Text

Final - Section C Operating
	ML040120862
Person / Time
Site:	Indian Point
Issue date:	12/12/2003
From:	Christman R; Entergy Nuclear Northeast
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	50-286/03-303 50-286/03-303
	Download: ML040120862 (64)
	v • d • e

Appendix D Scenario Outline Form ES-D-1 R,C (CRS,.

C(CRS.RO.Bw)

M,C M(CRS.RO.BW)

C (CRS.ROl RO.BPO)

(CRS.RO)

Facility: Indian Point 3 Scenario No.:

1 Op-Test No.:

I Examiners:

Alan Blamey(Don Jackson)

Operators:

Joe DAntonio Initial Conditions: Plant is at 95% Power, MOL, 31 ABFP is StoD Taaged For Troubleshooting a Ground.

Condensate Pump Trip (AOP)

Loss of Condenser Vacuum (AOP)

Turbine Trip/ Failure of Auto Reactor Trip (ATWS)

Steam Generator Tube Rupture On 32 S/G 32 MSlV Fails TO Close Turnover:

LCO Plant is at 95% Power, MOL, 31 ABFP is stoD tanned and is 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months into its I

I 2

3 4

5 6

I Event TvDe*

Event I DescriDtion I IRO.CRSl I Controllina Pressurizer Level Channel Fails High (AOP) 1 of41 NUREG-I 021, Draft Revision 9

PROGRAM: NRC Initial Licensed Operator Exam COURSE:

SIMULATOR

~~

TOPIC:

SIMULATOR EVALUATION LESSON:

Examination Scenario 1 (NEW)

LESSON NO.: N/A APPROXIMATE TIME FOR EXAM:

75 min.

REVISION:

0 INSTRUCTOR MATERIALS:

1. Lesson Guide

2. Attachment 1, Simulator Exercise Summary

3. Attachment 2, Simulator Documentation Record

4. Attachment 3, Shift Turnover LESSON

REFERENCES:

REMARKS:

SUBMITTED:

DATE:

EXERCISE: NRC Simulator Exam Scenario 1 SCENARIO NRCl Total Malfunctions (5-8/scenario):

Prior to EOP Entry:

1. Pressurizer Level Channel Failure

2. Condensate Pump Trip

3. Loss of Vacuum

4. Turbine Trip/Automatic Reactor Trip Failure After EOP Entry ( 1 -2/scenario):

1. Steam Generator Tube Rupture

2. Fail 32 MSIV Open Abnormal Events (2-4/scenario):

1. Pressurizer Level Channel Failure

2. Condensate Pump Trip

3. Loss of Vacuum Major Transients (1 -2hcenario):

1. ATWS

2. SGTR EOPs enteredrequiring substantive actions (1 -2/scenario):

~~

1. FR-S.l

2. E-3 EOP Contingencies requiring substantive action (0-2hcenario):

1. FR-S.l Scenario run time (45-60 minutes, one scenario may approach 90 minutes):

75 minutes EOP run time (40-70% of run time): 70%

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 1 - SIMULATOR EXERCISE

SUMMARY

1 of2

1.

2.

Perform IC reset Perform Simulator Check List

3.

Initialize Simulator to 95% Power IC.

I

6.

I Main Turbine Trip-Spurious Low Vacuum Comes In Early

4.

5.

Pressurizer Level Controlling Channel Fails High Loss of Condenser Vacuum

7.

Block Automatic Reactor Trip on Main Turbine Trip:

8.

IP2 Sim Eva1 Scenario 1.doc Steam Generator Tube Rupture 32 S/G

9.

Place 3 1 ABFP in PULLOUT and Stop Tag

10.

Fail 32 MSIV OPEN

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 1 - SIMULATOR EXERCISE

SUMMARY

2 of2 EXAMINER ACTIONS FOR SIMULATION INIT CUE Insert At Scenario Initialization Insert At Scenario Initialization Insert At Scenario Initialization Lead Evaluator Direction Lead Evaluator Direction Lead Evaluator Direction Lead Evaluator Direction Entry Into E-0, After FR-S. 1 CONSOLE ENTRY Tagged Out Malf 3 1 By 0, Insert Malf RPS 002A,Insert Malf RPS 002B, Insert SWI-EPS-021D-Off S WI-EPS-027D-Off S WI-EPS-027G-Off SWI-EPS-0.2 1 G-Off Malf-PRS-006B, 1 00,Insert Malf-CF W-005A,3600, Insert Malf -CND-002AY30,Insert Malf-TUR- 00 1,

Insert Malf-ATS 4A, Insert Malf-ATS 4B, Insert Trigger 1 - off of JPP 058,059,060 Malf-SGN 005B,15,Insert LP4(1) - LOA CFW SYMPTOMS / CUES / DESCRIPTION Place 3 1 ABFP in Pullout and Stop Tag Failure of 32 MSIV to Close ATWS Setup Controlling Pressurizer Level Channel (LI-460) Fails High 3 1 Condensate Pump Trip Loss of Condenser Vacuum Turbine Trip/Automatic Reactor Trip Failure/

Both MBFPs Trip At 2000 psig and lowering onATWS SGTR (32 Steam Generator)

IP2 Sim Eva1 Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 1 of22 EVENTEXPECTED OPERATOR RESPONSE:

A

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

11.

13.

PRESSURIZER LEVEL CHANNEL &I-460)

FAILURE Enters ONOP-RPC-1, Instrument Failures Verify the following controls: Turbine Load, Rod Control, PRZR pressure control, PRZR level control-Notices NOT normal, MBFP speed, S/G levels Takes RNO actions Perform:

Places Charging Pump Speed Control in Manual, and Controls pressurizer level Checks RCS Instrumentation-RCS Loop Temps-Normal, delta T set points-Normal, RCS Loop Flow-Normal, Pressurizer Instrumentation-NOT Normal, enters, Pressurizer Level Channel Failures Operates P U R heaters as necessary to maintain PRZR between 2205psig and 226Opsig Ensures Charging Pump speed controller is in MAN, controls P E R level to maintain program level.

Place L/460A, LEVEL DEFEAT switch for the failed instrument to the required position Perform:

Operates Level Defeat Switch In Cabinet B-6, L/460A to the DFT CH I1 Position Transfer Charging Pump speed control back to AUTO per SOP-CVCS-2, Charging Seal Water and Letdown Control Perform:

Transfers charging to AUTO Reset Pressurizer Heaters, Modulating-AUTO, 1 Backup-ON, 2 Backups-AUTO Place PRZR level recorder to an unaffected loop Check redundant bistable lights for failed instrument are extinguished.

Reference Tech Specs for Instrumentation failure-3.3.1 Function 8, Condition H-Place Channel in Trip in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be less than P-7 in 12 Hours Comments:

IP2 Sim Eva1 Scenario l.doc

I EXERCISE: NRC EX^ Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 2 of 22 Lead Evaluator can move to next event once CRS recognizes a Tech Spec needs to be referenced? a follow up question post scenario can examine Tech Spec knowledge, in addition ensure that the chargingpump speed controller is in Auto Comments:

IP2 Sim Eval Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 3 of 22 TIME EVENTEXPECTED OPERATOR RESPONSE:

B

1.

2.

3.

4.

5.

6.

Condensate Pump Trip Perform actions of ONOP-FW-1, Loss of Feed water Check MBFPs-Both Running Checks:

Both MBFPs are running Verify The Following Controls-MBFP Speed Control, SIG Levels Verifies:

MBFP Speed Control-Stable All S/G Levels-Stable Check Conditions Normal For the Following-Both MBFPs Running, Heater Drain Pumps Running, Condensate Pumps Running Checks:

Heater Drain Pump was lost transitions to step #5 Check MBFP Suction Pressure-Check > 35Opsig Performs:

MBFP suction pressure is <35Opsig, verifies start of condensate booster pump, Verify open CD-AOV-52 1 Polisher Bypass, Ensure CD-MOV-522 is fully open, Booster Pump Discharge Refer to Attachment 1 to determine load reduction required to maintain plant operation-9OOMwe Performs:

Determines that a power reduction is required to approximately 900 Mwe, limited by MBFP suction pressure.

May Reference TS 3.4.1 DNB due to down power, if pressure goes <2205psig-Applies if <5%/ min or 4 0 %

step change in power and pressure a 2 0 5 psig-Action restore in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SM X

X X

X RO -

X X

Comments:

IP2 Sim Eva1 Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRCl ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 4 of 22 EVENT/EXPECTED OPERATOR RESPONSE:

7.

8.

9.

Reduce unit load in 100 Mwe increments to obtain-MBFP suction pressure > 35Opsig, Steam and feed flow matched, LI-1127, HDT Level GO in.

Performs:

Commences Load Reduction Crew may Borate rods out per SOP-CVCS-003. In addition they will perform a flush of the line after the boration Performs:

Determine amount of Boron required from Reactivity Summary Sheet, Set YIC-110 for required Boron mount, Set FCV-1 1OA to desired flow rate, Ensure BA X-fer pump is set to slow and Auto, Place RCS Makeup Mode Selector to Borate, Place RCS Makeup Control switch to Start, Flush with 20 gal of Water, Ensure BA X-fer pump in slow and Auto, Ensure 1 Primary Water Pump is running, Ensure non-running Pri Water Pp is in Trip-Pullout, Set FCV-1 1OA to Manual, Set FCV-1 1 1A to Manual, Set FCV 11 1A to 20 Gal and set rate, Place RCS M/U Mode Switch to Manual, Place RCS Makeup Control switch to Start, When Complete-Place M/U control to Stop, Return System to Auto with FCV-110A and 11 1A set to proper blend.

Determine cause of pump trip and initiate repair Commence Loss of Condenser Vacuum At The Examiners Cue, As Power Is Being Stabilized X

X X

X Comments:

IP2 Sim Eva1 Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 5 of 22 EVENTEXPECTED OPERATOR RESPONSE:

C

1.

2.

3.

4.

5.

Comments:

LOSS OF CONDENSERVACUUM Performs actions of ONOP-C-1, Loss of Condenser Vacuum Monitor Turbine to determine if it should remain on-line:

Condenser Vacuum>25.5, Pressure Differential Between Condensers < 3Hg., Turbine Exhaust Hood remains< 250 degrees F except for 1 time not to exceed 15 min.

Checks:

Determines Not Applicable Stop any turbine accelerations or load increases Checks:

No load change is in progress Verify Circulating Water Pumps are operating properly Checks:

All Circ Water Pumps are in operation Direct the NPO to check the following:

0 Verify SJAEs are operating properly 0

Verify both MS-PCV-1132 and MS-PCV-1222 are operating properly Verify that the Gland Seal exhauster loop seal is intact 0

Verify that there is adequate water box vacuum 0

Verify that CD-FCV-1120 and CD-FCV-1113 are operating properly Checks:

All above parameters are reported back as normal X

X X

IP2 Sim Eva1 Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRCl ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 6 of 22 HME EVENT/EXPECTED OPERATOR RESPONSE:

6.

7.

8.

Comments:

Place Priming Jet Hoggers In Service IAW Att 1 Performs:

Assigns NPO This Step Places Priming Jet Hoggers In Service IAW Att 1 Direct an NPO to verify that:

0 0

Verifies:

All items are normal except the Condenser Flange Seal Water Head Tank is empty Performs:

Opens CT-139 Commence Turbine Load Reduction to maintain condenser vacuum Performs:

Crew commences a load reduction HD-LCV-1133 is controlling level in the Gland Steam Condenser Drain Tanks MS-PCV-1211 and MS-PCV-1212 are maintaining Gland Sealing Steam Pressure > 3psig Condenser Flange Seal Water Head Tank level is normal Main Steam is the supply of steam to the hoggers and GS Steam Services are normal to the MBFPs Insert Turbine Trip After an Observable Load Reduction or 10 Minutes Into Loss of Vacuum Trip of Both MBFPs At RCS Pressure 2OOOpsig and Lowering AfterATWS. In Addition Fail The Main Condenser Fullv as the MBFPs Trip X

X X

X IP2 Sim Eva1 Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRCl ATIACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 7 of 22 HME EVENTEXPECTED OPERATOR RESPONSE:

D

1.

2.

3.

4.

Comments:

TURBINE TRIPI ATWS The RO / CRS recognizes a Reactor Trip Condition (Turbine Trip > P-8) and Initiates a Manual Reactor Trip Crew Recognizes and Takes Actions For A Failure of Automatic and Manual Reactor Trip (CT#l)

The Reactor Fails to Trip Enters E-0, Reactor Trip or Safety Injection Performs:

Attempts to manually trip the reactor De-energizes 480V Buses 2A and 6A then re-energizes the bus after 5 seconds Trips the Turbine Enters FR-S. 1, Response to Nuclear Power Generation/

ATWS Attempt Manual Reactor Trip Insert Control Rods In Auto or Manual Dispatches an NPO to Locally Trip the reactor via operator aid Performs:

Attempts Manual Reactor Trip Inserts Control Rods In Auto or Manual Dispatches an NPO to Locally Trip the reactor via operator aid Verify the Turbine is Tripped Verifies:

Main Turbine Stop Valves are Closed, the turbine is Tripped X

X X

X IP2 Sim Eva1 Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRCl ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 8 of22 EVENTEXPECTED OPERATOR RESPONSE:

5.

6.

7.

8.

9.

Comments:

Check Auxiliary Feed is Running Checks:

Both motor driven ABFPs are running AFW total flow is > 730 gpm Initiate Emergency Boration of the RCS Performs:

0 0

Open CH-MOV-333 0

0 0

0 Checks any Charging pump running Close HCV 104 and 105 Start both boric acid pumps in fast speed Place operating charging pump in manual and raises speed Checks pressurizer pressure < 2235 psig Insert Local Reactor Trip Check if SI is Required or Initiated Checks:

SI is not initiated or required Transitions to Step 15, Verify the Reactor is Subcritical 0 Poweris<5%

0 0

Checks:

Reactor is Subcritical SUR is 0 or Negative on IR Channels All rods are inserted to < 20 steps Secure Emergency Boration 0

Verify CH-MOV-333 is Open 0

Close CH-MOV-333 0

0 Open HCV-104 and 105 Place both Boric Acid Pumps in Slow Performs:

All above Actions X

X X

X IP2 Sim Eva1 Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 9 of 22 RO X

X TIME BO1 X

EVENTEXPECTED OPERATOR RESPONSE:

10.

11.

12.

Comments:

Verify RCP Seal Cooling Verifies:

Seal Cooling Is Available Seal Injection and Thermal Barrier Cooling In Service Check Charging Pump Status Verifies:

0 CCW Cooling available Charging Pump In Service 0

Maintain Seal Injection 6-12 gpm Verify Adequate Shutdown Margin Verifies:

All control rods 20 steps Direct Chemist to Sample RCS for Boron Verify Boron Concentration is adequate Insert SGTR Upon Transfer to E-0 IP2 Sim Eva1 Scenario 1.doc

~~ I EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 10 of 22 EVENTEXPECTED OPERATOR RESPONSE:

E

1.

2.

3.

STEAM GENERATOR TUBE RUPTURE Booth Operator: Insert 15% SGTR on 32 Steam Generator NO RAMP E-0, REACTOR TRIP OR SAFETY INJECTION Veri@ Reactor Trip Checks:

Reactor Trip Breakers - OPEN Neutron Flux - DECREASING Rod Bottom Lights - LIT Rod Position Indicators -AT ZERO Performs:

MANUAL Reactor Trip is performed if not previously accomplished.

Verify Turbine Trip Checks:

Turbine Stop valves - CLOSED Turbine Control valves - CLOSED Verify that all 480V Buses are energized by Offsite Power Checks:

Bus Status X

X X -

7 X

X -

Comments:

IP2 Sim Eva1 Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1

' A'ITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 11 of22 TIME EVENTEXPECTED OPERATOR RESPONSE:

Check if SI is actuated Checks:

SI annunciator - LIT SI System pumps - RUNNING Perform:

SI is Manually initiated if not already in service based on lowering pressurizer level, and pressure.

Verify total AFW flow is greater than 365gpm, and controls feed flow to maintain S/G NR levels between 9% and 50%

Perform:

Notes 3 1 ABFP is tagged BOP Operator performs RO-1 (BOP EOP Actions)

Verify Feedwater Isolation-Both MBFPs-Tripped, MBFP Discharge Valves-Closed, Main and Bypass FRVs-Closed, S/G Blowdown Isolation Valves-Closed Veri@ SI Flow-Verifies RCS Pressure <165Opsig, Checks for HHSI pump flow Verifies :

Verifies SI flow adequate for pressure Verify Containment Spray is not required Checks:

Verifies Containment Pressure is G2psig Check RCP Seal Cooling Checks:

Checks RCP Bearing Flow Low Alarm, and Thermal Barrier Low Flow Alarm-Alarms are Clear X

X X

Comments:

IP2 Sim Eval Scenario 1.doc

I EXERCISE: NRC EX^ Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 12 of 22 EVENT/EXPECTED OPERATOR RESPONSE:

Establish Charging flow Perform: Checks RCS Pressure >325psig, verifies CCW cooling for Charging Pump, Checks HCV-142 Fully Open, CH-AOV-204B-Open, Opens CH-LCV-112B7 and Closes CH-LCV-l12C, Does Not Start Chg Pp Since CCW Is Available Check RCS Tave Checks: Verifies RCS Tave is stable at or trending to 547 degrees F, ensure S/G Atmospheric Reliefs are controlling Tave Check if RCPs Should Be Stopped Checks: Determines RCPs should not be stopped at this time Check PRZR PORVs, Safety Valves, and Spray Valves Checks: Determines all are closed and functioning properly, Tailpipe Temperatures Are Elevated Since PORVs Lifted During The ATWS. Acoustic Monitors Indicate PORVs and Safeties are Closed Determine if S/Gs are Faulted:

Checks: No Fault is Indicated Determine if S/G Tubes are Ruptured Perform: Recognizes S/G Level response is not correct for 32 S/G-Transitions to E-3 Steam Generator Tube Rupture, in addition R62B MSL Rad Monitor is 5x Normal X

X X

Comments:

IP2 Sim Eval Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRCl AITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 13 of 22 TIMI EVENTEXPECTED OPERATOR RESPONSE:

1.

2.

3.

4.

5.

6.

E-3, STEAM GENERATOR TUBE RUPTURE Obtain correct procedure-E-3, Steam Generator Tube Rupture Check if RCPs Should be Stopped Checks:

SI pumps running RCS Subcooling <32F (73F)

Determines RCPs do not need to be stopped INSTRUCTOR NOTE: This is a continuous action step Identify Ruptured SG(s)

Checks:

Unexpected rise in any SG narrow range level High radiation from any SG sample High radiation on and S/G Steamline Adjust ruptured SG Atmospheric steam dump controller maintain 1040 psig Perform: Controller is adjusted so ADV lifts at 1040 psig by selecting Manual and turning dial to raise the setpoint.

Check ruptured SG atmospheric steam dump valve -

CLOSED Checks:

SG Atmos verified closed Check that 32 and 33 S/Gs are intact Performs:

Closes MS-41 X

X X

X Comments:

IP2 Sim Eva1 Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 14 of 22 rIME EVENTEXPECTED OPERATOR RESPONSE:

X Verify blowdown is isolated from 32 S/G Checks: Verifies S/G blowdown isolation

7.

8.

9.

10.

11.

X Dispatch NPO to locally isolate ruptured S/G Performs: CRS dispatches NPO to complete the step X

X Ensure ruptured S/G steam line valves are closed Performs: Shuts 31,33,and 34 MSIVs and MSIV Bypass valves, Completes Attl, Alternate S/G Isolation Method, Uses intact S/G atmospheric dump valves to dump steam.

X X

Check ruptured S/G is isolated from at least one intact S/G Checks: There is at least 1 S/G isolated from the ruptured S/G Check Ruptured SG(s) Level Checks:

Narrow range level >9% (14%)

X X

Performs:

Stops feed flow to 32 SG when NR level >9% (26%)

IDENTIFYAND ISOLATEA RUPTURED STEAM GENERATOR (CT #2)

Check PRZR PORVs and Block Valves

12.

Checks:

Power available to block valves PORVs CLOSED Block Valves - OPEN INSTRUCTOR NOTE: This is a continuous action step Comments:

IP2 Sim Eval Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATI'ACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 15 of 22 P

I-EVENTEXPECTED OPERATOR RESPONSE:

13.

Comments:

Check if any SG is Faulted Checks:

Any SG pressure decreasing in an uncontrolled manner or completely depressurized, No Steam Generator is faulted X

IP2 Sim Eva1 Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRCl ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 16 of 22 EVENT/EXPECTED OPERATOR RESPONSE:

14.

15.

16.

17.

Comments:

Check Intact SG Levels Checks:

Narrow Range SG level >9% (26%) or responding normally in all intact S/Gs Performs:

Controls feed flow to maintain intact S/Gs between 9%

(26%) and 50%

INSTRUCTOR NOTE: This is a continuous action step Reset SI Check Steps 2-12 of RO-1 (BOP Actions) are complete Perform:

Press both SI reset buttons on panel SBF-2 Check:

SI Actuated Light Off Reset Containment Isolation Phase A and B Perform:

Place switches in close for 200A, 200B, 200C Press Phase A Reset Buttons Press Phase B Reset Buttons Establish Instrument Air to Containment Checks:

Inst Air Low Press alarm clear on panel SJF Perform:

Depress Inst Air reset button 28 on SMF Open IA-PCV-1228 3T,!

X X

IP2 Sim Eva1 Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 17 of 22 TIME EVENTDZXPECTED OPERATOR RESPONSE:

18.

19.

20.

21.

22.

23.

24.

Determine if RHR Pumps Should be stopped Perform:

Stops Both RHR Pumps Check Ruptured Steam Generator Pressure is greater than 4OOpsig Check:

Ruptured S/G Pressure will be greater than 4OOpsig Initiate RCS Cool down to the RCS temperature based table in step 13 Perform:

Fully opens 3 1,33, and 34 S/G Atmospherics Stops cool down at the required temperature and maintains CETs less than the required temperature from step 13 Check RCP Seal Cooling Established Checks:

Checks Thermal Barrier Cooling and Seal Injection in Operation Establish Charging Flow Performs:

Chg Pump cooling available Checks Open HCV-142 Opens CH-AOV-204B Open CH-LCV-112B Checks any Charging Pump Running Adjusts Charging Pump Speed To Maximum Check Ruptured S/G Pressure stable or rising Checks:

Ruptured S/G Pressure should be rising or at least 250 psig greater than S/G pressure Verifi Subcoolin; > 60 degrees F X

X X

Comments:

IP2 Sim Eva1 Scenario 1.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRCl ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 18 of 22 IrIME EVENT/EXPECTED OPERATOR RESPONSE:

25.

Depressurize RCS Using Pressurizer Spray Performs:

Increases P U R Spray to maximum in manual Stop Depressurization When:

RCS Pressure is less than S/G Pressure and PRZR level is Or P E R level > 75%

Or RCS Subcooling requirement is met 14%

Cooldown and Depressurize RCS to minimize flow out of SGTR (CT #3)

Terminate Scenario when Depressurization completed.

X X

Brief BOP Surrogate To Control 32 S/G Level at 30% During SGTR Such That AFW Control Valves Are Closed and Informs The CRS That The AFW Control Valves are Closed.

Comments:

IP2 Sim Eva1 Scenario l.doc

EXERCISE: NRC Exam Scenario 1 SCENARIO NRC1 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 19 of 22 Comments:

IP2 Sim Eva1 Scenario 1.doc

EXERCISE: NRC Examination Scenario #1 A'ITACHMENT 3 - SCENARIO OBJECTIVES SCENARIO NRCl 1of1 IP2 Sim Eva1 Scenario l.doc

A'ITACHMENT 3, SHIFT TURNOVER 1 of1 Watch Crew Turnover Sheet:

Datemime:

RCS Temp:

RCS Press:

PZR Level:

RCS Total Leakage:

RCS Unidentified Leakage:

Xenon:

EFPD:

PZR Press Control:

PZR Level Control:

Service Water:

TODAY 566.7"F 2235 psig 45.7%

0.2 gpm 0.2 gpm Equilibrium 150 PI-455-Ch I LI-460- Ch I1 1,2,3 ESW Headers Condition:

YO Power:

MW Gross:

River Water:

Boron Conc:

Rod Position:

Power Ops 95%

950 65 degrees F 1 180 ppm Bank D 21 1 Steps Plant Equipment Status:

1.

2.

3.

3 1 ABFP Stop Tagged for ground investigation.ITS LCO 3.7.5 Condition B in effect for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months of 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO.

MOV-535 is closed due to leakage past the PORV.

Power Reduced To 95% Due To Grid Instabilities.

IP2 Sim Eva1 Scenario l.doc

Amendix D Scenario Outline Form ES-D-I Event No.

1 Facility: Indian Point 3 Scenario No.:

2 Op-Test No.:

1 II Malf.

Event Event No.

Type*

Description R (CRSRO.BPO1 Continue Startup-Raise Power To 7%

Examiners:

Alan Blamev (Don Jackson)

Operators:

Joe DAntonio

/I 2

3 4

5 6

7 I (CRS.RO,)

Controlling Pressurizer Pressure Channel Fails High (AOP)

C (CRS.RO.BPOI LOSS Of 5A-480 VOk BUS (AOP)

C lCRS.RO1 C(CRS.RO1 M(cRs.Ro.spo)

Small Break LOCA C (CRS.RO1 34 RCP High Vibration (AOP) 34 RCP Seal Leak and Failure (AOP) 32 HHSl Pp Fails To Start

PROGRAM: NRC Initial Licensed Operator Exam COURSE:

SIMULATOR TOPIC:

SIMULATOR EVALUATION LESSON:

Examination Scenario 2 LESSON NO.: N/A APPROXIMATE TIME FOR EXAM:

75 min.

REVISION:

0 INSTRUCTOR MATERIALS:

1. Lesson Guide

2. Attachment 1, Simulator Exercise Summary

3. Attachment 2, Simulator Documentation Record

4. Attachment 3, Shift Turnover REMARKS:

SUBMITTED:

DATE:

1 EXERCISE: NRC Simulator EX=

scenario 2 SCENARIO: NRC2 I

Total Malhctions (5-8/scenario):

Prior to EOP Entry:

1. Controlling Pressurizer Pressure Channel Fails High

2. Loss of 5A 480 Volt Bus

3. 34 RCP High Vibration.

4. 34 RCP Seal Failure/ Small Break LOCA 1 After EOP Entry (1 -2/scenario):

1. 32 HHSI Pump Fails To Start Abnormal Events (2-4/scenario):

1. Controlling Pressurizer Pressure Channel Fails High

2. Loss of 5A 480 Volt Bus

3. High Vibration 34 RCP

4. 34 RCP Seal Failure Mai or Transients ( 1 -2/scenario):

1. Small Break LOCA EOPs enteredrequiring substantive actions (1 -2/scenario):

1. E-1 EOP Contingencies requiring substantive action (0-Yscenario):

N/A Scenario run time (45-60 minutes, one scenario may approach 90 minutes):

75 minutes EOP run time (40-70% of run time):

70%

EXERCISE: NRC Exam Scenario #2 SCENARIO: NRC 2 A'ITACHMENT 1 - SIMULATOR EXERCISE

SUMMARY

1.

2.

3.

4.

5.

1of1 Perform IC reset Perform Simulator Check List Sim Setup - 2% BOL-MBFP In Service Additional RCS Leakage In Conjunction With RCP Seal Failure Block Auto Start of 32 HHSI Pump I SIMULATOR SET-UP SYMPTOMS / CUES / DESCRIPTION I

TIMELINE AND EXAMINER ACTIONS FOR SIMULATION EVENT A

B C

D E

F INIT CUE Scenario Initialization Examiner Directed Examiner Directed Examiner Directed Examiner Directed Examiner Directed CONSOLE ENTRY Malf-SIS 004B, 1, Insert Malf-PRS 005A, 2500,100, Insert Malf-EPS 005C, Insert Malf-RCS 007D, 1 1, Insert Malf-RCS 0 12D, 1 00, Insert Malf-RCS 013D,l00, Insert Malf-RCS 014D,100, Insert Malf-RCS 005D, 15, Insert Block 32 HHSI Pump Auto Start Pressurizer Pressure Master Controller fails high.

Loss of 5A 480 Volt Bus 34 RCP High Vibration.

34 RCP Seal Failure (#1)

Small Break LOCA-Fail #1 Seal Until Seal Leak Off is Isolated, then Fail #2 and #3 Seals. In addition add 300 gpm addition to SBLOCA IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 SCENARIO: NRC2 AITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD rIME EVENTIEXPECTED OPERATOR RESPONSE:

1.

2.

A

1.

2.

3.

Normal Power Rise From 2% To 7% Power Pre-brief conducted and order given to raise power to 7%

using control rod withdrawal Withdraw control rods to raise reactor power to 7%

Performs:

Withdraws control rods in 3 step increments Monitors:

Rod position, Tave, Steam Dump Position, Feedwater Flow Insert Next Event AfterAn Observable Power Change and Before 5% Power Controlling Pressurizer Pressure Channel (PI-455) Fails High Perform actions of ONOP-RPC-1, Instrument Failures Verify the following controls: Turbine Load-Stable, Rod Control Stable, PRZR Pressure Control-Normal, PRZR Level Control-Normal, MBFP Speed-Normal, S/G Levels-Normal Performs:

Place Master Pressure Controller (PC-455K)in Manual By Placing Toggle On Controller To Manual Position, and Rotating Dial On Controller To Close Spray Valves.

Control to restore pressure to 2235 psig.

Check RCS Instrumentation: RCS Loop temperatures, RCS delta T set points, RCS coolant loop flow.

Checks:

All parameters are normal Enters Technical Specification 3.4.1 for DNB Parameters, due to Pressure < 2205psig-Action: Restore RCS Pressure> 2205 psig in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

X -

X X

X IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 SCENARIO: NRC 2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD Check P E R instrumentation: PRZR Levels, P E R Pressures Checks:

PRZR Levels and Pressures, and determines that the controlling pressurizer pressure channel (PI-455) has failed high - Proceeds to Attachment 7 ONOP-RET-1, Instrument Failures Ensure that the master pressure controller is in Manual and Control to maintain 2235 psig Perform:

If master pressure controller is not already in Manual, it is placed in manual and pressure is controlled at 2235 psig Place P/455A,Press Defeat switch for the failed instrument to the required position Performs:

Places P/455A to the DFT Ch IAV position in Rack B-6 Place delta T Defeat switch for the failed instrument to the required position Performs:

Places delta T Defeat (3T/411A) switch to the DFT Ch I in Rack B-8 If steam dumps are armed, then reset the steam dumps and place in temp control.

Checks:

Steam dumps should not be armed, may request fiom Shift Manager to N/A the step.

X X

X IP2 Sim Eval Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 SCENARIO: NRC 2 AITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD rIME EVENTEXPECTED OPERATOR RESPONSE:

9.

1c 11 1;

Place PC-455K, P U R pressure Controller in Auto per SOP-RCS-2, Pressurizer Pressure Control CUE: Step Requires Placing Variable Heater Control In Auto In Ruck B-6, Control Does Not Exist In the Simulator-Cue That The Switch Is In Automatic Performs:

Places PC-455K in Automatic If the failed instrument was selected to a Pressure or delta T recorder, select a functioning channel Performs:

Selects recorders to hctioning channels Examiner Note-May Proceed With Next Malfunction Any Time After PRZR Pressure Controller Placed In Auto Ensure compliance with:

Technical Specification 3.3.1 Function 7a and 7b,

Conditions E and H (Pressurizer High and Low Pressure Trips)- Action: Place Channel in Trip in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , or be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Technical Specification 3.3.2 Function Id, Condition D (Low Pressure SI )- Action: Place Channel in Trip in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , Mode 4 in 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

Technical Specification 3.3.1 Function5 Condition E (OT delta T ) Trip OT delta T Bistables in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Technical Specification 3.3.2 Function 7 (SI block permissive), Condition k, Verify Interlock in proper state in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Perform As A Follow Up Question IP2 Sim Eva1 Scenario 2.doc

Examination Scenario #2 SCENARIO: NRC 2 ATIACHMENT 2 - SIMULATOR DOCUMENTATION RECORD EVENTEXPECTED OPERATOR RESPONSE:

rIME Loss of 5A 480 Volt Bus B

1.

2.

3.

Performs actions of ONOP-EL-7, Loss of a 480 Volt Bus -

Above Cold Shutdown Check RCP Seal Cooling-Check if a Charging Pump is running, if not start a Charging Pump Verifies:

3 1 Charging Pump is Lost Performs:

Starts 32 Charging Pump, Maintains seal injection at 6-12 gpm, by raising Charging Flow on SC-141B Check Service Water Headers >60 psig-Checks Essential and Non-Essential headers and starts SW pumps as needed Verifies:

Adequate SW pressure and starts an extra SW pump if pressure is in alarm Check Circulating Water Pump Status-Checks that all CW Pumps are running Checks:

Circulating Water is unaffected, May ask shift manager to not take action to start other Circ Water pumps since only 3 are needed.

Check that the in service boric acid pump is running Checks:

In service boric acid pump is running, unaffected.

Check EDG Status-Checks 33 EDG status Checks:

33 EDG is running unloaded Check ABFP Status-Checks if any ABFP is running, maintains S/G level if necessary Checks:

ABFPs are secured Checks any waste release in progress-Performs:

No release is in progress, no action is needed fay Get CCWSurge Tank Leve1Alarm Due To Pump X

X X

4.

5.

6.

7.

Ivote-X X

X X

X -

Change IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 SCENARIO: NRC2 A-TrACHMENT 2 - SIMULATOR DOCUMENTATION RECORD STt EVENTEXPECTED OPERATOR RESPONSE:

TIME Checks Service Water Header Pressure between 60 psig and 97.5 psig in the essential and non-essential headers.

Checks:

SW header pressure is recovered since previous step.

Check Component Cooling Water Status-Check for system alarms, check 3 CCW Pumps running, Verify RCP thermal barrier flow established.

Performs:

31 CCW pump will be lost, a 32 and 33 pumps will be running, need to verify thermal barrier cooling.

Verify Seal Injection flow 6-12 gpm Verifies:

Seal Injection Flow is unaffected Check IA Header Pressure > 90 psig Checks:

LA Header pressure is unaffected Cue: May need a cue that an acrid smell is in the area of the 5A bus.

Check 480 Volt Bus 5A De-energized Checks:

5A 480 Volt Bus is dead Determine 33 EDG Status-Performs:

Sends an operator to locally shutdown 33 EDG, Will Get Safeguards Equip Locked Open Annunciator Refer to Tech Specs-3.8.1 Verifies:

Shutdown is required Inspect 33 EDG for problem and Repair 5A 480 Volt Bus Performs:

Initiates actions to repair bus Ensure compliance with Technical Specification 3.8.9 A-Action: Restore in 8 Hours to meet LCO Action, or Mode 3 in 6 Hours, and Mode 5 in 36 Hours Examiner Note: Begin next event as Technical Specifications are being referenced.

8.

9.

10.

11.

12.

13.

14.

15.

X X

X -

X X

X X -

X X

IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 SCENARIO: NRC2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD I

I EVENTEXPECTED OPERATOR RESPONSE:

C

1.

2.

34 RCP High Vibration.

Determine Vibration amplitude and trend, Enter ONOP-RCSS, Reactor Coolant Pump Malfunctions Perform:

Implements ONOP-RCS-5 Determine if the affected RCP should be shutdown: Check RCP Seal DIP 0

Check RCP Seal Return 0

0 0 Check RCP Seal Cooling 0

Check RCP Vibrations 0

0 0

Check CCW supplies Check RCP Seal Inlet Temperature Check RCP Seal Outlet Temperature Check RCP Motor Winding Temperature Check RCP Upper and Lower motor bearing temperatures Checks:

Determines 34 RCP Vibrations are in Alert, but does not meet trip criteria.

Begin #I Seal Failure After Check of RCP Shutdown Triggers X

X X

X IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 SCENARIO: NRC2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD SM rIME STi EVENTEXPECTED OPERATOR RESPONSE:

RO X

X X

x x

D

1.

2.

3.

BO x

x

4.

5.

34 RCP #1 Seal Leak Response to indications of RCP seal leakage.

Check RCP Seal Return Flow < 6gpm Performs:

Recognizes Seal Return Flow is Failed High and delta P Failed Low, begins RNO Actions as described in the following steps Veri@ 34 RCP Seal Inlet Temperature is <225 degrees F and Stable, and 34 RCP Seal Outlet Temperature is <235 degrees F and Stable.

Performs:

Recognizes 34 RCP Seal Temperature Parameters are rising, performs RCP Emergency Shutdown as described below.

Perform a Manual Reactor Trip and Stop 34 RCP Performs:

Manually trips reactor, and Stops 34 RCP Close RCP Seal Return Valve-CH-AOV-26 1 D Performs:

Closes CH-AOV-261D, 34 RCP Seal Return Valve aper lfi 4 actions of E-0.

Continue with E-0, Reactor Trip or Safety Injection.

E X

X X

IP2 Sim Eval Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 SCENARIO: NRC 2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD TIME EVENTEXPECTED OPERATOR RESPONSE:

E

1.

2.

3.

4.

Small Break LOCA Perform actions for E-0, Reactor Trip or Safety Injection Verify Reactor Trip Checks:

Reactor Trip Breakers - OPEN Neutron Flux - DECREASING Rod Bottom Lights - LIT Rod Position Indicators - < 20 Steps Verify Turbine Trip Checks:

Turbine Stop valves - CLOSED Veri9 480V AC Buses-All Energized By Offsite Power Checks:

All 480V AC Buses Energized By Offsite Power-Bus 5A has a fault, should sent an NPO or FSS to investigate fault.

Determine If SI Is Actuated Checks:

Any SI Annunciator Lit or SI Pumps Running, At this time SI should be running, or it will be manually initiated if it is not running via RNO.

RCP Emergency Shutdown and Isolation of RCP Seal Return. (CT-I)

Cue: Have Surrogate Go Slow In RO-1 So RO Will Start 32 HHSI Pump.

Insert #2 and #3 RCPSeal Failures when Seal Return Isolated, and Insert 300 GPMSBLOCA X

X X

X IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 SCENARIO: NRC2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD CR - R( BO EVENTEXPECTED OPERATOR RESPONSE:

TIME Verify total AFW flow-Greater than 365 GPM Checks:

AFW flow is >365GPM Performs:

Controls AFW Flow to raise S/G level to 9% (14%)- 50%.

Manually starts 31 and 33 ABFPs

5.

6.

7.

8.

9.

10.

Direct BOP Operator to Perform RO BOP Actions During EOP Usage Performs:

BOP Performs RO-1 X

X Verify Feedwater Isolation-Check MBFPs tripped, and MBFP discharge valves are closed, Main and Bypass FRVs closed, S/G Blowdown and Sampling is isolated Verifies:

Verifies Feedwater is Isolated-Some indications out, due to loss of Bus 5A.

Performs:

Must manually shut MOV-2-3 1 locally, still open due to loss of power.

Verify SI Flow-RCS Pressure 4 6 5 0 psig (2OOOpsig),

HHSI Flow indicated, RCS Pressure <325 psig (650 psig)

Verifies:

Pressure is 4 6 5 0 psig, but not <325 psig. HHSI flow is verified. Recognizes 32 HHSI Pump failed to start and successfully manually starts it.

X X

Take Actions For FaiIure Of Automatic SI Equipment -

Note-May Be Noticed In RO-I (CT# 2)

Verify Containment Spray is not required-Check that Containment Pressure has remained < 22 psig Verifies:

Containment Spray is not required X

IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 SCENARIO: NRC2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD TIME EVENTEXPECTED OPERATOR RESPONSE:

11.

12.

13.

14.

15.

16.

Check RCP Seal Cooling-Verify CCW flow to RCP thermal barrier, and RCP bearings by verifying alarms are clear for RCP cooling.

Verifies:

RCP Cooling alarms are clear Check RCS Average Temperature-Verify RCS Tave is stable at or trending to 547 degrees F Verifies:

RCS Tave is lowering Performs:

Stops Dumping Steam-Ensures PC-404 Is Controlling Steam Dumps Closed, Throttles AFW to minimum to restore S/G level via FCV-406 A,B,C,D, Closes MSIVs Checks if RCPs should be stopped-Verify at least one HHSI pump is running, Verify Subcooling <32 degrees F (75 degrees F), Stop all RCPs Performs:

Verifies conditions are met and stops all RCPs TRIP RCP OPERATION DURING EMERGENCYAND ABNORMAL CONDITIONS (CT#3)

Check Przr PORVs, Safety Valves, and Spray Valves-Checks Przr PORVs closed, Check Safety Valves Closed, Check Przr Spray Valves are Closed.

Checks:

Checks Przr PORVs, Safety, and Spray Valves Closed Determine if S/Gs are Faulted-Any S/G Pressure lowering in an uncontrolled manner or completely depressurized Checks:

S/G is currently not faulted X

X X

X R(3 X

X X

X IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 SCENARIO: NRC 2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD STA I

J CRh X

X TIME EVENT/EXPECTED OPERATOR RESPONSE:

I4

17.

18.

Determine if S/G Tubes are ruptured.- Checks S/G Level response, and abnormal radiation levels Checks:

Determines a S/G Tube Rupture does not exist verifies R-15,R-19 A-D, and R-62 A-D not in alarm or rising Determine if the RCS is intact-Containment Pressure, RCS Pressure, Sump, and Radiation Levels are normal Performs:

Determines RCS is not intact, and Transfers to E-1, Loss of Reactor or Secondary Coolant X

X IP2 Sim Eva1 Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 SCENARIO: NRC2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD TIME EVENTEXPECTED OPERATOR RESPONSE:

F

1.

2.

3.

4.

Perform actions of E-1, LOSS OF REACTOR OR SECONDARY COOLANT Check if RCPs Should Be Stopped Checks:

HHSI pumps running RCS Subcooling Note: This step may be performed during E-0 while monitoring Foldout Page criteria. However, the critical task is met if performed at this step.

TRIP RCP OPERATION DURING EMERGENCYAND ABNORMAL CONDITIONS (CT#3)

Determine if S/Gs are faulted-Checks any S/G Pressure lowering in an uncontrolled manner or completely depressurized.

Checks:

Any SG pressure decreasing in an uncontrolled manner or completely depressurized has been previously isolated Check Intact SG Levels Checks:

Narrow Range SG level 9% (1 4%)- 50%

Performs:

Controls aux feed flow to maintain between 9% (14%) and 5 0%

Reset SI-Check SI Auto action verification-Steps 2-12 of RO-1, BOP Operator Actions During Use of E0Ps-Completed Checks:

RO-1 Steps 2-12 Completed by BOP Performs:

Presses Train 1 and 2 SI Reset Buttons, Checks that SI Actuated Light is Off CR X

X X

X IP2 Sim Eval Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 SCENARIO: NRC2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD HME EVENTmXPECTED OPERATOR RESPONSE:

5.

6.

7.

8.

9.

Reset Containment Isolation Phase A and Phase B-Closes L/D Orifice Isolation Valves, Resets Phase A, and Phase B Performs:

Resets Phase A Using Reset Pushbuttons Resets Phase B Using Reset Pushbuttons Check Secondary Radiation-0 0

0 Reset S/G Sample valves 0

Checks:

Checks indications above and determines a S/G Tube Check if a Seismic Event has occurred Sample all S/Gs for activity Conduct radiation survey on Steamlines and B/D sample lines Check radiation monitors and S/G Levels for indications of a S/G Tube Rupture Rupture is not in progress.

Check Przr PORVs and Block Valves-Check Power Available To Block Valves, Check PORVs Closed, Check PORV Block Valves Open.

Checks:

Performs above checks, PORVs and Blocks in proper position and available. PORV Blockvalve 536 is not energized due to active leakage in the plant modeled on the simulator.

Establish Instnunent Air To Containment-Verify IA Low Pressure Alarm Is Clear, Press Reset Instr Air Reset Pushbutton on Panel SMF, Open IA-PCV-1225, Inst Air To Cont Performs:

Reset Inst Air and Open IA-PCV-1225 Check RCP Seal Cooling-Verify Seal Injection and Thermal Barrier Cooling in Service Verifies:

Seal Injection and Thermal Barrier Cooling in Service X

X X

X IP2 Sim Eval Scenario 2.doc

EXERCISE: NRC Examination Scenario #2 SCENARIO: NRC 2 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD EVENT/EXPECTED OPERATOR RESPONSE:

Check CCW for Charging Pump Cooling Available-Checks:

CCW Cooling is Available to Charging Pumps Determine if Charging Flow has been established-Checks either Charging Pump Suction Open, Checks Normal Charging Isolation Valve Open, Check HCV-142 Fully Open, Check ANY Charging Pump Open.

Performs:

Starts 32 Charging Pump, Opens 112B, Locally closes 112C due to power being lost.

Determine if SI Should Be Terminated-Check RCS Subcooling, Heat Sink, RCS Pressure, Pressurizer Level Checks:

Either Subcooling, RCS Pressure, or Pressurizer Level will not be met, such that SI can not be terminated. With Scenario Conditions, Subcooling Will Probably Not Be Met.

Determine if the Containment Spray Pump Should be Stopped-Check if any Spray Pump s running.

Checks:

No Spray Pump should be running, RNO sends to next step.

Determine if RHR Pumps Should be Stopped-Check if an RHR Pump is running, and if RCS Pressure is above 325 psig (650 psig) and stable or rising.

Checks:

RHR Pump is running, and pressure is adequate to stop RHR Pumps Performs:

Stop RHR Pumps and place in Auto Check RCS and S/G Pressures-Check S/G Pressures Stable or Rising. Check RCS Pressure Stable or Lowering Checks:

Above checks are met CR -

X X

RO X

X X

X IP2 Sim Eva1 Scenario 2.doc

NRC Examination Scenario #2 SCENARIO: NRC 2 2 - SIMULATOR DOCUMENTATION RECORD

16.

17.

TIME Determine if Diesel Generators Should be Stopped-480V AC Buses are powered from Offsite Power, Stop EDGs Performs:

Stops all EDGs Evaluate Plant Status-Initiate Att. 1, Plant Equipment Status Evaluation Performs:

Initiates Att. 1, Plant Equipment Status Evaluation 1

Check if RCS Cooldown and Depressurization is Required-Check RCS Pressure > 325 psig (650 psig)

Performs:

Conditions met, Implements ES-1.2, Post LOCA Cooldown and Depressurization Terminate Scenario upon Transition to ES-1.2, or at the direction of the Lead Evaluator.

SM -

X Brief Surrogate BPO To Go Slow IIZ RO-1 So RO Will Start 32 HHSI Pump.

X X

IP2 Sim Eva1 Scenario 2.doc

ATTACHMENT 3, SHIFT TURNOVER 1of1 Watch Crew Turnover Sheet:

Datemime:

TODAY RCS Temp:

547.3"F RCS Press:

2235 psig PZR Level:

23.1%

RCS Total Leakage:

0.2 gpm RCS Unidentified 0.2 gpm Leakage:

Condition:

% Power:

MW Gross:

River Water:

Boron Conc:

Power Ops 2%

0 W e 63 "F 1 58 1 ppm Xenon:

Xe Free-3 Days Post Trip EFPD:

150 PZR Press Control:

PT-455 Channel I PZR Level Control:

LI-460 Channel I1 Service Water:

1,2,3 ESW Plant Equipment Status:

1. All Equipment is Operable

2. Currently Conducting A Plant Startup AAer A Short Forced Outage. In Procedure-POP 1.3 - "Plant Start Up From 0% to 45%" step 4.27.

3. Orders Are To Enter Mode 1 (All Required Permission Has Been Received), Raise Power To 7% In Preparation For Main Turbine Roll.

4. MOV-535 Is Closed Due To Leakage Past Its PORV.

IP2 Sim Eva1 Scenario 2.doc

Appendix D Scenario Outline Form ES-D-1 Event No.

1 2

Facility: Indian Point 3 Scenario No.:

3 Op-Test No.:

1 Malf.

Event Event No.

Type*

Description I~CRS.RO.BOP~

C (CRS.RO1 T avg Channel Summer Fails High (AOP)

Loss of the Operating Charging Pump (AOP)

Examiners:

Alan Blamev (Don Jackson)

Operators:

Joe DAntonio 3

4 Initial Conditions: Unit 3 is at 32% Power with a Shut Down in progress to meet the reauirements of the AFW Svstem LCO. 32 ABFP is Stowed Tagged due to a damaged trip throttle valve.

C(CRS.RO.BOP1 Turbine Trip P-8 (No Reactor Trip Expected) (AOP)

C(CRS.RO)

Loss of Both MBFPs (Failed Instrument), Manual Reactor Trip Turnover:

Unit 3 is at 32% Power with with a Shut Down in Droaress to meet the reauirements of the ARN Svstem LCO. 32 ABFP is Stopped Taqqed due to a damaged trip throttle valve. Orders for the shift are to hold brieflv at 32% Power while 32 ABFP is being re-assessed. However, ensure plant is in mode 3 in 4 Hours if 32 ABFP is not made operable.

5

~

C lCRS.BPD)

Failure of 31 ABFP 6

~~

M<CRS.ROmQ Loss of All Feed, FR-H.l 1 of41 NUREG-I021, Draft Revision 9

PROGRAM: NRC Initial Licensed Operator Exam COURSE:

SIMULATOR TOPIC:

SIMULATOR EVALUATION LESSON:

Examination Scenario 3 (NEW)

LESSON NO.: N/A APPROXIMATE TIME FOR EXAM:

80 min.

REVISION:

0 INSTRUCTOR MATERIALS:

1. Lesson Guide

2. Attachment 1, Simulator Exercise Summary

3. Attachment 2, Simulator Documentation Record

4. Attachment 3, Shift Turnover REMARKS:

SUBMITTED:

DATE:

EXERCISE: NRC Examination Scenario #3 SCENARIO: NRC 3 ATTACHMENT 1 - SIMULATOR EXERCISE

SUMMARY

1of1 Total Malfunctions (5-8/scenario):

Prior to EOP Entry:

1. Tavg Summer Fails High

2. Loss of the Operating Charging Pump

3. Turbine Trip < P-8

4. Loss of Both MBFPs, Manual Reactor Trip I After EOP Entry (1 -2/scenario):

I 1. 33 AFW Pump Motor Overload Abnormal Events (2-4/scenario):

1. T avg Summer Fails High

2. Loss of the Operating Charging Pump

3. Turbine Trip < P-8

4. Loss of Both MBFPs Major Transients (1 -2/scenario):

1. Loss of All Feedwater EOPs enteredjrequiring substantive actions (1 -2/scenario):

1. FR-H. 1 - Loss of All Feed EOP Contingencies requiring substantive action (0-2/scenario):

1. FR-H. 1 - Loss of All Feed Scenario run time (45-60 minutes, one scenario may approach 90 minutes):

80 minutes EOP run time (40-70% of run time): 70%

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Examination Scenario #3 SCENARIO: NRC 3 ATTACHMENT 1 - SIMULATOR EXERCISE

SUMMARY

2of1

1.

2.

Perform IC reset Perform Simulator Check List

3.

Sim Setup - 32% BOL, Heater Drain Pumps 0 0 s

4.

5.

TIMELINE AND EXAMINER ACTIONS FOR SIMULATION 32 ABFP Stop Tagged Due To Damaged Trip Throttle Valve Both MBFPs Trip When Rods are Taken To Manual After Turbine Trip EVENT INIT CUE A

Scenario B

Scenario Initialization Initialization

6.

C D

E F

Loss of Bus 3A to Occur At Time of Reactor Trip G

Examiner Directed Examiner Directed Examiner Directed Examiner Directed Examiner Directed CONSOLE ENTRY Tagged Out JPP LP4 (1)

Malf-EPS-OOSB, Trigger 1 100, Insert Insert Malf-TUR 00 1, Insert Malf-RCS 006A, 645, Malf-CVCS 005A, Malf-ATS 004A, Insert Insert 00 1 C, 1,Insert Malf-ATS 004B, Malf-CFW-SYMPTOMS / CUES / DESCRIPTION 32 ABFP Stop Tagged Out of Service Failure of 480V Bus 3A At Reactor Trip T avg Summer Fails High Loss of the Operating Charging Pump Turbine Trip < P-8 Both MBFPs Trip, Inserted When Rods Taken To Manual Loss of 33 ABFP on Motor Overload IP2 Sim Eva1 Scenario 3.doc

~

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 1 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

A

1.

2.

3.

4.

5.

6.

7.

8.

STA T avg Summer Fails High (PI-412 C)

Perform actions of ONOP-RPC-1, Instrument Failures Verify the following controls: Turbine Load-Stable, Rod Control Stable, PRZR Pressure Control-Normal, P E R Level Control-Normal, MBFP Speed-Normal, S/G Levels-Normal Performs:

Places Rod Control in Manual Places 3 1 Charging Pump Speed Control In Manual Check RCS Instrumentation: RCS Loop temperatures, RCS delta T set points, RCS coolant loop flow.

Checks:

RCS Loop Tave and T hot have failed high, goes to step 3 Performs the appropriate attachment per table Performs:

Reviews table and selects Attachment 2 Ensure Rod Control is in Manual Performs:

If not already in manual, places rod control in manual.

Match reactor power and turbine load Performs:

May slightly lower turbine load, or raise rods to balance reactor and turbine power m

Place charging pump speed control in Manual Performs:

Places charging pump speed control in Manual Control charging to maintain PRZR level on program Performs:

Controls charging per Graph RCS-2 Verify all redundant TRIP Status Lights for T hot are extinguished.

Verifies:

There are no redundant lights lit X

X X -

X -

Comments:

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC 3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 2 of 18 D C R S X

X x

x x

x X

rIME EVENTLEXPECTED OPERATOR RESPONSE:

9 1

1 1

1 Place the Delta T Defeat switch for the failed instrument to the defeat position for the channel Performs:

Defeats Delta T for the failed channel. Places Switch In 3T/411 A-DFT Chl Position In Cabinet B-8 Place the T avg Defeat switch for the failed instrument to the required position Performs:

Defeats the Tavg Input by placing the Defeat switch into the correct position. Places Switch in T412A in Loop A U-1 Position In Cabinet D-8 Crew May Reduce Turbine Load or Raise Controls Rods To Match Tave and Tref If the Lo Power Rod Withdrawal Stop lamp is out then -

Ensure 2 minutes have elapsed, establish AUTO rod control, ensure steam dumps are reset and in Temp Control Performs:

Depending on power level the Lo Power Rod Stop is not lit.

Operator takes action as described in the step above.

Restore automatic PRZR level control Performs:

Returns PRZR level control to automatic Ensure compliance with Technical Specification 3.3.1,

Function 5 (OT delta T), Condition E-Action: Place delta T Channel in Trip condition in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and place unit in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Technical Specification 3.3.1, Function 6 (OP delta T),

Condition E, Place OP delta T channel in Trip condition in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and place unit in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Technical Specification 3.3.2, Function If (Low Tave, Hi Steam Flow SI), Condition D, Place channel in Trip condition in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Technical Specification 3.3.2, hction 4d (MSL Isol),

Condition D, Place channel in Trip condition in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Insert Next Event When P U R Level Control Is In Auto Comments:

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 CRS X

X X

X SCENARIO: NRC3 RO x

x x

x ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 3 of 18 6

rIME Charging is lined up for operation, CH-LCV-112C is open Start 1 Charging Pump-Take Pump speed control to EVENTEXPECTED OPERATOR RESPONSE:

Perform actions of ONOP-CVCS-1, Charging and Letdown Malhctions7 Starts 32 or 33 charging pump per the above instructions Check that Charging Flow is Established-Checks flow is indicated on FI-128B Verifies:

Flow on FI-128B is 0- recognizes Response Not Obtained actions for step 1 are required.

Close Letdown Isolation Valves CH-LCV-459, and CH-Performs:

Closes letdown isolations.

Check PRZR level > 19%

Checks:

Pressurizer Level is > 19%

Check VCT Level > 5% and 9%

Checks:

VCT Level is > 5% and 9%

Check that CH-LCV-112B7 CH-LCV-112C7 or CH-288 are open Checks:

LCV-460 SM -

8

-~

Checks:

Monitors radiation and sump levels in the Aux Bldg Check that charging flow is established-Checks flow on Verifies:

Flow is indicated on FI-128B FI-128B Comments:

X X

X X -

X IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 4 of 18 TIME EVENT/EXPECTED OPERATOR RESPONSE:

9 10 11 12 Determine Letdown Status-check letdown flow at Ogpm, check that orifice valves are closed (Closes 200B), place PCV-135 in manual and 50% output, place TCV-130 in manual at 50% output, ensure open CH-AOV-201, CH-AOV-202, CH-LCV-459, CH-LCV-460, Check TCV-149 and CH-LCV-112A in AUTO, Open CH-AOV-200B, and verify L/D flow on FI-134 Performs:

Performs above steps in order to establish Letdown Flow Control Charging and Letdown-Adjust PCV-135 to maintain L/D pressure 225psig-275 psig, adjust TCV-130 to maintain L/D temperature 100- 130 degrees F, Maintain RCP seal injection 6-12 gpm, adjust charging and letdown to return Pressurizer Level to program Performs:

Stabilizes charging and letdown as described above and restores P E R level to program Check parameters that indicate Charging or Letdown leakage Checks:

Checks for abnormal system level or radiation trends Establish TCV-130, PCV-135, and Charging Pump Speed control in Automatic Performs:

When conditions are stable, places controllers in AUTO Examiners Note: Begin Turbine Trip <P-8 when controllers are restored to automatic or 5 minutes after letdown is restored X

X X -

X -

X X

Comments:

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC 3 ATIACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 5 of 18 RO X

X X

TIME BOP EVENT/EXPECTED OPERATOR RESPONSE:

D

1.

2.

3.

Comments:

Turbine Trip < P-8 Performs actions of ONOP-TG-4,Turbine Trip Below P-8 Verify Reactor Power Less Than 35% (P-8 Lit)

Verifies:

Power is less than P-8 Place Rod Control In Manual Performs:

Places rods into manual Insert Trip of Both MBFPs When Control Rods Taken To Manual Verify that all MSIVs are OPEN, Steam Dumps are Available, and that a MBFP is running Verifies:

MSIVs are open, Steam Dumps are available and operating, MBFPs are tripped-Takes RNO action to Trip The Reactor Trip Reactor On Loss of Running MBFPs (CT#I)

X IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 6of 18 rIME EVENT/EXPECTED OPERATOR RESPONSE:

E

1.

2.

3.

4.

Comments:

MBFP Trips / Manual Reactor Trip/ Loss of 3A 480 Volt Bus (Bus Loss Linked To Reactor Trip)

Crew Enters E-0, Reactor Trip or Safety Injection May or May Not Enter ONOP-FW-1, Loss of Feedwater. Trips Reactor In Response To Loss of Both MBFPs Performs:

Orders Reactor Trip and E-0, Reactor Trip or Safety Injection entry.

Verify Reactor Trip Checks:

Reactor Trip AND Bypass Breakers - OPEN Neutron F l u - DECREASING Rod Bottom Lights - LIT Rod Position Indicators - < 20 Steps Verify Turbine Trip Checks:

Turbine Stop valves - CLOSED Verify 480V AC Buses-All energized by offsite power Verifies:

Checks status of 480V Buses, recognizes that bus 3A is deenergized.

Performs:

Checks 345KV generator breakers 1 and 3 open Attempt to restore Bus 3A per SOP-EL-1 and SOP-EL-5, however recognizes that Bus 3A has experienced a bus fault Report to Control Room ifasked to investigate bus 3A, that the bus has been damaged and will not be recovered for at least 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Insert Loss of 33 ABFP Due To Motor Overioad X

X X

1 IP2 %m Eval Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC 3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 7of 18 rlMEl EVENTEXPECTED OPERATOR RESPONSE:

Determine if SI is actuated, or is required per posted operator aid.

Checks:

Any SI annunciator lit SI pumps running SI has not actuated, and is not required per the operator aid Go to ES-0.1, Reactor Trip Response SM Comments:

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC 3 AWACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 8 of 18 RO X

X rIME BO1 X

x x

X EVENT/EXPECTED OPERATOR RESPONSE:

F

1.

2.

3.

4.

5.

Reactor Trip Response/ Loss of All Feed Performs actions in ES-0.1, Reactor Trip Response, and meets requirements to transition to FR-H. 1 Check RCS Average Temperature-RCS Tave stable at or trending to 547 degrees F Checks:

RCS Tave is stable at or trending to 547 degrees F.

Check FW Status-Tave <547 degrees F, Check Main and Bypass FRVs closed, Veri@ total AFW flow > 365gpm, Check S/G Blowdown isolated, ensure both MBFPs tripped Checks:

The above requirements are met except AFW flow, operator attempts to start 33 Al3FP.

Check if Emergency Boration is required-RCS temp degrees F, all control rods <20 steps Checks:

Checks the above and determines that emergency boration is not required 500 Crew recognizes loss of all feed and transitions to FR-H. 1, Response to Loss of Secondary Heatsink - Crew will wait until all S/Gs are <9%. They will continue with ES-0.1 Action Steps Until Transition Determine if a Secondary Heat Sink is Required-Checks if RCS Pressure is Greater than any non-faulted S/G Pressure, and that any Hot Leg temperature is > 350 degrees F.

Checks:

Determines that heat sink is required X

X X

Comments:

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC 3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 9 of 18 SM -

EVENTKXPECTED OPERATOR RESPONSE:

HME Prepare to establish AFW flow-Check S/G blowdown isolated, Check CST level > 3ft., Check AFW Pp suction valves open, Checks:

S/G Blowdown is isolated, CST level is > 3ft., and AFW suction valves are open Establish AFW Flow using motor driven pumps Performs:

Recognizes that both motor driven pumps are not available and transitions to Attachment 2, 32 AFW Pump Operation

6.

X X

7.

Determine 32 AFW Pump Status-Check if 32 AFW pump is running, Check alarm status of 32 AFW pump, transition to step 4.

Performs:

Recognizes that 32 AFW Pump is not available, and continues with Step 4

8.

X X

Stop all RCPs.

Performs:

Stops all RCPs

9.

10.

11.

Stops all RCPs To Limit Heat Input During Loss of Heat Sink(CT#2)

Check all MSIVs Closed.

Performs:

Manually closes all MSIVs X

X Try to establish FW flow to any S/G-Verify 6900V Bus 1,2, or 4 energized, Transition to Attachment 3 Verifies:

1,2, and 4 6900V buses are energized, transitions to X

X Comments:

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 10 of 18 TIME EVENTEXPECTED OPERATOR RESPONSE:

12.

13.

14.

15.

16.

17.

Check that a Low Pressure source of water is available-Checks that a Condensate pump is running, and ensures that only 1 is running.

Performs:

Stops all but 1 Condensate Pump Block Automatic SI Actuation-Check that SI has not actuated, Place SI block key switches to Defeat for Train A and Train B Performs:

Blocks SI for Train A and Train B Depressurize at least 1 S/G to less than 450 psig to establish feed flow-Manually dump steam from at least 1 S/G at the maximum rate Performs:

Utilizes S/G Atmospheric to dump steam with 1 fully open dump valve. Should use 1 S/G Only. Valve Taken to Manual and Signal Is Adjusted To Fully Open.

Dispatch NPO to MBFP Discharge valve breakers Performs:

Sends an operator to MCC-36A and MCC-36B Prepare to Align Flow path-Place FW isolation defeat key switches to Defeat.

Performs:

Places l/FWlDA and lFWlDB to defeat Reset SI-Veri@ SI has actuated Checks:

SI is not actuated, goes to step 7.

X X

X X -

X -

X X

Comments:

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC 3 ATTACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 11 of 18 EVENTEXPECTED OPERATOR RESPONSE:

TIME SM

18.

19.

20.

21.

22.

23.

Establish initial feed water conditions-Ensure Bypass FW MOVs-Open, Ensure Main FW MOVs-Open, Crack Open Bypass FW FRVs, Place Main FW FRVs in Manual and Closed Performs:

Performs the above alignment Align Feed water Header-Manually Close MBFP recirc, Open MBFP discharge valves, Open MBFP discharge valve breakers.

Performs:

Performs the above alignment Place Steam Flow and Feed Flow Recorders to Narrow Performs:

Sets up recorders as described above to be able to see condensate flow to S/Gs Control Bypass feed water FRVs to rapidly restore at least 1 S/G level to greater than 9%

Establish Feed water Flow To At Least 1 S/G- (CT#3)

Terminate Scenario When Flow EstabIkhed To At Least I S/G X

X -

X X

X X -

X I

Comments:

IP2 Sim Eva1 Scenario 3.doc

EXERCISE: NRC Exam Scenario 3 SCENARIO: NRC3 A'ITACHMENT 2 - SIMULATOR DOCUMENTATION RECORD 12 of 18 Comments:

IP2 Sim Eva1 Scenario 3,doc

EXERCISE: NRC Examination Scenario #3 ATI'ACHMENT 3 - SCENARIO OBJECTIVES SCENARIO: NRC3 1of1 IP2 Sim Eva1 Scenario 3.doc

ATTACHMENT 3, SHIFT TURNOVER 1

1of1 Watch Crew Turnover Sheet:

Datemime:

TODAY RCS Temp:

552.8OF RCS Press:

2235 psig PZR Level:

29.8%

RCS Total Leakage:

0.2 gpm RCS Unidentified 0.2 gpm Leakage:

Condition:

% Power:

MW Gross:

River Water:

Boron Conc:

Power Ops 32%

270Mwe 63 F 1243ppm Xenon:

Increasing EFPD:

150 PZR Press Control:

PZR Level Control:

Service Water:

1,2,3 ESW PT-455 Channel I LI-460 Channel I1 Plant Equipment Status:

1. 32 ABFP Stop Tagged for repair of damaged trip throttle valve, In ITS LCO 3.7.5 Condition B. 72 Hour LCO in effect for 68 hours7.87037e-4 days 0.0189 hours 1.124339e-4 weeks 2.5874e-5 months .

2. Holding at 32% To Reassess Shutdown LCO, and Restoration of 32 AI3FP.

3. MOV-535 Is Closed Due To Leakage Past Its PORV.

4. Both Heater Drain Pumps Have Been Secured, During The Power Reduction.

5. In Procedure Step, POP-3.1, Plant Shutdown From 45% Power, Step 4.1.12.

IP2 Sim Eval Scenario 3.doc

ML040120862

Contents

Text

REFERENCES:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

ML040120862

Text

REFERENCES:

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu

Search