ML102220238
| ML102220238 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/21/2010 |
| From: | NRC/RGN-III |
| To: | American Electric Power, Indiana Michigan Power Co |
| References | |
| ES-D-1 | |
| Download: ML102220238 (80) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility:
Cook Plant Unit 1 & Unit 2 Scenario No.:
COOK 2010-01 Op-Test No.:
Crews 1,2,& 3 Examiners: _________________ Operators:___________________ _________________ ___________________
_________________ ___________________
Initial Conditions: IC-37, 78% pwr, 1021 ppm Boron, 8 GWD, 554°F Tave, CBD @196 steps, 848 MW
Turnover: Swap NESW pumps. 1E MDAFW OOS. Unit was holding at 78% power due to a small oil leak on the West MFW Pump that has recently been repaired, Blender line is full of PW.
Event No.
Malf. No.
Event Type* Event Description 1 N Start South NESW Pump and Stop the North NESW pump.
2 R Raise Reactor Power and Turbine Load 3
CBPN FW58B C-BOP North CB pump trip; Middle CB pump fails to start in AUTO 4 NTP111 to 650 F I-RO TS Loop 1 Hot Leg NTP-111 Temperature Transmitter Fails High 5 QTC302 @ 50 F C-RO Letdown Temperature Controller fails LOW 6 MPP212 to 100% I-BOP TS S/G 11 Pressure Transmitter MPP-212 Fails High 7 RC10A ramp to 20%
RC01A at 50% after 5
min. Major Large Break Loss of Coolant Accident on Loop 1 (Starts Out Slowly) 8 RP19D - Preload C-RO Slave Relay Failure: 1E RHR and SI Pumps Fail to Auto Start 9 WRHR C-RO 1W RHR Pump Trips 15 minutes after SI
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 Page 1 of 1 Cook Plant Unit 1 & Unit 2 Page 2 of 2 Summary The scenario starts with the plant at 78% power. Power escalation has been on hold for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> while repairs were made to the West MFW Pump oil leak.
The crew is directed to start the South NESW Pump and shutdown the North NESW pump. An AEO has been briefed and the starting party is ready for the pump start. After NESW Pumps have
been swapped, the crew is directed to raise power.
The next event is a trip of the North Condensate Booster pump. This will result in reduced feedwater capability. BOP will be required to manually start the Middle Condensate Booster pump.
Crew will be required to implement compensatory actions to stabilize the plant.
The Loop 1 Hot Leg NTP-111 Temperature Transmitter fails high. The rods will insert and power will have to be restored. The crew will need to enter an Abnormal Operating Procedure, defeat the
failed channel, address Technical Specifications, and restore rod control to auto.
A short time later a failure of the Letdown Temperature controller will cause the transmitted value to the letdown heat exchanger temperature controller and temperature indicator to fail at the selected severity level. Selection of a severity level lower than the controller setpoint (normally 120°F.) will cause the letdown temperature control valve (CRV-470) to move to its fully closed position in AUTO. Actual letdown temperature will rise resulting in a rising VCT temperatures. The operator may limit the consequences of this malfunction by taking manual control of CRV-470.
Next the SG 11 Pressure Channel MPP-212 will fail high, requiring the BOP to take manual control and close the SG PORV valve. The crew should implement an Abnormal Operating Procedure, stabilize the plant, trip bistables, and declare SG PORV Radiation Monitor Inoperable.
Shortly after the SG Pressure Channel failure, a LOCA will slowly develop resulting in a large break LOCA. The plant will trip and Safety Injection will actuate. As the crew performs the actions of E-0 they will note that the 1E RHR and SI pumps failed to auto start on the SI due to a slave
relay K610 failure. The crew will transition to E-1 and to ES-1.3 to align for cold leg recirculation.
The 1W RHR will trip 15 minutes into the event. The crew will have to align ECCS to the recirculation sump without the 1W RHR pump. The scenario will terminate when the crew has
aligned ECCS for cold leg injection.
Critical Tasks Establish Low Pressure SI (RHR)
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 Operator Actions Form ES-D-2 Op-Test No.: Crews 1,2,& 3 Scenario No.:
Cook 2010-01 Event No.:
1 Event
Description:
Start South NESW Pump and Stop the North NESW pump Time Position Applicant's Actions or Behavior US Directs BOP to start the South NESW Pump and shutdown the North NESW pump as per 12-OHP-4021-020-002, Attachment 1
"Placing An Additional NESW Pump In Service Or Removing A
Pump From Service."
BOP Starts South NESW pump after verifying its discharge valve 1-WMO-902 is open.
BOP Stops the North NESW Pump after closing the discharge valve 1-WMO-901. Re-opens North NESW Pump discharge valve. Place 1 "N" NESW pump in AUTO.
US/BOP Notifies Chemistry of NESW alignment change.
Cook Plant Unit 1 & Unit 2 Page 3 of 3 Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 1,2,& 3 Scenario No.:
Cook 2010-01 Event No.:
2 Event
Description:
Raise Turbine Load / Reduce Reactor Power Time Position Applicant's Actions or Behavior RO Calculates the dilution required per 1-OHP-4021-005-002, Attachment 9, Boration or Dilution Volume Determination.
RO Briefs crew on reactivity plan for power escalation.
US Reviews reactivity plan.
US Directs RO to commence Power Escalation in accordance with 1-OHP-4021-001-006.
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/BOP Commences escalation: Raises turbine load (reactor power) using the DCS HMI. Maintains Tave/Tref deviation within limits by dilution and turbine load adjustments. (Administrative Limits of +/- 2
°F) Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.
BOP Acts as peer checker for RO during blender operations and with RO verifies appropriate reactivity feedback.
BOP Monitors and maintains main electrical generator temperatures within limits per: 1-OHP-4021-059-001, Generator Stator Cooling Water System 1-OHP-4021-080-003, Generator Hydrogen Gas System Cook Plant Unit 1 & Unit 2 Page 4 of 4 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Crews 1,2,& 3 Scenario No.:
Cook 2010-01 Event No.:
3 Event
Description:
North CB pump trip; Middle CB pump fails to start in AUTO Time Position Applicant's Actions or Behavior BOP Recognizes feedwater control problem and reports annunciator:
Panel #116 Drop 73 - CB pump trip
US Directs operator actions to stabilize the unit and restore Condensate Booster pump capacity.
RO Monitor RCS & Secondary parameters for normal operations.
BOP Manually start the Middle CB pump May Place North CB pump switch to TRIP and back to NEUTRAL (Clear
Alarms)
Monitor Secondary parameters for normal operations
CREW Stabilize Power if required: Place Blender in auto Hold turbine at constant load on HMI Place Rods In Auto Cook Plant Unit 1 & Unit 2 Page 5 of 5 Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 1,2,& 3 Scenario No.:
Cook 2010-01 Event No.:
4 Event
Description:
Loop 1 RCS Hot Leg Temperature Tr ansmitter (NTP-111) Fails High Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Ann. Panel 111 which are indicative of a RCS RTD failure.
Note: Based on the response time of the crew, an auto makeup may occur for the VCT due to letdown charging mismatch due to erroneous auctioneered high Tavg indication.
RO Places rod control in manual after verifying no runback in progress.
Identifies that PRZ Program Level is affected by this failure.
US Enters and directs actions of 01-OHP-4022-012-003, Continuous Control Bank Movement procedure, if rods moved.
RO If 1-OHP-4022-012-003 is entered, then performs the following as directed:
- 1. Checks for no turbine runback
- 2. Ensures control rods are in manual with no rod motion
- 3. Checks rod position above low-low rod insertion limit
Note: Delta T failure may affect RIL Setpoint - Must use COLR or manually calculate.
- 4. Checks axial flux difference (AFD) within target band
- 5. Initiates restoration of equilibrium conditions using either: Control rod movement Turbine load adjustment
- 6. Identifies failed RTD channel
US Enters and directs actions of 1-OHP-4022-013-007, RCS RTD Instrument Malfunction procedure.
- 1. Ensures control rods are in manual.
- 2. Reports Loop 1 as failed RCS temperature channel and aligns the following switches: Tavg defeat switch to Loop 1 position T defeat switch to Loop 1 position T/OPT/OTT recorder switch to Loop 2, 3, or 4 US Initiates actions to trip bistables associated with RCS loop 1 RTD failure per Attachment A of 1-OHP 4022-013-007.
Cook Plant Unit 1 & Unit 2 Page 6 of 6 Cook Plant Unit 1 & Unit 2 Page 7 of 7 Op-Test No.: Crews 1,2,& 3 Scenario No.:
Cook 2010-01 Event No.:
4 Event
Description:
Loop 1 RCS Hot Leg Temperature Tr ansmitter (NTP-111) Fails High Time Position Applicant's Actions or Behavior US Refers to TS LCO: TS 3.3.1, Reactor Trip System (RTS) Instrumentation (Table 3.3.1-1) o Function 6, Overtemperature T. Condition D o Function 7, Overpower T. Condition D TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS)
Instrumentation (Table 3.3.2-1) o Function 4e, Steam Line Isolation - High Steam Flow in Two Steam Lines (per steam line), Coincident with Tavg - Low Low Condition D o Function 8c, ESFAS Interlocks - Tavg - Low Low, P-12.
Condition D May enter the following TS if Pressure lowers to <2050 psig during the transient: TS 3.4.1, RCS Pressure, Temperature, and Flow DNB Limits. Condition A May refer to the following if LEFM readings are Magenta on PPC TRM 8.7.14, Leading Edge Flow Meter (Mode 1 > 3250 applicability)
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 1,2,& 3 Scenario No.:
Cook 2010-01 Event No.:
5 Event
Description:
CVCS Letdown Temperature Controller QTC-302 Output Fails Low Time Position Applicant's Actions or Behavior RO Recognize and reports annunciator Panel 109 Drop 45, VOLUME CONTROL TANK TEMP HIGH, alarms which indicates a loss of CCW
cooling to the letdown heat exchanger.
Note: Crew may note that LEFM (Leading Edge Flow Monitor) indication on the PPC has become unreliable and may begin looking for cause prior to letdown heat exchanger alarm.
US Directs operator actions to restore proper temperature control for letdown.
RO Performs the following: Places 1-CRV-470, Letdown Temperature Control valve, controller to MANUAL Opens 1-CRV-470 and restores letdown temperature to normal Verifies letdown flow diverted to RC Filter Note: OP-1-5129 shows that QTS-301 (switch which causes letdown to bypass the Demineralizers) is separate from the QTC-302 controller that is failed low and causing letdown problems. The demineralizers may be placed back in service with this
malfunction in place.
US Initiates action to have MTI (or WIN Team) investigate problem with letdown temperature controller.
US May Refer to TS (LCO): TRM 8.7.14, Leading Edge Flow Meter (Mode 1 > 3250 applicability)
Cook Plant Unit 1 & Unit 2 Page 8 of 8
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 1,2,& 3 Scenario No.:
Cook 2010-01 Event No.:
6 Event
Description:
SG 11 Pressure Transmitter (MPP-212) Fails High Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #114 which are indicative of a steam pressure instrument failure and a SG PORV
being open (Drops 21, 44).
BOP Manually closes 1-MRV-213, SG 11 PORV.
RO Monitors thermal/reactor power indications to detect potential effects of additional steam flow.
US Enters and directs actions of 1-OHP 4022-013-012, Steam Generator Pressure Instrument Malfunction procedure.
BOP Performs the following actions as directed:
- 2. Reports 1-MPP-212 has failed high
US Declares 1-MRA-1601, Loop 1 Steam Line Radiation Monitor inoperable.
US Initiates actions to trip bistables associated with 1-MPP-212 Steam Generator Pressure Instrument Failure per Attachment A-3
of 1-OHP-4022-013-012.
US Refers to the following technical Specifications: TS 3.3.2 ESFAS Instrumentation (Table 3.3.2-1, Function 1e(2), Condition D) TRM 8.3.8 Radiation Monitoring Instrumentation (Table 8.3.8-1, Function 1B, Condition C*)
- Note: Loss of AUTO function for SG PORV makes the associated Steam Line Rad Monitor Inoperable per 1-OHP-4022-013-012.
Cook Plant Unit 1 & Unit 2 Page 9 of 9 Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 1,2,& 3 Scenario No.:
Cook 2010-01 Event No.:
7/8/9 Event
Description:
Large Break LOCA 1E RHR Pump and 1N SI Pump Fails to Auto Start 1W RHR Pump Trips (after 15 minutes)
Time Position Applicant's Actions or Behavior RO/US Acknowledge Ann. Panel 122, Drop 83, ICE CONDENSER INLET DOORS OPEN, alarm.
Determines that a loss of reactor coolant is occurring based on the
following: Pressurizer and VCT level change Charging and letdown flow mismatch Containment radiation monitoring trend Containment pressure rise Containment sump level rise US May enter and direct actions of 1-OHP-4022-002-020, Excessive Reactor Coolant Leakage procedure.
RO Performs the following actions if directed:
- 1. Manually raises charging flow to maintain pressurizer level
- 2. Manually adjusts seal injection flow (6-12 gpm / each RCP)
- 3. Reduces/isolates letdown flow to maintain pressurizer level
- 4. Attempts to determine RCS leak rate
US Directs RO/BOP to manually trip the reactor and initiate safety injection and perform the immediate actions of E-0, Reactor Trip or Safety Injection (based on RCS leak rate beyond charging system capability or rising
Containment Pressure).
RO/BOP Perform 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 RO/BOP Reviews E-0 Foldout Page Criteria.
US Directs subsequent actions of E-0.
Cook Plant Unit 1 & Unit 2 Page 10 of 10 Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 1,2,& 3 Scenario No.:
Cook 2010-01 Event No.:
7/8/9 Event
Description:
Large Break LOCA 1E RHR Pump and 1N SI Pump Fails to Auto Start 1W RHR Pump Trips (after 15 minutes)
Time Position Applicant's Actions or Behavior RO Performs the following actions as directed: Checks CTS actuated Checks Cntmt Isol phase B actuated Stops all RCPs (May stop on Phase B signal) Stops All Lower Cntmt Vent Fans (CLVs) Stops All CRDM Fans RO/BOP Performs manual actions of E-0 Attachment A as directed by US.
RO/BOP Critical Task #1 Attachment A of E-0 Checks all ECCS pumps running and manually starts
RO/BOP Attachment A of E-0 performs the following: Places 1-HV-ACRF-1, (non-running) control room pressurization fan in stop Places 1-HV-ACR-DA-1, C/R Vent Intake Damper to ISOL Places Cntmt Hydrogen sample bypass switches to bypass:
- Train A
20% [28%] - 50% once one SG narrow range level is > 14%
[28%]. CREW Completes all actions of E-0 through step 19 (Check If RCS Is Intact). US Announces transition to E-1, Loss Of Reactor Or Secondary Coolant (at step 19 of E-0).
RO/BOP Reviews E-1 Foldout Page Criteria (see NOTE regarding cold leg switchover criteria).
NOTE: Momentary entry into FR-P.1 may be required until crew verifies RHR flow sufficient to indicate a LB LOCA has occurred.
Cook Plant Unit 1 & Unit 2 Page 11 of 11 Cook Plant Unit 1 & Unit 2 Page 12 of 12 NOTE: When RWST level lowers to < 30% then the crew must immediately Transition to ES-1.3, Transfer To Cold Leg Recirculation.
See Page 13 for applicants actions or behaviors associated with ES-1.3, Transfer To Cold Leg Recirculation.
Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 1,2,& 3 Scenario No.:
Cook 2010-01 Event No.:
7/8/9 Event
Description:
Large Break LOCA 1E RHR Pump and 1N SI Pump Fails to Auto Start 1W RHR Pump Trips (after 15 minutes)
Time Position Applicant's Actions or Behavior US Directs actions of E-1, Loss Of Reactor Or Secondary Coolant.
RO/BOP Acknowledges Annunciator 106, Drop 45, RHR PUMPS MOTOR INSTANT TRIP and reports 1W RHR pump trip.
US/RO Identifies and reports that the 1W RHR pump has tripped: Recognizes one train of RHR has lost recirculation capability Verifies at least one train of cold leg recirculation capability exists May attempt 1 restart of 1W RHR per the ARP.
BOP Maintains SG narrow range levels 20% - 50%.
RO/BOP Performs the following as directed:
- 1. Resets both trains of Safety Injection
- 2. Resets both trains of Phase A
- 3. Stops running Emergency Diesel Generators (EDGs)
- 4. Dispatches operator to secure EDG jacket water pumps
RO/BOP Performs the following as directed
- 1. Opens control air valves to containment
- 2. Directs chemistry to initiate post accident sampling
US Check if transfer to cold leg recirculation is required (RWST
<30%)
Cook Plant Unit 1 & Unit 2 Page 13 of 13 Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 1,2,& 3 Scenario No.:
Cook 2010-01 Event No.:
7/8/9 Event
Description:
Large Break LOCA 1E RHR Pump and 1N SI Pump Fails to Auto Start 1W RHR Pump Trips (after 15 minutes)
Time Position Applicant's Actions or Behavior Applicants actions or behavior associated with ES-1.3, Transfer To Cold Leg Recirculation. US Announces transition to ES-1.3, Transfer To Cold Leg Recirculation when RWST level < 30% per: E-0, Foldout Page, Criteria 3 E-1, Foldout Page, Criteria 5 E-1, Step 13 RO/BOP Resets both trains of Safety Injection
US Directs actions of ES-1.3,. Transfer To Cold Leg Recirculation
RO/BOP Checks CCW return flow on each RHR Hx at 3000-3500 gpm. (may only perform for the East CCW HX)
RO/BOP Checks the following prior to switching over to cold leg recirc: RWST level < 20% Cntmt water level > MIN RECIRC LEVEL US/RO Critical Task #2 Directs/Performs switchover as follows: NOTE: If RWST level < 9% then stop CCPs and SI pumps.
- 1. Stops and locks out East CTS pump
- 2. Stops and locks out East RHR pump
- 4. Initiates valve closure: 1-IMO-310, East RHR pump suction 1-IMO-215, East CTS pump suction from RWST
- 5. Stops and locks out West CTS pump
- 6. Stops and locks out West RHR pump
- 8. Initiates valve closure: 1-IMO-320, West RHR pump suction 1-IMO-225, West CTS pump suction from RWST Cook Plant Unit 1 & Unit 2 Page 14 of 14 Appendix D Operator Actions Form ES-D-2 Op-Test No.: Crews 1,2,& 3 Scenario No.:
Cook 2010-01 Event No.:
7/8/9 Event
Description:
Large Break LOCA 1E RHR Pump and 1N SI Pump Fails to Auto Start 1W RHR Pump Trips (after 15 minutes)
Time Position Applicant's Actions or Behavior US/RO Critical Task #2 Continues to direct/perform switchover as follows:
- 9. Restores control power to 1-ICM-305, Recirc sump to east RHR/CTS pumps
- 10. Checks 1-ICM-305 open interlock: 1-IMO-310 fully closed 1-IMO-215 fully closed
- 11. Opens 1-ICM-305
- 13. Restores control power to 1-ICM-306, Recirc sump to west RHR/CTS pumps
- 14. Checks 1-ICM-306 open interlock: 1-IMO-320 fully closed 1-IMO-225 fully closed
- 15. Opens 1-ICM-306
- 16. May attempt to start the West RHR pump (1 restart allowed)
- 17. Starts the West CTS pump
- 19. Resets CTS actuation
- 20. Closes spray additive tank valves: 1-IMO-202, outlet valve 1-IMO-204, outlet valve 1-IMO-212, eductor supply valve 1-IMO-222, eductor supply valve TERMINATE SCENARIO Cook Plant Unit 1 & Unit 2 Page 15 of 15 Cook Plant Unit 1 & Unit 2 Page 16 of 16 CRITICAL TASK
SUMMARY
(COOK 2010-01)
Task Elements Results #1 Manually starts 1E RHR pump (one low-head ECCS pump)
Cueing: Check ECCS Pumps ALL running (E-0, Step 7 -
Att. A Step 1) Check RHR Hx Flow Indicated (E-1, Step 12.
RNO) Check Cold Leg Recirc Capability (E-1, Step 11)
Performance Indicators:
Starts the 1E RHR pump and ensures at least one train of low-head ECCS available for cold leg recirculation. Must be performed prior to ES-1.3, Step 6.s "Check At Least One RHR Pump - Running On
Recirculation Sump."
Performance Feedback:
1E RHR pump red run light lit 1E RHR pump current indicated 1E RHR pump flow indicated SAT / UNSAT
- 2 Establish Cold Leg Recirculation Flow Cueing: E-0 Foldout Page, Criteria 3 (switchover criteria) E-1 Foldout Page, Criteria 5 (switchover criteria) E-1, Step 13, Check For Transfer To CL Recirc.
Performance Indicators:
At least one train of ECCS/CTS running aligned to the containment sump. CTS and RHR pumps stopped for no longer than 5 minutes during switchover. No total interruption of ECCS flow (CHG and SI) to the RCS during switchover.
Performance Feedback:
At least one train of ECCS/CTS pumps running / indicating flow with suction
aligned to Recirc Sump.
SAT / UNSAT
SIMULATOR INSTRUCTIONS (COOK 2010-01)
Setup: 1. Reset to IC 37. Verify that the North and South CB pumps are running.
- 2. Reset control rods and check group step counters
- 3. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position
- 4. Advance chart recorder paper
- 5. Go to RUN and acknowledge/clear alarms
- 6. Tagout 1E MDAFP as follows:
Place control switch in pull-to-lock
Place clearance tag on control switch Activate remote function FWR61 , final value RO U1_FWR61 7. Activate the following pre-load override/malfunction:
Cook Plant Unit 1 & Unit 2 Page 17 of 17
- FW58B , Middle CB pump fails to start in AUTO U1_FW58B U1_RP19D
- RP19D (ECCS slave relay failure)
- 9.
- Assign Malfunction WRHR with a 15 minute delay to event trigger ET10 U1_WRHR 10.
- Assign Malfunction RC10A to 20% with a 2 minute ramp to event trigger ET7 U1_RC10A
- Assign Malfunction RC01A to 50% with a 5 minute delay to event trigger ET7 U1_RC01A (continued on next page)
SIMULATOR INSTRUCTIONS (COOK 2010-01)
EVENT #1 Starting party standing by for pump start.
1 "S" NESW ready for start
Report South NESW pump running fine with Sout h NESW strainer DP ~ 65" (Less than 100" limit)
EVENT #2 No additional actions required EVENT #3 When crew has performed t he required power change, CBPN (North CB pump trip)
U1_CBPN If contacted as AEO to investigate Condensat e Booster pump operations, report back after some 3 min. delay that all parameters are in the normal band and stable. Report an overcurrent trip on North CB pump breaker and t hat the motor smells of burnt insulation.
If Required (to have Control Rods returned to Au to), Direct as Shift Manager to hold the
power escalation.
Cook Plant Unit 1 & Unit 2 Page 18 of 18 SIMULATOR INSTRUCTIONS (COOK 2010-01)
EVENT #4 NTP-111 , final value 650, to fail Loop 1 Hot Leg RTD high U1_NTP111 If required, Prompt Crew as Shift Manager to Restore Reactor Power/Temperature while waiting for bistables to be tripped.
If directed to trip bistables for NTP-111 use:
ZLOSTMC2[6] to ON to simulate opening CH 1 cabinet Door ZLOSTMC2_U1[6] (Override Lights/Relays - RX Flux panel)
Remote Bistable RPR119 TS-411G RPR121 TS-412D RPR117 TS-411C U1_RPR119 U1_RPR121 Cook Plant Unit 1 & Unit 2 Page 19 of 19 RPR120 TS-411H RPR122 TS-412G RPR118 TS-411D U1_RPR117 U1_RPR120 U1_RPR122 U1_RPR118 Override ZLOSTMC2[2] to ON to simulate lifting Test Rack ZLOSTMC2_U1[1]
Delete Override ZLOSTMC2[7]
to simulate closing cabinet Door ZLOSTMC2_U1[6]
EVENT #5 After crew has recovered from the RTD Failure QTC302, Final Value 50 , to cause Letdown Temperature Controller to fail LOW U1_QTC302 SIMULATOR INSTRUCTIONS (COOK 2010-01)
EVENT #6 IMF RX17C , final value 1200 (MPP-212 fails hi) after crew has addressed the Letdown failure. U1_MPP212 If directed to trip bistables for MPP-212 use:
Override ZLOSTMC2[9] to ON to simulate opening cabinet Door ZLOSTMC2_U1[9] (Override Lights/Relays - RX Flux panel)
Remote Bistable RPR096 PS-516C U1_RPR096 RPR097 PS-516D U1_RPR097 Override ZLOSTMC2[4] to ON to simulate lifting Test Rack ZLOSTMC2_U1[4]
Delete Override ZLOSTMC2[9]
to simulate closing cabinet Door ZLOSTMC2_U1[9]
Cook Plant Unit 1 & Unit 2 Page 20 of 20 SIMULATOR INSTRUCTIONS (COOK 2010-01)
EVENT #7 After crew has recovered from the failed SG Pressure Channel.
Activate Trigger 7 to start the RCS Leak\LOCA Activate TRG 7 EVENT #8 No additional actions required EVENT #9 Previously setup with a 15 minute delay to trigger ET1 IF the RHR Pump fails to trip after 15 minutes WRHR U1_WRHR Local actions after entry into E-0:
Locally stop U1 Ice Condenser AHUs MRF CHR01 to OFF U1_CHR01 Place PACHMAS in service - MRF CHR02 or 03 with 10 min delay.
OR U1_CHR03 U1_CHR02 (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 Cook Plant Unit 1 & Unit 2 Page 21 of 21 EGR 04B U1_EGR03A U1_EGR03A U1_EGR03B U1_EGR03B U1_EGR04A U1_EGR04A U1_EGR04B U1_EGR04B Appendix D Scenario Outline Form ES-D-1 Facility:
Cook Plant Unit 1 & Unit 2 Scenario No.:
Cook 2010-02 Op-Test No.:
Crews 1,2,& 3 Examiners: _________________ Operators:___________________ _________________ ___________________
_________________ ___________________
Initial Conditions: IC-38 ,100% pwr; 979 ppm Boron, 8 GWD, 556°F Tave, CBD @ 219 steps, 1107 MW Turnover: Swap CCP pumps. 1E MDAFW OOS. 100% power, Blender line is full of PW. A Small Leak on the West MFW Pump will require a power reduction.
Event No. Malf. No.
Event Type* Event Description 1 N Start West CCP and Stop East CCP (RO Performs) 2 R
Lower Reactor Power and Turbine Load 3
RX21A @ 0 I-BOP TS SG Feed Flow Instrument (FFC-210) fails LOW 4
NLP151 @ 0 I-RO TS Controlling Pressurizer Level Channel (NLP-151) fails LOW 5
WCP C-RO TS West CCP pump trips (May insert prior to letdown restoration in
event 4) 6 RX11D @100%
C-BOP TS SG PORV Controller Failure 7
ED05H ED05D M Loss of Bus T11A due to fault on Bus 1A 1A RCP Bus Fault (Loss of RCS Flow in Loop 1) 8 TC02A RP07A RP07B C-BOP Main Turbine Fails to Trip/ Steam Line Auto Isolation Failure
9 FW51 C-BOP TDAFW pump T&TV failure due to blown control power fuse West AFW pump power is lost (East AFW is OOS)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 Page 1 of 18
Cook Plant Unit 1 & Unit 2 Page 2 of 18 Summary The scenario starts with the pl ant at 100% power. Power reduction is required due to a small West MFW Pump oil leak.
The crew is directed to start the West Charging Pump and shutdown the East Charging Pump. An AEO has been briefed and the starting party is ready for the pump start. After the Charging pumps have been swapped, the crew is directed to reduce power.
After a small power change, a LOW failure of #11 Steam Generator Feed Flow instrument (FFC-210) will occur. This will result in a rise in feedwater flow to #11 SG with corresponding SG level rise. The BOP will be required to take manual control of FRV-210. Crew will be required to implement AOP actions to stabilize the plant and trip bistables.
The controlling Pressurizer Level channel instrument (NLP-151) will fail LOW. This results in charging flow rising, Pressurizer level rising, Pressurizer heaters OFF, and letdown isolation. RO will be required to restore normal letdown and charging flow conditions. Crew will be required to implement AOP actions to stabilize the plant and trip bistables.
The West Charging Pump will trip. This will result in the loss of charging and letdown. RO will be required to manually start the East Charging Pump to restore charging flow. Crew will be required to take manual control of charging and restore letdown to stabilize the plant.
The next event will involve the failure of the SG #14 PORV Controller.
The Controller will fail causing PORV 1-MRV-243 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 main event will involve the loss of RCP Bus 1A and Safety Bus T11A requiring a reactor trip. Failure of the Reactor Protection circuit will require a manual turbine trip. As the crew performs the actions of E-0, they should identify th e failure to provide ade quate feed flow. An SI is expected due to the failure of turbine to trip. The CSFST for Heat Sink will indicate RED due to the loss of all AFW. The crew will imme diately transition to FR-H.1 and re-establish feedwater flow using the TD AFW pump. The scenario will terminate when the crew has established adequate feed flow.
Critical Tasks Manually Trip Turbine/Isolate Steam Lines Establish AFW flow for Secondary Heat Sink Procedures E-0, Reactor Trip or Safety Injection FR-H.1, Loss of Secondary Heat Sink Cook Plant Operator Actions Form ES-D-2 Op-Test No.:
Crews 1,2,& 3 Scenario No.:
Cook 2010-02 Event No.:
1 Event
Description:
Start West CCP and Stop East CCP Time Position Applicant's Actions or Behavior US Directs operator actions per 1-OHP-4021-003-001, Attachment 5: Start West CCP Stop East CCP BOP Reviews procedural precautions and actions in Attachment 5: Maximum charging flow for normal ops is 150 gpm If charging flow is < 75 gpm, mini-flow valve for running CCP must be OPEN BOP Performs actions per Attachment 5, Step 4.2: Start East & West CCP Lube Oil pumps Place 1-QRV-251 controller in MANUAL May need to Open QMO-225 Start West CCP Place West Lube Oil pump switch in STBY Stop East CCP May close QMO-226 Swaps AES Fan Alignment Place 1-QRV-251 controller in AUTO BOP Reports West CCP running and East CCP stopped Cook Plant Unit 1 & Unit 2 Page 3 of 18
Cook Plant Operator Actions Form ES-D-2 Op-Test No.:
Crews 1,2,& 3 Scenario No.:
Cook 2010-02 Event No.:
2 Event
Description:
Reduce Turbine Load / Reduce Reactor Power Time Position Applicant's Actions or Behavior RO Calculates boric acid addition per 1-OHP 4021-005-002, Attachment 9, Boration or Dilution Volume Determination.
RO Briefs crew on reactivity plan for power reduction.
US Reviews reactivity plan.
US Directs RO to commence Power Reduction in accordance with 1-OHP-4021-001-003.
RO Energize Pressurizer Heaters RO Performs BORATION: batch add OR Continuous: Place RC Makeup Blend control switch in STOP Place RC Makeup Blend Control Mode switch in BORATE Adjust BA Controller/Totalizer to the desired flow rate and/or amount. 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 power reduction:
- Lowers turbine load (reactor power) using the HMI.
- Maintains Tave/Tref deviation within limits by boration and turbine load adjustments. (Administrative Limits of +/- 2°F)
- Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.
BOP/RO Acts as peer checker for RO during blender operations and with the RO verifies appropriate reactivity feedback.
Cook Plant Unit 1 & Unit 2 Page 4 of 18
Cook Plant Operator Actions Form ES-D-2 Op-Test No.:
Crews 1,2,& 3 Scenario No.:
Cook 2010-02 Event No.:
3 Event
Description:
SG 11 Feedwater Flow Transmitter (FFC-210) Fails LOW Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #113 Drops 2, Level Deviation and 13, SF>FW Flow.
BOP Verifies 1-FRV-210, SG 11 MFW Reg. Valve controller in manual Raises controller output to match the operable feed flow channel with steam
flow, and
Restores SG 11 level to program.
US Enters and directs actions of 1-OHP-4022-013-015, Feedwater Flow Instrument Malfunction procedure.
BOP Performs the following actions as directed:
- 1. Restores SG 11 level using manual control of 1-FRV-210
- 2. Reports 1-FFC-210 has failed
- 3. Places 1-FS-510-C selector switch in channel 2 position.
- 4. Nulls and returns 1-FRV-210 controller to auto.
US Initiates actions to trip bistables associated with 1-FFC-210 FW Flow Failure per Attachment A-1 of 1-OHP-4022-013-015.
US Refers to Tech Specs and Administrative Technical Requirements TS 3.3.1 RTS Instrumentation (Table 3.3.1-1, Function 15 Condition D). TRM 8.3.6 ATWS Mitigation System Actuation Circuitry Cook Plant Unit 1 & Unit 2 Page 5 of 18
Appendix D Operator Actions Form ES-D-2 Op-Test No.:
Crews 1,2,& 3 Scenario No.:
Cook 2010-02 Event No.:
4 Event
Description:
Pressurizer Level Channel (NLP-151) Fails LOW Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel #108 (Drops 4, 5 and 50) indicative of a pressurizer (PRZ) level instrument failure.
RO Places 1-QRV-251, Charging Flow Controller OR PRZ Level Controller to manual and manually adjusts output to restore charging header flow and seal injection to normal.
US Enters and directs actions of 1-OHP-4022-013-010, Pressurizer Level Instrument Malfunction procedure.
RO Performs the following actions as directed:
- 1. Restores PRZ level using 1-QRV-251 or level controller
- 2. Reports 1-NLP-151 has failed
- 3. Ensures PRZ level control is in manual
- 4. Places PRZ Level CTRL selector switch in Ch 2 & 3 position
- 5. Places PRZ Level REC selector switch in 2 or 3 position NOTE: May Insert Event 5 at this time (Letdown restoration actions will be repeated in event 5)
- 6. Restore Letdown per 1-OHP-4021-003-001
- 7. Cycle PRZ Heaters to restore control
- 8. Nulls and returns 1-QRV-251 and PRZ Level Controller back to auto
US Initiates actions to trip bistables associated with 1-NLP-151 PZR Level Failure per Attachment A of 1-OHP-4022-013-010.
US Refers to Tech Specs (TS): TS 3.3.1 RTS Instrumentation (Table 3.3.1-1, Function 9 Condition D) TS 3.3.4 Remote Shutdown Instrumentation TS 3.3.3 Post Accident (Minimum channels met)
Enters action statement that requires bistables to be tripped within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Cook Plant Unit 1 & Unit 2 Page 6 of 18
Cook Plant Operator Actions Form ES-D-2 Op-Test No.:
Crews 1,2,& 3 Scenario No.:
Cook 2010-02 Event No.:
5 Event
Description:
1W Centrifugal Charging Pump (CCP) Trips Time Position Applicant's Actions or Behavior RO Recognizes and reports multiple annunciators on Panel #107, #108 and #109 which are indicative of a loss of charging capability. Loss of charging flow Loss of letdown flow Loss of RCP seal injection flow RO Recognizes and reports that running (1W) CCP has tripped.
US Directs RO to start the 1E CCP per annunciator response(s): 1-OHP 4024-108 Drop 20, Charging Flow < Min Set Point 1-OHP 4024-109 Drop 21, West CCP Motor Instant Trip RO Performs the following as directed: Starts 1E CCP Adjusts QRV-200 and QRV-251 flow to maintain RCP seal flow and Pressurizer level. Resets/Energizes pressurizer heaters by taking each heater power switch to OFF then back to ON. Places normal letdown back in service in accordance with 1-OHP 4021.003.001, Attachment 13.
Place 1W CCP control switch in PTL May re-align AES fans.
(Continued on next page)
Cook Plant Unit 1 & Unit 2 Page 7 of 18
Cook Plant Unit 1 & Unit 2 Page 8 of 18 Op-Test No.: Crews 1,2,& 3 Scenario No.:
Cook 2010-02 Event No.:
5 Event
Description:
1W Centrifugal Charging Pump (CCP) Trips BOP Restores normal letdown per 1-OHP 4021.003.001 Attachment 13 as:
- 1. Places 1-QRV-302 in divert position
- 2. Verifies orifice isolations closed (QRV-160, 161 and 162)
- 4. Verifies open letdown isolation valves:
- a. 1-QCR-300, CVCS letdown cntmt isol
- b. 1-QCR-301, CVCS letdown cntmt isol
- c. 1-QRV-111, RC letdown to regen hx
- d. 1-QRV-112, RC letdown to regen hx
- 5. Adjusts 1-QRV-301, letdown pressure controller to 50% output
- 6. Checks/adjusts charging flow to > 75 gpm
- 7. Opens 1-QRV-161, 75 gpm letdown orifice isolation
- 8. Adjusts 1-QRV-301 to maintain 160 - 350 psig on 1-QPC-301
- 9. Performs steps as required to add 45 gpm orifice
- 10. Places 1-QRV-301 in auto (if desired)
- 11. Nulls and returns 1-CRV-470 controller to auto
- 12. Adjusts charging flow as required to maintain PRZ level
- 13. Places PRZ level control in automatic (if desired)
- 14. Places 1-QRV-302 in normal (demineralizer) position when letdown temperature is stable.
US Declares 1W CCP inoperable and refers to Tech Specs (TS): TS 3.5.2, ECCS Subsystems - Tavg > 350 F (Condition A) TRM 8.1.1, Boration Systems - Operating Enters action statements to restore 1W CCP to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Cook Plant Operator Actions Form ES-D-2 Op-Test No.:
Crews 1,2,& 3 Scenario No.:
Cook 2010-02 Event No.:
6 Event
Description:
SG PORV Controller Failure Time Position Applicant's Actions or Behavior BOP Recognize and reports Annunciator #114 Drop 24 that indicates SG #14 PORV 1-MRV-243 has failed Open
US Direct operator actions to close SG PORV and monitor Reactor Power BOP Place SG PORV #14 in Manual and Closes PORV.
US Declares the SG #14 PORV radiation Monitor 1-MRA-1602 Inoperable US Refers to the following Tech Specs (TS):
- TRM 8.3.8.
Radiation Monitoring Instrumentation Condition C
Restore in 7 days.
Cook Plant Unit 1 & Unit 2 Page 9 of 18
Cook Plant Operator Actions Form ES-D-2 Op-Test No.:
Crews 1,2,& 3 Scenario No.:
Cook 2010-02 Event No.:
7/8/9 Event
Description:
Loss of Bus T11A due to fault of Bus 1A - Loss of RCS flow in one loop; Failure of Turbine Trip; Loss of control power to TD AFW pump T&TV & Trip of West MDAFP Time Position Applicant's Actions or Behavior CREW Recognizes the loss of RCS flow in one loop and the reactor automatic trip. . US Directs RO/BOP to perform the immediate actions of E-0, Reactor Trip or Safety Injection.
RO Performs the (primary) immediate actions of E-0:
- 1. Checks reactor trip
- 2. Checks safety injection status
US/BOP Critical Task #1 Performs the (secondary) immediate actions of E-0:
- 1. Checks Turbine Trip Determines that ALL Turbine Stop Valves are NOT Closed. Attempts Manual Turbine trip via the solenoid Trip. Attempts to Manually actuate AMSAC
- 2. Determines that Turbine did NOT trip.
- 3. Isolates SG Stop Valves and Stop Valve Dump Valves BOP Checks power to AC emergency buses Reports Loss of 4KV Bus T11A (due to fault) and T11B Reports Trip of AB EDG (due to bus fault)
US Ensures immediate actions of E-0 are completed
RO/BOP Performs manual actions of E-0 Attachment A as directed by US.
RO/BOP Performs verifications/actions of E-0 as directed by US.
US Determines that No AFW pumps are running requiring transition to transition to FR-H.1 Cook Plant Unit 1 & Unit 2 Page 10 of 18
Cook Plant Operator Actions Form ES-D-2 Op-Test No.:
Crews 1,2,& 3 Scenario No.:
Cook 2010-02 Event No.:
7/8/9 Event
Description:
Loss of Bus T11A due to fault of Bus 1A - Loss of RCS flow in one loop; Failure of Turbine Trip; Loss of control power to TD AFW pump T&TV & Trip of West MDAFP Time Position Applicant's Actions or Behavior US/BOP Announces transition to FR-H.1, Response to Loss of Secondary Heat Sink per CSFST status.
RO/BOP Reviews foldout page for FR-H.1, Response to Loss of Secondary Heat Sink. US Directs actions of FR-H.1, Response to Loss of Secondary Heat Sink.
US/RO Recognizes one CCP available Verifies Bleed and Feed initiation is not required Verifies RCS pressure remains < 2335 psig US/BOP Critical Task #2 Attempts to establish secondary heat sink to one SG: Starts TDAFP from Control Room. Verify total feed flow > 240E3 PPH (FMO-211, 221, 231, 241 are throttled open).
US Announces transition to E-0, Reactor Trip or Safety Injection. TERMINATE SCENARIO Cook Plant Unit 1 & Unit 2 Page 11 of 18
Cook Plant Unit 1 & Unit 2 Page 12 of 18 CRITICAL TASK
SUMMARY
(COOK 2010-02)
Task Elements Results #1 Manually Trip Turbine/Isolate Steam Lines Cueing:
- Turbine Stop Valve Status Lights - NOT LIT (E-0 step 2)
- Turbine Control Valve Indicators - NOT at Zero
- SG Stop Valves - NOT Closed
- Steam generator pressure lowering
- RCS temperature lowering Performance Indicators: Isolate SG Steam Lines by closing SG Stop valves and Dump Valves
- Must be performed before developing an Orange path on Subcriticality or Integrity status tree.
Performance Feedback:
- SG Stop Valve Closed Lights - LIT
- 2 Manually Starts Turbine Driven AFW Pump Cueing: Check TDAFP Trip and Throttle Valves/Manually Start AFW pump(FR-H.1, Step 4.b.3 & 4.c)
Performance Indicators:
Manually starts the TDAFP from the control room. AFW flow must be established before SG dryout occurs (<17% WR level).
Performance Feedback:
TDAFP speed rising AFW flow > 240E3 PPH (FMO-211, 221, 231, 241 are throttled open)
SAT / UNSAT
SIMULATOR INSTRUCTIONS (COOK 2010-02)
Setup: 1. Reset to IC38
- 2. Reset control rods and check group step counters
- 3. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position
- 4. Advance chart recorder paper
& clear chart recorder memory.
- 5. Go to RUN and acknowledge/clear alarms
- 6. Tagout 1E MDAFP as follows: Place control switch in pull-to-lock
Place clearance tag on control switch Activate remote function FWR61 , final value RO U1_FWR61 7. Verify the following (pre-load) malfunctions:
- 8. Activate the following (pre-load) malfunctions: TC02, Main Turbine Fails to Trip
RP07A Train A Steamli ne Isolation Failure RP07B Train A Steamli ne Isolation Failure FW48C , Failure of TD AFW pump AUTO start U1_TC02 U1_RP07A U1_RP07B U1_FW48C 9. Assign the following (pre-load) malf unctions to Event Trigger (ET) 7:
ED05E, T11A Bus fault ED05A, 11A Bus fault U1_ED05E - On Trig 7 U1_ED05A - On Trig 7
- 10. Assign file "U1ReactorT ripBreaker" to event #9:
FW51 , TD AFW pump T&TV blown control fuse U1 Rx Trip U1_FW51 Cook Plant Unit 1 & Unit 2 Page 13 of 18
Cook Plant Unit 1 & Unit 2 Page 14 of 18 SIMULATOR INSTRUCTIONS (COOK 2010-02)
Scenario: EVENT #1 When requested by crew, provided the followi ng information during start of West CCP (1-OHP-4021-003-001, Att. 5):
Step 4.1.1:
Report that the following valves are sealed OPEN:
- 1-CS-296W, West CCP 1-PP-50W Suction Valve
- 1-CS-301W, West CCP 1-PP-50W Discharge Valve
- 1-CS-298W, 1-QMO-226 Outlet Valve Step 4.1.2:
Report that proper lube oil levels have been verified in the West CCP.
Step 4.1.3:
Report that CCW flow fr om West CCP is 61 gpm.
Step 4.1.4:
Report that the West CCP lube oil pressure at LP I-273 is 15 psig and proper oil flow is observed.
Step 4.1.5:
Report that the East CCP lube oil pressure at LPI-271 rose 4 psig.
Step 4.1.10:
Report that the West CCP Speed In creaser oil pressure is 20 psig.
Step 4.1.12: Report that the West CCP lube oil pressure at LPI-273 is 15 psig.
If requested, report as AEO that AES Fan Flows and filter Differential Pressure is acceptable.
EVENT #2 No Actions.
EVENT #3 After crew has lowered power:
IMF RX21A , final value 0 (FFC-210 fails LOW)
U1_FFC210 If directed to trip bistables for FFC-210 use:
Override ZLOSTMC2[6] to ON to simulate opening CH 1 cabinet Door ZLOSTMC2_U1[6] (Override Lights/Relays - RX Flux panel)
Remote Bistable RPR017 FS-510A U1_RPR017 RPR018 FS-510B RPR151 FS-510J U1_RPR018 U1_RPR151
IOV ZLOSTMC2[1] to ON to simulate lifting Test Rack Cook Plant Unit 1 & Unit 2 Page 15 of 18 ZLOSTMC2_U1[1]
Delete Override ZLOSTMC2[6]
to simulate closing cabinet Door ZLOSTMC2_U1[6]
SIMULATOR INSTRUCTIONS (COOK 2010-02)
EVENT #4 When crew has recovered from SG FW Flow channel failure: NLP151 , final value 0 (NLP-151 fails LOW)
If directed, to trip bistables for NLP-151 use: ZLOSTMC2[6] to ON to simulate opening CH 1 cabinet Door Cook Plant Unit 1 & Unit 2 Page 16 of 18 (Override Lights/Relays - RX Flux panel)
Remote Bistable RPR041 LS/459A ZLOSTMC2[1] to ON to simulate lifting Test Rack ZLOSTMC2[6] deleted to simulate closing cabinet Door ZLOSTMC2_U1[6]
U1_RPR041 ZLOSTMC2_U1[1] U1_NLP151 ZLOSTMC2_U1[6] NOTE: May Insert Event 5 at this time (Letdown restoration actions w ill be repeated in event 5)
EVENT #5 When crew has recovered from PRZ Level c hannel failure (Note - ma y be performed prior to restoring all Charging components to Auto - prior to letdown restoration):
WCP Stator Short Circuit (West CCP trip)
U1_WCP If contacted as AEO or Maintenance to eval uate West CCP operations, report back after some 5 min. delay that motor insulation sme lls burnt and the overcu rrent trip flag is indicated on the breaker.
SIMULATOR INSTRUCTIONS (COOK 2010-02)
EVENT #6 When the crew has restored Charging and selected an Operable channel: RX11D, final value 100 (SG PORV Controller failure)
U1_RX11D EVENT #7 Loss of T11A Bus (Pre-loaded as Event Trigger 7):
(Activate Trigger 7 {trg! 7})
Activate Trg E7 EVENT #8 Turbine Trip fails to AUTO actuate (Pre-Loaded)
Steam Line Isolation fails to AUTO actuate (Pre-Loaded) TD AFW pump fails to start (Pre-Loaded)
Cook Plant Unit 1 & Unit 2 Page 17 of 18
EVENT #9 After FR-H.1 determination that Bleed & Feed is NOT required, repor t as the AEO and/or Maintenance that T&TV appears to be functi onal with NO physical damage evident, but the fuse was blown and has been replaced.
DMF FW51 to replace the blown fuse. U1_FW51 Perform Local actions after entry into E-0 as requested:
Locally stop U1 Ice Condenser AHUs MRF CHR01 to OFF U1_CHR01 Place PACHMAS in service - MRF CHR02 or 03 with 10 min delay.
OR Cook Plant Unit 1 & Unit 2 Page 18 of 18 (both have 10 minute delay built in) U2 has aligned CR vent for U1 SI, Fan 2-HV-AS-2 is running.
Report Control Room Damper Positions ACRDA-1A, ACRDA-2 ar e closed. ACRDA-3 is open.
If directed to secure EDG jacket water pumps select OFF then AUTO Remote OFF AUTO EGR 03A EGR 03B EGR 04A EGR 04B U1_EGR03B U1_EGR03A U1_EGR04A U1_EGR04B U1_EGR04A U1_EGR04B U1_CHR03 U1_CHR02 U1_EGR03A U1_EGR03B Appendix D Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.:
COOK 2010-03 Op-Test No.: Crews 4 & 5 Examiners: _________________ Operators:___________________ _________________ ___________________
_________________ ___________________
Initial Conditions: IC-37, 78% pwr, 1021 ppm Boron, 8 GWD, 554°F Tave, CBD @196 steps, 848 MW
Turnover: Swap Hotwell Pumps, West CCP is OOS for Oil Change this shift. Pump has been OOS for 2 Hours. Event No. Malf. No.
Event Type* Event Description 1 N-BOP Start South Hotwell pump and Stop North Hotwell Pump 2 NTP240 @ 620 I-RO TS RCS Cold Leg Temperature Instrument (NTP-240) Fails HIGH 3 MFC140 @ 4E6 over 20 sec I-BOP TS #14 SG Steam Flow Transmitter (MFC-140) fails HIGH 4 RC17C to 50%
C-RO TS Pressurizer PORV NRV-153 Fails Open.
5 R-RO Lower Reactor Power and Turbine Load 6 FW05A C-BOP East Main Feed Pump Trip 7 FW05B M West Main Feed Pump Trip 8 RP03A RP03B C-RO AUTO/MANUAL Reactor trip actuation failure (ATWS) 9 MS01D @ 20 2 min Ramp M
Steam Line Break inside Containment (#14 SG)
10 RP19J C-RO RPS relay K626-X3 failure (1East CTS pump fails to start)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 Page 1 of 20
Summary The Crew is directed to start South Hotwell pump and stop North Hotwell Pump. Following the Hotwell pump shutdown, the crew is preparing to reduce power due to a small oil leak on the East MFP.
The RCS Loop 4 Cold Leg Temperature instrument (NTP-240) failing HIGH. This will result in the AUTO insertion of control rods and a lower trip setpoint value for OPT and OTT. The RO will be required to take manual control of rods to stop insertion. Crew will be required to implement AOP actions to stabilize the plant and trip bistables.
After the crew has addressed the RCS temperature the #14 SG Steam Flow instrument (MFC-140) failing HIGH. This will result in the opening of #14 SG FWRV (FRV-240) to raise feedwater flow. BOP will be required to take manual control and regulate FRV-240. Crew will be required to implement AOP actions to stabilize the plant and trip bistables.
The Pressurizer PORV NRV153 will fail partially Open. This results in Actual RCS pressure lowering. The RO will be required to take manual actions to isolate the PORV (close block valve) and restore normal pressure conditions.
Next a rapid power reduction is performed (Optional if reactivity change is required - note next event also involves a reactivity change which may be combined with this reactivity change)
based on a report of an Oil leak on the East Main feed Pump.
A trip of the East Main Feed Pump will result in a rapid power reduction to less than 60% if not already performed. The RO will be required to control reactivity while the BOP monitors the SG levels.
The main event will involve a Failure of the RPS function (ATWS) following a trip of the remaining FW pump. The RPS failure also results in failure of K626-X3 relay which prevents the auto start of the East CTS pump. The reactor must be locally tripped. The crew will implement FR-S.1 actions until reactor is subcritical. A Steam Line Break will cause SG #14 to blow down inside Containment. The BOP will be required to isolate the main steam lines. After the reactor is subcritical, the crew will perform the actions of E-0 to verify the SI actions and then transition to E-2. The scenario will terminate when the crew has completed isolation of the faulted SG in FR-S.1 (and completed required steps of E-0) or E-2.
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 Cook Plant Unit 1 & Unit 2 Page 2 of 20
Cook Plant Operator Actions Form ES-D-2 Op-Test No.:
Crews 4 & 5 Scenario No.: COOK 2010-03 Event No.:
1 Event
Description:
Swap Hotwell Pumps (Start South and Stop North)
Time Position Applicant's Actions or Behavior
US Directs actions of 1-OHP-4021-054-001, Attachment 2, Operation of Hotwell (HW) and Condensate Booster (CB) Pumps to start the South and stop the North HW pumps.
BOP Performs the following to swap HW pumps as directed:
Directs AEO to close South HW pump Seal Quench throttle valve (1-C-
119S)
Starts the South HW pump
Monitors HW discharge pressure and flow Directs AEO to close South HW pump disch vent valve (1-C-117S)
Places the following switches in neutral: (May be done before South HW Pump is started - parallel steps)
- Standby CB pump
- Standby TACW pump Stops the North HW pump Directs AEO to open North HW pump disch vent valve (1-C-117N)
Di rects AEO to throttle North HW pump seal package quench valve (1-C-119N) Places the following control switches in auto:
- Standby CB pump
- Standby TACW pump
- North Hotwell pump NOTE: Annunciator Panel 116 Drop 63 Hotwell Pump Discharge Pressure Low may alarm during pump swap. Alarm should be cleared when task is completed. Annunciator Panel 116 Drop 52 SJAE DP Low may alarm during pump swap.
US/BOP Notify chemistry of condensate system configuration change.
Cook Plant Unit 1 & Unit 2 Page 3 of 20
Cook Plant Operator Actions Form ES-D-2 Op-Test No.:
Crews 4 & 5 Scenario No.:
Cook 2010-03 Event No.:
2 Event
Description:
Loop 4 RCS Cold Leg Temperature Transmitter (NTP-240) Fails High Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Ann. Panel 111 which are indicative of a RCS RTD failure.
Note: Based on the response time of the crew, an auto makeup may occur for the VCT due to letdown charging mismatch due to erroneous auctioneered high Tavg indication.
RO Places rod control in manual after verifying no runback in progress. Identifies that PRZ Program Level is affected by this failure.
US Enters and directs actions of 01-OHP-4022-012-003, Continuous Control Bank Movement procedure, if rods moved.
RO If 1-OHP-4022-012-003 is entered, then performs the following as directed:
- 1. Checks for no turbine runback
- 2. Ensures control rods are in manual with no rod motion
- 3. Checks rod position above low-low rod insertion limit Note: Delta-T failure may affect RIL Setpoint - Must use COLR or manually calculate.
- 4. Checks axial flux difference (AFD) within target band
- 5. Initiates restoration of equilibrium conditions using either: Control rod movement Turbine load adjustment
- 6. Identifies failed RTD channel US Enters and directs actions of 1-OHP-4022-013-007, RCS RTD Instrument Malfunction procedure.
RO 1. Ensures control rods are in manual.
- 2. Reports Loop 4 as failed RCS temperature channel and aligns the following switches: Tavg defeat switch to Loop 4 position T defeat switch to Loop 4 position T/OPT/OTT recorder switch to Loop 1, 2, or 3 US Initiates actions to trip bistables associated with RCS loop 4 RTD failure per Attachment D of 1-OHP-4022-013-007.
Cook Plant Unit 1 & Unit 2 Page 4 of 20
Op-Test No.: Crews 4 & 5 Scenario No.:
Cook 2010-03 Event No.:
2 Event
Description:
Loop 4 RCS Cold Leg Temperature Transmitter (NTP-240) Fails High Time Position Applicant's Actions or Behavior US Refers to TS LCO: TS 3.3.1, Reactor Trip System (RTS) Instrumentation (Table 3.3.1-1) o Function 6, Overtemperature T. Condition D o Function 7, Overpower T. Condition D TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS)
Instrumentation (Table 3.3.2-1) o Function 4e, Steam Line Isolation - High Steam Flow in Two Steam Lines (per steam line), Coincident with Tavg - Low Low Condition D o Function 8c, ESFAS Interlocks - Tavg - Low Low, P-12. Condition D May enter the following TS if Pressure lowers to <2050 psig during the transient: TS 3.4.1, RCS Pressure, Temperature, and Flow DNB Limits. Condition A May refer to the following if LEFM readings are Magenta on PPC TRM 8.7.14, Leading Edge Flow Meter (Mode 1 > 3250 applicability)
Cook Plant Unit 1 & Unit 2 Page 5 of 20
Appendix D Operator Actions Form ES-D-2 Op-Test No.:
Crews 4 & 5 Scenario No.:
Cook 2010-03 Event No.:
3 Event
Description:
SG #14 Main Steam Flow Transmitter (MFC-140) Fails High Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #114 which are indicative of a steam flow instrument failure (Drop 41 - May also receive Drops 32 SG Level Deviation and Drops 43 SF>FWF Mismatch).
BOP Places 1-FRV-240, SG 14 MFW Reg. Valve controller to manual, lowers controller output to match feed flow with operable steam flow channel, and restores SG 14 level to program.
US Enters and directs actions of 1-OHP-4022-013-014, Steam Flow Instrument Malfunction procedure.
BOP Performs the following actions as directed:
- 1. Restores SG 14 level using manual control of 1-FRV-240
- 2. Places MFP P controller in manual and maintains pressure
- 3. Reports 1-MFC-140 has failed high
- 4. Places 1-FS-542C selector switch in channel 2 position
- 5. Nulls and returns 1-FRV-240 controller to AUTO
- 6. Returns MFP P controller to AUTO US Directs actions to trip bistables associated with 1-MFC-140 Steam Flow Failure per Attachment D-1 of 1-OHP-4022-013-014.
US Refers to Tech Specs: 3.3.1 RTS Instrumentation (Table 3.3.1-1, Function 15 Condition D) 3.3.2 ESFAS Instrumentation (Table 3.3.2-1, Function 4e Condition D)
Enters action statement that requires bistables to be tripped within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Cook Plant Unit 1 & Unit 2 Page 6 of 20
Appendix D Operator Actions Form ES-D-2 Op-Test No.:
Crews 4 & 5 Scenario No.:
Cook 2010-03 Event No.:
4 Event
Description:
Pressurizer PORV (NRV-153) Fails Open Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel #108 (Drop 23, 24, indicative of a pressurizer PORV opening. (Drops 8, 29, 34, 39, &
45 may also alarm)
US/RO Isolates failed open PORV per 1-OHP-4024-108, Drop 23: Attempts to manually close 1-NRV-153 PRZ PORV Manually closes 1-NMO-153, 1-NRV-153 PRZ PORV Block Valve US Declares 1-NRV-153 inoperable, refers to Tech Spec 3.4.11 RCS Relief valves - Operating and complies with Condition B: Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> close and remove power from the PORV block valve (1-NMO-153).
May enter Technical Specification 3.4.1 RCS Pressure, Temperature, and Flow DNB Limits if Pressure lowers to <2050 psig. May refer to TS 3.4.12, LTOP & 3.4.13 RCS Leakage.
NOTE: Crew may refer to 1-OHP-4022-002-009, Leaking Pressurizer Power Operated Relief Valve. Continue with next event while crew performs actions of this procedure.
RO Monitors PRZ pressure control system and ensures pressure returns to normal conditions (~2085 psig).
Cook Plant Unit 1 & Unit 2 Page 7 of 20
Cook Plant Operator Actions Form ES-D-2 Op-Test No.:
Crews 4 & 5 Scenario No.:
Cook 2010-03 Event No.:
5 Event
Description:
Reduce Turbine Load / Reduce Reactor Power Time Position Applicant's Actions or Behavior Note: If desired the Next event (FW Pump Trip) may be initiated prior to commencing the Rapid Power reduction.
CREW Determines that a Rapid Power reduction is required based on the FW Pump Oil Leak.
Turbine Load Reduction per 1-OHP-4022-001-006, Rapid Power Reduction Response US Directs RO to commence Rapid Power Reduction in accordance with 1-OHP 4022-001-006.
RO Performs BORATION: batch add OR Continuous: Place RC Makeup Blend control switch in STOP Place RC Makeup Blend Control Mode switch in BORATE Adjust BA Controller/Totalizer to the desired flow rate and/or amount. Place RC Makeup Blend control switch in START May take QRV-303 to Manual and Open as required to maintain VCT Level and Pressure. -OR- Performs EMERGENCY BORATION:
Place Boric Acid Transfer pump(s) to FAST speed Open 1-QMO-410, Emergency Boration To CHG Pump Suction Verify 1-QFI-410, Emer Boration Flow, indicates
> 44 gpm RO Commences power reduction:
- Lowers turbine load (reactor power) using HMI
- Ensures control rods in auto or manually inserts rods.
BOP Acts as peer checker for RO and verifies appropriate reactivity feedback.
Cook Plant Unit 1 & Unit 2 Page 8 of 20
Appendix D Operator Actions Form ES-D-2 Op-Test No.:
Crews 4 & 5 Scenario No.:
Cook 2010-03 Event No.:
6 Event
Description:
East Main Feed Pump Trip Time Position Applicant's 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 operator actions per 1-OHP-4022-055-001, Loss of One MFP:
- 1. Verify Turbine Load is automatically reduced to < 625Mw
- 2. Verify Rod Control in AUTO
- 3. Close the East FW Pump Emergency Leakoff Valves
- 4. Adjust West FW Pump speed as required
- 5. Start Standby Hotwell & Condensate Booster Pumps as required
- 6. Start AFW pumps if required.
RO Verify rod control switch in AUTO and functioning properly. Initiate normal or emergency boration flow (if required).
BOP Perform actions as directed:
- 1. Verify Turbine Load is automatically reduced to < 625Mw
- 2. Close the East FW Pump Emergency Leakoff Valves FRV-251 & 252
- 3. Adjust West FW Pump speed as required
- 4. Start Standby Hotwell & Condensate Booster Pumps if required
- 5. Start AFW pumps if required.
- 6. Verify West FW Pump Speed Increased
- 7. Verify SG levels are stable at or returning to normal (44%).
US Direct operator actions to restore normal system alignment: (as required) Restore AFD to required Band Reset Steam Dump Load Rejection Stop running AFW pumps and align for standby condition Align Condensate system for current plant conditions Complete FW Pump Shutdown NOTE: Crew May enter TS 3.4.1 for RCS DNB if Pressurizer Pressure lowers to < 2050 psig Cook Plant Unit 1 & Unit 2 Page 9 of 20
Appendix D Operator Actions Form ES-D-2 Op-Test No.:
Crews 4 & 5 Scenario No.:
Cook 2010-03 Event No.:
7/8/9/10 Event
Description:
West Main Feed Pump Trip RPS Reactor Trip - Failure Steam Line Leak EAST CTS Pump Fails to Start
Time Position Applicant's Actions or Behavior RO/US Determines that a loss of feedwater is occurring based on the following:
- SG level change
- FW & Steam flow mismatch US Directs RO to manually trip the reactor Directs RO/BOP to perform the immediate actions of E-0, Reactor Trip or
Safety Injection
RO Recognizes and reports failure of reactor to manually trip
US Directs actions of FR-S.1, Response to Nuclear Power Generation/ATWS:
RO Critical Task #1 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 check Turbine Trip
US Ensures immediate actions of FR.S-1 are completed
RO Critical Task #1 Initiate Emergency Boration of RCS(must Insert Negative Reactivity through Inserting Control Rods or Emergency Boration)
Cook Plant Unit 1 & Unit 2 Page 10 of 20
Appendix D Operator Actions Form ES-D-2 Op-Test No.:
Crews 4 & 5 Scenario No.:
Cook 2010-03 Event No.:
7/8/9/10 Event
Description:
West Main Feed Pump Trip RPS Reactor Trip - Failure Steam Line Leak EAST CTS Pump Fails to Start Time Position Applicant's Actions or Behavior Crew Determines that a Safety Injection has Actuated Verify SI actions per E-0 as time permits.
US Directs subsequent actions of FR.S-1: Local operation of reactor trip breakers or MG set output breakers Local turbine Trip Verify Reactor subcritical - WR log power < 5% & negative SUR
NOTE: Reactor Power may be below 5% WR with Negative SUR which will direct crew to Step 20
of FR-S.1 with a subsequent transition to E-0. If a Transition to E-0 is made continue on page 12.
BOP Manually controls AFW flow to maintain SG narrow range levels 20% - 50%
once one SG narrow range level is greater than 14%. Raises total AFW flow to > 450Kbh/hr RO Isolate ALL Dilution Paths CREW Determines that Steam Line Pressures are lowering from Steam Line Break.
US/BOP Verify Main Steam Isolation (SG Stop) valves & Steam Dumps closed MRV-210 MRV-220 MRV-230 MRV-240 (for Faulted SG #24) Steam Dumps CREW Identifies #14 steam generator as faulted CREW Critical Task #2 Manually closes the following valves for SG 14: 1-FMO-241, TDAFP discharge 1-FMO-242, MDAFP discharge NOTE: The following should be checked closed (not part of Critical Task - Already Closed) 1-FRV-240, feedwater reg. Valve 1-FMO-204, feedwater isolation valve 1-MRV-240, SG Stop Valve 1-MRV-243, PORV Cook Plant Unit 1 & Unit 2 Page 11 of 20
Appendix D Operator Actions Form ES-D-2 Op-Test No.:
Crews 4 & 5 Scenario No.:
Cook 2010-03 Event No.:
7/8/9/10 Event
Description:
West Main Feed Pump Trip RPS Reactor Trip - Failure Steam Line Leak EAST CTS Pump Fails to Start Time Position Applicant's Actions or Behavior Crew Transitions to E-0.
US Ensures immediate actions of E-0 are completed Determines that a Safety Injection has Actuated RO/BOP Report immediate actions complete and review foldout pages.
US Directs Actions of E-0 to verify equipment is aligned as required and determine if SI is valid.
Crew Verify Main Steam Isolation (SG Stop) valves Closed US Identifies that Containment Pressure is > 2.8 psig and directs actions to Stop RCPs and align containment systems as required per Step 6 RNO of E-0
US/RO Manually aligns/starts CNTMT Spray Train A: Starts 1E Containment Spray Pump RO Identifies and reports Phase B - Containment Isolation Actuation RO Stops all Reactor Coolant Pumps
RO/BOP Places lower Cntmt vent unit fans in OFF Places CRDM fans in STOP
Cook Plant Unit 1 & Unit 2 Page 12 of 20
Appendix D Operator Actions Form ES-D-2 Op-Test No.:
Crews 4 & 5 Scenario No.:
Cook 2010-03 Event No.:
7/8/9/10 Event
Description:
West Main Feed Pump Trip RPS Reactor Trip - Failure Steam Line Leak EAST CTS Pump Fails to Start Time Position Applicant's Actions or Behavior RO/BOP Performs manual actions of E-0 Attachment A as directed by US.
BOP Manually controls AFW flow to maintain SG narrow range levels 14% - 50%
once one SG narrow range level is greater than 14%.
US/BOP Verifies FW isolation and Isolates RCS cooldown Paths.
CREW Completes all actions of E-0 through step 17 (Check If SG Secondary Pressure Boundaries Are Intact).
US Announces transition to E-2, Faulted Steam Generator Isolation, for a SG depressurized (at step 17 of E-0).
NOTE: If SG Fault was isolated in FR-S.1 (AFW valves closed), then Scenario may be terminated (since actions of E-2 are essentially completed).
US Directs actions of E-2, Faulted Steam Generator Isolation.
BOP Checks closed - SGSV Dump valves CREW Identifies #14 steam generator as faulted CREW Critical Task #2 Manually closes the following valves for SG 14: 1-FMO-241, TDAFP discharge 1-FMO-242, MDAFP discharge NOTE: The following should be checked closed (not part of Critical Task - Already Closed) 1-FRV-240, feedwater reg. Valve 1-FMO-204, feedwater isolation valve 1-MRV-240, SG Stop Valve 1-MRV-243, PORV 1-DCR-304, blowdown sample valve 1-DCR-340, blowdown isolation valve Cook Plant Unit 1 & Unit 2 Page 13 of 20
Appendix D Operator Actions Form ES-D-2 Op-Test No.:
Crews 4 & 5 Scenario No.:
Cook 2010-03 Event No.:
7/8/9/10 Event
Description:
West Main Feed Pump Trip RPS Reactor Trip - Failure Steam Line Leak EAST CTS Pump Fails to Start
Time Position Applicant's Actions or Behavior BOP Closes 1-DRV-407, SG stop valve drain valve RO/BOP Performs the following as directed: Resets containment isolation phase A Directs chemistry to sample all SGs for activity CREW Determines that ECCS flow should be reduced . US Announces transition to ES-1.1 SI Termination (at step 8 of E-2).
TERMINATE SCENARIO Cook Plant Unit 1 & Unit 2 Page 14 of 20
Cook Plant Unit 1 & Unit 2 Page 15 of 20 CRITICAL TASK
SUMMARY
(COOK 2010-03)
Task Elements Results #1 Manually Trip Reactor Cueing: Challenge to multiple reactor trip setpoints:
- Low PRZ pressure reactor trip
- Low PRZ pressure safety injection RX TRIP BKR TRAIN A/B UV TRIP (ATWS) alarms Performance Indicators:
Insert Negative Reactivity through: Inserting Control Rods (Manually or Auto at >48 steps per minute) - OR -
Emergency Boration Must be performed prior to:
- SG Dryout (<15% wide range level)
- 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
- 2 Isolate Faulted Steam Generator Cueing:
- Steam generator pressure lowering
- RCS temperature lowering Performance Indicators:
Isolate SG 14 by closing:
- RCS cooldown stops
- Depressurization of intact SGs stop
SIMULATOR INSTRUCTIONS (COOK 2010-03)
Setup: 1. Reset to IC 37
- 2. Reset control rods and check group step counters
- 3. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position
- 4. Advance chart recorder paper
& clear chart recorder memory.
- 5. Go to RUN and acknowledge/clear alarms
- 6. Place 1-QMO-226 to Close
- 7. Activate the following to place 1W CCP OOS: 1W CCP W CCP Brkr T11A8 1W CCP Lube Oil Pump 1W CCP LO Brkr Cook Plant Unit 1 & Unit 2 Page 16 of 20 1-QMO-226
- 8. Place RED clearance tags on the following switches positioned as indicated: 1W CCP - PTL 1W CCP Lube Oil Pump - STOP 1-QMO-226 - CLOSED
- 9. Verify the following (pre-load) malfunctions:
- 10. Activate the following (pre-load) malfunctions: RP03A , Train A RPS Reactor Trip Breaker fails to open RP03B , Train B RPS Reactor Trip Breaker fails to open RP19J (RPS Relay K626-X3 failure) (E CTS fails to start)
- 11. Activate the following (pre-l oad) malfunctions on Trigger E7: FW05B (West MFP trip)
MS01D (SG #14 Steam Line Break) @ 20% over 2 Min. QMO226 Power U1_RP03A U1_RP03B U1_RP19J U1_FW05B U1_MS01D SIMULATOR INSTRUCTIONS (COOK 2010-03)
Scenario: EVENT #1 When directed, to align Hotwell Pump Seal Q uench valve (Step 4.1.2) report back that the South Hotwell Pump 1-C-119S Seal Quench Throttle Valve is CLOSED.
(Step 4.1.6) Report South HW pump disch vent valve (1-C-117S) is CLOSED after pump start. When Directed (After North Pump Shutdown) report that the North HW pump disch vent valve (1-C-117N) is OPEN (Step 4.2.4) and North Hotwell Pump 1-C-119N is Throttled (Step 4.2.5) to 12 drops per minute.
EVENT #2 ICF NTP240 , final value 620 (NTP-240 fails HIGH) after the HW pump is started.
U1_NTP240 If directed, to trip bistables for NTP-240 use: IOR ZLOSTMC2[9] to ON to simulate opening cabinet Door Cook Plant Unit 1 & Unit 2 Page 17 of 20 ZLOSTMC2_U1[9] (Override Lights/Relays - RX Flux panel) Remote Bistable RPR137 TS/441G U1_RPR137 RPR139 TS/442D U1_RPR139 RPR135 TS/441C U1_RPR135 RPR138 TS/441H RPR140 TS/442G RPR136 TS/441D IOR ZLOSTMC2[4] to ON to simulate lifting Test Rack DOR ZLOSTMC2[9] to simulate closing cabinet Door U1_RPR140 U1_RPR138 U1_RPR136 ZLOSTMC2_U1[4] ZLOSTMC2_U1[9]
SIMULATOR INSTRUCTIONS (COOK 2010-03)
EVENT #3 After crew has stabilized the plant from the RCS tem perature failure:
ICF MFC140 , final value 4E6 ramped over 20 seconds (MFC-140 fails HIGH)
U1_MFC140 If directed, to trip bistables for MFC-140 use: IOV ZLOSTMC2[6] to ON to simulate opening cabinet Door ZLOSTMC2_U1[6] (Override Lights/Relays - RX Flux panel) Remote Bistable RPR039 FS/542B RPR035 FS/540A RPR036 FS/540B U1_RPR039 U1_RPR035 U1_RPR036 IOV ZLOSTMC2[1] to ON to simulate lifting Test Rack Cook Plant Unit 1 & Unit 2 Page 18 of 20 ZLOSTMC2_U1[1]
DOV ZLOSTMC2[6] to simulate closing cabinet Door ZLOSTMC2_U1[6]
EVENT #4 After crew has stabilized the plant from the the Steam Flow Failure IMF RC17C, final value 50 (PRZ PORV NRV153 fails OPEN)
U1_RC17C If contacted to remove power from 1-NMO-153, then activate global malfunction (YG)
101NMO153 for breaker 1-EZC-D-3D.
U1_101NMO153
SIMULATOR INSTRUCTIONS (COOK 2010-03)
EVENT #5 When crew has recovered from the PRZ PORV failure:
Call control room and report oil spray (uniso lable) coming from Ea st MFP oil pump of approximately 10 gpm. Feed pump needs to be removed within the hour.
Note: If desired the Next event (FW Pump Tr ip) may be initiated prior to commencing the Rapid Power reduction.
EVENT #6 When the crew has changed power 2-3% or as directed by the lead examiner: IMF FW05A (East MFP trip)
U1_FW05A EVENT #7 After the Crew has stabilized following the FW Pump Trip activate trigger ET-7 (West FW Pump Trip, Control valve & SI preload malfunctions)
Activate Trg 7 EVENT #8 RPS Reactor Trip fails to actuate (Pre-Loaded) When directed as AEO to locally trip reactor, wait 2 minutes then Open Trip Breakers:
IRF RPR145 RO - (RTA)
Cook Plant Unit 1 & Unit 2 Page 19 of 20 IRF RPR146 RO - (RTB) U1_RPR145 U1_RPR146 SIMULATOR INSTRUCTIONS (COOK 2010-03)
Local actions after entry into E-0:
If contacted to remove power from 1-NMO-153, then activate global malfunction (YG) 101NMO153 for breaker 1-EZC-D-3D.
U1_101NMO153 Locally stop U1 Ice Condenser AHUs MRF CHR01 to OFF U1_CHR01 Place PACHMAS in service - MRF CHR02 or 03 with 10 min delay.
OR U1_CHR03 U1_CHR02 (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 Cook Plant Unit 1 & Unit 2 Page 20 of 20 EGR 03B EGR 04A EGR 04B U1_EGR04A U1_EGR04B U1_EGR03B U1_EGR03A U1_EGR03A U1_EGR03B U1_EGR04A U1_EGR04B Appendix D Scenario Outline Form ES-D-1 Cook Plant Unit 1 & Unit 2 Page 1 of 21 Facility: _Cook Plant Unit 1 & Unit 2
_ Scenario No.: COOK2010-04 Op-Test No.:
Crews 4 & 5 Examiners: _________________ Operators: ___________________ _________________ ___________________
_________________ ___________________
Initial Conditions: IC-992, 53% pwr, 1100 ppm Boron, 8 GWD, 551.5°F Tave, CBD @ 184 steps, 550 MW.
Turnover: Start the #13 CW Pump. 1CD EDG has been out of service for one day for fuel rack repairs. Event No.
Malf. No.
Event Type* Event Description 1 N-BOP Start Circulating Water Pump 2 R-RO Raise Turbine and Reactor Power to 100%.
3 CV04C C-RO 75 gpm Letdown Orifice Isolation Valve QRV-162 Fails
Closed 4 ECC, CC02B -
Preload C-BOP TS 1E CCW pump Trips (1W CCW [Standby] Fails to Auto
Start) 5 NPP151 to 2500 psig I-RO TS Pressurizer Pressure Channel NPP-151 Fails High 6 U1_BLP131
to 103 over
2 min I-BOP TS S/G 13 Level instrument (BLP-131) failing High 7 RC10D to 70% M-ALL Loop 4 Cold Leg Primary Coolant System 700gpm Leak inside Containment over 5 minutes 8 RP13A, RP13B -Preload C-BOP Failure of Automatic Phase A Actuation 9
- RP19G, RP20G -Preload C-RO Slave Relay failures: High Head Charging SI valves fail to align * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Cook Plant Unit 1 & Unit 2 Page 2 of 21 Summary The Crew is directed to start the 13 CW Pump. The operator will place the 13 CW in service in accordance with the normal operating procedure. Following the CW pump start the crew will perform the power escalation to 80%.
After a short ramp the letdown orifice valve will fail closed. The RO will need to restore
Letdown through a different valve.
While the RO is restoring letdown, a trip of the operating (East) Component Cooling Water (CCW) pump will require the BOP to manually start the standby pump (auto start failure).
After the Crew has addressed the Tech Specs for CCW, 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 Operati ng Procedure, defeat the failed channel, address Technical Specifications, then re store pressurizer pressure control to auto.
Following RCS pressure restoration, the #13 Steam Generator Level instrument (BLP-131) fails High. This results in a lowering feedwater flow and Steam Generator level. BOP will be required to take manual control and restore normal level. Crew will be required to implement AOP actions to stabilize the plant an d address Technical Specifications.
The major events will occur when the SG level has been stabilized. A 700 gpm Primary System Leak in Containment will occur requiring a Reacto r Trip and SI. On the SI, various slave relay failures will cause the High Head Charging SI injection flowpath to fail to align. The RO will need to manually align the High Head Injection Va lves. The auto Phase A Isolation will also fail requiring manual actuation to align Phase A equipment. The crew should progress through E-0 to E-1 to ES-1.2. The scenario will terminate once a transition has been made to ES-1.2.
Critical Tasks Restore High Head Injection Trip RCPs 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 Cook Plant Unit 1 & Unit 2 Page 3 of 21 Op-Test No.:
Crews 4 & 5 Scenario No.: COOK2010-04 Event No.:
1 Event
Description:
Start Circulating Water Pump Time Position Applicant's Actions or Behavior US Directs the operator to Start #13 CW pump as per 1-OHP-4021-057-001 Circulating System Operation Attachment 2
BOP Reviews procedural precautions and actions in 1-OHP-4021-057-001 Circulating System Operation Attachment 2.
BOP Performs actions per Attachment 2, Step 4.4: Start #13 CW Pump Place #13 CW Discharge valve to open & stop after 5-7 Seconds Open # 13 CW Discharge valve after 10-12 seconds. May open Waterbox Outlet valves following pump start.
BOP Reports 13 CW pump running Appendix D Required Operator Actions Form ES-D-2 Cook Plant Unit 1 & Unit 2 Page 4 of 21 Op-Test No.:
Crews 4 & 5 Scenario No.: COOK2010-04 Event No.: 2 Event
Description:
Raise Turbine Load/Reactor Power to 100%
Time Position Applicant's Actions or Behavior RO Calculates the dilution required per 1-OHP-4021-005-002, Attachment 9, Boration or Dilution Volume Determination.
RO Briefs crew on reactivity plan for power escalation.
US Reviews reactivity plan.
US Directs RO to commence Power Escalation in accordance with 1-OHP-4021-001-006.
RO Performs DILUTION: batch add OR Continous: 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/BOP Commences escalation: Raises turbine load (reactor power) using the DCS HMI. Maintains Tave/Tref deviation within limits by dilution and turbine load adjustments. (Administrative Limits of +/- 2
°F) Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.
BOP/RO Acts as peer checker for RO during blender operations and with the RO verifies appropriate reactivity feedback.
BOP Monitors and maintains main electrical generator temperatures within limits per: 1-OHP-4021-059-001, Generator Stator Cooling Water System 1-OHP-4021-080-003, Generator Hydrogen Gas System
Appendix D Required Operator Actions Form ES-D-2 Cook Plant Unit 1 & Unit 2 Page 5 of 21 Op-Test No.:
Crews 4 & 5 Scenario No.: COOK2010-04 Event No.:
3 Event
Description:
75 GPM Letdown Orifice Valve (QRV-162) Fails Closed Time Position Applicant's Actions or Behavior RO Identifies and reports rise in pressurizer (PRZ) level due to reduction in letdown flow (of 75 gpm) as a result of 1-QRV-162 failing closed.
US/RO Isolates letdown and minimizes charging flow to that amount required for seal injection.
NOTE If required, Shift manager will direct that normal letdown be established.
US Directs RO to restore normal letdown (using 1-QRV-161, 75 gpm letdown orifice and 1-QRV-160 45 gpm orifice) per 01-OHP-4021-003-001, Attachment 13.
RO Restores normal letdown per Attachment 13 as follows:
- 1. Places 1-QRV-302 in divert position
- 2. Verifies orifice isolations closed (QRV-160, 161 and 162)
- 3. Adjusts 1-CRV-470, CCW from LTDN HX outlet controller to 50% 4. Verifies open letdown isolation valves:
- a. 1-QCR-300, CVCS letdown cntmt isol
- b. 1-QCR-301, CVCS letdown cntmt isol
- c. 1-QRV-111, RC letdown to regen hx
- d. 1-QRV-112, RC letdown to regen hx
- 5. Adjusts 1-QRV-301, letdown pressure controller to 50% output
- 6. Checks/adjusts charging flow to > 75 gpm
- 7. Opens 1-QRV-161, 75 gpm letdown orifice isolation
- 8. Adjusts 1-QRV-301 to maintain 160 - 350 psig on 1-QPC-301
- 9. Performs steps as required to add 45 gpm orifice
- 10. Places 1-QRV-301 in auto (if desired)
- 11. Nulls and returns 1-CRV-470 controller to auto
- 12. Adjusts charging flow as required to maintain PRZ level
- 13. Places PRZ level control in automatic (if desired)
- 14. Places 1-QRV-302 in normal (demineralizer) position when letdown temperature is stable.
Appendix D Required Operator Actions Form ES-D-2 Cook Plant Unit 1 & Unit 2 Page 6 of 21 Op-Test No.:
Crews 4 & 5 Scenario No.: COOK2010-04 Event No.: 4 Event
Description:
1E CCW Pump Trips (Standby CCW Pump 1W Fails to Auto Start)
Time Position Applicant's Actions or Behavior BOP Recognizes and reports CCW annunciators on Ann. Panel 104 indicative of CCW pump trip (may include): Drop 83, CCW PUMP MOTOR INSTANT TRIP Drop 84, EAST CCW PUMP DISCHARGE PRESSURE LOW BOP Recognizes and reports that running (1E) CCW pump has tripped and standby (1W) CCW pump failed to auto start.
BOP Manually starts 1W CCW pump in accordance with CCW Annunicator Response Procedures.
US May refer to actions of 1-OHP-4022-016-001, CCW Malfunction procedure.
BOP If 1-OHP-4022-016-001, CCW Malfunction procedure is used, the performs the following actions as directed:
- 1. Ensures at least one CCW pump is running
- 2. Checks CCW surge tank level stable
- 4. Checks CCW Hx outlet temperature normal SRO Refers to TS LCO: TS 3.7.7, Component Cooling Water System. Condition A 1E CCW Pump is declared INOPERABLE. Note: Low Pressure Auto Start is NOT a Required Safety Function. The 1W CCW pump is technically not INOPERABLE, but SI auto start is required. The US may determine that TS 3.0.3 applies since he can not verify that 1W CCW auto start is available.
Note: CCW Surge tank valve 1-CRV-412 may close due to loss of flow to Rad Monitor.) If 1-CRV-412 closes, SRO directs actions per 12-OHP-4024-139 #10 CCW HX Rad Monitor to address Rad Monitor Low Flow and re-open 1-CRV-412.
Appendix D Required Operator Actions Form ES-D-2 Cook Plant Unit 1 & Unit 2 Page 7 of 21 Op-Test No.:
Crews 4 & 5 Scenario No.: COOK2010-04 Event No.:
5 Event
Description:
Pressurizer Pressure Channel (NPP-151) Fails High Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel #108 indicative of a pressurizer (PRZ) pressure instrument failure (Drops 6, 7, 8).
RO 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.
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 <2018 psig. (2050 psig admin limit)
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
- 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
- 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 from 1-QMO-225
- 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
Appendix D Required Operator Actions Form ES-D-2 Cook Plant Unit 1 & Unit 2 Page 8 of 21 Op-Test No.:
Crews 4 & 5 Scenario No.: COOK2010-04 Event No.:
5 Event
Description:
Pressurizer Pressure Channel (NPP-151) Fails High Time Position Applicant's Actions or Behavior US Declares the 1E Centrifugal Charging Pump inoperable.
US Initiates actions to trip bistables associated with 1-NPP-151 PZR Pressure Failure per Attachment A of 1-OHP-4022-013-009.
US Refers to Tech Specs (TS): TS 3.3.1 RTS Instrumentation (Table 3.3.1-1, Function 6, 8a, 8b Condition D) TS 3.3.2 ESFAS Instrumentation (Table 3.3.2-1, Function 1d Condition D, 8b Condition G *) TS 3.3.4 Remote Shutdown Instrumentation TS 3.5.2 ECCS Subsystems TRM 8.1.1 Rx Control Systems Charging Pumps - Operating TRM 8.7.14, LEFM, (Applicable above 3250 MW) *=Identifies requirement to verify the status of Permissive P-11 bistables 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 Cook Plant Unit 1 & Unit 2 Page 9 of 21 Op-Test No.:
Crews 4 & 5 Scenario No.: COOK2010-04 Event No.: 6 Event
Description:
- 13 SG Level Channel BLP-131 Fails HIGH Time Position Applicant's Actions or Behavior BOP Recognizes failure of BLP-131 High and reports associated alarms: Panel 114 Drops 1 and 2 - Level Deviation
BOP Places controller for 1-FRV-230 in manual, raises controller output to match feed flow with steam flow and stabilizes SG 23 level, as required.
US Directs actions of 1-OHP-4022-013-013, Steam Generator Level Instrument Malfunction procedure.
BOP Performs the following actions as directed:
- 1. Restores SG 13 level to program (44%), as required
- 2. Reports 1-BLP-131 has failed
US Direct actions to trip bistables per Attachment C-2 of 1-OHP-4022-013-013. Declares level channel input inoperable
US Refers to the following ITS LCOs: 3.3.1 RTS Instrumentation (Table 3.3.1-1, Function 14 - Cond D) 3.3.2 ESFAS Instrumentation (Table 3.3.2-1, Function 5b & 6c -
Cond D )
Appendix D Required Operator Actions Form ES-D-2 Cook Plant Unit 1 & Unit 2 Page 10 of 21 Op-Test No.:
Crews 4 & 5 Scenario No.: COOK2010-04 Event No.: 7/8/9 Event
Description:
Small Break LOCA Inside Containment Containment Isolation Phase A - Auto Failure ECCS Slave Relay Failures Time Position Applicant's Actions or Behavior RO/US Acknowledge Ann. Panel 122, Drop 83, ICE CONDENSER INLET DOORS OPEN, alarm.
Determines that a loss of reactor coolant is occurring based on the
following: Pressurizer and VCT level change Charging and letdown flow mismatch Containment radiation monitoring trend Containment pressure rise Containment sump level rise US May enter and direct actions of 1-OHP-4022-002-020, Excessive Reactor Coolant Leakage procedure.
RO Performs the following actions if directed:
- 1. Manually raises charging flow to maintain pressurizer level
- 2. Manually adjusts seal injection flow (6-12 gpm / each RCP)
- 3. Reduces/isolates letdown flow to maintain pressurizer level
- 4. Attempts to determine RCS leak rate
US Directs RO/BOP to manually trip the reactor and initiate safety injection and perform the immediate actions of E-0, Reactor Trip or Safety Injection (based on RCS leak rate beyond charging system capability or rising Containment Pressure).
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 Directs subsequent actions of E-0.
RO/BOP Reviews E-0 Foldout Page Criteria.
BOP Manually controls AFW flow to maintain SG narrow range levels 14% - 50% once one SG narrow range level is > 14%.
Appendix D Required Operator Actions Form ES-D-2 Cook Plant Unit 1 & Unit 2 Page 11 of 21 Op-Test No.: Crews 4 & 5 Scenario No.: COOK2010-04 Event No.: 7/8/9 Event
Description:
Small Break LOCA Inside Containment Containment Isolation Phase A - Auto Failure ECCS Slave Relay Failures Time Position Applicant's Actions or Behavior RO Reports that 1E CCW pump is NOT running - 1E CCW pump off due to previous failure.
US/RO Critical Task #1 Manually opens high head safety injection valves: BIT Outlet Valves o 1-ICM-250 -AND/OR- 1-ICM-251 Note: Event 9, Manually align the High Head Injection Valves.
US/RO Manually actuates Containment Isolation - Phase A.
CREW Critical Task #2 Manually stops all Reactor Coolant Pumps (RCPs) within 5 minutes of RCS pressure lowering below 1300 psig.
RO/BOP Performs manual actions of E-0 Attachment A (for Train A components which failed to start/reposition) as directed by US.
CREW Completes all actions of E-0 through step 19 (Check If RCS Is Intact).
US Announces transition to E-1, Loss Of Reactor Or Secondary Coolant (at step 19 of E-0).
RO/BOP Reviews E-1 Foldout Page Criteria.
US Directs actions of E-1, Loss Of Reactor Or Secondary Coolant.
BOP Maintains SG narrow range levels 20% - 50%.
US Checks if SI Termination Criteria is MET: RCS Subcooling >40 F Secondary Heat Sink (SG >14% or AFW Flow >240x10
- 3) RCS Pressure rising or stable Pressurizer Level >21%
Crew Transition to ES-1.1, Safety Injection Termination if criteria is met. ES-1.1 Actions are listed on Page
- 13. IF SI Termination Criteria are NOT met, THEN E-1 Actions Are Continued on Page 12.)
Appendix D Required Operator Actions Form ES-D-2 Cook Plant Unit 1 & Unit 2 Page 12 of 21 Op-Test No.: Crews 4 & 5 Scenario No.: COOK2010-04 Event No.: 7/8/9 Event
Description:
Small Break LOCA Inside Containment Containment Isolation Phase A - Auto Failure ECCS Slave Relay Failures Time Position Applicant's Actions or Behavior RO/BOP Performs the following as directed:
- 1. Resets both trains of Safety Injection
- 3. Stops running Emergency Diesel Generators (EDG)
- 4. Dispatches operator to secure EDG jacket water pumps (for EDG Stopped) 5. Directs chemistry to initiate post accident sampling US Announces transition to ES-1.2, Post LOCA Cooldown And Depressurization (at step 12 of E-1).
CREW Check if transition is made to ES-1.2, then perform the following: Reset SI Reset Containment Isolation: Establish Control Air To Containment TERMINATE SCENARIO
Appendix D Required Operator Actions Form ES-D-2 Cook Plant Unit 1 & Unit 2 Page 13 of 21 Op-Test No.:
Crews 4 & 5 Scenario No.: COOK2010-04 Event No.: 7/8/9 Event
Description:
Small Break LOCA inside Containment Containment Isolation Phase A - Auto Failure ECCS Slave Relay Failures Time Position Applicant's Actions or Behavior Note: Crew may transition to SI termination if criteria is 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 ES-1.1, Safety Injection Termination (step 6 of E-1).
RO/BOP Reviews ES-1.1, Foldout Page Criteria. Monitors RCS Subcooling >40F and PZR Level >21%, if NOT realign ECCS and GO TO E-1 US Directs Actions of ES-1.1 RO/BOP Performs the following as directed:
- 1. Resets both trains of Safety Injection
- 2. Stops one Charging Pump.
- 3. Resets both trains of Phase A
- 4. Establishes Control Air to Containment CREW Check if RCS Pressure is stable or Rising If Lowering, Transition to ES-1.2 RO/BOP Performs the following as directed:
- 1. Establish Normal Charging Flowpath
- 2. Isolate BIT Injection CREW Check if: Pressurizer Level is stable and RCS Pressure is Stable or Rising If NOT, Transition to ES-1.2 CREW Check if transition is made to ES-1.2, then perform the following: Reset SI Reset Containment Isolation: Establish Control Air To Containment TERMINATE SCENARIO
Critical Task Summary (UCOOK2010-04) Cook Plant Unit 1 & Unit 2 Page 14 of 21 Task Elements Results #1 Manually open high head safety injection valves Cueing: Check ECCS Flow: BIT - Flow Indicated (E-0, Attachment A Step 2.a) -OR- Check Systems In Proper Emergency Alignment: ECCS Monitor lights - Proper Status (E-0, Attachment A Step3) Performance Indicators:
While in E-0 before transitioning to E-1. Manually open BIT (outlet/inlet) valves to establish at least one train of high head safety injection flow.
Performance Feedback:
BIT flow is indicated to at least one train (as indicated by flow on two cold leg BIT injection flowmeters)
SAT / UNSAT
- 2 Manually trip all Reactor Coolant Pumps Cueing: RCS pressure - less than 1300 psig AND CCPs or SI pumps - at least one running o E-0, Foldout Page, Step 1 o E-0, Step 16 o E-1, Foldout Page, Step 1 o E-1, Step 1 Performance Indicators:
Within 5 minutes of the trip criteria being met: Manually stop all Reactor Coolant Pumps (RCPs) when RCS pressure is less than 1300 psig.
Performance Feedback:
RCP ammeters - zero current RCP trip low flow alarms - lit RCS loop flow meters - flow lowering SAT / UNSAT
Simulator Instructions (COOK2010-04 ) Cook Plant Unit 1 & Unit 2 Page 15 of 21 Setup: 1. Reset to IC- 992 MOL
- 2. Reset control rods and check group step counters
- 3. Verify Power Range Trip Setpoints are at 79 % and place correct tag on the drawer.
- 4. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position
- 5. Advance chart recorder paper
& clear chart recorder memory
- 6. Activate the following malfunctions to place 1CD EDG: EG10B U1_EG10B EG06B U1_EG06B EGR14 Value RO U1_EGR14 EGR15 Value RO EGR02 Value RO ZLO101FQTCD1 [GRN] Value OFF U1_EGR15 U1_EGR02 ZLO101FQTCD1_U1[GRN] ZLO101FQTCD2 [GRN] Value OFF ZLO101FQTCD2_U1[GRN]
- 7. Place RED clearance tags on the following switches positioned as indicated: T11C3 - PTL T11D8 - PTL CB1DGTCD - CENTER DG1CD STOP-RUN - CENTER 1-QT-106-CD1 - STOP 1-QT-106-CD2 - STOP Simulator Instructions (COOK2010-04 ) Cook Plant Unit 1 & Unit 2 Page 16 of 21
- 8. Go to RUN and acknowledge/clear alarms
- 9. Activate the following pre-load malfunctions: CC02B (1W CCW pump fails to auto start) U1_CC02B RP13A (Phase A isol./ train A auto failure) U1_RP13A RP13B (Phase A isol./ train B auto failure) U1_RP13B RP19G (ECCS slave relay failure) U1_RP19G RP20G (ECCS slave relay failure) U1_RP20G Simulator Instructions (COOK2010-04 ) Cook Plant Unit 1 & Unit 2 Page 17 of 21 Scenario: EVENT #1 Provide feedback as requir ed for #13 CW Pump Start. No Diving activities are taking place or planned. #13 CW pump was shutdown about 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago All CW tunnels are aligned Starting party Assembled, Seal Water Flow has been in service for > 30 minutes, Vacuum Priming is in service, Chemistry has been notified and will adjust chlorination as required.
Traveling Screens are a ll aligned for service.
If directed to Start the traveling screens select SPEED1, Select AUTO to place the Screens back to Auto Remote Speed 1 AUTO CWR22 U1_CWR22 CWR23 CWR24 CWR25 CWR26 CWR27 CWR28 U1_CWR23 U1_CWR23 U1_CWR24 U1_CWR24 U1_CWR25 U1_CWR25 U1_CWR26 U1_CWR26 U1_CWR27 U1_CWR27 U1_CWR28 U1_CWR22 U1_CWR28 Simulator Instructions (COOK2010-04 ) Cook Plant Unit 1 & Unit 2 Page 18 of 21 EVENT #2 No Additional Actions EVENT #3 After crew has demonstrated ability to raise power, THEN IMF CV04C, to cause QRV-162, 75 gpm letdown orifice to fail closed ) after crew has
demonstrated ability to lower power.
U1_CV04C If Desired, direct the Crew as the SM to restore ONLY 75 GPM letdown using section 4.2 of Attachment 13 (This shoul d help scenario runtime)
EVENT #4 While RO is occupied (to ensur e BOP must addr ess failure):
IMF U1_ECC, to cause the 1E CCW pump to trip on Stator Short Circuit [1W CCW Preloaded for fail of Auto Start] U1_ECC
If dispatched to check 1E CCW breaker T11D3, report that the breaker has tripped on OC. Report no indications of problems with the pump if checked locally.
Simulator Instructions (COOK2010-04 ) Cook Plant Unit 1 & Unit 2 Page 19 of 21 EVENT #5 After crew has addressed the CCW pump failure IMF U1_NPP151 , final value 2500 (NPP-151 fails hi)
U1_NPP151
If directed to trip bistables for NPP-151 use:
Override ZLOSTMC2[6] to ON to simulate opening cabinet door (Override Lights/Relays - RX Flux panel)
Remote Bistable RPR076 PS-455A RPR077 PS-455B RPR078 PS-455C RPR079 PS-455D RPR117 TS-411C RPR118 TS-411D Override ZLOSTMC2[1] to ON to simulate lifting Test Rack Delete Override ZLOSTMC2[6]
to simulate closing cabinet Door If directed to remove power from 1-QMO-225, then activate global malfunction (YG) 101QMO225 for breaker 1-ABV-D-5C.
ZLOSTMC2_U1[1] U1_RPR118 U1_RPR079 ZLOSTMC2_U1[6] U1_RPR076 U1_RPR077 U1_RPR078 U1_RPR117 ZLOSTMC2_U1[6] U1_101QMO225 Simulator Instructions (COOK2010-04 ) Cook Plant Unit 1 & Unit 2 Page 20 of 21 EVENT #6 ICF U1_BLP131, Final Value 103 over 2 Minutes , to cause Steam Generator #13 Channel (BLP-131) to fail High U1_BLP131 If directed to trip bistables for BLP-131 use:
Override ZLOSTMC2[6] to ON to simulate opening cabinet door ZLOSTMC2_U1[6] (Override Lights/Relays - RX Flux panel)
Remote Bistable RPR066 LS-539A U1_RPR066 RPR067 LS-539B U1_RPR067 Override ZLOSTMC2[1] to ON to simulate lifting Test Rack ZLOSTMC2_U1[1]
Delete Override ZLOSTMC2[6]
to simulate closing cabinet Door ZLOSTMC2_U1[6]
Simulator Instructions (COOK2010-04 ) Cook Plant Unit 1 & Unit 2 Page 21 of 21 EVENT #7 - 9 IMF RC10D , final value 70 over 5 min, Loop 4 Cold Leg SBLOCA (700 gpm) inside containment over a 5 minute period.
U1_RC10D Local actions after entry into E-0:
If directed to store power to 1-QMO-225, then delete global malfunction (YG) 101QMO225 for breaker 1-ABV-D-5C.
U1_101QMO225 Locally stop U1 Ice Condenser AHUs MRF CHR01 to OFF U1_CHR01 Place PACHMAS in service - MRF CHR02 or 03 with 10 min delay.
OR U1_CHR03 U1_CHR02 (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 U1_EGR03B U1_EGR03A U1_EGR03B U1_EGR03A