ML20357A566
| ML20357A566 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/13/2018 |
| From: | Chuck Zoia Operations Branch III |
| To: | Indiana Michigan Power Co |
| Zoia C | |
| Shared Package | |
| ML17164A385 | List: |
| References | |
| Download: ML20357A566 (10) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: DC COOK 1 & 2 Scenario No.: 1 Op-Test No.: _________
Examiners: ___________________________ Operators: ____________________________
Initial Conditions: 80 % Power .
Turnover:__Reduce power to perform Turbine Valve testing________________________________
Critical Tasks:_Trip RCPs, Initiate 1 train of Safety Injection .
Event Malf. No. Event Event No. Type* Description 1 U1_MPC253 I-RO Turbine Impulse Transmitter (MPC-253) fails LOW
@0 TS 2 R-RO Recover RODs and temperature 3
U1_MFC 121 I-BOP Steam Flow Channel (MFC-121) failure fails Low
@0 TS 4
ED07B C-RO PZR HTR Transformer Fails (11PHC Fails).
TS 5 U1_RC19A M Pressurizer Safety Starts leaking and progresses to full open
@ 100%
6 U1_RP10A C-RO Train A Safety Injection signal failure to actuate in AUTO 7 U1_RP10B C-RO Train B Safety Injection signal failure to actuate in AUTO or U1_RP11B C-BOP Manual on the PRZ panel only 8 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
Appendix D Scenario Outline Form ES-D-1 Event Summary A failure of Turbine Impulse instrument (MPC-253) results in a control rod insertion. The auto rod control circuit will see a power mismatch causing the rods to move in, decreasing reactor power and Tave. The auto rod control circuit will also see a decreased Tref (min 547 deg f) causing rods to move in. RO will be required to place rod control in manual. Crew will be required to implement AOP actions to stabilize the plant and trip Bistables.
The restoration of Tavg will require reactivity manipulations SG Steam Flow instrument (MFC-121) fails Low. This will result in the closing of #2 SG FWRV (FRV-220) to lower feedwater flow. The BOP will be required to take manual control and regulate FRV-230.
The Crew will be required to implement AOP actions to stabilize the plant and trip bistables.
A failure of the PZR HTR Bus 11PHC will occur. The PZR SCR heater control will need to be transferred to 11PHA. The crew should also refer to Technical Specifications.
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 (Trn B from SIpanel only) 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 Manually Actuate SI Stop all running RCPs when RCS pressure is below 1300 psig Procedures E-0, Reactor Trip or Safety Injection E-1, Loss of Reactor or Secondary Coolant
Appendix D Scenario Outline Form ES-D-1 Facility: DC COOK 1 & 2 Scenario No.: 2 Op-Test No.: _________
Examiners: ___________________________ Operators: ____________________________
Initial Conditions: ____ Unit is at 50% power .
Turnover:__The crew is in procedure 1-OHP-4021-001-003 and has completed Step 4.11.3 .
A tube leak on S/G #3 requires a T.S. shutdown .
Critical Tasks Isolate #13 Steam Generator, Cooldown RCS, Depressurize RCS to stop #13 SGTR leakage .
Event Malf. No. Event Event No. Type* Description 1 U1_RC24C R-RO SG Tube Leakage requiring shutdown
@ 20 - 2 N-gpm BOP 2 U2_EESW C- Unit 2 East ESW Pump Trip, Unit 1 West ESW fail to Start Short Circuit BOP U1_WPS70 (Need Alarm 104 drop 78 on trigger with drop 66) 5 fail 3 U1_NPP151 I-RO Pressurizer Pressure Channel Fails High to 2500 TS 4 U1_RX08A C-RO NRV-163 Controller Fails Open in Auto (insert with NPP151
@ 100% failure) 5 U1_MPP230 I-BOP SG Pressure Channel MPP-230 Fails Low.
to 1 over 30 TS Sec 6 U1_RC23C M SG #13 Tube Rupture 500 GPM
@ 50 ~ 500 Gpm 7 U1_RP13A C- Phase A Fails to auto Actuate U1_RP13B BOP 8 U1_RC15A C-RO NRV-163 & NRV -164 fail to OPEN (PORV must be used to U1_RC15B depressurize)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Event Summary The scenario begins at 50% power with a shutdown required due to SG tube leakage. The RO and BOP will perform actions of the rapid shutdown procedure to bring the plant offline.
A trip of the UNIT 2 East ESW Pump and failure of the West U1 ESW pump will require the BOP to start the West ESW pump on unit 1.
After the Crew has addressed the ESW failure, the 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, then restore pressurizer pressure control to auto.
Along with the Pressure Channel failure, a failure of the Pressurizer Spray Valve controller for NRV-163 to 100% causes NRV-163 to go full open. RCS pressure will begin to lower. The RO will be required to take manual control of NRV-163 and close the spray valve then return pressure to the normal band.
Pressurizer pressure control may still be operated in AUTO with NRV-164.
The next event will involve the SG Pressure Channel MPP-230 fails low. The BOP will be required to take manual control SG 13 Feedwater Regulating Valve FRV-230 to stabilize level. The crew will address the failure with an Abnormal Operating Procedure, address Technical Specifications, select an operable channel, and restore automatic control.
A Steam Generator Tube Rupture will build in to 500 gpm over 5 minutes. The crew will perform a Reactor Trip and Safety Injection. The crew should identify the Steam Generator Tube Rupture on #13 SG. The crew will transition to E-3 to isolate #13 SG. As the crew performs the actions of E-3 to depressurize the SG the Pressurizer Spray Valves will fail to open requiring use of the PORV for depressurization, The scenario will terminate when the crew has completed the cooldown, depressurization, and terminated SI.
Critical Tasks Isolate #13 Steam Generator Cooldown RCS Depressurize RCS to stop #13 SGTR leakage Procedures E-0, Reactor Trip or Safety Injection E-3, Steam Generator Tube Rupture
Appendix D Scenario Outline Form ES-D-1 Facility: DC COOK 1 & 2 Scenario No.: 3 Op-Test No.: _________
Examiners: ___________________________ Operators: ____________________________
Initial Conditions: ___Power is stable @ 1e-8 in Intermediate Range with AFW in service .
Turnover:_______Raise Power to 3% to place MFP in service .
Critical Tasks Manually Trip Reactor, Actuate SI, Establish Cold Leg Recirculation Event Malf. No. Event Event No. Type* Description 1 R-RO Raise Power to 3% using rods 2 N- Control SG levels using AFW BOP 3 U1_NPP15 I-RO Pressurizer Pressure Channel Fails Low 1 @ 1700 TS 4 U1_BLP1 C- Turbine Lift Pump Failure - Turning Gear Trips Off U1_LPS39 BOP 5 U1_MPP21 I-BOP SG PORV Pressure Transmitter Failure 2 to 1500 TS 6 U1_RC10A C-RO RCS Leakage ramps in over 5 min. ramp to 10%
7 U1_RC01A M RCS LOCA over 30 second. ramp at 50%.
8 U1_RP01A C- Auto RX trip Fails - Manual Works U1_RP01B RO 9 U1_RP10A I(ATC) Auto SI Fails - Manual Works U1_RP10B 10 U1_RP16B C- CTS (West) Train B - fails to actuate (AUTO/MANUAL)
U1_RP17B BOP
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Event Summary The scenario starts with the plant stable at ~ 1e-8 amps on IR . The crew will be directed to withdraw rods to raise power to 3 % to roll the Main FW pump. The BOP will need to control SG levels with AFW in Manual .
After power has been raised, The Controlling Pressurizer Pressure channel will fail low.
The RO will be required to take manual control of Pressurizer Pressure Master Controller and restore normal pressure control. The Crew will implement the Abnormal Operating Procedure, address Technical Specifications, select an operable channel, and restore pressure control to automatic.
The #1 bearing Lift Pump will trip off and the perturbation will cause the turning gear to trip. The BOP will need to bypass the Lift Pump Interlock to restart the turning gear.
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 AOP actions, and the US will need to declare the associated radiation monitor inoperable.
Shortly after the SG Pressure Channel failure, a slowly developing RCS leak will require the RO to control Charging in an attempt to stabilize the plant.
The RCS leakage will develop into a large break LOCA. The plant will NOT automatically trip and Automatic Safety Injection will NOT actuate. The Crew will be required to manually trip the reactor and actuate Safety Injection. The BOP should identify that train B of Containment Spray/Phase B has failed to actuate and align as required. The crew will transition to E-1 and to ES-1.3 to align for cold leg recirculation. The scenario will terminate when the crew has aligned ECCS for cold leg injection.
Critical Tasks Manually Trip Reactor Manually Actuate SI Establish Cold Leg Recirculation Procedures E-0 Reactor Trip or Safety Injection E-1 Loss of Reactor or Secondary Coolant ES-1.3 Transfer to Cold Leg Recirculation
Appendix D Scenario Outline Form ES-D-1 Facility: DC Cook 1 & 2 Scenario No.: 4 Op-Test No.: _________
Examiners: ___________________________ Operators: ____________________________
Initial Conditions: ______80% Power_____________________________________________
Turnover: Start the West TACW pump and stop the East TACW Pump .
Critical Tasks Align High Head Injection, Trip RCPs, Make-up / Reduce RWST Outflow Event Malf. No. Event Event No. Type* Description 1
N-BOP Swap Turbine Aux Cooling Water (TACW) Pumps.
2 U1_CV04C C-RO Letdown Orifice valve fails closed 3 U1_NLP151 I-RO Pressurizer Level Channel Failure (perform before letdown
@ 0% TS is restored) 4 U1_FFC220 I-BOP Feed Flow Channel Fails low on SG 2
@ 0 over 20 TS sec 5
U1_FW05A C-BOP East Main Feed Pump Trip R -RO 6 R-RO Stabilize Plant And Recover AFD from FW Pump Trip N-BOP 7 U1_RC02C M Hot Leg LOCA 100%
8 U1_ED05H C-BOP Loss of Power to T11D 9 U1_RP19G, C-RO Slave Relay failures: High Head [ECCS] Charging valves fail U1_RP20G to align (Preloaded) 10 U1_WRHR C- BOP RHR Pump Fails to Start ECA-1.1
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Event Summary The Crew is directed to start West TACW pump and stop East TACW Pump.
After the TACW pump swap, the in-service letdown orifice valve will fail closed. The RO will need to restore letdown through a different valve.
Prior to restoring letdown, the controlling Pressurizer Level channel NLP-151 fails LOW. Charging flow control valve (QRV-251) opens to raise charging flow which causes actual pressurizer level to rise.
Pressurizer water level low alarm comes in (letdown was previously isolated) and all pressurizer heaters will de-energize. The RO will need to take manual control of the Pressurizer Level controller and restore level. The crew should implement the AOP, stabilize the plant, trip bistables, select an operable channel, and restore letdown and level control to auto.
The #2 SG Feed Flow instrument (FFC-220) fails LOW. This will result in the opening of #2 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 AOP 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 stabile FW pump speed control.
The RO will be required to control reactivity while the BOP monitors the SG levels.
A Hot Leg break will result in a Reactor Trip and Safety Injection. On the SI, various slave relay failures will cause the High Head Charging (ECCS) Injection flowpath to fail to align. The RO will need to manually align the High Head Injection Valves. The crew will enter E-0 and transition to E-1. The West RHR pump will trip resulting in a loss of Recirculation Capability requiring entry into ECA-1.1.
On the Generator Trip, a loss of 4 KV bus T11D causes a trip of the running Charging Pump, Component Cooling Pump, and ESW pump. The Standby ESW (U2) and CCW pumps will start. (The East RHR and North SI pumps will also be unavailable)
Critical Tasks Align High Head Injection Trip RCPs Make-up / Reduce RWST Outflow Procedures E-0, Reactor Trip or Safety Injection E-1, Loss of Reactor or Secondary Coolant ECA-1-1, Loss of Emergency Coolant Recirculation
Appendix D Scenario Outline Form ES-D-1 Facility: DC Cook 1 & 2 Scenario No.: 5 Op-Test No.: _________
Examiners: ___________________________ Operators: ____________________________
Initial Conditions: ___100% power .
Turnover: Reduce power for East AFW pump inoperable > 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> - Shutdown in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> .
Critical Tasks Insert Negative Reactivity, Isolate the Faulted Steam Generator .
Event Malf. No. Event Event No. Type* Description 1 U1_QLC45 I-RO VCT Level Channel QLC 452 fails HIGH 2 to 100 TS 2 R-RO Perform Rapid Power Reduction N-BOP 3 U1_RX11D C-BOP SG PORV Controller Failure
@100%
4 U1_ECP C-RO East CCP pump trips TS 5 U1_BLP111 I-BOP #11 SG level Transmitter fails LOW
@ 0 over 30 TS sec 6 U1_MS01D M-ALL Steam Line Break inside Containment (#14 SG)
@ 20 over 2 min 7 U1_RP03A C-RO AUTO/MANUAL Reactor trip actuation failure (ATWS)
U1_RP03B 8 U1_RP07A C-BOP Steam Line Isolation fails to AUTO actuate U1_RP07B (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Event Summary The scenario starts with the East MDAF pump inoperable due to a failed coupling. The crew must perform a shutdown within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Prior to reducing power, the VCT Level Channel QLC-452 fails high. This will cause the QRV-303 VCT Divert valve to fully divert letdown flow to the HUT. The Operator is required to take Manual control of QRV-303 and direct letdown flow back to the VCT. Crew will be required to implement AOP actions to stabilize the plant and address Technical Specifications (TRM).
If required, the crew will be directed by the Shift Manager to lower power.
The next event will involve a trip of the East Charging Pump. This will result in the loss of charging and letdown. RO will be required to manually start the West Charging Pump to restore charging flow. Crew will be required to take manual control of charging and restore letdown to stabilize the plant.
A failure of the SG #11 PORV Controller while in Auto will occur. The Controller will fail causing PORV MRV-213 to fully open. This will also cause Reactor power to slightly rise. The BOP will need to take manual action to close the PORV and the US will need to declare the associated radiation monitor inoperable.
The #11 Steam Generator Level instrument (BLP-111) fails LOW. This results in a higher feedwater flow and Steam Generator level will rise. BOP will be required to take manual control and restore normal level. Crew will be required to implement AOP actions to stabilize the plant and address Technical Specifications.
The main event will involve a Steamline Break inside containment on the #14 SG. The unit will NOT trip and a Safety Injection will actuate. The reactor must be locally tripped. The crew will implement FR-S.1 actions until reactor is subcritical. Failure of the Feed Water Isolation actuation circuit will require a manual actuation. As the crew performs the actions of FR-S.1, they should identify the Main Steamline Break inside containment on the #14 SG. The crew will Isolate the SG in FR-S.1 or eventually transition to E-2 to isolate #14 SG. The scenario will terminate when the crew has isolated the Faulted SG.
Critical Tasks Insert Negative Reactivity Isolate the Faulted Steam Generator Procedures E-0, Reactor Trip or Safety Injection E-2, Faulted Steam Generator Isolation FR-S.1, Response to Anticipated Trip without Scram