill Valve Open 1PM03J-B401, High Pressure Heater 16 Extraction Steam Check Valve Not Open Key Parameter Response: Lower CD/CB Suction Header Pressure Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Per LOA-HD-101
| |
| * REDUCE Reactor Power as necessary without entering Region 2 o Reduce RR Flow 079.017 o INSERT CRAM Arrays, if available 079.020 ATC o INSERT control rods continuing from the back of the sequence
| |
| * MONITOR feedwater temperature
| |
| * REDUCE core flow at least 5 Mlbs/hr for every 10F feedwater temperature drops below the nominal temperature curve Per LOA-HD-101
| |
| * For any heater with a HIGH HIGH Level Trip, VERIFY CLOSED o ES Supply 079.017 079.020 BOP or o ES Non-Return Check
| |
| * CHECK Main Turbine - ON LINE
| |
| * CHECK all 13A/B/C heaters are on line 079.017 079.020 US
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 16 of 27
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| | |
| 19-1 NRC Exam Scenario 4 Revision 00 Event - 5
| |
| | |
| == Description:==
| |
| Loss of Feedwater Heating 16A Heater High Level Switch Failure Simulator Operator Actions When directed by the Lead Release Event 5 Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When reactor power has been reduced with the plant stable and at the discretion of the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 17 of 27
| |
| | |
| 19-1 NRC Exam Scenario 4 Revision 00 Event - 6
| |
| | |
| == Description:==
| |
| Motor Cooler Leak on 1A RR Pump Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: None Expected Annunciator: 1H13-P602-A304, RR 1A Motor Cooling Water Flow Low OR Motor Winding Cooler Leakage Key Parameter Response: None Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Per LOR-1H13-P602-A304
| |
| * The pump should be TRIPPED immediately if any of the following are met:
| |
| * Leakage into the windings occur:
| |
| 22.015 ATC
| |
| * both R pts are received
| |
| * REFER to LOA-RR-101, Reactor Recirc System Abnormal
| |
| * MONITOR abnormal trends or parameters until problem has been fully evaluated
| |
| * Monitor plant parameters and update the crew as required BOP
| |
| * Provide peer checks as required 022.015
| |
| * Direct above actions 201.011 US
| |
| * Enter Tech Spec 3.4.1, condition C, RA C.1 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 18 of 27
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| | |
| 19-1 NRC Exam Scenario 4 Revision 00 Event - 6
| |
| | |
| == Description:==
| |
| Motor Cooler Leak on 1A RR Pump Simulator Operator Actions When directed by the Lead Release Event 6 Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: When the Tech Spec call has been made and at the discretion of the Lead Evaluator SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 19 of 27
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| | |
| 19-1 NRC Exam Scenario 4 Revision 00 Event - 7
| |
| | |
| == Description:==
| |
| Unisolable Feedwater Rupture Inside Primary Containment Initiation: Per Lead Evaluator Cues:
| |
| Automatic Actions: None Expected Annunciator: 1H13-P603-B501, Primary Containment Pressure Hi/Lo Key Parameter Response: Rising Containment Pressure and deviation between MS and FW Flow.
| |
| Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Performs Reactor Scram and LGP-3-2
| |
| * ARM and DEPRESS Scram Pushbuttons 304.010
| |
| * PLACE Reactor Mode Switch in SHUTDOWN 413.000 ATC
| |
| * INSERT SRMs
| |
| * CHECK Control Rods INSERTED and Power Decreasing Per LGA-RH-103
| |
| * Place Div 1/2 Inj Override Switch to NON-ATWS
| |
| * Div I: With an ECCS signal present Verify White Manual Override light for 1E12-F042A AND 1E21-F005 Illuminated
| |
| * Div II: With an ECCS signal present Verify White Manual Override light for 1E12-F042B AND 1E12-F042C Illuminated Per LGA-RH-103
| |
| * When directed places Suppression Pool Cooling in service:
| |
| * Startup RHR Service Water as follows:
| |
| * OPEN 1A/1B RHR Hx Service Water Outlet Valve: 1E12-F068A/B
| |
| * At approximately 9 to 10 seconds after taking the 1E12-F068A/B switch to OPEN, START first RHR Service Water Pump: 1A or 1B/C or D
| |
| * When indicated flow reaches 3000 gpm, START second RHR Service Water Pump.
| |
| 419.020
| |
| * Startup RHR 419.030 BOP 421.010
| |
| * Start 1A/1B RHR Pump
| |
| * Establish RHR flow of 1500 to 7450 gpm:
| |
| * Throttle 1E12-F024A/B (Test Valve) OPEN.
| |
| * Close 1E12-F048A/B (HX Bypass)
| |
| * Place A/B HTX Bypass Throttle/Seal in switch to THROTTLE and THROTTLE CLOSED 1E12-F048A/B.
| |
| * Place A/B HTX Bypass Throttle/Seal in switch to SEAL IN and CLOSE 1E12-F048A/B
| |
| * When directed establish Suppression Chamber Spray:
| |
| * VERIFY 1A/1B RHR Pump is running
| |
| * OPEN 1E12-F027A/B
| |
| * When directed establish Drywell Spray: (CT)
| |
| * VERIFY 1A/1B RHR Pump is running
| |
| * THROTTLE 1E12-F024A/B CLOSED
| |
| * OPEN:1E12-F016A/B and 1E12-F017A/B 304.010
| |
| * May direct a manual reactor scram prior to reaching 1.93 psig in the Drywell 413.000
| |
| * Enters and directs actions of LGA-001 LEVEL LEG 419.020 US
| |
| * Establishes a RPV water level band of 20 to +50 inches 419.030
| |
| * Enters and directs actions of LGA-001 PRESSURE LEG 421.010 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
| |
| Page 20 of 27
| |
| | |
| 19-1 NRC Exam Scenario 4 Revision 00
| |
| * STABILIZE Reactor Pressure below 1059 psig
| |
| * When Drywell Pressure exceeds 1.93 psig, enters and directs actions of LGA-003
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| * Before Suppression Chamber Pressure exceeds 12 psig
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| * Verifies Containment Flood level below 723 ft.
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| * Directs start of Suppression Chamber Sprays
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| * When Suppression Chamber Pressure exceeds 12 psig, direct initiation of Drywell sprays
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| * Verifies Containment Flood level below 722 ft.
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| * Verifies Drywell Pressure and Temperature permit Drywell Sprays per Figure D
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| * Verifies both Recirc Pumps are tripped
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| * Direct initiation of Drywell sprays (CT)
| |
| * When Suppression Pool temperature exceeds 105ºF initiation of direct initiation of Suppression Pool Cooling Event - 7
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| | |
| == Description:==
| |
| Unisolable Feedwater Rupture Inside Primary Containment Simulator Operator Actions When directed by the Lead Release Event 7 Evaluator Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 21 of 27
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| 19-1 NRC Exam Scenario 4 Revision 00 Event - 8
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| | |
| == Description:==
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| Electrical ATWS, ARI Successful Initiation: Continued Cues:
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| Automatic Actions: none Expected Annunciator: Multiple Key Parameter Response: Rising secondary containment radiation levels and temperatures Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| Performs Reactor Scram and LGP 3-2
| |
| * INITIATE ARI (CT)
| |
| * INFORM Unit Supervisor of Control Rod Status and Reactor Power
| |
| * Operate Feedwater and/or ECCS as necessary to maintain RPV Water Level 304.010 20" to 50" or as specified by Unit Supervisor 413.000 ATC 431.000
| |
| * Place LFFRV in AUTO
| |
| * REPORT to the Unit Supervisor the status of RPV Level and Pressure
| |
| * If needed for level control:
| |
| * Place the FRV in AUTO
| |
| * STABILIZE Reactor Pressure <1020 psig
| |
| * Monitor plant parameters and update the crew as required BOP
| |
| * Provide peer checks as required 304.010 413.000 US
| |
| * Direct above actions 431.000 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 22 of 27
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| 19-1 NRC Exam Scenario 4 Revision 00 Event - 8
| |
| | |
| == Description:==
| |
| Electrical ATWS, ARI Successful Simulator Operator Actions None Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: Continued SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 23 of 27
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| 19-1 NRC Exam Scenario 4 Revision 00 Event - 9
| |
| | |
| == Description:==
| |
| Low Pressure Core Spray Fails to Auto Actuate Initiation: Continued Cues:
| |
| Automatic Actions: none Expected Annunciator: Multiple Key Parameter Response: LPCS Pump not running Task/
| |
| Position EXPECTED OPERATOR RESPONSE Obj.
| |
| * Monitor plant parameters and update the crew as required 413.000 ATC
| |
| * Provide peer checks as required
| |
| * Maintain reactor water level as directed by Unit Supervisor Per LGA-001 BOP
| |
| * With an actuation level reached, VERIFY needed auto actions occur
| |
| * ECCS (LPCS) start 413.000 US
| |
| * Direct above actions SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 24 of 27
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| 19-1 NRC Exam Scenario 4 Revision 00 Event - 9
| |
| | |
| == Description:==
| |
| Low Pressure Core Spray Fails to Auto Actuate Simulator Operator Actions none Simulator Operator Role Play Respond as required Floor Instructor Notes/OPEX/TRs Terminus: RPV Level restored above TAF and Primary Containment Conditions being controlled within the parameters of the LGA-003 curves and per the Lead Evaluator.
| |
| SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 25 of 27
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| | |
| 19-1 NRC Exam Scenario 4 Revision 00 REFERENCES Procedure Rev Title
| |
| : 1. INPO 15-004 Operations Fundamentals
| |
| : 2. SOER 10-2 Engaged, Thinking Organizations
| |
| : 3. LOR-1H13-P602- 4 Reactor Water Cleanup Recirculation Pump 1G33-C001A Automatic A106 Trip
| |
| : 4. LOR-1H13-P602- 3 Reactor Water Cleanup Recirculation Pumps 1G33-C001A/B Flow Low A206
| |
| : 5. LOR-1H13-P602- 7 RR 1A Motor Cooling Water Flow Low OR Motor Winding Cooler A304 Leakage
| |
| : 6. LOR-1H13-P602- 1 Reactor Water Cleanup Filter Demineralizer Trouble B103
| |
| : 7. LOR-1H13-P601- 3 HPCS Diesel Generator 1B Engine Running A201
| |
| : 8. LOR-1H13-P601- 3 HPCS System Actuated A205
| |
| : 9. LOR-1H13-P601- 3 Reactor Vessel Water Level 2 Lo-Lo A208
| |
| : 10. LOR-1H13-P601- 3 Reactor Vessel Water Level 2 Lo-Lo A308
| |
| : 11. LOR-1PM01J-B505 2 480V Bus 132X/Y 134X/Y 138 Undervoltage
| |
| : 12. LOR-1PM03J-B101 2 High Pressure Heater 16A/B Level High
| |
| : 13. LOR-1PM03J-B201 3 High Pressure Heater 16 Spill Valve Open
| |
| : 14. LOR-1PM03J-B401 1 High Pressure Heater 16 Extraction Steam Check Valve Not Open
| |
| : 15. LOA-AP-101 60 AC Power System Abnormal
| |
| : 16. LOA-HD-101 39 Heater Drain System Trouble
| |
| : 17. LOA-PWR-101 16 Unplanned Reactivity Addition
| |
| : 18. LOA-RR-101 43 Reactor Recirc System Abnormal
| |
| : 19. LOA-RT-101 21 Loss of Reactor Water Cleanup System
| |
| : 20. LOP-RT-02 54 RWCU System Startup and Pump Transfer
| |
| : 21. LOP-WT-02 17 Startup and Operation of the Turbine Building Closed Cooling Water System
| |
| : 22. LGP-3-2 75 Reactor Scram
| |
| : 23. LGP-3-1 70 Power Changes
| |
| : 24. LGA-001 18 RPV Control
| |
| : 25. LGA-003 18 Primary Containment Control
| |
| : 26. OP-LA-101-111-1002 71 LaSalle Operations Philosophy Handbook.
| |
| : 27. OP-LA-103-102-1002 17 Strategies for Successful Transient Mitigation SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 26 of 27
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| 19-1 NRC Exam Scenario 4 Revision 00 U1 SUPERVISOR TURNOVER Shift: Days Date: Today Mode: 1 OLR: Green Work Week: Div 2 Unit 1 power level Unit 2 power level
| |
| * 100 % Power
| |
| * 100 % Power U1 Thermal Limit Issues /Power Evolutions U2 Thermal Limit Issues /Power Evolutions
| |
| * None
| |
| * None Existing LCOs, date of next surveillance Existing LCOs, date of next surveillance
| |
| * None
| |
| * None LOSs in progress or major maintenance LOSs in progress or major maintenance
| |
| * None
| |
| * None Equipment removed from service or currently unavailable
| |
| * None
| |
| * None Grid Status is Green Comments, evolutions, problems, etc. Comments, evolutions, problems, etc.
| |
| * Swap from B WT pump to A WT pump per
| |
| * Non-Div Workweek. OLR is Green LOP-WT-02, Section E.2 SRRS 3D.126/3D.111: Retain approved lessons for life of plant OR Life of Insurance Policy + 1 Yr for RP lesson plans. May be retained in department for two years, then forwarded to Records Management.
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| Page 27 of 27}}
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