ML11129A297

2011 Point Beach Nuclear Power Plant Initial License Examination Simulator Scenario Outline Forms (D-1)

ML11129A297
Person / Time
Site:	Point Beach
Issue date:	04/25/2011
From:	Mcneil D Operations Branch III
To:
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Download: ML11129A297 (3)

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Appendix D Scenario Outline Form ES-D-1 Facility: ___Point Beach_____ Scenario No.: __1_____ Op-Test No.: 2011301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: _100% reactor power - EOL Turnover: Emergency diesel generator (G01) is OOS, motor-driven auxiliary feedwater pump (P38A) is OOS. The return to service time for both the G01 and P38A is approximately four hours from now. The plant is under a severe weather watch. G02 is aligned to 1A05 and 2A05 in accordance with OI-35A. IT 07G SW valve stroke time test is scheduled to be conducted immediately after shift turnover.

Event Malf. Event Event No. No. Type* Description N-BOP 1 Conduct IT-07G SW Valve Stroke Time Test N-SRO C-RO 2 C-SRO In-Service Charging Pump Failure TS-SRO I-BOP 3 S/G B Level Transmitter ILT-471 Failure High I-SRO I-RO 4 I-SRO Pressurize Pressure Channel Failure (PT-431) High TS-SRO C-BOP 5 C-SRO Steam Generator Tube Leak TS-SRO R-RO 6 N-SRO Conduct Rx Plant Shutdown N-BOP 7 M- ALL Steam Generator Tube Rupture 8 C-BOP Stuck Open Atmospheric Steam Dump Valve

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: ___Point Beach_____ Scenario No.: __2_____ Op-Test No.: 2011301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: _ Unit 1 is at 28% power, middle of life.

Turnover: The following equipment is out of service: AB@ safety injection pump in day 3 of 7 of LCO to replace the outboard seal, continuing with power escalation IAW OP-1C, Step 4.120.

Event Malf. Event Event No. No. Type* Description N-BOP 1 Start a Heater Drain Tank Pump.

N-SRO R-RO 2 Increase Reactor Power from 28% at the Normal Rate.

N-SRO I-BOP 2 I-SRO Turbine First Stage Pressure Instrument PT-485 Fails Low.

TS-SRO I-RO 3 I-SRO Pressurizer Level Instrument 1LT-428 Fails Low.

TS-SRO N-BOP 4 Restore normal letdown N-SRO C-BOP 5 C-SRO Power Operated Relief Valve 1RC-430 Seat Leakage.

TS-SRO 6 M- ALL Steam Line Break Upstream of the Unit 1 AA@ MSIV.

7 M-ALL Reactor Trip Breakers Fail to Open (ATWS)

C-BOP Train AA@ ESF Sequencer Fails to Actuate.

C-SRO

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Facility: Point Beach Nuclear Station Scenario No.: 3 Op-Test No.: 2011301 Examiners: D. McNeil Operators:

R. Walton D. Reeser Initial Conditions: Unit 1 is at 23% reactor power, BOL, equilibrium xenon conditions following a reactor trip from full power five days ago due to a failure of the Unit 1 Voltage Regulator. Unit 2 is at 100% reactor power. Present clock time is real time. Normal shift complement with the exception of the 3rd SRO.

Turnover: G-01 EDG is out of service for annual maintenance. It was taken OOS 2 days ago, and is expected to be returned to service in 3 days. G-02 EDG is aligned to 4.16kV buses 1-A05 and 2-A05 IAW OI-35A. P-38B, Electric Auxiliary Feedwater Pump was declared inoperable 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago due to recirculation line cracks and has just been tagged out for repair. A severe thunderstorm watch is in effect for the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The RCS is at normal operating pressure and temperature. Steam Generator water level is being controlled with the Main Feedwater Regulating valves in automatic on a single train of feedwater and condensate. OP-1C, "Low Power Operation to Normal Power Operation" is in progress. You are to continue with unit startup per OP-1C.

Event Malf. Event Event No. No. Type* Description 1 R Normal Up-Power 2 I Thot Instrument (TE-401A) Fails High Running CCW Pump Shaft Seizes w/Failure of Standby CCW 3 C Pump to Auto Start 4 I Controlling SG Pressure Channel (PT-478) Fails High 5 M Small RCS Leak in "A" RCS Loop Degrading to Large Break 6 M Large Break LOCA 7 I Failure of SI to Auto-Actuate 8 C Failure of Containment Accident Fan 1W-1A1 to Auto-Start 9 C Failure of 1SI-852A to Auto-Open

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

@ See scenario description pages 2 & 3 for malfunction numbers.