ML20356A149
| ML20356A149 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/25/2020 |
| From: | David Reeser Operations Branch III |
| To: | Indiana Michigan Power Co, NRC/RGN-III/DRS/OLB |
| Reeser D | |
| Shared Package | |
| ML19121A510 | List: |
| References | |
| Download: ML20356A149 (9) | |
Text
Scenario Instructor Actions 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 Event Malf. No. Event Event No. Type* Description 1
N-BOP Swap #1 Control Fluid Pump for #3 Control Fluid Pump 2 R-RO Raise Reactor Power to 100%
3 U1_101PW C-RO PW Pump Trips \ Fails to Auto Start 2N 4 MPP230 to I-BOP SG Pressure Channel MPP-230 Fails Low.
1 over 30 Sec TS 5 U1_NLP152 I-RO Pressurizer Level Control Bi-stable channel fails Low to 0%
TS 6 U1_HWPS C- Hotwell Pump Trip - Standby Fails to Start (Adjust U1_CPS101 BOP Hotwell Bypass flow to lower pressure post trip)
N U1_CPS103 S
7 U1_RC19A M Pressurizer Safety Starts leaking and progresses to full
@ 100% open 8 U1_RP10A C-RO Train A Safety Injection signal failure to actuate in AUTO 9 U1_RP10B C-RO Train B Safety Injection signal failure to actuate in AUTO U1_RP11B C-BOP or Manual on the PRZ panel only 10 U1_RP19D C-BOP 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 Event Summary
Scenario Instructor Actions The crew is directed to swap Control Fluid pumps due to potential problem with one of the running pumps.
The plant is at 80% power and the crew is directed to raise 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 changed power, SG Pressure Channel MPP-230 fails low. The BOP will be required to take manual control 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
Scenario Instructor Actions 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 Malf. No. Event Event No. Type* Description 1 U1_TACSE C-BOP East Turbine Aux Cooling Water pump trip Stator Short 2 R- RO Raise power 3 N-BOP Control SG Level in manual 4 U1_NPP151 I-RO Pressurizer Pressure Channel Fails High to 2500 TS 5 U1_MPP212 I-BOP SG PORV Pressure Transmitter Failure to 1500 TS 6 U1_ECP C-RO Trip of 1E CCP short circuit TS 7 U1_RP08B M-ALL Inadvertent FW Isolation and Intermediate Range U1_NI06 Failure 8 U1_RP03A C-ALL Reactor Trip Breakers fail to open U1_RP03B 9 U1_WMDAF C-BOP WMDAFW Pump trip P Short
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Scenario Instructor Actions Event Summary The Crew is directed to raise 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.
Next 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.
Next 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. 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
Scenario Instructor Actions 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, Isolate #14 Steam Generator, Actuate/Align CTS Event Malf. No. Event Event No. Type* Description 1 N-BOP Place an Additional Main FW Pump in Service 2 R-RO Raise Reactor Power to 100%
3 U1_NTP240 I-RO Loop 4 Tc fails high to 650 TS 4 U1_MFC140 I-BOP
- 14 SG Controlling Steam Flow Channel Fails Low
@0 TS 5
U1_ED07B C-RO PZR HTR Transformer Fails (11PHC Fails).
TS 6 Set C-BOP Main Steam Stop Valve Comes Off Detent (Open Limit Switch)
U1_MSVMR V210 .94 7
U1_MS01D M-ALL Steam Line Break inside Containment (#14 SG)
@ 20 over 2 min 8
U1_RP07A C-BOP Steam Line Isolation fails to AUTO actuate U1_RP07B 9
U1_RP16B C-RO CTS (West) Train B - fails to actuate (AUTO)
U1_RP20E Discharge Valves fail to Open U1_RP20J West CTS fails to Start 10 U1_ECSP C-RO East CTS pump Trip stator short
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Event Summary
Scenario Instructor Actions 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 raise 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 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 inside containment on the #14 SG. The unit will trip and a Safety Injection will actuate. Failure of the Main Steamline Isolation actuation circuit will require a manual actuation. As the crew performs the actions of E-0, they should identify the Main Steamline Break inside containment on the #14 SG. The crew will transition to E-2 to isolate #14 SG.
Containment Pressure will rise and CTS fails to Actuate. The crew may be required to transition to FR-Z.1 to restore CTS. The scenario will terminate when the crew has transitioned to ES-1.1.
Critical Tasks Stabilize SG Level on MFC140 Failure Isolate #14 Steam Generator Actuate/Align CTS Procedures E-0, Reactor Trip or Safety Injection E-2, Faulted Steam Generator Isolation FR-Z.1, Response to High Containment Pressure
Due to a reduction in the number of applicants to be examined, NRC2020 Scenario 4 was assigned as the spare scenario and is not included in this package.
Scenario Instructor Actions Facility: DC COOK 1 & 2 Scenario No.: NRC2020-5 Op-Test No.: _________
Examiners: ___________________________ Operators: ____________________________
Initial Conditions: 80 % Power .
Turnover: Restore power to 100% following Turbine Valve testing Critical Tasks: Stabilize SG#12 Level following FFC-220 Failure, Manually actuate safety Injection Event Malf. No. Event Event No. Type* Description 1 U1_FFC220 I-BOP Feed Flow Channel Fails low on SG #12
@ 0 over 20 TS sec 2 R-RO Raise Reactor Power to 100%
3 U1_FW05A C-BOP East Main Feed Pump Trip R -RO 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_NI10B I-RO 200 over 1 Power range detector (NI-42) fails high min TS 7
U1_RC11A C-RO #11 RCP vibrations, Manual Reactor Trip (E-0) ramps 8-15 8 U1_RC16 Major - Pressurizer Steam Space Rupture on Reactor Trip ALL 9 U1_RP10A C-RO Auto SI fails U1_RP10B
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Scenario Instructor Actions Event Summary The plant is at 80% power and the crew is directed to raise power to 100%.
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.
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 control reactivity while the BOP monitors the SG levels and secures AFW pumps.
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 PRNI failure to remove failed NI from service.
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