Text

DC Cook, 2010 Initial License Exam, Scenarios
	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)
	v • d • e

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 Event Type* Description 1 N Start South NESW Pump and Stop the North NESW pump.

2 R Raise Reactor Power and Turbine Load 3

CBPN C-BOP North CB pump trip; Middle CB pump fails to start in AUTO FW58B 4 NTP111 to I-RO Loop 1 Hot Leg NTP-111 Temperature Transmitter Fails High 650°F TS 5 QTC302 @ C-RO Letdown Temperature Controller fails LOW 50°F 6 MPP212 to I-BOP S/G 11 Pressure Transmitter MPP-212 Fails High 100%

TS 7 RC10A Major Large Break Loss of Coolant Accident on Loop 1 ramp to 20%

(Starts Out Slowly)

RC01A at 50% after 5 min.

8 RP19D - C-RO Slave Relay Failure: 1E RHR and SI Pumps Fail to Auto Start Preload 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

Summary The scenario starts with the plant at 78% power. Power escalation has been on hold for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 Cook Plant Unit 1 & Unit 2 Page 2 of 2

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 Transmitter (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.

RO 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

Op-Test No.: Crews 1,2,& 3 Scenario No.: Cook 2010-01 Event No.: 4 Event

Description:

Loop 1 RCS Hot Leg Temperature Transmitter (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)

Cook Plant Unit 1 & Unit 2 Page 7 of 7

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:

1. Checks SG PORVs closed

2. Reports 1-MPP-212 has failed high

3. Ensures 1-MRV-213, SG 11 PORV in manual 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 Attachment A of E-0 Checks all ECCS pumps running and manually starts:

Critical

1E RHR pump Task #1

1N SI pump (Not Critical)

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

Train B BOP Manually controls AFW flow to maintain SG narrow range levels 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

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.

Cook Plant Unit 1 & Unit 2 Page 12 of 12

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 Directs/Performs switchover as follows:

NOTE: If RWST level < 9% then stop CCPs and SI pumps.

Critical 1. Stops and locks out East CTS pump Task #2 2. Stops and locks out East RHR pump

3. Checks East CTS and East RHR pumps stopped

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

7. Checks West CTS and West RHR pumps stopped

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 Continues to direct/perform switchover as follows:

9. Restores control power to 1-ICM-305, Recirc sump to east Critical RHR/CTS pumps Task #2 10. Checks 1-ICM-305 open interlock:

1-IMO-310 fully closed

1-IMO-215 fully closed

11. Opens 1-ICM-305

12. Starts:

East RHR pump

East CTS pump

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

18. Checks at least one RHR pump running on the recirc sump

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

CRITICAL TASK

SUMMARY

(COOK 2010-01)

Task Elements Results

1 Cueing: SAT / UNSAT

Check ECCS Pumps ALL running (E-0, Step 7 -

Manually starts Att. A Step 1) 1E RHR pump

Check RHR Hx Flow Indicated (E-1, Step 12.

(one low-head RNO)

ECCS pump)

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

2 Cueing: SAT / UNSAT

E-0 Foldout Page, Criteria 3 (switchover criteria)

Establish Cold Leg

E-1 Foldout Page, Criteria 5 (switchover criteria)

Recirculation Flow

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.

Cook Plant Unit 1 & Unit 2 Page 16 of 16

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:

FW58B, Middle CB pump fails to start in AUTO U1_FW58B

RP19D (ECCS slave relay failure) U1_RP19D

8. Assign file SI Signal {U1_RP:SI(1) ll U1_RP:SI(2)} to event trigger ET10 U1 SI on Trg E10 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)

Cook Plant Unit 1 & Unit 2 Page 17 of 17

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 South NESW strainer DP ~ 65 (Less than 100 limit)

EVENT #2 No additional actions required EVENT #3 When crew has performed the required power change, CBPN (North CB pump trip)

U1_CBPN If contacted as AEO to investigate Condensate 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 that the motor smells of burnt insulation.

If Required (to have Control Rods returned to Auto), 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 U1_RPR119 TS-411G RPR121 U1_RPR121 TS-412D RPR117 U1_RPR117 TS-411C RPR120 U1_RPR120 TS-411H RPR122 U1_RPR122 TS-412G RPR118 U1_RPR118 TS-411D 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 Cook Plant Unit 1 & Unit 2 Page 19 of 19

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 U1_RPR096 PS-516C RPR097 U1_RPR097 PS-516D 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.

U1_CHR02 OR U1_CHR03 (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 U1_EGR03A U1_EGR03A EGR 03B U1_EGR03B U1_EGR03B EGR 04A U1_EGR04A U1_EGR04A EGR 04B U1_EGR04B U1_EGR04B Cook Plant Unit 1 & Unit 2 Page 21 of 21

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 Malf. No. Event Event No. Type* 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 SG Feed Flow Instrument (FFC-210) fails LOW TS 4 NLP151 @ 0 I-RO Controlling Pressurizer Level Channel (NLP-151) fails LOW TS 5 WCP C-RO West CCP pump trips (May insert prior to letdown restoration in TS event 4) 6 RX11D @100% C-BOP SG PORV Controller Failure TS 7 ED05H M Loss of Bus T11A due to fault on Bus 1A ED05D 1A RCP Bus Fault (Loss of RCS Flow in Loop 1) 8 TC02A C-BOP Main Turbine Fails to Trip/

RP07A Steam Line Auto Isolation Failure RP07B 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

Summary The scenario starts with the plant 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 the failure to provide adequate 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 immediately 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 Unit 1 & Unit 2 Page 2 of 18

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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

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)

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.

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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Cook Plant Unit 1 & Unit 2 Page 8 of 18

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):

TS 3.7.4, SG PORVs (Note: Only Manual Ops Required) - N/A

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 Performs the (secondary) immediate actions of E-0:

US/BOP 1. Checks Turbine Trip

Determines that ALL Turbine Stop Valves are NOT Closed.

Critical

Attempts Manual Turbine trip via the solenoid Trip.

Task #1

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 Attempts to establish secondary heat sink to one SG:

Starts TDAFP from Control Room.

Critical

Verify total feed flow > 240E3 PPH (FMO-211, 221, 231, 241 are Task #2 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

CRITICAL TASK

SUMMARY

(COOK 2010-02)

Task Elements Results

1 Cueing: SAT / UNSAT

Turbine Stop Valve Status Lights - NOT LIT (E-0 Manually Trip step 2)

Turbine/Isolate

Turbine Control Valve Indicators - NOT at Zero Steam Lines

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

SG Steam Flow at 0 lbm/hr

2 Cueing: SAT / UNSAT

Check TDAFP Trip and Throttle Valves/Manually Manually Starts Start AFW pump(FR-H.1, Step 4.b.3 & 4.c)

Turbine Driven AFW Pump 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)

Cook Plant Unit 1 & Unit 2 Page 12 of 18

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 U1_TC02 RP07A Train A Steamline Isolation Failure U1_RP07A RP07B Train A Steamline Isolation Failure U1_RP07B FW48C, Failure of TD AFW pump AUTO start U1_FW48C

9. Assign the following (pre-load) malfunctions to Event Trigger (ET) 7:

ED05E, T11A Bus fault U1_ED05E - On Trig 7 ED05A, 11A Bus fault U1_ED05A - On Trig 7

10. Assign file U1ReactorTripBreaker to event #9: U1 Rx Trip FW51, TD AFW pump T&TV blown control fuse U1_FW51 Cook Plant Unit 1 & Unit 2 Page 13 of 18

SIMULATOR INSTRUCTIONS (COOK 2010-02)

Scenario:

EVENT #1 When requested by crew, provided the following 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 from West CCP is 61 gpm.

Step 4.1.4: Report that the West CCP lube oil pressure at LPI-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 Increaser 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.

Cook Plant Unit 1 & Unit 2 Page 14 of 18

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 U1_RPR017 FS-510A RPR018 U1_RPR018 FS-510B RPR151 U1_RPR151 FS-510J IOV ZLOSTMC2[1] to ON to simulate lifting Test Rack ZLOSTMC2_U1[1]

Delete Override ZLOSTMC2[6] to simulate closing cabinet Door ZLOSTMC2_U1[6]

Cook Plant Unit 1 & Unit 2 Page 15 of 18

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)

U1_NLP151 If directed, to trip bistables for NLP-151 use:

ZLOSTMC2[6] to ON to simulate opening CH 1 cabinet Door ZLOSTMC2_U1[6]

(Override Lights/Relays - RX Flux panel)

Remote Bistable RPR041 U1_RPR041 LS/459A ZLOSTMC2[1] to ON to simulate lifting Test Rack ZLOSTMC2_U1[1]

ZLOSTMC2[6] deleted to simulate closing cabinet Door ZLOSTMC2_U1[6]

NOTE:

May Insert Event 5 at this time (Letdown restoration actions will be repeated in event 5)

EVENT #5 When crew has recovered from PRZ Level channel failure (Note - may 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 evaluate West CCP operations, report back after some 5 min. delay that motor insulation smells burnt and the overcurrent trip flag is indicated on the breaker.

Cook Plant Unit 1 & Unit 2 Page 16 of 18

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, report as the AEO and/or Maintenance that T&TV appears to be functional 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.

U1_CHR02 OR U1_CHR03 (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 are closed. ACRDA-3 is open.

If directed to secure EDG jacket water pumps select OFF then AUTO Remote OFF AUTO EGR 03A U1_EGR03A U1_EGR03A EGR 03B U1_EGR03B U1_EGR03B EGR 04A U1_EGR04A U1_EGR04A EGR 04B U1_EGR04B U1_EGR04B Cook Plant Unit 1 & Unit 2 Page 18 of 18

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 Malf. No. Event Event No. Type* Description 1 N-BOP Start South Hotwell pump and Stop North Hotwell Pump 2 NTP240 @ 620 I-RO RCS Cold Leg Temperature Instrument (NTP-240) Fails HIGH TS 3 MFC140 @ 4E6 I-BOP #14 SG Steam Flow Transmitter (MFC-140) fails HIGH over 20 sec TS 4 RC17C to 50% C-RO Pressurizer PORV NRV-153 Fails Open.

TS 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 C-RO AUTO/MANUAL Reactor trip actuation failure (ATWS)

RP03B 9 MS01D @ 20 M Steam Line Break inside Containment (#14 SG) 2 min Ramp 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)

Directs 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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:

Both FW pumps tripped (Panel 115 Drop 52, DCS Screen - Tripped status)

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 Performs the immediate actions of FR.S-1:

1. Checks reactor trip Critical Automatically/Manually insert control rods(must Insert Negative Task #1 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 Initiate Emergency Boration of RCS(must Insert Negative Reactivity Critical through Inserting Control Rods or Emergency Boration)

Task #1 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 Manually closes the following valves for SG 14:

1-FMO-241, TDAFP discharge Critical

1-FMO-242, MDAFP discharge Task #2 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 Manually closes the following valves for SG 14:

1-FMO-241, TDAFP discharge Critical

1-FMO-242, MDAFP discharge Task #2 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

CRITICAL TASK

SUMMARY

(COOK 2010-03)

Task Elements Results

1 Cueing: SAT / UNSAT

Challenge to multiple reactor trip setpoints:

Manually Trip

Low PRZ pressure reactor trip Reactor

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

2 Cueing: SAT / UNSAT

SG AFW Valves - NOT Closed Isolate Faulted

Steam generator pressure lowering Steam Generator

RCS temperature lowering Performance Indicators:

Isolate SG 14 by closing:

AFW valves

SG 14 must be isolated before transitioning out of E-2 Performance Feedback:

RCS cooldown stops

Depressurization of intact SGs stop

Feedwater flow to affected SG stops Cook Plant Unit 1 & Unit 2 Page 15 of 20

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

1-QMO-226 QMO226 Power

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 U1_RP03A RP03B, Train B RPS Reactor Trip Breaker fails to open U1_RP03B RP19J (RPS Relay K626-X3 failure) (E CTS fails to start) U1_RP19J

11. Activate the following (pre-load) malfunctions on Trigger E7:

FW05B (West MFP trip) U1_FW05B MS01D (SG #14 Steam Line Break) @ 20% over 2 Min. U1_MS01D Cook Plant Unit 1 & Unit 2 Page 16 of 20

SIMULATOR INSTRUCTIONS (COOK 2010-03)

Scenario:

EVENT #1 When directed, to align Hotwell Pump Seal Quench 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 ZLOSTMC2_U1[9]

(Override Lights/Relays - RX Flux panel)

Remote Bistable RPR137 U1_RPR137 TS/441G RPR139 U1_RPR139 TS/442D RPR135 U1_RPR135 TS/441C RPR138 U1_RPR138 TS/441H RPR140 U1_RPR140 TS/442G RPR136 U1_RPR136 TS/441D IOR ZLOSTMC2[4] to ON to simulate lifting Test Rack ZLOSTMC2_U1[4]

DOR ZLOSTMC2[9] to simulate closing cabinet Door ZLOSTMC2_U1[9]

Cook Plant Unit 1 & Unit 2 Page 17 of 20

SIMULATOR INSTRUCTIONS (COOK 2010-03)

EVENT #3 After crew has stabilized the plant from the RCS temperature 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 U1_RPR039 FS/542B RPR035 U1_RPR035 FS/540A RPR036 U1_RPR036 FS/540B IOV ZLOSTMC2[1] to ON to simulate lifting Test Rack 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 Cook Plant Unit 1 & Unit 2 Page 18 of 20

SIMULATOR INSTRUCTIONS (COOK 2010-03)

EVENT #5 When crew has recovered from the PRZ PORV failure:

Call control room and report oil spray (unisolable) coming from East MFP oil pump of approximately 10 gpm. Feed pump needs to be removed within the hour.

Note: If desired the Next event (FW Pump Trip) 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) U1_RPR145 IRF RPR146 RO - (RTB) U1_RPR146 Cook Plant Unit 1 & Unit 2 Page 19 of 20

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.

U1_CHR02 OR U1_CHR03 (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 U1_EGR03A U1_EGR03A EGR 03B U1_EGR03B U1_EGR03B EGR 04A U1_EGR04A U1_EGR04A EGR 04B U1_EGR04B U1_EGR04B Cook Plant Unit 1 & Unit 2 Page 20 of 20

Appendix D Scenario Outline Form ES-D-1 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 Event Type* 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, C-BOP 1E CCW pump Trips (1W CCW [Standby] Fails to Auto CC02B - TS Start)

Preload 5 NPP151 to I-RO Pressurizer Pressure Channel NPP-151 Fails High 2500 psig TS 6 U1_BLP131 I-BOP to 103 over TS S/G 13 Level instrument (BLP-131) failing High 2 min 7 RC10D to M-ALL Loop 4 Cold Leg Primary Coolant System 700gpm Leak 70% inside Containment over 5 minutes 8 RP13A, C-BOP Failure of Automatic Phase A Actuation RP13B -

Preload 9 C-RO Slave Relay failures: High Head Charging SI valves fail to RP19G, align RP20G -

Preload

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 Page 1 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 Operating Procedure, defeat the failed channel, address Technical Specifications, then restore 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 and 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 Reactor 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 Valves. 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 Cook Plant Unit 1 & Unit 2 Page 2 of 21

Appendix D Required Operator Actions Form ES-D-2 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 Cook Plant Unit 1 & Unit 2 Page 3 of 21

Appendix D Required Operator Actions Form ES-D-2 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 Cook Plant Unit 1 & Unit 2 Page 4 of 21

Appendix D Required Operator Actions Form ES-D-2 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.

Cook Plant Unit 1 & Unit 2 Page 5 of 21

Appendix D Required Operator Actions Form ES-D-2 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

3. Checks CCW flow to RCPs normal

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.

Cook Plant Unit 1 & Unit 2 Page 6 of 21

Appendix D Required Operator Actions Form ES-D-2 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 Cook Plant Unit 1 & Unit 2 Page 7 of 21

Appendix D Required Operator Actions Form ES-D-2 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of pressurizer pressure channel failure.

Cook Plant Unit 1 & Unit 2 Page 8 of 21

Appendix D Required Operator Actions Form ES-D-2 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 )

Cook Plant Unit 1 & Unit 2 Page 9 of 21

Appendix D Required Operator Actions Form ES-D-2 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%.

Cook Plant Unit 1 & Unit 2 Page 10 of 21

Appendix D Required Operator Actions Form ES-D-2 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 Manually opens high head safety injection valves:

BIT Outlet Valves Critical Task o 1-ICM-250 -AND/OR- 1-ICM-251

1 Note: Event 9, Manually align the High Head Injection Valves.

US/RO Manually actuates Containment Isolation - Phase A.

CREW Manually stops all Reactor Coolant Pumps (RCPs) within 5 minutes of RCS pressure lowering below 1300 psig.

Critical Task

2 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 >240x103)

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.)

Cook Plant Unit 1 & Unit 2 Page 11 of 21

Appendix D Required Operator Actions Form ES-D-2 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

2. Stops RHR pumps if RCS pressure is stable or rising

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 Cook Plant Unit 1 & Unit 2 Page 12 of 21

Appendix D Required Operator Actions Form ES-D-2 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 >40°F 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 Cook Plant Unit 1 & Unit 2 Page 13 of 21

Critical Task Summary (UCOOK2010-04)

Task Elements Results

1 Cueing: SAT / UNSAT

Check ECCS Flow: BIT - Flow Indicated (E-0, Manually open high Attachment A Step 2.a) head safety injection -OR-valves

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)

2 Cueing: SAT / UNSAT

RCS pressure - less than 1300 psig AND CCPs or SI Manually trip all pumps - at least one running Reactor Coolant o E-0, Foldout Page, Step 1 Pumps 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 Cook Plant Unit 1 & Unit 2 Page 14 of 21

Simulator Instructions (COOK2010-04 )

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 U1_EGR15

EGR02 Value RO U1_EGR02

ZLO101FQTCD1 [GRN] Value OFF 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 Cook Plant Unit 1 & Unit 2 Page 15 of 21

Simulator Instructions (COOK2010-04 )

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 Cook Plant Unit 1 & Unit 2 Page 16 of 21

Simulator Instructions (COOK2010-04 )

Scenario:

EVENT #1 Provide feedback as required for #13 CW Pump Start.

No Diving activities are taking place or planned.

#13 CW pump was shutdown about 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 all 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 U1_CWR22 CWR23 U1_CWR23 U1_CWR23 CWR24 U1_CWR24 U1_CWR24 CWR25 U1_CWR25 U1_CWR25 CWR26 U1_CWR26 U1_CWR26 CWR27 U1_CWR27 U1_CWR27 CWR28 U1_CWR28 U1_CWR28 Cook Plant Unit 1 & Unit 2 Page 17 of 21

Simulator Instructions (COOK2010-04 )

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 should help scenario runtime)

EVENT #4 While RO is occupied (to ensure BOP must address 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.

Cook Plant Unit 1 & Unit 2 Page 18 of 21

Simulator Instructions (COOK2010-04 )

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 ZLOSTMC2_U1[6]

(Override Lights/Relays - RX Flux panel)

Remote Bistable RPR076 U1_RPR076 PS-455A RPR077 U1_RPR077 PS-455B RPR078 U1_RPR078 PS-455C RPR079 U1_RPR079 PS-455D RPR117 U1_RPR117 TS-411C RPR118 U1_RPR118 TS-411D 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]

If directed to remove power from 1-QMO-225, then activate global malfunction (YG) 101QMO225 for breaker 1-ABV-D-5C.

U1_101QMO225 Cook Plant Unit 1 & Unit 2 Page 19 of 21

Simulator Instructions (COOK2010-04 )

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 U1_RPR066 LS-539A RPR067 U1_RPR067 LS-539B 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]

Cook Plant Unit 1 & Unit 2 Page 20 of 21

Simulator Instructions (COOK2010-04 )

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.

U1_CHR02 OR U1_CHR03 (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 U1_EGR03A U1_EGR03A EGR 03B U1_EGR03B U1_EGR03B Cook Plant Unit 1 & Unit 2 Page 21 of 21

ML102220238

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