ML20356A101
| ML20356A101 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/25/2020 |
| From: | Indiana Michigan Power Co |
| To: | NRC/RGN-III/DRS/OLB |
| Reeser D | |
| Shared Package | |
| ML19121A511 | List: |
| References | |
| Download: ML20356A101 (72) | |
Text
Appendix D Scenario Outline Form ES-D-1 Page 1 of 17 Facility: DC COOK 1 & 2 Scenario No.: NRC2020-1 Op-Test No.: _________
Examiners: ___________________________ Operators:
Initial Conditions: 80 % Power.
Turnover: Restore power to 100% following Turbine Valve testing_____________________________
Critical Tasks: Stabilize SG Level on MPP230 Failure, Manually Actuate SI_____________________
Even t No.
Malf. No.
Event Type*
Event Description 1
N-BOP Swap #1 Control Fluid Pump for #3 Control Fluid Pump 2
R-RO Commence raising Reactor Power to 100%
3 U1_101PW2N C-RO PW Pump Trips \\ Fails to Auto Start 4
MPP230 to 1 over 30 Sec I-BOP TS SG Pressure Channel MPP-230 Fails Low 5
U1_NLP152 to 0%
I-RO TS Pressurizer Level Control Bi-stable channel fails Low 6
U1_HWPS U1_CPS101N U1_CPS103S C - BOP Hotwell Pump Trip - Standby Fails to Start (Adjust Hotwell Bypass flow to lower pressure post trip) 7 U1_RC19A @
100%
M-CREW Pressurizer Safety Starts leaking and progresses to full open 8
U1_RP10A C-CREW Train A Safety Injection signal failure to actuate in AUTO 9
U1_RP10B U1_RP11B C-CREW Train B Safety Injection signal failure to actuate in AUTO or Manual on the PRZ panel only 10 U1_RP19D C-CREW RPS Relay Failure Train A equipment fails to start (CV, SI, RHR,CC & Control Room Ventilation)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Page 2 of 17 Event Summary The crew is directed to swap Control Fluid pumps due to potential problem with the running pump.
The plant is at 80% power and the crew is directed to commence raising power to 100%.
Once a Dilution is begun the PW pump will trip and the standby pump will fail to start The RO will be required to start the standby pump to continue the dilution.
After the crew completed the PW pump actions and began to change power, SG Pressure Channel MPP-230 fails low. The BOP will be required to take manual control of SG 3 Feedwater Regulating Valve FRV-230 to stabilize level. The crew will address the failure with the Abnormal Operating Procedure, address Technical Specifications, select an operable channel, and restore automatic control.
A Low failure of the Pressurizer Level Control Bi-stable channel will occur. The RO should identify the channel failure. The crew will need to address this failure with the Abnormal Operating Procedure and address Technical Specifications. This will also cause an isolation of normal Letdown. The crew will select an Operable Bi-stable channel and restore Letdown.
The South Hotwell Pump will trip requiring the BOP to manually start the Middle Hotwell pump.
The major event will start with a leaking Pressurizer Safety Valve. This will progress to SV-45A PRZ Safety Valve failing full open. A unit trip will be required. As the crew performs the actions of E-0, the Safety Injection will fail to automatically actuate. The Crew must manually actuate SI (Train B from SI panel only works) and/or align ECCS Pumps and Equipment as required. The crew will transition to E-1. The scenario will terminate when the crew has transitioned to ES-1.2 for Post LOCA cooldown.
Critical Tasks Stabilize SG Level on MPP-230 Failure Manually Actuate SI Procedures E-0, Reactor Trip or Safety Injection E-1, Loss of Reactor or Secondary Coolant
Appendix D Required Operator Actions Form ES-D-2 Page 3 of 17 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 1 Event
Description:
Swap #1 Control Fluid Pump for #3 Control Fluid Pump Time Position Applicant's Actions or Behavior US Directs use of 1-OHP-4021-050-006, Main and MFP Turbine Control Fluid Operation, Attachment 1, Control Fluid System Operation, Section 4.2, for swapping Control Fluid Pumps.
BOP Places Control Fluid Pump #1 in RUN.
BOP Acknowledges Alarms on MT DCS Ann. Panel:
Drop 179, No Ctrl Fluid Pump in Auto 2 Drop 208, More than 1 CTRL FLD Pump in Manual and Running BOP Places Control Fluid Pump #3 in OFF.
BOP Places Control Fluid Pump #3 in AUTO 2.
BOP Acknowledges Alarms clearing on MT DCS Panel.
RO Provides peer checks during evolution as appropriate.
Appendix D Required Operator Actions Form ES-D-2 Page 4 of 17 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 2 Event
Description:
Raise Turbine and Reactor Power NOTE: Place Event 3 Failure In prior to Crew starting dilution for Power Change Time Position Applicants Actions or Behavior RO Calculates the dilution required per OHP-4021-005-002,, Boration or Dilution Volume Determination.
RO Briefs crew on reactivity plan for power escalation.
US Reviews / concurs with reactivity plan.
US Directs RO to commence Power Escalation in accordance with OHP-4021-001-006, Power Escalation (at step 4.77)
RO Performs DILUTION (batch add OR Continuous):
Place RC Makeup Blend control switch in STOP Place RC Makeup Blend Control Mode switch in DILUTE or ALT DILUTE Adjust PW to the desired flow rate and/or amount.
May close QRV-451 if aligning to CCP Suction Only (if using Alt Dilute)
Place RC Makeup Blend control switch in START (Event 3 initiator)
May take QRV-303 to Manual and Open as required to maintain VCT Level and Pressure.
RO Commences escalation:
Raises turbine load (reactor power) using the DCS HMI.
Maintains Tavg / Tref deviation within limits by dilution and turbine load adjustments.
Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.
RO RO verifies appropriate reactivity feedback.
BOP Acts as peer checker for RO during blender operations.
Appendix D Required Operator Actions Form ES-D-2 Page 5 of 17 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 3 Event
Description:
North PW Pump trip / Failure to Start of Standby Pump Time Position Applicants Actions or Behavior RO Identifies that the North PW pump has tripped and a dilution is not occurring. ANN panel 109 Drops 28 and 29 US Directs RO to Stop attempted dilution and address the tripped pump using the ARP.
May Place North PW pump in stop RO Places South PW in Start and verifies that PW flow is available for dilution.
Appendix D Required Operator Actions Form ES-D-2 Page 6 of 17 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 4 Event
Description:
SG Pressure Channel MPP-230 Fails low Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel 114 which are indicative of a steam generator #3 water level control / pressure instrument failure (Drops 3, 12, 13, 14 ).
BOP Critical Task #
Reports instrument malfunction and performs the immediate actions of OHP-4022-IFR-001, Instrument Failure Response:
Places FRV-230, SG 3 MFW Reg. Valve controller to MANUAL, lowers controller output and restores SG 3 level to program (may also place MFP P controller in MANUAL or Speed control at this time).
Crew Performs plant stability checks.
US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.
US Enters and directs actions of 1-OHP-4022-013-012, Steam Generator Pressure Instrument Malfunction procedure.
BOP Performs the following actions as directed:
- 1. Reports MPP-230 has failed.
- 2. Places / verifies FRV-230 controller in MANUAL.
- 3. Places / verifies MFP P controller in MANUAL.
- 5. Places 1-FS-532C selector switch in channel 2 position.
- 6. Restores SG 3 level using manual control of FRV-230.
- 7. Nulls and returns FRV-230 controller to AUTO.
- 8. Returns MFP P controller to auto.
US Refers to Tech Specs (TS):
Function 15 - Cond. D Trip Bistables in 6 Hours
Function 1e(2) & 4e - Cond. D - Trip Bistables in 6 Hours
- TS 3.3.4 Remote Shutdown Instrumentation - Condition A - Restore within 30 Days US Initiates actions to trip bistables associated with MPP-230 per Attachment C-1 of 1-OHP-4022-013-012.
Appendix D Required Operator Actions Form ES-D-2 Page 7 of 17 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 5 Event
Description:
NLP-152, Pressurizer Level Control Bi-stable channel fails low Time Position Applicants Actions or Behavior RO Recognizes and reports annunciators on Panel #108 (Drop 5, 50).
Reports instrument malfunction indicative of a Pressurizer Level instrument failure.
RO Reports instrument malfunction and performs the immediate actions of OHP-4022-IFR-001, Instrument Failure Response:
- Close 1-QRV-200, using Charging Flow to Regen HX Controller
- Places 1-QRV-251, Charging Flow Controller in manual and manually adjusts output to minimum amount required for seal injection (~35 gpm).
Crew Performs plant stability checks.
US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.
US Enters and directs actions of OHP-4022-013-010, Pressurizer Level Instrument Malfunction procedure.
- Selects Operable Bi-stable Channel US Directs RO / BOP to restore normal letdown (using QRV-161, 75 gpm letdown orifice) per 1-OHP-4021-003-001, Letdown, Charging, and seal water Operation, Attachment 13.
RO Performs the following actions as directed:
- 1. Restores PRZ level using 1-QRV-251 or level controller
- 2. Reports 1-NLP-152 has failed
- 3. Ensures PRZ level control is in manual
- 4. Places PRZ Level CTRL selector switch in Ch 1 & 3 position
- 5. Places PRZ Level REC selector switch in 1 or 3 position
- 6. Resets PRZ Heaters to restore control Actions for restoring Letdown and returning Pressurizer Level Control to automatic are contained on the following page
Appendix D Required Operator Actions Form ES-D-2 Page 8 of 17 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 5 Event
Description:
NLP-152, Pressurizer Level Control Bi-stable channel fails low US Initiates actions to trip bi-stables associated with 1-NLP-152 PZR Level Failure per Attachment B of OHP-4022-013-010.
US Refers to Tech Specs (TS):
- TS 3.3.1 RTS Instrumentation (Condition A Table 3.3-1, Function 9 Cond. D Trip Bistables in 6 Hours)
- TS 3.3.3 Post Accident (Minimum channels met)
RO/BOP Restores normal letdown per Attachment 13, Section 4.1 as follows:
- 1. Places QRV-302 in divert position.
- 2. Verifies orifice isolations closed (QRV-160, 161 and 162).
- 3. Adjusts CRV-470 controller to >50% output.
- 4. Verifies open letdown isolation valves:
- a. QCR-300, CVCS letdown Cntmt isol
- b. QCR-301, CVCS letdown Cntmt isol
- c. QRV-111, RC letdown to Regen hx
- d. QRV-112, RC letdown to Regen hx
- 5. Adjusts QRV-301 controller to 50% output.
- 6. Checks/adjusts charging flow to > 75 gpm.
- 7. Opens QRV-161, 75 gpm letdown orifice isolation.
- 8. Adjusts QRV-301 to maintain 160 - 350 psig on QPC-301.
- 9. Places QRV-301 in auto (if desired).
- 10. Nulls and returns CRV-470 controller to auto.
- 11. Adjusts charging flow as required to maintain PRZ level.
- 12. Places PRZ level control in automatic (if desired).
- 13. Places QRV-302 in normal (demin) position when letdown temperature is stable.
Appendix D Required Operator Actions Form ES-D-2 Page 9 of 17 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 6 Event
Description:
South Hotwell Pump Trip - Middle (Standby) Fails to Start Time Position Applicant's Actions or Behavior BOP Recognizes feedwater control problem and reports alarms:
Panel #116 Drop 63 - Hotwell Pump Disch Pressure Low Drop 61 - Hotwell Pump Motor Instant Trip Drop 73 - Cndst Booster Pump Disch Pressure Low Panel #122 Drop 96 - Turb Aux Clg Water Pump Auto Start Up US Directs operator actions to stabilize the unit and restore Hotwell pump flow.
RO Monitor RCS & Secondary parameters during transient.
BOP Manually start the Middle Hotwell pump.
May Place South Hotwell pump control switch to TRIP and back to NEUTRAL (Clear Alarms).
Monitor Secondary parameters for normal operations.
US/RO Stabilize Power, if desired: (May be held from first event)
Verify Reactor Stable Verify SG levels Stable
Appendix D Required Operator Actions Form ES-D-2 Page 10 of 17 Op-Test No.: Cook 2018 Scenario No.: NRC2020-1 Event No.:.: 7,8,9,10 Event
Description:
Pressurizer Safety Leak Progressing to Full Open, Train A & B Auto Safety Injection failure with Train A Relay Failure (CV, SI, RHR,CCW &
Control Room Ventilation fails to auto start)
Time Position Applicants Actions or Behavior RO Recognize and reports abnormal RCS leakage:
RCS pressure lowering with PZR Heaters ON PRZ Safety Valve SV-45A indicates open Panel #108:
Drop 8 - Pressurizer Press Low Dev Backup Htrs On Drop 29 - PRZ SV A Disch Temp Hi Drop 31 - Prz Relief Tk Pressure High Or Low Drop 45 - Acoustic Monit Flow Detected Or Volt Fail BOP/RO Monitor Containment Pressure US Directs RO to Perform a Reactor Trip Directs RO/BOP to perform the immediate actions of 1-OHP-4023-E-0, Reactor Trip or Safety Injection.
RO/BOP Performs the immediate actions of E-0:
- 1. Checks reactor trip
- 2. Checks turbine trip
- 3. Checks power to AC emergency buses
- 4. Checks safety injection status
Appendix D Required Operator Actions Form ES-D-2 Page 11 of 17 Op-Test No.: Cook 2018 Scenario No.: NRC2020-1 Event No.:.: 7,8,9,10 Event
Description:
Pressurizer Safety Leak Progressing to Full Open, Train A & B Auto Safety Injection failure with Train A Relay Failure (CV, SI, RHR,CCW &
Control Room Ventilation fails to auto start)
Time Position Applicants Actions or Behavior RO/BOP Critical Task #2 Check Safety Injection Actuated:
Manually Actuate SI (From SI Panel for Train B) to establish High Head Injection Flowpath
-OR-NOTE: May be performed in E-0, Attachment A.
Manually Align Valves BIT Inlet Valves ICM-255 -AND/OR ICM-256 - OPEN BIT Outlet Valves ICM-250 -AND/OR ICM-251 - OPEN RWST to CCP Valves IMO-910 -AND/OR IMO-911 - OPEN VCT to CCP Valves QMO-451 -AND/OR QMO-452 - CLOSED
- Manually Start/Align ECCS Equipment and Actuate Phase A (Train A)
- Stop all RCPs when RCS is < 1300 psig and CCP/SI pump running BOP Manually controls AFW flow to maintain SG narrow range levels 13% - 50% once one SG narrow range level is greater than 13%.
US Ensures immediate actions of E-0 are completed
- Directs subsequent actions of E-0.
RO/BOP Completes actions of E-0 through step 19 as directed.
Appendix D Required Operator Actions Form ES-D-2 Page 12 of 17 Op-Test No.: Cook 2018 Scenario No.: NRC2020-1 Event No.:.: 7,8,9,10 Event
Description:
Pressurizer Safety Leak Progressing to Full Open, Train A & B Auto Safety Injection failure with Train A Relay Failure (CV, SI, RHR,CCW &
Control Room Ventilation fails to auto start)
Time Position Applicants Actions or Behavior RO/BOP Performs manual actions of E-0, Attachment A as directed by US.
Verifies CEQ Fans and CCW to CEQ Place DIS in Service - Turn on Igniters Verify Train A Control Room Pressurization aligned Reset Bypass switches for PACHMS Verifies Containment Ventilation & Phase A Isolations US/RO Checks if RCS is Intact - NO.
US Announces transition to 1-OHP-4023-E-1, Loss of Reactor or Secondary Coolant and directs operator actions.
RO/BOP Completes actions of E-1 through step 12 (Check if RCS Cooldown and Depressurization is required) as directed.
BOP Restore SG narrow range levels and maintain between 20% and 50%.
US/RO Checks if SI Termination Criteria is MET:
RCS Subcooling >40°F - NO Secondary Heat Sink (SG >13% or AFW Flow >240x103)
RCS Pressure rising or stable - NO Pressurizer Level >16%
US/RO Check if CTS can be stopped - Not running US/RO Check if RHR can be stopped (NO - RCS Pressure Lowering)
Check RCS Pressure > 300 psig and stable Check RCS and SG Pressures Pressure in all SGs - stable or rising RCS pressure - stable or lowering
Appendix D Required Operator Actions Form ES-D-2 Page 13 of 17 Op-Test No.: Cook 2018 Scenario No.: NRC2020-1 Event No.:.: 7,8,9,10 Event
Description:
Pressurizer Safety Leak Progressing to Full Open, Train A & B Auto Safety Injection failure with Train A Relay Failure (CV, SI, RHR,CCW &
Control Room Ventilation fails to auto start)
Time Position Applicants Actions or Behavior BOP Shutdown Unloaded EDGs.
US Evaluate Plant Status Check Cold Leg Recirculation Capability Check Aux. Building Radiation Check RCS Pressure > 300 psig US Announces transition to 1-OHP-4023-ES-1.2, Post LOCA Cooldown and Depressurization (at step 12).
Terminate Scenario
Critical Task Summary Page 14 of 17 Task Elements Results
- 1 Manually Control SG#13 Level on MPP-230 Failure Cueing:
- Panel #114 Drops 3,12,13,14
- MFC-131 Indication Lowering
- FRV-230 closing Performance Indicators:
- Place FRV-230 in Manual and control SG #13 Level to maintain it 15% - 67% preventing a Reactor Trip.
(May Select MFC-130 as Controlling Channel and Place\\Leave FRV-230 In Auto)
Performance Feedback:
- 2 Manually Actuate/Align one train of Safety Injection to establish HIGH Head Injection Flow Cueing:
Check SI Actuated Safety Injection Actuated Status Light LIT (E-0, Step 4.a)
-OR-Check BOTH CCP leakoff valve "Safety Injection Signal" white lights - LIT Performance Indicators:
Before transitioning from E-0 and reaching a Valid Orange Path in FR-C series Core Cooling Actuate 1 Train of SI
-OR-Manually Start/Align ECCS Equipment and Actuate Phase A (Train B)
Manually Align Valves BIT Inlet Valves ICM-255 -AND/OR ICM-256 -
OPEN BIT Outlet Valves ICM-250 -AND/OR ICM-251 -
OPEN RWST to CCP Valves IMO-910 -AND/OR IMO-911 - OPEN VCT to CCP Valves QMO-451 -AND/OR QMO-452 - CLOSED Ensure 1 CCP and SI running Performance Feedback:
ECCS flow is indicated to at least one train (as indicated by flow on cold leg BIT injection flowmeters)
One Train of Phase A Isolation is complete per E-0, Attachment A SAT / UNSAT
Scenario Instructor Actions Page 15 of 17 Setup:
- 1. Reset to IC-303 MOL; 80% power, 850 MW, 799.86 ppm, 565.5 F 194 Steps on D
- 2. Place ALL Pressurizer Heaters In ON
- 3. Reset control rods and check group step counters.
- 4. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position.
- 5. Advance chart recorder paper & clear chart recorder memory.
- 6. Activate the following (pre-load) malfunctions:
- 1.
Set Up South PW pump fail to Auto Start South PP in run on Trigger Global on South PW & Turn on Light Clear Global and Light on Start
- 2.
Set Up North PW pump trip on Auto Start PW flow on Trigger 4 Trip North PW Pump on Trg 4 Hotwell Pump 1N Pressure Switch Hotwell Pump 1S Pressure Switch Train A Safety Injection Auto Failure Train B Safety Injection Auto Failure Train B Safety Injection Manual on the PRZ panel only RPS Relay Failure Train A Equipment fails to start (CV, SI, RHR,CC & Control Room Ventilation)
ZLO101PW2S_U1[GRN]
U1 South PW In Run Trg 1 U1_RP11D U1_RP19D QFC412 PW Flow >.003 Trg 4 U1_RP10B U1_CPS101N U1_101PW2N U1_101PW2S U1_CPS103S U1_RP10A ZLO101PW2S_U1[GRN]
U1_101PW2S
Scenario Instructor Actions Page 16 of 17 Scenario Events:
NOTE: Verify Event 3 Failure In prior to Crew Starting Dilution EVENT #1 If required, Local Control Fluid Temperature is 124°F EVENT #2 Respond as required to power change notifications and requests EVENT #3 (Entered in Setup)
If dispatched, report that the North PW pump breaker appears to be tripped and will not reclose EVENT #4 After crew changes power, insert ICF U1_MPP230 final value 1 over 30 seconds (MPP-230 fails low).
EVENT #5 Insert U1_NLP152, final value 0 NLP-152 fails low to cause Letdown isolation, heater isolation, and alarm.
EVENT #6 IMF U1_HWPS to cause a South Hotwell Pump to Trip (Switches to failure auto start already in)
U1_NLP152 U1_MPP230 U1_HWPS
Scenario Instructor Actions Page 17 of 17 EVENTS #7,8,9,10 IMF U1_RC19A to 100 from.1 over 5 Minutes to simulate the PZR Safety leak to full open Malfunctions for Train A & B SI Auto Failure, Train B from PRZ Panel, and Train A Slave Relay have already been Entered.
Perform Local actions after entry into E-0 as requested:
- Locally stop U1 Ice Condenser AHUs MRF CHR01 to OFF
- Aux Tour will monitor Spent Fuel Pool Level and Temperatures
- Place PACHMAS in service - MRF CHR02 or 03 with 10 min delay.
OR (both have 10 minute delay built in)
- U2 has aligned CR vent for U1 SI, Fan 2-HV-AS-2 is running.
If directed to secure EDG jacket water pumps select OFF then AUTO Remote OFF AUTO EGR 03A EGR 03B EGR 04A EGR 04B U1_EGR04A U1_EGR03A U1_EGR03A U1_EGR04A U1_EGR03B U1_CHR03 U1_EGR04B U1_RC19A U1_CHR01 U1_EGR04B U1_CHR02 U1_EGR03B
Appendix D Scenario Outline Form ES-D-1 Page 1 of 18 Facility: DC COOK 1 & 2 Scenario No.: NRC2020-2 Op-Test No.: _________
Examiners: ___________________________ Operators:
Initial Conditions: 4 % Power.
Mode change approved. Plant startup, raise power to ~ 10% to warm and roll Main Turbine.
Critical Tasks: Stabilize PZR Pressure following NPP-151 failure, Insert Negative Reactivity.
Event No.
Malf. No.
Event Type*
Event Description 1
U1_TACSE Stator Short C-BOP East Turbine Aux Cooling Water pump trip 2
R-RO Raise power 3
N-BOP Control SG Level in manual 4
U1_NPP151 to 2500 I-RO TS Controlling Pressurizer Pressure Channel Fails High 5
U1_MPP212 to 1500 I-BOP TS SG PORV Pressure Transmitter Failure 6
U1_ECP short circuit C-RO TS Trip of 1E CCP 7
U1_RP08B U1_NI06 M-Crew Intermediate Range Failure and Reactor Trip Breakers fail to open 8
U1_RP03A U1_RP03B C-Crew Inadvertent FW Isolation 9
U1_WMDAF P Short C-Crew West MDAFW Pump trip (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Page 2 of 18 Event Summary The Crew is directed to commence raising power to ~10% for Main Turbine Start-up. The RO will withdraw rods to raise power while the BOP has Manual Control of Feed Reg Valves for SG level.
A trip of the East Turbine Aux Cooling Water pump occurs. This will result in reduced cooling capability for the Main Generator. BOP will be required to manually start the West Turbine Aux Cooling Water pump. Crew will be required to stabilize the plant.
The controlling Pressurizer Pressure Channel NPP-151 Fails High, Pressurizer spray valves will go full open. The crew will need to take manual control of pressurizer pressure and enter an Abnormal Operating Procedure, defeat the failed channel, address Technical Specifications, and then restore pressurizer pressure control to auto.
A failure of SG #11 Pressure Channel (MPP-212) fails high causing SG #11 PORV to fully open.
This will also cause Reactor power to slightly rise. The BOP will need to take manual action to close the PORV, the crew will implement Abnormal Operating Procedure actions, and the US will need to declare the associated radiation monitor inoperable.
A Loss of the East CCP will require the RO to Start the West CCP. Letdown will be lost on the loss of the running CCP and will be addressed by the crew. The US will need to address Technical Specifications.
A failure of the Intermediate Range N36 will generate a Reactor Trip signal along with an inadvertent Feedwater Isolation causing the crew to identify a need for a manual Reactor Trip.
The West MDAFW pump will not start to prevent the crew from attempting to lower power and stay on line using Aux feed. Crew should enter E-0 and perform the immediate actions. The crew will attempt to manually trip the reactor. Reactor trip breakers will not open causing the crew to enter 4023-FR-S.1, Response to Nuclear Power Generation / ATWS.
Critical Tasks Stabile PZR pressure following NPP-151 failure Insert Negative Reactivity in FR-S.1 Procedures E-0, Reactor Trip or Safety Injection FR-S.1, Response to Nuclear Power Generation / ATWS
Appendix D Required Operator Actions Form ES-D-2 Page 3 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 1 Event
Description:
East Turbine Aux Cooling Water Pump Trip Time Position Applicant's Actions or Behavior BOP Recognizes problem and reports annunciator:
Panel #122 Drop 97 Turbine Aux CLG Motor Failure US Directs operator actions to stabilize the unit and restore Turbine Aux Cooling Water capacity.
BOP Manually start the West Turbine Aux Cooling Water Pump Trip Pump May Place East Turbine Aux Cooling Water Pump Trip pump switch to TRIP and back to NEUTRAL (Clear Alarms)
Monitor Secondary parameters for normal operations
Appendix D Required Operator Actions Form ES-D-2 Page 4 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 2 Event
Description:
Raise Power to 10% Power Time Position Applicant's Actions or Behavior RO Briefs crew on reactivity plan for power rise.
US Reviews reactivity plan.
US Directs RO to commence Power Escalation in accordance with OHP-4021-001-006, Power Escalation procedure, step 20.
RO Commences escalation:
Withdraws rods in 3 Step Increments while monitoring Delta T Power, NI Power and Steam Dumps RO RO verifies appropriate reactivity feedback.
Appendix D Required Operator Actions Form ES-D-2 Page 5 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 3 Event
Description:
Control Feedwater Flow in Manual Time Position Applicant's Actions or Behavior US Direct the BOP to maintain SG Levels ~40% to 48% using Manual Control of FRV210-240 and Main FW Pump Speed / DP BOP Adjust FRV210 - 240 to Maintain SG levels within Designated band Adjust Main FW Pump Speed / DP target to ensure adequate FW Discharge to SG DP Place FW Regulating Valves in Auto if FRVs will control based on power
Appendix D Required Operator Actions Form ES-D-2 Page 6 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 4 Event
Description:
Pressurizer Pressure Channel NPP 151 Fails High Time Position Applicants Actions or Behavior RO Recognizes and reports annunciators on Panel #108 indicative of a pressurizer (PRZ) pressure instrument failure (Drops 6, 7, 8).
RO Critical Task
- 1 Reports instrument malfunction and performs the immediate actions of OHP-4022-IFR-001, Instrument Failure Response:
Places PRZ pressure master controller OR both PRZ spray valve controllers (1-NRV-163 and 164) to manual and lowers controller output to close spray valves Crew Performs plant stability checks.
US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.
US Enters and directs actions of 01-OHP-4022-013-009, Pressurizer Pressure Instrument Malfunction procedure.
May enter Technical Specification 3.4.1 RCS Pressure, Temperature, and Flow DNB Limits if Pressure lowers to <2168 psig. (2200 psig admin limit)
US Declares the 1E Centrifugal Charging Pump inoperable.
Appendix D Required Operator Actions Form ES-D-2 Page 7 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 4 Event
Description:
Pressurizer Pressure Channel NPP 151 Fails High Time Position Applicants Actions or Behavior RO Performs the following actions as directed:
- 1. Restores PRZ pressure using manual control of EITHER:
PRZ pressure master controller Both PRZ spray valve controllers
- 2. Reports 1-NPP-151 has failed HIGH
- 3. Ensures PRZ pressure master controller is in manual
- 4. Places PRZ Press Ctrl selector switch in Ch 2 & 3 position
- 5. Places the following recorder switches in Ch 2, 3 or 4 position:
PRZ Press Rec selector Delta T selector Overpower Delta T selector Overtemp Delta T selector RO Performs the following actions as directed:
- 6. Verifies 1-QMO-225, E CCP Leakoff is open NOTE: (May place QRV251 in Manual while opening Leakoff -
Letdown may also be reduced - QRV-251 should be returned to Auto)
- 7. Dispatches Aux operator to open breaker for 1-QMO-225 (1-ABV-D-5C)
- 8. Checks 1-NLP-151, PRZ Level Channel 1 and 1-NLI-151, PRZ Level Cold Calibration instruments for failure
- 9. Nulls and returns the following controllers to auto:
Both PRZ spray valve controllers PRZ pressure master controller US Initiates actions to trip Bi-stables associated with 1-NPP-151 PZR Pressure Failure per Attachment A of 1-OHP-4022-013-009.
Appendix D Required Operator Actions Form ES-D-2 Page 8 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 4 Event
Description:
Pressurizer Pressure Channel NPP 151 Fails High Time Position Applicants Actions or Behavior US Refers to Tech Specs (TS):
TS 3.3.1 RTS Instrumentation (Condition A Table 3.3.1-1, Function 6, 8a, 8b Cond. D Trip Bi-stables in 6 Hours)
TS 3.3.2 ESFAS Instrumentation (Condition A Table 3.3.2-1, Function 1d Condition D -6 hours, 8b Condition G - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> *)
TS 3.3.4 Remote Shutdown Instrumentation Condition A - 30 days TS 3.5.2 ECCS Subsystems Condition A - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> TRM 8.1.1 Rx Control Systems Charging Pumps - Operating Action A - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> TRM 8.7.14, LEFM, (N/A - Applicable above 3250 MW)
- =Identifies requirement to verify the status of Permissive P-11 Bi-stables within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of pressurizer pressure channel failure.
Appendix D Required Operator Actions Form ES-D-2 Page 9 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 5 Event
Description:
SG Pressure Channel MPP-212 Fails HIGH - SG 1 PORV Opens Time Position Applicants Actions or Behavior BOP Recognize and reports Annunciator Panel #114, Drop 21, 1-MRV-213 OP OR HSD1 PANEL OVERRIDE alarm that indicates SG #1 PORV (MRV-213) has opened.
BOP Place SG PORV #1 in Manual and Closes #1 PORV.
Crew Performs plant stability checks.
US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.
US Direct operator actions to determine cause, verify SG #1 PORV closed, and monitor Reactor Power.
BOP Reports MPP-212 has failed high.
US Enters and directs actions of 1-OHP-4022-013-012, Steam Generator Pressure Instrument Malfunction procedure.
- 1. Identifies 1-MPP-212 as failed channel a) If selected for PORV control - Verify PORV in manual b) Declare 1-MRA -1601 inoperable c) Select an Operable channel using 1-PS-514F d) Place PORV in AUTO and declare 1-MRA-1601 Operable
- 3. Check MFP Differential Control in AUTO
- 4. Refer to Tech Spec (see below)
- 5. Trip Bi-stables for malfunctioning instrument
Appendix D Required Operator Actions Form ES-D-2 Page 10 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 5 Event
Description:
SG Pressure Channel MPP-212 Fails HIGH - SG 1 PORV Opens Time Position Applicants Actions or Behavior US Refers to TS / TRM:
- TS 3.3.2 ESFAS Instrumentation (Condition A Table 3.3.2-1, Function 1.e (1& 2) & 4.d - all Condition D) Trip Bi-stables in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
- TRM 8.3.8. Radiation Monitoring Instrumentation (Condition A Table 8.3.8-1, Function 2.b - Condition C)
- Declares MRA-1601 inoperable
- Restore in 7 days US Notifies SM/MTI to Initiate actions to trip Bi-stables associated with MPP-212 Steam Generator Pressure Instrument Failure per Attachment A-3 of 1-OHP-4022-013-012.
Appendix D Required Operator Actions Form ES-D-2 Page 11 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 6 Event
Description:
Trip of 1E CCP Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators that are indicative of a trip of the East Charging Pump:
Annunciator 108 Drop - 20 Charging Flow Less Than Min Set Point Annunciator 108 Drop - 11 East CCP Motor Instant Trip US Directs RO to Start CCP for Seal Injection.
RO Recognizes and reports that running (East) CCP pump has tripped Manually starts 1W CCP pump in accordance with CCP ARPs RO/BOP Restores normal letdown per Attachment 13, Section 4.1 as follows:
- 1. Places QRV-302 in divert position.
- 2. Verifies orifice isolations closed (QRV-160, 161 and 162).
- 3. Adjusts CRV-470 controller to >50% output.
- 4. Verifies open letdown isolation valves:
- a. QCR-300, CVCS letdown Cntmt isol
- b. QCR-301, CVCS letdown Cntmt isol
- c. QRV-111, RC letdown to Regen hx
- d. QRV-112, RC letdown to Regen hx
- 5. Adjusts QRV-301 controller to 50% output.
- 6. Checks/adjusts charging flow to > 75 gpm.
- 7. Opens QRV-161, 75 gpm letdown orifice isolation.
- 8. Adjusts QRV-301 to maintain 160 - 350 psig on QPC-301.
- 9. Places QRV-301 in auto (if desired).
- 10. Nulls and returns CRV-470 controller to auto.
- 11. Adjusts charging flow as required to maintain PRZ level.
- 12. Places PRZ level control in automatic (if desired).
- 13. Places QRV-302 in normal (demin) position when letdown temperature is stable.
Appendix D Required Operator Actions Form ES-D-2 Page 12 of 18 Op-Test No.:
Scenario No.: NRC2020-2 Event No.: 7,8, 9 Event
Description:
Intermediate Range Failure, Reactor Trip Breakers fail to Open, Inadvertent FW Isolation Time Position Applicant's Actions or Behavior CREW Recognizes the IRNI failure and need for a reactor trip. West MDAFW pump will not start. FW Isolation prevents crews efforts to stay online.
US Directs RO to manually trip the reactor Directs RO/BOP to perform the immediate actions of 1-OHP-4023-E-0, Reactor Trip or Safety Injection.
RO Recognizes and reports failure of reactor to manually trip.
US Directs actions of 1-OHP-4023-FR-S.1, Response to Nuclear Power Generation/ATWS:
RO Critical Task #2 Performs the immediate actions of FR-S.1:
- 1. Checks reactor trip Automatically/Manually insert control rods (must Insert Negative Reactivity through Inserting Control Rods or Emergency Boration)
BOP Performs the immediate actions of FR-S.1:
- 1. Manually actuate AMSAC
- 2. Checks Turbine Trip US Ensures immediate actions of FR-S.1 are completed RO Critical Task #2 Initiate Emergency Boration of RCS (must Insert Negative Reactivity through Inserting Control Rods or Emergency Boration)
Appendix D Required Operator Actions Form ES-D-2 Page 13 of 18 Op-Test No.:
Scenario No.: NRC2020-2 Event No.: 7,8, 9 Event
Description:
Intermediate Range Failure, Reactor Trip Breakers fail to Open, Inadvertent FW Isolation Time Position Applicant's Actions or Behavior US Directs subsequent actions of FR-S.1:
Local operation of reactor trip breakers or MG set output breakers Verify Reactor subcritical - WR log power < 5% & negative SUR BOP Raises total AFW flow to > 450K pph/hr (Until 1 SG NR level is >
13%).
Manually controls AFW flow to maintain SG NR levels 20% - 50%.
US Verify Reactor subcritical - WR log power < 5% & negative SUR US Announces transition to OHP-4023-E-0, Reactor Trip or Safety Injection.
TERMINATE SCENARIO
Critical Task Summary Page 14 of 18 Task Elements Results
- 1 Stabilize PZR Pressure Prior to Reactor Trip with failure of NPP-151 Cueing:
Panel 108 Drop 6 Pressurizer Pressure High-High Pressurizer Pressure NPP-151 failed High with actual Pressure Lowering Performance Indicators:
Takes Manual Control of Pressurizer Master Controller or Spray Valve Controllers and Closes NRV-163 and NRV-164:
NRV-163 and NRV-164 Closed Indications May place to auto after Operable Channel is selected (
Pressurizer Pressure Stabilizes Prior to reaching 1950 psig - Pressurizer Low Pressure Reactor trip Performance Feedback:
RCS pressure stabilizing SAT / UNSAT
- 2 Insert negative reactivity into the core Cueing:
Challenge to RCS cooling with FW Isolation
- Identification that RX breakers have failed to OPEN (On NI 36 trip signal)
Insert Negative Reactivity through:
- Inserting Control Rods (Manually or Auto at >48 steps per minute) - OR -
- Emergency Boration Must be performed prior to:
- SRO Reaching Step 8 of FR-S.1 Performance Feedback:
RODS
- RPIs indicate rods - inserting
- Rod bottom lights - lit
- Neutron flux - lowering BORATION (any one of following)
- Boration Flow QFI-420 > 44 gpm
- IMO-910 or IMO-911 open
- Boration Flow QFC-421 > 36 gpm SAT / UNSAT
Scenario Instructor Actions Page 15 of 18 Setup:
- 1. Reset to IC-856 MOL; 4% power,1180.64 ppm, 550.62 F, 171 Steps on D
- 2. Place ALL Pressurizer Heaters In ON, Remove SFR-402 from PPC alarm.
- 3. Reset control rods and check group step counters.
- 4. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position.
- 5. Advance chart recorder paper & clear chart recorder memory.
- 6. Activate the following (pre-load) malfunctions:
Reactor Trip Breaker A Fails Reactor Trip Breaker B Fails TACW Pressure Switch West AFW Pump Trip Set Up on Trigger 1:
- Spurious FW Isolation Train B
- N36 IR to Fail High
- Ensure IR cant block Override SFR402 and sfr201 to hold air inleakage Disable AFD at low power AN10_U1(044)
U1_NI06B U1_RP03B U1_SFR201 U1_WMDAFP U1_RP08B U1_SFR402 U1_RP03A U1_CPS603 U1 IR Train B Block
Scenario Instructor Actions Page 16 of 18 Scenario Events:
EVENT #1 IMF U1_TACSE to cause the east TACW Pump to Trip EVENT #2 Respond as required to power change notifications and requests EVENT #3 Respond as required to power change notifications and requests EVENT #4 ICF U1_NPP151 to 2500 over 30 seconds cause the Pressurizer Pressure Channel to fail High When Requested to De-energize Power for QMO-225 (1-ABV-D-5C)
EVENT #5 ICF U1_MPP212 to 1200 over 4 seconds to cause the SG Pressure Channel MPP-212 to Fail High (SG11 PORV Opens in Auto)
EVENT #6 IMF U1_ECP to cause a Charging Pump Short Circuit U1_ECP U1_TACSE U1_NPP151 U1_EDPR10J U1_MPP212
Scenario Instructor Actions Page 17 of 18 EVENT #7 - 9 Activate Trigger 1 to cause a Spurious Train B FW Isolation and N36 IR to Fail High requiring a Reactor Trip signal If Dispatched to Open the Reactor Trip Breakers then turn off the MG Sets Activate Trigger 1 U1_RDR03 U1_RDR01
Scenario Instructor Actions Page 18 of 18 Reactivity Guide CBD Power Delta I Tave 165 3.3 0
550.6 168 3.8 0
551.0 171 5.2
+0.5 551.9 174 6.4
+1.0 552.6 177 8.0
+1.1 553.4 180 9.3
+2.0 554.1 183 10.5
+2.5 554.9
Appendix D Scenario Outline Form ES-D-1 Page 1 of 18 Facility: DC COOK 1 & 2 Scenario No.: NRC2020-3 Op-Test No.: _________
Examiners: ___________________________ Operators:
Initial Conditions: 50 % Power.
Turnover: Restore power to 100% following previous down power for MFP repairs Critical Tasks: Stabilize SG Level on MFC140 Failure, Throttle AFW to prevent a PTS challenge Event No.
Malf. No.
Event Type*
Event Description 1
N-BOP Place an Additional Main FW Pump in Service 2
R-RO Commence raising Reactor Power to 100%
3 U1_NTP240 to 650 I-RO TS Loop 4 Tc fails high 4
U1_MFC140
@ 0 I-BOP TS
- 14 SG Controlling Steam Flow Channel Fails Low 5
U1_ED07B C-RO TS PZR HTR Transformer Fails (11PHC Fails) 6 Set U1_MSVMR V210.94 C-BOP Main Steam Stop Valve Comes Off Detent (Open Limit Switch) 7 U1_MS01D
@ 20 over 2 min M-CREW Steam Line Break Outside Containment (#14 SG) 8 U1_RP07A U1_RP07B C-CREW Steam Line Isolation fails to AUTO actuate 9
U1_MS22A -
D C-CREW MSIVs fail to close Manually (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Page 2 of 18 Event Summary The Crew is directed to Place an Additional Main FW Pump in Service The plant is at 50% power and the crew is directed to commence raising power to 100%.
The Loop #4 Tc RTD will fail high. This will require the RO to place rods in manual to stop rod movement. The crew will implement Abnormal Operating Procedure actions to stabilize the plant.
The #14 SG Controlling Steam Flow Channel will fail low causing the FRV to close and SG level to Lower. The BOP will need to establish manual control of #14 FRV and MFP DP control to stabilize SG level. The Crew will need to enter the Abnormal Operating Procedure and select an operable channel, restore SG level control to auto, and address Technical Specifications.
A failure of the PZR HTR Bus 11PHC will occur. The PZR SCR heater control will need to be transferred to 11PHA using the Annunciator Response procedure. The crew should also refer to Technical Specifications.
The #1 SG Main Steam Stop Valve will come off the open limit switch/detent. The crew will need dispatch an operator to check the status and then reopen the Stop Valve using the Annunciator Response procedure to continue on.
The major event will involve a Main Steamline Break outside containment on the #14 SG. The crew will trip the reactor and a Safety Injection will actuate. As the crew performs the actions of E-0, they should identify the Main Steamline Break outside containment on the #14 SG. A failure of the Main Steamline Isolation actuation circuit will require a manual actuation which will be unsuccessful. The crew will transition to E-2 to isolate SG. The crew will then transition to ECA-2.1 when steam lines will not isolate. The scenario will terminate when the crew has Reset SI for ECCS Flow Reduction steps.
Critical Tasks Stabilize SG Level on MFC140 Failure Throttle AFW prior to PTS concern Procedures E-0, Reactor Trip or Safety Injection E-2, Faulted Steam Generator Isolation ECA-2.1 Uncontrolled Depressurization of All Steam Generators
Appendix D Required Operator Actions Form ES-D-2 Page 3 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 1 Event
Description:
Place Main Feedwater Pump in Service Time Position Applicants Actions or Behavior US Directs actions of 1-OHP-4021-055-003, Placing a Main Feed Pump in Service Attachment 4, West Feed Pump Startup As Second Feed Pump.
BOP Performs the following to place the MFP in Service as directed:
Selects target and ramp rate on HMI.
Starts the ramp by depressing GO on HMI.
Monitors FW discharge pressure and flow.
Stop AC Auxiliary Oil Pump Place MFP in DP control and Load Share US/BOP Notify chemistry of FW Pump configuration change.
Appendix D Required Operator Actions Form ES-D-2 Page 4 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 2 Event
Description:
Raise Turbine and Reactor Power NOTE: Place Event 3 Failure In prior to Crew Placing Rods In Manual for Power Change Time Position Applicants Actions or Behavior RO Calculates the dilution required per OHP-4021-005-002,, Boration or Dilution Volume Determination.
RO Briefs crew on reactivity plan for power escalation.
US Reviews / concurs with reactivity plan.
US Directs RO to commence Power Escalation in accordance with OHP-4021-001-006, Power Escalation (at step 4.74)
RO Performs DILUTION (batch add OR Continuous):
- Place RC Makeup Blend control switch in STOP
- Place RC Makeup Blend Control Mode switch in DILUTE or ALT DILUTE
- Adjust PW to the desired flow rate and/or amount.
- May close QRV-451 if aligning to CCP Suction Only
- Place RC Makeup Blend control switch in START
- May take QRV-303 to Manual and Open as required to maintain VCT Level and Pressure.
RO Commences escalation:
- Raises turbine load (reactor power) using the DCS HMI.
- Maintains Tavg/Tref deviation within limits by dilution and turbine load adjustments.
- Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.
RO RO verifies appropriate reactivity feedback.
BOP Acts as peer checker for RO during blender operations.
Appendix D Required Operator Actions Form ES-D-2 Page 5 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: __3___
Event
Description:
Loop #4 Tc Fails high.
Time Position Applicants Actions or Behavior RO Recognizes and reports annunciators on Panel 111 which are indicative of a RTD instrument failure (Drops 14, 15).
RO Reports malfunction and performs the immediate actions of OHP-4022-IFR-001, Instrument Failure Response:
Identifies failure of Loop #4 RTD Ensures control rods are in manual with no rod motion Places Pressurizer level control in Manual US / CREW Performs Plant Stability checks US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.
US Enters and directs actions of 1-OHP-4022-012-003, Continuous Control Bank Movement procedure.
- Check Rod Control
- 1) Check Rod position above RIL
- 2) Check AFD within target
- Check Power Range Channels - Operable
- Restore Equilibrium Conditions
- Check for Instrument Malfunction
- 1) Check MPC-253 Operable
- 2) Check Tave Channels - Operable (NO)
- 3) Check Power Range Channels - Operable US Enters and directs actions of 1-OHP-4022-013-007, RCS RTD Instrument Malfunction procedure.
Appendix D Required Operator Actions Form ES-D-2 Page 6 of 18 RO / BOP Performs the following as directed:
Verify Control Rods - MANUAL Check for Failed Temperature Channel Align following switches:
Tavg Defeat to loop4 Delta T Defeat to loop 4 Delta T Recorder to loop 1, 2, or 3 OPDT Recorder to loop 1, 2, or 3 OTDT Recorder to loop 1, 2, or 3 Check PZR Level Control in Auto RO / BOP Recover Rods to restore Tave and Flux
Appendix D Required Operator Actions Form ES-D-2 Page 7 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 4 Event
Description:
- 14 SG Controlling Steam Flow Channel MFC-140 Fails Low Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #114 (Drops 33, 42,
- 43) which are indicative of a steam flow instrument failure.
BOP Critical Task #1 Manually Control SG#14 Level on MFC-140 Failure Reports instrument malfunction and performs the immediate actions of OHP-4022-IFR-001, Instrument Failure Response:
Determine SG 4 level is lowering and that its Feedwater Regulating Valve (FRV-240) is not responding as expected.
Notify US and takes manual control of FRV-240.
Determine failure affects MFPs, and take P controller to MANUAL or may go to Speed Control.
Stabilize SG 2 level in manual.
US / CREW Performs Plant Stability checks US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.
US Enters and directs actions of 1-OHP-4022-013-014, Steam Flow Instrument Malfunction procedure.
BOP Performs the following actions as directed:
Restores SG 4 level using MANUAL control of FRV-240.
Places MFP P controller in MANUAL and maintains pressure. May place MFP in Speed Control.
Reports MFC-140 has failed low.
Places 1-FS-542C selector switch in channel 2 position.
Nulls and returns FRV-240 controller to AUTO.
Returns MFP P controller to AUTO.
US Refers to the following Tech Specs (TS):
TS 3.3.1 RTS Instrumentation (Table 3.3.1-1)
Condition A - Refer to Table Function 15 Condition D - Trip Bi-stables in 6 Hours TS 3.3.2 ESFAS Instrumentation (Table 3.3.2-1)
Condition A - Refer to Table Function 4e Condition D - Place channel in trip in 6 Hours
Appendix D Required Operator Actions Form ES-D-2 Page 8 of 18 US Initiates actions to trip bi-stables associated with MFC-140 failure per Attachment D-1 of 1-OHP-4022-013-014
Appendix D Required Operator Actions Form ES-D-2 Page 9 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 5 Event
Description:
PZR HTR Transformer Fails (11PHC Fails).
Time Position Applicants Actions or Behavior RO Recognizes and reports annunciators on Panel 108, Drops 46 and 50, indicative of a pressurizer (PRZ) heater power supply failure.
(Breaker T11D9 on Electrical Panel)
RO Reenergizes PRZ control (cycling) group heaters per 1-OHP-4024-108, Drop 50 annunciator response, as follows:
Opens breaker CB11PHC6 Closes breaker CB11PHA6 (Drop 50 clears)
RO Monitors PRZ pressure response and ensures normal PRZ heater operations for PHA supplied heaters.
US Refers to Tech Specs (TS):
TS 3.4.9.b Pressurizer - (Condition B.1) due to a loss of 1 train of pressurizer heaters. Restore B/U heaters to operable within 72 Hours.
Appendix D Required Operator Actions Form ES-D-2 Page 10 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 6 Event
Description:
Main Steam Stop Valve Comes Off Detent (Open Limit Switch)
Time Position Applicants Actions or Behavior BOP Recognizes and reports annunciator on Panel #113 indicative of a Stop Valve misalignment Drop 6 SG 1 STOP VLV1-MRV-210 ABNORMAL US Directs BOP to review ARP for annunciators and dispatch operator to Investigate.
BOP Determines Main Steam Stop Valve 1-MRV-210 has come off the open detent.
US Directs BOP to re-open Main Steam Stop Valve 1-MRV-210.
BOP Re-open Main Steam Stop Valve 1-MRV-210 by placing Control Switch to open.
May Refer to 1-OHP-4021-051-003 Removing a SG Stop Valve MMO or MRV from Service.
US May Refer to Technical Specification 3.7.2 Steam Generator Stop Valves (SGSVs)
Appendix D Required Operator Actions Form ES-D-2 Page 11 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 7/8/9 Event
Description:
Steam Line Break outside Containment (#14 SG) - Auto Steam Line Isolation fails and MSIVs wont close Time Position Applicant's Actions or Behavior RO/BOP Recognize RCS Temp / Pressure lowering. MT Megawatts will lower as well. Reactor Power may rise slightly.
US Recognize need for a reactor trip and directs RO/BOP to trip the reactor and perform the immediate actions of 01-OHP-4023-E-0, Reactor Trip or Safety Injection.
RO/BOP Performs the immediate actions of E-0:
- 1. Checks reactor trip
- 2. Checks turbine trip
- 3. Checks power to AC emergency buses
- 4. Checks safety injection status US Ensures immediate actions of E-0 are completed US/BOP Identify Main Steamline Isolation is required and has not occurred based on SG pressure < 500psig.
US/BOP Verify MSLI requirement met:
- 1. Attempts to Manually closes Main Steam Line Isolation (SG Stop) valves MRV-240 (Faulted SG #14)
MRV-210 MRV-220 MRV-230 Crew Complete actions in E-0 thru step 17 to check for Faulted SG Identifies a Faulted SG exists and MSIVs cannot be closed.
US Announces transition to 01-OHP-4023-E-2, Faulted Steam Generator Isolation, for a SG depressurized (at step 17 of E-0).
US Directs actions of E-2, Faulted Steam Generator Isolation.
Appendix D Required Operator Actions Form ES-D-2 Page 12 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 7/8/9 Event
Description:
Steam Line Break outside Containment (#14 SG) - Auto Steam Line Isolation fails and MSIVs wont close Time Position Applicant's Actions or Behavior RO/BOP Check SGSV closed - NO RO/BOP Check SGSV Dump valves closed RO/BOP Check if Any SG Pressure Boundary is Intact - NO, all lowering in uncontrolled manner US Announces transition to 01-OHP-4023-ECA-2.1, Uncontrolled Depressurization of All Steam Generators (RNO for step 3 of E-2).
US Directs actions of ECA-2.1, Uncontrolled Depressurization of All Steam Generators US/BOP Check Secondary Pressure Boundary SG Stop Valves - Closed - NO Feed Reg Valves and FW Isolations TDAFP Steam Supply SG PORVs Blowdown valves and Sample valves DRV-407 BOP/RO Critical Task #2 Control the AFW flow to minimize RCS cooldown during uncontrolled depressurization of all SGs Manually controls AFW flow to minimize RCS Cooldown Check cooldown rate in RCS Cold legs < 100F in any 60 minute period - reduce feed flow to 25,000 pph to each SG (Step 2 RNO)
US Recognizes the throttling of AFW above will give Red Status to Heat Sink CSFST and may enter FR-H-1 Response To Loss Of Secondary Heat Sink
Appendix D Required Operator Actions Form ES-D-2 Page 13 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 7/8/9 Event
Description:
Steam Line Break outside Containment (#14 SG) - Auto Steam Line Isolation fails and MSIVs wont close Time Position Applicant's Actions or Behavior US Reads CAUTION prior to step 1
- If total feed flow is less than 240.x103 pph due to operator action, this procedure should not be performed.
Exits and returns to procedure in effect BOP/RO Check RCS Hot Leg temperatures - Stable or Lowering Control Feed flow to stabilize temperature US/RO Monitor RCS Boron concentration - Greater than Required Direct Chemistry to periodically sample the RCS Refers to OHP-4023-SUP-013 for required boron US/RO Check if RCPs should be stopped RCS temperature Stable or Rising US/RO Check PORVs and Block Valves US/BOP Checks Secondary Radiation Resets containment isolation phase A Directs chemistry to sample all SGs for activity Check SG PORV Rad. Monitors Check Secondary Radiation US/RO Check if RHR pumps should be stopped RCS > 300 psig Pressure stable or rising Reset SI Stop RHR pumps US/RO Check if CTS should be stopped None running CREW Check RWST level > 30%
Appendix D Required Operator Actions Form ES-D-2 Page 14 of 18 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 7/8/9 Event
Description:
Steam Line Break outside Containment (#14 SG) - Auto Steam Line Isolation fails and MSIVs wont close Time Position Applicant's Actions or Behavior CREW Check if Accumulators should be Isolated (2 RCS Hot legs <
422.8 F)
Locally restore power to Accumulator Outlet valves Close Accumulator Outlet valves CREW Check If ECCS Flow Should Be Reduced Subcooling > 40 F RCS pressure Stable or Rising PZR Level > 16%
CREW Reset SI TERMINATE SCENARIO
Critical Task Summary Page 15 of 18 Task Elements Results
- 1 Manually Control SG#14 Level on MFC-140 Failure Cueing:
- Panel #114 Drops 42,43, & 33
- MFC-140 Indication Lowering
- FRV-240 closing Performance Indicators:
- Place FRV-240 in Manual and control SG #14 Level to maintain it 15% - 67% preventing a Reactor Trip.
(May Select MFC-141 as Controlling Channel and Place\\Leave FRV-240 In Auto)
Performance Feedback:
- 2 Control the AFW flow to minimize RCS cooldown during uncontrolled depressurization of all SGs Cueing:
- Indication of uncontrolled depressurization of all SGs
- RCS cold leg cooldown rate exceeds 100F per hour
- Valve position and flow rate indication that AFW continues to be delivered to the faulted SGs at a rate in excess of 25,000 pph per SG Performance Indicators:
Control the AFW flow rate to not more than 25,000 pph per SG in order to minimize the CS cooldown rate before a SEVERE (Orange path) challenge develops to the integrity CSF Performance Feedback:
- RCS cooldown stops
Scenario Instructor Actions Page 16 of 18 Setup:
- 1. Reset to IC-859 MOL; 50% power, 481 MW, 889 ppm, 558.2 F 173 Steps on D
- 2. Place ALL Pressurizer Heaters In ON
- 3. Reset control rods and check group step counters.
- 4. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position.
- 5. Advance chart recorder paper & clear chart recorder memory.
- 6. Activate the following (pre-load) malfunctions:
- 7. RP07A, Train A Steamline Isolation fails to AUTO actuate
- 8. RP07B, Train B Steamline Isolation fails to AUTO actuate
- 9. MS22 (B), MSIV MRV-220 MECHANICAL BINDING
- 10. MS22 (C), MSIV MRV-230 MECHANICAL BINDING
- 11. MS22 (D), MSIV MRV-240 MECHANICAL BINDING
- 13. MS04D TO 20% #14 SG Steamline Break on trg 2 U1_MS22C U1_MS22D U1_RP07A U1_MS22B U1_RP07B U1_MS22A U1_MS04D
Scenario Instructor Actions Page 17 of 18 Scenario Events:
EVENT #1 Respond to Fw Pump Bearing pressure request - 16.3 psig Respond as required Close HPD-140W EVENT #2 Respond as required to power change notifications and requests EVENT #3 Prior to starting the Ramp ICF U1_NTP240 to 650 to fail Loop 4 Tcold High EVENT #4 IMF U1_MFC140 to the #14 SG Steam Flow Channel to fail Low over 1 minute EVENT #5 IMF U1_ED07B to cause the PZR HTR Transformer Failure (11PHC Fails).
If contacted as AEO to investigate the PZR HTR Transformer Failure, report back after ~ 2 min. delay that Breaker T11D9 has an OC trip.
EVENT #6 Set the Main Steam Stop Valve to 94% to simulate valve off open detent.
U1_MFC140 set u1_MSVMRV210 0.94 U1_ED07B U1_NTP240
Scenario Instructor Actions Page 18 of 18 EVENTS #7,8, 9 & 10 Activate trigger 2 to Insert malfunction U1_MS04D, final value 20 (#14 SG Steamline Break downstream of MSIV) ramped over 2 minutes. Insert U1_MS22A, MSIV MRV-210 MECHANICAL BINDING Perform Local actions after entry into E-0 as requested:
- Locally stop U1 Ice Condenser AHUs MRF CHR01 to OFF
- Aux Tour will monitor Spent Fuel Pool Level and Temperatures
- Place PACHMAS in service - MRF CHR02 or 03 with 10 min delay.
OR (both have 10 minute delay built in)
- U2 has aligned CR vent for U1 SI, Fan 2-HV-AS-2 is running.
If directed to secure EDG jacket water pumps select OFF then AUTO Remote OFF AUTO EGR 03A EGR 03B EGR 04A EGR 04B U1_EGR04B U1_CHR01 U1_EGR03A U1_CHR02 U1_EGR04B U1_EGR03A U1_EGR04A U1_CHR03 U1_EGR03B U1_EGR04A U1_EGR03B
Due to a reduction in the number of applicants to be tested, NRC2020 Scenario was determined to be unnecessary and was reassigned as a possible spare scenario, therefore the scenario is not included in the package.
Appendix D Scenario Outline Form ES-D-1 Page 1 of 18 Facility: DC COOK 1 & 2 Scenario No.: NRC2020-5 Op-Test No.: _________
Examiners: ___________________________ Operators:
Initial Conditions: 80 % Power.
Turnover: Maintain power stable at 80% following Turbine Valve testing Critical Tasks: Stabilize SG#12 Level following FFC-220 Failure, Manually actuate safety Injection Event No.
Malf. No.
Event Type*
Event Description 1
U1_FFC220
@ 0 over 20 sec I-BOP TS Feed Flow Channel Fails low on SG #12 2
U1_NI10B 200 over 1 min I-RO TS Power range detector (NI-42) fails high 3
U1_FW05A C-BOP East Main Feed Pump Trip 4
R-RO Stabilize Plant And Recover AFD from FW Pump Trip 5
N-BOP Secure AFW and additional Pumps started from FW Pump Trip 6
U1_RC11A ramps 8-15 C-RO
- 11 RCP vibrations, Manual Reactor Trip (E-0) 7 U1_RC16 Major -
CREW Pressurizer Steam Space Rupture on Reactor Trip 8
U1_RP10A U1_RP10B C-CREW Auto SI fails (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Page 2 of 18 Event Summary The plant is at 80% power and the crew is directed to maintain power at 80%.
The #12 SG Feed Flow instrument (FFC-220) fails LOW. This will result in the opening of
- 12 SG FWRV (FRV-220) to raise feedwater flow. The BOP will be required to take manual control and regulate FRV-220. The Crew will be required to implement Abnormal Operating Procedure actions to stabilize the plant.
Power range NI detector (N-42) will fail high. The crew will stop rod movement using OHP-4022-IFR-001, transition to Uncontrolled Rod Movement Abnormal Operating Procedure and then to PR NI Abnormal Operating Procedure to remove failed NI from service. The RO will develop a reactivity plan to restore rods, temperature, and flux.
A trip of the East Main Feed Pump will result in a rapid power reduction to less than 60% if not already performed. The BOP will start additional pumps as required and stabilize FW pump speed control.
The RO will be required to monitor reactivity while the BOP monitors the SG levels and secures AFW pumps. Following the turbine runback the RO will develop a reactivity plan to restore Tave and reactor flux to normal values.
The next event will involve elevated vibrations on #11 RCP. The crew will implement Abnormal Operating Procedure actions until vibrations rise to Fold Out Page criteria requiring the RO to manually trip the reactor and the crew will implement OHP-4023-E-0. The crew will complete E-0 IAs and then use the RCP Malfunction Abnormal Operating Procedure to isolate the RCP.
The Major event will begin with a Pressurizer Steam Space Break (Small RCS Leak) upon the reactor Trip. Auto SI will fail to occur requiring crew actuation.
Critical Tasks Stabilize SG#12 Level following FFC-220 Failure Manually actuate safety Injection Procedures E-0 Reactor Trip or Safety Injection E-1 Loss Of Reactor Or Secondary Coolant ES-1.2 Post LOCA Cooldown and Depressurization
Appendix D Required Operator Actions Form ES-D-2 Page 3 of 18 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 1 Event
Description:
Feed Flow Channel (FFC-220) Fails low on SG 2 Time Position Applicants Actions or Behavior BOP Recognizes and reports annunciators on Panel #113 Drop 32, Steam Generator 2 Water LVL HI Deviation Drop 43, Steam Generator 2 SF > FWF Mismatch BOP Critical Task #1 Reports instrument malfunction and performs the immediate actions of OHP-4022-IFR-001, Instrument Failure Response:
- Places FRV-220, SG #2 MFW Reg. Valve controller in manual Lowers controller output to match the operable feed flow channel with steam flow.
- Restores SG #2 level to program.
- Performs Stability Checks Crew Performs plant stability checks.
US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.
US Enters and directs actions of OHP-4022-013-015, Feedwater Flow Instrument Malfunction procedure.
BOP Performs the following actions as directed:
- 1. Reports FFC-220 has failed low
- 2. Places FS-520-C selector switch in channel 2 position.
- 3. Nulls and returns FRV-220 controller to auto.
US Refers to Tech Specs 3.3.1 RTS Instrumentation (Condition A Table 3.3.1-1, Function 15, Condition D). Trip Bi-stables in 6 Hr US Notifies SM/MTI to Initiate actions to trip Bi-stables associated with FFC-220 FW Flow Failure per Attachment B-1 of OHP-4022-013-015.
Appendix D Required Operator Actions Form ES-D-2 Page 4 of 18 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 2 Event
Description:
Power Range Channel N42 Control Power fails/ Power Restoration Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel 110 which are indicative of a NI instrument failure (Drops 11, 13, 18, & 19).
RO Reports malfunction and performs the immediate actions of OHP-4022-IFR-001, Instrument Failure Response:
Checks for no turbine runback Ensures control rods are in manual with no rod motion CREW Performs Plant Stability checks US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.
Checks for no turbine runback Ensures control rods are in manual with no rod motion US Enters and directs actions of OHP-4022-012-003, Continuous Control Bank Movement procedure.
RO Performs the following as directed:
Checks rod position above low-low rod insertion limit Checks axial flux difference (AFD) within target band Identifies failed power range channel
- 1) Place Rod Stop Bypass Selector in the Failed Channel
- 2) Verify P-7,P-8, P-10 in correct state RO Develops reactivity plan to restore power and AFD to required conditions.
Initiates restoration of equilibrium conditions (power) using either:
Control rod movement Turbine load adjustment US Enters and directs actions of OHP-4022-013-004, Power Range Malfunction procedure.
Appendix D Required Operator Actions Form ES-D-2 Page 5 of 18 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 2 Event
Description:
Power Range Channel N42 Control Power fails/ Power Restoration Time Position Applicant's Actions or Behavior RO /BOP Performs the following as directed:
Verify Control Rods - MANUAL Place Rod Stop Bypass Selector In Failed Channel Position Remove Affected Channel From Service By Placing Selector Switches To Failed Channel Position:
Comparator Channel Defeat Selector Upper Section Detector Current Comparator Defeat Selector Lower Section Detector Current Comparator Defeat Selector Power Mismatch Bypass Selector Check The Following Interlocks Are In The Required State For Existing Conditions:
P-7 (Not LIT)
P-8 (Not LIT)
P-10 (LIT)
Check AFD - WITHIN TARGET BAND Verify Recorder Inputs - SELECTED TO AN UNAFFECTED CHANNEL POSITION:
Delta-T Overtemperature Delta-T Caution - Control Rods should not be placed in automatic until at least 5 minutes have elapsed after placing Power Mismatch Bypass Selector to failed channel.
Place Control Rods In AUTOMATIC If Applicable US Directs actions to trip Bi-stables associated with NI-42 Power Range Malfunction per Attachment D of 1-OHP-4022-013-004.
US Refers to Tech Specs:
3.3.1 RTS Instrumentation (Table 3.3.1-1, Functions 2a,2b, 3, 6 18c&d Conditions A, C, D, & L Place channel in trip - 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />)
P-8 & P-10 must be verified in Correct Condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of channel failure.
- 3.2.3 AFD Only applicable if Rods drive AFD outside of target band Restore AFD to within target band - 15 minutes
Appendix D Required Operator Actions Form ES-D-2 Page 6 of 18 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 2 Event
Description:
Power Range Channel N42 Control Power fails/ Power Restoration Time Position Applicant's Actions or Behavior 3.2.4 QPTR May be referenced.
Appendix D Required Operator Actions Form ES-D-2 Page 7 of 18 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 3 Event
Description:
East Main Feed Pump Trip Time Position Applicants Actions or Behavior BOP Recognizes indication of MFP trip and reports annunciator Panel
- 115, Drop 1, East FPT DCS Trouble, DCS Screen East FW Pump Tripped Status US Directs operators to perform the immediate actions per OHP-4022-055-001, Loss of One MFP.
RO Performs the following immediate actions:
- 1. Verify Turbine Load is automatically reduced to < 60%
- 2. Verifies rod control switch in AUTO and functioning properly.
BOP Performs the following immediate actions:
- 1.
Close the East FW Pump Emergency Leakoff Valves FRV-251 & 252
- 2.
Adjust West FW Pump speed/integration as required
- 3.
Start Standby Hotwell & Condensate Booster Pumps if required
- 4.
Start AFW pumps if required.
US Checks the immediate actions and directs operators to perform the subsequent actions of OHP-4022-055-001, Loss of One MFP.
BOP Verify SG levels are stable at or returning to normal (44%).
RO Initiate normal or emergency boration flow (if required) to maintain rods above the RIL (~1.89 * % power) using Attachment C or D of OHP-4022-055-001 CREW May enter Technical Specification 3.4.1 RCS Pressure, Temperature, and Flow DNB Limits (Condition A) if Pressure lowers to <2168 psig. (2200 psig admin limit) (may use PPC times to track TS entry/exit times)
Appendix D Required Operator Actions Form ES-D-2 Page 8 of 18 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 4,5 Event
Description:
Stabilize Plant And Recover AFD from FW Pump Trip Time Position Applicants Actions or Behavior US Direct operator actions to restore normal system alignment: (as required) OHP-4022-055-001 (Steps 8-16)
Restore AFD to required Band Restore Megawatt Control to OUT Return W MFP to DP control Check ALL PRZ Backup Heaters on Reset Steam Dump Load Rejection Stop running AFW pumps and align for standby condition (Attachment B)
Complete FW Pump Shutdown Align Condensate system for current plant conditions RO Borate to position rods to restore AFD to within Target Band (Attachment C or D of OHP-4022-055-001)
BOP Stop AFW Pumps and Place in Standby (Attachment B)
Stabilize West FW pump speed and restore required DP Reset Steam Dump Load Rejection Align Condensate system for current plant conditions
Appendix D Required Operator Actions Form ES-D-2 Page 9 of 18 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 6 Event
Description:
- 11 RCP vibrations that require a manual Reactor Trip Time Position Applicants Actions or Behavior RO Recognizes indication of RCP vibes and reports Annunciator Panel 107 Drop 52 RCP VIBRATION HIGH US Enters OHP-4022-002-001, Malfunction of a Reactor Coolant Pump BOP Reports #11 RCP vibes are 15 mils and rising US / RO Check RCP conditions:
RCP Seal Leakoff normal RCP Seal Injection normal VCT Temp normal BOP Reports #11 RCP vibes have reached 20 mils and FOP criteria requires going to step 15.a Reactor Trip US Performs Step 15 RNO and directs RO to Trip the Reactor
Appendix D Required Operator Actions Form ES-D-2 Page 10 of 18 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 7/8 Event
Description:
Pressurizer Steam Space Rupture, Auto SI Failure Time Position Applicant's Actions or Behavior US Directs RO/BOP to perform the immediate actions of OHP-4023-E-0, Reactor Trip or Safety Injection.
RO Performs the immediate actions of OHP-4023-E-0:
Verifies reactor trip Stop RCP # 11 (per OHP-4022-002-001 Step 15 RNO)
BOP Performs the immediate actions of OHP-4023-E-0:
Checks turbine trip Checks power to AC emergency buses RO Receives Alarms on Panel 104 Drop 41, 105 Drops 31 / 32 due to Containment Temperature and Pressure Recognize and reports abnormal RCS leakage:
RCS pressure lowering with PZR Heaters ON.
Rising Containment dew point, pressure, and radiation.
Appendix D Required Operator Actions Form ES-D-2 Page 11 of 18 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 7/8 Event
Description:
Pressurizer Steam Space Rupture, Auto SI Failure Time Position Applicant's Actions or Behavior CREW Critical Task #1 Check SI Actuated Safety Injection Actuated Status Light - NOT LIT Identifies That BOTH CCP leakoff valve "Safety Injection Signal" white lights - NOT LIT Determines that SI is Required due to Pressurizer Pressure Lowering and Containment Pressure Rising Manually Actuate Safety Injection to establish High Head Injection Flowpath
-OR-NOTE: May be performed in E-0, Attachment A.
Manually Start SI and CCP pumps Manually Align Valves BIT Inlet Valves ICM-255 -AND/OR ICM-256 - OPEN BIT Outlet Valves ICM-250 -AND/OR ICM-251 - OPEN
- VCT to CCP Valves QMO-451 -AND/OR QMO-452 - CLOSED US Ensures immediate actions of OHP-4023-E-0 are completed Directs subsequent actions of OHP-4023-E-0.
US/RO Foldout Page - RCP Trip Criteria:
Stop all RCPs when RCS is < 1300 psig and CCP/SI pump running BOP Manually controls AFW flow to maintain SG narrow range levels 13% - 50% once one SG narrow range level is greater than 13%.
RO/BOP Completes actions of OHP-4023-E-0 through step 19 as directed.
RO/BOP Performs manual actions of OHP-4023-E-0, Attachment A as directed by US.
US/RO Checks if RCS is Intact - NO
Appendix D Required Operator Actions Form ES-D-2 Page 12 of 18 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 7/8 Event
Description:
Pressurizer Steam Space Rupture, Auto SI Failure Time Position Applicant's Actions or Behavior US Announces transition to OHP-4023-E-1, Loss of Reactor or Secondary Coolant and directs operator actions.
RO/BOP Completes actions of OHP-4023-E-1 through step 12 (Check if RCS Cooldown and Depressurization is required) as directed.
BOP Restore SG narrow range levels >20%, but < 50%.
US/RO Checks if SI Termination Criteria is MET:
RCS Subcooling >40°F Secondary Heat Sink (SG >13% or AFW Flow >240x103)
RCS Pressure rising or stable - NO (May be Rising See next Step)
Pressurizer Level >16%
Crew Transition to OHP-4023-ES-1.1, Safety Injection Termination if criteria is met.
OHP-4023-ES-1.1 Actions are listed on Page 13.
IF SI Termination Criteria are NOT met, THEN OHP-4023-E-1 Actions Are Continued on Page 14.
Note:
Crew may transition to SI termination if criteria are met. This may involve stopping ECCS pumps and realigning charging until parameters change causing them to restart equipment and return to E-1 or ES-1.2. There are several points of transition to ES-1.2 from ES-1.1. The ES-1.1 Steps are listed below. The Scenario may be terminated upon transition to ES-1.2 US Announces transition to OHP-4023-ES-1.1, Safety Injection Termination (step 6 of OHP-4023-E-1).
RO/BOP Reviews OHP-4023-ES-1.1, Foldout Page Criteria.
Monitors RCS Subcooling >40°F and PZR Level >16%, if NOT realign ECCS and GO TO OHP-4023-E-1
Appendix D Required Operator Actions Form ES-D-2 Page 13 of 18 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 7/8 Event
Description:
Pressurizer Steam Space Rupture, Auto SI Failure Time Position Applicant's Actions or Behavior US Directs Actions of OHP-4023-ES-1.1 RO/BOP Performs the following as directed:
Resets both trains of Safety Injection Resets both trains of Phase A Establishes Control Air to Containment CREW Check if RCS Pressure is stable or Rising If Lowering, Transition to OHP-4023-ES-1.2 RO/BOP Performs the following as directed:
Establish Normal Charging Flowpath Isolate BIT Injection CREW Check if:
Pressurizer Level is stable and RCS Pressure is Stable or Rising If NOT, Transition to OHP-4023-ES-1.2 CREW Check if transition is made to OHP-4023-ES-1.2, then perform the following:
Reset SI Reset Containment Isolation:
Establish Control Air To Containment TERMINATE SCENARIO US/RO Check if RHR can be stopped:
Check RCS Pressure > 300 psig and stable Reset SI Shutdown RHR and place in Standby
Appendix D Required Operator Actions Form ES-D-2 Page 14 of 18 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 7/8 Event
Description:
Pressurizer Steam Space Rupture, Auto SI Failure Time Position Applicant's Actions or Behavior BOP Shutdown Unloaded EDGs.
US Announces transition to OHP-4023-ES-1.2, Post LOCA Cooldown and Depressurization (at step 12).
CREW Check if transition is made to OHP-4023-ES-1.2, then perform the following:
Reset SI Reset Containment Isolation:
Establish Control Air To Containment TERMINATE SCENARIO
Critical Task Summary Page 15 of 18 Task Elements Results
- 1 Manually Control SG#12 Level on FFC-220 Failure Cueing:
- Panel #113 Drops 43 & 32
- FFC-220 Indication Lowering
- FRV-220 opening Performance Indicators:
- Place FRV-220 in Manual and control SG #12 Level to maintain it 15% - 67% preventing a Reactor Trip.
(May Select FFC-221 as Controlling Channel and Place\\Leave FRV-220 In Auto)
Performance Feedback:
- 2 Manually Actuate Safety Injection Cueing:
- Pressurizer Pressure < 1775 psig
- Pressurizer Pressure Extreme Low PNL 108 Drop 10 Check SI Actuated Safety Injection Actuated Status Light - NOT LIT (E-0, Step 4.a)
-AND-Check BOTH CCP leakoff valve "Safety Injection Signal" white lights - NOT LIT Performance Indicators:
Before transitioning from E-0:
Actuate 1 Train of SI Performance Feedback:
ECCS flow is indicated to at least one train (as indicated by flow on cold leg BIT injection flowmeters)
One Train of Phase A Isolation is complete per E-0, Attachment A SAT / UNSAT
Scenario Instructor Actions Page 16 of 18 Setup:
- 1. Reset to IC-303 MOL; 79% power, 850 MW, 799.86 ppm, 565.51 F 194 Steps on D
- 2. Place ALL Pressurizer Heaters In ON
- 3. Reset control rods and check group step counters.
- 4. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position.
- 5. Advance chart recorder paper & clear chart recorder memory.
- 6. Activate the following (pre-load) malfunctions:
Train A Safety Injection Auto Failure Train B Safety Injection Auto Failure Set Reactor Trip on ET1 Reactor Trip on ET1 U1_RP10A U1_RP10B U1_RC16
Scenario Instructor Actions Page 17 of 18 Scenario Events:
EVENT #1 ICF U1_FFC220 to 0 over 120 Seconds to cause Feed Flow Channel FFC-220 to fail low on SG 2 EVENT #2 IMF U1 NI10B to cause a NI42 Power Range to fail High EVENT #3 IMF U1_FW05A to cause the East Main Feed Pump Trip EVENT #4 No additional Actions EVENT #5 No additional Actions EVENT #6 IMF U1_RC11A ramp from 8-15 to cause RCP #1 Vibration Rise U1_FFC220 U1_FW05A U1_NI10B U1_RC11A
Scenario Instructor Actions Page 18 of 18 EVENTS #7& 8 IMF RC16 to cause a Pressurizer Steam Space Break (Auto SI Failure already entered)
Perform Local actions after entry into E-0 as requested:
- Locally stop U1 Ice Condenser AHUs MRF CHR01 to OFF
- Aux Tour will monitor Spent Fuel Pool Level and Temperatures
- Place PACHMAS in service - MRF CHR02 or 03 with 10 min delay.
OR (both have 10 minute delay built in)
- U2 has aligned CR vent for U1 SI, Fan 2-HV-AS-2 is running.
If directed to secure EDG jacket water pumps select OFF then AUTO Remote OFF AUTO EGR 03A EGR 03B EGR 04A EGR 04B U1_EGR03A U1_EGR03B U1_CHR02 U1_EGR03B U1_EGR04B U1_EGR04B U1_EGR04A U1_RC16 U1_CHR01 U1_CHR03 U1_EGR03A U1_EGR04A