Text

Initial Submittal of Scenarios for D. C. Cook Initial Exam - March 2004
	ML041700471
Person / Time
Site:	Cook
Issue date:	03/15/2004
From:	Bailey R; American Electric Power Co
To:	; NRC/RGN-III
References
	50-315/OL04-301, 50-316/OL04-301
	Download: ML041700471 (99)
	v • d • e

Cook Plant Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK04-01 Op-Test No.: Set 1 Examiners: _________________ Operators:___________________

Initial Conditions: IC-26, BOL2: 78% power, 4 GWD, 1079 ppm Boron, Xenon building in Turnover: Thunderstorm Warning with 2CD EDG OOS; Shift Hotwell Pumps then Raise power to 99%.

Event Malf Event Event No. No. Type* Description 1 N Start South Hotwell pump and Stop North Hotwell Pump 2 R Raise Reactor Power and Turbine Load 3 RX05A @ 0 I-RO Controlling Pressurizer Level Channel (NLP-151) fails LOW 4 RX17F @ 1200 I-BOP #22 SG Pressure Instrument (MPP-222) fails HIGH 5 CC01A C-RO East CCW pump trips on overcurrent CC02B West CCW pump fails to AUTO start 6 SW07A C-BOP Main Turbine Oil Cooler Controller (WRV-970) fails LOW 7 RC01B @ 50 M RCS Loop 2 Large Break LOCA 8 RP07A C-BOP Both trains of Main Steamline Isolation fails to AUTO actuate RP07B 9 RP16A C-RO Both trains of CTS/Phase B isolation fails to AUTO actuate RP16B

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1 (Rev. 1, 1/12/2004)

Summary The scenario starts with the plant at 78% power. The crew is directed to start the South Hotwell Pump and shutdown the North Hotwell Pump. After the Hotwell pumps have been swapped, the crew is required to raise power to 99% for continued operations.

The first event will involve the controlling Pressurizer Level channel instrument (NLP-151) failing 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 second event will involve the #22 SG Pressure instrument (MPP-222) failing HIGH. This will result in the opening of #22 SG PORV (MRV-220) releasing steam to the atmosphere. BOP will be required to manually close the #22 SG PORV. Crew will be required to implement AOP actions to stabilize the plant, trip bistables, and declare #22 SG PORV Radiation Monitor Inoperable.

The third event will involve an overcurrent trip of the East CCW pump with failure of the West CCW pump to AUTO start. This will result in a loss of CCW flow until the West CCW pump is started. RO will be required to manually start the West CCW pump.

The fourth event will involve the Main Turbine Oil Cooler Controller failing LOW in AUTO. This will result in the loss of adequate cooling to the Main Turbine Oil Cooler and temperature alarms. BOP will be required to take manual control of WRV-970 and restore temperature control to the Main Turbine Oil Cooler.

The main event will involve a RCS Loop 2 LBLOCA The unit will trip and a Safety Injection will actuate. The CTS/Phase B and the Main Steamline Isolation circuits will fail to automatically actuate requiring manual actuations. The crew will transition from E-0 to E-1. A transition may be made to FR-P.1 but the crew will return to E-1 and then to ES-1.3. The scenario will terminate when the crew has aligned RHR and CTS to the containment sump.

Critical Tasks Initiate Containment Spray/Phase B Isolation Transfer to 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 (Rev. 1, 1/18/2004)

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-01 Event No.: 1 Page 1 of 13 Event

Description:

Swap Hotwell Pumps (Start South and Stop North)

Time Position Applicant's Actions or Behavior US Directs actions of 02-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:

1. Starts the South HW pump

2. Monitors HW discharge pressure and flow

3. Directs AEO to close South HW pump disch vent valve (2-C-117S)

4. Directs AEO to close South HW pump Seal Quench throttle valve (2-C-119S)

5. Places the following switches in neutral:

Standby CB pump

Standby TACW pump

6. Stops the North HW pump

7. Directs AEO to open North HW pump disch vent valve (2-C-117N)

8. Directs AEO to throttle North HW pump seal package quench valve (2-C-119N)

9. Places the following control switches in auto:

Standby CB pump

Standby TACW pump Standby Hotwell pump US Directs the following actions to realign condensate system:

Start the South HW pump

Stop the North HW pump

Notify chemistry of condensate system configuration change.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-01 Event No.: 2 Page 2 of 13 Event

Description:

Raise Turbine and Reactor Power (If required)

Time Position Applicant's Actions or Behavior RO Calculates primary water addition per 02-OHP 4021.005.001, Attachment 6, 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 02-OHP 4021.001.006.

RO Commences power escalation:

Raises turbine load (reactor power) using the load limiter.

Maintains Tave/Tref deviation within limits by dilution and turbine load adjustments.

Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.

US Acts as reactivity manager by peer checking RO during blender operations and by verifying appropriate reactivity feedback.

BOP Monitors and maintains main electrical generator temperatures within limits per:

02-OHP 4021.059.001, Generator Stator Cooling Water System

02-OHP 4021.080.003, Generator Hydrogen Gas System NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2 Cook Plant Operator Actions Form ES-D-2

Op-Test No.: Set 1 Scenario No.: Cook 04-01 Event No.: 3 Page 3 of 13 Event

Description:

Pressurizer Level Channel (NLP-151) Fails LOW Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel #208 (Drops 4 and 5) indicative of a pressurizer (PRZ) level instrument failure.

RO Places 2-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 02-OHP 4022.013.010, Pressurizer Level Instrument Malfunction procedure.

RO Performs the following actions as directed:

1. Restores PRZ level using 2-QRV-251 or level controller

2. Reports 2-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

6. Restore Letdown per 02-OHP-4021-003-001

7. Cycle PRZ Heaters to restore control

8. Nulls and returns 2-QRV-251 and PRZ Level Controller back to auto US Initiates actions to trip bistables associated with 2-NLP-151 PZR Level Failure per Attachment A of 02-OHP 4022.013.010.

US Refers to Tech Specs (TS):

TS 3.3.1.1 RTS Instrumentation (Table 3.3-1, *Action 7)

TS 3.3.3.5 Remote Shutdown Instrumentation

TS 3.3.3.6 Post Accident (Minimum channels met)

Identifies requirement to trip associated bistables within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of pressurizer level channel failure.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-01 Event No.: 4 Page 4 of 13 Event

Description:

SG Pressure Channel MPP-222 Fails HIGH Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #214 which are indicative of a steam generator #22 water level control / pressure instrument failure (Drop 22).

BOP Verifies SG 22 MFW Reg. Valve controlling level in AUTO (44%)

Places SG 22 PORV (2-MRV-223) in MANUAL and closes valve US Enters and directs actions of 02-OHP 4022.013.012, Steam Generator Pressure Instrument Malfunction procedure.

BOP Performs the following actions as directed:

1. Verifies SG 22 level at program

2. Verifies SG 22 PORV closed

3. Verifies MFP P controller proper operation in AUTO

4. Reports 2-MPP-222 has failed US Initiates actions to trip bistables associated for 2-MPP-222 per Attachment B-3 of 02-OHP 4022.013.012.

Declares rad monitor 2-MRA-2701 inoperable US Refers to the following Tech Specs (TS):

TS 3.3.2.1 ESFAS Instrumentation (Table 3.3-3, *Action 14)

TS 3.3.3.1 Radiation Monitoring Instrumentation (Table 3.3-6)

TS 3.3.3.6 Post Accident (Minimum channels met)

TS ATR LEFM-1 EIS Event (OHP-4021-011-001)

Identifies requirement to trip associated bistables within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of steam pressure channel failure.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-01 Event No.: 5 Page 5 of 13 Event

Description:

2E CCW Pump Trips (Standby 2W CCW Pump Fails to Auto Start)

Time Position Applicant's Actions or Behavior RO Recognizes and reports CCW annunciators on Panel #204 indicative of CCW pump trip (Drops 84, 93).

RO Recognizes and reports that running (2E) CCW pump has tripped and standby (2W) CCW pump failed to auto start.

RO Manually starts 2W CCW pump in accordance with CCW ARPs.

(NOTE: May attempt 1 restart of 2E CCW pump per ARP.)

US May refer to the actions of 02-OHP-4022.016.001, CCW Malfunction procedure.

RO Performs the following 02-OHP-4022.016.001 actions if 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 US Declares 2E CCW Pump inoperable and refers to Tech Spec 3.7.3.1, Component Cooling Water System. Enters action statement to restore 2E CCW pump to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (or be in HSB within next 6 hrs and CSD within following 30 hrs).

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-01 Event No.: 6 Page 6 of 13 Event

Description:

Main Turbine Oil Cooler Controller (WRV-970) fails LOW Time Position Applicant's Actions or Behavior BOP Recognizes and reports Main Turbine annunciators on Panel #218 indicative of oil temperature problem (Drops 9).

BOP Recognizes and reports that 2-WRV-970 failed CLOSED in AUTO.

US Enters annunciator response action, and directs operator actions to place 2-WRV-970 controller to manual and restore cooling.

BOP Takes manual control of 2-WRV-970 and stabilizes MT temperatures.

US Directs operator to monitor turbine temperatures for signs of bearing damage.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-01 Event No.: 7/8/9 Page 7 of 13 Event

Description:

RCS Loop 2 Large Break LOCA; MSLI actuation failure to AUTO actuate; CTS/Phase B Isolation failure to AUTO actuate.

Time Position Applicant's Actions or Behavior US Recognizes automatic reactor trip/safety injection and directs RO/BOP to perform the immediate actions of E-0, Reactor Trip and Safety Injection.

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.

RO Performs the following actions as directed:

Checks CTS actuated - NO Critical

Checks cntmt isol phase B actuated - NO Task #1

Manually Actuate CTS/Phase B

Stops all RCPs (May be stopped when RCS Pressure <1300 psig)

Verifies CEQ fans running

Verifies CEQ fan suction dampers open

Verifies CEQ fan CCW valves open

Dispatches operator to locally secure ice condenser AHUs

Starts all hydrogen igniters (after AHUs are secure)

BOP Manually Isolate the Steam Lines BOP Manually controls AFW flow to maintain SG narrow range levels 13% [24%] -

50% once one SG narrow range level is > 13% [24%].

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-01 Event No.: 7/8/9 Page 8 of 13 Event

Description:

RCS Loop 2 Large Break LOCA; MSLI actuation failure to AUTO actuate; CTS/Phase B Isolation failure to AUTO actuate.

Time Position Applicant's Actions or Behavior RO Checks all ECCS pumps running BOP/RO Obtains Attachment A of E-0 and performs the following:

Places 2-HV-ACRF-1, (non-running) control room pressurization fan in stop

Places 2-HV-ACR-DA-1, c/r vent intake damper to ISOL

Places cntmt hydrogen sample bypass switches to bypass:

Train A

Train B CREW Completes all actions of E-0 through step 23 (Check If RCS Is Intact).

US Announces transition to E-1, Loss Of Reactor Or Secondary Coolant (at step 23 of E-0).

RO/BOP Reviews E-1 Foldout Page Criteria (see NOTE regarding cold leg switchover criteria).

NOTE:

When RWST level lowers to < 25% then the crew must immediately Transition to ES-1.3, Transfer To Cold Leg Recirculation.

See Page 10 of 13 for applicants actions or behavior associated with ES-1.3, Transfer To Cold Leg Recirculation.

US Directs actions of E-1, Loss Of Reactor Or Secondary Coolant.

Crew Enter FR-P.1, Imminent Pressurized Thermal Shock Condition if conditions are met.

US Determines that FR-P.1 is not applicable after verifying RCS Pressure is

<300 psig and RHR heat exchanger flow is >400 gpm US Returns to E-1 step in effect.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-01 Event No.: 7/8/9 Page 9 of 13 Event

Description:

RCS Loop 2 Large Break LOCA; MSLI actuation failure to AUTO actuate; CTS/Phase B Isolation failure to AUTO actuate.

Time Position Applicant's Actions or Behavior BOP Maintains SG narrow range levels 26% - 50%.

RO Check if ECCS flow should be reduced (No PZR Level).

RO/BOP Performs the following as directed:

1. Resets both trains of Safety Injection

2. Stops running Emergency Diesel Generators (EDGs)

3. Dispatches operator to secure EDG jacket water pumps RO/BOP Performs the following as directed

1. Check cold leg recirculation capability

2. Check Auxiliary Building conditions NORMAL US Check if transfer to cold leg recirculation is required (RWST <25%)

NOTE: When RWST level is less than 25%, then transition to ES-1.3 NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-01 Event No.: 7/8/9 Page 10 of 13 Event

Description:

RCS Loop 2 Large Break LOCA; MSLI actuation failure to AUTO actuate; CTS/Phase B Isolation failure to AUTO actuate.

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 < 25% per:

E-0, Foldout Page, Criteria 3

E-1, Foldout Page, Criteria 5

E-1, Step 13 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.

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 lockout East CTS pump Task #2 2. Stops and lockout East RHR pump

3. Checks East CTS and East RHR pumps stopped

4. Initiates valve closure:

2-IMO-310, East RHR pump suction

2-IMO-215, East CTS pump suction from RWST

5. Stops and lockout West CTS pump

6. Stops and lockout West RHR pump

7. Checks West CTS and West RHR pumps stopped

8. Initiates valve closure:

2-IMO-320, West RHR pump suction

2-IMO-225, West CTS pump suction from RWST NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-01 Event No.: 7/8/9 Page 11 of 13 Event

Description:

RCS Loop 2 Large Break LOCA; MSLI actuation failure to AUTO actuate; CTS/Phase B Isolation failure to AUTO actuate.

Time Position Applicant's Actions or Behavior US/RO Continues to direct/perform switchover as follows:

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

2-IMO-310 fully closed

2-IMO-215 fully closed

11. Opens 2-ICM-305

12. Starts:

East RHR pump

East CTS pump

13. Restores control power to 2-ICM-306, Recirc sump to west RHR/CTS pumps

14. Checks 2-ICM-306 open interlock:

2-IMO-320 fully closed

2-IMO-225 fully closed

15. Opens 2-ICM-306

16. Starts:

§ West RHR pump

§ West CTS pump

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

18. Resets CTS actuation

19. Closes spray additive tank valves:

2-IMO-202, outlet valve

2-IMO-204, outlet valve

2-IMO-212, eductor supply valve

2-IMO-222, eductor supply valve US Directs BOP to perform Attachment A, Splitting CCW Trains while continuing with ES-1.3 procedure body steps.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-01 Event No.: 7/8/9 Page 12 of 13 Event

Description:

RCS Loop 2 Large Break LOCA; MSLI actuation failure to AUTO actuate; CTS/Phase B Isolation failure to AUTO actuate.

Time Position Applicant's Actions or Behavior BOP Independently performs the following actions of Attachment A:

1. Checks both CCW pumps running

2. Closes CCW discharge header crosstie valves:

2-CMO-412

2-CMO-414

3. Checks east CCW pump running

4. Splits CCW trains with the misc. header on the east train:

Checks east CCW train valves open:

2-CMO-415, east CCW hx outlet to misc services

2-CMO-411, CCW suction header crosstie

Closes west CCW train valves:

2-CMO-416, west CCW hx outlet to misc services

2-CMO-413, CCW suction header crosstie

Throttles CCW return flow for each RHR Hx to 5250 gpm:

2-CMO-419 (EAST Hx)

2-CMO-429 (WEST Hx)

US/RO Continues to direct/perform switchover as follows:

20. Checks CTS Hx - ESW valves open:

Critical

2-WMO-712, to east hx Task #2

2-WMO-714, from east hx

2-WMO-716, to west hx

2-WMO-718, from west hx

21. Checks CCPs suction from RWST valves open:

2-IMO-910

2-IMO-911

22. Checks RWST level < 11 %

23. Closes SI pump discharge crosstie valves:

2-IMO-270

2-IMO-275

24. Restores power and closes SI pump recirc to RWST valves:

2-IMO-262

2-IMO-263 NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-01 Event No.: 7/8/9 Page 13 of 13 Event

Description:

RCS Loop 2 Large Break LOCA; MSLI actuation failure to AUTO actuate; CTS/Phase B Isolation failure to AUTO actuate.

Time Position Applicant's Actions or Behavior US/RO Continues to directs/perform switchover as follows:

25. Resets and closes CCP leakoff valves:

Critical

2-QMO-225 Task #2

2-QMO-226

26. Establishes east RHR supply to CCPs and SI pumps:

Opens 2-IMO-340, CCP suction from east RHR hx

27. Establishes crosstie between SI pump/CCP suction:

Opens 2-IMO-361

Opens 2-IMO-362

Checks open 2-IMO-360

28. Starts any ECCS pumps stopped due to low RWST level

29. Isolates RWST:

Restores power and closes 2-IMO-390, RHR pump suction from RWST

Restores power and closes 2-IMO-261, SI pump suction from RWST

Closes CCP suction from RWST valves:

2-IMO-910

2-IMO-911

30. Checks SI pumps/CCPs suction aligned to discharge of RHR pumps.

TERMINATE SCENARIO NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

CRITICAL TASK

SUMMARY

(COOK04-01)

Task Elements Results

1 Cueing: SAT / UNSAT Containment pressure > 2.9 psig:

Actuate

CNTMT SPRAY ACTUATED alarm Containment Spray

LOWER CNTMT PRESS HI-HI alarm

E-0, step 5, Check CTS not required Performance Indicators:

Manually actuate or align:

Train A CTS or Train B CTS.

One train of CTS must be in service prior to exceeding a Red Path on the Containment (Z)

CSFST (containment pressure of 12 psig).

Performance Feedback:

At least one train of Containment Spray is Operating

CTS Run Lights Lit and Amps Indicated

SLM-9A or SLM-9B Lights Lit as required

2 Cueing: SAT / UNSAT Switchover Criteria = RWST <25%

Establish Cold Leg

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

Recirculation Flow

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

E-1, Step 13, Check For Transfer To CL Recirc.

Performance Indicators:

At least one train of ECCS/CTS running aligned to the containment sump.

CTS and RHR pumps stopped for no longer than 5 minutes during switchover.

No total interruption of ECCS flow (CHG and SI) to the RCS during switchover.

Performance Feedback:

At least one train of ECCS/CTS pumps running /

indicating flow with suction aligned to Recirc Sump.

SIMULATOR INSTRUCTIONS (COOK04-01)

Setup:

1. Reset to IC 26

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. Set Up PPC Point (10 min Avg) and Chart Recorders

6. Start Data Collection Program Save to file ______________

7. Go to RUN and acknowledge/clear alarms

8. Activate the following (pre-load) malfunctions:

CC02B, West CCW pump fails to AUTO start

RP07A, Train A Steamline Isolation fails to AUTO actuate

RP07B, Train B Steamline Isolation fails to AUTO actuate

RP16A, Train A CTS/Phase B Isolation fails to AUTO actuate

RP16B, Train B CTS/Phase B Isolation fails to AUTO actuate

9. Activate the following malfunctions to place 2CD EDG OOS:

§ IMF EG10B

§ IMF EG06B

§ IRF EGR14 RO

§ IRF EGR15 RO

§ IRF EGR02 RO

§ IOV AN01[64] CRYWOLF Place RED clearance tags on the following switches:

§ T21C3

§ T21D8

§ CB2DGTCD

§ 2-QT-106-CD1

§ 2-QT-106-CD2 (continued on next page)

Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

SIMULATOR INSTRUCTIONS (COOK04-01)

Scenario Events:

Event #3

1. Trigger (1) IMF RX05A, final value 0 (NLP-151 fails LOW) after crew has raised power between 3 to 5%.

Event #4

2. Trigger (3) IMF RX17F, final value 1200 (MPP-222 fails HIGH) when crew has recovered from PZR level channel failure.

Event #5

3. Trigger (5) IMF CC01A (East CCW pump trip) when crew has recovered from SG Press channel failure.

Event #6

4. Trigger (7) IMF SW07A (WRV-970 fails LOW) after crew has recovered CCW flow.

Event #7

5. Trigger (9) IMF RC01B, final value 50 (RCS Loop 2 Large Break LOCA):

Main Steamline Isolation fails to AUTO actuate

CTS/Phase B Isolation fails to AUTO actuate (continued on next page)

SIMULATOR INSTRUCTIONS (COOK04-01)

Response to Crews Requests:

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

IOV ZLOSTMC2[6] to ON to simulate opening CH 1 cabinet Door (Override Lights/Relays - RX Flux panel)

Remote Bistable RPR041 LS/459A IOV ZLOSTMC2[1] to ON to simulate lifting Test Rack DOV ZLOSTMC2[6] to simulate closing cabinet Door

2. If directed, to trip bistables for MPP-222 use:

IOV ZLOSTMC2[8] to ON to simulate opening CH 3 cabinet Door (Override Lights/Relays - RX Flux panel)

Remote Bistable RPR102 PS/526C RPR103 PS/526D IOV ZLOSTMC2[3] to ON to simulate lifting Test Rack DOV ZLOSTMC2[8] to simulate closing cabinet Door

3. If contacted as AEO or Maintenance to evaluate East CCW pump trip, report back after some 5 min.

delay that motor is HOT and breaker has OC trip indication.

4. If contacted as AEO to investigate Main Turbine Operations, report back after some 3 min. delay that parameters are at the high end of the normal band but stable.

Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

Cook Plant Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK04-02 Op-Test No.: Set 1 Examiners: _________________ Operators:___________________

Initial Conditions: IC-37, MOL; 99% power, 967 ppm Boron, 8 GWD, Equilibrium Xenon Turnover: Thunderstorm Warning with 2CD EDG OOS; Swap CB pumps; reduce power Event Malf. No. Event Event No. Type* Description 1 N Start Middle CB pump and place North CB pump in standby 2 R Lower reactor power and turbine load 3 Global 101BAP4 C-RO Boric Acid Pump Trip when shifting to Fast Speed 4 RX20G @ 5E6 I-BOP #24 SG Steam Flow Transmitter (MFC-140) fails HIGH 5 NI10B @ 200 I-RO Power Range NI42 fails HIGH 6 MS16A @ 0 C-BOP Main Turbine Steam seal controller (SRV-22) fails in AUTO 7 RC02C @ 40 M RCS Loop 3 SBLOCA (400 gpm) 2 min ramp 8 RP03A C-RO AUTO/MANUAL Reactor trip actuation failure (ATWS)

RP03B RP10A 9 RP10B C-RO AUTO Safety Injection actuation failure

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1 (Rev. 1, 1/23/04)

Summary The scenario starts with the plant at 99% power. The crew is directed to start the Middle Condensate Booster Pump and shutdown the North Condensate Booster Pump. After the Condensate Booster pumps have been swapped, the crew is required to lower power to 95% for Main Turbine Control Valve testing.

The first event will occur when the Boric Acid Pump shifts to Fast Speed The Boric Acid pump will trip requiring the RO to Select the Standby Boric Acid pump to continue the boration and power reduction.

The second event will involve the #24 SG Steam Flow instrument (MFC-140) failing HIGH. This will result in the opening of #24 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 third event will involve the Power Range N42 detector failing HIGH. This results in automatic control rod insertion. RO will be required to place the rod control switch in MANUAL and identify the failed channel. Crew will be required to implement AOP actions to stabilize the plant, trip Bistables, and defeat the failed channel.

The fourth event will involve the Main Turbine Steam Seal controller (SRV-22) failing in AUTO. This will result in the closing of the Steam Seal Spill valve (SRV-25)and the opening of the Steam Seal Pegging valve (SRV-22) causing a high pressure on sealing steam system. BOP will be required to take manual control, restore sealing steam.

The main event will involve an Failure of the RPS function (ATWS) with SBLOCA event. The reactor must be locally tripped and a manual Safety Injection will be required. The crew will implement FR-S.1 actions until reactor is subcritical. The crew will perform the actions of E-0, then transition to E-1. The scenario will terminate when the crew has transitioned to ES-1.2.

Critical Tasks Insert Negative Reactivity Manually actuate Safety Injection Procedures E-0, Reactor Trip or Safety Injection FR-S.1, Response to Anticipated Trip without Scram E-1, Loss of Reactor or Secondary Coolant (Rev. 1, 1/23/04)

NUREG-1021, Revision 8, Supplement 1

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-02 Event No.: 1 Page 1 of 11 Event

Description:

Swap Condensate Booster Pumps (Start Middle and Stop North)

Time Position Applicant's Actions or Behavior US Directs actions of 02-OHP 4021.054.001, Attachment 2, Operation of Hotwell (HW) and Condensate Booster (CB) Pumps to start the North CB and stop the Middle CB pumps.

BOP Performs the following to swap CB pumps as directed:

1. Places the following switches in NEUTRAL:

Standby Hotwell pump Standby TACW pump

2. Starts the North CB pump

3. Monitor Condensate flow > 2E6

4. Directs operator to close LP Heater Condensate Bypass valve

5. Places the following switches in AUTO:

Standby Hotwell pump

6. Standby TACW pump

7. Stops the Middle CB pump US Directs the following actions to realign condensate system:

Start the Middle CB pump

Stop the North CB pump

Notify chemistry of condensate system configuration change.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-02 Event No.: 2 Page 2 of 11 Event

Description:

Reduce Turbine Load / Reduce Reactor Power Time Position Applicant's Actions or Behavior RO Calculates boric acid addition per 02-OHP 4021.005.001, Attachment 6, 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 02-OHP 4021.001.003.

RO Commences power reduction:

Lowers turbine load (reactor power) using the load limiter.

Maintains Tave/Tref deviation within limits by boration and turbine load adjustments.

Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.

US Acts as reactivity manager by peer checking RO during blender operations and by verifying appropriate reactivity feedback.

BOP Monitors and maintains main electrical generator temperatures within limits per:

02-OHP 4021.059.001, Generator Stator Cooling Water System

02-OHP 4021.080.003, Generator Hydrogen Gas System NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-02 Event No.: 3 Page 3 of 11 Event

Description:

Boric Acid Pump Trip Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel #209 Drops 37 and 39 (after a time delay) which are indicative of a Boric Acid Pump Trip.

RO Verifies that 2-QRV-400 closes and/or stops makeup.

US Directs operator actions per 02-OHP-4024 Drops 37 and 39.

Directs RO to start Boric Acid Pump #3.

US Refers to Tech Specs:

3.1.2.2 Flow Paths - Operating (may be referenced) 3.1.2.6 Boric Acid Transfer Pumps - Operating (Note: Boric acid Flowpaths are still met.)

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-02 Event No.: 4 Page 4 of 11 Event

Description:

SG #24 Main Steam Flow Transmitter (MFC-140) Fails High Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #214 which are indicative of a steam flow instrument failure (Drop 41).

BOP Places 2-FRV-240, SG 24 MFW Reg. Valve controller to manual, lowers controller output to match feed flow with operable steam flow channel, and restores SG 24 level to program.

US Enters and directs actions of 02-OHP 4022.013.014, Steam Flow Instrument Malfunction procedure.

BOP Performs the following actions as directed:

1. Restores SG 24 level using manual control of 2-FRV-240

2. Places MFP P controller in manual and maintains pressure

3. Reports 2-MFC-140 has failed

4. Places 2-FS-542C selector switch in channel 2 position

5. Nulls and returns 2-FRV-240 controller to AUTO

6. Returns MFP P controller to auto US Directs actions to trip bistables associated with 2-MFC-140 Steam Flow Failure per Attachment D-1 of 02-OHP 4022.013.014.

US Refers to Tech Specs:

§ 3.3.1.1 RTS Instrumentation (Table 3.3-1, Action 7)

§ 3.3.2.1 ESFAS Instrumentation (Table 3.3-3, Action 14*).

(*)Identifies requirement to trip associated bistables within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of steam flow channel failure.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.:Cook04-02 Event No.: 5 Page 5 of 11 Event

Description:

Power Range NI42 fails HIGH.

Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel #210 which are indicative of a NI instrument failure (Drop 16, 18).

RO Places rod control switch to MANUAL.

Places Rod Stop Bypass selector in NI42 position Monitor RCS parameters US Directs operator actions per 02-OHP-4022-013-004, Power Range Malf:

Verify Rod Control switch in MANUAL Reduce turbine load to minimize Tave/Tref difference Remove NI42 channel from service RO/BOP Performs actions as directed to remove NI-42 from service Place Channel Defeat selector to NI-42 Place Upper Section Channel Current Comparator Defeat Selector to NI-42 Place Lower Section Channel Current Comparator Defeat Selector to NI-42 Place Power Mismatch Bypass selector to NI-42 Verify Delta-T Recorder Selector NOT in Channel 2 Verify Overtemperature Delta-T Recorder Selector NOT in Channel 2 Restore Rod Control to Automatic US Directs actions to trip bistables associated with NI-42 Power Range Malfunction per Attachment D of 02-OHP 4022.013.004.

US Refers to Tech Specs:

§ 3.3.1.1 RTS Instrumentation (Table 3.3-1, Action 7)

(*)Identifies requirement to trip associated bistables within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of channel failure.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-02 Event No.: 5 Page 5 of 11 Event

Description:

Reduce Turbine Load / Reduce Reactor Power Time Position Applicant's Actions or Behavior RO Calculates boric acid addition per 02-OHP 4021.005.001, Attachment 6, 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 02-OHP 4021.001.003.

RO Commences power reduction:

Lowers turbine load (reactor power) using the load limiter.

Maintains Tave/Tref deviation within limits by boration and turbine load adjustments.

Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.

US Acts as reactivity manager by peer checking RO during blender operations and by verifying appropriate reactivity feedback.

BOP Monitors and maintains main electrical generator temperatures within limits per:

02-OHP 4021.059.001, Generator Stator Cooling Water System

02-OHP 4021.080.003, Generator Hydrogen Gas System NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-02 Event No.: 6 Page 6 of 11 Event

Description:

Main Turbine Steam Seal Controller (SRV-22) fails Low Time Position Applicant's Actions or Behavior BOP Recognizes and reports Main Turbine annunciators on Panel #218 indicative of MT steam sealing problem (Drops 64).

BOP Recognizes and reports that 2-SRV-22 failed OPEN in AUTO and 2-SRV-25 failed CLOSED in AUTO.

US Enters annunciator response action:

Directs operator actions to place 2-SRV-22 controller in manual and restore sealing steam.

BOP Takes manual control of 2-SRV-22 and stabilizes Steam Seal Pressure.

US Directs operator to monitor main condenser and turbine parameters for proper operation.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-02 Event No.: 7/8/9 Page 7 of 11 Event

Description:

Small Break LOCA inside Containment RPS Reactor Trip - Failure Safety Injection Actuation - Auto Failure Time Position Applicant's Actions or Behavior RO/US 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 Enters and directs actions of 02-OHP 4022.002.020, Excessive Reactor Coolant Leakage procedure.

RO Performs the following actions as 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 to manually trip the reactor and initiate safety injection.

Directs RO/BOP to perform the immediate actions of E-0, Reactor Trip or Safety Injection (based on RCS leak rate beyond charging system capability per 02-OHP 4022.002.020).

RO Recognizes and reports failure of reactor to manually trip US Directs actions of FR-S.1, Response to Nuclear Power Generation/ATWS:

RO drive rods in manually BOP manually actuate AMSAC NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-02 Event No.: 7/8/9 Page 8 of 11 Event

Description:

Small Break LOCA inside Containment RPS Reactor Trip - Failure Safety Injection Actuation - Auto Failure Time Position Applicant's Actions or Behavior RO/BOP Performs the immediate actions of FR.S-1:

1. Checks reactor trip Critical Manually insert control rods Task #1 2. Manually actuate AMSAC

3. Checks check Turbine Trip US Ensures immediate actions of FR.S-1 are completed RO Initiate Emergency Boration of RCS Critical (must Insert Negative Reactivity through Task #1 Inserting Control Rods or Emergency Boration)

US Directs subsequent actions of FR.S-1:

Local operation of reactor trip breakers or MG set output breakers Isolation of All Dilution paths Verify Reactor subcritical - WR log power < 5% & negative SUR US Performs transition to 2-OHP-4023-E.0, Reactor Trip or Safety Injection (step 20 of FR.S-1)

US Ensures immediate actions of E-0 are completed RO/BOP Report immediate actions complete and review foldout pages.

RO/BOP Manually actuate Safety Injection signal Critical Task #2 NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-02 Event No.: 7/8/9 Page 9 of 11 Event

Description:

Small Break LOCA inside Containment RPS Reactor Trip - Failure Safety Injection Actuation - Auto Failure Time Position Applicant's Actions or Behavior BOP Manually controls AFW flow to maintain SG narrow range levels 26% - 50%

once one SG narrow range level is > 13%.

RO/BOP Performs verification of E-0 Attachment A actions as directed by US.

CREW Completes all actions of E-0 through step 23 (Check If RCS Is Intact).

US Announces transition to E-1, Loss Of Reactor Or Secondary Coolant (at step 23 of E-0).

RO/BOP Reviews E-1 Foldout Page Criteria.

US Directs actions of E-1, Loss Of Reactor Or Secondary Coolant.

BOP Restore SG narrow range levels >26%, but < 50%.

US Checks if SI Termination Criteria is MET:

§ RCS Subcooling <36°F

§ Secondary Heat Sink (SG >13% or AFW Flow >240x103

§ RCS Pressure rising or stable

§ Pressurizer Level >19%

Crew Transition to ES-1.1, Safety Injection Termination if criteria is met. (ES-1.1 Actions on Next Page. E-1 Actions Are Continued on the Last Page)

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-02 Event No.:7/8/9 Page 10 of 11 Event

Description:

Small Break LOCA inside Containment RPS Reactor Trip - Failure Safety Injection Actuation - Auto Failure 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 (at step 6 of E-1).

RO/BOP Reviews ES-1.1, Foldout Page Criteria.

Monitors RCS Subcooling >36°F and PZR Level >19%, 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. Isolate BIT Injection

2. Establish Charging Flow CREW Check if:

§ Pressurizer Level is stable and

§ RCS Pressure is Stable or Rising If NOT, Transition to ES-1.2 NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 04-02 Event No.:7/8/9 Page 11 of 11 Event

Description:

Small Break LOCA inside Containment RPS Reactor Trip - Failure Safety Injection Actuation - Auto Failure Time Position Applicant's Actions or Behavior E-1 Actions Continued 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

5. Opens control air valves to containment

6. Directs chemistry to initiate post accident sampling US Announces transition to ES-1.2, Post LOCA Cooldown &

Depressurization (step 12 of E-1).

TERMINATE SCENARIO NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

CRITICAL TASK

SUMMARY

(COOK04-02)

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 Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

CRITICAL TASK

SUMMARY

(COOK04-02) continued Task Elements Results

2 Cueing: SAT / UNSAT

Safety Injection Actuated Status Light - NOT LIT Manually Initiate (E-0 step 4.a)

Safety Injection

QMO-225 & QMO-226 Safety Injection Signal Lights - NOT LIT (E-0 step 4.b)

Check RCS Pressure < 1815 psig Flow: BIT -

Flow Indicated (E-0, Step 4a RNO)

Performance Indicators:

Manually Actuate at least one train of Safety Injection - OR -

Manually align pumps and valves to establish at least one train of high head safety injection flow.

Must be performed while in E-0 before transitioning.

Performance Feedback:

BIT flow is indicated to at least one train (as indicated by flow on cold leg BIT injection flow meters)

SIMULATOR INSTRUCTIONS (COOK04-02)

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

5. Set Up PPC Point (10 min Avg) and Chart Recorders

6. Start Data Collection Program Save to file ______________

7. Go to RUN and acknowledge/clear alarms

8. Activate the following (pre-load) malfunctions:

RP03A, Train A RPS Reactor Trip Breaker fails to open

RP03B, Train B RPS Reactor Trip Breaker fails to open

RP10A, Train A Safety Injection fails to AUTO actuate

RP10B, Train B Safety Injection fails to AUTO actuate (continued on next page)

Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

SIMULATOR INSTRUCTIONS (COOK04-02)

Setup (Continued):

9. Activate the following malfunctions to place 2CD EDG OOS:

§ IMF EG10B

§ IMF EG06B

§ IRF EGR14 RO

§ IRF EGR15 RO

§ IRF EGR02 RO

§ IOV AN01[64] CRYWOLF Place RED clearance tags on the following switches:

§ T21C3

§ T21D8

§ CB2DGTCD

§ 2-QT-106-CD1

§ 2-QT-106-CD2

10. Assign the following file to trigger (1):

boricacid4fast (@ZLO101BAP4(2) == -1)

Boric Acid Pump #4 FAST speed light lit (continued on next page)

SIMULATOR INSTRUCTIONS (COOK04-02)

Scenario Events:

Event #3

1. Trigger (1) ICF 101BAP4, triggered from Boric Acid Pump #4 FAST speed light lit using trigger file boricacid4fast (@ZLO101BAP4(2) == -1)

Event #4

2. Trigger (3) IMF RX20G, final value 5E6 (MFC-140 fails HIGH) after crew has swapped the Condensate Booster pumps.

Event #5

3. Trigger (5) IMF NI10B, final value 200 (NI42 fails HIGH), when crew has recovered from SG steam flow channel failure. Requires power reduction to < 85%.

Event #6

4. Trigger (7) IMF MS16A, final value 0 (MT Steam Seal controller fails LOW) after crew has lowered power by 3 to 5%.

Event #7

5. Trigger (9) IMF RC02C, final value 40 (Loop 3 RCS SBLOCA):

RPS Reactor Trip fails to AUTO actuate

Safety Injection fails to AUTO actuate (continued on next page)

Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

SIMULATOR INSTRUCTIONS (COOK04-02)

Response to Crews Requests:

1. If contacted as AEO to investigate Breaker 2-AB-A-1D for #4 boric acid Pump 2-PP-46-4, report that the breaker is tripped. Report that the Motor is hot and has a burnt electrical smell.

2. If directed, to trip bistables for MFC-140 use:

IOV ZLOSTMC2[6] to ON to simulate opening cabinet Door (Override Lights/Relays - RX Flux panel)

Remote Bistable RPR039 FS/542B RPR035 FS/540A RPR036 FS/540B IOV ZLOSTMC2[1] to ON to simulate lifting Test Rack DOV ZLOSTMC2[6] to simulate closing cabinet Door

3. If directed, to trip bistables for NI-42 use:

IOV ZLOSTMC2[7] to ON to simulate opening cabinet Door (Override Lights/Relays - RX Flux panel)

Remote Bistable RPR123 TS/421C RPR124 TS/421D IOV ZLOSTMC2[2] to ON to simulate lifting Test Rack DOV ZLOSTMC2[7] to simulate closing cabinet Door

4. If contacted as AEO to investigate Main Turbine Operations, report back after some 3 min. delay that all parameters are at the high end of the normal band but stable.

5. When directed as AEO to locally trip reactor, wait 2 minutes then insert IRF RPR145 RO and IRF RPR146 RO to open trip breakers.

Cook Plant Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK04-03 Op-Test No.: Set 2 Examiners: _________________ Operators:___________________

Initial Conditions: IC-932, 68% power, 150 MWD, 793 ppm Boron, Xenon building in Turnover: Perform ESW Pump Strainer functional test Event Malf. No. Event Event No. Type* Description 1 N Perform ESW pump strainer functional test 2 RX23B @ 2 I-BOP #21 SG Level transmitter fails LOW 3 RCR20 @ 3 C-RO PRZ PORV (NRV-153) Leak by (3 gpm) 101NMO153 NMO-153 fails Partially OPEN 4 R Reduce reactor power and turbine load for CSD 5 CV16A @ 100 I-RO VCT Level Transmitter (QLC-451) fails HIGH 6 FW05B C-BOP West Main Feed Pump Trip 7 RC17C @ 95 M PRZ PORV (NRV-153) fails OPEN 8 RP19C C-RO Train A K600 Relay failure: CCP to BIT Inlet valve (IMO-255) fails to Auto OPEN and 2CD EDG fails to start 9 RP10B C-RO Train B Safety Injection signal failure to actuate in AUTO or RP11B Manual mode RP11D

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1 (Rev. 1, 1-15-04)

Summary The Scenario starts with the plant at 68% power. The crew is directed to perform the ESW Pump Strainer functional test. After the ESW Pump Strainer test has been completed, the crew is required to respond to various events.

The first event will involve the #21 Steam Generator Level instrument (BLP-111) failing LOW. This results in a feedwater flow and Steam Generator level rise. BOP will be required to take manual control and restore normal level. Crew will be required to implement AOP actions to stabilize the plant and trip Bistables.

The second event will involve the Pressurizer PORV NRV-153 drifting partially open with the Block valve (NMO-153) failing to close. This will result in the loss of capability to stop NRV-153 leakage. Crew will be required to implement a power reduction to cold shutdown conditions.

The third event will involve the VCT Level instrument (QLC-451) failing HIGH. This will result in the VCT High Level alarm. RO will be required to perform a manual blend to RCS.

The fourth event will involve a trip of the West Main Feed Pump. This will result in a rapid power reduction to less than 60%. RO will be required to control reactivity while BOP lowers turbine load. Crew will be required to monitor plant conditions during power reduction.

The main event will involve the opening of NRV-153 to full open. A unit trip will be required. As the crew performs the actions of E-0, the Train B Safety Injection signal will fail to AUTO/MANUAL actuate. In addition, a K600 relay failure will prevent High Head Injection flow requiring manual actions to align the BIT.

The crew will transition to E-1. The scenario will terminate when the crew has transitioned to ES-1.2 for Post LOCA cooldown.

Critical Tasks Establish injection flow from at least one (1) high head ECCS pump Stop all running RCPs when RCS pressure is below 1300 psig Procedures E-0, Reactor Trip or Safety Injection E-1, Loss of Reactor or Secondary Coolant (Rev. 1, 1-15-04)

NUREG-1021, Revision 8, Supplement 1

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook04-03 Event No.: 1 Page 1 of 9 Event

Description:

Perform ESW pump strainer functional test (East ESW Pump in Service)

Time Position Applicant's Actions or Behavior US Directs the performance of 02-OHP-5030-019-001, ESW Pump Strainer Functional Check. Step 4.2.1 BOP Shift Backwash Selector switch to opposite strainer and verify:

Proper sequencing of strainer backwash indicating lights Minor lowering in ESW header pressure during backwash cycle BOP Shift Backwash Selector switch to opposite strainer and verify:

Proper sequencing of strainer backwash indicating lights Minor lowering in ESW header pressure during backwash cycle BOP Place the Control Mode switch to AUTO Verify local operator observed satisfactory equipment operation.

BOP Place ESW pump strainer control switch in AUTO NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 04-03 Event No.: 2 Page 2 of 9 Event

Description:

21 SG Level Channel BLP-111 Fails LOW Time Position Applicant's Actions or Behavior BOP Recognizes failure of BLP-111 Low and reports associated alarms:

Panel #213 Drops 3 and 5 - Level Low BOP Verifies controller for 2-FRV-210 in manual, raises controller output to match feed flow with steam flow and stabilizes SG 21 level, as required.

US Directs actions of 02-OHP 4022.013.013, Steam Generator Level Instrument Malfunction procedure.

BOP Performs the following actions as directed:

1. Restores SG 21 level to program (44%), as required

2. Reports 2-BLP-111 has failed US Direct actions to trip bistables per Attachment A-2 of 02-OHP 4022.013.013.

Declares level channel input inoperable US Refers to the following Tech Specs (TS):

TS 3.3.1.1 RTS Instrumentation (Table 3.3-1, *Action 7)

TS 3.3.2.1 ESFAS Instrumentation (Table 3.3-3, *Action 14)

TS 3.3.3.6 Post Accident Instrumentation (Minimum channels met)

Identifies requirement to trip associated bistables within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of level channel failure.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 04-03 Event No.: 3 Page 3 of 9 Event

Description:

Pressurizer PORV (NRV-153) Leakage/Block valve (NMO-153) fails Partially OPEN Time Position Applicant's Actions or Behavior RO Recognizes indication of partially open PORV and reports annunciators:

Panel #208 Drop 23 and 24 - PORV open.

US Directs RO to close PORV NRV-153.

Directs RO to close NMO-153, PORV Block Valve when the PORV wont CLOSE.

RO Attempts to manually close PORV (NMO-153) Block valve.

Recognizes / reports loss of NMO-153 indication and failure to CLOSE.

Note:

Procedure 02-OHP-4022-002-009 is written to identify the leaking valve and isolate it. The crew has indication as to which valve is leaking and so may reference the procedure as applicable.

US May Direct operator action per 02-OHP-4022-002-009, Leaking PORV:

Manually close All PORV Block valves US Declares PORV 2-NRV-153 and Block Valve2-NMO-153 inoperable, Refers to Tech Spec 3.4.11 and complies with Actions b & e:

Be in Hot Standby within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and

Be in Hot Shutdown within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Refers to Tech Spec 3.4.6.2, RCS Leakage RO Monitors PRZ pressure control system and ensures pressure remains at normal conditions (~2235 psig).

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 04-03 Event No.: 4 Page 4 of 9 Event

Description:

Reduce Turbine Load / Reduce Reactor Power Time Position Applicant's Actions or Behavior RO Calculates boric acid addition per 02-OHP 4021.005.001, Attachment 6, 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 02-OHP 4021.001.003.

RO Commences power reduction:

Lowers turbine load (reactor power) using the load limiter.

Maintains Tave/Tref deviation within limits by boration and turbine load adjustments.

Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.

US Acts as reactivity manager by peer checking RO during blender operations and by verifying appropriate reactivity feedback.

BOP Monitors and maintains main electrical generator temperatures within limits per:

02-OHP 4021.059.001, Generator Stator Cooling Water System

02-OHP 4021.080.003, Generator Hydrogen Gas System NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 04-03 Event No.: 5 Page 5 of 9 Event

Description:

VCT Level Transmitter (QLC-451) fails HIGH Time Position Applicant's Actions or Behavior RO Recognizes indication of VCT Level problem and reports annunciators:

Panel #209 Drop 47 - VCT Level High US Directs operator action per 02-OHP-4022-013-017, VCT Level Malf:

Restores Divert valve (QRV-303) to VCT position

Trip Interposing Relay in accordance with Attachment A RO Recognizes and reports failure of VCT Level Transmitter (QLC-451).

Place Divert valve (QRV-303) in VCT position

Perform MANUAL blend operation to maintain VCT level in band US Refers to the following Tech Specs (TS):

TS 3.1.2.2 Reactivity Control Systems Interposing Relay must be actuated for Refueling Water Sequence (4.1.2.2.c)

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 04-03 Event No.: 6 Page 6 of 9 Event

Description:

West Main Feed Pump Trip Time Position Applicant's Actions or Behavior BOP Recognizes indication of MFP trip and reports annunciators:

Panel #215 Drop 71 - West MFP Emergency System Tripped.

US Directs operator actions per 02-OHP-4022-055-001, Loss of One MFP:

Manually runback Turbine Load to < 60%

Verify Rod Control in AUTO

Start AFW pumps

Verify Standby Condensate Pumps running

Initiate Boration to maintain rods above RIL RO Verify rod control switch in AUTO and functioning properly.

Initiate normal or emergency boration flow.

BOP Manually runback turbine load to < 60% as directed.

Start All AFW pumps.

Verify Standby Condensate Booster and Hotwell pumps are running.

Raise East MFP Steam supply to Main Steam (2-ARV-11) controller to 95 psig.

Verify SG levels are stable at or returning to normal (44%).

US Direct operator actions to restore normal system alignment:

Stop running AFW pumps and align for standby condition

Align Condensate system for current plant conditions NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 04-03 Event No.: 7/8/9 Page 7of 9 Event

Description:

PZR PORV (NRV-153) fails OPEN causing Steam Space LOCA in Containment; Safety Injection Train B Isolation failure to AUTO/MANUAL actuate.

Time Position Applicant's Actions or Behavior RO Recognize and reports abnormal RCS leakage:

RCS pressure lowering with PZR Heaters ON

NRV-153 PORV indicates open US Directs RO/BOP to perform the immediate actions of E-0, Reactor Trip or Safety Injection.

RO/BOP Performs the immediate actions of E-0:

1. Checks reactor trip

2. Checks turbine trip

3. Checks power to AC emergency buses

4. Checks safety injection status US Ensures immediate actions of E-0 are completed Directs subsequent actions of E-0.

RO/BOP Check Systems in Proper Emergency Alignment:

Manually OPEN IMO-255, CCP to BIT inlet valve OR Train B BIT Critical Task #1 RO/BOP Check Systems in Proper Emergency Alignment:

Manually start Both EDGs

Manually align Train B ECCS equipment for SI US/RO Foldout Page - RCP Trip Criteria:

Stop all RCPs when RCS is < 1300 psig and CCP/SI pump running Critical Task #2 RO/BOP Performs manual actions of E-0 Attachment A as directed by US.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 04-03 Event No.: 7/8/9 Page 8 of 9 Event

Description:

PZR PORV (NRV-153) fails OPEN causing Steam Space LOCA in Containment; Safety Injection Train B Isolation failure to AUTO/MANUAL actuate.

Time Position Applicant's Actions or Behavior BOP Manually controls AFW flow to maintain SG narrow range levels 13% - 50%

once one SG narrow range level is greater than 13%.

RO Checks PRZ PORVs closed - NO US Announces transition to E-1, Loss of Reactor or Secondary Coolant and directs operator actions.

RO/BOP Completes actions of E-1 through step 12 (Check if RCS Cooldown and Depressurization is required) as directed.

BOP Restore SG narrow range levels >26%, but < 50%.

US Checks if SI Termination Criteria is MET:

§ RCS Subcooling <36°F

§ Secondary Heat Sink (SG >13% or AFW Flow >240x103

§ RCS Pressure rising or stable

§ Pressurizer Level >19%

Crew Transition to ES-1.1, Safety Injection Termination if criteria is met.

(ES-1.1 Actions on Next Page.

E-1 Actions Are Continued Below)

US/RO Verifies RCS pressure is NOT stable or rising US Announces transition to ES-1.2, Post LOCA Cooldown and Depressurization (at step 12).

TERMINATE SCENARIO NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 04-03 Event No.: 7/8/9 Page 9 of 9 Event

Description:

PZR PORV (NRV-153) fails OPEN causing Steam Space LOCA in Containment; Safety Injection Train B Isolation failure to AUTO/MANUAL actuate.

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 >36°F and PZR Level >19%, 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. Isolate BIT Injection

2. Establish Charging Flow CREW Check if:

§ Pressurizer Level is stable and

§ RCS Pressure is Stable or Rising If NOT, Transition to ES-1.2 TERMINATE SCENARIO NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

CRITICAL TASK

SUMMARY

(COOK04-03)

Task Elements Results

1 Cueing: SAT / UNSAT

Check ECCS Flow: BIT - Flow Indicated (E-0, Manually open high Step 12.a) head safety -OR-injection valves

Check Systems In Proper Emergency Alignment:

ECCS Monitor lights - Proper Status (E-0, Step 15.c)

Performance Indicators:

Manually open BIT (outlet/inlet) valves to establish at least one train of high head safety injection flow.

Must be performed while in E-0 before transitioning to E-1.

Performance Feedback:

BIT flow is indicated to at least one train (as indicated by flow on cold leg BIT injection flowmeters)

Cueing:

RCS pressure - less than 1300 psig AND CCPs

2 or SI pumps - at least one running SAT / UNSAT

E-0, Foldout Page, Step 1 Manually trip all

E-0, Step 19 Reactor Coolant

E-1, Foldout Page, Step 1 Pumps

E-1, Step 1 Performance Indicators:

Manually stop all Reactor Coolant Pumps (RCPs) when RCS pressure is less than 1300 psig.

RCPs must be tripped within 5 minutes of the trip criteria being met.

Performance Feedback:

RCP ammeters - zero current

RCP trip low flow alarms - lit

RCS loop flow meters - flow lowering

SIMULATOR INSTRUCTIONS (COOK04-03)

Setup:

1. Reset to IC 932 @ 68% Power

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. Set Up PPC Point (10 min Avg) and Chart Recorders

6. Start Data Collection Program Save to file ______________

7. Go to RUN and acknowledge/clear alarms

8. Restore Summary File COOK04-03

9. Verify the following (pre-load) malfunctions:

RP10B, Train B Safety Injection fails to AUTO actuate

RP11B, Train B Safety Injection fails to MANUAL actuate

RP11D, Train B Safety Injection fails to MANUAL actuate

RP19C, Train B K609 RELAY FAILURE Assign the following to Trigger 3:

Override NRV-153 RED light ON:

IOV ZLO101NRV153[RED] ON

Override Panel 208 Drop 23 annunciator ON:

IOV AN08[023] CRYWOLF Assign the following to Trigger 4:

IMF 101NMO153

Assign FILE: NMO153 to CLOSE (ZLO101NMO153(1) == -1)

(continued on next page)

Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

SIMULATOR INSTRUCTIONS (COOK04-03)

Scenario Events:

Event #2

1. Trigger (1) IMF RX23B, final value 2 (BLP-111 fails LOW).

Event #3

2. Trigger (3) IRF RCR20, final value 3, (NRV-153 partially open) when crew has recovered from SG level channel failure.

Event #5

3. Trigger (5) IMF CV16A, final value 100 (QLC-451 fails HIGH) when crew has performed a power reduction of 3% to 5%.

Event #6

4. Trigger (7) IMF FW05B (West MFP trip) when crew has recovered from the VCT Level channel failure.

Prior to trigger activation, call control room and report oil spray (unisolable) coming from West MFP oil pump of approximately 10 gpm.

Event #7

5. Trigger (9) MMF RC17C, final value 95 (RCS Steam Space LOCA):

Train B Safety Injection fails to AUTO/MANUAL actuate (continued on next page)

SIMULATOR INSTRUCTIONS (COOK04-03)

Response to Crews Requests:

1. If directed, to trip bistables for BLP-111 use:

IOV ZLOSTMC2[7] to ON to simulate opening cabinet Door (Override Lights/Relays - RX Flux panel)

Remote Bistable RPR050 LS/519A RPR051 LS/519B IOV ZLOSTMC2[2] to ON to simulate lifting Test Rack DOV ZLOSTMC2[7] to simulate closing cabinet Door

2. If contacted as AEO to investigate the trip of NMO-153 breaker EZC-D-3D, report that the breaker is tripped.

3. If directed to energize interposing relay for QLC-451 then use:

Remote Function RPR157 to Trip LBX-112B

4. If contacted as AEO to investigate West MFP Operations, report back after some 3 min. delay that excessive oil spray and residue in the area with the MFP tripped.

Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

Cook Plant Scenario Outline Form ES-D-1 Facility: _Cook Plant Unit 1 & Unit 2_ Scenario No.: _COOK04-04_ Op-Test No.: _Spare_

Examiners: _________________ Operators:___________________

Initial Conditions: IC-36, MOL; 79% power, 1013 ppm Boron, 8 GWD, Xenon building in Turnover: Power Escalation in progress; PRZ PORV NRV-153 leakage with Block valve NMO-153 closed Event Malf. No. Event Event No. Type* Description 1 R Raise reactor power and turbine load 2 RX18 @ 1200 I-BOP Main Steam Bypass Header Pressure transmitter (UPC-101) fails HIGH 3 FW34A C-BOP North CB pump trip; Middle CB pump fails to start in AUTO FW58B 4a RX09A @ 2 I-RO PRZ Pressure Master Controller fails LOW 4b ED07B C-RO Loss of Bus 21PHC 5a RC23C @ 30 M SGTR on #23 SG (300 gpm) 2 min ramp 5b MS04D @ 20 M Steam Line Break outside Containment (#24 SG) - downstream of 2 min delay MSIV 6 RP07A C-BOP Steam Line Isolation fails to AUTO actuate RP07B 7 RP20B C-BOP SI Train B - K609 Relay fails to actuate

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1 (Rev. 1, 1/9/2004)

Summary The scenario starts with the plant at 79% power. The crew is directed to raise power to 100% for continued operations.

The first event will involve the Main Steam Bypass Header pressure instrument (UPC-101) failing HIGH. This results in raising both Feed pumps speed and flow output with corresponding rise in steam generator level. BOP will be required to take manual control of feed pump speed.

The second event will involve 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 third event will involve the Pressurizer Pressure Master Controller failing LOW and a loss of Bus 21PHC.

This will result in < 50% Pressurizer Heaters capability. RO will be required to take manual control of Pressurizer Pressure Master Controller and restore normal pressure control. The Crew will be required to implement compensatory actions to restore power to Bus 21PHC and recover full heater capability.

The main event will involve a Main Steamline Break outside containment on the #24 SG (isolatable). The unit will trip and a Safety Injection will actuate. Failure of the Main Steamline Isolation actuation circuit will require a manual actuation. As the crew performs the actions of E-0, they should identify the Steam Generator Tube Rupture on #23 SG and the failure of the 2AB EDG to auto start. The crew will transition to E-3 to isolate #23 SG. The scenario will terminate when the crew has terminated SI.

Critical Tasks Isolate #23 Steam Generator Cooldown RCS Depressurize RCS to stop #23 SGTR leakage Terminate SI injection Procedures E-0, Reactor Trip or Safety Injection E-3, Steam Generator Tube Rupture (Rev. 1, 1/18/2004)

NUREG-1021, Revision 8, Supplement 1

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Spare Scenario No.: Cook 04-04 Event No.: 1 Page 1 of 8 Event

Description:

Raise Turbine and Reactor Power (If required)

Time Position Applicant's Actions or Behavior RO Calculates primary water addition per 02-OHP 4021.005.001, Attachment 6, 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 02-OHP 4021.001.006.

RO Commences power escalation:

Raises turbine load (reactor power) using the load limiter.

Maintains Tave/Tref deviation within limits by dilution and turbine load adjustments.

Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.

US Acts as reactivity manager by peer checking RO during blender operations and by verifying appropriate reactivity feedback.

BOP Monitors and maintains main electrical generator temperatures within limits per:

02-OHP 4021.059.001, Generator Stator Cooling Water System

02-OHP 4021.080.003, Generator Hydrogen Gas System NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Spare Scenario No.: Cook04-04 Event No.: 2 Page 2 of 8 Event

Description:

Main Steam Bypass Header Pressure transmitter (UPC-101) fails HIGH Time Position Applicant's Actions or Behavior BOP Recognizes feedwater control problem and reports annunciators:

Panel #215 Drop 53 - Feedwater Controller Trouble US Directs operator actions to identify feed pump controller (2-RU-5) problem US/BOP Recognize failure of instrument UPC-101 which affects Feedwater actual P signal (MU-163 output to feed pump speed control):

2-RU-5 controller fails to MANUAL

2-MR-24 recorder BLUE pen (FW P) fails LOW BOP

Monitors steam generator levels and feed pump speed.

Adjusts feed pump speed as necessary to maintain FWRVs.

US Contacts MTI to investigate failure.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Spare Scenario No.: Cook04-04 Event No.: 3 Page 3 of 8 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 annunciators:

Panel #216 Drop 72 and 73 - CB pump trip and discharge press low US Directs operator actions to stabilize the unit and restore Condensate Booster pump capacity.

Manually start standby CB pump

Place standby CB pump switch in CLOSE RO Monitor RCS & Secondary parameters for normal operations.

BOP Manually start the Middle CB pump Place North CB pump switch to TRIP and back to NEUTRAL (Clear Alarms)

Monitor Secondary parameters for normal operations NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Spare Scenario No.: Cook04-04 Event No.: 4 Page 4 of 8 Event

Description:

PRZ Pressure Master Controller fails LOW; Loss of Bus 21PHC - PRZ Heates Time Position Applicant's Actions or Behavior RO Recognizes pressurizer control problem and reports annunciators:

Panel #208 Drop 8 - PRZ Press Low Dev - Backup Htrs On Pane #208 Drop 46 & 50 - Loss of Power to heater bank Loss of TR 21 PHC breaker (trip on OL)

US Directs operator actions to take manual control of PRZ Press. Master Controller and restore normal pressure control (approx. 2235 psig)

US/RO Re-energizes PRZ control (cycling) group heaters per OHP 4024.208 Drop 46 annunciator response:

Opens breaker CB21PHD9

Closes breaker CB21PHA6 RO Monitors PRZ pressure response and ensures normal PRZ heater operations from PHA supplied heaters.

US Refers to Tech Specs (TS):

TS 3.4.4 Pressurizer (Action a) due to a loss of 1 train of pressurizer heaters.

Restore in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

TS 3.2.5 DNB & Tavg Parameters if RCS pressure goes <2000 psig.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Spare Scenario No.: Cook04-04 Event No.: 5/6/7 Page 5 of 8 Event

Description:

SGTR on #23 SG; Steam Line Break outside Containment (#24 SG) -

downstream of MSIV Time Position Applicant's Actions or Behavior RO Recognizes and reports excessive charging flow demand as indicated by:

Lowering Pressurizer level

Lowering Pressurizer pressure

PRZ level deviation alarm US Directs operator actions per 02-OHP-4022-002-020, Excessive RCS Leakage:

Raise charging flow and isolate letdown

Start the second CCP

Maintain VCT level RO Recognizes and reports RCS leak rate greater than the capacity of two charging pumps or unable to maintain pressurizer level/VCT level RO/BOP Recognizes and reports excessive NI Power rise with NO rise in containment pressure.

US Directs RO/BOP to perform the immediate actions of E-0, Reactor Trip or Safety Injection.

RO/BOP Performs the immediate actions of E-0:

1. Checks reactor trip

2. Checks turbine trip

3. Checks power to AC emergency buses

4. Checks safety injection status US Ensures immediate actions of E-0 are completed US/BOP Verify MSI requirement met:

Manually closes All Main Steam Isolation valves Critical Task #1 NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Spare Scenario No.: Cook04-04 Event No.: 5/6/7 Page 6 of 8 Event

Description:

Steam Line Break outside Containment (#24 SG) - downstream of MSIV; SGTR on #23 SG Time Position Applicant's Actions or Behavior RO/BOP Verify the following ECCS equipment alignment required for SI:

Manually start 2AB EDG.

Manually close QMO-226

Manually open IMO-256

Manually start South NESW Pump US Directs subsequent actions of E-0.

RO/BOP Performs manual actions of Attachment A in E-0 as directed by US.

US Completes all actions of E-0 through step 22 (Check If SG Tubes Are Intact).

US Announces transition to E-3, Steam Generator Tube Rupture (at step 22 of E-0).

US Directs actions of E-3, Steam Generator Tube Rupture.

US/BOP Identifies #23 steam generator as ruptured NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Spare Scenario No.: Cook04-04 Event No.: 5/6/7 Page 7 of 8 Event

Description:

Steam Line Break outside Containment (#24 SG) - downstream of MSIV; SGTR on #23 SG Time Position Applicant's Actions or Behavior US/BOP Manually closes the following valves for SG 23:

2-FMO-231, TDAFP discharge Critical

2-FMO-232, MDAFP discharge Task #1

2-MCM-231, TDAFP steam supply

2-DCR-303, blowdown sample valve NOTE: The following should be checked closed

2-FRV-230, feedwater reg. Valve

2-FMO-203, feedwater isolation valve

2-MRV-230, SG Stop Valve

2-MRV-233, PORV

2-DCR-330, blowdown isolation valve BOP Closes 2-DRV-407, SG stop valve drain valve US/BOP Directs RCS Cooldown to required core exit temperature:

Critical Task #2 RO/BOP Commence cooldown at maximum rate using INTACT (3) SG PORVs Monitor RCS Thermocouple readings for target temperature Critical Stop RCS cooldown when TCs < required temperature: _______________

Task #2 US Directs operator action to maintain TCs < required temperature (provide band)

RO/BOP Performs the following as directed:

Resets SI and Containment Isolation Phase A

Establish Control Air to Containment

Stop RHR Pumps NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Spare Scenario No.: Cook04-04 Event No.: 5/6/7 Page 8 of 8 Event

Description:

Steam Line Break outside Containment (#24 SG) - downstream of MSIV; SGTR on #23 SG Time Position Applicant's Actions or Behavior US Directs RCS Depressurization to minimize break flow:

Normal spray if RCPs are running Critical Task #3 RO Commence depressurization using Normal Spray as directed:

Monitor RCS pressure, PRZ level, and RCS Subcooling Critical

Stop RCS depressurization based upon: _______________

Task #3 US Check if ECCS flow should be terminated US/RO Terminate Safety Injection:

Stop Both SI Pumps Critical

Stop 1 CCP Task #4

Isolate BIT US/RO Establish normal charging flow Critical Task #4 US Verify ECCS flow NOT required TERMINATE SCENARIO NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

CRITICAL TASK

SUMMARY

(COOK04-04)

Task Elements Results

1 Cueing: SAT / UNSAT

Isolate Flow From Ruptured SG (E-3, Step 3)

Isolates Flow To

If Ruptured SG Then Close AFW Valves to and Affected SG (E-0, Step 7.b.3), RNO)

From The Ruptured

Check Feed Flow To Ruptured SG Isolated (E-3, Steam Generator Step 4.b)

Performance Indicators:

Isolates SG23:

Adjusts PORV setpoint at 1040 psig

Trips SGSV closed

Closes SGSV dump valves

Ensures feed flow isolated

Isolates TDAFP Steam Supply from SG #23

Isolates AFW to #23 SG when level is > 13%

Must be performed prior to RCS cooldown to preclude transition to ECA-3.1, Loss of Reactor Coolant -Subcooled Recovery Desired on low ruptured SG pressure < 250 psid above intact SG pressures.

Performance Feedback:

Stable or rising pressure in the ruptured SG.

No feedwater flow to the ruptured SG.

2 Cueing: SAT / UNSAT

Initiate RCS Cooldown (E-3, Step 7)

Establishes and Maintains RCS Performance Indicators:

Target Temperature

Performs RCS cooldown, establishes and maintains CETC temperatures below target temperature.

Temperature must be maintained within limits to prevent transition from E-3 due to either:

Loss of subcooling (high temp.)

CSF transition (low temp.)

Performance Feedback:

RCS temp. less than target temp.

CRITICAL TASK

SUMMARY

(COOK04-04) continued Task Elements Results

3 Cueing: SAT / UNSAT

Depressurize RCS Using Normal Spray (E-3, Depressurize RCS Step 17)

Performance Indicators:

Depressurizes RCS using PRZ Spray (NRV-163 &

NRV-164).

Final RCS conditions must meet SI termination criteria

Ruptured SG inventory should not risk potential consequences of SG overfill Performance Feedback:

RCS pressure lowering

PRZ level rising

4 Cueing:

Check if ECCS Should be terminated (E-3, Step Terminate Safety 20):

Injection RCS Subcooling Heat Sink >13%

RCS Pressure Rising PZR Level >19%

Performance Indicators:

Stop ECCS Pumps (2 SI & 1 CCP)

Isolate BIT Injection

Establish Normal Charging Flow Performance Feedback:

BIT Flow = 0 gpm

SI Pumps stopped

Charging Line Flow as required to Maintain PRZ Level.

SIMULATOR INSTRUCTIONS (COOK04-04)

Setup:

1. Reset to IC 36

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. Restore Summary File COOK04-04

7. Place NRV-153 and NMO-153 to CLOSE, then hang CAUTION tags:

IMF 101NMO153 Global failure

8. Verify the following (pre-load) malfunctions:

RP07A, Train A Steamline Isolation fails to AUTO actuate

RP07B, Train B Steamline Isolation fails to AUTO actuate

RP20B, Train B Safety Injection K609 Relay fails to actuate FW58B, Middle CB pump fails to start in AUTO (continued on next page)

Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

SIMULATOR INSTRUCTIONS (COOK04-04)

Scenario Events:

Event #2

1. Trigger (1) IMF RX18, final value 1200 (UPC-101 fails HIGH) after crew has raised power by 3 to 5%.

Event #3

2. Trigger (3) IMF FW34A (North CB pump trip) when crew has recovered from Main Steam Header pressure channel failure.

Event #4

3. Trigger (5) IMF RX09A, final value 2 (PZR Press master controller fails LOW) and IMF ED07B after crew has recovered from CB pump trip.

Event #5

4. Trigger (7) IMF RC23C, final value 30 (#23 SGTR) ramp over 2 mins, then: IMF MS04D, final value 20 (#24 SG Steamline Break upstream of MSIV) after 2 mins:

Steamline Isolation fails to AUTO actuate

Safety Injection Train B K609 relay fails to actuate (continued on next page)

SIMULATOR INSTRUCTIONS (COOK04-04)

Response to Crews Requests:

1. If contacted as MTI to investigate UPC-101 malfunction, report back after some 3 min. delay that the cause cannot be determine and further testing will be required.

2. 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 OL trip on North CB pump breaker.

3. If contacted as AEO to investigate Bus 21PHC operations, report back after some 3 min. delay that Breaker T21D9 has tripped on OC.

Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

Cook Plant Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK04-05 Op-Test No.: Set 1 Examiners: _________________ Operators:___________________

Initial Conditions: IC-932, 68% power, 150 MWD, 793 ppm Boron, Xenon building in Turnover: Thunderstorm Warnings with 2CD EDG Out of Service for fuel rack repairs; Swap NESW pumps.

Event Malf. No. Event Event No. Type* Description 1 N Start South NESW pump and Stop North NESW pump 2 RX19A @ 0 I-RO Turbine Impulse Transmitter (MPC-253) fails LOW 3 CV09 @ 50°F C-RO Letdown Temperature Controller fails LOW 4 RX25A @ 100 I-BOP #21 Main Feed Reg Valve (FRV-210) controller oscillation 5 FW12A @ 10 C-BOP East MFP lube oil leak 6 R Perform Rapid Power Reduction 7a ED19 @ 25 M Electrical Grid Load Rejection 7b ED01 M Loss of All AC Power (2 min delay)

ED25 EG01 8 EG08A C-BOP 2AB EDG Speed Governor failure 9 FW48C C-BOP TD AFW pump fails to AUTO start

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

Summary The crew is directed to start the South NESW Pump and shutdown the North NESW Pump while maintaining reactor power at 68%. After the NESW pumps have been swapped, the crew is required to maintain power at 79%.

The first event will involve the Turbine Impulse instrument (MPC-253) failing LOW. This results in a control rod insertion. RO will be required to place rod control in manual. Crew will be required to implement AOP actions to stabilize the plant and trip Bistables.

The second event will involve the Letdown Temperature Controller failing LOW in AUTO. This will result in the loss of letdown cooling. RO will be required to take manual control of CRV-470 and restore temperature to normal band.

The third event will involve the #21 SG Main Feedwater Regulating Valve (FRV-210) controller oscillating.

This will result in the opening and closing of FRV-210. BOP will be required to take manual control of FRV-210 to restore normal feed flow capability and restore SG level to program. The Crew will be required to implement actions to stabilize the unit. After the SG level is restored to Normal, Maintenance will replace the Failed Controller card and the FRV-210 can be restored to Auto.

The fourth event will involve an oil leak on the East MFP. This will result in a requirement to shutdown the pump. The Crew will be required to implement a power reduction to lower power to < 60%.

The main event will involve a GRID load rejection leading to a total loss of all AC power. The unit will trip.

Failure of the only available EDG will require entry into ECA-0.0 actions. Failure of the TD AFW pump to auto start will require a manual start to restore feedwater flow. The crew will be required to take actions to restore emergency (EP) power. The crew should transition to ECA-0.1 once power has been restored to one Safeguards Bus. The scenario will terminate when the crew has restored emergency power and transitioned to ECA-0.1.

Critical Tasks Establish AFW (Start TDAFWP)

Restore Emergency Power to Safeguards Bus Procedures E-0, Reactor Trip or Safety Injection ECA-0.0, Loss of All AC Power NUREG-1021, Revision 8, Supplement 1

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook04-05 Event No.: 1 Page 1 of 10 Event

Description:

Start South NESW pump and Stop North NESW pump Time Position Applicant's Actions or Behavior US Directs operator actions per 02-OHP-4021-020-002, Attachment 1:

Start South NESW pump

Stop North NESW pump RO/BOP Reviews procedural precautions and actions in Attachment 1:

Pump strainer P does not exceed 100 inches H2O

Inform Unit 1 Control Room of system alignment change RO/BOP Performs actions per Attachment 1:

Start South NESW pump

Close 2-WMO-901

Stop North NESW pump

Notify Chemistry of the NESW alignment change RO/BOP Reports North NESW pump running and South NESW pump stopped NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook04-05 Event No.: 2 Page 2 of 10 Event

Description:

First Stage Turbine Impulse transmitter (MPC-253) fails LOW Time Position Applicant's Actions or Behavior RO/BOP Recognizes and reports multiple annunciators on Panel 211, 213, and 214 for a Turbine Impulse pressure failure.

RO Verifies no runback in progress Places rod control switch in MANUAL Reports failure of MPC-253 instrument US Directs actions per

1. 02-OHP-4022.012.003, Continuous Control Bank Movement

2. 02-OHP 4022.013.016, Turbine First Stage Impulse Pressure Instrument Malfunction.

RO 1. Verifies rod control in manual.

2. Places AMSAC bypass/test switch in BYPASS/TEST

3. Places Steam Dump selector control switches to OFF US Initiates actions to trip bistables for MPC-253 failure per Attachment A of 02-OHP 4022.013.016.

RO Verifies proper bistable tripping per Attachment A.

Withdraw control rods to restore AFD as directed.

US Refers to Tech Specs:

1. TS 3.3.2.1 ESFAS Instrumentation (Table 3.3-3, Action 14)

2. TS 3.2.5, DNB (If Pressure drops <2200 psig)

3. ATR 2-AMSAC-1, ATWS Mitigation System Actuation Circuitry Identifies requirement to trip associated bistables within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of MPC-253 failure.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook04-05 Event No.: 3 Page 3 of 10 Event

Description:

CVCS Letdown Temperature Controller output fails LOW.

Time Position Applicant's Actions or Behavior RO Recognize and reports annunciator Panel 209 Drop 45 & 8 alarms which indicates a loss of CCW cooling to the letdown heat exchanger.

US Directs operator actions to restore proper temperature control for letdown.

RO Places 2-CRV-470, Letdown Temperature Control valve, controller to MANUAL Opens 2-CRV-470 and restores letdown temperature to normal Verifies letdown flow diverted to RC Filter US Initiates action to have MTI investigate problem with letdown temperature controller.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook04-05 Event No.: 4 Page 4 of 10 Event

Description:

Main Feedwater Regulating Valve (FRV-210) controller oscillations.

Time Position Applicant's Actions or Behavior BOP Recognizes and reports failure of #21 SG feedwater flow controller (FRV-210) in AUTO.

Abnormal #21 SG level

FRV-210 Controller alarm - in MANUAL US Directs operator action to take manual control and restore #21 SG level to program.

BOP Places feedwater controller for FRV-210 in MANUAL Raises Feed flow to recover SG level to program US Reports feedwater controller failure in AUTO and request Maintenance assistance in determining cause and corrective action.

US/BOP Coordinates placing FRV-210 in Auto after Maintenance repairs are complete.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook04-05 Event No.: 5 Page 5 of 10 Event

Description:

East Main Feed Pump Lube Oil leak requiring a power reduction < 60%.

Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciator Panel 215 Drop 28:

East FPT Lube Oil tank level low US Directs operator actions to verify system valve lineup and check for leaks.

US Informs SM of need to perform a rapid power reduction for East MFP

{NOTE: May recommend implementing PMP-6090-PCP-100, Spill Response -

Oil, Polluting, and Hazardous Materials.}

US Implements procedure 02-OHP-4021.001.003, Power Reduction, or 02-OHP-4022.001.006, Rapid Power Reduction, to reduce reactor power <

60%.

BOP References procedure 02-OHP-4021-055-004, Main Feedpump Turbine Shutdown, Attachment 1.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook04-05 Event No.: 6 Page 6 of 10 Event

Description:

Reduce Turbine Load / Reduce Reactor Power Time Position Applicant's Actions or Behavior Turbine Load Reduction per 02-OHP 4021.001.003, Power Reduction US Directs RO to commence Power Reduction in accordance with 02-OHP 4021.001.003.

RO Commences power reduction:

Lowers turbine load (reactor power) using the load limiter.

Maintains Tave/Tref deviation within limits by boration and turbine load adjustments.

Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.

US Acts as reactivity manager by peer checking RO during blender operations and by verifying appropriate reactivity feedback.

BOP Monitors and maintains main electrical generator temperatures within limits per:

02-OHP 4021.059.001, Generator Stator Cooling Water System

02-OHP 4021.080.003, Generator Hydrogen Gas System Turbine Load Reduction per 02-OHP 4022.001.006, Rapid Power Reduction Response US Directs RO to commence Rapid Power Reduction in accordance with 02-OHP 4022.001.006.

RO Commences power reduction:

Ensures control rods in auto or manually inserts rods.

Lowers turbine load (reactor power) using the load limiter or operating device.

US Acts as reactivity manager by peer checking RO and verifying appropriate reactivity feedback.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook04-05 Event No.: 7/8/9 Page 7 of 10 Event

Description:

Electrical Grid Load Rejection followed by a complete Loss of All AC Power /

2AB Emergency Diesel Generator Failure; Turbine Driven AFW Pump Fails to Auto Start Time Position Applicant's Actions or Behavior CREW Recognize and report a load rejection event US Implement procedure 02-OHP-4022-001-002, Loss of Load (Load Rejection)

RO Verify rod control in AUTO and controlling as expected Verify Panel 2-SML-18 Drop 5 and 10 are CLEAR BOP Verify Steam Dump control in Tavg Verify SG levels are stable or trending to program Verify Main Generator connected to GRID 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 BOP Performs the (secondary) immediate actions of E-0:

1. Checks turbine trip

2. Checks power to AC emergency buses:

Reports that NO AC emergency buses are energized NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook04-05 Event No.: 7/8/9 Page 8 of 10 Event

Description:

Electrical Grid Load Rejection followed by a complete Loss of All AC Power /

2AB Emergency Diesel Generator Failure; Turbine Driven AFW Pump Fails to Auto Start Time Position Applicant's Actions or Behavior US Announces transition to ECA-0.0, Loss Of All AC Power and directs RO/BOP to perform immediate actions for ECA-0.0.

RO/BOP Performs the immediate actions of ECA-0:0:

Checks reactor trip / turbine trip US Ensures immediate actions are completed and directs subsequent actions of ECA-0.0.

RO Checks RCS isolated:

1. Checks PRZ PORVs closed:

2. Checks letdown isolation valves closed

3. Checks excess letdown isolation valves closed

4. Places nuclear sampling isolate switches to ISOLATE:

Train A

Train B BOP Checks AFW flow > 240,000 PPH:

Manually starts the Turbine Driven AFW Pump Critical Task #1 US Recognizes that only available EDG is not running and dispatches an operator to locally close 2-QCM-350, RCP seal water return outside containment.

RO/BOP Resets SI NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook04-05 Event No.: 7/8/9 Page 9 of 10 Event

Description:

Electrical Grid Load Rejection followed by a complete Loss of All AC Power /

2AB Emergency Diesel Generator Failure; Turbine Driven AFW Pump Fails to Auto Start Time Position Applicant's Actions or Behavior RO/BOP Places the following equipment in pull to lock:

MDAFPs

CCPs

RHR pumps

SI pumps

CTS pumps

CCW pumps

NESW pumps US Dispatches an operator to locally establish vital cabinet cooling using Attachment C of ECA-0.0.

US Identifies the status of the following off-site power sources:

Reserve power - UNAVAILABLE

Emergency power (EP) - AVAILABLE US Directs Restoration of 4KV Power From EP using SUP.009 attachments to energize either pump bus first:

Attachment A - to energize Bus T21A from EP

Attachment D - to energize Bus T21D from EP BOP Energizes T21A (T21D) emergency bus from EP as directed:

1. Checks T21A (T21D) bus - not faulted Critical 2. Places DG2AB(CD) supply to bus T21A(D) in pull to lock Task #2 3. Verifies breakers open with green targets:

Bus 2A(D) supply to bus T21A(D)

4KV supply to TR21PHA(PHC)

4. Places the west (east) ESW pump in pull to lock

5. Closes 4KV EP supply to bus T21A(D)

6. Ensures EP supply current to Unit 2 remains < 600 AMPS NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook04-05 Event No.: 7/8/9 Page 10 of 10 Event

Description:

Electrical Grid Load Rejection followed by a complete Loss of All AC Power /

2AB Emergency Diesel Generator Failure; Turbine Driven AFW Pump Fails to Auto Start Time Position Applicant's Actions or Behavior US Directs BOP to energize the remaining emergency buses from EP (using SUP.009) while US and RO continue recovery actions of ECA-0.0.

BOP Energizes the remaining emergency buses from EP:

T21A(D)

T21B

T21C RO Performs the following recovery actions of ECA-0.0 as directed:

1. Controls SG PORVs to stabilize SG pressures

2. Checks the following equipment energized:

600V bus(es) associated with energized emergency bus

Control room AHU

Battery charger

CRID inverters

3. Starts available ESW pump (unless header supplied from U-1)

US Announces transition to ECA-0.1, Loss Of All AC Power Recovery Without SI Required.

TERMINATE SCENARIO NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

CRITICAL TASK

SUMMARY

(COOK04-05)

Task Elements Results

1 Cueing: SAT / UNSAT

Check AFW FlowVerify TDAFP Running (ECA-Manually Starts 0.0, Step 4, RNO)

Turbine Driven AFW Pump Performance Indicators:

Manually starts the TDAFP from the control room.

AFW flow must be established before SG dryout occurs (<15% WR level).

Performance Feedback:

TDAFP speed rising

AFW flow > 240E3 PPH

2 Cueing: SAT / UNSAT

Restore AC Power (ECA-0.0, Step 9.a, RNO a.2)

Restore Emergency Power Performance Indicators:

Restores emergency power (EP) to at least one 4KV emergency (pump) bus (i.e., T21A or T21D).

Power should be restored prior to depressurizing intact SGs to 190 psig (ECA-0.0, Step 19).

Performance Feedback:

T21A or T21D bus energized

Power available to safeguards equipment.

SIMULATOR INSTRUCTIONS (COOK04-05)

Setup:

1. Reset to IC 16

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. Set Up PPC Point (10 min Avg) and Chart Recorders

6. Start Data Collection Program Save to file ______________

7. Go to RUN and acknowledge/clear alarms

8. Activate the following (pre-load) malfunctions:

§ EG08A, 2AB EDG Speed Governor Failure

§ FW48C, TD AFW pump fails to AUTO start

9. Activate the following malfunctions to place 2CD EDG OOS:

§ IMF EG10B

§ IMF EG06B

§ IRF EGR14 RO

§ IRF EGR15 RO

§ IRF EGR02 RO

§ IOV AN01[64] CRYWOLF Place RED clearance tags on the following switches:

§ T21C3

§ T21D8

§ CB2DGTCD

§ 2-QT-106-CD1

§ 2-QT-106-CD2

10. Assign to Trigger 15

§ IMF FW07A, East FW pump bearing Failure

§ Assign file EFWPTLO Level Lo (FWLLOTKA < 32)

(continued on next page)

SIMULATOR INSTRUCTIONS (COOK04-05)

Scenario Events:

Event #2

1. Trigger (1) IMF RX19A, final value 0 (MPC-253 fails LOW) after crew has swapped the NESW pumps.

Event #3

2. Trigger (3) IMF CV09, final value 50 (Letdown Temp Controller fails LOW) when crew has recovered from turbine impulse channel failure.

Event #4

3. Trigger (5) IMF RX25A, final value 100 (FRV-210 controller oscillation) after crew has recovered from Letdown temperature controller failure.

Event #5

4. Trigger (7) IMF FW12A, final value 10 (E MFP oil leak) after crew has recovered from SG PORV controller failure.

Event #7

5. Trigger (9) IMF ED19, final value 25 (Grid Load Rejection):

IMF ED01 Delay 2 min 10 secs, Loss of 345 KV Bus 1

IMF ED25 Delay 2 min 10 secs, Loss of 765/345 KV Transformer Bank No. 4

IMF EG01 Delay 2 mins 10 secs, Main Generator Trip

Loss of Offsite AC Power

2AB EDG Speed Governor fails

TD AFW pump fails to AUTO start (continued on next page)

Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

SIMULATOR INSTRUCTIONS (COOK04-05)

Response to Crews Requests:

1. If directed, to trip bistables for MPC-253 use:

IOV ZLOSTMC2[6] to ON to simulate opening cabinet Door (Override Lights/Relays - RX Flux panel)

Remote Bistable RPR021 FS/512B RPR027 FS/522B RPR039 FS/542B RPR033 FS/532B RXR01 PS/505A RXR03 PS/505C IOV ZLOSTMC2[1] to ON to simulate lifting Test Rack DOV ZLOSTMC2[6] to simulate closing cabinet Door

2. If contacted as MTI investigate Letdown Temp controller, report back after some 5 min. delay that additional testing will be required to identify the problem.

3. If contacted as MTI investigate SG #21 Feedwater Regulating valve controller, report back after this failure has been previously identified and a replacement Card is Available. Prompt as Shift Manager as required to allow the card to be replaced and the FRV-210 restored to Auto.

DMF RX25A to simulate replacing the card.

4. If contacted as AEO to investigate East MFP operations, report unisolable leak adjacent to oil cooler

5. If directed to locally close 2-QCM-350 then SET CVVQCM350 0 (using ISD or JIS)

6. If directed to locally close 2-CCM-453 then SET CCVCCM453 0 (using ISD or JIS)

7. If directed act as AEO to perform Attachment C of ECA-0.0 (Cabinet Cooling)

8. If directed to locally close seal injection valves (2-CS-311N, 311S and 307) then activate remote functions:

CVR20 final value CLOSE

CVR21 final value CLOSE

9. If directed to restore N train battery charger then MRF EDR21 to train with power

Cook Plant Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK04-06 Op-Test No.: Set 2 Examiners: _________________ Operators:___________________

Initial Conditions: IC-17, BOL1: 99% power, 150 MWD, 729 ppm Boron, Xenon building in Turnover: Swap CCP pumps Event Malf. No. Event Event No. Type* Description 1 N Start East CCP and Stop West CCP 2 RX03D @ 650 I-RO RCS Cold Leg Temperature Instrument (NTP-241) Fails HIGH 3 R Lower Reactor Power and Turbine Load 4 RX21A @ 0 I-BOP SG Feed Flow Instrument (FFC-210) fails LOW 5 CV13A C-RO East CCP pump trips 6 RX11D @100% C-BOP SG PORV Controller Failure 7 ED05H M Loss of Bus T21D due to fault on Bus 2D ED05D 2D RCP Bus Fault (Loss of RCS Flow in Loop 1) - momentary 8 RP01A C-RO Reactor Trip (RTA) Fails to AUTO actuate RP01B Reactor Trip (RTB) Fails to AUTO actuate 9 FW51 C-BOP TDAFW pump T&TV failure due to blown control power fuse FW46B West MD AFW pump fails to start (to cause loss of all FW)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1 (Rev. 1, 1/18/2004)

Summary The scenario starts with the plant at 99% power. The crew is directed to start the East Charging Pump and shutdown the West Charging Pump. After the Charging pumps have been swapped, the crew is directed to reduce power to 80%.

The first event will involve the RCS Loop 4 Cold Leg Temperature instrument (NTP-241) 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 a small power change, the next event will involve a failure of #21 Steam Generator Feed Flow instrument (FFC-210) LOW. This will result in a rise in feedwater flow to #21 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 third event will involve the East Charging Pump trip. This will result in the loss of charging and letdown. RO will be required to manually start the West Charging Pump to restore charging flow. Crew will be required to take manual control of charging and restore letdown to stabilize the plant.

The fourth event will involve the failure of the SG #24 PORV Controller. The Controller will fail causing PORV 2-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 2D and Safety Bus T21D requiring a reactor trip. Failure of the Reactor Protection circuit will require a manual reactor trip. As the crew performs the actions of E-0, they should identify the failure to provide adequate feed flow. The crew will transition to ES-0.1 after verifying SI is not required. 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 Perform Manual Reactor Trip Establish AFW flow for Secondary Heat Sink Procedures E-0, Reactor Trip or Safety Injection FR-H.1, Loss of Secondary Heat Sink (Rev. 1, 1/18/2004)

NUREG-1021, Revision 8, Supplement 1

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook04-06 Event No.: 1 Page 1 of 8 Event

Description:

Start East CCP and Stop West CCP Time Position Applicant's Actions or Behavior US Directs operator actions per 02-OHP-4021-003-001, Attachment 5:

Start East CCP

Stop West CCP RO 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 RO Performs actions per Attachment 5, Step 4.2:

Start East & West CCP Lube Oil pumps

Place 2-QRV-251 controller in MANUAL

Start East CCP

Place East Lube Oil pump switch in STBY

Stop West CCP

Place 2-QRV-251 controller in AUTO RO Reports East CCP running and West CCP stopped NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook04-06 Event No.: 2 Page 2 of 8 Event

Description:

Loop 4 RCS Cold Leg Temperature Transmitter (NTP-241) Fails High Time Position Applicant's Actions or Behavior RO Recognizes and reports multiple annunciators on Panel #211 (RCS RTD failure.)

Auto rod motion inward RO/BOP Verifies NO runback in progress Places rod control switch in MANUAL US Directs actions per 02-OHP 4022.012.003, Continuous Control Bank Movement.

RO 1. Verifies rod control in manual.

2. Verifies rod motion has stopped

3. Verifies Rod position above Low-Low Insertion Limit

4. Verifies AFD within target band

5. Verifies NI power ranges operable

6. Reduce turbine load or Withdraw control rods to minimize Tavg/Tref mismatch

7. Report Tavg channel inoperable due to RCS Loop 4 RTD failure US Direct actions for RCS loop 4 RTD failure per 02-OHP 4022.013.007.

US Initiates actions to trip bistables for RCS loop 4 RTD failure per Attachment D RO Verifies proper bistable tripping per Attachment D.

US Refers to Tech Specs 3.3.1.1 RTS Instrumentation (Table 3.3-1, Action 6) and 3.3.2.1 ESFAS Instrumentation (Table 3.3-3, Action 14).

Identifies requirement to trip associated bistables within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of Loop 4 RCS RTD failure.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook04-06 Event No.: 3 Page 3 of 8 Event

Description:

Reduce Turbine Load / Reduce Reactor Power Time Position Applicant's Actions or Behavior RO Calculates boric acid addition per 02-OHP 4021.005.001, Attachment 6, 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 02-OHP 4021.001.003.

RO Commences power reduction:

Lowers turbine load (reactor power) using the load limiter.

Maintains Tave/Tref deviation within limits by boration and turbine load adjustments.

Ensures Axial Flux Difference (AFD) is maintained within target band by manual control rod movement as needed.

US Acts as reactivity manager by peer checking RO during blender operations and by verifying appropriate reactivity feedback.

BOP Monitors and maintains main electrical generator temperatures within limits per:

02-OHP 4021.059.001, Generator Stator Cooling Water System

02-OHP 4021.080.003, Generator Hydrogen Gas System NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook04-06 Event No.: 4 Page 4 of 8 Event

Description:

SG 21 Feedwater Flow Transmitter (FFC-210) Fails LOW Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #213 Drop 13 BOP Verifies 2-FRV-210, SG 21 MFW Reg. Valve controller in manual Raises controller output to match the operable feed flow channel with steam flow, and Restores SG 21 level to program.

US Enters and directs actions of 02-OHP 4022.013.015, Feedwater Flow Instrument Malfunction procedure.

BOP Performs the following actions as directed:

1. Restores SG 21 level using manual control of 2-FRV-210

2. Reports 2-FFC-210 has failed

3. Places 2-FS-510-C selector switch in channel 2 position.

4. Nulls and returns 2-FRV-210 controller to auto.

US Initiates actions to trip bistables associated with 2-FFC-210 FW Flow Failure per Attachment A-1 of 02-OHP 4022.013.015.

US Refers to Tech Specs and Administrative Technical Requirements

TS 3.3.1.1 RTS Instrumentation (Table 3.3-1, Action 7).

ATR - AMSAC-1 ATWS Mitigation System Actuation Circuitry

ATR - LEFM-1 Leading Edge Flow Meter Identifies requirement to trip associated bistables within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of steam flow channel failure.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook04-06 Event No.: 5 Page 5 of 8 Event

Description:

2E Centrifugal Charging Pump (CCP) Trips Time Position Applicant's Actions or Behavior RO Recognizes and reports multiple annunciators on Panel #207, #208 and

209 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 (2E) CCP has tripped.

US Directs RO to start the 2W CCP per annunciator response(s):

02-OHP 4024.208 Drop 20, Charging Flow < Min Set Point

02-OHP 4024.209 Drop 12, East CCP Motor Overload Trip RO Performs the following as directed:

Starts 2W CCP

Adjusts QRV-200 and QRV-251 flow to maintain RCP seal flow and Pressurizer level.

Places normal letdown back in service in accordance with 02-OHP 4021.003.001, Attachment 13.

US Declares 2E CCP inoperable and refers to Tech Specs (TS):

TS 3.1.2.4, Charging Pumps - Operating

TS 3.5.2, ECCS Subsystems - Tavg > 350°F Enters action statements to restore 2E CCP to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook04-06 Event No.: 6 Page 6 of 8 Event

Description:

SG PORV Controller Failure Time Position Applicant's Actions or Behavior BOP Recognize and reports Annunciator #214 Drop 24 that indicates SG #24 PORV 2-MRV-243 has failed Open US Direct operator actions to close SG PORV and monitor Reactor Power BOP Place SG PORV #24 in Manual and Closes PORV.

US Declares the SG #24 PORV radiation Monitor 2-MRA-2602 Inoperable US Refers to the following Tech Specs (TS):

TS 3.3.3.1 Radiation Monitoring Instrumentation (Table 3.3-6) Action 22B Restore in 7 days.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook04-06 Event No.: 7/8/9 Page 7 of 8 Event

Description:

Loss of Bus T21D due to fault of Bus 2D - Loss of RCS flow in one loop; Failure of RPS Reactor Trip signal to AUTO actuate; 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 failure of the reactor to automatically trip.

US/RO

Direct operator to locally open reactor trip breakers

Manually Trip Reactor Critical Task #1 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 BOP Performs the (secondary) immediate actions of E-0:

1. Verifies turbine trip

2. Checks power to AC emergency buses

Reports Loss of 4KV Bus T21D (due to fault)

Trips CD EDG or places T21D8 in PTL to prevent cyclic loading attempts US Ensures immediate actions of E-0 are completed US Announce transition to ES-0.1, Reactor Trip Response.

NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

Cook Plant Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook04-06 Event No.:7/8/9 Page 8 of 8 Event

Description:

Loss of Bus T21D due to fault of Bus 2D - Loss of RCS flow in one loop; Failure of RPS Reactor Trip signal to AUTO actuate; Loss of control power to TD AFW pump T&TV & Trip of West MDAFP Time Position Applicant's Actions or Behavior CREW Recognizes RED path on CSFST for Heat Sink which requires transition to FR-H.1 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:

Dispatches operator to locally reset TDAFP T&TV and replace Critical fuse.

Task #2

Directs operator to start TDAFP.

Verify total feed flow > 240E3 PPH.

US Announces transition to ES-0.1, Reactor Trip Response.

TERMINATE SCENARIO NUREG-1021, Revision 8, Supplement 1 Cook Plant Unit 1 & Unit 2

CRITICAL TASK

SUMMARY

(COOK04-06)

Task Elements Results

1 Cueing: SAT / UNSAT

Challenge to multiple reactor trip setpoints:

Manually Trip RCS Loop Flow Low Reactor RCP Trip Performance Indicators:

Manually open at least one reactor trip breaker from the control room.

Must be performed prior to:

SG Dryout (<15% wide range level)

Exceeding RCS safety valve limit (2485 psig)

Performance Feedback:

IRPIs indicate rods - fully inserted

Rod bottom lights - lit

Neutron flux - lowering

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 (<15% WR level).

Performance Feedback:

TDAFP speed rising

AFW flow > 240E3 PPH

SIMULATOR INSTRUCTIONS (COOK04-06)

Setup:

1. Reset to IC 17

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. Activate the following (pre-load) malfunctions:

RP01A, RTA fails to AUTO open

RP01B, RTB fails to AUTO open

FW48C, Failure of TD AFW pump AUTO start

FW46B, West MDAFP Trip/Fail to Start

7. Assign file RxTrip to event #11:

FW51, TD AFW pump T&TV blown control fuse (continued on next page)

SIMULATOR INSTRUCTIONS (COOK04-06)

Scenario Events:

Event #2

1. Trigger (1) IMF RX03D, final value 620 (NTP-241 fails HIGH) when crew has stabilized plant and addressed HDP leak-off valve failure.

Event #4

2. Trigger (3) IMF RX21A, final value 0 (FFC-210 fails LOW) when crew has recovered from RCS Cold Leg Temperature channel failure.

Event #5

3. Trigger (5) IMF CV13A (East CCP trip) when crew has recovered from SG Feed flow channel failure.

Event #6

4. Trigger (7) IMF RX11D, final value 100 (SG PORV Controller failure) when the crew has restored Charging and Letdown.

Event #7

5. Trigger (9) IMF ED05H; IMF ED05D (Loss of T21D Bus):

RPS Reactor Trip fails to AUTO actuate

TD AFW pump fails to start (continued on next page)

Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

SIMULATOR INSTRUCTIONS (COOK04-06)

Response to Crews Requests:

1. If contacted as AEO to investigate HDP Operations, report back after some 3 min. delay that emergency leak-off valve indicates full open.

2. If directed, to trip bistables for NTP-241 use:

IOR ZLOSTMC2[9] to ON to simulate opening cabinet Door (Override Lights/Relays - RX Flux panel)

Remote Bistable RPR137 TS/441G RPR139 TS/442D RPR135 TS/441C RPR138 TS/441H RPR140 TS/442G RPR136 TS/441D IOR ZLOSTMC2[4] to ON to simulate lifting Test Rack DOR ZLOSTMC2[9] to simulate closing cabinet Door

3. If contacted as AEO or Maintenance to evaluate East CCP operations, report back after some 5 min.

delay that motor/pump coupling damage is evident.

4. If contacted as AEO or Maintenance to evaluate TD AFW pump T&TV operations, report back after some 2 min. delay that T&TV appears to be functional with NO physical damage evident, but the fuse is blown.

DMF FW51 to replace the blown fuse.

TD AFW Local Operation:

IRF FWR78 to LOCAL

IRF FWR79 40 ramped over 1 min.(provides about 240K flow to SGs)

ML041700471

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