ML100690484

2009 Palisades Initial License Examination Administered Scenarios

ML100690484
Person / Time
Site:	Palisades
Issue date:	05/25/2009
From:	Valos N Operations Branch III
To:	Entergy Nuclear Operations
References
Download: ML100690484 (51)

Text

A ppendix D Scenario Outline Form ES-D-1 Facility: Palisades Scenario No.: ONE Op-Test No.: 1 Examiners: ____________________________ Operators:

Initial Conditions: 100% power with P-66B HPSI Pump tagged out.

Turnover:

P-66B HPSI Pump is tagged out for a coupling alignment and will be restored to operable in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Shift orders are to alternate running Service Water pumps and then lower power to approximately 87% at 4% per hour to perform Turbine valve testing on the next shift.

Event No.

Malf.

No.

Event Type*

Event Description 1

NA RO (N)

Alternate Running Service Water Pumps 2

NA SRO (N)

BOP (N)

RO (R)

Power Reduction 3

Override BOP (C)

SRO (C)

A Train CR HVAC Outside Air Damper fails closed 4

RP22A SRO (I, T)

RO (I)

Hot Leg RTD Failure Low 5

SG01A SRO (C, T)

BOP (C)

A S/G tube leak at 0.25 gpm (requires controlled shutdown).

Leak then rises to require a reactor trip. ( 0.4 gpm requires reactor trip.)

6 Override BOP (I)

C-02 Reactor Trip P/B fails (requires trip from C-06) 7 SG01A ALL (M)

SGTR on A S/G 8

Override RO (C)

Loop Injection MO-3066 fails to open on SIAS

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

Page 2 of 15 Scenario ONE - Simulator Operator Instructions Reset to IC 17 Hang Caution Tag on HPSI Pump P-66B (OOS) hand switch o RACKOUT breaker for P-66B using SI24 on PIDSI02 o Ensure EOOS indicates that P-66B is out of service Ensure SW Pumps P-7B and P-7C inservice INSERT the following OVERRIDES o Reactor Trip Pushbutton on Panel C-02 to OFF o MO-3066-1 to ON (HS stuck in close position) o MO-3066-R to OFF (red light off)

Create Event Triggers 5 and 6: Event: ZDI1P(171) [MO-3066 switch to OPEN position]

Create Event Trigger 7: Event: rdsr(13)<100 Create Event Trigger 8: Event ZDI6P(1060) [ V-96 switch to ON position] Action: dmf ANN-K-02-49 Create Event Trigger 9: Event ZDI6P(1070) [V-26A switch to ON position] Action: dmf ANN-K-02-49 Event #

Remote or Trigger #

Instructions 1

Alternate running SW Pumps-No actions required.

2 Power Reduction - No actions required.

3 REMOTE 1 Overrides HS-1673-D2-G (to ON), HS-1673-D2-R (to OFF), and ANN-K-02-49 (to ON) (Panel C-11A) CR HVAC Train A Outside Air Damper failed closed 4

REMOTE 2 RP22A (PIDRPNI1) Hot Leg #1 RTD Fail TE-0112H, Final Value = 0.0 REMOTE 3 SG01A (PIDSG01) Severity 0.025. Causes a S/G Tube Leak on A S/G.

5 REMOTE 4 Event: 0 Action: imf sg01a 0.40 [raises the severity of the tube leak to 4 gpm]

6 ACTIVE AT SETUP (override for reactor trip pushbutton on C-02 Panel)

TRIGGER 5 Action: dor MO-3066-1 TRIGGER 6 Action: dor MO-3066-R 7/8 TRIGGER 7 Action: imf sg01a 24.0 [raises severity of tube leak to 240 gpm]

Special instructions:

During SW Pp. swap, if called as Chemistry to recalculate mixing basin discharge flow volume, inform CR this is not required if they are alternating SW pps. When called as AO for SW Pp.

parameters, report discharge valve open, oil levels normal. Once P-7A has been started, when asked, report PI-1322 indicates 72 psig and stable; packing leakoff is NOT excessive.

Page 3 of 15 Scenario ONE - Turnover Information The plant is at 100% power. P-66B HPSI Pp. is tagged out for pump coupling alignment and will be restored to operable in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (LCO 3.5.2.B.1 - 72 hrs.). Shift orders are to alternate running Service Water pumps (Start P-7A and stop P-7B and place it in STDBY) and then commence a power reduction at 4% per hr. for performance of turbine valve testing on the next shift. GOP-8 has been completed up to Att. 1, Step 2.0.

Appendix D Required Operator Actions Form ES-D-2 Page 4 of 15 Op-Test No.: 1 Scenario No.: ONE Event No.:

1 Page _1_ of _1_

Event

Description:

Alternate Running Service Water Pumps Time Position Applicant's Actions or Behavior RO Refers to SOP-15, 7.1.1 and 7.1.2.

RO Starts P-7A SW pump.

Make PA announcement.

Check discharge valve, oil levels for P-7A (call to AO).

Remove P-7A from standby (place handswitch to TRIP).

Starts P-7A.

Check amps less than 92 amps.

Check local discharge pressure (call to AO).

Check packing leakoff not excessive.

Expected alarm: EK-1132 for P-7A basket strainer low dp (clears on its own)

RO Stops P-7B.

Note: Chemistry recalculation of mixing basin volume is NOT required.

RO Places P-7B to Standby Ensure P-7A and P-7C operating.

Depress STANDBY button on handswitch.

Check amber STANDBY light on.

Appendix D Required Operator Actions Form ES-D-2 Page 5 of 15 Op-Test No.: 1 Scenario No.: ONE Event No.:

2 Page _1_ of _1_

Event

Description:

Power Reduction Time Position Applicant's Actions or Behavior SRO BOP Ensure DEH is setup for 4% / hour load reduction.

ENTERS setter value SELECTS rate of 4% per hour SRO Reviews Precautions and Limitations of GOP-8.

RO BOP Reviews Precautions and Limitations of applicable SOPs RO INSERTS Group 4 Control Rods to less than 128 inches:

Control Rod joystick MANIPULATED to lower control rods RO Borates to commence downpower.

RESET BA and PMW Controllers if not already RESET SET quantity and batch flow limit on FIC-0210B, BA flow controller SET quantity and batch flow limit on FIC-0210A, PMW flow controller START BA Pump (P-56B preferred)

OPEN CV-2155, Make Up Stop Valve PUSH start pushbutton on FIC-0210B MONITORS reactor power and TAVE VERIFIES FIC-0210B output signal at zero when boration complete PUSH start pushbutton on FIC-0210A VERIFIES FIC-0210A output signal at zero when PMW flush complete CLOSES CV-2155 BOP Initiates turbine de-rate:

PUSHES GO pushbutton and observes white light illuminate Informs CRS/RO that turbine is in GO After power has been lowered 1%-2% OR at the discretion of the Lead Examiner, INSERT REMOTE #1

Appendix D Required Operator Actions Form ES-D-2 Page 6 of 15 Op-Test No.: 1 Scenario No.: ONE Event No.:

3 Page _1_ of _2_

Event

Description:

Train A CR HVAC Outlet Damper failed closed Time Position Applicant's Actions or Behavior Simulator Instructor: When event 3 is initiated, place placards on the back of C-11A showing DPIC-1659/1660 indicating '0' inches H2O BOP Diagnose loss of A Train CRHVAC:

Indications: D-2, Modulating Damper, fails closed; Control Room pressure indicates '0' inches H2O on DPIC-1659/1660 Major alarm: EK-0249, Control Room LOW Pressure DPIC-1659/1660 BOP Operator actions for EK-0249:

CHECK CR HVAC not operating per SOP-24, Ventilation and Air Conditioning System (D-2 is closed)

PLACE opposite CR HVAC train in service OR place operating train in Emergency Mode per SOP-24 Simulator Operator: If asked by NCO, report Turbine Building pressure indicates 0 inches H2O.

SRO Directs BOP to:

Place A Train CRHVAC in Emergency Mode per SOP-24, OR Place B train CR HVAC in service per SOP-24 Simulator Instructor: When CRHVAC is restored, post placards on the back of C-11A showing DPIC-1659/1660 indicating > 0.125 inches H2O BOP If directed by SRO, transfer CR HVAC to A Train to Emergency Mode per SOP-24, Section 7.7.9:

PLACE Control Switch for V-26A, Air Filter Unit Fan, to ON Verify Outside Air Damper or Modulating Damper is CLOSED (D-1 OR D-2)

Verify at least one Exhaust Fan Damper is CLOSED (D-18)

Verify at least one Purge Fan Damper is CLOSED (D-15)

Check remaining components status for Train A per procedure Ensure off Purge Fan V-94 and Switchgear Exhaust Fan V-47

Appendix D Required Operator Actions Form ES-D-2 Page 7 of 15 Op-Test No.: 1 Scenario No.: ONE Event No.:

3 Page _2_ of _2_

Event

Description:

Train A CR HVAC Outlet Damper failed closed Time Position Applicant's Actions or Behavior BOP If directed by SRO to place CR HVAC to B Train inservice per SOP-24, Section 7.7.2:

ENSURE Control Switch for V-26A, Air Filter Unit Fan, in AUTO PLACE Control Switch for VC-11, Condensing Unit, to OFF/RESET When VC-11 has pumped down and stopped:

ENSURE Control Switch for V-96, Air Handling Unit Fan, PLACED to ON PLACE Control Switch for V-95 to AUTO PLACE Control Switch for VC-11 to AUTO ENSURE Control Switch for VC-10 in AUTO CHECK indications for 'A' train being stopped:

o Outside Air Damper, D-1, closed o

Modulating Damper, D-2, closed o

Recirc Damper, D-3, closed o

Discharge Damper, D-4, closed CHECK indications for 'B' train being placed in service:

o Outside Air Damper, D-8, open o

Modulating Damper, D-9, mid-position o

Recirc Damper, D-10, open o

Recirc Damper, D-11, open SRO Refer to Technical Specifications and determine the following 30-day required actions MAY conservatively be entered for the inoperable A CR HVAC train:

LCO 3.7.10.A.1 At the discretion of the Lead Examiner, INSERT REMOTE #2

Appendix D Required Operator Actions Form ES-D-2 Page 8 of 15 Op-Test No.: 1 Scenario No.: ONE Event No.:

4 Page _1_ of _1_

Event

Description:

Hot Leg RTD Failure LOW Time Position Applicant's Actions or Behavior RO Diagnoses low failure of Loop #1 Thot signal

- EK-0967, LOOP 1 LOOP 2 TAVE DEVIATION, alarms

- EK-0968, LOOP 1 TAVE/TREF GROSS DEVIATION, alarms

- EK-06 Rack D 04, NUCLEAR - T POWER DEVIATION T-INLET OFF -

NORMAL/CALCULATOR TROUBLE CHANNEL A Lowering of calculated T Power and TM/LP trip setpoint for channel 'A' TI-0112HA and TIA-0111H, Loop 1 Hot Leg Temperature, indicate low RO Checks ARP-5 and ARP-21 for alarms present: report to CRS that ONP-13 needs to be referenced.

May also reference SOP-1A, attachment 1 for PCS Temperature Instrumentation functions.

May check T Power for the PIP Node and the SPI Node/Host Computer on a workstation and compare to actual heat balance power SRO May enter ONP-13, TAVE/TREF Controller Failure (none of the actions apply)

SRO Refers to and implements the following Tech Spec/ORM LCOs:

3.3.1.A (Table 3.3.1-1 Items 1 and 9), 7 day action statement 3.3.8.A (Table 3.3.8-1 item 4), 30 day action statement ORM 3.17.6 (Item 12.1), Prior to next MODE 1 entry from MODE 2 NOTE: Have the Shift Manager surrogate tell the CRS to direct the BOP operator to relieve the ATC operator so they can perform the next task.

RO Bypass the Variable High Power Trip and the TM/LP Trip for Channel A per SOP-36 (does not need to be in-hand)

1. Insert bypass keys (288 & 297) above affected RPS Trip Unit.

2. Turn key 90º clockwise.

3. Verify lit yellow light above bypass keyswitch.

4. Log evolution in the Reactor Logbook SRO Initiates troubleshooting and repairs After RPS has been bypassed OR at the discretion of the Lead Examiner, INSERT REMOTE #3

Appendix D Required Operator Actions Form ES-D-2 Page 9 of 15 Op-Test No.: 1 Scenario No.: ONE Event No.:

5/6/7/8 Page 1 of 7 Event

Description:

'A' Steam Generator Tube Leak/Rupture/Plant Trip Time Position Applicant's Actions or Behavior SRO BOP RO Diagnoses Steam Generator Tube Leak on A S/G:

EK-1364, GASEOUS WASTE MONITORING HI RADIATION alarms Monitors PZR level, pressure Monitors VCT level Charging-Letdown mismatch SRO RO BOP Notes trends on any of the following:

RIA-0631, Condenser Off-Gas Monitor RIA-2323, Main Steam Gamma Monitor (B S/G)

RIA-2324, Main Steam Gamma Monitor (A S/G)

RIA-0707, Steam Generator Blowdown Monitor RIA-2325/2326, Stack Gas Effluent Monitors RIA-2327, High Range Noble Gas Monitor SRO BOP Uses ONP-23.2, Att.1 and/or Att.2 or PPC Page 540 to calculate leak rate.

Calculates leak rate of ~ 0.25 gpm. May also use DWO-1 method (15 min)

Simulator Operator: If asked as Chemistry, PCS Gas Total Isotope activity = 0.57 µCi/cc SRO A S/G tube leak is identified and quantified, determines that plant shutdown per GOP-8 must occur (Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />). Action level 3 SRO Determines that Tech. Spec. 3.4.13.B applies - 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to MODE 3, 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to MODE 5. (> 150 gpd)

SRO Have HP determine dose rates on C-42 cation columns Have HP perform surveys per EOP Supplement 14 May have chemistry sample S/Gs for lithium and activity Simulator Operator: Inform control room that cation surveys for 'A' S/G indicate a higher than normal dose rate.

Appendix D Required Operator Actions Form ES-D-2 Page 10 of 15 Op-Test No.: 1 Scenario No.: ONE Event No.:

5/6/7/8 Page 2 of 7 Event

Description:

'A' Steam Generator Tube Leak/Rupture/Plant Trip Time Position Applicant's Actions or Behavior BOP/RO Isolates S/G Blowdowns by closing the following valves on panel C-13:

CV-0704, Blowdowns to mixing basin CV-0739, 'A' S/G Surface B/D CV-0767, 'A' S/G Bottom B/D CV-0771, 'A' S/G Bottom B/D CV-0738, 'B' S/G Surface B/D CV-0768, 'B' S/G Bottom B/D CV-0770, 'B' S/G Bottom B/D SRO BOP May raise RIA-0631, Condenser off-gas monitor, setpoint on back of panel C-11 BOP Operates turbine generator controls on the DEH panel for shutdown:

Enters setter value Selects rate of 30% per hour Pushes GO and observes white light energize Informs CRS/RO that turbine is in "GO" Simulator Operator: Once plant de-rate commences AND S/G Blowdowns for 'A' S/G are isolated, raise severity of leak to 4 gpm by INSERTING REMOTE #4 (

ALL Diagnoses that leak rate has risen to above 0.4 gpm. Requires reactor trip SRO Directs Reactor Trip Plant Trip RO Attempts Reactor trip from C-02 Panel, does not function BOP DEPRESSES C-06 Panel Reactor Trip Pushbutton (CRITICAL TASK PL-000 447 05 01)

Appendix D Required Operator Actions Form ES-D-2 Page 11 of 15 Op-Test No.: 1 Scenario No.: ONE Event No.:

5/6/7/8 Page 3 of 7 Event

Description:

'A' Steam Generator Tube Leak/Rupture/Plant Trip Time Position Applicant's Actions or Behavior RO Reactivity Control: YES: reactor was tripped from C-06 Panel Reactor power lowering negative SUR maximum of one control rod not inserted BOP Main Turbine Generator criteria: YES Main Turbine tripped Generator disconnected from grid BOP Feedwater criteria: YES:

PLACES Main FWP Controllers to MANUAL and RAMPS to minimum speed Main FRV and B/Ps CLOSED BOP Vital Auxiliaries-Electric:

Buses 1C and 1D energized: YES Bus 1E energized: NO (if SIS present)

Bus 1A and 1B energized: YES Y-01 energized: YES Six DC Buses energized: YES 3 of 4 Preferred AC Buses energized: YES

Appendix D Required Operator Actions Form ES-D-2 Page 12 of 15 Op-Test No.: 1 Scenario No.: ONE Event No.:

5/6/7/8 Page 4 of 7 Event

Description:

'A' Steam Generator Tube Leak/Rupture/Plant Trip Time Position Applicant's Actions or Behavior RO PCS Inventory Control: YES OR NO (Depends on Plant conditions)

PZR level 20% - 85%

PZR level trending 42% - 57%

PCS 25°F subcooled IF NO, would be on PCS being 25°F subcooled (NO CONTINGENCY) or PZR Level < 20% (CONTINGENCY: All available Charging Pumps in service and Orifice Stop Valves Closed)

RO PCS Pressure Control: NO Contingency - manually operates PZR heaters and spray, heaters will be off due to low PZR level, spray valves closed. When PCS pressure is

< 1605 psia, verify safety injection initiated, EK-1342 in alarm and all available HPSI and LPSI pumps in service and valves open Notes MO-3066, HPSI Train 2 to PCS Loop 1B, did not open, opens MO-3066 on panel C-03 (CRITICAL TASK PL-000 433 05 01)

If PCS pressure is < 1300 psia, stop A and D PCPs.

RO Core Heat Removal: YES At least one PCP operating Verify Loop T less than 10°F Verify PCS at least 25°F subcooled BOP PCS Heat Removal: YES Verify at least ONE S/G level 5% to 70% with Feedwater available (AFW to

'A' S/G may be isolated)

Verify TAVE between 525°F and 540°F Verify BOTH S/G pressures between 800 psia and 970 psia May start AFW Pump P-8A manually using start switch on panel C-01

Appendix D Required Operator Actions Form ES-D-2 Page 13 of 15 Op-Test No.: 1 Scenario No.: ONE Event No.:

5/6/7/8 Page 5 of 7 Event

Description:

'A' Steam Generator Tube Leak/Rupture/Plant Trip Time Position Applicant's Actions or Behavior RO Containment Isolation: YES Verify containment pressure less than 0.85 psig BOP Containment Isolation:

Containment Area Monitors CLEAR: YES Condenser Off Gas Monitor, RIA-0631, CLEAR: NO Main Steam Line Monitor: NO RO Containment Atmosphere: YES Verify temperature less than 125°F Verify Containment pressure less than 0.85 psig RO Vital Auxiliaries - Water: YES Verify at least two Service Water Pumps operating Verify BOTH Critical SW Header Pressures greater than 42 psig Verify at least one CCW Pump operating RO Vital Auxiliaries - Air: YES Instrument Air header pressure greater than 85 psig BOP Verify BOTH of the following: YES At least one Condensate Pump operating At least one Cooling Tower Pump operating BOP PLACES left or right train CRHVAC in emergency mode (depending on action chosen in event 3) :

STARTS V-26A OR V-26B, Air Filter Unit Fan ENSURES OFF: V-94, Purge Fan; V-47, Switchgear Exhaust Fan

Appendix D Required Operator Actions Form ES-D-2 Page 14 of 15 Op-Test No.: 1 Scenario No.: ONE Event No.:

5/6/7/8 Page 6 of 7 Event

Description:

'A' Steam Generator Tube Leak/Rupture/Plant Trip Time Position Applicant's Actions or Behavior ALL Diagnose 'A' S/G as affected SRO MAY direct isolating AFW to A S/G BOP When directed, isolates AFW to A S/G:

SELECTS MANUAL on FIC-0737A SELECTS MANUAL on FIC-0749 Raises output to 100% on each controller (RED signal indicator to the full right position)

SRO Performs EOP-1.0, attachment 1, Event Diagnostic Flow Chart Diagnoses a SGTR and enters EOP-5.0, Steam Generator Tube Rupture Recovery SRO Directs PCS cooldown to below 524°F on Loop Thots RO Commences a cooldown of the PCS:

Selects manual on PIC-0511 Adjusts signal on controller to achieve desired TBV position Monitors S/G pressures and cooldown rate Controls 'B' S/G level 60 - 70 %

BOP Perform SIS checklist, EOP Supplement 5 (SAT)

SRO/RO Establish PCS temperature and pressure control bands BOP/RO Closes Letdown orifice isolation valves on Panel C-02:

Places control switches for CV-2003, CV-2004, CV-2005, to CLOSE

Appendix D Required Operator Actions Form ES-D-2 Page 15 of 15 Op-Test No.: 1 Scenario No.: ONE Event No.:

5/6/7/8 Page 7 of 7 Event

Description:

'A' Steam Generator Tube Leak/Rupture/Plant Trip Time Position Applicant's Actions or Behavior SRO Direct chemistry to sample S/G for lithium and activity (if not previously performed per ONP-23.2)

SRO Direct EOP supplement 4, HPSI flow verification, completed SRO When lowest hot leg temperature is < 524 °F, orders A S/G isolated per EOP Supplement 12 BOP Performs EOP Supplement 12 to isolate A S/G inside control room (CRITICAL TASK PL-000 209 05 01):

If removing heat using the TBV, ensures MO-0501, 'B' S/G MSIV Bypass valve is open Closes 'A' S/G MSIV Bypass Valve, MO-0510 (if open for cooldown)

Closes MSIVs on panel C-01 Closes 'A' FRV, CV-0701, on panel C-01 Closes 'A' FRV Block valve, CV-0742, on panel C-01 Closes CV-0749, CV-0737, CV-0737A, AFW to 'A' S/G (if not performed earlier), on panel C-01 Closes 'A' S/G Blowdown Valves CV-0767, CV-0771, CV-0739, on panel C-13 (if not performed earlier)

Directs AO to perform EOP Supplement 12 to isolate A S/G from outside control room SIM OP: Use MS20/MS21 and SG09/SG11 on PIDMS01 to isolate A S/G Terminate Scenario when S/G is isolated or at examiner discretion

Appendix D Scenario Outline Form ES-D-1 Facility: Palisades Scenario No.: TWO Op-Test No.: 1 Examiners: ____________________________ Operators:

Initial Conditions: 60% power. P-7C, Service Water Pump, is out of service.

Turnover:

Shift orders are to alternate running Component Cooling Water pumps and then continue power ascension.

Event No.

Malf.

No.

Event Type*

Event Description 1

N/A RO (N)

Alternate operating CCW pumps 2

N/A SRO (N)

RO (R)

BOP (N)

Power ascension 3

RX08B SRO (I)

RO (I)

PZR Level Control Channel downscale demand 4

SI04D SRO (C, T)

RO (C)

T-82D, Safety Injection Tank loss of pressure (leak) 5 RM08G SRO (I, T)

West ESS Room Ventilation Radiation Monitor Failure 6

MS06B SRO (C)

RO (C)

Main Steam Relief Valve RV-0706 stuck open 7

FW03 BOP (C)

Failure of AFW Pumps to start in AUTO 8

RC04 ALL (M)

Primary Coolant System leak

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

Page 2 of 16 Scenario TWO - Simulator Operator Instructions Reset to IC-15 (or similar) 60% power MOL IC.

SW Pump P-7C is OOS with a Caution Tag hung on the handswitch.

o Use SW16 on PIDSW03 to rackout P-7C breaker o Ensure EOOS indicates P-7C is out of service ENSURE CCW Pump P-52C is in service, with P-52A and P-52B in STANDBY.

INSERT MF, FW03A (PIDFW01) P-8A Fail to AUTO start INSERT MF, FW03B (PIDFW01) P-8B Fail to AUTO start INSERT MF, FW03C (PIDFW01) P-8C Fail to AUTO start Create Event Trigger 5: Event: Reg Group 1 Rod 21 less than 110 Event #

Remote or Trigger #

Instructions 1

No actions required.

2 No actions required.

3 REMOTE 1 RX08B (PID RX01), PRESSURIZER LEVEL CONTROL CHANNEL DOWNSCALE DEMAND.

4 REMOTE 2 SI04D (PIDSI04) T-82D, Safety Injection Tank loss of pressure 5

REMOTE 3 RM08G (PID RM04) Low Rad West Eng SFGD Vent Monitor RIA-1811 6

REMOTE 4 MS06A (PIDMS01) RV-0706, Main Steam Line Relief Valve Leak, Severity = 100 7

ACTIVE AT SETUP - No actions required 8

TRIGGER 5 RC04 (PIDRC01) Primary Coolant Leak, Severity = 75, Ramp = 15 minutes Special instructions:

(EVENT #1) For alternating CCW pps. if asked:

o Initial CCW Hx dP is E-54A = 6.6 psid, E-54B = 6.8 psid.

o After starting P-52A, dPs are: E-54A = 14.1 psid, E-54B = 14.2 psid.

o When P-52C has been secured, dPs are E-54A = 6.8 psid, E-54B = 6.5 psid.

Page 3 of 16 Scenario TWO - Turnover Information The plant is at 60% power, MOL. A power ascension was in progress when an engineering hold was implemented to monitor the performance of both Main Feedwater Pumps. The engineering hold is no longer required and both Main Feedwater Pumps have been deemed acceptable for 100% power operation. P-7C, Service Water Pump, is out of service for a bearing inspection. It is expected to be 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> before bearing inspection is completed.

Shift orders are to alternate running CCW pumps by placing P-52A in service, and P-52C in STANDBY, per SOP-16, section 7.3.6. Once this is complete, the power ascension is to resume at 6% per hour.

At 86% power, the rate of power ascension will be adjusted to 4% per hour.

Appendix D Required Operator Actions Form ES-D-2 Page 4 of 16 Op-Test No.: 1 Scenario No.: TWO Event No.:

1 Page _1_ of _1_

Event

Description:

Alternate CCW Pumps Time Position Applicant's Actions or Behavior SRO RO Enters SOP-16, section 7.3.6.

RO Ensures locked open all available CCW pp. suction/discharge valves.

RO Coordinates with AO to open vent for P-52A.

RO Verifies both CCW Heat Exchangers in operation.

RO Starts P-52A.

RO Stops P-52C.

RO Places P-52C in standby:

Depress amber STANDBY button above handswitch.

Verify amber light is LIT.

RO May request final reading on CCW Heat Exchangers differential pressure, but not required.

Appendix D Required Operator Actions Form ES-D-2 Page 5 of 16 Op-Test No.: 1 Scenario No.: TWO Event No.:

2 Page _1_ of _1_

Event

Description:

Power Ascension Time Position Applicant's Actions or Behavior SRO Enters/continues and directs the actions of GOP-5.

BOP Operates turbine generator on the DEH panel for power escalation @ 6% per hour:

ENTERS setter value SELECTS rate of 6% per hour PUSHES "GO" pushbutton and observes white light illuminate Informs CRS/RO that turbine is in GO RO Performs periodic dilutions and/or control rod manipulations to maintain TAVE within 3°F of TREF For Dilution:

RESET PMW Controller if not already RESET SET quantity and batch flow limit on FIC-0210A, PMW flow controller OPEN CV-2155, Make Up Stop Valve PUSH start pushbutton on FIC-0210A VERIFIES FIC-0210A output signal at zero when dilution complete CLOSES CV-2155 MONITORS reactor power and TAVE For Control Rod manipulations:

WITHDRAWS Group 4 Regulating Rods in increments specified by CRS MONITORS reactor power and TAVE BOP Operates turbine generator on the DEH panel for power escalation @ 6% per hour:

RO May divert CVCS letdown to Clean Waste as VCT level rises:

PLACES CV-2056, Letdown to VCT or Radwaste, in the TO CLEAN WASTE RCVR TANKS position When desired VCT level is achieved, PLACES CV-2056 to the AUTO or TO VOL CNTRL TANK position (then AUTO)

After power has been raised 1%-2% OR at the discretion of the Lead Examiner, INSERT REMOTE #1

Appendix D Required Operator Actions Form ES-D-2 Page 6 of 16 Op-Test No.: 1 Scenario No.: TWO Event No.:

3 Page _1_ of _1_

Event

Description:

PZR LEVEL CONTROL CHANNEL DOWNSCALE DEMAND Time Position Applicant's Actions or Behavior SRO RO Diagnoses a failure of the B PZR level control channel:

EK-0761, Pressurizer Level HI-LO - alarm due to LIC-0101B failed high EK-0703, Letdown HT EX Tube Outlet HI Temp - alarm due to opening of Letdown Orifice Stop Valves Observes all three Letdown Orifice Stop Valves open.

P-55A variable speed pp lowers to minimum speed.

LIC-0101B process output at 100%.

SRO Directs RO to shift PZR level control to A Channel (LIC-0101A) or place LIC-0101B in MANUAL and control PZR level (manual control will be unsuccessful)

RO Places LIC-0101A in service by placing selector switch, 1/LRC-0101 in CHANNEL 'A' Places Pressurizer Heater Control Channel Selector Switch to CHANNEL 'A' SRO Directs RO to place LIC-0101A in CASCADE per SOP-1A RO Places A Channel PZR Level Controller, LIC-0101A, to CASCADE:

Adjusts raise/lower pushbutton to match blue pointer to red pointer Depresses A pushbutton Adjusts raise/lower pushbutton to adjust blue pointer to approximately 51% level Depresses C pushbutton BOP/RO May check LIC-0101BL on back of C-13 to verify a failed instrument SRO May refer to LCO 3.4.9 (no actions apply)

After PZR level control is reestablished OR at the discretion of the Lead Examiner, INSERT REMOTE #2

Appendix D Required Operator Actions Form ES-D-2 Page 7 of 16 Op-Test No.: 1 Scenario No.: TWO Event No.:

4 Page _1_ of _1_

Event

Description:

T-82D, Safety Injection Tank loss of pressure Time Position Applicant's Actions or Behavior RO Diagnose failure of T-82D:

Indications: T-82D nitrogen pressure lowering Major alarms:

EK-1334, Safety Inj Tank HI-LO Pressure EK-1336, Safety Inj Tank LO pressure SIMULATOR OPERATOR: When T-82D pressure is less than 200 psig AND the crew is pressurizing T-82D, call the control room and report that the pressure build valve on the bulk nitrogen tank was closed and that you have opened it, THEN delete malfunction SI04D.

RO Operator actions for EK-1134/1136:

CHECK tank level normal CHECK CLOSED CV-3051, T-82D Vent Valve CHECK tank pressure on PPC (EK-1136 only)

Adjusts tank pressure per SOP-3, section 7.5.6 to clear alarm (Follow Up Action)

Open CV-1358, Nitrogen to Containment Open CV-3050, T-82D Nitrogen Valve Close CV-3050 when T-82D is at desired pressure SRO Declares Tank inoperable while the pressure switch is actuated The following T.S. LCO applies:

3.5.1, Action: B.1, enter due to loss of pressure in SIT, 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> action statement After CRS has briefed loss of pressure in T-82D OR at the discretion of the Lead Examiner, INSERT REMOTE #3

Appendix D Required Operator Actions Form ES-D-2 Page 8 of 16 Op-Test No.: 1 Scenario No.: TWO Event No.:

5 Page _1_ of _1_

Event

Description:

West ESS Room Ventilation Radiation Monitor Failure Time Position Applicant's Actions or Behavior RO Informs the SRO of alarm:

EK-1371, Rad Monitor Sys Ckt Failure RO Checks ARP-7 and SOP-38 Attachment 1 section 3 for actions:

Coordinates with BOP on status of RIA-1811 BOP Checks RIA-1811 on Panel C-11 and notes failure low condition: reports to SRO that RIA-1811 is failed.

SRO Enters LCO 3.3.10.A.1 and directs RO to verify closed West ESS Room Dampers.

RO May place keyswitch to CLOSE for West ESS Room Damper PO-1811 and may direct AO to check status of remote damper PO-1812.

Simulator Operator: If asked as AO to check status of remote ventilation damper PO-1812, report that it is closed SRO May refer to ODCM. Item number 6 of Table A-1 specifies that if either channel fails low or is otherwise inoperable, the ventilation dampers associated with that channel shall be closed immediately and action shall be taken to have the affected channel repaired. (This is identical to action statement in LCO 3.3.10.A.1.)

After CRS has briefed on West ESS Room ventilation rad monitor OR at the discretion of the Lead Examiner, INSERT REMOTE #4

Appendix D Required Operator Actions Form ES-D-2 Page 9 of 16 Op-Test No.: 1 Scenario No.: TWO Event No.:

6 Page _1_ of _1_

Event

Description:

A S/G RV-0706 stuck open Time Position Applicant's Actions or Behavior BOP Informs the SRO that indications of excessive load exist:

Reactor power rising Tave lowering SRO Enters ONP-9, Excessive Load Determines that unisolable load rise exceeds 1% change in NI or Delta-T Power (may wait for HB Power Steady to also be above 1%)

Directs a reactor trip.

RO Trips reactor by depressing reactor trip pushbutton at Panel C-02 SRO/BOP May direct AO to check for source of steam release.

Simulator Operator: If contacted by Control Room as AO to check on steam leak, wait a few minutes and REPLY back: there is a Steam Generator relief valve open that is blowing steam in SIRWT roof area.

Appendix D Required Operator Actions Form ES-D-2 Page 10 of 16 Op-Test No.: 1 Scenario No.: TWO Event No.:

6/7/8 Page _1_ of _7_

Event

Description:

A S/G RV-0706 stuck open, PCS LOCA (750 gpm), Failure of AFW Pumps to start in AUTO Time Position Applicant's Actions or Behavior BOP Informs SRO that S/G pressures < 800 psia, CONTINGENCY ACTION:

MSIVs, CV-0510 and CV- 0501, CLOSED by taking one HS to CLOSE BOP Informs SRO that AFW did not initiate, CONTINGENCY ACTION:

P-8A or C STARTED OR CV-0522B, Steam Supply to P-8B OPENED RO Informs SRO that PCS pressure < 1300 psia, CONTINGENCY ACTION:

STOP an operating PCP in each loop, P-50A and P-50D SRO EOP-1.0 verbal verifications RO Reactivity Control: YES:

Reactor power lowering negative SUR maximum of one control rod not inserted

Appendix D Required Operator Actions Form ES-D-2 Page 11 of 16 Op-Test No.: 1 Scenario No.: TWO Event No.:

6/7/8 Page _2_ of _7_

Event

Description:

'A S/G RV-0706 stuck open, PCS LOCA (750 gpm), Failure of AFW Pumps to start in AUTO Time Position Applicant's Actions or Behavior BOP Main Turbine Generator criteria: YES Main Turbine tripped Generator disconnected from grid BOP Feedwater criteria: YES PLACES Main FWP Controllers to MANUAL and RAMPS to minimum speed PLACES Main FW Controllers to MANUAL, Main FRV and B/Ps CLOSED BOP Vital Auxiliaries-Electric: YES Buses 1C and 1D energized Bus 1E energized Buses 1A and 1B energized Y-01 energized Six DC Buses energized 3 of 4 Preferred AC Buses energized RO PCS Inventory Control: NO PZR level 20% - 85% NO: verifies max Charging and min Letdown PZR level trending toward 42% - 57%: NO - verifies max Charging and min Letdown PCS 25°F subcooled: YES RO PCS Pressure Control: NO PZR pressure 1650 - 2185 psia and trending toward 2010 - 2100 psia:

NO - verifies PZR spray valves closed and maximum heaters At 1605 psia, verifies Safety Inj Initiated alarm EK-1342 and ensures all available HPSI and LPSI pumps operating with the associated loop isolation valves open At 1300 psia, stop PCPs as needed to establish one PCP operating in each loop

Appendix D Required Operator Actions Form ES-D-2 Page 12 of 16 Op-Test No.: 1 Scenario No.: TWO Event No.:

6/7/8 Page _3_ of _7_

Event

Description:

'A S/G RV-0706 stuck open, PCS LOCA (750 gpm), Failure of AFW Pumps to start in AUTO Time Position Applicant's Actions or Behavior BOP PCS Heat Removal At least one S/G has; level 5% - 70% with Feedwater available NO:

CONTINGENCY taken: Start an AFW Pump (CRITICAL TASK PL-061 102 01 01) to ensure PCS Heat Removal is met: (Event 7)

Places P-8A or P-8C Handswitch to START and verifies flow to S/Gs is 165 gpm on FIC-0727/0749 or FIC-0736A/0737A (may elect to isolate AFW flow to 'A' S/G.

OR Places P-8B Handswitch to OPEN and verifies flow to S/Gs is 165 gpm on FIC-0727/0749(may elect to isolate AFW flow to 'A' S/G.

TAVE 525°F - 540°F NO: verifies Turbine Bypass Valve and ADVs are closed Verify BOTH S/G pressures 800 psia - 970 psia NO: CONTINGENCY:

CLOSE MSIVs, CV-0510 and CV-0501 if S/G pressures < 800 psia, by taking one of these HSs to CLOSE RO Containment Isolation: YES Containment pressure < 0.85 psig (may be NO, depends on timing of verification: no contingencies until 4 psig)

BOP Containment Isolation: YES Containment Area Monitor alarms clear Condenser Off Gas Monitor alarm clear Main Steam Line Monitor alarms clear RO Containment Atmosphere: YES Containment temperature < 125°F Containment Pressure < 0.85 psig (may be NO, depends on timing of verification: no contingencies until 4 psig)

Appendix D Required Operator Actions Form ES-D-2 Page 13 of 16 Op-Test No.: 1 Scenario No.: TWO Event No.:

6/7/8 Page _4_ of _7_

Event

Description:

'A S/G RV-0706 stuck open, PCS LOCA (750 gpm), Failure of AFW Pumps to start in AUTO Time Time Time RO Vital Auxiliaries - Water: YES At least two SW Pumps operating BOTH Critical SW Headers in operation with pressure > 42 psig At least one CCW Pump operating RO Vital Auxiliaries - Air: YES Instrument Air Pressure > 85 psig BOP PLACES left train CRHVAC in emergency mode:

STARTS V-26A Air Filter Unit Fan ENSURES OFF: V-94, Purge Fan; V-47, Switchgear Exhaust Fan BOP Verify BOTH of the following: YES At least one Condensate Pump operating At least one Cooling Tower Pump operating SRO MAY direct isolating AFW to A S/G BOP When directed, isolates AFW to A S/G:

SELECTS MANUAL on FIC-0749, P-8A/B flow to S/G A SELECTS MANUAL on FIC-0737A, P-8C flow to S/G A Raises flow output to 100% on each controller (RED signal indicator to the full right position)

RO/BOP May TRIP both MFW Pumps

Appendix D Required Operator Actions Form ES-D-2 Page 14 of 16 Op-Test No.: 1 Scenario No.: TWO Event No.:

6/7/8 Page _5_ of _7_

Event

Description:

'A S/G RV-0706 stuck open, PCS LOCA (750 gpm), Failure of AFW Pumps to start in AUTO Time Position Applicant's Actions or Behavior SRO Performs Event Diagnostic Flow Chart per EOP-1.0, Attachment 1 Diagnoses EOP-9.0, Functional Recovery Procedure, LOCA and ESDE Performs EOP-9.0 strategy brief Establishes PCS pressure and temperature bands with RO SRO Directs closing CV-1064 and CV-1065, CWRT vent valves BOP CLOSES CV-1064 and CV-1065 SRO Directs performance of EOP Supplement 5, Checklist for Safeguards Equipment Following SIAS BOP Completes EOP Supplement 5 SRO Directs placing a Hydrogen Monitor in service in accident mode BOP Places left train H2 monitor in service in accident mode on back of Panel C-11A:

PLACES HS-2419 to ACCI PLACES HS-2417 to OPEN and RELEASES PLACES HS-2413A, HS-2413B, HS-2415A, and HS-2415B, to OPEN Energizes H2 Recorder, AR-2401, by: PLACING to ON Power Switch and PLACES to ON' Chart Drive Switch PLACES HS-2427L to 'ANALYZE' position REMOVES pen caps from chart pens (NOT in procedure)

Appendix D Required Operator Actions Form ES-D-2 Page 15 of 16 Op-Test No.: 1 Scenario No.: TWO Event No.:

6/7/8 Page _6_ of _7_

Event

Description:

'A S/G RV-0706 stuck open, PCS LOCA (750 gpm), Failure of AFW Pumps to start in AUTO Time Position Applicant's Actions or Behavior RO MAY secure last two running PCPs IF subcooling <25°F (CRITICAL TASK PL-000 007 05 01)

SRO Determines success paths for each safety function:

Reactivity: RC-3 Maintenance of Vital Auxiliaries-Electric: DC-1, AC-1 PCS Inventory: IC-2 PCS Pressure: PC-3 PCS/Core Heat Removal: HR-2 Containment Isolation: CI-1 Containment Atmosphere: CA-2 (Containment pressure > 0.85 psig)

Maintenance of Vital Auxiliaries-Air: MVAW-1, MVAA-1 Determines PCS/Core Heat Removal (HR-2) is jeopardized due to S/G Safety Relief Valve open SRO Directs actions from HR-2:

Perform EOP Supplement 4, SI flow verification (SE action)

May secure Emergency Boration Commence a cooldown using ADVs (may direct using TBV is MSIV Bypass Valves are opened)

If all PCPs have been secured will verify natural circulation exists Isolate 'A' S/G RO Commences a cooldown using ADVs (or TBV):

Places HIC-0780A, Steam Dump Controller, in manual (may use TBV Controller, PIC-0511, if MSIV Bypass valves are opened)

Adjusts output of controller to desired setting Monitors cooldown rate on PPC

Appendix D Required Operator Actions Form ES-D-2 Page 16 of 16 Op-Test No.: 1 Scenario No.: TWO Event No.:

6/7/8 Page _7_ of _7_

Event

Description:

'A S/G RV-0706 stuck open, PCS LOCA (750 gpm), Failure of AFW Pumps to start in AUTO Time Position Applicant's Actions or Behavior BOP Isolates A S/G per Supplement 17: (CRITICAL TASK PL-000 209 05 01)

CLOSE CV-0742, A S/G Main Feed Reg Block Valve CLOSE S/G E-50A Blowdown Valves: CV-0767, CV-0771, and CV-0739 TERMINATE Scenario when A S/G has been isolated per EOP Supplement 17 OR at the discretion of the Lead Examiner.

Appendix D Scenario Outline Form ES-D-1 Facility: Palisades Scenario No.: THREE Op-Test No.: 1 Examiners: Operators:

Initial Conditions: 25% power.

Turnover:

The plant is at approximately 25% power MOL following a startup from a forced outage.

P-8A, AFW Pump, is OOS for seal replacement and is currently 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> into the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO action statement. P-66A is out of service for a bearing replacement and is currently 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> into the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO action statement. The Turbine Drain Valves are closed per SOP-8. A Chemistry hold has just been lifted with S/G chemistry within specifications.

GCL-5.1, Power Escalation in Mode 1, has been completed through Step 2.12f. Shift orders are to place DEH Speed Loop to OUT and commence a power escalation to full power at 8%/hour.

Event No.

Malf.

No.

Event Type*

Event Description 1

N/A BOP (N)

Place DEH Speed Loop to OUT 2

N/A SRO (N)

RO (R)

Power escalation 3

MS11 SRO (C)

BOP (C)

Turbine Bypass Valve fails open. Requires manual action to terminate steam demand 4

CV06 SRO (I, T)

RO (I)

Loss of CVCS Letdown Backpressure Controller 5

RP27D SRO (I, T)

BOP (I)

'A' S/G Level Indication Safety Channel Indication Failure 6

Override SRO (C, T)

Diesel Generator Low Lube Oil temperature 7

MS03A SRO (C)

RO (C)

A S/G Main Steam Line Leak Inside Containment (small leak requiring a manual plant trip) 8 MS03A ALL (M)

ESDE inside containment (ramped in at time of trip) 9 CH05A CH05B ED13A ED13B SI01B RO (I)

Right and Left Channel CHP/SIS Signals fail with failure of P-66B.

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

Page 2 of 20 Scenario THREE - Simulator Operator Instructions Reset to IC-14 Place DEH Speed Loop to IN.

Setup for TBV fail open:

o Place PIC-0511 to Manual (press M) o Insert OVRD PIC-0511-M light to OFF o Insert OVRD PIC-0511-A light to ON Remove P-8A AFW Pump from service:

o INSERT FW16A (PIDFW01) o Override DI P-8A-G (PAL04B2) P-8A AFW Pump Green Light to OFF o Override DI P-8A-W (PAL04B2) P-8A AFW Pump White Light to OFF o Place Caution Tag on handswitch for P-8A stating pump is tagged out o Ensure EOOS indicates that P-8A is out of service Remove P-66A HPSI Pump from service:

o Place Remote SI23 in Rackout for P-66A HPSI Pump o Place Caution Tag on handswitch for P-66A stating pump is tagged out o Ensure EOOS indicates that P-66A is out of service OVERRIDE PB1-1 and PB1-2 (SI Initiate pushbuttons) to OFF INSERT CH05A and CH05B (PIDCH01)

INSERT ED13A and ED13B (PIDSI01)

Create triggers to delete TBV malfunction when 'manual' pushbutton is depressed on PIC-0511:

Event Trigger 6:

Event: zdi3p(717)

Action: dor pic-0511-MNC-2 Event Trigger 7:

Event: zdi3p(717)

Action: dor pic-0511-m Event Trigger 8:

Event: zdi3p(717)

Action: dor pic-0511-a Event #

Remote or Trigger #

Instructions 1

No actions required.

2 No actions required.

3 REMOTE 1 PIC-0511-MNC-2 (PAL04B3) to ON

[TRIGGERS 6, 7, and 8 allow operator to control CV-0511]

4 REMOTE 2 CV06 (PIDCV03) Loss of Letdown Pressure Control Low 6

REMOTE 3 ANN-K-05-57(PALARM7C) Diesel Generator 1-2 Trouble to ON 5

REMOTE 10 RP27D (PIDRPNI2) 'D' Channel 'A' S/G Level Safety Indicators to 0.

7 REMOTE 4 MS03A (PIDMS01) A S/G Main Steam Line Break Inside Containment; Severity value = 2%, 5 minute ramp 8

TRIGGER 5 Event: Reg Group 1 Rod 21 less than 110 Action: imf ms03a 10 (raises severity of steam rupture to 10%)

9 TRIGGER 9 Event: zlo1p(259) (P-66B HPSI Pump Start)

Action: imf si01b (delay of 2 minutes)

Event: zlo1p(225) (Containment Spray Valve red light) action: imf mso3a 8 (lowers severity of steam rupture to 8%)

Special instructions:

Provide a marked up copy of GCL 5.1 completed through step 2.12f.

Provide Reactivity Sheets for Core Life.

Page 3 of 20 Scenario THREE - Turnover Information The plant is at approximately 25% power MOL following a startup from a forced outage. P-8A, AFW Pump, is OOS for seal replacement and is currently 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> into the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO action statement.

P-66A is out of service for a bearing replacement and is currently 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> into the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO action statement. The Turbine Drain Valves are closed per SOP-8. A Chemistry hold has just been lifted with S/G chemistry within specifications. GCL-5.1, Power Escalation in Mode 1, has been completed through Step 2.12f. Shift orders are to place DEH Speed Loop to OUT and commence a power escalation to full power at 8%/hour.

Appendix D Required Operator Actions Form ES-D-2 Page 4 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 1 Page _1_ of _1_

Event

Description:

Place DEH Speed Loop to Out Time Position Applicant's Actions or Behavior BOP Change status of Speed Feedback Loop:

ENSURE DEH is in HOLD PRESS Feedback Loops on Display keypad MOVE cursor to SPEED feedback loop field PRESS SELECT on numeric keypad PRESS STOP on Control Keypad Speed Feedback Loop on DEH should indicate OUT

Appendix D Required Operator Actions Form ES-D-2 Page 5 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 2 Page _1_ of _1_

Event

Description:

Power Ascension Time Position Applicant's Actions or Behavior SRO Enters/continues and directs the actions of GOP-5.

BOP Operates turbine generator on the DEH panel for power escalation @ 8% per hour:

ENTERS setter value SELECTS rate of 8% per hour PUSHES GO pushbutton and observes white light illuminate Informs CRS/RO that turbine is in GO RO Performs periodic dilutions and/or control rod manipulations to maintain TAVE within 3°F of TREF For Dilution:

RESET PMW Controller if not already RESET SET quantity and batch flow limit on FIC-0210A, PMW flow controller OPEN CV-2155, Make Up Stop Valve PUSH start pushbutton on FIC-0210A VERIFIES FIC-0210A output signal at zero when dilution complete CLOSES CV-2155 MONITORS reactor power and TAVE For Control Rod manipulations:

WITHDRAWS Group 4 Regulating Rods in increments specified by CRS MONITORS reactor power and TAVE RO May divert CVCS letdown to Clean Waste as VCT level rises:

PLACES CV-2056, Letdown to VCT or Radwaste, in the TO CLEAN WASTE RCVR TANKS position When desired VCT level is achieved, PLACES CV-2056 to the AUTO or TO VOL CNTRL TANK position (then AUTO)

After power has been raised 1%-2% OR at the discretion of the Lead Examiner, INSERT REMOTE #1

Appendix D Required Operator Actions Form ES-D-2 Page 6 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 3 Page _1_ of _1_

Event

Description:

Turbine Bypass Valve Fails Open Time Position Applicant's Actions or Behavior SRO BOP RO Diagnoses Turbine Bypass Valve has failed open:

Notes TAVE lowering Power rising Steam flow rising May observe GREEN/RED status light change on C-01 for TBV position.

Possible alarms including:

Nuclear Power / T, EK-0603, 4, 7, 8, Rack D (if TBV is open long enough)

Charging Pump Seal Cooling Low Pressure, EK-0734, due to charging pump starting on lowering PZR level SRO Enters and directs the actions of ONP-9.0, Excessive Load Increase BOP Manually closes the TBV:

Places controller PIC-0511 to Manual Lowers output signal to zero SRO BOP Reduce turbine load to restore reactor power to pre-event power level or less.

(Not required if TBV is manually closed.)

ALL May go to HOLD on turbine, based on crew judgment SRO Initiate troubleshooting/repair At the discretion of the Lead Examiner, INSERT REMOTE #2

Appendix D Required Operator Actions Form ES-D-2 Page 7 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 4 Page _1_ of _1_

Event

Description:

Loss of CVCS Letdown Back Pressure Controller Time Position Applicant's Actions or Behavior RO Diagnoses failure of PIC-0202, Intermediate Pressure Letdown Controller:

Indications: PIC-0202 red alarm light illuminated; Pressure rising on PIC-0202 (red pen); PIC-0202 output signal Full Closed; TIA-0202, Intermediate Pressure Letdown RV Discharge Temperature rising; FIC-0202, Letdown Flow reads 0.

Major alarms: EK-0704, Letdown HT EX Tube Inlet HI-LO Press; EK-0702, Relief Valve 2006 Discharge HI Temp RO Operator Actions from EK-0704 and EK-0702:

MANUALLY CONTROL PIC-0202 at approximately 460 psig SRO DIRECTS MANUAL CONTROL of PIC-0202 with control, approximately 460 psig RO MANUAL CONTROLS PIC-0202:

Depresses MANUAL pushbutton on PIC-0202 USES Slide Bar to slowly move controller signal the OPEN (to the right)

PIC-0202 CONTROLLED approximately 460 psig SRO May enter LCO 3.4.13, Action: A.1, PCS leakage, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> After the SRO has briefed the loss of the Letdown Backpressure Controller OR at the discretion of the Lead Examiner, INSERT REMOTE #10

Appendix D Required Operator Actions Form ES-D-2 Page 8 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.:5 Page _1_ of _1_

Event

Description:

S/G Level Safety Channel Failed low Time Position Applicant's Actions or Behavior BOP Respond to alarms for Low 'A' S/G Level (LIA-0751D):

EK-0604A "Low Level SG1 Channel Trip" EK-0608A "Low Level SG1 Channel Pre-Trip" EK-0137 "AFAS FOGG Subsystem Trip" Determines that 'A' S/G Low Level Trip on RPS Channel 'D' must be bypassed.

SRO DIRECTS BOP to bypass 'A' S/G Low Level Trip on RPS Channel 'D' per SOP-36.

BOP Bypass the 'A' S/G Low Level Trip on RPS Channel 'D' per SOP-36 (does not need to be in-hand):

Insert bypass key #292 above affected RPS Trip Unit (#4).

Turn key 90º clockwise.

Verify yellow light lit above bypass keyswitch.

Log evolution in the Reactor Logbook SRO Determines the following Tech Spec Actions apply LCO 3.3.1, Condition A, item #4. Place affected trip unit in TRIP within 7 days LCO 3.3.3, Condition A item #4a. Place affected bistable in TRIP within 7 days.

If asked, inform the CRS that the Shift Manager will look into bypassing AFAS sensor channels.

At the discretion of the Lead Examiner, INSERT REMOTE #3

Appendix D Required Operator Actions Form ES-D-2 Page 9 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.:6 Page _1_ of _1_

Event

Description:

Diesel Generator Lube Oil Temperature Low Time Position Applicant's Actions or Behavior BOP Respond to D/G 1-2 Trouble alarm per ARP-3, window 57:

Contacts Auxiliary Operator to investigate Simulator Operator: As AO, report back that D/G 1-2 local alarm panel has window #2, "Pre-Lube Pump Failure," and window #8, Low Lube Oil Temperature, in alarm and that TI-1488 (K-6B Lube Oil Temp Ind) reads 89°F. If asked, report that Prelube pump is not running and local breaker for Prelube pump is closed and not in the trip-free position.

Simulator Operator: Clear Override on alarm ANN-K-05-57 after AO report is made.

SRO Determines that D/G 1-2 is inoperable based on lube oil temperature and enters the following action statements from LCO 3.8.1.B:

B.1 - Perform offsite source checks within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

B.2 - Declare required features inoperable associated with inoperable D/G when redundant feature is also inoperable within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. If P-8C is declared inoperable, LCO 3.7.5.B applies, be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

B.3 - Perform common cause analysis to verify other D/G is not inoperable OR test start other D/G within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B.4 - Restore D/G to operable status within 7 days.

SRO DIRECTS BOP to perform offsite source check per LCO 3.8.1.B.1 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

BOP Performs offsite source check per SR 3.8.1.1 SRO May direct starting D/G 1-2 to warm up lube oil above 90°F.

At the discretion of the Lead Examiner, INSERT REMOTE #10

Appendix D Required Operator Actions Form ES-D-2 Page 10 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 7 Page _1_ of _1_

Event

Description:

ESDE Inside Containment requiring a Plant trip Time Position Applicant's Actions or Behavior SRO/RO/BOP Diagnose ESDE Inside Containment:

Indications: TAVE lowering; A Charging Pump speed rising; Containment Pressure rising Major alarms:

EK-1148, Fire System Panel C-47, C-47A/B or C-49 Off Normal; EK-1344, Containment Air Cooler VHX-2 Dry Pan HI Level; EK-1346, Containment Air Cooler VHX-4 Dry Pan HI Level; EK-1362, Containment Pressure Off Normal RO/BOP No Operator actions apply to EK-1148, EK-1344, EK-1346, and EK-1362, for ESDE SRO Enters ONP-9, Excessive Load DIRECTS Plant trip RO DEPRESSES CO-2 Panel Reactor Trip Pushbutton BOP/RO PERFORM immediate actions of EOP-1.0, Standard Post Trip Actions

Appendix D Required Operator Actions Form ES-D-2 Page 11 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 8/9 Page _1_ of _10_

Event

Description:

EOP-1.0 actions/EOP-6.0 (larger ESDE)/SIAS/CHP Auto Failure with failure of P-66B Time Position Applicant's Actions or Behavior RO When Containment pressure reaches 4.0 psig, PERFORMS the following per EOP-1.0 Immediate Actions (attached):

DEPRESS Containment Hi Rad actuation pushbuttons, CHR-L and CHR-R (push buttons do not actuate Containment isolation)

Closes MSIVs, FRVs, FRV Bypass Valves, and CCW to/from containment isolation valves, CV-0910, 0911 and 0940 Left and Right Channel SI Initiate pushbuttons PUSHED but do not actuate SI.

START P-67A/B LPSI Pumps, and P-66B, Left Channel HPSI Pump, and OPEN all Loop Injection Valves OPEN Containment Spray Valves, CV-3001/3002 START ALL Containment Spray Pumps, P-54A/B/C (CRITICAL TASK PL-000 433 05 01)

NOTE: P-66B, HPSI Pump, will trip after running for two minutes.

SRO EOP-1.0 verbal verifications RO Reactivity Control: YES Reactor power lowering Negative SUR Maximum of one control rod not inserted BOP Main Turbine Generator criteria: YES Main Turbine tripped Generator disconnected from grid BOP Feedwater criteria: YES:

PLACES MFP Controller to MANUAL and RAMPS to minimum speed:

YES/NO: (A NO answer may be given due to MSIVs being closed (no steam to MFPs))

Main FRV and B/Ps CLOSED

Appendix D Required Operator Actions Form ES-D-2 Page 12 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 8/9 Page _2_ of _10_

Event

Description:

EOP-1.0 actions/EOP-6.0 (larger ESDE)/SIAS/CHP Auto Failure with failure of P-66B Time Position Applicant's Actions or Behavior BOP Vital Auxiliaries-Electric:

Buses 1C and 1D energized: YES Bus 1E energized: YES (due to SI Initiate Pushbuttons not working)

Bus 1A and 1B energized: YES Y-01 energized: YES Six DC Buses energized: YES 3 of 4 Preferred AC Buses energized: YES RO PCS Inventory Control:

PZR level 20% - 85% YES OR NO (Depends on timing)

PZR level trending 42% - 57% NO Applicable Contingency Actions:

Ensure all orifice stop valves are closed Ensure all available charging pumps are operating PCS 25°F subcooled YES RO PCS Pressure Control:

PZR pressure 1650 - 2185 psia YES OR NO (Depends on timing)

PZR pressure trending toward 2010 - 2100 psia NO Applicable Contingency Actions:

Ensure Spray Valves are closed Ensure all available heaters are energized (all heaters will be de-energized due to PZR level < 36%

Start HPSI Pump, P-66B, LPSI Pumps, P-67A and P-67B, Open all loop injection valves (12 total) (May not open right train HPSI loop injection valves due to P-66A OOS)

(CRITICAL TASK PL-000 433 05 01)

Appendix D Required Operator Actions Form ES-D-2 Page 13 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 8/9 Page _3_ of _10_

Event

Description:

EOP-1.0 actions/EOP-6.0 (larger ESDE)/SIAS/CHP Auto Failure with failure of P-66B Time Position Applicant's Actions or Behavior RO Core Heat Removal:

May secure ALL PCPs due to loss of CCW for cooling At least one PCP operating: YES or NO (depends on timing)

Verify Loop T less than 10°F: NO Verify PCS at least 25°F subcooled: YES BOP PCS Heat Removal:

Verify at least one S/G has; level 5% - 70%; Feedwater available: YES Verify TAVE 525°F - 540°F: NO Applicable Contingency Action:

Ensures Turbine Bypass Valve and Atmospheric Steam Dump Valves are closed Verify BOTH S/G pressures 800 psia - 970 psia: NO Applicable Contingency Action:

Ensure closed both MSIVs, Feed Regulating Valves, and Feed Regulating Bypass Valves SRO MAY direct isolating AFW to A S/G BOP If directed to isolate AFW to A S/G:

SELECTS MANUAL on FIC-0749, P-8A/B flow to S/G A SELECTS MANUAL on FIC-0737A, P-8C flow to S/G A Ensuring/raising flow output to 100% on each controller (RED signal indicator to the full right position)

CLOSES CV-0522B, Steam from A S/G to P-8B, Turbine Driven AFW Pump

Appendix D Required Operator Actions Form ES-D-2 Page 14 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 8/9 Page _4_ of _10_

Event

Description:

EOP-1.0 actions/EOP-6.0 (larger ESDE)/SIAS/CHP Auto Failure with failure of P-66B Time Position Applicant's Actions or Behavior RO Containment Isolation: NO Containment pressure > 0.85 psig Applicable Contingency Actions:

If/When Containment pressure > 4.0 psig perform all of the following per EOP-1.0 immediate actions(attached):

PUSH High Radiation Pushbuttons on Panel 13 (CIS EK-1126 will NOT alarm)

ENSURE CLOSED: Both MSIVs (MO-0510 and MO-0501); Main FRVs; Main FRV Bypasses; CCW Isolation Valves ENSURE EK-1342 (Safety INJ Initiated) OR PUSH left and right Injection Initiate pushbuttons on Panel EC-13 (Note that the initiate pushbuttons will NOT work)

START all available HPSI and LPSI Pumps and open associated Loop Isolation Valves (CRITICAL TASK PL-000 433 05 01 if not previously done)

BOP Containment Isolation:

Verify Containment Area Monitor alarms clear: NO (Depends on timing: All four in alarm, not corroborated with High Range Gamma Monitors)

Verify Condenser Off Gas Monitor alarm clear: YES Verify Main Steam Line Monitor alarms clear: YES RO Containment Atmosphere: NO Containment temperature > 125°F Containment Pressure > 0.85 psig Applicable Contingency Actions:

ENSURE OPERATING ALL available Containment Air Cooler A Fans and ensure all CAC Hi Capacity outlet valves are open OPEN Containment Spray Valves CV-3001 and CV-3002 START all Containment Spray Pumps, P-54A/B/C (CRITICAL TASK PL-000 433 05 01, If not previously done)

Appendix D Required Operator Actions Form ES-D-2 Page 15 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 8/9 Page _5_ of _10_

Event

Description:

EOP-1.0 actions/EOP-6.0 (larger ESDE)/SIAS/CHP Auto Failure with failure of P-66B Time Position Applicant's Actions or Behavior RO Vital Auxiliaries - Water: YES Verify at least two SW Pumps operating Verify BOTH Critical SW Headers in operation with pressure > 42 psig Verify at least one CCW Pump operating RO Vital Auxiliaries - Air: YES Instrument Air Pressure > 85 psig SRO DIRECTS performance of EOP Supplement 6, Checklist For Containment Isolation and CCW Restoration DIRECTS performance of EOP Supplement 5, Checklist for Safeguards Equipment Following SIAS BOP PERFORMS EOP Supplement 5 and Supplement 6 BOP PLACES left train CRHVAC in emergency mode:

STARTS V-26A Air Filter Unit Fan (will auto start if CHP has occurred)

ENSURES OFF: V-94, Purge Fan; V-47, Switchgear Exhaust Fan BOP Verify BOTH of the following:

At least one Condensate Pump operating At least one Cooling Tower Pump operating BOP TRIPS both Main Feed Pump Turbines due to MSIVs being closed

Appendix D Required Operator Actions Form ES-D-2 Page 16 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 8/9 Page _6_ of _10_

Event

Description:

EOP-1.0 actions/EOP-6.0 (larger ESDE)/SIAS/CHP Auto Failure with failure of P-66B Time Position Applicant's Actions or Behavior SRO Performs Event Diagnostic Flow Chart per EOP-1.0, Attachment 1 Diagnoses EOP-6.0, Excess Steam Demand Event Performs EOP-6.0 strategy brief Establishes PCS pressure and temperature bands with RO NOTE: CRS May directly enter EOP-9.0 at this point due to loss of both HPSI pumps.

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The following are applicable steps from EOP-6.0. Excess Steam Demand Event --------

SRO DIRECTS SE to perform Safety Function Status checks for EOP-6.0 RO Commences emergency boration: (Also in EOP-9.0)

STARTS Boric Acid Feed Pumps, P-56A/B OPENS Pumped Feed Valve, MO-2140 OPENS Boric Acid Gravity Feed Valves, MO-2169/2170 CLOSES VCT Outlet, MO-2087 CLOSES SIRWT to Charging Pumps, MO-2160 (may re-open if VCT level is low)

SRO DIRECTS check to verify minimum SI flow per EOP Supplement 4, Pre-RAS Minimum HPSI Injection Flow BOP/SE PERFORMS EOP Supplement 4 (will be UNSAT when PCS pressure reaches ~1150 psia)

SRO DIRECTS steaming unaffected S/G (B) to within 50 psi of affected S/G (A)

(Also in EOP-9.0)

RO Begins steaming B S/G: (Also in EOP-9.0)

HIC-0780A, Steam Dump Controller, MANUAL pushbutton PUSHED Slidebar taken to the OPEN position MONITORS S/G pressures and cooldown rate

Appendix D Required Operator Actions Form ES-D-2 Page 17 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 8/9 Page _7_ of _10_

Event

Description:

EOP-1.0 actions/EOP-6.0 (larger ESDE)/SIAS/CHP Auto Failure with failure of P-66B Time Position Applicant's Actions or Behavior SRO May DIRECT use of PZR Auxiliary Spray to lower PCS pressure RO Refers to EOP Supplement 37, PZR Pressure Control Using Auxiliary Spray:

ENSURE CV-1057 and CV-1059 switches in CLOSE ENSURE at least one charging pump in operation ENSURE OPEN HS-2111, Charging Line Stop ENSURE CLOSED MO-3072, Charging Pump Discharge to Train 2 OPERATE HS-2117, Aux. Spray CV-2117 keyswitch as desired SRO DIRECTS placing handswitches for Letdown Orifice Stop Valves to close RO PLACES handswitches to CLOSE:

HS-2003 (CV-2003)

HS-2004 (CV-2004)

HS-2005 (CV-2005)

SRO DIRECTS isolating A S/G per EOP Supplement 17, A S/G ESDE Isolation Checklist BOP Isolates A S/G per Supplement 17: (EOP-9.0, HR-2 directs this also)

CLOSE CV-0742, A S/G Main Feed Reg Block Valve CLOSE S/G E-50A Blowdown Valves: CV-0767, CV-0771, and CV-0739 (may be performed in EOP supplement 6)

DIRECTS Auxiliary Operator to isolate 'A' S/G per EOP Supplement 17 (CRITICAL TASK PL-000 209 05 01)

Appendix D Required Operator Actions Form ES-D-2 Page 18 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 8/9 Page _8_ of _10_

Event

Description:

EOP-1.0 actions/EOP-6.0 (larger ESDE)/SIAS/CHP Auto Failure with failure of P-66B Time Position Applicant's Actions or Behavior Simulator Operator: When instructed by BOP to isolate A S/G outside the Control Room per Supplement 13, then perform the following:

MS20 (PIDMS01) Main Steam Dump Manual Valve CA-0781, value = CLOSE MS21 (PIDMS01) Main Steam Dump Manual Valve CA-0782, value = CLOSE SG09 (PIDMS01) Manual Throttle Vlv MS-101 for CV-0782, value = 0 SG11 (PIDMS01) Manual Throttle Vlv MS-103 for CV-0781, value = 0 SRO When informed that the Inventory Control Safety Function is not being met, determines that EOP-9.0 Functional Recovery Procedure, must be entered.

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The following are applicable steps from EOP-9.0. Functional Recovery Procedure -------

SRO DIRECTS closing CV-1064 and CV-1065, CWRT vent valves BOP CLOSES CV-1064 and CV-1065 SRO DIRECTS placing a Hydrogen Monitor in service BOP Places left train H2 monitor in service in accident mode on back of Panel C-11A:

PLACES HS-2419 in ACCI position PLACES HS-2417 to OPEN and RELEASES PLACES HS-2413A, HS-2413B, HS-2415A, and HS-2415B, to OPEN Energizes H2 Recorder, AR-2401, by: PLACING to ON Power Switch and PLACES to ON Chart Drive Switch PLACES HS-2427L to 'ANALYZE position REMOVES pen caps from chart pens (NOT in procedure)

Appendix D Required Operator Actions Form ES-D-2 Page 19 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 8/9 Page _9_ of _10_

Event

Description:

EOP-1.0 actions/EOP-6.0 (larger ESDE)/SIAS/CHP Auto Failure with failure of P-66B Time Position Applicant's Actions or Behavior SRO Determines success paths for each safety function:

Reactivity: RC-3 Maintenance of Vital Auxiliaries-Electric: DC-1, AC-1 PCS Inventory: IC-2 (jeopardized)

PCS Pressure: PC-3 PCS/Core Heat Removal: HR-2 (jeopardized)

Containment Isolation: CI-1 Containment Atmosphere: CA-3 Maintenance of Vital Auxiliaries-Air: MVAW-1, MVAA-1 Determines IC and HR are jeopardized due to loss of both HPSI Pumps The following are applicable steps from IC-2, PCS Inventory Control Safety Function, and HR-2, PCS And Core Heat Removal Via S/G with SIS in operation SRO Attempts to maximize safety injection flow (HPSI flow)

Requests maintenance restore P-66A as soon as possible Requests maintenance troubleshoot and restore P-66B SRO Verifies all available charging pumps operating SRO Evaluates securing Containment Spray (will not meet requirements for this due to EOP supplement 4 HPSI flow not met)

Appendix D Required Operator Actions Form ES-D-2 Page 20 of 20 Op-Test No.: 1 Scenario No.: THREE Event No.: 8/9 Page _10_ of _10_

Event

Description:

EOP-1.0 actions/EOP-6.0 (larger ESDE)/SIAS/CHP Auto Failure with failure of P-66B Time Position Applicant's Actions or Behavior SRO DIRECTS isolating A S/G per EOP Supplement 17, A S/G ESDE Isolation Checklist (if not performed in EOP-6.0)

BOP Isolates A S/G per Supplement 17: (if not performed in EOP-6.0)

CLOSE CV-0742, A S/G Main Feed Reg Block Valve CLOSE S/G E-50A Blowdown Valves: CV-0767, CV-0771, and CV-0739 (may be performed in EOP supplement 6)

DIRECTS Auxiliary Operator to isolate 'A' S/G per EOP Supplement 17 (CRITICAL TASK PL-000 209 05 01)

TERMINATE Scenario when crew has determined that IC-2 needs to be entered OR at the discretion of the Lead Examiner