ML062900423

- References procedure 2.1.10.

- Lowers the speed of both reactor recirc pumps.

- Monitors plant as power lowers

- Ensures that RR flows are balanced.

ROLE PLAY:

As SO at the AB@ SW Pump report the pump is ready for operation.

CRS Directs BOP operator to shift operating SW Pumps by placing AB@ SW Pump in service and securing the AD@ SW Pump per 2.2.71.

Lesson

Title:

CRD Discharge Filter Failure, RR Pump Seal Failure, Large Break LOCA /Loss of Startup Transformer/Lock out of 4160 1G, manually align CS to inject Lesson#:

SKL052-52-XX Scenario 3 (IC227)

Rev. No.:

00 Page 9 of 14 Conditions/Instructor Activities Operator Activities ROLE PLAY:

If asked by the control room report that no sounding is in progress and silt levels are below the limit.

ROLE PLAY:

If asked by the control room for Zurn strainer D/P report D/P at 2 psid.

ROLE PLAY:

If contacted after the pump swap report that the AB@ SW Pump is ready operating normally.

BOP Contacts SO at the AB@ SW Pump to insure pump is ready to start.

Place mode selector switch for the AB@ SW Pump in MAN.

Start AB@ SW Pump by placing CS to START.

Verify normal system pressures.

Place mode selector switch for AB@ SW Pump to STANDBY.

Place mode selector switch for the AD@ SW Pump in MAN.

Stop AD@ SW Pump by placing CS to STOP.

Notes Overload Trip Annunciator and reports to CRS.

Verify mode selector switch positioned per 2.2.71.

- Refers to Tech Specs 3.7.2 and determines a 30 day LCO.

ACTION When the crew has completed the Service Water Pump Swap and Tech Spec call Insert Trigger E12 and Trigger 1:

Battery Room Vent Fan Trip indication.

ACTION After the BOP starts the alternate fan wait 5 seconds and delete the fan annunciator overrides inserted on trigger 1 BOP

- Responds to Annunciator Card and reports that the Operating Battery Room Vent Fan has failed.

- Starts alternate fan CRS

- Refers to TRM 3.8.1 and determines a 7 day TLCO with one fan inoperable.

Lesson

Title:

CRD Discharge Filter Failure, RR Pump Seal Failure, Large Break LOCA /Loss of Startup Transformer/Lock out of 4160 1G, manually align CS to inject Lesson#:

SKL052-52-XX Scenario 3 (IC227)

Rev. No.:

00 Page 10 of 14 Conditions/Instructor Activities Operator Activities ACTION When the crew has completed the Battery Vent Fan actions Insert Trigger E2:

DG Trouble Annunciator ROLE PLAY Station operator reports that the cause of the DG Trouble alarm is low oil temperature, the actual oil temperature is 85°F. Also inform the Control Room that alarm procedure DG-2/1-5 directs that if temperature is less than 90°F the SM be informed to declare DG2 inoperable.

- Announces DG#2 Trouble Alarm and dispatches a SO to investigate.

- Declares DG2 inoperable enters 7 day LCO.

- Addresses TS 3.8.1

- Directs the performance of SR 3.8.1.1

- Declares SLC pump 1B inoperable with 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months restoration time.

ACTION When the crew has finished the Tech Spec call on the Diesel Generator, Insert Trigger E4:

RD08B CRD Pump 1B Trip RO Announces Suction Filter High D/P alarm.

Announces CRD pump 1B Trip Place CRD-FC-301 in MAN.

Adjust CRD-FC-301 to minimum Start CRD Pump A.

Slowly adjust CRD-FC-301 to obtain flow of 50 gpm.

Balance CRD-FC-301.

Place CRD-FC-301 to BAL Informs the CRS that CRD pump 1A is in service.

CRS Directs the RO to place the Standby pump in Service.

Lesson

Title:

CRD Discharge Filter Failure, RR Pump Seal Failure, Large Break LOCA /Loss of Startup Transformer/Lock out of 4160 1G, manually align CS to inject Lesson#:

SKL052-52-XX Scenario 3 (IC227)

Rev. No.:

00 Page 11 of 14 ACTION When the CRD pump 1A is running.

Insert Trigger E5:

RR10 Recirc Pump #1 Seal Failure In four minutes RR11 Recirc Pump #2 Seal Failure RO Reports abnormal indications on A RR pump.

May diagnose the failure as #1 pump seal.

- Enters and directs actions of 2.4RR.

RO Reports annunciator 9-4-3/E4 RECIRC A/B PUMP MOTOR HI/LOW TEMP Reduces the speed of RR pump 1A.

RO/BOP

- Reports failure of #2 seal and rising drywell pressure.

- Trips and isolates the A RR pump

- Reports Reactor Scram

- Performs Scram Actions

- Makes Scram Report CRS

- Directs RR pump A shutdown and the loop isolated.

BOP Reports Failure of 41601F to Auto Transfer.

Manually transfers 41601F to the Emergency transformer Reports that DG1 Failed to start.

Reports the lockout of 41601G.

CRS Enters and directs actions 2.1.5 and EOP1A.

Lesson

Title:

CRD Discharge Filter Failure, RR Pump Seal Failure, Large Break LOCA /Loss of Startup Transformer/Lock out of 4160 1G, manually align CS to inject Lesson#:

SKL052-52-XX Scenario 3 (IC227)

Rev. No.:

00 Page 12 of 14 ACTION When the A RR pump is isolated and 4160 1F transferred to the Emergency transformer Activate Trigger E6:

RR32 Reactor Recirc Discharge Loop Rupture RO/BOP

- Reports rapidly lowering reactor water level.

- Directs actions per EOP-1A and EOP-3A.

RO/BOP

- Verifies CS and RHR automatically align and inject to the RPV.

- Reports that CS A and RHR A and D are running.

- Reports that CS injection valve failed to open.

- Opens the CS injection valve.

- Directs water level restored to +3 to 54.

- May direct rapid emergency depressurization of the RPV.

- Directs injection through the RHR HX.

- Directs that RHR loop B be placed in DW and Torus Sprays.

- Direct 6 SRVs open.

- Open 6 SRVs

- When RPV pressure low enough, ensure RHR pump injecting BOP Restores RPV level.

Lesson

Title:

CRD Discharge Filter Failure, RR Pump Seal Failure, Large Break LOCA /Loss of Startup Transformer/Lock out of 4160 1G, manually align CS to inject Lesson#:

SKL052-52-XX Scenario 3 (IC227)

Rev. No.:

00 Page 13 of 14 CRS Depending on final containment conditions may classify the even as event as a Site Area or a General Emergency (based on EAL 2.4.1).

VI.

SCENARIO TERMINATION When emergency depressurization is complete, RPV water level has been restored +3" to +54", have been made, FREEZE the simulator.

VIII.

CRITICAL TASK PERFORMANCE A.

Crew Performance CREW CRITICAL TASKS SAT UNSAT The crew shall restore 41601F to service to provide containment and core cooling.

The crew shall align CS injection valve to restore and maintain reactor water level greater than TAF.

B.

Individual Performance CREW:

DATE:

CRS PASS / FAIL RO PASS / FAIL BOP PASS / FAIL

Lesson

Title:

Lesson#:

SKL052-52-XX Scenario 3 (IC227)

Rev. No.:

00 Page 14 of 14 IX.

INITIAL CONDITIONS A.

Plant Status:

1.

100% power, steady state, near Middle of Cycle in the month of MAY.

Thunder storms are likely, in the area.

2.

Rod Sequence Information:

Step:

1 Rod:

26-19 Notch:

08 B.

Tech. Spec. Limitations in effect:

1.

3.1.7 Condition A for 1A SLC Pump. On day 1 of the 7 day LCO.

C.

Significant problems/abnormalities:

1.

SLC pump 1A is under clearance to replace the discharge relief valve.

2.

Division 2 is protected.

D.

Sentinel Status:

Green E.

Evolutions/maintenance for the on-coming shift:

1.

Reduce Power to 80% to support rod swap.

2.

Start SW pump B and secure SW D due to overheating concerns.

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 CW pump failure, RHR discharge line break, APRM Failure, DEH failure/Group 1 isolation, Containment steam leak and ED due to PSP.

Facility: Cooper Nuclear Station Scenario No.: 4 No.:

Examiners: ____________________________ Operators:

Initial Conditions:

Power is at approximately 80% following maintenance on CBP. Operation is near the end of the fuel cycle.

The plant is in day 1 of a 7 day LCO with SLC pump 1A inoperable due to a stuck open discharge relief valve.

Turnover:

Today is not a red light day. Raise power to 690 MW to support line testing when requested by the dispatcher.

Event No.

Malf.

No.

Event Type*

Position Event Description

1.

1 C N BOP/CRS CW pump 1A trips and 2A is started

2.

2 C

BOP/CRS RHR Loop A discharge leak, Tech Spec

3.

N/A R

RO/CRS Power raise to support Line testing.

4.

3 C

RO/CRS APRM A fails upscale / half scram. Tech Spec

5.

4 C**

ALL DEH Failure Depressurization, Group 1 isolation Failure

6.

5 M

ALL Containment Steam Leak, Pressure suppression function fails.

7.

6 C**

ALL Loss of RHR spray valve permissives, Spray/Cool containment

8.

N/A M**

ALL Emergency Depressurization

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

The plant is operating at 80% power near the end of the fuel cycle with 1A SLC pump out of service. One of the operating CW pumps trips. The crew responds and starts additional pump and enters 2.4VAC.

After idle CW pump is running a maintenance activity breaks a drain nipple off the discharge side of A loop RHR.

The crew responds per EOP 5A and isolates Aux Condensate to the affected loop. When the plant is stable, APRM C fails upscale and causes a half scram. The crew addresses Technical Specifications for the failure and bypasses the affected APRM and resets the half scram.

A DEH failure then occurs resulting in a maximum signal for the turbine control valves. Reactor pressure decreases and the group 1 isolation failures. Only prompt action by the crew to scram the reactor and/or close the MSIVs prevents exceeding a reactor safety limit.

The transient causes a preexisting flaw at an SRV weld to fail resulting in a steam leak directly to the drywell atmosphere. The stress from the steam flow and condensation causes a corroded weld an a downcomer to fail.

This allows the steam to discharge to torus atmosphere. This is a failure of the pressure suppression function of containment. Containment pressure rises rapidly. The crew initiates drywell sprays and initially controls drywell pressure. After the sprays are in service and drywell pressure decreases a malfunction occurs in the control circuit for spray valve control that results in a closure of the RHR drywell spray valve.

Drywell pressure increases eventually requiring the crew to emergency depressurize the reactor vessel when drywell pressure approaches the Pressure Suppression Pressure limit.

The scenario ends when the reactor vessel is depressurized and reactor water level is being controlled 3 to 54.

CREW CRITICAL TASKS The crew shall scram the reactor before reactor pressure safety limit is exceeded.

The crew shall close the MSIVs to prevent exceeding a 100°F/hr cooldown rate.

The crew shall emergency depressurize the RPV when PSP is exceeded or shall rapidly depressurize the RPV to prevent exceeding PSP.

Lesson

Title:

CW pump failure,,, DEH failure/Group 1 isolation, Containment steam leak and ED due to PSP.

Rev. No.: 00 Lesson#:

SKL052-52-XX Scenario 4 SAP BET #

Prerequisites:

None Duration (Hours): 1

References:

1.

Technical Specifications

a.

3.8.1 AC Sources - Operating

b.

2.

Procedures

a.

GOP 2.1.5 Reactor Scram

b.

GOP 2.1.10 Station Power Changes

c.

ACP 2.4GEN Generator or Hydrogen Abnormal

d.

EP 5.3EMPWR

e.

ACP 2.4RR Reactor Recirculation Abnormal

f.

ACP 2.4CRD

g.

EPIP 5.7.1 Emergency Classification

h.

EOP 5.8 RPV Control - 1A

i.

EOP 5.8 Emergency RPV Depressurization - 2A

j.

EOP 5.8 Primary Containment Control - 3A

3.

Miscellaneous

a.

None

4.

PRA

a.

Class of Sequence - Steam Leak in Primary Containment

b.

Key Contributor - Pressure Suppression Pressure COMMITMENT LIST Commitment Rev. Added None

Lesson

Title:

CW pump failure, Sustained OG Combustion, Flow Converter Failure, DEH failure/Group 1 isolation, Containment steam leak and ED due to PSP.

Lesson No.:

SKL052-52-XX Rev. No.:

00 Page 2 of 14 Method:

This evaluation scenario is intended to be used as an examination mechanism for evaluating Licensed Operator knowledge in a dynamic plant situation.

Crew configurations shall be consistent with the normal crew compliment used to operate the lant.

p Special Equipment/Materials/Special Instructions:

The validation simulator load was XXXX. Compare current simulator load to the validation load.

If they are not the same, run the scenario and look for possible changes.

I.

SCENARIO

SUMMARY

The plant is operating at 80% power near the end of the fuel cycle with 1A SLC pump out of service. One of the operating CW pumps trips. The crew responds and starts additional pump and enters 2.4VAC.

After idle CW pump is running a maintenance activity breaks a drain nipple off the discharge side of A loop RHR. The crew responds per EOP 5A and isolates Aux Condensate to the affected loop. When the plant is stable, APRM C fails upscale and causes a half scram. The crew addresses Technical Specifications for the failure and bypasses the affected APRM and resets the half scram.

A DEH failure then occurs resulting in a maximum signal for the turbine control valves. Reactor pressure decreases and the group 1 isolation failures. Only prompt action by the crew to scram the reactor and/or close the MSIVs prevents exceeding a reactor safety limit.

The transient causes a preexisting flaw at an SRV weld to fail resulting in a steam leak directly to the drywell atmosphere. The stress from the steam flow and condensation causes a corroded weld on a downcomer to fail. This allows the steam to discharge to torus atmosphere.

This is a failure of the pressure suppression function of containment. Containment pressure rises rapidly. The crew initiates drywell sprays and initially controls drywell pressure. After the sprays are in service and drywell pressure decreases a malfunction occurs in the control circuit for spray valve control that results in a closure of the RHR drywell spray valve.

Drywell pressure increases eventually requiring the crew to emergency depressurize the reactor vessel when drywell pressure approaches the Pressure Suppression Pressure limit.

The scenario ends when the reactor vessel is depressurized and reactor water level is being controlled 3 to 54.

Lesson

Title:

CW pump failure, Sustained OG Combustion, Flow Converter Failure, DEH failure/Group 1 isolation, Containment steam leak and ED due to PSP.

Lesson No.:

SKL052-52-XX Rev. No.:

00 Page 3 of 14 II.

TASKS RO 200020O0401 Perform Emergency Shutdown From Power and Scram Response 275010O0101 Remove CW Pumps From Service 276020C0401 Respond to Service Water Casualties 200198A0501 Conduct RPV Injection With the LPCI System With the Heat Exchanger in Service 202031P0401 Respond to Trip of Both Reactor Recirculation Pumps 217003O0101 Manually Initiate RCIC System 200199A0501 Conduct RPV Injection With Core Spray System 200198A0501 Conduct RPV Injection With the LPCI System With the Heat Exchanger in Service 226002O0101 Manually Initiate Drywell Spray 230002O0101 Manually Initiate Torus Spray SRO 200336G0503 Direct Actions To Control Reactor Pressure 200337G0503 Direct Actions To Control Reactor Level 200338G0503 Direct Actions to Emergency Depressurize Reactor 200340G0503 Direct Actions For Emergency Shutdown From Power 200344G0503 Direct Actions to Control Drywell Temperature 200347G0503 Direct Actions to Control Torus Water Temperature 202047G0403 Direct Actions for Trip of Reactor Recirc Pumps 262119G0403 Direct Actions for 4160V Switchgear Failure 341030W0303 Evaluate Plant Systems Performance And Coordinate Appropriate Actions Per Technical Specifications In The Event A Limiting Condition For Operation is Entered/Not Satisfied 344018O0303 Classify Emergency Events Requiring Emergency Plan Implementation 344022O0303 Direct Emergency Response As Emergency Director (Emergency Plan)

Lesson

Title:

CW pump failure, Sustained OG Combustion, Flow Converter Failure, DEH failure/Group 1 isolation, Containment steam leak and ED due to PSP.

Lesson No.:

SKL052-52-XX Rev. No.:

00 Page 4 of 14 344037O0303 Perform Required Notifications Of On-Site And Off-Site Personnel For Abnormal/Emergency Events III.

COMMON OPERATOR ERRORS A.

None identified.

IV.

SIMULATOR SET-UP A.

Materials Required None B.

Initialize the simulator in IC20 (EOC)

Batch File Name -

C.

Change the simulator conditions as follows:

1.

Triggers Number File Name Description E1 None Default to False E2 None Default to False E3 None Default to False E10 zdinmsws3[2]

Installs EOP PTMs 31-34 when APRM C is bypassed E20 zaopcpr2a2

>29 mmf mso2c 0.1

2.

Malfunctions Number Title Trigger TD Severity Ramp Initial RP04 Group-1 Isolation Failure A

N/A N/A N/A N/A MC05C Circ Water Pump Trip E1 N/A N/A N/A N/A RH05A RHR Sys Disch Line Break E2 N/A 2

N/A N/A NM09C APRM C Failure E3 N/A 100%

N/A N/A MS08A DEH System Pressure Transmitter Failure E4 0

97%

5:00 As Is

Lesson

Title:

CW pump failure, Sustained OG Combustion, Flow Converter Failure, DEH failure/Group 1 isolation, Containment steam leak and ED due to PSP.

Lesson No.:

SKL052-XX-XX Rev. No.:

00 Page 5 of 14 PC-12 Primary Containment Downcomer Leak E5 2:00 100%

N/A N/A MS02C Main Steam Line Rupture Inside Primary Containment E5 N/A 10%

10:00 0

3.

Remotes Number Title Trigger Value Ramp RH01 Condensate Supply Vlv 296/297 to RHR 16 0

4.

Overrides Instrument Tag Trigger TD Value Ramp SLC pump 1A Control Switch A

N/A OFF N/A SLC pump 1A Green Light A

N/A OFF N/A SLC Squib Vlv A Ready-W A

N/A OFF N/A EOP PTM 31 10 N/A Installed N/A EOP PTM 32 10 N/A Installed N/A EOP PTM 33 10 N/A Installed N/A EOP PTM 34 10 N/A Installed N/A Spray Valve Control Switch E6 N/A OFF N/A D.

Panel Set-up

1.

Ensure PMIS IDTs are blank.

2.

Run Rx Recirc pumps back to make power ~80%

3.

Hang a red tag on SLC pump 1A.

4.

Update Safety System Status Panel (9-5) to reflect that A SLC pump is INOP.

Lesson

Title:

CW pump failure, Sustained OG Combustion, Flow Converter Failure, DEH failure/Group 1 isolation, Containment steam leak and ED due to PSP.

Lesson No.:

SKL052-XX-XX Rev. No.:

00 Page 6 of 14

5.

Balance Master Feedwater Controller.

6.

Balance Main Generator voltage regulator.

7.

Ensure Recirc Controllers are selected to S.

8.

Verify 1B, 1C and 1D CW pumps are running.

Lesson

Title:

CW pump failure, Sustained OG Combustion, Flow Converter Failure, DEH failure/Group 1 isolation, Containment steam leak and ED due to PSP.

Lesson No.:

SKL052-XX-XX Rev. No.:

00 Page 7 of 14

9.

V.

SCENARIO CONDUCT Conditions/Instructor Activities Operator Activities Take the simulator out of FREEZE and allow the crew time to walkdown the panels.

CREW Panel walkdown.

ROLE PLAY:

When the crew has assumed the watch Activate Trigger E1:

MC05C Circ Water Pump Trip ROLE PLAY:

Call the control room as the load dispatcher and request that net load be raised to 690 MWe.

Note: Speed controllers need to be ~76.4 to equal 690 MW.

References Annunciator Procedure A-4/C1.

Monitors vacuum and announces the need to enter 2.4VAC.

Starts 1D CW Pump.

CRS Directs entry into 2.4VAC.

References Procedure 2.1.10.

Raises the speed of both reactor Recirc pumps.

Monitors reactor response as power is raised.

Ensures that RR Pump controllers are matched.

CRS Acts as the reactivity manager.

Monitors Plant parameters.

Acts as peer check for RR controller manipulations.

Lesson

Title:

CW pump failure, Sustained OG Combustion, Flow Converter Failure, DEH failure/Group 1 isolation, Containment steam leak and ED due to PSP.

Lesson No.:

SKL052-XX-XX Rev. No.:

00 Page 8 of 14 ACTION:

After the crew has raised reactor power as specified, Activate Trigger E2:

RH05A RHR A Loop Discharge Line Break.

ROLE PLAY:

As Station Operator report that the drain nipple right downstream of the common discharge of the pumps has been broken off by some maintenance personnel and they are leaving to go get something to repair it.

If asked how bad the leak is, report that it is coming out under pressure and needs to be isolated.

ROLE PLAY:

As the Building SO wait 2 minutes and report that CM-V 296 and 297 have been closed.

ACTION:

Activate Trigger 16, to close the CM-V 296 and 297 valves.

ROLE PLAY:

As the RX Bldg SO call and report that the leak is slowing down.

Reports annunciator 9-3-1/E-4 RHR Discharge Supply Press Low or 9-3-3/E-2 RHR B Pressure Maintenance Supply pressure low.

Contacts Rx SO to investigate.

Reports lower than normal Hx Pressure.

Reports Annunciator S-1/A-1 Rx Bldg Sump A High High Level.

Reports that Sump A is filling and that both pumps are operating.

CRS Enters EOP 5A and directs all systems be isolated that are leaking into Sec. Cont.

Contacts the building SO to isolate Condensate to the A RHR Loop.

Reports that Ann 9-3-1/E4 is alarming and the pumps should not be used.

Reports that A Sump level is lowering.

Exits EOP 5A

Contacts WCC and Ops Management

Refers to T.S. 3.5.1 to declare A loop RHR inop.

3.5.1 7 Day LCO 3.6.2.3 7 Day LCO T3.6.1 7 Day LCO

Lesson

Title:

CW pump failure, Sustained OG Combustion, Flow Converter Failure, DEH failure/Group 1 isolation, Containment steam leak and ED due to PSP.

Lesson No.:

SKL052-XX-XX Rev. No.:

00 Page 9 of 14 ACTION When the crew has completed actions for RHR Activate Trigger E2:

NM09C APRM C Failure RO

- Announces half scram.

- Announces APRM C is upscale.

- Request to bypass the APRM and reset the 1/2 Scram.

- Directs the APRM be bypassed and the 1/2 scram be reset.

- Addresses Technical Specifications for the failed APRM.

Potential LCO on APRM C.

CAUTION:

Prior to activation of Trigger E4 verify that net MWe is 690 + 1 MWe. If net megawatts are not with in this range then contact the control room as the load dispatcher and direct adjustment of the load to achieve 690 Mwe.

Note to Examiners:

For this failure there is no annunciation prior to the MSL low-pressure alarm and since the other cues are somewhat subtle the crew may not take any action until the MSL low pressure annunciates the failure.

NOTE:

After activation of Trigger E5 monitor RPV pressure and note reactor pressure when the crew scrams the reactor. Record below.

ACTION When the crew has addressed the flow converter failure Activate Trigger E4:

MS08a DEH system pressure transmitter failure BOP May report rising generator net load and the A DEH pressure controller failing high.

RO May report lowering reactor pressure.

Lesson

Title:

CW pump failure, Sustained OG Combustion, Flow Converter Failure, DEH failure/Group 1 isolation, Containment steam leak and ED due to PSP.

Lesson No.:

SKL052-XX-XX Rev. No.:

00 Page 10 of 14 CRS

May direct actions per 2.4DEH

May direct reactor scram if pressure cannot be maintained > 900 psig.

RX Pressure at SCRAM: _____________

RO May scram the reactor when pressure falls to 900 psig.

CRS May direct BOP to place pressure set point in manual.

BOP May attempt to place pressure set in manual, reports that action is unsuccessful CRS May direct BOP to take manual control of BPV and GOV.

BOP May attempt to take manual control of BPV and GOV, reports action unsuccessful.

Note to Examiners: Due to the reduced reactor pressure and the nature of this event the reactor water level is likely to exceed 60" before the operators can respond. This is because reactor pressure may fall below the shutoff head of the condensate booster pumps.

Reports Annunciator 9-5-1 MSL low pressure

Reports Reactor pressure low and lowering CRS Directs the reactor scrammed before pressure is reduced below 785 psig.

Scrams the reactor before pressure falls below 785 psig.

Takes scram actions per 2.1.5

Lesson

Title:

CW pump failure, Sustained OG Combustion, Flow Converter Failure, DEH failure/Group 1 isolation, Containment steam leak and ED due to PSP.

Lesson No.:

SKL052-XX-XX Rev. No.:

00 Page 11 of 14 CRS Directs MSIVs closed before 100°F/hr cooldown rate is exceeded.

BOP/RO Closes the MSIVs before 100°F/hr cooldown rate is exceeded.

ACTION:

After the crew has scrammed the reactor, closed the MSIVs, stabilized reactor water level, and when directed by the lead examiner Activate Trigger E5:

MS02c Main Steam Line Rupture Inside Containment.

CRS/BOP/RO Recognize/Report increasing drywell pressure and/or lowering reactor water level.

CRS Enters EOP 1A and 3A CRS Directs the use of Table 3 systems to maintain level.

RO/BOP Starts/Verifies the start of HPCI and RCIC.

BOP Utilizes condensate system if reactor pressure is less than the CBP shutoff head.

ACTION:

When drywell and torus sprays are in service Activate Trigger E6.

Failure of Spray valve control CRS Directs that torus and drywell sprays be initiated.

Initiates Drywell and Torus sprays.

Reports lowering Drywell Pressure.