Text

2020 DC Cook Ile As-Administered Simulator Scenarios
	ML21005A431
Person / Time
Site:	Cook
Issue date:	08/25/2020
From:	; Indiana Michigan Power Co
To:	; NRC/RGN-III/DRS/OLB
	Reeser D
Shared Package
ML19121A512	List: ML20356A257; ML20356A259; ML20356A265; ML21005A431;
References
	Download: ML21005A431 (87)
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Appendix D Scenario Outline Form ES-D-1 Facility: DC COOK 1 & 2 Scenario No.: NRC2020-1 Op-Test No.: _________

Examiners: ___________________________ Operators: ____________________________

Initial Conditions: 80 % Power .

Turnover: Restore power to 100% following Turbine Valve testing_____________________________

Critical Tasks: Stabilize SG Level on MPP230 Failure, Manually Actuate SI_____________________

Even Malf. No. Event Event t No. Type* Description 1

N-BOP Swap #1 Control Fluid Pump for #3 Control Fluid Pump 2 R-RO Commence raising Reactor Power to 100%

3 U1_101PW2N C-RO PW Pump Trips \ Fails to Auto Start 4 MPP230 to 1 I-BOP SG Pressure Channel MPP-230 Fails Low over 30 Sec TS 5 U1_NLP152 I-RO Pressurizer Level Control Bi-stable channel fails Low to 0%

TS 6 U1_HWPS C - BOP Hotwell Pump Trip - Standby Fails to Start (Adjust U1_CPS101N Hotwell Bypass flow to lower pressure post trip)

U1_CPS103S 7 U1_RC19A @ C- Pressurizer Safety Starts leaking 7% CREW 8 U1_RP10A M- Pressurizer Safety progresses to full open CREW Train A Safety Injection signal failure to actuate in AUTO U1_RP10B Train B Safety Injection signal failure to actuate in U1_RP11B AUTO or Manual on the PRZ panel only U1_RP19D RPS Relay Failure Train A equipment fails to start (CV, SI, RHR, CC & Control Room Ventilation)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NOTE: Blue text indicates changes made to reflect as-administered scenario.

Page 1 of 21

Appendix D Scenario Outline Form ES-D-1 Event Summary The crew is directed to swap Control Fluid pumps due to potential problem with the running pump.

The plant is at 80% power and the crew is directed to commence raising power to 100%.

Once a Dilution is begun the PW pump will trip and the standby pump will fail to start The RO will be required to start the standby pump to continue the dilution.

After the crew completed the PW pump actions and began to change power, SG Pressure Channel MPP-230 fails low. The BOP will be required to take manual control of SG 3 Feedwater Regulating Valve FRV-230 to stabilize level. The crew will address the failure with the Abnormal Operating Procedure, address Technical Specifications, select an operable channel, and restore automatic control.

A Low failure of the Pressurizer Level Control Bi-stable channel will occur. The RO should identify the channel failure. The crew will need to address this failure with the Abnormal Operating Procedure and address Technical Specifications. This will also cause an isolation of normal Letdown. The crew will select an Operable Bi-stable channel and restore Letdown.

The South Hotwell Pump will trip requiring the BOP to manually start the Middle Hotwell pump.

The major event will start with a leaking Pressurizer Safety Valve. The crew may enter 4022-002-020, Excessive Reactor Coolant Leakage procedure. A unit trip will be required. This will lead to SV-45A PRZ Safety Valve failing full open. As the crew performs the actions of E-0, the Safety Injection will fail to automatically actuate. The Crew must manually actuate SI (Train B from SI panel only works) and/or align ECCS Pumps and Equipment as required.

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

Critical Tasks Stabilize SG Level on MPP-230 Failure Manually Actuate SI Procedures E-0, Reactor Trip or Safety Injection E-1, Loss of Reactor or Secondary Coolant Page 2 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 1 Event

Description:

Swap #1 Control Fluid Pump for #3 Control Fluid Pump Time Position Applicant's Actions or Behavior US Directs use of 1-OHP-4021-050-006, Main and MFP Turbine Control Fluid Operation, Attachment 1, Control Fluid System Operation, Section 4.2, for swapping Control Fluid Pumps.

BOP Places Control Fluid Pump #1 in RUN.

BOP Acknowledges Alarms on MT DCS Ann. Panel:

Drop 179, No Ctrl Fluid Pump in Auto 2

Drop 208, More than 1 CTRL FLD Pump in Manual and Running BOP Places Control Fluid Pump #3 in OFF.

BOP Places Control Fluid Pump #3 in AUTO 2.

BOP Acknowledges Alarms clearing on MT DCS Panel.

RO Provides peer checks during evolution as appropriate.

When pump swap is complete or at Lead Evaluators direction commence the next event Page 3 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 2 Event

Description:

Raise Turbine and Reactor Power NOTE: Place Event 3 Failure In prior to Crew starting dilution for Power Change Time Position Applicants Actions or Behavior Crew Reactivity brief for reactivity plan for power escalation.

US Directs RO to commence Power Escalation in accordance with OHP-4021-001-006, Power Escalation (at step 4.80)

NOTE Event #3 will be initiated when the dilution is started RO Performs DILUTION (batch add OR Continuous):

Place RC Makeup Blend control switch in STOP

Place RC Makeup Blend Control Mode switch in DILUTE or ALT DILUTE

Adjust PW to the desired flow rate and/or amount.

May close QRV-451, Blender to VCT if aligning to CCP Suction Only (if using Alt Dilute)

Place RC Makeup Blend control switch in START (Event 3 initiator)

May take QRV-303, VCT/Holdup Tk Inlet Selector to Manual and Open as required to maintain VCT Level and Pressure.

RO Commences escalation:

Raises turbine load (reactor power) using the DCS HMI.

Places MT in MW INOUT

Sets Turbine Load Target

Sets Turbine Ramp Rate

Selects Go

Maintains Tavg / Tref deviation within limits (+/- 2F or as designated by US) by dilution and turbine load adjustments.

Ensures Axial Flux Difference (AFD) is maintained within target RO RO verifies appropriate reactivity feedback.

BOP Acts as peer checker for RO during blender operations.

Page 4 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 3 Event

Description:

North PW Pump trip / Failure to Start of Standby Pump Time Position Applicants Actions or Behavior RO Identifies that the North PW pump has tripped and a dilution is not occurring. ANN panel 109 Drops 28 and 29 NOTE RO may stop attempted dilution and address the tripped pump using the ARP.

May Place North PW pump in stop RO Places South PW in Start and verifies that PW flow is available for dilution.

BOP Dispatch AEO to investigate North PW pump and/or breaker NOTE Report from field: Thermal overloads are tripped and cannot be reset SM If required have the Shift Manager direct crew to continue with Power Escalation / dilution US Initiates corrective action for failed pump

a. Notifies Shift Manager

b. Asks SM to make notifications including Work Control Page 5 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 4 Event

Description:

SG Pressure Channel MPP-230 Fails low Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel 114 which are indicative of a steam generator #3 water level control / pressure instrument failure (Drops 3, 12, 13, 14).

BOP Reports instrument malfunction and performs the immediate actions of OHP-4022-IFR-001, Instrument Failure Response:

Critical Places FRV-230, SG 3 MFW Reg. Valve controller to MANUAL, Task # lowers controller output and restores SG 3 level to program (may also place MFP P controller in MANUAL or Speed control at this time).

Crew Performs plant stability checks. (Order not important)

RO

1. Rx Power

2. RCS Temp

3. RCS Pressure

4. Pressurizer level

5. AFD BOP

1. Turbine Load

2. SG Level

3. MFP DP US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.

1. Check Steam Generator Narrow Range Level - STABLE OR TRENDING to 44%

2. Check Steam Generator PORVs - CLOSED

3. Check MFP Differential Pressure - Controlling At Appropriate Differential Pressure For Current Actual Steam Flow US Enters and directs actions of 1-OHP-4022-013-012, Steam Generator Pressure Instrument Malfunction procedure.

Page 6 of 21

Appendix D Required Operator Actions Form ES-D-2 BOP Performs the following actions as directed:

1. Reports MPP-230 has failed.

2. Places / verifies FRV-230 controller in MANUAL.

3. Places / verifies MFP P controller in MANUAL.

4. Checks SG PORVs closed.

5. Places 1-FS-532C selector switch in channel 2 position.

6. Restores SG 3 level using manual control of FRV-230.

7. Nulls and returns FRV-230 controller to AUTO.

8. Returns MFP P controller to auto.

US Refers to Tech Specs (TS):

TS 3.3.1 RTS Instrumentation Condition A - Check Table 3.3.1-1 Function: Function 15 -

Cond. D Trip Bi-stables in 6 Hours

TS 3.3.2 ESFAS Instrumentation Condition A - Check Table 3.3.2-1 Functions: Function 1e(2) &

4e - Cond. D - Trip Bi-stables in 6 Hours

TS 3.3.4 Remote Shutdown Instrumentation - Condition A - Restore within 30 Days

TRM 8.7.14 PPC Derived Thermal Power -Condition B - Maintain Power <100% on highest reading NI- Immediately) o TRM 8.7.14 PPC Derived Thermal Power - Recognizes that TRM 8.7.14 requirements are not APPLICABLE at the current power level.

US Initiates corrective action for failed channel

a. Notifies Shift Manager

b. Asks SM to make notifications including Work Control US Initiates actions to trip bi-stables associated with MPP-230 per Attachment C-1 of 1-OHP-4022-013-012.

When SM notification is made or at Lead Evaluators direction commence the next event Page 7 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 5 Event

Description:

NLP-152, Pressurizer Level Control Bi-stable channel fails low Time Position Applicants Actions or Behavior RO Recognizes and reports annunciators on Panel #108 (Drop 5, 50).

Reports instrument malfunction indicative of a Pressurizer Level instrument failure.

RO Reports instrument malfunction and performs the immediate actions of OHP-4022-IFR-001, Instrument Failure Response:

Close 1-QRV-200, using Charging Flow to Regen HX Controller

Places 1-QRV-251, Charging Flow Controller in manual and manually adjusts output to minimum amount required for seal injection (~35 gpm).

Crew Performs plant stability checks. (Order not important)

RO

1. Rx Power

2. RCS Temp

3. RCS Pressure

4. Pressurizer level

5. AFD BOP

1. Turbine Load

2. SG Level

3. MFP DP US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.

1. Check Pressurizer Level - Stable or Trending to Program Level.

2. Check Letdown - in service Page 8 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 5 Event

Description:

NLP-152, Pressurizer Level Control Bi-stable channel fails low US Enters and directs actions of OHP-4022-013-010, Pressurizer Level Instrument Malfunction procedure.

1. IF NLP-152 is the bi-stable channel THEN verify PZR level control is in manual using one of the following:

PRZ Level Control (master controller)

-OR-1-QRV-251, CCP Discharge Flow Controller

2. Verify PRZ Level CTRL selector switch in Channels 1&3 position.

3. Verify PRZ Level Rec selector switch in Chan 1 or 3 position

4. Check 1-NLP-152, PRZ Pressure Channel 2 for failure US Directs RO / BOP to restore normal letdown (using QRV-161, 75 gpm letdown orifice) per 1-OHP-4021-003-001, Letdown, Charging, and seal water Operation, Attachment 13.

RO Performs the following actions as directed:

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

2. Reports 1-NLP-152 has failed

3. Ensures PRZ level control is in manual

4. Places PRZ Level CTRL selector switch in Ch 1 & 3 position

5. Places PRZ Level REC selector switch in 1 or 3 position

6. Resets PRZ Heaters to restore control Actions for restoring Letdown and returning Pressurizer Level Control to automatic are contained on the following page US Initiates corrective action for failed instrument

a. Notifies Shift Manager

b. Asks SM to make notifications including Work Control Page 9 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 5 Event

Description:

NLP-152, Pressurizer Level Control Bi-stable channel fails low US Initiates actions to trip bi-stables associated with 1-NLP-152 PZR Level Failure per Attachment B of OHP-4022-013-010.

US Refers to Tech Specs (TS):

TS 3.3.1 RTS Instrumentation (Condition A Table 3.3-1, Function 9 Cond. D Trip Bi-stables in 6 Hours) o TS 3.3.3 Post Accident (Minimum channels met) o TRM 8.7.14 PPC Dervived Thermal Power -Condition B -

Maintain Power <100% on highest reading NI- Immediately (Already entered from event 4) o TRM 8.7.14 PPC Derived Thermal Power - Recognizes that TRM 8.7.14 requirements are not APPLICABLE at the current power level.

RO/BOP Restores normal letdown per Attachment 13, Section 4.1 as follows:

1. Places QRV-302, Cold Letdown Path Select in divert position.

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

3. Adjusts CRV-470, Letdown HX Temp Ctrl controller to >50%

output.

4. Verifies open letdown isolation valves:

a. QCR-300, CVCS letdown Cntmt isol

b. QCR-301, CVCS letdown Cntmt isol

c. QRV-111, RC letdown to Regen hx

d. QRV-112, RC letdown to Regen hx

5. Adjusts QRV-301, Letdown Press Ctrl controller to 50% output.

6. Checks/adjusts charging flow to > 75 gpm.

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

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

9. Places QRV-301 in auto (if desired).

10. Nulls and returns 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 QRV-302 in normal (demin) position when letdown temperature is stable.

With letdown restored, SM notification made, and pressurizer level is being restored to setpoint or at Lead Evaluators direction commence the next event Page 10 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-1 Event No.: 6 Event

Description:

South Hotwell Pump Trip - Middle (Standby) Fails to Start Time Position Applicant's Actions or Behavior BOP Recognizes Feedwater control problem and reports alarms:

Panel #116 Drop 63 - Hotwell Pump Disch Pressure Low Drop 61 - Hotwell Pump Motor Instant Trip Drop 73 - Cndst Booster Pump Disch Pressure Low Panel #122 Drop 96 - Turb Aux Clg Water Pump Auto Start Up US Directs operator actions to stabilize the unit and restore Hotwell pump flow.

RO Monitor RCS & Secondary parameters during transient.

BOP

Manually start the Middle Hotwell pump.

May Place South Hotwell pump control switch to TRIP and back to NEUTRAL (Clear Alarms).

Monitor Secondary parameters for normal operations.

US/RO Stabilize Power, if desired: (May be held from first event)

Verify Reactor Stable

Verify SG levels Stable US Initiates corrective action for failed pump

a. Notifies Shift Manager

b. Asks SM to make notifications including Work Control When secondary plant is stable or at Lead Evaluators direction commence the next event Page 11 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2018 Scenario No.: NRC2020-1 Event No.: 7, 8 Event

Description:

Pressurizer Safety Leak Progressing to Full Open, Train A & B Auto Safety Injection failure with Train A Relay Failure (CV, SI, RHR,CCW &

Control Room Ventilation fails to auto start)

Time Position Applicants Actions or Behavior RO Recognize and reports abnormal RCS leakage:

RCS pressure lowering with PZR Heaters ON

PRZ Safety Valve SV-45A indicates open

Panel #108:

Drop 8 - Pressurizer Press Low Dev Backup Htrs On Drop 29 - PRZ SV A Disch Temp Hi Drop 31 - Prz Relief Tk Pressure High Or Low Drop 45 - Acoustic Monit Flow Detected Or Volt Fail NOTE US may order a reactor trip based on safety valve leakage being unisolable.

If not crew should enter 1-4022-002-020, Excessive Reactor Coolant Leakage procedure.

US Enters 1-4022-002-020, Excessive Reactor Coolant Leakage RO Monitor PZR Level

1. Maintain PZR level by adjusting QRV-251 and QRV-200 as necessary

2. # Monitor Containment Pressure - if approaching 1psig then perform the following: Trip the Reactor, Go to 1-OHP-4023-E0, Reactor Trip or Safety Injection, when the Reactor is verified Tripped, THEN initiate Safety Injection.

RO/BOP Monitor Containment Pressure RO Monitor VCT Level RO Determine RCS Leak Rate Page 12 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2018 Scenario No.: NRC2020-1 Event No.: 7, 8 Event

Description:

Pressurizer Safety Leak Progressing to Full Open, Train A & B Auto Safety Injection failure with Train A Relay Failure (CV, SI, RHR,CCW &

Control Room Ventilation fails to auto start)

Time Position Applicants Actions or Behavior US Check Unit Status

TS 3.4.13 RCS Operational Leakage -Cond. A -4 hours (may not refer to until asked at end of scenario due to time restraints) o TS 3.4.1 RCS Pressure, Temperature, and Flow DNB Limits (Condition A) if Pressure lowers to <2168 psig. (2200 psig admin limit) (may use PPC times to track TS entry/exit times)

US Identify Source of Primary Leak US Directs RO to Perform a Reactor Trip based on Low RCS Pressure or High Containment Pressure leading to Safety Injection Directs RO/BOP to perform the immediate actions of 1-OHP-4023-E-0, Reactor Trip or Safety Injection.

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

1. Checks reactor trip - reactor Trip and Bypass breakers Open, all rods < 10 steps, neutron flux lowering

2. Checks turbine trip - MTSV Closed Status Lights Lit

3. Checks power to AC emergency buses - T11A or T11D at least one energized

4. Checks safety injection status - SI Status Light Lit (QMO-225/226 white lights Lit) Required if:

a. PZR Pressure < 1775#

b. CNTMNT Pressure > 1.0#

c. SG Pressure < 500#

d. STM Line DP > 100psid Page 13 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2018 Scenario No.: NRC2020-1 Event No.: 7, 8 Event

Description:

Pressurizer Safety Leak Progressing to Full Open, Train A & B Auto Safety Injection failure with Train A Relay Failure (CV, SI, RHR,CCW &

Control Room Ventilation fails to auto start)

Time Position Applicants Actions or Behavior RO/BOP Check Safety Injection Actuated:

Manually Actuate SI (From SI Panel for Train B) to establish Critical High Head Injection Flowpath Task #2

-OR-NOTE: May be performed in E-0, Attachment A.

Manually Align Valves

BIT Inlet Valves ICM-255 -AND/OR ICM-256 - OPEN

BIT Outlet Valves ICM-250 -AND/OR ICM-251 - OPEN

RWST to CCP Valves IMO-910 -AND/OR IMO-911 - OPEN

VCT to CCP Valves QMO-451 -AND/OR QMO-452 - CLOSED

Manually Start/Align ECCS Equipment and Actuate Phase A (Train A)

SI

RHR RO/BOP Reviews E-0 Foldout Page Criteria.

US/RO Foldout Page - RCP Trip Criteria:

Stop all RCPs when RCS is < 1300 psig and CCP/SI pump running BOP Manually controls AFW flow to > 240,000 to < 450,000 pph to maintain SG narrow range levels 13% - 50% once one SG narrow range level is greater than 13%.

US Ensures immediate actions of E-0 are completed

Directs subsequent actions of E-0.

Page 14 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2018 Scenario No.: NRC2020-1 Event No.: 7, 8 Event

Description:

Pressurizer Safety Leak Progressing to Full Open, Train A & B Auto Safety Injection failure with Train A Relay Failure (CV, SI, RHR,CCW &

Control Room Ventilation fails to auto start)

Time Position Applicants Actions or Behavior RO/BOP Completes actions of E-0 through step 19 as directed.

Step 5 - Check Main Steamline Isolation NOT required (Steamline pressure > 500 #, flow < 1.42x106 PPH, Containment < 2.8#)

Step 6 -Check CTS NOT required (Containment < 2.8#)

Step 7 - Implement Attachment A while continuing

Step 8 - Check if Ruptured SG is Suspected (No NR level rising in uncontrolled manner)

Step 9 - Check AFW Pumps running (MDAFPs and TDAFP running)

Step 10 - Check total AFW flow > 240 x 103 PPH Step 11 - Minimize Unnecessary RCS Cooldown (NR level > 13%,

control flow to maintain NR level between 13 - 50%)

Step 12 - Check AFW Discharge valves Open or Throttled Step 13 - Check FW Isolation (MFPs tripped, Discharge valves closed, FRVs closed, FW Isolation valves closed)

Step 14 - Check RCS Temperature (RCP running - RCS Tavg 547F)

Step 15 - Check PZR PORVs and Spray Valves Step 16 - Check if RCPs should be Stopped (RCS Pressure <

1300# and 1 CCP or SI pump running)

Step 17 - Check if SG Secondary Boundaries are Intact (No SG Pressure lowering in Uncontrolled manner or completely Depressurized)

Step 18 - Check if SG Tubes are Intact (NO NR level Rising in uncontrolled manner)

Step 19 - Check if RCS is Intact (CNTMNT Radiation, Pressure, Water Levels Normal)

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

Verifies CEQ Fans and CCW to CEQ

Place DIS in Service - Turn on Igniters

Verify Train A Control Room Pressurization aligned

Reset Bypass switches for PACHMS

Verifies Containment Ventilation & Phase A Isolations Page 15 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2018 Scenario No.: NRC2020-1 Event No.: 7, 8 Event

Description:

Pressurizer Safety Leak Progressing to Full Open, Train A & B Auto Safety Injection failure with Train A Relay Failure (CV, SI, RHR,CCW &

Control Room Ventilation fails to auto start)

Time Position Applicants Actions or Behavior US/RO Checks if RCS is Intact - NO.

US Evaluates Critical Safety Function Status US Announces transition to 1-OHP-4023-E-1, Loss of Reactor or Secondary Coolant and directs operator actions.

RO/BOP Reviews E-1 Foldout Page Criteria.

Page 16 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2018 Scenario No.: NRC2020-1 Event No.: 7, 8 Event

Description:

Pressurizer Safety Leak Progressing to Full Open, Train A & B Auto Safety Injection failure with Train A Relay Failure (CV, SI, RHR,CCW &

Control Room Ventilation fails to auto start)

Time Position Applicants Actions or Behavior RO/BOP Completes actions of OHP-4023-E-1 through step 12 (Check if RCS Cooldown and Depressurization is required) as directed.

1. Check if RCPs should be stopped - RCS Pressure< 1300#

2. Check if SG Secondary Pressure Boundaries are Intact -

No pressure lowering in uncontrolled manner or completely depressurized

3. Check intact SG levels - NR level > 13%

4. Check Secondary Radiation - Rest Phase A and direct Chemistry to sample SGs for activity

5. Check PZR PORVs and Block valve - Block valves energized and at least one open, PORVs closed

6. Check if ECCS flow should be reduced - RCS subcooling >

40F, Secondary Heat Sink, RCS Pressure stable or rising, and PZR level > 16% - Go to ES-1.1

7. Check if CTS should be stopped - CTS running, RCS Pressure > 300#, Containment Pressure < 2.0#

8. Check if RHR pumps should be stopped - RCS Pressure >

300#, RCS Pressure stable or rising, RHR pump running aligned to RWST

9. Check RCS and SG Pressures - Pressure in all SGs Stable or rising, RCS Pressure Stable or Lowering

10. Check if EDGs should be stopped - Emergency busses Energized by Off-Site

11. Initiate evaluation of plant status - check Cold Leg Recir Capability

12. Check if RCS Cooldown and Depressurization is required -

RCS Pressure > 300#

US Announces transition to 1-OHP-4023-ES-1.2, Post LOCA Cooldown and Depressurization (at step 12).

At transition or Lead Evaluators discretion Terminate Scenario Page 17 of 21

Critical Task Summary Task Elements Results Cueing:

Panel #114 Drops 3,12,13,14

1

MFC-131 Indication Lowering SAT / UNSAT

FRV-230 closing Manually Control SG#13 Level on MPP- Performance Indicators:

230 Failure

Place FRV-230 in Manual and control SG #13 Level to maintain it 15% - 67% preventing a Reactor Trip.

(May Select MFC-130 as Controlling Channel and Place\Leave FRV-230 In Auto)

Performance Feedback:

SG FW Flow raises (FRV-230 opens)

SG Level Stabilizes and returns to band

2 Cueing: SAT / UNSAT

Check SI Actuated Safety Injection Actuated Manually Status Light LIT (E-0, Step 4.a)

Actuate/Align one -OR-train of Safety

Check BOTH CCP leakoff valve "Safety Injection Injection to establish Signal" white lights - LIT HIGH Head Injection Flow Performance Indicators:

Before transitioning from E-0 and reaching a Valid Orange Path in FR-C series Core Cooling

Actuate 1 Train of SI

-OR-

Manually Start/Align ECCS Equipment and Actuate Phase A (Train B)

Manually Align Valves (Train A listed First, Train B)

BIT Inlet Valves IMO-255 -AND/OR IMO-256 -

OPEN

BIT Outlet Valves ICM-250 -AND/OR ICM-251 -

OPEN

RWST to CCP Valves IMO-910 -AND/OR IMO-911 - OPEN

VCT to CCP Valves QMO-451 -AND/OR QMO-452 - CLOSED

Ensure 1 CCP and SI running Performance Feedback:

ECCS flow is indicated from at least one train (as indicated by flow on cold leg BIT injection flowmeters 1-IFI-51 thru 1-IFI-54)

One Train of Phase A Isolation is complete per E-0, Attachment A Page 18 of 21

Scenario Instructor Actions Setup:

1. Reset to IC-303 MOL; 80% power, 850 MW, 799.86 ppm, 565.5 F 194 Steps on D

2. Place ALL Pressurizer Heaters In ON

3. Reset control rods and check group step counters.

4. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position.

5. Advance chart recorder paper & clear chart recorder memory.

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

1. Set Up South PW pump fail to Auto Start

South PP in run on Trigger U1 South PW In Run Trg 1

Global on South PW & Turn on Light U1_101PW2S ZLO101PW2S_U1[GRN]

Clear Global and Light on Start U1_101PW2S ZLO101PW2S_U1[GRN]

2. Set Up North PW pump trip on Auto Start

PW flow on Trigger 4 QFC412 PW Flow >.003 Trg 4

Trip North PW Pump on Trg 4 U1_101PW2N Hotwell Pump 1N Pressure Switch U1_CPS101N Hotwell Pump 1S Pressure Switch U1_CPS103S Train A Safety Injection Auto Failure U1_RP10A Train B Safety Injection Auto Failure U1_RP10B Train B Safety Injection Manual on the PRZ panel only U1_RP11D RPS Relay Failure Train A U1_RP19D Equipment fails to start (CV, SI, RHR,CC & Control Room Ventilation)

Setup trigger for reactor trip Reactor trip on Trigger 6 Modify Safety valve leak Safety valve to 100%

Page 19 of 21

Scenario Instructor Actions Scenario Events:

NOTE: Verify Event 3 Failure In prior to Crew Starting Dilution EVENT #1 If required, Local Control Fluid Temperature is 124°F EVENT #2 Respond as required to power change notifications and requests EVENT #3 (Entered in Setup)

If dispatched, report that the North PW pump breaker appears to be tripped and will not reclose Report from field: Thermal overloads are tripped and cannot be reset EVENT #4 After crew changes power, insert ICF U1_MPP230 final value 1 over 30 seconds (MPP-230 fails low).

U1_MPP230 EVENT #5 Insert U1_NLP152, final value 0 NLP-152 fails low to cause Letdown isolation, heater isolation, and alarm.

U1_NLP152 EVENT #6 IMF U1_HWPS to cause a South Hotwell Pump to Trip (Switches to failure auto start already in)

U1_HWPS Page 20 of 21

Scenario Instructor Actions EVENT #7 IMF U1_RC19A to 7 from .1 over 10 Minutes to simulate the PZR Safety leak U1_RC19A Malfunctions for Train A & B SI Auto Failure, Train B from PRZ Panel, and Train A Slave Relay have already been Entered.

Perform Local actions after entry into E-0 as requested:

Locally stop U1 Ice Condenser AHUs MRF CHR01 to OFF U1_CHR01

Aux Tour will monitor Spent Fuel Pool Level and Temperatures

Place PACHMAS in service - MRF CHR02 or 03 with 10 min delay.

U1_CHR02 OR U1_CHR03 (both have 10 minute delay built in)

U2 has aligned CR vent for U1 SI, Fan 2-HV-AS-2 is running.

If directed to secure EDG jacket water pumps select OFF then AUTO Remote OFF AUTO U1_EGR03A U1_EGR03A EGR 03A U1_EGR03B U1_EGR03B EGR 03B U1_EGR04A U1_EGR04A EGR 04A U1_EGR04B U1_EGR04B EGR 04B Page 21 of 21

Appendix D Scenario Outline Form ES-D-1 Facility: DC COOK 1 & 2 Scenario No.: NRC2020-2 Op-Test No.: _________

Examiners: ___________________________ Operators: ____________________________

Initial Conditions: 4 % Power .

Mode change approved. Plant startup, raise power to ~ 10% to warm and roll Main Turbine.

Critical Tasks: Stabilize PZR Pressure following NPP-151 failure, Insert Negative Reactivity.

Event Malf. No. Event Event No. Type* Description 1 R- RO Raise power 2 U1_TACSE C-BOP East Turbine Aux Cooling Water pump trip Stator Short 3 N-BOP Control SG Level in manual 4 U1_NPP151 I-RO Controlling Pressurizer Pressure Channel Fails High to 2500 TS 5 U1_MPP212 I-BOP SG PORV Pressure Transmitter Failure to 1500 TS 6 U1_ECP C-RO Trip of 1E CCP short circuit TS*

7 U1_RP08B M-Crew Intermediate Range Failure and Reactor Trip Breakers U1_NI06 fail to open U1_RP03A Inadvertent FW Isolation U1_RP03B U1_WMDAF West MDAFW Pump trip P Short

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Applicable Tech Spec (TS) Limiting Conditions for Operation (LCO) were addressed during event 4. No new TS LCO applications were generated by Event 6.

NOTE: Blue text indicates changes made to reflect as-administered scenario.

Page 1 of 21

Appendix D Scenario Outline Form ES-D-1 Event Summary The Crew is directed to commence raising power to ~10% for Main Turbine Start-up. The RO will withdraw rods to raise power while the BOP has Manual Control of Feed Reg Valves for SG level.

A trip of the East Turbine Aux Cooling Water pump occurs. This will result in reduced cooling capability for the Main Generator. BOP will be required to manually start the West Turbine Aux Cooling Water pump. Crew will be required to stabilize the plant.

The controlling Pressurizer Pressure Channel NPP-151 Fails High, Pressurizer spray valves will go full open. The crew will need to take manual control of pressurizer pressure and enter an Abnormal Operating Procedure, defeat the failed channel, address Technical Specifications, and then restore pressurizer pressure control to auto.

A failure of SG #11 Pressure Channel (MPP-212) fails high causing SG #11 PORV to fully open.

This will also cause Reactor power to slightly rise. The BOP will need to take manual action to close the PORV, the crew will implement Abnormal Operating Procedure actions, and the US will need to declare the associated radiation monitor inoperable.

A Loss of the East CCP will require the RO to Start the West CCP. Letdown will be lost on the loss of the running CCP and will be addressed by the crew. The US will need to address Technical Specifications.

A failure of the Intermediate Range N36 will generate a Reactor Trip signal along with an inadvertent Feedwater Isolation causing the crew to identify a need for a manual Reactor Trip.

The West MDAFW pump will not start to prevent the crew from attempting to lower power and stay on line using Aux feed. Crew should enter E-0 and perform the immediate actions. The crew will attempt to manually trip the reactor. Reactor trip breakers will not open causing the crew to enter 4023-FR-S.1, Response to Nuclear Power Generation / ATWS.

Critical Tasks Stabile PZR pressure following NPP-151 failure Insert Negative Reactivity in FR-S.1 Procedures E-0, Reactor Trip or Safety Injection FR-S.1, Response to Nuclear Power Generation / ATWS Page 2 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 1 Event

Description:

Raise Power to 10% Power Time Position Applicant's Actions or Behavior RO Briefs crew on reactivity plan for power rise.

US Reviews reactivity plan.

US Directs RO to commence Power Escalation in accordance with OHP-4021-001-006, Power Escalation procedure, step 20.

RO Commences escalation:

Withdraws rods in 3 Step Increments while monitoring Delta T Power, NI Power and Steam Dumps Note Insert event 2 after first rod withdrawal RO RO verifies appropriate reactivity feedback.

o RCS Temp rise o Steam Dump Demand signal increase o Reactor Delta T Power indication rise o Reactor Delta Flux becoming more positive Page 3 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 2 Event

Description:

East Turbine Aux Cooling Water Pump Trip Time Position Applicant's Actions or Behavior BOP Recognizes problem and reports annunciator:

Panel #122

Drop 97 Turbine Aux CLG Motor Failure US Directs operator actions to stabilize the unit and restore Turbine Aux Cooling Water capacity.

BOP

Manually start the West Turbine Aux Cooling Water Pump

May Place East Turbine Aux Cooling Water Pump switch to TRIP and back to NEUTRAL (Clear Alarms)

Monitor Secondary parameters for normal operations BOP Dispatch AEO to investigate East Turbine Aux Cooling Water Pump and/or breaker US Initiates corrective action for failed pump

a. Shift Manager

b. Asks SM to make notifications including Work Control Note If crew delays continuation of power ascension, then step in as Shift Manager and direct continuing power ascension Note Transition to event 4 @ 6-7% and Steam Generator levels being controlled in manual (Event 3) or at lead examiners direction Page 4 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 3 Event

Description:

Control Feedwater Flow in Manual Time Position Applicant's Actions or Behavior BOP

Adjust FRV210 - 240 to Maintain SG levels within Designated band

Adjust Main FW Pump Speed / DP target to ensure adequate FW Discharge to SG DP

Place FW Regulating Valves in Auto if FRVs will control based on power Page 5 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 4 Event

Description:

Pressurizer Pressure Channel NPP 151 Fails High Time Position Applicants Actions or Behavior RO Recognizes and reports annunciators on Panel #108 indicative of a pressurizer (PRZ) pressure instrument failure (Drops 6, 7, 8).

Reports instrument malfunction and performs the immediate RO actions of OHP-4022-IFR-001, Instrument Failure Response:

Critical Task Places PRZ pressure master controller OR both PRZ spray

1 valve controllers (1-NRV-163 and 164) to manual and lowers controller output to close spray valves Crew Performs plant stability checks. (Order not important)

RO

1. Rx Power

2. RCS Temp

3. RCS Pressure

4. Pressurizer level

5. AFD BOP

1. Turbine Load

2. SG Level

3. MFP DP US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.

US Enters and directs actions of 01-OHP-4022-013-009, Pressurizer Pressure Instrument Malfunction procedure.

May enter Technical Specification 3.4.1 RCS Pressure, Temperature, and Flow DNB Limits if Pressure lowers to <2168 psig. (2200 psig admin limit)

US Declares the 1E Centrifugal Charging Pump inoperable. (NPP-151 is the input pressure signal to the East CCP Emergency Leak-off Valve.)

Page 6 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 4 Event

Description:

Pressurizer Pressure Channel NPP 151 Fails High Time Position Applicants Actions or Behavior RO Performs the following actions as directed:

1. Restores PRZ pressure (~ 2235#) using manual control of EITHER:

PRZ pressure master controller

Both PRZ spray valve controllers

2. Reports 1-NPP-151 has failed HIGH

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 RO Performs the following actions as directed:

6. Verifies 1-QMO-225, E CCP Leakoff is open NOTE: (May place QRV251 in Manual while opening Leakoff -

Letdown may also be reduced - QRV-251 should be returned to Auto)

7. Dispatches Aux operator to open breaker for 1-QMO-225 (1-ABV-D-5C)

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

9. Ensures PRZ pressure master controller is in manual

10. Nulls and returns the following controllers to auto:

Both PRZ spray valve controllers

PRZ pressure master controller Page 7 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 4 Event

Description:

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

TS 3.3.1 RTS Instrumentation (Condition A Table 3.3.1-1, Function 6, 8a, 8b Cond. D Trip Bi-stables in 6 Hours)

TS 3.3.2 ESFAS Instrumentation (Condition A Table 3.3.2-1, Function 1d Condition D -6 hours, 8b Condition G - 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months *)

TS 3.3.4 Remote Shutdown Instrumentation (Condition A - 30 days)

TS 3.5.2 ECCS Subsystems Condition A - 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (E CCP)

TRM 8.1.1 Rx Control Systems Charging Pumps - Operating (Action A - 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) o TRM 8.7.14, LEFM, (N/A - Applicable above 3250 MW) o TRM 8.1.3, Boration Systems - Hot Shutdown (N/A in Mode 1)

=Identifies requirement to verify the status of Permissive P-11 Bi-stables within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of pressurizer pressure channel failure.

US Initiates actions to trip Bi-stables associated with 1-NPP-151 PZR Pressure Failure per Attachment A of 1-OHP-4022-013-009.

Initiates corrective action for failed channel US

a. Notifies Shift Manager

b. Asks SM to make notifications including Work Control When PZR pressure is restored and controlled at ~ 2235# and Tech Specs are addressed or at Lead Evaluators direction proceed to next event Page 8 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 5 Event

Description:

SG Pressure Channel MPP-212 Fails HIGH - SG 1 PORV Opens Time Position Applicants Actions or Behavior BOP Recognize and reports Annunciator Panel #114, Drop 21, 1-MRV-213 OP OR HSD1 PANEL OVERRIDE alarm that indicates SG #1 PORV (MRV-213) has opened.

BOP Reports MPP-212 has failed high.

BOP Place SG PORV #1 in Manual and Closes #1 PORV.

Crew Performs plant stability checks. (Order not important)

RO

1. Rx Power

2. RCS Temp

3. RCS Pressure

4. Pressurizer level

5. AFD BOP

1. Turbine Load

2. SG Level

3. MFP DP US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.

BOP For a Steam Generator Pressure OR Level Control OR Main Feed Pump D/P Issue OR any failure that affects these parameters perform the following:

a. Check Steam Generator Narrow Range Level - STABLE OR TRENDING to 44%

b. Check Steam Generator PORVs - CLOSED: MRV-213

Manually close any Steam Generator PORV which is open due to an instrument OR control system malfunction

c. Check MFP Differential Pressure - CONTROLLING AT APPROPRIATE DIFFERENTIAL PRESSURE for CURRENT ACTUAL STEAM FLOW Page 9 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 5 Event

Description:

SG Pressure Channel MPP-212 Fails HIGH - SG 1 PORV Opens Time Position Applicants Actions or Behavior US Enters and directs actions of 1-OHP-4022-013-012, Steam Generator Pressure Instrument Malfunction procedure.

1. Identifies 1-MPP-212 as failed channel a) If selected for PORV control - Verify PORV in manual b) Declare 1-MRA -1601 inoperable due to PORV being in Manual (Procedurally required) c) Select an Operable channel using 1-PS-514F d) Place PORV in AUTO and declare 1-MRA-1601 Operable

2. Check SG Water Level Control in AUTO (FRVs remain in manual due to low power)

3. Check MFP Differential Control in AUTO

4. Refer to Tech Spec (see below)

5. Trip Bi-stables for malfunctioning instrument US Refers to TS / TRM:

TS 3.3.2 ESFAS Instrumentation (Condition A Table 3.3.2-1, Function 1.e (1& 2) & 4.d - all Condition D) Trip Bi-stables in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

TS 3.7.4 Steam Generator PORV (Condition A May be referenced but PORV is Operable since it can be manually operated) Restore in 7 days

TRM 8.3.8. Radiation Monitoring Instrumentation (Condition A Table 8.3.8-1, Function 2.b - Condition C)

Declares MRA-1601 inoperable

Restore in 7 days Initiates corrective action for failed channel US

c. Notifies Shift Manager

a. Asks SM to make notifications including Work Control Work Control Page 10 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 5 Event

Description:

SG Pressure Channel MPP-212 Fails HIGH - SG 1 PORV Opens Time Position Applicants Actions or Behavior US Notifies SM/MTI to Initiate actions to trip Bi-stables associated with MPP-212 Steam Generator Pressure Instrument Failure per Attachment A-3 of 1-OHP-4022-013-012.

When Steam Generator PORV is closed and SG pressure is stabilized and Tech Specs are addressed, or at Lead Evaluators direction proceed to next event.

Page 11 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-2 Event No.: 6 Event

Description:

Trip of 1E CCP Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators that are indicative of a trip of the East Charging Pump:

Annunciator 108 Drop - 20 Charging Flow Less Than Min Set Point Annunciator 109 Drop - 11 East CCP Motor Instant Trip US Directs RO to Start CCP for Seal Injection.

RO Recognizes and reports that running (East) CCP pump has tripped Manually starts 1W CCP pump in accordance with CCP ARPs

1. Start West CCP Aux Lube Oil pump

2. Verify the West CCP has a suction (QMO-451 & 452 -

Open)

3. Start the West CCP RO/BOP Restores normal letdown per Attachment 13, Section 4.1 as follows:

1. Places QRV-302, Letdown Divert Valve in divert position.

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

3. Adjusts CRV-470, Letdown Temperature Control Valve controller to >50% output.

4. Verifies open letdown isolation valves:

a. QCR-300, CVCS letdown Cntmt isol

b. QCR-301, CVCS letdown Cntmt isol

c. QRV-111, RC letdown to Regen hx

d. QRV-112, RC letdown to Regen hx

5. Adjusts QRV-301, Letdown Pressure Control Valve controller to 50% output.

Page 12 of 21

Appendix D Required Operator Actions Form ES-D-2

6. Checks/adjusts charging flow to > 75 gpm.

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

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

9. Places QRV-301 in auto (if desired).

10. Nulls and returns 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 QRV-302 in normal (demin) position when letdown temperature is stable.

US Initiates corrective action for tripped pump

a. Notifies shift Manager

b. Asks SM to make notifications including Work Control US Refers to TS / TRM:

o TS 3.5.2 ECCS - Operating Condition A - Restore train to Operable Status in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (LCO Actions entered in Event 4) o TRM 8.1.1 Boration System - Operating Condition A - Restore in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (LCO Actions entered in Event 4)

When Letdown flow is restored and crew is stabilizing Letdown temperature, Tech Specs are addressed or at Lead Evaluators discretion proceed to next event.

Page 13 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: NRC2020-2 Event No.: 7 Event

Description:

Intermediate Range Failure, Reactor Trip Breakers fail to Open, Inadvertent FW Isolation Time Position Applicant's Actions or Behavior CREW Recognizes the IRNI failure and need for a reactor trip. West MDAFW pump will not start. FW Isolation prevents crews efforts to stay online.

NOTE FW Isolation prevents crews efforts to stay online due to power being above AFW capacity.

West MDAFW pump will not start to further limit their ability to remain on line US Directs RO to manually trip the reactor Directs RO/BOP to perform the immediate actions of 1-OHP-4023-E-0, Reactor Trip or Safety Injection.

RO Recognizes and reports failure of reactor to manually trip- Rx Trip breakers closed after actuating Manual trip switches (twice).

US Directs actions of 1-OHP-4023-FR-S.1, Response to Nuclear Power Generation/ATWS:

RO Performs the immediate actions of FR-S.1:

1. Checks reactor trip (RX Trip Bkrs Open, Rod Bottom Lights Critical Lit, All Rods, <10 steps, Neutron Flux Lowering)

Task #2 Automatically/Manually insert control rods (must Insert Negative Reactivity through Inserting Control Rods or Emergency Boration)

BOP Performs the immediate actions of FR-S.1:

1. Manually actuate AMSAC

2. Checks Turbine Trip (MT Stop Valve Closed Status Lights LIT)

Page 14 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: NRC2020-2 Event No.: 7 Event

Description:

Intermediate Range Failure, Reactor Trip Breakers fail to Open, Inadvertent FW Isolation Time Position Applicant's Actions or Behavior US Ensures immediate actions of FR-S.1 are completed RO Initiate Emergency Boration of RCS (must Insert Negative Reactivity through Inserting Control Rods or Emergency Critical Boration)

Task #2 1. Check CCPs at least one running

2. Start both boric acid transfer pumps in fast speed

3. Open 1-QMO-410

4. Check Emergency Boration flow > 44 gpm on QFI-410

5. Check PZR Pressure < 2335#

US Directs subsequent actions of FR-S.1:

Check Containment Vent Isolation Valves Closed - VCR-101 thru 107 and VCR-201 thru 207

Check SI Status - Safety Injection Actuated Status Light NOT Lit

Check Reactor Tripped - Local operation of reactor trip breakers or MG set output breakers

Verify Reactor subcritical - WR log power < 5% & negative SUR (Go to Step 20) Continue Boration to Maintain Adequate Shutdown Margin

Return to Procedure and Step in Effect - E-0 US Verify Reactor subcritical - WR log power < 5% & negative SUR US Announces transition to OHP-4023-E-0, Reactor Trip or Safety Injection.

Page 15 of 21

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: NRC2020-2 Event No.: 7 Event

Description:

Intermediate Range Failure, Reactor Trip Breakers fail to Open, Inadvertent FW Isolation Time Position Applicant's Actions or Behavior RO/BOP Performs the immediate actions of E-0:

1. Checks reactor trip - reactor Trip and Bypass breakers Open, all rods < 10 steps, neutron flux lowering

2. Checks turbine trip - MTSV Closed Status Lights Lit

3. Checks power to AC emergency buses - T11A or T11D at least one energized

4. Checks safety injection status - SI Status Light Lit (QMO-225/226 white lights Lit) Required if:

a. PZR Pressure < 1775#

b. CNTMNT Pressure > 1.0#

c. SG Pressure < 500#

d. STM Line DP > 100psid BOP Manually controls AFW flow between 240,000 to 450,000 pph until one SG narrow range level is greater than 13%.

US Announces transition to OHP-4023-ES-0.1, Reactor Trip Response When feed flow < 450,000 pph or at Lead Evaluators discretion TERMINATE SCENARIO Page 16 of 21

Critical Task Summary Task Elements Results

1 Cueing: SAT / UNSAT

Panel 108 Drop 6 Pressurizer Pressure High-High Stabilize PZR

Pressurizer Pressure NPP-151 failed High with actual Pressure Prior to Pressure Lowering Reactor Trip with failure of NPP-151 Performance Indicators:

Takes Manual Control of Pressurizer Master Controller or Spray Valve Controllers and Closes NRV-163 and NRV-164:

NRV-163 and NRV-164 Closed Indications

May place to auto after Operable Channel is selected (

Pressurizer Pressure Stabilizes

Prior to reaching 1950 psig - Pressurizer Low Pressure Reactor trip Performance Feedback:

RCS pressure stabilizing

2 Cueing:

Challenge to RCS cooling with FW Isolation SAT / UNSAT Insert negative

Identification that RX breakers have failed to OPEN (On reactivity into the core NI 36 trip signal)

RX TRIP BKR TRAIN A/B UV TRIP (ATWS) alarms Performance Indicators:

Insert Negative Reactivity through:

Inserting Control Rods (Manually or Auto at >48 steps per minute) - OR -

Emergency Boration is initiated Must be performed prior to:

SRO Reaching Step 8 of FR-S.1 Performance Feedback:

RODS

RPIs indicate rods - inserting

Rod bottom lights - lit

Neutron flux - lowering BORATION (any of the following)

Boration Flow QFI-410 > 44 gpm

IMO-910 or IMO-911 open

Boration Flow QFC-421 > 36 gpm Page 17 of 21

Scenario Instructor Actions Setup:

1. Reset to IC-856 MOL; 4% power,1180.64 ppm, 550.62 F, 171 Steps on D

2. Place ALL Pressurizer Heaters In ON, Remove SFR-402 from PPC alarm.

3. Reset control rods and check group step counters.

4. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position.

5. Advance chart recorder paper & clear chart recorder memory.

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

Reactor Trip Breaker A Fails U1_RP03A

Reactor Trip Breaker B Fails U1_RP03B

TACW Pressure Switch U1_CPS603

West AFW Pump Trip U1_WMDAFP Set Up on Trigger 1:

U1_RP08B

Spurious FW Isolation Train B

N36 IR to Fail High U1_NI06B

Ensure IR cant block U1 IR Train B Block Override SFR402 and U1_SFR402 sfr201 to hold air inleakage U1_SFR201 Disable AFD at low power AN10_U1(044)

Page 18 of 21

Scenario Instructor Actions Scenario Events:

EVENT #1 IMF U1_TACSE to cause the east TACW Pump to Trip U1_TACSE EVENT #2 Respond as required to power change notifications and requests EVENT #3 Respond as required to power change notifications and requests EVENT #4 ICF U1_NPP151 to 2500 over 30 seconds cause the Pressurizer Pressure Channel to fail High U1_NPP151 When Requested to De-energize Power for QMO-225 (1-ABV-D-5C)

U1_EDPR10J EVENT #5 ICF U1_MPP212 to 1200 over 4 seconds to cause the SG Pressure Channel MPP-212 to Fail High (SG11 PORV Opens in Auto)

U1_MPP212 EVENT #6 IMF U1_ECP to cause a Charging Pump Short Circuit U1_ECP Page 19 of 21

Scenario Instructor Actions EVENT #7 - 9 Activate Trigger 1 to cause a Spurious Train B FW Isolation and N36 IR to Fail High requiring a Reactor Trip signal Activate Trigger 1 If Dispatched to Open the Reactor Trip Breakers then turn off the MG Sets U1_RDR01 U1_RDR03 Page 20 of 21

Scenario Instructor Actions Reactivity Guide CBD Power Delta I Tave 165 3.3 0 550.6 168 3.8 0 551.0 171 5.2 +0.5 551.9 174 6.4 +1.0 552.6 177 8.0 +1.1 553.4 180 9.3 +2.0 554.1 183 10.5 +2.5 554.9 Page 21 of 21

Appendix D Scenario Outline Form ES-D-1 Facility: DC COOK 1 & 2 Scenario No.: NRC2020-3 Op-Test No.: _________

Examiners: ___________________________ Operators: ____________________________

Initial Conditions: 50 % Power, WMFP is spinning ~ 3800 rpm .

Turnover: Restore power to 100% following previous down power for MFP repairs Critical Tasks: Stabilize SG Level on MFC140 Failure, Throttle AFW to prevent a PTS challenge Event Malf. No. Event Event No. Type* Description 1 N-BOP Place an Additional Main FW Pump in Service 2 U1_NTP240 I-RO Loop 4 Tc fails high to 650 TS 3 R-RO Commence raising Reactor Power to 100%

4 U1_MFC140 I-BOP

14 SG Controlling Steam Flow Channel Fails Low

@0 TS 5

U1_ED07B C-RO PZR HTR Transformer Fails (11PHC Fails)

TS 6 Set C-BOP Main Steam Stop Valve Comes Off Detent (Open Limit U1_MSVMR Switch)

V210 .94 7

U1_MS01D M-CREW Steam Line Break Outside Containment (#14 SG)

@ 20 over 2 (Steam Line Isolation fails to AUTO actuate, MSIVs fail to min close Manually)

U1_RP07A U1_RP07B U1_MS22A -

D

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NOTE: Blue text indicates changes made to reflect as-administered scenario.

Page 1 of 22

Appendix D Scenario Outline Form ES-D-1 Event Summary The Crew is directed to Place an Additional Main FW Pump in Service. 1-OHP-4021-055-003, Attachment 4, West Feed Pump Startup As Second Feed Pump is complete up to step 4.6 and the pump is spinning ~ 3800 rpm.

The Loop #4 Tc RTD will fail high. This will require the RO to place rods in manual to stop rod movement. The crew will implement Abnormal Operating Procedure actions to stabilize the plant.

The plant is at 50% power and the crew is directed to commence raising power to 100%.

The #14 SG Controlling Steam Flow Channel will fail low causing the FRV to close and SG level to Lower. The BOP will need to establish manual control of #14 FRV and MFP DP control to stabilize SG level. The Crew will need to enter the Abnormal Operating Procedure and select an operable channel, restore SG level control to auto, and address Technical Specifications.

A failure of the PZR HTR Bus 11PHC will occur. The PZR SCR heater control will need to be transferred to 11PHA using the Annunciator Response procedure. The crew should also refer to Technical Specifications.

The #1 SG Main Steam Stop Valve will come off the open limit switch/detent. The crew will need dispatch an operator to check the status and then reopen the Stop Valve using the Annunciator Response procedure to continue on.

The major event will involve a Main Steamline Break outside containment on the #14 SG. The crew will trip the reactor and a Safety Injection will actuate. As the crew performs the actions of E-0, they should identify the Main Steamline Break outside containment on the #14 SG. A failure of the Main Steamline Isolation actuation circuit will require a manual actuation which will be unsuccessful. The crew will transition to E-2 to isolate SG. The crew will then transition to ECA-2.1 when steam lines will not isolate. The scenario will terminate when the crew has Reset SI for ECCS Flow Reduction steps.

Critical Tasks Stabilize SG Level on MFC140 Failure Throttle AFW prior to PTS concern Procedures E-0, Reactor Trip or Safety Injection E-2, Faulted Steam Generator Isolation ECA-2.1 Uncontrolled Depressurization of All Steam Generators Page 2 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 1 Event

Description:

Place Main Feedwater Pump in Service Time Position Applicants Actions or Behavior US Directs actions of 1-OHP-4021-055-003, Placing a Main Feed Pump in Service Attachment 4, West Feed Pump Startup As Second Feed Pump.

BOP External comms are included on Scenario Instructor Action Sheet at back Performs the following to place the MFP in Service as directed from step 4.6:

Raises speed in Speed Control by selecting a higher value

When speed is ~ 3850 to 4200 rpm inform US T.S. 3.3.2 Condition H may be exited.

Verify operation of shaft driven oil pump - Stop the Aux Oil pump and place in Auto (Check oil pressures stable on HMI and Annunciator 115 drop 81 (West FPT AC Aux Oil Pp Running - NOT Lit)

Check lube oil and bearing temps on recorder within limits

Place pump in DP Control

1. Raise speed until West MFP is feeding S/Gs

2. Press West DP Control Pushbutton on HMI

3. Verify Load Sharing Active light lit

Enable Auto bias operation

1. Verify Auto Bias is selected

2. Observe Loadsharing adjusts Bias value and both MFP speeds until suction flows are matched

When FPT Control Valve < 30% open close 1-HPD-104W

If desired, realign seal water by stopping Seal water pump and place it in auto US/BOP Notify chemistry of FW Pump configuration change.

Page 3 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: __2___

Event

Description:

Loop #4 Tc Fails high.

Time Position Applicants Actions or Behavior RO Recognizes and reports annunciators on Panel 111 which are indicative of a RTD instrument failure (Drops 14, 15).

RO Reports malfunction and performs the immediate actions of OHP-4022-IFR-001, Instrument Failure Response:

Identifies failure of Loop #4 RTD

Ensures control rods are in manual with no rod motion

Places Pressurizer level control in Manual US / CREW Performs plant stability checks. (Order not important)

RO

1. Rx Power

2. RCS Temp

3. RCS Pressure

4. Pressurizer level

5. AFD BOP

1. Turbine Load

2. SG Level

3. MFP DP US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.

Page 4 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: __2___

Event

Description:

Loop #4 Tc Fails high.

RO For a PRZ Level Instrument OR Control System Issue perform the following:

a. Place PRZ Level control in Manual using one of the following AND restore PRZ Level to Program Level:

PRZ Level Master Controller

-OR-

1-QRV-251, CCP Discharge Flow Controller

b. Establish manual control band For Unexpected Control Rod Motion perform the following:

a. Check Load Rejection OR Runback - NOT IN PROGRESS

b. Check Rod Control in manual : Place Rod Control in manual and verify rod motion has stopped

c. Establish manual temperature control band

d. IF Unexpected Rod Motion Occurred, THEN transition to

e. 1-OHP-4022-012-003, Continuous Control Bank Movement.

US Enters and directs actions of 1-OHP-4022-012-003, Continuous Control Bank Movement procedure.

Check Rod Control

1) Check Rod position above RIL

2) Check AFD within target

Check Power Range Channels - Operable

Restore Equilibrium Conditions

Check for Instrument Malfunction

1) Check MPC-253 Operable

2) Check Tave Channels - Operable (NO)

US Enters and directs actions of 1-OHP-4022-013-007, RCS RTD Instrument Malfunction procedure.

Page 5 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: __2___

Event

Description:

Loop #4 Tc Fails high.

RO / BOP Performs the following as directed:

Verify Control Rods - MANUAL

Check for Failed Temperature Channel

Align following switches:

Tavg Defeat to loop4

Delta T Defeat to loop 4

Delta T Recorder to loop 1, 2, or 3

OPDT Recorder to loop 1, 2, or 3

OTDT Recorder to loop 1, 2, or 3

Check PZR Level Control in Auto (No)

Place 1-QRV-251 CCP Discharge Flow Control in Auto as follows:

a. Verify PRZ Level Master Controller in Manual

1) Adjust PRZ Level Master Controller to null 1-QRV-251 Controller

2) Place 1-QRV-251 in Auto

PRZ Level Control (Master Controller) in Auto as follows

a. Verify 1-QRV-251, CCP Discharge Flow Control in Auto

b. Verify PRZ Level at programmed level AND stable

c. Place PRZ Level Master Controller in Auto.

Page 6 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: __2___

Event

Description:

Loop #4 Tc Fails high.

RO / BOP Recover Rods to restore Tave and Flux US Refers to the following Tech Specs (TS):

TS 3.3.1 RTS Instrumentation (Table 3.3.1-1)

Condition A - Refer to Table Function 6 Condition D - Trip Bi-stables in 6 Hours Function 7 Condition D - Trip Bi-stables in 6 Hours TS 3.3.2 ESFAS Instrumentation (Table 3.3.2-1)

Condition A - Refer to Table Function 4e Condition D - Place channel in trip in 6 Hours Function 8c Condition D - Place channel in trip in 6 Hours o TRM 8.7.14 (PPC) Derived Reactor Thermal Power (MODE 1 greater than 3250 MWt power)

US Initiates actions to trip Bi-stables associated with 1-NPP-151 PZR Pressure Failure per Attachment A of 1-OHP-4022-013-009.

Initiates corrective action for failed channel US a. Notifies Shift Manager

b. Asks SM to make notifications including Work Control When failed instrument has been removed from service or at Lead Evaluators discretion commence the next event Page 7 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 3 Event

Description:

Raise Turbine and Reactor Power Time Position Applicants Actions or Behavior RO Calculates the dilution required per OHP-4021-005-002, Attachment 9, Boration or Dilution Volume Determination.

RO Briefs crew on reactivity plan for power escalation.

US Reviews / concurs with reactivity plan.

US Directs RO to commence Power Escalation in accordance with OHP-4021-001-006, Power Escalation (at step 4.74)

RO Performs DILUTION (batch add OR Continuous):

Place RC Makeup Blend control switch in STOP

Place RC Makeup Blend Control Mode switch in DILUTE or ALT DILUTE

Adjust PW to the desired flow rate and/or amount.

May close QRV-451 if aligning to CCP Suction Only

Place RC Makeup Blend control switch in START

May take QRV-303 to Manual and Open as required to maintain VCT Level and Pressure.

RO Commences escalation:

Raises turbine load (reactor power) using the DCS HMI.

1. Selects Load Target and Ramp Rate on MT HMI

2. Selects GO

Maintains Tavg/Tref deviation within limits (+/- 2F or as designated by US) by dilution and turbine load adjustments.

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

Page 8 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 3 Event

Description:

Raise Turbine and Reactor Power Time Position Applicants Actions or Behavior RO RO verifies appropriate reactivity feedback.

o RCS Temp rise o Steam Dump Demand signal increase o Reactor Delta T Power indication rise o Reactor Delta Flux becoming more positive BOP Acts as peer checker for RO during blender operations.

Page 9 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 4 Event

Description:

14 SG Controlling Steam Flow Channel MFC-140 Fails Low Time Position Applicant's Actions or Behavior BOP Recognizes and reports annunciators on Panel #114 (Drops 33, 42,

43) which are indicative of a steam flow instrument failure.

BOP Reports instrument malfunction and performs the immediate actions Critical of OHP-4022-IFR-001, Instrument Failure Response:

Task #1 Determine SG 4 level is lowering and that its Feedwater Regulating Manually Valve (FRV-240) is not responding as expected.

Control

Notify US and takes manual control of FRV-240.

SG#14 Level on MFC-140

Determine failure affects MFPs, and take P controller to Failure MANUAL or may go to Speed Control.

Stabilize SG 4 level in manual.

US / CREW Performs plant stability checks. (Order not important)

RO

1. Rx Power

2. RCS Temp

3. RCS Pressure

4. Pressurizer level

5. AFD BOP

1. Turbine Load

2. SG Level

3. MFP DP US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.

BOP

a. Check Steam Generator Narrow Range Level - STABLE OR TRENDING to 44%

Restore Steam Generator Narrow Range Level using Manual control of the appropriate Feedwater Regulating Valve: 1-FRV-240

b. Check Steam Generator PORVs - CLOSED: MRV-243

c. Check MFP Differential Pressure - CONTROLLING AT APPROPRIATE DIFFERENTIAL PRESSURE for CURRENT ACTUAL STEAM FLOW Page 10 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 4 Event

Description:

14 SG Controlling Steam Flow Channel MFC-140 Fails Low Time Position Applicant's Actions or Behavior US Enters and directs actions of 1-OHP-4022-013-014, Steam Flow Instrument Malfunction procedure.

BOP Performs the following actions as directed:

Restores SG 4 level using MANUAL control of FRV-240.

Places MFP P controller in MANUAL and maintains pressure. May place MFP in Speed Control.

Reports MFC-140 has failed low.

Places 1-FS-542C selector switch in channel 2 position.

Nulls and returns FRV-240 controller to AUTO.

Returns MFP P controller to AUTO.

US Refers to the following Tech Specs (TS):

TS 3.3.1 RTS Instrumentation (Table 3.3.1-1)

Condition A - Refer to Table Function 15 Condition D - Trip Bi-stables in 6 Hours TS 3.3.2 ESFAS Instrumentation (Table 3.3.2-1)

Condition A - Refer to Table Function 4e Condition D - Place channel in trip in 6 Hours US Initiates actions to trip bi-stables associated with MFC-140 failure per Attachment D-1 of 1-OHP-4022-013-014 US Initiates corrective action for failed channel

a. Notifies Shift Manager

b. Asks SM to make notifications including Work Control When secondary plant is stable or at Lead Evaluators discretion commence the next event Page 11 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 5 Event

Description:

PZR HTR Transformer Fails (11PHC Fails).

Time Position Applicants Actions or Behavior RO Recognizes and reports annunciators on Panel 108, Drops 46 and 50, indicative of a pressurizer (PRZ) heater power supply failure.

(Breaker T11D9 on Electrical Panel)

RO Reenergizes PRZ control (cycling) group heaters per 1-OHP-4024-108, Drop 50 annunciator response, as follows:

Opens breaker CB11PHC6

Closes breaker CB11PHA6 (Drop 50 clears)

RO Monitors PRZ pressure response and ensures normal PRZ heater operations for PHA supplied heaters.

US Refers to Tech Specs (TS):

TS 3.4.9.b Pressurizer - (Condition B.1) due to a loss of 1 train of pressurizer heaters. Restore B/U heaters to operable within 72 Hours. 11PHC failing results in a loss of the A train of PZR backup Heaters.

US Initiates corrective action for failed channel

a. Shift Manager

b. Asks SM to make notifications including Work Control When the primary plant is stable or at Lead Evaluators discretion commence the next event Page 12 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 6 Event

Description:

Main Steam Stop Valve Comes Off Detent (Open Limit Switch)

Time Position Applicants Actions or Behavior BOP Recognizes and reports annunciator on Panel #113 indicative of a Stop Valve misalignment Drop 6 SG 1 STOP VLV1-MRV-210 ABNORMAL US Directs BOP to review ARP for annunciators and dispatch operator to Investigate.

NOTE Crew may wait for AEO report that valve is off detent before opening BOP Determines Main Steam Stop Valve 1-MRV-210 has come off the open detent.

US Directs BOP to re-open Main Steam Stop Valve 1-MRV-210.

BOP Re-open Main Steam Stop Valve 1-MRV-210 by placing Control Switch to open.

May Refer to 1-OHP-4021-051-003 Removing a SG Stop Valve MMO or MRV from Service.

US May Refer to Technical Specification 3.7.2 Steam Generator Stop Valves (SGSVs)

When the Stop valve is re-opened or at Lead Evaluators discretion commence the next event Page 13 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 7 Event

Description:

Steam Line Break outside Containment (#14 SG) - Auto Steam Line Isolation fails and MSIVs wont close Time Position Applicant's Actions or Behavior RO/BOP Recognize RCS Temp / Pressure lowering. MT Megawatts will lower as well. Reactor Power may rise slightly.

Recognize need for a reactor trip and directs RO/BOP to trip US the reactor and perform the immediate actions of 01-OHP-4023-E-0, Reactor Trip or Safety Injection.

Performs the immediate actions of E-0:

RO/BOP 1. Checks reactor trip - reactor Trip and Bypass breakers Open, all rods < 10 steps, neutron flux lowering

2. Checks turbine trip - MTSV Closed Status Lights Lit

3. Checks power to AC emergency buses - T11A or T11D at least one energized

4. Checks safety injection status - SI Status Light Lit (QMO-225/226 white lights Lit) Required if:

a. PZR Pressure < 1775#

b. CNTMNT Pressure > 1.0#

c. SG Pressure < 500#

d. STM Line DP > 100psid US Ensures immediate actions of E-0 are completed RO/BOP Reviews E-0 Foldout Page Criteria.

US/BOP Identify Main Steamline Isolation is required and has not occurred based on SG pressure < 500psig.

US/BOP Verify MSLI requirement met:

1. Attempts to Manually closes Main Steam Line Isolation (SG Stop) valves

MRV-240 (Faulted SG #14)

MRV-210

MRV-220

MRV-230 Page 14 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 7 Event

Description:

Steam Line Break outside Containment (#14 SG) - Auto Steam Line Isolation fails and MSIVs wont close Time Position Applicant's Actions or Behavior Crew Completes actions of E-0 through step 17 as directed.

Step 5 - Check Main Steamline Isolation NOT required (Steamline pressure > 500 #, flow < 1.42x106 PPH, Containment < 2.8#)

Step 6 -Check CTS NOT required (Containment < 2.8#)

Step 7 - Implement Attachment A while continuing

Step 8 - Check if Ruptured SG is Suspected ( No NR level rising in uncontrolled manner)

Step 9 - Check AFW Pumps running (MDAFPs and TDAFP running)

Step 10 - Check total AFW flow > 240 x 103 PPH Step 11 - Minimize Unnecessary RCS Cooldown (NR level >

13%, control flow to maintain NR level between 13 - 50%)

Step 12 - Check AFW Discharge valves Open or Throttled Step 13 - Check FW Isolation (MFPs tripped, Discharge valves closed, FRVs closed, FW Isolation valves closed)

Step 14 - Check RCS Temperature (RCP not running - RCS Tc 547F)

Step 15 - Check PZR PORVs and Spray Valves Step 16 - Check if RCPs should be Stopped (RCS Pressure <

1300# and 1 CCP or SI pump running)

Step 17 - Check if SG Secondary Boundaries are Intact (No SG Pressure lowering in Uncontrolled manner or completely Depressurized)

Identifies a Faulted SG exists and MSIVs cannot be closed.

US Evaluates Critical Safety Function Status US Announces transition to 01-OHP-4023-E-2, Faulted Steam Generator Isolation, for a SG depressurized (at step 17 of E-0).

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

RO/BOP Check SGSV closed - NO Page 15 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 7 Event

Description:

Steam Line Break outside Containment (#14 SG) - Auto Steam Line Isolation fails and MSIVs wont close Time Position Applicant's Actions or Behavior RO/BOP Check SGSV Dump valves closed RO/BOP Check if Any SG Pressure Boundary is Intact - NO, all lowering in uncontrolled manner US Announces transition to 01-OHP-4023-ECA-2.1, Uncontrolled Depressurization of All Steam Generators (RNO for step 3 of E-2).

US Directs actions of ECA-2.1, Uncontrolled Depressurization of All Steam Generators US/BOP Check Secondary Pressure Boundary

SG Stop Valves - Closed - NO (RNO IF valves can NOT be manually closed, THEN locally close valve(s) or associated isolation valve(s), ONE loop at a time using Attachment A)

Feed Reg Valves and FW Isolations

TDAFP Steam Supply

SG PORVs

Blowdown valves and Sample valves

DRV-407 BOP/RO Manually controls AFW flow to minimize RCS Cooldown Critical Task #2

Check cooldown rate in RCS Cold legs < 100F in any Control AFW 60-minute period - reduce feed flow not less than flow to minimize 25,000 pph to each SG (Step 2 RNO)

RCS cooldown during NOTE uncontrolled A momentary drop below 25,000 pph is acceptable as valves depressurization are throttled to achieve this rate of all SGs US Recognizes the throttling of AFW above will give Red Status to Heat Sink CSFST and may enter FR-H-1 Response To Loss Of Secondary Heat Sink Page 16 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 7 Event

Description:

Steam Line Break outside Containment (#14 SG) - Auto Steam Line Isolation fails and MSIVs wont close Time Position Applicant's Actions or Behavior US Reads CAUTION prior to step 1

If total feed flow is less than 240.x103 pph due to operator action, this procedure should not be performed.

Exits and returns to procedure in effect BOP/RO Check RCS Hot Leg temperatures - Stable or Lowering

Control Feed flow to stabilize temperature US/RO Monitor RCS Boron concentration - Greater than Required

Direct Chemistry to periodically sample the RCS

Refers to OHP-4023-SUP-013 for required boron US/RO Check if RCPs should be stopped

RCS temperature Stable or Rising US/RO Check PORVs and Block Valves US/BOP Checks Secondary Radiation

Resets containment isolation phase A

Directs chemistry to sample all SGs for activity

Check SG PORV Rad. Monitors

Check Secondary Radiation US/RO Check if RHR pumps should be stopped

RCS > 300 psig

Pressure stable or rising

Reset SI

Stop RHR pumps US/RO Check if CTS should be stopped

None running CREW Check RWST level > 30%

Page 17 of 22

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Cook 2020 Scenario No.: NRC2020-3 Event No.: 7 Event

Description:

Steam Line Break outside Containment (#14 SG) - Auto Steam Line Isolation fails and MSIVs wont close Time Position Applicant's Actions or Behavior CREW Check if Accumulators should be Isolated (2 RCS Hot legs <

422.8 F)

Locally restore power to Accumulator Outlet valves

Close Accumulator Outlet valves CREW Check If ECCS Flow Should Be Reduced

Subcooling > 40 F

RCS pressure Stable or Rising

PZR Level > 16%

CREW Reset SI When crew resets SI or at Lead Evaluators direction TERMINATE SCENARIO Page 18 of 22

Critical Task Summary Task Elements Results Cueing:

Panel #114 Drops 42,43, & 33

1

MFC-140 Indication Lowering SAT / UNSAT

FRV-240 closing Manually Control SG#14 Level on Performance Indicators:

MFC-140 Failure

Place FRV-240 in Manual and control SG #14 Level to maintain it 15% - 67% preventing a Reactor Trip.

(May Select MFC-141 as Controlling Channel and Place\Leave FRV-240 In Auto)

Performance Feedback:

SG FW Flow raises (FRV-240 opens)

SG Level Stabilizes and returns to band

2 Cueing: SAT / UNSAT

Indication of uncontrolled depressurization of all Control the AFW SGs flow to minimize

RCS cold leg cooldown rate exceeds 100F per hour RCS cooldown

Valve position and flow rate indication that AFW during uncontrolled continues to be delivered to the faulted SGs at a depressurization of rate in excess of 25,000 pph per SG all SGs Performance Indicators:

Control the AFW flow rate to not less than 25,000 pph per SG in order to minimize the RCS cooldown rate before a severe (ORANGE path) challenge develops to the integrity CSF. A momentary drop below 25,000 pph is acceptable as valves are throttled to achieve this rate.

Performance Feedback:

RCS cooldown stops

Severe (Orange path) challenge to integrity CSF does not develop Page 19 of 22

Scenario Instructor Actions Setup:

1. Reset to IC- 859 MOL; 50% power, 481 MW, 889 ppm, 558.2 F 173 Steps on D

2. Place ALL Pressurizer Heaters In ON

3. Reset control rods and check group step counters.

4. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position.

5. Advance chart recorder paper & clear chart recorder memory.

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

U1_RP07A

7. RP07A, Train A Steamline Isolation fails to AUTO actuate

8. RP07B, Train B Steamline Isolation fails to AUTO actuate U1_RP07B

9. MS22 (B), MSIV MRV-220 MECHANICAL BINDING U1_MS22B

10. MS22 (C), MSIV MRV-230 MECHANICAL BINDING U1_MS22C

11. MS22 (D), MSIV MRV-240 MECHANICAL BINDING U1_MS22D

12. MS22 (A) MSIV MRV-210 MECHANICAL BINDING ON TRG 2 U1_MS04D

13. MS04D TO 20% #14 SG Steamline Break on trg 2 U1_MS22A Page 20 of 22

Scenario Instructor Actions Scenario Events:

EVENT #1 Respond to Fw Pump Bearing pressure request - 16.3 psig Respond as required Close HPD-140W EVENT #2 ICF U1_NTP240 to 650 to fail Loop 4 Tcold High U1_NTP240 EVENT #3 Respond as required to power change notifications and requests EVENT #4 IMF U1_MFC140 to the #14 SG Steam Flow Channel to fail Low over 1 minute U1_MFC140 EVENT #5 IMF U1_ED07B to cause the PZR HTR Transformer Failure (11PHC Fails).

U1_ED07B If contacted as AEO to investigate the PZR HTR Transformer Failure, report back after ~ 2 min. delay that Breaker T11D9 has an OC trip.

EVENT #6 Set the Main Steam Stop Valve to 94% to simulate valve off open detent.

set u1_MSVMRV210 0.94 If contacted as AEO report MRV-210 is open but off the OPEN Detent Page 21 of 22

Scenario Instructor Actions EVENTS #7 Activate trigger 2 to Insert malfunction U1_MS04D, final value 20 (#14 SG Steamline Break downstream of MSIV) ramped over 2 minutes. Insert U1_MS22A, MSIV MRV-210 MECHANICAL BINDING Actvate Trigger 2 Events Perform Local actions after entry into E-0 as requested:

Locally stop U1 Ice Condenser AHUs MRF CHR01 to OFF U1_CHR01

Aux Tour will monitor Spent Fuel Pool Level and Temperatures

Place PACHMAS in service - MRF CHR02 or 03 with 10 min delay.

U1_CHR02 OR U1_CHR03 (both have 10 minute delay built in)

U2 has aligned CR vent for U1 SI, Fan 2-HV-AS-2 is running.

If directed to secure EDG jacket water pumps select OFF then AUTO Remote OFF AUTO U1_EGR03A U1_EGR03A EGR 03A U1_EGR03B U1_EGR03B EGR 03B U1_EGR04A U1_EGR04A EGR 04A U1_EGR04B U1_EGR04B EGR 04B Page 22 of 22

Appendix D Scenario Outline Form ES-D-1 Facility: DC COOK 1 & 2 Scenario No.: NRC2020-5 Op-Test No.: _________

Examiners: ___________________________ Operators: ____________________________

Initial Conditions: 80 % Power .

Turnover: Maintain power stable at 80% following Turbine Valve testing Critical Tasks: Stabilize SG#12 Level following FFC-220 Failure, Manually actuate safety Injection Event Malf. No. Event Event No. Type* Description 1 U1_FFC220 I-BOP Feed Flow Channel Fails low on SG #12

@ 0 over 20 TS sec 2

U1_NI10B I-RO 200 over 1 Power range detector (NI-42) fails high min TS 3

U1_FW05A C-BOP East Main Feed Pump Trip 4 R-RO Stabilize Plant And Recover AFD from FW Pump Trip 5 N-BOP Secure AFW and additional Pumps started from FW Pump Trip 6

U1_RC11A C-RO #11 RCP vibrations, Manual Reactor Trip (E-0) ramps 8-15 7 U1_RC16 Major - Pressurizer Steam Space Rupture on Reactor Trip CREW 8 U1_RP10A C-CREW Auto SI fails U1_RP10B

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NOTE: Blue text indicates changes made to reflect as-administered scenario.

Page 1 of 23

Appendix D Scenario Outline Form ES-D-1 Event Summary The plant is at 80% power and the crew is directed to maintain power at 80%.

The #12 SG Feed Flow instrument (FFC-220) fails LOW. This will result in the opening of

12 SG FWRV (FRV-220) to raise feedwater flow. The BOP will be required to take manual control and regulate FRV-220. The Crew will be required to implement Abnormal Operating Procedure actions to stabilize the plant.

Power range NI detector (N-42) will fail high. The crew will stop rod movement using OHP-4022-IFR-001, transition to Uncontrolled Rod Movement Abnormal Operating Procedure and then to PR NI Abnormal Operating Procedure to remove failed NI from service. The RO will develop a reactivity plan to restore rods, temperature, and flux.

A trip of the East Main Feed Pump will result in a rapid power reduction to less than 60% if not already performed. The BOP will start additional pumps as required and stabilize FW pump speed control.

The RO will be required to monitor reactivity while the BOP monitors the SG levels and secures AFW pumps. Following the turbine runback the RO will develop a reactivity plan to restore Tave and reactor flux to normal values.

The next event will involve elevated vibrations on #11 RCP. The crew will implement Abnormal Operating Procedure actions until vibrations rise to Fold Out Page criteria requiring the RO to manually trip the reactor and the crew will implement OHP-4023-E-0. The crew will complete E-0 IAs and then use the RCP Malfunction Abnormal Operating Procedure to isolate the RCP.

The Major event will begin with a Pressurizer Steam Space Break (Small RCS Leak) upon the reactor Trip. Auto SI will fail to occur requiring crew actuation.

Critical Tasks Stabilize SG#12 Level following FFC-220 Failure Manually actuate safety Injection Procedures E-0 Reactor Trip or Safety Injection E-1 Loss Of Reactor Or Secondary Coolant ES-1.2 Post LOCA Cooldown and Depressurization Page 2 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 1 Event

Description:

Feed Flow Channel (FFC-220) Fails low on SG 2 Time Position Applicants Actions or Behavior BOP Recognizes and reports annunciators on Panel #113

Drop 32, Steam Generator 2 Water LVL HI Deviation

Drop 43, Steam Generator 2 SF > FWF Mismatch BOP Reports instrument malfunction and performs the immediate actions of OHP-4022-IFR-001, Instrument Failure Response:

Critical

Places FRV-220, SG #2 MFW Reg. Valve controller in Task #1 manual Lowers controller output to match the operable feed flow channel with steam flow.

Restores SG #2 level to program.

Performs Stability Checks Crew Performs plant stability checks. (Order not important)

RO

1. Rx Power

2. RCS Temp

3. RCS Pressure

4. Pressurizer level

5. AFD BOP

1. Turbine Load

2. SG Level

3. MFP DP US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.

Page 3 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 1 Event

Description:

Feed Flow Channel (FFC-220) Fails low on SG 2 Time Position Applicants Actions or Behavior BOP For a Steam Generator Pressure OR Level Control OR Main Feed Pump D/P Issue OR any failure that affects these parameters perform the following:

a. Narrow Range Level - STABLE OR TRENDING to 44%

Restore Steam Generator Narrow Range Level using manual control of the appropriate Feedwater Regulating Valve: FRV-220

b. Check Steam Generator PORVs - CLOSED: MRV-223

c. Check MFP Differential Pressure - CONTROLLING AT APPROPRIATE DIFFERENTIAL PRESSURE for CURRENT ACTUAL STEAM FLOW (yes)

US Enters and directs actions of OHP-4022-013-015, Feedwater Flow Instrument Malfunction procedure.

BOP Performs the following actions as directed:

1. Reports FFC-220 has failed low

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

3. Nulls and returns FRV-220 controller to auto.

US Refers to Tech Specs 3.3.1 RTS Instrumentation (Condition A Table 3.3.1-1, Function 15, Condition D. Trip Bi-stables in 6 Hr)

US Initiates corrective action for failed channel

a. Notifies management and WCSRO

b. Directs BOP to generate work request US Notifies SM/MTI to Initiate actions to trip Bi-stables associated with FFC-220 FW Flow Failure per Attachment B-1 of OHP-4022-013-015.

When FRV is in auto or at Lead Evaluators direction commence next event.

Page 4 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 2 Event

Description:

Power Range Channel N42 Control Power fails/ Power Restoration Time Position Applicant's Actions or Behavior RO Recognizes and reports annunciators on Panel 110 which are indicative of a NI instrument failure (Drops 11, 13, 18, & 19).

RO Reports malfunction and performs the immediate actions of OHP-4022-IFR-001, Instrument Failure Response:

Checks for no turbine runback

Ensures control rods are in manual with no rod motion CREW Performs plant stability checks. (Order not important)

RO

1. Rx Power

2. RCS Temp

3. RCS Pressure

4. Pressurizer level

5. AFD BOP

1. Turbine Load

2. SG Level

3. MFP DP US Enters and directs actions of OHP-4022-IFR-001, Instrument Failure Response procedure.

RO For Unexpected Control Rod Motion perform the following:

a. Check Load Rejection OR Runback - NOT IN PROGRESS

b. Check Rod Control in manual : Place Rod Control in manual and verify rod motion has stopped

c. Establish manual temperature control band

d. IF Unexpected Rod Motion Occurred, THEN transition to 1-OHP-4022-012-003, Continuous Control Bank Movement.

US Enters and directs actions of OHP-4022-012-003, Continuous Control Bank Movement procedure.

Page 5 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 2 Event

Description:

Power Range Channel N42 Control Power fails/ Power Restoration Time Position Applicant's Actions or Behavior RO Performs the following as directed:

Checks rod position above low-low rod insertion limit

Checks axial flux difference (AFD) within target band

Identifies failed power range channel

1) Place Rod Stop Bypass Selector in the Failed Channel

2) Verify P-7, P-8, P-10 in correct state RO Develops reactivity plan to restore power and AFD to required conditions.

Initiates restoration of equilibrium conditions (power) using either:

Control rod movement

Turbine load adjustment US Checks for Instrument Failure - N42 US Enters and directs actions of OHP-4022-013-004, Power Range Malfunction procedure.

Page 6 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 2 Event

Description:

Power Range Channel N42 Control Power fails/ Power Restoration Time Position Applicant's Actions or Behavior RO /BOP Performs the following as directed:

Verify Control Rods - MANUAL

Place Rod Stop Bypass Selector In Failed Channel Position

Remove Affected Channel From Service By Placing Selector Switches To Failed Channel Position:

Comparator Channel Defeat Selector

Upper Section Detector Current Comparator Defeat Selector

Lower Section Detector Current Comparator Defeat Selector

Power Mismatch Bypass Selector

Check The Following Interlocks Are In The Required State For Existing Conditions:

P-7 (Not LIT)

P-8 (Not LIT)

P-10 (LIT)

Check AFD - WITHIN TARGET BAND

Verify Recorder Inputs - SELECTED TO AN UNAFFECTED CHANNEL POSITION:

Delta-T

Overtemperature Delta-T Caution - Control Rods should not be placed in automatic until at least 5 minutes have elapsed after placing Power Mismatch Bypass Selector to failed channel.

Place Control Rods In AUTOMATIC If Applicable US Directs actions to trip Bi-stables associated with NI-42 Power Range Malfunction per Attachment D of 1-OHP-4022-013-004.

Page 7 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 2 Event

Description:

Power Range Channel N42 Control Power fails/ Power Restoration Time Position Applicant's Actions or Behavior US Refers to Tech Specs:

3.3.1 RTS Instrumentation (Table 3.3.1-1, Functions 2a,2b, 3, 6 18c&d Conditions A, C, D, & L Place channel in trip - 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months )

P-8 & P-10 must be verified in Correct Condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of channel failure.

o 3.3.2 AFD Only applicable if Rods drive AFD outside of target band Restore AFD to within target band - 15 minutes o 3.2.4 QPTR May be referenced.

US Initiates corrective action for failed channel

a. Notifies Shift Manager

b. Asks SM to make notifications including Work Control When failed NI has been removed from service or at Lead Evaluators direction commence the next event Page 8 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 3 Event

Description:

East Main Feed Pump Trip Time Position Applicants Actions or Behavior BOP Recognizes indication of MFP trip and reports annunciator Panel

115, Drop 1, East FPT DCS Trouble, DCS Screen East FW Pump Tripped Status US Directs operators to perform the immediate actions per OHP-4022-055-001, Loss of One MFP.

RO Performs the following immediate actions:

1. Verify Turbine Load is automatically reduced to < 60%.

Returns MT control to MW Out following runback

2. Verifies rod control switch in AUTO and functioning properly.

BOP Performs the following immediate actions:

1. Close the East FW Pump Emergency Leakoff Valves FRV-251 & 252

2. Adjust West FW Pump speed/integration as required to prevent overfeeding SG

3. Start Standby Hotwell & Condensate Booster Pumps as required [The need to start these pumps is dependent on plant conditions and may be dependent upon if a trip of one of these pumps caused the MFP trip.]

4. Start AFW pumps as required. [At the current power level, start of the AFW pumps is unnecessary.]

US Checks the immediate actions and directs operators to perform the subsequent actions of OHP-4022-055-001, Loss of One MFP.

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

RO Initiate normal or emergency boration flow (if required) to maintain rods above the RIL (~1.89 * % power) using Attachment C or D of OHP-4022-055-001 Page 9 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 3 Event

Description:

East Main Feed Pump Trip Time Position Applicants Actions or Behavior CREW o 3.4.1 RCS Pressure, Temperature, and Flow DNB Limits (Condition A) if Pressure lowers to <2168 psig. (2200 psig admin limit) (may use PPC times to track TS entry/exit times) o 3.3.2 3.2.3 AFD Only applicable if Rods drive AFD outside of target band Restore AFD to within target band - 15 minutes Page 10 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 4,5 Event

Description:

Stabilize Plant And Recover AFD from FW Pump Trip Time Position Applicants Actions or Behavior US Direct operator actions to restore normal system alignment: (as required) OHP-4022-055-001 (Steps 8-16)

Restore AFD to required Band If AFD was outside the acceptable region, THEN transition to OHP-4022-001-006 Rapid Power Reduction, to lower power < 50%, while continuing on with this procedure

Restore Megawatt Control to OUT

Return W MFP to DP control using Attachment A Verify Auto Perm Met light lit Press the DP Target Selector Auto Button

Check ALL PRZ Backup Heaters on

Reset Steam Dump Load Rejection Momentarily place Steam Dump Mode Control switch in RESET

Stop running AFW pumps and align for standby condition (Attachment B)

Complete FW Pump Shutdown

Align Condensate system for current plant conditions RO Borate to position rods to restore AFD to within Target Band (Attachment C or D of OHP-4022-055-001)

BOP Stop AFW Pumps and Place in Standby (Attachment B)

MDAFPs - close FMOs, turn pumps off, open FMOs TDAFP - close FMOs Trip pump, throttle FMOs to required position (requires report from field), close Trip and Throttle valve to relatch, Stabilize West FW pump speed and restore required DP When secondary plant is stable or at Lead Evaluators direction commence the next event Page 11 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 6 Event

Description:

11 RCP vibrations that require a manual Reactor Trip Time Position Applicants Actions or Behavior RO Recognizes indication of RCP vibes and reports Annunciator Panel 107

Drop 52 RCP VIBRATION HIGH US Enters OHP-4022-002-001, Malfunction of a Reactor Coolant Pump

1. Checks for RCP Trip Criteria

a. Complete Loss of RCP Seal Cooling

b. #1 Seal leakoff temp > 185°F and a loss of seal injection

c. #1 Seal leakoff temp > 200°F coincident with low seal leakoff flow or lowering seal injection or rising bearing temp

d. Lower Bearing Water temp > 225°F with rising seal leakoff temps

e. Upper RCP MTR bearing temp > 200°F with low oil level alarm

f. RCP vibration > 20 mils Reports #11 RCP vibes are 15 mils and rising BOP US / RO Check RCP conditions:

RCP Seal Leakoff normal

RCP Seal Injection normal

VCT Temp normal Page 12 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 6 Event

Description:

11 RCP vibrations that require a manual Reactor Trip Time Position Applicants Actions or Behavior BOP Reports #11 RCP vibes have reached 20 mils and FOP criteria requires going to step 15.a Reactor Trip US Performs Step 15 RNO and directs RO to Trip the Reactor Page 13 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 7/8 Event

Description:

Pressurizer Steam Space Rupture, Auto SI Failure Time Position Applicant's Actions or Behavior US Recognize need for a reactor trip and directs RO/BOP to trip the reactor and perform the immediate actions of 01-OHP-4023-E-0, Reactor Trip or Safety Injection.

RO Performs the immediate actions of OHP-4022-002-001 Step 15 RNO:

Verifies reactor trip- reactor Trip and Bypass breakers Open, all rods < 10 steps, neutron flux lowering

Stop RCP # 11 RO/BOP Performs the immediate actions of E-0:

1. Checks reactor trip - reactor Trip and Bypass breakers Open, all rods < 10 steps, neutron flux lowering

2. Checks turbine trip - MTSV Closed Status Lights Lit

3. Checks power to AC emergency buses - T11A or T11D at least one energized

4. Checks safety injection status - SI Status Light Lit (QMO-225/226 white lights Lit) Required if:

a. PZR Pressure < 1775#

b. CNTMNT Pressure > 1.0#

c. SG Pressure < 500#

d. STM Line DP > 100psid RO/BOP Reviews E-0 Foldout Page Criteria.

RO Receives Alarms on Panel 104 Drop 41, 105 Drops 31 / 32 due to Containment Temperature and Pressure Recognize and reports abnormal RCS leakage:

RCS pressure lowering with PZR Heaters ON.

Rising Containment dew point, pressure, and radiation.

Page 14 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 7/8 Event

Description:

Pressurizer Steam Space Rupture, Auto SI Failure Time Position Applicant's Actions or Behavior CREW Check SI Actuated Critical

Safety Injection Actuated Status Light - NOT LIT Task #2

Identifies That BOTH CCP leakoff valve "Safety Injection Signal" white lights - NOT LIT Determines that SI is Required due to Pressurizer Pressure Lowering and Containment Pressure Rising Manually Actuate Safety Injection to establish High Head Injection Flowpath

-OR-NOTE: May be performed in E-0, Attachment A.

Manually Start SI and CCP pumps Manually Align Valves

BIT Inlet Valves ICM-255 -AND/OR ICM-256 - OPEN

BIT Outlet Valves ICM-250 -AND/OR ICM-251 - OPEN

RWST to CCP Valves IMO-910 -AND/OR IMO-911 - OPEN

VCT to CCP Valves QMO-451 -AND/OR QMO-452 - CLOSED US Ensures immediate actions of OHP-4023-E-0 are completed Directs subsequent actions of OHP-4023-E-0.

US/RO Foldout Page - RCP Trip Criteria:

Stop all RCPs when RCS is < 1300 psig and CCP/SI pump running BOP Manually controls AFW flow > 240,00 to < 450,000pph to maintain SG narrow range levels 13% - 50% once one SG narrow range level is greater than 13%.

Page 15 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 7/8 Event

Description:

Pressurizer Steam Space Rupture, Auto SI Failure Time Position Applicant's Actions or Behavior RO/BOP Completes actions of E-0 through step 19 as directed.

Step 5 - Check Main Steamline Isolation NOT required (Steamline pressure > 500 #, flow < 1.42x106 PPH, Containment < 2.8#)

Step 6 -Check CTS NOT required (Containment < 2.8#)

Step 7 - Implement Attachment A while continuing

Step 8 - Check if Ruptured SG is Suspected (No NR level rising in uncontrolled manner)

Step 9 - Check AFW Pumps running (MDAFPs and TDAFP running)

Step 10 - Check total AFW flow > 240 x 103 PPH Step 11 - Minimize Unnecessary RCS Cooldown (NR level > 13%,

control flow to maintain NR level between 13 - 50%)

Step 12 - Check AFW Discharge valves Open or Throttled Step 13 - Check FW Isolation (MFPs tripped, Discharge valves closed, FRVs closed, FW Isolation valves closed)

Step 14 - Check RCS Temperature (RCP running - RCS Tavg 547F)

Step 15 - Check PZR PORVs and Spray Valves Step 16 - Check if RCPs should be Stopped (RCS Pressure <

1300# and 1 CCP or SI pump running)

Step 17 - Check if SG Secondary Boundaries are Intact (No SG Pressure lowering in Uncontrolled manner or completely Depressurized)

Step 18 - Check if SG Tubes are Intact (NO NR level Rising in uncontrolled manner, secondary rad monitors normal)

Step 19 - Check if RCS is Intact (CNTMNT Radiation, Pressure, Water Levels Normal)

RO/BOP Performs manual actions of OHP-4023-E-0, Attachment A as directed by US.

US/RO Checks if RCS is Intact - NO US Evaluates Critical Safety Function Status US Announces transition to OHP-4023-E-1, Loss of Reactor or Secondary Coolant and directs operator actions. Directs Fold Out Page Review Page 16 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 7/8 Event

Description:

Pressurizer Steam Space Rupture, Auto SI Failure Time Position Applicant's Actions or Behavior RO/BOP Completes actions of OHP-4023-E-1 through step 12 (Check if RCS Cooldown and Depressurization is required) as directed.

1. Check if RCPs should be stopped - RCS Pressure< 1300#

2. Check if SG Secondary Pressure Boundaries are Intact - No pressure lowering in uncontrolled manner or completely depressurized

3. Check intact SG levels - NR level > 13%

4. Check Secondary Radiation - Rest Phase A and direct Chemistry to sample SGs for activity

5. Check PZR PORVs and Block valve - Block valves energized and at least one open, PORVs closed

6. Check if ECCS flow should be reduced - RCS subcooling >

40F, Secondary Heat Sink, RCS Pressure stable or rising, and PZR level > 16% - Go to ES-1.1 See page 19

7. Check if CTS should be stopped - CTS running, RCS Pressure > 300#, Containment Pressure < 2.0#

8. Check if RHR pumps should be stopped - RCS Pressure >

300#, RCS Pressure stable or rising, RHR pump running aligned to RWST

9. Check RCS and SG Pressures - Pressure in all SGs Stable or rising, RCS Pressure Stable or Lowering

10. Check if EDGs should be stopped - Emergency busses Energized by Off-Site

11. Initiate evaluation of plant status - check Cold Leg Recir Capability

12. Check if RCS Cooldown and Depressurization is required -

RCS Pressure > 300#

BOP Restore SG narrow range levels >20%, but < 50%.

US/RO Checks if SI Termination Criteria is MET:

RCS Subcooling >40°F Secondary Heat Sink (SG >13% or AFW Flow >240x103)

RCS Pressure rising or stable - NO (May be Rising See next Step)

Pressurizer Level >16%

Page 17 of 23

Appendix D Required Operator Actions Form ES-D-1 Op-Test No: Cook 2020 Scenario No.: NRC2020-5 Event No: 7/8 Event

Description:

Pressurizer Steam Space Rupture, Auto SI Failure Time Position Applicant's Actions or Behavior Crew Transition to OHP-4023-ES-1.1, Safety Injection Termination if criteria is met.

OHP-4023-ES-1.1 Actions are listed on Page 19.

US/RO Check if RHR can be stopped:

Check RCS Pressure > 300 psig and stable

Reset SI

Shutdown RHR and place in Standby BOP Shutdown Unloaded EDGs.

US Announces transition to OHP-4023-ES-1.2, Post LOCA Cooldown and Depressurization (at step 12).

CREW Check if transition is made to OHP-4023-ES-1.2, then perform the following:

Reset SI

Reset Containment Isolation:

Establish Control Air To Containment When transition is made or at Lead Evaluators direction TERMINATE SCENARIO Page 18 of 23

Appendix D Required Operator Actions Form ES-D-1 ES-1.1 Steps Note:

Crew may transition to SI termination if criteria are met. This may involve stopping ECCS pumps and realigning charging until parameters change causing them to restart equipment and return to E-1 or ES-1.2. There are several points of transition to ES-1.2 from ES-1.1. The ES-1.1 Steps are listed below. The Scenario may be terminated upon transition to ES-1.2 US Announces transition to OHP-4023-ES-1.1, Safety Injection Termination (step 6 of OHP-4023-E-1).

RO/BOP Reviews OHP-4023-ES-1.1, Foldout Page Criteria.

Monitors RCS Subcooling >40°F and PZR Level >16%, if NOT realign ECCS and GO TO OHP-4023-E-1 US Directs Actions of OHP-4023-ES-1.1 RO/BOP Performs the following as directed:

Resets both trains of Safety Injection

Resets both trains of Phase A

Establishes Control Air to Containment CREW Check if RCS Pressure is stable or Rising If Lowering, Transition to OHP-4023-ES-1.2 RO/BOP Performs the following as directed:

Establish Normal Charging Flowpath

Isolate BIT Injection CREW Check if:

Pressurizer Level is stable and RCS Pressure is Stable or Rising If NOT, Transition to OHP-4023-ES-1.2 CREW Check if transition is made to OHP-4023-ES-1.2, then perform the following:

Reset SI Reset Containment Isolation:

Establish Control Air To Containment When transition is made or at Lead Evaluators direction TERMINATE SCENARIO Page 19 of 23

Appendix D Critical Task Summary Form ES-D-1 Task Elements Results Cueing: SAT / UNSAT

Panel #113 Drops 43 & 32

1

FFC-220 Indication Lowering

FRV-220 opening Manually Control SG#12 Level on Performance Indicators:

FFC-220 Failure

Place FRV-220 in Manual and control SG #12 Level to maintain it 15% - 67% preventing a Reactor Trip.

(May Select FFC-221 as Controlling Channel and Place\Leave FRV-220 In Auto)

Performance Feedback:

SG FW Flow raises (FRV-220 opens)

SG Level Stabilizes and returns to band

2 Cueing: SAT / UNSAT

Pressurizer Pressure < 1775 psig Manually Actuate

Pressurizer Pressure Extreme Low PNL 108 Drop Safety Injection 10

Check SI Actuated Safety Injection Actuated Status Light - NOT LIT (E-0, Step 4.a)

-AND-

Check BOTH CCP leakoff valve "Safety Injection Signal" white lights - NOT LIT Performance Indicators:

Before transitioning from E-0:

Actuate 1 Train of SI by turning the SI actuation Switch on PZR Panel or SI Panel Performance Feedback:

ECCS flow is indicated from at least one train (as indicated by flow on cold leg BIT injection flowmeters IFI-51 thru 54)

One Train of Phase A Isolation is complete per E-0, Attachment A Page 20 of 23

Scenario Instructor Actions Setup:

1. Reset to IC-303 MOL; 79% power, 850 MW, 799.86 ppm, 565.51 F 194 Steps on D

2. Place ALL Pressurizer Heaters In ON

3. Reset control rods and check group step counters.

4. Place Master Annunciator Silence pushbutton lockout ring in LOCKOUT position.

5. Advance chart recorder paper & clear chart recorder memory.

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

Train A Safety Injection Auto Failure U1_RP10A Train B Safety Injection Auto Failure U1_RP10B Set Reactor Trip on ET1 Reactor Trip on ET1 U1_RC16 Page 21 of 23

Scenario Instructor Actions Scenario Events:

EVENT #1 ICF U1_FFC220 to 0 over 120 Seconds to cause Feed Flow Channel FFC-220 to fail low on SG 2 U1_FFC220 EVENT #2 IMF U1 NI10B to cause a NI42 Power Range to fail High U1_NI10B EVENT #3 IMF U1_FW05A to cause the East Main Feed Pump Trip U1_FW05A EVENT #4 No additional Actions EVENT #5 No additional Actions EVENT #6 IMF U1_RC11A ramp from 8-15 to cause RCP #1 Vibration Rise U1_RC11A Page 22 of 23

Scenario Instructor Actions EVENTS #7& 8 IMF RC16 to cause a Pressurizer Steam Space Break (Auto SI Failure already entered)

U1_RC16 Perform Local actions after entry into E-0 as requested:

Locally stop U1 Ice Condenser AHUs MRF CHR01 to OFF U1_CHR01

Aux Tour will monitor Spent Fuel Pool Level and Temperatures

Place PACHMAS in service - MRF CHR02 or 03 with 10 min delay.

U1_CHR02 OR U1_CHR03 (both have 10 minute delay built in)

U2 has aligned CR vent for U1 SI, Fan 2-HV-AS-2 is running.

If directed to secure EDG jacket water pumps select OFF then AUTO Remote OFF AUTO U1_EGR03A U1_EGR03A EGR 03A U1_EGR03B U1_EGR03B EGR 03B U1_EGR04A U1_EGR04A EGR 04A U1_EGR04B U1_EGR04B EGR 04B Page 23 of 23

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