Text

Final As-Administered Scenarios for D. C. Cook Initial Exam - March 2004
	ML041700498
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: ML041700498 (129)
	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 (933), BOL2: 78% power, 4 GWD, 1079 ppm Boron, Xenon building in, U2 Aux steam 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 11 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. Places the following switches in neutral:

Standby CB pump

Standby TACW pump

2. Starts the South HW pump

3. Monitors HW discharge pressure and flow

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

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

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 11 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 Performs DILUTION batch add:

§ Place RC Makeup Blend control switch to STOP

§ Place RC Makup Blend Mode switch in DILUTE

§ Set desired batch on PW batch controller

§ Place PW pump in RUN

§ Place RC Makeup Blend control switch in START 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 11 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 11 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 11 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 11 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 11 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 11 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 11 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 11 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 11 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 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 RHR/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 RHR/CTS pumps running /

indicating flow with suction aligned to Recirc Sump.

SIMULATOR INSTRUCTIONS (COOK04-01)

Setup:

1. Reset to IC 26 (933)

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

§ IOV ZLO1012QTCD1 [GRN] OFF

§ IOV ZLO1012QTCD2 [GRN] OFF 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 (935), 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 12 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 Middle CB and stop the North 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 Middle 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 North CB pump US Directs the following actions to realign condensate system:

Start the North CB pump

Stop the Middle 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 12 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 Performs BORATION batch add:

§ Place RC Makeup Bend control switch in STOP

§ Place RC Makeup Blend Control Mode switch in BORATE

§ Set desired batch on BA batch controller

§ Place RC Makeup Blend control switch in START 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 12 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*

(*)Identifies requirement to restore Boric Acid Pump #4 (or EDG source to BA

3) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of BA Pump #4 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.: 4 Page 4 of 12 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 12 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).

US Enters and directs actions of 02-OHP 4022.012.003, Continuous Control Bank Movement procedure.

RO Performs the following as directed:

1. Checks for no turbine runback

2. Ensures control rods are in manual with no rod motion

3. Checks rod position above low-low rod insertion limit

4. Checks axial flux difference (AFD) within target band

5. Initiates restoration of equilibrium conditions using either:

Control rod movement

Turbine load adjustment

6. Identifies failed power range channel US Enters and directs actions of 02-OHP 4022.013.004, Power Range Malfunction procedure.

US Directs operator actions per 02-OHP-4022-013-004, Power Range Malf:

Verify Rod Control switch in MANUAL Places Rod Stop Bypass selector in NI42 position 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 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 6 of 12 Event

Description:

Power Range NI42 fails HIGH.

Time Position Applicant's Actions or Behavior 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.: 6 Page 7 of 12 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 8 of 12 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 9 of 12 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 10 of 12 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 11 of 12 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 12 of 12 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 (935)

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

§ IOV ZLO1012QTCD1 [GRN] OFF

§ IOV ZLO1012QTCD2 [GRN] OFF 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 (9):

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

Event #4

2. Trigger (1) IMF RX20G, final value 5E6 (MFC-140 fails HIGH) after crew has swapped the Condensate Booster pumps.

Event #5

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

Event #7

5. Trigger (7) 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-938, 62% power, 150 MWD, 830 ppm Boron 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 62% 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 1. Place the Control Mode Switch for East ESW strainer to MANUAL

2. 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

3. 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.

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, lowers 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 Note:

The crew may elect to implement 02-OHP-4022-002-020, Excessive Reactor Coolant Leakage.

US May Direct operator action per 02-OHP-4022-002-020, RCS Leakage:

Check PRZ Level and adjust Charging as required.

Check VCT Level

Determine RCS Leakrate

Check PRZ PORV and Safety Valve Leakage 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 Performs BORATION batch add:

§ Place RC Makeup Bend control switch in STOP

§ Place RC Makeup Blend Control Mode switch in BORATE

§ Set desired batch on BA batch controller

§ Place RC Makeup Blend control switch in START 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 938 @ 65% 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.: COOK04-03a Op-Test No.: Set 2 Examiners: _________________ Operators:___________________

Initial Conditions: IC-938, 62% power, 150 MWD, 830 ppm Boron 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)