ML23038A140

Scenarios

ML23038A140
Person / Time
Site:	Perry
Issue date:	01/12/2023
From:	NRC/RGN-III/DORS/OB
To:
Greg Roach
Shared Package
ML21188A238	List: ML23038A137 ML23038A138 ML23038A139 ML23038A140 ML23038A141 ML23038A142
References
Download: ML23038A140 (85)

Text

ES-3.3, Page 16 of 17 Form 3.3-1 Scenario Outline Facility:

Perry Scenario #:

1. 1 - 100% Power Scenario Source:

New Op. Test #:

2022-1 Examiners:

Applicants/

Operators:

Initial Conditions: Plant is at 100% power. Main Generator was placed on the Manual Voltage Regulator yesterday for repair of the Auto Voltage Regulator. Maintenance is now complete on the Auto Voltage Regulator.

Containment Spray valve 1E12-F537A is tagged out for MOVATS testing. HPCS Pump, 1E22-C001 tagged out for seal leak repair. Stator Water Cooling pump B 1N43-C001B is tagged out for motor replacement. Hydrogen Analyzer B is tagged out for inlet cooling valve replacement. SCC will request a power reduction later this shift.

eSOMS Narrative Log is down. PSA Risk is Green and the Grid Risk is Normal.

Turnover / Planned Activities: Shift main generator from Manual Voltage Regulator to Auto Voltage Regulator then lower power to meet SCC request IAW reactivity plan and IOI-3 when contacted by SCC. Make any Narrative Log entries on your note pads.

Critical Tasks:

1. Isolate Secondary Containment leak

2. Anticipate ED or ED to allow LP systems to inject Event No.

Malf.

No.

Event Type*

Event Description 1

N-BOP/SRO Shift Main Generator to Auto Voltage Regulator 2

R-ATC/SRO Extraction Steam isolated to FW Heater #6A Enter ONI-N36 3

C-ATC/SRO Condensate Booster Pump A trips 4

I-BOP/SRO TS - SRO MC-BOP RCIC Suppression Pool Level instrument fails high 5

C-BOP/SRO TS - SRO MC-BOP Leak in RWCU pump room Enter EOP-03 6

M-All Loss of Feedwater 7

C-ATC MC-ATC RPS fails in AUTO and MANUAL. ARI works in MANUAL or AUTO Enter EOP-01 8

C-ATC MC-ATC Generator Field Breaker fails to auto open 9

M-All Loss of High-Pressure Injection - Anticipate Emergency Depressurization 10 M-All (Conditional) ED if unable to maintain RPV level > -25 with LPCS (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Page 1 of 19 Event

Description:

N/A - Driver Instructions Time Position Applicants Actions or Behavior Driver Driver Simulator Setup:

Reset Simulator to IC 151 Load Schedule File: 2022 Scen-1.sch Verify Schedule File NRC 2022 H2 Analyzers.sch loads Verify Event File: NRC 2022 Scen-1.evt loads Remove Requal IOI-3 and Rod Book from horseshoe.

Place STAR marker on Manual Voltage Regulator In Director, if necessary, toggle Override ZL1M51HS1B-GRN to OFF If P845-B1 alarm in, insert malfunction 1H13P8451AB1 to ALARM OFF Driver Driver Verify Initial Conditions:

Reactor Power 100%. MOC_STARTUP_TRAINING_SEQ Pull Sheets, Rods @

Step 67.

Verify APRM gains are adjusted Place yellow switch cap on:

• HPCS Pump & Injection valve

• 1N43-C001B

• H2 Analyzer B SYSTEM FUNCTION SWITCH

• 1E12-F537A Green Risk.

Driver Driver Initial Conditions:

Plant is at 100% power. Main Generator was placed on the Manual Voltage Regulator yesterday for repair of the Auto Voltage Regulator. Maintenance is now complete on the Auto Voltage Regulator. Stator Water Cooling Pump B, N43-C001B is tagged out for bearing replacement. The M29 Control Room Humidification Boiler is tagged out for leak repair. HPCS Pump, 1E22-C001 is tagged out for seal leak repair (Two days into the LCO). Hydrogen Analyzer B was tagged out yesterday for inlet cooling valve replacement (One day into the LCO).

CNTMT SPRAY SECOND SHUTOFF, 1E12-F537A is tagged out for MOVATS testing (Twelve hours into the LCO). SCC will request a power reduction later this shift. eSOMS Narrative Log is down. PSA Risk is Green and the Grid Risk is Normal.

Turnover: Planned activities; Shift main generator from Manual Voltage Regulator to Auto Voltage Regulator.

When contacted by SCC, lower power to meet SCC request IAW reactivity plan and IOI-3. Make any Narrative Log entries on your note pads. Perform Prejob Briefs and Reactivity Briefs prior to entering the Simulator.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.:

1 Page 2 of 19 Event

Description:

1

- Shift Main Generator to Auto Voltage Regulator Symptoms/Cue: From Turnover Time Position Applicants Actions or Behavior Driver Role play as SCC as directed.

Shift Mgr If crew determines that the AUTO voltage regulator is not responding, direct crew to continue going to RAISE on the AUTO voltage regulator.

SRO Direct BOP to transfer Main Generator to AUTO Voltage Regulator BOP Perform SOI-N32, Main Turbine Generator And Turning Gear System and transfer to the Auto Voltage Regulator.

7.26 Transfer from the Manual Voltage Regulator to the Auto Voltage Regulator 7.26.1 ADJUST the AUTO. VOLT. ADJUST to achieve 0 volts on the REG TRANSFER DIFF VOLTS.

7.26.2 PLACE the VOLTAGE REGULATOR in AUTO.

7.26.3 MAINTAIN the desired output voltage using the AUTO. VOLT.

ADJUST.

7.26.4 NOTIFY the S.C.C. Generation Dispatcher of shifting to Automatic Voltage Regulation.

7.26.5 RECORD shifting to Automatic Voltage Regulation in the Plant Narrative log.

BOP Inform SRO when voltage regulator transfer is complete.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.:

2 Page 3 of 19 Event

Description:

2

- Extraction Steam isolated to FW Heater #6A Enter ONI-N36 Symptoms/Cue: ARI-H13-P870-05-E1 Time Position Applicants Actions or Behavior Driver

• When directed, insert Event 2.

• Role play as directed.

• If directed to manually open Heater 6A Drain to Cndr 1N25-F280A, then in 1/2 hour report the valve has been manually opened

• If asked to look at HEATER 6A DRN TO HTR 5A, 1N25-F290A locally, after appropriate time, respond that it looks like it is sticking.

• If directed (as I&C) to pull trip units C71-N652AD, IAW ONI-N36 Step 2.0, wait 4 minutes them report trip units pulled.

ATC Announce unexpected alarms and give stability report.

BOP Announce HTR 6A EXST & INLET DRAINS ISOL LEVEL HIGH alarm.

Walkdown H13-P870 and determine and announce 6A FW Heater is isolating/has isolated.

Report ONI-N36 entry condition.

Evaluator Some automatic #6 FW Heater valves reposition during and after this event. The crew may reposition the valves to the Automatic Actions position of the ARI.

SRO Announce entry into ONI-N36, Loss of Feedwater Heating ATC Perform ONI-N36 Immediate Action - Lower Rx power 96% using Recirc Flow.

(<3608 MWt)

Evaluator Power reduction should be immediate and performed without direction from the SRO. Depending on timing of action to lower Rx power, may get Turbine Bypass Valve open.

SRO Announce entry into ONI-C51, Unplanned Change in Rx Power or Reactivity and obtain ONI-C51 Flow Chart BOP Monitor the remaining FW heaters for proper operation.

SRO Direct ATC and BOP to perform Supplemental Actions in ONI-N36 and Subsequent Operator Actions for ARI H13-P870-05A-E1 BOP Verify that the valves identified in ARI H13-P870-5A-E1 have automatically repositioned. Perform ARI Subsequent Operator Actions when directed by the SRO SRO Direct ONI-C51 flow chart Actions:

Direct ATC to monitor nuclear instrumentation for oscillations and Scram the Rx if any occur (Step C51-4)

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.:

2 Page 4 of 19 Event

Description:

2

- Extraction Steam isolated to FW Heater #6A Enter ONI-N36 Symptoms/Cue: ARI-H13-P870-05-E1 Time Position Applicants Actions or Behavior ATC Monitor nuclear instrumentation for oscillations and Scram the Rx if any occur SRO Direct BOP to perform ONI-SPI-G4 Power Verification. (ONI-C51-flow chart Step C51-5)

BOP Perform ONI-SPI G4, Power Verification.

SRO Direct ATC to confirm jet pump operation within established limits. (ONI-C51 flow chart Step C51-15)

ATC Confirm jet pump operation within established limits by observing ICS Jet Pump Screen and report to SRO SRO Continue working through ONI-C51 Flow Chart to EXIT boxes.

Evaluator SRO may refer to Tech Specs based on ONI-N36 Attachment 3. However, at the current power level and plant conditions, all LCOs are being met.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.:

3 Page 5 of 19 Event

Description:

3

- Condensate Booster Pump A trips Symptoms/Cue: ARI-H13-P680-02-D6 & A6 Time Position Applicants Actions or Behavior Driver

• When directed, insert Event 3.

• Role play as NLO as directed.

• If asked to investigate CBP A pump, report that the motor is hot to the touch.

• If asked to investigate CBP A breaker, H1103, report that the Overcurrent relay is tripped.

• If requested to respond as NLO to Condensate Filter System - High Differential Pressure alarm - reset on Acknowledgement (Use Extreme View to acknowledge local alarms)

Evaluator ATC has approximately 3.5 minutes before HST level lowers to 60. Starting the 2nd Condensate Booster pump will stop level lowering and restore HST level.

ATC Announce unexpected alarms and give stability report.

Observe alarms, CBP breaker status lights, and discharge pressure meters on P680 and determines CBP A has tripped.

Informs crew of CBP A trip.

SRO Direct ATC to perform ARI Subsequent Actions if ATC not doing so.

ATC Refers to ARI-H13-P680-02-A6 and starts standby CBP IAW Subsequent Actions:

4.1 IF the turbine has NOT tripped, THEN start the standby CBP, 1N21-C002C 4.2 MONITOR HOT SURGE TANK LEVEL & CNDS TO HTR 4 FLOW.

1N21-R323 4.3 IF required, THEN REDUCE reactor power to stabilize Hot Surge Tank level. 1N21-R323 4.4 MAINTAIN motor current <353 amps. (1N21-C001B & 1N21-C001C)

ATC Inform SRO that CBP C was started and HST level is recovering.

BOP Direct NLOs to investigate CBP trip and local condensate filter alarms.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.:

4 Page 6 of 19 Event

Description:

4

- RCIC Suppression Pool Level instrument fails high Symptoms/Cue: ARI-H13-P601-21-G5 Time Position Applicants Actions or Behavior Driver Prior to inserting Event 4, place picture of E51-N636A & E on P629 Driver

• When directed, insert Event 4.

• If requested report as I&C Tech that I&C will begin preparing a work package to investigate.

ATC Announce unexpected alarms and give stability report.

Evaluator NOP-OP-1002, Conduct Of Operations, Section 4.10.3 step 5 states If automatic actions fail to occur when required, it is the responsibility of the operator to take manual actions to perform the system or component function. Pump or component auto start failures are examples where operators are expected to take manual action.

BOP Announce RCIC SUPR POOL SUCT VLV OPEN SUPR PL LVL HI alarm.

Walkdown H13-P601 and determine that RCIC PUMP SUPR PL SUCT ISOL, 1E51-F031, is opening but RCIC PUMP CST SUCTION VALVE, 1E51-F010, did not close.

Announces that Immediate Actions did not occur and closes 1E51-F010.

Verifies that 1E51-F010 closes.

BOP Inform SRO that 1E51-F010 is closed.

Evaluator 1E51-F010 gets a close signal from the open limit switch of the 1E51-F031 valve.

BOP Observes Suppression Pool level indications and reports that levels are within normal band.

SRO Direct BOP to investigate back panels for indication of Suppression Pool level indication problem.

BOP Investigates back panels and informs SRO that 1E51-N636A is pegged high, is tripped and has a gross fail light illuminated on panel P629.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.:

4 Page 7 of 19 Event

Description:

4

- RCIC Suppression Pool Level instrument fails high Symptoms/Cue: ARI-H13-P601-21-G5 Time Position Applicants Actions or Behavior SRO Evaluate Technical Specifications TS 3.3.5.3 Action A.1 - Enter the Condition referenced in Table 3.3.5.3 Immediately (Identifies Table 3.3.5.3-1 Function 4 is applicable)

D.2.1 - Place channel in trip - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OR D2.2 - Align RCIC pump suction to the suppression pool - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Evaluator TS 3.3.5.3 Action D.1 not required since RCIC suction is on Suppression Pool.

TS 3.3.5.3 Action D.2.2 requirements are already met since RCIC pump is now aligned to Suppression Pool.

Driver At end of the scenario, remove picture of E51-N636A & E from P629

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.:

5 Page 8 of 19 Event

Description:

5

- Leak in RWCU pump room Enter EOP-03 Symptoms/Cue: ARI-H13-P680-01-B4, C4, D4, D5, & C5 and ARI-H13-P601-18-A3 Time Position Applicants Actions or Behavior Driver

• When directed, insert Event 5.

• Role play as NLO as directed.

Evaluator It takes approximately 2 minutes for first alarm to come in after event is initiated.

It is not anticipated that the crew will enter EOP-01. The leakage from RWCU is isolable from the control room.

ATC Announce unexpected alarms and give stability report.

BOP Walkdown back panel H13-P632 / P642 and informs crew that RWCU Pump A Room temperature is rising. Monitors area temperatures using EOP-03 Condition Monitoring Hardcard ATC Announce unexpected RWCU ISOL PUMP A/B RM TEMP HI alarm and give stability report. Inform crew that this is an EOP-03 entry condition.

BOP Review ARI and valve Isolation Matrix determine that RWCU failed to isolate.

Inform SRO that none of the required RWCU isolation valves closed.

Driver If asked to investigate RWCU rooms for leakage:

Before isolation - Report steam coming from RWCU rooms and cant get closer for a better look.

After isolation - Report steam visible in RWCU rooms but diminishing and dont feel safe to get closer for a better look.

If asked to investigate RCIC room, report no visible leakage.

SRO Announce entry into EOP-03, Secondary Containment Control and may enter ONI-N11, Pipe Break Outside Containment.

Direct BOP to Monitor and Control SC area Temperatures and Water Levels.

Direct BOP to perform Immediate and Supplemental Actions of ONI-N11 Direct crew to perform Rapid Manual Shutdown of RWCU.

Direct BOP to isolate all systems discharging into the affected SC area. (Critical Task 1)

BOP/ATC Performs Rapid Manual Shutdown of RWCU. (Trips both RWCU Pumps)

BOP/ATC Make plant announcement to evacuate the Aux Building.

BOP Isolate RWCU as directed. (Critical Task 1)

BOP Continues to monitor area temperatures using EOP-03 Condition Monitoring Hardcard to determine if isolation actions were effective.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.:

5 Page 9 of 19 Event

Description:

5

- Leak in RWCU pump room Enter EOP-03 Symptoms/Cue: ARI-H13-P680-01-B4, C4, D4, D5, & C5 and ARI-H13-P601-18-A3 Time Position Applicants Actions or Behavior Evaluator It will take several minutes for RWCU pump room temperature to stabilize then start to lower.

Evaluate Technical Specifications T.S. 3.3.6.1 Action (Identifies Table 3.3.6.1-1 Function 4d is applicable)

A.1 - Place channel in trip. - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 2.b, 5.b, and 5.d B.1 - Restore isolation capability - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C.1 - Enter the Condition referenced in Table 3.3.6.1-1 for the Channel -

Immediately F.1 - Isolate the affected penetration flow path(s). - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Evaluator Condition B is entered because the isolation Function is lost for Group 7 valves.

Condition C is entered 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after Condition B.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.:

6 Page 10 of 19 Event

Description:

6

- Loss of Feedwater Symptoms/Cue: ARI-H13-P680-0002-E3, ARI-H13-P680-003-D1 through D4 Time Position Applicants Actions or Behavior Driver

• When directed, insert Event 6

• Role play as directed Evaluator Initiating event is failed instrument causing a low Hot Surge Tank level indication which will trip all RFBPs.

If all RFBPs tripped due to low Hot Surge Tank level, then RFP A, RFP B and the MFP will trip.

ATC Announce unexpected alarms and loss of all feedwater.

ATC Announce Low Hot Surge Tank Level followed by loss of all RFBPs Determine that Reactor Water Level is below Level 3 and that Scram did not occur BOP Make Plant announcement for the Scram and evacuate containment ATC Locks the Mode Switch in Shutdown.

Determines that scram did not occur.

Evaluator Actions continue in subsequent sequences.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.:

7 Page 11 of 19 Event

Description:

7

- RPS fails in AUTO and MANUAL. ARI works in MANUAL or AUTO Symptoms/Cue: RPV level trend Time Position Applicants Actions or Behavior Driver Role play as directed.

Evaluator Automatic RPS scram will not work. If RPV level lowers to L2, automatic ARI will insert rods. A manual Scram or ARI initiation will cause control rods to insert.

ATC Recognizes failure of Mode Switch and RPS pushbuttons and initiates ARI.

Recognize manual ARI inserts all control rods.

ATC Perform Scram Hard Card Actions:

1. VERIFY the following actions completed:

• Mode Switch Locked in Shutdown. (Note power once scram signal inserted)

• RPS Initiated, if all control rods are not fully inserted.

• ARI Initiated, if RPS failed to Scram the reactor.

Evaluator Step 2 below is N/A as all rods are inserted.

ATC

2. IF Reactor power is above 4%, THEN PERFORM the following:

3. STABILIZE Reactor level using Feedwater / RCIC / HPCS.

4. STABILIZE Reactor pressure using Turbine / Turbine Bypass valves / SRVs

5. PERFORM crew update with the following information:

• The Mode Switch is locked in shutdown (RPS and ARI initiated if required)

• Reactor Power is ________________%

• Reactor Pressure is _______________psig

• Reactor Level is __________________inches

• EOP-01 Entry IS / IS NOT met SRO Enter EOP-01, RPV Control Evaluator When Turbine Bypass Valves close, ATC should stabilize RPV pressure using the Pressure Control Hardcard as time permits.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.:

8 Page 12 of 19 Event

Description:

8

- Generator Field Breaker fails to auto open Symptoms/Cue: Generator Field Breaker status light Time Position Applicants Actions or Behavior ATC Continues Scram Hard Card Actions:

6. WHEN generator load is reduced to less than 90 MWe, THEN PERFORM the following:

a) Depressing the TURBINE TRIP push-button.

b) VERIFY the following:

• MAIN STOP VALVES are shut (4)

• CONTROL VALVES are shut (4)

• COMBINED INTERMEDIATE VALVEs are shut (6)

• GEN BRKRs S-610-PY-TIE and S-611-PY-TIE is open

• GEN FIELD BREAKER is open

• EXCITER FIELD BREAKER is open ATC Recognize the Generator Field Breaker failed to automatically trip and take the Generator Field Breaker handle to TRIP.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.:

9 Page 13 of 19 Event

Description:

9

- Loss of High-Pressure Injection - Anticipate Emergency Depressurization Symptoms/Cue: From EOP-01 Level leg Time Position Applicants Actions or Behavior Evaluator RCIC will feed the RPV for several minutes following the scram then will trip.

SRO In EOP-01, RPV Control Answers YES to Decision Diamonds, Are APRMs downscale and Is the Reactor shutdown by control rods Crew Identify RCIC trip and announce loss of all high pressure injection.

SRO Enters Level Control leg:

Direct BOP to verify Actuations and Isolations for L3 and L2.

Works way down Level Leg and directs EOP-SPI 4.1, CRD Alternate Injection and EOP-SPI 4.5, SLC Demin Water Alternate Injection ATC/BOP Performs EOP-SPI 4.1 and EOP-SPI 4.5.

SRO Determines that RPV level cannot be maintained >130 and directs BOP to lineup low pressure ECCS systems for injection to lineup injection systems IAW:

EOP-SPI 6.5, LPCS Injection EOP-SPI 6.1, RHR A Injection EOP-SPI 6.2, RHR B Injection EOP-SPI 6.3, RHR C Injection BOP Commence lining up LP systems for injection and informs the SRO when 2 systems are lined up for injection.

Informs SRO when all LP systems are lined up for injection.

SRO Continue EOP-01, RPV Control - Level Leg actions.

Answers NO to Decision Diamond, Can RPV level be restored and maintained 130 in. to 219 in.

Answers YES to Decision Diamond, Can two or more ECCS/Feedwater sources be lined up Makes determination that RPV level cannot be maintained above 16.5 in. and proceeds through Hold Box.

Determines that AED is required before RPV level lowers to 16.5 inches or ED is required before RPV level lowers to -25 inches.

Enters EOP-02 and directs BOP to startup B H2 analyzer and H2 igniters.

Evaluator The SRO can determine that RPV level cannot be maintained >16.5 when existing injection cannot arrest the RPV level decrease, regardless of how high above 16.5 actual RPV level is

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.:

9 Page 14 of 19 Event

Description:

9

- Loss of High-Pressure Injection - Anticipate Emergency Depressurization Symptoms/Cue: From EOP-01 Level leg Time Position Applicants Actions or Behavior Evaluator If AED is commenced with RPV level is > 30 inches, AED will be successful and preclude need to ED.

Crew may elect to Emergency Depressurize rather than AED. In this case, the ED portion of Critical Task-2 will be evaluated rather than the AED portion of Critical Task-2. The auto ADS initiation has been disabled. Additionally, ED may cause RPV water level to go below TAF which would the crew to recover level >TAF.

If crew fails to commence AED action, nine minutes after the scram an SRV will fail open causing additional loss of inventory. Depending on timing, this may require crew to Emergency Depressurize.

SRO Enters Pressure Control leg:

Enters Anticipate ED 1st If-While-Executing Step (IWE) and directs BOP to perform EOP-SPI 2.3 to bypass MSIV interlocks.

Direct ATC to USE Main Turbine Bypass Valves to rapidly depressurize the RPV as needed to preclude Emergency Depressurization and EXCEED Cool down rate as required (Critical Task 2)

Direct ATC/BOP to monitor for low-pressure injection.

ATC Operates the BPV Jack to open Bypass Valves (Critical Task 2)

BOP Performs EOP-SPI 2.3 to bypass MSIV low level isolation ATC/BOP Monitor for LPCS injection.

Inform SRO when injection has commenced Report when RPV level is stabilized and recovering.

Evaluator Crew should have ability to lower RPV pressure enough to obtain injection from LPCS, then stabilize RPV pressure and control LPCS injection.

SRO Determines that RPV level can be stabilized/recovered with low-pressure injection systems and determines that AED is no longer required and proceeds to stabilize RPV pressure step.

Directs ATC to stabilize RPV pressure to establish a cooldown rate < 100 °F/ hour.

Directs ATC to establish an RPV level band of 178 to 260 inches.

ATC Operates BPV Jack to stabilize RPV pressure.

Controls low-pressure injection to raise Rx water level.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Event No.: 10 Page 15 of 19 Event

Description:

10 - (Conditional) ED if unable to maintain RPV level > -25 with LPCS Symptoms/Cue:

Time Position Applicants Actions or Behavior SRO From the EOP-01 Level Control Leg Makes determination that Emergency Depressurization is Required before RPV level lowers to -25 inches and transitions to EOP-01-2, Emergency RPV Depressurization.

SRO Enters EOP-01-2, Emergency RPV Depressurization.

Answers NO to Decision Diamond, Has Drywell Pressure exceeded 1.68 psig.

Directs ATC/BOP to open all ADS valves. (Critical Task-2)

ATC/BOP Opens all ADS valves. (Critical Task-2)

Inform SRO that 8 ADS valves are open.

SRO Answers YES to Decision Diamond, Are 6 or more SRVs Open.

Directs crew to maintain RPV pressure <30 psig.

Directs ATC to establish RPV level band of 178 to 260 inches.

ATC Controls low-pressure injection to raise Rx water level >TAF

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Page 16 of 19 Event

Description:

Scenario Termination Criteria Time Position Applicants Actions or Behavior

1. Primary leak into Secondary Containment is isolated

2. Reactor shutdown.

3. RPV pressure lowered to allow low-pressure injection to recover RPV level.

4. RPV level being restored to level band of 178 to 260

5. Lead Examiners discretion

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Page 17 of 19 Event

Description:

Critical Task 1 Time Position Applicants Actions or Behavior With a primary system discharging into the secondary containment, take action to manually isolate the break.

1. Safety Significance:

Isolating high energy sources can preclude failure of secondary containment and subsequent radiation release to the public.

2. Cues:

Procedural compliance.

Area temperature indication.

3. Measured by:

With the reactor at pressure and a primary system discharging into the secondary containment, operator takes action to manually isolate the break within 15 minutes.

4. Feedback:

Valve position indication.

In field reports.

NOTE: 15 minute criteria for isolation based on entry into E-plan (SU5.1)

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 1 - 100%

Page 18 of 19 Event

Description:

Critical Task 2 Time Position Applicants Actions or Behavior With reactor shutdown and reflood systems available, reduce RPV pressure to allow for restoration of RPV level by low pressure injection.

1. Safety Significance:

Maintain adequate core cooling; prevent degradation of fission product barrier.

2. Cues:

Procedural compliance (ED required, ED Anticipated, controlled cooldown, use of 5-5-2 LPCS injection strategy)

Water level trend.

3. Measured by:

Observation:

ED Anticipated Bypass Valve Jack used to reduce RPV pressure without regard to cooldown rate.

ED Required At least 6 SRVs opened prior to RPV level dropping below -25.

4. Feedback:

RPV pressure trend.

Bypass Valve / SRV position indications.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.:1 - 100%

Page 19 of 19 Event

Description:

Procedures to verify clean Procedure Number Check IV Procedure Number Check IV ARI-H13-P601-18-A3 ARI-H13-P601-21-G5 ARI-H13-P680-0002-E3 ARI-H13-P680-003-D1 through D4 ARI-H13-P680-01-B4, C4, &C5 ARI-H13-P680-02-A6 & -D6 ARI-H13-P870-05-E1 EOP & ONI Charts EOP-SPI 2.3 EOP-SPI 4.1 EOP-SPI 4.5 EOP-SPI 6.1 EOP-SPI 6.2 EOP-SPI 6.3 EOP-SPI 6.5 Hardcards - All ONI-C51 ONI-N11 ONI-N36 ONI-SPI G.4 ORM 6.2.1 PDB-I-03 pp. 12-15 SOI-G33 Sect 6.4 SOI-N21 P&Ls & Sects 4.4, 6.1, & 7.3 SOI-N32 P&Ls and Sect 7.26 SRO Oversight Checklist TS 3.3.5.3 TS 3.3.6.1

ES-3.3, Page 16 of 17 Form 3.3-1 Scenario Outline Facility:

Perry Scenario #:

1. 2 - 80% Power Scenario Source:

New Op. Test #:

2022-1 Examiners:

Applicants/

Operators:

Initial Conditions:

Plant is at 80% power due to FW limitations. CCCW Chill Water Pump C, P47-C001C is tagged out for motor replacement. Stator Water Cooling Pump B, N43-C001B is tagged out for bearing replacement. The M29 Control Room Humidification Boiler is tagged out for leak repair. Hydrogen Analyzer B was tagged out yesterday for inlet cooling valve replacement (One day into the LCO). CNTMT SPRAY SECOND SHUTOFF, 1E12-F537A is tagged out for MOVATS testing (Twelve hours into the LCO). Replacement of a speed sensor on RFPT B is complete. Maintenance Engineer requested Ops to pause RFPT B startup at various RPMs to gather data. Currently RFPTs A & B are in AUTO and the MFP is in MANUAL. eSOMS Narrative Log is down. PSA Risk is Green and the Grid Risk is Normal.

Turnover / Planned Activities: Continue Feedwater shift from MFP to RFPT B. An NLO is on station to support the shift. Raise reactor power to 85% power IAW reactivity plan and IOI-3. Make any Narrative Log entries on your note pads. Perform Prejob Briefs and Reactivity Briefs prior to entering the Simulator.

Critical Tasks:

1. Insert manual reactor scram when power oscillations are observed and auto RPS fails

2. When Containment temperature cannot be maintained < 185 °F, perform ED Event No.

Malf.

No.

Event Type*

Event Description 1

N-BOP/SRO Shift from MFP to RFPT A & B in service 2

R-ATC/SRO Raise Rx power to 85% (Control Rods) 3 C-ATC/SRO TS-SRO Uncoupled Control Rod Tech Spec 3.1.3 4

C-BOP/SRO ESW Pump House Fan B loses power 5

C-ATC/SRO MC-ATC HST Level Control Valve, N21-F230 fails closed 6

TS-SRO Combustible Gas Mixing Compressor A power loss Tech Spec 3.6.3.3 7

C-ATC/SRO Rx Recirc pumps down-shift to SLOW Enter ONI-C51 8

C-ATC/SRO Power oscillations Enter EOP-01 on failure to Scram 9

M-ALL SDV Leak in Containment Enter EOP-02 10 C-BOP/SRO Failure of Containment Spray valve Enter EOP-01-2 Emergency Depressurize 11 C-BOP/SRO SRV B21-F041A fails to open on ED (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Page 1 of 22 Event

Description:

N/A - Driver Instructions Time Position Applicants Actions or Behavior Driver Driver Simulator Setup:

Reset Simulator to IC 152 Load Schedule File: NRC 2022-2.sch Verify Schedule File NRC 2022 H2 Analyzers.sch loads Verify Event File: NRC 2022-2.evt Loads In Director, if necessary, toggle Override ZL1M51HS1B-GRN to OFF Remove Requal IOI-3 and Rod Book from horseshoe.

Markup Crew Sheet to show Turbine Tour NLO supporting FW shift Cycle left DFWCS Screen & cycle ESWPH B fan control switch.

Driver Driver Verify Initial Conditions:

Reactor Power 80%. MOC_STARTUP_TRAINING_SEQ Pull Sheets, Rods @

Step 67 with last 2 inserted to 12.

IOI-3 Attachment 3 is in progress.

Verify APRM gains are adjusted Place yellow switch cap on:

• CCCW C Chiller & CW Pump

• N43-C001B

• H2 Analyzer B SYSTEM FUNCTION SWITCH

• 1E12-F537A Green Risk.

Driver Driver Initial Conditions:

Plant is at 80% power due to FW limitations. CCCW Chill Water Pump C, P47-C001C is tagged out for motor replacement. Stator Water Cooling Pump B, N43-C001B is tagged out for bearing replacement. The M29 Control Room Humidification Boiler is tagged out for leak repair. Hydrogen Analyzer B was tagged out yesterday for inlet cooling valve replacement (One day into the LCO).

CNTMT SPRAY SECOND SHUTOFF, 1E12-F537A is tagged out for MOVATS testing (Twelve hours into the LCO). Replacement of a speed sensor on RFPT B is complete. Maintenance Engineer requested Ops to pause RFPT B startup at various RPMs to gather data. Currently RFPTs A & B are in AUTO and the MFP is in MANUAL. eSOMS Narrative Log is down. PSA Risk is Green and the Grid Risk is Normal.

Turnover: Planned activities; Continue Feedwater shift from MFP to RFPT B. An NLO is on station to support the shift. Raise reactor power to 85% power IAW reactivity plan and IOI-3. Make any Narrative Log entries on your note pads.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

1 Page 2 of 22 Event

Description:

1

- Shift from MFP to RFPT A & B in service Symptoms/Cue: From Turnover Time Position Applicants Actions or Behavior Driver Role play as NLO as directed.

SRO Direct BOP to shift from MFP to RFPT A & B in service and shutdown the MFP IAW SOI-C34, Feedwater Control System.

Provide oversight.

BOP Perform SOI-C34, Placing Reactor Feed Pump in Service from 1100 RPM:

4.4 Placing Reactor Feed Pump in Service from 1100 RPM to RFPT Flow Control 4.4.17 IF removing a feed pump from service, THEN REFER TO one of the following:

• Section 6.2, MFP Shutdown to Casing Warmup BOP Perform SOI-C34, MFP Shutdown to Casing Warmup:

6.2 MFP Shutdown to Casing Warmup 6.2.1 DIRECT Chemistry to ALIGN Hydrogen Water Chemistry as required.

NOTES The MFP min flow/recirc flowpath is NOT adequate to support operation of the Hydrogen Water Chemistry (HWC) system. As a result, when flow to the vessel from the MFP is stopped, the HWC system may trip if Chemistry has not completed the realignment of the HWC system.

The Margins and Limits Hardcard (OAI-1703) should be reviewed for this evolution.

6.2.2 CONFIRM one or both of the following:

• RFPT A operating with the RFPT A MANUAL/AUTO STATION in AUTO 1C34-R601A

• RFPT B operating with the RFPT B MANUAL/AUTO STATION in AUTO 1C34-R601B 6.2.3 VERIFY that the capacity of the remaining Feed Pumps is sufficient to maintain RPV Level.

6.2.4 VERIFY the MFP FCV MAN/AUTO STATION is in MANUAL.

1C34-R601C 6.2.5 WHILE maintaining RPV level in band, ADJUST the MFP FCV MAN/AUTO STATION to 0%.

1C34-R601C

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

1 Page 3 of 22 Event

Description:

1

- Shift from MFP to RFPT A & B in service Symptoms/Cue: From Turnover Time Position Applicants Actions or Behavior BOP 6.2.6 VERIFY the following valves are closed:

• MFP FULL FLOW CONTROL VALVE 1N27-F010

• MFP LOW FLOW CONTROL VALVE 1N27-F110 6.2.7 PLACE the MFP in OFF.

1N27-C004 6.2.8 VERIFY the MFP RCIRC FLOW CONTROLLER at 0%.

1N27-R077 6.2.9 RFPT A is NOT Tripped 1N27-C003A RFPT B is NOT Tripped 1N27-C003B THEN PERFORM the following:

6.2.9.a PLACE the MFP in AUTO.

1N27-C004 6.2.9.b VERIFY the MFP AUTO XFER is ENABLED.

Continue with SOI-C34, Placing Reactor Feed Pump in Service from 1100 RPM:

4.4.18 SLOWLY ADJUST the RECIRC FLOW CONTROLLER MINIMUM OUTPUT to 0% OR until minimum flow requirements are satisfied for any operating feedwater pump. 1N27-K162B_OP1 4.4.19 BOTH of the RFP Suction Flow transmitters are indicating on scale BOTH of the RFP Suction Flow transmitters are available THEN REMOVE the bypassed transmitter from bypass:

• RFPT SUCT FLOW RDNT XMTR 1N27-N087A 1N27-N087B 4.4.20 IF NOT performed in Step 4.4.12.d, THEN DIRECT Chemistry to ALIGN Hydrogen Water Chemistry as required.

BOP Inform SRO that Feedwater shift is complete

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

2 Page 4 of 22 Event

Description:

2

- Raise Rx power to 85%

Symptoms/Cue: From Turnover Time Position Applicants Actions or Behavior Driver Role play as Tenaska, Rx Engineer, RP, and Chemistry as directed.

SRO Direct ATC to raise reactor power to 85% IAW the Reactivity Plan and IOI-3, Power Maneuvering, Attachment 3.

Provide oversight Evaluator It is expected that the ATC will use Control Rods to raise power.

When the 2nd rod is withdrawn for a coupling check at position 48 it will become uncoupled. See Event-3 The RWL enforces a 2-notch limit for withdrawal at this Rx power level. The Candidate will need to deselect and reselect the control rods every two notches.

ATC Notify Tenaska, RP and Chemistry of intended power change ATC Perform SOI-C11(RC&IS), Rod Control And Information System to raise power.

7.1 Single Rod Selection 7.1.1 Momentarily depress DRIVE MODE to select INDIVID DRIVE mode.

7.1.2 Simultaneously depress the XX and YY coordinates for any rod member of that gang on the RSM to select the desired gang.

7.5 Continuous Withdrawal For A Single Rod or Gang 7.5.1 Select the single rod or rod gang.

7.5.2 Simultaneously Depress And Hold the following:

• WITHDRAW

• CONT WITHDRAW 7.5.3 Observe the following:

• The IN light comes on.

• The OUT light comes on

• The CONT OUT light comes on

• The RDM is updating rod or gang positions.

• Expected changes occur in nuclear instrumentation 7.5.4 When the rod or gang just passes the desired position, then release both pushbuttons to allow the rod or gang to settle into the desired notch.

7.5.5 Observe the following:

• The RDM indicates the new rod position(s).

• The SETTLE light comes on for approximately 6 seconds and goes off.

• If in gang withdrawal, the new position is displayed in the GANG POSITION subsection of the RDM and the green STABLE status LED will be on.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

2 Page 5 of 22 Event

Description:

2

- Raise Rx power to 85%

Symptoms/Cue: From Turnover Time Position Applicants Actions or Behavior SRO Report to SRO that Control Rod 34-23 is uncoupled and this is an entry condition to ONI-C11-2, Uncoupled Control Rod SRO Enter ONI-C11-2, Uncoupled Control Rod ATC Report to SCC that power increase is on hold.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

3 Page 6 of 22 Event

Description:

3

- Uncoupled Control Rod Symptoms/Cue: ARI-H13-P680-05-D9 Time Position Applicants Actions or Behavior Driver Role play as Rx Engineer and NLO as directed.

If asked about a recovery plan, one will be developed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SRO Direct ATC to stop control rod withdrawal ATC Inform SRO that control rod withdrawal has been stopped.

SRO Reviews Supplemental actions of ONI-C11-2 4.1 CONTACT the Reactor Engineer.

4.2 IF the Periodic Log is available, THEN DETERMINE if the following have been exceeded:

• Local power limits

• Gross power limits Directs BOP to contact Rx Engineer and run a Periodic Log SRO Continues reviewing Supplemental actions of ONI-C11-2 CAUTION Scramming a control rod drive with an uncoupled rod could result in control rod or drive damage.

NOTE In Mode 1 and 2, an uncoupled control rod needs to be fully inserted within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> AND disarmed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to comply with Technical Specifications (T.S. 3.1.3 and 3.10.8) 4.3 IF in Mode 1, THEN PERFORM the following:

4.3.1 DECLARE the control rod inoperable.

4.3.2 INSERT the control rod to the position from which it was withdrawn.

Directs ATC to insert control rod 34-23 to position 12.

ATC Inserts control rod 34-23 to position 12.

Informs SRO that control rod 34-23 is at position 12 SRO 4.3.3 DIRECT the Reactor Engineer to develop an action plan for control rod recoupling.

Contacts Rx Engineering to develop an action plan for recoupling.

Determines that action plan preparation will not meet Tech Spec requirements and directs ATC to fully insert control 34-23 ATC Inserts control rod 34-23 from position 12 to 00.

Informs SRO that control rod 34-23 is fully inserted

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

3 Page 7 of 22 Event

Description:

3

- Uncoupled Control Rod Symptoms/Cue: ARI-H13-P680-05-D9 Time Position Applicants Actions or Behavior SRO Directs ATC/BOP to direct NLO to disarm control rod 34-23.

ATC/BOP Directs NLO to disarm control rod 34-23.

SRO Evaluate Tech Specs Tech Spec. 3.1.3 Action C.1 - Fully insert inoperable control rod. - 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> AND C.2 - Disarm the associated CRD. - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

4 Page 8 of 22 Event

Description:

4

- ESW Pump House Fan B loses power Symptoms/Cue: ARI-H13-P800-01-D4 & E4 Time Position Applicants Actions or Behavior Driver

• When directed, initiate Event 4

• Role play as NLO as directed

• If asked to investigate MCC EF1C12-J, 2 mainline power fuses are blown Evaluator The Power Loss alarm will be preceded by a Low Flow alarm for 60 seconds. The ARI for the Low Flow contains direction to start the A vent fan.

IAW OAI-1701, if either train of ESWPH ventilation is functional, then Operability of ESW is maintained ATC Announce unexpected P800 alarm and give stability report.

BOP Announce ESW B PUMP HOUSE SUPP FAN FLOW LOW alarm and ESW PUMP HOUSE VENT SYSTEM OVLD/PWR LOST alarms. Walkdown H13-P800 and determine and ESW B pump house fan has lost power.

Reviews ARI and informs SRO of need to startup ESW Pump House vent fan A.

Direct NLO to investigate loss of power to ESW pump hours fan.

SRO Evaluate Operability of ESW B with ESW B pump house fan off and ESW pump hours fan in operation.

Direct BOP to startup ESW Pump House vent fan A.

BOP Performs SOI-M32, Manual Startup From Standby Ready to start ESWPH fan A.

4.3.1 Take the oncoming ESW PMP HOUSE VENT SUPP FAN 1 control switch to START.

1M32-C001A 4.3.2 Verify the oncoming ESW PMP HOUSE EXH LOUVER 70 opens.

1M32-F070A Inform SRO that ESWPH supply fan A has been started

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

5 Page 9 of 22 Event

Description:

5

- HST Level Control Valve, N21-F230 fails closed Symptoms/Cue: ARI-H13-P680-07-E12 & ARI-H13-P680-02-E3 & D2 Time Position Applicants Actions or Behavior Driver

• When directed, initiate Event 5.

• Role play as NLO as directed.

• If directed to investigate N21-F230 locally, inform crew that there is nothing abnormal locally.

ATC Announce unexpected alarms and give stability report.

Observes HST level controller not operating properly and Condensate flow decreasing.

Reports HST level and trend ATC Inform the SRO of the need to place HST Level controller in MANUAL.

Evaluator Directed HST level band should be between Lo & Hi level alarms (104131)

If Candidate opens N21-F220 too much for too long, a Hot Surge Tank high level may result. This may cause an isolation of #4 FW heater. The isolation can be stopped if HST level is lowered and the Extraction Steam valve to the #4 FW heater closure is stopped. If the isolation is completed, the crew will need to enter ONI-N36 for a heater isolation and ONI-C51 if a power change occurs.

SRO Direct ATC to take manual control of HST Level controller.

Direct HST level band.

Direct ATC to insert a manual scram if HST level lowers to 60 inches IAW Margins and Limits Hardcard.

ATC Attempts to place HST Level controller in MANUAL and attempts to adjust HST Level control valve position.

Determines HST level controller is not responding and will need to adjust HST Alternate Level control valve, N21-F220.

SRO Directs ATC to take control of HST level using Alternate Hot Surge Tank Level Control IAW SOI-N21 ATC Performs SOI-N21, Condensate System to control HST level 7.18 Alternate Hot Surge Tank Level Control NOTES

• This section may be performed upon a malfunction of the Hot Surge Tank Level Control Valve, 1N21-F230, OR when supplemental flow is required in the event feedwater heater drains are being sent directly to the condenser.

• 1N21-F220, HST LVL CV MANUAL CONTROL potentiometer is adjusted by IOI-3, Power Changes as necessary to maintain Hot Surge Tank Level, and may be open, dependent on Reactor power level.

7.18.1 MANUALLY CONTROL HST Level with 1N21-F220, HST LVL CV MANUAL CONTROL potentiometer as follows:

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

5 Page 10 of 22 Event

Description:

5

- HST Level Control Valve, N21-F230 fails closed Symptoms/Cue: ARI-H13-P680-07-E12 & ARI-H13-P680-02-E3 & D2 Time Position Applicants Actions or Behavior ATC 7.18.1.a IF HST LVL CV MANUAL CONTROL is OFF, THEN VERIFY the following:

• HST LVL CV MANUAL CONTROL is adjusted to zero 1N21-F220 closed 1N21-R7097.18.1.b VERIFY the HST LVL CV MANUAL CONTROL in ON.

7.18.1.c SIMULTANEOUSLY PERFORM the following to control Hot Surge Tank Level at 104 to 131 inches.

7.18.1.c.1 ADJUST the HST LVL CV MANUAL CONTROL potentiometer.

7.18.1.c.2 IF desired, THEN PERFORM the following:

• PLACE the HOT SURGE TANK LEVEL CONTROL, 1N21-F230 in MANUAL.

1N21-R475

• CLOSE the HOT SURGE TANK LEVEL CONTROL valve.

1N21-F230 7.18.1.d STABILIZE Hot Surge Tank level at the desired level.

ATC Inform SRO that HST level is recovering.

SRO Direct level band for Hot Surge Tank ATC Controls Hot Surge Tank level in directed band.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

6 Page 11 of 22 Event

Description:

6

- Combustible Gas Mixing Compressor A power loss Symptoms/Cue: ARI-H13-P800-02-A5 Time Position Applicants Actions or Behavior Driver

• When directed, initiate Event 6

• If requested to investigate the disconnect (EF1B08-T) for CGMC A - inform the BOP that the control power fuse is blown - no obvious reason ATC Announce unexpected P800 alarm and give stability report.

BOP Investigate P800 alarm and determine that Combustible Gas Mixing Compressor A has no power and inform SRO.

Dispatch an NLO to investigate the loss of power.

Review ARI-H13-P800-2-A5 and informs SRO of possible Tech Spec implications.

SRO Evaluate Tech Specs T.S. 3.6.3.3 Action A.1 - Restore combustible mixing subsystem to OPERABLE status. - 30 days

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

7 Page 12 of 22 Event

Description:

7

- Rx Recirc pumps down-shift to SLOW Enter ONI-C51 Symptoms/Cue: ARI-H13-P680-04-A3 & A12 Time Position Applicants Actions or Behavior Driver

• When directed, initiate Event 7.

• Role play as Rx Engineer as directed.

• After the first Cram Rod is inserted, power oscillations will worsen (next event)

Evaluator Power oscillations (next Event) will commence a few minutes after the down-shift and will worsen upon insertion of the first Cram Rod.

ATC Announces Unexpected alarms and gives stability report.

Determines that both A and B Recirculation pumps have shifted to slow speed and informs SRO of entry condition to ONI-C51.

ATC Observes Reactor Power and Core Plate P and determines that the Immediate Exit Region of the Power To Flow Map has been entered and action to insert Cram Rods is necessary (per FTI-B02).

SRO Announces entry into ONI-C51 and confirms that plant is in Immediate Exit Region of Power To Flow Map. Verifies that ATC is inserting Cram Rods per FTI-B02.

SRO Directs ATC to monitor nuclear instruments for power oscillations. If oscillations are observed, then scram the reactor.

ATC Perform FTI-B02, Control Rod Movements to insert Cram Rods.

4.7 Use of Cram Rods NOTE There are three methods to control the use of cram rods. The Command SRO will select the method to be used based on the situation 4.7.1 Method 1 - Use of the Control Rod Movement Sheet

1. Insert Cram Rods listed on the Control Rod Movement Sheet steps in descending order.

2. Gang motion is recommended where not prohibited.

3. Select the control rods listed in the Current Step of the Control Rod Movement Sheet and continuously insert to positions between 04 and 00, inclusive. Further leveling of all rods in a step between 04 and 00 is not required. Skip the step if the rods are already between 04 and 00.

4. Per Step 4.5.5, the Current Step is the lowest numbered step in which all the control rods in that step are not positioned at the withdrawal limit. If all steps are at the withdrawal limit, then the last step is the current step.

5. Do not leave control rods at an intermediate position, i.e., a position other than the withdraw limit or between 04 and 00.

6. Complete the insertion of a control rod or gang in the step even if the required power reduction has been achieved.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

7 Page 13 of 22 Event

Description:

7

- Rx Recirc pumps down-shift to SLOW Enter ONI-C51 Symptoms/Cue: ARI-H13-P680-04-A3 & A12 Time Position Applicants Actions or Behavior

7. Document in the comments on the Control Rod Movement Sheets the altered insert limits when inserting Cram Rods. Documentation may be performed when plant conditions permit.

8. Deselect the final Cram Rod or gang to reset the Rod Withdrawal Limiter, RWL.

9. Continue with Step 4.7.4.

4.7.4 When Cram Rods are inserted and Thermal Power is 19% RTP, assume the Rod Pattern does not meet the Low Power Setpoint constraints of the Rod Pattern Controller.

4.7.5 Increasing recirc flow after inserting Cram Rods may lead to thermal limits problems.

4.7.6 Contact Reactor Engineering expeditiously after the insertion of Cram Rods for the coordination of recovery actions.

Evaluator It is not expected that the SRO will progress past the evaluation of thermal limits in ONI-C51 prior to receiving a 1/2 scram on OPRMs.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

8 Page 14 of 22 Event

Description:

8

- Power oscillations Enter EOP-01 on failure to Scram Symptoms/Cue: ARI-H13-P680-6A-A3 Time Position Applicants Actions or Behavior Evaluator After first Cram Rod is inserted in previous Event, Power Oscillations will worsen.

Evaluator Numerous annunciators will alarm as power oscillations start then increase in size.

ATC should be able to diagnose power oscillations by observing P680 annunciators and APRM indications. Prior to manually scramming its expected that a full scram signal will be generated (but automatic scram will not occur).

ATC Respond to alarms on P680. Recognize a Reactor scram should have occurred Recognize failure of automatic and manual Rx scram and arms and depresses ARI pushbuttons (Critical Task 1)

Commence Reactor Scram Hardcard actions

1. VERIFY the following actions completed:

• Mode Switch Locked in Shutdown (Note power once scram signal inserted)

• RPS Initiated, if all control rods are not fully inserted

• ARI Initiated, if RPS failed to Scram the reactor

2. IF Reactor Power is above 4% OR unknown, THEN PERFORM the following:

3. STABILIZE Reactor level using Feedwater / RCIC / HPCS

4. STABILIZE Reactor pressure using Turbine / Turbine Bypass valves / SRVs

5. PERFORM crew update with the following information:

• The Mode Switch is locked in shutdown, (RPS and ARI initiated if required)

• Reactor Power is

(~0%)

• Reactor Pressure is _______________psig

• Reactor Level is __________________inches

• EOP-01 Entry IS / IS NOT met

• IF MSIVs are closed, THEN a Time Critical Operator Action for Suppression Pool Cooling is applicable.

Time: _____________.

SRO Announce entry into EOP-01, RPV Control SRO Works way through EOP-01 Chart.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

9 Page 15 of 22 Event

Description:

9

- SDV Leak in Containment Enter EOP-02 Symptoms/Cue: ARI-H13-P601-17-D2 & 20-F4 Time Position Applicants Actions or Behavior Evaluator By the time Containment Temperature annunciators alarm and the crew recognizes Containment temperature and pressure are rising, Containment pressure should be

>0.8 psig (condition in first IWE block for Containment Spray Operations).

With Containment Spray A valve tagged out, crew will need to use Containment Spray B, which has a 35 second time delay. Valve E12-F028B will lose power when called to open.

Crew Announce unexpected Containment Temperature alarms and identify Containment Temperature and pressure are rising. Identify entry conditions into EOP-02.

SRO Announce entry into EOP-02, Primary Containment Control.

Works way to 1st If-While-Executing Step (IWE) and directs BOP/ATC to perform EOP-SPI 3.1 to spray Containment.

Direct BOP to monitor and control Containment parameters.

Directs BOP to operate all available Containment cooling and bypass CVCW isolations BOP/ATC Initiate Containment Spray IAW EOP-SPI 3.1.

3.0 RHR Containment Spray Loop B is NOT lined up to vent Containment Containment Spray A loop is NOT initiated Additional Containment Spray is required Containment Spray B loop is available THEN INITIATE Containment Spray B Loop as follows:

3.1 IF Drywell Pressure is less than 1.68 psig, THEN AT H13-P618, PLACE CNTMT SPRAY B HI DW PRESS BYP Keylock switch in BYPASS.

E12A-S76 3.2 CONFIRM Containment Pressure is above 0.8 psig.

3.3 ARM AND DEPRESS CNTMT SPRAY B MANUAL INITIATION pushbutton for at least 35 seconds.

E12A-S63B 3.4 VERIFY RHR PUMP B is running.

E12-C002B 3.5 IF ESW PUMP B is available, THEN VERIFY ESW PUMP B is running.

P45-C001B 3.6 IF ECC PUMP B is available, THEN VERIFY ECC PUMP B is running.

P42-C001B 3.7 VERIFY the following valves are OPEN:

• CNTMT SPRAY B FIRST SHUTOFF E12-F028B

• CNTMT SPRAY B SECOND SHUTOFF E12-F537B

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.:

9 Page 16 of 22 Event

Description:

9

- SDV Leak in Containment Enter EOP-02 Symptoms/Cue: ARI-H13-P601-17-D2 & 20-F4 Time Position Applicants Actions or Behavior BOP Operates all available Containment cooling fans, bypasses CVCW isolations IAW EOP-SPI 2.2, and directs NLO to restart a Containment Vessel chiller.

BOP/ATC Identifies that CNTMT SPRAY B FIRST SHUTOFF, E12-F028B lost power and did not open and Containment Spray could not be initiated and informs the SRO.

Evaluator Continued on next Event

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.: 10 Page 17 of 22 Event

Description:

10 - Failure of Containment Spray valve Enter EOP-01-2 Emergency Depressurize Symptoms/Cue:

Time Position Applicants Actions or Behavior SRO Continue EOP-02 actions.

Determines in EOP-02 Step CN/T-3 that Containment temperature cannot be maintained below 185 °F and Emergency Depressurization is required.

SRO Reenters EOP-01 and works way to 1st IWE block in Pressure Control Leg.

Determines Emergency Depressurization is or has been required and transitions to EOP-01-2, RPV Emergency Depressurization.

SRO Works way down EOP-01-2 chart and Answers YES to Decision Diamond, Has Drywell Pressure exceeded 1.68 psig.

Directs BOP to Prevent ECCS systems not required for continuous injection.

Directs ATC/BOP to open all ADS valves. (Critical Task-2)

ATC/BOP Opens all ADS valves (Critical Task-2)

Determines ADS SRV 1B21-F041A failed to open and informs SRO.

Evaluator Continued on next Event

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Event No.: 11 Page 18 of 22 Event

Description:

11 - SRV B21-F041A fails to open on ED Symptoms/Cue:

Time Position Applicants Actions or Behavior Evaluator It is not anticipated that RPV water level will go below TAF. Therefore restoring RPV water level >TAF was not included as a Critical Task.

SRO Continue EOP-01-2 actions.

Directs ATC/BOP to open additional SRVs until 8 SRVs are open.

ATC/BOP Open an additional SRV to obtain 8 open SRVs and informs SRO.

SRO Directs ATC/BOP to establish an RPV level band of 150 to 219 inches and override ECCS systems as necessary to maintain level in band.

ATC/BOP Coordinate injection of ECCS and Feedwater to establish directed level band.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Page 19 of 22 Event

Description:

Scenario Termination Criteria Time Position Applicants Actions or Behavior

1. Reactor is shutdown

2. Reactor depressurization to less than or equal to 30 psig is in progress

3. RPV water level controlled/restored

4. Lead Examiners discretion

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Page 20 of 22 Event

Description:

Critical Task 1 Time Position Applicants Actions or Behavior If a reactor scram is required and RPS fails to shutdown the reactor, initiate ARI.

1.

Safety Significance:

Shutting down reactor can preclude failure of containment or equipment necessary for the safe shutdown of the plant.

Correct reactivity control.

2. Cues:

Reactor power indication.

Procedural compliance.

3. Measured by:

Observation - ARI pushbuttons armed and depressed to cause control rod insertion within 2 minutes of receiving annunciators H13-P680-06-B5 (C5, D5, & E5) APRM X/Y UPSC INOP/TRIP OPRM X/Y TRIP.

4.

Feedback:

Reactor power trend.

Rod status indication.

Under worst-case conditions, thermal-hydraulic induced flux oscillations can grow very rapidly, reaching 25% peak-to-peak in approximately 60 seconds and resulting in some fuel damage within 120 seconds of a significant reduction in recirculation flow. EOP-01-5 p 29

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 2 - 80%

Page 21 of 22 Event

Description:

Critical Task 2 Time Position Applicants Actions or Behavior When Containment Temperature cannot be maintained below the Containment Design Temperature limit (185 °F), perform Emergency Depressurization.

1.

Safety Significance:

Precludes failure of containment and exceeding environmental qualification of safety related electrical equipment within the containment.

2.

Cues:

Procedural compliance High Containment Temperature

3. Measured by:

Observation - Prior to exceeding 185 °F, perform ED activities per the following guidance:

If operation IAW EOP-01:

At least 6 SRV opened.

4.

Feedback:

RPV pressure decreasing SRV / Bypass Valve open status indications

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.:2 - 80%

Page 22 of 22 Event

Description:

Procedures to verify clean Procedure Number Check IV Procedure Number Check IV ARI-H13-P601-17-B6 SOI-C34, Sec. 4.2, 6.3, 6.4 ARI-H13-P601-17-D2 SOI-C11(RC&IS) 7.1 & 7.5 ARI-H13-P601-20-F4 SOI-M32 Sec. 4.3 & P&Ls ARI-H13-P680-02-E1, E3 & D2 SOI-N21 Sec. 7.18 ARI-H13-P680-04-A3 & A12 SRO Oversight Checklist ARI-H13-P680-05-D9 TS 3.1.3 & Bases ARI-H13-P680-07-E12 TS 3.6.3.3 & Bases ARI-H13-P800-1-D4 & E4 ARI-H13-P800-2-A5 EOP & ONI Charts EOP-SPI 2.2 EOP-SPI 3.1 FTI-B0002 pages 16-18 Hardcards - All IOI-3 OAI-1701 ONI-C11-2 ONI-C51

ES-3.3, Page 16 of 17 Form 3.3-1 Scenario Outline Facility:

Perry Scenario #:

1. 3 - 96% Power Scenario Source:

New Op. Test #:

2022-1 Examiners:

Applicants/

Operators:

Initial Conditions:

Power was reduced two hours ago to 96% for surveillance testing, which is now complete.

SCC has requested we restore to rated power. The M29 Control Room Humidification Boiler is tagged out for leak repair. TBCC Pump C, P44-C001C is tagged out for seal replacement. Stator Water Cooling Pump B, N43-C001B is tagged out for bearing replacement. Hydrogen Analyzer B was tagged out yesterday for inlet cooling valve replacement (One day into the LCO). eSOMS Narrative Log is down. PSA Risk is Green and the Grid Risk is Normal.

Turnover / Planned Activities: Raise Reactor Power to 100% IAW reactivity plan and IOI-3 per SCC request.

Start HPCS in Full Flow Test SP mode for vibration analysis. An NLO is on station to support HPCS startup. Contact Maintenance Engineer for vibration analysis when HPCS is started. Once vibration analysis is complete, place HPCS in Standby. Perform Prejob Briefs and Reactivity Briefs prior to entering the Simulator.

Critical Tasks:

1. Manually start non-running Emergency Service Water loops

2. Manually start RCIC to avoid Emergency Depressurization on low RPV level Event No.

Malf.

No.

Event Type*

Event Description 1

R-ATC/SRO Raise Reactor Power to 100% (Flow) 2 N-BOP/SRO TS-SRO Start HPCS in Test Mode to Suppression Pool Tech Spec 3.5.1 3

C-BOP/SRO NCC A Pump trip Enter ONI-P43 4

C-ATC/SRO APRM H fails upscale 5

C-BOP/SRO TS-SRO Shutdown HPCS Test Valve, E22-F023 Loses power Tech Specs 3.5.1 & 3.6.1.3 6

C-BOP/SRO R-ATC/SRO Earthquake > OBE Enter ONI-D51 Initiate Normal Rx Shutdown:

Start all ESW loops 7

TS-SRO Earthquake causes leak in SLC tank Tech Spec 3.1.7 8

C-ATC/SRO 2nd Earthquake causes Loss of Feedwater Enter EOP-01 9

M-All MC-ATC Low power ATWS Enter EOP-01-5 10 C-BOP/SRO MC-BOP RCIC auto start failure (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Page 1 of 20 Event

Description:

N/A - Driver Instructions Time Position Applicants Actions or Behavior Driver Driver Simulator Setup:

Reset Simulator to IC 153.

Verify earthquake sound computer works.

Load Schedule File: 2022 Scen-3.sch.

Verify Schedule File NRC 2022 H2 Analyzers.sch loads.

Verify Schedule Files: 2022 Scen-3-A.sch, 2022 Scen-3-Seismic1.sch, & 2022 Scen-3-Seismic2.sch are available to load.

In Director, if necessary, toggle Override ZL1M51HS1B-GRN to OFF Mark-up Crew Sheet to show NI-In NLO Supporting HPCS run.

Driver Driver Verify Initial Conditions:

Reactor Power 96%. MOC_STARTUP_TRAINING_SEQ Pull Sheets, Rods @

Step 67.

IOI-3 Attachment 3 is in progress.

Place yellow switch cap on:

• TBCC Pump C

• Stator Water Cooling Pump B

• H2 Analyzer B SYSTEM FUNCTION SWITCH Green Risk.

Driver Driver Initial Conditions:

Power was reduced two hours ago to 96% for surveillance testing, which is now complete. SCC has requested we restore to rated power. The M29 Control Room Humidification Boiler is tagged out for leak repair. TBCC Pump C, P44-C001C is tagged out for seal replacement. Stator Water Cooling Pump B, N43-C001B is tagged out for bearing replacement. Hydrogen Analyzer B was tagged out yesterday for inlet cooling valve replacement (One day into the LCO). eSOMS Narrative Log is down. PSA Risk is Green and the Grid Risk is Normal.

Turnover: Planned activities; Raise Reactor Power to 100% IAW reactivity plan and IOI-3 per SCC request. Start HPCS in Full Flow Test SP mode for vibration analysis. An NLO is on station to support HPCS startup. Contact Maintenance Engineer for vibration analysis when HPCS is started. Once vibration analysis is complete, place HPCS in Standby.

Perform Prejob Briefs and Reactivity Briefs prior to entering the Simulator.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

1 Page 2 of 20 Event

Description:

1

- Raise Reactor Power to 100%

Symptoms/Cue: From Turnover Time Position Applicants Actions or Behavior Driver Role play as Rx Engineer, RP, SCC, and Chemistry as directed.

SRO Direct ATC to raise reactor power to 100% IAW the Reactivity Plan and IOI-3, Power Maneuvering, Attachment 3.

Provide oversight Evaluator It is expected that the ATC will use Recirc Flow to raise power.

ATC should maintain Loop Flow mismatch <5% (observable on overhead screen)

Target power is 3758 MWT (100%)

ATC Notify RP and Chemistry of intended power change ATC Perform SOI-B33, Reactor Recirculation System to raise Rx power.

Section 7.7, Rcirc Flow Control in Loop Manual 7.7.1 Confirm RCIRC LOOP FLOW CONTROL is in MAN.

1B33K603A 7.7.2 Confirm RCIRC LOOP FLOW CONTROL is in MAN.

1B33K603B 7.7.3 Adjust the following as required for the desired Recirc Flow while maintaining recirculation loop flow mismatch within limits:

RCIRC LOOP FLOW CONTROL 1B33K603A RCIRC LOOP FLOW CONTROL 1B33K603B ATC Report to SRO that Reactor power has been raised to 100% power using Rx Recirc flow.

ATC Report to SCC that power is at 100%

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

2 Page 3 of 20 Event

Description:

2

- Start HPCS in Test Mode to Suppression Pool Symptoms/Cue: From Turnover Time Position Applicants Actions or Behavior Driver Role play as RP, NLOs and Jeff Reeves as directed.

SRO Direct BOP to start HPCS in Test Mode to the Suppression Pool IAW SOI-E22A, High Pressure Core Spray System, section 7.9 HPCS Full Flow Test to Suppression Pool Evaluator HPCS is to be declared Inoperable when operating in secondary mode. (P&L 2.17)

SRO Evaluate Tech Specs for HPCS operating in a secondary mode.

T.S. 3.5.1 Action B.1 - Verify by administrative means RCIC System is OPERABLE when RCIC is required to be OPERABLE. - 1 Hour B.2 - Restore HPCS to OPERABLE status - 14 days BOP Perform SOI-E22A, High Pressure Core Spray System to start HPCS in Test Mode to Suppression Pool 7.9.1 RECORD the appropriate Maintenance Rule status in the Plant Narrative Log.

7.9.2 NOTIFY Radiation Protection that a Suppression Pool evolution will be conducted so the survey frequency may be increased as necessary.

7.9.3 REFER TO SOI-P45/49 and START the HPCS ESW Loop.

BOP 4.5 HPCS ESW Loop Manual Startup from Standby Readiness 4.5.1 TAKE the HPCS ESW PUMP control switch to START.

1P45C002 4.5.2 VERIFY the following:

• HPCS ESW PUMP DISCH VALVE starts opening.

1P45-F140

• WHEN the discharge valve reaches approximately 10% open, THEN the HPCS ESW PUMP starts.

1P45C002

• HPCS ESW PUMP DISCH VALVE opens fully.

1P45-F140 4.5.3 DIRECT Chemistry to perform the following:

• OBTAIN required samples per REC-0104.

• CHLORINATE HPCS ESW as required.

4.5.4 RECORD in the Narrative Log a Channel Check of ESW Effluent flow indication per the Technical Specification Rounds.

BOP Continues with HPCS startup.

7.9.4 REFER TO SOI-G42 and VERIFY the Suppression Pool Cleanup System is shutdown.

Verifies SPCU is shutdown.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

2 Page 4 of 20 Event

Description:

2

- Start HPCS in Test Mode to Suppression Pool Symptoms/Cue: From Turnover Time Position Applicants Actions or Behavior BOP Continues with HPCS startup.

7.9.5 VERIFY the HPCS SUPR POOL SUCTION VALVE is open.

1E22F015 7.9.6 VERIFY the HPCS CST SUCTION VALVE is closed.

1E22F001 7.9.7 TAKE the HPCS PUMP to START.

1E22C001 7.9.8 VERIFY the HPCS PUMP MIN FLOW VALVE opens.

BOP CAUTION Prior to opening 1E22-F023, the HPCS Pump must be running to prevent draining HPCS lines to the Suppression Pool which may result in severe water hammer.

7.9.9 WHILE performing the following step, VERIFY the HPCS PUMP MIN FLOW VALVE closes WHEN HPCS PUMP FLOW is >725 gpm.1E22F012 1E22R603 7.9.10 HOLD the HPCS TEST VALVE TO SUPR POOL in OPEN UNTIL one of the following conditions is met:

1E22F023

• HPCS PUMP FLOW indicates 7800 gpm 1E22-R603

• HPCS TEST VALVE TO SUPR POOL is full open.

1E22-F023 BOP Contact Maintenance Engineer to start HPCS pump vibration testing.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

3 Page 5 of 20 Event

Description:

3

- NCC A Pump trip Enter ONI-P43 Symptoms/Cue: ARI-H13-P970-B1 Time Position Applicants Actions or Behavior Driver

• When directed, insert Event 3.

• Role play as NLO as directed.

• If asked to investigate NCC A pump, report that you observe nothing abnormal.

• If asked to investigate NCC A breaker XH1102, report that the Overcurrent relay is tripped.

ATC Announce unexpected P970 alarm and give stability report.

BOP Announce NCC PUMP DISCH HEADER PRESSURE LOW alarm. Walkdown H13-P970 and determine NCC A Pump is not running.

BOP Review ARI-H13-P970-0001-B1, 4.1 REFER TO ONI-P43, Loss of Nuclear Closed Cooling.

Inform the SRO of entry condition for ONI-P43, Loss of Nuclear Closed Cooling SRO Enters ONI-P43, Loss of Nuclear Closed Cooling Evaluator The BOP should perform ONI-P43 Immediate Actions from memory without SRO direction Immediate Action 3.1 is N/A BOP The BOP will start a Standby NCC pump IAW the Immediate Actions of ONI-P43 3.0 Immediate Actions 3.2 Only one NCC Pump is running A Standby NCC Pump is available START a standby NCC Pump SRO Directs the BOP to perform Supplemental Actions of ONI-P43 BOP Reviews ONI-P43 Supplemental Actions and determines none are applicable and informs SRO

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

4 Page 6 of 20 Event

Description:

4

- APRM H fails upscale Symptoms/Cue: ARI-H13-P680-06-C4 Time Position Applicants Actions or Behavior Driver

• When directed, insert Event 4.

• Role play as I&C as directed.

• If asked to investigate APRM failure, report that you agree it looks failed and you will write a Notification and a CR.

ATC Announce multiple unexpected P680 alarms and give stability report.

ATC Announce APRM UPSC INOP/TRIP OPRM D/H TRIP & ROD BLOCK APRM UPSCALE alarms. Walkdown H13-P680 and determine that APRM H failed and informs SRO Reviews ARIs for possible cause and actions to perform and informs SRO:

• ROD BLOCK APRM UPSCALE 4.6 If an APRM has failed, then refer to SOI-C51 (APRM) and bypass it.

SRO Directs BOP/ATC to bypass APRM H and reset 1/2 scram.

BOP/ATC Perform SOI-C51(APRM), Average Power Range Monitor System to bypass APRM H 7.4 Bypassing an APRM Channel 7.4.1 Refer to Technical Specification Table 3.3.1.1-1 Item 2 for applicability.

7.4.3 Place the NEUTRON MONITOR BYPASS, APRM joystick on 1H13-P680, in the BYPASS position for the APRM Channel being bypassed. 1C51B-S6 CH H 7.4.4 Confirm that the BYPASS half of the APRM's DNSC/BYPASS status light is on.

7.4.5 Confirm that the APRM Bypass status light comes on at the selected APRMs Power Range Neutron Mon Panel. 1H13-P672 7.4.6 If the bypassed APRM channel caused any trips or alarms, then reset those trips or alarms.

ATC/BOP Perform SOI-C71, Reactor Protection System to reset the half scram.

7.4 Reset RPS 7.4.1 Verify the following:

• The conditions which caused the full or half scram have cleared.

• There is reasonable assurance that another scram signal will not be generated.

7.4.3 Verify the Manual Scram pushbuttons are not armed.

7.4.4 Momentarily depress the appropriate RPS division pushbuttons on P680: RPS B 1C71A-S5D

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

4 Page 7 of 20 Event

Description:

4

- APRM H fails upscale Symptoms/Cue: ARI-H13-P680-06-C4 Time Position Applicants Actions or Behavior ATC Inform SRO that APRM H was bypassed and the half scram was reset.

Evaluator Tech Spec require 3 Operable channels per trip system - LCO 3.3.1.1 is met SRO Evaluate Tech Specs and determine LCO 3.3.1.1 is met.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

5 Page 8 of 20 Event

Description:

5

- Shutdown HPCS Test Valve, E22-F023 Loses power Symptoms/Cue: ARI-H13-P601-16-D4 Time Position Applicants Actions or Behavior Driver

• When directed, call the Control Room as Maintenance Engineer and inform them that vibration testing is completed and is satisfactory and inform them that the HPCS pump may be shutdown.

• Role play as NLO as directed.

• If asked to investigate MCC EF1E1-L for E22-F023, report that the control power transformer is heat damaged and the control power fuse is blown.

• If directed to close E22-F023 locally, respond that the valve is stuck.

• If directed to S/D HPCS to secured status, initiate Event 27 to rack out breaker EH1304. Initiate Event 28 to open EF1E1-F for E22-F004 (inj valve) and initiate Event 29 to open EF1E1-C for water leg pump.

Shift Mgr If crew decides to not shutdown the HPCS pump, then direct the US shutdown the HPCS pump.

SRO Directs the BOP to shutdown the HPCS pump to standby Evaluator While closing 1E22F023, the valve will lose power while still partially open.

BOP Continues SOI-E22A, Section 7.9 7.9.11 WHEN desired to shutdown Full Flow Test to the Suppression Pool, THEN PERFORM the remaining steps of this section.

7.9.12 HOLD the HPCS TEST VALVE TO SUPR POOL in CLOSE UNTIL the HPCS PUMP FLOW is 500-600 gpm.

1E22F023 1E22R603 ATC Announce unexpected P601 alarm and give stability report.

BOP Announce HPCS OUT OF SERVICE alarm received.

BOP Recognizes the MOV POWER LOSS amber light illuminated on the status matrix, the loss of valve indication on 1E22-F023, and flow indicated on 1E22-R603 and informs the SRO.

SRO Evaluate Tech Specs T.S. 3.5.1 Action Previously evaluated when HPCS was started. RAs are still applicable.

T.S.3.6.1.3 Action A.1 - Isolate the affected penetration flow path - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Evaluator Isolation of the affected penetration flow path requires HPCS pump to be shutdown.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

5 Page 9 of 20 Event

Description:

5

- Shutdown HPCS Test Valve, E22-F023 Loses power Symptoms/Cue: ARI-H13-P601-16-D4 Time Position Applicants Actions or Behavior SRO Direct BOP to shutdown HPCS pump.

BOP Continues SOI-E22A, Section 7.9 7.9.15 Take the HPCS pump to stop.

1E22-C001 7.9.16 VERIFY the HPCS PUMP MIN FLOW VALVE closes 1E22-F012 Inform SRO that HPCS is shutdown.

Evaluator Shutdown of HPCS Room Cooler and HPCS ESW not required to be complete prior to continuing scenario.

SRO As time permits, direct BOP to continue SOI-E22A, Section 7.9 to shutdown the HPCS Room Cooler and HPCS ESW.

BOP Continues SOI-E22A, Section 7.9 7.9.18 If HPCS Pump Room Cooler is no longer required, then refer to SOI-M39 and shutdown to standby readiness.

7.9.19 If HPCS ESW in not required, then refer to SOI-P45/49 and shutdown the HPCS ESW loop to standby readiness.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

6 Page 10 of 20 Event

Description:

6

- Earthquake > OBE Enter ONI-D51 Initiate Normal Rx Shutdown & Start all ESW loops Symptoms/Cue: ARI-H13-P680-08-C3 Time Position Applicants Actions or Behavior Driver

• When directed, initiate Event 6. Then, call the control room as the Security Shift Supervisor and report that several Officers reported they felt an earthquake.

• Role play as directed.

• If asked about ERROR OR TROUBLE LEDs on local panel H51-P021 -

respond that none are illuminated.

• If asked about TRIGGER LEDs on local panel H51-P021 - respond that all are illuminated.

• Five minutes after earthquake, after being directed to local panel H51-P021, report OBE and CAV lights are illuminated.

• If asked about flooding in the buildings (Att.-2) - no flooding observed.

• If asked to investigate for leaks in underground piping, wait until after feedwater is lost to report that water us bubbling up from near the roadway south of the SW Pump house.

ATC Announce multiple unexpected alarms and give stability report.

ATC Announce SEISMIC ALARM P969 & multiple equipment vibration alarms.

Reviews ARI H13-P680-8-C3 for possible cause and actions to perform:

4.1 If personnel on site felt an earthquake, then go to ONI-D51 Earthquake.

4.2 Report indications from local panel H51-P021 to the Control Room.

Directs NLO to report to H51-P021 and report indications.

Evaluator The OBE ALARM light on P696 will illuminate 5 minutes after the earthquake.

Startup of ESW pumps is performed after the light illuminates.

A low pressure condition in the Service Water System will become apparent by a P970 alarm at the same time the OBE light illuminates. Service Water supplies keep-fill pressure to the Emergency Service Water Systems when they are in standby.

BOP Walks down P969 and observe seismic TRIGGER ALARM light illuminated and inform SRO.

Continues to monitor P969 for OBE light illumination SRO Enters ONI-D51 Earthquake Directs the BOP to perform ONI-D51 Supplemental Actions. (Critical Task 1 is Supplemental Action 4.5.2)

ATC Announces P970 alarm.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

6 Page 11 of 20 Event

Description:

6

- Earthquake > OBE Enter ONI-D51 Initiate Normal Rx Shutdown & Start all ESW loops Symptoms/Cue: ARI-H13-P680-08-C3 Time Position Applicants Actions or Behavior BOP Investigates P970 alarm and observes annunciator SW PUMP DISCH HEADER PRESSURE LOW alarm.

Announces above alarm to crew.

Throttles valve P41-F400 closed to raise header pressure to clear alarm.

May investigate recorder P41-R417 on P907 to determine SW flow trend is decreasing.

Reports results to SRO.

BOP Performs ONI-D51 Supplemental Actions.

4.1 DETERMINE magnitude of the earthquake in accordance with Section 1.0 Parameters from indications received at the following:

(Direct NLO to investigate Seismic Instrument Panel, H51-P021 at IBO/02 599.)

BOP 4.5 IF indications exist that OBE levels have been exceeded, THEN PERFORM the following concurrently:

4.5.1 PERFORM the following:

• REFER TO Attachment 2, Inside Actions and PERFORM the required actions.

• REFER TO Attachment 1, Safe Shutdown Buildings/Areas Inspection and INSPECT Safe Shutdown Buildings/Areas to ensure that Safe Shutdown capability is maintained.

• REFER TO Attachment 3, Outside Actions and PERFORM the required actions.

BOP (BOP starts all loops of ESW and ESW Pump House Ventilation) 4.5.2 REFER TO SOI-P45/49 and PERFORM the following:

• ESW Loop A (B) Manual Startup from Standby Readiness.

(Critical Task 1)

• HPCS ESW Manual Startup from Standby Readiness.

BOP/ATC 4.5.3 Evaluate the following plant parameters to determine the extent of any plant damage:

• Control rod positions

• Reactor power and water level

• Feedwater flow and Steam flow

• Generator load

• Condenser vacuum

• Turbine vibration and bearing temperatures

• Sump alarms and pump-out rates.

• Off-Gas flow rates

• Airborne, Process and Area Radiation Monitors

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

6 Page 12 of 20 Event

Description:

6

- Earthquake > OBE Enter ONI-D51 Initiate Normal Rx Shutdown & Start all ESW loops Symptoms/Cue: ARI-H13-P680-08-C3 Time Position Applicants Actions or Behavior BOP 4.5.5 IF Cumulative Absolute Velocity (CAV) has been exceeded, then perform a normal reactor shutdown in accordance with IOI-3, Power Changes and IOI-4, Shutdown.

Evaluator Power reduction not required to be observed prior to proceeding with next event.

SRO Directs crew to commence a normal reactor shutdown in accordance with IOI-3 starting at Section 4.7 ATC Commences lowering Rx power IAW Reactivity Plan (insert control rods - 1 group then Recirc Flow to 58 Mlbm/hr.)

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

7 Page 13 of 20 Event

Description:

7

- Earthquake causes leak in SLC tank Symptoms/Cue: ARI-H13-P601-19-F1 Time Position Applicants Actions or Behavior Driver

• Event 7 is initiated by Event 6 and will become apparent a few minutes after the earthquake.

• Role play as NLO as directed.

• If asked to investigate SLC tank leak, report that there is a cracked weld on the B pump suction line at the tank.

ATC Announce unexpected P601 alarm and give stability report.

BOP Announce SLC STORAGE TANK LEVEL HI/LO P601-19A, F1.

SRO Directs the BOP to report the level in the SLC Tank SRO Evaluate Tech Specs T.S. 3.1.7 Action A.1 - Restore SLC subsystem to operable status - 7 days B.1 - Restore one SLC subsystem to OPERABLE status - 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

8 Page 14 of 20 Event

Description:

8

- 2nd Earthquake causes Loss of Feedwater Enter EOP-01 Symptoms/Cue: ARI-H13-P680-03-D6, D7, & D8 Time Position Applicants Actions or Behavior Driver When directed, insert Event 8.

Call Control Room as Security SS to inform that aftershock reported by guards.

Evaluator Automatic and manual scram actions will not work. Also, if RPV level lowers to L2, automatic ARI will not insert rods. Control rods must be manually inserted.

ATC Announce 2nd earthquake and multiple unexpected alarms.

ATC Recognizes loss of all feedwater.

Informs crew of loss of feedwater and intent to scram the Rx.

Takes actions to scram the Rx.

BOP Make Plant announcement for the Scram and evacuate containment ATC Recognizes failure of Mode Switch and RPS pushbuttons and initiates ARI.

ATC Performs Scram Hard Card Actions:

1. VERIFY the following actions completed:

• Mode Switch Locked in Shutdown. (Note power once scram signal inserted)

• RPS Initiated, if all control rods are not fully inserted.

• ARI Initiated, if RPS failed to Scram the reactor.

Evaluator Step 2 below is N/A as Rx power is < 4%.

ATC

2. IF Reactor power is above 4%, THEN PERFORM the following:

ATC

3. STABILIZE Reactor level using Feedwater / RCIC / HPCS.

4. STABILIZE Reactor pressure using Turbine / Turbine Bypass valves / SRVs ATC

5. PERFORM crew update with the following information:

• The Mode Switch is locked in shutdown (RPS and ARI initiated if required)

• Reactor Power is ________________%

• Reactor Pressure is _______________psig

• Reactor Level is __________________inches

• EOP-01 Entry IS / IS NOT met ATC Inform SRO that 5 control rods are not fully inserted.

SRO Announce entry into EOP-01, RPV Control SRO Works way through EOP-01 chart and answers NO at Decision Diamond, Is the Reactor shutdown by control rods SRO Transitions to EOP-01-5, ATWS RPV Control

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.:

9 Page 15 of 20 Event

Description:

9

- Low power ATWS Enter EOP-01-5 Symptoms/Cue: Control Rod positions / Rod Full-In lights Time Position Applicants Actions or Behavior SRO Announces entry into EOP-01-5, ATWS RPV Control.

SRO Enters Power Control leg:

Directs ATC to perform EOP-SPI 1.1 through 1.7 to insert control rods.

Evaluator EOP-SPI 1.3 will be most expeditious method to insert the control rods.

ATC/BOP Coordinate to perform EOP-SPI 1.2 and/or 1.3 to insert control rods ATC Announce control rods are inserting.

Announce when all control rods are inserted.

SRO Enters Pressure Control leg:

Direct ATC to maintain pressure band of 800 to 1000 psig (nominal) or lower if required.

ATC Maintains RPV pressure in directed band.

Performs Pressure Control Hardcard actions if required SRO Enters Level Control leg:

Directs BOP to Inhibit ADS.

Direct BOP to verify Actuations and Isolations for L3 and L2.

Direct BOP to perform EOP-SPI 2.5, Bypass of RPV Interlocks.

Direct ATC to restore/maintain RPV level band of 178 to 219 inches (nominal) or -

25 to 100 inches (maximum) using one of more of the Table L-1 Injection Sources (Critical Task 2)

BOP Inhibits ADS.

Verifies Actuations and Isolations for L3 and L2.

Perform EOP-SPI 2.5, Bypass of RPV Interlocks.

ATC/BOP Determines RCIC did not auto start on Level 2 Evaluator RCIC failure to start continued on next event.

SRO Transition to EOP-01 when all control rods are inserted.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Event No.: 10 Page 16 of 20 Event

Description:

10 - RCIC auto start failure Symptoms/Cue: RPV level/RCIC Initiation Status Time Position Applicants Actions or Behavior Evaluator HPCS is unable to inject to the RPV due to the failed Test Valve BOP Recognize that RCIC failed to initiate on L2 and inform the SRO.

SRO Direct the ATC/BOP to start RCIC IAW EOP-SPI 6.6 (Critical Task 2)

Evaluator EOP-SPI 6.6 steps 1 and 2 may be performed from memory.

ATC/BOP Performs RCIC Start IAW EOP-SPI 6.6 2.0 IF RCIC is in Standby Readiness, THEN PERFORM the following:

2.1 ARM AND DEPRESS the RPV MAN INIT.

1E51A-S37 (ATC/BOP restores RPV level to directed band) (Critical Task 2)

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Page 17 of 20 Event

Description:

Scenario Termination Criteria Time Position Applicants Actions or Behavior

1. All control rods are inserted.

2. Emergency Service Water Pumps A & B are running.

2. Injects to establish RPV level between 150 and 219.

3. Lead Examiners discretion

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Page 18 of 20 Event

Description:

Critical Task 1 Time Position Applicants Actions or Behavior With low pressure indicated in the Service Water System and Emergency Service Water loops in Standby Readiness, start Emergency Service Water Pumps.

1.

Safety Significance:

Loss of ultimate heat-sink. The Service Water System supplies keep-fill pressure to the Emergency Service Water Loops. If keep-fill pressure is lost, the Emergency Service Water Loops must be placed in secured status.

2.

Cues:

Procedural compliance.

Service Water Header pressure.

Service Water flow

3. Measured by:

Emergency Service Water Pumps started in accordance with SOI-P45/49 as directed by ONI/ARI Actions within 10 minutes of indication of low Service Water Pressure.

4.

Feedback:

Emergency Service Water pump flow and pressure trends.

Emergency Service Water pump and valve indicating lights.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.: 3 - 96%

Page 19 of 20 Event

Description:

Critical Task 2 Time Position Applicants Actions or Behavior Prior to decision to Emergency Depressurize based on low RPV level, RCIC is manually initiated or started.

1.

Safety Significance:

Maintaining adequate core cooling.

2.

Cues:

RPV level indication.

3. Measured by:

RCIC is manually started and used for injection before decision to perform Emergency Depressurization is made (RPV Water Level -25 per Core Cooling Criteria Assessment (Table L-6 of EOP-01-5)).

4.

Feedback:

RPV level trend.

RCIC injection valve open.

Form 3.3-2 Required Operator Actions Op. Test No.: 2022-1 Scenario No.:3 - 96%

Page 20 of 20 Event

Description:

Procedures to verify clean Procedure Number Check IV Procedure Number Check IV ARI-H13-P601-19-F1 ARI-H13-P680-03-D6, D7, & D8 ARI-H13-P680-05(B7, B9, E10)

ARI-H13-P680-06 (C4, E5)

ARI-H13-P680-08-C3 ARI-H13-P970-B1 EOP & ONI Charts EOP-SPI 1.11.7 EOP-SPI 2.3 EOP-SPI 2.8 EOP-SPI-6.6 Hardcards - All ONI-C34 ONI-D51 ONI-P43 SOI-B33 P&Ls & Section 7.7 SOI-C51 (APRM) P&Ls & Section 7.4 SOI-C71 P&L & 7.4 SOI-E22A P&Ls & Section 7.2 & 7.9 SOI-G42 6.1 & 6.2 SOI-P45/49 P&Ls & Section 4.2 & 4.5 SRO Oversight Checklist TS 3.1.7 and Bases TS 3.3.1.1 and Bases and Table TS 3.5.1 and Bases TS 3.6.1.3 and Bases

ES-3.3, Page 16 of 17 Form 3.3-1 Scenario Outline Facility:

Perry Scenario #:

1. 4 - 1% Power Scenario Source:

New Op. Test #:

2022-1 Examiners:

Applicants/

Operators:

Initial Conditions: Plant startup following a planned shutdown is in progress per IOI-0002, Hot Startup, Section 4.5, with the Reactor currently at ~220 psig (Mode 2). RFBPs are in service on Low Flow Control. The MFP is tagged OOS. RPV Level band is 192 - 200 in. I&C is performing SVI-B21-T1176, RCS H/U & C/D surveillance.

HPCS was tagged out 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ago for a 10CFR Part 21 defect on the HPCS Pump breaker cell switch. The cell switch has been replaced and HPCS will be returned to service later this shift. Maintenance Services is demobilizing tools and equipment from ECCS rooms. Main Turbine Shell Warming time commenced 30 minutes ago. eSOMS Narrative Log is down. PSA Risk is Green and Grid Risk is Normal.

Turnover / Planned Activities: Withdraw control rods to obtain 80% open on #1 Bypass Valve then shift Feedwater from RFBPs to RFPT A. An NLO is on station to support the FW shift. Then, continue Reactor heat-up and transition into Mode 1 per IOI-0002 (Section 4.7). The RE recommends gang rod movement where not prohibited by the pull sheets. Make any Narrative Log entries on your note pads. Perform Prejob Briefs and Reactivity Briefs prior to entering the Simulator.

Critical Tasks:

1. Shut MSIVs to prevent exceeding 100 °F per hour cooldown rate

2. Emergency Depressurize when unable to maintain Suppression Pool level >14.25 feet Event No.

Malf.

No.

Event Type*

Event Description 1

R-ATC/SRO Continue startup and maintain Heat-up rate. (BPV-1 20-80% Open) 2 N-BOP/SRO Shift RFPT to Low Flow Controller 3

TS/SRO Inadvertent HPCS Initiation Tech Specs 3.3.5.1, 3.5.1, 3.3.6.1 4

C-BOP/SRO MC-BOP TS/SRO HPCS ESW Pump Discharge valve fails to open automatically Tech Spec 3.7.2 5

C-ATC/BOP/

SRO Short-circuit in Bypass Valve Jack control circuit causing depressurization resulting in excessive cooldown (SCRAM & Activities to minimize cooldown) 6 C-ATC/SRO CRD Suction Filter clogs and pump trips preventing manual control rod insertion (Able to restore CRD) 7 C-ATC/SRO MC-ATC One control rod fail to insert, shutdown criteria is met 8

M-All Dropped N2 cylinder in RHR C Pump Room. Supp Pool Leak Enter EOP-03 and EOP-02 C-Crew Water-tight door in RHR C Pump room wont close Enter EOP-01 and EOP-01-2 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Page 1 of 20 Event

Description:

N/A - Driver Instructions Time Position Driver Driver Simulator Setup:

Reset Simulator to IC 154 Load Schedule File: NRC 2022-SCEN-4.sch Verify Schedule File: NRC 2022-SCEN-4 Setup.sch loads Verify Schedule File: NRC 2022-Scen-4 Event 25.sch is in the SCHEDULE folder Verify Event File: NRC 2022-SCEN-1.evt loads Obtain pictures of RPV level instruments for P625 and 1B21-N673C and 1B21-N673G Trip Units.

Remove Requal IOI-3 and Rod Book from horseshoe.

Markup Crew Sheet to show who is supporting Turbine warm-up.

Add SYM STATUS placard with 1N62-F601 6% open Remove other SYM STATUS placards associated with Heater 5 isolation Driver Driver Verify Initial Conditions:

Reactor Power ~1%. A2_CYCLE19SU.SEQ Pull Sheets, Rods @ Step 10, Gang 26

@08.

IOI-2 at Step 4.5.10.

Verify IRM and SRM recorders are in SLOW speed.

Place yellow switch cap on:

• MFP & suction & discharge valves and oil pumps

• HPCS Pump & Injection valve Green Risk.

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Page 2 of 20 Event

Description:

N/A - Driver Instructions Time Position Driver Driver Initial Conditions:

Plant startup following a planned shutdown is in progress per IOI-0002, Hot Startup, Section 4.5, with the Reactor currently at ~220 psig (Mode 2). RFBPs are in service on Low Flow Control. The MFP is tagged OOS. RPV Level band is 192 -

200 in. I&C is performing SVI-B21-T1176, RCS H/U & C/D surveillance. HPCS was tagged out 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ago for a 10CFR Part 21 defect on the HPCS Pump breaker cell switch. The cell switch has been replaced and HPCS will be returned to service later this shift. Maintenance Services is demobilizing tools and equipment from ECCS rooms. Main Turbine Shell Warming time commenced 30 minutes ago.

eSOMS Narrative Log is down. PSA Risk is Green and Grid Risk is Normal.

Turnover: Planned activities.

Withdraw control rods to obtain 80% open on #1 Bypass Valve then shift Feedwater from RFBPs to RFPT A. An NLO is on station to support the FW shift. Then.

continue Reactor heat-up and transition into Mode 1 per IOI-0002 (Section 4.7).

The RE recommends gang rod movement where not prohibited by the pull sheets.

Make any Narrative Log entries on your note pads. Perform Prejob Briefs and Reactivity Briefs prior to entering the Simulator.

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Event No.

1 Page 3 of 20 Event

Description:

1 -

Continue startup and maintain Heat-up rate. (BPV-1 20-80% Open)

Symptoms/Cue: From Turnover Time Position Applicants Actions or Behavior Driver Role play as a Reactor Engineer as directed.

Evaluator Crew will need to pull ~1.5 gangs to get to ~ 3% power and BPV #1 ~80% open.

Shift Manager may intervene to prompt FW shift when Lead Examiner satisfied with power change SRO Direct ATC to raise Reactor Power and pressure with Control Rods and Pressure Set in accordance with SOI-C11(RC&IS), IOI-2 and the Reactivity Plan.

Provide Oversight.

ATC Raise Rx power and pressure to maintain Bypass Valve #1 between 20% and 80%

open in accordance with SOI-C11(RC&IS) & the Reactivity Plan with Control Rods SOI-C11(RC&IS), Rod Control And Information System 7.2 Rod Gang Selection 7.2.1 Momentarily depress DRIVE MODE to select GANG DRIVE mode.

7.2.2 Simultaneously depress the XX and YY coordinates for any rod member of that gang on the RSM to select the desired gang.

7.4 Notch Withdrawal for Single Rod or Gang 7.4.2 Select the single rod or rod gang.

7.4.3 Momentarily depress WITHDRAW.

7.4.4 Observe the following:

• The IN light comes on momentarily and goes off.

• The OUT light comes on and goes off after approximately 2 seconds.

• The RDM indicates the new rod position(s).

• The SETTLE light comes on for approximately 6 seconds and goes off.

• Expected changes occur in Nuclear Instrumentation.

• IF in gang withdrawal, then the new position is displayed in the GANG POSITION subsection of the RDM and the green STABLE status LED will be on.

ATC Monitor Main turbine bypass valve position for proper response to the power change.

Wait between notch withdrawals for BPV to stabilize.

ATC Range IRMs to maintain between 25/125 and 75/125.

Evaluator Following rod withdrawal and prior to raising Rx pressure, crew will need to perform feedwater shift.

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Event No.

2 Page 4 of 20 Event

Description:

2 -

Shift RFPT to Low Flow Controller Symptoms/Cue: From Turnover Time Position Applicants Actions or Behavior Driver

• Role play as an NLO as directed.

• If directed to crack open RFPT A discharge valve, N27-F100A, report you are on station. Wait 60 seconds then initiate Event 2. Report discharge valve is off closed seat.

SRO Direct BOP to shift RFPT A to the Low Flow Controller IAW SOI-C34 Provide oversight.

BOP Shifts RFPT A to the Low Flow Controller IAW SOI-C34 Section 7.3 7.3 Shifting from RFBP on Low Flow Control to RFPT Low Flow Control NOTES

• LOW FLOW CONTROLLER, 1N27-F175, maximum operating output is 1,400 gpm.

• Differential pressure across the Low Flow Control Valve may be allowed to exceed 100 psid, if required, to achieve higher feed flow rates. Time at above normal differential pressures should be minimized. A differential pressure of 400 psid should not be exceeded.

• The Margins and Limits Hardcard (OAI-1703) should be reviewed for this evolution.

7.3.1 Confirm the on-coming Reactor Feed Pump is idling at 1100 rpm with RFP Suction flow > 2000 gpm.

1N27-C002A NOTE The Low Flow Controller flowrate should be greater than 200 gpm to place the 1N27-F175 Controller into Automatic.

7.3.2 Verify the LOW FLOW CONTROLLER in AUTO.

1N27-F175 7.3.3 Verify the oncoming RECIRC FLOW CONTROLLER MINIMUM OUTPUT to 100%.

1N27-K162A_OP1 NOTE

• Opening RFP DISCH VALVE will make flow available to DFWCS

• A valve hook may be required to manually crack open the RFP DISCH VALVE. 1N27-F100A/B 7.3.4 IF the on-coming RFP DISCH VALVE is Closed, then perform the following:

1N27-F100A 7.3.4.a Crack open RFP DISCH VALVE.

1N27-F100A 7.3.4.b Hold the oncoming RFP DISCH VALVE in OPEN, until the valve is fully open.

1N27-F100A

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Event No.

2 Page 5 of 20 Event

Description:

2 -

Shift RFPT to Low Flow Controller Symptoms/Cue: From Turnover Time Position Applicants Actions or Behavior BOP NOTE Pressure indication is not available on DCS. It is available on ICS and analog meters.

7.3.5 Select FAST (500 rpm/min) on RFPT Speed Control Mode.

A 7.3.6 RAISE RFPT speed to maintain RFP discharge pressure 90-100 psig above Reactor pressure.

A Evaluator P between RFPT discharge pressure and RPV pressure will be >100 psig based on RFPT being at 1100 RPM. No speed change should be done.

BOP 7.3.7 CLOSE the FDW PUMPS BYPASS VALVE.

1N27-F200 NOTE The Low Flow Controller flowrate should be greater than 200 gpm to place the 1N27-F175 Controller into Automatic.

7.3.8 CONTROL RPV feed flow as follows:

• Control RPV Level using LOW FLOW CONTROLLER in MANUAL or AUTO. 1N27-F175

• Maintain RFP discharge pressure 90-100 psig above Reactor pressure.

BOP Inform SRO that feedwater shift is complete.

Evaluator Later, when RPV pressure is being raised, RO will need to adjust RFPT discharge pressure by increasing rpm.

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Event No.

3 Page 6 of 20 Event

Description:

3 -

Inadvertent HPCS Initiation Symptoms/Cue: ARI-H13-P601-16-C5 Time Position Applicants Actions or Behavior Driver

• When directed, insert Event 3.

• Role play as an NLO as directed.

• Verify pictures are hung on back-panel P625 prior to inserting event.

Evaluator Since the HPCS pump is tagged out, no injection will occur. However, the initiation signal will still cause the HPCS DG to start.

ATC Announce unexpected P601 alarm and give stability report.

BOP Investigate P601 alarm and announce HPCS RX LEVEL LO L2 alarm.

Observes 2 independent RPV level instruments and determines HPCS initiation is invalid and informs SRO.

Announce entry condition for ONI-E12-1.

SRO Announce entry into ONI-E12-1, Inadvertent Initiation Of ECCS/RCIC.

Direct BOP to perform ONI-E12 Supplemental Actions for inadvertent HPCS initiation.

BOP Reviews ONI-E12 Supplemental Actions for inadvertent HPCS initiation and determines that none are applicable.

Informs SRO that no Supplemental Actions are applicable.

BOP Reviews ARI and determines that the right combination of RPV level transmitter failure could cause an inadvertent HPCS initiation.

Walks down back panel P625 and observes failed level instruments.

Informs SRO that instrument 1B21-N673C is pegged low with TRIP and GROSS FAIL lights illuminated and 1B21-N673G is moving up and down.

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Event No.

3 Page 7 of 20 Event

Description:

3 -

Inadvertent HPCS Initiation Symptoms/Cue: ARI-H13-P601-16-C5 Time Position Applicants Actions or Behavior SRO Evaluate Technical Specifications TS 3.5.1 Action B.1 - Verify by admin means that RCIC is OPERABLE... - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND B.2 - Restore HPCS system to OPERABLE status - 14 Days TS 3.3.5.1 Action A.1 - Enter the Condition referenced in Table 3.3.5.1 Immediately (Identifies Function 3.a is applicable)

B.2 - Declare High Pressure Core Spray (HPCS) System inoperable - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from loss of HPCS injection capability.

B.3 - Place channel in trip - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TS 3.3.6.1 Action A.1 - Place channel in trip (Function 2.e) - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Event No.

4 Page 8 of 20 Event

Description:

4 -

HPCS ESW Pump Discharge valve fails to open automatically Symptoms/Cue: HPCS Automatic Initiation Time Position Applicants Actions or Behavior Driver

• Role play as an NLO as directed.

• This event does not require Driver initiation.

Evaluator The HPCS ESW pump will start if operator takes HPCS ESW discharge valve to Open or the pump to Start.

If the HPCS ESW pump is not started with ~5 minutes, the HPCS DG will receive a trip signal but will continue to run due to the LOCA signal.

BOP Observe HPCS ESW pump failed to auto start on HPCS initiation and informs SRO.

Attempts to start HPCS ESW pump by taking pump control switch to START or HPCS ESW Pump discharge valve to OPEN.

Inform SRO of HPCS ESW pump failure to auto start and that it was started manually.

OR If unable to start HPCS ESW pump, informs SRO of need to perform Emergency Shutdown of HPCS DG.

SRO If HPCS ESW pump not started, direct BOP to perform Emergency Shutdown of Div. 3 DG IAW SOI-E22B BOP If directed, performs Emergency Shutdown of Div. 3 DG IAW SOI-E22B, Section 6.4, Emergency Shutdown:

6.4.1 IF performing shutdown from ECCS Benchboard 1H13-P601, THEN PERFORM the following:

NOTE When operating the Diesel Generator control switch (from PULL-TO-LOCK to AUTO, or from AUTO to PULL-TO-LOCK), a deliberate pause in the STOP position is required in order to ensure proper operation of the associated circuitry.

6.4.1.a PLACE DIESEL GENERATOR in PULL-TO-LOCK.

6.4.1.b TAKE DIESEL GEN BRKR to TRIP.

EH13-01 Directs NLO to perform Step 6.4.1.c SRO Evaluate Technical Specifications TS 3.7.2 Action A.1 - Declare HPCS System inoperable - Immediately Note: TS 3.8.1 not required to be entered with HPCS declared inoperable.

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Event No.

5 Page 9 of 20 Event

Description:

5 -

Short-circuit in Bypass Valve Jack control circuit results in depressurization above reactor capacity resulting in excessive cooldown Symptoms/Cue: CV Amp In Control alarm resets and IRM need to be ranged down Time Position Applicants Actions or Behavior Driver

• When directed, insert Event 5.

• Role play as an NLO as directed.

ATC Observes CV AMP IN CONTROL alarm resetting and investigates P680 indications. Informs SRO that Main Turbine Bypass Valves are opening causing RPV pressure to lower.

SRO Directs ATC to insert a Rx scram.

ATC Inserts a manual Rx scram by locking the Mode Switch in SHUTDOWN.

Commence Reactor Scram Hardcard actions

1. VERIFY the following actions completed:

• Mode Switch Locked in Shutdown (Note power once scram signal inserted)

• RPS Initiated, if all control rods are not fully inserted

• ARI Initiated, if RPS failed to Scram the reactor

2. IF Reactor Power is above 4% OR unknown, THEN PERFORM the following:

3. STABILIZE Reactor level using Feedwater / RCIC / HPCS Evaluator Step 2 of the Reactor Scram Hardcard is N/A.

ATC

4. STABILIZE Reactor pressure using Turbine / Turbine Bypass valves / SRVs

5. PERFORM crew update with the following information:

• The Mode Switch is locked in shutdown, (RPS and ARI initiated if required)

• Reactor Power is

(~0%)

• Reactor Pressure is _______________psig

• Reactor Level is __________________inches

• EOP-01 Entry IS / IS NOT met

• IF MSIVs are closed, THEN a Time Critical Operator Action for Suppression Pool Cooling is applicable.

Time: _____________.

SRO Announce entry into ONI-C71-1, Reactor Scram

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Event No.

5 Page 10 of 20 Event

Description:

5 -

Short-circuit in Bypass Valve Jack control circuit results in depressurization above reactor capacity resulting in excessive cooldown Symptoms/Cue: CV Amp In Control alarm resets and IRM need to be ranged down Time Position Applicants Actions or Behavior SRO Direct ATC to perform Pressure Control Hardcard actions including closing MSIVs.

ATC Performs Pressure Control Hardcard actions:

1.0 IF RPV Pressure is lowering AND the MSIVs are OPEN, THEN PERFORM the following, UNTIL pressure control is returned to the turbine bypass valves:

a)

IF using the Turbine Bypass Valve Jack, THEN VERIFY Turbine Bypass Valve Jack is properly adjusted.

b)

RECORD the as found and VERIFY the following valves are CLOSED:

• AT H13-P870, CLOSE MSL drain valves 1N22-F340A-D as follows:

1) TAKE controller 1N22-R235 to 100%.

2) WHEN at least 10 seconds has elapsed, THEN TAKE controller 1N22-R235 to 0%.

• AT H13-P870, IF RFPTs are NOT being used for level control, THEN TAKE MST To RFPT A & B Supply Valve, 1N11-F100 to CLOSED.

• AT H13-P601

• MSL Low Point DRN Shutoff, 1B21-F015

• Shutoff Vlv Before Seat Warmup DRN, 1N22-F455

• Shutoff Vlv Before Seat Norm DRN, 1N22-F450

• INBD MSIV Before Seat Normal Drain, 1B21-F033

• INBD MSIV Before Seat Warmup Drain, 1B21-F021

• MSIV BYP VLV For MST Line Warm Up, 1B21-F020 c)

If RPV level is above L2 (130) and RCIC operation is not needed, then take the RCIC STEAM SHUTOFF, 1E51-F045 to CLOSE d)

The Reactor is Shutdown by Control Rod Insertion Reactor is NOT Shutdown by Control Rod Insertion Depressurization is not caused by a stuck open SRV MSIV closure directed by Unit Supervisor Cannot maintain cooldown rate 100 °F/hr (425 psig from Rated)

Then perform the following:

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Event No.

5 Page 11 of 20 Event

Description:

5 -

Short-circuit in Bypass Valve Jack control circuit results in depressurization above reactor capacity resulting in excessive cooldown Symptoms/Cue: CV Amp In Control alarm resets and IRM need to be ranged down Time Position Applicants Actions or Behavior (1) NOTIFY the Unit Supervisor that the MSIVs are being closed.

(2) VERIFY one or more the following control switches in CLOSE for each MSL:

(Critical Task 1)

INBD MSIV 1B21-F022B OTBD MSIV 1B21-F028B INBD MSIV 1B21-F022D OTBD MSIV 1B21-F028D INBD MSIV 1B21-F022A OTBD MSIV 1B21-F028A INBD MSIV 1B21-F022C OTBD MSIV 1B21-F028C Evaluator Temperature at 220 psig is 395.5 °F (Initial pressure)

Pressure at 295 °F is 47.5 psig (Lowest pressure W/I 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)

ATC Informs SRO that MSIVs are closed and Rx pressure has stabilized

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Event No.

6 Page 12 of 20 Event

Description:

6 -

CRD Suction Filter clogs and CRD pump trips preventing manual control rod insertion (Able to restore CRD)

Symptoms/Cue: ARI-H13-P601-22 H3 Time Position Applicants Actions or Behavior Driver

• Role play as an NLO as directed.

• If directed to shift or bypass CRD suction strainers, wait ~ 4 minutes then insert Event 19 and report complete.

ATC/BOP Observe H13-P601-22 alarms, CRD PUMP SUCTION FILTER DIFF PRESS HI &

CRD PUMP A TRIP SUCT PRESS LOW.

Inform SRO of CRD A pump trip.

Reviews ARI for Filter Differential Pressure High and directs NLO to shift or bypass suction filters IAW SOI-C11(CRDH), Section 7.3.

SRO Direct ATC/BOP to restart CRD pump following suction filter bypass or shift.

Evaluator The operators can use either SOI-C11(CRDH), Section 7.6, CRD Pump Trip Recovery or EOP-SPI 1.3 steps to restart a CRD pump. Either A or B pump can be started.

ATC/BOP Starts CRD pump IAW EOP-SPI 1.3:

7.4 NO CRD pump is running CRD PUMP A is available THEN AT H13-P601, PERFORM the following:

7.4.1 START CRD AUX OIL PUMP A.

C11-C002A 7.4.2 VERIFY blue PERM light is energized.

7.4.3 START CRD PUMP A.

C11-C001A

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Event No.

7 Page 13 of 20 Event

Description:

7 -

One control rod fail to insert, shutdown criteria met Symptoms/Cue: Full Core Display - Rod Position indication Time Position Applicants Actions or Behavior SRO Direct ATC/BOP to perform ONI-C71-1 Supplemental Actions to insert control rods.

ATC/BOP Perform ONI-C71-1 Supplemental Actions:

4.1 IF any control rod is NOT fully inserted, THEN PERFORM the following concurrently with this instruction:

4.1.1 REFER TO EOP-SPI 1.1 through 1.7 and INSERT Control Rods.

Coordinate to insert control rod IAW EOP-SPI 1.3.

Evaluator EOP-SPI 1.3 will be the most expeditious way to insert control rods.

The CRD pump will need to be restarted for EOP-SPI 1.3.

ATC/BOP Perform EOP-SPI 1.3 to insert control rods.

4.0 VERIFY the following keylock switches in BYPASS:

• AT H13-P629, LO POWER SET PT DIV 1 BYPASS C11A-S4

• AT H13-P618, LO POWER SET PT DIV 2 BYPASS C11A-S3 3.0 AT H13-P601, PERFORM the following:

3.1 VERIFY CRD HYDRAULICS FLOW CONTROL is in MANUAL.

C11-R600 3.2 ADJUST CRD HYDRAULICS FLOW CONTROL output to 100.

3.3 VERIFY CRD DRIVE PRESS CONTROL VALVE is CLOSED.

C11-F003 1.0 WHEN any CRD Pump is running, THEN PERFORM the following concurrently with the remainder of this procedure:

1.1 AT H13-P680, PERFORM the following to Insert all control rods to position 00:

• DEPRESS AND HOLD the IN TIMER SKIP pushbutton.

SELECT Control Rods as required.

ATC Inform crew when control rod insertion has commenced.

Inform SRO when all control rods are inserted.

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Event No.

8 Page 14 of 20 Event

Description:

8 -

Explosion in RHR C Pump Room. Suppression Pool Leak Symptoms/Cue: ARI-H13-P601-18 D3 Time Position Applicants Actions or Behavior Driver When directed initiate Event 8 and call the control room with the following:

Report as Maintenance Services that a large nitrogen cylinder in the overhead of the RHR C Pump room fell over and broke off the end cap and valve causing the cylinder to act like a rocket. It caused damage inside RHR C pump room and water is spraying out. Everybody got out of the room safely.

After AUX BLDG. EL 568 WATER LVL HIGH (H13-P870-03-C1) alarms, if asked about water in Aux 568, respond theres about 2 inches on the floor.

If directed to investigate RHR C suction valve MCC, report EF1D07-HH has 3 blown main line fuses.

BOP Direct NLO to investigate damage in RHR C pump room.

Driver As NLO, report water is spraying out of the RHR C suction valve. You cant get close enough to see exactly where the damage is. Also, the N2 cylinder damaged the watertight door and it cant be closed.

If asked water level is below the floor grating.

BOP Announce and investigate unexpected P601 alarm and announce RHR C PUMP ROOM SUMP LEVEL HIGH alarm and inform SRO of EOP-03 entry criteria.

SRO Enters EOP-03, Secondary Containment Control.

Directs BOP to monitor and control Secondary Containment Parameters.

Directs BOP to OPERATE available sump pumps for the affected areas and OPERATE cubicle sump drain valves as required.

BOP Directs Rad Waste control room to operate available sump pumps for the Aux Bldg.

Directs NLO to operate RHR C room cubicle sump drain valve as required.

SRO Continues EOP-03 actions:

Determines that Area Water Level cannot be restored and maintained.

Direct BOP to isolate RHR C by closing the RHR C pump suction valve.

BOP Attempts to close RHR C pump suction valve and reports loss of power to the valve.

SRO Continues EOP-03 actions:

Determines Control Room actions to isolate discharging system(s) are complete.

Answers NO to Decision Diamond, Is ANY primary system discharging into the affected area. And proceeds to HOLD box waiting for 2 or more areas to be above Max Safe water level.

BOP Announce and investigate unexpected P601 alarm and announce SUPR POOL LEVEL A(B) HI/LO alarms and reports pool level ~17.9 feet and lowering.

Informs SRO of EOP-02 entry criteria at 17.8 feet.

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Event No.

8 Page 15 of 20 Event

Description:

8 -

Explosion in RHR C Pump Room. Suppression Pool Leak Symptoms/Cue: ARI-H13-P601-18 D3 Time Position Applicants Actions or Behavior SRO Enters EOP-02, PRIMARY CONTAINMENT CONTROL:

Enters Suppression Pool Level Control leg and directs BOP to initiate SPMU.

Evaluator SPMU will not be able to be initiated. SPMU Valves G43-F030A(B) and G43-F040A(B) will not open at EOP-SPI 3.2 Step 4.6.

Driver If directed to use P11 to M/U to SP, respond that the valve wont open.

BOP Initiates SPMU IAW EOP-SPI 3.2:

3.0 VERIFY CNTMT POOLS SUPP ISOL is CLOSED.

G41-F100 4.0 IF SPMU is NOT INITIATED AND electric power is available, THEN INITIATE both divisions of SPMU as follows:

4.1 VERIFY the following keylock switches are in AUTO:

• SUPR POOL MAKE-UP A LOGIC G43-S6

• SUPR POOL MAKE-UP B LOGIC G43-S8 4.2 AT H13-P869, PLACE SUPR POOL MAKEUP A FULL FLW TEST PERM keylock switch in TEST.

G43-S13 4.3 AT H13-P868, PLACE SUPR POOL MAKEUP B FULL FLW TEST PERM keylock switch in TEST.

G43-S12 4.4 ARM AND DEPRESS the SUPR PL MAKE-UP A MANUAL INITIATION pushbutton.

G43-S5 4.5 ARM AND DEPRESS the SUPR PL MAKE-UP B MANUAL INITIATION pushbutton.

G43-S7 4.6 CONFIRM the SPMU valves are OPEN G43-F030A(B)

G43-F040A(B)

Inform SRO of SPMU failure and SP level trend.

SRO Continues EOP-02 actions:

Answer NO to Decision Diamond, Can Suppression Pool Level be maintained above 17.8 ft.

Determines that ED will be required before SP level lowers to 14.25 feet and enters EOP-01, RPV Control.

SRO Works through EOP-01 flowchart to ED Required IWE in the Pressure Control Leg.

Transitions to EOP-01-5, Emergency RPV Depressurization.

Directs RO to open all ADS valves. (Critical Task 2)

ATC/BOP Opens all ADS valves and reports status to SRO. (Critical Task 2)

SRO Answers YES to Decision Diamond, Are 6 or more SRVs Open and works to next HOLD box.

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Page 16 of 20 Event

Description:

Scenario Termination Criteria Time Position Applicants Actions or Behavior

1. All control rods are inserted

2. Reactor depressurized to less than or equal to 30 psig.

3. Injects to maintain level between 150 and 219.

4. Lead Evaluators discretion.

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Page 17 of 20 Event

Description:

Critical Task #1 Time Position Applicants Actions or Behavior With reactor pressure lowering due to open Bypass Valve, initiate action to prevent an RPV cooldown rate in excess of 100 °F per hour.

1.

Safety Significance:

Preclude exceeding Tech. Spec RPV cool down rate limit.

2.

Cues:

Procedural compliance.

RPV pressure trending down.

3.

Measured by:

Observation - RPV cooldown rate does not exceed 100 °F/hour, by performance of Pressure Control Hardcard actions and / or manual closure of the MSIVs.

4.

Feedback:

RPV pressure / temperature trend.

MSIV status indication.

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Page 18 of 20 Event

Description:

Critical Task #2 Time Position Applicants Actions or Behavior Perform Emergency Depressurization when Suppression Pool level cannot be maintained above 14.25 feet.

1. Safety Significance:

Precludes failure of Containment.

2. Cues:

Procedural compliance.

Suppression Pool level trend.

3. Measured by:

Observation - US determines (indicated by announcement or observable transition to appropriate EOP) that Emergency Depressurization is required before Suppression Pool level drops below 14.25 feet.

AND Observation - RO opens at least 6 SRV's during performance of Emergency Depressurization actions.

4. Feedback:

RPV pressure trend.

Suppression Pool temperature trend.

SRV status indication.

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Page 19 of 20 Event

Description:

Critical Task #3 Time Position Applicants Actions or Behavior

Form 3.3-2 Required Operator Actions Op-Test No.: 2022-04 Scenario No.: 4 - 1%

Page 20 of 20 Event

Description:

Procedures to verify clean Procedure Number Check IV Procedure Number Check IV All EOP Flowcharts All Hardcards ARI-H13-P601-16-C5 ARI-H13-P601-18-D3 ARI-H13-P601-22 H3 & G2 EOP-SPI 1.3 EOP-SPI 3.2 FTI-B0002 Sect 4.1 and 4.2 H13-P601-17 A2 & A5 and G3 & F3 ONI-C71-1 ONI-E12-1 PDB-I series SOI-C11(CRDH) Sect 7.6 SOI-C11(RC&IS) Sects 7.2 & 7.4 SOI-C34 Sect 7.3 SOI-E12 Sect 4.9 SOI-E22B Sect 6.4 TS 3.3.5.1 TS 3.3.6.1 TS 3.5.1 TS 3.7.2