ML15223B321

Robinson Initial Exam 2011-301 Draft Simulator Scenarios

ML15223B321
Person / Time
Site:	Hatch
Issue date:	05/21/2015
From:	NRC/RGN-II
To:	Progress Energy Carolinas
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Download: ML15223B321 (149)

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I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.: 1 Op Test No.: Examiners:

Operators:

SRO-RO-BOP-Initial Conditions:

• 100% RTP MOL, 9000 MWDIMTU, 745 ppm Boron . * "A" CCW pump inoperable with the breaker racked out

• 5 GPO primary to secondary leakage into SIG "C" Turnover:

• Reduce power to 85% to support maintenance on "A" Heater Drain Pump excessive packing leakage. Critical Tasks:

• Start one SI Pump to provide injection to the RCS .

• Isolate SIG "B" due to tube rupture IAW Supplement G and PATH-2 . Event Malf. Event Type* Event No. No. Description 1 (R) RO Reduce turbine load IAW OP-105 to 85%. (N) BOP, SRO 2 (I) BOP, SRO Feedwater Flow Transmitter FT-477 fails HIGH (TS) SRO 3 (I) RO, SRO (TS) SRO PZR Pressure Transmitter PT-444 fails HIGH 4 (C) RO, SRO RCP "A" #1 Seal Failure 5 (M) ALL SIG "B" tube rupture following the manual Reactor Trip 6 (C) RO Both Safety Injection Pumps do not Auto Start 7 (C) BOP Isolate Seal Return from RCP "A" IAW AOP-018 8 (C) BOP Isolate SIG "B" using Supplement G * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp.1 I Appendix D Scenario Outline Form ES-D-1 ILC-11-1 NRC SCENARIO 1

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 100% steady state power. The previous shift had identified seal leakage on CCW Pump "A". The motor breaker has been racked out and the pump has been isolated and cleared for maintenance.

5 GPD primary to secondary leakage has been identified into S/G "C" with elevated readings on the applicable radiation monitors.

Shift instructions are to reduce reactor power and turbine load to support maintenance on Heater Drain Pump "A" packing leakage. The crew will reduce reactor power and turbine load IAW OP-105 to 85% to support maintenance on "A" Heater Drain Pump. Feedwater flow channel FT-477 fails HIGH, affecting the automatic operation of Feedwater Regulating Valve FCV-478 for S/G "A". The operator will have to take manual control of the FRV and restore the SIG to program level. The crew will perform the immediate actions for FT-477 failure IAW AOP-025, RTGB Instrument Failure, Section E. The crew will perform the necessary transfer to the controlling channel and restore the FRV to automatic operation.

The failed feedwater flow transmitter will be removed from service IAW OWP-026, FWF-2. Once the feedwater flow transmitter has been removed from service, the FRV returned to automatic and the Chief Examiner is satisfied with the Tech Specs compliance, the Chief Examiner will cue the next event. PZR Pressure Transmitter PT-444 will fail HIGH, causing the PZR PORV PCV-455C to open and both PZR Spray valves to open. Immediate actions of AOP-025, RTGB Instrument Failure, Section C will be performed by the crew. PCV-455C will not respond to the closure signal from the control switch and will require the operator to manually close the PZR PORV Block valve RC-536. The PZR Spray valves will have to be manually closed by manual control of the PZR Pressure Controller PC-444J or manual control of each of the PZR Spray Valves PCV-455A and PCV-4558.

Due to the PZR PORV PCV-455C being failed open, the SRO will be required to implement ITS 3.4.11, Condition B. This action includes opening the power supply breaker to the block valve RC-536, which was closed to isolate the failed open PZR PORV. The Chief Examiner will cue the next event when the necessary ITS requirements have been implemented.

On cue from the Chief Examiner, the #1 seal on RCP "A" will fail. This will require entry into AOP-018, Reactor Coolant Pump Abnormal Conditions, to identify and determine that a manual reactor trip will be required due to the plant conditions.

A manual reactor trip will be initiated along with the securing of the affected RCP from actions directed from AOP-018. Within 3 to 5 minutes following the securing of the RCP, the seal return isolation valve must be closed to isolate the excessive seal leakage. These actions are performed along with the actions of PATH-1 due to AOP-018 being a concurrent AOP. During the actions of PATH-1, the Chief Examiner will cue the tube rupture in S/G B. The crew may note the lowering PZR level and pressure, along with the rising S/G level to determine that a SIG tube rupture has occurred.

There will not be any radiation monitor response from the tube rupture due to the radiation monitor response being disabled.

Once the safety injection is Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 initiated, the operator will observe that the SI Pumps do not automatically start and manually start them as required.

PATH-1 and PATH-2, along with Supplement G will be used by the crew to isolate the ruptured SIG and equalize the RCS and ruptured S/G pressures to stop the excessive primary to secondary leakage. The Chief Examiner may terminate the scenario at any time after the SI Pumps are secured in PATH-2 for the termination of the primary to secondary leakage. Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.: 2 Op Test No.: Examiners:

Operators:

SRO-RO-BOP-Initial Conditions:

• 50% RTP BOL, 150 MWDIMTU, 1277 ppm Boron . * "A" CCW pump inoperable with the breaker racked out * "B" MFP breaker racked out for maintenance .

• 5 GPO primary to secondary leakage into SIG "C" Turnover:

• Holding reactor power at 50% for maintenance on Main Feedwater Pump B motor. Critical Tasks:

• Isolate feedwater to SIG B

• Open at least 1 of the CV Spray Pump Discharge valves to provide CV Spray flow.

• Throttle AFW flow to the SIGs at 80-90 GPM . Event Malf. Event Type* Event No. No. Description 1 (I) RO, SRO VCT Level Transmitter L T-112 fails HIGH 2 (1) RO, BOP, SRO First Stage Pressure Transmitter PT-446 fails LOW (TS) SRO 3 (C) RO, SRO CCW Pump B trips and CCW Pump C fails to auto start (TS) SRO 4 (C) BOP, SRO CondenserVacuumleakage 5 (R) RO Load Reduction due to Condenser Vacuum lowering (N) BOP, SRO 6 (M) ALL Steam Line Break inside the CV 7 (M) ALL All SIGs Faulted inside the CV on the Reactor Trip 8 (C) BOP Isolate feedwater to SIG B 9 (C) RO Open one of the Sl-880 valves to provide CV Spray flow 10 (C) BOP Throttle AFW flow to the SIGs at 80-90 GPM * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 I ILC-11-1 NRC SCENARIO 2

SUMMARY

DESCRIPTION The crew will assume the watch with the unit being maintained at 50% RTP while maintenance is performed on Main Feedwater Pump B motor. The previous shift had identified seal leakage on CCW Pump A The motor breaker has been racked out and the pump has been isolated and cleared for maintenance.

5 GPO primary to secondary leakage has been identified in SIG C with elevated readings on the applicable radiation monitors.

Shift instructions are to maintain current reactor power until MFW Pump B is returned to service. On cue from the Chief Examiner, VCT Level Transmitter L T-112 will fail HIGH. This will cause LCV-115A to divert all letdown flow to the CVCS HUTs and will cause LC-112, VCT Level Controller, to go to full output. This failure will result in an automatic makeup to the VCT, which will alert the operators to determine the cause of the makeup operation.

AOP-003, Malfunction of Reactor Makeup Control, will be implemented and LCV-115A will be overridden to the VCT until the VCT level control can be restored on the alternate channel. This will require that the alternate channel (L T-115) be selected for all control functions of VCT level. Once AOP-003 actions are completed and on cue from the Chief Examiner, First Stage Pressure Transmitter PT-446 will fail LOW. The crew will perform the immediate actions for PT-446 failure IAW AOP-025, RTGB Instrument Failure, Section H. The crew will perform the necessary transfer of the controlling channel and restore the S/Gs to their programmed level for the present reactor power level. The failed pressure transmitter will be removed from service IAW OWP-033, FSP-1. Once the pressure transmitter has been removed from service and the Chief Examiner is satisfied with the Tech Specs compliance, the Chief Examiner will cue the next event. CCW Pump B will trip on overcurrent and CCW Pump C will fail to auto start on CCW System low pressure.

The crew will manually start the standby CCW Pump by following the actions in APP-001-F4 for motor overload, APP-001-F5 for system low pressure or enter AOP-014, Component Cooling Water System Malfunction, Section C for System Low Pressure.

The SRO will implement ITS 3.7.6, Condition A due to CCW Pump Bis powered from an emergency power source. Once the Chief Examiner is satisfied with the Tech Spec compliance, he can cue the next event. On cue from the Chief Examiner, Condenser vacuum leak will be initiated and vacuum will start to lower. This will be noted by rising Condenser backpressure and lowering net MWe. AOP-012, Partial Loss of Condenser Vacuum or Circulating Water Pump Trip, will be implemented.

The standby Condenser Vacuum Pump will be started and a search for the vacuum leak will be initiated.

Unit load will have to be reduced to ensure that operation within the Condenser Backpressure Limits is maintained in the allowable region of the curve. Once the Chief Examiner is satisfied with the crew response to the unit load reduction, he can cue the next event. The steam line from SIG B will fault inside the CV. The crew will diagnose the event and make the determination that the reactor needs to be manually tripped. Upon the reactor trip, all S/Gs will be faulted inside the CV. PATH-1 will be implemented with Safety Injection initiated.

Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 The discharge valves for the CV Spray Pumps will not automatically open and will require that at least one of the valves be manually opened to provide CV Spray flow. Feedwater Regulating Valve FCV-488 and its respective Feedwater Block valve V2-6B will fail to close on the SI signal, resulting in excessive feedwater flow into S/G B and will have to be manually closed to terminate the flow. The crew will transition through PATH-1 and will transition to FRP-P.1, Response to Imminent Pressurized Thermal Shock, to throttle AFW flow to all of the S/Gs at a reduced rate of 80-90 GPM to each SIG. After throttling AFW the crew will transition to FRP-H.1, Response to Loss of Secondary Heat Sink, and immediately reset SPDS and return to procedure and step in effect since entry was due to operator actions. The Chief Examiner may terminate the scenario at any time after AFW flow has been established to all of the S/Gs at a reduced flow rate. Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.: 3 Op Test No.: Examiners:

Operators:

SRO-RO-BOP-Initial Conditions:

• 1E-8 amps BOL, 150 MWD/MTU, 1531 ppm Boron . * "A" CCW pump inoperable with the breaker racked out

• 5 GPO primary to secondary leakage into S/G "C" Turnover:

• Maintain current reactor power until the RCP "C" oil leak issue is resolved.

Critical Tasks:

• Align low head injection by starting RHR Pump A and opening RHR-744A or 744B valves.

• Start HVE-19A or 19B for Control Room Pressurization

• Identify that Emergency Coolant Recirculation capability has been lost and implement EPP-15. Event Malf. Event Type* Event No. No. Description 1 (C) BOP, SRO HVE-3 (CV Iodine Removal Fan) Trips 2 (I) RO, SRO PT-145 Letdown Pressure Transmitter Fails LOW 3 (N) RO, SRO Place Excess Letdown in Service 4 (C) BOP, SRO Service Water Booster Pump B Trips (TS) SRO 5 (C) ALL Degraded Voltage on System Grid (TS) SRO 6 (M) ALL LOCA occurs when the reactor trips 7 (C) ALL Safeguards sequencers fail to start loads 8 (C) RO Restoration of Charging Pump I Seal Cooling 9 (C) RO RHR Pump A trips 10 (C) RO Loss of Emergency Coolant Recirculation capability requires entry into EPP-15 * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 ILC-11-1 NRC SCENARIO 3

SUMMARY

DESCRIPTION The crew will assume the watch with the reactor at 1 E-8 amps and the turbine on the turning gear with GP-005 in effect. The unit is being maintained in the present configuration while Engineering personnel resolve the RCP C oil leak issue. The previous shift had identified seal leakage on CCW Pump A The motor breaker has been racked out and the pump has been isolated and cleared for maintenance.

5 GPO primary to secondary leakage has been identified in S/G C with elevated readings on the applicable radiation monitors.

Shift instructions are to maintain current reactor power until the RCP oil leak issue is resolved.

On cue from the Chief Examiner, HVE-3 (CV Iodine Removal Fan) will trip. APP-01 O-C6 is received and HVE-3 has lost indication on the RTGB. The crew will investigate and proceed to start HVE-4 to restore the cooling function for the CV Dome Vent. Once APP-01 O actions are completed, the Chief Examiner can cue the next event. Pressure Transmitter PT-145 for Letdown Line Pressure will fail LOW, causing PCV-145 to close and isolate letdown flow. AOP-025, RTGB Instrument Failure, Section A will be implemented to isolate the letdown line, reduce charging flow and place Excess Letdown in service. Once the Chief Examiner is satisfied with the crew's actions, the Chief Examiner will cue the next event. Service Water Booster Pump B will trip on overcurrent.

APP-002-AS, 88, CS and 08 will be received when the pump trips and will direct the crew to start the standby SWBP and restore normal flow to the CV HVH units. ITS 3.7.7, Condition A will be entered for the SWBP failure and ITS 3.6.6, Condition D will be entered due to the failure to meet SR 3.6.6.3 for the CV HVH units. Once the Chief Examiner is satisfied with the Tech Spec compliance, he can cue the next event. On cue from the Chief Examiner, system grid voltage will start degrading.

APP-036-E3 will be received and the crew will monitor 115kV and 230kV voltages.

AOP-026, Grid Instability, will be entered. ITS 3.8.1, Condition A will be entered due to the offsite power source being inoperable.

Grid voltage will continue to lower until 480V Susses E-1 and E-2 separate from the grid due to the actuation of the Degraded Grid Voltage relays for the Emergency Susses, the Emergency Diesel Generators start and re-energize the busses. When 480V Bus E-1 separates from the grid, the reactor will trip due to de-energizing Intermediate Range N-35. The reactor trip will trigger a LOCA and an SI will be generated.

The crew will enter PATH-1 and continue through the actions of the PATH. The SDAFW pump trips while attempting to start. No loads will start on the safeguards sequencers.

The operators must manually start safeguards loads. Valves RHR-744A and 7448 will not automatically open when the SI signal is generated.

The operator will open one of the valves to ensure that low head core injection is available.

The crew will manually start a Charging Pump within the 15 minutes to restore seal injection to the RCPs or determine that the 15 minute criteria has been exceeded and choose to allow the pump to remain idle. Charging Pumps B and C will be available once the SI signal has been Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 reset. Charging Pump A will be available if the crew directs that the Dedicated Shutdown Diesel Generator be started in accordance with EPP-25, Energizing Supplemental Plant Equipment using the DSDG, to re-energize the 480V Bus DS. The Chief Examiner may terminate the scenario when the crew has made the determination that EPP-15, Loss of Emergency Coolant Recirculation, must be implemented due to the loss of all RHR Pumps. Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 I Facility:

HB ROBINSON Scenario No.: 4 Op Test No.: Examiners:

Operators:

SRO-RO-BOP-Initial Conditions:

• 75% RTP EOL, 15697 MWD/MTU, 132 ppm Boron . * "A" CCW pump inoperable with the breaker racked out

• 5 GPO primary to secondary leakage into S/G "C" Turnover:

• Awaiting Engineering personnel to install vibration monitoring equipment to allow starting Heater Drain Pump "B". Critical Tasks:

• Manually runback the turbine to stop the steam flow

• Provide heat removal by RCS Bleed and Feed Event Malf. Event Type* Event No. No. Description 1 (C) RO, BOP, SRO Loss of Instrument Bus #1 (TS) SRO 2 (I) RO, SRO PZR Pressure Controller PC-444J Range Shifts (TS) SRO 3 (I) BOP, SRO Steam Pressure Channel PT-485 fails LOW (TS) SRO 4 (C) BOP, SRO Loss of Cooling to the Auxiliary Transformer 5 (R) RO Load Reduction to 50% (N) BOP, SRO 6 (M) ALL Feedwater Header Rupture 7 (C) BOP Turbine Trip Does Not Occur 8 (C) BOP MDAFW and SDAFW Pumps Trip when Start Signal Received 9 (C) BOP Steam Dump Valves fail Open on Reactor Trip 10 (C) BOP MSIVs fail to Close when Demanded * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 ILC-11-1 NRC SCENARIO 4

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 75% RTP and waiting on Engineering personnel to install vibration monitoring equipment on Heater Drain Pump "B" to support pump startup. The previous shift had identified seal leakage on CCW Pump A. The motor breaker has been racked out and the pump has been isolated and cleared for maintenance.

5 GPO primary to secondary leakage has been identified in SIG C with elevated readings on the applicable radiation monitors.

On cue from the Chief Examiner, Instrument Bus #1 will de-energize due to the tripping of the normal supply breaker on MCC-5. AOP-024, Loss of Instrument Bus, immediate actions will be taken by the crew and the procedure will proceed to energize the instrument bus from its alternate power supply. The crew will ensure that all of the controllers have been returned to auto. ITS 3.8.7, Condition A will be implemented by the SRO. Once AOP-024 and ITS actions are completed, the Chief Examiner can cue the next event. PZR Pressure Controller PC-444J control range will shift causing the PZR Spray valves to open and lower PZR pressure.

AOP-019, Malfunction of RCS Pressure Control, immediate actions will be taken and the procedure will take actions to restore pressure to the normal control band with PC-444J operated in manual control. ITS 3.4.1 will be entered due to PZR Pressure being less than 2205 psig. Once the Chief Examiner is satisfied with the crew's actions, the Chief Examiner will cue the next event. Steam Pressure Transmitter PT-485 will fail LOW, causing the controlling steam flow channel on SIG B to fail low and causing a transient on the Feedwater Regulating valve FCV-488. AOP-025, RTGB Instrument Failure, Section G immediate actions will be taken by the crew to stabilize the SIG level transient.

The procedure will place an alternate control channel in service and direct the removal of the channel from service. ITS Table 3.3.1-1, 3.3.2-1, 3.3.3-1 and 3.3.6-1 requirements will be reviewed by the SRO to ensure that all of the ITS specs are satisfied.

Once the SIG level control has been stabilized and the Chief Examiner is satisfied with the Tech Spec compliance, he can cue the next event. Auxiliary Transformer Trouble alarm (APP-009-C6) will be received on the RTGB. The report from the field is that all cooling fans and oil pumps on the transformer have been lost. AOP-037, Large Transformer Malfunctions, will be implemented by the crew with the requirement to reduce load to less than 50% within 30 minutes. Power reduction will commence and will continue until the Chief Examiner cues the next event. Feedwater header rupture will occur at the discharge of the Main Feedwater Pumps. This will cause an immediate reduction in the SIG levels and the crew will manually trip the reactor. Once the reactor is tripped, the crew will enter PATH-1. The turbine will not trip automatically or manually from the RTGB and the operator will have to manually runback the turbine with the EH controls until the governor valves are closed. The MDAFW and SDAFW Pumps will trip when the start signal is received.

Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Steam dump valves will fail open on the trip and the MSIVs will fail to close when demanded from the RTGB control switches.

If requested to locally fail close the MS IVs, the task will be successful to close the valves. The crew will transition to FRP-H.1, Response to Loss of Secondary Heat Sink, due to the inability to feed the S/Gs. During the procedure, following the initiation of RCS bleed and feed, one MDAFW Pump will be restored to allow feedwater flow to be initiated to the S/Gs. The Chief Examiner may terminate the scenario after the crew has restored AFW flow to at least one SIG. Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.: 1 Op Test No.: Examiners:

Operators:

SRO-RO-BOP-Initial Conditions:

• 100% RTP MOL, 9000 MWDIMTU, 745 ppm Boron . * "A" CCW pump inoperable with the breaker racked out

• 5 GPO primary to secondary leakage into SIG "C"

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.

Turnover:

• Reduce power to 85% to support maintenance on "A" Heater Drain Pump excessive packing leakage. Critical Tasks:

• Start one SI Pump to provide injection to the RCS .

• Close valve CVC-303A to isolate RCP seal return .

• Isolate SIG "B" due to tube rupture IAW Supplement G and PATH-2 . Event Malf. Event Type* Event No. No. Description 1 (R) RO (N) BOP, SRO Reduce turbine load IAW OP-105 to 85%. 2 (I) BOP, SRO (TS) SRO Feedwater Flow Transmitter FT-477 fails LOW 3 (I) RO, SRO (TS) SRO PZR Pressure Transmitter PT-444 fails HIGH 4 (C) RO, SRO RCP "A" #1 Seal Failure 5 (M) ALL SIG "B" tube rupture following the manual Reactor Trip 6 RO Both Safety Injection Pumps do not Auto Start 7 BOP Isolate Seal Return from RCP "A" IAW AOP-018 8 BOP Isolate SIG "B" using Supplement G * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 ILC-11-1 NRC SCENARIO 1

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 100% steady state power. The previous shift had identified seal leakage on CCW Pump "A". The motor breaker has been racked out and the pump has been isolated and cleared for maintenance.

5 GPD primary to secondary leakage has been identified into SIG "C" with elevated readings on the applicable radiation monitors.

Shift instructions are to reduce reactor power and turbine load to support maintenance on Heater Drain Pump "A" packing leakage. The crew will reduce reactor power and turbine load IAW OP-105 to 85% to support maintenance on "A" Heater Drain Pump. Feedwater flow channel FT-477 fails LOW, affecting the automatic operation of Feedwater Regulating Valve FCV-478 for SIG "A". The operator will have to take manual control of the FRV and restore the SIG to program level. The crew will perform the immediate actions for FT-477 failure IAW AOP-025, RTGB Instrument Failure, Section E. The crew will perform the necessary transfer to the controlling channel and restore the FRV to automatic operation.

The failed feedwater flow transmitter will be removed from service IAW OWP-026, FWF-2. The SRO will implement ITS Table 3.3.1-1 Item 14 which requires 2 SIG Level channels (not affected by the failure) and 2 Steam Flow I Feedwater Flow mismatch channels with Condition E -Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or Be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Once the feedwater flow transmitter has been removed from service, the FRV returned to automatic and the Chief Examiner is satisfied with the Tech Specs compliance, the Chief Examiner will cue the next event. PZR Pressure Transmitter PT-444 will fail HIGH, causing the PZR PORV PCV-455C to open and both PZR Spray valves to open. Immediate actions of AOP-025, RTGB Instrument Failure, Section C will be performed by the crew. PCV-455C will not respond to the closure signal from the RTGB control switch and will require the operator to manually close the PZR PORV Block valve RC-536. The PZR Spray valves will have to be manually closed by manual control of the PZR Pressure Controller PC-444J or manual control of each of the PZR Spray Valves PCV-455A and PCV-455B.

Due to the PZR PORV PCV-455C being failed open, the SRO will be required to implement ITS 3.4.11, Condition B -One PORV inoperable and not capable of being manually cycled. Actions include the following:

B.1 Close associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND B.2 Remove power from the associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND B.3 Restore PORV to Operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The actions include opening the power supply breaker to the block valve RC-536, which was closed to isolate the failed open PZR PORV. The Chief Examiner will cue the next event when the necessary ITS requirements have been implemented.

On cue from the Chief Examiner, the #1 seal on RCP "A" will fail. This will require entry into AOP-018, Reactor Coolant Pump Abnormal Conditions, to identify and determine that a manual reactor trip will be required due to the plant conditions.

A manual reactor trip will be initiated along with the securing of the affected RCP from actions directed from AOP-018. The reactor trip pushbutton near the reactor controls area above TR-408 on the RTGB has been ridden. The candidate will need to utilize the reactor trip pushbutton that is below the SI Valve Status Lights on the RTGB. This reactor trip pushbutton will successfully trip the reactor. Appendix D NUREG-1021, Rev. 9, Supp.1 I Appendix D Scenario Outline Form ES-D-1 Within 3 to 5 minutes following the securing of the RCP, the seal return isolation valve must be closed to isolate the excessive seal leakage. These actions are performed along with the actions of PATH-1 due to AOP-018 being a concurrent AOP. Immediately upon the initiation of the reactor trip a tube rupture will occur in SIG "B". The crew may note the lowering PZR level and pressure, along with the rising SIG level to determine that a SIG tube rupture has occurred.

There will not be any radiation monitor response from the tube rupture due to the radiation monitor response being disabled.

Once the safety injection is initiated, the operator will observe that the SI Pumps do not automatically start and manually start them as required.

After safety injection is initiated the tube rupture on SIG "B" will increase to 800 gpm. PATH-1 and PATH-2, along with Supplement G will be used by the crew to isolate the ruptured SIG and equalize the RCS and ruptured SIG pressures to stop the excessive primary to secondary leakage. The Chief Examiner may terminate the scenario at any time after the RCS cooldown has been commenced or at his discretion.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 ILC-11-1 NRC SCENARIO 1 SIMULATOR SETUP IC/SETUP:

• IC-801, SCN: 008_NRC_ 1 * "A" CCW Pump inoperable with the breaker racked out. Switch RED capped.

• 5 GPO primary to secondary leakage into S/G "C"

• R-15 at 24 cpm, R-19C at 232 cpm, R-31 Cat 0.450 mR/hr

• R-198 and R-318 overridden AS IS

• Status board updated to reflect IC-13.

• YELLOW Caution cap on RV-3 ("C" Steam Line PORV) PRE-LOADED EVENTS: The following events should occur on the reactor trip: Event 6: Both Safety Injection Pumps do not Auto Start EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:

Event 1: Event 2: Event 3: Event 4: Reduce turbine load IAW OP-105 to 85%. Feedwater Flow Transmitter FT-477 fails LOW PZR Pressure Transmitter PT-444 fails HIGH RCP A #1 Seal Failure Event 5: SIG B tube rupture following the manual Reactor Trip EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

• OP-105

• AOP-025 Main Body and Section E

• OWP-026, FWF-2

• AOP-025 Main Body and Section C

• AOP-018 Main Body and Section A

• PATH-1

• FoldoutA

• Supplement G

• PATH-2

• Foldout C Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -----Page 5 of _3_5 ___ -1 1 Event

Description:

Reduce turbine load IAW OP-105 to 85%. Time II Position II Aoolicant's Actions or Behavior NOTE: The crew will use OP-105, MANEUVERING THE PLANT WHEN GREATER THAN 25% POWER, to perform the plant down power. Only the applicable steps have been listed. SRO Notify the Load Dispatcher that unit load will be reduced. SRO Notify RC that increased radiation levels are expected in the CV Pump Bays and in Pipe Alley due to normal shutdown crud bursts. RO Monitor the highest operable Power Range Channel and the highest operable Intermediate Range Channel on NR-45. SRO/RO IF Reactor Engineering has not provided technical guidance, THEN determine the reactivity chanQe required.

IF additional letdown flow is desired, THEN: RO

• Start additional Charging Pumps as necessary,

• Place additional letdown orifice in service . RO IF a significant change in RCS Boron concentration occurs, THEN energize additional PZR heaters as needed. NOTE: OP-301, Section 8.2.8 Quick Boration Checklist (shaded area) is included in the following steps, but may be used following the commencement of the plant down power. RO DETERMINE the amount of Boric Acid to add to the RCS and OBTAIN an independent check of the volume required.

NOTE: -51 gallons of Boric Acid will be added based on rods stepping to 191 steps. (The crew will add Boric Acid in 1-2 batches.)

RO OBTAIN permission from the CRSS OR the SSO to borate. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # -------Page 6 of _3_5 ___ -1 1 Event

Description:

Reduce turbine load IAW OP-105 to 85%. Time II Position II Applicant's Actions or Behavior RO PLACE the RCS MAKEUP MODE selector switch to BORA TE. RO SET YIC-113, BORIC ACID TOTALIZER to desired quantity.

RO IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN AND ADJUST using the UP and DOWN pushbuttons.

RO Momentarily PLACE the RCS MAKEUP SYSTEM switch to START. IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:

RO

• Rod Motion is blocked or in the wrong direction

• T AVG increases

• Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:

• FCV-113A, BORIC ACID FLOW, closes . RO

• FCV-113B, BLENDED MU TO CHG SUCT, closes .

• IF in Auto, THEN the operating Boric Acid Pump stops .

• The RCS MAKEUP SYSTEM is OFF . Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 1 Event # Page 7 of 35 Event

Description:

Reduce turbine load IAW OP-105 to 85%. A licant's Actions or Behavior IF desired, THEN FLUSH the Boric Acid flow path as follows:

• PLACE the RCS MAKEUP MODE selector switch in the ALT DILUTE position.

• SET YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons .

• PLACE FCV-114B, BLENDED MU TO VCT to CLOSE.

• Momentarily PLACE RCS MAKEUP SYSTEM switch to START.

• IF any of the below conditions occur, THEN momentarily place RO the RCS MAKEUP SYSTEM switch in the STOP position:

0 Unanticipated Rod Motion 0 Primary Water addition reaches the desired value

• WHEN the desired amount of Primary Water has been added to the RCS, THEN verify the following:

0 FCV-114A closes. 0 FCV-113B closes. 0 IF in Auto, THEN the operating Primary Water Pump stops. 0 The RCS MAKEUP SYSTEM is OFF. RETURN the RCS Makeup System to automatic as follows:

• VERIFY FCV-114A is in AUTO .

• PLACE FCV-114B to the AUTO position . RO

• PLACE the RCS MAKEUP MODE switch in AUTO .

• VERIFY FCV-113A is in AUTO .

• Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.

RECORD, in AUTO LOG, as indicated by PRIMARY WATER RO TOTALIZER, YIC-114 AND Boric Acid TOTALIZER, YIC-113 the total amount of Primary Water AND Boric Acid added during the boration.

RO MONITOR parameters for the expected change in reactivity AND inform the CRSS OR the SSO of the results of the boration.

IF EH Turbine Control is in OPER AUTO, THEN reduce turbine load as follows:

• Place the EH Turbine Control in the desired position:

IMP IN . BOP Set the desired load in the SETTER. *

• Select the desired Load Rate .

• Depress the GO pushbutton . Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario#

--Event# Event

Description:

Reduce turbine load IAW OP-105 to 85%. Time Position II Aoolicant's Actions or Behavior BOP Maintain Gland Seal Steam Header Pressure in the normal operating band (3 to 6 psig) (Pl-4004, Pl-1382 or ERFIS Pt GSP2095A)

RO WHEN Reactor Power is <90% as indicated on NR-45, THEN CHECK that APP-005-06 is received. (YES) BOOTH OPERATOR:

As soon as the power reduction is 5% or at the discretion of the Chief Examiner, insert the next event. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # --2 Page 9 of 35 Event

Description:

FT-477 fails LOW Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 2, Feedwater Flow Transmitter FT-477 fails LOW EVENT INDICATIONS:

APP-006-A2; S/G A STM > FW FLOW APP-006-A3; S/G A LVL DEV APP-006-D2; SIG A NAR RANGE HI LEVEL FR-478 Green Pen goes low and FCV-478 opens BOP Recognizes FT-477 has failed and performs Immediate Actions for AOP-025, RTGB INSTRUMENT FAILURE. BOP Immediate Action Step: Place the affected FRV (FCV-478 for SIG "A") in MAN. BOP Immediate Action Step: Restore Affected SIG Level To Between 39% And 52%. SRO Enters AOP-025, RTGB INSTRUMENT FAILURE, Section E, and verifies Immediate Actions. RO/BOP Make PA announcement for entry into AOP-025. BOP Place the affected SIG Feed Flow Selector Switch to the alternate channel. (CH-476, FR-478 recorder pen will return to normal status) Continuous Action Step: Restore Affected Controller To Automatic:

BOP

• Check S/G level within +/-:. 1 % of programmed level. (If YES, place in Auto and Go To Step 6) WHEN S/G level is within +/-:. 1 % of programmed level, THEN place the affected Controller in AUTO. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # --_2 _____ Page 10 of _3_5 ___ _, 1 Event

Description:

FT-477 fails LOW Time II Position II Aoolicant's Actions or Behavior SRO Reviews, briefs and directs taking FT-477 instrument out of service using OWP-026, FWF-2. Remove the affected transmitter from service using OWP-026, FWF-2.

• FR-478 selector switch selected to CH-476 .

• Remove FT-477 input to the CALO program. (Two Options)

• Option 1 -Remove via CALO ERFIS program . 0 Access Calorimetric on ERFIS by typing CALO 0 Click on the DELETE INPUTS button. This will display the DELETE INPUT FROM CALORIMETRIC page. BOP 0 Select FWF0404A 0 Click on the ENTER DATA button.

• Option 2 -Delete the ERFIS point from scan . 0 Access the Delete function by typing DR. 0 Click on DELETE SCAN 0 Enter FWF0404A (APP-036-L 1 will be received when Hagan Rack door is opened)

• Trip bistable FC-478B-1. (APP-006-A2 will be received)

Examiner Note: Question during follow up. What actions are required for tripping bistables?

SRO Go To Procedure Main Body, Step 2. SRO Implement the EALs. Review ITS for applicable LCO.

• ITS Table 3.3.1-1 Item 14 which requires 2 SIG Level channels SRO (not affected by the failure) and 2 Steam Flow I Feedwater Flow mismatch channels with Condition E -Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or Be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SRO Return to procedure and step in effect. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario#

Event# _2 _____ Page 11 of _3_5 ___ ___, 1 Event

Description:

FT-477 fails LOW Time II Position II Applicant's Actions or Behavior I I NOTE: Crew should notify wee SRO and/or l&C to write a work request, investigate and initiate repairs, and notify the Operations Manager. I I Examiner Note: Ensure power has been reduced by at least 10% prior to initiating the Event #3, PT-444 failure. I I Booth Operator Initiate Event #3 (PT-444 Fails High) on cue from the Chief Examiner.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: __ Scenario # 1 Event# _3 _____ Page 12 of _3;;..;;5

___ _.1 Event

Description:

PT-444 Fails High on A licant's Actions or Behavior BOOTH OPERATOR:

When directed, initiate Event 3, PT-444 fails HIGH EVENT INDICATIONS:

APP-003-C3, PRT HIGH PRESS APP-003-C7, PZR PRESS CONTROLLER HI OUTPUT APP-003-06, PZR PORV/SAFETY VLV OPEN APP-003-08, PZR CONTROL HI/LO PRESS APP-003-E6, PZR PORV LN HI TEMP APP-003-F6, PZR SAFETY LINE HI TEMP APP-003-A2, PCV-455C LP PROT ACT/TROUB (Received once RC-536 is closed.) RO Recognizes that PT-444 is failed high and performs Immediate Actions of AOP-025. Immediate Action Step: Determine if PZR PORVs should be closed. RO

• Check Pressurizer pressure less than 2335 psig (YES).

• Verify both PZR PORVs CLOSED (NO, PCV-455C OPEN) .

• Manually close RC-536, PORV BLOCK NOTE: May use PC-444J OR Spray Valve Controller in Manual to close spray valves. Immediate Action Step: RO Control Pressurizer Spray Valves and Pressurizer Heaters to restore RCS pressure to the desired control band. SRO Enters AOP-025, RTGB INSTRUMENT FAILURE, Section C and verifies Immediate Actions. NOTE: Crew will enter LCO 3.4.1.A if pressure lowers < 2205 PSIG. Pressure must be restored>

2205 psig within 2 hrs. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 1 Event # _3"------Page 13 of _3;;..;;5

___ -1 1 Event

Description:

PT-444 Fails High Time Ii Position II Aoolicant's Actions or Behavior Crew Make PA announcement for entry into AOP-025. SRO/RO Check PT-444 is the failed transmitter. (YES) Control pressurizer pressure controller PC-444J:

• Place PC-444J in MAN . RO

• Verify PZR SPRAY VALVES IN AUTO .

• Verify PZR Heaters energized as desired .

• Restore PZR Pressure to the desired control band . RO Verify PCV-455C in AUTO. (Crew may decide to leave PCV-455C in the CLOSE position since it failed to close.) RO Verify Selector Switch PM-444 is selected to operable channel:

• REC-445 . SRO Informs SSO to implement EALs. Enters LCO 3.4.1, Condition A for RCS pressure less than 2205 psig. ITS 3.4.11, Condition B -One PORV inoperable and not capable of SRO being manually cycled. Actions include the following:

B.1 Close associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND B.2 Remove power from the associated block valve within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND B.3 Restore PORV to Operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Verbally acknowledge that RC-536 must be closed and breaker open SRO within one hour. SRO may direct WCC SRO to dispatch operator to open the breaker to RC-536. NOTE: Crew should notify WCC SRO and/or l&C to write a work request, investigate and initiate repairs, and notify the Operations Manager. At Chief Examiner's discretion after ITS is addressed, proceed to Event 4 {RCP "A" #1 Seal Failure).

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 1 Event # _4_,..._s

....... 6 ___ Page 14 of _3_5 ___ -l 1 Event

Description:

RCP "A" #1 Seal Failure, SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:

When directed, insert Event 4, RCP "A" #1 seal failure. EVENT INDICATIONS:

RCP "A" Seal Leakoff rising (Pen #1 on FR-154A) APP-001-02, RCP #1 SEAL LEAKOFF HIGH FLOW RO Refer to APP-001-02.

SRO Enters AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS.

SRO Evaluate plant conditions and Go to Section A. RO Continuous Action Step: Check any RCP #1 seal leakoff flow> 5.7 GPM. (YES) Check RCP #1 seal leakoff flow on unaffected RCPs decreased (YES) OR RO RCP Thermal Barrier DP on affected RCP decreased. (YES) CAUTION: To prevent damage to the RCP seal stack, the RO should close seal leakoff valve CVC-303A between 3 and 5 minutes of stopping the RCP. SRO Check Plant status in Mode 1, and direct tripping the Reactor, tripping RCP "A" and then going to PATH-1. RO Attempts to trip the reactor using the reactor trip pushbutton above TR-408. Candidate identifies that reactor does not trip. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 1 Event # _4_._, 5_,_, _6 ___ Page 15 of _3_5 ____ 11 Event

Description:

RCP "A" #1 Seal Failure, SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time Position II Aoolicant's Actions or Behavior RO Attempts to trip the reactor using the reactor trip pushbutton below the Safety Injection Valve Status Lights. RO Verifies that the reactor has tripped. RO Trips "A" RCP BOOTH OPERATOR:

Insert Event 5, SIG "B" Tube Rupture when the reactor is tripped. RO Immediate Action Step: Reactor Tripped. (YES) BOP Immediate Action Step: Turbine Tripped. (YES) BOP Immediate Action Step: E-1 AND E-2 energized (YES) RO Immediate Action Step: SI initiated. (NO) RO Immediate Action Step: SI initiation required. (YES) SRO Enters PATH-1 and verifies PATH-1 Immediate Actions. NOTE: Following the performance and verification of PATH-1 Immediate Actions, the crew will continue with AOP-018. These steps may be handed off to the RO/BOP to perform independently.

The remaining steps of AOP-018 are listed here. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _4_,_s ...... 6 ___ Page 16 of _3_5 ___ .... 1 Event

Description:

RCP "A" #1 Seal Failure, SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Applicant's Actions or Behavior Critical RO/BOP WHEN at least 3 minutes have elapsed since tripping the affected RCP, Task THEN Close Seal leakoff valve for RCP "A". (CVC-303A)

RO/BOP The Seal leakoff valve should be closed within 5 minutes of stopping the affected RCP. RO/BOP Check SI -Actuated. (YES) RO/BOP Check APP-002-F7, INSTR AIR HOR LO PRESS -EXTINGUISHED (YES) RO/BOP Reset Safety Injection RO/BOP Reset Containment Isolation Phase A RO/BOP Momentarily place IA PCV-1716, INSTRUMENT AIR ISO TO CV Switch, to RESET position.

RO/BOP Check INST AIR VALVE TO CONT. PCV-1716 -OPEN (YES) RO/BOP Check RCP "B" or "C" running. (YES) RO/BOP Check RCP "B" running (YES) RO/BOP Check RCP C running (YES) RO/BOP Check RCP seal injection flow between 8 and 13 GPM. (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # --4 , 5, 6 Page 17 of 35 Event

Description:

RCP "A" #1 Seal Failure, SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Applicant's Actions or Behavior Dispatch an operator to locally throttle RCP SEAL WATER FLOW CONTROL VALVE(S) to obtain flow to each RCP between 8 gpm and 13 gpm. -CVC-297A RO/BOP -CVC-297B -CVC-297C IF required to maintain minimum flow, THEN throttle HIC-121, CHARGING FLOW Valve while maintaining Charging Pump Discharge pressure less than 2500 PSIG. RO/BOP Check FCV-626, THERM BAR FLOW CONT Valve CLOSED. (NO) RO/BOP Inform SRO to Implement EALs and Refer to Technical Specifications 3.4.17, 3.4.13, 3.4.4, 3.4.5, 3.4.6, 3.6.3. Examiner Note: This is the end of AOP-018 steps. PATH-1 steps recommence below. SRO Open Foldout A BOP MSR Isolation

-Closes all Purge and Shutoff Valves Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario#

1 Event# _4_._, s ..... _6 ___ Page 18 of _3_5 ___ --1 1 Event

Description:

RCP "A" #1 Seal Failure, SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Applicant's Actions or Behavior RUPTURED S/G ISOLATION CRITERIA (BOP may not recognize the ruptured S/G during initial Foldout A entry depending on time Event #5 initiated and/or plant conditions.)

IF the conditions below are met, THEN perform the following:

The Ruptured SIG is identified by observing an uncontrolled level increase OR abnormal radiation level on the R-19s or R-31s. AND The Ruptured S/G Level is Greater than 8% [18%] BOP a. Reset SI. Indications Available:

b. CLOSE the appropriate Auxiliary Feedwater isolation valves to the Ruptured S/Gs. S/G"B"

• V2-14B. SDAFW PUMP DISCH

• V2-16B. AFW HOR DISCH c. WHEN desired, THEN Perform Supplement G, Steam Generator Isolation "B" S/G level trending up at a faster rate than "A" and "C" S/Gs. "B" S/G level continues to trend up when feed secured to "B" S/G. PZR level continues to decrease.

PZR Pressure continues to decrease.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _5_a_n_d_6

___ Page 19 of _3_5 ___ """ 1 Event.Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Position A licant's Actions or Behavior NOTE: RO may recognize that neither SI Pump started and take early action to start both SI pumps. NOTE: Candidate may direct that Supplement G be performed to isolate S/G B. Supplement G steps begin on Page 32. SRO Foldout A is in effect. RO Verify Phase A Isolation valves closed (YES) BOP Verify FW isolation valves closed (YES) BOP Verify both FW pumps tripped (YES) BOP Verify both MDAFW pumps running (YES) BOP If Additional Feedwater is required, THEN Start SDAFW Pump (RunninQ)

Critical Verify two SI pumps running (NO) (RO will have to manually start Task RO both SI pumps. May have been previously started after the SI was initiated.)

Booth Operator:

Increase "B" S/G tube rupture to 800 gpm. RO Verify both RHR pumps running (YES) RO Verify SI valves properly aligned (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

1

--_5_a_n_d 6 ___ Page 20 of _3.;..;;5

___ -1 1 Event

Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Annlicant's Actions or Behavior RO At least one CCW pump running (YES) BOP All SW & SW booster pumps running (YES) RO Verify CV Fans HVH-1,2,3 & 4 running (YES) RO Verify IVSW initiated (YES) Verify CV ventilation isolation (YES) Verify the following valves -CLOSED: -V12-6, CONT PURGE VALVE -V12-7, CONT PURGE VALVE RO -V12-8, CONT PURGE VALVE -V12-9, CONT PURGE VALVE -V12-10, CONTAINMENT PRESSURE RELIEF -V12-11, CONTAINMENT PRESSURE RELIEF -V12-12, CONTAINMENT VACUUM RELIEF -V12-13, CONTAINMENT VACUUM RELIEF Verify control room ventilation aligned for pressurization mode (YES) Operator to verify the following:

-Verify CONT RM AIR EXHAUST Fan, HVE-16 -STOPPED -Verify CLEANING Fan HVE-19 A/B -RUNNING BOP -Verify CONTROL ROOM AIR EXHAUST FAN DISCHARGE DAMPER, CR-D1A-SA

-CLOSED -Verify CONTROL ROOM AIR EXHAUST FAN DISCHARGE DAMPER, CR-D1 B-SB -CLOSED -!E CR-D1A-SA OR CR-D1 B-SB have lost power, THEN locally verify oosition in the Control Room Kitchen. ( BOP Verify both EDGs running (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # --5 and 6 Page 21 of 35 Event

Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Aoolicant's Actions or Behavior Continuous Action Step BOP Restart Battery Chargers within 30 minutes of Power Loss using OP-601 (Not Required)

RO Continuous Action Step CV pressure remained below 10 psig (YES) BOP Automatic steam line isolation initiated (NO) BOP Automatic Steam Line Isolation Required (NO) BOP Locally open the breaker for HVS-1 at MCC-5 within 60 minutes of SI Initiation Booth Operator Open breaker for HVS-1 on MCC-5 compartment 7-J 3 minutes after being contacted by the crew. RO RCS pressure greater than 1350 psig [1250 psig] (NO) RO SI flow verified (YES) RO RCS pressure >125 psig (YES) BOP At least 300 GPM AFW flow available (YES) BOP Verify AFW valves properly aligned (YES) BOP Control AFW flow to maintain SIG levels between 8% [18%] and 50% Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # --_5_a_n_d_6

___ Page 22 of _3_5 ___ -1 1 Event

Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start A licant's Actions or Behavior RO RCP Thermal Barrier Cooling Water Hi or Lo flow alarms illuminated (NO) BOP Place Steam Dump Mode switch to Steam Pressure RO RCS temperature stable at or trending to 547°F (NO) RO RCS Temperature Greater than 547°F (YES) BOP Dump Steam using Condenser Dumps or Steam Line PORVs to attain 547°F. RO PZR PORVs Closed (NO) RO RCS PRESS Greater Than 2335 psig (NO) RO Close PZR PORVs RO PZR PORVs Closed (NO) RO Close PORV Blocks RO PORV Blocks Closed (YES) PZR Spray & Aux Spray valves closed (YES) RO (Note: With PC-444J in Manual this question may be answered NO if the output of PC-444J is not adjusted to close the spray valves. The following steps with a"@" are if answered NO.) RO @RCS PRESS Greater than 2260 psig. (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _5_a_n_d_6

___ Page 23 of _3_5 ___ Event

Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time Position A licant's Actions or Behavior RO @Close PZR Spray AND Aux Spray Valves RO @IF PZR Spray Valves Fail to Close THEN Stop RCP Supplying Failed Valve RO @IF Aux Spray Valves Fail to Close, THEN Close LCV-460A AND B AND HCV-121 RO At least one RCP running (YES) RO At least one SI Pump Running (YES) (Both SI pumps had to be manually started.)

RO RCS Subcooling Less Than 35°F [55°F] (NO) BOP Any SIG with uncontrolled depressurization (NO) BOP Any SIG Completely Depressurized (NO) BOP R-19s, R-31s, R-15 rad levels normal (YES) BOP R-2, R-32A, R-32B Rad Levels Normal (YES) RO CV Pressure Normal (YES) RO CV Sump Level Normal (YES) RO RCS Subcooling greater than 35°F. (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario#

--Event# _5.;...a.;...n_d_6

___ Page 24 of _3.;..;;5;.__

__ -1 Event

Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Applicant's Actions or Behavior BOP Level in at least one SIG Greater than 8%. (YES) RO RCS Pressure greater than 1650 psig. (NO) RO Reset SPDS and monitor CSFSTs. BOP Control AFW Flow to Maintain SIG Levels between 8% and 50%. (SIGs A and C) BOP Any SIG with uncontrolled level increase. (YES -"B" SIG) SRO Transition to Path-2, Entry Point J RO Reset SPDS AND Initiate Monitoring of Critical Safety Function Status Trees CREW Open Foldout C {No steps apply) RO When Below 10-10 AMPS, THEN Energize Source Range Detectors AND Transfer Recorder BOP Request Periodic Activity Samples of All SIGs BOP Place Steam Dump Mode Switch to Steam Pressure BOP Open QCV-10426 to bypass Condensate Polishers BOP Close C-48A AND C-48B to isolated Hotwell return to CST Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # --_5_a_n_d_6

___ Page 25 of _3_5 ___ _.1 Event

Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Applicant's Actions or Behavior RO At Least One RCP Running (YES) RO At Least One SI Pump Running (YES) RO RCS Subcooling Less than 35°F [55°F] (NO) BOP Ruptured S/G Identified (YES) BOP Maintain at Least One S/G Available for RCS Cooldown BOP Verify Ruptured Steam Line PORV Setpoint at 1035 PSIG using Status Board BOP Verify RCS Temperature Less Than 547°F Prior to MSIV Closure BOP Close Ruptured S/G MSIV and MSIV Bypass BOP Ruptured S/G MSIV and MSIV Bypass Closed (YES) Continuous Action Step BOP When Ruptured S/G Pressure decreases Below 1035 PSIG THEN Verify Ruptured Steam Line PORV Closed BOP IF MDAFW Pump is not Available, THEN Maintain at least One SIG supply to SDAFW Pump BOP Close Ruptured S/G Steam Shutoff to SDAFW Pump BOP Verify S/G Slowdown Isolation and Sample Valves Closed Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 1 Event # _5_a_n_d_6

___ Page 26 of _3_5 ___ -1 1 Event

Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Aoolicant's Actions or Behavior BOP Locally Close Warmup Steam Supply From Ruptured SIG to SDAFW Pump Booth Operator Close Warmup Steam Supply Valve (MS-29) and Report action 3 Minutes after requested BOP Locally Close MSIV Above and Below Seat Drains from Ruptured SIG Booth Operator Report Above and Below Seat Drains are closed 3 Minutes after requested BOP Isolate Feed Flow to Any Ruptured SIG that is Faulted Unless Needed for RCS Cooldown Continuous Action Step BOP When Ruptured SIG Level Greater Than 8% [18%] THEN Isolate Feed Flow Continuous Action Step BOP Open Breakers for any V1-8, V2-14 AND V2-16 Valve Closed to Isolate Ruptured SIG Booth Operator Wait 3 minutes to Open Breakers as requested and report action complete.

BOP Control Feed Flow to Maintain Intact SIG Level Between 8% [18%] and 50% BOP Any Other SIG with Uncontrolled Level Increase (NO) RO PZR PORVs Closed (NO) RO RCS PRESS Greater than 2335 PSIG (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _5_a_n_d_6

___ Page 27 of _3_5 ___ _.1 Event

Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Applicant's Actions or Behavior RO CLOSE PZR PORVs RO PZR PORVs CLOSED (NO) RO CLOSE PORV BLOCKS. RO PORV BLOCKS CLOSED (YES) RO Open At Least One PORV Block Unless Closed to Isolate an Open PZR PORV Continuous Action Step RO IF PZR PORV Opens on High Pressure, THEN Verify Reclosure at or Below 2335 PSIG. Close PORV Blocks as Necessary RO Reset SI Continuous Action Step RO/BOP IF Offsite Power is Lost, THEN Restart Emergency Safeguard Equipment RO Reset CV Spray RO Reset Phase A and Phase B RO Establish Instrument Air to CV. IF Compressor not Running, THEN Start Compressor BOP All AC Susses Energized by Offsite Power (YES) RO RCS Pressure Greater Than 275 PSIG [400 PSIG] (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 1 Event # --5 and 6 Page 28 of 35 Event

Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Aoolicant's Actions or Behavior RO Stop RHR Pumps Continuous Action Step RO IF RCS Pressure Decreases Below 275 PSIG [400 PSIG], THEN Restart RHR Pumps Critical Ruptured S/G Isolated (YES) Task The following must be Isolated to satisfy isolation:

-V1-38, MSIV -MS-3538, MSIV V1-38 BYP -"B" SIG PORV Closed and setpoint at 1035 psig. -FRV "B" (Not needed if V2-6B closed.) -FRV"B" BYP BOP -V2-68, FW HOR SECTION (Not needed if FRV and FRV BYP closed.) -V2-14B, SDAFW PUMP DISCH Valve -V2-16B, AFW HOR DISCH Valve -V1-88, SDAFW STEAM SHUTOFF Valve -SIG B Slowdown AND Slowdown Sample Valves -MS-29 (No indication in Control Room) -SIG "B" MSIV Above and Below Seat Drain Valves (No indication in Control Room.) BOP Ruptured S/G Pressure Greater Than 220 PSIG (YES) BOP At Least One Intact SIG Available for RCS Cooldown (YES) NOTE: After the Low Steam Line Pressure SI Signal is Blocked, Main RO/BOP Steam Line Isolation will occur if Hi Steam Line Flow Rate Setpoint is Exceeded Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 1 Event # _5_a_n_d_6

___ Page 29 of _3_5 ___ -l 1 Event

Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Aoolicant's Actions or Behavior Determine Required Core Exit Temperature From Table-3 Table -3 Ruptured S/G Pressure (PSIG) Required Core Exit Temperature RO/BOP (oF) Greater than 1000 490 [470] 900-1000 480 [460] 800-899 465 r445l 700-799 450 [430] 600-699 435 [415] Continuous Action Step RO When PZR Pressure Decreases to Less Than 2000 PSIG, THEN Block PZR Pressure/HiQh Steam Line DP SiQnals RO IF RCPs are NOT Running, THEN Do Not Monitor CSF-4 BOP Condenser Available For Steam Dump (YES) RO Verify T-AVG less Than 543°F AND Block T-AVG SI Signal Prior to Maximum Steam Dump BOP Place Steam Dump Control Switch to Bypass T-avg Interlock Dump Steam From Intact S/G to Condenser at Maximum Rate BOP -PC-464B is placed in manual with output adjusted to approx. 42%. -Second AFW pump should be started RO At Least One Charging Pump Running (YES) RO Align Charging Pump Suction To RWST RO Establish Charging Flow to Maintain PZR Level Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 1 Event # _5_a_n_d_6

___ Page 30 of _3_5 _____ 1 Event

Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Applicant's Actions or Behavior Core Exit Temperature Less Than Required Temperature (NO) RO (PATH-2 begins a loop until CET is less than Required Temperature)

RO WHEN CET is less than Required the steps begin again. Core Exit Temperature Less Than Required Temperature (YES) BOP Reduce Steam Flow to Stabilize RCS Temperature CREW Allow RCS Temperature to Stabilize from cooldown prior to continuing BOP Ruptured S/G pressure stable or increasing (YES) RO RCS Subcooling Greater Than 55°F [75°F] (YES) RO Normal Spray Available (YES) RO Close Spray valve associated with the idle RCP(s) using Table 1 (N/A) RO PZR Level Greater Than 71 % [60%] (NO) RO/BOP Ruptured S/G pressure greater than RCS pressure (NO) Continuous Action Step RO When PZR level greater than 10% [32%], Then reduce charging flow to minimum RO RCS Subcooling Less Than 35°F [55°F] (NO) Open PZR Spray Valves to Depressurize RCS, IF Spray valves will RO not open, THEN go to Entry Point L (PATH-2 begins a loop until the PZR level is greater than 71%) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _5_a_n_d_6

___ Page 31 of _3_5 ___ _, 1 Event

Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time II Position II Applicant's Actions or Behavior RO PZR Level Greater Than 71 % [60%] (YES) RO Verify PZR Spray and Aux Spray valves closed. RO IF PZR Spray Valves fail to close, THEN Stop RCP supplying failed valve. RO IF Aux Spray Valve Fails to close, THEN Close CVC-460A and BAND HCV-121 RO/BOP Maintain RCS and Ruptured S/G Pressures Less than 1035 PSIG RO RCS Subcooling Greater Than 35°F [55°F] (YES) BOP Level in at least one intact S/G greater than 8% [18%] (YES) RO RCS Pressure Stable or Increasing (YES) RO PZR Level Greater Than 10% [32%] (YES) RO Stop SI Pumps The Chief Examiner may terminate the scenario anytime after the RCS cooldown has been commenced or at his discretion.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _5.;,__ ____ Page 32 of _3;;;..;5;..._

__ Event

Description:

SIG "B" Tube Rupture (Supplement G) Time II Position II Aoolicant's Actions or Behavior SUPPLEMENT G Steps SRO Directs the BOP to perform Supplement G to isolate SIG "B" Go To Appropriate Step From Following Table: BOP I SIG TO BE ISOLATED I STEP I I SIG B I 18 I BOP Check SIG B -FAUL TED (NO). BOP Continuous Action Step When Tavg less than 547°F THEN Close V1-3B and MS-353B. Continuous Action Step BOP When SIG B level is greater than 8% THEN perform the following steps: BOP Verify FRV B -Closed (YES) BOP Verify FRV B BYP -Closed (YES) BOP Verify V2-6B, FW HOR SECTION Valve -CLOSED. (YES) BOP Verify V2-14B, SDAFW PUMP DISCH Valve -CLOSED. (YES) BOP Verify V2-16B, AFw HOR DISCH Valve CLOSED. (YES) Continuous Action Step BOP Verify "B" Steam Line PORV setpoint at 1035 psig using Status Board. (YES) BOP Verify V1-8B, SDAFW STEAM SHUTOFF Valve -CLOSED. (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 1 Event # _s _____ Page 33 of _3_5 ___ _, 1 Event

Description:

SIG "B" Tube Rupture (Supplement G) Time II Position II Applicant's Actions or Behavior BOP Verify S/G B Slowdown AND Slowdown Sample Valve Status Light indication

-CLOSED. (YES) Dispatch Operator To The Pipe Jungle To Close MS-29, SG "B" BOP BYPASS ORN & WARM-UP LINE TO AFW PUMP (located above/right of V1-8B). Booth Operator Close Warmup Steam Supply Valve (MS-29) and Report action 3 Minutes after asked BOP Check S/G "B" MSIV Above And Below Seat Drain Valves -CLOSED. Booth Operator Report Above and Below Seat Drains are closed 3 Minutes after requested.

BOP Dispatch Operator To The Aux. Bldg I E1-E2 Room To Perform The Following:

At MCC-9, verify V2-14B closed AND open breaker V2-14B, SDAFW PUMP TO SIG B (CMPT-1 C) At MCC-6, verify V1-8B closed AND open breaker V1-8B, SDAFW PUMP STEAM ISOLATION (CMPT-16M)

At MCC-10, verify V2-16B closed AND open breaker V2-16B, MDAFW PUMP HEADER DISCHARGE TO SIG B (CMPT-4F)

Booth Operator Wait 3 minutes to Open Breakers as requested and report action complete BOP Go to Step 49 BOP Check All Faulted AND Ruptured S/Gs -ISOLATED (YES) BOP Check any S/G -Ruptured (YES) BOP Perform the following to minimize Secondary system contamination:

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _5 _____ Page 34 of _3_5 ___ -1 1 Event

Description:

SIG "B" Tube Rupture (Supplement G) Time II Position II Aoolicant's Actions or Behavior

• Direct AO to start Auxiliary Boilers .

• IF Condensate Polishers are in service:

• Verify QCV-10426, SECONDARY BYPASS -OPEN. (YES)

• Locally depress the OFF Pushbutton on Condensate Polisher Vessels A, B, C, D, E and F.

• Secure ANY evolution that passes water through the beds, such as a low volume rinse. BOP Verify Hotwell return to CST isolated as follows:

• Locally verify C-48A, LCV-1417B INLET -CLOSED .

• Locally verify C-48B, LCV-1417B DISCHARGE

-LOCKED CLOSED. BOP Dispatch An Operator To Close GS-36, MANUAL GLAND STEAM DUMP. End of Supplement G Steps Appendix D NUREG-1021, Rev. 9, Supp. 1 ILC-11-1 NRC SCENARIO 1 TURNOVER SHEET POWER LEVEL: Core Burnup: EFPD: Boron: Xenon: Tavg: Bank D Rods 100% RTP 9000 MWD/MTU 257 EFPD 745 PPM EQXenon 575.9°F 218 Steps EQUIPMENT UNDER CLEARANCE:

• "A" CCW Pump OOS and Breaker Racked Out EQUIPMENT STATUS:

• 5 GPO Primary to Secondary Leakage identified into "C" SIG

• R-24C in Alarm (APP-036-C7)

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties."

• RV-3 ("C" Steam Line PORV) Caution Capped. INSTRUCTIONS FOR THE WATCH:

• Reduce Reactor Power and Turbine Load to 85% to support Maintenance on "A" Heater Drain Pump. "A" Heater Drain Pump has severe packing leakage. Appendix D NUREG-1021, Rev. 9, Supp. 1 Unit 2 Status Board I Date: lToday ITime: 16:00:00 AMICvcle:

27 MWD/MT: 9000 Desicm: 16590 IEFPD l257 I Design l473.5 I Tank Level% I Status HUT Level% Status Monitor A 10 Standby eves-A 20 Filling Monitor B 38 Standby CVCS-B 10 Standby WCTA 37 Standby CVCS-C 86 Standby WCTB 7 Standby WHUT #NAME? Filling WCTC 9 Standby WCTD 10 Standby Data Linked to Pl WCTE 9 Standby WGDTS Pressure PSIG I Status A #NAME? PSIG On cover DEMINERALIZERS B #NAME? PSIG In Service PPM In Service Date I Resin Replaced c #NAME? PSIG Isolated MBA 2194 YES 7/17/2010 5/4/2010 D #NAME? PSIG Standby MBB 2265 NO 7/17/2010 3/29/2010 CATION 1021 NO 9/17/2010 12/9/2009 Shutdown Requirement Temp Boron DEBA 0 NO New 2/3/2010 1.77% =L>K/K 547 F Hot 795 DEBB 0 NO 3/28/2010 1.77% =L:'.>K/K F 1053 SFP 1963 NO 9/23/2008 4/22/2008 2.6% =L:'.>K/K 100 F Cold 1182 6% =L:'.>K/K N/A 1950 SGBD Condenser Air lnleakage Target Value GPM Status PORV Settings A 13 CFM A 50 Flash Tank Setting Date POT GP-3 Psig B 0 CFM B 50 With Heat A 7/18/2010 3.21 1000 Known 8 CFM c 50 Recovery B 7/18/2010 3.12 1040 Total 5 CFM N2 Flow 8 SCFM c 7/18/2010 3.44 1000 Effluent Radiation Monitor Setpoints RCS Leakage 0.00 Unidentified Rad Current Alert Value 200X NUEValue Monitor Setpoint 2X Total 0.03 GPM R-14C 1.01E+04 N/A 2.020E+04 PRT 0.02 GPM R-20 7.40E+03 N/A 1.480E+04 RCDT Leakage 0.01 GPM R-18 1.00E+06 2.000E+08 2.000E+06 Charging Leakoff 0 GPM R-19A 1.05E+04 2.100E+06 2.100E+04 Misc Identified 0 GPM R-19B 9.72E+03 1.944E+06 1.944E+04 Primary/Secondary 0 GPO R-19C 9.58E+03 1.916E+06 1.916E+04 Secondarv Loss 17.3 GPM R-37 8.53E+03 1.706E+06 1.706E+04 Manually Entered Data Linked to Chem data base Hi Flux At Shutdown Boron PPM Date PPM Date 'PPM Previous ARI Counts Setpoint RCS Today 745 Nl-31 50 150 BAST-A 9/16/2010 21,535 #NAME? #NAME? Nl-32 60 180 BAST-B 9/16/2010 21,032 #NAME? #NAME? SFP 9/15/2010 2246 #NAME? #NAME? Normal Currents RWST 9/16/2010 2219 #NAME? #NAME? UPPER LOWER TARGET %BAND Accum-A 8/30/2010 2211 #NAME? #NAME? N-41 125 119 *1.5 5 +/-Accum-B 8/30/2010 2206 #NAME? #NAME? N-42 110 109 -1.5 5 +/. Accum-C 8/30/2010 2230 #NAME? #NAME? N-43 105 99 -1.5 5 +/. RHR 7/6/2010 2221 N-44 98 94 *1.5 5 +/. Refuel Canal POWERTRAX Rev# 2.1.0 RNP %APL 112.55 Refuel Cavity SFP Canal FANS Test/Hrs Date/Tst HVE-1A/B 35640.6 3/8/10 Notes/Additional Data HVE-15A 18643.5 3/18/10 IC-13, 42 HVE-19A/B 6928.3 5/3/10 MOL SR 3.7.11.2 Last Completed 5/27/2010 19:45 .

I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.: 2 Op Test No.: Examiners:

Operators:

SRO-RO-BOP-Initial Conditions:

• 50% RTP BOL, 150 MWDIMTU, 1277 ppm Boron . * "A" CCW pump inoperable with the breaker racked out * "B" MFP breaker racked out for maintenance .

• 5 GPD primary to secondary leakage into SIG "C"

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties Turnover:

• Holding reactor power at 50% for maintenance on Main Feedwater Pump B motor. Critical Tasks:

• Isolate feedwater to SIG B

• Open at least 1 of the CV Spray Pump Discharge valves to provide CV Spray flow.

• Throttle AFW flow to the SIGs at 80-90 GPM . Event Malf. Event Type* Event No. No. Description 1 (I) RO, SRO VCT Level Transmitter LT-112 fails HIGH 2 (I) RO, BOP, SRO First Stage Pressure Transmitter PT-446 fails LOW (TS) SRO 3 (C) RO, SRO CCW Pump B trips and CCW Pump C fails to auto start (TS) SRO 4 (C) BOP, SRO CondenserVacuumleakage 5 (R) RO Load Reduction due to Condenser Vacuum lowering (N) BOP, SRO 6 (M) ALL Steam Line Break inside the CV 7 ALL All SIGs Faulted inside the CV on the Reactor Trip * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1

\Appendix D Scenario Outline Form ES-D-1 I ILC-11-1 NRC SCENARIO 2

SUMMARY

DESCRIPTION The crew will assume the watch with the unit being maintained at 50% RTP while maintenance is performed on Main Feedwater Pump B motor. The previous shift had identified seal leakage on CCW Pump A. The motor breaker has been racked out and the pump has been isolated and cleared for maintenance.

5 GPO primary to secondary leakage has been identified in S/G C with elevated readings on the applicable radiation monitors.

Shift instructions are to maintain current reactor power until MFW Pump B is returned to service. On cue from the Chief Examiner, VCT Level Transmitter LT-112 will fail HIGH. This will cause LCV-115A to divert all letdown flow to the CVCS HUTs and will cause LC-112, VCT Level Controller, to go to full output. This failure will result in an automatic makeup to the VCT, which will alert the operators to determine the cause of the makeup operation.

AOP-003, Malfunction of Reactor Makeup Control, will be implemented and LCV-115A will be overridden to the VCT until the VCT level control can be restored on the alternate channel. This will require that the alternate channel (L T-115) be selected for all control functions of VCT level. Once AOP-003 actions are completed and on cue from the Chief Examiner, First Stage Pressure Transmitter PT-446 will fail LOW. The crew will perform the immediate actions for PT-446 failure IAW AOP-025, RTGB Instrument Failure, Section H. The immediate actions include checking that a turbine load reduction is not in progress, checking that S/G levels are being controlled in auto to 39% and placing the control rods in manual to maintain reactor power at less than 100%. When the rods are placed in manual the Automatic Rod Control function for the rods will be removed. The rods will have to be controlled in manual. The crew will perform the necessary transfer of the controlling channel and restore the S/Gs to their programmed level for the present reactor power level. The failed pressure transmitter will be removed from service IAW OWP-033, FSP-1. ITS Table 3.3.1-1 Item 17e, Turbine Impulse Pressure, P-7 input Condition T requires to verify interlock is in required state for existing unit conditions within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in Mode 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (Current plant conditions requires that the REACTOR TRIP BLOCK P-7 status light be extinguished).

ITS Table 3.3.2-1 Items 1f, 1g, 4d, and 4e for Safety Injection and Steam Line Isolation High Steam Line Flow with Low Tave or Low Steam Line Pressure -Condition D: Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR Be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Be in Mode 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. ITS Table 3.3.6-1 Item 4 Safety Injection for Containment Ventilation Isolation Instrumentation refers to LCO 3.3.2 Functions 1.a-f (which have already been addressed).

Once the pressure transmitter has been removed from service and the Chief Examiner is satisfied with the Tech Specs compliance, the Chief Examiner will cue the next event. CCW Pump B will trip on overcurrent and CCW Pump C will fail to auto start on CCW System low pressure.

The crew will manually start the standby CCW Pump by following the actions in APP-001-F4 for motor overload, APP-001-F5 for system low pressure or enter AOP-014, Component Cooling Water System Malfunction, Section C for System Low Pressure.

The SRO will implement ITS 3.7.6, Condition A due to CCW Pump Bis powered from an emergency power source. Once the Chief Examiner is satisfied with the Tech Spec compliance, he can cue the next event. On cue from the Chief Examiner, Condenser vacuum leak will be initiated and vacuum will start to lower. This will be noted by rising Condenser backpressure and lowering net MWe. AOP-012, Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 Partial Loss of Condenser Vacuum or Circulating Water Pump Trip, will be implemented.

The standby Condenser Vacuum Pump will be started and a search for the vacuum leak will be initiated.

Unit load will have to be reduced to ensure that operation within the Condenser Backpressure Limits is maintained in the allowable region of the curve. The Condenser vacuum leak will be varied from 80 -100 scfm to ensure crew continues with power reduction.

Once the Chief Examiner is satisfied with the crew response to the unit load reduction, he can cue the next event. The steam line from SIG B will fault inside the CV. The crew will diagnose the event and make the determination that the reactor needs to be manually tripped. Upon the reactor trip, all SIGs will be faulted inside the CV. PATH-1 will be implemented with Safety Injection initiated.

The discharge valves for the CV Spray Pumps will not automatically open and will require that at least one of the valves be manually opened to provide CV Spray flow. Feedwater Regulating Valve FCV-488 and its respective Feedwater Block valve V2-6B will fail to close on the SI signal, resulting in excessive feedwater flow into SIG B and will have to be manually closed from the RTGB control switches to terminate the flow. The crew will transition through PATH-1 and will transition to FRP-P.1, Response to Imminent Pressurized Thermal Shock, to throttle AFW flow to all of the SIGs at a reduced rate of 80-90 GPM to each SIG. After throttling AFW the crew will transition to FRP-H.1, Response to Loss of Secondary Heat Sink, and immediately reset SPDS and return to procedure and step in effect since entry was due to operator actions. The Chief Examiner may terminate the scenario at any time after AFW flow has been established to all of the SIGs at a reduced flow rate. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 ILC-11-1 NRC SCENARIO 2 SIMULATOR SETUP IC/SETUP:

• IC-802, SCN:008_NRC_2

• "A" CCW Pump inoperable with the breaker racked out * "B" Main Feed Pump breaker racked out for maintenance.

• 5 GPO primary to secondary leakage into S/G C

• R-15 at 24 cpm, R-19C at 232 cpm, R-31C at 0.450 mR/hr

• Status board updated to reflect IC-4. PRE-LOADED EVENTS: The following events should occur on the reactor trip: Event 7: All S/Gs Faulted inside the CV Event 8: FCV-488 and V2-6B fail to Close on SI Event 9: CV Spray Pump Discharge Valves Sl-880s fail to Open EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:

Event 1: VCT Level Transmitter LT-112 fails HIGH Event 2: First Stage Pressure Transmitter PT-446 fails LOW Event 3: Event 4: CCW Pump B Trips on Overcurrent and CCW Pump C fails to auto start Condenser Vacuum Leakage Event 5: Event 6: Load Reduction due to Condenser Vacuum lowering Steam Line Break on SIG B inside the CV EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

• AOP-003

• OWP-005, CVC-19

• AOP-025 Main Body and Section H

• OWP-033, FSP-1

• AOP-014 Main Body and Section C

• AOP-012

• PATH-1

• Foldout A

• FRP-P.1

• FRP-H.1 Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -----Page 5 of _2_7 ___ _, 1 Event

Description:

VCT Level Transmitter L T-112 fails HIGH Time ii Position Ii Aoolicant's Actions or Behavior BOOTH OPERATOR:

When directed, insert Event 1, VCT Level Transmitter L T-112 fails HIGH EVENT INDICATIONS:

VCT/HLDP TK DIV LCV-115A aligns to the Holdup Tank Ll-115 lowering Auto makeup occurs at 20 inches VCT Level LC-112 fails to full scale APP-003-E3, VCT HI/LO LVL, illuminated if level decreases to 17 inches RO Diagnoses high failure of VCT level transmitter L T-112. SRO Enters AOP-003, "Malfunction of Reactor Makeup Control".

RO Check for failure of a level transmitter as follows:

• Obtain VCT level for LT-115 from ERFIS .

• Obtain VCT level for L T-112 from ERFIS .

• Check VCT Level Indicators

-Oscillating Level Deviation Observed (NO)

• Check deviation between L T-112 and L T-115 greater than 8" (13%) (YES) RO Check L T-115 failed. (NO) RO Check LT-112 failed. (YES) RO Check L T-112 -Failed High (YES) CAUTION: With NO operator action, L T-112 failing high with makeup flow less than charging suction flow will result in a loss of Charging Pump suction. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # --Page 6 of 27 Event

Description:

VCT Level Transmitter L T-112 fails HIGH Time II Position II Applicant's Actions or Behavior RO Place LCV-115A, VCT I HLDP TK DIV, to VCT position.

BOP Obtain Hagan Rack Key number 10. BOP Implement OWP-005, CVC-19 * (OWP-005, CVC-19) Place the selector switch in the bottom of Hagan Rack 19 to LT-115 position.

BOOTH OPERATOR:

Place selector to LT-115 by inserting IRF CVC067 LT-115 and report back that OWP-005, CVC-19 has been completed.

SRO Check OWP-005, CVC-19-COMPLETED (YES) RO Place LCV-115A in AUTO position.

SRO Contact l&C to repair failed channel. CREW Make PA Announcement for Procedure Entry RO Continuous Action Step Check VCT level decreases to less than 12.5" (21 %) (NO) RO Check VCT level less than 20" (33%) (NO). RO Check VCT level less than 51.5" (86%) (YES) RO Verify Charging and Letdown flows are normal for plant conditions (YES). RO Check APP-003-D5, BA FLOW DEV, illuminated (NO). Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -----Page 7 of _2_7 ___ -1 1 Event

Description:

VCT Level Transmitter LT-112 fails HIGH Time II Position II Aoolicant's Actions or Behavior RO Check APP-003-E5, MAKEUP WATER DEV, illuminated (NO). RO/SRO Check boration required (NO). RO/SRO Check dilution required. (NO) SRO Check ITS for applicable LCO. (NONE apply.) SRO Implement the EALs (NONE apply.) NOTE: Crew should notify wee SRO and/or l&C to write a work request, investigate and initiate repairs, and notify the Operations Manager. Booth Operator Insert Event #2 (PT-446 fails low) on cue from the Chief Examiner.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Page 8 of 27 2 Event

Description:

PT-446 fails LOW Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 2 -First Stage Pressure Transmitter PT-446 fails LOW EVENT INDICATIONS:

PT-446 pressure indication fail to 0 PSIG APP-003-D4, TAVG/TREF DEV APP-005-FS, AMSAC TROUBIBYPD APP-006-D4, E4, F4, SIG A, B, C STM LINE HI FLOW TR-408 Pen #2 defaults to 547°F Crew Determines PT-446 failed low and performs Immediate Actions of AOP-025. Immediate Action Step: BOP Check Turbine Load Reduction in progress or has occurred. (NO, Go TO Step 3) BOP Immediate Action Step: Check SIG Level trend controlling in AUTO to 39%. (YES) Immediate Action Step: Manually control Reactor power and T AvG: RO

• Place the Rod Control Selector Switch in Manual.

• Operate rods to maintain reactor power less than 100%. Booth Operator Insert the malfunction to remove the Automatic Rod Control function once the Rod Control Selector Switch is placed in Manual. SRO Determines AOP-025, RTGB INSTRUMENT FAILURE and enters Section H and verifies Immediate Actions. Crew Make PA announcement for entry into AOP-025. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 2 Event # _2 _____ Page 9 of _2_7 ___ .... 1 Event

Description:

PT-446 fails LOW Time II Position II Aoolicant's Actions or Behavior BOP Check SIG levels stabilized at between 39% and 52%. (YES) Place all FRV Controllers in MANUAL: BOP

• FCV-478, FCV-488, and FCV-498. BOP Place the First Stage Pressure Selector Switch to the alternate channel (PT-447).

EXPECTED ALARMS: APP-006-A3, 83, C3 (S/G A, B, C LEVEL DEV) BOP Restore each SIG level to program level using FRVs or Bypass Valves Continuous Action Step: Restore each FRV to AUTOMATIC as follows: BOP

• Check SIG level within +I-1 % of program level.

• Place the affected controller in AUTO. Continuous Action Step: Restore Rod Control to AUTOMATIC as follows:

• Check TAvG within -0.5 to +0.5°F of T REF AND Axial Offset within RO the target band. (NO) 0 Restore T AVG using manual rod control prior to placing rods in auto.

• Place the Rod Control Selector Switch in AUTO. SRO Remove PT-446 from service using OWP-033, FSP-1. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario#

--2 Event# _2 _____ Page 10 of 27 -----1 Event

Description:

PT-446 fails LOW Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:

When requested, perform steps of OWP-033 to remove PT-446 from service. Actions should include AMSAC portion of OWP-033. If requested to check PT-446, there is no visible damage or leakage noted. SRO Go to procedure Main Body, Step 2. SRO Inform SSO to implement EALs. NOTE: Crew should notify wee SRO and/or l&C to write a work request, investigate and initiate repairs, and notify the Operations Manager. Check Tech Specs for applicable LCOs:

• ITS Table 3.3.1-1 Item 17e, Turbine Impulse Pressure, P-7 input Condition T requires to verify interlock is in required state for existing unit conditions within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in Mode 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (Current plant conditions requires that the REACTOR TRIP BLOCK P-7 status light be extinguished).

SRO

• ITS Table 3.3.2-1 Items 1f, 1g, 4d, and 4e for Safety Injection and Steam Line Isolation High Steam Line Flow with Low Tave or Low Steam Line Pressure -Condition D: Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR Be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Be in Mode 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.

• ITS Table 3.3.6-1 Item 4 Safety Injection for Containment Ventilation Isolation Instrumentation refers to LCO 3.3.2 Functions 1.a-f (which have already been addressed).

SRO Return to Procedure and Step in effect. Booth Operator When Tech Specs are identified and at Chief Examiner's discretion, proceed to Event #3. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # --Page 11 of 27 3 Event

Description:

CCW Pump "B" Trips and CCW Pump "C" fails to auto start Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 3, CCW Pump "B" Trips and CCW Pump "C" fails to auto start EVENT INDICATIONS:

Dual Indication on "B" CCW Pump Fl-613 indicates 0 GPM APP-001-F4, CCW PMP MOTOR OVLD/TRIP APP-001-FS, CCW PMP LO PRESS APP-001-B1, RCP BRG COOL WTR LO FLOW APP-001-01, RCP THERM BAR COOL WTR LO FLOW APP-001-B7, RHR PMP A COOL WTR LO FLO APP-001-C7, RHR PMP B COOL WTR LO FLO APP-001-AS, CCW TO CROM LOW FLOW APP-002-E1, CV SRY PMP COOL WTR LO FLOW APP-002-ES, SI PMP COOL WTR LO FLOW APP-001-AG, LTDN FLOW HI TEMP DEMIN BYPD (Delayed)

Note: Candidates may enter APP-001-F4 and/or APP-001-FS and start the standby CCWPump. The following steps are from the APPs. RO IF the running CCW Pump has tripped, THEN VERIFY Standby CCW Pump STARTED (RO manually starts "C" CCW Pump) RO Dispatches an operator to check breaker and Current Limiter Fuses. (APP-001-F4)

Note: Candidates may enter AOP-014 to address the CCW Low Pressure.

The following steps if AOP-014 is entered. SRO Directs entry to AOP-014. SRO Implement EALs (NONE Applicable.)

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # --3 Page 12 of 27 Event

Description:

CCW Pump "B" Trips and CCW Pump "C" fails to auto start Time II Position II Applicant's Actions or Behavior SRO/RO Go to the appropriate section for indicated Malfunction:

CCW Pump Discharge Pressure Low -Go to Section C RO Check Spray AND Blackout Signal Actuated (NO) BOP Check E 1 AND E2 Susses -Energized by Offsite Power (YES) RO Start one CCW Pump ("C" CCW Pump Manually started.)

RO Check CCW Pump Status -At least one running (YES) RO Check APP-001-FS, CCW PMP LO PRESS -Extinguished (YES) RO Check FCV-626 Closed due to starting Pump (NO) SRO Go to Main Body, Step 4, of AOP-014 RO Check RCS temperature less than 350°F (NO) IF CCW HX outlet temperature is greater than 105°F, then go to step 3 (NO) RO OR IF CCW HX outlet temperature is less than 105°F, then go to step 4.c. (YES) RO Check CCW HX outlet temperature

-Stable OR Decreasing (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario#

2 Event# _3 _____ Page 13 of _2_7 ___ Event

Description:

CCW Pump "B" Trips and CCW Pump "C" fails to auto start Time Position II Aoolicant's Actions or Behavior RO Check APP-001-F5, CCW PMP LO PRESS -Extinguished (YES) Refer to Technical Specifications for Applicable LCOs SRO Enter LCO 3.7.6, Condition A, One required CCW train inoperable

-Restore required CCW train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, due to CCW Pump B OOS and is powered from an emergency power source. SRO Return to Procedure and Step in Effect. NOTE: Crew should notify WCC SRO and/or l&C to write a work request, investigate and initiate repairs, and notify the Operations Manager. Look at Auto Start function of "C" CCW Pump and breaker trip of "B" CCW Pump. Booth Operator Initiate Event #4 (Condenser Vacuum leakage) after ITS entry and on cue from the Chief Examiner.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 2 Event # _4_a_n_d_5

___ Page 14 of _2.;.;.;7

___ --1 1 Event

Description:

Condenser Vacuum leakage and Load Reduction due to Condenser Lowering Vacuum Time A licant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 4, Condenser Vacuum Leakage. EVENT INDICATIONS:

Rising condenser backpressure as indicated on Pl-1310, 1311, 1312 and 1313. Lowering net MWe BOP Diagnosis the lowering condenser vacuum BOP Immediate Action Check Circulating Water Pump -Any Tripped (NO) SRO Enters AOP-012 and verifies immediate actions. BOP Check Condenser Vacuum previously established. (YES) BOP Verify all available Vacuum Pumps Running. (YES) Manually starts "A" Vacuum Pump BOP Verify Vacuum breakers MS-70A and MS-70B closed. (YES) RO/BOP Make PA announcement for entry into AOP-012. SRO Check plant conditions in Mode 1 or Mode 2. (YES) Booth Operator Condenser vacuum leakage (air inleakage) will have to be varied from 80 -100 scfm for condenser backpressure to rise dependent on load reduction by the crew. Continuous Action Step: BOP Check Condenser Backpressure approaches restricted region of Attachment 3, Condenser Backpressure Limit Curve. (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario#

2 Event# _4_a_n_d_5

___ Page 15 of _2_7 ____ 1 Event

Description:

Condenser Vacuum leakage and Load Reduction due to Condenser Lowering Vacuum Time Pos A licant's Actions or Behavior BOP Continuous Action Step: Check Pl-1310 AND Pl-1311 -INCREASING (YES) CREW Reduce Turbine Load using Attachment 2, as necessary, to maintain Condenser back pressure in the allowed region of Attachment

3. Notify Load Dispatcher of the load reduction.

SRO (SRO should also notify Operations Management and/or On-call Manager of the need to perform the power reduction.) -Turbine Load Reduction BOP Check Turbine Control Mode -Automatic (YES) BOP Depress the IMP IN Pushbutton BOP Set the Desired Load in the setter BOP Set the Desired Load Rate (1 %/min) (Higher load rate may be chosen but is not necessary)

BOP/RO Depress the GO and HOLD Pushbuttons as necessary to reduce load. NOTE: The Automatic Rod Control function has been defeated.

If the Crew places the Rod Control Selector switch in AUTO, they should identify the malfunction when turbine load is reduced and Tave-Tref deviation calls for inward rod motion. Crew should determine that rods must be controlled in Manual. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # --4 and 5 Page 16 of 27 Event

Description:

Condenser Vacuum leakage and Load Reduction due to Condenser Lowering Vacuum Time II Position II Aoolicant's Actions or Behavior NOTE: The RO will need to add boric acid to maintain AFD within band while reducing power with Rod Control in Manual. The following steps are for the addition of boric acid from OP-301, Section 8.2.8, Quick Boration Checklist.

Boric Acid additions will most likely be added in multiple batches. Steps only listed once. RO DETERMINE the amount of Boric Acid to add to the RCS and OBTAIN an independent check of the volume required.

RO OBTAIN permission from the CRSS OR the SSO to borate. RO PLACE the RCS MAKEUP MODE selector switch to BORA TE. RO SET YIC-113, BORIC ACID TOTALIZER to desired quantity.

RO IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN AND ADJUST using the UP and DOWN pushbuttons.

RO Momentarily PLACE the RCS MAKEUP SYSTEM switch to START. IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:

RO

• Rod Motion is blocked or in the wrong direction

• T AVG increases

• Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:

• FCV-113A, BORIC ACID FLOW, closes . RO

• FCV-113B, BLENDED MU TO CHG SUCT, closes .

• IF in Auto, THEN the operating Boric Acid Pump stops .

• The RCS MAKEUP SYSTEM is OFF . Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario#

--2 Event# 4 and 5 Page 17 of 27 Event

Description:

Condenser Vacuum leakage and Load Reduction due to Condenser Lowering Vacuum Time II Position II Applicant's Actions or Behavior IF desired, THEN FLUSH the Boric Acid flow path as follows:

• PLACE the RCS MAKEUP MODE selector switch in the ALT DILUTE position.

• SET YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons .

• PLACE FCV-114B, BLENDED MU TO VCT to CLOSE.

• Momentarily PLACE RCS MAKEUP SYSTEM switch to START .

• IF any of the below conditions occur, THEN momentarily place the RO RCS MAKEUP SYSTEM switch in the STOP position:

0 Unanticipated Rod Motion 0 Primary Water addition reaches the desired value

• WHEN the desired amount of Primary Water has been added to the RCS, THEN verify the following:

0 FCV-114A closes. 0 FCV-113B closes. 0 IF in Auto, THEN the operating Primary Water Pump stops. 0 The RCS MAKEUP SYSTEM is OFF. RETURN the RCS Makeup System to automatic as follows:

• VERIFY FCV-114A is in AUTO .

• PLACE FCV-114B to the AUTO position . RO

• PLACE the RCS MAKEUP MODE switch in AUTO.

• VERIFY FCV-113A is in AUTO .

• Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.

RECORD, in AUTO LOG, as indicated by PRIMARY WATER TOTALIZER, RO YIC-114 AND Boric Acid TOTALIZER, YIC-113 the total amount of Primary Water AND Boric Acid added durinq the boration.

RO MONITOR parameters for the expected change in reactivity AND inform the CRSS OR the SSO of the results of the boration.

END OF BORATION STEPS BOP Check Condenser Nitrogen Addition in service (YES) BOP Dispatch an Operator to Close NS-143, N2 Injection to Condenser Isolation BOP Verify all available Circ. Water Pumps running (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # --Page 18 of 27 4 and 5 Event

Description:

Condenser Vacuum leakage and Load Reduction due to Condenser Lowering Vacuum Time Ii Position II Aoolicant's Actions or Behavior BOP Check APP-008-F3, EXH HOOD HI TEMP Alarm Illuminated (NO) Continuous Action Step BOP Check TURBINE GENERATOR SUPERVISORY RECORDER-ANY VIBRATION GREATER THAN 14.0 MILS (NO) BOP Check status of Auxiliary Boilers -In Service (NO) BOP Check Slowdown status -Split between flash tank and condenser (NO) BOP Check Cause of Vacuum Loss -Identified (NO) SRO/BOP Dispatch personnel to locally perform Attachment 1, Local Actions. CREW Monitor Condenser Backpressure during performance of Attachment

1. SRO/BOP Notify Chemistry Personnel to Monitor Secondary Chemistry.

SRO/BOP Direct measurement of condenser lnleakage using OP-504, Condenser Air Removal BOP Check Cause of Vacuum Loss Found (NO) BOOTH OPERATOR:

As soon as the power reduction is 5% or at the discretion of the Chief Examiner, insert Event 6, Steam Line Break on S/G B inside the CV. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Time II Position BOOTH OPERATOR:

Operator Action Form ES-D-2 Scenario # 2 Event # 6, 7,8,9, 10 Page 19 of 27 -------;1 Steam Line Break on SIG "B" inside the CV, All SIGs Faulted inside the CV on the Reactor Trip, Isolate feedwater to SIG B, Open one of the Sl-880 to provide CV Spray Flow, Throttle AFW flow to the SIGs at 80 -90 GPM. Applicant's Actions or Behavior At the discretion of the Chief Examiner, insert Event 6, Steam Line Break on S/G B inside the CV. EVENT INDICATIONS:

APP-002-B7 CV Narrow Range Hi/Lo Pressure APP-006-E4 S/G B Steam Line Hi Flow B S/G Pressure Dropping CV Pressure Rising CREW Crew will determine that a Reactor Trip is required.

SRO Directs RO to Manually trip the reactor. Note: Upon manually tripping the Reactor All S/Gs become faulted inside the CV. PATH-1 Actions RO Immediate Action Step Reactor tripped (YES) BOP Immediate Action Step Turbine tripped (YES) BOP Immediate Action Step E1 & E2 energized (YES) RO Immediate Action Step SI initiated (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Operator Action Form ES-D-2 Scenario # 2 Event # 6, 7, 8,9, 10 Page 20 of 27 ____ ___,I Steam Line Break on SIG "B" inside the CV, All SIGs Faulted inside the CV on the Reactor Trip, Isolate feedwater to SIG B, Open one of the Sl-880 to provide CV Spray Flow, Throttle AFW flow to the SIGs at 80 -90 GPM. Time ii Position II Aoolicant's Actions or Behavior Open Foldout A RCP TRIP CRITERIA IF the PHASE B Isolation Valves are Closed, THEN stop all RCPs. (YES) MSR Isolation Criteria BOP IF ANY Purge OR Shutoff Valve does not indicated fully closed. THEN place the associated RTGB Switch to CLOSE FAUL TED SIG ISOLATION CRITERIA !E both the conditions below are met, THEN perform the following:

• Any S/G pressure is decreasing in an uncontrolled manner OR Any S/G has completely depressurized.

AND BOP

• At least ONE S/G is intact. (NO, all faulted.)

a. Reset SI. b. CLOSE the appropriate Auxiliary Feedwater isolation valves to the faulted S/Gs AND OPEN the associated breaker for the valves closed. RO Verify Phase A Isolation valves closed (YES) Verify FW isolation valves closed (NO) Critical

• Manually closes FCV-488 Task 1 BOP Manually closes V2-6B

• 1 (Candidate must close at least one of the above valves to isolate FW Flow to SIG B to meet the Critical Task.) BOP Verify both FW pumps tripped (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Operator Action Form ES-0-2 Scenario#

2 Event# 6, 7,8,9, 10 Page 21 of 27 -------1 Steam Line Break on SIG "B" inside the CV, All SIGs Faulted inside the CV on the Reactor Trip, Isolate feedwater to SIG B, Open one of the Sl-880 to provide CV Spray Flow, Throttle AFW flow to the SIGs at 80 -90 GPM. Time II Position II Aoolicant's Actions or Behavior BOP Verify both MDAFW pumps running (YES) BOP If Additional Feedwater is required, THEN Start SDAFW Pump (Tripped on Low Pressure)

RO Verify two SI pumps running (YES) RO Verify both RHR pumps running (YES) RO Verify SI valves properly aligned (YES) RO At least one CCW pump running (YES) BOP All SW & SW booster pumps running (YES) RO Verify CV Fans HVH-1,2,3

& 4 running (YES) RO Verify IVSW System initiated (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Operator Action Form ES-D-2 Scenario # 2 Event # 6, 7,8,9, 10 Page 22 of _2_7 ___ Steam Line Break on SIG "B" inside the CV, All SIGs Faulted inside the CV on the Reactor Trip, Isolate feedwater to SIG B, Open one of the Sl-880 to provide CV Spray Flow, Throttle AFW flow to the SIGs at 80 -90 GPM. Time ii Position Ii Aoolicant's Actions or Behavior Verify CV ventilation isolation (YES) Verify the following valves -CLOSED: -V12-6, CONT PURGE VALVE -V12-7, CONT PURGE VALVE RO -V12-8, CONT PURGE VALVE -V12-9, CONT PURGE VALVE -V12-10, CONTAINMENT PRESSURE RELIEF -V12-11, CONTAINMENT PRESSURE RELIEF -V12-12, CONTAINMENT VACUUM RELIEF -V12-13, CONTAINMENT VACUUM RELIEF Verify control room ventilation aligned for pressurization mode (YES) -Verify CONT RM AIR EXHAUST Fan, HVE-16-STOPPED -Verify CLEANING Fan HVE-19 A/B -RUNNING -Verify CONTROL ROOM AIR EXHAUST FAN DISCHARGE BOP DAMPER, CR-D1A-SA-CLOSED -Verify CONTROL ROOM AIR EXHAUST FAN DISCHARGE DAMPER, CR-D1 B-SB -CLOSED -IF CR-D1A-SA OR CR-D1 B-SB have lost power, THEN locally verify position in the Control Room Kitchen. BOP Verify both EDGs running (YES) Continuous Action Step BOP Restart Battery Chargers within 30 minutes of Power Loss using OP-601 (Not Required)

RO Continuous Action Step CV pressure remained below 10 psig (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event

Description:

Operator Action Form ES-D-2 6, 7,8,9, 10 Page 23 of _2_7 ___ -1 1 Steam Line Break on SIG "B" inside the CV, All SIGs Faulted inside the CV on the Reactor Trip, Isolate feedwater to SIG B, Open one of the Sl-880 to provide CV Spray Flow, Throttle AFW flow to the SIGs at 80 -90 GPM. Time II Position II Aoolicant's Actions or Behavior NOTE: Crew should identify and announce that Adverse Numbers are in effect. RO Verify CV Spray Initiated (YES) Critical Verify All CV Spray Pumps Running With Valves Properly Aligned Task 1 (NO) RO

• Manually Opens Sl-880A,B,C and D 1 (Candidate must open at least one of the Sl-880 Valves to meet the Critical Task.} RO Verify Approximately 12 GPM Spray Additive Tank Flow (RO will throttle flow using Sl-845C) RO Verify Phase B Isolation Valves Closed (YES) RO Stop All RCPs BOP Verify All MSIVs AND MSIV Bypasses Closed BOP Locally Open Breaker for HVS-1, At MCC-5 Compartment 7 J within 60 minutes of SI Initiation Booth Operator:

After 3 min. delay open the breaker for HVS-1, MCC-5, Compartment 7 J. RO RCS pressure greater than 1350 psig [1250 psig] (YES) BOP At least 300 gpm AFW flow available (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Operator Action Form ES-D-2 Scenario#

2 Event# 6, 7,8,9, 10 Page 24 of 27 ____ __,I Steam Line Break on SIG "B" inside the CV, All SIGs Faulted inside the CV on the Reactor Trip, Isolate feedwater to SIG B, Open one of the Sl-880 to provide CV Spray Flow, Throttle AFW flow to the SIGs at 80 -90 GPM. Time Position Ii Aoolicant's Actions or Behavior BOP Verify AFW valves properly aligned (YES) BOP Control AFW flow to maintain SIG levels between 8% [18%] and 50% RO RCP Thermal Barrier Cooling Water Hi or Lo flow alarms illuminated (YES) RO At Least one Charging Pump Running (YES) RO Greater than 5 inches Thermal Barrier on all Running RCPs (YES) BOP Place Steam Dump Mode switch to Steam Pressure RO RCS temperature stable at or trending to 547°F (NO) RO RCS Temperature greater than 547°F (NO) RO Attempt to limit cooldown BOP If RCS cooldown continues and is not due to SI flow, then close all MSIVs and MSIV bypasses RO PZR PORVs Closed (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: Event

Description:

Operator Action Form ES-D-2 6, 7,8,9, 10 Page 25 of 27 ____ _,I Steam Line Break on SIG "B" inside the CV, All SIGs Faulted inside the CV on the Reactor Trip, Isolate feedwater to SIG B, Open one of the Sl-880 to provide CV Spray Flow, Throttle AFW flow to the SIGs at 80 -90 GPM. Time II Position II APPiicant's Actions or Behavior RO PZR Spray & Aux Spray valves closed (YES) RO At Least One RCP Running (NO) BOP Any SIG with Uncontrolled Depressurization (YES) RO Reset SPDS AND Initiate Monitoring of Critical Safety Function Status Trees SRO Transition to FRP-P.1, Response to Imminent Pressurized Thermal Shock, due to an ORANGE on CSF-4. Continuous Action Step BOP Check CST Level -Less than 10% (NO) If becomes less than 10% align Service Water to the suction of AFW Pumps using OP-402. Determine if RCS Cooldown is due to a Large Break LOCA (NO) Check both of the following conditions exist: RO RCS pressure -LESS THAN 275 PSIG [400 PSIG] (NO) AND RHR flow on Fl-605 -GREATER THAN 1200 GPM (NO) RO Check RCS Cold Leg Temperature Decreasing (YES) BOP Verify Steam Line PORVs Closed (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event

Description:

Time Position BOP RO BOP BOP BOP Critical Task BOP CREW BOP SRO Operator Action Form ES-D-2 Scenario#

2 Event# 6, 7,8,9, 10 Page 26 of _2_7 ____ 1 Steam Line Break on SIG "B" inside the CV, All SIGs Faulted inside the CV on the Reactor Trip, Isolate feedwater to SIG B, Open one of the Sl-880 to provide CV Spray Flow, Throttle AFW flow to the SIGs at 80 -90 GPM. Applicant's Actions or Behavior Verify Steam Dumps Closed (YES) Check RHR System Aligned for core cooling (NO) Check S/G Status -Any Intact (NO) Verify closed all MSIVs and MSIV BYPs. (YES) Verify closed all Steam Shutoffs to the SDAFW Pump. Close V1-8A, -8B, -8C Maintain feed flow to each SIG between 80 gpm and 90 gpm BOP will coordinate with AOs to open the breakers to the AFW Discharge Valves and manually throttle them to achieve 80 to 90 gpm. Identifies RED on Heat Sink Critical Safety Function Status Tree and enters FRP-H.1, Response to Loss of Secondary Heat Sink. Check Total Feed Flow -LESS THAN 300 GPM DUE TO OPERA TOR ACTION (YES) Reset SPDS and Return to Procedure and Step in Effect The Chief Examiner may terminate the scenario anytime after reduced AFW flow has been established to all of the S/Gs. Appendix D NUREG-1021, Rev. 9, Supp. 1 ILC-11-1 NRC SCENARIO 2 TURNOVER SHEET POWER LEVEL: Core Burnup: EFPD: Boron: Xenon: Tavg: Bank D Rods 50% RTP 150 MWD/MTU 4.3 EFPD 1277 PPM EQ Xenon 560°F 153 Steps EQUIPMENT UNDER CLEARANCE:

• "A" CCW Pump OOS and Breaker Racked Out * "B" Main Feed Pump OOS and Breaker Racked Out EQUIPMENT STATUS:

• 5 GPO Primary to Secondary Leakage identified on "C" SIG.

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.

INSTRUCTIONS FOR THE WATCH: Holding reactor power at 50% for maintenance on Main Feedwater Pump "B" motor. Appendix D NUREG-1021, Rev. 9, Supp. 1 Unit 2 Status Board Date: !Today Time: j6:00:00 AM Cycle: 27 MWD/MT: 150 I Design: 16590 EFPD i4.3 Design i473.5 Tank Level% Status HUT Level% I Status Monitor A 10 Standby eves-A 20 Filling Monitors 38 Standby CVCS-8 10 Standby WCTA 37 Standby CVCS-C 86 Standby WCTB 7 Standby WHUT #NAME? Fillina WCTC 9 Standby WCTD 10 Standby Data Linked to Pl WCTE 9 Standby WGDTS I Pressure PSIG Status A #NAME? PSIG On cover DEMINERALIZERS B #NAME? PSIG In Service PPM In Service Date Resin Replaced c #NAME? PSIG Isolated MBA 2194 YES 7/17/2010 5/4/2010 D #NAME? PSIG Standby MBB 2265 NO 7/17/2010 3/29/2010 CATION 1021 NO 9/17/2010 12/9/2009 Shutdown Requirement Temp Boron DEBA 0 NO New 2/3/2010 1.77% =L'.1K/K 547 F Hot 1051 DEBB 0 NO 3/28/2010 1.77% =L'.1K/K ?,350 F 1281 SFP 1963 NO 9/23/2008 4/22/2008 2.6% =L'.1K/K 100 F Cold 1430 6% =L'.1K/K N/A 1950 SGBD Condenser Air lnleakage Target Value GPM !Status PORV Settings A 13 CFM A 50 Flash Tank Setting Date POT GP-3 Psig B 0 CFM B 50 With Heat A 7/18/2010 3.21 1000 Known 8 CFM c 50 Recovery B 7/18/2010 3.12 1040 Total 5 CFM N2 Flow 8 SCFM c 7/18/2010 3.44 1000 Effluent Radiation Monitor Setpoints RCS Leakage 0.00 Unidentified Rad Current Alert Value 200X NUE Value Monitor Setpoint 2X Total 0.03 GPM R-14C 1.01E+04 N/A 2.020E+04 PRT 0.02 GPM R-20 7.40E+03 N/A 1.480E+04 RCDT Leakage 0.01 GPM R-18 1.00E+06 2.000E+08 2.000E+06 Charging Leakoff 0 GPM R-19A 1.05E+04 2.100E+06 2.100E+04 Misc Identified 0 GPM R-198 9.72E+03 1.944E+06 1.944E+04 Primary/Secondary 0 GPO R-19C 9.58E+03 1.916E+06 1.916E+04 Secondary Loss 17.3 GPM R-37 8.53E+03 1.706E+06 1.706E+04 Manually Entered Data Linked to Chem data base Hi Flux At Shutdown Boron PPM Date PPM Date PPM Previous ARI Counts Setpoint RCS Today 1277 Nl-31 50 150 BAST-A 9/16/2010 21,535 #NAME? #NAME? Nl-32 60 180 BAST-B 9/16/2010 21,032 #NAME? #NAME? SFP 9/15/2010 2246 #NAME? #NAME? Normal Currents RWST 9/16/2010 2219 #NAME? #NAME? UPPER LOWER TARGET %BAND Accum-A 8/30/2010 2211 #NAME? #NAME? N-41 115 109 2.3 5 +/-Accum-8 8/30/2010 2206 #NAME? #NAME? N-42 101 100 2.3 5 +/-Accum-C 8/30/2010 2230 #NAME? #NAME? N-43 96 89 2.3 5 +/-RHR 7/6/2010 2221 N-44 91 87 2.3 5 +/-Refuel Canal POWERTRAX Rev# 2.1.0 RNP %APL 112.55 Refuel Cavity SFP Canal FANS Test/Hrs Date/Tst HVE-1A/B 35640.6 3/8/10 Notes/Additional Data HVE-15A 18643.5 3/18/10 IC-4 HVE-19A/B 6928.3 5/3/10 BOL SR 3. 7 .11.2 Last Completed 5/27/2010 19:45 I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.: 3 Op Test No.: Examiners:

Operators:

SRO-RO-BOP-Initial Conditions:

• 1E-8 amps BOL, 150 MWD/MTU, 1531 ppm Boron . * "A" CCW pump inoperable with the breaker racked out.

• Power Range N-43 has been removed from service due to Power Supply Failure.

• Thunderstorm watch is in effect for Darlington

& Chesterfield counties . Turnover:

• Maintain current reactor power until the RCP "C" oil leak issue is resolved.

Critical Tasks:

• Align Safety Injection by starting at least one SI Pump and open one of the Sl-870 valves.

• Align low head injection by starting RHR Pump A and opening RHR-744A or 744B valves. * (Conditional)

Restore seal injection by starting one charging pump .

• Identify that Emergency Coolant Recirculation capability has been lost and implement EPP-15. Event Malf. Event Type* Event No. No. Description 1 (C) BOP, SRO HVE-3 (CV Iodine Removal Fan) Trips 2 (I) RO, SRO PT-145 Letdown Pressure Transmitter Fails LOW 3 (N) RO, SRO Place Excess Letdown in Service 4 (C) BOP, SRO Service Water Booster Pump B Trips (TS) SRO 4A (TS) SRO PT-455, PZR Pressure Transmitter, fails HIGH 5 (C) ALL Degraded Voltage on System Grid (TS) SRO 6 (M) ALL LOCA occurs when the reactor trips 7 ALL Safeguards sequencers fail to start loads 8 RO Loss of ALL RCP seal cooling. 9 RO RHR Pump A trips * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 ILC-11-1 NRC SCENARIO 3

SUMMARY

DESCRIPTION The crew will assume the watch with the reactor at 1 E-8 amps and the turbine on the turning gear with GP-005 in effect. The unit is being maintained in the present configuration while Engineering personnel resolve the RCP C oil leak issue. The previous shift had identified seal leakage on CCW Pump A. The motor breaker has been racked out and the pump has been isolated and cleared for maintenance.

Power Range N-43 has been removed from service due to a power supply failure. Shift instructions are to maintain current reactor power until the RCP oil leak issue is resolved.

On cue from the Chief Examiner, HVE-3 (CV Iodine Removal Fan) will trip. APP-01 O-C6 is received and HVE-3 has lost indication on the RTGB. The crew will investigate and proceed to start HVE-4 to restore the cooling function for the CV Dome Vent. Once APP-01 O actions are completed, the Chief Examiner can cue the next event. Pressure Transmitter PT-145 for Letdown Line Pressure will fail LOW, causing PCV-145 to close and isolate letdown flow. AOP-025, RTGB Instrument Failure, Section A will be implemented to isolate the letdown line, reduce charging flow and place Excess Letdown in service. Once the Chief Examiner is satisfied with the crew's actions, the Chief Examiner will cue the next event. Service Water Booster Pump B will trip on overcurrent.

APP-002-AB, 88, CB and D8 will be received when the pump trips and will direct the crew to start the standby SWBP and restore normal flow to the CV HVH units. ITS 3.7.7, Condition A, one Service Water System (SWS) train inoperable

-Restore SWS train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, will be entered for the SWBP failure and ITS 3.6.6, Condition D, Two Containment Cooling Trains inoperable

-Restore one containment cooling train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, will be entered due to the failure to meet SR 3.6.6.3 (Verify cooling water flow rate to each cooling unit is.::: 750 gpm) for the CV HVH units. Once the Chief Examiner is satisfied with the Tech Spec compliance, he can cue the next event. PT-455, PZR Pressure Transmitter, will fail high. APP-003-AB, PZR PROT HI PRESS, will be received and the crew will enter APP-003-AB.

Once the crew has identified that PT-455 has failed the CRS should review I brief the crew on OWP-029, PPT-1, Pressurizer Pressure Channel PT-455. The Crew should determine that OWP-029 cannot be implemented since OT ..6. T LOOP 3 bistables are already tripped due to N-43 being OOS. Crew should determine that ITS 3.3.1, Condition E, and ITS 3.3.2, Conditions D and H are applicable.

ITS 3.3.2, Condition D will be the most limiting LCO and require that the plant be placed in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 4 in 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. Crew should begin making preparations for plant shutdown in accordance with GP-006. On cue from the Chief Examiner, the system load dispatcher will notify the control room that system grid voltage is unstable and LOCA voltage cannot be maintained for offsite power. ITS 3.8.1, Condition A, The qualified offsite circuit inoperable

-Declare required features(s) with no offsite power available inoperable when its redundant required feature(s) is inoperable within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Restore offsite circuit to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will be entered due to the Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 offsite power source being inoperable.

APP-036-E3 will be received and the crew will monitor 115kV and 230kV voltages.

AOP-026, Grid Instability, will be entered. Grid voltage will continue to lower until 480V Susses E-1 and E-2 separate from the grid due to the actuation of the Degraded Grid Voltage relays for the Emergency Susses, the Emergency Diesel Generators start and re-energize the busses. When 480V Bus E-1 separates from the grid, several reactor trip signals will be generated such as Intermediate Range Trip, Power Range High Range Trip, Power Range Low Range Trip, OTL\.T Trip and OPL\.T Trip. The crew will have to manually trip the reactor from the RTGB once it is identified that the reactor did not automatically trip. The reactor trip will trigger a LOCA and an SI will be generated.

The crew will enter PATH-1 and continue through the actions of the PATH. The SDAFW pump trips while attempting to start. No loads will start on the safeguards sequencers.

The operators must manually start safeguards loads. FT-949, Spray Additive Tank Flow Transmitter, has failed to zero gpm. The candidate should identify this failure when verifying CV Spray Actuation in PATH-1. Valves RHR-744A and 7448 will not automatically open when the SI signal is generated.

The RO will open at least one of the valves to ensure that low head core injection is available.

This will be identified during the initial phase of the Safety Injection signal as PATH-1 determines that the SI valves are properly aligned. The crew will manually start a Charging Pump within the 15 minutes to restore seal injection to the RCPs or determine that the 15 minute criteria has been exceeded and choose to allow the pump to remain idle. Charging Pumps B and C will be available once the SI signal has been reset. Charging Pump A will be available if the crew directs that the Dedicated Shutdown Diesel Generator be started in accordance with EPP-25, Energizing Supplemental Plant Equipment using the DSDG, to re-energize the 480V Bus DS. Once FRP-P.1 has been exited, RHR Pump A will trip and meet the conditions that Supplement D components cannot be met. This will lead to the entry of EPP-15 due to loss of emergency recirculation capability.

EPP-15 will be entered with the subsequent restoration of RHR Pump B. This will allow EPP-15 to be exited based on the first continuous action step that emergency recirculation capability has been restored.

The Chief Examiner may terminate the scenario when the crew has made the determination that EPP-15, Loss of Emergency Coolant Recirculation, can be exited. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action ILC-11-1 NRC SCENARIO 3 SIMULATOR SETUP IC/SETUP:

• IC-803, SCN: 008_NRC_3

• "A" CCW Pump inoperable with the breaker racked out.

• N-43 removed from service.

• Status board updated to reflect IC-1. PRE-LOADED EVENTS: The following events should occur on the reactor trip: Event 6: LOCA occurs when the reactor trips Event 7: Safeguards sequencers fail to start loads EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:

Event 1: Event 2: Event 3: Event 4: Event 4A: Event 5: Event 8: Event 9: HVE-3 (CV Iodine Removal Fan) Trips Low Pressure Letdown PT-145 fails LOW Place Excess Letdown in Service Service Water Booster Pump "B" Trips PT-455, PZR Pressure Transmitter, fails HIGH Degraded Voltage on System Grid Restoration of Charging Pump I Seal Cooling RHR Pump "A" trips EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

• APP-01 O-C6

• OP-921, Section 8.1.2

• AOP-025 Main Body and Section A

• AOP-025 Attachment 2

• APP-002-AS, 88, ca, D8

• APP-003-AS

• APP-036-E3

• AOP-026

• PATH-1

• Foldout A

• Foldout B

• FRP-P.1

• EPP-15 Form ES-D-2 Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # -------Page 5 of _2_6 ___ _, 1 Event

Description:

HVE-3 (CV Iodine Removal Fan) Trips Time Position II Applicant's Actions or Behavior BOOTH OPERATOR:

When directed, insert Event 1, HVE-3 Trip EVENT INDICATIONS:

APP-010-C6 HVE-3 AIR TROUB I MOTOR OVLD HVE-3 has no RTGB indication.

BOP Announce APP-01 O-C6, HVE-3 AIR TROUB I MOTOR OVLD, illuminated.

BOP Check Breaker at MCC-5, CMPT 8B, for tripped condition. (YES) BOP Check damper positions. (YES -DOME VENT) BOP IF the breaker has tripped, THEN ATTEMPT Reclosure once (YES -the breaker would not close.) BOP Start HVE-4, CV IODINE RMVL FAN. (OP-921 Section 8.1.2) NOTE: Crew should notify WCC SRO of breaker trip on HVE-3 and assistance needed to investigate cause and to write a work request and notify the Operations Manager. Booth Operator Insert Event #2 (PT-145 fails LOW) on cue from the Chief Examiner.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: __ Scenario#

3 Event# _2_a.;....n""""d""""3

___ Page 6 of ....;2;;.;;6

___ -1 1 Event

Description:

PT-145 fails LOW Time II Position II Annlicant's Actions or Behavior BOOTH OPERATOR:

Event 2 -PT-145 fails LOW EVENT INDICATIONS:

APP-001-EG, LP LTDN RELIEF HI TEMP Letdown flow will lower to zero gpm. RO Per APP-001-E6, IF PCV-145 is malfunctioning, THEN REFER to AOP-025. SRO Enters AOP-025 for PT-145 Malfunction.

RO Place LCV-460A & B in the CLOSE Position.

RO Verify ONLY ONE Charging Pump Running RO Place Excess Letdown In Service Using Attachment 2, Placing Excess Letdown in Service Examiner Note: Ensure that the candidate in the RO position performs AOP-025 Att. 2. NOTE: The following steps will place Excess Letdown in Service using Attachment

2. Actions of AOP-025 will continue on Paae 7. Verify Closed the following valves:

• LCV-460A & B , L TON LINE STOP

• CVC-200A, LETDOWN ORIFICE ISOLATION RO/BOP

• CVC-2008, LETDOWN ORIFICE ISOLATION

• CVC-200C, LETDOWN ORIFICE ISOLATION

• CVC-204A.

LETDOWN LINE ISO

• CVC-2048, LETDOWN LINE ISO Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _2_a_n_d_3

___ Page 7 of _2_6 ___ ,_.1 Event

Description:

PT-145 fails LOW Time II Position II Applicant's Actions or Behavior RO/BOP Verify Open CC-739, CCW FROM EXCESS L TON HX. (YES) RO/BOP Position CVC-389, EXCESS L TON DIV, to the RCDT Position RO/BOP Open CVC-387, EXCESS L TON STOP RO/BOP SLOWLY OPEN HCV-137, EXCESS LTDN FLOW not to exceed 195°F as indicated on Tl-139, EXCESS L TON HX OUTLET TEMP RO/BOP Notify the CRS that Excess Letdown is in service. Update the ERFIS Calorimetric program to reflect Excess Letdown is in service.

• Access Calorimetric on ERFIS by typing CALO RO/BOP

• Click on ENTER DATA

• Click on Excess Letdown In Service YES box .

• Click on ENTER DATA IF required to control Pressurizer level, THEN CONTACT Chemistry RO/BOP to perform the alignment for purging the Pressurizer Liquid sample line with full flow to the VCT IAW CP-003. Position CVC-389, EXCESS L TON DIV, to the VCT RO/BOP (Crew may elect to position CVC-389 to the RCDT depending on PZR Level trend.) Notify Radiation Control that Excess Letdown is in service through the RO/BOP Seal Water Return Filters and Heat Exchanger, which will result in INCREASED radiation levels in these areas. Note: End of Attachment 2, Placing Excess Letdown In Service. Crew Make PA Announcement for procedure entry. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 3 Event # _2_a_n_d_3

___ Page 8 of _2_6 ___ --1 1 Event

Description:

PT-145 fails LOW Time II Position II APPiicant's Actions or Behavior RO Check RCP Seal Injection Flow -Between 8 GPM and 13 GPM (NO) Dispatch an operator to locally throttle RCP SEAL WATER FLOW CONTROL VALVE(S) to obtain flow to each RCP between 8 gpm and 13 gpm. -CVC-297A -CVC-2978 RO -CVC-297C IF required to maintain minimum flow, THEN throttle HIC-121, CHARGING FLOW Valve while maintaining Charging Pump Discharge pressure less than 2500 PSIG. IF the normal Seal Injection Range can NOT be maintained, THEN an expanded ranQe of between 6 gpm and 20 gpm may be used. SRO Contact Plant Operations Staff to Expedite Repair of PT-145. SRO Implement the EALs Check Technical Specifications for applicable LCOs SRO ITS LCO, 3.3.1, 3.3.2, 3.3.3, 3.3.4, 3.4.1, 3.4.9, 3.4.17. (None apply) Potential for ITS 3.4.17, Condition E, to be momentarily entered due to seal injection flow beinQ below the ITS limit. SRO Return to Procedure and Step In Effect. Booth Operator Insert Event #4 (Service Water Booster Pump B Trips) on cue from the Chief Examiner.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # --_4 _____ Page 9 of _2_6 ___ _, 1 Event

Description:

Service Water Booster Pump "B" Trips Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 4, Service Water Booster Pump "B" Trips. EVENT INDICATIONS:

APP-002-A8, HVH-1 WTR OUTLET LO FLOW APP-002-B8, HVH-2 WTR OUTLET LO FLOW APP-002-C8, HVH-3 WTR OUTLET LO FLOW APP-002-08, HVH-4 WTR OUTLET LO FLOW Service Water Booster Pump "B" Lost Indication Enters APP-002-A8, B8, C8 and D8. Recommends starting Standby Service Water Booster Pump RO (HVH units can be operated for brief periods of up to 15 minutes without cooling water to the fan motor. Caution statement in OP-921, section 8.1) BOP Announces starting SWBP "A" and then starts Service Water Booster Pump "A" BOP Dispatches AO to check local indication of "A" SWBP and breaker for "B" SWBP Declares "B" SWBP out of service and enters ITS 3.7.7, Condition A, one Service Water System (SWS) train inoperable

-Restore SWS train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, will be entered for the SWBP SRO failure and ITS 3.6.6, Condition D, Two Containment Cooling Trains inoperable

-Restore one containment cooling train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, will be entered due to the failure to meet SR 3.6.6.3 (Verify cooling water flow rate to each cooling unit is .:: 750 gpm) for the CV HVH units. NOTE: Crew should notify WCC SRO and/or l&C to write a work request, investigate and initiate repairs for cause of SWBP "B" breaker trip, and notify the Operations Manager. Booth Operator Insert Event #4A (PT-455, PZR Pressure Transmitter, fails HIGH) on cue from the Chief Examiner.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # --_4_A ____ Page 10 of _2_6 ___ -1 1 Event

Description:

PT-455, PZR Pressure Transmitter fails High Time Position Applicant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 4A, PT-455, PZR Pressure Transmitter, fails HIGH. EVENT INDICATIONS:

APP-003-A8, PZR PROT HI PRESS Pl-455 failed HIGH RO Acknowledge APP-003-AS, PZR PROT HI PRESS, and enters APP-003-AS RO Identifies that PT-455 has failed high. Recommends removing the failed channel from service using OWP-029 IAW APP-003-AS.

SRO Makes copy of OWP-029, PPT-1, Pressurizer Pressure Channel PT-455, and reviews/briefs with the Crew. Crew determines that OWP-029 would trip OT/':,. T LOOP 1 bistables.

SRO Since OT/':,. T LOOP 3 bistables are already tripped due to N-43 being OOS, the crew should determine that OWP-029, PPT-1, cannot be implemented.

Determines that the ITS 3.3.1, Condition E, and ITS 3.3.2, Conditions SRO D and H are applicable.

ITS 3.3.2, Condition D is the most limiting LCO by requiring the plant to be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 4 in 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. SRO Contacts WCC SRO and/or Maintenance to initiate a W/R to investigate and repair the failed pressure transmitter.

SRO Informs crew of the need to perform a plant shutdown IAW GP-006. Booth Operator Prior to Event #5 (Degraded Voltage on System Grid) initiation, notify the Control Room as the Load Dispatcher that "problems on the system grid has caused voltage instability and that LOCA voltage support cannot be maintained" (The crew needs enough time to implement ITS 3.8.1 for the off-site power circuit prior to initiating Event #5). Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 3 Event # _5 _____ Page 11 of _2_6 ___ ...., 1 Event

Description:

Degraded Voltage on System Grid Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 5, Degraded Voltage on System Grid. EVENT INDICATIONS:

APP-036-E3, SUT PRI OVER/UNDER VOLTAGE 115 kV voltage lowering 230 kV voltage lowering SRO will enter the ITS requirement due to the notification from the load dispatcher.

ITS 3.8.1, Condition A, The qualified offsite circuit inoperable

-Declare SRO required features(s) with no offsite power available inoperable when its redundant required feature(s) is inoperable within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Restore offsite circuit to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will be entered due to the offsite power source being inoperable.

CREW Enter AOP-026, Grid Instability.

RO Check Plant Status -Mode 1 or 2 (YES) RO/BOP Continuous Action Step Check system frequency

-Less than 58.4 Hz (NO) Examiners Note: Unit is offline. SRO or BOP should call Unit#1 or Load Dispatcher for frequency information.

Frequency is 59.8 Hz. Crew Make PA Announcement for AOP-026 Entry BOP Check ANY of the following Diesel Generators Paralleled to the Grid. (NO) BOP Check Turbine Status -On Line (NO) BOP Check with Load Dispatcher

-Adequate Voltage Support is Presently Available For a LOCA Event (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario#

3 Event# Event

Description:

Degraded Voltage on System Grid Time Position A licant's Actions or Behavior SRO Declare off-site power Inoperable and implement the required actions of ITS 3.8.1 and Notify personnel and Evaluate plant risk. BOP Monitor ERFIS Points for BOTH Emergency Bus Voltages Continuous Action Step BOP Check Emergency Bus E-1 AND E-2 Voltage -Decreased to Less than 430 Volts for Qreater than 10 seconds. (YES) Verify the following for the affected Emergency Bus: BOP

• Normal supply breaker opens (YES)

• EOG starts (YES)

• EOG output breaker closes. (YES) NOTE: When 480V Bus E-1 separates from the grid, a reactor trip signal will be generated from multiple bistables.

The crew should identify that the reactor did not automatically trip and manually trip the reactor and enter PATH-1. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # --Page 13 of 26 6 Event

Description:

LOCA when Reactor Trips. Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:

The reactor trip will automatically trigger a LOCA. Safeguards sequencers will fail to start loads. EVENT INDICATIONS:

RCS Pressure Lowering Rapidly PZR Level Lowering Rapidly Containment Sump Level and Pressure Rising Rapidly Safety Injection has automatically initiated.

PATH-1 Actions RO Immediate Action Step Reactor tripped (YES) (Manually actuated.)

BOP Immediate Action Step Turbine tripped (YES) BOP Immediate Action Step E1 & E2 energized (YES) RO Immediate Action Step SI initiated (YES) Open Foldout A RCP TRIP CRITERIA a. IF BOTH conditions below are met, THEN stop all RCPs: (YES) RO

• SI Pumps -AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE

• RCS Subcooling

-LESS THAN 35°F [55°F] b. IF the PHASE B Isolation Valves are Closed, THEN stop all RCPs. EXCESS LETDOWN ISOLATION CRITERIA RO IF a Phase A Isolation signals occurs, THEN verify:

• CVC-387, EXCESS L TDN STOP -CLOSED

• HIC-137, EXCESS LTDN FLOW-CONTROLLER AT 0% Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # --6 Page 14 of 26 -----------11 Event

Description:

LOCA when Reactor Trips. Time Ii Position II Aoolicant's Actions or Behavior MSR ISOLATION CRITERIA IF ANY Purge OR Shutoff Valve does not indicate fully closed, THEN BOP place the associated RTGB Switch to CLOSE. END Foldout A Verify Phase A Isolation valves closed (NO) The following valves did not CLOSE on Phase A signal and must be closed manually or by use of the Containment Isolation Pushbutton:

FP-248, ELECT. PENETRATION CV ISOLATION FP-249, ELECT. PENETRATION CV ISOLATION FP-256, RCP SPRINKLER ISOLATION VALVE FP-258, RCP SPRINKLER ISOLATION VALVE Sl-855, ACCUMULATOR NITROGEN SUPPLY CC-739, EXCESS LTDN HX OUTLET WD-1721, RCDT PUMP DISCHARGE LINE AUTO ISOLATION Critical WD-1722, RCDT PUMP DISCHARGE LINE AUTO ISOLATION Task RO WD-1723, CONT. SUMP PUMP DISCHARGE AUTO ISOLATION WD-1728, CONT. SUMP PUMP DISCHARGE AUTO ISOLATION WD-1786, RCDT VENT WD-1787, RCDT VENT WD-1789, RCDT SAMPLE LINE TO GAS ANALYZER WD-1794, RCDT SAMPLE LINE TO GAS ANALYZER PCV-1716, INSTRUMENT AIR ISO TO CV The following valves did not OPEN on Phase A signal: PCV-1922A, AUTOMATIC HEADER PRESSURE CONTROL VALVE PCV-19228, AUTOMATIC HEADER PRESSURE CONTROL VALVE Examiners Note: Containment Isolation Pushbuttons will initiate Phase A Isolation Signal. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # --6 Page 15 of 26 Event

Description:

LOCA when Reactor Trips. Time Position Ii Aoolicant's Actions or Behavior BOP Verify FW isolation valves closed (YES) BOP Verify both FW pumps tripped (YES) BOP Verify both MDAFW pumps running (YES) BOP If Additional Feedwater is required, THEN Start SDAFW Pump (NO) (SDAFW Pump tripped on overspeed.

Unable to restart.)

Verify two SI pumps running (NO) Critical RO

• Starts SI Pumps (May have been previously done.) Task (Must start at least one for Critical Task.)

• RO or BOP should verify EDGs loads as expected . Critical Verify both RHR pumps running (NO) Task RO

• Starts "A" RHR pump (May have been previously done.)

• RO or BOP should verify EDGs loads as expected . Verify SI valves properly aligned (NO -RHR-744A and Band Sl-870A Critical RO and B did not open automatically.)

Task

• Opens RHR-744A or RHR-744B AND Sl-870A or Sl-870B with RTGB Control Switch. (May have been previously done.) RO At least one CCW pump running (YES) BOP All SW & SW booster pumps running (NO) BOP Attempt to start all SW and SWBPs BOP North OR South SW HDR low pressure alarms illuminated. (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # --6 Page 16 of 26 Event

Description:

LOCA when Reactor Trips. me Positio A licant's Actions or Behavior Verify CV Air Recirc Coolers HVH-1,2,3 & 4 running (NO) RO

• Starts HVH-1, 2, 3 & 4 .

• RO or BOP should verify the EDGs loads as expected . Verify IVSW System initiated (YES)* RO *(If the crew did not depress the Containment Isolation Pushbuttons then PCV-1922A and PCV-1922B will be closed and an operator will have to be dispatched to isolate air to PCV-1922A/B and open the associated air regulator petcocks to bleed air from the valve.) Verify CV ventilation isolation (YES) Verify the following valves -CLOSED: -V12-6, CONT PURGE VALVE -V12-7, CONT PURGE VALVE RO -V12-8, CONT PURGE VALVE -V12-9, CONT PURGE VALVE -V12-10, CONTAINMENT PRESSURE RELIEF -V12-11, CONTAINMENT PRESSURE RELIEF -V12-12, CONTAINMENT VACUUM RELIEF -V12-13, CONTAINMENT VACUUM RELIEF Verify control room ventilation aligned for pressurization mode (NO) Operator to verify the following:

-Verify CONT RM AIR EXHAUST Fan, HVE-16 -STOPPED -Verify CLEANING Fan HVE-19 A/B -RUNNING (Must manually start HVE-19A.)

BOP -Verify CONTROL ROOM AIR EXHAUST FAN DISCHARGE DAMPER, CR-D1A-SA

-CLOSED -Verify CONTROL ROOM AIR EXHAUST FAN DISCHARGE DAMPER, CR-D1 B-SB -CLOSED -!E CR-D1A-SA OR CR-D1 B-SB have lost power, THEN locally verify position in the Control Room Kitchen. BOP Verify both EDGs running (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 3 Event # _6 _____ Page 17 of _2_6 ___ -1 1 Event

Description:

LOCA when Reactor Trips. Time II Position II Applicant's Actions or Behavior Continuous Action Step BOP Restart Battery Chargers within 30 minutes of Power Loss using OP-601 (Not Required -Battery Chargers Automatically restart.)

RO Continuous Action Step CV pressure remained below 10 psig (NO) RO Verify CV Spray Initiated. (YES) RO Verify ALL CV Spray Pumps Running with Valves Properly Aligned (YES) Verify Approximately 12 GPM Spray Additive Tank Flow. (Manually RO throttles Sl-845C from RTGB.) (Fl-949 has failed low. Flow from the Spray Additive Tank will have to be estimated based on rate of tank level decrease.)

RO Verify Phase B Isolation Valves Closed. (YES) RO Stop all RCPs (All previously secured.)

BOP Verify All MSIVs AND MSIV Bypasses closed. (YES) BOP Locally open the breaker for HVS-1 at MCC-5 within 60 minutes of SI Initiation Booth Operator Open breaker for HVS-1 on MCC-5 compartment 7-J approximately 3 minutes after being contacted by the crew. RO RCS pressure greater than 1350 psig [1250 psig] (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 3 Event # _6 _____ Page 18 of _2_6 ___ _, 1 Event

Description:

LOCA when Reactor Trips. ime Position A licant's Actions or Behavior RO SI flow verified (YES) RO RCS pressure >125 psig (NO) RO RHR flow verified (YES) BOP At least 300 gpm AFW flow available (YES) BOP Verify AFW Valves Properly Aligned (YES) BOP Control AFW flow to maintain SIG levels between 8% [18%] and 50% RO RCP Thermal Barrier Cooling Water Hi or Lo flow alarms illuminated (YES) RO At least one charging pump running (NO) RO Stop all RCPs IF adequate diesel capacity not available to run charging pumps THEN RO shed non-critical loads using Supplement F. Pumps will not start until SI is reset. RO Reset SI Continuous Action Step CREW IF offsite power is lost, THEN restart emergency safeguards equipment.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # --_6 _____ Page 19 of _2_6 ___ --1 1 Event

Description:

LOCA when Reactor Trips. : Time II Position II Aoolicant's Actions or Behavior IF seal injection has been lost for less than 15 min then start one charging pump. (YES)

• Start "B" or "C" Charging Pump.(or do not start a charging pump, dependent on the time elapsed since the loss of charging)

OMM-022 exert 8.3.22 RCP Seal Cooling Restoration

1. In the event that RCP Seal Cooling is completely lost (both CCW and Seal Injection) cooling from at least one source must be restored Critical in less than 15 minutes. Task RO 2. IF at least one form of seal cooling can NOT be restored within 15 minutes, THEN the RCPs should be tripped AND the seals should be isolated PRIOR TO restoring flow from Charging OR CCW by closing the following valves:

• FCV-626, THERM BARRIER OUTLET OR CC-736, CC FROM RCP "A", "B", "C" THERMAL BARRIER.

• RCP SEAL WATER FLOW CONTROL VALVEs 1) CVC-297A 2) CVC-297B 3) CVC-297C BOP Place Steam Dump Mode switch to Steam Pressure RO RCS temperature stable at or trending to 547°F (NO) (No RCPs are running. Candidate should use T/Cs.) RO RCS temperature greater than 547°F (NO) (No RCPs are running. Candidate should use T/Cs.) RO Attempt to limit cooldown Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _6 _____ Page 20 of _2_6 ___ -1 1 Event

Description:

LOCA when Reactor Trips. Time II Position II Aoolicant's Actions or Behavior IF RCS Cooldown continues and is not due to SI flow, THEN CLOSE RO MSIVs and MSIV Bypasses.

• MSIV and MSIV Bypasses are closed . RO PZR PORVs Closed (YES) RO PZR Spray & Aux Spray valves closed (YES) RO At least one RCP running (NO) BOP Any S/G with uncontrolled depressurization (NO) BOP Any S/G Completely Depressurized (NO) BOP R-19s, R-31s, R-15 rad levels normal (YES) BOP R-2, R-32A, R-32B Rad Levels Normal (YES) RO CV Pressure Normal (NO)

• GO TO PATH-1 Entry Point C RO Reset SPDS, initiate monitoring CSFSTs NOTE: Crew will transition to FRP-P .1 once recognized that RED condition exists on Integrity Critical Safety Function Status Tree Continuous Action Step BOP Check CST Level -Less than 10% (NO) If becomes less than 10% align Service Water to the suction of AFW Pumps using OP-402. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _6 _____ Page 21 of _2_6 ___ '""" 1 Event

Description:

LOCA when Reactor Trips. Time II Position II Applicant's Actions or Behavior Determine if RCS Cooldown is due to a Large Break LOCA (YES) Check both of the following conditions exist: RO RCS pressure is less than 275 psig [400 psig]. (YES) AND RHR flow on Fl-605 -Greater than 1200 GPM (YES) RO Reset SPDS AND return to procedure and step in effect. NOTE: Crew will transition back to PATH-1, Entry Point C. CREW Open Foldout B. (No actions needed from this Foldout.}

BOP Request Periodic Activity Samples of All S/Gs RO At Least One RCP Running (NO) BOP Any S/G with Uncontrolled Depressurization (NO) BOP Any S/G Completely Depressurized (NO) BOP Control AFW Flow to Maintain S/G Levels between 8% [18%] and 50% BOP Any S/G with Uncontrolled Level Increase (NO) BOP R-19s, R-31s, AND R-15 Rad Levels Normal (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 3 Event # --_6 _____ Page 22 of _2_6 ___ ..., 1 Event

Description:

LOCA when Reactor Trips. Time Position A licant's Actions or Behavior RO PZR PORVs Closed (YES) RO Open at least one PORV Block unless Closed to Isolate an Open PZR PORV Continuous Action Step RO IF PZR PORV Opens on High Pressure, THEN Verify Reclosure at or Below 2335 PSIG. Close PORV Blocks as Necessary.

RO Reset SI Continuous Action Step CREW !E..Offsite Power is Lost, THEN Restart Emergency Safeguard Equipment RO Reset CV Spray RO Reset Phase A AND Phase B Booth Operator Insert trip of "A" RHR Pump. RO Establish Instrument Air to CV. lE Compressor Not Running, THEN Start Compressor.

Booth Operator Start "A" and/or "B" Instrument Air Compressor 3 minutes after the crew asks. BOP Offsite Power Available to Charging Pumps (NO) BOP IF Adequate diesel capacity not available to run charging pumps THEN shed non-essential loads using Supplement F. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 3 Event # _6 _____ Page 23 of _2_6 ___ -1 1 Event

Description:

LOCA when Reactor Trips. Time Position APPiicant's Actions or Behavior RO At Least One Charging Pump Running (YES) RO Establish Charging Flow as Necessary RO CV Spray Pumps Running (YES) Continuous Action Step RO When CV Press decreases below 4 psig then stop CV Spray pumps and close Sl-880 valves RO RCS Subcooling Greater Than 35°F [55°F] (NO) Continuous Action Step RO WHEN Below 10-10 Amps, THEN Energize Source Range detectors and monitor recorder.

RO RCS Pressure Greater Than 275 PSIG [400 PSIG] (NO) BOP E-1 AND E-2 Energized by Offsite Power (NO) BOP Attempt to restore offsite power to E-1 AND E-2 BOP Restart Battery Chargers within 30 min of power loss using OP-601. BOP Verify EDGs Properly Loaded (YES) BOP Verify Emergency Oil Pump Running (YES) BOP Locally verify Air Side Seal Oil Backup Pump running. (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _6 _____ Page 24 of _2_6 _____ 1 Event

Description:

LOCA when Reactor Trips. Time II Position II Aoolicant's Actions or Behavior lE Diesel Capacity is not adequate to run Instr Air Compressors AND BOP Battery Chargers, THEN shed non-essential loads using Supplement F. BOP Locally Load Instr Air Compressors AND Battery Chargers BOP E-1 OR E-2 Energized by Offsite Power (NO) Critical RO Supplement D components capable of recirc (NO) Task NOTE Crew will transition to EPP-15, Loss of Emergency Coolant Recirculation Continuous Action Step RO Check Emergency Coolant Recirculation Capability

-Restored (NO) If Emergency Coolant Recirculation is restored, THEN perform Step 2. Go to Step 3. CREW Foldout pages are not applicable during performance of this procedure.

Continuous Action Step RO Check suction source to any of the following pumps -LOST (NO) SI Pumps, RHR Pumps, CV Spray Pumps If suction source lost to pump(s), THEN perform Step 5. Go to Step 6. RO Check Emergency Recirculation Equipment-AVAILABLE USING SUPPLEMENT D (NO) RO RNO -Try to restore at least one train while continuing with this procedure.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario#

--3 Event# Page 25 of 26 6 Event

Description:

LOCA when Reactor Trips. Time II Position II Applicant's Actions or Behavior RO Verify the following CV RECIRC FANs -RUNNING (YES) HVH-1, HVH-2, HVH-3, HVH-4 Booth Operator Notify the Control Room that l&C personnel has corrected the problem with RHR Pump B breaker and can be started if needed. RHR Pump B can be started. The crew should return to Step 2 of RO EPP-15 which will reset SPDS and return to procedure and step in effect. The Chief Examiner may terminate the scenario at his discretion or once it has been identified that transition out of EPP-15 is allowed. Appendix D NUREG-1021, Rev. 9, Supp. 1 ILC-11-1 NRC SCENARIO 3 TURNOVER SHEET POWER LEVEL: Core Burnup: EFPD: Boron: Xenon: Tavg: Bank D Rods 1E-8 amps 150 MWD/MTU 4.3 EFPD 1531 PPM EQ Xenon 548°F 100 Steps EQUIPMENT UNDER CLEARANCE:

• "A" CCW Pump OOS and Breaker Racked Out EQUIPMENT STATUS:

• Reactor is at 1 E-8 amps and the turbine is on the turning gear with GP-005 in effect.

• RCP "C" has an oil leak issue.

• Power Range N-43 has been removed from service due to Power Supply Failure.

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.

INSTRUCTIONS FOR THE WATCH:

• Maintain current reactor power until the RCP "C" oil leak issue is resolved.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Unit 2 Status Board IDate: lTodav ITime: j6:00:00 AMICvcle:

27 IMWD/MT: 150 IDesicrn:

16590 IEFPD [4.3 IDesiqn [473.5 I Tank Level% Status HUT Level% Status Monitor A 10 Standby eves-A 20 Filling Monitor B 38 Standby CVCS-B 10 Standby WCTA 37 Standby CVCS-C 86 Standby WCTB 7 Standby WHUT #NAME? Fillinci WCTC 9 Standby WCTD 10 Standby Data Linked to Pl WCTE 9 Standby WGDTS Pressure PSIG Status A #NAME? PSIG On cover DEMINERALIZERS B #NAME? PSIG In Service PPM In Service Date Resin Replaced c #NAME? PSIG Isolated MBA 2194 YES 7/17/2010 5/4/2010 D #NAME? PSIG Standby MBB 2265 NO 7/17/2010 3/29/2010 CATION 1021 NO 9/17/2010 12/9/2009 Shutdown Requirement Temp Boron DEBA 0 NO New 2/3/2010 1.77% =L:.K/K 547 F Hot 1051 DEBB 0 NO 3/28/2010 1.77% =L:.K/K F 1281 SFP 1963 NO 9/23/2008 4/22/2008 2.6% =L:.K/K 100 F Cold 1430 6% =L:.K/K N/A 1950 SGBD Condenser Air lnleakage Target Value GPM Status PORV Settings A 13 CFM A 50 Flash Tank Setting Date POT GP-3 Psig B 0 CFM B 50 With Heat A 7/18/2010 3.21 1000 Known 8 CFM c 50 Recovery B 7/18/2010 3.12 1040 Total 5 CFM N2 Flow 8 SCFM c 7/18/2010 3.44 1000 Effluent Radiation Monitor Setpoints RCS Leakage 0.00 Unidentified Rad Current Alert Value 200X NUE Value Monitor Setpoint 2X Total 0.03 GPM R-14C 1.01E+04 NIA 2.020E+04 PRT 0.02 GPM R-20 7.40E+03 N/A 1.480E+04 RCDT Leakage 0.01 GPM R-18 1.00E+06 2.000E+08 2.000E+06 Charging Leakoff 0 GPM R-19A 1.05E+04 2.100E+06 2.100E+04 Misc Identified 0 GPM R-19B 9.72E+03 1.944E+06 1.944E+04 Primary/Secondary 0 GPO R-19C 9.58E+03 1.916E+06 1.916E+04 Secondarv Loss 17.3 GPM R-37 8.53E+03 1.706E+06 1.706E+04 Manually Entered Data Linked to Chem data base Hi Flux At Shutdown Boron PPM Date PPM Date PPM Previous ARI Counts Setpoint RCS Today 1531 Nl-31 50 150 BAST-A 9/16/2010 21,535 #NAME? #NAME? Nl-32 60 180 BAST-B 9/16/2010 21,032 #NAME? #NAME? SFP 9/15/2010 2246 #NAME? #NAME? Normal Currents RWST 9/16/2010 2219 #NAME? #NAME? UPPER LOWER TARGET %BAND Accum-A 8/30/2010 2211 #NAME? #NAME? N-41 115 109 2.3 5 +/-Accum-B 8/30/2010 2206 #NAME? #NAME? N-42 101 100 2.3 5 +/-Accum-C 8/30/2010 2230 #NAME? #NAME? N-43 96 89 2.3 5 +/-RHR 7/6/2010 2221 N-44 91 87 2.3 5 +/-Refuel Canal POWERTRAX Rev# 2.1.0 RNP %APL 112.55 Refuel Cavity SFP Canal FANS Test/Hrs Date/Tst HVE-1A/B 35640.6 3/8/10 Notes/Additional Data HVE-15A 18643.5 3/18/10 IC-1, 2, 40 HVE-19A/B 6928.3 5/3/10 BOL SR 3. 7 .11.2 Last Completed 5/27/2010 19:45 I Appendix D Scenario Outline Form ES-D-1 Facility:

HB ROBINSON Scenario No.: 4 Op Test No.: Examiners:

Operators:

SRO-RO-BOP-Initial Conditions:

• 75% RTP EOL, 15697 MWDIMTU, 132 ppm Boron . * "A" CCW pump inoperable with the breaker racked out

• 5 GPO primary to secondary leakage into SIG "C"

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.

Turnover:

• Awaiting Engineering personnel to install vibration monitoring equipment to allow starting Heater Drain Pump "A". Critical Tasks:

• Manually runback the turbine to stop the steam flow

• Secure all RCPs due to two SIG WIR levels less than 10%

• Provide heat removal by RCS Bleed and Feed Event Malf. Event Type* Event No. No. Description 1 (C) RO, BOP, SRO Loss of Instrument Bus #1 (TS) SRO 2 (I) RO, SRO PZR Pressure Controller PC-444J Range Shifts (TS) SRO 3 (I) BOP, SRO Steam Pressure Channel PT-485 fails LOW (TS) SRO 4 (C) BOP, SRO Loss of Cooling to the Auxiliary Transformer 5 (R) RO Load Reduction to 50% (N) BOP, SRO 6 (M) ALL Feedwater Header Rupture 7 BOP Turbine Trip Does Not Occur 8 BOP MDAFW and SDAFW Pumps Trip when Start Signal Received 9 BOP Steam Dump Valves fail Open on Reactor Trip 10 BOP MSIVs fail to Close when Demanded * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 ILC-11-1 NRC SCENARIO 4

SUMMARY

DESCRIPTION The crew will assume the watch with the plant at 75% RTP and waiting on Engineering personnel to install vibration monitoring equipment on Heater Drain Pump "A" to support pump startup. The previous shift had identified seal leakage on CCW Pump A The motor breaker has been racked out and the pump has been isolated and cleared for maintenance.

5 GPO primary to secondary leakage has been identified in SIG C with elevated readings on the applicable radiation monitors.

On cue from the Chief Examiner, Instrument Bus #1 will de-energize due to the tripping of the normal supply breaker on MCC-5. AOP-024, Loss of Instrument Bus, immediate actions will be taken by the crew and the procedure will proceed to energize the instrument bus from its alternate power supply. The crew will ensure that all of the controllers have been returned to auto. ITS 3.8.7, Condition A, One AC Instrument Bus power source inoperable

-Restore AC Instrument Bus Power Source to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and ITS 3.8.9 Condition B, One AC instrument bus subsystem inoperable

-Restore AC instrument bus subsystem to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, will be implemented by the SRO. Once AOP-024 and ITS actions are completed, the Chief Examiner can cue the next event. PZR Pressure Controller PC-444J control range will shift causing the PZR Spray valves to open and lower PZR pressure.

AOP-019, Malfunction of RCS Pressure Control, immediate actions will be taken and the procedure will take actions to restore pressure to the normal control band with PC-444J operated in manual control. ITS 3.4.1, Condition A, One or more RCS DNB parameters not within limits -Restore RCS DNB parameters to within limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, will be entered due to PZR Pressure being less than 2205 psig. Once the Chief Examiner is satisfied with the crew's actions, the Chief Examiner will cue the next event. Steam Pressure Transmitter PT-485 will fail LOW, causing the controlling steam flow channel on SIG B to fail low and causing a transient on the Feedwater Regulating valve FCV-488. AOP-025, RTGB Instrument Failure, Section G immediate actions will be taken by the crew to stabilize the SIG level transient.

The procedure will place an alternate control channel in service and direct the removal of the channel from service. ITS Table 3.3.1-1 Item 14 which requires 2 SIG Level channels (not affected by the failure) and 2 Steam Flow I Feedwater Flow mismatch channels with Condition E -Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or Be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ITS Table 3.3.2-1 Items 1e, 1g, and 4e for Safety Injection and Steam Line Isolation High Steam Line Flow with Low Tave or Low Steam Line Pressure -Condition D: Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR Be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Be in Mode 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. ITS Table 3.3.3-1 Item 20 Post Accident Monitoring Instrumentation for Steam Generator pressure required channels is 2 per SIG which is currently met. ITS Table 3.3.6-1 Item 4 Safety Injection for Containment Ventilation Isolation Instrumentation refers to LCO 3.3.2 Functions 1.a-f (which have already been addressed) requirements will be reviewed by the SRO to ensure that all of the ITS specs are satisfied.

Once the SIG level control has been stabilized and the Chief Examiner is satisfied with the Tech Spec compliance, he can cue the next event. Auxiliary Transformer Trouble alarm (APP-009-C6) will be received on the RTGB. The report from the field is that all cooling fans and oil pumps on the transformer have been lost. AOP-037, Large Transformer Malfunctions, will be implemented by the crew with the requirement to Appendix D NUREG-1021, Rev. 9, Supp. 1 I Appendix D Scenario Outline Form ES-D-1 I reduce load to less than 50% within 30 minutes and unload the transformer.

Power reduction will commence and will continue until the Chief Examiner cues the next event. Feedwater header rupture will occur at the discharge of the Main Feedwater Pumps. This will cause an immediate reduction in the SIG levels and the crew will manually trip the reactor. Once the reactor is tripped, the crew will enter PATH-1. The turbine will not trip automatically or manually from the RTGB and the operator will have to manually runback the turbine with the EH controls until the governor valves are closed. Both MDAFW Pumps and the SDAFW Pump will trip when the start signal is received.

Steam dump valves will fail open on the trip and the MSIVs will fail to close when demanded from the RTGB control switches.

If requested to locally fail close the MSIVs or close the Steam Dump valves, the task will be successful to close the valves. The crew will transition to FRP-H.1, Response to Loss of Secondary Heat Sink, due to the inability to feed the SIGs. During the procedure, following the initiation of RCS bleed and feed through the PZR PO RVs, one MDAFW Pump will be restored to allow feedwater flow to be initiated to the SIGs. The Chief Examiner may terminate the scenario after the crew has restored AFW flow to at least one SIG. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action ILC-11-1 NRC SCENARIO 4 SIMULATOR SETUP IC/SETUP:

• IC-804, SCN: 008_NRC_ 4 * "A" CCW Pump inoperable with the breaker racked out

• 5 GPO primary to secondary leakage into SIG C

• R-15 at 24 cpm, R-19C at 232 cpm, R-31C at 0.450 mR/hr

• Status board updated to reflect IC-22. PRE-LOADED EVENTS: The following events should occur on the reactor trip: Event 7: Turbine Trip does not occur Event 8: MDAFW and SDAFW Pumps Trip when Start Signal Received Event 9: Steam Dump Valves fail Open on Reactor Trip Event 10: MS IVs fail to Close when Demanded EVENTS/TRIGGERS INITIATED DURING THE SCENARIO:

Event 1: Event 2: Event 3: Event 4: Event 5: Event 6: Loss of Instrument Bus #1 PZR Pressure Controller PC-444J Range Shifts Steam Pressure Channel PT-485 fails LOW Loss of Cooling to the Auxiliary Transformer Load Reduction to 50% Feedwater Header Rupture EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

• AOP-024

• AOP-019

• AOP-025 Main Body and Section G

• OWP-025, SGP-8

• APP-046

• AOP-037

• PATH-1

• Foldout A

• FRP-H.1

• Supplement L Form ES-D-2 Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 4 Event # -----Page 5 of _4_5 ___ ..... 1 Event

Description:

Loss of Instrument Bus #1 Time ii Position Ii Applicant's Actions or Behavior BOOTH OPERATOR:

When directed, insert Event 1, Loss of Instrument Bus #1 EVENT INDICATIONS:

Rack #1 Nuclear Instruments Lost (N-31, N-35, N-41) Bistable Status Panel B Extinguished FR-478 Extinguished AOP-024 LOSS OF INSTRUMENT BUS BOP Immediate Action Step Place The Main Turbine in Manual BOP Immediate Action Step Verify S/G(s) Maintained At Program Level RO Immediate Action Step Place Rods in M (Manual) SRO Enters AOP-024 and verifies Immediate Actions. RO Maintain Reactor Power :::;100% Continuous Action Step Determine if RCS Makeup needs to be stopped: RO Check Auto Makeup, Boration OR Dilution -In Progress (NO) (Auto Makeup may or may not be in progress, but could occur.) OR Check Instrument Bus 2 AND Instrument Bus 7 -De-energized (NO) RO Place the RCS Makeup System Switch to STOP. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --Event

Description:

Loss of Instrument Bus #1 Time II Position II Applicant's Actions or Behavior Control PZR Heaters and Sprays to restore RCS Pressure to the desired control band. RO (No control of PZR heaters and sprays until Instrument Bus is energized.)

RO Control Charging and Letdown Flow to Maintain PZR Level. (Letdown cannot be restored until Instrument Bus is energized.)

RO Verify RCP Seal Injection Flow Between 6 GPM and 20 GPM. CREW Make PA Announcement For Procedure Entry Determine Failed Instrument Bus (IB) From Any Of The Following:

• Available indications OR BOP

• Table Below Instrument Bus Indication to Check 1 FR-478, "A" SIG Level Continuous Action Step BOP Check Emergency Susses E-1 AND E-2 -ENERGIZED FROM THE 4160V SUSSES (YES) RO/BOP Continuous Action Step Check Affected Instrument Bus -Energized (NO) RO Check CVC-460A & B, LTDN LINE STOP-CLOSED (YES) RO Place The Selector Switch For CVC-460A & B In The Closed Position Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -----Page 7 of _4_5 ___ -;1 Event

Description:

Loss of Instrument Bus #1 : Time II Position II Aoolicant's Actions or Behavior RO Verify only ONE Charging Pump running at minimum speed RO Verify RCP Seal Injection Flow between 6 GPM and 20 GPM Check Affected Instrument Bus -ENERGIZED (NO) Locally perform the applicable step below: BOP

• IB-1 through IB-4

• IF MCC-8 is supplying an Instrument Bus, THEN Go To Step 58. (NO)

• Transfer the affected Instrument Bus to the alternate (MCC-8) power suoolv. Examiner's Note: LCO 3.4.1 for PZR Pressure < 2205 psig. Booth Operator Transfer Instrument Bus 1 to Alternate Power Supply SRO Stop All Radioactive Batch Releases Check Status Of Local Actions: BOP a. Check Local Actions Of Step 19 RNO -REQUIRED (YES) b. Check Local Actions Of Step 19 RNO -ATTEMPTED (YES) BOP Continuous Action Step Check Affected Instrument Bus -ENERGIZED (YES) Restore Affected Controllers On The RTGB To AUTO Mode RO/BOP {All Controllers go to Auto EXCEPT FC-605 which has no instrument air aligned to it normally)

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 4 Event # -----Page 8 of _4_5 _____ 1 Event

Description:

Loss of Instrument Bus #1 Time II Position II Applicant's Actions or Behavior Restore RCS Makeup Control -IN AUTO

• Place the RCS MAKEUP SYSTEM Switch in STOP

• Verify the RCS MAKEUP MODE Switch in AUTO

• Momentarily place the RCS MAKEUP SYSTEM Switch to START RO (If Charging Pump Suction has been allowed to swap to the RWST, then APP-003-D5, BA FLOW DEV and APP-003-E5, MAKEUP WATER DEV, will be received and FCV-1138 will automatically close. Crew should identify that FCV-1148 will need to be opened to allow for Makeup to be routed to the top of the VCT.) Continuous Action Step Restore Rod Control To Automatic As Follows: RO a. Check Power -GREATER THAN 15% (YES) b. Check Automatic Rod Control-AVAILABLE (YES) c. Check Tavg -WITHIN -1.5 TO +1.5°F OF TREF d. Place the Rod Control Selector Switch to A (Automatic)

BOP Check Emergency Susses E-1 AND E-2 -ENERGIZED (YES) Continuous Action Step BOP Check Emergency Susses E-1 AND E-2 -ENERGIZED FROM THEIR 4160V SUSSES (YES) SRO Implement The EALs Note Possible ITS LCO 3.4.9 entry for PZR Level greater than 63.3%. Continuous Action Step BOP Check Status Of Turbine:

• Check Instrument Bus 4 -ENERGIZED (YES)

• Place Turbine Controls in Automatic Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --Page 9 of 45 Event

Description:

Loss of Instrument Bus #1 A licant's Actions or Behavior RO Check CCW Pumps -More than one running (NO) BOP Check RMS-1, RMS-2, RMS-3 AND RMS-4 -ALL OPEN (YES) BOP Continuous Action Step Check Affected Instrument Bus -ENERGIZED (YES) Check PZR Heater Status -DEENERGIZED (YES) RO (May have been energized earlier as directed to control heaters and spray.) Reset PZR Heaters As Follows: a. Place PZR HTR CONTROL GROUP Control Switch to OFF position AND return to ON position RO b. Place PZR HTR BACK-UP GROUP A Control Switch to OFF position AND return to AUTO OR ON position as desired c. Place PZR HTR BACK-UP GROUP B Control Switch to OFF position AND return to AUTO OR ON position as desired RO Check Normal Letdown -ISOLATED (YES) RO Restore Normal Letdown Using Attachment 15, Restoration of Normal Letdown. NOTE: The following are the steps to restore normal letdown using Attachment 15 of AOP-024. RO/BOP Normal charging flow through the Regenerative Heat Exchanger is in service. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --Page 10 of 45 Event

Description:

Loss of Instrument Bus #1 Time Position A licant's Actions or Behavior RO/BOP A Phase "A" Containment Isolation signal is NOT present. RO/BOP The Residual Heat Removal System is NOT in service. VERIFY the following valves are CLOSED:

• CVC-204A, LETDOWN LINE ISO

• CVC-204B, LETDOWN LINE ISO RO/BOP

• LCV-460A, L TON LINE STOP

• LCV-460B, L TON LINE STOP

• CVC-200A, LETDOWN ORIFICE ISOLATION

• CVC-200B, LETDOWN ORIFICE ISOLATION

• CVC-200C, LETDOWN ORIFICE ISOLATION RO/BOP VERIFY FULL OPEN HIC-121, CHARGING FLOW (CR 95-01752)

RO/BOP Check Pressurizer level is greater than OR equal to program level. (YES) RO/BOP IF desired, THEN PLACE TCV-143, VCT/DEMIN.

DIVERSION, in the VCT position.

RO/BOP PLACE PC-145, PRESSURE, in MANUAL. RO/BOP SET PC-145 to throttle PCV-145 to 45% to 55% open to ensure the Letdown line is NOT overpressurized.

RO/BOP OPEN CVC-204A, LETDOWN LINE ISO. RO/BOP OPEN CVC-204B, LETDOWN LINE ISO. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix 0 Operator Action Form ES-0-2 Op Test No.: Scenario # 4 Event # --Page 11 of 45 Event

Description:

Loss of Instrument Bus #1 Time Position A licant's Actions or Behavior PERFORM the following:

RO/BOP

• OPEN LCV-460A&B by placing switch CVC-460A&B L TON LINE STOP to OPEN.

• PLACE L TON LINE STOP CVC-460 A&B switch to AUTO . PLACE TC-144, NON-REGEN HX OUTLET TEMP, in MANUAL AND RO/BOP adjust as necessary to ensure Letdown temperature does NOT increase above 127°F when letdown is reestablished.

While MAINTAINING Charging Pump discharge pressure as indicated RO/BOP on RTGB instrument Pl-121 LESS THAN 2500 psig, ADJUST charging pump speed to the expected letdown flow to be established in the next step. RO/BOP OPEN one L TON ORIFICE valve: CVC-200A, CVC-200B or CVC-200C PLACE PC-145 in AUTO AND CHECK letdown pressure as indicated RO/BOP on Pl-145, LOW PRESS LTON PRESS, is being maintained between 300 psiQ and 320 psiQ. RO/BOP PLACE TC-144, NON-REGEN HX OUTLET TEMP, in AUTO. RO/BOP IF TCV-143 was selected to the VCT, THEN Position TCV-143 as directed by the CRS/SM. IF Charging flow is changed, THEN establish RCP Seal Injection Flow between 8 GPM and 13 GPM by throttling the following:

RO/BOP

• CVC-297A, RCP "A" SEAL WATER FLOW CONTROL VALVE

• CVC-297B, RCP "B" SEAL WATER FLOW CONTROL VALVE

• CVC-297C, RCP "C" SEAL WATER FLOW CONTROL VALVE Appendix 0 NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Page 12 of 45 Event

Description:

Loss of Instrument Bus #1 Time II Position II Applicant's Actions or Behavior IF increased letdown flow is desired, THEN place additional letdown orifices in service as follows:

• Verify HIC-121, Charging Flow is Full Open .

• Verify Charging Pump discharge pressure as indicated on RTGB instrument Pl-121 less than 2500 psig.

• IF required, THEN start the second Charging Pump on MINIMUM SPEED.

• IF required, THEN while maintaining Charging Pump discharge pressure as indicated on RTGB instrument Pl-121 LESS THAN RO/BOP 2500 psig, ADJUST charging pump speed to meet flow requirement.

• Place PC-145, PRESSURE, in MANUAL.

• Slowly Throttle Open PC-145 to achieve 180-200 psig on Pl-145 to ensure the Letdown Line is NOT overpressurized.

• OPEN one additional L TON ORIFICE valve .

• Place PC-145 in AUTO and Check letdown pressure as indicated on Pl-145, LOW PRESS LTDN PRESS, is being maintained between 300 psig and 320 psig.

• Verify Seal Injection Flow between 8 GPM and 13 GPM by throttling the following:

CVC-297 A, B, C. NOTE: Decision on additional letdown flow may be dependent on PZR Level. PZR Level at > 63.3% is ITS LCO 3.4.9, Condition A. RO/BOP Notify RC that letdown flow has been restored and the affected areas should be monitored for changing radiological conditions.

BOP Check All Radiation Monitor Alarms -EXTINGUISHED (YES) Check R-11 OR R-12 IN SERVICE (YES) BOP RMS-1,2,3,4

-OPEN (YES) R-11 and R-12 Vacuum Pump Operating (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -----Page 13 of _4_5 ___ -1 1 Event

Description:

Loss of Instrument Bus #1 Time A licant's Actions or Behavior Check Control Room Ventilation

-ALIGNED FOR PRESSURIZATION BOP MODE (NO)

• Go To Step 41 . RO Check PZR PRV Safety Acoustic Monitor Lights -ILLUMINATED (YES) Locally Reset PZR Safety Acoustic Monitors At INSTRUMENT CABINET A In The Computer Room By Performing The Following:

BOP

• Depress RESET RC-551A Pushbutton.

• Depress RESET RC-551 B Pushbutton .

• Depress RESET RC-551 C Pushbutton . Booth Operator Reset PZR Safety Valve Acoustic Monitors NOTE: The crew may choose to unsaturate PZR Pressure Controller PC-444J. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: -----Page 14 of _4_5 ___ --1 1 Event

Description:

Loss of Instrument Bus #1 Time II Position II Applicant's Actions or Behavior Continuous Action Step Check Instrument Susses 1, 2, 3, AND 4 -ENERGIZED FROM THEIR NORMAL SOURCE (As Indicated Below):

• 18-1: MCC-5 (Via E-1) (On Alternate)

• IB-2: INVERTER A

• IB-3: INVERTER B

• 18-4: MCC-6 WHEN the Instrument Bus normal source becomes available, THEN transfer the affected Instrument Bus back to its normal supply using BOP the appropriate attachment below: Bus Attachment 18-1 Attachment 9 IB-2 Attachment 1 O 18-3 Attachment 11 18-4 Attachment 12

• Restore the Instrument Bus to the normal power supply within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• IF the normal power supply can NOT be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, THEN be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AND Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. BOP Check Status of EDGs -START SIGNAL RECEIVED (NO)

• Observe the NOTE prior to Step 63 and Go To Step 63 . BOP Check ALL Safety Related Electrical Buses -ENERGIZED (YES) Check Technical Specifications For Applicable LCOs

• ITS LCO 3.8.1, AC Sources -Operating (None)

• ITS 3.8.7, Condition A, One AC Instrument Bus power source SRO inoperable

-Restore AC Instrument Bus Power Source to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

• ITS 3.8.9 Condition B, One AC instrument bus subsystem inoperable

-Restore AC instrument bus subsystem to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --Page 15 of 45 -----

Event

Description:

Loss of Instrument Bus #1 Time II Position II Aoolicant's Actions or Behavior RO Check Annunciator APP-005-A3, PR DROP ROD -ILLUMINATED (YES) Reset Dropped Rod Alarm By Momentarily Placing DROPPED ROD RO MODE Selector Switch For The Affected Power Range Drawer To RESET Position and then back to NORMAL (N-41 Only) BOP Check APP-006-F5, Steam Dump Armed -Illuminated (NO) RO Check APP-005-F5, AMSAC TROUB/BYP-Illuminated (YES) RO Reset AMSAC TROUB/BYP Alarm by depressing the System Reset Pushbutton on AMSAC Front Panel. (Key 52 is required.)

Booth Operator Reset AMSAC Trouble Alarm. NOTE: Crew should notify wee SRO and/or l&C to write a work request, investigate and initiate repairs, and notify the Operations Manager. SRO Return to Procedure and Step in Effect. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --_2 _____ Page 16 of _4_5 ___ _, 1 Event

Description:

PZR Pressure Controller PC-444J Range Shifts Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 2, PC-444J Range Shifts EVENT INDICATIONS:

PZR Spray Valves open at pressure lower than normal. PZR Pressure lowering.

APP-003-08, PZR Control HI/LO Pressure AOP-019 MALFUNCTION OF RCS PRESSURE CONTROL RO Immediate Action Step Determine If PZR PORVs Should Be Closed:

• Check PZR pressure -LESS THAN 2335 PSIG (YES)

• Verify Both PZR PORVs -CLOSED (YES) Immediate Action Step RO Control The PZR SPRAY VALVES AND PZR Heaters To Restore RCS Pressure To The Desired Control Band

• Place PC-444J in Manual to Control Pressure Crew Make PA Announcement for Procedure Entry RO Continuous Action Step Check PZR Pressure -UNDER OPERA TOR CONTROL (YES) Continuous Action Step RO Check Pressurizer Pressure Transmitter PT-444 OR PT-445 Failed. (NO) Check PC-444J, PZR PRESS -OPERA TING PROPERLY IN AUTO (NO) RO Place PC-444J in Manual. *

• IF PC-444J is operable in manual, THEN go to Step 9. (YES) RO Check PZR SPRAY VALVE Controllers

-In Auto (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --_2 _____ Page 17 of _4_5 ___ -1 1 Event

Description:

PZR Pressure Controller PC-444J Range Shifts Time II Position II Aoolicant's Actions or Behavior RO Check PZR Heaters -In Normal Configuration (YES) RO Manually adjust PC-444J to maintain PZR pressure.

RO Check PZR pressure -Under control (YES) SRO Go to step 29 SRO Implement the EALs SRO Contact l&C to make repairs to the PZR Pressure Control System Refer To ITS For Applicable LCOs

• LCO 3.4.11, PZR PORV (N/A)

• TRM 3.4, PZR Spray t:,. T (N/A)

• LCO 3.4.4 AND 3.4.5, RCS Loops (N/A) SRO

• ITS 3.4.1, Condition A, One or more RCS DNB parameters not within limits -Restore RCS DNB parameters to within limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, will be entered due to PZR Pressure being less than 2205 psig (The only applicable LCO.)

• LCO 3.4.9, PZR Level (N/A) SRO Return To Procedure And Step In Effect Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --Page 18 of 45 -----

3 Event

Description:

Steam Pressure Transmitter PT-485 fails LOW A licant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 3, Steam Pressure Transmitter PT-485 fails LOW EVENT INDICATIONS:

APP-006-A4 Steam Line High L'.iP APP-006-81 S/G B FW>STM Flow APP-006-82 SIG B STM>FW Flow (When bistables are tripped.)

APP-006-83 S/G B Level Dev APP-006-E3 S/G B Wide Range Hi/Lo Level APP-006-E5 Steam Line Low Pressure FR-488, Pen #1 -Lowering and Pen #3 -Lowering AOP-025 RTGB INSTRUMENT FAILURE SRO Go To The Appropriate Section For The Failed Transmitter:

I SIG Steam Pressure I Section G I Page 21 I SECTION G -SIG Steam Pressure Transmitter Failure Immediate Action Step BOP Place The Affected FRV In MAN FCV-478 (FRV "A") (NO) FCV-488 (FRV "B") (YES) FCV-498 (FRV "C") (NO) BOP Immediate Action Step Restore Affected SIG Level To Between 39% And 52% RO Make PA Announcement For Procedure Entry Place The Affected SIG Steam Flow Selector Switch To The Alternate BOP Channel Below: I Failed Channel I Affected Channel I Selected Position I I PT-485 I Fl-484 I CH 485 I Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Page 19 of 45 3 Event

Description:

Steam Pressure Transmitter PT-485 fails LOW Time II Position II Applicant's Actions or Behavior Continuous Action Step Restore Affected Controller To Automatic As Follows: BOP a. Check SIG level -WITHIN +/-1 % OF PROGRAMMED LEVEL b. Place the affected Controller in AUTO Remove The Affected Transmitter From Service Using OWP-025: BOP I Channel IOWP I I PT-485 I SGP-8 I OWP-025 SGP-8 STEAM GENERATOR PRESSURE Main Steam Line "B" Pressure Transmitter PT-485 BOP FR-488 (STM) Selected To 485 DELETE INPUT PT-485 FROM CALO PROCESSING. (MSP0421A)

{Two Options)

• Option 1 -Remove via CALO ERFIS program . 0 Access Calorimetric on ERFIS by typing CALO 0 Click on the DELETE INPUTS button. This will display the BOP DELETE INPUT FROM CALORIMETRIC page. 0 Select MSP0421A 0 Click on the ENTER DATA button.

• Option 2 -Delete the ERFIS point from scan . 0 Access the Delete function by typing DR. 0 Click on DELETE SCAN 0 Enter MSP0421 A BOP Trip the Bistables for PT-485 {END OWP-025) Booth Operator Trip the bistables for PT-485 in accordance with OWP-025, SGP-8, after the operator requests and report completed actions SRO Implement The EALs Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario#

--4 Event# _3 _____ Page 20 of _4_5 ___ ___, 1 Event

Description:

Steam Pressure Transmitter PT-485 fails LOW Time Position II Aoolicant's Actions or Behavior Check Technical Specifications (ITS) For Applicable LCOs

• ITS Table 3.3.1-1 Item 14 which requires 2 SIG Level channels (not affected by the failure) and 2 Steam Flow I Feedwater Flow mismatch channels with Condition E -Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or Be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• ITS Table 3.3.2-1 Items 1e, 1g, and 4e for Safety Injection and Steam Line Isolation High Steam Line Flow with Low Tave or Low SRO Steam Line Pressure -Condition D: Place channel in trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR Be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Be in Mode 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.

• ITS Table 3.3.3-1 Item 20 Post Accident Monitoring Instrumentation for Steam Generator pressure required channels is 2 per SIG which is currently met.

• ITS Table 3.3.6-1 Item 4 Safety Injection for Containment Ventilation Isolation Instrumentation refers to LCO 3.3.2 Functions 1.a-f (which have already been addressed)

NOTE: Crew should notify WCC SRO and/or l&C to write a work request, investigate and initiate repairs, and notify the Operations Manager. SRO Return To Procedure And Step In Effect Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.:

4

--_4_a_n_d_5

___ Page 21 of _4_5 ___ _, 1 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%. Time A licant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 4, Loss of Cooling to the Auxiliary Transformer.

EVENT INDICATIONS:

APP-009-CG AUX TRANSF TROUBLE BOP Dispatch an Operator to respond IAW APP-046. BOP Operator reports Alarm 46-11, Loss of Normal 480Vac Power Source. BOP APP-046-11 actions are to REFER TO AOP-037. SRO Directs crew entry to AOP-037. Crew Make PA Announcement for Procedure Entry SRO Go to Section B for Auxiliary Transformer Dispatch an Operator to the Auxiliary Transformer to determine BOP the alarming function, acknowledge the alarm and attempt to reset the alarm. BOP Check Alarm Function -Remains Illuminated. (YES) SRO NOTE: The APP-046 alarms in the table below are prioritized by importance.

Observe the NOTE OR CAUTION prior to the step and go to the SRO appropriate step based on the listed alarm function that is illuminated.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --_4_a_n_d 5 ___ Page 22 of _4_5 _____ 1 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%. Time II Position II Aoolicant's Actions or Behavior BOP Alarm 46-11, Loss of Normal 480Vac Power Source (18G) (Step 4) Caution: !Ethe Auxiliary Transformer is operated for more than SRO 30 minutes with no fans or pumps, THEN damage to the Transformer could occur. BOP Dispatch an Operator to Observe the Status of the Fans and Pumps NOTE:JE APP-046-11 or APP-046-12 are valid alarms, THEN SRO there will be no fans OR pumps running and APP-046-3, APP-046-4, APP-046-7, and APP-46-8 will also be illuminated.

BOP Check Status of the Fans and Pumps -ALL LOST (YES) BOP Check Status of 480 Volt Bus 3 -POWER LOST (NO) Go to Step 11 BOP Check Status of MCC-4 -POWER LOST (NO) Go to Step 17 BOP Check Status of MCC-4, Breaker 4BR -TRIPPED (YES) BOP Attempt to Reset and Close MCC-4, Breaker 4BR One Time. (YES) BOP Check Status of MCC-4, Breaker 4BR -Closed (NO) SRO Initiate action to repair problem causing the tripped breaker. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _4_a_n_d_5

___ Page 23 of _4_5 ___ ...., 1 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%. Time II Position II Aoolicant's Actions or Behavior SRO !f breaker MCC-4 (4BR) can NOT be reclosed promptly, THEN Qo to Step 28. Continuous Action Step BOP Determine If Trip Required As Follows: -Check time elapsed since loss of all cooling -Greater than 30 min. (NO) SRO IF the Auxiliary Transformer is NOT unloaded within 30 minutes, THEN perform Step 28.b. Caution Rapid power reductions at the beginnings of core life may result SRO in the axial flux difference exceeding the operating band values and require a power reduction to less than 50% to comply with ITS 3.2.3, Condition C. Crew Reduce power to less than 50% using Attachment 4, Turbine Load Reduction Check ANY of the following Diesel Generators

-Paralleled to the Grid BOP -EOG A (NO) -EOG B (NO) -OS Diesel (NO) RO Check Power -Less than 50% (NO) (Go to Power Reduction.)

NOTE: The crew is currently in a loop until power is less than 50% RTP and the Auxiliary Transformer Unloaded.

The following steps are for the Power Reduction. (Attachment 4, Turbine Load Reduction)

BOP/SRO Notify Load Dispatcher of Load Decrease to less than 50% power. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --_4_a_n_d_5

___ Page 24 of _4_5 ___ -1 1 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%. e Position A licant's Actions or Behavior BOP Check Turbine Control Mode -Automatic (YES) BOP Depress the IMP IN Pushbutton BOP Set the Desired Load in the SETTER BOP Set the Desired Load Rate BOP/RO Depress the GO Pushbutton NOTE: OP-301, Section 8.2.8 Quick Boration Checklist (shaded area) is included in the following steps, as it will be needed for the rapid down power. RO DETERMINE the amount of Boric Acid to add to the RCS and OBTAIN an independent check of the volume required.

NOTE: -100 gallons of Boric Acid. (The crew will add Boric Acid in 2-4 batches.) (Values based on 3%/min load reduction rate.) If rods left in Auto, Boric Acid quantity may be less than -100 gallons. RO OBTAIN permission from the CRSS OR the SSO to borate. RO PLACE the RCS MAKEUP MODE selector switch to BORATE. RO SET YIC-113, BORIC ACID TOTALIZER to desired quantity.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: 4 and 5 Page 25 of 45 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%. Tim Position A licant's Actions or Behavior RO IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN AND ADJUST using the UP and DOWN pushbuttons.

RO Momentarily PLACE the RCS MAKEUP SYSTEM switch to START. IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:

RO

• Rod Motion is blocked or in the wrong direction

• T AVG increases

• Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:

• FCV-113A, BORIC ACID FLOW, closes . RO

• FCV-113B, BLENDED MU TO CHG SUCT, closes .

• IF in Auto, THEN the operating Boric Acid Pump stops .

• The RCS MAKEUP SYSTEM is OFF . IF desired, THEN FLUSH the Boric Acid flow path as follows:

• PLACE the RCS MAKEUP MODE selector switch in the ALT DILUTE position.

• SET YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons .

• PLACE FCV-114B, BLENDED MU TO VCT to CLOSE .

• Momentarily PLACE RCS MAKEUP SYSTEM switch to START.

• IF any of the below conditions occur, THEN momentarily place RO the RCS MAKEUP SYSTEM switch in the STOP position:

0 Unanticipated Rod Motion 0 Primary Water addition reaches the desired value

• WHEN the desired amount of Primary Water has been added to the RCS, THEN verify the following:

0 FCV-114A closes. 0 FCV-113B closes. 0 IF in Auto, THEN the operating Primary Water Pump stops. 0 The RCS MAKEUP SYSTEM is OFF. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _4_a_n_d_5

___ Page 26 of _4_5 ___ -1 1 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%. Time II Position II Applicant's Actions or Behavior RETURN the RCS Makeup System to automatic as follows:

• VERIFY FCV-114A is in AUTO .

• PLACE FCV-114B to the AUTO position . RO

• PLACE the RCS MAKEUP MODE switch in AUTO .

• VERIFY FCV-113A is in AUTO .

• Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.

RECORD, in AUTO LOG, as indicated by PRIMARY WATER RO TOTALIZER, YIC-114 AND Boric Acid TOTALIZER, YIC-113 the total amount of Primary Water AND Boric Acid added during the boration.

RO MONITOR parameters for the expected change in reactivity AND inform the CRSS OR the SSO of the results of the boration.

NOTE: End of Boration and Power Reduction Steps. AOP-037 steps continue below. Stop the following components:

1. Circulating Water Pump "A" BOP 2. Feedwater Pump "A" 3. Heater Drain Pump "A" 4. Condensate Pump "B" Transfer loads from the Auxiliary Transformer to the Startup BOP Transformer with the Unit at greater than 11 O Mwe using Attachment 5, Transfer of Electrical Loads to the Startup Transformer.

NOTE: The following steps are from Attachment 5, Transfer of Electrical Loads to the Startup Transformer.

BOP Notify the Load Dispatcher of the 4KV switching evolution BOP Insert key into Startup Transf synchroscope switch AND turn switch to STARTUP BUS 2 position Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --Page 27 of 45 4 and 5 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%. A licant's Actions or Behavior BOP WHEN the synchroscope come up to the 12 o'clock position, THEN close START-UP TO 4KV BUS 2 BKR 52/12 BOP WHEN breaker 52/12 indicates closed, THEN return switch to the mid-position AND verify UNIT AUX TO 4KV BUS 1 BKR 52/7 has opened. BOP Insert key into 4KV TIES synchroscope switch AND turn switch to BUS 3 & 4 position.

BOP WHEN synchroscope comes up to 12 o'clock position, THEN close 4KV BUS 3-4 TIE BKR 52/19. WHEN breaker 52/19 indicates closed, THEN return switch to the mid-BOP position AND verify UNIT AUX TO 4KV BUS 4 BKR 52/20 has opened. BOP Turn synchroscope key switch to mid position.

BOP Check Auxiliary Transformer

-Unloaded (YES) Check Auxiliary Transformer Alarm Status as Follows: BOP a. Press and release the Reset pushbutton.

b. Check all APP-046 Alarms extinguished. (NO) SRO IF APP-046 Alarms are present than have not been addressed, THEN QO to Step 3. SRO Implement the EALs. Check Technical Specifications for Applicable Action Statements.

3.8.1 -AC Sources Operating (N/A) SRO 3.8.2 -AC Sources -Shutdown (N/A) 3.8.9 -Distribution Systems -Operating (N/A) 3.8.10 -Distribution Systems -Shutdown (N/A) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario#

--4 Event# _4_an_d_5

___ Page 28 of 45 ------1 Event

Description:

Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%. ion

• ant's Actions or Behavior NOTE: Crew should notify wee SRO and/or l&C to write a work request, investigate and initiate repairs for the loss of cooling to the transformer, and notify the Operations Manager. SRO Check Status of Condition Causing Alarm -Corrected (NO) BOOTH OPERATOR:

As soon as the power reduction is 5% or at the discretion of the Chief Examiner, insert the next event. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _6 _____ Page 29 of _4_5 ___ -1 1 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close ' Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR:

At the discretion of the Chief Examiner, insert Event 6, Feedwater Header Rupture EVENT INDICATIONS:

All S/G Levels lowering.

All FRVs go to full open. FW Flow lowering APP-006-A3 S/G A LVL DEV APP-006-B3 S/G B LVL DEV APP-006-C3 S/G C LVL DEV APP-007-05 FW HOR LO PRESS RO/BOP Operators note the lowering SIG Levels and FRVs full open and recommend tripping the Reactor. RO Immediate Action Step: Reactor Tripped. (YES) Immediate Action Step: Critical Turbine Tripped.(NO)

Task BOP Trip or Runback the Turbine. (YES, Runback was successful) (The Gov. Fast function has been over-ridden.

The GVs will close at a slower than normal rate.) Booth Operator:

Manually trip the Turbine locally, if requested, after a 3 min time delay. BOP Immediate Action Step: E-1 AND E-2 energized. (YES) RO Immediate Action Step: SI Initiated. (YES) SRO Enters PATH-1 and verifies Immediate Actions. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --_6 _____ Page 30 of _4_5 _____ 11 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time II Position II Aoolicant's Actions or Behavior CREW Open Foldout A.

• RCP Trip criteria.

IF BOTH conditions are met, THEN stop all RCPs: (NO) RO 0 SI Pumps -AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW TO THE CORE 0 RCS Subcooling

-< 35 degrees F [55 degrees F]

• MSR Isolation criteria.

IF ANY Purge OR Shutoff Valve does not BOP indicate fully closed, THEN place the associated RTGB Switch to CLOSE. Faulted SIG isolation criteria.

!E both the following conditions are met, THEN perform the following:

• Any SIG pressure is decreasing in an uncontrolled manner BOP (YES) OR

• Any SIG has completely depressurized.(NO)

AND

• At least ONE SIG is intact. (NO) NOTE: Operators may identify that steam dumps valves have failed open and cannot be closed and attempt to close the MSIVs. The MSIVs and Steam Dumps will fail to close from the RTGB. Booth Operator:

If requested to locally close the MSIVs or the Steam Dumps, the task will be successful to close the valves once two SIG W/R levels are less than 10%. RO Verify Phase A Isolation valves are closed. (YES) BOP Verify FW Isolation valves are closed. (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --_6 _____ Page 31 of _4_5 ___ -1 1 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time II Position II APPiicant's Actions or Behavior BOP Verify both FW pumps are tripped. (YES) BOP Verify both MDAFW pumps are running. (NO) (Unable to start from RTGB.) BOP If additional Feedwater is required, start the SDAFW pump. (NO, Pump started but tripped) SRO WCC SRO or AO may be dispatched to investigate the cause of the SDAFW pump trip. RO Verify 2 SI pumps running. (YES) RO Verify Both RHR pumps running. (YES) RO Verify SI valves are properly aligned. (YES) RO At least 1 CCW pump is running. (YES) BOP All SW and SW Booster pumps running. (YES) RO Verify CV Fans HVH-1, 2, 3, 4 running. (YES) RO Verify IVSW System Initiated. (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --Page 32 of 45 6 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time Position II Anolicant's Actions or Behavior Verify CV Ventilation isolation. (YES) Verify the following valves -CLOSED: -V12-6, CONT PURGE VALVE -V12-7, CONT PURGE VALVE RO -V12-8, CONT PURGE VALVE -V12-9, CONT PURGE VALVE -V12-10, CONTAINMENT PRESSURE RELIEF -V12-11, CONTAINMENT PRESSURE RELIEF -V12-12, CONTAINMENT VACUUM RELIEF -V12-13, CONTAINMENT VACUUM RELIEF Verify Control Room Vent aligned for Pressurization Mode. (YES) Operator to verify the following:

-Verify CONT RM AIR EXHAUST Fan, HVE-16 -STOPPED -Verify CLEANING Fan HVE-19 A/B -RUNNING BOP -Verify CONTROL ROOM AIR EXHAUST FAN DISCHARGE DAMPER, CR-D1A-SA-CLOSED -Verify CONTROL ROOM AIR EXHAUST FAN DISCHARGE DAMPER, CR-D1 B-SB -CLOSED -IF CR-D1A-SA OR CR-D1 B-SB have lost power, THEN locally verify position in the Control Room Kitchen. BOP Verify both EDGs running. (YES) CONTINUOUS ACTION STEP: BOP Restart battery chargers within 30 minutes of power loss using OP-601. CONTINUOUS ACTION STEP: RO CV Pressure has remained below 10 psig. (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --Page 33 of 45 6 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close me Position A licant's Actions or Behavior RO Automatic Steam Line Isolation Initiated (NO) RO Automatic Steam Line Isolation Required (NO) SRO Locally open breaker for HVS-1 at MCC-5 CMPT ?J within 60 min of SI Initiation.

Booth Operator Open the breaker for HVS-1 within approximately 3 minutes of request. RCS pressure>

1350 psig. [1250 psig] (YES) RO (May be NO if manual turbine run back not started immediately or if the steam dump malfunction not identified.

Contingency steps have been added should RCS pressure be less than 1350 psig and are annotated with a"@" symbol.) RO @ SI Flow Verified (YES) RO @ RCS pressure > 125 psig (YES) BOP At least 300 GPM AFW flow available. (NO) BOP Level in at least one SIG greater than 8% [18%] (NO) BOP Align AFW valves. BOP At least 300 GPM AFW flow verified (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --_6 _____ Page 34 of _4_5 ___ _, 1 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time Po A licant's Actions or Behavior RO Reset SPDS and Initiate monitoring of Critical Safety Function Status Trees SRO Transition to FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK. BOP Check Total Feed Flow less than 300 GPM due to operator action. (NO) Determine if Secondary Heat Sink is required:

• Check RCS pressure greater than any non-faulted S/G pressure. (YES) RO

• Check RCS temperature greater than 350°F [310°F] (YES) (May be NO if manual turbine runback not started immediately or if the steam dump malfunction not identified.

Contingency steps have been added should RCS temperature be less than 350°F and are annotated with a"@" symbol.) SRO @ Place RHR System in service using Supplement I. SRO @ Consult Plant Operations Staff to determine if RHR should be placed in Core Cooling Mode. Booth Operator Operations Staff is not currently available for consultation.

RO @ Check RHR System -To be used in core cooling mode. (YES) RO @ Check RCS Pressure -Less than 375 psig [350 psig] (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: _6 _____ Page 35 of _4_5 ___ ""'" 1 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close : Time II Position II Aoolicant's Actions or Behavior RO @ WHEN RCS pressure less than 375 psig [350 psig], THEN go to Step 4. Examiner's Note: Crew should have realized at this point that Supplement I is not the appropriate mitigation strategy and transition back to FRP-H.1. BOP Continuous Action Step: Check Any TWO SIG Wide Range Levels less than 10%. [19%] (YES) Critical RO Stop All RCPs Task SRO Observe CAUTION prior to Step 31 and Go to Step 31. SRO Steps 31 through 35 must be performed quickly in order to establish RCS heat removal by RCS bleed and feed. RO Depress the Initiate Safety Injection Pushbutton RO Verify SI Pumps -At least one running (YES) RO At the RTGB, verify SI Valves for at least one flow path -ALIGNED FOR COLD LEG INJECTION (YES) RO Verify APP-002-F?, INSTR AIR HOR LO PRESS -EXTINGUISHED (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 4 Event # _6 _____ Page 36 of _4_5 ___ _, 1 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Position A licant's Actions or Behavior RO Place IA PCV-1716, INSTRUMENT AIR ISO TO CV Control Switch to the OVERRIDE position.

Establish RCS Bleed Path as follows:

• Verify power to PZR PORV Block Valves -Available (YES) RO

• Place all PZR Heater Control Switches to the OFF position.

• Verify PZR PORV Block Valves -BOTH OPEN (YES)

• Open both PZR PORVs Verify Adequate RCS Bleed Path as Follows: Critical RO

• PZR PORVs -BOTH OPEN (YES) Task PZR PORV Block Valves -BOTH OPEN (YES)

• RO/BOP Verify Auto Start of All SI Equipment Using Supplement L. (YES) NOTE: Supplement L steps included at the end of the scenario starting on Page 37. Maintain RCS Heat Removal As Follows: RO Maintain Safety Injection Flow (YES) Maintain PZR PORVs -BOTH OPEN (YES) RO Reset Safety Injection Examiner's Note: SI reset when white light extinguished for EDGs. RO Momentarily place the Containment Spray Key Switch to the OVRD/RESET position and return to the NORMAL position.

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Page 37 of 45 6 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time II Position II Applicant's Actions or Behavior RO Reset Phase A and Phase B RO Check Status of PCV-1716-IN OVERRIDE POSITION (YES) RO Momentarily place IA PCV-1716 Switch to RESET AND return to AUTO. BOP Check E-1 OR E-2-Energized by EOG (NO) RO Check Charging Pumps -All Stopped. (NO) Align Charging Pump Suction to RWST as follows:

• Verify LCV-1158-OPEN (YES) RO

• Verify LCV-115C -CLOSED (YES)

• Start all available Charging Pumps

• Increase running Charging Pumps speed to maximum

• Verify maximum charging flow on Fl-122A. (YES) RO Continuous Action Step Check RWST Level -LESS THAN 27% (NO) Continuous Action Step RO Check CV Pressure -HAS INCREASED TO GREATER THAN 10 PSIG (NO) RO Continuous Action Step Check CV Pressure -LESS THAN 4 PSIG (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --_6 _____ Page 38 of _4_5 ___ _, 1 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time II Position II APPiicant's Actions or Behavior RO Stop the operating CV Spray Pump (None running) RO Verify CV SPRAY PUMP DISCH Valves -CLOSED (Sl-880A,B,C,D) (YES) RO Verify Spray Additive Tank Discharge Valves -CLOSED (Sl-845A,B) (YES) BOP Continuous Action Step Check CST level -Greater Than 10% (YES) BOP Check AFW Lines -INTACT (YES) BOP Check AFW Pump Breakers -Tripped (YES) BOP Position the MDAFW Pump Control Switch to the STOP position and to the ST ART position BOP Check MDAFW Pump -RUNNING (NO) Attempt to Start SDAFW Pump:

• Verify STEAM DRIVEN AFW PUMP STM SHUTOFF VALVES OPEN. (V1-8A, V1-8B, V1-8C) (YES, then reclose.)

BOP Verify STEAM DRIVEN AFW PUMP DISCH Valves OPEN * (V2-14A, V2-14B, V2-14C) (YES)

• Check AFW flow to S/Gs Greater Than 300 GPM (NO) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --_6 _____ Page 39 of _4_5 ___ -1 1 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time II Position II *-. '-* * "" or Behavior Locally Investigate AND Attempt To Restore AFW Flow: BOP

• Verify AFW Pump suction supply is available. (YES) (6 psig)

• Position MDAFW Pump LOCAL/REMOTE Switch to LOCAL. Attempt to reclose any tripped breakers:

• Depress the MDAFW Pump local STOP pushbutton . BOP

• Depress the MDAFW Pump local START pushbutton .

• Check MDAFW Pump started. (YES) BOP Check AFW flow to S/Gs-GREATER THAN 300 GPM. (YES) BOP Check Level in at least One SIG -Greater than 8% [18%] (NO) BOP Continuous Action Step Check CST level -Greater Than 10% (YES) BOP Check AFW Lines -INTACT (YES) BOP Check AFW Pump Breakers -Tripped (YES) (B" MDAFW Tripped.)

BOP Attempt to reclose breaker on "B" MDAFW Pump (NO) BOP Check MDAFW Pump-RUNNING (NO) BOP Verify AFW HOR DISCH Valves -OPEN (V2-16A,B,C) (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --6 Page 40 of 45 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time II Position II Applicant's Actions or Behavior BOP Check AFW flow to S/Gs -GREATER THAN 300 GPM. (YES) The Chief Examiner may terminate the scenario anytime after AFW flow has been established to at least one SIG. NOTE: The following are Supplement L steps. RO/BOP Verify Containment Isolation Phase A Valves -Closed (NO) (Instrument Air PCV-1716 to CV is open.) Verify Excess Letdown -Isolated RO/BOP

• CVC-387, Excess LTDN Stop -Closed (YES)

• HIC-137, Excess LTDN FLOW-Controller at 0% (YES) Verify FW Isolation Valves -CLOSED (YES)

• FRVs

• FRV Bypass Valves RO/BOP

• V2-6A, FW HOR SECTION

• V2-6B, FW HOR SECTION

• V2-6C, FW HOR SECTION RO/BOP Verify Both FW Pumps -TRIPPED (YES) RO/BOP Check Both MDAFW Pumps -RUNNING (NO) RO/BOP Start SDAFW Pump (NO -Pump tripped.)

Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --_6 _____ Page 41 of _4_5 ___ '""'1 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time A icant's Actions or Behavior RO/BOP Verify Two SI Pumps -RUNNING (YES) RO/BOP Verify Both RHR Pumps -RUNNING (YES) RO/BOP Verify SAFETY INJECTION Valves -PROPERLY ALIGNED (YES) RO/BOP Check CCW Pumps -AT LEAST ONE RUNNING (YES) RO/BOP Verify ALL SW Pumps -RUNNING (YES) RO/BOP Verify BOTH SW Booster Pumps -RUNNING (YES) Verify CV RECIRC FANS -RUNNING (YES)

• HVH-1 RO/BOP

• HVH-2

• HVH-3

• HVH-4 Verify IVSW System -INITIATED (YES) RO/BOP

• IVSWS VA PCV-1922A

• IVSWS VA PCV-1922B Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 4 Event # Page 42 of 45 --------------11 6 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time II Position II Aoolicant's Actions or Behavior Verify CONTAINMENT VENTILATION ISOLATION

-INITIATED (YES) Verify the following valves -CLOSED: -V12-6, CONT PURGE VALVE -V12-7, CONT PURGE VALVE RO/BOP -V12-8, CONT PURGE VALVE -V12-9, CONT PURGE VALVE -V12-10, CONTAINMENT PRESSURE RELIEF -V12-11, CONTAINMENT PRESSURE RELIEF -V12-12, CONTAINMENT VACUUM RELIEF -V12-13, CONTAINMENT VACUUM RELIEF Verify Control Room Ventilation System Has Shifted To Emergency Pressurization Mode As Follows: a. CONT RM AIR EXHAUST Fan, HVE-16-STOPPED (YES) RO/BOP b. CLEANING Fan HVE-19A ORB-RUNNING (YES) c. CONTROL ROOM AIR EXHAUST FAN DISCHARGE DAMPER, CR-D1A-SA-CLOSED (YES) d. CONTROL ROOM AIR EXHAUST FAN DISCHARGE DAMPER, CR-D1 B-SB -CLOSED (YES) RO/BOP Verify Both EDGs -RUNNING (YES) RO/BOP Check CV Pressure -EXCEEDED 10 PSIG (NO) RO/BOP Check Steam Line Isolation

-INITIATED (YES) RO/BOP IF Steam Line Isolation required (YES), then perform step 24. Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --_6.___ ____ Page 43 of _4_5 ___ _, 1 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time II Position II Aoolicant's Actions or Behavior Verify All MSIVs AND MSIV BYPs -IN CLOSED POSITION (NO) (If only attempted from RTGB). RO/BOP (Crew should request assistance through the WCC SRO for closing the MSIVs.) MSIVs and MSIV Bypasses can be closed locally, if requested.

RO/BOP At MCC-5, open breaker AUX BUILDING SUPPLY FAN, HVS-1 (CMPT-7 J) Check SW Header Pressure AND Transition To Steps Indicated By The Table Below: SW PRESSURE CONDITION STEP RO/BOP LESS 40 PSIG 27 GREATER THAN so PSIG 28 BETWEEN li() PSIG h@ 50 PSIG 29 RO/BOP Check number of SW Pumps Running -Greater than 2 (YES) RO/BOP Reset SI RO/BOP Stop 1 SW Pump RO/BOP Check SW Header Pressure GREATER THAN 50 PSIG (YES) RO/BOP Check number of SW Pumps Running -Greater than 2 (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # --Page 44 of 45 6 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time II Position 11 Applicant's Actions or Behavior RO/BOP Reset SI RO/BOP Stop 1 SW Pump RO/BOP Check SW Header Pressure GREATER THAN 50 PSIG (YES) RO/BOP Check number of SW Pumps Running -Greater than 2 (NO) RO/BOP Dispatch an operator to locally perform Attachment 1, Throttling CCW Heat Exchanger SW Valves while continuing with this procedure.

RO/BOP Return to procedure and step in effect. NOTE: End of Supplement L steps. Appendix D NUREG-1021, Rev. 9, Supp. 1 ILC-11-1 NRC SCENARIO 4 TURNOVER SHEET POWER LEVEL: Core Burnup: EFPD: Boron: Xenon: Tavg: Bank D Rods 75% EOL 15697 MWD/MTU 448 EFPD 132 PPM EQ Xenon 567.5°F 169 Steps EQUIPMENT UNDER CLEARANCE:

• "A" CCW Pump OOS and Breaker Racked Out EQUIPMENT STATUS:

• 5 GPO primary to secondary leakage into S/G "C"

• Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.

INSTRUCTIONS FOR THE WATCH:

• Awaiting Engineering personnel to install vibration monitoring equipment to allow starting Heater Drain Pump "A". Appendix D NUREG-1021, Rev. 9, Supp. 1 Unit 2 Status Board Date: !Todav Time: !6:00:00 AMICvcle:

127 MWD/MT: 115697 Design: 116590 EFPD 1448 IDesicm 1473.5 Tank !Level% I Status HUT Level% Status Monitor A 10 Standby CV CS-A 20 Filling Monitor B 38 Standby CVCS-B 10 Standby WCTA 37 Standby CVCS-C 86 Standby WCTB 7 Standby WHUT #NAME? Fillinq WCTC 9 Standby WCTD 10 Standby Data Linked to Pl WCTE 9 Standby WGDTS Pressure PSIG I Status A #NAME? PSIG On cover DEMINERALIZERS B #NAME? PSIG In Service PPM In Service Date Resin Replaced c #NAME? PSIG Isolated MBA 2194 YES 7/17/2010 5/4/2010 D #NAME? PSIG Standby MBB 2265 NO 7/17/2010 3/29/2010 CATION 1021 NO 9/17/2010 12/9/2009 Shutdown Requirement Temp Boron DEBA 0 NO New 2/3/2010 1.77% =L:.K/K 547 F Hot 258 DEBB 0 NO 3/28/2010 1.77% =L:.K/K !"._350 F 611 SFP 1963 iNO 9/23/2008 4/22/2008 2.6%=L:.K/K 100 F Cold 776 6%=L:.K/K N/A 1950 SGBD Condenser Air lnleakage Target Value GPM Status PORV Settings A 13 CFM A 50 Flash Tank Setting Date POT GP-3 Psig B 0 CFM B 50 With Heat A 7/18/2010 3.21 1000 Known 8 CFM c 50 Recovery B 7/18/2010 3.12 1040 Total 5 CFM N2 Flow 8 SCFM c 7/18/2010 3.44 1000 Effluent Radiation Monitor Setpoints RCS Leakage 0.00 Unidentified Rad Current Alert Value 200X INUE Value Monitor Setpoint 2X Total 0.03 GPM R-14C 1.01E+04 N/A 2.020E+04 PRT 0.02 GPM R-20 7.40E+03 N/A 1.480E+04 RCDT Leakage O.Q1 GPM R-18 1.00E+06 2.000E+08 2.000E+06 Charging Leakoff 0 GPM R-19A 1.05E+04 2.100E+06 2.100E+04 Misc Identified 0 GPM R*19B 9.72E+03 1.944E+06 1.944E+04 Primary/Secondary 0 GPO R-19C 9.58E+03 1.916E+06 1.916E+04 Secondary Loss 17.3 GPM R-37 8.53E+03 1.706E+06 1.706E+04 Manually Entered Data Linked to Chem data base Hi Flux At Shutdown Boron PPM Date PPM Date PPM Previous ARI Counts Setpoint RCS Today 132 Nl-31 50 150 BAST-A 9/16/2010 21,535 #NAME? #NAME? Nl-32 60 180 BAST-B 9/16/2010 21,032 #NAME? #NAME? SFP 9/15/2010 2246 #NAME? #NAME? Normal Currents RWST 9/16/2010 2219 #NAME? #NAME? UPPER LOWER TARGET %BAND Accum-A 8/30/2010 2211 #NAME? #NAME? N-41 144 136 0.0212 5 +/-Accum-B 8/30/2010 2206 #NAME? #NAME? N-42 126 125 0.0212 5 +/-Accum-C 8/30/2010 2230 #NAME? #NAME? N-43 121 113 0.0212 5 +/-RHR 7/6/2010 2221 N-44 112 108 0.0212 5 +/-Refuel Canal POWERTRAX Rev# 2.1.0 RNP %APL 112.55 Refuel Cavity SFP Canal FANS Test/Hrs Date/Tst HVE-1A/B 35640.6 3/8/10 Notes/Additional Data HVE-15A 18643.5 3/18/10 IC-17, 20, 22 HVE-19A/B 6928.3 5/3/10 EOL SR 3.7.11.2 Last Completed 5/27/2010 19:45