ML100610543

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Initial License Exam, Proposed Scenarios
ML100610543
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 01/12/2009
From: Walton R
Operations Branch III
To:
FirstEnergy Nuclear Operating Co
References
ES-D-1
Download: ML100610543 (67)
v • d • e


Text

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 2 - 75% Op-Test No.: 2009-01 Examiners: Operators:

Initial Conditions: Reactor Power 72%. MOL Pull Sheets, Rods @ Step 55 at Position 48.

Power ascension is in progress. IOI-3 Step 4.5.35.

B CRD pump & C CBP in secured status.

Green Risk.

Suppression Pool Temperature 90°F due to leaking SRVs.

Turnover: Raise Rx Power to 75% with Recirculation Flow and then complete Step 56 of MOL Pull Sheets. Place RHR B in Suppression Pool Cooling to lower Suppression Pool Temperature.

Event Malf. No. Event Event No. Type* Description 1 mv05/mv08_ C (BOP) Place RHR B in Suppression Pool Cooling (BOP).

1e12f064b 1E12F0064B fails to Auto close then fails when full closed.

SRO Tech Spec 3.5.1 for RHR B, 3.6.1.3 for 1E12F064B (if position unknown) 2 EG05 C (ATC) Main generator voltage regulator failure in auto.

3 TH23A/ TH23B C (ATC) Reactor Recirc FCVs start to open after flow adjustment.

Arms and Depresses HPU shutdown pushbuttons to lock FCVs.

SRO Enters ONI-C51 Unplanned Change in Reactor Power. Tech Spec 3.4.1 Loop Flows R (ATC) Inserts Cram Rods 4 pt01_ 1c34- M Loss of Feedwater, EOP-1 RPV Control n04a/b/c C (BOP) HPCS fails to Auto Start. Start with Control Switch 5 RD16 M SDV rupture, EOP-2 Containment Control C (BOP) Containment Spray A will not initiate, transition to Containment Spray B or Emergency Depressurize

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

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 2 of 18 Event

Description:

Place RHR B in Suppression Pool Cooling Time Position Applicants Actions or Behavior Driver Driver Reset Simulator to IC-149 Driver Driver Load Schedule NRC_75.sch & NRC_Info.sch SRO Direct BOP to place RHR B in Suppression Pool Cooling BOP Place RHR B in Pool Cooling per SOI-E12 Section 4.4 4.4.2 Notify HP that a Suppression Pool evolution will be conducted 4.2.6 Close RHR B HX Bypass 1E12-F048B 4.2.7 Throttle RHR B HX Outlet Valve 1E12-F003B closed 18 to 20 seconds 4.2.8 Start RHR Pump B 1E12-C002B 4.2.10 Open RHR B Test Valve to SUPR Pool 1E12-F024B 4.2.11 Verify RHR Pump B Minimum Flow Valve 1E12-F064B closes when flow is greater than 1650 gpm NRC NRC Minimum Flow Valve will not close in Auto, Operator Closes and when it is full closed it will lose power BOP Report Failure of 1E12-F064B Driver Driver If sent to EF1D07-CC for E12F064B, no obvious problems Throttle RHR B HX Outlet Valve 1E12-F003B to obtain 7100 to 7300 gpm SRO Tech Spec for 1E12-F064B:

3.5.1 Condition A - 7 days 3.6.1.7 Condition A - 7 Days 3.6.2.3 Condition A - 7 Days 3.3.5.1 Conditions A - Immediately & Condition E - 1 hr 3.6.1.3 Condition A - if BOP reports unknown condition of 1E12-F064B SRO Assign BOP increased monitoring of RHR B to ensure it does not Operate at less than 1650 gpm for greater than 8 seconds or may direct RHR B be Shutdown.

BOP Performs increased monitoring or shuts down RHR B Pump

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 3 of 18 Event

Description:

Main Generator Voltage Regulator Failure Time Position Applicants Actions or Behavior Driver Driver Upon Lead examiner direction and while BOP Operator is placing RHR B in Pool Cooling, initiate Trigger 5, Main Generator Auto Voltage Regulator Failure ATC Respond to alarms on P680-09 B3 and D4, GENERATOR FIELD OVER VOLTAGE and AUTO VOLTAGE REGULATOR TRIP per ARIs Place Auto-Manual Voltage Regulator Selector switch in Manual Driver Driver Report Perry Grid HI VOLTAGE alarm. Restore to Schedule voltage Adjust Bus 1 Voltage to 349 KV, S42-R011 NRC NRC BUS 1 volts should be around 351 KV, prior to adjusting; grid voltage alarm @ 350.1 Kv

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 4 of 18 Event

Description:

Power increase Time Position Applicants Actions or Behavior Driver Driver After ATC adjusts power with A FCV insert Trigger 8, to fail A & B FCVs ATC Raise Reactor Power by opening Recirculation Flow Control Valves Monitor Reactor Power Maintain RFPT deviations near zero Maintain Loop Flows balanced Maintain Turbine Load Set 120 Mwe above turbine load NRC NRC With FCV failure in, A FCV will open and B FCV will not move ATC Respond to increasing Reactor Power, report A FCV opening Attempt to stop power increase by closing FCV A ONI-C51 Immediate Action - Arms and Depresses FCV A HPU Shutdown pushbutton Report FCV movement has stopped NRC NRC Depending on response time of Operator CV AMP in Control and Steam Bypass Valve Open alarms may come in ATC If CV AMP in Control or Steam Bypass open alarms are in, raises Load Set to close Bypass Valves SRO Enter ONI-C51 Unplanned Power Change

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 5 of 18 Event

Description:

ONI-C51 Unplanned Power Change Time Position Applicants Actions or Behavior SRO Direct ATC to monitor for Power oscillations Answer NO to, Is power in either Immediate Exit Region or Controlled Entry/Immediate Exit region?

Direct Reactor Engineer to perform ONI-SPI-G4 Answers YES to, Has an Unplanned Power Increase Occurred?

Direct ATC to Lower Power with FCV B ATC Attempt to lower Power with FCV; Reports B FCV will not move SRO Direct ATC to lower Power by use of Cram Rods to the Power level pre transient ATC Insert Cram Rods Step 55 Gang 50 Rods 30-07, 06-31, 34-31, 30-55, to position 00 SRO Answer YES to, Is Recirc Flow Mismatch greater than 10.4 Mlbm/hr?

Direct BOP to Record Loop Parameters per ONI-SPI-G2 Answer NO to, Is Recirc Flow Mismatch within limits?

Flow Mismatch is not with in limits Tech Spec 3.4.1 Condition A - 2 Hours Should also direct FCV B to be locked up, since it will not move.

ATC Arm and Depress FCV B pushbutton to prevent inadvertent movement of FCV B

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 6 of 18 Event

Description:

Loss of High Pressure Reactor Feedwater Pumps Time Position Applicants Actions or Behavior Driver Driver Upon Lead examiner direction, initiate Trigger 3 for a loss of feedwater due to narrow instruments failing high ATC Report Trip of Feed Pumps and places the Mode Switch in Shutdown Perform SCRAM Hardcard actions Verify the following actions completed:

  • Mode Switch Locked in Shutdown.

If Reactor Recirc Pumps are running in fast speed:

Then simultaneously take the following to XFER:

  • RECIRC PUMP A BRKR 5A
  • RECIRC PUMP A BRKR 5A Perform crew update with the following information:
  • The Mode Switch is locked in shutdown
  • Reactor Power is _______________
  • Reactor Pressure is _______________
  • Reactor Level is _______________

When generator load less than 90 MWe,

  • Verify Main Stop valves, Control valves and CIVs are shut
  • Verify Gen BRKRs S-610-PY-TIE and S-611-PY-TIE are open
  • Verify Gen Field Breaker open Insert Nuclear Instruments, SRMs & IRMs VERIFY HST LVL CV MANUAL CONTROL, N21-S19, IN OFF.

STABLIZE reactor water level.

  • HPCS STABLIZE reactor pressure:

a) Turbine / Turbine Bypass valves (REFER TO REACTOR SCRAM PRESSURE CONTROL HARDCARD) b) SRVs

  • Evacuate Containment
  • REFER TO REACTOR SCRAM PRESSURE CONTROL HARDCARD
  • Evaluate placing RCIC in pressure Control Mode BOP Recognize HPCS Pump fails to start at Level 2 then Start HPCS Pump BOP Recognize 1E51-F045 lost Power. Dispatch NLO to ED1A09-J Driver Driver If sent to ED1A09-J, found both mainline fuses blown

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 7 of 18 Event

Description:

EOP-1 RPV Control Time Position Applicants Actions or Behavior SRO Enter EOP-1 RPV Control at Level 2 Direct ATC to stabilize Reactor Pressure and Level Level Leg - Assign BOP to verify Isolations and Actuations for Level 2 & Level 3 BOP Perform Isolations and Actuation verification for Level 2 & 3 as time permits SRO Direct a Level Band of 150 to 215 inches. (Critical Task 4)

ATC Control Reactor Level in assigned band with HPCS by cycling 1E22-F004 HPCS Injection Valve (Critical Task 4)

SRO Pressure Leg - Direct a Reactor Pressure band of 600 to 1000 psig on Main Turbine Bypass Valves ATC Maintain pressure band with bypass valves and pressure control hardcard

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 8 of 18 Event

Description:

Pressure Control Hardcard Actions - if required Time Position Applicants Actions or Behavior ATC IF Reactor Pressure is lowering with pressure control on the Turbine Bypass Valves, THEN PERFORM the following:

VERIFY Turbine Bypass Valves properly adjusted IF RCIC turbine is running AND NOT needed for level control, THEN TRIP RCIC turbine.

RECORD the as found positions and VERIFY the following valves closed.

LATCH controller 1N22-R235, Main Turb Stop Valves Before Seat DRN Valve controller, by taking to 100% then to 0% to close the 1N22-F340A-D IF RFPTs are not being used for level control, THEN CLOSE MST To RFPT A & B Supply Valve, 1N11-F100 MSL Low Point DRN Shutoff, 1B21-F015 Shutoff Vlv Before Seat Norm DRN, 1N22-F450 Shutoff Vlv Before Seat Warmup DRN, 1N22-F455 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 CLOSE at least one of the following: (Notify the Unit Supervisor)

VERIFY OPEN MSL DRN & MSIV BYP OTBD ISOL, 1B21-F019 VERIFY OPEN MSL DRN & MSIV BYP INBD ISOL, 1B21-F016 OPERATE the following valves:

  • INBD MSIV Before Seat Warmup Drain, 1B21-F021 SRO Direct MSIVs Closed prior to exceeding a Cooldown rate of 100°F, pressure of 450 to 500 psig. (Critical Task 1)

ATC Close MSIVs if directed (Critical Task 1)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 9 of 18 Event

Description:

EOP-2 Containment Control, Containment Temperature Time Position Applicants Actions or Behavior Crew Report degrading Containment Temperature and Pressure SRO Enter EOP-2 Containment Control when Containment Temperature is 96°F Proceed through Containment Temperature HOLD step and Direct BOP to Operate all Containment Cooling Fans and Restore Containment Cooling per EOP-SPI 2.2 BOP Start the two non running Containment Cooling Fans Perform EOP-SPI 2.2 At H13-P871 Bay C Terminal Strip AA Terminal 9 remove and insulate wire P500717G At H13-P872 Bay C Terminal Strip AA Terminal 10 remove and insulate wire P500917G At H13-P872 Bay C Terminal Strip AA Terminal 14 remove and insulate wire P501017G AT 1H13-P800 Open P50-F060, P50-F150 and P50-F140 Direct an NLO to Start a P50 Chiller locally

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 10 of 18 Event

Description:

EOP-2 Containment Control, Containment Pressure Time Position Applicants Actions or Behavior SRO Proceed through Containment Pressure Hold step when Containment pressure exceeds 0.5 psig Before Containment Pressure Exceeds PSP determine Containment Spray is required.

(Critical Task 2)

In the If While Executing step, verify Containment Spray is required and Containment Pressure is above the Containment Spray Initiation Limit (CSIL); Direct an Operator to Initiate Containment Spray per EOP-SPI 3.1 (Critical Task 2)

BOP/ATC Perform EOP-SPI 3.1 for Containment Spray Loop A At 1H13-P629 Place CNTMT Spray A HI DW PRESS Bypass switch in Bypass E12A-S75 Confirm Containment Pressure above CSIL Arm and Depress CNTMT Spray A Manual Initiation button E12A-S63A NRC NRC Switch for Containment Spray A is failed. Containment Spray A will not initiate. Status of RHR B: If still available will initiate for Containment Spray B, If it is not available SRO will decide to Anticipate ED or to ED prior to exceeding PSP.

BOP/ATC Perform EOP-SPI 3.1 for Containment Spray Loop B (Critical Task 2)

At 1H13-P618 Place CNTMT Spray B HI DW PRESS Bypass switch in Bypass E12A-S76 Confirm Containment Pressure above CSIL Arm and Depress CNTMT Spray B Manual Initiation button E12A-S63B Verify RHR B Pump Running Verify Containment Spray Valves 1E12-F537B and 1E12-F028B Open BOP/ATC Terminate Containment Sprays prior to a Containment Pressure of 0 psig Take LPCI B Injection Valve Control Switch to Close 1E12-F042B Place CNTMT Spray B Manual Initiation button E12A-S63B in Disarm Depress CNTMT Spray B Seal In Reset E12A-S64B Close Containment Spray Valves 1E12-F537B and 1E12-F028B

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 11 of 18 Event

Description:

EOP-2 Containment Control, Drywell Pressure Time Position Applicants Actions or Behavior SRO Direct Terminate and Prevent of low pressure injection systems not required for adequate core cooling BOP Terminate and prevent LPCS - Close LPCS Injection Valve 1E21-F005, LPCI A & C -

Close LPCI A and C Injection Valves 1E12-F042A and 1E12-F042C NRC NRC IF RHR B was allowed to remain in Pool Cooling and it has not been started in Containment Spray yet, it will realign for LPCI injection and with the minimum flow valve failed it will not be protected. BOP Operator was assigned to monitor RHR B Flow, Opens 1E12-F024B to place back in Pool Cooling and provide minimum flow

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 12 of 18 Event

Description:

Contingent Anticipate ED (if RHR B was not used for Containment Spray)

Time Position Applicants Actions or Behavior SRO Prior to exceeding PSP (3.6 psig), with a Containment Pressure of 3.0 psig and MSIVs Open Direct ATC to Anticipate ED and Open All Bypass Valves ATC Opens Seven Bypass Valves

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 13 of 18 Event

Description:

Scenario Termination Time Position Applicants Actions or Behavior SRO Prior to exceeding PSP (3.6 psig) (Critical Task 3)

Enter EOP-4-2 Emergency Depressurization when Containment Pressure is less than PSP Answer YES to Is Reactor Shutdown?

Direct Operator to Open 8 ADS Valves ATC/BOP Opens 8 ADS Valves (Critical Task 3)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 14 of 18 Event

Description:

Scenario Termination Criteria Time Position Applicants Actions or Behavior

1. The reactor has been emergency depressurized prior to exceeding PSP OR Containment Spray was initiated preventing PSP from being exceeded.
2. Reactor Level is being maintained greater than 100 with HPCS
3. All Control Rods are Inserted
4. Cooldown rate was maintained less than 100 degrees in an hour as long as ED or Anticipate ED was not utilized.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 15 of 18 Event

Description:

Critical Task 1 Time Position Applicants Actions or Behavior Prevent from exceeding a 100 degree per hour cool down of the Reactor prior to Emergency Depressurization being required.

1. Safety Significance:

Precludes degradation of a fission product barrier

2. Cues:

Procedural compliance

3. Measured by:

Observation - Reactor Pressure Maintained above 450 psig

4. Feedback:

RPV pressure increasing MSIVs Closed if required

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 16 of 18 Event

Description:

Critical Task 2 Time Position Applicants Actions or Behavior With Containment pressure exceeding the Containment Spray Initiation Limit (CSIL), and prior to reaching the Pressure Suppression Pressure, initiate Containment Spray.

1. Safety Significance:

Precludes degradation of a fission product barrier.

2. Cues:

Containment pressure increase.

Procedural compliance.

3. Measured by:

Observation - When above the CSIL, Containment Spray is manually initiated prior to reaching the Pressure Suppression Pressure.

4. Feedback:

Containment pressure.

"CONTAINMENT SPRAY START SIGNAL RECEIVED" annunciator status.

Containment Spray flowrate.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 17 of 18 Event

Description:

Critical Task 3 Time Position Applicants Actions or Behavior When Containment Pressure cannot be maintained below the PSP limit, US determines that Emergency Depressurization is required and RO initiates Emergency Depressurization as directed by US.

1. Safety Significance:

Precludes failure of containment

2. Cues:

Procedural compliance High Containment Pressure

3. Measured by:

Observation - US determines (indicated by announcement or observable transition to EOP-04-2) that Emergency Depressurization is required before Containment pressure exceeds the PSP limit.

AND Observation - RO opens at least 5 SRV's during performance of Emergency Depressurization actions.

4. Feedback:

RPV pressure decreasing SRV open status indications

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 2 - 75% Page 18 of 18 Event

Description:

Time Position Applicants Actions or Behavior Prior to Reactor Level lowering to Top of Active Fuel, crew restores HPCS to control Reactor Level.

1. Safety Significance:

Maintain adequate core cooling by submergence

2. Cues:

Procedural compliance Reactor Level trend.

3. Measured by:

Observation - Reactor Level maintained greater than ZERO inches.

4. Feedback:

Reactor level trend HPCS Injection rate

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 4 - 3% Op-Test No.: 2009-01 Examiners: Operators:

Initial Conditions: Reactor Power 3%, MOL Pull Sheets, Rods @ Step 30 Gang 32 at Position 12.

Power ascension in progress.

IOI-2 Hot Startup Section 4.7.

RFBP B and NCC Pump C are Out of Service.

APRM A is bypassed for I&C SVI-C51-T0027A.

Reactor Engineer is available in the Control Room.

Turnover: Continue Power Ascension per IOI-2 Hot Startup. Place Circulating Water Pump C in service per SOI-N71 Circulating Water System. Hot Water Inlet MOVs 5 and 10 are closed and the fill and vent is complete on condenser train D Event Malf. No. Event Event No. Type* Description 1 R (ATC) Pull Control Rods per IOI-2 for Transfer to Run 2 N (BOP) Place Circulating Water Pump C in service 3 rd01r1819 C (ATC) Control Rod 18-19 Stuck at Position 12, will move to position 20 SRO Tech Spec 3.1.3 for Stuck Withdrawn Control Rod 4 RP01A C (Crew) RPS Bus A EPA Failure, Loss of RPS Bus A BOP Transfer RPS A to Alternate, Reset NS4 Isolation and recovery NM02G ATC IRM G Fails upscale, Bypass IRM G, Range IRMs and Reset 1/2 Scram mv06_ 1b21f019 SRO ONI-C71-2 Loss of RPS Bus, Tech Spec 3.3.1.1(IRM G), 3.3.1.3, 3.3.6.1, 3.3.2.1, and 3.6.1.3 (1B21F019) 5 PC04 M Suppression Pool Leak, EOP-3 Secondary Containment Control and EOP-2 Containment Control Emergency Depressurize EOP-4-2, on lowering Pool Level 6 ZD1E22F0004 C (BOP) HPCS Injection valve fails open. Override HPCS Pump to off cb04_1p42c0001a C (BOP) ECC A pump fails to auto start - manually start ECC pump

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

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 2 of 26 Event

Description:

Pull Control Rods per IOI-2 for Transfer to RUN Time Position Applicants Actions or Behavior Driver Driver Reset Simulator to IC-147 Driver Driver Load Schedule NRC_03.sch & NRC_Info.sch Driver Driver Place yellow switch caps on RFBP B and NCC Pump C Driver Driver Reactor Engineer recommends gang withdrawal SRO Direct RO to start a third Circulating Water Pump SRO IOI-2 step 4.7.1 Direct RO to withdraw rods until all APRM Downscale indicating lights are off and to perform IRM/APRM Overlap per step 4.7.17 ATC Withdraw Rods per US direction, Should withdraw gangs 32, 33 and start to withdraw 38.

Selects Correct Rod or Gang.

Gang 32 Rods are 10-27, 26-51, 50-35 and 34-11.

Gang 33 Rods are 26-11, 10-35, 34-51, and 50-27.

Gang 38 Rods are 18-19, 18-43, 42-43 and 42-19.

Withdraw Rods from position 12 to position 48 Monitor Reactor Power on IRM / APRM and Bypass Valve position When Rods are at Position 48 perform a coupling check

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 3 of 26 Event

Description:

Place Circulating Water Pump C in service Time Position Applicants Actions or Behavior BOP Start the third Circulating Water Pump per SOI-N41 Sect 4.3 4.3 Starting The Third Circulating Water Pump NOTE When adjusting pump discharge pressures, computer points N71BA035, N71BA036 and N71BA037 may be used in place of meters 1N71-R012A, B and C.

4.3.1 VERIFY the following are closed at Cooling Tower Flow Distribution Panel, 1H51-P273:

  • HOT WATER INLET MOV #10 1N71-F634 4.3.2 IF WHILE aligning condenser trains the oncoming condenser train inlet and outlet valves are both closed, THEN REFER TO Section 7.13, Filling and Returning an Isolated Main Condenser Section to Service, and RESTORE the Condenser train.

4.3.3 VERIFY the following valves are open for all condenser trains:

  • CIRC WATER PUMP DISCH PRESS between 36 and 48 psig, but as close as possible to 36 psig.
  • CIRC WATER PUMP AMPS less than 260.

4.3.5 WHILE observing the requirements of the following step, TAKE the third CIRW PUMP to START on 1H13-P870. 1N71-C001C 4.3.6 IF the oncoming discharge valve does NOT begin opening within 7 seconds, THEN IMMEDIATELY TAKE the oncoming CIRW PUMP to STOP.

4.3.7 VERIFY the third CIRW PUMP DISCH VALVE opens. 1N71-F020C 4.3.8 CONFIRM that CIRC WATER PUMP DISCH PRESS has stabilized. 1N71-R012C 4.3.9 THROTTLE the CIRW PUMP DISCH VALVE on each running pump to maintain the following on all 3 pumps:

  • CIRC WATER PUMP DISCH PRESS between 36 and 48 psig, but as close as possible to 36 psig.
  • CIRC WATER PUMP AMPS less than 260.

4.3.10 DIRECT Chemistry to align the Circulating Water Chemical Treatment System for the current Circulating Water System lineup in accordance with SOI-P83A.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 4 of 26 Event

Description:

Control Rod 18-19 Stuck at position 12 Time Position Applicants Actions or Behavior ATC Report Control Rod 18-19 will not move with normal drive pressure Driver Driver If asked for history, this rod needs 400 # to move SRO Direct use of Alternate Control Methods ATC Perform SOI-C11(RCIS) Section 7.25 7.25 Alternate Control Method Rod Initially at a Position Other Than 00 Driver Driver Inform SRO as the Reactor Engineer that Rod 18-19 does not have a settle condition.

ATC 7.25.2 RAISE CRDH drive differential pressure in 50 psid increments UNTIL

  • rod motion is possible
  • 500 psid is reached Driver Driver Once Drive water pressure is raise modify stuck rod failure (malfunction RD01R1819) to position 20.

ATC Withdraw Rod to 20; once again raise drive water pressure.

NRC NRC ROD will not move ATC 7.25.3 IF the rod is immovable at 500 psid, THEN REFER TO ONI-C11-1, Inability to Move Control Rods.

SRO Enter ONI-C11-1 ATC 7.25.5 IF NOT moving control rods in accordance with Tech Spec 3.10.6, THEN RETURN Drive Water Pressure to normal WHEN any one of the following condition is met:

  • The rod is at the withdrawal limit
  • Rod movement is suspended
  • The US/SO determine the elevated pressure is no longer needed

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 5 of 26 Event

Description:

ONI-C11-1 -- Control Rod 18-19 Stuck at position 20 Time Position Applicants Actions or Behavior SRO ONI-C11-1, Inability to Move Control Rods 3.1 MAINTAIN plant parameters as steady as possible.

4.12 IF a withdrawn rod is suspected to be stuck, THEN PERFORM the following:

4.12.1 DECLARE the control rod inoperable.

4.12.2 CONFIRM the stuck control rod does NOT occupy a location adjacent to:

  • Another withdrawn stuck control rod 4.12.3 REFER TO the following:
  • T.S. 3.1.4, Control Rod Scram Times SRO T.S. 3.1.3, Control Rod Operability Condition A1 -Immediately; Condition A2 -2 hrs; Condition A3 -N/A Condition A4 - working T.S. 3.1.4, Control Rod Scram Times - N/A Driver Driver As Reactor Engineer, will perform SVI (A4) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> SRO Direct disarming of rod 18-19 (A2)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 6 of 26 Event

Description:

Loss of RPS Bus A Time Position Applicants Actions or Behavior Driver Driver Upon Lead examiner direction initiate Trigger 10, Loss of RPS Bus A ATC/BOP Report Loss of RPS Bus A SRO Enter ONI-C71-2, Loss of One RPS Bus Driver Driver If sent to investigate RPS, found EPA A tripped - undervoltage is indicated - MG is coasting down Direct BOP to select alternate source A - ALT A BOP RPS A bus is de-energized MG SET TRANSFER switch is in NORM RPS Bus A GEN ALT AVAIL light on THEN PLACE the MG SET TRANSFER switch 1C71-S1in RPS Bus A Alternate Source on P640.

SRO 4.1.8 REFER TO the following Technical Specifications:

  • 3.3.1.3 Oscillation Power Range Monitor (OPRM) Instrumentation
  • 3.4.7, RCS Leakage Detection Instrumentation
  • ORM 6.2.2, Source Range Monitors Control Rod Block Instrumentation

4.1.10 VERIFY all SRV control switches on P601 are in AUTO.

4.1.11 VERIFY all SRV control switches on P631 are in AUTO.

4.1.12 VERIFY GROSS/FAIL TRIP/LATCH lights are reset at the following panels:

1H13-P692, 1H13-P693, 1H13-P691, 1H13-P694 4.1.13 REFER TO IOI-18 and RESTORE the following isolations as appropriate.

  • BALANCE OF THE PLANT ISOLATION (L2 /1.68#) RESTORATION 4.1.16 If required then OPEN the MSL DRN & MSIV BYP OTBD ISOL on P601.

1B21-F019

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 7 of 26 Event

Description:

Loss of RPS Bus A Time Position Applicants Actions or Behavior Technical Specification 3.3.1.1 for IRM G - Condition A (potential LCO) no actions ORM 6.2.3 for IRM G - no action Technical Specification 3.6.1.3 for B21-F019 - Condition A ORM 6.3.1.5 - 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> sample

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 8 of 26 Event

Description:

Bypass IRM G and Reset 1/2 Scram Time Position Applicants Actions or Behavior NRC NRC IRM G failed upscale on RPS bus loss ATC Observe/Report IRM G failed upscale SRO Direct ATC to Bypass IRM G per SOI-C51 ATC Bypass IRM G per SOI-C51(IRM) Sect 7.4 7.4.1 VERIFY that a valid IRM upscale trip does NOT exist on IRM to be bypassed 7.4.2 PLACE the NEUTRON MONITOR BYPASS switch, for the IRM Channel being bypassed, in the BYPASS position. 1C51A-S6 CH G 7.4.2 PLACE the NEUTRON MONITOR BYPASS switch, for the IRM Channel being bypassed, in the BYPASS position. 1C51A-S6 CH G 7.4.4 CONFIRM the BYPASSED IRM light on applicable Startup Range Rad Mon Panel comes on. CH G Driver Driver Inform when asked that back panel Bypass Light is lit ATC Ranges up on all Division 1 IRMs to clear trips ATC Reset RPS per SOI-C71 Sect 7.4 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.

7.4.4 MOMENTARILY DEPRESS the appropriate RPS division pushbuttons on P680:

  • INSTR VOLUME VENT VLV OPEN
  • INSTR VOLUME DRAIN VLV OPEN

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 9 of 26 Event

Description:

ONI-C71-2 Actions and IOI-18 Time Position Applicants Actions or Behavior BOP ONI-C71-2 Actions 4.1.10 VERIFY all SRV control switches on P601 are in AUTO 4.1.11 VERIFY all SRV control switches on P631 are in AUTO 4.1.12 VERIFY GROSS/FAIL TRIP/LATCH lights are reset at the following panels:

  • 1H13-P694 Driver Driver When asked the above light are reset BOP 4.1.13 REFER TO IOI-18 and RESTORE the following isolations as appropriate.
  • BALANCE OF THE PLANT ISOLATION (L2 /1.68#) RESTORATION 4.1.16 If required then OPEN the MSL DRM & MSIV BYP OTBD ISOL B21F019 Observe/Report B21-F019 lost power - dispatch NLO to investigate Driver Driver If asked, EF1A07-E for B21-F019 - all main line fuses are blown BOP IOI-18 Actions Perform Attachment 32 - BALANCE OF THE PLANT ISOLATION (LEVEL 2 / 1.68#)

1.0 CONFIRM the following alarms reset:

  • BOP ISOL DW PRESS HIGH H13-P601-19A-A6
  • BOP ISOL RX LEVEL LO L2 H13-P601-19A-B6 2.0 MOMENTARILY DEPRESS the following:
  • MSL & NS4 INBD ISOL SEAL IN RESET. B21H-S33 4.0 IF restoring an outboard isolation (Division 1), THEN PERFORM the following:

4.1 VERIFY the following open:

  • SA SUPPLY HDR CNTMT ISOL. P51-F150
  • CTS SUPPLY HDR CNTMT ISOL. P11-F060

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 10 of 26 Event

Description:

ONI-C71-2 Actions and IOI-18 Time Position Applicants Actions or Behavior 4.2 AT 1H13-P881, VERIFY the following are open:

  • PERS AL EL 603 OTBD ALRM ISOL P53-F070
  • PERS AL EL 692 OTBD ALRM ISOL P53-F075
  • PERS AL EL 692 SUPP AIR OTBD ISOL P52-F170
  • PERS AL EL 603 SUPP AIR OTBD ISOL P52-F160
  • DW EQUIP DRAIN OTBD DW ISOL G61-F035
  • DW FLOOR DRAIN OTBD DW ISOL G61-F155
  • CNTMT EQUIP DRAIN OTBD ISOL G61-F080
  • CNTMT FLOOR DRAIN OTBD ISOL G61-F170
  • RWCU BACKWASH OUT OTBD ISOL G50-F277
  • MIXED BED WTR CNTMT SUPPLY ISOL P22-F010
  • DW CO2 SUPPLY OTBD ISOL P54-F395 4.3 VERIFY the valves closed:
  • PERS AL EL 603 INNER DR AEGTS ISOL P53-F035
  • PERS AL EL 692 INNER DR AEGTS ISOL P53-F045 4.4 IF the Containment Airborne Radiation Monitor was in service, THEN VERIFY the following valves open:
  • CNTMT RAD MON OTBD SUCT ISOL D17-F081A
  • CNTMT RAD MON OTBD DISCH ISOL D17-F089A 4.5 IF the Drywell Airborne Radiation Monitor was in service, THEN VERIFY the following valves open:
  • DW RAD MON OTBD SUCT ISOL D17-F071A
  • DW RAD MON OTBD DISCH ISOL D17-F079A 5.0 IF Containment Vessel Chilled Water was in service, PERFORM the following:

5.1 AT H13-P800, VERIFY the following valves open:

  • CVCW OTBD SUPP ISOL VALVE P50-F060
  • CVCW OTBD RETURN MOV ISOL VALVE P50-F150
  • CVCW INBD RETURN MOV ISOL VALVE P50-F140 5.2 REFER to SOI-P50 and SHIFT chillers.

Direct an NLO to start a P50 chiller per SOI-P50 and SHIFT chillers.

6.0 TAKE the following to closed at 1H13-P800:

  • DW VAL RLF MOV ISOL VALVE M16-F010A
  • DW VAL RLF MOV ISOL VALVE M16-F010B 7.0 VERIFY the following are open at 1H13-P800:
  • CNTMT VAC RLF MOV ISOL VALVE M17-F015
  • CNTMT VAC RLF MOV ISOL VALVE M17-F025
  • CNTMT VAC RLF MOV ISOL VALVE M17-F035
  • CNTMT VAC RLF MOV ISOL VALVE M17-F045

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 11 of 26 Event

Description:

EOP-3 Secondary Containment Control - Suppression Pool Leak Time Position Applicants Actions or Behavior Driver Driver Upon Lead examiner direction initiate Trigger 2, Suppression Pool Leak Crew Receive/Acknowledge alarm H13-P601-18-D3 RHR C PUMP ROOM SUMP LEVEL HI Dispatch NLO to investigate Respond to Sump Room Alarm and Suppression Pool Level Alarms Driver Driver Report a large leak in RHR C Pump Room, door is severely damaged and can not be closed SRO Enter EOP-3 Secondary Containment Control on RHR C Sump Room Alarm.

Entry Condition met for Area Water Level, Proceeds through HOLD step NRC NRC No Primary system is discharging to area SRO Answers NO to Is any Primary System discharging into the affected area?

Wait in Hold Box for two (2) MAX SAFEs to shutdown Reactor (Critical Task 6)

NRC NRC May Shutdown Reactor Before Max Safe is reached Driver Driver 4 minutes after leak start, report water is over the grating in RHR C Room NRC NRC Water Over Grating is a MAX SAFE Condition SRO Direct BOP to Isolate RHR C Suppression Pool Suction Valve 1E12-F105 per ARI BOP Attempts to close RHR C Suppression Pool Suction Valve 1E12-F105 Observe/report 1E12-F105 lost indication NRC NRC 1E12-F105 looses power when taken to CLOSE Driver Driver If NLO sent to investigate, EF1D07-HH for 1E12-F105 has burnt control power transformer

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 12 of 26 Event

Description:

EOP-2 Containment Control - Suppression Pool Level Time Position Applicants Actions or Behavior SRO Enter EOP-2 Containment Control at less than 17.8 in the Suppression Pool Proceeds down Suppression Pool Level Control Leg Directs BOP to initiate SPMU per EOP-SPI 3.2 BOP Initiates SPMU Makeup AT H13-P869, PLACE SUPR POOL MAKEUP A FULL FLW TEST PERM keylock switch in TEST. G43-S13 AT H13-P868, PLACE SUPR POOL MAKEUP B FULL FLW TEST PERM keylock switch in TEST. G43-S12 ARM AND DEPRESS the following pushbuttons:

  • SUPR PL MAKE-UP A MANUAL INITIATION G43-S5
  • SUPR PL MAKE-UP A MANUAL INITIATION G43-S7 CONFIRM the following valves are OPEN:
  • SUPR PL MAKE-UP A FIRST SHUTOFF G43-F030A
  • SUPR PL MAKE-UP A SECOND SHUTOFF G43-F040A
  • SUPR PL MAKE-UP B FIRST SHUTOFF G43-F030B
  • SUPR PL MAKE-UP B SECOND SHUTOFF G43-F040B VERIFY CLOSED CNTMT POOLS SUPP ISOL G41-F100 SRO After SPMU is initiated, when Suppression Pool Level is approaching Less than 17.8.

Answer NO to Can Suppression Pool Level be maintained above 17.8?

Consider further actions to maintain Pool Level Should decide at this point that Pool Level CANNOT be maintained greater than 14.25 and transition to Emergency Depressurization (ED) (Critical Task 3)

Transition to EOP-1 RPV Control, EOP-1A Level and Power Control and then to EOP-4-2 Emergency Depressurization. (Critical Task 3)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 13 of 26 Event

Description:

ONI-C71-1 Reactor Scram (ATWS)

Time Position Applicants Actions or Behavior SRO Direct Reactor Scram Enter ONI-C71-1 ATC Scram the Reactor by taking the Mode Switch to SHUTDOWN and complete scram hard card actions Verify the following actions completed:

  • Mode Switch Locked in Shutdown.

If Reactor Recirc Pumps are running in fast speed:

Then simultaneously take the following to XFER:

  • RECIRC PUMP A BRKR 5A
  • RECIRC PUMP A BRKR 5A Perform crew update with the following information:
  • The Mode Switch is locked in shutdown
  • RPS was initiated (report failure)
  • ARI was initiated (report failure)
  • Reactor Power is _______________
  • Reactor Pressure is _______________
  • Reactor Level is _______________

When generator load less than 90 MWe, then perform the following:

  • Verify Main Stop valves, Control valves and CIVs are shut
  • Verify Gen BRKRs S-610-PY-TIE and S-611-PY-TIE are open
  • Verify Gen Field Breaker open Insert Nuclear Instruments,
  • Place recorders in IRM (leave A or E in APRM)

VERIFY HST LVL CV MANUAL CONTROL, N21-S19, IN OFF STABLIZE reactor water level.

a) Feedwater (REFER TO REACTOR SCRAM FEEDWATER HARDCARD) b) RCIC c) HPCS

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 14 of 26 Event

Description:

ONI-C71-1 Reactor Scram (ATWS)

Time Position Applicants Actions or Behavior STABLIZE reactor pressure:

a) Turbine / Turbine Bypass valves (REFER TO REACTOR SCRAM PRESSURE CONTROL HARDCARD) b) SRVs

  • Evacuate Containment
  • REFER TO REACTOR SCRAM PRESSURE CONTROL HARDCARD
  • Evaluate placing RCIC in pressure Control Mode SRO Direct a reactor water level band of 178 to 219 inches ATC Level Control should remain in Automatic with the Motor Feed Pump SRO Direct a Pressure Band of 800 to 1000 psig ATC/BOP Maintain pressure band with bypass valves and Pressure Control Hardcard IF Reactor Pressure is lowering with pressure control on the Turbine Bypass Valves, THEN PERFORM the following:

VERIFY Turbine Bypass Valves properly adjusted.

IF RCIC turbine is running AND NOT needed for level control, THEN TRIP RCIC turbine.

RECORD the as found positions and VERIFY the following valves closed.

LATCH controller 1N22-R235, Main Turb Stop Valves Before Seat DRN Valve controller, by taking to 100% then to 0% to close the 1N22-F340A-D IF RFPTs are not being used for level control, THEN CLOSE MST To RFPT A & B Supply Valve, 1N11-F100 MSL Low Point DRN Shutoff, 1B21-F015 Shutoff Vlv Before Seat Norm DRN, 1N22-F450 Shutoff Vlv Before Seat Warmup DRN, 1N22-F455 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 CLOSE at least one of the following: (Notify the Unit Supervisor)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 15 of 26 Event

Description:

ONI-C71-1 Reactor Scram (ATWS)

Time Position Applicants Actions or Behavior ATC/BOP IF RPV pressure is raising AND the MSIVs are closed, THEN PERFORM the following to control RPV Pressure:

VERIFY OPEN MSL DRN & MSIV BYP OTBD ISOL, 1B21-F019 VERIFY OPEN MSL DRN & MSIV BYP INBD ISOL, 1B21-F016 OPERATE the following valves:

ATC Insert Control Rods per EOP-SPI 1.3 (Critical Task 1) 2.0 VERIFY CRD HYDRAULICS FLOW CONTROL is in MANUAL. 1C11-R600 ADJUST CRD HYDRAULICS FLOW CONTROL output to 100 3.0 CLOSE CRD DRIVE PRESS CONTROL VALVE. 1C11-F003 5.0 WHEN any CRD Pump is running, THEN INSERT all control rods to position 00 concurrently with the remainder of this procedure as follows:

5.1 DEPRESS AND HOLD the IN TIMER SKIP pushbutton 5.2 SELECT the desired Control Rod 6.0 VERIFY the following keylock switches in BYPASS

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 16 of 26 Event

Description:

EOP-1A Level Power Control (Level Leg)

Time Position Applicants Actions or Behavior SRO Enter EOP-1 RPV Control and transition to EOP-1A Enter EOP-1A Level Power Control (Level Leg)

Direct Inhibit ADS (Critical Task 2)

ATC/BOP Inhibit ADS - Places ADS Inhibit switches in INHIBIT (Critical Task 2)

SRO Direct MSIV and ECCS interlocks per EOP-SPI 2.3 BOP As time permits, perform EOP-SPI 2.3 SRO Direct Terminate and Prevent Feedwater and ECCS Injection for Depressurization and wait in HOLD step until complete (Critical Task 4)

ATC Terminate and Prevent Feedwater (Critical Task 4)

  • Verify closed Heater 6A and 6B Bypass Valve 1N27-F135
  • Verify Low Flow Controller is Manual and the Low Flow Control Valve is Closed 1N27-F175 BOP Terminate HPCS
  • ARMS and DEPRESSES HPCS Manual Initiation pushbutton E22-S2 NRC NRC Control Switch for valve is Failed, BOP will need to take Pump Control Switch to STOP BOP Operator to stop HPCS pump

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 17 of 26 Event

Description:

EOP-1A Level Power Control (Level Leg)

Time Position Applicants Actions or Behavior BOP Terminate and Prevent Low Pressure ECCS (Critical Task 4)

Verify LOCA Bypass is in BYPASS for BUS XH11 and XH12 HOLD LPCS Injection Valve 1E21F005 and LPCI A Injection Valve 1E12-F042A in CLOSE ARM and DEPRESS LPCS and LPCI A Manual Initiation pushbutton E21A-S9 Verify Closed 1E12-F042A, 1E21-F005, 1E12-F053A, and 1E12-F023 HOLD LPCI B Injection Valve 1E12-F042B and LPCI C Injection Valve 1E12-F042C in CLOSE.

ARM and DEPRESS LPCI B and LPCI C Manual Initiation pushbutton E12A-S21 Verify Closed 1E12-F042B, 1E12-F053B, and 1E12-F042C NRC NRC Auto Start of ECC A pump Failed, BOP will need to take Pump Control Switch to START SRO May direct RHR C override to OFF ATC/BOP Report Terminate and Prevent is Complete

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 18 of 26 Event

Description:

EOP-4-2 Emergency Depressurization Time Position Applicants Actions or Behavior SRO Enter EOP-4-2 Emergency Depressurization (Critical Task 3)

Answers NO to Is Reactor Shutdown?

SRO Direct BOP Operator to Open 8 ADS Valves BOP Open 8 ADS Valves (Critical Task 3)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 19 of 26 Event

Description:

EOP-1A Level Power Control Time Position Applicants Actions or Behavior SRO Enter EOP-1A at T in the Level Leg Direct Operator to Restore and Maintain Level in Directed Level Band when Reactor Pressure is less than the MSCP Pressure of 140 psig (Critical Task 5)

ATC Restore Reactor Level to directed band (178 to 219) after Reactor Pressure is less than MSCP of 140 psig (Critical Task 5)

To restore level using feedwater - preferred:

1. Verify MFP in OFF
2. Verify FDW Pumps Bypass Valve is open, N27-F200
3. Slowly throttle Low Flow Controller in manual, 1N27-F175
4. If additional injection is required, then throttle Heater 6A and 6B FDW Bypass Valve, 1N27-F135 To restore level using RHR:
1. Restore level using RHR A or B outside the shroud:
2. IF directed to inject outside the shroud, THEN Perform the following:
3. Throttle Shutdown Cooling A/B to FDW Shutoff to the desired flowrate. E12-F053A/B

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 20 of 26 Event

Description:

Scenario Termination Criteria Time Position Applicants Actions or Behavior

1. Control Rods are being inserted
2. The reactor has been emergency depressurized prior to a Suppression Pool Level of 14.25
3. Feedwater or RHR is being used to maintain RPV level

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 21 of 26 Event

Description:

Critical Task 1 Time Position Applicants Actions or Behavior With a reactor scram required and the reactor not shutdown, initiate action to reduce power by inserting control rods.

1. Safety Significance:

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

2. Cues:

Procedural compliance.

3. Measured by:

Control Rod insertion commenced in accordance with Section 1.0 of EOP-SPIs.

4. Feedback:

Reactor Power trend.

Control Rod indications.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 22 of 26 Event

Description:

Critical Task 2 Time Position Applicants Actions or Behavior With reactor scram required and the reactor not shutdown, to prevent an uncontrolled RPV depressurization and subsequent power excursion, inhibit ADS.

1. Safety Significance:

Precludes core damage due to an uncontrolled reactivity addition.

2. Cues:

Procedural compliance.

3. Measured by:

ADS logic inhibited prior to an automatic initiation unless all required injection systems are Terminated and Prevented.

4. Feedback:

RPV pressure trend.

RPV level trend.

ADS "ADS OUT OF SERVICE" annunciator status.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 23 of 26 Event

Description:

Critical Task 3 Time Position Applicants Actions or Behavior When Suppression Pool level cannot be maintained above 14.25 feet the US determines that Emergency Depressurization is required, RO initiates Emergency Depressurization as directed by US.

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 EOP-04-2) that Emergency Depressurization is required before Suppression Pool level drops below 14.25 feet.

AND Observation - RO opens at least 5 SRV's during performance of Emergency Depressurization actions.

4. Feedback:

RPV pressure trend.

Suppression Pool temperature trend.

SRV status indication.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 24 of 26 Event

Description:

Critical Task 4 Time Position Applicants Actions or Behavior During an ATWS, when conditions with Emergency Depressurization required, Terminate and Prevent RPV injection from ECCS and Feedwater until reactor pressure is below the MSCP as directed by US.

1. Safety Significance:

Prevention of fuel damage due to uncontrolled feeding.

2. Cues:

Procedural compliance.

3. Measured by:

Observation - No ECCS injection prior to being less than the MSCP.

AND Observation - Feedwater terminated and prevented until less than the MSCP.

4. Feedback:

Reactor power trend, power spikes, reactor short period alarms.

Injection system flow rates into RPV.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 25 of 26 Event

Description:

Critical Task 5 Time Position Applicants Actions or Behavior With RPV pressure <MSCP, slowly increase and control injection into RPV to restore and maintain RPV level above MSCRWL (-25") as directed by US.

1. Safety Significance:

Maintaining adequate core cooling and preclude possibility of large power excursions.

2. Cues:

Procedural compliance.

RPV pressure indication.

3. Measured by:

Observation - Injection not commenced until less than MSCP, and injection controlled such that power spikes are minimized, level restored and maintained greater than or equal to -25".

4. Feedback:

RPV level trend.

RPV pressure trend.

Injection system flow rate into RPV.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 4 - 3% Page 26 of 26 Event

Description:

Critical Task 6 Time Position Applicants Actions or Behavior The Decision to Emergency Depressurize must be based on Suppression Pool Level. A misinterpretation of EOP-3 Secondary Containment Control and performing Emergency Depressurization based on exceeding Two Max Safes would be inappropriate

1. Safety Significance:

Emergency Depressurization based on NO Primary System Discharging

2. Cues:

Procedural misinterpretation

3. Measured by:

Early Decision to ED Suppression Pool Level greater than 17.8

4. Feedback:

Enters EOP-1 RPV Control from Secondary Containment EOP-3 Enters EOP-4-2 Emergency Depressurization from Secondary Containment EOP-3 HOLD step.

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 5 - 100% Op-Test No.: 2009-01 Examiners: Operators:

Initial Conditions: Reactor Power 100%. MOL Pull Sheets, Rods @ Step 57 at Position 6.

IOI-3 Step 4.5 is complete.

RCIC outage is in progress. Day 7 of 14 day LCO.

Yellow Risk.

Protected systems: HPCS and Div 3 DG, MFP, L10.

Turnover: Shift Stator Water Cooling Pumps and test pickup feature. NLO has been briefed and is on station. Lower Power to 90% to support surveillance testing.

Event Malf. No. Event Event No. Type* Description 1 R (ATC) Power reduction to 90%

2 N (BOP) Shift Stator Water Cooling Pumps A B and test pickup feature.

3 cb01_1n21c000 C (ATC) Hotwell Pump C trips, ATC starts Hotwell Pump A 1c 4 tf01_2r11s0003 C (Crew) Loss of LH-2-A Interbus Transformer, Loss of Div 1 Bus SRO ONI-R22-1, ONI-C11-1, ONI-P43. Tech Spec 3.5.1 and 3.5.3 HPCS and RCIC, 3.5.1 for RHR A and LPCS. 3.8.1 for Two DGs, 3.1.5 for Loss of CRD.

ATC Recover CRD Pump A or B within 20 minutes mv06_1p45f0140 C (BOP) ESW C Discharge Valve fails, Place Div 3 DG in Pull-to-Lock.

Loss of Div 3 Bus BOP Restores Div 1 Bus, closes in Preferred Source Breaker 5 Loss of Feed M No high pressure injection EOP-1 RPV Control Emergency Depressurize EOP-4-2, on lowering Reactor Level

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

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 2 of 23 Event

Description:

Lower Power to 90%

Time Position Applicants Actions or Behavior Driver Driver Reset Simulator to IC-146 Driver Driver Load Schedule NRC_100_Second_R1.sch & NRC_Info.sch Driver Driver Install Protected Train barriers for HPCS, MFP & Bus L10 SRO Direct Power Reduction to 90% for Surveillances, IOI-3 Attachment 3 Power Maneuvering ATC Lower Reactor Recirculation flow until power is 90%

Monitor Reactor Power Maintain RFPT deviations near zero Maintain Loop Flows balanced Maintain Turbine Load Set 120 Mwe above turbine load

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 3 of 23 Event

Description:

Shift Stator Water Cooling Pumps Time Position Applicants Actions or Behavior SRO Direct BOP to shift Stator Water Cooling Pumps from A to B and test pickup feature BOP Shift Stator Water Cooling Pumps from A to B per SOI-N43 Section 7.5 7.3.1 - PLACE the oncoming STATOR COOLING PUMP in ON.

7.3.2 - PLACE the offgoing STATOR COOLING PUMP in OFF.

7.3.3 - PLACE the standby STATOR COOLING PUMP control switch in STBY.

7.3.4 - IF desired to check the standby STATOR COOLING PUMP pickup feature, THEN PERFORM the following:

NRC NRC Stator Water Cooling Pump is started locally by NLO Driver Driver Insert Remote Function EG07 when directed by BOP Operator, and return to Normal when directed BOP 7.3.4.a through 7.3.4.c are in the field.

7.3.4.d - PLACE the offgoing STATOR COOLING PUMP control switch in OFF.

7.3.4.e - PLACE the standby STATOR COOLING PUMP control switch in STBY.

Driver Driver Acknowledge Local Alarms

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 4 of 23 Event

Description:

Hotwell Pump 'C in trip Time Position Applicants Actions or Behavior Driver Driver Upon Lead examiner direction, initiate Trigger 12. - Hotwell Pump C trip ATC Report trip of Hotwell Pump C ATC Start Hotwell Pump A verify Hot Surge Tank Level stabilizes Driver Driver If sent to investigate breaker, found overcurrent relays trip targets showing NRC NRC Depending on how long the ATC takes to start the Standby Hotwell Pump, Both RFPT Seal Injection Pumps may trip and then both will restart on Hotwell Pump Start.

BOP Discovers Two Seal Injection Pumps operating Place a Seal Injection Pump in Off Waits 5 seconds return the Pump to Standby

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 5 of 23 Event

Description:

LH-2-A Interbus Transformer Lockout, Loss of Division 1 and Division 3 Buses Time Position Applicants Actions or Behavior Driver Driver Upon Lead examiner direction Initiate Trigger 3 and as Field Supervisor, Report LH-2-A Trouble Alarm in Unit 2 Control Room BOP Inform Unit Supervisor that EH11 (Div 1) and EH13 (Div 3) are being supplied by LH-2-A Driver Driver When LH-2-A trips report LH-2-A Lockout Alarm ATC Report Power, Pressure, & Level are stable SRO Enter ONI-R22-1 Loss of Essential 4.16KV Bus 4.1 REFER TO the following instructions concurrently with this instruction:

  • ONI-P43, Loss of Nuclear Closed Cooling.

4.2 REFER TO IOI-18, Plant Emergency Instruction And Isolation Restoration AND RESTORE the following isolations as appropriate:

  • BALANCE OF THE PLANT ISOLATION (L2 /1.68#) RESTORATION 4.5 An EH Bus is de-energized The Diesel Generator failed to start Interbus Transformer LH-1-A is available LH-1-A is the preferred option to restore power to the bus quickly.

THEN PERFORM the following:

4.5.1.a - VERIFY the ALTN PREFERRED SOURCE BRKR is open. EH1115 4.5.1.b - CLOSE the PREFERRED SOURCE BRKR. EH1114 Direct BOP Operator to Perform ONI-R22-1 Step 4.5

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 6 of 23 Event

Description:

LH-2-A Interbus Transformer Lockout, Loss of Division 1 and Division 3 Buses Time Position Applicants Actions or Behavior BOP Report failure of HPCS ESW Pump to start, loss of indication on Discharge Valve 1P45-F140 Driver Driver If NLO is directed to check MCC EF1C12-H for 1P45F140 - found blown mainline fuses If NLO is directed to check valve locally - can not de-clutch valve handwheel BOP Place Division 3 DG in Pull-to-Lock BOP Restore EH11 - verify EH1115 is Open and Close EH1114 SRO Establish Restoration priorities: CRD Recovery is 1st - have 20 minutes from second accumulator fault. 2nd priority would be to recover one NCC Pump, and 3rd would be IOI-18 restoration SRO Tech Specs: HPCS and RCIC are Inoperable - 3.5.1 Conditions A, B, & C, Two DGs are Inoperable - 3.8.1 Condition A, B, & D.

Control Rod Scram Accumulators - 3.1.5 Condition A & B, 20 minutes to restore CRD after second accumulator fault or Mode Switch to Shutdown.

Driver Driver If the CREW goes to place the MODE Switch in SHUTDOWN, then initiate Trigger 7 Loss of Feedwater

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 7 of 23 Event

Description:

ONI-C11-1 and CRD Pump Trip recovery Time Position Applicants Actions or Behavior SRO Enter ONI-C11-1 Inability to Move Control Rods 4.1 - IF a CRD Pump is NOT operating, THEN REFER TO SOI-C11 (CRDH) and PERFORM CRD Pump Trip Recovery. Direct ATC to perform (Critical task 4) 4.2 - In Mode 1 or 2.

At least 2 CRD accumulators inoperable.

At least one inoperable accumulator is associated with a withdrawn control rod Reactor pressure 600 psig CRD PRESSURE CHARGING WATER indicating < 1600 psig.

THEN within 20 minutes PLACE the REACTOR MODE SWITCH in SHUTDOWN.

ATC Perform CRD PUMP TRIP RECOVERY - will start either CRD A or B Pump per SOI-C11(CRDH) section 7.6 (Critical task 4) 7.6 CRD Pump Trip Recovery 7.6.2 - TAKE the tripped CRD PUMP to STOP. 1C11-C001A 7.6.3 - TAKE the oncoming CRD AUX OIL PUMP to START 7.6.4 - CONFIRM the CRD PUMP TRIP OIL PRESS LOW alarm clears.

7.6.5 - PLACE the CRD HYDRAULICS FLOW CONTROL in Manual. 1C11-R600 7.6.6 - LOWER the CRD HYDRAULICS FLOW CONTROL output UNTIL the in-service CRD FLOW CONTROL VALVE is closed 7.6.7 - TAKE the oncoming CRD PUMP to START. 1C11-C001A, 1C11-C001B 7.6.8 - SLOWLY THROTTLE the in service CRD FLOW CONTROL VALVE UNTIL flow is restored on the CRD HYDRAULICS FLOW CONTROL.

7.6.9 - PLACE the CRD HYDRAULICS FLOW CONTROL in AUTO. 1C11-R600 7.6.10 - IF the tripped CRD Pump will NOT be re-started, THEN PERFORM the following:

7.6.10.a - TAKE the tripped CRD PUMP to STOP. 1C11-C001A 7.6.10.b - TAKE the CRD AUX OIL PUMP to STOP. 1C11-C002A Driver Driver When a CRD Pump is started remove accumulator faults Driver Driver If the CREW goes to put the MODE Switch in Shutdown, initiate the Loss of Feedwater Trigger 7

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 8 of 23 Event

Description:

ONI-P43 and CRD Start of Standby NCC pump Time Position Applicants Actions or Behavior SRO Enter ONI-P43, Loss of Nuclear Closed Cooling 4.1 - IF only ONE NCC pump is running, THEN REFER TO SOI-P43 and START the standby NCC pump. Directs (BOP) to perform.

BOP Perform Startup of Standby NCC Pump A per SOI-P43 Section 4.2 Additional NCC Pump Startup Driver Driver When directed:

4.2.1 - THROTTLE the oncoming NCC Pump Disch valve P43-F513A 10% open using Remote Function SW014 BOP 4.2.2 - TAKE the oncoming NCC PUMP control switch on Common Long Response Control Panel H13-P970 to START. P43-C001A Driver Driver When directed:

4.2.3 OPEN the oncoming NCC Pump Disch. P43-F513A using Remote Function SW014 BOP 4.2.4 - VERIFY NCC HDR PRESSURE on P970 stabilizes between 94 - 123 psig. P43-R221

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 9 of 23 Event

Description:

IOI-18, BOP Restoration Time Position Applicants Actions or Behavior BOP 4.1.13 - REFER TO IOI-18 and RESTORE the following isolations as appropriate.

  • BALANCE OF THE PLANT ISOLATION (L2 /1.68#) RESTORATION.

Attachment 32 - BALANCE OF THE PLANT ISOLATION (LEVEL 2 / 1.68#)

1.0 CONFIRM the following alarms reset:

  • BOP ISOL DW PRESS HIGH H13-P601-19A-A6
  • BOP ISOL RX LEVEL LO L2 H13-P601-19A-B6 2.0 MOMENTARILY DEPRESS the following:
  • MSL & NS4 INBD ISOL SEAL IN RESET. B21H-S33 4.0 IF restoring an outboard isolation (Division 1), THEN PERFORM the following:

4.1 VERIFY the following open:

  • SA SUPPLY HDR CNTMT ISOL. P51-F150
  • CTS SUPPLY HDR CNTMT ISOL. P11-F060 4.2 AT 1H13-P881, VERIFY the following are open:
  • PERS AL EL 603 OTBD ALRM ISOL P53-F070
  • PERS AL EL 692 OTBD ALRM ISOL P53-F075
  • PERS AL EL 692 SUPP AIR OTBD ISOL P52-F170
  • PERS AL EL 603 SUPP AIR OTBD ISOL P52-F160
  • DW EQUIP DRAIN OTBD DW ISOL G61-F035
  • DW FLOOR DRAIN OTBD DW ISOL G61-F155
  • CNTMT EQUIP DRAIN OTBD ISOL G61-F080
  • CNTMT FLOOR DRAIN OTBD ISOL G61-F170
  • RWCU BACKWASH OUT OTBD ISOL G50-F277
  • MIXED BED WTR CNTMT SUPPLY ISOL P22-F010
  • DW CO2 SUPPLY OTBD ISOL P54-F395 4.3 VERIFY the valves closed:
  • PERS AL EL 603 INNER DR AEGTS ISOL P53-F035
  • PERS AL EL 692 INNER DR AEGTS ISOL P53-F045 4.4 IF the Containment Airborne Radiation Monitor was in service, THEN VERIFY the following valves open:
  • CNTMT RAD MON OTBD SUCT ISOL D17-F081A
  • CNTMT RAD MON OTBD DISCH ISOL D17-F089A 4.5 IF the Drywell Airborne Radiation Monitor was in service, THEN VERIFY the following valves open:
  • DW RAD MON OTBD SUCT ISOL D17-F071A
  • DW RAD MON OTBD DISCH ISOL D17-F079A

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 10 of 23 Event

Description:

IOI-18, BOP Restoration Time Position Applicants Actions or Behavior BOP 5.0 IF Containment Vessel Chilled Water was in service, PERFORM the following:

5.1 AT H13-P800, VERIFY the following valves open:

  • CVCW OTBD SUPP ISOL VALVE P50-F060
  • CVCW OTBD RETURN MOV ISOL VALVE P50-F150
  • CVCW INBD RETURN MOV ISOL VALVE P50-F140 5.2 REFER to SOI-P50 and SHIFT chillers.

Direct an NLO to start a P50 chiller per SOI-P50 and SHIFT chillers.

Driver Driver When RO requests, start a P50 chiller using Remote Functions SWO95 -97 for CW pump start, SWO98 - 100 for start permissive, & SWO101-103 for chiller start BOP 6.0 TAKE the following to close at 1H13-P800:

  • DW VAL RLF MOV ISOL VALVE M16-F010A
  • DW VAL RLF MOV ISOL VALVE M16-F010B 7.0 VERIFY the following are open at 1H13-P800:
  • CNTMT VAC RLF MOV ISOL VALVE M17-F015
  • CNTMT VAC RLF MOV ISOL VALVE M17-F025
  • CNTMT VAC RLF MOV ISOL VALVE M17-F035
  • CNTMT VAC RLF MOV ISOL VALVE M17-F045

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 11 of 23 Event

Description:

Loss of Feed and Reactor Scram Time Position Applicants Actions or Behavior Driver Driver Upon Lead examiner direction, initiate Trigger 7 Loss of Feed ATC Report Computer Trouble alarms on digital feedwater system ATC Report Turbine Speed or Feed Rate degrading ATC May attempt to control with Manual Dial, will not work NRC NRC Loss of Power to RFPT Speed Control runs back RFPT speed to zero with no trip of Pump ATC/SRO Scram the Reactor ATC Perform SCRAM Hardcard actions Verify the following actions completed:

  • Mode Switch Locked in Shutdown.

If Reactor Recirc Pumps are running in fast speed:

Then simultaneously take the following to XFER:

  • RECIRC PUMP A BRKR 5A
  • RECIRC PUMP A BRKR 5A Perform crew update with the following information:
  • The Mode Switch is locked in shutdown
  • Reactor Power is _______________
  • Reactor Pressure is _______________
  • Reactor Level is _______________

When generator load less than 90 MWe,

  • Verify Main Stop valves, Control valves and CIVs are shut
  • Verify Gen BRKRs S-610-PY-TIE and S-611-PY-TIE are open
  • Verify Gen Field Breaker open Insert Nuclear Instruments, SRMs & IRMs VERIFY HST LVL CV MANUAL CONTROL, N21-S19, IN OFF.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 12 of 23 Event

Description:

Loss of Feed and Reactor Scram Time Position Applicants Actions or Behavior STABLIZE reactor water level.

  • HPCS STABLIZE reactor pressure:

a) Turbine / Turbine Bypass valves (REFER TO REACTOR SCRAM PRESSURE CONTROL HARDCARD) b) SRVs

  • Evacuate Containment
  • REFER TO REACTOR SCRAM PRESSURE CONTROL HARDCARD
  • Evaluate placing RCIC in pressure Control Mode

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 13 of 23 Event

Description:

EOP-1 RPV Control Time Position Applicants Actions or Behavior SRO Enter EOP-1 RPV Control at Level 2 Direct ATC to stabilize Reactor Pressure and Level Level Leg - Assigns BOP Isolations and Actuations for Level 2 & Level 3 BOP Perform Isolations and Actuations for Level 3 & Level 2 as time permits Report no High Pressure injection systems, Motor Feed Pump, RCIC and HPCS are not ATC available SRO Answer NO to, Can Reactor Level be restored and maintained above 130?

Direct EOP-SPI 4.1 CRD Alternate Injection and EOP-SPI 4.5 SLC Demin Alternate Injection ATC/BOP Perform EOP-SPI 4.1 and 4.5 Wait in Hold Step to answer Can Reactor Level can be restored and maintained above SRO 16.5?

Pressure Leg - Direct a Reactor Pressure band of 800 to 1000 psig on Main Turbine Bypass Valves ATC Control Reactor Pressure in designated band.

If Pressure begins to lower uses Pressure Control Hard Card to maintain Reactor Pressure

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 14 of 23 Event

Description:

EOP-1 RPV Control - Alternate Level Control Systems Time Position Applicants Actions or Behavior ATC/BOP Perform EOP-SPI 4.1 CRD Alternate Injection PLACE BUS XH11 LOCA BYPASS keylock switch in BYPASS PLACE BUS XH12 LOCA BYPASS keylock switch in BYPASS AT H13-P970, VERIFY only one NCC Pump is running VERIFY CRD HYDRAULICS FLOW CONTROL is in MANUAL. 1C11-R600 ADJUST CRD HYDRAULICS FLOW CONTROL output to 100 to maximize flow.

OPEN CRD DRIVE PRESS CONTROL VALVE. C11-F003 START the second CRD Pump as follows Direct an NLO to bypass the suction filters and to place an additional drive water filter in service Driver Driver Bypass CRD Pump Filters using Remote Function RD37 START CRD AUX OIL PUMP VERIFY blue PERM light is energized START CRD PUMP Direct the NLO to close the Minimum Flow Valves for CRD Pump A and B ATC/BOP Perform EOP-SPI 4.5 SLC Demin Alternate Injection COMMENCE injection into the RPV as follows VERIFY the following pumps are running:

SLC PUMP A and SLC PUMP B

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 15 of 23 Event

Description:

Pressure Control Hardcard Actions - if required Time Position Applicants Actions or Behavior ATC Maintain pressure band with bypass valves and pressure control hardcard IF Reactor Pressure is lowering with pressure control on the Turbine Bypass Valves, THEN PERFORM the following:

VERIFY Turbine Bypass Valves properly adjusted.

IF RCIC turbine is running AND NOT needed for level control, THEN TRIP RCIC turbine.

RECORD the as found positions and VERIFY the following valves closed.

LATCH controller 1N22-R235, Main Turb Stop Valves Before Seat DRN Valve controller, by taking to 100% then to 0% to close the 1N22-F340A-D IF RFPTs are not being used for level control, THEN CLOSE MST To RFPT A & B Supply Valve, 1N11-F100 MSL Low Point DRN Shutoff, 1B21-F015 Shutoff Vlv Before Seat Norm DRN, 1N22-F450 Shutoff Vlv Before Seat Warmup DRN, 1N22-F455 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 CLOSE at least one of the following: (Notify the Unit Supervisor)

VERIFY OPEN MSL DRN & MSIV BYP OTBD ISOL, 1B21-F019 VERIFY OPEN MSL DRN & MSIV BYP INBD ISOL, 1B21-F016 OPERATE the following valves:

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 16 of 23 Event

Description:

EOP-1 RPV Control - Level less than 16.5 Time Position Applicants Actions or Behavior SRO Answer NO to, Can Reactor Level be restored and maintained above 16.5?

Direct Operator to Inhibit ADS (Critical Task 1)

ATC/BOP Inhibits ADS, Places ADS A and B Inhibit switches in Inhibit (Critical Task 1)

SRO Direct BOP to start H2 Igniters and start H2 Analyzers BOP Start H2 Igniters by placing switches in ON BOP Start H2 Analyzers Start ESW Pumps A and B Starts ECC Pumps A and B Opens Comb Gas H2 ANAL Sample Valves Places Mode & Function Selector switch in Sample Places System Function switch in ON Directs an NLO to complete H2 Analyzer Startup in the field SRO Direct the Operators to align two or more injection systems: RFBP, LPCS, RHR B, and RHR C are available.

ATC Align RFBP for Injection - Open 1N27-F200 BOP Align/verify LPCS, RHR B and C for Injection SRO Answers YES to Can two or more systems be lined up?

SRO Wait for Reactor Level to lower to ZERO inches. (Critical Task 2)

SRO At Level One, MSIVs close, direct ATC to maintain 800 to 1000 psig pressure band with SRVs ATC Use SRVs to maintain directed Pressure band

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 17 of 23 Event

Description:

EOP-4-2 Emergency Depressurization Time Position Applicants Actions or Behavior SRO Enter EOP-4-2 Emergency Depressurization when RPV Level is less then Zero inches and above minus 25 inches. (Critical Task 2)

Answers YES to Is Reactor Shutdown?

Direct Operator to Open 8 ADS Valves ATC/BOP Open 8 ADS Valves (Critical Task 2)

ATC/BOP Control Injection rate once injection systems start to inject, RFBPs at about 270 psig and RHRs about 230 psig and LPCS about 450 psig (Critical Task 3)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 18 of 23 Event

Description:

EOP-2 Containment Control Time Position Applicants Actions or Behavior Crew After Emergency Depressurization three Containment Control Entry conditions should be reported. Suppression Pool Temperature, Suppression Pool Level and Drywell Temperature SRO Enter EOP-2 Containment Control For Drywell Temperature above 145°F, Direct all available Drywell Cooling Fans started and EOP-SPI 2.1 BOP Start all available Drywell Cooling Fans Perform EOP-SPI 2.1 Places NCC LOCA Bypass switch in Bypass P43-BS2, Opens P43-F215 and P43-F400 Places NCC LOCA Bypass switch in Bypass P43-BS1, Opens P43-F355, F410, F140 and F055 SRO For High Suppression Pool Temperature, transitions RHR B from Level Control to Pool Cooling when confident in LPCS, RHR C, and RFBPs ability to maintain RPV level BOP If Directed places RHR B in Suppression Pool Cooling Close 1E12-F042B LPCI Injection Valve Close 1E12-F048B RHR HX Bypass Valve Throttle Closed 1E12-F003B RHR HX Outlet Valve Open 1E12-F024B RHR Test Valve to SUPR Pool.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 19 of 23 Event

Description:

Scenario Termination Criteria Time Position Applicants Actions or Behavior

1. The reactor has been emergency depressurized after zero inches and before minus 25 inches.
2. Reactor Level is being maintained greater than 100
3. All Control Rods are Inserted

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 20 of 23 Event

Description:

Critical Task 1 Time Position Applicants Actions or Behavior To prevent an uncontrolled RPV depressurization and subsequent loss of Reactor Vessel inventory, inhibit ADS.

1. Safety Significance:

Precludes core damage due to loss of inventory.

2. Cues:

Procedural compliance.

3. Measured by:

ADS logic inhibited prior to an automatic initiation

4. Feedback:

RPV pressure trend.

RPV level trend.

ADS "ADS OUT OF SERVICE" annunciator status.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 21 of 23 Event

Description:

Critical Task 2 Time Position Applicants Actions or Behavior With an injection system(s) operating and the reactor shutdown and at pressure, after RPV water level drops to 0 inches, initiate Emergency Depressurization before RPV level lowers to -25 inches.

1. Safety Significance:

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

2. Cues:

Procedural compliance.

Water level trend.

3. Measured by:

Observation - At least 5 SRV's must be opened before RPV level lowers to -

25 inches.

4. Feedback:

RPV pressure trend.

SRV status indications.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 22 of 23 Event

Description:

Critical Task 3 Time Position Applicants Actions or Behavior With RPV pressure below the Shutoff Head of the available Low Pressure system(s), operate available Low Pressure system(s) to restore RPV water level above T.A.F. (0 inches).

1. Safety Significance:

Maintaining adequate core cooling.

2. Cues:

Procedural compliance.

Pressure below low pressure ECCS system(s) shutoff head.

3. Measured by:

Operator manually starts or initiates at least one low pressure ECCS system and injects into the RPV to restore water level above 0 inches.

4. Feedback:

Reactor water level trend.

Reactor pressure trend.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.: 2009-01 Scenario No.: 5 - 100% Page 23 of 23 Event

Description:

Critical Task 4 Time Position Applicants Actions or Behavior Within 20 minutes of 2nd accumulator fault following CRD pump trip, perform CRD PUMP TRIP RECOVERY - to start either CRD A or B Pump or crew places REACTOR MODE SWITCH in SHUTDOWN.

1. Safety Significance:

Prevent violation of facility license condition (T.S. 3.1.5).

2. Cues:

Procedural compliance.

HCU accumulator alarms.

3. Measured by:

Within 20 minutes of 2nd accumulator fault following CRD pump trip, the crew will start either CRD A or B Pump OR With all of the following present, 2 accumulators INOP, RPV pressure > 600 psig, CRD charging pressure < 1520 psig, and 20 minutes elapsed, crew immediately places the REACTOR MODE SWITCH in SHUTDOWN.

4. Feedback:

Reactor Power trend.

Control Rod indication

.

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