Text

Initial Submittal of the Scenarios for the D.C. Cook Examination - Nov/ DEC 2002
	ML030700386
Person / Time
Site:	Cook
Issue date:	01/02/2003
From:	Lanksbury R; NRC/RGN-III/DRS/OLB
To:	Bakken A; American Electric Power Co
References
	50-315/02-301, 50-316/02-301 50-315/02-301, 50-316/02-301
	Download: ML030700386 (78)
	v • d • e

INITIAL SUBMITTAL OF THE SCENARIOS FOR THE D. C. COOK EXAMINATION - NOV/DEC 2002

Appendix D Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK02-02 Op-Test No.: Set I Examiners: Operators:

Initial Conditions: IC 36, 81% power Xenon Equilibrium, Tave 567TF, 790ppm Boron, 8GWD Turnover: 2CD DG is tagged out for governor replacement. NRV-i152 PZR PORV is isolated for leakage.

Event Malf. No. Event Event No. Type* Description 0 RCR19 to PORV NRV-152 leaks 10 gpm 10 1 CV16A I-RO QLC-451 VCT Level Transmitter fails high 100%

2 RX17J to I-BOP SG Pressure Channel MPP-240 Fails Low 0%

3a FW38 to C- Loss of condenser vacuum Ramp in over 15 45% BOP minutes to 45%

4 R Power reduction 5 N Reduce Turbine Load 3b FW38 to Condenser vacuum degrades requiring a Reactor 100% Trip. Ramp in over 5 minutes to 100%

6 ED01 Major Loss of all AC power (345kv & 765kv lines)

ED25 causing entry into ECA-0.0 6a EG08A - 2 AB DG Speed Governor failure; DG will not Preload reach rated speed resulting in Incomplete Sequence.

7 FW48C - C- Turbine Driven AFW pump Fails to Auto Start Preload BOP 8 RC17A to C-RO Pressurizer PORV (NRV-151 will stick open @

50% 50% upon reactor trip.)

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

Summary VCT Level Control channel QLC-45 1 will fail high causing a failure of auto makeup and the divert valve to fully divert to the HUT. The RO will need to reposition The divert valve and manually maintain VCT level. The crew will address the failure with an Abnormal Operating Procedure and trip associated bistables.

When the VCT is stabilized, the SG Pressure Channel MPP-240 fails low. The BOP will be required to take manual control SG 24 Feedwater Regulating Valve FRV-240 to stabilize level.

The crew will address the failure with an Abnormal Operating Procedure, trip associated bistables, select an operable channel, and restore automatic control.

After SG level is restored a loss of Condenser Vacuum will occur. The crew will take actions to stabilize vacuum but will need to reduce power due to loss Feedwater Pump capacity.

After power has been reduced, the vacuum leak will worsen, requiring a reactor trip.

Upon the reactor trip a loss of all AC power will occur. The crew will enter ECA-0.0, Loss of All AC Power and take action to stabilize the plant. The BOP will need to manually start the TD AFW pump. A failed open (50%) Pressurizer PORV (NRV-151) will result in a Safety Injection Actuation.

The crew should proceed through ECA-0.0. and take actions to restore power. Power will be made available via Emergency Power (Supplement 9). The crew will energize the vital buses, isolate the stuck PORV, and transition ECA-0.2, Loss of All AC Power Recovery with SI. The scenario ends after a CCP has been started or seal injection has been isolated.

Critical Tasks Establish AFW (Start TDAFWP)

Isolate Pressurizer PORV Restore Emergency Power Procedures E-0 Reactor Trip or Safety Injection ECA-0.0. Loss of All AC Power ECA-0.2 Loss of All AC Power Recovery with SI

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set I Scenario No.: Cook 02-02 Event No.: 1 Page 1 of 9 Event

Description:

QLC-451, VCT Level Transmitter Fails High Time Position Applicant's Actions or Behavior RO Acknowledges and reports annunciator Panel #209, Drop 47, VCT LEVEL HI DIVERT TO HOLDUP TANKS.

US Enters and directs actions of 02-OHP 4022.013.017, VCT Instrument Malfunction procedure.

RO Performs the following as directed:

1. Places 2-QRV-303, VCT/Holdup tank inlet selector in the VCT position

2. Identifies 2-QLC-451 failure

3. Maintains VCT level >15% using boric acid blender in manual US Initiates actions to energize interposing relay associated with 2 QLC-451 failure per Attachment A of 02-OHP 4022.013.017.

US Refers to Tech Specs 3.1.2.2.b. Boration Systems Flow Paths Operatinq (Action b). Identifies requirement to restore RWST flowpath (energize interposing relay) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of 2-QLC-451 failure.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-02 Event No.: 2 Page 2 of 9 Event

Description:

SG Pressure Channel MPP-240 Fails Low Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #214 which are indicative of a steam generator #24 water level control / pressure instrument failure (Drops 44, 42, 33).

BOP Places 2-FRV-240, SG 24 MFW Reg. Valve controller to manual, raises controller output to match feed flow with operable steam flow channel, and restores SG 24 level to program (may also place MFP AP controller in manual at this time).

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

2. Checks SG PORVs closed

3. Places MFP AP controller in manual

4. Reports 2-MPP-240 has failed

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

6. Declares steam flow channel 2-MFC-140 inoperable

7. Nulls and returns 2-FRV-240 controller to auto

8. Returns MFP AP controller to auto US Initiates actions to trip bistables associated with 2-MPP-240 Steam Generator Pressure Instrument Failure per Attachment D-1 of 02-OHP 4022.013.012.

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)

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.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set I Scenario No.: Cook 02-02 Event No.: 3a/3b Page 3 of 9 Event

Description:

Loss of Condenser Vacuum Condenser Vacuum Degrades Requiring A Reactor Trip Time Position Applicant's Actions or Behavior BOP Acknowledges and reports annunciators on Panel #218, Drops 12/13/14, CONDENSER A/B/C VACUUM LOW US Directs actions per 02-OHP 4024.218 Drops 12/13/14.

BOP Places the start-up steam jet air ejectors (SJAEs) in service:

1. Opens 2-SMO-401, steam to the start-up SJAEs

2. Opens start-up SJAE air off-takes:

2-SMO-405 2-SMO-406 2-SMO-407 US Directs actions to reduce turbine load by using either: (see NOTE) 02-OHP 4021.001.003, Power Reduction 02-OHP 4022.001.006, Rapid Power Reduction Response NOTE:

See either page 4 or 5 of 9 for actions associated with power / turbine load reduction BOP Dispatches operator to check the alignment of:

Steam Seals Air Ejectors Circulating Water Vacuum Breakers (including seal water flow)

Condenser Water Boxes (vented)

RO/BOP Monitors secondary plant parameters including:

Main condenser vacuum Main turbine load (MWe)

Main feedpumps condenser vacuum Main feedwater pump flow capability CREW Manually trips the reactor when condenser vacuum approaches 21" Hg.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-02 Event No.: 4/5 Page 4 of 9 Event

Description:

Power Reduction / Reduce Turbine Load 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.

1 1 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.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-02 Event No.: 415 Page 5 of 9 Event

Description:

Power Reduction / Reduce Turbine Load Time:ý Position I Applicant's Actions or Behavior I uruine Load Rueduction per UZ-UHP 4U02.001.006, 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.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-02 Event No.: 6/7/8 Page 6 of 9 Event

Description:

Loss of All AC Power/ 2AB Emergency Diesel Generator Failure Turbine Driven AFW Pump Fails to Auto Start Pressurizer PORV (NRV-151) Sticks Open Time Position Applicant's Actions or Behavior 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 RO Performs the (secondary) immediate actions of E-0:

1. Checks turbine trip

2. Checks power to AC emergency buses:

Reports that all AC emergency buses are de-energized 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:

Attempts to manually close 2-NRV-151 (stuck open)

2. Checks letdown isolation valves closed 2-QRV-111 2-QRV-112

3. Checks excess letdown isolation valves closed 2-QRV-113 2-QRV-114

4. Places nuclear sampling isolate switches to ISOLATE:

Train A Train B Cook Plant Unit I & Unit 2 NUREG-1021, Revision 8, Supplement 1

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-02 Event No.: 6/7/8 Page 7 of 9 Event

Description:

Loss of All AC Power I 2AB Emergency Diesel Generator Failure Turbine Driven AFW Pump Fails to Auto Start Pressurizer PORV (NRV-151) Sticks Open Time Position Applicant's Actions or Behavior BOP Checks AFW flow > 240,000 PPH:

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

RO/BOP Resets SI 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 NOTE: Bus T21A is preferred (MCC EZC-A) provides power to the stuck open PRZ PORV's block valve (2-NMO-151).

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-02 Event No.: 6/7/8 Page 8 of 9 Event

Description:

Loss of All AC Power I 2AB Emergency Diesel Generator Failure Turbine Driven AFW Pump Fails to Auto Start Pressurizer PORV (NRV-151) Sticks Open Time Position Applicant's Actions or Behavior 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 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.

CREW Closes 2-NMO-151, PORV Block Valve when power is available (to stop LOCA to PRT)

Critical Task #3 BOP Energizes the remaining emergency buses from EP:

T21A(D)

T21 B 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-i)

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-02 Event No.: 6/7/8 Page _9of 9 Event

Description:

Loss of All AC Power ! 2AB Emergency Diesel Generator Failure Turbine Driven AFW Pump Fails to Auto Start Pressurizer PORV (NRV-151) Sticks Open Time Position Applicant's Actions or Behavior US Announces transition to ECA-0.2, Loss Of All AC Power Recovery With Sl Required.

RO/BOP Performs the following actions of ECA-0.2 as directed:

1. Checks Sl reset

2. Checks emergency valve alignment:

ESW CCW ECCS

3. Closes either RCP thermal barrier isolation valve:

2-CCM-453 (Train A) 2-CCM-454 (Train B)

4. Establishes CCW:

Checks CCW Hx outlet valves closed Starts CCW pump Checks CCW Hx outlet valve for running pump open

5. Starts RHR pump

6. Starts Sl pump

7. Dispatches operator to locally close RCP seal injection filter isolation valves outside containment.

8. Starts CCP TERMINATE SCENARIO Cook Plant Unit I & Unit 2 NUREG-1021, Revision 8, Supplement 1

CRITICAL TASK

SUMMARY

(S02-02)

Task Elements Results

1 Cueing: SAT / UNSAT

Check AFW Flow.. .Verify TDAFP Manually Starts Turbine Running (ECA-0.0, Step 4, RNO)

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 I UNSAT

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

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:

ST21A or T21D bus energized

Power available to safeguards equipment.

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

CRITICAL TASK

SUMMARY

(Cont.)

(S02-02)

Task Elements Results

3 Cueing: SAT/UNSAT Isolate PRZ PORV

Check If RCS Is Isolated, PRZ PORVs Closed (ECA-0.0, Step 3.a)

Performance Indicators:

"* Closes 2-NMO-151, PORV Block Valve when power is available.

"* PORV must be isolated prior to transitioning to E-1 (from ECA-0.2).

Performance Feedback:

RCS pressure stabilizes

PORV block valve indicates closed Cook Plant Unit I & Unit 2 NUREG-1021, Revision 8, Supplement 1

SIMULATOR INSTRUCTIONS (S02-02)

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. Tagout CD EDG as follows:

imf EG10B (start failure) mrf EGR14 (RO) mrf EGR15 (RO) mrf EGR02 (RO) imf EG06B ior AN: APO1 [64] CRYWOLF Place clearance tags on control switches

6. Close NMO-152 and caution tag control switch

7. Go to RUN and acknowledge/clear alarms

8. Activate the following pre-load malfunctions:

RCR19, final value 10 (NRV-152 leaks 10 gpm)

EG08A (AB EDG failure)

FW48C (TDAFP fails to auto start)

(Continued on next page)

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

SIMULATOR INSTRUCTIONS (S02-02)

Scenario:

1. Trigger malfunction CV16A, final value 100 (QLC-451 fails hi) shortly after the crew accepts the watch.

2. Trigger malfunction RX17J, final value 0 (MPP-240 fails lo) when the crew has recovered from VCT level instrument failure.

3. Trigger malfunction FW38, final value 45, ramp 15:00 (loss of condenser vacuum to 45% over 15 min.) when MTI is called to trip bistables for MPP-240..

4. Modify malfunction FW38, final value 100, ramp 5:00 (loss of condenser vacuum to 100% over 5 min.) when crew has demonstrated ability to reduce power.

5. Trigger malfunctions upon reactor trip:

ED01 (loss of offsite 345KV lines)

ED25 (loss of offsite 765KV lines)

RCI7A, final value 50 (NRV-151 sticks 50% open)

(Continued on next page)

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

SIMULATOR INSTRUCTIONS (S02-02)

Response to Crew's Requests:

1. If directed to energize interposing relay for QLC-451 then activate remote function CVR72

2. If directed to trip bistables for MPP-240 use:

Remote Bistable RPR105 PS-534B RPRI04 PS-534A RPR035 FS-540A RPR036 FS-540B

3. If directed to locally close 2-QCM-350 then "SET CVVQCM350 0"

4. If directed to locally close 2-CCM-453 then "SET CCVCCM453 0"

5. If directed to locally close seal injection valves (2-CS-31 1N, 311 S and 307) then activate remote functions:

CVR20 final value CLOSE CVR21 final value CLOSE Cook Plant Unit 1.& Unit 2 NUREG- 1021, Revision 8, Supplement 1

Appendix D Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK02-03 Op-Test No.: Set 1 Examiners: Operators:

Initial Conditions: IC 35, 49% power, 3GWD burnup, Xenon Building, 5580 F, 1572 ppm Boron 2E MDAFW OOS Turnover: The 2W TDFP has just been returned following work on its condenser. Increase Power to 80% for next hold point.

Event Malf. No. Event Event No. Type* Description 1 N Raise Turbine Power 2 R Raise Reactor Power 3 CC01A, C-BOP 2E CCW pump Trips (2W CCW [Standby] Fails to CC02B - Auto Start)

Preload 4 RX02B to I-RO Loop 2 Hot Leg NTP-121 Temperature Transmitter 650OF Fails High 5 RX20A to I-BOP MFC-1 10 Main Steam Flow Transmitter Fails High 100% on 21 SG 6 CV13A C-RO 2E Charging Pump Trip 7 RC10D to Major Loop 4 Cold Leg Primary Coolant System 600gpm 60% Leak inside Containment over 5 minutes 8 RP 13A, C- Failure of Automatic Phase A Actuation RP13B - BOP Preload 9 RP19G, C-RO Slave Relay failures: High Head Charging SI RP20G - valves fail to align Preload 10 RP20B - C- Slave Relay failure: DG 2AB fails to auto start (&

Preload BOP High Head Charging Valve)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 NUREG-1 021, Revision 8, Supplement 1

Summary Plant is at 50% power on way back to 100% after a short outage on the 2W TDFP Condenser.

After a short ramp, the Component Cooling Water (CCW) pump will trip. The BOP will have to start the standby pump manually (auto start failure).

After the Crew has addressed the Tech Specs for CCW, the Loop 2 Hot Leg NTP- 121 Temperature Transmitter fails high. The rods will be in manual but the Pressurizer Level control will be affected. The crew will need to enter an Abnormal Operating Procedure, defeat the failed channel, trip bistables, and restore Pressurizer Level control to auto.

When the RCS Temperature channel has been defeated, MFC- 110, the #22 S/G Main Steam Flow transmitter will fail high. The BOP will need to take manual control of the Feedwater Regulating Valve FRV-220 and restore level. This failure will also increase FW pump speed (apparent steam flow increase tries to maintain a higher DP). The crew will need to enter an Abnormal Operating Procedure, trip bistables, and transfer to operable channel, and return to the FRV-220 to auto.

When the SG level has stabilized, the East CCP will trip, requiring the RO start the West CCP.

After Charging has restored a 600 gpm Primary System Leak in Containment will occur requiring a Reactor Trip and SI.

On the SI, various slave relay failures will cause the High Head Charging SI injection flowpath to fail to align and the 2AB DG to fail to auto start. The RO will need to manually align the High Head Injection Valves and the BOP will need to manually start the 2AB DG. The auto Phase A Isolation will also fail requiring manual actuation to align Phase A equipment. The crew should progress through E-0 to E-1 to ES-1.2. The scenario will terminate once a cooldown is started per ES-1.2.

RP20B - Failure of the K609 coil prevents

1. Emergency diesel generator 2AB auto start

2. SI blackout interlock

3. K609-XI prevents QMO-226 from auto close, and prevents IMO-256 from auto open.

4. K609-X2 prevents IMO-140 from auto open and prevents NESW pump 2S from starting.

RP19G/RP20G - Failure of the K608-XI coil prevents

1. ICM-250/ICM-251 will not automatically open

2. lIMO-I 0/IMO-120 will not automatically open Critical Tasks Restore High Head Injection Trip RCPs Procedures E-0 Reactor Trip or Safety Injection E-1 Loss of Reactor or Secondary Coolant ES-1.2 Post LOCA Cooldown and Depressurization

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-03 Event No.: 1/2 Page 1 of 9 Event

Description:

Raise Turbine and Reactor Power 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 Cook Plant Unit I & Unit 2 NUREG-1021, Revision 8, Supplement 1

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-03 Event No.: 3 Page 2 of 9 Event

Description:

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

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

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

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

US Enters and directs actions of 02-OHP4-22.016.001, CCW Malfunction procedure.

BOP Performs the following actions as directed:

1. Ensures at least one CCW pump is running

2. Checks CCW surge tank level stable

3. Checks CCW flow to RCPs normal

4. Checks CCW Hx outlet temperature normal SRO Declares 2E CCW Pump inoperable and refers to Tech Spec 3.7.3.1, Component Coolinq 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 w/i next 6 hrs and CSD w/i following 30 hrs).

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-03 Event No.: 4 Page 3 of 9 Event

Description:

Loop 2 RCS Hot Leg Temperature Transmitter (NTP-121) Fails High Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel #211 which are indicative of a RCS RTD failure.

US Enters and directs actions of 02-OHP 4022.013.007, RCS RTD Instrument Malfunction procedure.

RO 1. Ensures control rods are in manual.

2. Checks and reports the following conditions:

"* Reactor cdtical "a Tavg>551°F

"* Tavg-Tref deviation alarm reset

3. Reports Loop 2 as failed RCS temperature channel and aligns the following switches:

"* Tavg defeat switch to Loop 2 position

"* AT defeat switch to Loop 2 position

"* AT/OPAT/OTAT recorder switch to Loop 1, 3, or 4 US Initiates actions to trip bistables associated with RCS loop 2 RTD failure per Attachment B of 02-OHP 4022.013.007.

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 2 RCS RTD failure.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-03 Event No.: 5 Page 4 of 9 Event

Description:

SG #21 Main Steam Flow Transmitter (MFC-110) Fails High Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #213 which are indicative of a steam flow instrument failure (Drop 11, 13).

BOP Places 2-FRV-210, SG 21 MFW Reg. Valve controller to manual, lowers controller output to match feed flow with operable steam flow channel, and restores SG 21 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 21 level using manual control of 2-FRV-21 0

2. Places MFP AP controller in manual and maintains pressure

3. Reports 2-MFC-1 10 has failed

4. Places 2-FS-512C selector switch in channel 2 position

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

6. Returns MFP AP controller to auto US Initiates actions to trip bistables associated with 2-MFC-1 10 Steam Flow Failure per Attachment A-1 of 02-OHP 4022.013.014.

US Refers to Tech Specs 3.3.1.1 RTS Instrumentation (Table 3.3-1, Action 7) 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 steam flow channel failure.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-03 Event No.: 6 Page 5 of 9 Event

Description:

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

209 which are indicative of a charging pump failure.

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, E CCP Motor Overload Trip RO Performs the following as directed:

"* Starts 2W CCP

"* Adjusts charging and seal injection flow as necessary

"* Starts to place 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 > 350OF 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 .

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-03 Event No.: 7/8/9/10 Page 6 of 9 Event

Description:

Small Break LOCA inside Containment Containment Isolation Phase A - Auto Failure ECCS Slave Relay Failures 2AB EDG Slave Relay 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/BOP to manually trip the reactor and initiate safety injection and perform the immediate actions of E-0, Reactor Trip or Safety Injection (based on RCS leak rate beyond charging system capability per 02-OHP 4022.002.020).

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-03 Event No.: 7/8/9/10 Page 7 of 9 Event

Description:

Small Break LOCA inside Containment Containment Isolation Phase A - Auto Failure ECCS Slave Relay Failures 2AB EDG Slave Relay Failure Time Position Applicant's Actions or Behavior US Directs subsequent actions of E-0.

RO/BOP Reviews E-0 Foldout Page Criteria.

BOP Manually starts 2AB Emergency Diesel Generator.

BOP Manually controls AFW flow to maintain SG narrow range levels 13% - 50% once one SG narrow range level is > 13%.

RO Reports that not all ECCS pumps are running - 2E CCP off due to previous failure.

RO Reports that both CCW pumps are not running - 2E CCW pump off due to previous failure.

USIRO Manually opens high head safety injection valves:

2-IMO-256, BIT Inlet Critical 2-1CM-250, BIT Outlet Task #1 2-1CM-251, BIT Outlet US/RO Manually actuates Containment Isolation - Phase A.

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

Critical Task #2 Cook Plant Unit I & Unit 2 NUREG- 102 1, Revision 8, Supplement 1

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 1 Scenario No.: Cook 02-03 Event No.: 7/8/9/10 Page 8 of 9 Event

Description:

Small Break LOCA inside Containment Containment Isolation Phase A - Auto Failure ECCS Slave Relay Failures 2AB EDG Slave Relay Failure Time Position Applicant's Actions or Behavior RO/BOP Performs manual actions of E-0 Attachment A (for Train A components which failed to start/reposition) as directed by US.

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

US Announces transition to E-A, 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 Maintains SG narrow range levels 26% - 50%.

4--

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 And Depressurization (at step 12 of E-1).

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

Op-Test No.: Set 1 Scenario No.: Cook 02-03 Event No.: 7/8/9/10 Page 9 of 9 Event

Description:

Small Break LOCA inside Containment Containment Isolation Phase A - Auto Failure ECCS Slave Relay Failures 2AB EDG Slave Relay Failure Time Position Applicant's Actions or Behavior RO/BOP Reviews ES-1.2 Foldout Page Criteria.

RO Trips all pressurizer heaters CREW Initiate RCS cooldown to cold shutdown.

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

CRITICAL TASK

SUMMARY

(S02-03)

Task Elements Results

1 Cueing: SAT / UNSAT Check ECCS Flow: BIT - Flow Indicated (E-0, Step Manually open high 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 two cold leg BIT injection flowmeters)

2 Cueinc: SAT I UNSAT

RCS pressure - less than 1300 psig AND CCPs or Manually trip all SI pumps - at least one running Reactor Coolant E-0, Foldout Page, Step 1 Pumps E-0, Step 19 E-1, Foldout Page, Step I E-1, Step I 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 Cook Plant Unit I & Unit 2 NUREG-1021, Revision 8, Supplement 1

SIMULATOR INSTRUCTIONS (S02-03)

Setup:

1. Reset to IC 35

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. Tagout 2E MDAFP as follows:

"* Place control switch in pull-to-lock

"* Place clearance tag on control switch

"* Activate remote function FWR61, final value RO

6. Go to RUN and acknowledge/clear alarms

7. Activate the following pre-load malfunctions:

CC02B (2W CCW pump fails to auto start)

RP13A (phase A isol./ train A auto failure)

RP13B (phase A isol./ train B auto failure)

RP19G (ECCS slave relay failure)

RP20G (ECCS slave relay failure)

RP20B (AB EDG slave relay failure)

(continued on next page)

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

SIMULATOR INSTRUCTIONS (S02-03)

Scenario:

1. Trigger malfunction CCO0A (2E CCW pump trip) after crew has demonstrated ability to raise power and RO is still actively engaged in power escalation (BOP event).

2. Trigger malfunction RX02B, final value 650 (NTP-1 21 fails hi) after crew has recovered from CCW pump trip.

3. Trigger malfunction RX20A, final value 100 (MFC-1 10 fails hi) after crew has recovered from L-2 RTD instrument failure.

4. Trigger malfunction CVI3A (2E CCP trip) after crew has recovered from steam flow instrument failure.

5. Trigger malfunction RCIOD, final value 60, ramp 5:00 (SB LOCA) after crew has restored charging flow.

(continued on next page)

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

SIMULATOR INSTRUCTIONS (S02-03)

Response to Crew's Requests:

1. If directed to trip bistables for NTP-121 (L2 RTD) use:

Remote Bistable RPR123 TS-421C RPR124 TS-421 D RPR125 TS-421G RPR126 TS-421 H RPR127 TS-422D RPR128 TS-422G

2. If directed to trip bistables for MFC-110 use:

Remote Bistable RPR021 FS-512B RPRO17 FS-510A RPR018 FS-510B

3. If directed to stop all ice condenser AHUs then activate remote function:

. CHR01, final value OFF

4. If directed to secure EDG jacket water pumps then modify remote functions as follows:

EGR 03, select OFF then AUTO EGR 04, select OFF then AUTO Cook Plant Unit I & Unit 2 NUREG-1021, Revision 8, Supplement I

Appendix D Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK02-04 Op-Test No.: Set 2 Examiners: Operators:

Initial Conditions: IC 37, 100% power, 8GWD, 750 ppm Boron, Equilibrium Xenon, 2E MDAFW OOS, Turnover: Plant is at 100% reducing power to remove 2E TDFP from service due to oil leak.

Event Malf. No. Event Event No. Type* Description 1 N Reduce Turbine Load 2 R Reduce Reactor Power 3 RX05A to I-RO PZR Level Channel NLP-151 Fails High (fail to 100% 100% over 5 minutes) 4 ED07B C-RO PZR HTR Transformer Fails (21 PHC fails) 5 RX21 C to I-BOP SG 22 FW Flow Transmitter FFC-220 Fails High 4E+6 6 ED0827 C-BOP Loss of 600 V MCC 2-EZC-C (Containment Cooling Failure) 7 ED10A C-BOP Loss of Instrument Bus CRID I (Disable Train A SSPS) 8 RP01A C-RO Failure of Reactor to Automatically Trip RP01B 9 FW01 B at Major SG 22 FW Line Rupture Inside Containment 20% (ramp to 20% over 5 minutes - 4M Ibm/hr) 10 RP16B C-BOP Containment Spray Failure to Auto Actuate preload (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

Summary Plant is at 100% reducing power to remove 2E TDFP from service due to oil leak.

After a short ramp, the Pressurizer Level Controlling Channel NLP-151 will fail high. The RO will have to manually control level. The crew will need to implement an Abnormal Operating Procedure, trip bistables, select an operable channel, and restore Pressurizer Level controller to auto.

When the operable channel is selected, a failure of the PZR HTR Bus T21PHC will occur. The PZR SCR heater control will need to be transferred to T2 1PHA.

After the crew has addressed the failed Pressurizer channel, the #22 S/G FW Flow Transmitter FFC-220 will slowly fail high. The BOP will need to take manual control of the Feedwater Regulating Valve FRV-220 to restore level. The crew will need to implement an Abnormal Operating Procedure, trip bistables, transfer to operable channel, and return FRV-220 to auto.

The 600V MCC 2-EZC-C will trip causing the loss of several Containment Fans requiring the BOP to take action to restore cooling. Several other components will lose power requiring Technical Specification Action statements.

(Ref 02-OHP-4021-082-023 Figure 1 Page 37 & 38)

IMO-316 RHR to Cold leg, ICM-129 RCS HL to RHR, IMO-51 BIT to CL, RMO -110 SI ACC Discharge, ICM-1I1 RHR to RCS CL 2&3, Hydrogen Recombiner &

Containment Fans After the loss of the MCC is addressed, Instrument Bus CRID I trips causing a loss of instrumentation, Train A SSPS Output, a FW Isolation and a subsequent Reactor Trip signal. The Reactor will not automatically trip and must be tripped by the RO.

The trip will cause a FW line break on the #22 SG requiring a Safety Injection. All Train A SSPS equipment will need to be manually started or repositioned due to the loss of the CRID.

Additionally, Train B Containment Spray actuation will fail requiring manual initiation. The crew should progress from E-0 to E-2. The scenario will terminate once a transition is made to ES- 1.1 SI Termination.

Critical Tasks Trip Reactor Actuate Containment Spray Isolate Faulted Steam Generator Procedures E-0 Reactor Trip or Safety Injection E-2 Faulted Steam Generator Isolation

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

Description:

Reduce Turbine Load and 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 Cook Plant Unit I & Unit 2 NUREG-1021, Revision 8, Supplement 1

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-04 Event No.: 3 Page 2 of 9 Event

Description:

Pressurizer Level Channel (NLP-151) Fails High Applicant's Actions or Behavior Recognizes and reports annunciators on Panel #208 (Drops 3 and 1) indicative of a pressurizer (PRZ) level instrument failure.

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.

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. 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

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.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-04 Event No.: 4 Page 3 of 9 Event

Description:

Pressurizer Heater Transformer (TR21PHC) Fails Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel #208 (Drops 46 and 50) indicative of a pressurizer (PRZ) heater power supply failure.

US/RO Reenergizes PRZ control (cycling) group heaters per OHP 4024.208 Drop 46 annunciator response, as follows:

"* Opens breaker CB21PHC6

"* Closes breaker CB21 PHA6 RO Monitors PRZ pressure response and ensures normal PRZ heater operations for PHA supplied heaters.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-04 Event No.: 5 Page 4 of 9 Event

Description:

SG 22 Feedwater Flow Transmitter (FFC-220) Fails High Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #213 (Drop 34) which are indicative of a feedwater flow instrument failure.

BOP Places 2-FRV-220, SG 22 MFW Reg. Valve controller to manual, raises controller output to match the operable feed flow channel with steam flow, and restores SG 22 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 22 level using manual control of 2-FRV-220

2. Reports 2-FFC-220 has failed

3. Places 2-FS-520-C selector switch in channel 2 position.

4. Nulls and returns 2-FRV-220 controller to auto.

US Initiates actions to trip bistables associated with 2-FFC-220 FW Flow Failure per Attachment B-1 of 02-OHP 4022.013.015.

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 steam flow channel failure.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-04 Event No.: 6 Page _5of 9 Event

Description:

Loss of Vital 600VAC MCC (2-EZC-C) - Containment Cooling Failure Time Position Applicant's Actions or Behavior US/BOP Performs the following per 02-OHP-4024-220 Drop 10, BATTERY CHARGER 2CD2 FAILURE alarm:

Dispatches Aux. Operator to place 2CD1 charger in service.

Dispatches Aux. Operator to check 2CD2 charger status.

Requests MTE (Electricians) to check 2CD2 charger.

Refers to Tech Spec 3.8.2.3 DC Distribution - Operating US/BOP Performs the following per 02-OHP-4024-220 Drop 29, CRID I INVERTER ABNORMAL alarm:

Dispatch Aux. Operator to check status of CRID I Inverter Refers to Tech Spec 3.8.2.1 AC Distribution - Operating US/BOP Performs the following per 02-OHP-4024-203 Drop 2, UPPER CNTMT VENT FANS FAILURE alarm:

Starts 2-HV-CUV-1, Upper Cntmt Vent Unit #1 Monitors upper containment temperature 4 4--

US/BOP Performs the following per 02-OHP-4024-203 Drop 3, LOWER CNTMT VENT FANS FAILURE alarm:

Starts 2-HV-CUV-4B, Lower Cntmt Vent Unit #4B Monitors lower containment temperature US/BOP Performs the following per 02-OHP-4024-203 Drop 15, CRDM EXHAUST FAN FAILURE alarm:

Starts 2-HV-CRD-4B, Control Rod Drive Mechanism Fan 4B US Time permitting, may refer to the following Tech Specs (TS) due to loss of power (see 02-OHP-4021-082-023, Fig. 1 Load List):

TS 3.5.2 ECCS Subsystems - Tavgq > 350°F TS 3.6.4.2 Electric Hydrogen Recombiners TS 3.6.5.6 Containment Air Recirculation Systems TS 3.8.2.3 D.C. Distribution - Operating Cook Plant Unit I & Unit 2 NLYREG-1021, Revision 8, Supplement 1

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-04 Event No.: 7/8 Page 6 of 9 Event

Description:

Loss of Instrument Bus (CRID I) I Failure of Automatic Reactor Trip Time Position Applicant's Actions or Behavior CREW Recognizes the need to manually trip the reactor (feedwater isolation occurs on SGs 21 and 24).

CREW Manually opens reactor trip breakers in response to (either):

0 Multiple parameters approaching reactor trip setpoint Critical 0 Failure of reactor to trip automatically (ATWS alarms)

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

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

Description:

Feed Line Rupture Inside CNTMT I Automatic CNTMT Spray Failure Time Position Applicant's Actions or Behavior 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 Directs subsequent actions of E-0.

CREW If the crew identifies the faulted SG prior to entering E-2, Faulted Steam Generator Isolation they may take the following actions in accordance with OHI-4023, EOP Users Guide:

"* Isolates feedwater to 22 Steam Generator

"* Closes Steam Generator Stop Valves US/RO 1. Manually actuates CNTMT Spray (Train B will actuate)

2. Manually aligns/starts CNTMT Spray Train A:

Critical = Opens 2-IMO-210, 2E CTS Pump Discharge Valve Task #2 . Opens 2-IMO-211, 2E CTS Pump Discharge Valve

Opens 2-IMO-202, Spray Additive Tank Outlet Valve

Starts 2E Containment Spray Pump RO Stops all Reactor Coolant Pumps RO/BOP Places Distributed Ignition System (DIS) in service:

1. Dispatches operator to stop all ice condenser AHUs

2. Starts all hydrogen igniters Cook Plant Unit I & Unit 2 NUREG-1021, Revision 8, Supplement 1

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

Description:

Feed Line Rupture Inside CNTMT / Automatic CNTMT Spray Failure 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 Manually starts ECCS pumps (Train A):

"* 2E RHR pump

"* 2N SI pump RO Manually aligns Train A emergency safeguard systems:

"* CCW

"* ECCS RO Attempts to manually actuate Train A - Phase A Containment I Containment Ventilation Isolation RO/BOP Performs manual actions of E-0 Attachment A (for Train A components which failed to start/reposition) as directed by US.

BOP Closes all Train A - SGSV Dump valves CREW Completes all actions of E-0 through step 21 (Check If SG Secondary Pressure Boundaries Are Intact).

US Announces transition to E-2, Faulted Steam Generator Isolation (at step 21 of E-0).

US Directs actions of E-2, Faulted Steam Generator Isolation.

US/BOP Identifies 22 steam generator as faulted Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-04 Event No.: 9/10 Page 9 of 9 Event

Description:

Feed Line Rupture Inside CNTMT / Automatic CNTMT Spray Failure Time Position Applicant's Actions or Behavior US/BOP Manually closes the following valves for SG 22:

2-FMO-221, TDAFP discharge Critical

2-FMO-222, MDAFP discharge Task #3

2-MCM-221, TDAFP steam supply

2-DCR-302, blowdown sample valve NOTE: The following should be checked closed

"* 2-FRV-220, feedwater reg. Valve

"* 2-FMO-202, feedwater isolation valve

"* 2-MRV-223, PORV

"* 2-DCR-320, blowdown isolation valve BOP Closes 2-DRV-407, SG stop valve drain valve RO/BOP Performs the following as directed:

"* Resets containment isolation phase A

"* Directs chemistry to sample all SGs for activity CREW Determines that ECCS flow should be reduced US Announces transition to ES-1.1 SI Termination (at step 8 of E-2).

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

CRITICAL TASK

SUMMARY

(S02-04)

Task Elements Results

1 Cueing: SAT I UNSAT Symptoms which require a reactor trip (i.e.,

Manually Trip Reactor loss of feedwater flow to SGs)

Challenge to multiple reactor trip instrumentation setpoints (i.e.):

Lo SG Level with FF/SF mismatch Lo-Lo SG level RX TRIP BKR TRAIN A/B UV TRIP (ATWS) alarms Performance Indicators:

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

Reactor trip breaker must be opened prior to exceeding the RCS pressure safety valve limit of 2485 psig).

Performance Feedback:

RPIs indicate rods - fully inserted Rod bottom lights - lit Neutron flux - lowering

2 Cueing: SAT I UNSAT Containment pressure > 2.9 psig:

Actuate Containment

CNTMT SPRAY ACTUATED alarm Spray a LOWER CNTMT PRESS HI-HI alarm

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

"* Manually actuate Train B CTS or manually align and start Train A 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:

Flow is indicated on at least one train of Containment Spray Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

CRITICAL TASK

SUMMARY

(Cont.)

(S02-04)

Task Elements Results

3 Cueing: SAT / UNSAT E-2, steps 1, 2 and 5 Isolate Faulted Steam Steam generator pressure lowering Generator RCS temperature lowering Performance Indicators:

"* Isolate SG 22 by closing:

MFW valves**

AFW valves**

TDAFP steam supply valves**

SGBD sample valves**

"* SG 22 must be isolated before transitioning out of E-2 Performance Feedback:

RCS cooldown stops Depressurization of intact SGs stop Feedwater flow to affected SG stops Cook Plant Unit I & Unit 2 NUREG-1021, Revision 8, Supplement I

SIMULATOR INSTRUCTIONS (S02-04)

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. Tagout 2E MDAFP as follows:

Place control switch in pull-to-lock Place clearance tag on control switch Activate remote function FWR61, final value RO

6. Go to RUN and acknowledge/clear alarms

7. Activate the following pre-load malfunctions:

RPOIA (Reactor Trip / Train A auto failure)

RP01B (Reactor Trip / Train B auto failure)

RP16B (CTS / Train B auto failure)

Scenario:

1. Trigger malfunction RX05A, initial value 54, final value 100, ramp 5:00 (NLP-151 fails hi over 5 min.) after crew has demonstrated ability to raise power.

2. Trigger malfunction ED07B (PZR heater transformer fails) when an operable PZR level channel is selected.

3. Trigger malfunction RX21C, final value 4,000,000 (FFC-220 fails hi) after crew has recovered from the PZR level instrument and heater power supply failure.

4. Trigger malfunction ED0827 (Loss of 600V MCC EZC-C) after the crew has recovered from the feedwater flow instrument failure.

5. Trigger malfunction ED10A (Loss of CRID 1) after crew has placed an operable CD battery charger to service and restored containment ventilation.

6. Trigger malfunction FW01B, final value 20, ramp 5:00 (SG22 FW line rupture over 5 min.) upon reactor trip.

(continued on next page)

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

SIMULATOR INSTRUCTIONS (S02-04)

Response to Crew's Requests:

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

Remote Bistable RPR041 LS-459A

2. If directed to trip bistables for FFC-220 use:

Remote Bistable RPR023 FS-520A RPR024 FS-520B

3. If contacted to locally check CRID I inverter, then report CRID I is on alternate (DC) power supply.

4. If contacted to locally place 2CD1 battery charger in service then activate remote function EDR75, final value 2CD1.

5. If contacted to locally check 2CD2 battery charger, then report charger has lost power supply.

6. If directed to stop all ice condenser AHUs then activate remote function CHROI to OFF.

7. If directed to secure EDG jacket water pumps then modify remote functions as follows:

EGR 03, select OFF then AUTO EGR 04, select OFF then AUTO Cook Plant Unit I & Unit 2 NUREG-102 1, Revision 8, Supplement 1

Appendix D Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK02-05 Op-Test No.: Set 2 Examiners: Operators:

Initial Conditions: 1C37, 100% power, 8GWD, 750 ppm Boron, Equilibrium Xenon, 2W MDAFW OOS Turnover: Plant is at 100% Decreasing to remove 2W TDFP from service due to a clogging waterbox.

Event Malf. No. Event Event No. Type* Description 1 N Reduce Turbine Load 2 R Reduce Reactor Power 3 SW08A[B] C- 2E Essential Service Water Pump Strainer to 75% BOP Clogged (fails to auto backwash) {ZDI101S2E to Manual}

4 RX17C to I-BOP S/G 21 Pressure Transmitter MPP-212 Fails High 100%

5 RX04A to I-RO Pressurizer Pressure Channel NPP-151 Fails High 100%

6 RC17C to C-RO Pressurizer PORV NRV-153 Fails Open.

50%

7 RC01A at Major Large Break Loss of Coolant Accident on Loop 1 50%

8 RP19D - C-RO Slave Relay Failure: 2E RHR and SI Pumps Fail to Preload Auto Start 9 RH01 B C- 2W RHR Pump Trips 15 minutes after SI BOP (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 required to reduce power due to a clogging condenser on the West TDFWP.

The first event will be a clogged strainer on the 2E Essential Service Water Pump. The Strainer will fail to swap to automatically the standby strainer and backwash. The BOP will be required to select the correct strainer and manually backwash.

Next SG 21 Pressure Channel MPP-212 will fail high, requiring the BOP to take manual control and close the SG PORV valve. The crew should implement an Abnormal Operating Procedure, stabilize the plant, trip bistables, and declare SG PORV Radiation Monitor Inoperable.

The controlling Pressurizer Pressure channel NPP-151 will fail high. The RO will need to take manual control of the Pressurizer Pressure controller and restore pressure. The crew should implement an Abnormal Operating Procedure, stabilize the plant, trip bistables, select an operable channel, and restore pressure control to auto.

A short time later Pressurizer PORV NRV-152 will open and fail to fully close. The block valve for NRV-152 will need to be manually closed.

Shortly after the PORV failure, a LOCA will develop resulting in a large break LOCA. The plant will trip and Safety Injection will actuate. As the crew performs the actions of E-0 they will note that the 2E RHR and SI pumps failed to auto start on the SI due to a slave relay K610 failure. The crew will transition to E-1 and to ES-1.3 to align for cold leg recirculation. The 2W RHR will trip 15 minutes into the event. The crew will have to align ECCS to the recirculation sump without the 2W RHR pump. The scenario will terminate when the crew has aligned ECCS for cold leg injection.

Failure of the K610 coil prevents the following equipment from operating automatically during a Safety Injection: (2 98367)

1. Safety Injection Pump 2N Will Not Automatically Start

2. Residual Heat Removal Pump 2E Will Not Automatically Start

3. Charging Pump 2E Will Not Automatically Start

4. Component Cooling Pump 2E Will Not Automatically Start

5. Will Not Energize K6IO-XI & K610-X2 which:

"* Prevents ESW Pump IW From Automatically Starting

"* Prevents Damper HV-ACRDA4 From Automatically Closing

"* Prevents Fans HV-AESI, 2HV-ACRF1 & 1HV-ACRF1 From Automatically Starting Critical Tasks Establish Low Pressure SI (RHR)

Establish Cold Leg Recirculation Procedures E-0 Reactor Trip or Safety Injection E-I Loss of Reactor or Secondary Coolant ES-1.3 Transfer to Cold Leg Recirculation

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-05 Event No.: 1/2 Page I of 13 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 TaveFTref 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 Cook Plant Unit I & Unit 2 NUREG-1021, Revision 8, Supplement 1

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-05 Event No.: 3 Page 2 of 13 Event

Description:

2E ESW Pump Strainer Clogged (fails to auto backwash)

Time Position Applicant's Actions or Behavior RO Recognizes and reports Panel #204, Drop 55, EAST ESW PUMP STRAINER DP HIGH alarm.

US/BOP Identifies that the 2E ESW pump strainer failed to automatically backwash.

BOP Manually backwashes the 2E ESW pump strainer per 02-OHP 4024-204, Drop 55:

"* Places strainer control in MANUAL

"* Places backwash selector in RIGHT STN GATE CLOSED

"* Depresses manual BACKWASH pushbutton US/BOP Ensures DP high alarm clears and initiates/discusses need for a condition report to address failure of auto backwash.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-05 Event No.: 4 Page 3 of 13 Event

Description:

SG 21 Pressure Transmitter (MPP-212) Fails High Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #214 which are indicative of a steam pressure instrument failure and a SG PORV being open (Drops 21, 44).

BOP Manually closes 2-MRV-213, SG 21 PORV.

RO Monitors thermal/reactor power indications to detect potential effects of additional steam flow.

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. Checks SG PORVs closed

2. Reports 2-MPP-212 has failed

3. Ensures 2-MRV-213, SG 21 PORV in manual US Declares 2-MRA-2601, Loop 1 Steam Line Radiation Monitor inoperable.

US Initiates actions to trip bistables associated with 2-MPP-212 Steam Generator Pressure Instrument Failure per Attachment A-3 of 02-OHP 4022.013.012.

US Refers to Tech Specs 3.3.2.1 ESFAS Instrumentation (Table 3.3 3, *Action 14) and 3.3.3.1 Radiation Monitoring Instrumentation (table 3.3-6, Action 22B)

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.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-05 Event No.: 5 Page 4 of 13 Event

Description:

Pressurizer Pressure Channel (NPP-151) Fails High Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel #208 indicative of a pressurizer (PRZ) pressure instrument failure (Drops 6, 7, 8).

RO Places PRZ pressure master controller OR both PRZ spray valve controllers (2-NRV-1 63 and 164) to manual and lowers controller output to close spray valves.

US Enters and directs actions of 02-OHP 4022.013.009, Pressurizer Pressure Instrument Malfunction procedure.

RO Performs the following actions as directed:

1. Restores PRZ pressure using manual control of EITHER:

"* PRZ pressure master controller

"* Both PRZ spray valve controllers

2. Reports 2-NPP-151 has failed

3. Ensures PRZ pressure master controller is in manual

4. Places PRZ Press Ctrl selector switch in Ch 2 & 3 position

5. Places the following recorder switches in Ch 2, 3 or 4 position:

"* PRZ Press Rec selector

"* Delta T selector

"* Overpower Delta T selector

"* Overtemp Delta T selector

6. Verifies 2-QMO-225, E CCP Leakoff is open

7. Dispatches Aux operator to open breaker from 2-QMO-225

8. Checks 2-NLP-151, PRZ Level Channel 1 and 2-NLI-151, PRZ Level Cold Calibration instruments for failure

9. Nulls and returns the following controllers to auto:

"* Both PRZ spray valve controllers

"* PRZ pressure master controller US Declares the 2E Centrifugal Charging Pump inoperable.

US Initiates actions to trip bistables associated with 2-NPP-1 51 PZR Pressure Failure per Attachment A of 02-OHP 4022.013.009.

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

Op-Test No.: Set 2 Scenario No.: Cook 02-05 Event No.: 5 Page 5 of 13 Event

Description:

Pressurizer Pressure Channel (NPP-151) Fails High Time Position Applicant's Actions or Behavior US Refers to Tech Specs (TS):

"* TS 3.3.1.1 RTS Instrumentation (Table 3.3-1, *Action 6)

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

"* TS 3.3.3.5 Remote Shutdown Instrumentation

"* TS 3.5.2 ECCS Subsystems

"* TS 3.1.2.4 Rx Control Systems Charcqinp Pumps - Operating

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 pressure channel failure.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-05 Event No.: 6 Page 6 of 13 Event

Description:

Pressurizer PORV (NRV-153) Fails Open Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel #208 (Drop 23, 24, 45 and 8) indicative of a pressurizer PORV opening.

US/RO Isolates failed open PORV per 02-OHP 4024.208, Drop 23:

Attempts to manually close 2-NRV-153 PRZ PORV

Manually closes 2-NMO-153, 2-NRV-153 PRZ PORV Block Valve US Declares 2-NRV-153 inoperable, refers to Tech Spec 3.4.11 RCS Relief valves - Operatinq and complies with Action b:

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months close and remove power from the PORV block valve (2-NMO-153).

RO Monitors PRZ pressure control system and ensures pressure returns to normal conditions (-2235 psig).

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-05 Event No.: 7/8/9 Page 7 of 13 Event

Description:

Large Break LOCA 2E RHR Pump and 2N SI Pump Fails to Auto Start 2W RHR Pump Trips (after 15 minutes)

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

"* Checks cntmt isol phase B actuated

"* Stops all RCPs

"* 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 controls AFW flow to maintain SG narrow range levels 13% [24%] - 50% once one SG narrow range level is > 13%

[24%].

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-05 Event No.: 7/8/9 Page 8 of 13 Event

Description:

Large Break LOCA 2E RHR Pump and 2N SI Pump Fails to Auto Start 2W RHR Pump Trips (after 15 minutes)

Time Position Applicant's Actions or Behavior RO Checks all ECCS pumps running and manually starts:

0 2ERHRpump Critical 0 2N SI pump Task #1 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, cdr 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.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-05 Event No.: 7/8/9 Page 9 of 13 Event

Description:

Large Break LOCA 2E RHR Pump and 2N Sl Pump Fails to Auto Start 2W RHR Pump Trips (after 15 minutes)

Time Position Applicant's Actions or Behavior US Directs actions of E-1, Loss Of Reactor Or Secondary Coolant.

RO/BOP Acknowledges Annunciator 206, Drop 50, RHR PUMPS MOTOR OVERLOAD TRIP and reports 2W RHR pump trip.

BOP Maintains SG narrow range levels 26% - 50%.

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 US/RO Identifies and reports that the 2W RHR pump has tripped:

"* Recognizes Train B has lost recirculation capability

"* Verifies at least one train of cold leg recirculation capability exists RO/BOP Performs the following as directed

1. Opens control air valves to containment

2. Directs chemistry to initiate post accident sampling US Check if transfer to cold leg recirculation is required (RWST <25%)

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-05 Event No.: 7/8/9 Page 10 of 13 Event

Description:

Large Break LOCA 2E RHR Pump and 2N Sl Pump Fails to Auto Start 2W RHR Pump Trips (after 15 minutes)

Time Position Applicant's Actions or Behavior Applicants actions or behavior associated with ES-I.3, Transfer To Cold Leg Recirculation.

US Announces transition to ES-1.3, Transfer To Cold Leg Recirculation when RWST level < 25% per:

0 E-0, Foldout Page, Criteria 3

E-1, Foldout Page, Criteria 5 0 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:

0 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 locksout East CTS pump Task #2 2. Stops and locksout 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 locksout West CTS pump

6. Stops and locksout 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 Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement 1

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-05 Event No.: 7/8/9 Page 11 of 13 Event

Description:

Large Break LOCA 2E RHR Pump and 2N Sl Pump Fails to Auto Start 2W RHR Pump Trips (after 15 minutes)

Time Position Applicant's Actions or Behavior USIRO Continues to directlperform switchover as follows:

9. Restores control power to 2-ICM-305, Recirc sump to east Critical RHR/CTS 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. May attempt to start the West RHR pump (1 restart allowed)

17. Starts the West CTS pump

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

19. Resets CTS actuation

20. Closes spray additive tank valves:

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.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-05 Event No.: 7/8/9 Page 12 of 13 Event

Description:

Large Break LOCA 2E RHR Pump and 2N Sl Pump Fails to Auto Start 2W RHR Pump Trips (after 15 minutes)

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-41 5, east CCW hx outlet to misc services 2-CMO-41 1, 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:

21. Checks CTS Hx - ESW valves open:

Critical

2-WMO-712, to east hx Task #2 0 2-WMO-714, from east hx

2-WMO-716, to west hx 0 2-WMO-718, from west hx

22. Checks CCPs suction from RWST valves open:

2-IMO-910

2-IMO-911

23. Checks RWST level < 11 %

24. Closes Sl pump discharge crosstie valves:

"* 2-IMO-270

"* 2-IMO-275

25. Restores power and closes Sl pump recirc to RWST valves:

"* 2-IMO-262

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-05 Event No.: 7/8/9 Page 13 of 13 Event

Description:

Large Break LOCA 2E RHR Pump and 2N Sl Pump Fails to Auto Start 2W RHR Pump Trips (after 15 minutes)

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

26. Resets and closes CCP leakoff valves:

Critical 0 2-QMO-225 Task #2 # 2-QMO-226

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

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

28. Establishes crosstie between SI pump/CCP suction:

"* Opens 2-IMO-361

"* Opens 2-IMO-362

"* Checks open 2-IMO-360

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

30. Isolates RWST:

0 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-91 1

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

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

CRITICAL TASK

SUMMARY

(S02-05)

Task Elements Results

1 Cueing: SAT ! UNSAT

Check ECCS Pumps ALL running (E-0, Step 11)

Manually starts

Check RHR Hx Flow Indicated (E-0, Step 12.e) 2E RHR pump

Check Cold Leg Recirc Capability (E-1, Step 11)

(one low-head ECCS pump) Performance Indicators:

"*Starts the 2E RHR pump and ensures at least one train of low-head ECCS available for cold leg recirculation.

"* Must be performed prior to ES-1.3, Step 6.g "Check At Least One RHR Pump - Running On Recirculation Sump."

Performance Feedback:

2E RHR pump red run light lit

2E RHR pump current indicated o 2E RHR pump flow indicated

2 Cueing: SAT 1UNSAT

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

Establish Cold Leg

E-0 Foldout Page, Criteria 5 (switchover criteria)

Recirculation Flow

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

Performance Indicators:

"*At least one train of ECCSICTS 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 I indicating flow with suction aligned to Recirc Sump.

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

SIMULATOR INSTRUCTIONS (S02-05)

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. Tagout 2W MDAFP as follows:

Place control switch in pull-to-lock Place clearance tag on control switch Activate remote function FWR62, final value RO

6. Go to RUN and acknowledge/clear alarms

7. Activate the following pre-load override/malfunction:

ZDIt0IS2E, final value Manual (2E ESW strainer control switch)

RP19D (ECCS slave relay failure)

Scenario:

1. Trigger malfunction SW08B, final value 75 (2E ESW strainer clogged) after crew has demonstrated ability to lower power.

2. Trigger malfunction RX17C, final value 1200 (MPP-212 fails hi) after crew has manually backwashed the ESW strainer.

3. Trigger malfunction RX04A, final value 2500 (NPP-151 fails hi) after crew has recovered from the SG pressure instrument failure.

4. Trigger malfunction RC17C, final value 50 (NRV-153 fails open) after crew has recovered from the PRZ pressure instrument failure.

5. Trigger malfunction RC01A, final value 50 (LB LOCA - loop 1) after crew has recovered from the failed open PRZ PORV.

6. Trigger malfunction RHOIB (2W RHR pump trip) 15 minutes after SI actuation.

(continued on next page)

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

SIMULATOR INSTRUCTIONS (S02-05)

Response to Crew's Requests:

1. Ifcontacted to check 2E ESW pump strainer AP, then report >95" (gauge pegged high).

2. If directed to trip bistables for MPP-212 use:

Remote Bistable RPRO96 PS-516C RPR097 PS-516D

3. Ifdirected to trip bistables for NPP-1 51 use:

Remote Bistable RPR076 PS-455A RPR077 PS-455B RPR078 PS-455C RPR079 PS-455D RPRI17 TS-411C RPR118 TS-411D

4. If contacted to remove power from 2-QMO-225, then activate global malfunction (YG) 101QM0225.

5. If contacted to remove power from 2-NMO-153, then activate global malfunction (YG) 101NMO153.

6. Ifdirected to stop all ice condenser AHUs then activate remote function CHR01 to OFF.

7. If contacted to restore power to 2-QMO-225, then delete global malfunction (YG) 101QM0225.

8. Ifdirected to secure EDG jacket water pumps then modify remote functions as follows:

EGR 03, select OFF then AUTO EGR 04, select OFF then AUTO Cook Plant Unit I & Unit 2 NUREG-1021, Revision 8, Supplement I

Appendix D Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK02-06 Op-Test No.: Set 2 Examiners: Operators:

Initial Conditions: IC36, 81% power, 8GWD, Xenon Equilibrium, Tave 5670F, 2W MDAFW OOS Turnover: Increase Power to I 00% Mmintmin I 9n nnm Ifdin*,n Ahim f'ln g',,,,r4 fi~kh , nI Event Maif. No. Event Event No. Type* Description 0 CV013B 2W Centrifugal Charging Pump Trip (fail to start) 1 N Raise Turbine Load 2 R Raise Reactor Power 3 RX04A to I-RO Pressurizer Pressure Channel NPP-1 51 Fails Low 1700 4 CV04C C-RO 75 gpm Letdown Orifice Isolation Valve QRV-162 Fails Closed 5 RX18 to 0 I-BOP Feedwater Differential Pressure UPC-1 01 Fails Low 6 RX04C to Major PZR Pressure Channel NPP-153 Fails Low, 1700 (generating Reactor Trip and SI Signals) 7 RP01A, C-RO Reactor Fails to Automatically Trip RP01B, Preload 8 TC03 - C-BOP Turbine Fails to Automatically Trip Preload 9 ED05H C-BOP Loss of 4KV Bus T21 D (Loss of E CCP and E MDAFP) on the Reactor Trip 10 FW46C C-BOP Turbine Driven AFW pump Trips on Reactor Trip Loss of Heat Sink criteria established Coo)kl an, Uni)ct iVUity, kl)nstrumenI, 1tu)omponent, (M)aJor Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 8, Supplement I

Summary The Scenario begins at 81% increasing to 100% following a forced outage.

After the power change, NPP-151 Pressurizer Pressure Channel fails low. The RO will need to take manual control. The crew will implement an Abnormal Operating Procedure, trip bistables, select an operable channel, and restore pressure control to automatic.

The letdown orifice valve will fail closed as bistables are being tripped. The RO will need to restore Letdown through a different valve.

After letdown is restored, the UPC-1 01 FW Discharge DP Controller fails causing a feedwater transient. The BOP will need to take manual control of FW Pump Speed to establish the proper DP.

On the failure of NPP-1 53, a SI signal is generated. The automatic Reactor Trip fails requiring the RO to manually trip the Reactor. The automatic Turbine Trip fails requiring the BOP to manually trip the Turbine.

On the Reactor trip, a fault occurs on bus T21 D and, separately, the TDAFP trips on mechanical overspeed. The BOP must shutdown the CD DG to prevent the cycling.

The crew will implement E-0 and transition to FR-H. 1 loss of Heat Sink within the first few steps. Once FR-H. 1 is implemented, the crew will be required to trip the RCPs and initiate feed and bleed. The crew will direct actions to restore FW and should dispatch an operator to reset and start the TDAFP. The scenario will terminate once flow is restored to the SGs.

Critical Tasks Trip Reactor Establish RCS Feed and Bleed Procedures E-0 Reactor Trip or Safety Injection FR-H. 1 Response to Loss of Heat Sink

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-06 Event No.: 1/2 Page 1 of 8 Event

Description:

Raise Turbine Load / Raise Reactor Power 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 Brefs 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 Cook Plant Unit I & Unit 2 NUREG- 1021, Revision 8, Supplement 1

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-06 Event No.: 3 Page 2 of 8 Event

Description:

Pressurizer Pressure Channel (NPP-151) Fails Low Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel #208 indicative of a pressurizer (PRZ) pressure instrument failure (Drops 8, 9, 10).

US Enters and directs actions of 02-OHP 4022.013.009, Pressurizer Pressure Instrument Malfunction procedure.

RO Performs the following actions as directed:

1. Restores PRZ pressure using manual control of EITHER:

"* PRZ pressure master controller

"* Both PRZ spray valve controllers

2. Reports 2-NPP-151 has failed

3. Ensures PRZ pressure master controller is in manual

4. Places PRZ Press Ctrl selector switch in Ch 2 & 3 position

5. Places the following recorder switches in Ch 2, 3 or 4 position:

0 PRZ Press Rec selector 0 Delta T selector

Overpower Delta T selector

Overtemp Delta T selector

6. Verifies 2-QMO-225, E CCP Leakoff is open

7. Dispatches Aux operator to open breaker from 2-QMO-225

8. Checks 2-NLP-151, PRZ Level Channel 1 and 2-NLI-151, PRZ Level Cold Calibration instruments for failure

9. Nulls and returns the following controllers to auto:

"* Both PRZ spray valve controllers

"* PRZ pressure master controller US Declares the 2E Centrifugal Charging Pump inoperable.

US Initiates actions to trip bistables associated with 2-NPP-1 51 PZR Pressure Failure per Attachment A of 02-OHP 4022.013.009.

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

Op-Test No.: Set 2 Scenario No.: Cook 02-06 Event No.: 3 Page 3 of 8 Event

Description:

Pressurizer Pressure Channel (NPP-161) Fails Low Time Position Applicant's Actions or Behavior US Refers to Tech Specs (TS):

"* TS 3.3.1.1 RTS Instrumentation (Table 3.3-1, *Action 6)

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

"* TS 3.3.3.5 Remote Shutdown Instrumentation

"* TS 3.5.2 ECCS Subsystems

"* TS 3.1.2.4 Rx Control System Charging Pump - Operating

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 pressure channel failure.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-06 Event No.: 4 Page 4 of 8 Event

Description:

75 GPM Letdown Orifice Valve (QRV-162) Fails Closed Time Position Applicant's Actions or Behavior RO Identifies and reports rise in pressurizer (PRZ) level due to reduction in letdown flow (of 75 gpm) as a result of 2-QRV-162 failing closed.

US/RO Isolates letdown and minimizes charging flow to that amount required for seal injection.

US Directs RO to restore normal 120 gpm letdown (using 2-QRV-1 61, 75 gpm letdown orifice) per 02-OHP-4021-003-001, Attachment 13.

RO Restores normal letdown per Attachment 13 as follows:

1. Places 2-QRV-302 in divert position

2. Checks/adjusts charging flow to > 75 gpm

3. Verifies orifice isolations closed (QRV-160, 161 and 162)

4. Opens 2-CRV-470, CCW from letdown hx outlet controller

5. Verifies open letdown isolation valves:

"* 2-QCR-300, CVCS letdown cntmt isol

"* 2-QCR-301, CVCS letdown cntmt isol

"* 2-QRV-1 11, RC letdown to regen hx

"* 2-QRV-1 12, RC letdown to regen hx

6. Adjusts 2-QRV-301, letdown pressure controller to 50% output

7. Opens 2-QRV-161, 75 gpm letdown orifice isolation

8. Adjusts 2-QRV-301 to maintain 160 - 350 psig on 2-QPC-301

9. Places 2-QRV-301 in auto (ifdesired)

10. Nulls and returns 2-CRV-470 controller to auto

11. Adjusts charging flow as required to maintain PRZ level

12. Places PRZ level control in automatic if desired)

13. Places 2-QRV-302 in normal (demineralizer) position when letdown temperature is stable.

Note: RO should continue, placing the 45 gpm letdown orifice in service as follows:

14. Adjusts 2-QRV-301, to lower letdown pressure to -160 psig.

15. Raises charging flow to match expected letdown flow.

16. Opens 2-QRV-160, 45 gpm letdown orifice isolation

17. Adjusts 2-QRV-301 to control letdown pressure 160-350 psig.

18. Places 2-QRV-301 in auto (if desired)

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-06 Event No.: 5 Page 5 of 8 Event

Description:

Feedwater Differential Pressure (UPC-101) Fails Low Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #216, 213, and 214 and indications which are indicative of a failure affecting main feedwater to all steam generators (SGs):

"* All SG levels lowering

"* All feedwater regulating valves opening

"* Main feedwater pumps speed lowering BOP Places MFP differential pressure controller in manual and raises output (raise MFW discharge pressure I flow) to match feedwater flow with steam flow and restore SG levels to program.

CREW Identifies that 2-UPC-1I01, main steam bypass header pressure instrument has failed low affecting actual low side pressure input to the MFP differential pressure controller.

BOP Monitors/adjusts MFP differential pressure to restore SG levels to program.

RO Monitors thermal/nuclear power during feedwater transient.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-06 Event No.: 617819/10 Page 6 of 8 Event

Description:

PZR Press Channel (NPP-1 53) Fails Low - Reactor Trip Signal Reactor Fails To Automatically Trip Turbine Fails To Automatically Trip Loss of 4KV Bus T21 D On Reactor Trip Turbine Driven AFW Pump Trips On Reactor Trip Time Position Applicant's Actions or Behavior CREW Recognizes the need to manually trip the reactor (2/4 PRZ pressure channels failed low).

CREW Manually opens reactor trip breakers in response to (either):

0 PRZ pressure < reactor trip/safety injection setpoints Critical 0 Failure of reactor to trip automatically (ATWS alarms)

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. Recognizes turbine failed to automatically trip:

a Manually actuates turbine trip

2. Checks power to AC emergency buses 0 Reports Loss of 4KV Bus T21D (due to fault)

Trips CD EDG to prevent cyclic loading attempts US Ensures immediate actions of E-0 are completed US Directs subsequent actions of E-0.

US/BOP Announces transition to FR-H.1, Response to Loss of Secondary Heat Sink per E-0, Step 7.a. - RNO (SG narrow range levels off scale low and no AFW flow).

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-06 Event No.: 6/718/9/10 Page 7 of 8 Event

Description:

PZR Press Channel (NPP-153) Fails Low - Reactor Trip Signal Reactor Fails To Automatically Trip Turbine Fails To Automatically Trip Loss of 4KV Bus T21 D On Reactor Trip Turbine Driven AFW Pump Trips On Reactor Trip Time Position Applicant's Actions or Behavior 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 0 Recognizes no CCPs available

"* Trips all RCPs

"* Goes to Step 18 of FR-H.1 (RCS Bleed and Feed)

CREW Initiates RCS bleed and feed:

1. Checks SI actuated Critical 2. Checks RCS feed path:

Task #2 0 South SI pump running

ECCS monitor lights in proper status

3. Establishes RCS bleed path

"* Checks PRZ PORV block valves energized and open

"* Places all (3) PRZ PORV switches to open position

4. Resets Sl

5. Resets containment isolation phase A

6. Opens control air to containment valves:

"* 2-XCR-100

"* 2-XCR-101

"* 2-XCR-102

"* 2-XCR-103

7. Checks bleed path:

"* All 3 PRZ PORVs open

"* All 3 PRZ PORV block valves open

8. Perform E-0, Steps 5 - 17 (as time permits)

US/BOP Continues attempts to establish secondary heat sink:

0 Dispatches operator to reset TDAFP mechanical overspeed.

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

Appendix D Operator Actions Form ES-D-2 Op-Test No.: Set 2 Scenario No.: Cook 02-06 Event No.: 6/7/8/9/10 Page 8 of 8 Event

Description:

PZR Press Channel (NPP-1 53) Fails Low - Reactor Trip Signal Reactor Fails To Automatically Trip Turbine Fails To Automatically Trip Loss of 4KV Bus T21 D On Reactor Trip Turbine Driven AFW Pump Trips On Reactor Trip Time Position Applicant's Actions or Behavior US/BOP Relatches and restarts TDAFP BOP Restores AFW flow to the SGs from the TDAFP.

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

CRITICAL TASK

SUMMARY

(S02-06)

Task Elements Results

1 Cueing: SAT I 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:

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:

"* RPIs indicate rods - fully inserted

"*Rod bottom lights - lit

"*Neutron flux - lowering

2 Cueing: SAT I UNSAT

Enters FR-H.1 at Step 7 of E-0 (Check AFW Flow)

Establish RCS

Commences bleed and feed actions from Step 7 Bleed (and Feed) when it has been determined that no CCPs are running.

Performance Indicators:

"* Stops all RCPs (extends time to SG dryout)

"* Opens all PRZ PORVs (establishes bleed path)

"* Must be performed prior to SG Dryout (<15%

wide range level)

(Note: RCS Feed initiatedby automaticSI)

Performance Feedback:

"* PRZ PORV red lights lit

"* PRZ PORV tailpipe temperatures rising

"* PRT pressure/temperaturellevel rising Cook Plant Unit I &,Unit 2 NUJREG-1021, Revision 8, Supplement 1

SIMULATOR INSTRUCTIONS (S02-06)

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. Tagout 2W MDAFP as follows:

Place control switch in pull-to-lock Place clearance tag on control switch Activate remote function FWR62, final value RO

6. Go to RUN and acknowledge/clear alarms

7. Activate the following pre-load malfunctions:

CV013B (2W CCP fails to start)

RP01A (Auto reactor trip / train A failure)

RPOIB (Auto reactor trip / train B failure)

TC03 (Main turbine auto trip failure)

Scenario:

1. Trigger malfunction RX04A, final value 1700 (NPP-151 fails Io) after crew has demonstrated ability to raise power.

2. Trigger malfunction CV04C, final value 0 (QRV-162 fails closed) when the final bistables are being tripped for PZR pressure instrument failure.

3. Trigger malfunction RX18, initial value 850, final value 0, ramp 1:00 (UPC-101 fails to over I min.) after the crew restores normal letdown.

4. Trigger malfunction RX04C, final value 1700 (NPP-153 fails 1o - RT/SI signal) after the crew recovers from the feedwater transient.

5. Trigger the following malfunctions when the reactor trip is tripped manually:

"* ED05H (Loss of 4KV Bus T21 D)

"* FW46C (TDAFP trip)

(continued on next page)

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

SIMULATOR INSTRUCTIONS (S02-06)

Response to Crew's Requests:

1. Ifdirected to trip bistables for NPP-1 51 use:

Remote Bistable RPR076 PS-455A RPR077 PS-455B RPR078 PS-455C RPR079 PS-455D RPRI17 TS-411C RPRI18 TS-411D

2. Ifdirected to remove power from 2-QMO-225, then activate global malfunction (YG) 101QM0225.

3. Ifcontacted as chemistry regarding loss of normal letdown, then request 120 gpm normal letdown should be placed in service ASAP due to elevated lithium.

4. If directed to locally reset the TDAFP mechanical overspeed device, delay/wait until RCS bleed and feed has been initiated (all PRZ PORVs open), then delete malfunction FW46C and reportto the control room that the TDAFP mechanicaloverspeed device has been reset locally.

5. If directed to stop all ice condenser AHUs then activate remote function CHROI to OFF.

6. If directed to secure EDG jacket water pumps then modify remote functions as follows:

EGR 03, select OFF then AUTO EGR 04, select OFF then AUTO Cook Plant Unit I & Unit 2 NUREG-1021, Revision 8, Supplement 1

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