ML17198D304
| ML17198D304 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/03/2017 |
| From: | NRC/RGN-III |
| To: | Detroit Edison, Co |
| Shared Package | |
| ML17061A781 | List: |
| References | |
| Download: ML17198D304 (39) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: __Fermi 2_________
Scenario No.:
______1_______ Op-Test No.: __2017-1__
Examiners:
Operators:
Initial Conditions: IC-20, MOL, 100% Rx. Power Turnover: The plant has been operating at 100 % Reactor power. #5 Circ Water Pump is OOS for motor replacement. Expected return to service is two weeks.
Event No.
Malf. No.
Event Type*
Event Description 1
C51MF0003 I(ATC)
I(SRO)
APRM Downscale - Bypass APRM 3 - TS 3.3.2.1 Tracking 2
NGADN3021C 002TVSP C(BOP)
C(SRO)
- 2 TCV Unitized Actuator Failure (Oil Leak) - 4D2 3
R(ATC)
R(SRO)
Reduce Reactor Power < 93% to lock down #2 TCV 4
N(BOP)
N(SRO)
Lock Down #2 TCV - 23.109, Main Turbine 5
BADCB21N09 6ATVSP I(BOP)
I(SRO)
Cond. Pressure Instrument Failure CRS enters TS 3 3.6.1 6
C93RF0001 C97MF1087 NA Earthquake - AOP 20.000.01 - AOP Actions 7
E51MF0010 EOPRF0024 EOPRF0025 C(BOP)
C(SRO)
RCIC Steam Leak. Auto Isolation Fails. Manual isolation Successful.
R11MF3471 M(All)
Loss of 65D - AOP 20.300.65D - Mode Switch to S/D EOP 29.100.01 Sheet 1 - RPV Control 9
E41MF0009 C(All)
Auto Start Failure of HPCI. Manual Start Successful (CT-2)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: __Fermi 2_________
Scenario No.:
______1_______ Op-Test No.: __2017-1__
Examiners:
Operators:
Initial Conditions: IC-20, MOL, 100% Rx. Power Event No.
Malf. No.
Event Type*
Event Description 10 B31MF0066 M(All)
Leak in drywell - EOP 29.100.01 Sheet 2 - Primary Containment Control Inhibit ADS (CT -3)
Emergency Depressurization EOP 29.100.01 Sheet 3 -
Open 5 SRV before -25 (CT-4) 11 E21RF0005 C(ATC)
C(SRO)
Auto Start Failure - Div. 1 Core Spray 12 E11MF0016 C(ATC)
C(SRO)
Containment Spray Valve Failure E1150-F016A Torus Cooling and Sprays Spray Drywell (CT 5)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Op-Test No.: 2017-1 Scenario No.:
1 Event No.: N/A Event
Description:
Overview Initial Conditions:
The plant has been operating at 100 % Reactor power. #5 Circ Water Pump is OOS for motor replacement. Expected return to service is two weeks.
The objectives of this scenario are to:
- 1.
Recognize, respond to, and take the required actions for an instrument / equipment failures requiring the use of operator and Tech Spec actions.
- 2.
Recognize and respond to an APRM Downscale.
- 3.
Recognize and respond to an Cond. Pressure Instrument Failure
- 4.
Recognize and respond to a Unitized Actuator Failure.
- 5.
Recognize and respond to a Seismic Event.
- 6.
Recognize and respond to a RCIC Steam Leak
- 7.
Recognize and respond to Loss of Bus 65D
- 8.
Recognize and respond to LOCA conditions.
- 9.
Operate RHR in all modes for Primary Containment Control.
- 10.
Execute steps in Primary Containment Control and operate the RHR System to control Drywell and Torus Temperature and Pressure.
- 11.
Execute the steps of RPV Control for level (L) and pressure (P).
- 12.
Direct and supervise the Shift team during Normal, Abnormal, and Emergency operations.
The crew will be required to respond to the following order of events:
APRM Downscale - Bypass APRM 3 Failure #2 TCV Unitized Actuator - Oil leak Reactor Power reduction to <93% Power Cond. Pressure Instrument Failure Earthquake RCIC Steam Leak Loss of Bus 65D/Auto Start Failure of HPCI Leak in Drywell
Op-Test No.: 2017-1 Scenario No.: 1 Event No.: 1 Event
Description:
APRM downscale Time Position Applicant's Actions or Behavior
+2 min MALF: C51MF0003, APRM Downscale SRO Respond to 3D98 Enter TS 3.3.1.1 Tracking Enter TR 3.3.2.1 Tracking Direct APRM 3 bypassed ATC Respond to 3D98 Report APRM 3 reading downscale Dispatch operator to Relay Room to check APRM 3 ROLE PLAY: Report APRM 3 reading downscale, nothing else abnormal.
Bypass APRM 3 Dispatch operator to Relay Room to check APRM 3 ROLE PLAY: Report APRM 3 Blue Bypass light is on.
BOP Monitors plant conditions.
May direct operator to Relay Room to Check APRM 3 ROLE PLAY: Report APRM 3 reading downscale, nothing else abnormal.
Op-Test No.: 2017-1 Scenario No.: 1 Event No.: 2,4__
Event
Description:
- 2 HPCV Unitized Actuator Failure, Lock Down #2 TCV - 23.109, Main Turbine Time Position Applicant's Actions or Behavior
+8m MALF: NG12N3021LSEN236BTFCLOSE #2 TCV UA LL Alarm SRO Respond to 4D2, Unitized Actuator Throttle Vlv Fault.
Briefs crew on actions for UA Failure.
Briefs Power Reduction to lock-down UA.
Directs lockdown of #2 HPCV ATC Monitors plant conditions.
BOP Respond to 4D2, Unitized Actuator Throttle Vlv Fault.
Direct operator to investigate #2 HPCV Unitized Actuator.
ROLE PLAY: Report leak inside UA enclosure. Cannot see where leak is coming from, oil spray obscuring window. No leakage outside UA enclosure. Standing by in low dose area. If crew shuts off pump before role play, dont report oil spray in enclosure. If update requested, report conditions unchanged.
Perform #2 HPCV lock-down per 23.109 Section 7.1.
Raise Load Demand till it stops rising with Speed/Load raise push-button.
Place Steam Valve On Load Test Mode Select switch to 10%
Depress SELECT Pushbutton for #2 HPCV.
Open N30-39-F613, HP Turb Loop B Line Drain Valve.
Depress VALVE TEST pushbutton.
Depress TRIP SOLENOID A and TRIP SOLENOID B pushbuttons.
Depress CANCEL TEST pushbutton Perform #2 HPCV UA shutdown per 23.110.
o Place UA to be shutdown in OFF.
o Directs rounds operator to close TBCCW Valve for shutdown UA (P4300-F091E).
o ROLE PLAY: Rounds operator reports TBCCW valve to #2 HPCV Unitized Actuator closed (P4300-F091E) May ask for pressure, report glass still has oil on it, cannot read right now.
Depress Select/locked Closed pushbutton.
Depress VALVE TEST pushbutton.
Depress TRIP RESET pushbutton.
Reset Half scram by cycling reset
Op-Test No.: 2017-1 Scenario No.: 1 Event No.: 3 Event
Description:
Power Reduction to <93%
Time Position Applicant's Actions or Behavior
+9m SRO Directs power reduction to <91.5% per SOP 23.109 prerequisite for closing #2 HPCV.
Monitors power reduction to <91.5%.
Plant announcement of power reduction.
ATC Monitors plant conditions.
Lower reactor power by reduction of reactor recirculation pump speed per SOP 23.138.01.
Reports power less than 91.5% when completed.
May request rounds operator monitor Recirc oil temperatures.
BOP Monitors plant conditions.
Brief lockdown of #2 HPCV per 23.109.
Brief Shutdown of Unitized Actuator per 23.110.
Op-Test No.: 2017-1 Scenario No.: 1 Event No.:_5 Event
Description:
Cond. Pressure Instrument Failure Time Position Applicant's Actions or Behavior
+30m MALF: BADCB21N096ATVSP Cond Press Inst Fail SRO Responds to alarms (1D39).
Review 23.601 for failed instrument.
Enters TS 3 3.6.1 Contact Tagging Center and/or Work Control for assistance with failed instrument.
Brief TS Action.
BOP Responds to alarms (1D39).
Monitors Condenser Pressure.
Review 23.601 for failed instrument.
Dispatch operator to Testability.
ROLE PLAY: When dispatched to Testability Cabinets, wait about 3 min, and report B21-N696A indicates upscale with RED TRIP light ON.
Op-Test No.:2017-1 Scenario No.:
1 Event No.: 6_
Event
Description:
Seismic Event Time Position Applicant's Actions or Behavior T+35m MALF: C97MF1087 6D69 - Seismic System Event/Trouble MALF: C93RF0001 Earthquake Sound SRO Responds to Seismic Event and enters 20.000.01, Acts of Nature.
Briefs Crew on Seismic event.
Makes Hi-Com announcement of event.
Directs Monitoring the following for abnormal values:
o Reactor Vessel Level.
o Reactor Vessel Pressure.
o Reactor Power.
o Drywell Pressure.
o Torus Water Level.
o Drywell Unidentified Leakage.
o Process Radiation Monitors.
o Spent Fuel Pool Water Level.
o Spent Fuel Pool Temperature.
Directs seismic event actions for Condition AC.
May contact offsite agencies to confirm Earthquake.
ROLE PLAY: if contacted as offsite agency, confirm earthquake at 0.02G horizontal and 0.02G vertical.
ATC Monitors Power, Pressure and Level as directed by SRO for the seismic event.
May dispatch operators to perform visual inspection of plant systems.
Op-Test No.:2017-1 Scenario No.:
1 Event No.: 6_
Event
Description:
Seismic Event Time Position Applicant's Actions or Behavior BOP Responds to alarm 6D69, Seismic Event/Trouble.
Dispatches an operator to the relay room to check status of Seismic Panel indications (RR H11-P831) per 23.612.
ROLE PLAY: Operator reports from the relay room that seismic event has occurred with an indication of 0.02 G Horizontal and 0.02G Vertical - red ERROR LED is OFF.
Reports Relay Room indications of 0.02 G. horizontal and 0.02G vertical to CRS.
NOTE: The following actions may be briefed but do not have to be completed prior to proceeding with next event.
Starts all RHRSW MDCT Fans and checks for proper running indications.
ROLE PLAY: When directed, report satisfactory operation of MDCT fans following start.
Directs rounds operator to reset D1 and D2 CCHVAC Purge Compressors.
ROLE PLAY: When directed, after about 5 min, report D1 and D2 CCHVAC Purge Compressors are reset.
May dispatch operators to perform visual inspection of plant systems.
NOTE: Perform role play just prior to initiating next event.
ROLE PLAY: As part of seismic walk down prior to triggering steam leak, Rounds Operator report 1 foot steam plume from packing gland area of E5150-F045.
Op-Test No.:2017-1 Scenario No.:
1 Event No.: 7 Event
Description:
RCIC Steam Leak.
Time Position Applicant's Actions or Behavior T+45m MALF: E51MF0010, RCIC Steam Leak SRO Respond to 1D66, 1D70, 16D27, 8D46 and 17D46.
Enter 29.100.01 Sheet 5.
Determine rising room temperature in RCIC/Core Spray room and RB pressure High.
Enter 29.100.01 Sheet 5, Secondary Containment Control.
May direct RCIC isolation.
Validate isolation of leak by monitoring for lowering room temperatures.
Orders Tech Spec actions for TS 3.5.3 RCIC ATC Monitors plant conditions.
BOP Respond to 1D66, 1D70, 16D27, 8D46 and 17D46.
Monitor RCIC system and determine RCIC Automatic isolation did NOT occur IF room temperature exceeds 154°.
Manually isolate RCIC System by closing E5150-F007 and E5150-F008. (CT-1)
Validate isolation of leak by monitoring for lowering room temperatures.
Perform Tech Spec actions for TS 3.5.3 RCIC
Op-Test No.:2017-1 Scenario No.:
1 Event No.: 8 Event
Description:
Loss of 65D Time Position Applicant's Actions or Behavior T+55m MALF: R11MF3471 Loss of Bus 65D SRO Directs Mode Switch to Shutdown per AOP 20.300.65D.
Directs Scram reports from ATC and BOP.
Enters EOP 29.100.01, Sheet 1, RPV Control.
Establishes Level band of 173 to 214 inches and pressure band of 900 to 1050 psig.
ATC Places Reactor Mode Switch in Shutdown due to loss of all high pressure Feed or CRS direction from AOP.
Provides Scram report.
Verifies all control rods are fully inserted.
May dispatch operator to 65D Bus in BOP Swgr Room to investigate.
ROLE PLAY: If dispatched to 65D Bus, after about 5 min, report 64 Ground Fault Relay has actuated.
Op-Test No.:2017-1 Scenario No.:
1 Event No.: 9 Event
Description:
Loss of High Pressure Feed Sources, HPCI manual start Time Position Applicant's Actions or Behavior T+55m MALF: E41MF0009, HPCI autostart Failure SRO May direct ATC to perform Scram Procedure AOP 20.000.21.
Expands Level band to 0 to 214 inches.
Briefs crew on options and intended course of action May order attempt to restart Center HFP.
Directs start of SLC Pump.
Directs start of HPCI.(CT-2).
ATC May report HPCI Auto Start Failure.
Starts A or B SLC Pump.
May attempt to restart Center HFP.
Manually Starts HPCI to raise level (CT-2).
BOP Reports SBFW unavailable due to F001 failure.
Reports HPCI Auto Start failure.
Manually Starts HPCI to raise level. (CT-2).
May attempt to restart Center HFP.
May dispatch operator to N2103-F001 valve.
May dispatch operator to N2103-F001 power supply (2PC-1-5A) to turn it off, to allow manual operation of SBFW.
ROLE PLAY: If dispatched to N2103 F001 valve, after about 5 min, report unable to manually open valve ROLE PLAY: If dispatched to 2PC-1-5A, after about 5 min, turn off 2PC-1-5A, and report it is off.
ROLE PLAY: If ordered to manually open N2103-F001 report it will not open and request mechanical maintenance assistance.
Op-Test No.:2017-1 Scenario No.:
1 Event No.: 10,11 Event
Description:
Recirculation Loop Rupture, ED, Level recovery Time Position Applicant's Actions or Behavior T+65m MALF: B31MF0066, Recirc Loop Rupture A MALF: E21RF0005, Auto Start Failure - Div. 1 CS SRO Enters EOP 29.100.01 Sheet 2, Primary Containment Control.
Establishes Level band of 173 to 214 inches, expands band to 0 to 214 inches.
May order attempt to restart Center HFP.
Conduct EOP Brief.
Directs ADS inhibited (CT-3).
Orders second CRD pump started.
Orders SLC injection.
Conduct Brief for Emergency Depressurization.
May order DW Pneumatics bypassed and restored.
Enter 29.100.01, Sheet 3, Emergency Depressurization.
At TAF and before -25, Direct 5 ADS SRVs opened. (CT-4)
Directs placing RHR in Torus Cooling and Torus Spray.
Directs level band of 173 to 214 following ED.
ATC Reports rising Drywell Pressure.
May attempt to restart Center HFP.
May start second CRD pump started.
May perform SLC injection.
Coordinate with BOP to shutdown/operate LP Pumps to restore and maintain RPV water level 173 to 214 inches.
Places RHR in Torus Cooling and Torus Spray as directed.
May bypass and restore DW pneumatics.
ROLE PLAY If dispatched, after 5 min report, report D 1(D2)
Radiation Monitor Sample Pump in service.
BOP Reports rising Drywell Pressure.
May attempt to restart Center HFP.
Reports unable to maintain RPV level with available high pressure sources.
May start second CRD pump started.
May perform SLC injection.
Reports Division 1 Core Spray Pumps failed to start, manually starts/align Division 1 Core Spray Pumps.
Inhibits ADS. (CT-3)
Opens 5 SRVs as directed.(CT-4)
Coordinate with ATC to shutdown/operate LP Pumps to restore and maintain RPV water level 173 to 214 inches.
May bypass and restore DW pneumatics.
ROLE PLAY If dispatched, after 5 min report, report D 1(D2)
Radiation Monitor Sample Pump in service.
Op-Test No.:2017-1 Scenario No.:
1 Event No.: 12 Event
Description:
Containment Cooling and Failures Time Position Applicant's Actions or Behavior T+75m MALF: E11MF0016/17 - Containment Spray Valve Failure E1150-F16A/B SRO Directs placing RHR in Torus Cooling and Torus Spray. (May order E1150-F010 closed)
When Torus Pressure reached 9 psig directs Drywell Spray after Recirc Pumps verified OFF and stopping all Drywell Cooling Fans.
Directs securing Drywell and Torus Sprays before Drywell and Torus Pressure reach 0 psig.
Monitors DWSIL curve prior to spraying drywell.
Directs Drywell Spray on Division 1 or 2 RHR. (CT-5)
ATC Verify or Shutdown the Reactor Recirc pumps.
Shuts down all drywell cooling fans.
Places RHR Div 1or 2 in Torus Cooling and Torus Sprays.
o Place Containment Spray Mode Select Switch in MANUAL.
o Unlock and Open E1150-F028A or B.
o Start 1 RHR Pump.
o Open E1150-F024 A or B.
o Open E1150-F027 A or B.
o Partially open E1150-F068 A or B.
o Start both RHRSW Pumps.
o Fully open E1150-F068 A or B.
Places RHR Div 1or 2 in Drywell Spray. (CT-5) o Place or verify Containment Spray Mode Select Switch in MANUAL.
o Initiate Drywell Spray when directed.
o Open E1150-F021 A or B.
o Start second RHR pump.
o Unlock and Open E1150-F016 A or B.
Reports Failure of E1150-F016 A or B Secures Torus and Drywell Sprays before Drywell and Torus pressure reach 0 psig.
ROLE PLAY If dispatched to E1150-F16A breaker, after 3 min report, acrid burned insulation smell near MCC (72C-3A-5D). If dispatched to E1150-F16B breaker, after 3 min report, acrid burned insulation smell near MCC (72F-4A-3AR).
ROLE PLAY If dispatched, after 3 min report, report D 1(D2)
Radiation Monitor Sample Pump in service.
Op-Test No.:2017-1 Scenario No.:
1 Event No.: 12 Event
Description:
Containment Cooling and Failures BOP Verify or Shutdown the Reactor Recirc pumps.
Shuts down all drywell cooling fans.
Places RHR Div 1or 2 in Torus Cooling and Torus Sprays.
o Place Containment Spray Mode Select Switch in MANUAL.
o Unlock and Open E1150-F028A or B.
o Start 1 RHR Pump.
o Open E1150-F024 A or B.
o Open E1150-F027 A or B.
o Partially open E1150-F068 A or B.
o Start both RHRSW Pumps.
o Fully open E1150-F068 A or B.
Places RHR Div 1or 2 in Drywell Spray. (CT-5) o Place or verify Containment Spray Mode Select Switch in MANUAL.
o Initiate Drywell Spray when directed.
o Open E1150-F021 A or B.
o Start second RHR pump.
o Unlock and Open E1150-F016 A or B.
Reports Failure of E1150-F016 A or B Secures Torus and Drywell Sprays before Drywell and Torus pressure reach 0 psig.
ROLE PLAY If dispatched to E1150-F16A breaker, after 3 min report, acrid burned insulation smell near MCC (72C-3A-5D). If dispatched to E1150-F16B breaker, after 3 min report, acrid burned insulation smell near MCC (72F-4A-3AR).
ROLE PLAY If dispatched, after 3 min report, report D 1(D2)
Radiation Monitor Sample Pump in service.
Appendix D Scenario Outline Form ES-D-1 Facility: _Fermi 2______________ Scenario No.:
____2______
Op-Test No.:_2017-1_
Examiners:
Operators:
Initial Conditions: IC-20, MOL, 100% Rx. Power.
Turnover: The plant has been operating at 100 % Reactor power for the last 185 days. Center Recirc MG Cooling fan is OOS for motor replacement. Expected return to service is one week.
Event No.
Malf. No.
Event Type*
Event Description 1
N(BOP)
N(SRO)
Shift RBCCW Pumps 2
B21MF004 I(BOP)
I(SRO)
Drywell Pressure Transmitter Failure TS 3.3.1.1, 3.3.6.1, 3.3.6.2, 3.3.7.1( Drywell Pressure Instrumentation) 3 C11MF1106 C(ATC)
C(SRO)
CR 58-39 Individual SCRAM from half scram during Drywell Pressure Transmitter Failure and blown fuse. Disarm CR due to badly damaged fuse clip.
4 TAXMP817_
A096NOISE TACET41C01 2TVSP C(BOP)
C(SRO)
High Vibration North Recirculation MG Cooling Fan (Field report) with flashing amps.
Trip North Recirculation MG Cooling Fan (Manual or Automatic) 5 R(SRO)
Direct manual Trip of North Rx Recirculation Pump (or automatic if temp limit reached)
AOP Entry 20.138.01 Recirculation Pump Trip - TS Entry 3.4.1 AOP Entry 20.107.02 Loss feed water Heating R(ATC)
Reduce power with CRAM array and monitor for thermal hydraulic instabilities. (in exit region of power to flow) (CT-1)
- 6.
B31MF0057 C71MF0006 C11MF0001 M(All)
Trip of South Rx Recirculation Pump (due to collateral damage from cooling fan failure). Mode Switch to Shut down.. Manual RPS Fails to Cause a Scram (Total Scram Failure) and All Rods Stuck, inhibit ADS(CT-
- 2)
- 7.
C41RF0008 C41RF0009 C(ATC)
C(SRO)
SRO directs SLC injection. ATC Injects SLC. SLC Squib valve fails to fire Crew Injects SLC (CT 3) 8 ALL SRO directs 29.ESP.03. ATC manually inserts Control Rods per 29.ESP.03 (CT 4) SRO directs 29.ESP.10. ATC resets ARI to perform scram-reset-scram per 29.ESP.03. All rods insert when ARI is re-initiated twice 9
ALL SRO directs Terminate and Prevent. BOP performs Terminate and Prevent for Level to lower RPV level <114 inches. Maintain RPV level 50 to 100 inches (CT 5).
10 E51MF0002 C(BOP)
C(SRO)
RCIC isolates on high exhaust diaphragm pressure. BOP utilizes alternate systems to maintain level.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Op-Test No.: 2017-1 Scenario No.:
2 Event No.: N/A Event
Description:
Overview Initial Conditions:
The plant has been operating at 100 % Reactor power for the last 185 days. Center Recirc MG Cooling fan is OOS for motor replacement. Expected return to service is one weeks. Plans for the shift are to maintain full power.
The objectives of this scenario are to:
Recognize, respond to, and take the required actions for an instrument / equipment failures requiring the use of operator and Tech Spec actions.
Shift RBCCW Pumps.
Recognize and respond Scram of one control rod.
Recognize and respond to a Drywell Pressure Instument Failure.
Recognize and respond to imminent equipment failure.
Recognize and respond trip of Reactor Recirculation Pump Execute steps of RPV Control - ATWS Sheet 1A.
Execute steps of PC Control - 29.100.01 Sheet 2.
Recognize and respond to failures in SLC system.
Manually insert Control Rods per 29.ESP.03.
Recognize and respond to isolation of RCIC.
The crew will be required to respond to the following order of events:
Shift RBCCW Pumps Drywell Pressure Instrument Failure (TS 3.3.1.1,3.3.6.1,3.3.6.2, 3.3.7.1) with Scram of one Rod High Vibration North Recirculation MG Cooling Fan Manual trip of North Reactor Recirculation pump.
Spurious trip of South Reactor Recirculation pump.
Mode Switch to SHUTDOWN, (ATWS)
SLC Squib valve fails to fire RCIC isolates on start at L2
Op-Test No.: 2017-2 Scenario No.: 2 Event No.: 1 Event
Description:
Shift RBCCW Pumps Time Position Applicant's Actions or Behavior
+0 min SRO Directs BOP to shift RBCCW Pumps for scheduled maintenance on the center pump.
BOP Shifts RBCCW Pumps in accordance with 23.127, Section 6.1:
- 1. Directs Rounds Operator to place T4100-B033, Battery Rooms AC Unit, switch in OFF.
ROLE PLAY: After ~1 minute, RB Rounds reports T4100-B033 switch is in OFF.
- 2. Closes P4400-F613, Div 1 EECW To Batt Rms A/C Iso Vlv (H11-P808).
NOTE: 2D119, RBCCW PUMPS DIFF PRESS HIGH/LOW, may alarm during pump shift.
- 5. Starts the South RBCCW Pump.
- 6. Stops the Center RBCCW Pump.
- 7. If necessary reviews ARP 2D119.
- 8. Verifies P42-F403, RBCCW DP Control Vlv, is maintaining proper differential pressure by verifying annunciators 2D100 and 2D104 are clear.
- 9. Opens P4400-F613, Div 1 EECW To Batt Rms A/C Iso Vlv (H11-P808).
- 10. Direct the Rounds Operator to place T4100-B033, Battery Rooms AC Unit, switch in AUTO, and to verify RPS MG Set doors are closed.
ROLE PLAY: After ~1 minute, RB Rounds reports T4100-B033 switch is in AUTO.
Periodically monitors RBCCW system temperatures and pressures to ensure proper system operation.
Op-Test No.: 2017-2 Scenario No.: 2 Event No.: 2__
Event
Description:
Drywell Pressure Instrumentation Failure Time Position Applicant's Actions or Behavior
+15 min MALF: B21MF0004 Drywell Pressure Transmitter Failure SRO
- Respond to Half Scram (High Drywell Pressure)(3D73, 3D80, 3D81, 3D85)
Review 23.601 for failed instrument.
Enter TS 3.3.1.1, 3.3.6.1, 3.3.6.2,3.3.7.1 9 (Drywell Pressure Instrumentation)
Contract Tagging Center and/or Work Control for assistance with failed instrument.
Brief crew on TS impact.
ATC Respond to Half Scram (High Drywell Pressure)(3D73, 3D80, 3D81, 3D85)
Monitors Power, Pressure and Level May dispatch operator to Testability Cabinets to check drywell pressure instrumentation.
ROLE PLAY: When dispatched to Testability, after about 3 min, report C71-N650A reading upscale, all other channels reading normal.
BOP Respond to Half Scram (High Drywell Pressure)(3D73, 3D80, 3D81, 3D85)
Monitor drywell pressure Review 23.601 for failed instrument.
Will dispatch operator to Testability Cabinets to check drywell pressure instrumentation.
ROLE PLAY: When dispatched to Testability, after about 3 min, report C71-N650A reading upscale, all other channels reading normal.
Op-Test No.: 2017-1 Scenario No.: 2 Event No.:
3 Event
Description:
CR 58-39 Individual SCRAM Time Position Applicant's Actions or Behavior T+15m MALF: C11MF1106 Scram CR 58-39 SRO Brief actions for individual rod scram.
Contact SNE about individual rod scram.
Direct CR 58-39 disarmed after fuse clip damage reported.
Direct closing C11-F112 ATC Monitors plant conditions.
Reports half scram, rod drift alarm and individual rod scram CR 58-39.
Dispatch operator to check HCU 58-39.
ROLE PLAY: Rounds operator reports both Scram Valves open at HCU 58-39. Nothing else is abnormal.
Dispatch operator to check fuses for CR 58-39.
ROLE PLAY: Report blown fuse and severely damaged and charred fuse clips on B side for 58-39.
Directs rounds operator to disarm CR 58-39 per 23.106.
Direct closing C11-F112
Op-Test No.: 2017-2 Scenario No.: 2 Event No.: 4 Event
Description:
High Vibration North Recirculation MG Cooling Fan Time Position Applicant's Actions or Behavior T+30m MALF:
TAXMP817_A096NOISE - Center fan amp meter noise TACET41C012TVSP - Center Fan Trip SRO Directs Trip of North Recirculation MG Cooling Fan Brief Trip of Reactor Recirculation Pump A (AOP 20.138.01)
ATC Respond to 3D142, RECIRC SYS A MG DRIVE SET AIR TEMP HIGH BOP ROLE PLAY: Reactor Building Rounds reports via radio There is severe vibration on the N. Recirc MG Set Cooling Fan. Recommend tripping the fan Respond to annunciators, 17D72 and17D49.
Trip North Recirculation MG Cooling Fan
Op-Test No.: 2017-2 Scenario No.: 2 Event No.: 5 Event
Description:
Trip North Rx Recirculation Pump Time Position Applicant's Actions or Behavior T+32m SRO Direct manual Trip of North Rx Recirculation Pump.
Enter AOP 20.138.01 Hi-Com announcements of events.
Conducts AOP brief (if not already done).
Directs ATC to perform 20.138.01, Condition A Actions.
Directs BOP to verify feedwater heating changes are due to the power change IAW ARP 5D85, Loss of Heater Drains.
Directs the notification or notifies Station Nuclear Engineer (SNE) of the unplanned power change and requests his assistance.
ROLE PLAY: SNE states he will come to the control room as soon as possible. Until he gets there, increase monitoring for thermal-hydraulic instabilities.
Notifies RP and Chemistry of power change >15%. (Condition E)
Reviews TS 3.4.1, requirements for SLO. (4 hrs for adjustment of RPS set points and Thermal Limits for SLO)
Notifies Work Control personnel of RRMG A problem, requests a Condition Assessment Resolution Document (CARD) be written, protected system signs be posted for RRMG B, and review of Plan of the Day for activities that might affect current plant conditions.
ATC When directed Trips RRMG A.
Monitors reactor power and flow conditions, on the power/flow map.
20.138.01 Immediate Action (IC) Insert the Cram Array when in the exit region. (CT-1)
Monitors for THI when in exit region.
When directed, performs AOP 20.138.01, Condition A Actions: (May peer check or perform actions)
Place Recirc A & B Flow Limiter 2/3 Defeat Switch in DEFEAT.
Increase core monitoring for instability (24.000.01 Attachment 34b).
Close B3105-F031A (B) for tripped RR Pump.
After 5 minutes fully open B3105-F031A (B).
Maintain RR MG Set speed as per 23.138.01 Inform SNE of unplanned power change.
BOP Responds to annunciator 5D85, LOSS OF HEATER DRAINS Reports loss of Heater Drains due to Recirc Pump Trip.
Reviews AOP 20.107.02, Loss of Feedwater Heating, Enclosure A.
Reports Feedwater temperature change is consistent with power change.
Peer checks closure of B3105-F031A.
Peer checks re-opening of B3105-F031A.
When directed, performs AOP 20.138.01, Condition A Actions: (May peer check or perform actions)
Place Recirc A & B Flow Limiter 2/3 Defeat Switch in DEFEAT.
Increase core monitoring for instability (24.000.01 Attachment 34b).
Close B3105-F031A (B) for tripped RR Pump.
After 5 minutes fully open B3105-F031A (B).
Maintain RR MG Set speed as per 23.138.01 Inform SNE of unplanned power change.
Op-Test No.: 2017-2 Scenario No.: 2 Event No.: 6 Event
Description:
Trip of South Rx Recirculation Pump, with ATWS Time Position Applicant's Actions or Behavior T+45m MALF: B31MF0057 1 SRO
- Acknowledge Mode Switch in Shutdown
- Directs Scram Reports
- Directs ATC to perform FSQ 1 thru 8.
- Directs BOP to confirm isolations and actuations for level as they occur.
- Directs BOP to maintain pressure 900 to 1050 psig. May expand lower end of band due to leak in drywell.
- SRO acknowledges FSQ-1 thru 8 complete.
- SRO acknowledges report on FSQ 1 thru 8 complete and Reactor Power.
- Recognizes trip of South Reactor Recirculation pump.
- Performs Immediate action (20.138.01 IA), places Mode Switch in Shutdown
- Reports Failure to Scram to CRS.
- Performs FSQ 1 thru 8 using Hard Card:
- Reports FSQ 1 thru 8 complete and Reactor Power to CRS.
BOP ROLE PLAY: Reactor Building Rounds reports via radio Small leak from cooling coils of North Recirculation MG Cooling Fan (50 drops per minute).
Debris from the fan imbedded in both RR MG Sets. No obvious problems with the RR MG Sets.
- Verifies isolations and actuations for level as they occur using Hard Card.
- Inhibits ADS ((CT-2))
- Reports ADS inhibited.
- Defeats Drywell Pneumatic Isolation with Keylock Switches on H11-P808 and P817.
- Contacts Tagging Center (Operator outside CR) to perform 29.ESP.11.
- Reports Drywell Pneumatics bypassed and restored and 29.ESP.11 ordered.
ROLE PLAY: About 10 min. after request, install defeats for 29.ESP.11 and report to Control Room that 29.ESP.11 is complete.
Op-Test No.: 2017-2 Scenario No.: 2 Event No.: 7 Event
Description:
SLC Squib valve fails to fire Time Position Applicant's Actions or Behavior T+48 MALF:
C41RF0008 C41RF0009 SRO Directs SLC injection. (CT-3).
Receives report of SLC injection, noting time for injection and SLC Tank level ATC Place key lock for selected SLC pump to run.
After diagnosis, determines Squib did not fire.
Selects other SLC pump. (CT-3)
Verifies proper pump operation and isolation of RWCU.
Marks time of SLC initiation and SLC Tank level.
Reports failure of squib valve to CRS.
Op-Test No.: 2017-2 Scenario No.: 2 Event No.: 8 Event
Description:
Manual Insertion of Control Rods/Scram-Reset-Scram per 29.ESP.03 Time Position Applicant's Actions or Behavior
+49 min SRO Directs ATC to Defeat ARI using 29.ESP.10.
Directs ATC to insert Control Rods using 29.ESP.03.(CT-4)
After all rods in, SRO directs SLC shutdown.
After all rods in, SRO transitions back to 29.100.01 Sheet 1.
ATC Contacts Tagging Center (Operator outside CR) and directs performance of 29.ESP.10.
ROLE PLAY: Tagging Center acknowledges perform 29.ESP.10.
ROLE PLAY: About 10 min. after request, trigger ESP10 Defeats and report to Control Room that 29.ESP.10 is complete.
Using 29.ESP.03, utilizes one or more of the following to attempt to insert Control Rods:
Raise CRD Hydraulic D/P. (section 2.0)
Manual Control Rod Insertion. (section 3.0)
Scram-Reset-Scram. (section 4.0)
Attempts to drift rods using section 2.0:
Place CRD Flow Controller in MANUAL.
Open Flow Control Valve using CRD Flow controller.
Open C1152-F003 to maximize cooling water flow.
Manually inserts Control Rods(CT-4)
Place CRD Flow Controller in MANUAL.
Adjust Flow Controller and C1152-F003 to maintain sufficient D/P for rod motion.
Place the RWM in Bypass.
Close C11-F034 if needed to maintain drive D/P.
Insert the Cram Array.
Insert rods in checkerboard pattern spiraling out from center.
Continue inserting remaining rods spiraling out from center.
Op-Test No.: 2017-2 Scenario No.: 2 Event No.: 8 Event
Description:
Manual Insertion of Control Rods/Scram-Reset-Scram per 29.ESP.03 Time Position Applicant's Actions or Behavior ATC (continue)
Scram Reset and Scram Re-initiation:
o Verify 8 Blue Scram lights are on.
o May re-open C1100-F034 to re-charge accumulators.
o After 29.ESP.10 is complete, reset ARI.
o Verify SDV vent and drain valves are open.
o Allow the SDV to drain (3D94 clear).
o Initiate a manual scram by performing one or both of the following:
Depress four manual scram pushbuttons.
Arm and depress ARI pushbuttons.
o If Rods move inward, repeat.
Observes inward rod movement, resets ARI and waits for 3D94 to clear.
Initiates ARI and again observes inward rod movement (2nd time).
Verifies all rods in with RWM and full core display.
Crew Update: All rods in Shuts down running SLC pump.
Op-Test No.: 2017-2 Scenario No.: 2 Event No.: 9 Event
Description:
Terminate and Prevent/Maintain RPV Water Level Time Position Applicant's Actions or Behavior
+50 min SRO Determines that Terminate and Prevent is required. Crew Update We have met the conditions to Terminate and Prevent for Level Directs BOP to Terminate and Prevent all injection into the RPV with the exception of Boron, CRD and RCIC.
Directs level lowered less than 114 Wide Range. Directs BOP to maintain RPV level 50 to 100 inches. (CT-5)
After all rods in, directs BOP to restore and maintain RPV water level 173 to 214 inches.
BOP Acknowledges order to Terminate and Prevent.
Acknowledges lower RPV level less than 114 inches. Maintain level 50 to 100 inches on Wide Range.
Performs Terminate and Prevent (Hard Card):
- 1. CS Division 1 Pumps to OFF.
- 2. RHR Division 1 Pumps to OFF.
- 3. SBFW Pumps to OFF.
- 4. CS Division 2 Pumps to OFF.
- 5. RHR Division 2 Pumps to OFF.
- 7. Crew Update Lowering RPV Level.
- 8. If RFP Running, lower speed on both RFP in Manual to close FW Check Valves.
- 9. When RPV Level is less than 114 inches, commence feeding with available sources. (CT-5)
Uses FW or SBFW to maintain RPV level 50 to 100 inches. (CT-5)
After rods are all in, restores and maintains RPV level 173 to 214 inches using available systems.
Op-Test No.: 2017-2 Scenario No.: 2 Event No.: 10 Event
Description:
RCIC isolates on start at L2 Time Position Applicant's Actions or Behavior MALF: - E51MF0002
+60 min SRO Acknowledges RCIC Isolation.
May inquire if available sources are adequate to maintain level.
BOP Identifies RCIC has isolated.
Utilizes SBFW or Feedwater to Maintain RPV Level 50 to 100 inches.
(CT-5)
May direct investigation by Rounds Operator for cause of RCIC isolation at Testability Cabinets.
Appendix D Scenario Outline Form ES-D-1 Facility: _Fermi 2______________ Scenario No.:
____3______
Op-Test No.:_2017-1_
Examiners:
Operators:
Initial Conditions: IC-10 MOL 5.6% Rx Power 650 psig Reactor Pressure. N RFP is feeding via the SULCV.
Turnover: Reactor startup is in progress. GOP 22.00.02 Up to step 6.2.24 is complete. Current direction is to continue the GOP by raising pressure, and complete step 6.2.25. Additional crew is being briefed to perform GOP 7.2.1 through 7.2.3 (Preparing Main Turbine for Roll), they will be coming to the control room in about an hour. Diesel Fire Pump is tagged out, due to spurious start earlier today.
An Emergent Issues Team (MWC 18) has been formed and is troubleshooting the Diesel Fire Pump.
Event No.
Malf. No.
Event Type*
Event Description 1
C11RF0398 R(ATC)
R(SRO)
Raise reactor pressure with pressure regulator.
Maintain Bypass valve 15-30% open my withdrawing control rod to increase Reactor Power.
2 C11MF0037 C(ATC)
C(SRO)
Control Rod 02-39 Drift into the core.
3 P41MF0006 C(BOP)
C(SRO)
Trip #2 GSW Pump. Enter AOP 20.131.01 Loss Of General Service Water System. Direct start of standby GSW pump using hard card.
4 N(BOP)
N(SRO)
Shutdown Electric Fire Pump Per SOP 23.501.01 Fire Water Suppression System Enter TR 3.12.2 5
E41MF0007 E41RF0033 C(BOP)
C(SRO)
HPCI Steam Leak (field report). Manual isolation unsuccessful, E4150-F600 Breaker Trips.
AOP 20.000.02 Abnormal Release Of Radioactive Material CRS enter TS, HPCI 6
M(All)
EOP 29.100.01 Sheet 5, Secondary Containment - >MSO Temperature -
HPCI exceeds Max Safe -> Mode Switch to Shutdown (CT 1) 7 P603_A048_1 P603_A048_2 P603_A048_3 P603_A048_4 C(ATC)
C(SRO)
Mode SW failure EOP 29.100.01 Sheet 1 RPV Control 8
TA20TEN206 ZOUT M(All)
Two Areas > MSO Temperature due to HPCI watertight door not closed -
EOP 29.100.01 Sheet 3 - Emergency Depressurization (CT 2) 9 B21MF0030 C(BOP)
C(SRO)
SRV H Failure during ED - Open One other SRV (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Op-Test No.: 2017-1 Scenario No.:
3 Event No.: N/A Event
Description:
Overview Initial Conditions:
IC-10 4% Rx Power 650 psig Reactor Pressure. N RFP is feeding via the SULCV. Reactor startup is in progress. GOP 22.00.02 Up to step 6.2.24 is complete. Current direction is to continue the GOP by raising pressure, and complete step 6.2.25. Additional crew is being briefed to perform GOP 7.2.1 through 7.2.3 (Preparing Main Turbine for Roll), they will be coming to the control room in about an hour. Diesel Fire Pump is tagged out, due to spurious start earlier today. An Emergent Issues Team (MWC 18) has been formed and is troubleshooting the Diesel Fire Pump. Currently on Step 345 of rod pull. STE is logging temperature and pressure as required.
The objectives of this scenario are to:
Recognize, respond to, and take the required actions for an instrument / equipment failures requiring the use of operator and Tech Spec actions.
Raise reactor power using the RMC system.
Recognize, respond to, and take the required actions for Control Rod Drift.
Recognize, respond to, and take the required actions for Trip GSW pump Shutdown Electric Fire Pump.
Recognize, respond to, and take the required actions for steam leak in Secondary Containment.
Recognize, respond to, and take the required actions for SRV failure to operate.
Recognize, respond to, and take the required actions for automatic action not occuring.
The crew will be required to respond to the following order of events:
Raise power ~3%
Respond to Control Rod Drift Trip GSW pump - start Standby GSW pump - Shutdown Electric Fire Pump.
HPCI Steam Leak One Area Exceeds Max Safe - Mode Switch to Shutdown.
Two Areas Exceeds Max Safe - Emergency Depressurize.
Auto Start Failure Div 1 LPCI
Op-Test No.: 2017-1 Scenario No.: 3 Event No.: 1 Event
Description:
Raise reactor pressure with pressure regulator / Control Rods Time Position Applicant's Actions or Behavior Malf - C11MF0398 - Re-initialize NUMAC RWM
+0 min SRO
- Direct increase Reactor Pressure Per the GOP using Pressure Regulator and Control Rods.
- Provide oversite of reactivity change.
- Maintain Bypass valve 15-30% open my withdrawing control rod to increase Reactor Power. Control Rod Withdrawal (23.623)
- Peer checks reactivity manipulations.
Op-Test No.: 2017-1 Scenario No.: 3 Event No.: 2 Event
Description:
Control Rod 02-39 Drift into the core Time Position Applicant's Actions or Behavior
+15 min Malf - C11MF0037 - Control Rod 02-39 Drift into the core ATC Observes Alarm 3D80, Control Rod Drift Alarm.
Announces alarm for CRS.
Identifies rod 02-39 drifting, places the Rod Select Power to ON, and selects rod 02-39.
Reports rod 02-39 drifting in to the core to CRS.
If rod is not fully in, ATC will fully insert using EMER ROD IN.
Monitors critical parameter, second drifting rod.
Coordinate with Rounds Operator to disarm the control rod.
ROLE PLAY: Close C11-F103 and C11-F105 for HCU 02-39.
Delete Malf - C11MF0037.
BOP Act as peer checker for ATC actions.
SRO Acknowledges Alarm 3D80, Control Rod Drift Alarm report.
Announces and enters 20.106.07 Control Rod Drift AOP.
Announces the 20.106.07 Control Rod Drift event over the Hi-Com.
AOP Brief for 20.106.07 Control Rod Drift.
Directs ATC to perform subsequent actions for condition C of 20.106.07.
Reviews 3.1.3, Control Rod Operability, Section 3.1.6, Rod Pattern Control, and Section 3.3.2.1, Control Rod Block Instrumentation.
Conducts a crew brief.
Notifies Work Control personnel of rod 02-39 disarmed, requests a CARD be written, protection tags be hung for C11-F103 and C11-F105, and a review of POD for activities that might affect current plant conditions.
Op-Test No.: 2017-1 Scenario No.: 3 Event No.: 3 Event
Description:
Trip #2 GSW Pump Time Position Applicant's Actions or Behavior
+20 min MALFUNCTION - P41MF0006 - Trip of #2 GSW Pump SRO Acknowledges report of #2 GSW Pump Trip.
Crew Update Entering AOP for Loss of GSW.
Enters AOP 20.131.01, Loss of GSW.
Conducts AOP Brief.
Directs BOP to start available GSW Pump using hard card (may do before brief).
Acknowledges indicated cause of pump trip.
May request follow-up by Tagging Center/WWM.
May direct clearing of 7D72 per the ARP BOP Announces Motor Tripped Alarm 7D72.
Announces Trip of #2 GSW Pump.
Directs Outside Rounds to investigate trip of #2 GSW Pump at pump and breaker.
ROLE PLAY: Outside Rounds Operator acknowledges investigate Trip of Number 2 GSW Pump.
Starts available GSW Pump.
Makes plant announcement for start of GSW Pump.
Contacts Outside Rounds Operator to inform that GSW Pump has been started.
Directs Outside Rounds Operator verifies local lake level and strainer operation.
ROLE PLAY: Outside Rounds reports, Normal strainer operation and no change in lake level.
Monitors GSW pressure to ensure correct system response to pump start.
ROLE PLAY: Outside Rounds reports, Good start on Number ? GSW Pump.
Acknowledges good start on GSW start.
Checks indicated GSW intake level indication.
ROLE PLAY: Outside Rounds reports, 64 Device tripped on Number 2 GSW Pump Breaker.
Reports indicated cause of #2 GSW Pump trip to SRO.
Clears 7D72 per ARP with permission for CRS
Op-Test No.: 2017-1 Scenario No.: 3 Event No.: 4 Event
Description:
Shutdown Electric Fire Pump Per SOP Time Position Applicant's Actions or Behavior
+23 min SRO Directs shutdown of Electric Fire Pump to standby Enters TRM Section TR 3.12.2, Fire Suppression Water System for INOP of Electric Fire pump BOP Directs rounds operator to GSW pump house for placing Electric Fire Pump in standby Place Electric Fire Pump in standby per 23.501.01 Place P8000-C002, Electric Fire Pump, CMC switch in OFF/RESET.
Direct field operator to Push STOP button on Electric Fire Pump Local Panel P80-P415, Electric Fire Pump P.B. Station.
Verify 7D11, ELECTRIC FIRE PUMP LOCAL START, clear.
Verify P41-R809, Fire Protection Header Pressure Indicator (red needle), is greater than 135 psig.
Place P8000-C002, Electric Fire Pump, CMC switch in AUTO.
Op-Test No.: 2017-1 Scenario No.: 3 Event No.: 5 Event
Description:
HPCI Steam Leak Time Position Applicant's Actions or Behavior
+30 min MALF: E41MF0007, HPCI Steam Leak MALF: E41MF0008, Failure E41-F002 MALF: E41RF0033 E41-F600 Breaker Trip SRO ROLE PLAY: Operator was entering area from South East Subbasement.
Loud bang and a cloud of steam. Was unable to close watertight door in to HPCI area. Leaving RB.
Respond to 1D66, 1D70, 16D27 Enter 29.100.01 Sheet 5, Secondary Containment Control Directs Isolation of HPCI Brief Actions for Steam Leak/Scram.
Enter AOP 20.000.02 Abnormal Release of Radioactive material.
May direct RB evacuated BOP Respond to 1D70, 1D66,6D27 Attempt isolation of HPCI Attempt Closure of E4150-F002 Attempt Closure of E4150-F600 Reports failure of HPCI to isolate - E41-F002 and E41-F600 failed to close Dispatch operator to check MCC for E41-F600.(2PB1-1C)
Op-Test No.: 2017-1 Scenario No.: 3 Event No.: 6 Event
Description:
HPCI exceeds Max Safe Time Position Applicant's Actions or Behavior MALF: P603_A048_1 Mode SW forced P603_A048_2 Mode SW forced P603_A048_3 Mode SW forced P603_A048_4 Mode SW forced
+35 min CRS
- Direct Mode Switch to Shutdown prior to MSO Temperature.(CT-1)
- Enter 29.100.01 Sheet 1, RPV Control
- Direct 173 to 214 inches level band and 900 to 1050 psig pressure band
- Provides scram report.
- Maintains level and pressure as directed ATC Places Reactor Mode Switch in Shutdown when directed (CT 1)
Reports failure of Reactor Mode Switch and depresses SCRAM pushbutton causing SCRAM Provides Scram report.
Verifies all control rods are fully inserted.
- Perform actions in AOP 20.000.21
Op-Test No.: 2017-1 Scenario No.: 3 Event No.: 7,8,9 Event
Description:
Two Areas > MSO : Emergency Depressurize Time Position Applicant's Actions or Behavior MALF: B21MF0030 H SRV FAILURE MALF: E21RF0005 CS DIV 1 AUTO START FAIL
+45 min SRO Conduct Brief for Emergency Depressurization.
Acknowledge report of South East Subbasement > MSO Enter 29.100.01, Sheet 3, Emergency Depressurization.
Direct 5 ADS SRVs opened. (CT-2)
Directs placing RHR in Torus Cooling and Torus Spray.
Directs level band of 173 to 214 following ED.
- Coordinate with BOP to shutdown/operate LP Pumps to restore and maintain RPV water level 173 to 214 inches.
- Places RHR in Torus Cooling and Torus Spray as directed.
- ROLE PLAY If dispatched, after 5 min report, report D 1(D2) Radiation Monitor Sample Pump in service.
- Reports rising Drywell Pressure.
- Reports South East Subbasement > MSO
- Coordinate with ATC to shutdown/operate LP Pumps to restore and maintain RPV water level 173 to 214 inches.
- ROLE PLAY If dispatched, after 5 min report, report D 1(D2) Radiation Monitor Sample Pump in service.