Text

Initial Exam 2009-302 Final Simulator Scenarios
	ML093430170
Person / Time
Site:	Hatch
Issue date:	12/07/2009
From:	; NRC/RGN-II/DRS/OLB
To:	; Southern Nuclear Operating Co
References
	50-321/09-302, 50-366/09-302
	Download: ML093430170 (155)
	v • d • e

FACILITY NAME: __C;.. ;. .H_ _

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____ Section 4 REPORT NUMBER: 05000321/2009302 AND 05000366/2009302 DRAFT SIMULATOR SCENARIOS CONTENTS:

o Draft Simulator Scenarios o Each containing ES-D-1 "Scenario Outline" o Each containing ES-D-2 "Required Operator Actions" Location of Electronic Files:

O;\Hatch Examinations\lnitial Exam 2009-302 O:\Hatch Submitted By: Bruno Caballero verifiedBy1YlJj. ~k

Page 1 of 31 Appendix D Scenario Outline ES-D-l Form ES-D-1 NRC Draft Facility: E. I Hatch E.IHatch Scenario No.: 5-01 Op-Test No.: 2009-302 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is at 60% RTP Turnover: Continue reactor startup and place the '2A' RFPT in service. 2D11-K615B, 2DII-K615B, Offgas Post treatment radiation monitor, failed Downscale, RAS written. 2C Condo Booster pump is Danger Tagged Out for breaker pm with tag out restoration in progress.

Event Malf. No. Event Event No. Type* Description 1 NIA N/A N (BOP) Continue startup and place the RFPT '2A' in service.

2 N/A NIA R (ATC) Raise reactor power with Recirc to 65% power.

3 mfP42_71A mtP42_71 A C (ATC) RBCCW Pump '2A' (simulate sheared shaft) mfP42_72C mtP42_72C Standby RBCCW pump fails to start loP42-C001AA3 loP42-COOlAA3 (manually started)

( loP42-COOIAG 1 loP42-COOlAG loP42-C001AR2 loP42-COOlAR2 ET-53 4-

~ diD11-K615A-Sl I (BOP) diDII-K615A-SI 2D 11-K615A, Offgas Post treatment radiation monitor, intermittently 2DII-K615A, fails Inop. Stack isolation valves closes and must be re-opened.

5 mfR22_183 C (BOP) 4160 V Emergency Bus '2F' de-energizes. With time compression mfR22_256 TS (SRO) repair and re-energizes. 1B IB EDG Generator Over current Alarm mf65223700 rnf65223700 (OFF)

ET-R43-1 6 C (ATC) Loss ofCRD.

TS (SRO) 7 mfR22_181 M (ALL) 4160 V Station Service Bus '2D' Fault L L.;:;""

mfE4L107 HPCI Failure To Start (2E41-FOOl Stuck) \A' ';','

mfG3L242 rnfG3L242 RWCU Non-Isol Leak in DW "

diC11B-S4A diCIIB-S4A CRD LOCA Reset A diC11B-S4B diCIIB-S4B CRD LOCA Reset B 8 diE11-F027 diE 11-F027 A C (ATC) RHR 2E11-F027A 2EII-F027 A or B RHR Torus Spray or Test Valve failed diE11-F027B diEII-F027B closed. (Critical Task)

ET-Ell-l rET-E11-1 ET-EII-2 IET-Ell-2 9 mfE51_61 C (BOP) RCIC trips on Overspeed Start CBP 2C then RFPT prior to RWL reaching -100" OR at -155", Emergency Depress due to low reactor water level.

I (Critical Task) 1*1* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

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Appendix D Required Operator Actions Form ES-D-2 I,

I~

Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 1 Page 2 of 31 Event

Description:

Placing the "2A" RFPT in service Time I Position I Applicant's Actions or Behavior I 12 mins SRO Orders Operator to place 2A "RFPT" in service BOP

Enters 34S0-N21-007-2 at step 7.1.11.9 .

Increases speed with the Speed Setter switch to 2100 rpm

Verifies MIA station permissive light illuminates and that the MIA station is following the Speed Setter.

Places the TMR Mode switch to MIA.

Confirms the MIA Station green light illuminates.

Slowly increases the MIA station to match input and output while monitoring RWL, RFPT 2A discharge pressure and RFPT 2A & & 2B speed.

( Alarm 656-039, "RFP C005A Disch Flow Low" will clear when RFPT 2A is placed into service. Alarm 650-135, "Heater Trouble" may come in and clear. This is expected for this plant condition.

Places MIA station for RFPT 2A in auto

As required, adjust RFP 2A Speed Control Bias Setting to maintain RFPT 2A and 2B speed within 100 RPM.

Informs SS that the 2A RFPT is in service in automatic control.

SRO

Informs ATC to increase power with Recirc to 65% power.

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Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2 Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 2 Page 3 of31 of 31 Event

Description:

Raise reactor power to approximately 65%

I Time I Position I Applicant's Actions or Behavior I 10 min SRO

Directs ATC to increase reactor power to 65 % by increasing Recirc flow. Power increases should be made as recommended by the ST AlReactor Engineering at a rate not to exceed 10 MWe/min.

STAJReactor STA

Recommends to increase to 65 % power via Recirc not to exceed 10 MWe/min.

ATC

Increases reactor power with Recirc flow IAW 34GO-OPS-005-2 and 34S0-B31-001-2 by depressing either the Master Recirc Flow Control

( raise pushbuttons or the individual pump Speed Control raise pushbuttons.

Monitors power increase by observing APRM and generator output indications.

May get the (603-202) "RBM Upscale" and (603-238) "Rod Out Block" alarm, if a peripheral control rod is not selected. This is expected and the operator may select a peripheral rod at this time.

May also get Alarm 650-135, "Heater Trouble" alarm. This is expected at this power level.

Simulator Operator enters the next event after power has been increased by 5% or at the Chief Examiner's request.

Appendix D 0 Required Operator Actions ES-O-2 Form ES-D-2

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( , Op-Test Op* Test No.: 2009*302 2009-302 Scenario No.: 5-01 Event No.:

5*01 3 Page 4 of 31 of31 Event

Description:

2A RBCCW Pump shaft shears, 2C RBCCW pump fails to auto start, must be manually started; RB-3 (mfP42_71A, mfP42_72C, loP42_COOlAR2, loP42_COOIAR2, loP42_COOlAGl, loP42 COOIAGl,loP42loP42_COOJAA3)

COOlAA3)

I I Position I Applicant's Actions or Behavior I 8 min At the Chief Examiner's direction, Simulator operator, lNSTRUCT INSTRUCT the BOP operator by phone to stay on the line until told to hang up. THEN ENTER:

RB-3

mfP42_7lA mfP42_71A

mfP42_72C, loP42_COOJAR2 loP42_COOlAR2 (On), loP42_COOJAGl loP42_COOIAGl (Off),

loP42_COOJAA3 loP42_COOlAA3 (Off)

ATC

When RBCCW pump 2A is tripped, responds to "RBCCW Pumps Disch Press Low" alarm (650-239).

ATC

Acknowledges the alarms and informs the SS that the RBCCW system pressure is low and that the "2C" RBCCW pump did not auto start.

( (2C RBCCW may be started manually prior to recognizing failure to auto start.) (There is not an obvious reason for the pressure being low.)

SRO

Directs an Operator to start the 2C RBCCW pump.

ATC

Manually starts the "2C" RBCCW pump per 34AR-650-239-2 or 34AB-P42-001-2, "Loss of RBCCW". (May not pull procedures until after the pump has been started.

Monitors for increasing system pressure (>90psig).

Dispatches SO/Maint SOlMaint to investigate the cause of the RBCCW Low system pressure.

Appendix D Required Operator Actions Reauired Form ES-D-2 I,.,

Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.:

-- Page 5 of31 of 31 Event

Description:

2A RBCCW Pump shaft shears, 2C RBCCW pump fails to auto start, must be manually started; RB-3 (mfP42_71A, mfP42_72C, loP42_COOIAR2, COOIAGl, loP42 COOlAA3) loP42 COOIAGI,loP42 Position Applicant's Actions or Behavior I SRO

Confirms/sends SOlMaint to investigate RBCCW Low system pressure.

Simulator Operator ensures the RBCCW TRIGGER is entered, then After 3 minutes of being sent to investigate the RBCCW system low pressure, the Simulator Operator reports that the "2A" RBCCW pump motor is running, but the pump shaft is not turning.

( SRO

Directs the operator to place the RBCCW Pump "2A" pump to PTL off.

ATC

Places 2P42-COOIA 2P42-C001A control switch to PTL OFF position and reports this to the SS.

Simulator operator proceeds to the next event at the Chief Examiner's direction.

Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2 Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 4 Page 6 of 31 Event

Description:

2DII-K615A, Offgas Post treatment radiation monitor, fails INOP. Stack isolation valves closes and must be re-opened. (diD II_K615A SI (diDll_K615A S 1 to Inop)

I Time I Position I Applicant's Actions or Behavior I At the Chief Examiner's direction, Simulator Operator enters RB-4 (diDll_K615A Sl S1 to Inop) 601-405, "Post Treatment O/G Radiation HI HI HI I Inop" alarm is received followed shortly by N62-029, "Inlet Flow To Stack Low".

BOP

Enters ARP 34AR-601-405-2

Verifies 2N62-F057 and Offgas drain valves are closed

DII-K615A is reading normal.

Determines that Dll-K615A

May Notify Lab and Verify Charcoal adsorbers are not being bypassed.

N62-029, "Inlet Flow To Stack Low" alarm is received.

(

Sends operator to 34S0-N62-001-2, Off-Gas system.

After one minute, Simulator Operator, DELETE (diDll_K615A S1 to 1nop)

(diD11_K615A Sl Inop)

AND, as II&C&C tech, report to the Control Room that you were dispatched to work on 2D 11-K615B and inadvertently unplugged the cable to 2D 2D11-K615B 11-K615A, 2D11-K615A, instead of 2D ll-K615B. The cable has been re-connected and a CR will be of2D11-K615B.

initiated.

SRO

Directs operator to open 2N62-F057 which will clear N62-029, "Inlet Flow To Stack Low" alarm.

601-405, "Post Treatment O/G Radiation HI HI HI I Inop" alarm Clears.

Note: May receive 650-232, "3 lill Stage SJAE A Steam Flow Low" alarm, if "3K1J 2N62-F057 is not opened within about 2 minutes.

BOP Enters 34S0-N62-00l-2 34S0-N62-001-2 to open 2N62-F057, Stack Isolation Valve.

( ,I.1

D Appendix 0 Required Operator Actions Reguired ES-D-2 Form ES-O-2 II'I Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 4 of 31 Page 7 of31 Event

Description:

2D11-K615A, Offgas Post treatment radiation monitor, fails INOP. Stack isolation valves closes and must be re-opened. (diD11_K615A Sl to Inop)

II Time Position Applicant's Actions or Behavior I BOP

DEPRESS 2N62-F057 RESET Pushbutton at panel 2N62-P600 .

OPEN 2N62-F057, Off Gas Stack Inlet valve at pane12N62-P600 .

BOP Verifies that 2N62-F057 opens.

Note: Annunciator N62-029, "Inlet Flow To Stack Low" AND 650-232, "3RD Stage SJAE A Steam Flow Low" alarms will clear soon after opened.

2N62-F057 is opened

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Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2 "II Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 5 of 31 Page 8 of31 Event

Description:

2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior 15 min Note to Chief examiner:

Event 5 (4160V (4160 V Emergency Bus 2F loss) and Event 6 (Loss of CRD) will be concurrently.

running concu"ently.

Simulator Operator

At direction of the lead examiner, ACTIVATE: (RB-5) and Event Trigger ET-R43-1

mfR22_183, "2F" 4160 bus fault

ET-R43-1

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Note: With the loss of2F 4160V bus, the BOP may address 34AB-R22-002-2, Bus ", first. Also thefollowing Loss of 4160V Emergency Bus",jirst. the following alarms may be addressed in any order.

The following alarms associated with 2F 4160V bus will be received:

652-202, "Loss Of Off Site Power"

652-210, "PSW Press Low"

652-217, "4160V Bus 2F BRKR 135564 TRIPPEDILKDOUT' TRIPPEDILKDOUT"

650-137, "4160 STA SVC FDR BRKR Trip" BOP

Responds to annunciators 652-202, "LOSS Of OFF SITE POWER",

652-217, "4160V Bus 2F BRKR 135564 TRIPPEDILKDOUT" AND 652-210, "PSW Press Low".

D Appendix 0 Required Operator Actions Reguired ES-D-2 Form ES-O-2 trIf

( Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.:

5-01 Event No.: 5 5 of 31 Page 9 of31

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Event

Description:

2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior I BOP

Responds to annunciator, "LOSS Of OFF SITE POWER,"

Confirms the following on 2H11-P652:

2H 11-P65 2:

EDG IB is operating

4160V 4I60V Bus 2F LOSP Lockout Relay is locked out

4160V 4I60V Emergency Bus 2F is energized.

600V Emergency Buses 2C AND 2D are energized BOP

Responds to annunciator 652-217, "4160V Bus 2F BRKR 135564 TRIPPEDILKDOUT,"

( ,

On 2H11-P652 confirms the following:

Normal Supply breaker 135574 open

Alternate Supply breaker 135564 open

1B IB EDG Output breaker 135570 open:

Dispatches 4I60V Bus 2F SOlMaintenance to investigate the loss of 4160V Simulator Operator

When directed by operator, ACTIVATE: (RB-I) "4KV 2F ALTERNATE SUPPLY BKR LOCKOUT" to RESET

Once 2F Emergency bus is energized, notifies SOlMaint to reset relay trips.

BOP

Responds to annunciator, 652-210, "PSW Press Low"

On 2H11-P652 2HII-P652 confirms the following;

1R24-S026 lR24-S026 is energized (IT IS NOT)

2P41-C002 Standby PSW pump is energized (IT IS NOT)

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Appendix D Required Operator Actions Form ES-D-2 II'I Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 5 Page 10 of 31 Event

Description:

2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior I

BOP

Enters 34AB-R22-002-2. "Loss of 4160V4I60V Emergency Bus"

Confirm 1B Diesel Generator has auto started

Ensure adequate cooling water is available to the 1BIB Diesel Generator

Observes 2P4I-C002, 2P41-C002, "STBY PSW Pump", has no lights illuminated.

Places Feeder to SST 2F1 2Fl 2S II-S009 Alt Sply 1R24-S026 2S11-S009 IR24-S026 Diesel Bldg MCC 1B",lB", to TRIP.

Observes 2P4I-C002, 2P4l-C002, "STBY PSW Pump", red light IB Diesel illuminates. (This restores cooling water to the 1B Generator. )

(

SRO

Directs the BOP to enter 34AB-R22-002-2 for the loss of 4160V 4I60V Emergency Bus

As time allows, addresses Tech Specs 3.8.7 and enters an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months RAS per TS 3.8.7.C to restore AC electrical power distribution subsystem to operable status.

Terminates RAS once 4160V 4I60V Emergency Bus 2F is energized.

Appendix 0 Required Operator Actions Form ES-O-2 II'I

( Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 5 Page 11 of 31 Event

Description:

2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior I

Simulator Operator

At direction of the Chief Examiners, DELETE:

(RB-S)

(RB-5) mfR22_183, "2F" 4160 bus fault

At Chief Examiners direction, contact the U2 SS and INFORM, as Shift Manager, that the Maintenance Electrical Team Leader notified you that the fault on 2F Emergency bus was a loose cable connector and (with time compression) has now been repaired. You have my permission and the Maintenance Electrical Team Leaders permission to reset the 86 lockout and energize the 2F Emergency bus from the 2D Startup Auxiliary Transformer (SAT).

As Shift Manager, INFORM the U2 SS that it is not desired for the diesel generator 1B to be tripped AND tagged out OR the Alternate (Startup) Supply Breaker, ACB 135564, racked out, OR the B Diesel

( Test SAT 2C OUT OF SVC Interlock switch placed to TEST.

SRO Directs the BOP to re-energize 2F Emergency bus from 2D SAT.

BOP

IA IAWW 34AB-R22-002-2 step 4.6.1 enters 34S0-R22-001-2, "4160VAC System", to energize 2F Emergency bus.

Appendix 0 Required Operator Actions Form ES-O-2 Il Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 5 Page 12 of 31 Event

Description:

2F Emergency Bus de-energizes/restoration Time Position Applicant's Actions or Behavior I

Section 7.3.1.2 of 34S0-R22-00l-2 34S0-R22-001-2 .

Place Diesel Generator 1B Mode Select Switch in Test. (652-205 will alarm)

Place Sync Switch (SSW) ACB 135574 in ON.

Requests permission from SS to reset the 4160V Bus 2F LOSP Lockout Relay, IAW 30AC-OPS-003-0, Plant Operations, AND 31GO-OPS-021-0, 31 GO-OPS-021-0, Manipulation of Control and Equipment, SRO

Grants permission to reset the Loss of Off-Site Power Relay.

(SM & & Maintenance Electrical Team Leader have already granted permission)

(

BOP

Simultaneously performs the following steps:

Holds 4160V Bus 2F LOSP Lockout Relay in RESET.

Holds ACB 135574, 4160V Bus 2F Normal Supply, control switch to CLOSE until breaker closes.

Place Sync Switch (SSW) ACB 135574 in OFF.

Place the Diesel Generator 1B Mode Select Switch in NORM.

Informs the SS that 2F emergency bus is powered from 2D SAT.

BOP

Responds to annunciator 650-137, "4160 STA SVC FDR BRKR Trip"

On 2H11-P650 confirms that 2C PSW pump amber light is illuminated.

Once cause has been determined and corrected, takes the control switch for 2C PSW pump to off and spring returns to auto to clear amber light.

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Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 6 Page 13 of 31 Event

Description:

Loss of CRD due to power failure I Time Position Applicant's Actions or Behavior I Note to Simulator Operator: No additional malfunctions need to be entered enteredfor for this event. This event stems from the loss of of2F 2F 4J60V 4160V bus.

Note: With the loss of CRD, the ATC may address 34AB-CJJ-OOJ-2, 34AB-Cll-001-2, "Loss Of CRD ", first. Thefollowing CRD",first. The following alarms may be addressed in any order.

The following alarms associated with 2F 4160V bus will be received:

603-129, "CRD Pump B Breaker Trip"

603-140, "CRD Temp High"

603-148, "CRD Accumulator Press Low or Level High" ATC

Notifies SS that B CRD pump has tripped.

(

SRO Directs ATC to enter 34AB-C11-00l-2, 34AB-C 11-00 1-2, "Loss Of CRD" ATC

Responds to annunciator, "CRD Pump B Breaker Trip" (603-129)

Check the following indications on 2HII-P603:

2H11-P603:

Pump indicating lights.

2C11-R600, 2CII-R600, CRD Flow controller, indicates zero flow.

2C11-R605, 2CII-R605, Cooling Wtr indicator, indicates zero flow.

2C11-R60l, 2CII-R601, Charging Water Pressure indicator decreasing.

2Cll-R602, 2CII-R602, Drive Water DP indicator decreasing.

2C11-R603, 2C 11-R603, Cooling Water DPD P indicator decreasing.

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Appendix 0 Required Operator Actions Form ES-D-2 IIIf Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 6 Page 14 of 31 Event

Description:

Loss of CRD due to power failure Time Position Applicant's Actions or Behavior I ATC

Responds to annunciators CRD HYD TEMP HIGH, 603-140 and CRD ACCUMULATOR PRESS LOW OR LEVEL HIGH, 603-148

Enter 34AB-C11-00l-2, 34AB-CII-00l-2, Loss Of CRD.

Dispatches an operator to CRD Temperature Recorder, 2C11-ROI8, 2CI1-ROI8, (130Rx Bldg) and check temperatures.

Dispatches an operator to determine local accumulator pressures.

Simulator Operator after 3 minutes, As the operator sent to the CRD temperature recorder, report that the highest temperature was 270 of and several CRDs at this temperature. Also inform that the operator sent to the CRD accumulators, reports that there are several accumulators with pressures

( less than 940 psig.

ATC

Enters 34AB-Cll-001-2, 34AB-Cll-00l-2, "Loss of CRD."

Places 2CII-R600, CRD Flow Control, in manual and decreases 2CI1-R600, the output to zero.

Starts the A CRD pump.

Returns the flow controller to auto and output to the pre-trip position.

the applicant does not start the A CRD pump and the following IF conditions exist:

Two or more withdrawn control rod scram accumulators inoperable

AND

Charging water header pressure <940 PSIG

THEN: within 20 minutes restore charging water header pressure> 940 PSIG or insert a scram.

(

Appendix 0 Required Operator Actions Form ES-O-2 I

,II

\ Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.:

6 Page 15 of 31 Event

Description:

Loss of CRD due to power failure Time Position Applicant's Actions or Behavior SRO

As time allows, addresses Tech Specs 3.1.5

By the time the SS addresses TS 3.1.5; two or more accumulators will have a trouble alarm lit. Once it has been determined that 2 or more accumulators are inoperable, the SS begins a 20 minute RAS per TS 3.1.5.B to insert a scram and declares the rods slow or inoperable in one hour.

Terminates RAS once charging water pressure is restored above 940 psig.

Simulator Operator After 2F 4160V Emergency bus is energized from 2D SAT AND CRD has been

( returned to service AND at the direction of the Chief examiner, enter next II malfunction to start the major event.

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Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2 Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 7 Page 16 of 31 Event

Description:

4160 V AC "D" trips causing a loss of 2 condensate and condensate booster VAC pumps, HPCI fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.

II Time I Position I Applicant's Actions or Behavior I 10 min Simulator Operator, at Chief Examiners direction, stage an operator in the simulator control room ready to remove the Danger tag on the 2C CBP.

START the major event. Once both RFPTs have tripped, report to the SS for permission to remove the Danger tag and place 2C CBP switch in automatic.

Remove the Danger tag and place the control switchfor 2C CBP in the automatic position. As the operator, inform the SS that the Danger Tag on 2C CBP has been removed and the 2C CBP automatically started when you placed the control switch to automatic.

Simulator Operator, at Chief Examiners direction, ACTIVATE RB-7

( (mfR22_l8l (mjR22_l8l (4KV Bus 2D Fault), mfE4l_l07 (HPCI FOOl fails to open) and mfG3l 242)

ALL

Recognizes a loss of "D" 4160 V AC station service electrical bus has occurred resulting in a loss of condensate and condensate booster pumps A and B.

The team may insert a scram manually due to decreasing reactor water level.

Identify drywell pressure is greater than 1.85 psig and increasing.

SRO

Assigns the AATC TC to perform RC-l.

RC-1.

Assigns the BOP operator to perform RC-2 and RC-3.

3 1EO-EOP-O 10-2, RC EOP flow chart Enters 31EO-EOP-01O-2,

Enters 31EO-EOP-012-2, Primary Containment flow chart.

Assigns a RWL R WL band between 3" and 50"

(

Appendix D Required Operator Actions Form ES-D-2 Op-Test Op* 2009-302 Scenario No.:

Test No.: 2009*302 5-01 5*01 Event No.: 7 Page 17 of 31 Event

Description:

4160 V AC "D" trips causing a loss of 2 condensate and condensate booster pumps, HPCI fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.

III Time Position Applicant's Actions or Behavior I SRO

As time allows,

Notifies maintenance to repair 2D 4160 VAC

Dispatches personnel to the EDGs to check for proper operation.

Directs reopening 2P41-F316A-D IAW 34AB-P41-001-2, Loss of PSW ATC

Performs RC-1 consisting of:

(

Inserts a manual scram.

Places the mode switch to shutdown.

Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.

Notifies SS of rod position check.

Places SDV isolation valve switch to "isolate" && confirms closed.

If not tripped, places the Recirc pumps at minimum speed.

Inserts SRMs and IRMs.

Shifts recorders to read IRMS, when required.

Ranges IRMS to bring reading on scale.

Notifies the SS when the above actions are complete.

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0 Appendix D Required Operator Actions Form ES-D-2

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Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 7 Page 18 of 31 Event

Description:

4160 VAC "D" trips causing a loss of 2 condensate and condensate booster pumps, HPCI HPCr fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.

Time Position Applicant's Actions or Behavior I BOP

Performs RC-2 actions consisting of:

Confirms proper Level Control response:

Checks ECCS Injection Systems and secure as necessary.

Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.

IF set down does not auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.

Starts RCrC RCIC for level control

Notifies SS that the HPCI HPCr FOOl valve will not open and dispatches SO/Maint to investigate.

(

BOP

When feed flow is less than the capacity of the sru level control valve

(;::::: 1.5 mlbmlhr), then:

Opens 2N21-F125.

Places 2C32-R619, FW sru level control valve controller, in Auto, set at approximately 9 inches.

Closes 2N21-F11O.

May attempt to start the CRD pumps

Controls RWL with the RCrc. RCIC. Notifies SS if RWL gets outside assigned band.

(

Appendix D Required Operator Actions Form ES-D-2 I~

Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 7 Page 19 of 31 Event

Description:

4160 VAC "D" trips causing a loss of 2 condensate and condensate booster pumps, HPCI fails to start due to 2E41-F001 2E41-FOOl (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.

II Time Position Applicant's Actions or Behavior I BOP

At panel 2H11-P60 1, Confirms 4 RHR pumps and 2 Core Spray pumps are running.

BOP

Performs RC-3 consisting of:

Monitor RPV pressure.

Confirm proper operation of pressure control system (TBV, LLS, etc.).

necessary, allow RPV pressure to exceed 1074 psig then cycle If any SRV to initiate LLS.

(

Maintain RPV pressure between 1074 and 800 psig.

Notify SS of pressure control system operation.

ATC

Re-opens 2P41-F316s due to high temp on the Condensate Pumps/Booster pumps per 34AB-P41-00l-2, 34AB-P41-001-2, Loss of PSW, Placard.

ofPSW,

Places the "A" and "B" Isolation Override switches on the 2H11-P652 panel to Override

Fully opens 2P41-F316A or C and 2P41-F316B or D

Throttles 2P41-F316C or A and 2P41-F316D or B to open while monitoring PSW division 1 and 2 pressure on 2H11-P650 panel ensuring that PSW pressure remains above 80 psig.

( ,I

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 8 Page 20 of 31 of31 Event

Description:

RHR 2E11-F028A!B 2E11-F028AIB Torus Spray valve fails. 1 Loop of Torus spray Inop (diE11-F027A (diE11-F027 A and diE11-F027B)

I Time Position Applicant's Actions or Behavior SRO

Per the PC flowchart, verifies torus level is <285 inches and directs an operator to place Torus Sprays in service Simulator Operator, confirm EVENT TRIGGER (Ell-1 or Ell-2)

(Ell-lor E11-2) is activated when the operator positions 2Ell-F027A 2EII-F027A or B to open.

ATC

Sprays the Torus per 34S0-E 11-01 0-2 placard on the 2Hll-P601 34S0-Ell-01O-2 2H 11-P60 1 Panel as follows:

Places Cnmt Spray Vlv Cntl switch in the MANUAL position.

Starts RHR pump(s) in loop A (B), if not already running.

(

Opens 2E 11-F028A or B

Opens 2Ell-F027A 2E11-F027 A or B (ONE WILL NOT OPEN AND OPERATOR TRANSITIONS TO THE OTHER LOOP)

OPERATOR

Throttles Open 2E11-F027 A(B) (Critical Task)

Notifies SS that RHR is in Torus Sprays (The flow is only 700gpm, so it may be difficult to see flow indication from a distance.)

ATC

Informs SS that the 2E 2Ell-F027A 11-F027A (or B) will not Open SRO

Directs ATC to spray the Torus with the other loop of RHR.

(

Appendix D0 Required Operator Actions Form ES-D-2 ES-O-2

,.,~

Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 8 Page 21 of 31 Event

Description:

RHR 2EII-F028AJB Torus Spray valve fails. 1I Loop of Torus spray Inop (diE II-F027 A and diE (diEll-F027 diEll-F027B)

II-F027B)

I Time Position Applicant's Actions or Behavior I SRO

If time allows, directs an operator to restore drywell chillers and coolers per 31EO-EOP-100-2.

ATC

Restores drywell chillers per 31EO-EOP-100-2 section 3.7 by:

Verifies drywell temperature is below 250°F using SPDS and/or recognizes the leak in primary containment is small.

Place 2P64-S3, LOCA Override Switch, to BYPASS on panel 2HII-P700

Has the SSS Reset 86 lockout relays on drywell chiller breaker on 4160V buses "E" and "G" (2R22-S005 Fr. 11 and 2R22-S007 Fr.

11

(

May have the SSS to reset the POR relay for each chiller.

Monitors for chiller start by observing the red light on 2HII-P700 2HI1-P700 or input from the SSS.

Restores the drywell coolers per 31EO-EOP-100-2 section 3.6 by:

Verifies drywell temperature is below 250 OF on SPDS and/or recognizes there is not a leak in primary containment.

Place drywell cooling fans system A key-lock LOCA override switch to BYPASS on 2H11-P657.

2Hll-P657.

Place drywell cooling fans system B key-lock LOCA override switch to BYPASS on 2H11-P654.

2Hll-P654.

Observes the drywell cooler fans start by observing their red lights illuminating on 2HII-P654 2H II-P654 and panel P657.

(

Appendix 0 D Required Operator Actions Form ES-D-2 ES-O-2

'l'I Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 8 Page 22 of 31 Event

Description:

RHR 2EII-F028AIB 2E11-F028AIB Torus Spray valve fails. 1 Loop of Torus spray Inop (diEII-F027A and diEll-F027B)

(diEll-F027A diEII-F027B)

Time Position Applicant's Actions or Behavior SRO

If Torus pressure exceeds 11 psig, verifies that Torus Level is <215 inches, in the safe area of Graph 8 (DWSIL) and Directs an operator to:

Place the DW cooling fans to Off

Shutdown Recirc pumps (if running)

SpraytheDW Spray the DW ATC

Places all DW cooling fans control switches in the OFF position.

Notifies the SS that the fans are Off.

(

Sprays the Drywell using 34S0-E11-0l0-2 34S0-EI1-010-2 placard at the 2HI1-P601 2H11-P601

" panel.

Places Cnmt Spray (A or B) Vlv Cntl switch in the MANUAL position.

Starts RHR pump(s) in loop A (B), if not already running.

Opens 2Ell-F021A 2E II-F021A or B

Opens 2Ell-F0l6A 2E11-F0l6A or B

(

Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2 Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 9 Page 23 of 31 Event

Description:

RCIC trips on Overspeed; RWL recovered via RFPT I Time Position Applicant's Actions or Behavior I Simulator Operator, 10 minutes after removing the Danger tag on 2C CBP OR when the operator starts to place either RFPT in service, ACTIVATE RB-9 (mfE51 61)

(mfE51_61)

BOP

Recognize that RCIC tripped and responds to annunciator RCIC Turbine Trip, 34AR-602-301-2.

Confirms RCIC Turbine Tripped per the following indications:

0 2E51-F524, Trip &

2E5l-F524, & Throttle Valve, indicates closed.

0 Turbine Speed decreasing 0 2E52-F013, Pump Discharge Valve, indicates closed.

0 2E51-FOI9, Min Flow Valve, indicates closed.

Recognizes that the 2E5l-F524, 2E51-F524, Trip && Throttle Valve actuator will not run down and determines that RCIC has tripped on Overspeed.

(

Dispatches SO to locally reset RCIC Overspeed condition.

SRO Directs the operator to restart a RFPT for injection BOP

Enters Attachment 15 (placard) of 34S0-N21-007-2

Appendix 0 Required Operator Actions Form ES-O-2

'I Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 9 Page 24 of31 of 31 Event

Description:

RCIC trips on Overspeed; RWL recovered via RFPT Time Position Applicant's Actions or Behavior I BOP

Starts RFPT per placard:

Confirm the trip condition has reset AND the condensate system is available.

Take RFPT 2A or 2B Reset-Trip control switch to RESET AND confirm:

RFPT 2A or 2B HP Stop Valve Red Open light ILLUMINATED

RFPT 2A or 2B LP Stop Valve Red Open light ILLUMINATED

RFPT 2A or 2B TRIP annunciator 650-325 (650-326) CLEAR

Slowly raise RFPT 2A or 2B speed with RFPT 2A or 2B Speed Setter Switch, UNTIL RFPT 2A or 2B speed is at 2100 rpm+/-rpm +/- 100 rpm, as indicated at 2N32-R603A (2N32-R603B) AND confIrm confirm MIA Station Permissive 2A or 2B, White light ILLUMINATES.

Place the RFPT 2A or 2B TMR Mode Switch to MIA, confirm MIA Station GREEN light ILLUMINATES.

(

Slowly increase RFPT 2A or 2B speed with RFP A or B MIA Station, UNTIL 2N21-R635A or B, RFP Disch Press is:::: 2C32-R605A, Reactor Pressure.

Controls Reactor Water Level Manually by performing one of the following:

IF controlling the 2A or 2B Rx Feed Pump with 2C32-R601A or B, perform the following:

Ensure the RFPT 2A or 2B 1MR TMR Mode Switch MIA Station green light is ILLUMINATED.

Adjust the manual open/close lever to control level.

leveL

Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2 Il!~

Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 9 Page 25 of 31 Event

Description:

RCIC trips on Overspeed; RWL recovered via RFPT II Time Position Applicant's Actions or Behavior BOP

IF controlling the 2A or 2B Rx Feed Pump with the Speed Setter, perform the following:

Place the RFPT, 2A or 2B TMR Mode Switch to SS confirm SPEED SETTER yellow light ILLUMINATES.

Adjust the 2A or 2B Speed Setter to make control RWL level.

BOP

IF desired, place Feedwater Control in Single Element Mode as follows

Confirm OR place 2C32-R600, FW Master Controller, and

( 2C32-R601A or B, RFP A or B MIA Station, in MANUAL.

Confirm OR place the Reactor Level Mode Select Switch to AUTO position AND confirm its indicating light ILLUMINATED.

Place Feedwater Control Mode Select switch in the 1I ELEM position.

Match the input and the output of Pump A or B MIA Station by depressing the PF key and reading the controller output (PF lamp, lit), THEN depress the PF key so the input to the controller is displayed (PF lamp is OFF). Adjust the manual output lever on 2C32-R600, FW Master Controller, UNTIL the input and output of the Pump A or B MIA Station are equal as indicated on the digital display.

Place RFP A or B MIA Station in AUTOMATIC by depressing the

'A' pushbutton UNTIL it ILLUMINATES.

Null out 2C32-R600, FW MASTER CONTROLLER, by adjusting setpoint, AND place it in AUTOMATIC by depressing the 'A' pushbutton, UNTIL it ILLUMINATES.

(

Appendix 0 Required Operator Actions Form ES-O-2 I

Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 9 Page 26 of 31 of31 Event

Description:

RCIC trips on Overspeed; RWL recovered via RFPT II Time Position Applicant's Actions or Behavior I BOP

Maintains RWL above -100 inches. (Critical Task)

Note: If RWL R WL drops below -101 inches, the MSIV MSIVss will close requiring the following actions to take place.

NOTE The following steps are contingent on whether RWL can be maintained above

-100 inches.

(

\

BOP

Confirms all MSIV s close

Monitors RPV water level as it trends down.

Informs the S SSS of water level reaching -155."

Manually arms LLS actuation logic by performing the following:

Confirms RPV pressure> 1074 psig

Opens any SRV by placing control switch to open

Confirms red and yellow indicator light for SRV illuminated

Returns LLS valve control switch to close or ADS valve to auto

Monitors RPV pressure to confirm proper operation of LLS.

SRO

Per CP-l

Orders emergency depressurization after RWL level decreases to below -155 inches; but prior to RWL decreasing to below

-185 inches

Orders all available table 8 systems injecting until RWL increases to above -155 inches

(

0 Appendix D Required Operator Actions Form ES-D-2 ES-O-2 1\-\

Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 9 Page 27 of 31 Event

Description:

RCIC trips on Overspeed; RWL recovered via RFPT Time Position Applicant's Actions or Behavior I ATC

Opens 7 ADS valves prior to -185 inches. (Critical Task)

ATC

Places switches for the ADS valves to OPEN.

Recognizes all ADS valves amber lights illuminate.

Notifies the SS SRO

If SBLC was started previously, directs that SBLC be secured following the Emergency Depress before SBLC tank level decreases to

( below 8%.

ATC/BOP ATCIBOP

Verifies I Opens RHR and Core Spray injection valves open once the Reactor Pressure Low 500 psig alarm illuminates.

Verifies injection from Core Spray and RHR pumps begins as soon as reactor pressure decreases below the shut off head of the pumps.

When water level is restored above Top of Active Fuel throttles flow for CIS and RHR per the SS directions.

If directed by the SS, places the SBLC switch (P603) to the off (mid) position.

May use I transfer to the Condensate system for RWL control

Monitors and I or throttles the Feedwater Startup Level Control Valve (SULCV) following Emergency Depress II

Appendix 0 Required Operator Actions Form ES-O-2

,I

\ Op-Test No.: 2009-302 Scenario No.: 5-01 Event No.: 9 Page 28 of 31 Event

Description:

RCIC trips on Overspeed; RWL recovered via RFPT II Time Position Applicant's Actions or Behavior With Chief Examiners Permission:

The scenario should be terminated when the crew has:

0 Started the RFPT AND established injection prior to RWL reaching

-100 inches OR 0 Emergency depressurized the reactor AND re-established adequate core cooling with water level above TAF

(

Page 29 of 31 AppendixD Scenario Outline Form ES-D-l NRC Draft

(

Facility: E. I Hatch Scenario No.: 5-01 Op-Test No.: 2009-302 Examiners: ______________________ Operators: _______________________________SRO S_R_O

---------------------------------- RO BOP Initiating Conditions: Unit 2 is at 60%.

Turnover Continue reactor startup and place the '2A' RFPT in service. 2D11-K615B, Offgas Post treatment radiation monitor, failed Downscale. RAS written. 2C Condo Booster pump is filled and vented with tag out restoration in progress.

Summary:

Event 1: The "2A" RFPT will be placed into service.

Event 2: After the "2A" RFPT is in service the ATC operator will raise reactor power using the Recirc system to approximately 65% power.

Event 3: Component; RBCCW Pump '2A' will experience a sheared shaft and the standby RBCCW pump will not automatically start. The operator will manually start the standby RBCCW pump to restore system flow/pressure to normal.

Event 4: Component; 2D11-K615A, Offgas Post treatment radiation monitor, fails !NOP. INOP. Stack isolation valves closes and must be re-opened. The A ATC TC operator dispatches I&C to investigate.

( The AATC TC will re-align the stack isolation valve once I&C recovers the monitor.

Event 5: ComponentlTS; 4160 V Emergency Bus '2F' will de-energize causing a loss of 2B CRD pump. The SS addresses Tech Specs for inoperable AC electrical distribution subsystem.

BOP will restore cooling water to the running EDG. With time compression repair 4160 V Emergency Bus '2F' will be re-aligned to Startup Auxiliary Transformer 2D.

Event 6: Loss of CRD due to loss of electrical power. The A ATC TC will address loss of CRD and start the A CRD pump.

Event 7: Major; A loss of all high pressure injection occurs as a result of the following: 4160 V Station Service Bus '2D' experiences a fault and de-energizes, "2C" Condensate Booster pump is tagged out (control switch PTL), HPCI fails to start due to 2E41-F001 (Turbine Steam Supply) is stuck closed. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.

Event 8: Component; RHR 2EI1-F027 2Ell-F027 A or B Torus Spray/Test Valve (depends on which loop of RHR the operator attempts first) will fail closed when the operator attempts to place Torus Spray/Cooling in service. The operator must transition to the other loop of RHR to spray/cool the Torus. (Critical Task)

Event 9: Component; RCIC trips on Overspeed causing RWL to decrease. The SS will direct an operator to establish injection with a RFPT. If RFPT is not restored prior to -100", then at TAF, TAP, the SS will direct the A TC operator to open all SRV ATC SRVss to Emergency Depressurize the RPV and restore RWL with low pressure ECCS pumps. The plant will be emergency depressed due to low reactor water level or the RFPT will be placed into service to restore RWL prior to -100".

(Critical Task)

of 31 Page 30 of31 Critical Tasks DRAFT Facility: E. I Hatch Scenario No.: 5-01 Test No.:

Op-Test Op- 2009-302 Critical Tasks

2Ell-F027 AlB Torus Sprayffest Manually open RHR 2EII-F027 SprayfTest Valve prior to exceeding 11 psig in the Torus to preclude damage to the downcomers. (Event 8)

Restore RWL with RFPT injection prior to -100" OR open ADS valves before RWL reaches -185 inches (Event 9)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 6 1. RBCCW 2A fails; stby does not start (Event 3) 2Dll-K6l5A, Off

2. 2Dll-K615A, Offgas gas Post treatment radiation monitor inop (Event 4)

3. 2F Emergency Bus de-energizes (Event 5)

4. Loss HP feed (Event 7) 11-F027A or B fails (Event 8) 2Ell-F027A

5. 2E

6. RCIC trips on Overspeed (Event 9)

2. Malfunctions After 1-2 2 1. 2E 11-F027A or B fails (Event 8)

EOP Entry EOPEntry 2. RCIC trips on Overspeed (Event 9)

( 3. Abnormal Events 2-4 3 1. RBCCW 2A fails; stby does not start (Event 3)

2. 2F Emergency Bus de-energizes (Event 5)

3. Loss of CRD (Event 6)

4. Major Transients 1-2 1 1. Loss HP feed (Event 7)

5. EOPs entered, 1-2 2 1. RC EOP Flow Chart (Event 7) requiring substantive 2. PC EOP Flow Chart (Event 7) actions

6. EOPs contingencies 0-2 1 1. CP 1 flow chart (Event 9) requiring substantive actions

7. Critical Tasks 2-3 2 1. Manually open RHR 2EII-F027 2Ell-F027AIBAlB (Event 8)

2. Restore RWL with RFPT injection prior to -100" OR open ADS valves before RWL reaches -185 inches (Event 9)

HLT 5 NRC Operating Exam Scenario 1 SIDFT TURNOVER UNIT 1 STATUS Power: l00%RTP Activities in progress: None UNIT 2 STATUS Power: Approximately 60% R TP RTP The following equipment is 2Dll-K615B, 2DII-K615B, Offgas Post treatment radiation monitor.

inoperable: 2C Condensate Booster pump Scheduled evolutions: Place RFPT '2A' in service lAW IAW 34S0-N21-007-2, "Condensate And Feedwater System" starting at step 7.1.11.9.

Return 2C Condensate Booster pump to service after tag out restoration. Return to 100% power IAW the reactivity plan.

(

Surveillances due this None shift:

Active clearances: 2C Condensate Booster pump Rod Configuration: SeeRWM

AppendixD Appendix D Scenario Outline Form ES-D-lES-D-1 NRC Dralt Draft

( Facility: E.IHatch E. I Hatch Scenario No.: 5-1 Op-Test No.: 2009-302 Examiners: Operators: SRO RO BOP

".--"-"~ ---- ........

~

Initial Conditions. Unit 2 is operating at approximate(y approximateiy 65% RTP RTPwith

"."." " ~

with the '2C' Condensate Pump out of service for bearing replacement. Continue reactor staftup startup and andplaceplace the '2A' RFPT in service.

The 'B' APRM is bypassed due to failed CPU.

Turnover:

Event Malf. No. ~vent Event Event No. Type* Description 1 N (BOP) Continue startup and place the RFPT '2A' in service.

2 lRR (ATC) Raise reactor power with Recirc to 65% power.

3 C (BOP) ~4160 60 y~ergency V Emergency Bus '2F' de-energizes with time compression TS (SRO) -_ .. re-en~I$lZ!~D

(.!egaiX-itna-re:'energizilig:)

q:e12air and _._.... .. ..'

f VlSu VlSCuCre ;;(6;;2 e ('

C~D i ' ' ' ; . ,~

(Z I) iv l ' c" Feedwater master controller losses power with time compression ~

~t d

4 C (ATC) 'L~"

a@air and re-ali!:mmenDto cWair re-alignmenDto Auto. :JOb J,O!)';

( 5(;f#.PA~ 3.: f'VC,I.)

5lG;',;{.:t:5 C:.* *f 3 tJIi: .:~ I'u 5 C (BOP) RBCCW Pump '2A' (simulate sheared shaft)

Standby RBCCW pump fails to start (manually started) 6 C (ATC) ~~IC Inad:v.ertent$Lat1_~iQ1~~~~~P5~

..RCIClnad-vertentStart with time compression.:repai~ andfe=-7 TS (SRO) ~lignment to_Auto _£

ce.:tCV'v~ \ alignment to Auto ;<oorr<;;:c.~*! :,,:~.;-cz~;e-:.*_~ 3;J- <[,~::1' 1 7 . . -,,-~.. ' ..._-/ 7 .--" M-(ALL) L) I '-------- ,. _ _ .~ ~ __ .... ~ __

_~

4160 V Station Service Bus '2D' Fault

. .-., r_'~' ,_~. *

,;::~. ~, ". l." . ~ " )- ~ I' (J I

J) c,_ ./ E i~~\_.-<;

,,-,IE ~ HPCI Failure To Start (2E41-F001 (2E41-FOOl Stuck) .. If! [i 1 SIhi.!U' ~!2--< Y&vw1 ;;.-, c:L .. ' ( RCIC Trip (::H,,' (~ RWCU Non-Isol Leak in DW "--.1 l". ~- ~. /Mtq'W;; V,It' \ ~~ '- I "". ' --..-.~ :.- 8 RHR 2E11-F028A or B RHR Torus Spray or Test Valve failed II C (BOP) closed. (Critical Task) I 9 '- ------. "'.'-- 1M 1\1 (ALL) 1 Emergency Depress due to low reactor water level. (Critical Task) -.. -.~~.-.-- ("

- (N)ormal, (R)eactivity, (R)eacti vi ty, (I)nstrument, (C)omponent, (M)ajor

./ of 3 Page 2 of3 Scenario Summary Facility: E. I Hatch Scenario No.: 5-01 Op-Test ap-Test No.: 2009-302 Draft NRC Dralt ( Initiating Conditions: Unit 2 is at 65%. Turnover Continue reactor startup and place the '2A' RFPT in service Summary:

Event 1: The "2A" RFPT will be placed into service.

Event 2: After the "2A" RFPT is in service the ATCA TC operator will raise reactor power using the Recirc system to approximately 65% power.

Event 3: ComponentlTS; 4160 V Emergency Bus '2F' will de-energize. The SS addresses Tech Specs for inoperable AC electrical distribution subsystem. With time compression repair 4160 V Emergency Bus '2F' will be re-aligned to Startup Auxiliary Transformer 2D.

Event 4: Component; The Feedwater master controller losses power with time compression repair and re-alignment to Auto.

Event 5: Component; RBCCW Pump '2A' will experience a sheared shaft and the standby RBCCW pump will not automatically start. The operator will manually start the standby RBCCW pump to restore system flow/pressure to normal.

Event 6: ComponentlTS; RCIC will experience an inadvertent start with time compression repair and re-alignment to standby.

(

Event 7: Major; A loss of all high pressure injection occurs as a result of the following: 4160 V Station Service Bus '2D' experiences a fault and de-energizes, "2C" Condensate Booster pump 2E41-F001 (Turbine Steam trips on low suction pressure (Time Delay), HPCI fails to start due to 2E41-FOOl Supply) is stuck closed, RCIC receives an unrecoverable trip. Also a small RWCU system leak occurs in the DW which causes DW pressure to exceed 1.85 psig.

Event 8: Component; RHR 2E11-F028A or B Torus Spray/Test Valve (depends on which loop of RHR the operator attempts first) will fail closed when the operator attempts to place Torus Spray/Cooling in service. The operator must transition to the other loop of RHR to spray/cool the Torus. (Critical Task)

Event 9: RWL will decrease to TAP.TAF. The SS will direct the ATC operator to open all SRVs to Emergency Depressurize the RPV. Reactor pressure will decrease to below the shut-off head of the low pressure ECCS pumps and RWL will be restored to above TAF using all available injection systems. After RWL is determined to be above TAP,TAF, injection valves will be throttled to control injection and raise RWL to the normal EOP RWL band. The plant will be emergency depressed due to low reactor water level. (Critical Task)

Page 3 of3 of 3 Critical Tasks NRC Draft Facility: E. I Hatch Scenario No.: 5-01 Op-Test No.: 2009-302 Critical Tasks

Manually open RHR 2EII-F028A1B 2EII-F028NB Torus Spray/Test Valve prior to exceeding 11 psig in the Torus to preclude damage to the downcomers. (Event 8)

Open ADS valves before RWL reaches -185 inches (Event 9)

( Page 1 of 19 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility: E. I Hatch Scenario No.: 5-02 Op-Test No.: 2009-302 Examiners: Operators: SRO RO BOP Initial Conditions. Reactor power is approximately 70% power holding for control rod sequence exchange due next shift. Turnover: APRM 'B' is bypassed due to failed CPU. RCIC is isolated following repair of the outboard isolation valve breaker. System restoration to standby per 34S0-E51-00l-2, RCIC System, is in progress at step 7.1.1.36. The functional test for the Valve has been performed. RCIC system will be unisolated and placed in standby. Event Malf. No. Event Event No. Type* Description ( N/A ~ N (BOP) Unisolate RCIC and place in standby 1 mfE5L250 C (BOP) RCIC Steam Line breaks in the Rx bldg. 2 svoE51074 TS (SRO) RCIC isolation valves fail to auto close (Critical Task) svoE51075 mfC5L14A TS (SRO) APRM '2A' Failure 3 mfN2L88A C (ATC) RFPT loop seal failure ~4 mf70022407 C (BOP) '2C' SSAC high temp condition 5 '2A & 2B' SSACs are manually started by BOP mfN21_87A C (ATC) RFPT '2A' receives High vibration trip signal but does not trip. ATC 6 manually trips RFPT '2A' N/A IN/A R (ATC) Insert Control Rods to exit RPI 7 mfS11_161 M(ALL) M (ALL) Loss of Offsite Power 8 mfR43_167A '2A' & '2C' EDG Fails to Start and cannot be started. mfR43 49C 'lB' EDG supplies power to '2F' 4160 V bus mfE41_235A C (BOP) HPCI fails to auto start on low RPV level or high DW pressure 9 mfE41 235B (Critical Task)

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

Appendix 0 Required Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.: 5-02 Event No.: 1 Page 2 of 19 Event

Description:

Unisolate RCIC and place in standby III Time I Position I Applicant's Actions or Behavior I SRO Directs BOP to unisolate RCIC and place in standby IAlAWW 34S0-E51-001-2, RCIC System, starting at step 7.1.1.36.

SIMULATOR OPERATOR: When 2E51-F007 is open, ENSURE Event Trigger (E51-1) is ACTWATED ACTIVATED BOP

Opens 2E51-F054 Steam Line Drain Valve

Opens 2E51-F008 Steam Supply Line Isol Valve

2E5l-F007 Steam Supply Isol Valve Throttles 2E51-F007

Fully Opens 2E51-F007 when turbine steam inlet pressure is within 50 psig of reactor pressure on 2B21-R623A 2B 21-R623 A or B (P601 (P60 1 panel)

Closes 2E51-F054, Steam Line Drain Valve when annunciator

( 602-308, 'RCIC Turbine Inlet Drain Pot Level High' clears Simulator Operator: At the direction of the Chief Examiner proceed to the next event.

0 Appendix D Required Operator Actions Form ES-D-2 ES-O-2 Op-Test No.: 2009-302 Scenario No.: 5-02 Event No.: 2 Page 3 of 19 Event

Description:

RCIC steam line break Time I Position I Applicant's Actions or Behavior Simulator Operator: At the direction of the Chief Examiner, ACTIVATE (RB-2)

mfE51_250 (RCIC Leak)

svoE51075 (F008 stuck open)

NOTE: It takes approximately 3 minutesfor minutes for the "Stm Chase SEC Clr Auto Started" to alarm.

When "Stm Chase SEC Clr Auto Started" alarms, ACTIVATE (RB-I): (RB-l):

svoDll174 D11-K609A Rx Bldg Pot ContamArea Contam Area Vnt 10 ramp 20

svoDll175 Dll-K609B Rx Bldg Pot ContamArea D11-K609B RxBldg Contam Area Vnt 10 ramp 20

svoDll176 svoD11176 Dll-K609C D 11-K609C Rx Bldg Pot ContamArea Contam Area Vnt 10 ramp 20

svoD11177 svoDll177 Dll-K609D Rx Bldg Pot ContamArea Vnt 10 ramp 20

mj601411 mf601411 026 Rx Bldg Pot Contam Area Radiation High (Annunciator On)

(

ALL Recognize annunciators:

657-006, 'Stm Chase SEC Clr Auto Started'

601-321, 'Leak Det Diff Temp High' BOP Responds to annunciator, 'Stm Chase SEC Clr Auto Started'"

Enters 657-006 and starts investigating the cause of the cooler auto start.

Confirms 2T41-B009, Secondary Stm. Chase Cooler is running

Monitors Steam Tunnel temps

Enters 34AB-T22-001-2, 'Primary Coolant System Pipe Break - Rx Building.

(

Appendix 0 Required Operator Actions Form ES-O-2 I,'l Op-Test No.: 2009-302 Scenario No.: 5-02 Event No.: 2 Page 4 of 19 Event

Description:

RCIC steam line break Time Position Applicant's Actions or Behavior I ATC Acknowledges 601-321, 'Leak Det Diff DiffTemp Temp High' and reports to SS.

Enters 601-321 and starts investigating.

Confirms which area is producing alarm

Enters 34AB-T22-003-2, 'Secondary Containment Control' SIMULATOR OPERATOR: ENSURE Event Trigger (ESl-2) (E51-2) is ACTIVATED when Steam Chase diff temp red light illuminates.

Note: It will take about 30 minutes for a Group 1I isolation to occur. At direction of the Chief Examiner, if P603-2 "Group 1I System A Trip" alarms, IMMEDIATELY DELETE mjESl_2S0.mfE51_250.

(

SRO

Enters the 31EO-EOP-014-2, 'Secondary Containment' EOP Flowchart on Secondary Containment High Differential Temperature.

Has an operator monitor Sec Cont. Temps.

Has operators monitor systems for source of the leak.

SIMULATOR OPERATOR: When EOP SC entered and Chief Examiner concurs:

ACTIVATE mfE5I_II3 mfESl_1l3 (RB-7) (RCIC Auto Isolation E5I-FOO8)

ESI-FOO8)

ENSURE Event Trigger (ESl-l)

(E51-1) is ACTIVATED when F007 is manually closed:

svoDIII74 svoDl1l74

svoDll17S svoDIII75

svoDIII76 svoDll176

svoDIII77 svoDll177

(

mf60I4II026 mf601411026

Appendix D Required Operator Actions Form ES-D-2

~I Op-Test No.: 2009-302 Scenario No.: 5-02 Event No.: 2 Page 5 of 19 Event

Description:

RCIC steam line break Time Position Applicant's Applicanfs Actions or Behavior I ALL Recognize annunciators:

602-302, 'RCIC Steam Line Diff Press High'

602-301, 'RCIC Turbine Trip'

602-313, 'RCIC Isolation Signal Logic A' BOP Responds to the following annunciators:

602-302, 'RCIC Steam Line Diff Press High'

602-301, 'RCIC Turbine Trip'

602-313, 'RCIC Isolation Signal Logic A'

(

Responds to failure of RCIC Isolation:

Places 2E51-F007 control switch to CLOSE.

Places 2E51-F008 control switch to CLOSE.

Informs SS of failure of 2E51-F008 to close SRO Reviews Tech Specs section 3.6.1.3.A "Primary Containment Isolation Valves" and determines:

2E51-F008 Inop

2E51-F007 must be closed and deactivated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.

Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2

\ If,~ Op-Test No.: 2009-302 Scenario No.: 5-02 Event No.:

3 Page 6 of 19 Event

Description:

APRM 2A failure I Time Position Applicant's Actions or Behavior I SIMULATOR OPERATOR: After Primary Containment Tech Spec cali, call, and as directed by the Chief Examiner, ENTER (RB-3) mfC51_14A (APRM 'A' Failure)

ALL Recognize annunciators:

603-210, 'APRM/OPRM Trip'

603-238, 'Rod Out Block'

603-239, 'RMCS/RWM Rod Block or Sys Trouble' ATC Responds to annunciators:

603-210, 'APRM/OPRM Trip'

603-238, 'Rod Out Block'

(

603-239, 'RMCS/RWM Rod Block or Sys Trouble' Informs SS APRM "A" failed downscale SRO

Reviews Tech Specs section 3.3.1.1 Condition A and determines that one required channel is inoperable and must be placed in trip in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.

(

Appendix D0 Required Operator Actions Form ES-D-2 ES-O-2 I~

. Op-Test No.: 2009-302 Scenario No.: 5-02 Event No.: 4 Page 7 of 19 Event

Description:

RFPT loop seal failure III Time Position Applicant's Actions or Behavior I SIMULATOR OPERATOR: At the direction of the Chief Examiner, ACTIVATE (RB-4)

mj65031541 "RFP Loop Seal Level Low (Annunciator On)"

mfN61_73 "Main Condenser Air In-leakage" NOTE: It takes approximately 10 minutes for vacuum to decrease to 25.7".

ALL Recognize "RFP Loop Seal Level Low" annunciator SIMULATOR OPERATOR: When sent as an SO out to the plant, wait 3 minutes and report:

(

2N22-F398 was closed and now is open

Seal water pressures are normal andlbut the lineup check is not completed.

ATe Respond to annunciator RFP Loop Seal Level Low

Sends an SO to confirm 2N22-F398 is open

Monitors vacuum at 2Hll-P650, 2HII-P650, on 2N21-R602

Sends an SO to confirm seal water lineup and pressures BOP Monitors Inlet Flow to Stack on 2N62-P600

Appendix 0D Required Operator Actions ES-D-2 Form ES-O-2 II

. Op-Test No.: 2009-302 Scenario No.: 5-02 Event No.: 4 Page 8 of 19 Event

Description:

RFPT loop seal failure I Time Position Applicant's Actions or Behavior I SIMULATOR OPERATOR: Delete m/65031541 mf65031541 when one of the following o/thefollowing occurs:

Condenser vacuum drops to 25.7"

2N21-F265 is closed DELETE mfN61_73 one minute after mf65031541 is deleted.

ATC With seal water pressures normal, closes 2N2l-F265 after 5 minutes of alarm 650-319, 'RFP Loop Seal Level Low' being received.

ATC Opens 2N21-F265 when 650-319, 'RFP Loop Seal Level Low' clears.

(

SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.

Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2 II'I Op-Test No.: 2009-301 Scenario No.: 5-02 Event No.: 5 Page 9 of 19 Event

Description:

'2C' SSAC high temp condition and secured. '2A & & 2B' SSACs are manually started.

II Time Position Applicant's Actions or Behavior I SIMULATOR OPERATOR: At the direction of the Chief Examiner ACTIVATE (RB-S)

mj70022407 Control Bldg Aftclr BOOlC BODlC Disch Temp High (Annunciator On)

aoPS2-R600 "Service Air Pressure"

aoPSI-R600 "Control Air Pressure" SIMULATOR OPERATOR: When the operator dispatches a SO locally, 2P51-R312C is wait 3 minutes, then NOTIFY operator that local temp on 2P5l-R312C l25°F and 2P5l-R302C 125°F 2P51-R302C is reading 385°F.

BOP Responds to annunciator 700-216, 'Control Bldg Aftclr BOOlC B001C Disch Temp High':

Sends SO to locally confirm temperature is>

is > 120 deg F on 2P51-R312C and 2P51-R302C.

(

Starts the 2A or 2B Service Air Compressor

Secures the 2C Service Air Compressor by placing its control switch in Pull-to-Lock.

SIMULATOR OPERATOR: When the operator secures the 2C Service Air Compressor, ENSURE Event Trigger (PSI-I) is ACTIVATED:

DELETES the following:

aoPS2-R600 "Service Air Pressure"

aoPSI-R600 "Control Air Pressure"

mj70022407 Control Bldg Aftclr BOOl BODlC C Disch Temp High (Annunciator On)

SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next event.

(

Appendix D 0 Required Operator Actions Form ES-D-2 II Op-Test No.: 2009-302 Scenario No.: 5-02 Event No.: 6 Page 10 of 19 Event

Description:

RFPT 2A high vibration trip signal I Time Position Applicant's Actions or Behavior I SIMULATOR OPERATOR: At the direction of the Chief Examiner, ACTIVATE mf65031553 mj6503I553 (RB-6) RFPT '2A' Excessive Vibration (Annunciator On).

ALL Recognize "RFPT 2A Excessive Vibration" ATC Responds to annunciator 650-331, 'RFPT 2A Excessive Vibration' and executes the Alarm Response Procedure:

Dispatches an SO to report local vibration on TMR Workstation Mark V Control Panel.

Confirm oil temperature is being maintained at 120 to 130°F

Contact System Engineer for further instructions

(

SIMULATOR OPERATOR: When contacted by the ATC, as the System Engineer, tell the operator you will look into the RFPT vibration and get back to the operator As the SO, wait two minutes after being dispatched and then report that 2A RFPT vibrations are 8 mils and increasing.

ATC With RFPT vibration> 6.0 mils, trips 2A RFPT.

SRO Directs A ATe TC to trip 2A RFPT.

SIMULATOR OPERATOR: When the operator trips the 2A RFPT, ENSURE Event Trigger (N21-1) is ACTIVATED:

DELETES 'RFPT '2A' Excessive Vibration' alarm SIMULATOR OPERATOR; At Chief Examiners direction, proceed to the next II event.

Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2

/ IIIf

\ Op-Test No.: 2009-302 Scenario No.: 5-02 Event No.: 7 Page 11 of 19 Event

Description:

Inserting control rods to exit RPI Time Position Applicant's Actions or Behavior ALL Recognize annunciator "Recirc A(B) Flow Limit" ATC Responds to annunciators 602-134 & & 602-234, 'Recirc A & & B Flow Limit'

Confirms Recirc pump A (B) speed has ronback by observing percent speed or RPMs.

Evaluate for Loop Flow Mismatch by observing there is NOT> 7.7 Mlbmlhr difference between the two loop flows.

Determine which speed limiter is enforcing by observing 33% speed on the speed meter.

Determines Region of Potential Instabilities is entered and requests STA's direction

(

SIMULATOR OPERATOR: As the STA, when the operator asks Jor for direction, then instructs the operator to insert control rods until Reactor Power is 30%.

SRO

Within 15 minutes of entering the Immediate Exit Region of the Power to Flow map, directs operator to exit the region by inserting control rods.

Ensures the plant has exited the Immediate Exit Region of the Power to Flow map within one hour.

Has a control rod movement brief per 34GO-OPS-065-0

Contacts Georgia Control Center (GCC) and Power Coordination Center (PCC)

SIMULATOR OPERATOR: As the STA, when the SS directs crew entry into 34GO-OPS-005-2, Power Changes, calls the SS and informs iriforms him that you will perform peiform the computer Jeedwater feedwater flow cross over corrections.

( SIMULATOR OPERATOR: When contacted as the GCC and pec, PCC, acknowledge the communication.

Appendix 0 Required Operator Actions Form ES-O-2

(\'\

( Op-Test No.: 2009-302 Scenario No.: 5-02 Event No.: 7 Page 12 of 19 Event

Description:

Inserting control rods to exit RPI Time Position Applicant's Actions or Behavior I ATC

Inserts control rods per 34GO-OPS-065-0, starting with control rod Group 54.

During rod insertion, rod steps will be performed in reverse sequential order, starting at the highest numbered step. (** rod steps are not required to be performed sequentially, but must be positioned to their RWM insert limit prior to inserting lower numbered groups).

Selects Rod

Places Control Rod movement switch to the IN position

Verifies Rod moves using Rod display information and Rx and Generator power decreasing.

ATC

If required, adjust 2C11-F003 2CII-F003 to get 220 - 280 psid drive water dp.

(\

ATC Note: RBM Downscale alarm may alarm during this movement due to the significant rod worth of these rods. It is allowed to flag the RBM Downscale and Rod Block alarm.

Releases Rod movement switch so that the control rod stops 1 position before the insert limit unless the insert limit is 00.

Initials Rod movement Sheet.

Verifier, if available, Initials Rod movement sheet.

Notifies the SS when they are out of the region of potential instabilities.

BOP Removes a CBP from service.

Note; It is not intended to wait until a Condensate Booster pump is removed from service, at Chief Examiner's direction, move on to the next Event

(

Appendix D Required Operator Actions Form ES-D-2 I,

.~

Op-Test No.: 2009-302 Scenario No.: 5-02 Event No.: 8 Page 13 of 19 Event

Description:

LOSP with 2A & 2C EDGs failure I Time Position Applicant's Actions or Behavior I SIMULATOR OPERATOR: At the direction of the Chief Examiner, mfSlI_I6I, "Loss of Offsite Power".

ACTIVATE (RB-8), mfSll_161, ALL Recognize a loss of offsite power and plant scram.

Note: The SS may assign one operator to perform Scram procedure placards RC-1, RC-2 and RC-3.

SRO

ATC to perform RC-1.

Assigns the ATC

Assigns the BOP operator to perform RC-2 and RC-3.

If time allows assigns TC-1 to be performed.

Enters the RC EOP flow chart, 31EO-EOP-01O-2, once reactor water level decreases to 3,"or reactor pressure increases to 1074 psig.

(

Directs EOP RC level control band of +3" to +50" ATC

RC-1 consisting of:

Performs RC-l

Inserts a manual scram.

Places the mode switch to shutdown.

ConfIrms Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.

NotifIes Notifies the SS of rod position check.

Places SDV isolation valve switch to "isolate" & confIrms confirms closed.

Inserts SRMs and IRMs.

Shifts recorders to read IRMS, when required.

Ranges IRMS to bring reading on scale.

NotifIes Notifies the SS when the above actions are complete.

Note: With a Loss of Offsite Power, the pertinent operator RC-2 actions are limited to checking ECCS.

(

11II

Appendix D0 Required Operator Actions ES-O-2 Form ES-D-2

'I'\

Op. Test No.: 2009*302 Op-Test 2009-302 Scenario No.: 5*02 5-02 Event No.: 8 Page 14 of 19 Event

Description:

LOSP with 2A & 2C EDGs failure I Time Position Applicant's Actions or Behavior BOP

Checks ECCS Injection Systems and verifies no initiation signal present.

Performs RC-3 consisting of:

Monitor RPV pressure.

Confirm proper operation of pressure control system (LLS and SRVs).

necessary, allows RPV pressure to exceed 1074 psig then cycles If any SRV to initiate LLS.

Maintain RPV pressure between 1074 and 800 psig.

Notify SS that LLS is the pressure control system.

(

SRO

ATC to address the plant electrical systems and enter the Directs ATC "Station Black" abnormal procedure, 34AB-R22-003-2, and "Diesel Generator Recovery" abnormal, 34AB-R43-001-2.

Calls for maintenance support in restoring all emergency 4160 VAC buses.

ATC Reviews EDG "2A" annunciators and determines there is a "Start Failure".

34AB-R43-00l-2, Diesel Generator Recovery, for EDG "A" :

IAW 34AB-R43-001-2,

Determines the EDG is not running

Determines the Auto Start System Operative Light is NOT lit.

Depresses the Shutdown Relay Pushbutton

Determines the EDG did NOT start.

Sends an SO to locally start the EDG

~II

0 Appendix D Required Operator Actions Reguired E8-0-2 Form ES-D-2 II

( Op-Test No.: 2009-302 Scenario No.: 5-02 Event No.:

8 Page 15 of 19 Event

Description:

LOSP with 2A & & 2C EDGs failure Time Position Applicant's Actions or Behavior II ATC Reviews EDG "2C" annunciators and determines a "Lube Oil Press Low" and "Emergency Engine Shutdown".

ATC Sends an SO to investigate the shutdown of the EDG SIMULATOR OPERATOR: When "When called about EDG "B" local switch, activate remote function ifR43_241, (RB-9) "Diesel Gen lB IB Engine Control Switch, assigned to U2, and inform the operator it is now selected to Unit 2.

( "When Unit 2 is selected, the EDG will automatically align and energize Note: When Unit 2.

ATC lAW 34AB-R43-00l-2, 34AB-R43-001-2, Diesel Generator Recovery, for EDG "B" :

Determines the EDG is running

Coordinates with Unit 1 SS to take the local switch to Unit 2

Reports to SS Bus 2F is now energized SIMULATOR OPERATOR: When "When called as the SO to investigate the EDGs, wait two minutes and report:

EDG "A" will not start locally, you will investigate further

EDG "c" has a break on the oil pump discharge discharRe line Note: The crew may start HPCI before -35" RWL or DW pressures increases to 1.85psig and therefore not be aware the auto initiation signal has failed.

f------+--+-------iI

0 Appendix D Required Operator Actions Form ES-D-2 ES-O-2

'I,~ Op-Test No.: 2009-302 Scenario No.: 5-02 Event No.: 8 Page 16 of 19 Event

Description:

LOSP with 2A & & 2C EDGs failure II Time I Position JI Applicant's Actions or Behavior BOP

Recognizes HPCI fails to auto start at -35" or 1.85 psig DW pressure and manually starts per 34S0-E41-001-2, prior to emergency depressurization.

Opens 2E41-F059, Lube Oil Cooling Wtr Vlv.

Starts 2E41-C002-2, Barometric Condenser Vacuum Pump.

Opens 2E41-F001, Turbine Stearn Steam Supply Vlv

Takes 2E41-C002-3, Aux Oil Pump, control switch to the START position.

Opens 2E41-F006, Pump Discharge Valve.

BOP

Confirm the following valves OPENED:

0 Turbine Control Vlv

( 0 Turbine Stop Vlv

Confirm the turbine comes up to speed

2E41-F012, Min Flow When flow increases to 790 GPM, confirms 2E41-FOI2, Vlv, closed.

Adjust flow with 2E41-R612, Flow Control to maintain water level.

BOP

If water level is above the auto initiation setpoint the operator may secure HPCI by:

0 Reducing speed to 2000 rpm using the flow controller in manual.

0 2E41-F001 is Depressing the trip pushbutton and holding until the 2E41-FOOI fully closed.

0 steam supply valve 2E41-FOO1.

Closing the stearn 2E41-FOOl.

Termination criteria: The scenario may be terminated, at the direction of the Chief Examiner, water level is being controlled with HPCI and 4160 VAC Bus F is re-energized.

(

Page 17 of 19 Scenario Summary Facility: E. I Hatch Scenario No.: S*02 5-02 OR* Test No.:

On-Test 2009-302

( NRC Draft Initiating Conditions: Unit 2 is at 70% power holding for control rod sequence exchange on next shift.

Turnover APRM 'B' is bypassed due to failed CPU. RCIC is isolated following repair of the outboard isolation valve breaker. System restoration to standby per 34S0-E51-001-2, RCIC System, is in progress at step 7.1.1.36. The functional test for the Valve has been performed. RCIC system will be unisolated and placed in standby Summary:

Event 1: Unisolate RCIC system and place in standby.

Event 2: ComponentlTS; ComponenUTS; A RCIC steam line will break outside of Primary Containment. The outboard isolation valve is failed open and cannot be closed. Both isolation valves fail to automatically close on an automatic isolation signal and must be manually closed. (Critical Task) The SS addresses Tech Specs for inoperable Primary Containment Isolation Valve.

Event 3: TS; APRM '2A' will experience a CPU failure and trip. The SS addresses Tech Specs for inoperable RPS instrumentation.

Event 4: Component; The RFPT loop seal will experience a low level condition causing condenser vacuum to degrade. The ATC operator will isolate the loop seal drain which stops

( condenser vacuum decreasing. Once the loop seal level is restored, the operator returns the loop seal system to normal lineup.

EventS:

Event 5: Component; The "2C" Station Service Air Compressor (SSAC) will receive a high discharge air temp alarm. The operator will start the 2A & 2B SSAC's and shutdown 2C SSAC.

Event 6: Component; The '2A' RFPT receives a high vibration trip signal but does not automatically trip. The ATC manually trips the '2A' RFPT

Event 7: The ATC inserts control rods to exit the Region of Potential Instabilities.

Event 8: Major; The plant will experience a Loss of Offsite power with the failure of the '2A' and '2C' Emergency Diesel Generators to start. 4160 V '2F' Emergency bus will be energized

'1 B' Emergency Diesel Generator or when the high by the operator taking manual control of the 'lB' DW pressure condition is received.

Event 9: As RWL decreases the HPCI system will fail to auto start on low RWL or high DW pressure. The operator will have to manually start the HPCI system to maintain RWL. (Critical Task)

(

Page 18 of 19 Critical Tasks NRC Draft Facility: E. I Hatch Scenario No.: 5-02 Op-Test No.: 2009-302 Critical Tasks

Manually isolate the RCIC isolation valves prior to exceeding the Maximum Safe Operating Temperature on the EOP Secondary Containment Flowchart. (Event 2)

Restores R WL injection with HPCI before RWL reaches -185 inches (Event 9)

RWL ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 7 1. RCIC steam line break outside Primary Containment (Event 2)

2. APRM '2A' CPU failure (Event 3)

3. RFPT loop seal low level (Event 4)

4. "2C" SSAC high discharge air temp (Event 5)

5. '2A' RFPT high vibration trip signal (Event 6)

6. LOSP with the failure of the '2A' and '2C' EDG (Event 8)

7. HPCI fail to start (Event 9)

(

")

')

Malfunctions After 1-2 1 1. HPCI fail to start (Event 9)

EOPEntry EOP Entry

3. Abnormal Events 2-4 3 1. RCIC steam line break outside Primary Containment (Event 2)

2. RFPT loop seal low level (Event 4)

3. "2C" SSAC high discharge air temp (Event 5)

4. Major Transients 1-2 1 1. LOSP with the failure of the '2A' and '2C' EDG (Event 8)

5. EOPs entered, 1-2 2 1. EOP SC/RR flowchart requiring substantive 2. EOP RC flowchart actions

6. EOPs contingencies 0-2 0 requiring substantive actions

7. Critical Tasks 2-3 2 1. Isolate RCIC isolation valves (Event 2)

RWL > -185 inches (Event 9)

2. Maintain RWL>

(

HLT 5 NRC Operating Exam Scenario 2 SHIFT TURNOVER I

\

UNIT 1 STATUS Power: 100%

Activities in progress: None Power: Approximately 70% power The following equipment is APRM 2B is bypassed due to failed CPU inoperable: RCIC is isolated following repair of the outboard isolation

( valve val ve breaker.

Turbine Eccentricity Vibration recorder 2N32-R600 is Out of Service and being worked by I&C.

Scheduled evolutions: System restoration to standby per 34S0-E51-001-2, 34S0-E51-00l-2, RCIC System, is in progress at step 7.1.1.36. The functional test for the Valve has been performed. Complete the procedure for placing RCIC in standby.

Surveillances due this None shift:

Active clearances: None

(

Rod Configuration: SeeRWM

Page 1 of 3 AppendixD Appendix D Scenario Outline Form ES-D-l NRC Draft Facility: E. I Hatch Scenario No.: 5-2 Op-Test No.: 2009-302 Examiners: Operators: SRO RO BOP

. /

Initial Conditions. APRM 'B' is bypassed due to failed CPU. Reactor power is approximately 70%

power holding for control rod sequence exchange due next shift. RCIC system will be unisolatedaucr unisolated and place in standby.

Turnover:

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

,..-; f'/

N (BOP) Unisolate RCIC and place in standby ~ ;} 00-:1

007 >

c.'i,

".- ,,'. "-i. /

( _. ,:;;",

2 f<'0/\ ,. ./ ? , C (BOP) RCIC Steam Line breaks in the Rx bldg. !

TS (SRO) RCIC isolation valves fail to auto close. (Critical Task) J

\!

I

.-I

.,.,,""\

TS (SRO) APRM '2A' Failure O(C 0(,/

3 ,L

~ C (ATC) RFPT '2A' Lube Oil Cooling Failure 5J 0DD~ 0~ ;,cOvYe'-J'c' 5cov'ce>tA.,) J, ~ (l)fut Yt!ftct \

S)

I'~:

~

( 5 ZotCJ i <ld; o /, l <;/'? "

;.,. '-'~ . :*,4 4

/ C (BOP) Loss of '2C' SSAC Co,..t0b" !'"(l-t-e.

COV£.,1.,.:#." dL.ce. ~?,~~:",,\ \)Cc \._ :,I-C j<";., 17(:/'f~'5"" -*h

- _*f--;:;. li ~"-; ~. .:f ,.:/-

(/~V1~

q)~(/Jt (I " '2B' SSAC does not start. BOP manually starts '2A' SSAC. SSAC.-\ '\ ;1 ItA 6 C (ATC) RFPT '2A' receives High vibrationJr4'fFstgnatbut-does'-not-trip.

vibrati0n,Jrci'fFstgfi1it-l?ut-does-not-trip.-_-.-.

ATC manually trips RFPT '2A'. ,'P,UtiJ..e ATCmanuallytripsRFPT ;?ve(e&"" v.-) vi' . C;~;/J v,viv';_:~0fj;:'--

~z}afif'!v,,,c.d:"*~'

"-;'~_ 1//

/

exit R

!-: '.1' "';".. ,-" C' i ~',,.,,

. IY:-'.',:_.L._

U?_~_.~__

'\

)

7 R (ATC)

Insert Control Insert Control Rods Rods to to exit RPI P I - " [('!' (y., .--"

8 M(ALL) Loss of Offsite Power loop lOor

'2A' & '2C' EDG Fails to Start and cannot be started.

supplies power to '2F' 4160 V bus.

'lB' EDG sUPRliesp_ower 9 C (BOP) HPCI fails to auto start on low RPV level or high DW pressure (Critical Task)

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

of 3 Page 2 of3 Scenario Summary Facility: E. I Hatch Scenario No.: 5-02 OD-Test Op-Test No.: 2009-302 NRC Draft Initiating Conditions: Unit 2 is at 70% power holding for control rod sequence exchange on next shift.

Turnover APRM 'B' is bypassed due to failed CPU. Reactor power is approximately 70%

power holding for control rod sequence exchange due next shift. RCIC system will be unisolated and place in standby.

Summary:

Event 1: Unisolate RCIC system and place in standby.

Event 2: ComponentlTS; A RCIC steam line will break outside of Primary Containment. The inboard isolation valve is failed open and cannot be closed. Both isolation valves fail to automatically close on an automatic isolation signal and must be manually closed (Critical Task). The SS addresses Tech Specs for inoperable Primary Containment Isolation Valve

Event 3: TS; APRM '2A' will experience a CPU failure and trip. The SS addresses Tech Specs for inoperable RPS instrumentation.

Event 4: Component; The RFPT '2A' lube oil cooling water temperature control valve will fail in the closed direction causing temperatures to rise on the '2A' RFPT. The operator takes manual control of the temperature control valve and re-establishes cooling water flow.

Event 5: Component; The "2C" Station Service Air Compressor (SSAC) will trip. The "2B" SSAC will not auto start, and the BOP operator will start the "2A" SSAC restoring air system.

(

Event 6: Component; The '2A' RFPT receives a high vibration trip signal but does not automatically trip. The ATC manually trips the '2A' RFPT

Event 7: The ATC inserts control rods to exit the Region of Potential Instabilities.

Event 8: Major; The plant will experience a Loss of Offsite power with the failure of the '2A' and '2C' Emergency Diesel Generators to start. 4160 V '2F' Emergency bus will be energized

'1 B' Emergency Diesel Generator or when the high by the operator taking manual control of the 'IB' DW pressure condition is received.

Event 9: As RWL decreases the HPCI system will fail to auto start on low RWL or high DW pressure. The operator will have to manually start the HPCI system to maintain RWL. (Critical Task)

/" \

Page 3 of 3 Critical Tasks NRC Draft Facility: E. I Hatch Scenario No.: 5-02 Op-Test No.: 2009-302 Critical Tasks

Manually isolate the RCIC isolation valves prior to exceeding the Maximum Safe Operating Temperature on the EOP Secondary Containment Flowchart. (Event 2)

Restores RWL injection with HPCI before RWL reaches -185 inches (Event 9)

(

AppendixD Scenario Outline Form ES-D-l ES*D*1 NRC Drajt Draft Facility: E. I Hatch E.IHatch Scenario No.: 5*03 5-03 Op* Test No.:

Op-Test 2009*302 2009-302 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at 75% power reducing to 70% making preparations for Main Turbine Control Valve Instrument Functional Testing.

Turnover: Perform 34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Test", for CV CV-l.

-1.

Event Malf.No.

Malf. No. ~vent Event Event No. Type* Description 1 N/A R (ATC) Reduce reactor power to 70% for Turbine Testing

~/A N/A N (BOP) Perform 34SV-C7l-005-2,"

34SV-C71-005-2," Turbine Control Valve Fast Closure

~2 Instrument Functional Test", for CV-1 ONLY starting at step 7.2.6.

,33 mfE51_65 mfE5L65 I (ATC) RCIC Torus Level Sensor Fails High; with failure of CST valve in

( loE51_FO 10E5 LFO 10G lOG 1 TS (SRO) mid position (Valve overload). Time compression repair and re-loE51_F01OR2 10E5LFOlOR2 alignment back to CST.

mf6023l26l mf60231261

~ mfCll_31A mfClL3lA C (ATC) CRD FCV '2A' Slow Failure mf603l1327 mf60311327 TS (SRO) aoCll-R600-l aoC11-R600-1 aoCll-R600-2 aoC11-R600-2 aoClI-R60l aoCll-R601 aoCll-R602 aoCll-R603 aoClI-R605 aoCll-R605

~5 mfE41_103 mfE4L103 C (BOP) Inadvertent start of HPCI. (Critical Task) 6 mtP64_l93A mfP64_193A C (BOP) Loss of DW Chillers mtP64 193B mfP64 f7 17 mfB21_123A mfB2L123A M (ALL)

M(ALL) Steam Line Break inside Drywell 8 diEll-F0l6A diE11-F016A C (ATC) RHR 2Ell-F016AIB 2E11-F016A/B Containment Spray Valve fails to OPEN and

~iE11-F016B diElI-F016B RHR Loop A pumps trip

~T-XXXfor iET-XXXfor (mfE11_115A (mfElLl15A mfElI 1I5C) mfE11 115C) 9 M (ALL)

M(ALL) Emergency Depress prior to Bulk Average DW temperature of 340°F (Critical Task)

(

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

Appendix 0 Reguired Operator Actions Form ES-O-2 II Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 1 Page 2 of 30 Event

Description:

Trip of "2C" Station Service Air Compressor I Time I Position I Applicant's Actions or Behavior I SRO

Directs RO to decrease reactor power to 70% by decreasing Recirc flow. Power decreases should be made as recommended by the STAlReactor Engineering at a rate not to exceed 10 MWe/min.

ATC

Decreases reactor power with Recirc flow lAW IAW 34GO-OPS-005-2 and 34S0-B31-001-2 by depressing either the Master Recirc Flow Control lower pushbuttons or the individual pump Speed Control lower pushbuttons.

Monitors power decrease by observing APRM and generator output indications.

(

May get the RBM Upscale and Rod Out Block alarm, if a peripheral control rod is not selected. This is expected and the operator may select a peripheral rod at this time.

May also get some Feedwater F eedwater heater level alarms. This is expected at this power level.

Simulator Operator enters the next event after power has been decreased by 5% or at the Chief Examiner's request.

Appendix D Reguired Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 2 Page 3 of30 of 30 Event

Description:

Perform 34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument CV-1 starting at step 7.2.6.

Functional Test", for CV-l Time 1I Position I Applicant's Actions or Behavior I BOP

From the MSV -CV test screen

Select CV#1

Select Test START

Confirm CV#1 slowly closes to 5% then fast closes from 5% to 0%

Confirm CV#4 opens, if CV#2 and CV#3 approach full open

Confirm annunciators alarm:

603-102, TURB CNTL VLV FAST CLOSURE TRIP,

603-117, REACTOR AUTO SCRAM SYSTEM A TRIP

(

BOP

WHEN plant conditions have stabilized

Select Test OFF

CONFIRM CV # 1 slowly opens from 0% to pretest position

CONFIRM all reactor parameters return to normal

RESET Half Scram using 2C71-S5, Reactor Scram Reset switch, 2H11-P603 2Hll-P603

CONFIRM Control Valve CV # 1 OPENS

CONFIRM CV # 4 CLOSES

CONFIRM the following annunciators CLEAR:

603-117, REACTOR AUTO SCRAM SYSTEM A TRIP

603-102, TURB CNTL VLV FAST CLOSURE TRIP, ATC

Enters 34AR-603-117-2, and confirms no control rod movement by running a Control Rod position check. Notifies SS of results

(

Appendix D Required Operator Actions Form ES-D-2 II'\

Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 2 Page 4 of30 of 30 Event

Description:

34SV-C71-005-2,"

Perform 34SV -C71-005-2," Turbine Control Valve Fast Closure Instrument CV-l Functional Test", for CV -1 starting at step 7.2.6.

I Time Position Applicant's Actions or Behavior BOP

Contacts SSS to confirm:

A1l2C71A-K8A, 2C71A-K8B, 2C71A-K8C, 2C71A-K8D, relays, are energized.

BOP

CV#l Test in complete.

Notifies the SS that CV#1

(

Simulator Operator enters the next event after surveillance is complete OR at the Chief Examiner's request.

(

Appendix D 0 Reguired Operator Actions Form ES-D-2 ES-O-2

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Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 3 Page 5 of30 Event

Description:

RCIC Torus Level Sensor Fails High; with failure of CST valve in mid position.

I Time Position Applicant's Actions or Behavior At the Chief Examiner's direction, Simulator operator enters: RB-3 mfE51_65 loE51_FOIOGl loE51_F01OGl loE51_FOIOR2 loE51_F01OR2 mj60231261 All * "TORUS LEVEL HIGH RCIC", (602-230) and "RCIC VALVES MOTOR OVERLOAD" (602-309) alarms are received on P601 SS

Directs an operator to enter 34AR-602-230-2 and 34AR-602-309-2

( ATC

Enters 34AR-602-230-2

Determines that RCIC Suction has aligned to the torus

Verifies 2E51-F003, 2E51-F031 and 2E51-F029 are open .

Verifies that 2E51-FOlO is closed. (Cannot perform this step because 2E51-FOlO 2E51-FOIO has no light indication)

Determines that Torus level is not high and is stable.

Determines that RCIC should not have auto swapped to the torus.

Notifies SS that RCIC suction valve, 2E51-FOlO, has no light indication.

ATC

Enters 34AR-602-309-2

Determines that 2E51-FOIO 2E51-FOlO has no lights illuminated.

Dispatches operator/Maint operatorlMaint to reset the thermal overload for 2E51-FOlO (MCC 2R24-S021 Brkr # 2B)

(

Appendix D Reguired Operator Actions Required Form ES-D-2

~r Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.:

of30 Page 6 of 30

~.

Event

Description:

RCIC Torus Level Sensor Fails High; with failure of CST valve in mid position.

III Time Position Applicant's Actions or Behavior SS

2E51-FOIO Dispatches operatorlMaint to reset the thermal overload for 2E51-FOI0 (MCC 2R24-S021 Brkr # 2B) (ATC may do this also)

Directs operator to monitor suction pressure on HPCI.

Simulator Operator, 5 S minutes after Maint is sent to investigate, notify the 2ES1-LS-N062B hasfailed control room that 2E51-LS-N062B has failed upscale.

ATC

Reports to the SS that 2E51-LS-N662B has failed upscale SS

Enters Tech Specs 3.3.5.2, Condition D.2.1 & D.2.2, to place the channel in trip or align RCIC suction to the Suppression pool within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Simulator Operator, after 3 minutes from being dispatched to the breaker, loES1-F010G1, loE51-F010R2 DELETE overrides loE51-F010G1, loES1-F010R2 and mf60231261 AND 2ES1-F010 As operator, notifies the control room that the breaker for 2E51-FO 10 has been reset.

ATC

2E51-FOIO has traveled full closed.

Confirms 2E51-FOlO

Informs SS that 2E51-FOlO is full closed.

Appendix 0 Required Operator Actions Form ES-O-2

(

If~

Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: Page 7 of 30

-- Event

Description:

RCIC Torus Level Sensor Fails High; with failure of CST valve in mid position.

Time Position Applicant's Actions or Behavior I At the Chief Examiner's direction, Simulator Operator, DELETE mfE51_65, then as 1& I & C, report that it is now one hour later (time compression) and that 2E51-N062B repair and calibration is complete.

SS

Directs Operator to align RCIC to the CST ATC

34S0-E51-001-2 step 7.3.7 to align RCIC to the CST.

Enters 34S0-ESI-001-2

Starts' closing 2ESI-F029 2E51-F029 and 2ESI-F031, 2E51-F031, then starts opening

( 2E51-FOlO prior to 2ESI-F029 2ESI-FOlO 2E51-F029 and 22E51-F031 ESI-F031 going full closed.

When valves have completed stroking, notifies the SS that RCIC is aligned to the CST.

SS

Determines that the LCO for 2ESI-N062B 2E51-N062B is met.

Simulator Operator Proceed to the next Event at the Chief Examiner's direction.

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 4 Page 8 of 30 Event

Description:

CRD FCV '2A' Slow Failure; Places standby FCV in service Time I Position I Applicant's Actions or Behavior At the Chief Examiner's direction, Simulator operator enters: RB-2 aoC11-R60l aoCll-R601 aoC11-R605 aoC11-R600-1 aoC11-R600-2 aoC11-R602 Simulator operator when aoC11-R601 indicates 1482 psig enters RB-3 and 30 seconds later enter RB-4.

ATC

Receives Recei ves Charging Water Pressure High alarm alann

Will also receive CRD Hydraulic Temp High alarm alann a short time later

Determines that the CRD Flow Control Valve A has failed closed.

Notifies SS that the CRD Flow Control Valve A has failed closed.

Enters

603-139, Charging Water pressure High

603-140, CRD Hydraulic Temp High

34AB-Cll-001-2, Loss ofCRD of CRD System Note: With the loss of the CRD FCY, FCV, the ATC may address 34AB-C11-001-2, 34AB-Cll-00l-2, Loss ofCRD",jirst.

SS

SS/ATC dispatches a SO/Maint to investigate the cause of the FCV failing closed.

SS/ATC dispatches a SO to Monitor CRD temperatures

Directs the operator to perform actions per the ARPs and of CRD system.

34AB-C11-001-2, Loss ofCRD 34AB-Cll-001-2,

May direct operator to swap Flow Control Valves at this time, or may wait for report from SO, before ordering the swap.

(

Appendix 0 Required Operator Actions Form ES-O-2 I'\~

Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 4 Page 9 ofof30 30 Event

Description:

CRD FCV '2A' Slow Failure; Places standby FCV in service I Time Position Applicant's Actions or Behavior ATC

603-139, Charging Water pressure High step 5.6 directs operator to shift to standby flow control valve per 34S0-Cll-005-2.

34S0-C11-005-2.

603-140, CRD Hydraulic Temp High

Dispatches a SO to monitor CRD temperatures locally at 2C11-R018 (130 Rx Bldg) 2CII-ROI8 Simulator Operator reports, as SO at the FCV, that the FCV has failed closed due to an air leak on the supply line, and that you have isolated the air line and stopped the leak.

IflWhen requested and if the CRD High Temp alarm is illuminated, Simulator lflWhen Operator, as operator checking CRD Temps, reports that 2 CRD drives are

>250°F. 30-11 at 260°F, 22-35 at 265°F and some others are slowly increasing.

SS Directs operator to swap Flow Control Valves ATC Enters:

34S0-CII-005-2, 34S0-C11-005-2, CRD System, to swap Flow Control valves

Places 2CII-R600 2C11-R600 to Manual

Directs SO to locally shift CRD FCV Simulator operator DELETE the following overrides:

aoCII-R600-1 aoCJJ-R600-J aoCJJ-R600-2 aoCII-R600-2 aoCJJ-R602 aoCII-R602 aoCII-R603 aoCJJ-R603 aoCJJ-R605 aoCII-R605 Simulator Operator, if the operator does not place 2C11-R600 2CII-R600 to manual with

( the output at "0", tell him as the SO that the system flow is matched at "0" gpm and tell him that you are ready for him to take control of the system from the Control Room.

Appendix 0 Required Operator Actions Form ES-O-2 I,

!~

( Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.:

5-03 Event No.: 4 of30 Page 10 of 30 Event

Description:

CRD FCV '2A' Slow Failure; Places standby FCV in service III Time Position Applicant's Actions or Behavior Simulator Operator ENTER rfCll_24 to "B", then as the SO, report that the CRD FCV's have been shifted locally and that control room actions to complete the shift can be taken.

ATC

Returns CRD System to normal configuration by:

Adjusting 2CII-R600 to desired flow

Places 2CII-R600 to AUTO

Confirms system parameters are normal 2Cll-R600 output, DELETE Simulator Operator, as the operator increases 2CJJ-R600 aoCll-R601 and mj60311327.

aoCll-R60J mf60311327.

(

ATC * "Charging Water Pressure High" alarm clears

"CRD Hydraulic Temp High" alarm clears

Reports to SS that CRD flow control valves have been shifted and the CRD System has been restored to normal configuration.

Simulator Operator Proceed to the next llC IIC failure at the Chief Examiner's direction.

(

Appendix D 0 Required Operator Actions Reguired ES-D-2 Form ES-O-2 Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 5 Page 11 of 30 Event

Description:

HPCI system inadvertent start II Time I Position I Applicant's Actions or Behavior I Simulator Operator, at Chief Examiner's direction, call the ATC operator and as the Lab request the control room get a routine reading on the Inlet Flow to 2N62-R604 located on 2N62-P600 panel.

Stack on recorder 2N62-R604located (This is to get the ATC operator to go away from the HPCI panel, allowing the BOP the opportunity to respond to HPCI.)

Simulator Operator, at Chief Examiner's direction, ENTER RB-S, RB-5, mfE41 103, HPCI Inadvertent Initiation.

ALL

Recognize and report HPCI has started from an invalid initiation signal.

(

BOP

Verifies reactor water level is stable.

(May receive APRM Hi Alarm and Reactor Water Level Hi alarm.)

Verifies Drywell Pressure is normal.

Enters 34AB-ElO-001-2 SS

Direct the operator to secure HPCI from placard IAW 34S0-E41-001-2, High Pressure Coolant Injection (HPCI) System.

0 Appendix D Required Reguired Operator Actions Form ES-D-2 ES-O-2

"'\

( Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 5 Page 12 of 30 Event

Description:

HPCI system inadvertent start Time Position Applicant's Actions or Behavior BOP

Secure HPCI as follows: (Critical Task)

Depresses and holds the HPCI Turbine Trip push-button.

When HPCI turbine has stopped, places the HPCI Aux Oil Pump in Pull To Lock off.

When the "HPCI Turbine Brg Oil Press Low" alarm is received, releases the HPCI Turbine Trip push-button.

BOP

IF injection occurs from HPCI, may receive the "FEEDWATER

( CONTROL SYSTEM TROUBLE" alarm, 603-132

Enters ARP and places Reactor Level Mode Select Switch to MAN and Feedwater Control Mode select switch to l-ELEM.

After HPCI is shutdown, returns the Reactor Level Mode Select Switch to AUTO and Feedwater Control Mode select switch to 3-ELEM lAW 34S0-N21-007-2.

(

Appendix 0 Required Operator Actions Form ES-O-2 I~I~

Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 5 Page 13 of 30 Event

Description:

HPCI system inadvertent start Time Position Applicant's Actions or Behavior Simulator Operator - After the SS declares HPCI inop per tech spec 3.5.1.

3.S.1.C, C,

as I && C tech called to resolve the HPCI problem, inform the SS that the HPCI initiation logic appears to be causing the inadvertent start signal and that you will be investigating the problem further.

SS

Declares HPCI inoperable and determines that Tech Spec 3.5.1 Condition C.1 and C.2 must be met consisting of:

Verifying within one hour that RCIC is operable by administrative means, and

HPCI is restored to operable status within 14 days .

(

Proceed to the next event at the Chief Examiner's direction

Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2 I,1\

Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 6 Page 14 of30 of 30 Event

Description:

Loss of Drywell Chillers I Time Position Applicant's Actions or Behavior I At the Chief Examiner's direction, Simulator Operator enters RB-6, (mjP64_193A&nifP64_193B)

(mjP64_193A&mjP64_193B)

ALL

The following alarms will be received:

650-201, DRYWELLrrORUS RCDR R627 TEMP HIGH

700-105, DRWL CHILLED WTR B006A SAFETY SID

657-025, MULTIPOINT TEMP RCDR 2T47-R626 TEMP HIGH

654-004, MULTIPOINT TEMP RCDR 2T47-R620 TEMP HIGH

650-214, PANEL 2HI1-P654 2HII-P654 SYSTEM TROUBLE

650-224, PANEL 2HI1-P657 2HII-P657 SYSTEM TROUBLE

603-115, PRIMARY CNMT PRESSURE HIGH

(

Note: With the loss of both DW chillers, the BOP/SS may address Coolers",

34AB-T47-001-2, Loss of DW Coolers ", first.

SS

When venting is required; Directs Operator to vent the drywell .

Appendix 0 Required Operator Actions Form ES-O-2 Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 6 Page 15 of 30 Event

Description:

Loss of Drywell Chillers Time Position Applicant's Actions or Behavior I BOP

Enters 34S0-T46-00l-2, "Standby Gas Treatment System" procedure or uses placard at the 2HII-P657/P654 panel to start SBGT 2A or 2B.

BOP 0 2T46-FOOI (A or B) or 2T46-F003 (A or B) for the Opens 2T46-FOOl (Placard) subsequent train.

0 Places SBGT Fan (2A or 2B) control switch to "RUN."

0 Receives alarm 2B (or 2A) SBGT Switch Not In Auto (654-076)

(or 657-091) 0 Confirms 2T46-F002 (A or B) OPENS 0 Confirms SBGT Heater red light illuminates.

(

Enters 34S0-T48-002-2, "Containment Atmosphere Dilution System" or uses placard to vent the Drywell.

BOP 0 Opens 2T48-F334A or 2T48-F334B (both valves may be opened)

(Placard) 0 Receives alarm DW Vent Exh Bypass Vlv Open (654-002) or (657-008) 0 Receives alarm DRWUTorus N2 MID MIU 2 Inch Isol Valves Open (654-035) or (657-042) 0 Opens 2T48-F335A or 2T48-F335B(both valves may be opened) 0 Opens 2T48-F336A or 2T48-F336B. (both valves may be opened) 0 Monitors DW pressure

(

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0 Appendix D Reguired Operator Actions Required Form ES-D-2

-,I~

5-03 Event No.:

Op-Test No.: 2009-302 Scenario No.:

Page 16 of 30 Event

Description:

Loss of Drywell Chillers I Time Position Applicant's Actions or Behavior I SS

IAW 34S0-T48-002-2 .

Direct the operator to fast vent the Drywell lAW BOP

Confirms that none of the following alarms are illuminated:

SBGTIDRYWELL SBGT/DRYWELL AND TORUS RADIATION mGH HIGH (601-402)

FISSION PRODUCT PARTIC RADN mGHllNOP HIGHIINOP (602-406)

FISSION PRODUCT IODINE RADN HIGHIINOP (602-412)

FISSION PRODUCT GAS mGHllNOP HIGHIINOP (602-418)

CONTAINMENT RADIATION HIGHIINOP (602-436)

Opens 2T48-F319, Drywell Vent Vlv (2Hll-P602).

(

Opens 2T48-F320, Drywell Vent Vlv (2Hll-P601).

(2Hll-P60l).

WHEN Drywell pressure is < 0.5 PSIG on 2T48-R607A 2T48-R607 A OR 2T48-R607B, close 2T48-F320, Drywell Vent Vlv.

Close 2T48-F319, Drywell Vent Vlv.

(

Appendix D Required Operator Actions Form ES-D-2

'l'I

( Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 6 Page 17 of 30 Event

Description:

Loss of Drywell Chillers I Time Position Applicant's Actions or Behavior I ATC

Enters 34AB-T47-001-2, Loss ofDW Coolers

Monitors Drywell pressure and temperature

Corrects reactor water level indications as necessary for high Drywell temperatures per 34AB-B21-002-2, RPV Water Level Corrections

Reminds SS of PC EOP Flow chart entry conditions

Monitors for any peak Drywell temperatures per Attachment 1 on SPDS panel and if exceeded for 30 minutes, enters 34GO-OPS-014-2, Fast Reactor Shutdown

May request to crosstie Rx Bldg Chilled Water to the Drywell Chilled Water System per the Cross Connecting The 2P64 and 2P65 Systems section of 34S0-P64-001-2.

34S0-P64-00l-2.

(

SS

Enters 31EO-EOP-012-2, Primary Containment flow chart.

Simulator Operator enters the next event at the Chief Examiner's request.

(

Appendix 0 Reguired Operator Actions Form ES-O-2 If Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 7 Page 18 of 30 Event

Description:

Steam line breaks inside containment Time I Position I Applicant's Actions or Behavior I At the Chief Examiner's direction, Simulator operator enters: RB-7

mfB2L123A All

Determines that DW pressure is increasing and approaching 1.85 psig.

SS

Orders the Rx manually scrammed (may not have time to insert manual scram before the Rx auto scrams).

Directs ATC ATC to perform RC-l placard

(

Directs BOP to perform RC-2 and RC-3 placards

Enters RC EOP Flowchart

As time allows,

Dispatches personnel to the EDGs to check for proper operation .

Directs reopening 2P41-F316A-D lAW JAW 34AB-P41-00l-2, 34AB-P41-001-2, Loss of PSW

(

Appendix 0 Required Operator Actions Form ES-O-2 If Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 7 Page 19 of 30 Event

Description:

Stearn line breaks inside containment II Time Position Applicant's Actions or Behavior ATC

Performs RC-1 consisting of:

Inserts a manual scram.

Places the mode switch to shutdown.

Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.

Notifies SS of rod position check.

Places SDV isolation valve switch to "isolate" && confirms closed.

If not tripped, places the Recirc pumps at minimum speed.

Inserts SRMs and IRMs.

Shifts recorders to read IRMS, when required.

Ranges IRMS to bring reading on scale.

Notifies the SS when the above actions are complete.

BOP

Performs RC-2 actions consisting of:

Confirms proper Level Control response:

Checks ECCS Injection Systems and secure as necessary.

Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.

IF set down does not auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.

Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2 II

( Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 7 Page 20 of30 of 30 Event

Description:

Steam line breaks inside containment Time Position Applicant's Actions or Behavior I BOP

When feed flow is less than the capacity of the Stu level control valve

(~ 1.5 mlbmlhr), then:

(:::::

Opens 2N21-F125.

2N21-FI25.

Places 2C32-R619, FW Stu level control valve controller, in Auto, set at approximately 9 inches.

Closes 2N21-FIlO.

2N21-FllO.

Trips One RFPT.

Controls RWL with RFPTs, HPCI and/or RCIC. Notifies SS if RWL gets outside assigned band.

RWL

( All

At paneI2HII-P601, Confirms 2 Core Spray pumps are running and that ONLY the BLoop RHR pumps are running (A Loop RHR pumps failed and will not run)

SS

Notifies Maintenance to investigate the A Loop of RHR pump failure

(

Appendix D 0 Reguired Operator Actions Form ES-D-2 ES-O-2 Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 8 Page 21 of30 of 30 Event

Description:

RHR 2EII-FOI6AIB 2E11-F016AIB Containment Spray Valve failure with RHR Loop A pump failure Time I Position I Applicant's Actions or Behavior I SS

Per the PC flowchart, verifies torus level is <285 inches and directs an operator to place Torus Sprays in service ATC

Sprays the Torus per 34S0-EII-010-2 34S0-E11-010-2 placard on the 2Hll-P601 2H11-P601 Panel as follows:

Places Cnmt Spray Vlv Cntl switch in the MANUAL position.

Starts RHR pump(s) in loop AlB, if not already running.

Opens 2Ell-F028A1B 2E 11-F028A1B

Throttles Open 2E11-F027A1B 2Ell-F027A1B

Notifies SS that RHR is in Torus Sprays

( (One loop of RHR will be placed in Torus Sprays. The flow is only 700gpm, so it may be difficult to see flow indication from a distance.)

SS

When Torus pressure exceeds 11 psig, verifies that Torus Level is <215 inches, in the safe area of Graph 8 (DWSIL) and Directs an operator to:

Place all DW D W cooling fans to off

Place both Recirc pumps to P1L PTL off

(

Appendix D Required Operator Actions Reguired Form ES-D-2 I~

~ ,

Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 8 Page 22 of30 Event

Description:

RHR 2EII-F016NB 2E11-F016NB Containment Spray Valve failure with RHR Loop A pump failure II Time Position Applicant's Actions or Behavior I ATC

Places all DW cooling fans control switches in the OFF position.

Places both Recirc pumps to the PTL Off

Notifies the SS that the fans are off.

Notifies the SS that both Recirc pumps are off.

Sprays the Drywell using 34S0-E11-010-2 34S0-EII-0l0-2 placard at the 2HII-P601 panel.

Places Cnmt Spray NB Vlv Cntl switch in the MANUAL position.

Starts RHR pump(s) in loop AlB, if not already running.

Opens 2EII-F021NB 2E11-F021A1B

Opens 2Ell-F016NB 2E11-FOI6A1B (NEITHER VALVE WILL OPEN AND BOTH RHR LOOP A PUMPS HA HAVE VE TRIPPED)

( Note: If the operator starts with the B Loop of RHR to spray the DW, the 2EII-F0I6B valve will not open requiring the operator to transition to the A 2E11-FOl6B Loop of RHR. Once the control switch is placed to OPEN on 2Ell-FOl6A 2E11-F016A both RHR pumps in the A Loop will trip.

ATC

Informs SS that the 2EII-FOI6B 2EII-F016B will not open and both RHR Loop A pumps have tripped and DW sprays cannot be performed.

Dispatches SOlMaint to investigate 2EII-FOI6B 2EII-F016B and both RHR Loop A pumps.

SS 2EII-FOlO May direct the operator to crosstie RHR loops using the 2E 11-FO 10 crosstie valve and spray using the A RHR Loop DW spray valves.

(\ Simulator operator, if the crew requests the breaker to be turned onfor on for 2E11-FOlO, after 4 minutes, inform the SS that the breaker for this valve will not FOIO, close in.

Appendix 0 Required Operator Actions Form ES-O-2 ES-D-2 Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 9 Page 23 of 30 Event

Description:

Emergency Depress prior to Bulk Average DW temperature of 340 0P 340°F III Time I Position I Applicant's Actions or Behavior I SS

Prior to Bulk Average DW Temp exceeding 340°F.

Directs Anticipating Emergency Depressurization Note: Based on the timing of the transition to the RC-RPV Control (Non A TWS), there may not be time to Anticipate Emergency Depress prior to ATWS),

performing Emergency Depressurization

Orders 7 ADS valves open for Emergency Depress .

(Critical Task - Open 7 SRVs prior to Bulk Average DW Temp exceeding 340°F. Critical task is met when 5 SRVs have been opened).

SS

If the need to Emergency Depressurize is recognized in time, then Anticipates Emergency Depressurization.

Assign an operator to fully open all Main Turbine Bypass Valves .

(

Appendix 0 Required Operator Actions Form ES-O-2

'~II Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 9 Page 24 of 30 Event

Description:

Emergency Depress prior to Bulk Average DW temperature of 340°F Time Position Applicant's Actions or Behavior I ATCIBOP

On the DEHC panel 0 Select the Control> Bypass Valve screen.

0 illsert Insert a ramp rate of 100, then press OK.

0 Insert illsert a bypass valve position of 100, then press OK.

0 Checks that the Bypass Valve Jack status is active.

0 Recognizes that all Bypass Valves open.

0 Reports to the SS that all Bypass Valves open ATCIBOP

Places the switches for 7 ADS valves in the open position .

(Critical Task - Open 7 SRVs prior to Bulk Average DW Temp

( exceeding 340°F. Critical task is met when 5 SRVs have been opened).

0 If Anticipate Emergency Depressurization was performed, the amber lights for the SRV s will not illuminate if pressure has been reduced to below approximately 300 psig. ill In this case the operator must use 2HII-P614 2HI1-P614 recorder indication to monitor tail pipe temperatures for the SRVs to verify the valves actually opened (Recorder 2B21-R614).

0 Depending on Reactor Water Level prior to opening ADS valves, RWL may swell to above 60 inches, requiring the operator to enter 34AB-C32-00l-2, Reactor Water Level Above 60 inches.

34AB-C32-001-2,

Operator secures all injection other than CRD

(

Appendix D Required Operator Actions Form ES-D-2 I,

~,

Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 9 Page 25 of 30 Event

Description:

Bulk: Average DW temperature of 340 Emergency Depress prior to Bulk 340°F 0P I Time Position Applicant's Actions or Behavior I BOP

Starts controlling RWL with low pressure systems (LPCI, Core Spray, or Condensate) as Rx pressure decreases. During the Emergency Depress will not be able to maintain inside the RWL band, but should restore RWL to within the band at some point after the Emergency Depress.

Simulator Operator - The scenario can be stopped at any time after emergency performed and when the crew determines that RPV Flooding is depress is peiformed required OR as directed by the Chief Examiner. Placing Torus cooling in service is not a required part of this event.

ATC

If time and man power allows, places torus cooling in service per 34S0-EII-01O-2, RHR System, using the placard.

NOTE: Only the B Loop of RHR will be placed into service due to the A Loop RHR pump failures

(

Appendix 0 Required Operator Actions Form ES-O-2 If'I Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 9 Page 26 of30of 30 Event

Description:

Emergency Depress prior to Bulk Average DW temperature of 340°F I Time Position Applicant's Actions or Behavior

Place RHRSW in operation per 34S0-EII-010-2 by performing the following:

Prelube RHRSW pump.

Override 2EII-F068B Low Discharge Pressure Interlock.

Position 2EII-F068B to 45% OPEN

Start RHRSW pump.

Place 2EII-F068B Low Discharge Pressure Interlock switch to NORMAL position.

Position 2EII-F068B to obtain < 4400 GPM AND < 450 PSIG.

(

IF desired to start SECOND pump,

Throttle 2EII-F068B to achieve max flow rate (not to exceed 4400 GPM).

2EII-F068B an additional 5%.

Open 2Ell-F068B

Start Second RHRSW Pump.

Position 2EII-F068B to obtain < 7600 GPM or with SS approval

<8800 GPM AND < 450 PSIG.

NOTE; Since operation is lAW the EOPs, Shift Supervisor approval is

~ 8800 required prior to exceeding 7600 GPM. In this case, flow is limited to ::{

GPM with two RHR Service Water Pumps operating in a single RHR Service Water loop.

Open 2E2EII-F048B.

11-F048B.

Open 2E 11-F003B.

2EII-F003B.

Start RHR Loop B pump(s).

Open 2EII-F028B.

(

Appendix D 0 Reguired Operator Actions Form ES-D-2 ES-O-2

,"~

(,

Op-Test No.: 2009-302 Scenario No.: 5-03 Event No.: 9 Page 27 of30 of 30 Event

Description:

Emergency Depress prior to Bulk Average DW temperature of 340°F I Time Position Applicant's Actions or Behavior I NOTE: RHR system rated flow is 7700 gpm with one pump or 17,000 gpm with two pumps.

IF the Hx Bypass Vlv, 2EII-F048B is NOT full OPEN, RHR Flow

s; 11,500 gpm.

is limited to ::;

Throttle Open 2EII-F024B.

Open 2EII-F047B.

Close 2EII-F048B

Throttle 2EII-F068B to maintain> 20 PSID Hx B dp.

(

Refer to 34S0-EII-01O-2.

34S0-Ell-0l0-2.

Simulator Operator - The scenario can be stopped at any time after emergency depress is peiformed performed and when the crew determines that RPV Flooding is required OR as directed by the Chief Examiner.

(

of30 Page 28 of 30 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility: E. I Hatch Scenario No.: 5-03 0Op-Test 0 -Test No.: 2009-302 Examiners: _ _ _ _ _ _ _ _ _ _ _ Operators: _ _ _ _ _ _ _ _ _ _ _ _ _ _--=S:..::R.:..O:::- SRO

---------------------------------- RO BOP Initiating Conditions: Unit 2 is at 75%.

Turnover 34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Perform 34SV-C71-005-2,"

Functional Test", for CV-1 ONLY Summary:

Event 1: Reduce reactor power to 70% using Recirc for Turbine Testing.

34SV-C71-005-2," Turbine Control Valve Fast Closure Instrument Functional Event 2: Perform 34SV-C71-005-2,"

Test", for CV-l ONLY starting at step 7.2.6.

InstrumentrrS; The RCIC Torus Level Sensor Fails High; with failure of CST valve in Event 3: InstrumentffS; mid position (Valve overload). Time compression repair and re-alignment back to CST.

Event 4: Component; The CRD FCV '2A' will slowly fail causing a loss of CRD. The operator

( normal.

will take manual actions to swap FCV and return the CRD system to normaL

Event 5: Component; rrs;ITS; The HPCI system will experience an inadvertent start. The operator takes manual control to secure HPCI. (Critical Task)

Event 6: Component; Loss OF DW Chillers.

Drywell.

Event 7: Major; Steam line breaks inside DrywelL

2E 11-FO 16A or B Containment Spray Valve will not open Event 8: Component; The RHR 2Ell-FOI6A Drywell. When 2Ell-requiring the operator to transition to the other loop of RHR to spray the DrywelL 2E 11-F016A is positioned to open, RHR A and C pumps will trip.

Event 9: Major; Emergency Depress prior to Bulk Average DW temperature of 340°F (Critical Task)

(

Page 29 of 30 Critical Tasks NRC DRAFT Facility: E. I Hatch Scenario No.: 5-03 On-Test No.: 2009-302 Critical Tasks

Secure HPCI system prior to receiving the APRMlOPRM high reactor power trip. (Event 5)

Emergency Depress prior to Bulk Average DW temperature of 340°F. (Event 9)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 6 1. RCIC Torus Level Sensor Fails High (Event 3)

2. CRD FCV '2A' will slowly fail (Event 4)

3. HPCI system will inadvertently start (Event 5)

4. Loss OF DW Chillers (Event 6)

5. Steam line breaks inside containment with A Loop RHR pumps failed (Event 7)

6. 2EII-FOI6A/B Containment Spray Valve RHR 2E11-F016AJB will not open along with RHR Loop A pumps tripping (Event 8)

( 2. Malfunctions After 1-2 1 1. 2Ell-FOI6A/B Containment Spray Valve RHR 2Ell-F016AJB EOPEntry will not open along with RHR Loop A pumps tripping (Event 8)

3. Abnormal Events 2-4 3 1. CRD FCV '2A' will slowly fail (Event 4)

2. HPCI system will inadvertently start (Event 5)

3. Loss OF DW Chillers (Event 6)

4. Major Transients 1-2 2 1. Steam line breaks inside containment with A Loop RHR pumps failed (Event 7)

2. Emergency Depress prior to 340°F (Event 9)

5. EOPs entered, 1-2 2 1. RC EOP Flow Chart (Event 7) requiring substantive 2. PC EOP Flow Chart (Event 7) actions

6. EOPs contingencies 0-2 1 1. CP-1 CP-l EOP Flow Chart. (Event 9) requiring substantive actions

7. Critical Tasks 2-3 2 1. Secure HPCI system before APRM trip (Event 5)

2. Emergency Depress prior to Bulk Average DW temperature of 340°F. (Event 9)

HLT 5 NRC Operating Exam Scenario 3 SIDFT TURNOVER UNIT 1 STATUS Power: 100%

Activities in progress: None Power: Unit 2 is operating at approximately 75% power.

The following equipment is None inoperable:

(

Scheduled evolutions: Lower reactor power IAW 34GO-OPS-005-2 to 70% and then perform 34SV-C71-005-2," Turbine Control Valve Fast CV-l ONLY starting Closure Instrument Functional Test", for CV-1 at step 7.2.6.

Surveillances due this 34SV-C71-005-2," Turbine Control Valve Fast Closure shift: CV-l Instrument Functional Test", for CV -1 ONLY.

Active clearances: None Rod Configuration: SeeRWM

(

Page 1 of3 of 3 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility: E. I Hatch Scenario No.: 5-3 Op-Test No.: 2009-302 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at~ng at CfQO~aking preparations to reduce reactor power to 94% for Main Turbine Stop Valve Instrument InstrumentFlfITc(lonal u onal Testing. Off-Gas Cooler Condensers will be shifted after reactor power is reduced.

Turnover:

Event Malf. No. Event Event No. 'I rI , Type* Description 1 VV)l;:,~;:~v~;Y *1 .Q/1., ~

~~~7~1Q/t

'< R (ATC) Reduce reactor power to 94% for Turbine Testing

\ " ~ /'G vuC .k- j,t vaflA.re s~ '???

V 2 ~6v 1(\17" (\,I .:. , 07/; Shift Off-Gas Cooler Condensers ~ l~/YL we -t:?-(,.

\ n IN N (BOP) 3 '

~l:(~~-:~;

~\~~ 'v ,; ~I (ATC) RCIC Torus Level Sensor Fails High; with time compression repair 1

\rl.v~6f'

'1"; ~', '~ "

/I I TS (SRO) and re-alignment back to CST. ~o "40 tAJ"V'4 vil-vt{<2..

VVV'_c}/c"q :)""/: {C *

,u .

~4 C (BOP) Inadvertent start of HPCI. (Critical Task)

TS (SRO) (e.

[tAQw1.L {l

{If'1/ L,( tr, LC } 1; ;) "~1- (. . .

(. rt4..fo I'~ .- /'~'

-,j.

( ~' V',,~(.t., ..,*

5 C (ATC) CRD FCV '2A' Failure , M4h /i!Li{.h, , ~&v'J: -rtti}v,t Vvf.C/l 'itf/V}

j V\;{VLl,yt'/ ~, -\/. '. ." t :/ oyw.duae 6 i.

i '".

~

C (BOP) Stator Cooling Pump '2B' Trips 2001 ;2001,<. ,', >:'1.,C.'. ,' ~13v~2'

?13vVV'~t 2' Stator Cooling Pump '2A' fails to Auto Start (manually start '2A') ,

7 M (ALL)

M(ALL) Steam Line Break inside DW 5-Je~ l£-.A ; v Dw ! ~- yW '1 8 C (ATC) 2EII-F016A1B Containment Spray Valve fails to OPEN RHR 2EII-F016NB therefore requiring the opposite loop of DW spray to be used.

4/&'

/;;

(Critical Task) 9 C (BOP) RCIC Overspeed trip when started requiring RFPTs for RWL control.

(Critical Task)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor tst /1 \

Page 2 of3 of 3 Scenario Summary Facility: E. I Hatch Scenario No.: 5-03 Oo-Test No.:

aD-Test 2009-302 NRC Draft Initiating Conditions: Unit 2 is operating at 100% RTP making preparations to reduce reactor power to 94% for Main Turbine Stop Valve Instrument Functional Testing.

Turnover Off-Gas Cooler Condensers will be shifted after reactor power is reduced per 34S0-N61-001-2.

Summary:

Event 1: Reduce reactor power to 94% using Recirc for Turbine Testing.

Event 2: Shift Off-Gas Cooler Condensers

Event 3: InstrumentlTS; Instrument/TS; The RCIC Torus Level Sensor Fails High causing a suction swap for RCIC. Using time compression repair, RCIC is re-aligned back to the CST.

Event 4: ComponentlTS; The HPCI system will experience an inadvertent start. The operator takes manual control to secure HPCI. (Critical Task)

Event 5: Component; The CRD FCV '2A' will fail causing a loss of CRD. The operator will take manual actions to swap FCV and return the CRD system to normal.

Event 6: Component; The Stator Cooling Pump '2B' trips and the '2A' pump fails to auto start requiring the operator to take manual actions to place the '2A' pump in service.

Event 7: Major; Steam line breaks inside containment. HPCI system will become unavailable due to the failure of the auxiliary oil pump.

Event 8: Component; The RHR 2Ell-F016A 2EIl-FOI6A or B Containment Spray Valve will not open (depends on which loop of RHR the operator attempts first) requiring the operator to transition to the other loop of RHR to spray the Drywell. (Critical Task)

Event 9: As RWL decreases the RCIC system will trip on Overspeed. The operator will have to maintain RWL using the Feedwater system. (Critical Task)

{

" r

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Page 3 of of33 Critical Tasks NRC Draft Facility: E. I Hatch Scenario No.: 5-03 Op-Test No.:

Oo-Test 2009-302 Critical Tasks

APRM/OPRM high reactor power trip. (Event 4)

Secure HPCI system prior to receiving the APRMlOPRM

Manually open RHR 2EII-POI6A1B Containment Spray Valve prior to exceeding 340 00 P in the Drywell or exceeding EOP Graph 7 Pressure Suppression Pressure to preclude damage to containment. (Event 8)

Using the CondensatelFeedwater system maintain RWL above TAP (-155"). (Event 9)

(

\\

'\

Page 1 of 31 AppendixD Scenario Outline Form ES-D-l NRC Draft Facility: E.IHatch E. I Hatch Scenario No.: 5-04 Op-Test No.: 2009-302 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at approximately 90% RTP. Raise reactor power to 100% after 34IT-N30-001-2, "Main Turbine & & Auxiliaries Weekly Test", PowerlLoad Unbalance Test is performed.

Turnover: After the Turbine test is complete, have the ATC ATC Increase Reactor Pressure to 1025 psig (Ops Management has determined that Attachment 3 of 34GO-OPS-005-2 is NOT required.), then increase Reactor power to 95% using the Rx Recirc system, with a 10 MWe limit on power change rate.

Event Malf. No. ~vent IEvent Event No. Type* Description 1 N/A ~

~(BOP)

(BOP) 34IT-N30-00l-2, "Main Turbine & & Auxiliaries Weekly Test",

PowerlLoad Unbalance Test N/A [R R (ATC) Increase reactor power to 95% using Recirc and adjusting DEHC

,. 22 pressure set to achieve reactor pressure> 1025 psig.

pressure >1025

( '33 mfDRL_509 C 12 (BOP) Reactor Building Exhaust fan failure with the Standby Exhaust fan failing to start. Standby Exhaust fan manually started or SBGT fan started to re-establish Rx Bldg dp. (Critical Task) mfB31_135B C 12 (ATC) Recirc '2B' ASD Cell Bypass; "2B" Recirc speed decreases

~4 Irs IrS (SRO) resulting in a flow mismatch mfB31_41B C (ATC) Recirc Pump '2B' High Vibration requiring reducing reactor 5

power in an attempt to clear alarm. Alarm remains in until pump is tripped.

6 N/A C (BOP) HPCI Room fire Irs ITS (SRO) 7 N71_70 N7L70 M M(ALL)(ALL) Con Bay Flooding svoE41102 'B' MSL fails to isolate automatically on low vacuum, manual 10B21-F022BG loB21-F022BGI1 isolation required 10B21-F022BR2 loB21-F022BR2 HPCI Gov valve will not open to provide sufficient steam to loB21-F022BMG1 loB21-F022BMGl turbine.

loB21-F022BMR2 Ct. j;;

,,,.,..C- />/ ..

loB21-F028BG loB21-F028BGI1 J 10B21-F028BR2 loB21-F028BR2 J i

loB21-F028BMG1 loB21-F028BMGl loB21-F028BMR2 8 mfB21_130B C (ATC) 1'-' 'B' SRV fails open and remains partially open after fuses are pulled.

mfE51_113 mfE5L113 C (BOP) RCIC 2E51-F008 isolation

~9 mfN2L99 rnfN2L99 SULCV 2N21-Fl11 2N21-F111 fails closed (Critical Task)

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

0 Appendix D Required Operator Actions Form ES-D-2 ES-O-2

'I~I Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 1 Page 2 of31 of 31 Event

Description:

34IT-N30-001-2, "Main Turbine & & Auxiliaries Weekly Test" surveillance for Power-Load-Unbalance only II Time Position Applicant's Actions or Behavior I SRO Directs the BOP to perform 34IT-N30-001-2, "Main Turbine & & Auxiliaries Weekly Test", PowerlLoad Unbalance Test.

BOP Enters 34IT-N30-001-2, "Main Turbine & & Auxiliaries Weekly Test", Section 7.2, "PowerlLoad Unbalance Test" (All Steps are performed from 2N32-K4001A or B (DEHC Computers) ITests! Test~

screen)

Enters the IPLU test I screen: A or B CONFIRMs that the Intermediate Pressure is is> > 40% (will be approx. 92%

and is read at the bottom of the PLU TEST page)

Observes the PLU Status for slots 17 and 18 are I OFF1 oFF1

(

Selects PLU TEST ~

Clicks the OK button on the "Tum PLU Test On?" message box CONFIRMs "PLU TEST SUCCESSFUL IN <R>, ~~, and <T> CORE" for:~~

~~PLU TEST-Slot 17 AND TEST-Slot PLU TEST- Slot 18 Selects PLU TEST I OFF1 Clicks the OK button on the "Tum PLU Test Off?" message box~~

\

~~CONFIRMs PLU Status for slot 17 (all three) reads "OFF" AND CONFIRMs PLU Status for slot 18 (all three) reads "OFF" Notifies the SS that the test has been completed satisfactorily.~~

(

\

~~Appendix D Required Operator Actions Form ES-D-2~~

(

~~Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 2 of 31 Page 3 of31 Event~~

~~Description:~~
Increase reactor power to 95% using Recirc and adjust pressure set for 1025#
I Time Position Applicant's Actions or Behavior I SRO Directs the ATC to increase reactor pressure to 1025 psig using ERC pressure set.
ATC Enters 34GO-OPS-005-2, Power Changes, at step 7.1.10 and at the DERC panel computer, perform the following steps:
Selects the 1Control 1---+
1--+-11 psi- load 1screen Intermittently uses (Clicks) the I1 Raise I1 button to increase reactor pressure to 1025 psig. (This will take approx. 4 minutes.)
Notifies the SS that Rx pressure is at 1025 psig.
SRO Directs the ATC to increase Rx Power to 95% using Recirc.
(
ATC IAW 34S0-B31-001-2, the ATC increases Recirc pump speed, not to exceed 10 MWE per minute by depressing the RAISE SLOW or RAISE MEDIUM pushbuttons on the Master or Individual controls until reactor power is 95%.
Notifies the SS that reactor power has been increased to 95%.
(
Appendix 0 Required Operator Actions Form ES-O-2 I~
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 3 Page 4 of 31 Event
~~Description:~~
Reactor Building Exhaust fan failure Time Position Applicant's Actions or Behavior I At Chief Examiners direction the Simulator Operator ENTERS (RB-3) mfDRL 509, Rx Bldg Exhaust Fan A fails & standby does not start 2HII-P650 panel alarms 650-214, 'PaneI2H11-P654 On the 2H11-P650 'PaneI2HII-P654 Panel System Trouble' and 650-224, 'PaneI2HII-P657
'PaneI2H11-P657 Panel System Trouble' are received BOP
~~Announces the alarm to the SS SRO~~
~~The SS repeats the alarm and dispatches the BOP operator to the 2HII-P654 & P657 panels.~~
2H11-P654
(
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 3 Page 5 of 31 Event
~~Description:~~
Reactor Building Exhaust fan failure I Time Position Applicant's Actions or Behavior I Note: This failure will require entry into the SC EOP Flow Chart as well as two Abnormal procedures. The following sequence may be slightly out of order because of this.
If the operator enters 657-081 first, then the following actions will be addressed, otherwise skip to the next alarm.
BOP
~~Acknowledges 657-081, 'RB Exhaust Fan 2T41-C007A1B Flow Low' alarm and enters 657-081.~~
~~Confirms the Standby Rx Bldg Vent Exhaust Fan has not automatically started (IT SHOULD HAVE AUTO STARTED), the operator will place the control switch for 2T41-C007A to OFF AND 2T41-C007B to Run.~~
~~Confirm the following dampers are OPEN:~~
(
~~2T41-F044A, RIB Inboard Isol Dampers Inacc. Areas Exhaust Fans Disch on 2H11-P657.~~
~~2T41-F044B, RIB Outboard Isol Dampers Inacc Areas Exhaust Fans Dish on 2H11-P654.~~
~~2Hll-P654.~~
~~2T41-F028, Rx Bldg Vent Filter D005 Inlet Damper on 2Hll-P657.~~
~~Confirm RB Exhaust flow on 2T41-R618 point 2 is indicating approximately 6.5 KCFM.~~
~~Once RB Exhaust and Supply flows have stabilized, confirms 654-001,~~
'RB Inside To Outside Air Diff Press Low' clears and notifies SS.
(
\
II
0 Appendix D Required Operator Actions Form ES-D-2 ES-O-2 If
.~
!\ Op. Test No.: 2009*302 Op-Test 2009-302 Scenario No.: 5*04 5-04 Event No.: 3 of 31 Page 6 of31 Event
~~Description:~~
Reactor Building Exhaust fan failure Time Position Applicant's Actions or Behavior I If the operator enters 654-001 first, then the following actions will be addressed.
BOP
~~Acknowledges 654-001, 'RB Inside To Outside Air Diff DiffPress Press Low' alarm and enters 654-001 and performs the following actions:~~
~~Confirms Reactor Building to outside air differential pressure, is less than -0.06" WC, as indicated on 2T46-R604B, Sec Cnmt Diff Press B, red pen, 2HII-P700.~~
~~Determines that the 2T41-C007A, 'Rx Bldg Exhaust' fan red light is illuminated and the 2T41-COOIA, 'Rx Bldg Supply' fan red light is illuminated.~~
~~Determines RB Exhaust flow on 2T41-R618 point 2 is indicating approximately 0 KCFM.~~
(
~~Informs the SS that the 2T41-C007A, 'Rx Bldg Exhaust' fan is running (Red light illuminated) and the 2T41-COOIA, 'Rx Bldg Supply' fan is running (Red light illuminated) and that Rx Bldg dp is 0".~~
~~Dispatches a SOlMaint to confirm 2R25-S065, BRKR 15 is closed and to investigate why the RB Exhaust fan has a low flow condition.~~
~~Enters 34AB-T22-002-2, 'Loss of Secondary Containment Integrity' and 34AB-T22-003-2, 'Secondary Containment Control', and notifies Management of the plant conditions.~~
Appendix 0 Required Operator Actions ES-O-2 Form ES-D-2 1I Op. Test No.: 2009*302 Op-Test 2009-302 Scenario No.: 5*04 Event No.: 3 5-04 Event No.: of 31 Page 7 of31 Event
~~Description:~~
~~Reactor Building Exhaust fan failure Time Position Applicant's Actions or Behavior BOP~~
~~Enters 34AB-T22-003-2, 'Secondary Containment Control'.~~
~~Monitors secondary containment parameters.~~
~~Notifies the SS to enter 31EO-EOP-014-2, 31EO-EOP-OI4-2, EOP Secondary Containment flowchart due to low RB dp.~~
~~Dispatches a SOlMaint to investigate the low RB dp.~~
~~Enters 34AB-T22-002-2, 'Loss of Secondary Containment Integrity' .~~
~~SRO~~
~~Dispatches a SOlMaint to determine why the Rx Bldg Fan experienced low flow and why the standby fan did not start.~~
~~3 I EO-EOP-014-2, EOP Secondary Containment flowchart.~~
Enters 31EO-EOP-014-2, Simulator Operator waits 2 minutes and reports to the SS, as a SO, that Breaker 15 at 2R25-S065 is closed. Also report as Maintenance that the ARB A RB Exhaust fan motor was running but the fan was not turning.
SRO Directs operator to start SBGT with suction from the Rx Bldg or restart RB Ventilation using the 2T41-C007B, 'RB Exhaust' fan.
Appendix 0 Required Operator Actions Form ES-O-2 I(I
( Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 3 Page 8 of 31 Event
~~Description:~~
Reactor Building Exhaust fan failure III Time Position Applicant's Actions or Behavior If the SS directs SBGT started, the following actions will be taken, otherwise skip this part.
BOP
~~Starts the 2A or 2B SBGT with a suction from the Rx Bldg by performing the following:~~
~~At 2HII-P657 2H 11-P657 for "2A" or 2H 11-P654 for "2B" performs the 2HII-P654 following action IAW the SBGT Placard or 34S0-T46-001-2, SBGT System.~~
~~Opens 2T46-FOOIA(B) 2T46-F001A(B)~~
~~Places SBGT A (B) in RUN position.~~
~~Confirms 2T46-F002A (B) OPENS.~~
~~Confirms SBGT A (B) HTR Red Light ILLUMINATES.~~
~~Confirms SBGT Flow increases to 1500 - 4000 SCFM.~~
(
SRO
~~Orders the Rx Bldg Ventilation system re-started IAW 34S0-T41-005-2.~~
lfthe If the SS directs RB Ventilation started the following actions will be taken, otherwise skip this part.
BOP
~~Enters 34S0-T41-005-2 and performs the following actions:~~
~~Momentarily depresses Rx Bldg Supply Fans Reset.~~
~~Momentarily depresses Rx Bldg Recirc Fan 2T41-B017 Reset.~~
Appendix 0 Required Operator Actions Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 3 Page 9 of 31 Event
~~Description:~~
Reactor Building Exhaust fan failure II Time Position Applicant's Actions or Behavior I Simulator Operator, when requested to peiform the following, inform the operator that the Unit 1 pushbuttons have been depressed.
~~Momentarily depresses 1T4112T41, Rx Bldg/RfFlr BldglRfFIr ISOL DMPR RESET A pushbutton, pane11H11-P657.~~
~~Momentarily depresses 1T4112T41, BldglRfFlr 1T4112T41, Rx BldglRf FIr ISOL DMPR Reset B pushbutton, pane11H11-P654.~~
~~panel1H11-P654.~~
~~Momentarily depresses 2T41-D005, Reactor Building Filter, Deluge reset.~~
~~Open 2T4l-F028, 2T41-F028, Rx Bldg Vent Filter D005 Inlet Damper.~~
~~Confirm Open/Open 2T41-F044A, Rx Bldg Inboard Isol Dampers Inaccessible Areas Exhaust Fans Disch.~~
(
~~Confirm Open/Open 2T4l-F044B, 2T41-F044B, Rx Bldg Outboard Isol Dampers Inaccessible Areas Exhaust Fans Disch, panel 2H11-P654.~~
~~2Hll-P654.~~
~~Place in RUN 2T4l-C007B, 2T41-C007B, Rx Bldg Vent Exhaust Fan.~~
~~Place in STBY 2T41-C007A, Rx Bldg Vent Exhaust Fan.~~
~~(Fan Broke)~~
~~Confirm Open/Open 2T41-FOllA, Rx Bldg Inboard Isol Dampers Supply Fans Disch.~~
~~Confirm Open/Open 2T41-FOIIB, 2T41-F011B, Rx Bldg Outboard Isol Dampers Supply Fans Disch, pane12Hll-P654.~~
~~paneI2H11-P654.~~
~~Place in RUN 2T41-COOIA 2T41-C001A or 2T41-COOIB, 2T41-C001B, Rx Bldg Supply Fan.~~
~~Place in STBY 2T41-C001B 2T41-COOIB or 2T41-COOIA, 2T41-COOlA, Rx Bldg Supply Fan.~~
Appendix 0 Required Operator Actions Form ES-O-2 II"
(
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 3 Page 10 of31 of 31 Event
~~Description:~~
~~Reactor Building Exhaust fan failure I Time Position Applicant's Actions or Behavior I~~
~~ADJUST 2T41-FC-R027 to maintain Rx Bldg Vent Exhaust Flow approximately 6.5 KCFM as indicated by the green pen on 2T41-R618, flow recorder, located on 2HII-P657.~~
~~2H11-P657.~~
~~ADJUST 2T41-FC-R022 to maintain Rx Bldg Vent Supply Flow approximately 5.3 KCFM as indicated by the red pen on 2T41-R618, flow recorder, located on 2H11-P657.~~
~~2HI1-P657.~~
~~While maintaining approximately 6.5 KCFM for Rx Bldg Vent Exhaust Flow and~~
~~5.3 KCFM Bldg Vent Flow respectively,~~
~~ADJUST Flow Controllers 2T41-FC-R027 and 2T41-FC-R022 to obtain 0.25 inches water pressure on 2T46-DPR-R604A&B.~~
(
BOP
~~Informs the SS that the Rx Bldg dp has returned to normal SRO~~
If SBGT was started, directs SBGT returned to Standby and exits the SC EOP Flowchart Note; It is not intended to wait until SBGT is returned to Standby, therefore, at Chief Examiner's direction, move on to the next Event
(
\
0 Appendix D Required Operator Actions Form ES-D-2 ES-O-2 I
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 4 Page 11 of 31 Event
~~Description:~~
"2B" Recirculation Pump ASD Cell will auto bypass Time Position Applicant's Actions or Behavior I Simulator Operator At Chief Examiner's direction, press (RB-4) to activate:
~~mfB31_135B, Recirc ASD B Cell Bypass SRO/TS~~
~~Direct ATC to respond to 602-208, "ASD B TROUBLE" Annunciator~~
~~Direct maintenance be contacted to determine cause of Recirc speed decrease~~
~~TS LCOIRAS Recirculation Loops Operating (TS 3.4.1 Condition A.l is to satisfy the LCO within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ).~~
(
Simulator Operator At Chief Examiner's direction:
~~Call the Control Room as I&C with the following message:~~
- -. - \ 0 The "2B" Recirculation Pump ASD has automatically bypassed a cell, conditions at the ASD are normal for this condition.
(
Appendix 0 Required Operator Actions Form ES-O-2 I,
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 4 Page 12 of 31 Event
~~Description:~~
"2B" Recirculation Pump ASD Cell will auto bypass I Time Position Applicant's Actions or Behavior Note: With the 2B ASD Cell Bypassed, the operator may enter 34AB-B31-001-34AB-B3J-OOJ-2, Reactor Recirculation Pump(s) Trip, Recirc Loops Mismatch, OR ASD Cell Bypass",first Bypass ", first due to Recircflow Recirc flow mismatch.
ATC
~~Respond to 602-208, "ASD B TROUBLE" Annunciator~~
~~Diagnose Recirc pump speed mismatch~~
~~Confirm that an ASD cell has failed and is bypassed using SPDS or by having it verified locally at the ASD cabinet.~~
~~Enter 34AB-B3l-00l-2, 34AB-B31-001-2, "Reactor Recirculation Pump(s) Trip, Recirc Loops Mismatch, or ASD Cell Bypass"~~
~~Confirm the "SPD HLD RESET" pushbutton is illuminated~~
~~Enter section ill of 34AB-B31-001-2 34AB-B31-00l-2~~
(
If Recirc speed mismatch >35%, inform SS of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months limit to balance Recirc Pump flows If If the SS decides to increase Recirc flow to exit the region, then the following actions will be taken, otherwise skip this part and go to the next.
~~STA If asked, Reactor Engineering guidance for raising power is:~~
~~"Limit the rate of power change to 10 MWe/minute."~~
Appendix D 0 Required Operator Actions ES-D-2 Form ES-O-2 I
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 4 Page 13 of 31 Event
~~Description:~~
~~"2B" Recirculation Pump ASD Cell will auto bypass I Time Position Applicant's Actions or Behavior I ATC~~
~~When directed by SS with STASTA guidance:~~
~~Depress the respective SPD HLD RESET pushbutton indicating lamp~~
~~Increase speed of the "2B" Recirc Pump per 34S0-B31-00 34S0-B31-001-2,1-2, Reactor Recirc System"~~
~~After 34AB-B31-001-2 has been addressed entered, the operator will depress the Fault Reset pushbutton to reset the "ASD B Trouble" alarmIAW alarm IAW 34AR-602-108-2, "ASD Trouble."~~
Note to examiners: TS SR 3.4.1.1 requires Recirc flow mismatch be less than 5% if operating at greater than or equal to 70% rated core flow, and mismatch be less than 10% if operating at less than 70% rated core flow.
Simulator Operator At Chief Examiner's direction:
(
~~Call the Control Room as I&C with the following message:~~
The "2B" Recirculation Pump ASD has automatically bypassed a cell, conditions at the ASD are normal for this condition.
Appendix D0 Required Operator Actions Form ES-O-2 ES-D-2 1\~
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 4 Page 14 of 31 Event
~~Description:~~
~~"2B" Recirculation Pump ASD Cell will auto bypass Time Position Applicant's Actions or Behavior I SRO~~
~~Within 15 minutes of entering the Immediate Exit Region of the Power to Flow map, directs operator to exit the region by inserting control rods.~~
~~Ensures the plant has exited the Immediate Exit Region of the Power to Flow map within one hour.~~
~~Has a control rod movement brief per 34GO-OPS-065-0 Simulator Operator lfthe Team calls for the STA or Reactor Engineering, for rod movement~~
~~( recommendations:~~
~~Respond as follows:~~
~~"Use the Reactivity Manipulations Turnover."~~
Appendix 0 Required Operator Actions Form ES-O-2 II
.~
( Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 4 Page 15 of 31 Event
~~Description:~~
~~"2B" Recirculation Pump ASD Cell will auto bypass II Time Position Applicant's Actions or Behavior ATC~~
~~Inserts control rods per 34GO-OPS-065-0, starting with control rod Group 54.~~
During rod insertion, rod steps will be performed in reverse sequential order, starting at the highest numbered step. (** rod steps are not required to be performed sequentially, but must be positioned to their RWM insert limit prior to inserting lower numbered groups).
~~Selects Rod~~
~~Places Control Rod movement switch to the IN position~~
~~Verifies Rod moves using Rod display information and Rx and Generator power decreasing.~~
~~ATC~~
~~If required, adjust 2CII-F003 to get 220 - 280 psid drive water dp.~~
( ,
ATC Note: RBM Downscale alarm may alarm during this movement due to the significant rod worth of these rods. It is allowed to flag the RBM Downscale and Rod Block alarm.
~~Releases Rod movement switch so that the control rod stops 1 position before the insert limit unless the insert limit is 00.~~
~~Initials Rod movement Sheet.~~
~~Verifier, if available, Initials Rod movement sheet.~~
~~Notifies the SS when they are out of the region of potential instabilities.~~
Note: Advise the STA to recommend inserting the current rod group to its insert limit.
SRO
~~Directs the operator to insert the rods to the insert limit after consulting with the STSTA.~~
A.
Note; At Chief Examiner's direction, move on to the next Event
Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2
,~
'\
( Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.:
5 Page 16 of 31
~
Event
~~Description:~~
~~Recirc Pump '2B' will experience high vibration I Time Position Applicant's Actions or Behavior Simulator Operator At Chief Examiner's direction, press (RB-S) to activate:~~
~~mfB31 41B, Recirc Pump B High Vibration mfB31_41B, All~~
~~Receives 602-204, "Recirc Pump B High Vibration" alarm SRO~~
~~Directs operator to enter 602-204 ATe~~
~~Enters 602-104~~
~~Depresses the Hi vibration reset pushbutton and determines that the alarm does not clear.~~
~~Notifies the SS that the vibration alarm did not clear.~~
~~Notifies the SS that the ARP requires reducing Recirc flow and attempting to reset the alarm again.~~
~~SRO~~
~~Directs the operator to reduce Rx power with Recirc per 34GO-OPS-005 and 34S0-B31-001-2, exceeding 10 MWE/minute if necessary.~~
~~Reminds the operator that entry into the immediate exit region of the Power to Flow map is allowed.~~
~~Notifies Plant Management, Load Dispatcher, and Engineering that the power increase has been halted pending investigation of Recirc Pump 2B high vibration condition.~~
(
\
0 Appendix D Required Operator Actions Form ES-D-2 I~,~
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 5 Page 17 of 31 Event
~~Description:~~
~~Recirc Pump '2B' will experience high vibration I Time Position Applicant's Actions or Behavior I ATC~~
~~Enters the following procedures~~
~~34GO-OPS-005-2, "Power Changes"~~
~~34S0-B3l-00 34S0-B31-00 1-2, "Recirculation System"~~
~~lAWIAW 34S0-B31-001-2, the ATC decreases Recirc pump speed by depressing the Slow, Medium or Fast LOWER pushbuttons on the Master or Individual controls.~~
~~Monitors power decrease by observing APRM and generator output indications.~~
~~Stops power reduction periodically and depresses the High vibration reset pushbutton.~~
~~The alarm will not remain clear until the pump is tripped .~~
~~Continues to decrease Recirc pump speed until minimum~~
~~Notifies SS when B Recirc Pump is at minimum.~~
~~Notifies the SS that the vibration alarm DID NOT clear after reducing Recirc pump speed.~~
(
SRO
~~Directs the operator to shutdown the B ASD lAWIAW 34S0-B3l-00l-2 34S0-B31-001-2 section 7.2.1.4.~~
~~ATC~~
~~Place ASD B control switch 2B31-S002B to Pull to Lock or depresses the ASD B Shutdown pushbutton on panel pane12H11-P602.~~
~~2H11-P602.~~
~~Enters 34AB-B3l-001-2, 34AB-B31-001-2, Reactor Recirculation Pump(s) Trip, Recirc Loops Flow Mismatch, Or ASD Cell Bypass for single Recirc pump trip.~~
(
Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2
~\ Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 5 Page 18 of 31 Event
~~Description:~~
~~Recirc Pump '2B' will experience high vibration Time Position Applicant's Actions or Behavior I SRO~~
~~Has the operator determine if the plant is in the analyzed region of the Power to Flow map.~~
~~ATe~~
~~Determines that the plant is in the immediate exit region of the Power to Flow map.~~
The intent is NOT to watch the crew again insert controls rods to exit the
( Immediate Exit Region. The intent is to move on to the next event.
Note; At Chief Examiner's direction, move on to the next Event
D Appendix 0 Required Operator Actions Form ES-D-2 ES-O-2
,II Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 6 Page 19 of 31 Event
~~Description:~~
HPCI Room Fire I Time Position Applicant's Actions or Behavior I Simulator Operator At Chief Examiner's direction, NOTIFY the Shift Supervisor, as the SO on rounds, that smoke is coming from the Unit 2 HPCI room and you cannot see what is actually burning. You are leaving the area.
SRO
~~Directs BOP to enter 34AB-X43-001-2, 'Fire Procedure' and make the announcement.~~
~~BOP~~
~~Enters 34AB-X43-001-2, 'Fire Procedure' and performs the following:~~
(
~~Sounds the fire alarm (SIREN) over the plant PA system~~
\
~~Notifies Rad Waste Control room that Reactor Building floor drain sump pumps are in Automatic~~
~~Notifies Health Physics to respond to the fire area~~
~~Transitions to section 8.0 for Fire in 'Reactor Bldg.'~~
~~Stops the following equipment at Panels 2H11-P654 & P657:~~
~~2T41-C001A, 2T41-COOlA, Rx Bldg Supply Fan.~~
~~2T41-C001B, Rx Bldg Supply Fan.~~
~~2T41-C007A, Rx Bldg Exhaust Fan.~~
~~2T41-C007B, 2T4l-C007B, Rx Bldg Exhaust Fan.~~
~~2T41-C002A, 2T4l-C002A, Refuel FIr Vent Supply Fan.~~
~~2T41-C002B, 2T4l-C002B, Refuel FIr Vent Supply Fan.~~
~~2T41-C005A, Refuel FIr Vent Exh Fan.~~
~~2T41-C005B, Refuel FIr Vent Exh Fan.~~
Simulator Operator Wait 2 minutes and NOTIFY the Shift Supervisor, as the Fire Brigade Leader, to place HPCI Aux Oil pump in PTL-Off to prevent HPCI from starting while
( Fire Brigade is in the HPCI room.
Appendix D 0 Required Operator Actions ES-O-2 Form ES-D-2 III Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 6 Page 20 of 31 Event
~~Description:~~
~~HPCI Room Fire I Time Position Applicant's Actions or Behavior I BOP~~
~~Transitions to section 8.5 for Fire in 'South Half of Reactor Bldg.'~~
~~Transitions to section 8.5.6 for Fire in 'HPCI Room'~~
~~Places 2T41-B005A 2T4I-B005A HPCI Pump Rm Cooler in Off, P657.~~
~~Places 2T4I-B005B 2T41-B005B HPCI Pump Rm Cooler in Off, P654.~~
~~Places HPCI Aux Oil pump in PTL Off, P60I.P601.~~
~~Dispatches a SO to open Brkr 6 in 2R25-S002~~
~~Closes the following HPCI Valves on P601~~
~~2E41-FOO2 2E4I-F002~~
~~2E41-FOO3 2E4I-F003~~
~~2E41-F041 2E4I-F04I~~
~~2E41-F042 2E4I-F042 Simulator Operator~~
(
Wait 5 minutes and NOTIFY the Shift Supervisor, that the fire in the HPCI room is OUT. A storage locker under the stairwell was onfire. We put out the fire without spraying water on any HPCI components.
SRO
~~Announces to the crew the fire is out.~~
~~As time allows, Directs the operator to leave the HPCI Aux oil pump in PTLOff~~
~~Refers to TS for HPCI inop~~
~~3.5 ECCS and RCIC System~~
3.5.1 ECCS Operating Enters a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months RAS per TS 3.5.1.C.I 3.5.1.C.l to verify by admin means RCIC is operable and per TS 3.5.1.C.2 to restore HPCI to operable status within 14 days.
Simulator operator, proceed to the next event at the Chief Examiner's direction
(
Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2
~~
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 7 Page 21 of 31 Event
~~Description:~~
Circ Water Leak Leak: causing Con Bay Flooding Time Position Applicant's Actions or Behavior I Simulator Operator At Chief Examiner's direction, press (RB-7) to activate:
~~mfN71_71, Circulation Water System Leak (0-100,00 mfN71_71,Circulation (0 - 100, 00 gpm)~~
Simulator Operator After 2 minutes notify the SS, that as Unit 2 Inside rounds, there is water coming out from under the Con Bay door on the 112' elevation. (It will take approximately 3 minutes to receive the Condenser Room Flooding alarm.)
All
~~Recognizes that Condenser Water Box A R602A dp is approaching O.~~
(
SRO
~~As time allows, dispatches a SO to locally investigate the reduced Circ Water dp and for a possible leak.~~
leak:.
SRO
~~When 650-164, "Condenser Room Flooding" alarm is received, directs the ATC enter 34AB-C71-00l-2, 34AB-C71-001-2, Scram Procedure, and scram the reactor.~~
~~Assigns the A ATC TC to perform RC-1.~~
~~Assigns the BOP operator to perform RC-2 and RC-3.~~
~~Assigns a RWL band between 3" and 50"~~
(
Appendix D 0 Required Operator Actions ES-O-2 Form ES-D-2 I
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 7 Page 22 of 31 Event
~~Description:~~
~~Circ Water Leak causing Con Bay Flooding I Time Position Applicant's Actions or Behavior I ATC~~
~~Performs RC-l RC-1 consisting of:~~
~~Inserts a manual scram.~~
~~Places the mode switch to shutdown.~~
~~Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.~~
~~Notifies SS of rod position check.~~
~~Places SDV isolation valve switch to "isolate" & confirms closed.~~
~~If not tripped, places the Recirc pumps at minimum speed.~~
~~Inserts SRMs and IRMs.~~
~~Shifts recorders to read IRMS, when required.~~
~~Ranges IRMS to bring reading on scale.~~
~~Notifies the SS when the above actions are complete.~~
(
BOP
~~Performs RC-2 actions consisting of:~~
~~Confirms proper Level Control response:~~
~~Checks ECCS Injection Systems and secure as necessary.~~
~~Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.~~
~~IF set down does not auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.~~
~~Starts RCIC for level control BOP~~
~~If HPCI Aux Oil pump is taken out of PTL off, notifies SS that the HPCI Governor valve is not operating properly and is securing HPCI.~~
Notifies MaintlI&C to investigate and repair.
(
Appendix 0 Required Operator Actions Form ES-O-2 III Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 7 Page 23 of 31 Event
~~Description:~~
~~Circ Water Leak causing Con Bay Flooding Time Position Applicant's Actions or Behavior I BOP~~
~~When feed flow is less than the capacity of the S/U level control valve~~
(~ 1.5 mlbrnlhr),
mlbmlhr), then:
~~Opens 2N21-F125.~~
~~Places 2C32-R619, FW SID level control valve controller, in Auto, set at approximately 9 inches.~~
~~Closes 2N21-F11O.~~
~~May attempt to start the CRD pumps~~
~~Controls RWL with the RCIC. Notifies SS if RWL gets outside assigned band.~~
(
BOP
~~Performs RC-3 consisting of:~~
~~Monitor RPV pressure.~~
~~Confirm proper operation of pressure control system (TBV, LLS, etc.).~~
~~If necessary, allow RPV pressure to exceed 1074 psig then cycle any SRV to initiate LLS.~~
~~Maintain RPV pressure between 1074 and 800 psig.~~
~~Notify SS of pressure control system operation.~~
Simulator operator ensures ET-B21-10 & & ET-B21-11 for deleting MSIV lights is ACTIVATED when the 2B21-F022B AND F028B is positioned to close.
All
~~Recognizes the B MSL failed to isolate on low condenser vacuum and places both control switches for 2B21-F022B and F028B to close.~~
~~SRO~~
~~Directs operator to place B MSL control switches, 2B21-F022B and F028B, to close and confirm valves indicates close.~~
Appendix D Required Operator Actions Form ES-D-2
,I~~
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 8 of31 Page 24 of 31 Event
~~Description:~~
'B' SRV fails open and remains partially open after fuses are pulled III Time Position Applicant's Actions or Behavior I Simulator Operator After LLS is armed or when the B SRV is open, press (RB-8) to activate:
~~mfB21_130B SRO~~
~~Directs operator to enter 34AB-B21-003-2, 34AB-B2l-003-2, "Failure of SafetylRelief valves".~~
~~ATC~~
~~Determines that SRV "B" is open.~~
~~Cycles the SRV Control Switch several times in an attempt to close the SRV.~~
~~Attempts to reset LLS as follows:~~
~~Depresses the LLS Channel AlC Reset pushbutton (2B21-S15A).~~
~~Depresses the LLS Channel BID Reset pushbutton (2B21-S15B).~~
~~Informs SS that the "B" SRV will not close.~~
~~SRO~~
~~Directs operator to pull the fuses for SRV "B".~~
~~ATC~~
~~Enters 34AB-B2l-003-2, 34AB-B21-003-2, Failure of SafetylRelief valves~~
~~Dispatches an operator to pull the fuses for SRV "B".~~
Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2 I
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 8 Page 25 of 31 Event
~~Description:~~
'B' SRV fails open and remains partially open after fuses are pulled Time Position Applicant's Actions or Behavior Simulator Operator-after 3 minutes, ENTER (RB-2) for leaking SRV Band ifB21_301 to pull the fuses for SRV B, THEN, notify the crew thefuses the fuses have been pulled for SRV "B".
pulledfor ATC
~~Confirms that SRV "B" is still partially open by monitoring:~~
~~SRV tailpipe temperature stabilizing at value and not decreasing~~
~~Torus Temp still increasing~~
~~Torus level still increasing~~
~~RPV pressure still decreasing ATC~~
Resets the SRV leak detection by placing the Leak Detection Logic A Reset keylock switch and/or andlor Leak Detection Logic B Reset keylock switch to Reset position and back to Normal position and confirm that
~~( the Amber SRV indicating lights have NOT Extinguished.~~
~~Informs the SS that SRV "B" is still partially open.~~
Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2
\. Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 9 Page 26 of 31 Event
~~Description:~~
RCIC 2E51-F008 isolation along with SULCV 2N21-FIll 2N21-Flll fails closed III Time Position Applicant's Actions or Behavior I Simulator Operator At Chief Examiner's direction, press (RB-9) to activate:
~~mfE51_113 RCIC isolation & mfN21_99 fails closed All~~
~~The following alarms are received:~~
~~RCIC Turbine Trip~~
~~RCIC Isolation Signal Logic A~~
~~RCIC Steam Line Diff Press High~~
~~RCIC Isolation Vlv F007IF008 F007/F008 Not Fully Open~~
~~Determines that RCIC has Isolated SRO~~
~~Directs BOP to pull RCIC ARPs and determine the cause of the RCIC isolation.~~
NOTE: The operators may transition to inject with the condensatelFeedwater system prior to entering the following ARPs. The operators may enter different ARPs first. The following actions are for all four ARPs. The evaluator will have to determine which ARP has been entered to follow the correct set of actions.
D Appendix 0 Required Operator Actions Form ES-D-2 ES-O-2 II Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 9 Page 27 of 31 Event
~~Description:~~
~~RCIC 2E51-F008 isolation along with SULCV 2N21-F111 fails closed Time Position Applicant's Actions or Behavior BOP~~
~~Enters ARP 602-302, for the RCIC Stearn Steam Line Diff Press High annunciator and performs the following actions.~~
~~Confirms 2E51-F008 is closed~~
~~Closes 2E51-F007 (This valve does not have an isolation signal, but may be closed)~~
~~Notifies the SS that RCIC has a HIGH steam stearn flow (steam (stearn line dp) signal and that 2E51-N657A&B and 2E51-N660AlB 2E51-N660A/B at the ATTS panels provide inputs to this signal.~~
~~SRO~~
~~Dispatches an operator to and requests maintenance help for~~
( determining the status of 2E51-N657 AlB and 2E51-N660A/B of2E51-N657A1B 2E51-N660AlB at the ATTS panels.
BOP
~~Enters ARP 602-301, RCIC Turbine Trip~~
~~Confirms 2E51-F524, Trip & Throttle Vlv, indicates CLOSED~~
~~Confirms 2E51-F013, Pump Discharge Vlv, indicates CLOSED~~
~~Confirms 2E51-F019, Min Flow Vlv, indicates CLOSED BOP~~
~~Enters ARP 602-307, RCIC Isolation Signal Logic A~~
~~Confirms 2E51-F008, SteamStearn Supply Line Isol Vlv, is CLOSED.~~
~~Enters RCIC STEAM LINE DIFF PRESS HIGH (602-302) ARP, if not already performed~~
((\
II
Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2
(
.I~~
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 9 Page 28 of of31 31 Event
~~Description:~~
~~RCIC 2E51-F008 isolation along with SULCV 2N21-Flll 2N21-F111 fails closed Time Position Applicant's Actions or Behavior I BOP~~
~~Enters ARP 602-336, RCIC Isolation Vlv F0071F008 Not Fully Open~~
~~Confirms 2E5l-F008, 2E51-F008, Steam Supply Line Isol Vlv, is CLOSED~~
~~Enters RCIC ISOLATION SIGNAL LOGIC A (602-307) ARP, if not already performed~~
~~Determines that RCIC needs to be returned to standby line-up per 34S0-E51-001-2, 34S0-E5l-001-2, RCIC System, when the isolation signal is cleared.~~
~~BOP~~
~~The BOP recognizes the SULCV has failed closed.~~
~~Performs the following to inject water into the reactor.~~
~~0 Throttles open 2N21-FllO, 2N21-FIlO, and injects water into the reactor.~~
~~Reports SULCV problem to the SS.~~
Critical Task - Aligns 2N21-Fll 2N21-F11 0 for vessel injection to maintain RWL greater than -155 inches.
Simulator Operator
~~With Chief Examiners permission AND~~
~~When reactor water is being controlled after reactor pressure is below the Condensate Booster pump discharge head, THEN~~
( Terminate the scenario.
II
Page 29 of 31 AppendixD Appendix D Scenario Outline Form ES-D-1 NRC Draft
.iacility: E. I Hatch Scenario No.: 5-04 Op-Test No.: 2009-302 SRO Examiners:

~~Operators: ----------------------------------~~

~~

RO BOP Initiating Conditions: Unit 2 is operating at approximately 90% RTP.
Turnover Raise reactor power to 92% then raise pressure set lAW 34GO-OPS-005-2.
After pressure adjustment, raise reactor power to 95%.
Summary:
~~Event 1: Perform 34IT-N30-001-2, "Main Turbine & Auxiliaries Weekly Test" surveillance for Power-Load-Unbalance only.~~
~~Event 2: Increase reactor power to 95% using Recirc and adjusting DEHC pressure set to achieve reactor pressure> 1025 psig.~~
Event 3: Component; Reactor Building Exhaust fan failure with the Standby Exhaust fan failing to start. The operator takes manual control to place the Standby Exhaust fan or SBGT in service to re-establish the required Reactor Building DP. (Critical Task).
~~Event 4: Reactivity/ComponentlTS; A "2A" Recirculation Pump ASD Cell will auto bypass.~~
( This will result in a flow and power reduction. The ASD Cell Bypass and Recirc flow mismatch will be addressed by annunciator response procedures and an abnormal procedure. The SS will address TS for Recirc flow mismatch. The plant will be operating in the Immediate Exit Region of the Power-to-Flow map. The ATC operator will insert control rods or increase Recirc Pump speed to exit the Immediate Exit Region of the P/F map.
Event 5: ComponentlTS; Recirc Pump '2A' will experience high vibration requiring reducing reactor power in an attempt to clear the alarm. Alarm remains in until pump is tripped. The SS addresses TS for an inoperable Recirc pump. The plant will be operating in the Immediate Exit Region of the Power-to-Flow map. The ATC operator will insert control rods to exit the Immediate Exit Region of the P/F map.
~~Event 6: ComponentlTS; HPCI Room fire.~~
Event 7. Major; Condenser Bay Flooding is received which de-energizes 4160V 2A & & 2B, requiring the operator to insert a manual scram. HPCI governor valve will not open to provide sufficient steam to the HPCI turbine. B MSL fails to automatically close; manual works.
~~Event 8: Component; SRV 'B' fails open and remains partially open after the fuses are pulled.~~
Event 9: Component; RCIC isolates due to false high flow signal and the Startup Level Control Valve 2N21-Flll will fail in the closed direction prohibiting Feedwater flow for injection. The operator will take manual actions to maintain RWL above TAF (-155") (Critical Task)
Page 30 of31 of 31 Critical Tasks NRC Draft
( ~"'acility:
Facility: E. I Hatch Scenario No.: 5-04 Op-Test No.: 2009-302 Critical Tasks
~~Manually start the standby reactor building exhaust fan or SBGT to return Reactor Building DP to a more negative value. (Event 3)~~
~~Throttle open the 2N21-FIlO Startup Level Control Valve and use the CondensatelFeedwater system to maintain RWL above TAFTAP (-ISS"). (Event 9)~~
~~ES 301-4 Attributes Required Actual Items~~
~~1. Total Malfunctions 5-8 7 1. Reactor Building Exhaust fan failure. (Event 3)~~
~~2. Recirculation Pump "2B" ASD Cell bypass.~~
~~(Event 4)~~
~~3. Recirc Pump '2B' high vibration (Event 5)~~
~~4. HPCI Room fire (Event 6)~~
~~5. Condenser Bay Flooding (Event 7)~~
~~6. SRV 'B' OPENSlleaks partially open (Event 8)~~
~~7. RCIC isolates with Startup Level Control Valve 2N21-Flll 2N21-Fl11 failing closed. (Event 9)~~
~~2. Malfunctions After 1-2 2 1. SRV 'B' OPENSlleaks OPENS/leaks partially open (Event 8)~~
~~( EOPEntry EOP Entry 2. RCIC isolates with Startup Level Control Valve 2N21-Flll 2N21-Fll1 failing closed. (Event 9)~~
~~3. Abnormal Events 2-4 4 1. Reactor Building Exhaust fan failure. (Event 3)~~
~~2. Recirculation Pump "2B" ASD Cell bypass.~~
~~(Event 4)~~
~~3. HPCI Room fire (Event 6)~~
~~4. Condenser Bay Flooding (Event 7)~~
~~4. Major Transients 1-2 1 1. Condenser Bay Flooding (Event 7)~~
~~5. EOPs entered, 1-2 2 1. EOP RC (Non-ATWS) requiring substantive 2. EOPPC actions~~
~~6. EOPs contingencies 0-2 0 requiring substantive actions~~
~~7. Critical Tasks 2-3 2 1. Manually start the standby reactor building exhaust fan or SBGT (Event 3)~~
~~2. Throttle open the 2N21-FII0 2N21-FllO SLCV to maintain RWL above TAF (-ISS").~~
(-155"). (Event 9)
HLT 5 NRC Operating Exam Scenario 4 SHIFT TURNOVER UNIT 1 S'FATUS Power: 100 % power Activities in progress: None Power: 92.5% power with RPV pressure at 1020 psig The following equipment is None inoperable:
Scheduled evolutions: Have the BOP operator perform 34IT-N30-00l-2, "Main Turbine & Auxiliaries Weekly Test", PowerlLoad Unbalance Test section 7.2 only.
OATC Increase After the Turbine test is complete, have the OATe COps Management has Reactor Pressure to 1025 psig (Ops
( determined that Attachment 3 of 34GO-OPS-005-2 is NOT required.), then increase Reactor power to 95% using the Rx Recirc system, with a 10 MWe limit on power change rate.
Surveillances due this 34IT-N30-00l-2, "Main Turbine &
34IT-N30-001-2, & Auxiliaries Weekly Test",
shift: PowerlLoad Unbalance Test section 7.2 only.
Active clearances: None Rod Configuration: SeeRWM
Page 1 of 21 AppendixD Scenario Outline Form ES-D-l ES*D*1 Draft Facility: E. I Hatch Scenario No.: 5*05 5-05 Op*Test No.:
Op-Test 2009-302 2009*302 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at approximately 5% power preparing to remove the Mechanical Vacuum Pump from service per step 7.3.26 ,o~ 34GO-OPS-001-2 34GO-OPS-OOI-2 .
Turnover: Continue with startup IA lAW W 34GO-OPS-001-2. RWM is inoperable and a second licensed operator is available for rod movement verifications.
Event Malf. No. IEvent Event No. Type* Description Descrl:l!tion 1 loN22_FOO7R2 IN aoN22_FOO7R2 N (BOP) Secure Mechanical Vacuum Pump per 34S0-N61-001-2 with suction valve 2N22-F007 failing to full close Ivalve
~/A N/A ~R (ATC) Pull control rods to continue Startup to - 8% power and raise pressure 2
fwm 915 to 920 psig~
set fmm psig.
3 mfC12_23 26-23 C (ATC) Control Rod (pick one from pull sequence) uncoupled and allowed to mfC12_2326-23 TS (SRO) Irecouple per Annunciator Response Procedure.
rrS
( j4 14- mfN33_154 C (BOP) Turbine Gland Seal Reg Fails Closed (must be in chest warming) mfG3L207A C(BOP) RWCU line breaks outside of Primary Containment. Must be manually
~5 svoG31071 TS (SRO) isolated (Critical Task), with failure of outboard isolation valve to ImfG31_52 mfG3L52 close.
svoB21220 C (ATC) SRV 2B21-F013G opens. The SRV will close after the ATC depresses k>6 loB2LF013GR2 the he LLS Reset PB IA lAW W section for electrically open. (Critical Task)
The SS will initiate a tracking RAS.
~21_247A WS21_247A M (ALL) Inadvertent Group 1 Isolation, MSN MSIV closure
~7 mfB21_247B mfB21 247B Scram Discharge Volume A ATWS TWS (Critical task)
~Cl1-211 mfC11 211 8 mfC4L240A ImfC4L240A C2 (ATC) SBLC Pump '2A' start failure
~C4L240B mfC4L240B SBLC Pump '2B' start failure Inject SBLC locally Iniect diE51_S33 diE51 S33 C (BOP) RCIC Manual Initiation PB fails
~9 ~5L109 mfE51_109 level/hi DW pressure. Manual RCICIHPCI fails to Auto start on low levellhi
~L235A mfE41_235A actions required for injection.
mfE41 235B
~~(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor~~
Appendix 0 Required Operator Actions ES-D-2 Form ES-O-2 II'I Op-Test No.: 2009-302 Scenario No.: 5-05 Event No.: 1 Page 2 of 21 of21 Event
~~Description:~~
~~Remove Mechanical Vacuum Pump from service with valve failure Time Position Applicant's Actions or Behavior I BOP Removes MVP from service:~~
~~Trips 2N22-C002, MVP, by taking its control switch to STOP~~
~~Confirms 2N22-FOlO Vacuum Pump Disch Vlv CLOSED~~
~~Recognizes 2N22-F007 Vacuum Pump Suction Vlv did NOT fully close~~
~~Sends an SO to:~~
0 confirm the seal pump stops 0 Close 2P21-F021 Makeup Valve 0 Investigate failure of N22-F007 to close Simulator Operator: After the SO is sent to the MVP, wait 2 minutes and DELETE loN22_F007R2 and report thefollowing:
the following:
~~2N22-F007 was manually closed and you will write a CR and Work Order for it~~
~~The seal pump is stopped~~
~~The 2P21-F021 Makeup Valve is closed Simulator Operator, at the Chief Examiners direction, as Shift Manager, direct the SS to proceed to raising pressure set to 920 psig.~~
Appendix D Required Operator Actions Form ES-D-2 I,-,
( Op-Test No.: 2009-302 Scenario No.: 5-05 Event No.: 2 Page 3 of 21 Event
~~Description:~~
Pull control rods to - 8% power, raise pressure set to 920 psig and transfer the reactor mode switch to run Time Position Applicant's Actions or Behavior I Note: lAW 34GO-OPS-001 34GO-OPS-00l -2, Attachment 15, the maximum increase above 500 psig is < 1.6 psig/min due to SRV leakage considerations.
SRO ATC to increase reactor pressure to 920 psig using ERC pressure Directs the ATC set.
ATC Enters 34GO-OPS-001-2, 34GO-OPS-00l-2, 'Plant Startup', at step 7.4.1 and at the DERC panel computer, performs the following steps:
Selects the IControl I~ I psi- load Iscreen Intermittently uses (Clicks) the I Raise I button to increase reactor
( pressure to 920 psig. (This will take approx. 4 minutes.)
Notifies the SS that Rx pressure is at 920 psig.
BOP Notifies Lab Foreman to take required samples for power operation.
(
II
Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2 II
( Op-Test No.: 2009-302 Scenario No.: 5-05 Event No.: 2 Page 4 of of21 21 Event
~~Description:~~
Pull control rods to - 8% power, raise pressure set to 920 psig and transfer the reactor mode switch to run I Time Position Applicant's Actions or Behavior I Note:
~~When asked, tell the operator that you are the second licensed operator and peer checker.~~
~~When the operator selects a rod, as peer checker state the rod number (e.g. 22-23) and the operator will state "I~~
~~"/ agree".~~
~~For other communications the operator makes (e.g. stating where the~~
"/ agree".
rod is to be moved to), as peer checker, state "I ATC
~~Withdraws the control rods within a step to the withdraw limit~~
~~Initials for control rod withdrawal~~
~~Dates for control rod withdrawal~~
~~If the rod is a position 48 performs a coupling check by:~~
~~Apply a withdraw signal by placing the Rod Movement Control switch to the withdraw position.~~
~~Confirm the withdraw logic actuates by illumination of the red withdraw light.~~
~~Confirm the rod attempts to move by a momentary loss of the "48" position indication.~~
~~Confirm the rod does NOT move beyond position 48.~~
~~Confirm annunciator ROD OVERTRAVEL (603-248) is NOT received.~~
~~Document the coupling check on a Control Rod Movement Sequence form Note; When control rod 26-23 is moved the rod will be uncoupled, which will start the next event.~~
~~ATC~~
~~Stops control rod withdrawal when highest reading APRM is reading between 6%-7%.~~
(
II
Appendix D Required Operator Actions Form ES-D-2 (I'I Op-Test No.: 2009-302 Scenario No.: 5-05 Event No.: 3 Page 5 of21 of 21 Event
~~Description:~~
~~Control rod uncoupled when moved Time Position Applicant's Actions or Behavior I ATC~~
~~Enters the following alarm procedures:~~
~~603-248, 'Rod Overtravel'~~
~~603-247, 'Rod Drift'~~
~~Determines control' rod 26-23 is the affected rod controlrod~~
Notifies the SS REIManagement about determining if the Simulator Operator: If contacted as REIManagement control rod is uncoupled, inform the operator that it has been determined the control rod IS uncoupled.
Simulator Operator: After the operator inserts the rod, delete the uncoupled mfC12 23 26-23.
rod malfunction mjC12 ATC
~~Attempt to recouple the rod by moving in not more than 3 notches~~
(
~~Withdraw the rod and confirm the rod is coupled by performing a check coupling check~~
~~Notifies the SS of the Tech Spec 3.1.3 and that the rod is now coupled~~
~~Resets the Rod Drift alarm Note: Due to the short period of time the rod will be inoperable the SS may not declare that the rod was inoperable during the scenario.~~
Simulator Operator: For conservatism, the SS may still consider the rod inoperable even though coupled, and stop the startup. With Chief Examiner approval, call as the Shift Manager and inform the SS that Licensing and Engineering agree that the rod is operable.
SRO Reviews Tech Spec 3.1.3 and determines the rod was inoperable requiring it to be fully inserted within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and disarmed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months but is now operable.
(
Simulator Operator, at the direction of the Chief Examiner, proceed to next event.
Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2
'III Op-Test No.: 2009-302 Scenario No.: 5-05 Event No.: 4 Page 6 of21 of 21 Event
~~Description:~~
Main Turbine Gland Seal Regulator valve fails closed I Time Position Applicant's Actions or Behavior I Simulator Operator: At the direction of the Chief Examiner, ENTER malfunction mfN33_154 mjN33_154 (RB-4).
Note: If the F004 valve is not opened, it takes approximately 2.5 minutes for the turbine to trip on low vacuum.
ALL Recognize 650-125, 'Steam Seal Press Low' annunciator BOP Responds to 650-125, 'Steam Seal Press Low' annunciator
~~Confirms 2N33-R601A, Steam Seal Hdr Pressure fudicator, Indicator, is below 1.5 psig, panel 2Hll-P650.~~
~~2H11-P650.~~
~~Confirms OPEN 2N33-F003, Steam Seal Main Steam Feed Vlv.~~
~~Confirms CLOSED 2N33-FOO5, 2N33-F005, Unloading Bypass Vlv.~~
(
~~Confirms CLOSED 2N33-F008, Aux Steam Feed Vlv.~~
,
~~Throttle OPEN 2N33-F004, Steam Seal Feed Vlv Bypass, to bring steam -seal pressure to between 2.5 PSIG and 4.5 PSIG.~~
~~Sends an SO to the Steam Seal Feed Valve Controller to confirm> 20 #~~
Inlet Pressure AND < 15 # Air Outlet Pressure.
Air fulet Simulator Operator: If sent as the SO to check on Steam Seal Feed Valve Controller air pressure, wait 2 minutes and report air inlet is > 20 psig and air outlet is 0.5 psig.
Simulator Operator, at the direction of the Chief Examiner, proceed to next event.
Appendix D 0 Required Operator Actions ES-O-2 Form ES-D-2 Op-Test No.: 2009-302 Scenario No.: 5-05 Event No.: 5 Page 7 of 21 of21 Event
~~Description:~~
RWCU line will break outside of Primary Containment I Time Position Applicant's Actions or Behavior Applicanfs Simulator Operator: When power is approximately 7%, at the direction of the Chief Examiner:
~~ENTER malfunction mfG31_52. (RB-S)~~
~~DELETE svoG31071 when the F004 control switch is taken to close.~~
~~ALL Recognize "RWCU Sys Leak" annunciator BOP Responds to "RWCU Sys Leak" annunciator~~
~~Determines that an isolation is required and enters 34AB-G31-001-2.~~
~~Confirms automatic actions by:~~
~~Tripping RWCU Pump "2B~~
~~Places control switch for 2G31-FOOI 2G31-F001 to close~~
~~Places control switch 2G31-F004 to the close (Critical Task)~~
~~Notifies SS of conductivity monitoring requirements of TRM T3.4.1.~~
(
~~Notifies SS of possible SC-Secondary Containment Control Entry~~
~~Notifies SS of the failure of RWCU to isolate and that 2G31- FOOl will not close.~~
~~Suspects a leak has occurred and enters 34AB-T22-001-2~~
~~fuforms Informs ATC to monitor level and power SRO~~
~~Dispatches SO to determine RWCU leak location.~~
~~Dispatches SOlMaintenance to determine why 2G31-F001 and FOO4 did not auto close.~~
~~Enters TS for 2G31-FOO1.~~
~~2G31-FOOl.~~
~~Determines that LCO 3.6.1.3.A applies and that the RWCU Line must be isolated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .~~
~~Enters TRM for continuous conductivity monitoring~~
~~Determines the TSR 3.4.1.1 requires 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months surveillance requirement~~
~~Reviews EOP SC for possible entry conditions~~
Appendix D 0 Required Operator Actions Form ES-D-2 ES-O-2 II Op-Test No.: 2009-302 Scenario No.: 5-05 Event No.: 6 Page 8 of 21 Event
~~Description:~~
SRV "2G" Opens Time Position Applicant's Actions or Behavior Simulator Operator: To insure the ATC operator gets the next malfunction, wait until the BOP is in the back panels OR as Shift Manger, request the BOP to get some back panel readings.
Simulator Operator: When RWCU actions are complete and at the direction of the Chief Examiner, ACTIVATE: (RB-6)
~~svoB21220~~
~~loB21_F013GR2 Simulator Operator: When the operator depresses the LLS Reset PB, then delete above overrides.~~
~~All~~
~~Recognize annunciators:~~
~~602-311, 'Safety Blowdown Valve Leaking'~~
~~603-122, 'Safety Blowdown Pressure High'~~
(
The ATC may enter the abnormal procedure first before addressing the ARPs.
ATC
~~Enters 602-311 and 603-122 annunciators~~
~~Confirm which safety relief valve has opened using the amber valve leakage indicator~~
~~Confirms green light is OFF~~
~~Directs BOP to check back panel tail pipe temperatures~~
Appendix 0 Required Operator Actions Form ES-O-2 II
( Test No.: 2009-302 Scenario No.:
Op-Test Op- 5-05 Event No.: 6 Page 9 of 21 Event
~~Description:~~
~~SRV "2G" Opens I Time Position Applicant's Actions or Behavior I BOP~~
~~Confirm "G" is leaking using the indication on 2B21-R614, Auto BlowdowniSafety Vlv Temps recorder.~~
~~Blowdown/Safety~~
~~Reports to the SS and ATC operator that "G" SRV is open The ATC may depress the ADS Logic AlB Timer Reset pushbuttons even though 'G' is a LLS valve.~~
~~ATC~~
~~Executes 34AB-B21-003-2 steps~~
~~Confirms the Red Light is illuminated~~
~~Cycle the SRV control switch several times between OPEN/CLOSE~~
(
~~Depress the ADS Logic AlB Timer Reset pushbuttons~~
~~Depress the LLS Reset pushbuttons (Critical Task)~~
~~When SRV closes confirms;~~
~~Torus water level increase has stopped.~~
~~Torus temperature increase has stopped.~~
~~Reactor Power is at its original value~~
Resets the SRV leak: detection AMBER SRV indicating lights SRO IAW TS 3.3.6.3, Condition D, Declares 'G' SRV inoperable within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or IA IAWW TS 3.6.1.6 declares 'G' inoperable and initiates a tracking RAS.
Simulator Operator, at the Chief Examiners direction, proceed to the next event.
(
Appendix D 0 Required Operator Actions ES-D-2 Form ES-O-2
'I'\
( Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 7 of21 Page 10 of 21 Event
~~Description:~~
Inadvertent Group 1 and ATWS fuadvertent
'I Time JI Position Applicant's Actions or Behavior Simulator Operator: After SRV actions are complete and at the direction of the Chief Examiner, activate: (RB-7)
~~mjB21_247A mfB21_247A~~
~~mfB21 247B ALL Recognizes annunciators and plant conditions:~~
~~Reactor Auto Scram System AlB Trip - Full reactor scram required~~
~~Group 1 System AlB Trip - Full Group 1, MSN isolation SRO~~
~~Assigns the ATC ATC to perform RC-I.~~
~~RC-1.~~
~~Assigns the BOP operator to perform RC-2 and RC-3.~~
~~If time allows assigns TC-1 TC-I to be performed.~~
~~Enters the RCA EOP flow chart, 31EO-EOP-Oll-2, for a scram condition and reactor power above 5%.~~
~~Enters CP-3 EOP flow chart, 31EO-EOP-017-2, for ATWS level control.~~
(
D Appendix 0 Required Operator Actions Form ES-D-2 ES-O-2 II'\
( Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 8 Page 11 of21 of 21 Event
~~Description:~~
~~RCICIHPCI Failures and ATWS Time I Position Applicant's Actions or Behavior I ATC~~
~~Performs RC-l RC-1 consisting of:~~
~~Inserts a manual scram.~~
~~Places the mode switch to shutdown.~~
~~Attempts to confirm all rods are inserted by observing full in lights, SPDS, or the RWM display.~~
~~Notifies the SS that control rods are out~~
~~Places SDV isolation valve switch to "isolate" & confirms closed.~~
~~Trips Recirc Pumps (power >5%)~~
~~Inserts SRMs and IRMs.~~
~~Injects SBLC (power >5%)~~
~~Unlocks and places SBLC pump select switch in "Start Sys A" or "Start Sys B" position.~~
~~Confirms Squib Valve Ready Lights are extinguished.~~
~~Confirms SBLC Loss of Continuity to Squib Valve annunciator is alarmed.~~
~~Recognizes that the selected SBLC pump DID NOT start.~~
(
~~Places SBLC pump select switch in "Start Sys B" or "Start Sys A" position. (The pump not attempt first.)~~
~~Recognizes that the selected SBLC pump DID NOT start.~~
~~Confirms ConfIrms closed 2G31-F004 (RWCU Isolation Valve)~~
~~Reports to SS failure of SBLC to inject from control room and local initiation lAW 34S0-C41-003-2 is required.~~
~~Shifts recorders to read IRMs, when required.~~
~~Ranges IRMs to bring reading on scale.~~
~~Notifies NotifIes the SS when the above actions are complete.~~
ATC Directs SO to manually initiate SLC locally lAW 34S0-C41-003-2.
Simulator Operator: When called as the SO and SLC initiation, acknowledge the communication. If called again, say that you are working on it and will
( call when completed.
Note: With MSIV closure, checking of ECCS is the only pertinent RC-2 action.
Appendix D Required Operator Actions Form ES-D-2
(
I~~
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 8 Page 12 of21 of 21 Event
~~Description:~~
~~RCICIHPCI Failures and ATWS I Time I Position Applicant's Actions or Behavior I BOP Performs RC-2 by checking status of ECCS systems.~~
~~Performs RC-3 consisting of:~~
~~Monitor RPV pressure.~~
~~Confirm proper operation of pressure control system (LLS and SRVs).~~
~~If necessary, allows RPV pressure to exceed 1074 psig then cycles any SRV to initiate LLS.~~
~~Maintain RPV pressure between 1074 and 800 psig.~~
Notify SS that LLS is the pressure control system.
SRO
~~Directs ATC to:~~
(
~~Confirm the reactor Mode Switch in Shutdown.~~
~~Confirm ARI Initiation.~~
~~ATC~~
~~Reports to the SS that:~~
~~The Reactor Mode Switch is in the Shutdown position.~~
~~ARI has been initiated (ATC may initiate ARI at this time)~~
~~Recirc is at minimum speed or tripped if power> 5%.~~
(
Appendix 0 Required Operator Actions Form ES-O-2 I,
( Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 8 Page 13 of 21 Event
~~Description:~~
~~RCICIHPCI Failures and ATWSATWS Time I Position Applicant's Actions or Behavior I SRO~~
~~ATC Directs A STA to report reactor power or observes reactor power TC or STA on SPDS.~~
~~Directs ATC to Reset ARI and insert control rods IAW 31EO-EOP-I03-2.~~
31EO-EOP-103-2.
Note: If asked, STA will direct the ATe to start in the center of the core and spiral out in a "black and white" pattern.
ATC
~~Enters 31EO-EOP-103-2, "EOP Control Rod Insertion Methods".~~
~~Confirms ARI initiation signals are clear~~
~~Depresses ARI Reset pushbutton~~
(
~~Check annunciator ARI INITIATED, clear~~
~~Attempts to drive rods by:~~
~~Place Reactor Mode switch to REFUEL.~~
~~Place Rod Worth Minimizer bypass switch to BYPASS.~~
~~Obtain recommendations from STA~~
~~Verifies adequate CRD drive water pressure for driving rods and may operate 2CII-R600, 2C11-R600, CRD Flow Control, to achieve higher drive water DP.~~
~~May start second CRD pump~~
~~Drive rods to at least 02 using the Emerg In or IN (Critical Task)~~
~~BOP~~
~~As time allows, performs TC-1 TC-l~~
~~Confirm Trip of the Turbine.~~
~~Confirm TSV's, TSV' s, TCV's, and CN's CIY's have properly closed.~~
~~Confirm/Place TGM in auto.~~
~~Start TG Oil Pump~~
~~Motor Suction Pump~~
~~Lift Pumps~~
(
I
Appendix D Required Operator Actions Form E8-D-2 ES-D-2 i
.,II
( Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 8 Page 14 of 21 of21 Event
~~Description:~~
~~RCIC/HPCI Failures and A ATWS TWS Time I Position Applicant1s Actions or Behavior Applicant's I SRO~~
~~Directs BOP control RWL -60 inches to -90 inches.~~
~~Directs STA to verify Isolations and ECCS initiations.~~
~~BOP~~
~~Reduces injection to control RWL -60 inches to -90 inches.~~
~~To control HPCI injection the operator may place 2E41-C002-3, HPCI Aux. Oil Pump, in PULL-TO-LOCK or reduce controller output.~~
~~To control RCIC injection the operator may depress the RCIC turbine trip push-button or reduce controller output.~~
(
ALL
~~Recognizes torus temperature is above 95°F.~~
~~BOP~~
~~Enters 34AB-T23-003-2, Torus Temperature Above 95°F~~
~~Confirms the high temperature by observing the Suppression Pool bulk average temperature on the SPDS primary display~~
~~Places RHR in Suppression Pool cooling per 34S0-E11-010-2, 34S0-E 11-0 10-2, Residual Heat Removal.~~
(
Appendix D 0 Required Operator Actions ES-O-2 Form ES-D-2
'\
Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 8 of21 Page 15 of 21 Event
~~Description:~~
RCICIHPCI Failures and ATWS
!I Time I Position Applicant's Actions or Behavior NOTE: The operator may place torus cooling in service by using the Placard that's available or using the appropriate section of the procedure. These steps assume the Placard is used.
The A or B loop of RHR may be used. The following steps are written assuming "B" loop and "B" pump is used. If "A" loop is used, substitute "A" for "B" for valves and if "B" pump is not used substitute "A", "e", or "D" "A ", "C",
for "B" pump.
BOP
~~Enters 34S0-EII-0I0-2, 34S0-EII-01O-2, Residual Heat Removal or uses placard on (Placard) 2HII-P601.~~
~~Places RHRSW in service~~
~~Prelubes RHRSW pump~~
~~Overrides 2EII-F068B Low Discharge Pressure Interlock~~
~~Positions 2EII-F068B to 45% OPEN~~
~~Starts RHRSW pump B~~
~~( - RHR HX B DiffDiffPress Press Low (601-215) alarms~~
~~Places 2EII-F068B Low Discharge Pressure Interlock switch to normal position.~~
~~Positions 2EII-F068B to obtain < 4400 GPM AND < 450 PSIG~~
~~RHR HX B DiffPress Diff Press Low (601-215) alarm clears~~
(
Appendix D Required Operator Actions Form ES-D-2 II
( Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 8 Page 16 of 21 Event
~~Description:~~
~~RCICIHPCI Failures and ATWS Time I Position Applicant's Actions or Behavior I BOP~~
~~Place RHR loop B in Suppression Pool Cooling (Placard)~~
~~Does NOT position the 2/3 Core Height Permissive switch.~~
~~(RWL will NOT be lowered to below 2/3 core height)~~
~~Does NOT place the Containment Spray valve Control switch in the manual position. (LOCA signal is not present)~~
~~Confirm open 2E11-F048B, 2EII-F048B, HX Bypass Vlv.~~
~~2EII-F047B, Hx Inlet Vlv.~~
~~Close 2E11-F047B,~~
~~Confirm open 2Ell-F003A, HX Outlet Vlv~~
~~Start "2B RHR pump~~
- SEC System Auto Initiation Signal Present (650-234) alarms
- Auto Blow Down CS or RHR Press Permissive (602-312) alarms
- RHR Flow Low (601-215) alarms
~~Open 2EII-F028B, 2E11-F028B, Torus Spray or Test Vlv.~~
~~Throttle open 2E11-F024B, 2EII-F024B, Full Flow Test Line Vlv. and establish RHR flow of less than or equal to 7700 gpm (R603B)~~
~~( - RHR Flow Low (601-215) alarm clears~~
~~Open 2Ell-F047B, 2EI1-F047B, Hx Inlet Vlv.~~
~~Close 2E11-F048B, 2EII-F048B, Hx Bypass Vlv.~~
~~Reports to SS that RHR has been placed in Suppression Pool Cooling mode.~~
BOP Controls RWL -60 inches to -90 inches.
(
Appendix D0 Required Operator Actions Form ES-D-2 ES-O-2 I,
~ ,
. Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 8 Page 17 of 21 Event
~~Description:~~
~~RCIC/HPCI Failures and ATWS Time JI Position Applicant's Actions or Behavior BOP IF RCIC injection is attempted AND RCIC was manually tripped:~~
~~Transfers 2E51-R612, Turbine Controller, to MANUAL AND adjust output to 50%.~~
~~Closes 2E51-F524, Trip & Throttle Valve.~~
~~Opens 2E51-F045, Stm to Turb Valve.~~
~~Opens 2E51-F046, Turb Clg Water Valve.~~
~~Starts 2E51-C002-2, Barom Cndsr Vac Pump.~~
~~Throttle opens 2E51-F524, Trip & Throttle Valve, AND concurrently 2E51-F0l3, Pump Discharge Valve opens 2E51-F013,~~
~~Confirms 2E51-F019, Min Flow Valve, Opens, AND subsequently Closes, WHEN system flow is greater than 79.3 gpm.~~
~~Continues to throttle 2E51-F524 Open, UNTIL turbine speed is limited by 2E51-R612, Turbine Controller, THEN perform the following:~~
~~Fully opens 2E51-F524, Trip & Throttle Valve.~~
(
~~Increases 2E51-R612, Turbine Controller, output to achieve 3000 to 4000 rpm.~~
~~Transfers 2E51-R612, Turbine Controller, to AUTO AND adjust to desired flow rate.~~
~~Maintains level -60" to -90" BOP IF RCIC injection is attempted and RCIC is NOT tripped:~~
~~Depresses RCIC Manual Initiation PIB (failed)~~
~~Opens 2E51-F046~~
~~Starts Barom Cndsr Vac Pmp~~
~~Opens 2E51-F045~~
~~Confirms open 2E51-F019 2E51-FO 19~~
~~Confirms closed 2E51-F019 at flow> 79.3 gpm~~
~~Opens 2E51-FO 2E51-F013 13~~
~~Adjusts controller for desired flow~~
~~Maintains level -60" to -90"~~
(
Appendix 0 Required Operator Actions Form ES-O-2 I,II
( . Op-Test No.: 2009-302 Scenario No.: 5-04 Event No.: 8 Page 18 of 21 Event
~~Description:~~
RCICIHPCI Failures and ATWS II Time I Position Applicant's Actions or Behavior I Note: With an initial torus temperature of 86 deg F., after the Group 1 isolation and without rod insertion or Torus Cooling, it takes - 6 minutes for torus temperature to reach 100 deg F.
SRO Enters EOP PC chart on a Torus Temperature of 100 deg F and directs BOP:
~~To monitor:~~
~~Torus Temp~~
~~Torus Level~~
~~Drywell Temp~~
~~Containment Pressure~~
~~Place Hydrogen and Oxygen analyzers in service lAW IAW 34S0-P33-001-2~~
(
Simulator Operator With Chief Examiner's permission Scenario will stop here.
Page 19 of 21 Scenario Summary Facility: E. I Hatch Scenario No.: 5-05 Op-Test No.: 2009-302
( NRC Draft Dra/t Initiating Conditions: Unit 2 is operating at approximately 5% RTP in Chest Warming Turnover Continue startup lAW 34GO-OPS-00 34GO-OPS-001-21-2 and remove the Mechanical Vacuum Pump from service Summary:
~~Event 1: Remove the Mechanical Vacuum Pump from service with suction valve 2N22-F007 failing to full close.~~
~~Event 2: Pull control rods to continue Startup to -~ 7% power, raise pressure set to 920.~~
~~Event 3: ComponentfTS; While withdrawing control rods a control rod will become uncoupled.~~
~~The operator takes manual control to re-couple the control rod per the annunciator response procedures. The SS will address Tech Specs for the uncoupled control rod.~~
~~Event 4: Component; The main turbine Gland Seal Regulator valve will fail closed while in chest warming. The operator will take manual actions to restore the steam seal header pressure to normal.~~
~~Event 5: ComponentffS; ComponentfTS; A RWCU line will break outside of Primary Containment. The inboard and outboard isolation valves fail to close automatically. The operator will take manual~~
~~( actions to isolate the leaking RWCU line. (Critical Task) The SS addresses Tech Specs for inoperable Primary Containment Isolation Valves.~~
Event 6: ComponentfTS; SRV "2G" opens. The ATC operator will attempt to close the SRV lAW the abnormal procedure for an electrically open SRV. After the ATC operator depresses the LLS Reset pushbuttons (PB), the SRV will close. (Critical task). If Torus temperature exceeds 95°F, the BOP operator will place RHR in Suppression Pool Cooling. SS addresses TS for inoperable SRV.
~~Event 7: Major; Inadvertent Group 1 isolation causes MSNsMSIVs closure. An ATWS condition will exist, requiring the ATC operator to manually insert control rods (Critical task).~~
~~Event 8: Component; Both SBLC pumps will fail to start from the control room. The operator will take manual actions to inject SBLC locally.~~
~~Event 9: RCIC and HPCI fail to auto start. RCIC must be manually aligned and started to R WL -60" to -90".~~
maintain RWL-60"
of21 Page 20 of 21 Critical Task List Facility: E. I Hatch Scenario No.: 5-05 Op- Test No.:
Op-Test 2009-302
(
Critical Tasks
~~Manually isolate RWCU before exceeding maximum safe Secondary Containment Control EOP parameters (Temperatures, Radiation levels or SC water levels). (Event 5)~~
~~Depresses the LLS Reset pushbuttons to close SRV (Event 6)~~
~~Commence insertion of control rods within 20 minutes and before entering the unsafe region of the Heat Capacity Temperature Limit graph (Event 7)~~
~~ES 301-4 Attributes Required Actual Items~~
~~1. Total Malfunctions 5-8 7 1. Control rod becomes uncoupled (Event 3)~~
~~2. Gland Seal Regulator valve fails (Event 4)~~
~~3. RWCU line break outside of Primary Containment (Event 5)~~
~~4. SRV "2G" begins leaking (Event 6)~~
~~5. Inadvertent Group 1 on low vacuum along with an A TWS (Event 7)~~
~~ATWS~~
~~6. Both SBLC pumps will fail (Event 8)~~
~~7. RCIC and HPCI fail to auto start. (Event 9)~~
(
~~2. Malfunctions After 1-2 2 1. Both SBLC pumps will fail (Event 8)~~
~~EOPEntry EOP Entry 2. RCIC and HPCI fail to auto start. (Event 9)~~
~~3. Abnormal Events 2-4 2 1. RWCU line break outside of Primary Containment (Event 5)~~
~~2. SRV "2G" opens (Event 6)~~
~~4. Major Transients 1-2 1 1. Inadvertent Group 1 on low vacuum along with an ATWS (Event 7)~~
~~5. EOPs entered, 1-2 2 1. EOP RCA (ATWS) requiring substantive 2. EOPCP-3 actions~~
~~6. EOPs contingencies 0-2 1 1. EOP CP-3 requiring substantive actions~~
~~7. Critical Tasks 2-3 3 1. Manually isolate RWCU. (Event 5)~~
~~2. Uses LLS Reset PB to close SRV (Event 6)~~
~~3. Insert Rods during ATWS (Event 7)~~
(
HLT 5 NRC Operating Exam Scenario 5 SIDFT TURNOVER UNIT 1 STATUS Power: 100%
Activities in progress: None UNIT 2 STATUS Power: Unit 2 is operating at approximately 5% power preparing to remove the Mechanical Vacuum Pump from service per step 7.3.26 of 34GO-OPS-001-2.
34GO-OPS-OOl-2.
The following equipment is Rod Worth Minimizer. A second licensed operator is available inoperable: for rod movement verifications and peer check.
Scheduled evolutions: Continue with startup lAW 34GO-OPS-001-2.
There are no further Drywell entries to be made.
( Hydrogen Water Chemistry Injection is ready for service at 35% power lAW 34S0-P73-001-2.
Surveillances due this None shift:
Active clearances: None Rod Configuration: Sequence A2, Step 19, Rod 34-31

ML093430170

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