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| number = ML15223B321
| number = ML15223B321
| issue date = 05/21/2015
| issue date = 05/21/2015
| title = Robinson Initial Exam 2011-301 Draft Simulator Scenarios
| title = Initial Exam 2011-301 Draft Simulator Scenarios
| author name =  
| author name =  
| author affiliation = NRC/RGN-II
| author affiliation = NRC/RGN-II
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:I Appendix D Scenario Outline Form ES-D-1 Facility:
{{#Wiki_filter:I Appendix D                                 Scenario Outline                         Form ES-D-1 Facility:       HB ROBINSON                 Scenario No.:     1   Op Test No.:
HB ROBINSON Scenario No.: 1 Op Test No.: Examiners:
Examiners:                                             Operators:   SRO-RO-BOP-Initial Conditions:
Operators:
* 100% RTP MOL, 9000 MWDIMTU, 745 ppm Boron .
SRO-RO-BOP-Initial Conditions:
                      *   "A" CCW pump inoperable with the breaker racked out
* 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:
* 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:
* 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 .
* 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  
* 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 PZR Pressure Transmitter PT-444 fails HIGH (TS) SRO 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==
==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.
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.
5 GPD primary to secondary leakage has been identified into S/G "C" with elevated readings on the applicable radiation monitors.
The crew will reduce reactor power and turbine load IAW OP-105 to 85% to support maintenance on "A" Heater Drain Pump.
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.
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.
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.
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.
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.
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.
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
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.
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.
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.
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:
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.
HB ROBINSON Scenario No.: 2 Op Test No.: Examiners:
Appendix D                                                 NUREG-1021, Rev. 9, Supp. 1
Operators:
 
SRO-RO-BOP-Initial Conditions:
I Appendix D                                   Scenario Outline                         Form ES-D-1 Facility:       HB ROBINSON                   Scenario No.:     2   Op Test No.:
* 50% RTP BOL, 150 MWDIMTU, 1277 ppm Boron . * "A" CCW pump inoperable with the breaker racked out * "B" MFP breaker racked out for maintenance .
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:
* 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:
* Holding reactor power at 50% for maintenance on Main Feedwater Pump B motor.
Critical Tasks:
* Isolate feedwater to SIG B
* Isolate feedwater to SIG B
* Open at least 1 of the CV Spray Pump Discharge valves to provide CV Spray flow.
* 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  
* 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                 (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==
==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.
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.
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, 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 (LT-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.
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.
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.
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.
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.
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.
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 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 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.
The standby Condenser Vacuum Pump will be started and a search for the vacuum leak will be initiated.
Appendix D                                                       NUREG-1021, Rev. 9, Supp. 1
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:
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.
HB ROBINSON Scenario No.: 3 Op Test No.: Examiners:
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.
Operators:
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.
SRO-RO-BOP-Initial Conditions:
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.
* 1E-8 amps BOL, 150 MWD/MTU, 1531 ppm Boron . * "A" CCW pump inoperable with the breaker racked out
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:
* 5 GPO primary to secondary leakage into S/G "C" Turnover:
* Maintain current reactor power until the RCP "C" oil leak issue is resolved.
* Maintain current reactor power until the RCP "C" oil leak issue is resolved.
Line 65: Line 83:
* Align low head injection by starting RHR Pump A and opening RHR-744A or 744B valves.
* 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
* 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  
* 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==
==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.
DESCRIPTION The crew will assume the watch with the reactor at 1E-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.
5 GPO primary to secondary leakage has been identified in S/G C with elevated readings on the applicable radiation monitors.
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.
Shift instructions are to maintain current reactor power until the RCP oil leak issue is resolved.
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.
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.
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.
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.
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.
APP-036-E3 will be received and the crew will monitor 115kV and 230kV voltages.
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.
AOP-026, Grid Instability, will be entered. ITS 3.8.1, Condition A will be entered due to the offsite power source being inoperable.
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.
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.
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 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 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
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.
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 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:
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.
HB ROBINSON Scenario No.: 4 Op Test No.: Examiners:
Appendix D                                                 NUREG-1021, Rev. 9, Supp. 1
Operators:
 
SRO-RO-BOP-Initial Conditions:
I Appendix D                                   Scenario Outline                         Form ES-D-1 I Facility:       HB ROBINSON                   Scenario No.:     4   Op Test No.:
* 75% RTP EOL, 15697 MWD/MTU, 132 ppm Boron . * "A" CCW pump inoperable with the breaker racked out
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:
* 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:
* 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
* 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  
* 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==
==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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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.
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:
The MDAFW and SDAFW Pumps will trip when the start signal is received.
HB ROBINSON Scenario No.: 1 Op Test No.: Examiners:
Appendix D                                                   NUREG-1021, Rev. 9, Supp. 1
Operators:
 
SRO-RO-BOP-Initial Conditions:
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.
* 100% RTP MOL, 9000 MWDIMTU, 745 ppm Boron . * "A" CCW pump inoperable with the breaker racked out
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"
* 5 GPO primary to secondary leakage into SIG "C"
* Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.
* Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.
Turnover:
Turnover:
* Reduce power to 85% to support maintenance on "A" Heater Drain Pump excessive packing leakage. Critical Tasks:
* 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 .
* Start one SI Pump to provide injection to the RCS .
* Close valve CVC-303A to isolate RCP seal return .
* 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  
* 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 LOW (TS) SRO 3                 (I) RO, SRO PZR Pressure Transmitter PT-444 fails HIGH (TS) SRO 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==
==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.
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.
5 GPD primary to secondary leakage has been identified into SIG "C" with elevated readings on the applicable radiation monitors.
The crew will reduce reactor power and turbine load IAW OP-105 to 85% to support maintenance on "A" Heater Drain Pump.
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.
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 hours or Be in Mode 3 within 12 hours. 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.
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 hours or Be in Mode 3 within 12 hours. 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.
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 hour AND B.2 Remove power from the associated block valve within 1 hour AND B.3 Restore PORV to Operable status within 72 hours. 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.
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:
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 over-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.
B.1 Close associated block valve within 1 hour AND B.2 Remove power from the associated block valve within 1 hour AND B.3 Restore PORV to Operable status within 72 hours. 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.
Appendix D                                                     NUREG-1021, Rev. 9, Supp.1
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.
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.
There will not be any radiation monitor response from the tube rupture due to the radiation monitor response being disabled.
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.
Once the safety injection is 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 SIG pressures to stop the excessive primary to secondary leakage.
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.
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:
Appendix D                                                   NUREG-1021, Rev. 9, Supp. 1
* IC-801, SCN: 008_NRC_ 1 * "A" CCW Pump inoperable with the breaker racked out. Switch RED capped.
 
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"
* 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-15 at 24 cpm, R-19C at 232 cpm, R-31 Cat 0.450 mR/hr
* R-198 and R-318 overridden AS IS
* R-198 and R-318 overridden AS IS
* Status board updated to reflect IC-13.
* 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:
* YELLOW Caution cap on RV-3 ("C" Steam Line PORV)
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:
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:       Reduce turbine load IAW OP-105 to 85%.
Event 2:      Feedwater Flow Transmitter FT-477 fails LOW Event 3:      PZR Pressure Transmitter PT-444 fails HIGH Event 4:      RCP A #1 Seal Failure Event 5:       SIG B tube rupture following the manual Reactor Trip EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
* OP-105
* OP-105
* AOP-025 Main Body and Section E
* AOP-025 Main Body and Section E
Line 139: Line 188:
* Supplement G
* Supplement G
* PATH-2
* 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
* 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_ _ _-11 Event


== Description:==
== 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.
Notify RC that increased radiation levels are expected in the CV Pump SRO Bays and in Pipe Alley due to normal shutdown crud bursts.
Monitor the highest operable Power Range Channel and the highest RO operable Intermediate Range Channel on NR-45.
IF Reactor Engineering has not provided technical guidance, THEN SRO/RO 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 .
IF a significant change in RCS Boron concentration occurs, THEN RO 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.
DETERMINE the amount of Boric Acid to add to the RCS and RO 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


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.
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:             Scenario #       1   Event #
IF additional letdown flow is desired, THEN: RO
                --                                         - - - - - Page             6 of _3_5_ _ _-1 1 Event
* 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:==
== Description:==
 
Reduce turbine load IAW OP-105 to 85%.
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.
Time     II Position II                         Applicant's Actions or Behavior RO         PLACE the RCS MAKEUP MODE selector switch to BORATE.
RO IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN AND ADJUST using the UP and DOWN pushbuttons.
RO         SET YIC-113, BORIC ACID TOTALIZER to desired quantity.
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:
IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN RO 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
RO
* Rod Motion is blocked or in the wrong direction
* Rod Motion is blocked or in the wrong direction
* T AVG increases
* TAVG increases
* Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:
* 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
RO
* FCV-113A, BORIC ACID FLOW, closes .
* FCV-113B, BLENDED MU TO CHG SUCT, closes .
* FCV-113B, BLENDED MU TO CHG SUCT, closes .
* IF in Auto, THEN the operating Boric Acid Pump stops .
* 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
* 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
                                                                                          ~~~~~I Event


== Description:==
== Description:==
 
Reduce turbine load IAW OP-105 to 85%.
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:
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.
* PLACE the RCS MAKEUP MODE selector switch in the ALT DILUTE position.
* SET YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons .
* SET   YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons .
* PLACE FCV-114B, BLENDED MU TO VCT to CLOSE.
* PLACE     FCV-114B, BLENDED MU TO VCT to CLOSE.
* Momentarily PLACE RCS MAKEUP SYSTEM switch to START.
* 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:
* 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
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:
* 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:
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 .
* VERIFY FCV-114A is in AUTO .
* PLACE FCV-114B to the AUTO position . RO
* PLACE FCV-114B to the AUTO position .
RO
* PLACE the RCS MAKEUP MODE switch in AUTO .
* PLACE the RCS MAKEUP MODE switch in AUTO .
* VERIFY FCV-113A is in AUTO .
* VERIFY FCV-113A is in AUTO .
* Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.
* 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.
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.
MONITOR parameters for the expected change in reactivity AND RO 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:
IF EH Turbine Control is in OPER AUTO, THEN reduce turbine load as follows:
* Place the EH Turbine Control in the desired position:
BOP
IMP IN . BOP Set the desired load in the SETTER. *
* Place the EH Turbine Control in the desired position: IMP IN .
* Set the desired load in the SETTER.
* Select the desired Load Rate .
* 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#
* Depress the GO pushbutton .
--Event# Event
Appendix D                                                       NUREG-1021, Rev. 9, Supp. 1
 
Appendix D                               Operator Action                               Form ES-D-2 Op Test No.:
                - - Scenario#                  Event#
Event


== Description:==
== Description:==
Reduce turbine load IAW OP-105 to 85%.
Time      ~  Position  II                        Aoolicant's Actions or Behavior Maintain Gland Seal Steam Header Pressure in the normal operating BOP band (3 to 6 psig) (Pl-4004, Pl-1382 or ERFIS Pt GSP2095A)
WHEN Reactor Power is <90% as indicated on NR-45, THEN CHECK RO 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


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)
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:             Scenario #     1     Event #     2                 Page   9 of 35
RO WHEN Reactor Power is <90% as indicated on NR-45, THEN CHECK that APP-005-06 is received. (YES) BOOTH OPERATOR:
                  --                                        ~~~~~                          ~~~~~1 Event
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:==
== 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 Recognizes FT-477 has failed and performs Immediate Actions for BOP AOP-025, RTGB INSTRUMENT FAILURE.
Immediate Action Step:
BOP Place the affected FRV (FCV-478 for SIG "A") in MAN.
Immediate Action Step:
BOP Restore Affected SIG Level To Between 39% And 52%.
Enters AOP-025, RTGB INSTRUMENT FAILURE, Section E, and SRO verifies Immediate Actions.
RO/BOP        Make PA announcement for entry into AOP-025.
Place the affected SIG Feed Flow Selector Switch to the alternate BOP 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


FT-477 fails LOW Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                                 Operator Action                                     Form ES-D-2
At the discretion of the Chief Examiner, insert Event 2, Feedwater Flow Transmitter FT-477 fails LOW EVENT INDICATIONS:
_2_ _ _ _ _ Page          10 of _3_5_ _ __,
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:
Op Test No.:
BOP
                  - - Scenario #           1     Event #
* 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
1 Event


== Description:==
== Description:==
 
FT-477 fails LOW Time     II Position II                           Aoolicant's Actions or Behavior Reviews, briefs and directs taking FT-477 instrument out of service SRO using OWP-026, FWF-2.
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.
Remove the affected transmitter from service using OWP-026, FWF-2.
* FR-478 selector switch selected to CH-476 .
* FR-478 selector switch selected to CH-476 .
* Remove FT-477 input to the CALO program. (Two Options)
* 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 1 - Remove via CALO ERFIS program .
* 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)
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)
* Trip bistable FC-478B-1. (APP-006-A2 will be received)
Examiner Note: Question during follow up. What actions are required for tripping bistables?
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.
SRO       Go To Procedure Main Body, Step 2.
* 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 hours or Be in Mode 3 within 12 hours 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#
SRO       Implement the EALs.
Event# _2 _____ Page 11 of _3_5 ___ ___, 1 Event
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 hours or Be in Mode 3 within 12 hours SRO       Return to procedure and step in effect.
Appendix D                                                           NUREG-1021, Rev. 9, Supp. 1
 
Appendix D                               Operator Action                                   Form ES-D-2
_2_ _ _ _ _ Page          11 of _3_5_ _ ____,
Op Test No.:
                  - - Scenario#               Event#
1 Event


== Description:==
== 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


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                             Operator Action                                   Form ES-D-2 Op Test No.:     _ _ Scenario #       1   Event#     _3_ _ _ _ _ Page           12 of _3;;..;;5_ _ __.
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
___ _.1 Event


== Description:==
== 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:
PT-444 Fails High on A licant's Actions or Behavior BOOTH OPERATOR:
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.)
When directed, initiate Event 3, PT-444 fails HIGH EVENT INDICATIONS:
Recognizes that PT-444 is failed high and performs Immediate Actions RO of AOP-025.
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
Immediate Action Step:
Determine if PZR PORVs should be closed.
RO
* Check Pressurizer pressure less than 2335 psig (YES).
* Check Pressurizer pressure less than 2335 psig (YES).
* Verify both PZR PORVs CLOSED (NO, PCV-455C OPEN) .
* 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>
* Manually close RC-536, PORV BLOCK NOTE:                     May use PC-444J OR Spray Valve Controller in Manual to close spray valves.
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
Immediate Action Step:
___ -1 1 Event
RO     Control Pressurizer Spray Valves and Pressurizer Heaters to restore RCS pressure to the desired control band.
Enters AOP-025, RTGB INSTRUMENT FAILURE, Section C and SRO 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:==
== Description:==
 
PT-444 Fails High Time     Ii Position II                         Aoolicant's Actions or Behavior Crew       Make PA announcement for entry into AOP-025.
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:
SRO/RO         Check PT-444 is the failed transmitter. (YES)
* Place PC-444J in MAN . RO
Control pressurizer pressure controller PC-444J:
* Place PC-444J in MAN .
RO
* Verify PZR SPRAY VALVES IN AUTO .
* Verify PZR SPRAY VALVES IN AUTO .
* Verify PZR Heaters energized as desired .
* 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:
* Restore PZR Pressure to the desired control band .
* 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:
Verify PCV-455C in AUTO. (Crew may decide to leave PCV-455C in RO the CLOSE position since it failed to close.)
B.1 Close associated block valve within 1 hour AND B.2 Remove power from the associated block valve within 1 hour AND B.3 Restore PORV to Operable status within 72 hours. 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).
Verify Selector Switch PM-444 is selected to operable channel:
Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario # 1 Event # _4_,..._s  
RO
....... 6 ___ Page 14 of _3_5 ___ -l 1 Event
* 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 hour AND B.2 Remove power from the associated block valve within 1 hour AND B.3 Restore PORV to Operable status within 72 hours.
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
_4_,..._s.......6
_ _ _ Page     14   of _3_5_ _ _-l Op Test No.:
                  - - Scenario #          1      Event #
1 Event


== Description:==
== 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.
Enters AOP-018, REACTOR COOLANT PUMP ABNORMAL SRO CONDITIONS.
SRO        Evaluate plant conditions and Go to Section A.
Continuous Action Step:
RO 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.
Check Plant status in Mode 1, and direct tripping the Reactor, tripping SRO RCP "A" and then going to PATH-1.
Attempts to trip the reactor using the reactor trip pushbutton above TR-RO 408. Candidate identifies that reactor does not trip.
Appendix D                                                                    NUREG-1021, Rev. 9, Supp. 1


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:
Appendix D                                 Operator Action                                   Form ES-D-2
When directed, insert Event 4, RCP "A" #1 seal failure. EVENT INDICATIONS:
_4_._,5_,_,_6_ _ _ Page    15 of _3_5_ _ _ _
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.
Op Test No.:
SRO Enters AOP-018, REACTOR COOLANT PUMP ABNORMAL CONDITIONS.
                --       Scenario #       1     Event #
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
11 Event


== Description:==
== 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 Attempts to trip the reactor using the reactor trip pushbutton below the RO 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.
Immediate Action Step:
RO Reactor Tripped. (YES)
Immediate Action Step:
BOP Turbine Tripped. (YES)
Immediate Action Step:
BOP E-1 AND E-2 energized (YES)
Immediate Action Step:
RO SI initiated. (NO)
Immediate Action Step:
RO 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


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:
Appendix D                               Operator Action                                     Form ES-D-2 Op Test No.:                                                 _4_,_s......6_ _ _ Page   16 of _3_5_ _ _....
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.
1 Event
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:==
== 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                      WHEN at least 3 minutes have elapsed since tripping the affected RCP, RO/BOP Task                          THEN Close Seal leakoff valve for RCP "A". (CVC-303A)
The Seal leakoff valve should be closed within 5 minutes of stopping RO/BOP the affected RCP.
RO/BOP        Check SI - Actuated. (YES)
Check APP-002-F7, INSTR AIR HOR LO PRESS - EXTINGUISHED RO/BOP (YES)
RO/BOP        Reset Safety Injection RO/BOP        Reset Containment Isolation Phase A Momentarily place IA PCV-1716, INSTRUMENT AIR ISO TO CV RO/BOP 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


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)
Appendix D                               Operator Action                                     Form ES-D-2 Op Test No.:
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.
                - - Scenario #           1     Event #     4 , 5, 6
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
___,......._~~~
Page   17 of   35
                                                                                                ~~~~~1 Event


== Description:==
== 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)
Inform SRO to Implement EALs and Refer to Technical Specifications RO/BOP 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


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
Appendix D                                 Operator Action                                     Form ES-D-2
-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#
_4_._,s....._6_ _ _ Page Op Test No.:
1 Event# _4_._, s ..... _6 ___ Page 18 of _3_5 ___ --1 1 Event
                  - - Scenario#           1     Event#                                 18 of _3_5_ _ _--1 1
Event


== Description:==
== 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.)
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:
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:
The Ruptured SIG is identified by observing an uncontrolled level increase OR abnormal radiation level on the R-19s or R-31s.
: b. CLOSE the appropriate Auxiliary Feedwater isolation valves to the Ruptured S/Gs. S/G"B"
AND The Ruptured S/G Level is Greater than 8% [18%]
BOP       a. Reset SI.
: b. CLOSE the appropriate Auxiliary Feedwater isolation valves to the Ruptured S/Gs.
S/G"B"
* V2-14B. SDAFW PUMP DISCH
* 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.
* V2-16B. AFW HOR DISCH
: c. WHEN desired, THEN Perform Supplement G, Steam Generator Isolation Indications Available:
"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.
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
Appendix D                                                               NUREG-1021, Rev. 9, Supp. 1
___ 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)
Appendix D                               Operator Action                                     Form ES-D-2 Op Test No.:                                                 _5_a_n_d_6_ _ _ Page       19 of _3_5_ _ _"""
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.)
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.
Booth Operator:
NOTE:                       Candidate may direct that Supplement G be performed to isolate S/G B. Supplement G steps begin on Page 32.
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.:
SRO       Foldout A is in effect.
1  
RO       Verify Phase A Isolation valves closed (YES)
--_5_a_n_d 6 ___ Page 20 of _3.;..;;5
BOP       Verify FW isolation valves closed (YES)
___ -1 1 Event
BOP       Verify both FW pumps tripped (YES)
BOP       Verify both MDAFW pumps running (YES)
If Additional Feedwater is required, THEN Start SDAFW Pump BOP (RunninQ)
Verify two SI pumps running (NO) (RO will have to manually start Critical RO       both SI pumps. May have been previously started after the SI was Task 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.:
                  --      s~n~o#          1     &e~#        _5_a_n_d6
_ _ _ Page         20 of _3.;..;;5_ _ _-1 1
Event


== Description:==
== Description:==
SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time      I  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
                                        - V12-8, CONT PURGE VALVE RO
                                        - 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 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


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:
Appendix D                                 Operator Action                                   Form ES-D-2 Op Test No.:             Scenario #       1     Event #     5 and 6           Page   21 of 35
-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
                  --                                        ~----                            ~---~I Event
-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:==
== Description:==
SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time      II  Position  I                          Aoolicant's Actions or Behavior Continuous Action Step BOP          Restart Battery Chargers within 30 minutes of Power Loss using OP-601 (Not Required)
Continuous Action Step RO CV pressure remained below 10 psig (YES)
BOP          Automatic steam line isolation initiated (NO)
BOP          Automatic Steam Line Isolation Required (NO)
Locally open the breaker for HVS-1 at MCC-5 within 60 minutes of SI BOP 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


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)
Appendix D                           Operator Action                                     Form ES-D-2 Op Test No.:
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
                  - - Scenario #     1     Event #     _5_a_n_d_6_ _ _ Page       22 of _3_5_ _ _-1 1
___ Page 22 of _3_5 ___ -1 1 Event
Event


== Description:==
== Description:==
SIG "B" Tube Rupture and Both SI Pumps do not Auto Start A  licant's Actions or Behavior RCP Thermal Barrier Cooling Water Hi or Lo flow alarms illuminated RO (NO)
BOP    Place Steam Dump Mode switch to Steam Pressure RO      RCS temperature stable at or trending to 547&deg;F (NO)
RO      RCS Temperature Greater than 547&deg;F (YES)
Dump Steam using Condenser Dumps or Steam Line PORVs to BOP attain 547&deg;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


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&deg;F (NO) RO RCS Temperature Greater than 547&deg;F (YES) BOP Dump Steam using Condenser Dumps or Steam Line PORVs to attain 547&deg;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
Appendix D                               Operator Action                                     Form ES-D-2
___ Page 23 of _3_5 ___ Event
_5_a_n_d_6_ _ _ Page      23 of _3_5_ _ _~
Op Test No.:
1 Event


== Description:==
== 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
                            @IF PZR Spray Valves Fail to Close THEN Stop RCP Supplying Failed RO Valve
                            @IF Aux Spray Valves Fail to Close, THEN Close LCV-460A AND B RO AND HCV-121 RO        At least one RCP running (YES)
At least one SI Pump Running (YES) (Both SI pumps had to be RO manually started.)
RO        RCS Subcooling Less Than 35&deg;F [55&deg;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&deg;F. (YES)
Appendix D                                                            NUREG-1021, Rev. 9, Supp. 1


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.)
Appendix D                               Operator Action                                           Form ES-D-2 Op Test No.:
RO RCS Subcooling Less Than 35&deg;F [55&deg;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&deg;F. (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario#
                --       Scenario#            Event#     _5.;...a.;...n_d_6_ _ _ Page   24   of _3.;..;;5;.___ _-1 Event
--Event# _5.;...a.;...n_d_6
___ Page 24 of _3.;..;;5;.__
__ -1 Event


== Description:==
== 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.
Control AFW Flow to Maintain SIG Levels between 8% and 50%.
BOP (SIGs A and C)
BOP        Any SIG with uncontrolled level increase. (YES - "B" SIG)
SRO        Transition to Path-2, Entry Point J Reset SPDS AND Initiate Monitoring of Critical Safety Function Status RO Trees Open Foldout C CREW
{No steps apply)
When Below 10-10 AMPS, THEN Energize Source Range Detectors RO 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


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
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:
___ Page 25 of _3_5 ___ _.1 Event
                - - Scenario #           1     Event #     _5_a_n_d_6_ _ _ Page       25 of _3_5_ _ __.
1 Event


== Description:==
== 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&deg;F [55&deg;F] (NO)
BOP        Ruptured S/G Identified (YES)
BOP        Maintain at Least One S/G Available for RCS Cooldown Verify Ruptured Steam Line PORV Setpoint at 1035 PSIG using BOP Status Board BOP        Verify RCS Temperature Less Than 547&deg;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 IF MDAFW Pump is not Available, THEN Maintain at least One SIG BOP 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


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&deg;F [55&deg;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&deg;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
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
___ Page 26 of _3_5 ___ -1 1 Event
                --                                                                                      1 Event


== Description:==
== Description:==
SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time      II  Position  II                        Aoolicant's Actions or Behavior Locally Close Warmup Steam Supply From Ruptured SIG to SDAFW BOP 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 Isolate Feed Flow to Any Ruptured SIG that is Faulted Unless Needed BOP 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.
Control Feed Flow to Maintain Intact SIG Level Between 8% [18%]
BOP 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


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.
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:                                               _5_a_n_d_6_ _ _ Page       27 of _3_5_ _ __.
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
1 Event
___ Page 27 of _3_5 ___ _.1 Event


== Description:==
== Description:==
SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time      I  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)
Open At Least One PORV Block Unless Closed to Isolate an Open RO 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 Establish Instrument Air to CV. IF Compressor not Running, THEN RO 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


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
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:             Scenario #     1     Event #     5 and 6           Page   28 of 35
                  --                                        ~~~~~                            ~~~~~I Event


== Description:==
== 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
                                      - V2-68, FW HOR SECTION (Not needed if FRV and FRV BYP BOP 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


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:
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
-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
                --                                                                                      1 Event
___ Page 29 of _3_5 ___ -l 1 Event


== Description:==
== 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 (oF)
RO/BOP 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)
Verify T-AVG less Than 543&deg;F AND Block T-AVG SI Signal Prior to RO 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


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&deg;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
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:
___ Page 30 of _3_5 _____ 1 Event
                  - - Scenario #         1     Event #     _5_a_n_d_6_ _ _ Page       30 of _3_5_____
1 Event


== Description:==
== 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)
WHEN CET is less than Required the steps begin again.
RO 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&deg;F [75&deg;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&deg;F [55&deg;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


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)
Appendix D                               Operator Action                                     Form ES-D-2 Op Test No.:                                               _5_a_n_d_6_ _ _ Page       31 of _3_5_ _ __,
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&deg;F [75&deg;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&deg;F [55&deg;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
1 Event
___ Page 31 of _3_5 ___ _, 1 Event


== Description:==
== 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.
IF PZR Spray Valves fail to close, THEN Stop RCP supplying failed RO valve.
IF Aux Spray Valve Fails to close, THEN Close CVC-460A and BAND RO HCV-121 RO/BOP        Maintain RCS and Ruptured S/G Pressures Less than 1035 PSIG RO        RCS Subcooling Greater Than 35&deg;F [55&deg;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


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&deg;F [55&deg;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                               Operator Action                                   Form ES-D-2 Op Test No.:                                               _5.;,___ _ _ _ Page       32 of _3;;;..;5;...__ _~
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
__ Event


== Description:==
== 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 - FAULTED (NO).
Continuous Action Step BOP When Tavg less than 547&deg;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


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&deg;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
Appendix D                                 Operator Action                                   Form ES-D-2
_s_____
Op Test No.:
                  - - Scenario #           1     Event #                       Page   33 of _3_5_ _ __,
1 Event


== Description:==
== Description:==
SIG "B" Tube Rupture (Supplement G)
Time      II  Position  II                          Applicant's Actions or Behavior Verify S/G B Slowdown AND Slowdown Sample Valve Status Light BOP 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.
Dispatch Operator To The Aux. Bldg I E1-E2 Room To Perform The BOP Following:
At MCC-9, verify V2-14B closed AND open breaker V2-14B, SDAFW PUMP TO SIG B (CMPT- 1C)
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


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
Appendix D                                 Operator Action                                   Form ES-D-2 Op Test No.:                                               _5_ _ _ _ _ Page           34 of _3_5_ _ _-1 1
-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.
Event
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:==
== Description:==
 
SIG "B" Tube Rupture (Supplement G)
SIG "B" Tube Rupture (Supplement G) Time II Position II Aoolicant's Actions or Behavior
Time     I  Position   II                         Aoolicant's Actions or Behavior
* Direct AO to start Auxiliary Boilers .
* Direct AO to start Auxiliary Boilers .
* IF Condensate Polishers are in service:
* IF Condensate Polishers are in service:
* Verify QCV-10426, SECONDARY BYPASS -OPEN. (YES)
* Verify QCV-10426, SECONDARY BYPASS - OPEN. (YES)
* Locally depress the OFF Pushbutton on Condensate Polisher Vessels A, B, C, D, E and F.
* 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:
* Secure ANY evolution that passes water through the beds, such as a low volume rinse.
* Locally verify C-48A, LCV-1417B INLET -CLOSED .
BOP         Verify Hotwell return to CST isolated as follows:
* Locally verify C-48B, LCV-1417B DISCHARGE  
* Locally verify C-48A, LCV-1417B INLET - CLOSED .
-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&deg;F 218 Steps EQUIPMENT UNDER CLEARANCE:  
* Locally verify C-48B, LCV-1417B DISCHARGE - LOCKED CLOSED.
* "A" CCW Pump OOS and Breaker Racked Out EQUIPMENT STATUS:
Dispatch An Operator To Close GS-36, MANUAL GLAND STEAM BOP DUMP.
End of Supplement G Steps Appendix D                                                         NUREG-1021, Rev. 9, Supp. 1
 
ILC-11-1 NRC SCENARIO 1 TURNOVER SHEET POWER LEVEL:           100% RTP Core Burnup:         9000 MWD/MTU EFPD:                257 EFPD Boron:                745 PPM Xenon:                EQXenon Tavg:                  575.9&deg;F Bank D Rods          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
* 5 GPO Primary to Secondary Leakage identified into "C" SIG
* R-24C in Alarm (APP-036-C7)
* R-24C in Alarm (APP-036-C7)
* Currently thunderstorm watch is in effect for Darlington and Chesterfield counties."
* Currently thunderstorm watch is in effect for Darlington and Chesterfield counties."
* RV-3 ("C" Steam Line PORV) Caution Capped. INSTRUCTIONS FOR THE WATCH:
* RV-3 ("C" Steam Line PORV) Caution Capped.
* 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:
INSTRUCTIONS FOR THE WATCH:
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 .
* Reduce Reactor Power and Turbine Load to 85% to support Maintenance on "A" Heater Drain Pump. "A" Heater Drain Pump has severe packing leakage.
I Appendix D Scenario Outline Form ES-D-1 Facility:
Appendix D                                                 NUREG-1021, Rev. 9, Supp. 1
HB ROBINSON Scenario No.: 2 Op Test No.: Examiners:
 
Operators:
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 IResin 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             ~350 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 Rad      Current                                    NUEValue RCS Leakage             0.00     Unidentified Monitor  Setpoint Alert Value 200X 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?
SRO-RO-BOP-Initial Conditions:
Nl-32         60                       180                                   BAST-B         9/16/2010 21,032           #NAME?       #NAME?
* 50% RTP BOL, 150 MWDIMTU, 1277 ppm Boron . * "A" CCW pump inoperable with the breaker racked out * "B" MFP breaker racked out for maintenance .
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"
* 5 GPD primary to secondary leakage into SIG "C"
* Currently thunderstorm watch is in effect for Darlington and Chesterfield counties Turnover:
* 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:
* Holding reactor power at 50% for maintenance on Main Feedwater Pump B motor.
Critical Tasks:
* Isolate feedwater to SIG B
* Isolate feedwater to SIG B
* Open at least 1 of the CV Spray Pump Discharge valves to provide CV Spray flow.
* 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
* Throttle AFW flow to the SIGs at 80-90 GPM .
\Appendix D Scenario Outline Form ES-D-1 I ILC-11-1 NRC SCENARIO 2  
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==
==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.
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.
5 GPO primary to secondary leakage has been identified in S/G C with elevated readings on the applicable radiation monitors.
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 (LT-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.
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.
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 hour or be in Mode 2 within 7 hours (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 hours OR Be in Mode 3 in 12 hours AND Be in Mode 4 within 18 hours. 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.
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 hour or be in Mode 2 within 7 hours (Current plant conditions requires that the REACTOR TRIP BLOCK P-7 status light be extinguished).
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.
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 hours OR Be in Mode 3 in 12 hours AND Be in Mode 4 within 18 hours. 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).
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
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.
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 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 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 standby Condenser Vacuum Pump will be started and a search for the vacuum leak will be 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.
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.
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.
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 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 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:
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.
* IC-802, SCN:008_NRC_2  
Appendix D                                                   NUREG-1021, Rev. 9, Supp. 1
* "A" CCW Pump inoperable with the breaker racked out * "B" Main Feed Pump breaker racked out for maintenance.
 
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
* 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
* 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:
* Status board updated to reflect IC-4.
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:
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:       CCW Pump B Trips on Overcurrent and CCW Pump C fails to auto start Event 4:      Condenser Vacuum Leakage Event 5:       Load Reduction due to Condenser Vacuum lowering Event 6:      Steam Line Break on SIG B inside the CV EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
* AOP-003
* AOP-003
* OWP-005, CVC-19
* OWP-005, CVC-19
Line 431: Line 825:
* Foldout A
* Foldout A
* FRP-P.1
* 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
* 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:==
== Description:==
VCT Level Transmitter LT-112 fails HIGH Time      i  Position  Ii                          Aoolicant's Actions or Behavior BOOTH OPERATOR: When directed, insert Event 1, VCT Level Transmitter LT-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 LT-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 LT-112 from ERFIS .
* Check VCT Level Indicators - Oscillating Level Deviation Observed (NO)
* Check deviation between LT-112 and LT-115 greater than 8" (13%) (YES)
RO        Check LT-115 failed. (NO)
RO        Check LT-112 failed. (YES)
RO        Check LT-112 - Failed High (YES)
CAUTION:          With NO operator action, LT-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


VCT Level Transmitter L T-112 fails HIGH Time ii Position Ii Aoolicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:
When directed, insert Event 1, VCT Level Transmitter L T-112 fails HIGH EVENT INDICATIONS:
                  - - Scenario #         2     Event #     ~~~~~
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".
Page   6 of 27
RO Check for failure of a level transmitter as follows:
                                                                                            ~~~~~I Event
* 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:==
== Description:==
VCT Level Transmitter LT-112 fails HIGH Time      II  Position  I                          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 COMPLETED (YES)
RO        Place LCV-115A in AUTO position.
SRO        Contact l&C to repair failed channel.
CREW        Make PA Announcement for Procedure Entry Continuous Action Step RO 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)
Verify Charging and Letdown flows are normal for plant conditions RO (YES).
RO        Check APP-003-D5, BA FLOW DEV, illuminated (NO).
Appendix D                                                          NUREG-1021, Rev. 9, Supp. 1


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.
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:                                                 - - - - - Page           7 of _2_7_ _ _-11 Event
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:==
== 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


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                               Operator Action                                 Form ES-D-2 Op Test No.:                                               2
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
                                                          ~~~~~
Page   8 of 27
                                                                                          ~~~~~I Event


== Description:==
== Description:==
PT-446 fails LOW Time      I  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&deg;F Determines PT-446 failed low and performs Immediate Actions of Crew AOP-025.
Immediate Action Step:
BOP        Check Turbine Load Reduction in progress or has occurred.
(NO, Go TO Step 3)
Immediate Action Step:
BOP 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.
Determines AOP-025, RTGB INSTRUMENT FAILURE and enters SRO Section H and verifies Immediate Actions.
Crew        Make PA announcement for entry into AOP-025.
Appendix D                                                        NUREG-1021, Rev. 9, Supp. 1


PT-446 fails LOW Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                               Operator Action                                   Form ES-D-2
At the discretion of the Chief Examiner, insert Event 2 -First Stage Pressure Transmitter PT-446 fails LOW EVENT INDICATIONS:
_2_ _ _ _ _ Page          9 of _2_7_ _ _....
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&deg;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
Op Test No.:
* Place the Rod Control Selector Switch in Manual.
                  - - Scenario #           2     Event #
* 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
1 Event


== Description:==
== 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.
Place the First Stage Pressure Selector Switch to the alternate BOP 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&deg;F of T REF AND Axial Offset within RO                the target band. (NO) 0  Restore TAVG 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


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
Appendix D                                 Operator Action                                   Form ES-D-2 Op Test No.:             Scenario#         2     Event#     _2_ _ _ _ _ Page           10 of 27
* FCV-478, FCV-488, and FCV-498. BOP Place the First Stage Pressure Selector Switch to the alternate channel (PT-447).
                  --                                                                          -----1 Event
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&deg;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:==
== 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.
PT-446 fails LOW Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:
If requested to check PT-446, there is no visible damage or leakage noted.
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:
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 hour or be in Mode 2 within 7 hours (Current plant conditions requires that the REACTOR TRIP BLOCK P-7 status light be extinguished).
* 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 hour or be in Mode 2 within 7 hours (Current plant conditions requires that the REACTOR TRIP BLOCK P-7 status light be extinguished).
SRO
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 hours OR Be in Mode 3 in 12 hours AND Be in Mode 4 within 18 hours.
* 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 hours OR Be in Mode 3 in 12 hours AND Be in Mode 4 within 18 hours.
* 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).
* 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
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 #     3
                                                            ~~~~~
Page   11 of 27
                                                                                              ~~~~~1 Event


== Description:==
== 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.
IF the running CCW Pump has tripped, THEN VERIFY Standby CCW RO Pump STARTED (RO manually starts "C" CCW Pump)
Dispatches an operator to check breaker and Current Limiter Fuses.
RO (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


CCW Pump "B" Trips and CCW Pump "C" fails to auto start Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:             Scenario #     2     Event #     3                 Page   12 of 27
At the discretion of the Chief Examiner, insert Event 3, CCW Pump "B" Trips and CCW Pump "C" fails to auto start EVENT INDICATIONS:
                  --                                      ~~~~~                            ~~~~~1 Event
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:==
== Description:==
CCW Pump "B" Trips and CCW Pump "C" fails to auto start Time      II  Position  II                        Applicant's Actions or Behavior Go to the appropriate section for indicated Malfunction:
SRO/RO 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&deg;F (NO)
IF CCW HX outlet temperature is greater than 105&deg;F, then go to step 3 (NO)
RO        OR IF CCW HX outlet temperature is less than 105&deg;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


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:
Appendix D                               Operator Action                                   Form ES-D-2 2                _3_ _ _ _ _ Page          13 of _2_7_ _ _~
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.)
Op Test No.:
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&deg;F (NO) IF CCW HX outlet temperature is greater than 105&deg;F, then go to step 3 (NO) RO OR IF CCW HX outlet temperature is less than 105&deg;F, then go to step 4.c. (YES) RO Check CCW HX outlet temperature
                  - - Scenario#               Event#
-Stable OR Decreasing (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Operator Action Form ES-D-2 Op Test No.: --Scenario#
1 Event
2 Event# _3 _____ Page 13 of _2_7 ___ Event


== Description:==
== 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 hours, 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


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
Appendix D                           Operator Action                                   Form ES-D-2 Op Test No.:
-Restore required CCW train to operable status within 72 hours, 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.
                  - - Scenario #       2     Event #   _4_a_n_d_5_ _ _ Page       14 of _2.;.;.;7_ _ _--1 1
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
Event
___ Page 14 of _2.;.;.;7
___ --1 1 Event


== Description:==
== 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 Immediate Action BOP Check Circulating Water Pump - Any Tripped (NO)
SRO    Enters AOP-012 and verifies immediate actions.
BOP    Check Condenser Vacuum previously established. (YES)
Verify all available Vacuum Pumps Running. (YES)
BOP 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


Condenser Vacuum leakage and Load Reduction due to Condenser Lowering Vacuum Time A licant's Actions or Behavior BOOTH OPERATOR:
Appendix D                           Operator Action                                   Form ES-D-2 Op Test No.:           Scenario#     2   Event#     _4_a_n_d_5_ _ _ Page       15 of _2_7_ _ _ _
At the discretion of the Chief Examiner, insert Event 4, Condenser Vacuum Leakage. EVENT INDICATIONS:
                  --                                                                                1 Event
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:==
== Description:==
Condenser Vacuum leakage and Load Reduction due to Condenser Lowering Vacuum Time          Pos                              A  licant's Actions or Behavior Continuous Action Step:
BOP Check Pl-1310 AND Pl-1311 - INCREASING (YES)
Reduce Turbine Load using Attachment 2, as necessary, to maintain CREW 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.)
Attachment 2 - Turbine Load Reduction BOP  Check Turbine Control Mode - Automatic (YES)
BOP  Depress the IMP IN Pushbutton BOP  Set the Desired Load in the setter Set the Desired Load Rate (1 %/min) (Higher load rate may be chosen BOP 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


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
Appendix D                                 Operator Action                                   Form ES-D-2 Op Test No.:               Scenario #       2   Event #     4 and 5           Page   16 of 27
: 3. Notify Load Dispatcher of the load reduction.
                  --                                        ~----                            ----~I Event
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:==
== 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.
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.
DETERMINE the amount of Boric Acid to add to the RCS and RO OBTAIN an independent check of the volume required.
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 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         PLACE the RCS MAKEUP MODE selector switch to BORATE.
RO IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN AND ADJUST using the UP and DOWN pushbuttons.
RO         SET YIC-113, BORIC ACID TOTALIZER to desired quantity.
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:
IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN RO 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
RO
* Rod Motion is blocked or in the wrong direction
* Rod Motion is blocked or in the wrong direction
* T AVG increases
* TAVG increases
* Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:
* 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
RO
* FCV-113A, BORIC ACID FLOW, closes .
* FCV-113B, BLENDED MU TO CHG SUCT, closes .
* FCV-113B, BLENDED MU TO CHG SUCT, closes .
* IF in Auto, THEN the operating Boric Acid Pump stops .
* 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#  
* The RCS MAKEUP SYSTEM is OFF .
--2 Event# 4 and 5 Page 17 of 27 Event
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
                  --                                            ~~~~-                            ~~~~~I Event


== Description:==
== 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:
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.
* PLACE the RCS MAKEUP MODE selector switch in the ALT DILUTE position.
* SET YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons .
* SET YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons .
* PLACE FCV-114B, BLENDED MU TO VCT to CLOSE.
* PLACE FCV-114B, BLENDED MU TO VCT to CLOSE.
* Momentarily PLACE RCS MAKEUP SYSTEM switch to START .
* 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:
* IF any of the below conditions occur, THEN momentarily place the RCS MAKEUP SYSTEM switch in the STOP position:
0 Unanticipated Rod Motion 0 Primary Water addition reaches the desired value
RO 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:
* 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:
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 .
* VERIFY FCV-114A is in AUTO .
* PLACE FCV-114B to the AUTO position . RO
* PLACE FCV-114B to the AUTO position .
RO
* PLACE the RCS MAKEUP MODE switch in AUTO.
* PLACE the RCS MAKEUP MODE switch in AUTO.
* VERIFY FCV-113A is in AUTO .
* VERIFY FCV-113A is in AUTO .
* Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.
* 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.
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.
MONITOR parameters for the expected change in reactivity AND RO 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
END OF BORATION STEPS BOP       Check Condenser Nitrogen Addition in service (YES)
Dispatch an Operator to Close NS-143, N2 Injection to Condenser BOP 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 #     4 and 5
                                                          ~~~~~
Page   18 of 27
                                                                                            ~~~~~I Event


== Description:==
== 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.
Direct measurement of condenser lnleakage using OP-504, Condenser SRO/BOP 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


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
Appendix D                                Operator Action                                         Form ES-D-2 Op Test No.:
: 1. SRO/BOP Notify Chemistry Personnel to Monitor Secondary Chemistry.
                  - - Scenario #          2      Event #      6, 7,8,9, 10      Page    19  of    27
SRO/BOP Direct measurement of condenser lnleakage using OP-504, Condenser Air Removal BOP Check Cause of Vacuum Loss Found (NO) BOOTH OPERATOR:
                                                                                                    -------;1 Event
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:==
== Description:==
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                                Applicant's Actions or Behavior BOOTH OPERATOR: 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)
Immediate Action Step BOP Turbine tripped (YES)
Immediate Action Step BOP E1 & E2 energized (YES)
Immediate Action Step RO SI initiated (YES)
Appendix D                                                            NUREG-1021, Rev. 9, Supp. 1


Time II Position BOOTH OPERATOR:
Appendix D                                Operator Action                                         Form ES-D-2 Op Test No.:              Scenario #       2     Event #     6, 7, 8,9, 10     Page     20  of _  27_ _ ____,I Event
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:==
== Description:==
 
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.
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:
Time     i  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 FAULTED 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.
* Any S/G pressure is decreasing in an uncontrolled manner OR Any S/G has completely depressurized.
AND BOP
AND BOP
* At least ONE S/G is intact. (NO, all faulted.)  
* 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
: a. Reset SI.
* Manually closes FCV-488 Task 1 BOP Manually closes V2-6B
: b. CLOSE the appropriate Auxiliary Feedwater isolation valves to the faulted S/Gs AND OPEN the associated breaker for the valves closed.
* 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
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                                 Operator Action                                          Form ES-0-2 Op Test No.:
                  - - Scenario#            2      Event#      6, 7,8,9, 10    Page      21  of
                                                                                                    -------1 27 Event


== Description:==
== Description:==
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)
If Additional Feedwater is required, THEN Start SDAFW Pump BOP (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


Operator Action Form ES-0-2 Scenario#
Appendix D                                Operator Action                                         Form ES-D-2 Op Test No.:
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)
                  - - Scenario #           2     Event #     6, 7,8,9, 10     Page     22  of _2_7_ _ _~
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
1 Event
& 4 running (YES) RO Verify IVSW System initiated (YES) Appendix D NUREG-1021, Rev. 9, Supp. 1 Appendix D Op Test No.: --Event


== Description:==
== Description:==
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      i  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
                                      - V12-8, CONT PURGE VALVE RO
                                      - 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 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)
Continuous Action Step RO CV pressure remained below 10 psig (NO)
Appendix D                                                            NUREG-1021, Rev. 9, Supp. 1


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)
Appendix D                                Operator Action                                         Form ES-D-2 Op Test No.:                                                   6, 7,8,9, 10     Page      23  of _2_7_ _ _-1 1
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
Event


== Description:==
== Description:==
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      I  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 Task1                        (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.}
Verify Approximately 12 GPM Spray Additive Tank Flow (RO will RO 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 Locally Open Breaker for HVS-1, At MCC-5 Compartment 7J within 60 BOP minutes of SI Initiation Booth Operator: After 3 min. delay open the breaker for HVS-1, MCC-5, Compartment 7J.
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


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
Appendix D                                Operator Action                                         Form ES-D-2 Op Test No.:                                2
* 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:
                  - - Scenario#                    Event#      6, 7,8,9, 10     Page     24  of _  27_ _ ___,I Event
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:==
== Description:==
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%
RCP Thermal Barrier Cooling Water Hi or Lo flow alarms illuminated RO (YES)
RO          At Least one Charging Pump Running (YES)
RO          Greater than 5 inches Thermal Barrier ~P on all Running RCPs (YES)
BOP          Place Steam Dump Mode switch to Steam Pressure RO          RCS temperature stable at or trending to 547&deg;F (NO)
RO          RCS Temperature greater than 547&deg;F (NO)
RO          Attempt to limit cooldown If RCS cooldown continues and is not due to SI flow, then close all BOP MSIVs and MSIV bypasses RO          PZR PORVs Closed (YES)
Appendix D                                                            NUREG-1021, Rev. 9, Supp. 1


Operator Action Form ES-D-2 Scenario#
Appendix D                                Operator Action                                         Form ES-D-2 Op Test No.:                                                    6, 7,8,9, 10     Page     25  of _  27_ _ __,I Event
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&deg;F (NO) RO RCS Temperature greater than 547&deg;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:==
== Description:==
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      I  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)
Reset SPDS AND Initiate Monitoring of Critical Safety Function Status RO Trees Transition to FRP-P.1, Response to Imminent Pressurized Thermal SRO Shock, due to an ORANGE on CSF-4.
Continuous Action Step Check CST Level - Less than 10% (NO)
BOP 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


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
Appendix D                                Operator Action                                         Form ES-D-2 Op Test No.:                              2      Event#      6, 7,8,9, 10     Page     26  of _2_7_ _ _ _
                  - - Scenario#                                                                                1 Event


== Description:==
== Description:==
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                                Applicant's Actions or Behavior BOP        Verify Steam Dumps Closed (YES)
RO        Check RHR System Aligned for core cooling (NO)
BOP        Check S/G Status - Any Intact (NO)
BOP        Verify closed all MSIVs and MSIV BYPs. (YES)
Verify closed all Steam Shutoffs to the SDAFW Pump.
BOP Close V1-8A, -8B, -8C Critical                    Maintain feed flow to each SIG between 80 gpm and 90 gpm Task            BOP        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 CREW enters FRP-H.1, Response to Loss of Secondary Heat Sink.
Check Total Feed Flow - LESS THAN 300 GPM DUE TO BOP OPERATOR ACTION (YES)
SRO        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


Time Position BOP RO BOP BOP BOP Critical Task BOP CREW BOP SRO Operator Action Form ES-D-2 Scenario#
ILC-11-1 NRC SCENARIO 2 TURNOVER SHEET POWER LEVEL:           50% RTP Core Burnup:           150 MWD/MTU EFPD:                  4.3 EFPD Boron:                1277 PPM Xenon:                EQ Xenon Tavg:                  560&deg;F Bank D Rods            153 Steps EQUIPMENT UNDER CLEARANCE:
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&deg;F 153 Steps EQUIPMENT UNDER CLEARANCE:  
* "A" CCW Pump OOS and Breaker Racked Out
* "A" CCW Pump OOS and Breaker Racked Out * "B" Main Feed Pump OOS and Breaker Racked Out EQUIPMENT STATUS:
* "B" Main Feed Pump OOS and Breaker Racked Out EQUIPMENT STATUS:
* 5 GPO Primary to Secondary Leakage identified on "C" SIG.
* 5 GPO Primary to Secondary Leakage identified on "C" SIG.
* Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.
* 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:
INSTRUCTIONS FOR THE WATCH:
HB ROBINSON Scenario No.: 3 Op Test No.: Examiners:
Holding reactor power at 50% for maintenance on Main Feedwater Pump "B" motor.
Operators:
Appendix D                                                 NUREG-1021, Rev. 9, Supp. 1
SRO-RO-BOP-Initial Conditions:
 
* 1E-8 amps BOL, 150 MWD/MTU, 1531 ppm Boron . * "A" CCW pump inoperable with the breaker racked out.
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       IPressure      PSIG                 Status A           #NAME?       PSIG       On cover                                                       DEMINERALIZERS Resin B           #NAME?         PSIG     In Service                                           PPM         In Service   Date 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 Rad      Current                                    NUE Value RCS Leakage             0.00   Unidentified Monitor  Setpoint Alert Value 200X 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.
* Power Range N-43 has been removed from service due to Power Supply Failure.
* Thunderstorm watch is in effect for Darlington  
* Thunderstorm watch is in effect for Darlington & Chesterfield counties .
& Chesterfield counties . Turnover:
Turnover:
* Maintain current reactor power until the RCP "C" oil leak issue is resolved.
* Maintain current reactor power until the RCP "C" oil leak issue is resolved.
Critical Tasks:
Critical Tasks:
* Align Safety Injection by starting at least one SI Pump and open one of the Sl-870 valves.
* 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)
* Align low head injection by starting RHR Pump A and opening RHR-744A or 744B valves.
Restore seal injection by starting one charging pump .
                      *     (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  
* 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==
==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.
DESCRIPTION The crew will assume the watch with the reactor at 1E-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.
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.
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.
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.
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  
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 hours, will be entered for the SWBP failure and ITS 3.6.6, Condition D, Two Containment Cooling Trains inoperable -
-Restore SWS train to operable status within 72 hours, 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 hours, 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.
-Restore one containment cooling train to operable status within 72 hours, 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.
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 hours and Mode 4 in 18 hours. Crew should begin making preparations for plant shutdown in accordance with GP-006.
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.
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 hours and Restore offsite circuit to operable status within 24 hours will be entered due to the Appendix D                                                   NUREG-1021, Rev. 9, Supp. 1
ITS 3.3.2, Condition D will be the most limiting LCO and require that the plant be placed in Mode 3 in 12 hours and Mode 4 in 18 hours. 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 hours and Restore offsite circuit to operable status within 24 hours 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.
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.
APP-036-E3 will be received and the crew will monitor 115kV and 230kV voltages.
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.
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.
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 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 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.
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.
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.
The RO will open at least one of the valves to ensure that low head core injection is available.
This will allow EPP-15 to be exited based on the first continuous action step that emergency recirculation capability has been restored.
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.
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.
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.
Appendix D                                                     NUREG-1021, Rev. 9, Supp. 1
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  
Appendix D                           Operator Action                         Form ES-D-2 ILC-11-1 NRC SCENARIO 3 SIMULATOR SETUP IC/SETUP:
* "A" CCW Pump inoperable with the breaker racked out.
* IC-803, SCN: 008_NRC_3
    *   "A" CCW Pump inoperable with the breaker racked out.
* N-43 removed from service.
* 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:
* Status board updated to reflect IC-1.
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:
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:       HVE-3 (CV Iodine Removal Fan) Trips Event 2:      Low Pressure Letdown PT-145 fails LOW Event 3:      Place Excess Letdown in Service Event 4:      Service Water Booster Pump "B" Trips Event 4A:      PT-455, PZR Pressure Transmitter, fails HIGH Event 5:      Degraded Voltage on System Grid Event 8:      Restoration of Charging Pump I Seal Cooling Event 9:      RHR Pump "A" trips EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
* APP-01 O-C6
* APP-01 O-C6
* OP-921, Section 8.1.2
* OP-921, Section 8.1.2
Line 675: Line 1,324:
* Foldout B
* Foldout B
* FRP-P.1
* 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
* EPP-15 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:==
== 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.
Announce APP-01 O-C6, HVE-3 AIR TROUB I MOTOR OVLD, BOP illuminated.
BOP        Check Breaker at MCC-5, CMPT 8B, for tripped condition. (YES)
BOP        Check damper positions. (YES - DOME VENT)
IF the breaker has tripped, THEN ATTEMPT Reclosure once (YES -
BOP 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


HVE-3 (CV Iodine Removal Fan) Trips Time Position II Applicant's Actions or Behavior BOOTH OPERATOR:
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
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:==
== Description:==
 
PT-145 fails LOW Time     II Position II                         Annlicant's Actions or Behavior BOOTH OPERATOR: Event 2 - PT-145 fails LOW EVENT INDICATIONS:
PT-145 fails LOW Time II Position II Annlicant's Actions or Behavior BOOTH OPERATOR:
APP-001-EG, LP LTDN RELIEF HI TEMP Letdown flow will lower to zero gpm.
Event 2 -PT-145 fails LOW EVENT INDICATIONS:
Per APP-001-E6, IF PCV-145 is malfunctioning, THEN REFER to RO AOP-025.
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.
SRO         Enters AOP-025 for PT-145 Malfunction.
RO Place LCV-460A & B in the CLOSE Position.
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  
RO         Verify ONLY ONE Charging Pump Running Place Excess Letdown In Service Using Attachment 2, Placing Excess RO Letdown in Service Examiner Note:               Ensure that the candidate in the RO position performs AOP-025 Att. 2.
: 2. Actions of AOP-025 will continue on Paae 7. Verify Closed the following valves:
NOTE:                         The following steps will place Excess Letdown in Service using Attachment 2. Actions of AOP-025 will continue on Paae 7.
* LCV-460A & B , L TON LINE STOP
Verify Closed the following valves:
* LCV-460A & B , LTON LINE STOP
* CVC-200A, LETDOWN ORIFICE ISOLATION RO/BOP
* CVC-200A, LETDOWN ORIFICE ISOLATION RO/BOP
* CVC-2008, LETDOWN ORIFICE ISOLATION
* CVC-2008, LETDOWN ORIFICE ISOLATION
* CVC-200C, LETDOWN ORIFICE ISOLATION
* CVC-200C, LETDOWN ORIFICE ISOLATION
* CVC-204A.
* CVC-204A. LETDOWN LINE ISO
LETDOWN LINE ISO
* CVC-2048, LETDOWN LINE ISO Appendix D                                                                   NUREG-1021, Rev. 9, Supp. 1
* 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
Appendix D                                 Operator Action                                   Form ES-D-2 Op Test No.:                                                 _2_a_n_d_3_ _ _ Page       7 of _2_6_ _ _,_.
1 Event


== Description:==
== Description:==
 
PT-145 fails LOW Time     II Position II                           Applicant's Actions or Behavior RO/BOP         Verify Open CC-739, CCW FROM EXCESS LTON HX. (YES)
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&deg;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.
RO/BOP         Position CVC-389, EXCESS LTON DIV, to the RCDT Position RO/BOP         Open CVC-387, EXCESS LTON STOP SLOWLY OPEN HCV-137, EXCESS LTDN FLOW not to exceed RO/BOP 195&deg;F as indicated on Tl-139, EXCESS LTON HX OUTLET TEMP RO/BOP         Notify the CRS that Excess Letdown is in service.
* Access Calorimetric on ERFIS by typing CALO RO/BOP
Update the ERFIS Calorimetric program to reflect Excess Letdown is in service.
RO/BOP
* Access Calorimetric on ERFIS by typing CALO
* Click on ENTER DATA
* Click on ENTER DATA
* Click on Excess Letdown In Service YES box .
* 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
* 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.
___ Page 8 of _2_6 ___ --1 1 Event
Position CVC-389, EXCESS LTON 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.:                                               _2_a_n_d_3_ _ _ Page        8 of _2_6_ _ _--1
                  - - Scenario #           3     Event #
1 Event


== Description:==
== Description:==
PT-145 fails LOW Time      I  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 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)
SRO 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


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                                 Operator Action                                     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 # --_4 _____ Page 9 of _2_6 ___ _, 1 Event
_4_ _ _ _ _ Page          9  of _2_6_ _ __,
Op Test No.:
                  - - Scenario #           3   Event #                                                   1 Event


== Description:==
== 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)
Announces starting SWBP "A" and then starts Service Water Booster BOP Pump "A" Dispatches AO to check local indication of "A" SWBP and breaker for BOP "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 hours, will be entered for the SWBP failure and ITS 3.6.6, Condition D, Two Containment Cooling Trains SRO inoperable - Restore one containment cooling train to operable status within 72 hours, 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


Service Water Booster Pump "B" Trips Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                                 Operator Action                                   Form ES-D-2 Op Test No.:
At the discretion of the Chief Examiner, insert Event 4, Service Water Booster Pump "B" Trips. EVENT INDICATIONS:
                - - Scenario #           3   Event #     _4_A_ _ _ _ Page           10 of _2_6_ _ _-1 1
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
Event
-Restore SWS train to operable status within 72 hours, 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 hours, 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:==
== 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 Acknowledge APP-003-AS, PZR PROT HI PRESS, and enters APP-RO 003-AS Identifies that PT-455 has failed high. Recommends removing the RO failed channel from service using OWP-029 IAW APP-003-AS.
Makes copy of OWP-029, PPT-1, Pressurizer Pressure Channel PT-SRO 455, and reviews/briefs with the Crew.
Crew determines that OWP-029 would trip OT/':,.T LOOP 1 bistables.
Since OT/':,.T LOOP 3 bistables are already tripped due to N-43 being SRO 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 D and H are applicable. ITS 3.3.2, Condition D is the most limiting SRO LCO by requiring the plant to be in Mode 3 in 12 hours and Mode 4 in 18 hours.
Contacts WCC SRO and/or Maintenance to initiate a W/R to SRO 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


PT-455, PZR Pressure Transmitter fails High Time Position Applicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                                  Operator Action                                    Form ES-D-2
At the discretion of the Chief Examiner, insert Event 4A, PT-455, PZR Pressure Transmitter, fails HIGH. EVENT INDICATIONS:
_5_ _ _ _ _ Page          11 of _2_6_ _ _....,
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.
Op Test No.:
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.
                  - - Scenario #           3     Event #
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.
1 Event
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 hours and Mode 4 in 18 hours. 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:==
== Description:==
Degraded Voltage on System Grid Time      I  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 hours and Restore offsite circuit to operable status within 24 hours 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)
Continuous Action Step RO/BOP 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 Check ANY of the following Diesel Generators Paralleled to the Grid.
BOP (NO)
BOP        Check Turbine Status - On Line (NO)
Check with Load Dispatcher - Adequate Voltage Support is Presently BOP Available For a LOCA Event (NO)
Appendix D                                                            NUREG-1021, Rev. 9, Supp. 1


Degraded Voltage on System Grid Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                               Operator Action                                 Form ES-D-2 Op Test No.:             Scenario#     3     Event#
At the discretion of the Chief Examiner, insert Event 5, Degraded Voltage on System Grid. EVENT INDICATIONS:
Event
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 hours and Restore offsite circuit to operable status within 24 hours 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:==
== Description:==
 
Degraded Voltage on System Grid Time         Position                             A   licant's Actions or Behavior Declare off-site power Inoperable and implement the required actions SRO of ITS 3.8.1 and Notify personnel and Evaluate plant risk.
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
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:
* Normal supply breaker opens (YES)
* Normal supply breaker opens (YES)
BOP
* EOG starts (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.
* EOG output breaker closes. (YES)
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
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 #     6
                                                          ~~~~~
Page   13 of 26
                                                                                            ~~~~~I Event


== Description:==
== Description:==
LOCA when Reactor Trips.
Time      I  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.)
Immediate Action Step BOP Turbine tripped (YES)
Immediate Action Step BOP E1 & E2 energized (YES)
Immediate Action Step RO 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&deg;F [55&deg;F]
: b. IF the PHASE B Isolation Valves are Closed, THEN stop all RCPs.
EXCESS LETDOWN ISOLATION CRITERIA IF a Phase A Isolation signals occurs, THEN verify:
RO
* CVC-387, EXCESS LTDN STOP - CLOSED
* HIC-137, EXCESS LTDN FLOW- CONTROLLER AT 0%
Appendix D                                                        NUREG-1021, Rev. 9, Supp. 1


LOCA when Reactor Trips. Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:
The reactor trip will automatically trigger a LOCA. Safeguards sequencers will fail to start loads. EVENT INDICATIONS:
                  - - Scenario #         3     Event #     6 Page   14 of 26
RCS Pressure Lowering Rapidly PZR Level Lowering Rapidly Containment Sump Level and Pressure Rising Rapidly Safety Injection has automatically initiated.
                                                                                            ------11 Event
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&deg;F [55&deg;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:==
== 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 WD-1722, RCDT PUMP DISCHARGE LINE AUTO ISOLATION Critical RO Task                        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


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:
Appendix D                               Operator Action                                     Form ES-D-2 Op Test No.:
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
                - - Scenario #           3     Event #       6
                                                            ~~~~~
Page   15 of 26
                                                                                              ~~~~~1 Event


== Description:==
== 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)
If Additional Feedwater is required, THEN Start SDAFW Pump (NO)
BOP (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 .
Verify both RHR pumps running (NO)
Critical 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                    and B did not open automatically.)
RO 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


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.
Appendix D                             Operator Action                                   Form ES-D-2 Op Test No.:
Unable to restart.)
                  - - Scenario #       3     Event #     6
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.)
Page   16 of 26
* RO or BOP should verify EDGs loads as expected . Critical Verify both RHR pumps running (NO) Task RO
                                                                                          ~~~~~1 Event
* 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:==
== 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)*
                            *(If the crew did not depress the Containment Isolation Pushbuttons RO      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
                                    - V12-8, CONT PURGE VALVE RO
                                    - 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 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


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
Appendix D                                 Operator Action                                   Form ES-D-2 Op Test No.:             Scenario #       3   Event #     _6_ _ _ _ _ Page           17 of _2_6_ _ _-1
* Starts HVH-1, 2, 3 & 4 .
                  --                                                                                    1 Event
* 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:==
== 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.)
Continuous Action Step RO CV pressure remained below 10 psig (NO)
RO        Verify CV Spray Initiated. (YES)
Verify ALL CV Spray Pumps Running with Valves Properly Aligned RO (YES)
Verify Approximately 12 GPM Spray Additive Tank Flow. (Manually throttles Sl-845C from RTGB.)
RO (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)
Locally open the breaker for HVS-1 at MCC-5 within 60 minutes of SI BOP 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


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.)
Appendix D                               Operator Action                                   Form ES-D-2
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.)
_6_ _ _ _ _ Page              of _2_6_ _ __,
RO Verify Phase B Isolation Valves Closed. (YES) RO Stop all RCPs (All previously secured.)
Op Test No.:
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
                  - - Scenario #         3     Event #                               18 1
Event


== Description:==
== 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%
RCP Thermal Barrier Cooling Water Hi or Lo flow alarms illuminated RO (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


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                               Operator Action                                     Form ES-D-2 Op Test No.:             Scenario #       3     Event #     _6_ _ _ _ _ Page           19 of _2_6_ _ _--1
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
                    --                                                                                      1 Event


== Description:==
== Description:==
 
LOCA when Reactor Trips.
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)
:   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)
* 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  
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:
: 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 in less than 15 minutes.
Critical RO Task                       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.
* 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&deg;F (NO) (No RCPs are running. Candidate should use T/Cs.) RO RCS temperature greater than 547&deg;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
* RCP SEAL WATER FLOW CONTROL VALVEs
: 1) CVC-297A
: 2) CVC-297B
: 3) CVC-297C BOP       Place Steam Dump Mode switch to Steam Pressure RCS temperature stable at or trending to 547&deg;F (NO)
RO (No RCPs are running. Candidate should use T/Cs.)
RCS temperature greater than 547&deg;F (NO)
RO (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:==
== 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)
CV Pressure Normal (NO)
RO
* 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 Check CST Level - Less than 10% (NO)
BOP 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


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.
Appendix D                             Operator Action                                     Form ES-D-2 Op Test No.:                                               _6_ _ _ _ _ Page           21 of _2_6_ _ _'"""
* 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)
1 Event
* 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:==
== Description:==
LOCA when Reactor Trips.
Time      I  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.
Open Foldout B.
CREW (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)
Control AFW Flow to Maintain S/G Levels between 8% [18%] and BOP 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


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.}
Appendix D                               Operator Action                                   Form ES-D-2
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
_6_ _ _ _ _ Page          22 of _2_6_ _ _...,
Op Test No.:
                  - - Scenario #         3   Event #
1 Event


== Description:==
== Description:==
LOCA when Reactor Trips.
Time          Position                            A  licant's Actions or Behavior RO        PZR PORVs Closed (YES)
Open at least one PORV Block unless Closed to Isolate an Open PZR RO 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)
IF Adequate diesel capacity not available to run charging pumps BOP THEN shed non-essential loads using Supplement F.
Appendix D                                                        NUREG-1021, Rev. 9, Supp. 1


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.
Appendix D                             Operator Action                                     Form ES-D-2
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.
_6_ _ _ _ _ Page            23 of _2_6_ _ _-1 Op Test No.:
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
                  - - Scenario #       3       Event #
1 Event


== Description:==
== 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&deg;F [55&deg;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


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&deg;F [55&deg;F] (NO) Continuous Action Step RO WHEN Below 10-10 Amps, THEN Energize Source Range detectors and monitor recorder.
Appendix D                                 Operator Action                                   Form ES-D-2 Op Test No.:                                                 _6_ _ _ _ _ Page           24 of _2_6_____
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
1 Event


== Description:==
== 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 Check Emergency Coolant Recirculation Capability - Restored (NO)
RO If Emergency Coolant Recirculation is restored, THEN perform Step
: 2. Go to Step 3.
Foldout pages are not applicable during performance of this CREW procedure.
Continuous Action Step Check suction source to any of the following pumps - LOST (NO)
RO SI Pumps, RHR Pumps, CV Spray Pumps If suction source lost to pump(s), THEN perform Step 5. Go to Step 6.
Check Emergency Recirculation Equipment-AVAILABLE USING RO SUPPLEMENT D (NO)
RNO - Try to restore at least one train while continuing with this RO procedure.
Appendix D                                                          NUREG-1021, Rev. 9, Supp. 1


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
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:
-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.
                  - - Scenario#          3     Event#     6
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#
Page   25 of 26
--3 Event# Page 25 of 26 6 Event
                                                                                          ~~~~--11 Event


== Description:==
== Description:==
LOCA when Reactor Trips.
Time      II  Position  I                        Applicant's Actions or Behavior Verify the following CV RECIRC FANs - RUNNING (YES)
RO 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


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&deg;F 100 Steps EQUIPMENT UNDER CLEARANCE:  
ILC-11-1 NRC SCENARIO 3 TURNOVER SHEET POWER LEVEL:           1E-8 amps Core Burnup:            150 MWD/MTU EFPD:                  4.3 EFPD Boron:                  1531 PPM Xenon:                  EQ Xenon Tavg:                    548&deg;F Bank D Rods            100 Steps EQUIPMENT UNDER CLEARANCE:
* "A" CCW Pump OOS and Breaker Racked Out EQUIPMENT STATUS:
  * "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.
* Reactor is at 1E-8 amps and the turbine is on the turning gear with GP-005 in effect.
* RCP "C" has an oil leak issue.
* RCP "C" has an oil leak issue.
* Power Range N-43 has been removed from service due to Power Supply Failure.
* Power Range N-43 has been removed from service due to Power Supply Failure.
Line 862: Line 1,739:
INSTRUCTIONS FOR THE WATCH:
INSTRUCTIONS FOR THE WATCH:
* Maintain current reactor power until the RCP "C" oil leak issue is resolved.
* 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:
Appendix D                                                 NUREG-1021, Rev. 9, Supp. 1
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:
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 Resin B           #NAME?       PSIG       In Service                                           PPM         In Service   Date 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           ~350 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 Rad      Current                                    NUE Value RCS Leakage             0.00   Unidentified Monitor  Setpoint Alert Value 200X 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?
HB ROBINSON Scenario No.: 4 Op Test No.: Examiners:
Nl-32         60                     180                                 BAST-B           9/16/2010 21,032           #NAME?       #NAME?
Operators:
SFP             9/15/2010 2246             #NAME?       #NAME?
SRO-RO-BOP-Initial Conditions:
Normal Currents                                 RWST             9/16/2010 2219             #NAME?       #NAME?
* 75% RTP EOL, 15697 MWDIMTU, 132 ppm Boron . * "A" CCW pump inoperable with the breaker racked out
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"
* 5 GPO primary to secondary leakage into SIG "C"
* Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.
* Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.
Turnover:
Turnover:
* Awaiting Engineering personnel to install vibration monitoring equipment to allow starting Heater Drain Pump "A". Critical Tasks:
* 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
* Manually runback the turbine to stop the steam flow
* Secure all RCPs due to two SIG WIR levels less than 10%
* 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  
* 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                                     MDAFW and SDAFW Pumps Trip when Start Signal BOP 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==
==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.
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.
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 hours, and ITS 3.8.9 Condition B, One AC instrument bus subsystem inoperable - Restore AC instrument bus subsystem to operable status within 2 hours, will be implemented by the SRO. Once AOP-024 and ITS actions are completed, the Chief Examiner can cue the next event.
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  
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 hours, 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.
-Restore AC Instrument Bus Power Source to operable status within 24 hours, and ITS 3.8.9 Condition B, One AC instrument bus subsystem inoperable  
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 hours or Be in Mode 3 within 12 hours. 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 hours OR Be in Mode 3 in 12 hours AND Be in Mode 4 within 18 hours. 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.
-Restore AC instrument bus subsystem to operable status within 2 hours, 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.
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
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 hours, 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 hours or Be in Mode 3 within 12 hours. 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 hours OR Be in Mode 3 in 12 hours AND Be in Mode 4 within 18 hours. 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.
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.
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.
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.
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.
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.
Steam dump valves will fail open on the trip and the MSIVs will fail to close when demanded from the RTGB control switches.
Both MDAFW Pumps and the SDAFW Pump will trip when the start signal is received.
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:
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.
* IC-804, SCN: 008_NRC_ 4 * "A" CCW Pump inoperable with the breaker racked out
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                           Form ES-D-2 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
* 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
* 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:
* Status board updated to reflect IC-22.
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:
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:     Loss of Instrument Bus #1 Event 2:      PZR Pressure Controller PC-444J Range Shifts Event 3:      Steam Pressure Channel PT-485 fails LOW Event 4:      Loss of Cooling to the Auxiliary Transformer Event 5:      Load Reduction to 50%
Event 6:      Feedwater Header Rupture EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:
* AOP-024
* AOP-024
* AOP-019
* AOP-019
Line 903: Line 1,803:
* Foldout A
* Foldout A
* FRP-H.1
* 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
* Supplement L 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:==
== Description:==
Loss of Instrument Bus #1 Time      i  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 Immediate Action Step BOP Verify S/G(s) Maintained At Program Level Immediate Action Step RO 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:
Check Auto Makeup, Boration OR Dilution - In Progress (NO) (Auto RO 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


Loss of Instrument Bus #1 Time ii Position Ii Applicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                               Operator Action                                 Form ES-D-2 Op Test No.:             Scenario #     4     Event #
When directed, insert Event 1, Loss of Instrument Bus #1 EVENT INDICATIONS:
Event
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:==
== 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.)
Control Charging and Letdown Flow to Maintain PZR Level.
RO (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 ENERGIZED FROM THE 4160V SUSSES (YES)
Continuous Action Step RO/BOP 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


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.)
Appendix D                                 Operator Action                                 Form ES-D-2 Op Test No.:                                               - - - - - Page             7 of _4_5_ _ _-;1 Event
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:==
== 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)
Continuous Action Step BOP 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


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
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:
* IB-1 through IB-4
                  - - Scenario #         4     Event #     - - - - - Page             8 of _4_5_____  1 Event
* 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:==
== Description:==
 
Loss of Instrument Bus #1 Time     II Position II                           Applicant's Actions or Behavior Restore RCS Makeup Control - IN AUTO
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
* Place the RCS MAKEUP SYSTEM Switch in STOP
* Verify the RCS MAKEUP MODE Switch in AUTO
* 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&deg;F OF TREF d. Place the Rod Control Selector Switch to A (Automatic)
* 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.
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:
Crew should identify that FCV-1148 will need to be opened to allow for Makeup to be routed to the top of the VCT.)
* Check Instrument Bus 4 -ENERGIZED (YES)
Continuous Action Step Restore Rod Control To Automatic As Follows:
* 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
RO           a. Check Power - GREATER THAN 15% (YES)
: b. Check Automatic Rod Control-AVAILABLE (YES)
: c. Check Tavg - WITHIN -1.5 TO +1.5&deg;F OF TREF
: d. Place the Rod Control Selector Switch to A (Automatic)
BOP         Check Emergency Susses E-1 AND E ENERGIZED (YES)
Continuous Action Step BOP         Check Emergency Susses E-1 AND E 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 Check Status Of Turbine:
BOP
* 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
                                                                                        ~~~~~I Event


== Description:==
== 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)
Continuous Action Step BOP 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)
Restore Normal Letdown Using Attachment 15, Restoration of Normal RO Letdown.
NOTE: The following are the steps to restore normal letdown using Attachment 15 of AOP-024.
Normal charging flow through the Regenerative Heat Exchanger is in RO/BOP service.
Appendix D                                                      NUREG-1021, Rev. 9, Supp. 1


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
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:
                  - - Scenario #         4     Event #
                                                            ~----
Page   10 of 45
                                                                                            -~~~--11 Event


== Description:==
== 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.
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:
RO/BOP         The Residual Heat Removal System is NOT in service.
VERIFY the following valves are CLOSED:
* CVC-204A, LETDOWN LINE ISO
* CVC-204A, LETDOWN LINE ISO
* CVC-204B, LETDOWN LINE ISO RO/BOP
* CVC-204B, LETDOWN LINE ISO RO/BOP
* LCV-460A, L TON LINE STOP
* LCV-460A, LTON LINE STOP
* LCV-460B, L TON LINE STOP
* LCV-460B, LTON LINE STOP
* CVC-200A, LETDOWN ORIFICE ISOLATION
* CVC-200A, LETDOWN ORIFICE ISOLATION
* CVC-200B, 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)
* 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.
Check Pressurizer level is greater than OR equal to program level.
DIVERSION, in the VCT position.
RO/BOP (YES)
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.
IF desired, THEN PLACE TCV-143, VCT/DEMIN. DIVERSION, in the RO/BOP VCT position.
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
RO/BOP         PLACE PC-145, PRESSURE, in MANUAL.
SET PC-145 to throttle PCV-145 to 45% to 55% open to ensure the RO/BOP 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
                  --                                        ~~~~~                            ~~~~~1 Event


== Description:==
== Description:==
 
Loss of Instrument Bus #1 Time         Position                               A licant's Actions or Behavior PERFORM the following:
Loss of Instrument Bus #1 Time Position A licant's Actions or Behavior PERFORM the following:
RO/BOP
RO/BOP
* OPEN LCV-460A&B by placing switch CVC-460A&B L TON LINE STOP to OPEN.
* OPEN LCV-460A&B by placing switch CVC-460A&B LTON 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&deg;F when letdown is reestablished.
* PLACE LTON LINE STOP CVC-460 A&B switch to AUTO .
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:
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&deg;F when letdown is reestablished.
While MAINTAINING Charging Pump discharge pressure as indicated on RTGB instrument Pl-121 LESS THAN 2500 psig, ADJUST RO/BOP charging pump speed to the expected letdown flow to be established in the next step.
OPEN one LTON ORIFICE valve:
RO/BOP 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.
IF TCV-143 was selected to the VCT, THEN Position TCV-143 as RO/BOP 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
RO/BOP
* CVC-297A, RCP "A" SEAL WATER FLOW CONTROL VALVE
* CVC-297A, RCP "A" SEAL WATER FLOW CONTROL VALVE
* CVC-297B, RCP "B" 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
* 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
                                                                                              ~~~~~1 Event


== Description:==
== 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:
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 HIC-121, Charging Flow is Full Open .
* Verify Charging Pump discharge pressure as indicated on RTGB instrument Pl-121 less than 2500 psig.
* 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 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.
* IF required, THEN while maintaining Charging Pump discharge pressure as indicated on RTGB instrument Pl-121 LESS THAN 2500 psig, ADJUST charging pump speed to meet flow RO/BOP                  requirement.
* Place PC-145, PRESSURE, in MANUAL.
* 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.
* 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 .
* OPEN one additional LTON 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.
* 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:
* Verify Seal Injection Flow between 8 GPM and 13 GPM by throttling the following: CVC-297 A, B, C.
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.
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.
BOP Check All Radiation Monitor Alarms -EXTINGUISHED (YES) Check R-11 OR R-12 IN SERVICE (YES) BOP RMS-1,2,3,4  
Notify RC that letdown flow has been restored and the affected areas RO/BOP should be monitored for changing radiological conditions.
-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
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:==
== Description:==
 
Loss of Instrument Bus #1 Time                                           A licant's Actions or Behavior Check Control Room Ventilation - ALIGNED FOR PRESSURIZATION BOP   MODE (NO)
Loss of Instrument Bus #1 Time A licant's Actions or Behavior Check Control Room Ventilation  
* Go To Step 41 .
-ALIGNED FOR PRESSURIZATION BOP MODE (NO)
Check PZR PRV Safety Acoustic Monitor Lights - ILLUMINATED RO (YES)
* 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:
Locally Reset PZR Safety Acoustic Monitors At INSTRUMENT CABINET A In The Computer Room By Performing The Following:
BOP
BOP
* Depress RESET RC-551A Pushbutton.
* Depress RESET RC-551A Pushbutton.
* Depress RESET RC-551 B 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
* 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_ _ _--11 Event


== Description:==
== 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 1O 18-3        Attachment 11 18-4        Attachment 12
* Restore the Instrument Bus to the normal power supply within 24 hours.
* IF the normal power supply can NOT be restored within 24 hours, THEN be in Mode 3 within 6 hours AND Mode 5 within 36 hours.
Check Status of EDGs - START SIGNAL RECEIVED (NO)
BOP
* 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 inoperable - Restore AC Instrument Bus Power Source to SRO operable status within 24 hours
* ITS 3.8.9 Condition B, One AC instrument bus subsystem inoperable - Restore AC instrument bus subsystem to operable status within 2 hours Appendix D                                                            NUREG-1021, Rev. 9, Supp. 1


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):
Appendix D                               Operator Action                                     Form ES-D-2 Op Test No.:
* 18-1: MCC-5 (Via E-1) (On Alternate)
                  - - Scenario #         4     Event #
* IB-2: INVERTER A
Page   15 of 45
* IB-3: INVERTER B
                                                                                              ----~I Event
* 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 hours.
* IF the normal power supply can NOT be restored within 24 hours, THEN be in Mode 3 within 6 hours AND Mode 5 within 36 hours. 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 hours
* ITS 3.8.9 Condition B, One AC instrument bus subsystem inoperable
-Restore AC instrument bus subsystem to operable status within 2 hours 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:==
== Description:==
Loss of Instrument Bus #1 Time      II  Position  II                          Aoolicant's Actions or Behavior Check Annunciator APP-005-A3, PR DROP ROD - ILLUMINATED RO (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)
Reset AMSAC TROUB/BYP Alarm by depressing the System Reset RO 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


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.)
Appendix D                               Operator Action                                     Form ES-D-2
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
_2_ _ _ _ _ Page          16 of _4_5_ _ __,
Op Test No.:
                  - - Scenario #         4     Event #
1 Event


== Description:==
== Description:==
PZR Pressure Controller PC-444J Range Shifts Time      I  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 Immediate Action Step RO        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 Continuous Action Step RO Check PZR Pressure - UNDER OPERATOR CONTROL (YES)
Continuous Action Step RO        Check Pressurizer Pressure Transmitter PT-444 OR PT-445 Failed.
(NO)
Check PC-444J, PZR PRESS - OPERATING 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


PZR Pressure Controller PC-444J Range Shifts Time II Position II Aoolicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                             Operator Action                                     Form ES-D-2 Op Test No.:             Scenario #     4     Event #     _2_ _ _ _ _ Page           17 of _4_5_ _ _-1
At the discretion of the Chief Examiner, insert Event 2, PC-444J Range Shifts EVENT INDICATIONS:
                --                                                                                      1 Event
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:==
== Description:==
PZR Pressure Controller PC-444J Range Shifts Time      I  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 hours, 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


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.
Appendix D                           Operator Action                                       Form ES-D-2 Op Test No.:
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
                  - - Scenario #     4     Event #
* LCO 3.4.11, PZR PORV (N/A)
                                                        - - -          Page     18 of 45
* TRM 3.4, PZR Spray t:,. T (N/A)
                                                                                            ----~I Event
* 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 hours, 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:==
== 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)
Immediate Action Step BOP 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 Channel Below:
BOP 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


Steam Pressure Transmitter PT-485 fails LOW A licant's Actions or Behavior BOOTH OPERATOR:
Appendix D                                 Operator Action                                   Form ES-D-2 Op Test No.:                                                 3
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.)
Page   19 of 45
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:
                                                                                              ~~~~~1 Event
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:==
== Description:==
Steam Pressure Transmitter PT-485 fails LOW Time      I  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 DELETE INPUT FROM CALORIMETRIC page.
BOP 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 Trip the Bistables for PT-485 BOP
{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


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)
Appendix D                                 Operator Action                                   Form ES-D-2 Op Test No.:                               4                _3_ _ _ _ _ Page          20 of _4_5_ _ ____,
{Two Options)
                  - - Scenario#                  Event#
* 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.
1 Event
* 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:==
== Description:==
 
Steam Pressure Transmitter PT-485 fails LOW Time         Position   II                         Aoolicant's Actions or Behavior Check Technical Specifications (ITS) For Applicable LCOs
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 hours or Be in Mode 3 within 12 hours.
* 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 hours or Be in Mode 3 within 12 hours.
* 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 SRO hours OR Be in Mode 3 in 12 hours AND Be in Mode 4 within 18 hours.
* 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 hours OR Be in Mode 3 in 12 hours AND Be in Mode 4 within 18 hours.
* 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 3.3.3-1 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)
* 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.:
NOTE:                         Crew should notify WCC SRO and/or l&C to write a work request, investigate and initiate repairs, and notify the Operations Manager.
4
SRO         Return To Procedure And Step In Effect Appendix D                                                         NUREG-1021, Rev. 9, Supp. 1
--_4_a_n_d_5
 
___ Page 21 of _4_5 ___ _, 1 Event
Appendix D                               Operator Action                                       Form ES-D-2 Op Test No.:
                  --   Sren~o#          4      Ew~#          _4_a_n_d_5_ _ _ Page       21 of _4_5_ _ __,
1 Event


== Description:==
== 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.
Operator reports Alarm 46-11, Loss of Normal 480Vac Power BOP 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)
NOTE: The APP-046 alarms in the table below are prioritized by SRO 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


Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%. Time A licant's Actions or Behavior BOOTH OPERATOR:
Appendix D                                 Operator Action                                       Form ES-D-2
At the discretion of the Chief Examiner, insert Event 4, Loss of Cooling to the Auxiliary Transformer.
_4_a_n_d5
EVENT INDICATIONS:
_ _ _ Page        22  of _4_5_ _ _ _ _
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.
Op Test No.:
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.
                  - - Scenario #           4     Event #                                                       1 Event
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:==
== Description:==
Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%.
Time      II  Position  II                            Aoolicant's Actions or Behavior Alarm 46-11, Loss of Normal 480Vac Power Source (18G) (Step BOP 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.
Dispatch an Operator to Observe the Status of the Fans and BOP 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)
Check Status of 480 Volt Bus 3 - POWER LOST (NO)
BOP Go to Step 11 Check Status of MCC POWER LOST (NO)
BOP Go to Step 17 BOP        Check Status of MCC-4, Breaker 4BR - TRIPPED (YES)
Attempt to Reset and Close MCC-4, Breaker 4BR One Time.
BOP (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


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.
Appendix D                                 Operator Action                                       Form ES-D-2 Op Test No.:                                                   _4_a_n_d_5_ _ _ Page       23   of _4_5_ _ _....,
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
1 Event
___ Page 23 of _4_5 ___ ...., 1 Event


== Description:==
== 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 Determine If Trip Required As Follows:
BOP
                                - Check time elapsed since loss of all cooling - Greater than 30 min. (NO)
IF the Auxiliary Transformer is NOT unloaded within 30 minutes, SRO 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.
Reduce power to less than 50% using Attachment 4, Turbine Crew 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


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
Appendix D                                 Operator Action                                       Form ES-D-2 Op Test No.:
-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.)
                - - Scenario #           4     Event #       _4_a_n_d_5_ _ _ Page       24 of _4_5_ _ _-1 1
NOTE: The crew is currently in a loop until power is less than 50% RTP and the Auxiliary Transformer Unloaded.
Event
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:==
== 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.
DETERMINE the amount of Boric Acid to add to the RCS and RO 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


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.
Appendix D                                 Operator Action                                       Form ES-D-2 Op Test No.:                                                     4 and 5
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
Page   25 of 45
                                                                                                  ~~~~~I Event


== Description:==
== Description:==
 
Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%.
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.
Tim           Position                                 A   licant's Actions or Behavior IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN RO 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       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
RO
* Rod Motion is blocked or in the wrong direction
* Rod Motion is blocked or in the wrong direction
* T AVG increases
* TAVG increases
* Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:
* 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
RO
* FCV-113A, BORIC ACID FLOW, closes .
* FCV-113B, BLENDED MU TO CHG SUCT, closes .
* FCV-113B, BLENDED MU TO CHG SUCT, closes .
* IF in Auto, THEN the operating Boric Acid Pump stops .
* 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:
* 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.
* PLACE the RCS MAKEUP MODE selector switch in the ALT DILUTE position.
* SET YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons .
* SET YIC-114, PRIMARY WTR TOTALIZER to 15-20 gallons .
* PLACE FCV-114B, BLENDED MU TO VCT to CLOSE .
* PLACE FCV-114B, BLENDED MU TO VCT to CLOSE .
* Momentarily PLACE RCS MAKEUP SYSTEM switch to START.
* 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:
* 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
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:
* 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
0   FCV-114A closes.
___ Page 26 of _4_5 ___ -1 1 Event
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:==
== Description:==
 
Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%.
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:
Time     II Position II                             Applicant's Actions or Behavior RETURN the RCS Makeup System to automatic as follows:
* VERIFY FCV-114A is in AUTO .
* VERIFY FCV-114A is in AUTO .
* PLACE FCV-114B to the AUTO position . RO
* PLACE FCV-114B to the AUTO position .
RO
* PLACE the RCS MAKEUP MODE switch in AUTO .
* PLACE the RCS MAKEUP MODE switch in AUTO .
* VERIFY FCV-113A is in AUTO .
* VERIFY FCV-113A is in AUTO .
* Momentarily PLACE the RCS MAKEUP SYSTEM switch in the START position.
* 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.
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.
MONITOR parameters for the expected change in reactivity AND RO 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:  
NOTE:                         End of Boration and Power Reduction Steps. AOP-037 steps continue below.
: 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.
Stop the following components:
NOTE: The following steps are from Attachment 5, Transfer of Electrical Loads to the Startup Transformer.
: 1. Circulating Water Pump "A" BOP             2. Feedwater Pump "A"
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
: 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 Insert key into Startup Transf synchroscope switch AND turn switch to BOP 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 #       4 and 5          Page   27 of 45
                  --                                        ~~~~~                              ~~~~~1 Event


== Description:==
== Description:==
Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%.
A  licant's Actions or Behavior WHEN the synchroscope come up to the 12 o'clock position, THEN BOP close START-UP TO 4KV BUS 2 BKR 52/12 WHEN breaker 52/12 indicates closed, THEN return switch to the mid-BOP position AND verify UNIT AUX TO 4KV BUS 1 BKR 52/7 has opened.
Insert key into 4KV TIES synchroscope switch AND turn switch to BUS BOP 3 & 4 position.
WHEN synchroscope comes up to 12 o'clock position, THEN close BOP 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)
IF APP-046 Alarms are present than have not been addressed, THEN SRO 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


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.
Appendix D                               Operator Action                                       Form ES-D-2 Op Test No.:
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.
                  --     Scenario#        4     Event#       _4_an_d_5_ _ _ Page         28 of
BOP Check Auxiliary Transformer
                                                                                                ------1 45 Event
-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:==
== 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


Loss of Cooling to the Auxiliary Transformer and Power Reduction to 50%. ion
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:                                               _6_ _ _ _ _ Page           29 of _4_5_ _ _-1 1
* 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:
Event
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:==
== Description:==
Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close
'    Time      I  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 Operators note the lowering SIG Levels and FRVs full open and RO/BOP recommend tripping the Reactor.
Immediate Action Step:
RO 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.
Immediate Action Step:
BOP E-1 AND E-2 energized. (YES)
Immediate Action Step:
RO SI Initiated. (YES)
SRO        Enters PATH-1 and verifies Immediate Actions.
Appendix D                                                        NUREG-1021, Rev. 9, Supp. 1


Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close ' Time II Position II Applicant's Actions or Behavior BOOTH OPERATOR:
Appendix D                                 Operator Action                                     Form ES-D-2
At the discretion of the Chief Examiner, insert Event 6, Feedwater Header Rupture EVENT INDICATIONS:
_6_ _ _ _ _ Page          30 of _4_5_____
All S/G Levels lowering.
Op Test No.:
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)
                  - - Scenario #           4       Event #
Task BOP Trip or Runback the Turbine. (YES, Runback was successful) (The Gov. Fast function has been over-ridden.
11 Event
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:==
== Description:==
Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time      I  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 (YES)
BOP 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


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.
Appendix D                               Operator Action                                   Form ES-D-2
* RCP Trip criteria.
_6_ _ _ _ _ Page            31  of _4_5_ _ _-1 Op Test No.:
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
                  - - Scenario #         4   Event #
-< 35 degrees F [55 degrees F]
1 Event
* 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:==
== Description:==
Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time      I  Position  II                        APPiicant's Actions or Behavior BOP        Verify both FW pumps are tripped. (YES)
Verify both MDAFW pumps are running. (NO) (Unable to start from BOP RTGB.)
If additional Feedwater is required, start the SDAFW pump. (NO, BOP Pump started but tripped)
WCC SRO or AO may be dispatched to investigate the cause of the SRO 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


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
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:             Scenario #     4     Event #     6                Page   32 of   45
                  --                                        ~~~~~                            ~~~~~1 Event


== Description:==
== 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
                                  - V12-8, CONT PURGE VALVE RO
                                  - 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 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


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:
Appendix D                               Operator Action                                   Form ES-D-2 Op Test No.:
-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
                  - - Scenario #         4   Event #     6
                                                          ~~---
Page   33 of   45
                                                                                              ----~I Event


== Description:==
== 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)
Locally open breaker for HVS-1 at MCC-5 CMPT ?J within 60 min of SRO SI Initiation.
Booth Operator              Open the breaker for HVS-1 within approximately 3 minutes of request.
RCS pressure> 1350 psig. [1250 psig] (YES)
(May be NO if manual turbine run back not started immediately or if the RO      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


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.
Appendix D                           Operator Action                                     Form ES-D-2 Op Test No.:           Scenario #   4     Event #   _6_ _ _ _ _ Page           34 of _4_5_ _ __,
Booth Operator Open the breaker for HVS-1 within approximately 3 minutes of request. RCS pressure>
                  --                                                                                  1 Event
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:==
== Description:==
Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time          Po                                A  licant's Actions or Behavior Reset SPDS and Initiate monitoring of Critical Safety Function Status RO Trees Transition to FRP-H.1, RESPONSE TO LOSS OF SECONDARY SRO HEAT SINK.
Check Total Feed Flow less than 300 GPM due to operator action.
BOP (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&deg;F [310&deg;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&deg;F and are annotated with a"@" symbol.)
SRO    @ Place RHR System in service using Supplement I.
                          @ Consult Plant Operations Staff to determine if RHR should be SRO 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


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:
Appendix D                               Operator Action                                     Form ES-D-2 Op Test No.:                                               _6_ _ _ _ _ Page           35 of _4_5_ _ _""'"
* Check RCS pressure greater than any non-faulted S/G pressure. (YES) RO
1 Event
* Check RCS temperature greater than 350&deg;F [310&deg;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&deg;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:==
== Description:==
Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close
:    Time      II  Position  II                        Aoolicant's Actions or Behavior
                                @ WHEN RCS pressure less than 375 psig [350 psig], THEN go to RO 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.
Continuous Action Step:
BOP 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.
Steps 31 through 35 must be performed quickly in order to establish SRO RCS heat removal by RCS bleed and feed.
RO        Depress the Initiate Safety Injection Pushbutton RO        Verify SI Pumps - At least one running (YES)
At the RTGB, verify SI Valves for at least one flow path - ALIGNED RO FOR COLD LEG INJECTION (YES)
Verify APP-002-F?, INSTR AIR HOR LO PRESS - EXTINGUISHED RO (YES)
Appendix D                                                        NUREG-1021, Rev. 9, Supp. 1


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
Appendix D                               Operator Action                                     Form ES-D-2 Op Test No.:                                             _6_ _ _ _ _ Page            36  of _4_5_ _ __,
                - - Scenario #         4     Event #
1 Event


== Description:==
== Description:==
 
Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Position                             A licant's Actions or Behavior Place IA PCV-1716, INSTRUMENT AIR ISO TO CV Control Switch to RO the OVERRIDE position.
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:
Establish RCS Bleed Path as follows:
* Verify power to PZR PORV Block Valves -Available (YES) RO
* Verify power to PZR PORV Block Valves - Available (YES)
RO
* Place all PZR Heater Control Switches to the OFF position.
* Place all PZR Heater Control Switches to the OFF position.
* Verify PZR PORV Block Valves -BOTH OPEN (YES)
* Verify PZR PORV Block Valves - BOTH OPEN (YES)
* Open both PZR PORVs Verify Adequate RCS Bleed Path as Follows: Critical RO
* Open both PZR PORVs Verify Adequate RCS Bleed Path as Follows:
* PZR PORVs -BOTH OPEN (YES) Task PZR PORV Block Valves -BOTH OPEN (YES)
Critical         RO
* 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.
* PZR PORVs - BOTH OPEN (YES)
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
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.
Momentarily place the Containment Spray Key Switch to the RO 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.:                                               6
                                                          ~~~~~
Page   37 of   45
                                                                                              ~~~~~I Event


== Description:==
== Description:==
 
Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time     I  Position II                         Applicant's Actions or Behavior RO         Reset Phase A and Phase B RO         Check Status of PCV-1716- IN OVERRIDE POSITION (YES)
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:
Momentarily place IA PCV-1716 Switch to RESET AND return to RO AUTO.
* Verify LCV-1158-OPEN (YES) RO
BOP       Check E-1 OR E Energized by EOG (NO)
* Verify LCV-115C -CLOSED (YES)
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
* Start all available Charging Pumps
* Increase running Charging Pumps speed to maximum
* 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
* Verify maximum charging flow on Fl-122A. (YES)
Continuous Action Step RO Check RWST Level - LESS THAN 27% (NO)
Continuous Action Step RO         Check CV Pressure - HAS INCREASED TO GREATER THAN 10 PSIG (NO)
Continuous Action Step RO Check CV Pressure - LESS THAN 4 PSIG (YES)
Appendix D                                                         NUREG-1021, Rev. 9, Supp. 1
 
Appendix D                               Operator Action                                   Form ES-D-2
_6_ _ _ _ _ Page            38  of _4_5_ _ __,
Op Test No.:
                - - Scenario #           4   Event #
1 Event


== Description:==
== Description:==
Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time      I  Position  II                        APPiicant's Actions or Behavior RO        Stop the operating CV Spray Pump (None running)
Verify CV SPRAY PUMP DISCH Valves - CLOSED RO (Sl-880A,B,C,D) (YES)
Verify Spray Additive Tank Discharge Valves - CLOSED RO (Sl-845A,B) (YES)
Continuous Action Step BOP Check CST level - Greater Than 10% (YES)
BOP        Check AFW Lines - INTACT (YES)
BOP        Check AFW Pump Breakers - Tripped (YES)
Position the MDAFW Pump Control Switch to the STOP position and BOP to the START 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


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:
Appendix D                               Operator Action                                     Form ES-D-2 Op Test No.:             Scenario #     4   Event #   _6_ _ _ _ _ Page         39     of _4_5_ _ _-1
* Verify STEAM DRIVEN AFW PUMP STM SHUTOFF VALVES OPEN. (V1-8A, V1-8B, V1-8C) (YES, then reclose.)
                  --                                                                                    1 Event
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:==
== Description:==
 
Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time     I  Position II                         *- . '- * * "" or Behavior Locally Investigate AND Attempt To Restore AFW Flow:
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
BOP
* Verify AFW Pump suction supply is available. (YES) (6 psig)
* Verify AFW Pump suction supply is available. (YES) (6 psig)
* Position MDAFW Pump LOCAL/REMOTE Switch to LOCAL. Attempt to reclose any tripped breakers:
* Position MDAFW Pump LOCAL/REMOTE Switch to LOCAL.
* Depress the MDAFW Pump local STOP pushbutton . BOP
Attempt to reclose any tripped breakers:
BOP
* Depress the MDAFW Pump local STOP pushbutton .
* Depress the MDAFW Pump local START pushbutton .
* 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.)
* Check MDAFW Pump started. (YES)
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
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)
Continuous Action Step BOP 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)
Verify AFW HOR DISCH Valves - OPEN BOP (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
                                                                                            ~~~~~1 Event


== Description:==
== Description:==
 
Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time     I  Position II                         Applicant's Actions or Behavior BOP         Check AFW flow to S/Gs - GREATER THAN 300 GPM. (YES)
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
The Chief Examiner may terminate the scenario anytime after AFW flow has been established to at least one SIG.
* CVC-387, Excess LTDN Stop -Closed (YES)
NOTE:                       The following are Supplement L steps.
* HIC-137, Excess LTDN FLOW-Controller at 0% (YES) Verify FW Isolation Valves -CLOSED (YES)
Verify Containment Isolation Phase A Valves - Closed (NO)
* FRVs
RO/BOP (Instrument Air PCV-1716 to CV is open.)
* FRV Bypass Valves RO/BOP
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 RO/BOP
* FRV Bypass Valves
* V2-6A, FW HOR SECTION
* V2-6A, FW HOR SECTION
* V2-6B, 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.)
* V2-6C, FW HOR SECTION RO/BOP         Verify Both FW Pumps - TRIPPED (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 41 of _4_5 ___ '""'1 Event
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
_6_ _ _ _ _ Page          41  of _4_5_ _ _'""'
Op Test No.:
                - - Scenario #     4     Event #                                                   1 Event


== Description:==
== 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)
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)
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-1 RO/BOP
* HVH-2
* HVH-2
* HVH-3
* HVH-3
* HVH-4 Verify IVSW System -INITIATED (YES) RO/BOP
* HVH-4 Verify IVSW System - INITIATED (YES)
RO/BOP
* IVSWS VA PCV-1922A
* 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
* 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 #     6                Page   42 of   45
                  --                                       -----                            ---------11 Event


== Description:==
== 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 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


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
Appendix D                               Operator Action                                       Form ES-D-2
-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
_6.____ _ _ _ Page          43 of _4_5_ _ __,
-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
Op Test No.:
                - - Scenario #           4       Event #
1 Event


== Description:==
== Description:==
Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time      I  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.
At MCC-5, open breaker AUX BUILDING SUPPLY FAN, HVS-1 RO/BOP (CMPT- 7 J)
Check SW Header Pressure AND Transition To Steps Indicated By The Table Below:
SW PRESSURE CONDITION                            STEP RO/BOP          LESS    TI:L~N    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


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.
Appendix D                               Operator Action                                     Form ES-D-2 Op Test No.:
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
                  - - Scenario #         4     Event #     6
                                                          ~~~~-
Page   44 of   45
                                                                                            ~~~~___.I Event


== Description:==
== 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)
Dispatch an operator to locally perform Attachment 1, Throttling CCW RO/BOP 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


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.
ILC-11-1 NRC SCENARIO 4 TURNOVER SHEET POWER LEVEL:           75% EOL Core Burnup:           15697 MWD/MTU EFPD:                  448 EFPD Boron:                  132 PPM Xenon:                EQ Xenon Tavg:                  567.5&deg;F Bank D Rods            169 Steps EQUIPMENT UNDER CLEARANCE:
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&deg;F 169 Steps EQUIPMENT UNDER CLEARANCE:  
* "A" CCW Pump OOS and Breaker Racked Out EQUIPMENT STATUS:
* "A" CCW Pump OOS and Breaker Racked Out EQUIPMENT STATUS:
* 5 GPO primary to secondary leakage into S/G "C"
* 5 GPO primary to secondary leakage into S/G "C"
* Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.
* Currently thunderstorm watch is in effect for Darlington and Chesterfield counties.
INSTRUCTIONS FOR THE WATCH:
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:
* Awaiting Engineering personnel to install vibration monitoring equipment to allow starting Heater Drain Pump "A".
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}}
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 Resin B           #NAME?       PSIG       In Service                                           PPM         In Service   Date 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 Rad        Current                                  INUE Value RCS Leakage             0.00     Unidentified Monitor    Setpoint Alert Value 200X 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}}

Latest revision as of 09:48, 5 February 2020

Initial Exam 2011-301 Draft Simulator Scenarios
ML15223B321
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Issue date: 05/21/2015
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Text

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 .
  • 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 PZR Pressure Transmitter PT-444 fails HIGH (TS) SRO 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 .
  • "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:

  • 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 (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 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 (LT-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:

  • 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 1E-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 .
  • 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 .
  • 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 Reduce turbine load IAW OP-105 to 85%.

(N) BOP, SRO 2 (I) BOP, SRO Feedwater Flow Transmitter FT-477 fails LOW (TS) SRO 3 (I) RO, SRO PZR Pressure Transmitter PT-444 fails HIGH (TS) SRO 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 over-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: Reduce turbine load IAW OP-105 to 85%.

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

  • OWP-026, FWF-2
  • PATH-1
  • FoldoutA
  • Supplement G
  • PATH-2

Appendix D Operator Action Form ES-D-2 Op Test No.: - - - - - Page 5 of _3_5_ _ _-11 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.

Notify RC that increased radiation levels are expected in the CV Pump SRO Bays and in Pipe Alley due to normal shutdown crud bursts.

Monitor the highest operable Power Range Channel and the highest RO operable Intermediate Range Channel on NR-45.

IF Reactor Engineering has not provided technical guidance, THEN SRO/RO 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 .

IF a significant change in RCS Boron concentration occurs, THEN RO 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.

DETERMINE the amount of Boric Acid to add to the RCS and RO 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 BORATE.

RO SET YIC-113, BORIC ACID TOTALIZER to desired quantity.

IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN RO 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
  • TAVG increases
  • Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:

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

~~~~~I 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.

MONITOR parameters for the expected change in reactivity AND RO 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:

BOP

  • Place the EH Turbine Control in the desired position: IMP IN .
  • 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 Maintain Gland Seal Steam Header Pressure in the normal operating BOP band (3 to 6 psig) (Pl-4004, Pl-1382 or ERFIS Pt GSP2095A)

WHEN Reactor Power is <90% as indicated on NR-45, THEN CHECK RO 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

-- ~~~~~ ~~~~~1 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 Recognizes FT-477 has failed and performs Immediate Actions for BOP AOP-025, RTGB INSTRUMENT FAILURE.

Immediate Action Step:

BOP Place the affected FRV (FCV-478 for SIG "A") in MAN.

Immediate Action Step:

BOP Restore Affected SIG Level To Between 39% And 52%.

Enters AOP-025, RTGB INSTRUMENT FAILURE, Section E, and SRO verifies Immediate Actions.

RO/BOP Make PA announcement for entry into AOP-025.

Place the affected SIG Feed Flow Selector Switch to the alternate BOP 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

_2_ _ _ _ _ Page 10 of _3_5_ _ __,

Op Test No.:

- - Scenario # 1 Event #

1 Event

Description:

FT-477 fails LOW Time II Position II Aoolicant's Actions or Behavior Reviews, briefs and directs taking FT-477 instrument out of service SRO 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

_2_ _ _ _ _ Page 11 of _3_5_ _ ____,

Op Test No.:

- - Scenario# Event#

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.)

Recognizes that PT-444 is failed high and performs Immediate Actions RO 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.

Enters AOP-025, RTGB INSTRUMENT FAILURE, Section C and SRO 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 .

Verify PCV-455C in AUTO. (Crew may decide to leave PCV-455C in RO the CLOSE position since it failed to close.)

Verify Selector Switch PM-444 is selected to operable channel:

RO

  • 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

_4_,..._s.......6

_ _ _ Page 14 of _3_5_ _ _-l Op Test No.:

- - Scenario # 1 Event #

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.

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

SRO Evaluate plant conditions and Go to Section A.

Continuous Action Step:

RO 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.

Check Plant status in Mode 1, and direct tripping the Reactor, tripping SRO RCP "A" and then going to PATH-1.

Attempts to trip the reactor using the reactor trip pushbutton above TR-RO 408. Candidate identifies that reactor does not trip.

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2

_4_._,5_,_,_6_ _ _ Page 15 of _3_5_ _ _ _

Op Test No.:

-- Scenario # 1 Event #

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 Attempts to trip the reactor using the reactor trip pushbutton below the RO 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.

Immediate Action Step:

RO Reactor Tripped. (YES)

Immediate Action Step:

BOP Turbine Tripped. (YES)

Immediate Action Step:

BOP E-1 AND E-2 energized (YES)

Immediate Action Step:

RO SI initiated. (NO)

Immediate Action Step:

RO 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 WHEN at least 3 minutes have elapsed since tripping the affected RCP, RO/BOP Task THEN Close Seal leakoff valve for RCP "A". (CVC-303A)

The Seal leakoff valve should be closed within 5 minutes of stopping RO/BOP the affected RCP.

RO/BOP Check SI - Actuated. (YES)

Check APP-002-F7, INSTR AIR HOR LO PRESS - EXTINGUISHED RO/BOP (YES)

RO/BOP Reset Safety Injection RO/BOP Reset Containment Isolation Phase A Momentarily place IA PCV-1716, INSTRUMENT AIR ISO TO CV RO/BOP 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

~~~~~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 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)

Inform SRO to Implement EALs and Refer to Technical Specifications RO/BOP 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

_4_._,s....._6_ _ _ Page Op Test No.:

- - Scenario# 1 Event# 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.

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

S/G"B"

  • V2-16B. AFW HOR DISCH
c. WHEN desired, THEN Perform Supplement G, Steam Generator Isolation Indications Available:

"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)

If Additional Feedwater is required, THEN Start SDAFW Pump BOP (RunninQ)

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

-- s~n~o# 1 &e~# _5_a_n_d6

_ _ _ Page 20 of _3.;..;;5_ _ _-1 1

Event

Description:

SIG "B" Tube Rupture and Both SI Pumps do not Auto Start Time I 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

- V12-8, CONT PURGE VALVE RO

- 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 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

-- ~---- ~---~I Event

Description:

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

Continuous Action Step RO CV pressure remained below 10 psig (YES)

BOP Automatic steam line isolation initiated (NO)

BOP Automatic Steam Line Isolation Required (NO)

Locally open the breaker for HVS-1 at MCC-5 within 60 minutes of SI BOP 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 RCP Thermal Barrier Cooling Water Hi or Lo flow alarms illuminated RO (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)

Dump Steam using Condenser Dumps or Steam Line PORVs to BOP 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

_5_a_n_d_6_ _ _ Page 23 of _3_5_ _ _~

Op Test No.:

1 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

@IF PZR Spray Valves Fail to Close THEN Stop RCP Supplying Failed RO Valve

@IF Aux Spray Valves Fail to Close, THEN Close LCV-460A AND B RO AND HCV-121 RO At least one RCP running (YES)

At least one SI Pump Running (YES) (Both SI pumps had to be RO 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.

Control AFW Flow to Maintain SIG Levels between 8% and 50%.

BOP (SIGs A and C)

BOP Any SIG with uncontrolled level increase. (YES - "B" SIG)

SRO Transition to Path-2, Entry Point J Reset SPDS AND Initiate Monitoring of Critical Safety Function Status RO Trees Open Foldout C CREW

{No steps apply)

When Below 10-10 AMPS, THEN Energize Source Range Detectors RO 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 Verify Ruptured Steam Line PORV Setpoint at 1035 PSIG using BOP 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 IF MDAFW Pump is not Available, THEN Maintain at least One SIG BOP 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 Locally Close Warmup Steam Supply From Ruptured SIG to SDAFW BOP 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 Isolate Feed Flow to Any Ruptured SIG that is Faulted Unless Needed BOP 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.

Control Feed Flow to Maintain Intact SIG Level Between 8% [18%]

BOP 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 I 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)

Open At Least One PORV Block Unless Closed to Isolate an Open RO 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 Establish Instrument Air to CV. IF Compressor not Running, THEN RO 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

-- ~~~~~ ~~~~~I 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

- V2-68, FW HOR SECTION (Not needed if FRV and FRV BYP BOP 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 (oF)

RO/BOP 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)

Verify T-AVG less Than 543°F AND Block T-AVG SI Signal Prior to RO 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)

WHEN CET is less than Required the steps begin again.

RO 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.

IF PZR Spray Valves fail to close, THEN Stop RCP supplying failed RO valve.

IF Aux Spray Valve Fails to close, THEN Close CVC-460A and BAND RO 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 - FAULTED (NO).

Continuous Action Step BOP 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

_s_____

Op Test No.:

- - Scenario # 1 Event # Page 33 of _3_5_ _ __,

1 Event

Description:

SIG "B" Tube Rupture (Supplement G)

Time II Position II Applicant's Actions or Behavior Verify S/G B Slowdown AND Slowdown Sample Valve Status Light BOP 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.

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

At MCC-9, verify V2-14B closed AND open breaker V2-14B, SDAFW PUMP TO SIG B (CMPT- 1C)

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 I 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.

Dispatch An Operator To Close GS-36, MANUAL GLAND STEAM BOP DUMP.

End of Supplement G Steps Appendix D NUREG-1021, Rev. 9, Supp. 1

ILC-11-1 NRC SCENARIO 1 TURNOVER SHEET POWER LEVEL: 100% RTP Core Burnup: 9000 MWD/MTU EFPD: 257 EFPD Boron: 745 PPM Xenon: EQXenon Tavg: 575.9°F Bank D Rods 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 IResin 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 ~350 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 Rad Current NUEValue RCS Leakage 0.00 Unidentified Monitor Setpoint Alert Value 200X 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 .
  • "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:

  • 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 (LT-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
  • "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: CCW Pump B Trips on Overcurrent and CCW Pump C fails to auto start Event 4: Condenser Vacuum Leakage Event 5: Load Reduction due to Condenser Vacuum lowering Event 6: Steam Line Break on SIG B inside the CV EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

  • OWP-005, CVC-19
  • OWP-033, FSP-1
  • PATH-1
  • Foldout A
  • FRP-P.1

Appendix D Operator Action Form ES-D-2 Op Test No.: - - - - - Page 5 of _2_7_ _ __, 1 Event

Description:

VCT Level Transmitter LT-112 fails HIGH Time i Position Ii Aoolicant's Actions or Behavior BOOTH OPERATOR: When directed, insert Event 1, VCT Level Transmitter LT-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 LT-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 LT-112 from ERFIS .
  • Check VCT Level Indicators - Oscillating Level Deviation Observed (NO)
  • Check deviation between LT-112 and LT-115 greater than 8" (13%) (YES)

RO Check LT-115 failed. (NO)

RO Check LT-112 failed. (YES)

RO Check LT-112 - Failed High (YES)

CAUTION: With NO operator action, LT-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

~~~~~I Event

Description:

VCT Level Transmitter LT-112 fails HIGH Time II Position I 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 COMPLETED (YES)

RO Place LCV-115A in AUTO position.

SRO Contact l&C to repair failed channel.

CREW Make PA Announcement for Procedure Entry Continuous Action Step RO 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)

Verify Charging and Letdown flows are normal for plant conditions RO (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_ _ _-11 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.: 2

~~~~~

Page 8 of 27

~~~~~I Event

Description:

PT-446 fails LOW Time I 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 Determines PT-446 failed low and performs Immediate Actions of Crew AOP-025.

Immediate Action Step:

BOP Check Turbine Load Reduction in progress or has occurred.

(NO, Go TO Step 3)

Immediate Action Step:

BOP 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.

Determines AOP-025, RTGB INSTRUMENT FAILURE and enters SRO 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

_2_ _ _ _ _ Page 9 of _2_7_ _ _....

Op Test No.:

- - Scenario # 2 Event #

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.

Place the First Stage Pressure Selector Switch to the alternate BOP 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 TAVG 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 # 3

~~~~~

Page 11 of 27

~~~~~1 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.

IF the running CCW Pump has tripped, THEN VERIFY Standby CCW RO Pump STARTED (RO manually starts "C" CCW Pump)

Dispatches an operator to check breaker and Current Limiter Fuses.

RO (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

-- ~~~~~ ~~~~~1 Event

Description:

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

SRO/RO 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 2 _3_ _ _ _ _ Page 13 of _2_7_ _ _~

Op Test No.:

- - Scenario# Event#

1 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 Immediate Action BOP Check Circulating Water Pump - Any Tripped (NO)

SRO Enters AOP-012 and verifies immediate actions.

BOP Check Condenser Vacuum previously established. (YES)

Verify all available Vacuum Pumps Running. (YES)

BOP 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 Continuous Action Step:

BOP Check Pl-1310 AND Pl-1311 - INCREASING (YES)

Reduce Turbine Load using Attachment 2, as necessary, to maintain CREW 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.)

Attachment 2 - Turbine Load Reduction BOP Check Turbine Control Mode - Automatic (YES)

BOP Depress the IMP IN Pushbutton BOP Set the Desired Load in the setter Set the Desired Load Rate (1 %/min) (Higher load rate may be chosen BOP 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

-- ~---- ----~I 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.

DETERMINE the amount of Boric Acid to add to the RCS and RO 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 BORATE.

RO SET YIC-113, BORIC ACID TOTALIZER to desired quantity.

IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN RO 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
  • TAVG increases
  • Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:

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

-- ~~~~- ~~~~~I 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 RCS MAKEUP SYSTEM switch in the STOP position:

RO 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.

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

END OF BORATION STEPS BOP Check Condenser Nitrogen Addition in service (YES)

Dispatch an Operator to Close NS-143, N2 Injection to Condenser BOP 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 # 4 and 5

~~~~~

Page 18 of 27

~~~~~I 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.

Direct measurement of condenser lnleakage using OP-504, Condenser SRO/BOP 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 Operator Action Form ES-D-2 Op Test No.:

- - Scenario # 2 Event # 6, 7,8,9, 10 Page 19 of 27

;1 Event

Description:

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 Applicant's Actions or Behavior BOOTH OPERATOR: 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)

Immediate Action Step BOP Turbine tripped (YES)

Immediate Action Step BOP E1 & E2 energized (YES)

Immediate Action Step RO SI initiated (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 2 Event # 6, 7, 8,9, 10 Page 20 of _ 27_ _ ____,I Event

Description:

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 i 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 FAULTED 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 Operator Action Form ES-0-2 Op Test No.:

- - Scenario# 2 Event# 6, 7,8,9, 10 Page 21 of

1 27 Event

Description:

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)

If Additional Feedwater is required, THEN Start SDAFW Pump BOP (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 Operator Action Form ES-D-2 Op Test No.:

- - Scenario # 2 Event # 6, 7,8,9, 10 Page 22 of _2_7_ _ _~

1 Event

Description:

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 i 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

- V12-8, CONT PURGE VALVE RO

- 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 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)

Continuous Action Step RO CV pressure remained below 10 psig (NO)

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 6, 7,8,9, 10 Page 23 of _2_7_ _ _-1 1

Event

Description:

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 I 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 Task1 (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.}

Verify Approximately 12 GPM Spray Additive Tank Flow (RO will RO 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 Locally Open Breaker for HVS-1, At MCC-5 Compartment 7J within 60 BOP minutes of SI Initiation Booth Operator: After 3 min. delay open the breaker for HVS-1, MCC-5, Compartment 7J.

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 Operator Action Form ES-D-2 Op Test No.: 2

- - Scenario# Event# 6, 7,8,9, 10 Page 24 of _ 27_ _ ___,I Event

Description:

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%

RCP Thermal Barrier Cooling Water Hi or Lo flow alarms illuminated RO (YES)

RO At Least one Charging Pump Running (YES)

RO Greater than 5 inches Thermal Barrier ~P 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 If RCS cooldown continues and is not due to SI flow, then close all BOP MSIVs and MSIV bypasses RO PZR PORVs Closed (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: 6, 7,8,9, 10 Page 25 of _ 27_ _ __,I Event

Description:

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 I 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)

Reset SPDS AND Initiate Monitoring of Critical Safety Function Status RO Trees Transition to FRP-P.1, Response to Imminent Pressurized Thermal SRO Shock, due to an ORANGE on CSF-4.

Continuous Action Step Check CST Level - Less than 10% (NO)

BOP 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 Operator Action Form ES-D-2 Op Test No.: 2 Event# 6, 7,8,9, 10 Page 26 of _2_7_ _ _ _

- - Scenario# 1 Event

Description:

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 Applicant's Actions or Behavior BOP Verify Steam Dumps Closed (YES)

RO Check RHR System Aligned for core cooling (NO)

BOP Check S/G Status - Any Intact (NO)

BOP Verify closed all MSIVs and MSIV BYPs. (YES)

Verify closed all Steam Shutoffs to the SDAFW Pump.

BOP Close V1-8A, -8B, -8C Critical Maintain feed flow to each SIG between 80 gpm and 90 gpm Task BOP 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 CREW enters FRP-H.1, Response to Loss of Secondary Heat Sink.

Check Total Feed Flow - LESS THAN 300 GPM DUE TO BOP OPERATOR ACTION (YES)

SRO 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: 50% RTP Core Burnup: 150 MWD/MTU EFPD: 4.3 EFPD Boron: 1277 PPM Xenon: EQ Xenon Tavg: 560°F Bank D Rods 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 IPressure PSIG Status A #NAME? PSIG On cover DEMINERALIZERS Resin B #NAME? PSIG In Service PPM In Service Date 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 Rad Current NUE Value RCS Leakage 0.00 Unidentified Monitor Setpoint Alert Value 200X 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:

  • 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 1E-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 Form ES-D-2 ILC-11-1 NRC SCENARIO 3 SIMULATOR SETUP IC/SETUP:

  • IC-803, SCN: 008_NRC_3
  • 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: HVE-3 (CV Iodine Removal Fan) Trips Event 2: Low Pressure Letdown PT-145 fails LOW Event 3: Place Excess Letdown in Service Event 4: Service Water Booster Pump "B" Trips Event 4A: PT-455, PZR Pressure Transmitter, fails HIGH Event 5: Degraded Voltage on System Grid Event 8: Restoration of Charging Pump I Seal Cooling Event 9: RHR Pump "A" trips EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

  • APP-01 O-C6
  • APP-002-AS, 88, ca, D8
  • APP-003-AS
  • APP-036-E3
  • PATH-1
  • Foldout A
  • Foldout B
  • FRP-P.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.

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

BOP Check Breaker at MCC-5, CMPT 8B, for tripped condition. (YES)

BOP Check damper positions. (YES - DOME VENT)

IF the breaker has tripped, THEN ATTEMPT Reclosure once (YES -

BOP 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.

Per APP-001-E6, IF PCV-145 is malfunctioning, THEN REFER to RO 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 Place Excess Letdown In Service Using Attachment 2, Placing Excess RO 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 , LTON 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 LTON HX. (YES)

RO/BOP Position CVC-389, EXCESS LTON DIV, to the RCDT Position RO/BOP Open CVC-387, EXCESS LTON STOP SLOWLY OPEN HCV-137, EXCESS LTDN FLOW not to exceed RO/BOP 195°F as indicated on Tl-139, EXCESS LTON 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.

RO/BOP

  • Access Calorimetric on ERFIS by typing CALO
  • 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 LTON 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.: _2_a_n_d_3_ _ _ Page 8 of _2_6_ _ _--1

- - Scenario # 3 Event #

1 Event

Description:

PT-145 fails LOW Time I 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 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)

SRO 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

_4_ _ _ _ _ Page 9 of _2_6_ _ __,

Op Test No.:

- - Scenario # 3 Event # 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)

Announces starting SWBP "A" and then starts Service Water Booster BOP Pump "A" Dispatches AO to check local indication of "A" SWBP and breaker for BOP "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 failure and ITS 3.6.6, Condition D, Two Containment Cooling Trains SRO 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 Acknowledge APP-003-AS, PZR PROT HI PRESS, and enters APP-RO 003-AS Identifies that PT-455 has failed high. Recommends removing the RO failed channel from service using OWP-029 IAW APP-003-AS.

Makes copy of OWP-029, PPT-1, Pressurizer Pressure Channel PT-SRO 455, and reviews/briefs with the Crew.

Crew determines that OWP-029 would trip OT/':,.T LOOP 1 bistables.

Since OT/':,.T LOOP 3 bistables are already tripped due to N-43 being SRO 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 D and H are applicable. ITS 3.3.2, Condition D is the most limiting SRO 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 />.

Contacts WCC SRO and/or Maintenance to initiate a W/R to SRO 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

_5_ _ _ _ _ Page 11 of _2_6_ _ _....,

Op Test No.:

- - Scenario # 3 Event #

1 Event

Description:

Degraded Voltage on System Grid Time I 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)

Continuous Action Step RO/BOP 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 Check ANY of the following Diesel Generators Paralleled to the Grid.

BOP (NO)

BOP Check Turbine Status - On Line (NO)

Check with Load Dispatcher - Adequate Voltage Support is Presently BOP 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 Declare off-site power Inoperable and implement the required actions SRO 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:

  • Normal supply breaker opens (YES)

BOP

  • 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 # 6

~~~~~

Page 13 of 26

~~~~~I Event

Description:

LOCA when Reactor Trips.

Time I 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.)

Immediate Action Step BOP Turbine tripped (YES)

Immediate Action Step BOP E1 & E2 energized (YES)

Immediate Action Step RO 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 IF a Phase A Isolation signals occurs, THEN verify:

RO

  • CVC-387, EXCESS LTDN 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 WD-1722, RCDT PUMP DISCHARGE LINE AUTO ISOLATION Critical RO Task 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

~~~~~1 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)

If Additional Feedwater is required, THEN Start SDAFW Pump (NO)

BOP (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 .

Verify both RHR pumps running (NO)

Critical 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 and B did not open automatically.)

RO 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

~~~~~1 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)*

  • (If the crew did not depress the Containment Isolation Pushbuttons RO 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

- V12-8, CONT PURGE VALVE RO

- 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 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.)

Continuous Action Step RO CV pressure remained below 10 psig (NO)

RO Verify CV Spray Initiated. (YES)

Verify ALL CV Spray Pumps Running with Valves Properly Aligned RO (YES)

Verify Approximately 12 GPM Spray Additive Tank Flow. (Manually throttles Sl-845C from RTGB.)

RO (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)

Locally open the breaker for HVS-1 at MCC-5 within 60 minutes of SI BOP 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

_6_ _ _ _ _ Page of _2_6_ _ __,

Op Test No.:

- - Scenario # 3 Event # 18 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%

RCP Thermal Barrier Cooling Water Hi or Lo flow alarms illuminated RO (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 in less than 15 minutes.

Critical RO Task 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 RCS temperature stable at or trending to 547°F (NO)

RO (No RCPs are running. Candidate should use T/Cs.)

RCS temperature greater than 547°F (NO)

RO (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.

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)

CV Pressure Normal (NO)

RO

  • 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 Check CST Level - Less than 10% (NO)

BOP 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 I 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.

Open Foldout B.

CREW (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)

Control AFW Flow to Maintain S/G Levels between 8% [18%] and BOP 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

_6_ _ _ _ _ Page 22 of _2_6_ _ _...,

Op Test No.:

- - Scenario # 3 Event #

1 Event

Description:

LOCA when Reactor Trips.

Time Position A licant's Actions or Behavior RO PZR PORVs Closed (YES)

Open at least one PORV Block unless Closed to Isolate an Open PZR RO 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)

IF Adequate diesel capacity not available to run charging pumps BOP THEN shed non-essential loads using Supplement F.

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2

_6_ _ _ _ _ Page 23 of _2_6_ _ _-1 Op Test No.:

- - Scenario # 3 Event #

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 Check Emergency Coolant Recirculation Capability - Restored (NO)

RO If Emergency Coolant Recirculation is restored, THEN perform Step

2. Go to Step 3.

Foldout pages are not applicable during performance of this CREW procedure.

Continuous Action Step Check suction source to any of the following pumps - LOST (NO)

RO SI Pumps, RHR Pumps, CV Spray Pumps If suction source lost to pump(s), THEN perform Step 5. Go to Step 6.

Check Emergency Recirculation Equipment-AVAILABLE USING RO SUPPLEMENT D (NO)

RNO - Try to restore at least one train while continuing with this RO procedure.

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.:

- - Scenario# 3 Event# 6

~~~~~

Page 25 of 26

~~~~--11 Event

Description:

LOCA when Reactor Trips.

Time II Position I Applicant's Actions or Behavior Verify the following CV RECIRC FANs - RUNNING (YES)

RO 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: 1E-8 amps Core Burnup: 150 MWD/MTU EFPD: 4.3 EFPD Boron: 1531 PPM Xenon: EQ Xenon Tavg: 548°F Bank D Rods 100 Steps EQUIPMENT UNDER CLEARANCE:

  • "A" CCW Pump OOS and Breaker Racked Out EQUIPMENT STATUS:
  • Reactor is at 1E-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 Resin B #NAME? PSIG In Service PPM In Service Date 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 ~350 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 Rad Current NUE Value RCS Leakage 0.00 Unidentified Monitor Setpoint Alert Value 200X 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 .
  • 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 MDAFW and SDAFW Pumps Trip when Start Signal BOP 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 Form ES-D-2 ILC-11-1 NRC SCENARIO 4 SIMULATOR SETUP IC/SETUP:

  • IC-804, SCN: 008_NRC_4
  • 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: Loss of Instrument Bus #1 Event 2: PZR Pressure Controller PC-444J Range Shifts Event 3: Steam Pressure Channel PT-485 fails LOW Event 4: Loss of Cooling to the Auxiliary Transformer Event 5: Load Reduction to 50%

Event 6: Feedwater Header Rupture EXPECTED PROCEDURE FLOWPATH OR COPIES NEEDED:

  • OWP-025, SGP-8
  • APP-046
  • PATH-1
  • Foldout A
  • FRP-H.1
  • Supplement L 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 i 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 Immediate Action Step BOP Verify S/G(s) Maintained At Program Level Immediate Action Step RO 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:

Check Auto Makeup, Boration OR Dilution - In Progress (NO) (Auto RO 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.)

Control Charging and Letdown Flow to Maintain PZR Level.

RO (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 ENERGIZED FROM THE 4160V SUSSES (YES)

Continuous Action Step RO/BOP 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)

Continuous Action Step BOP 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 ENERGIZED (YES)

Continuous Action Step BOP Check Emergency Susses E-1 AND E 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 Check Status Of Turbine:

BOP

  • 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

~~~~~I 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)

Continuous Action Step BOP 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)

Restore Normal Letdown Using Attachment 15, Restoration of Normal RO Letdown.

NOTE: The following are the steps to restore normal letdown using Attachment 15 of AOP-024.

Normal charging flow through the Regenerative Heat Exchanger is in RO/BOP 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

-~~~--11 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, LTON LINE STOP
  • LCV-460B, LTON 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)

Check Pressurizer level is greater than OR equal to program level.

RO/BOP (YES)

IF desired, THEN PLACE TCV-143, VCT/DEMIN. DIVERSION, in the RO/BOP VCT position.

RO/BOP PLACE PC-145, PRESSURE, in MANUAL.

SET PC-145 to throttle PCV-145 to 45% to 55% open to ensure the RO/BOP 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

-- ~~~~~ ~~~~~1 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 LTON LINE STOP to OPEN.
  • PLACE LTON 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 on RTGB instrument Pl-121 LESS THAN 2500 psig, ADJUST RO/BOP charging pump speed to the expected letdown flow to be established in the next step.

OPEN one LTON ORIFICE valve:

RO/BOP 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.

IF TCV-143 was selected to the VCT, THEN Position TCV-143 as RO/BOP 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

~~~~~1 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 2500 psig, ADJUST charging pump speed to meet flow RO/BOP 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 LTON 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.

Notify RC that letdown flow has been restored and the affected areas RO/BOP 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 .

Check PZR PRV Safety Acoustic Monitor Lights - ILLUMINATED RO (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_ _ _--11 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 1O 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 />.

Check Status of EDGs - START SIGNAL RECEIVED (NO)

BOP

  • 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 3.8.7, Condition A, One AC Instrument Bus power source inoperable - Restore AC Instrument Bus Power Source to SRO 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

~I Event

Description:

Loss of Instrument Bus #1 Time II Position II Aoolicant's Actions or Behavior Check Annunciator APP-005-A3, PR DROP ROD - ILLUMINATED RO (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)

Reset AMSAC TROUB/BYP Alarm by depressing the System Reset RO 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

_2_ _ _ _ _ Page 16 of _4_5_ _ __,

Op Test No.:

- - Scenario # 4 Event #

1 Event

Description:

PZR Pressure Controller PC-444J Range Shifts Time I 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 Immediate Action Step RO 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 Continuous Action Step RO Check PZR Pressure - UNDER OPERATOR CONTROL (YES)

Continuous Action Step RO Check Pressurizer Pressure Transmitter PT-444 OR PT-445 Failed.

(NO)

Check PC-444J, PZR PRESS - OPERATING 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 I 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

  • TRM 3.4, PZR Spray t:,.T (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.)

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

~I 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)

Immediate Action Step BOP 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 Channel Below:

BOP 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.: 3

~~~~~

Page 19 of 45

~~~~~1 Event

Description:

Steam Pressure Transmitter PT-485 fails LOW Time I 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 DELETE INPUT FROM CALORIMETRIC page.

BOP 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 Trip the Bistables for PT-485 BOP

{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.: 4 _3_ _ _ _ _ Page 20 of _4_5_ _ ____,

- - Scenario# Event#

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 Steam Line Pressure - Condition D: Place channel in trip within 6 SRO hours 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)

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.:

-- Sren~o# 4 Ew~# _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.

Operator reports Alarm 46-11, Loss of Normal 480Vac Power BOP 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)

NOTE: The APP-046 alarms in the table below are prioritized by SRO 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

_4_a_n_d5

_ _ _ Page 22 of _4_5_ _ _ _ _

Op Test No.:

- - Scenario # 4 Event # 1 Event

Description:

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

Time II Position II Aoolicant's Actions or Behavior Alarm 46-11, Loss of Normal 480Vac Power Source (18G) (Step BOP 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.

Dispatch an Operator to Observe the Status of the Fans and BOP 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)

Check Status of 480 Volt Bus 3 - POWER LOST (NO)

BOP Go to Step 11 Check Status of MCC POWER LOST (NO)

BOP Go to Step 17 BOP Check Status of MCC-4, Breaker 4BR - TRIPPED (YES)

Attempt to Reset and Close MCC-4, Breaker 4BR One Time.

BOP (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 Determine If Trip Required As Follows:

BOP

- Check time elapsed since loss of all cooling - Greater than 30 min. (NO)

IF the Auxiliary Transformer is NOT unloaded within 30 minutes, SRO 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.

Reduce power to less than 50% using Attachment 4, Turbine Crew 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.

DETERMINE the amount of Boric Acid to add to the RCS and RO 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

~~~~~I Event

Description:

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

Tim Position A licant's Actions or Behavior IF desired, THEN PLACE FCV-113A, BORIC ACID FLOW, in MAN RO 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
  • TAVG increases
  • Boric Acid addition exceeds the desired value WHEN the desired amount of Boric Acid has been added, THEN verify the following:

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.

MONITOR parameters for the expected change in reactivity AND RO 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 Insert key into Startup Transf synchroscope switch AND turn switch to BOP 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 # 4 and 5 Page 27 of 45

-- ~~~~~ ~~~~~1 Event

Description:

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

A licant's Actions or Behavior WHEN the synchroscope come up to the 12 o'clock position, THEN BOP close START-UP TO 4KV BUS 2 BKR 52/12 WHEN breaker 52/12 indicates closed, THEN return switch to the mid-BOP position AND verify UNIT AUX TO 4KV BUS 1 BKR 52/7 has opened.

Insert key into 4KV TIES synchroscope switch AND turn switch to BUS BOP 3 & 4 position.

WHEN synchroscope comes up to 12 o'clock position, THEN close BOP 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)

IF APP-046 Alarms are present than have not been addressed, THEN SRO 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

1 45 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 I 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 Operators note the lowering SIG Levels and FRVs full open and RO/BOP recommend tripping the Reactor.

Immediate Action Step:

RO 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.

Immediate Action Step:

BOP E-1 AND E-2 energized. (YES)

Immediate Action Step:

RO 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

_6_ _ _ _ _ Page 30 of _4_5_____

Op Test No.:

- - Scenario # 4 Event #

11 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time I 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 (YES)

BOP 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

_6_ _ _ _ _ Page 31 of _4_5_ _ _-1 Op Test No.:

- - Scenario # 4 Event #

1 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time I Position II APPiicant's Actions or Behavior BOP Verify both FW pumps are tripped. (YES)

Verify both MDAFW pumps are running. (NO) (Unable to start from BOP RTGB.)

If additional Feedwater is required, start the SDAFW pump. (NO, BOP Pump started but tripped)

WCC SRO or AO may be dispatched to investigate the cause of the SRO 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 # 6 Page 32 of 45

-- ~~~~~ ~~~~~1 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

- V12-8, CONT PURGE VALVE RO

- 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 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 # 6

~~---

Page 33 of 45

~I 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)

Locally open breaker for HVS-1 at MCC-5 CMPT ?J within 60 min of SRO SI Initiation.

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

RCS pressure> 1350 psig. [1250 psig] (YES)

(May be NO if manual turbine run back not started immediately or if the RO 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 Reset SPDS and Initiate monitoring of Critical Safety Function Status RO Trees Transition to FRP-H.1, RESPONSE TO LOSS OF SECONDARY SRO HEAT SINK.

Check Total Feed Flow less than 300 GPM due to operator action.

BOP (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.

@ Consult Plant Operations Staff to determine if RHR should be SRO 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

@ WHEN RCS pressure less than 375 psig [350 psig], THEN go to RO 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.

Continuous Action Step:

BOP 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.

Steps 31 through 35 must be performed quickly in order to establish SRO RCS heat removal by RCS bleed and feed.

RO Depress the Initiate Safety Injection Pushbutton RO Verify SI Pumps - At least one running (YES)

At the RTGB, verify SI Valves for at least one flow path - ALIGNED RO FOR COLD LEG INJECTION (YES)

Verify APP-002-F?, INSTR AIR HOR LO PRESS - EXTINGUISHED RO (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2 Op Test No.: _6_ _ _ _ _ Page 36 of _4_5_ _ __,

- - Scenario # 4 Event #

1 Event

Description:

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

Momentarily place the Containment Spray Key Switch to the RO 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.: 6

~~~~~

Page 37 of 45

~~~~~I Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time I Position II Applicant's Actions or Behavior RO Reset Phase A and Phase B RO Check Status of PCV-1716- IN OVERRIDE POSITION (YES)

Momentarily place IA PCV-1716 Switch to RESET AND return to RO AUTO.

BOP Check E-1 OR E 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)

Continuous Action Step RO Check RWST Level - LESS THAN 27% (NO)

Continuous Action Step RO Check CV Pressure - HAS INCREASED TO GREATER THAN 10 PSIG (NO)

Continuous Action Step RO Check CV Pressure - LESS THAN 4 PSIG (YES)

Appendix D NUREG-1021, Rev. 9, Supp. 1

Appendix D Operator Action Form ES-D-2

_6_ _ _ _ _ Page 38 of _4_5_ _ __,

Op Test No.:

- - Scenario # 4 Event #

1 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time I Position II APPiicant's Actions or Behavior RO Stop the operating CV Spray Pump (None running)

Verify CV SPRAY PUMP DISCH Valves - CLOSED RO (Sl-880A,B,C,D) (YES)

Verify Spray Additive Tank Discharge Valves - CLOSED RO (Sl-845A,B) (YES)

Continuous Action Step BOP Check CST level - Greater Than 10% (YES)

BOP Check AFW Lines - INTACT (YES)

BOP Check AFW Pump Breakers - Tripped (YES)

Position the MDAFW Pump Control Switch to the STOP position and BOP to the START 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 I 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:

BOP

  • Depress the MDAFW Pump local STOP pushbutton .
  • 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)

Continuous Action Step BOP 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)

Verify AFW HOR DISCH Valves - OPEN BOP (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

~~~~~1 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time I 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.

Verify Containment Isolation Phase A Valves - Closed (NO)

RO/BOP (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)

  • FRV Bypass Valves
  • 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

_6_ _ _ _ _ Page 41 of _4_5_ _ _'""'

Op Test No.:

- - Scenario # 4 Event # 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

Appendix D Operator Action Form ES-D-2 Op Test No.: Scenario # 4 Event # 6 Page 42 of 45

-- ----- ---------11 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 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

_6.____ _ _ _ Page 43 of _4_5_ _ __,

Op Test No.:

- - Scenario # 4 Event #

1 Event

Description:

Feedwater Header Rupture, Steam Dumps Fail Open and MSIVs Fail to Close Time I 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.

At MCC-5, open breaker AUX BUILDING SUPPLY FAN, HVS-1 RO/BOP (CMPT- 7 J)

Check SW Header Pressure AND Transition To Steps Indicated By The Table Below:

SW PRESSURE CONDITION STEP RO/BOP LESS TI:L~N 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 # 6

~~~~-

Page 44 of 45

~~~~___.I 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)

Dispatch an operator to locally perform Attachment 1, Throttling CCW RO/BOP 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: 75% EOL Core Burnup: 15697 MWD/MTU EFPD: 448 EFPD Boron: 132 PPM Xenon: EQ Xenon Tavg: 567.5°F Bank D Rods 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 Resin B #NAME? PSIG In Service PPM In Service Date 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 Rad Current INUE Value RCS Leakage 0.00 Unidentified Monitor Setpoint Alert Value 200X 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

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