Text

Final - Section C Operating
	ML022550317
Person / Time
Site:	Susquehanna
Issue date:	08/12/2002
From:	Hunt W; Susquehanna
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	50-387/02301, 50-388/02301, NRC0201 50-387/02301, 50-388/02301
	Download: ML022550317 (140)
	v • d • e

PP&L-SUSQUEHANNA TRAINING CENTER SIMULATOR SCENARIO Scenario

Title:

NRC INITIAL LICENSE OPERATOR EXAMINATION Scenario Duration:

2 Hours Scenario Number: NRC0201 Revision/Date:

Rev 0, 411/2002 Course:

PCO17, NRC Initial License Operator Examination Operational Activities:

6. Power reduction for Stuck Rod

1. DIG Surveillance

7. Leak in Drywell

2. Breaker 1A20204 Trip

8. HPCI Auto Start Failure

3. Trip of RPS MG A

9. MSL Rupture Inside Drywell

4. Control Rod Scram

10. Drywell Spray Valve Failure

5. Stuck Control Rod Prepared By:y l

Instructor Date Reviewed By:

wlNzP z

l NuclearY tk5i1ons Training Supervisor Date Approved By:

?Wg 1vr 7 2 Supervisin2 Mana er/Shift S ervisor Date Form STCP-QA-612A Rev. 1, (05/01)

Page 1 of 25 File No. R11-3

Page 2 Scenario NRC0201 Rev. 0, 4/22/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 2 of 25 File No. R1 1-3

Page 3 Scenario NRC0201 Rev. 0, 4/2212002 lI SCENARIO

SUMMARY

The scenario begins with both Units at 100% power EOL. RCIC system is out of service due to oil system contamination. DIG 'B' is running and synchronized to Bus 1 B lAW S0-024-001. DIG run time requirements have been met, the crew will unload and shutdown DIG 'B' lAW SO-024-001. When DIG load is reduced to ;1000KW, output breaker 1A20204 will trip open resulting in DIG 'B' being declared inoperable per Technical Specification 3.8.1.

An RPS MG set 'A' shaft seizure results in RPS bus 1Y201A de-energizing and a concurrent scram of rod 42-27 to position 10. The RPS bus loss results in isolation system actuation and half scram condition requiring transfer to alternate power source. The critical component is the Reactor Recirculation Pump motor cooler affected by isolation of chilled water. Rod 42-27 will be stuck at position 10, Off-Normal procedures require a 20% power reduction if the rod is not capable of being inserted to position 00.

Following the power reduction a small leak develops in the primary containment. The crew should perform scram imminent actions and manually scram the reactor. HPCI will fail to auto-start, requiring the crew to perform a component by component start of the system for injection. After the reactor scram the break size increases in main steam line A requiring entry into Emergency Operating Procedures for RPV Control and Primary Containment Control. Plant Aux Load Shed will result in loss of condensate and feedwater injection. The leak size will allow the crew to maintain RPV water level above TAF during the transient.

The crew will initiate Suppression Chamber Sprays, when Suppression Chamber pressure exceeds 13 psig, Drywell Sprays are required. When drywell sprays are attempted the Drywell spray valve A(B) will fail to open. This will require the crew to shift to the other loop to spray the Drywell.

When Drywell Spray has been performed and actions are in progress to restore RPV water level to +13" to +54", the scenario will be terminated.

Form STCP-QA-612A Rev. 1, (05101)

Page 3 of 25 File No. R11-3

Page 4 Scenario NRC0201 Rev. 0, 4/22/2002

-:1-'s... N Form STCP-QA-612A Rev. 1, (05/01)

Page 4 of 25 File No. R11-3

Page 5 Scenario NRC0201 Rev. 0, 4/22/2002 l1 SCENARIO OBJECTIVES The SSIUS will:

1. Shut down the Reactor when it is determined Reactor safety is in jeopardy, or when operating parameters exceed any RPS setpoint and scram does not occur (00.AD.131).

2. Ensure ififfiation of ESF equipment if automatic operation was not properly initiated (00.AD.131).

3. Inform other shift members and plant management of changes in plant status, potential problems or limitations (0O.AD.131).

4. Implement appropriate portions of Reactivity Management and Controls program (00.AD.047).

5. Implement control of LCOs, TROs, and Safety Function Determination program (00.AD.273)

6. Ensure that required actions per Technical Specifications are met when a LCO is not met (00.TS.002).

7. Implement Appropriate Portions of the Diesel Start Log (24.AD.001).

8. Implement Loss of RPS (58.ON.004).

9. Implement Alarm Response procedures (00.AR.005).

10. Implement Rod Drift (55.ON.013).

11. Perform a 10% Power Change with Rods/Recirc Flow (00.GO.012).

12. Implement Scram (00.ON.018).

13. Implement-Containment Isolation (59.ON.006)

14. Implement RPV Control (00.EO.026).

15. Implement Primary Containment Control (00.EO.027).

The PCOs will:

1. Perform Monthly Diesel Generator Operability Test (24.SO.002).

2. Perform Offsite Power Source and Onsite Class 1 E Operability Test (24.SO.001).

3. Implement Appropriate Portions of the Diesel Start Log (24.AD.001).

4. Implement Alarm Response procedures (00.AR.005).

5. Implement Loss of RPS (58.ON.004).

6. Implement Rod Drift (55.ON.013).

7. Perform a 10% Power Change with Rods/Recirc Flow (00.GO.012).

8. Implement Scram (00.ON.018).

9. Perform HPCI manual startup (52.OP.002).

10. Perform maximizing CRD flow (55.OP.001).

11. Implement RPV Control (00.EO.026).

12. Implement Primary Containment Control (00.EO.027).

13. Perform RHR Operation in Containment Suppression Pool Sprays (49.OP.004).

14. Perform LPCI injection through heat exchanger (49.OP.013)

Form STCP-QA-612A Rev. 1, (05/01)

File No. R11-3 Page 5 of 25

Page 6 Scenario NRC0201 Rev. 0, 4/22/2002 Form STCP-QA-612A Rev. 1, (05101)

Page 6 of 25 File No. R11-3

Page 7 Scenario NRC0201 Rev. 0, 4/2212002 CRITICAL TASKS 1J Sprays the Drywell when Suppression Chamber exceeds 13 psig.

-limits Drywell Spray flow to between 1000 and 2800 gpm fbr the first 30 seconds.

Maintain RPV water level above -161" with available injection sources.

Denotes Simulator Critical Task Form STCP-QA-612A Rev. 1, (05/01)

Page 7 of 25 File No. R11-3

Page 8

Scenaro NRC0201 Rev. 0, 4/22/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 8 of 25 File No. R11-3

Page 9

Scenaro NRC0201 Rev. 0, 4/22/2002 i1 SCENARIO REFERENCES

1. D/G SURVEILLANCE-BREAKER 1A20204 TRIP SO-024-001 B OP-024-005 01-024-004 SO-024-013 T.S. 3.8.1 AR-015-D13 OP-AD-004 MONTHLY DIESEL GENERATOR OPERABILITY TEST DIESEL GENERATOR START LOG DIESEL GENERATOR OPERATING LOG OFFSITE POWER SOURCE AND ONSITE CLASS 1 E OPERABILITY TEST AC SOURCES - OPERATING DG B SUPPLY BKR TO BUS 1 B/2B TRIP OPERATIONS STANDARDS FOR ERROR AND EVENT PREVENTION

2. TRIP OF RPS MG SET 'A' ON-1 58-001 LOSS OF RPS

3. ROD 42-27 SCRAM TO POSITION 10, STUCK CONTROL ROD, 20% POWER REDUCTION ON155-001 CONTROL ROD PROBLEMS T.S.3.1.3 CONTROL ROD OPERABILITY CORE REACTIVITY CONTROL BOOK GO-100-012 POWER MANEUVERS

4. SMALL LEAK IN DRYWELL ON-100-101 OP-152-001 SCRAM HPCI SYSTEM

5. MSL 'A' RUPTURE INSIDE DRYWELL EO-000-102 EO-000-103 OP-149-004 AR-1 12-D03 AR-104-B03 RPV CONTROL PRIMARY CONTAINMENT CONTROL RHR SYSTEM OPERATION IN CONTAINMENT SPRAY MODE DW/SUPP CHAMBER HI/LOW PRESSURE PRI CONTAINMENT HI/LOW PRESSURE Form STCP-QA-612A Rev. 1, (05/01)

Page 9 of 25 File No. R11-3

Page 10 Scenario NRC0201 Rev. 0, 4/22/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 10 of 25 File No. RI1-3

Page 11 Scenario NRC0201 Rev. 0, 4/22/2002 SCENARIO SPECIAL INSTRUCTIONS I

1. Initialize the simulator to IC-20, both units at 100% power EOL.

2. Set up the simulator for the scenario by performing the following:

a. Start 'A' and 'B' ESW pumps.

b. Start up and load D/G 'B' to 4KV Bus 1A202 IAW SO-024-001.

c. Raise load to z3800 KW.

d. Remove RCIC from service:

Close and status control pink tag RCIC F007 & F008.

Place the RCIC Div % out of service switches to INOP.

Place the controller in MAN set @ '0'%.

Depressurize the steam supply line by opening F054, then re-close.

3. Type restorepref YPP.NRC0201; verify the following pre-inserts and Program Button assignments.

Also verify that the Environment Window shows 0 Event Trigger active.

bat RCB.RCICOOS SIMULATES RCIC OUT OF SERVICE bat HPB.HPCIFAIL HPCI FAILURE TO AUTO START IMF MV07:HV151FO21A 0 RHR F021A FAILED CLOSED IMF MV07:HVI51F021B 0 RHR F021B FAILED CLOSED

[P-1] IMF BR03:1A20204 BREAKER 1A20204 TRIP

[P-2] bat YPB.NRC0201A RPS MS SET 'A' TRIP, ROD 42-27 SCRAM TO POSN 10

[P-3] MRF RM179024 RESET MSL RAD MON 'A' RESET

[P-4] MRF RM179026 RESET MSL RAD MON 'C' RESET

[P-5] IMF RR1 64010 1 4:00 SMALL LEAK INTO DRYWELL

[P-6] IMF 183007 5 0 0 MSL 'A' BREAK IN DRYWELL

[P-7] DMF MV07:HV151FO21A RHR F021A FAILED CLOSED

[P-8] DMF MV07:HVI51F021B RHR F021B FAILED CLOSED

4. Prepare a turnover sheet indicating:

a. Both Units are at 100% power EOL..

b. RCIC is out of service due to oil system contamination and will not be returned to service this shift.

c. D/G 'B' is running and synchronized to Bus 1 B IAW SO-024-001. D/G run time requirements have been met, unload and shutdown D/G 'B' IAW SO-024-001.

d. ESW Pumps 'A' and 'B' are in service.

5. Prepare a markup copy of SO-024-001 up to step 6.1.17 s. (3) including a surveillance coversheet.

6. Prepare a markup copy of OP-024-005, Attachment A and place it in the D/G Start Log Book.

7. Prepare an LCO sheet indicating RCIC has been out of service for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months due to oil system contamination.

Form STCP-QA-612A Rev. 1, (05/01)

Page 11 of 25 File No. R11-3

Page 12 Scenaro NRC0201 Rev. 0, 4/2212002 Form STCP-QA-612A Rev. 1, (05/01)

Page 12 of 25 File No. R11-3

Page 13 Scenaro NRC0201 Rev. 0, 4/22/2002 SCENARIO EVENT DESCRIPTION FORM Initial Conditions: Initialize the Simulator to IC-20. Place the Simulator to RUN. Ensure the Program Buttons are assigned as indicated on the Special Instructions sheet via the appropriate Preference File. Assign Shift positions.

Direct the start of the 5 minute panel walkdown.

EVENT TIME [

DESCRIPTION 1

UNLOAD AND SHUTDOWN 'B' EDG 2

BREAKER 1A20204 TRIP FOR 'B' EDG 3

TRIP RPS MG SET 'A' 4

CONTROL ROD 42-27 SCRAM TO POSITION 10 5

STUCK CONTROL ROD 6

POWER REDUCTION FOR STUCK ROD 7

SMALL LEAK IN DRYWELL 8

HPCI AUTO START FAILURE 9

MSL'A' RUPTURE IN DRYWELL 10 DRYWELL SPRAY VALVE FAILURE

_ I

_ I I_

Form STCP-QA-612A Rev. 1, (05/01)

Page 13 of 25 File No. R11-3

Page 14 Scenario NRC0201 Rev. 0, 4/22/2002 SCENARIO EVENT FORM Event No:

1,2 Brief

Description:

Unload and Shutdown 'B' EDG I Breaker 1A20204 Trip POSITION TIME STUDENT ACTIVITIES PCOP Reduces 'B' DG load to 1000 KW to 380 KW.

Recognize and reports breaker 1A20204 tripped.

Dispatches a plant operator to breaker 1A20204 to investigate.

Verifies Bus 1 B remains energized.

May refer to ON-1 04-202, LOSS OF 4 KV BUS 1 B.

US Contacts EM to investigate breaker problem.

Refers to Technical Specification 3.8.1, Condition B.

Declares DIG 'B' inoperable on Unit 1.

Makes notifications IAW OP-AD-002, STANDARDS FOR SHIFT OPERATIONS.

Directs performance of SO-024-013.

May direct shutdown of D/G 'B' after 15 minutes cooldown is complete.

PCOP When directed, performs a shutdown of D/G 'B'.

I

_ I

1-1-

I~

I 1-1

Denotes Critical Task NOTES:

Form STCP-QA-612A Rev. 1, (05/01)

Page 14 of 25 File No. R 11-3

Page 15 Scenario NRC0201 Rev. 0, 4/2212002 INSTRUCTOR ACTIVITIES, ROLE PLAY, l1 AND INSTRUCTOR'S PERSONAL NOTES Event No:

Brief

Description:

1, 2 Unload and Shutdown 'B' EDG I Breaker 1A20204 Trip INSTRUCTOR ACTIVITY:

Monitor the load decrease and trip breaker 1A20204 at 1000 KW load or immediately following the load reduction, Depress P-1.

[P-1] IMF BR03:1A20204 OC TRIP ON BKR 1A20204 NOTE: D/G load will be reduced to a value between 1000 KW and 380 KW.

ROLE PLAY:

As plant operator dispatched to breaker 1A20204, wait 2 mins. and report the breaker is tripped. All other bus 1A202 conditions are normal.

As plant operator at the DIG, report the DIG is running unloaded and conditions are normal, standpipe high level is ONLY ALARM.

As Electrical Maintenance sent to breaker 1A20204, wait 2 mins. and report the breaker is tripped, appears to be related to Unit 1 breaker only, further investigation is required to determine why. We will inform you of any new information.

Form STCP-QA-612A Rev. 1, (05/01)

Page 15 of 25 File No. R11-3

Page 16 Scenario NRC0201 Rev. 0, 4/22/2002 SCENARIO EVENT FORM Event No:

3, 4, 5, 6 Brief

Description:

TRIP RPS MG SET 'A' / ROD 42-27 SCRAM TO POSITION 10 / STUCK ROD I POWER REDUCTION POSITION TIME STUDENT ACTIVITIES PCOM Reports RPS half scram condition.

Selects display rods drifting, identifies rod 42-27 as d~ifting.

Selects rod 42-27 to monitor position, reports rod position.

Identifies status light for scram valves open.

Selects display scram valves open, identifies scram valves open on rod 42-27.

Implements ON-155-001, CONTROL ROD PROBLEMS US Directs the implementation of ON-1 55-001, CONTROL ROD PROBLEMS.

Directs PCO to fully insert rod 42-27 to position 00.

Contacts Reactor Engineering.

Contact FIN Team/Maintenance to investigate HCUiand control rod 42-27.

PCOM Attempts to insert rod 42-27 to position 00.

Notifies US rod 42-27 did not insert, rod remains at position 10.

US Direct PCO to reduce reactor power by 20% or reduce core flow to value specified in the CRC Book.

Notifies Chemistry and Health Physics of power change.

PCOM Reduces reactor power as directed by US.

Plots power change on P/F map.

Denotes Critical Task

[lNOTES:

]

Form STCP-QA-612A Rev. 1, (05/01)

Page 16 of 25 File No R11-3

Page 17 Scenario NRC0201 Rev. 0, 4/22/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

Brief

Description:

3, 4, 5, 6 TRIP RPS MG SET 'A' / ROD 42-27 SCRAM TO POSITION 10 / STUCK ROD I POWER REDUCTION INSTRUCTOR ACTIVITY:

When actions for breaker 1A20204 trip are complete, insert the loss of RPS MG Set 'A' and scram control rod 42-27 to position 10; Depress P-2.

[P-2] bat YPB.NRC0201A ROLE PLAY:

As Reactor Engineer when contacted about the stuck rod a position 10, state I will run a monitor and take a look at core parameters for now. I need to get our options outlined and talk to some folks, then I'll get back to you.

As plant operator sent to HCU 42-27 wait 3 mins., report the scram valves appear open by local indication and the lines are hot.

As FIN Team/Maintenance sent to investigate rod 42-27 wait 10 mins., report a blown fuse was found and we are still investigating to find a cause. When we have completed our investigation I will call you.

Form STCP-QA-612A Rev. 1, (05101)

Page 17 of 25 File No. R11-3

Page 18 Scenario NRC0201 Rev. 0, 4122/2002 SCENARIO EVENT FORM Event No:

3, 4, 5, 6 Brief

Description:

TRIP RPS MG SET 'A' / ROD 42-27 SCRAM TO POSITION 10/ STUCK ROD / POWER REDUCTION POSITION TIME STUDENT ACTIVITIES PCOP Identifies RPS MG Set 'A' power available light OFF.

Dispatches plant operator to RPS MG Set 'A'.

Implements ON-158-001, LOSS OF RPS.

US Directs implementation of ON-158-001, LOSS OF RPS.

Directs PCO to transfer to alternate power source.

Directs PCO to monitor Reactor Recirc Pump motor temperatures.

PCOP Transfers RPS 'A' to alternate power source.

Directs plant operator to reset the MSL Rad Monitors 'A' & 'C'.

US Directs PCO to reset RPS half scram on Div 1.

Directs PCO to reset N4S isolation signals and restore RRP cooling.

PCOM Resets RPS half scram.

PCOP Resets N4S isolation logic.

Resets and opens RBCW to RRPs.

Denotes Critical Task NOTES:

Form STCP-QA-612A Rev. 1, (05/01)

Page 18 of 25 File No. R11-3

Page 19 Scenario NRC0201 Rev. 0, 4/22/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

Brief

Description:

3, 4,5, 6 TRIP RPS MG SET 'A' / ROD 42-27 SCRAM TO POSITION 10/ STUCK ROD / POWER REDUCTION INSTRUCTOR ACTIVITY:

When requested to reset the MSL Rad Monitors A & C, Depress P-3 and P4.

[P-3] MRF RM179024 RESET

[P-4] MRF RM179026 RESET ROLE PLAY:

As plant operator sent to RPS MG Set, wait 2 mins. and report the area smells of something hot, the motor is to very hot to the touch. The normal source EPA breakers are open.

Form STCP-QA-612A Rev. 1, (05/01)

Page 19 of 25 File No. R11-3

Page 20 Scenario NRC0201 Rev. 0, 4122/2002 SCENARIO EVENT FORM Event No:

7 Brief

Description:

SMALL LEAK INTO DRYWELL POSITION TIME STUDENT ACTIVITIES PCO Recognizes/reports increasing Drywell pressure/temperature.

Recognizes/reports AR-112-D03, DRWUSUPP CHAMBER HI-LO PRESS.

US Directs monitoring Primary Containment parameters.

Directs performance of scram imminent actions.

Directs manual scram before drywell pressure exceeds 1.72 psig.

PCOM Performs scram imminent actions.

Decreases TCF to 065 mIbm/hr.

Place reactor mode switch to Shutdown.

Verifies all rods fully inserted except rod 42-27.

Inserts SRM and IRM detectors.

Implements ON-100-101, SCRAM.

PCOP Performs scram imminent actions.

Transfer Aux Buses 11A/11 B to Tie-Bus.

US Enters EO-000-1 02, RPV CONTROL when drywell pressure exceeds 1.72 psig.

Also has entry condition due to < +13 " RPV Water Level Directs RPV water level be restored and controlled between +13' and +54" with available systems.

Denotes Critical Task NOTES:

I 1

II Form STCP-QA-612A Rev. 1, (05/01)

Page 20 of 25 File No. R11-3

Page 21 Scenario NRC0201 Rev. 0, 4/22/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

7 Brief

Description:

SMALL LEAK INTO DRYWELL INSTRUCTOR ACTIVITY:

Following the 20% power reduction insert a small leak into the drywell, Depress P-5.

[P-5] IMF RRI 64010 1 4:00 SMALL LEAK INTO DW NOTE:

1. Drywell pressure will increase to 1.0 psig in z3.5 mins. and 1.72 psig in -4.5 mins.

2. When plant aux load shed occurs injection from FW/Condensate is lost.

ROLE PLAY:

As necessary Form STCP-QA-612A Rev. 1, (05101)

Page 21 of 25 File No. R11-3

Page 22 Scenario NRC0201 Rev. 0, 4/22/2002 SCENARIO EVENT FORM Event No:

8,9,10 Brief

Description:

HPCI AUTO START FAILURE I MSL 'A' BREAK INSIDE DRYWELL I RHR F021 FAILURE POSITION TIME STUDENT ACTIVITIES PCOP Reports HPCI system auto start failure when drywell pressure exceeds 1.72 psig.

Performs component by component start up of HPCI system.

Restores RPV water level with HPCI system.

Maintains RPV water level above -161" with available injection sources.

US Enters EO-000-103, PRIMARY CONTRAINMENT CONYTROL when drywell pressure exceeds 1.72 psig.

Directs Suppression Chamber Sprays placed in service.

PCOM Reports loss of feedwater and condensate systems.

PCOP Reports rapid increase in drywell pressure and tempTerature.

Reports decrease in RPV water level.

US Directs alignment of injection sources as necessary to maintain RPV level above TAF.

Directs alignment of RHR for Drywell Sprays when Supp Chamber exceeds 13 psig.

_Directs Drywell spray flow limited to between 1000 and 2800 gpm for first 30 seconds.

PCOP Reports failure of Drywell spray valve, RHR F021.

US Directs other loop of RHR placed in service for Drywell sprays.

Request maintenance support as necessary.

Denotes Critical Task gNOTES:l II Form STCP-QA-612A Rev. 1, (05/01)

Page 22 of 25 File No. R11-3

Page 23 Scenario NRC0201 Rev. 0, 4/22/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

8, 9,10 Brief

Description:

HPCI AUTO START FAILURE / MSL 'A' BREAK INSIDE DRYWELL I RHR F021 FAILURE INSTRUCTOR ACTIVITY:

Following the reactor scram insert a MSL 'A' break inside the drywell, Depress P-6.

[P-6] IMF MS183007 5 0 0 MSL 'A' BREAK INSIDE DRYWELL After the crew addresses the failed RHR Containment Spray valve F021A or B and makes the decision to swap to the opposite loop of RHR, delete that loop's valve failure, Depress EITHER:

[P-7] DMF MV07:HV151F021A If A Loop is to be aligned.

OR

[P-8] DMF MV07:HV151F021B If B Loop is to be aligned.

ROLE PLAY:

As necessary.

Form STCP-QA-612A Rev. 1, (05/01)

Page 23 of 25 File No. R11-3

Page 24 Scenario NRC0201 Rev. 0, 4/22/2002 SCENARIO EVENT FORM Event No:

8, 9, 10 Brief

Description:

HPCI AUTO START FAILURE I MSL 'A' BREAK INSIDE DRYWELL / RHR F021 FAILURE POSITION TIME STUDENT ACTIVITIES PCOP Shutdown DW coolers and RRPs as necessary.

Aligns RHR for DW sprays.

Limits DW spray flow to between 1000 and 2800 gpm for first 30 seconds.

Reports lowering DW pressure and temperature.

US Directs sprays terminated before Drywell/Supp Chamber pressure drops to 0 psig.

PCOP Terminates sprays before Drywell/Suppression chamber pressure drops to 0 psig.

.9.

1-

.9.

1I 1

I

4.

4

Denotes Critical Task E NOTES:

Form STCP-QA-612A Rev. 1, (05101)

Page 24 of 25 File No. R1 1-3

Page 25 Scenario NRC0201 Rev. 0, 4/22/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES I

Event No:

Brief

Description:

8, 9,10

-HPCI AUTO START FAILURE I MSL 'A' BREAK INSIDE DRYWELL I RHR F021 FAILURE INSTRUCTOR ACTIVITY:

None.

ROLE PLAY:

As necessary.

TERMINATION CUE:

Drywell sprays have been initiated and actions are in progress to restoreRPV water level to +13" to +54" the scenario will be terminated.

Form STCP-QA-612A Rev. 1, (05/01)

Page 25 of 25 File No. R1 1-3

UNIT SUPERVISOR TURNOVER SHEET UNIT:

1 Date: July 30, 2002 SHIFT 1900 to 0700 SHIFT 0700 to 1900 Start End Start End MODE 1

POWER LEVEL 100 GENERATOR OUTPUT 1150 MWe MODE POWER LEVEL GENERATOR OUTPUT MWe

1.

RCIC is out of service due to oil system contamination and will not be returned to service this shift.

2.

DIG 'B' is running and synchronized to Bus 1 B lAW SO-024-001. D/G run time requirements have been met, you are to unload and shutdown D/G 'B' IAW SO-024-001.

3.

ESW Pumps 'A' and 'B' are in service.

4.

Unit 2 is in MODE 1 at 100% power EOL.

5.

Chemistry/Rx Engineering investigating Off Gas System spike observed during last Control Rod Exercising Surveillance.

COMMON:

Form OP-AD-W03-7, Rev.3, DUPLEX, Page 1 of 2 (File Number R5-5)

I PP&L-SUSQUEHANNA TRAINING CENTER

.1.

SIMULATOR SCENARIO Scenario

Title:

NRC INITIAL LICENSE OPERATOR EXAMINATION Scenario Duration:

2 Hours Scenario Number: NRC0202 Revision/Date:

Rev 0, 4/1/2002 Course:

PCO17, NRC Initial License Operator Examination Operational Activities:

6. ATWS

1. Swap CRD Pumps

7. SBLC System Failure

2. Power Change 100 MWe

8. Main Turbine Trip

3. RFPT Trip

9. RCIC Speed Control Failure

4. Recirc Drive Flow Instr Failure

10. Loss of Aux Buses 11AM1B

5. Loss of CRD Flowilnoperable Accum Prepared By: i6/7Z Instructor Date Reviewed By:

sat 4

d1l OZ Nuc a

erations Training Supervisor Date Approved By:

e 7-z'te 7Z-Supervising Manager/Shifoupervisor Date Form STCP-QA-612A Rev. 1, (05/01)

Page 1 of 15 File No. R11-3

Page 2 Scenario NRC0202 Rev. 0, 4/22/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 2 of 17 File No. R11-3

Page 3 Scenario NRC0202 Rev. 0, 4/22/2002 SCENARIO

SUMMARY

The scenario begins with both Units at 100% power, EOL.. The HPCI system is out of service for governor valve adjustments. The HPCI system will not be returned to service this shift. A minimum generation alert has been issued for the PJM network.

The crew wilterform a swap of CRD pumps, Start 'B' and Stop 'A' to allow maintenance to record vibration data.

PCC will call for a 1OOMWe load decrease on Unit 1 due to a Minimum Generation Emergency. The crew will follow Reactor Engineering Instructions in the CRC Book to conduct the power decrease.

Following the power decrease 'A' RFP will trip. A Reactor Recirc limiter 2 runback will result in power lowering to -65%. The crew will implement Off-Normal procedures to stabilize the plant. The speed limiter will not be reset.

Reactor Recirc Flow Unit 'D' fails downscale resulting in a half scram and rod block condition. The crew will bypass the failed flow unit and remove it's input to the low flow auctioneer circuit. Technical Specifications will require declaring one of the two required APRM Flow Biased Simulated Thermal Power

- High channels in Division 2 inoperable.

A loss of CRD occurs when the operating CRD Pump trips and the backup pump fails to start. Shortly after several CRD accumulators on withdrawn control rods are determined inoperable requiring the crew to manually scram the reactor.

When the reactor is scrammed, control rods will fail to insert due to a failure of RPS. When the crew injects SLC, the "A" SLC pump will start, but will eventually trip on over current. The "B" SLC pump-shaft will shear, resulting in no SLC injection. Division I ARI will fail, preventing ARI actuation. RPV water level will be lowered to control power and alternate methods of control rod insertion will be attempted.

When level is stabilized with feedwater, the Main Turbine will trip along with a loss of Aux Buses 1 1A and 11 B and a subsequent loss of normal HP injection sources. When started, RCIC's speed control circuitry will fail at 1000 rpm and will be unrecoverable. With the unavailability of HPCI and RCIC, RPV water level will decrease to TAF requiring performance of Rapid Depressurization.

After Rapid Depressurization and subsequent RPV level restoration to >TAF, level will be restored and maintained with LPCI between -60" and -161". RPS fuses will be pulled and control rods will be fully inserted.

When all control rods are fully inserted and actions are in progress to restore RPV water level to +13" to +54",

the scenario will be terminated.

Form STCP-QA-612A Rev. 1, (05/01)

File No. R11-3 Page 3 of 17

Page 4 Scenaro NRC0202 Rev. 0, 4/22/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 4 of 17 File No. R1 1-3

Page 5

Scenario NRC0202 Rev. 0, 4/22/2002 SCENARIO OBJECTIVES The SS/US will:

1. Shut down the Reactor when it is determined Reactor safety is in jeopardy, or when operating parameters exceed any RPS setpoint and scram does not occur (00.AD. 131).

2. Ensure initiation of ESF equipment if automatic operation was not properly initiated (00.AD.131).

3. Ensure that required actions per Technical Specifications are met when a LCO is not met (O0.TS.002).

4. Implement-appropriate portions of Reactivity Management and Controts program (0O.AD.047).

5. Inform other shift members and plant management of changes in plant status, potential problems or limitations (00.AD.131).

6. Implement control of LCOs, TROs, and Safety Function Determination program (0Q.AD.273)

7. Implement Alarm Response procedures (00.AR.005)

8. Implement Recirc Drive Flow Instrument Failure (64.ON.009).

9. Implement 13.8 KV Bus 11A/M1B Load Shedding on Bus UV (03.ON.006).

10. Implement Loss of CRD System Flow (55.ON.014).

11. Implement Scram (00.ON.018).

12. Implement ATWS (00.ON.026).

13. Implement RPV Control (00.EO.026).

14. Implement Level/Power Control (0Q.EO.031).

15. Implement Primary Containment Control (0O.EO.027).

16. Implement SLC injection with RCIC (50.EO.009).

17. Implement De-energizing Scram Pilot Solenoids (58.EO.005).

18. Implement Rapid Depressurization (00.EO.030).

The PCOs will:

1. Perform RHR operation in the Suppression Pool Cooling Mode (49.OP.003).

2. Implement Alarm Response procedures (Q0.AR.005)

3. Perform overriding RHR Injection (49.OP.01 1).

4. Perform initiation of Standby Liquid Control System (53.OP.003).

5. Perform inserting manual scram. (55.OP.006).

6. Perform swapping operating CRD pumps (55.0P.005)

7. Perform inhibiting ADS (83.OP.005).

8. Perform a 10% power change with rods/recirc flow (00.GO.012).

9. Perform Loss of CRD System Flow (55.ON.014).

10. Implement Recirc Drive Flow Instrument Failure (64.ON.009).

11. Implement 13.8 KV Bus 11A/1IB Load Shedding on Bus UV (03.ON.006).

12. Implement Scram (00.ON.018).

13. Implement ATWS (00.ON.026).

14. Implement RPV Control (00.EO.026).

15. Implement Level/Power Control (00.EO.031).

16. Implement Primary Containment Control (00.EO.027).

17. Perform Rapid Depressurization (00.EO.030).

18. Reset Main Generator Lockouts (98.ON.001).

Form STCP-QA-612A Rev. 1, (05/01)

File No. R11-3 Page 5 of 17

Page 6

Scenario NRC0202 Rev. 0, 4/22/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 6 of 17 File No. R11-3

Page 7 Scenario NRC0202 Rev. 0, 4/22/2002 CRITICAL TASKS Inhibit ADS Inserts control rods IAW EO-000-1 13, Sheet 2, Control Rod Insertion Stops and prevents injection except from RCIC.

Performs Rapid Depressurization by opening all ADS SRVs.

Slowly restores RPV level to - 60" to - 161" with LPCI.

Denotes Simulator Critical Task Form STCP-QA-612A Rev. 1, (05/01)

Page 7 of 17 File No. R11-3

Page 8

Scenario NRC0202 Rev. 0, 4/22/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 8 of 17 File No. R11-3

Page 9

Scenaro NRC0202 Rev. 0, 4/22/2002 11 SCENARIO REFERENCES

1. SHIFT CONTROL ROD DRIVE PUMPS OP-155-001 OP-AD-004 CONTROL ROD DRIVE HYDRAULIC SYSTEM OPERATIONS STANDARDS FOR ERROR AND EVENT PREVENTION

2. POWER DECREASE CORE REACTIVITY CONTROL BOOK OP-AD-338 COMMUNICATION REQUIREMENTS FOR REACTIVITY MANIPULATIONS O0-AD-029 EMERGENCY LOAD CONTROL GO-100-012 POWER MANEUVERS

3. TRIP OF RFPT'A' ON-145-001 ON-164-002 RPV LEVEL CONTROL SYSTEM MALFUNCTION LOSS OF RECIRCULATION FLOW

4. RECIRC FLOW UNIT FAILURE DOWNSCALE ON-164-001 AR-103-001 T.S. 3.3.1.1 RECIRC DRIVE FLOW INSTRUMENT FAILURE RPS DIV 1 lC651 RPS INSTRUMENTATION

5. LOSS OF CRD ON-1 55-007 T.S. 3.1.5 AR-107-D02 ON-100-101 LOSS OF CRD SYSTEM FLOW CONTROL ROD ACCUMULATORS CRD PUMP 'B' TRIP SCRAM

6. ATWS I LEVEUPOWER CONTROL / RPV CONTROL EO-100-102 EO-100-113 OP-184-001 ES-158-001 RPV CONTROL LEVEL POWER CONTROUCONTROL ROD INSERTION MAIN STEAM SYSTEM DE-ENERGIZING SCRAM PILOT SOLENOIDS

7. RAPID DEPRESSURIZATION / PRIMARY CONTAINMENT CONTROL EO-100-112 EO-100-103 OP-149-005 RAPID DEPRESSURIZATION PRIMARY CONTAINMENT CONTROL RHR OPERATION IN SUPPRESSION POOL COOLING MODE Form STCP-QA-612A Rev. 1, (05/01)

Page 9 of 17 File No. R11-3

Page 10 Scenado NRC0202 Rev. 0, 4/22/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 10 of 17 File No. R11-3

Page 11 Scenario NRC0202 Rev. 0, 4/22/2002 l1 SCENARIO SPECIAL INSTRUCTIONS

1. Initalize the simulator to IC-20, both Units at 100% power EOL..

2. Set up the simulator for the scenario by performing the following:

Shut-HPCI F002 and F003 valves, place the Flow Controller in MAN set at 0%, and place the Div I/Il inop switches to inop. Depressurize steam header.

Place status control pink tags on HPCI F002 and F003.

3. Type restorepref YPP.NRC0202; verify that the following pre-inserts and Program Button assignments.

Also verity that the Environment window shows I Event Trigger active:

bat HPB.HPCIOOS SIMULATES HPCI OOS IMF TC1 93025 ALL TBVs FAILED CLOSED IMF BR05:1A10104 AUX BUS 11A BKR FAILURE IMF BR05:1A10204 AUX BUS 11B BKR FAILURE TRG El SLC.STRTSW SLC START SWITCH IN START IMF PM03:1P208A (El 3:00 0)

A SLC PUMP MOTOR SHORT CIRCUIT IMF PM05:1P208B 18 SLC PUMP SHAFT SHEAR IMF RC150002 1000 RCIC SPEED CONTROL FAILURE, 1000 RPM EP-1] MRF RD155014 0

[P-21 MRF RD155014 100

[P-3] IMF FW145009A

[P-4] IMF NMI78012D

[P-51 MRF NM178008 ZERO

[P-6] bat RPB.ATWS-ELEC P-7] bat YPB.NRC0202A

[P-8] bat YPB.NRC0202B

[P-9] bat RPB.ES158001A

[P-10] bat RPB.ES158001B HV-146F0148 CLOSED HV-146F014B OPEN

'A' RFPT TRIP

'D' FLOW UNIT FAIL DNSC

'D' FLOW UNIT TO ZERO FAILURE TO SCRAM LOSS OF CRD/4 ACCUMULATOR ALARMS MAIN TURBINE TRIP ES-158-001 DIV 1 FUSES PULLED ES-158-001 DIV 2 FUSES PULLED

4. Prepare a turnover sheet indicating:

a. Unit 1 and Unit 2 are at 100% power EOL.

b. HPCI is out of service for governor valve adjustments. The system will not be returned to service this shift.

c. Perform a swap of CRD pumps to allow maintenance to record vibration data on 'B' CRD pump.

d. A minimum generation alert has been issued for the PJM network.

5. Prepare an LCO sheet identifying that HPCI has been out of service for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Form STCP-QA-612A Rev. 1, (05/01)

Page 11 of 17 File No. R11-3

Page 12 Scenario NRC0202 Rev. 0, 4/22/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 12 of 17 File No. R11-3

Page 13 Scenaro NRC0202 Rev. 0, 4/22/2002 SCENARIO EVENT DESCRIPTION FORM Initial Conditions: Initialize the Simulator to IC-20. Place the Simulator to RUN. Ensure the Program Buttons are mccinnari !c jnrj!i2t&r1 nn tho SZnojr-in Inctnfrsi4nnc ch--f -., thV Ar4-OLII.J

=;lA AIPO lul -L.:,"

+;A Direct the start of the 5 minute Danel walkdown.

EVENT_.4 TIME DESCRIPTION-1 SWAP IN SERVICE CRD PUMPS.

2 DECREASE POWER 100MWe.

3 TRIP OF RFPT 'A'.

4 RECIRC FLOW UNIT FAILURE DOWNSCALE.

5 LOSS OF CRD FLOW WITH INOPERABLE ACCUMULATORS.

6 FAILURE TO SCRAM, ATWS.

7 SLC SYSTEM FAILURE.

8 MAIN TURBINE TRIP.

9 RCIC SPEED CONTROL FAILURE 10 LOSS OF AUX BUSES i1A/11B.

I Form STCP-QA-612A Rev. 1, (05/01)

Page 13 of 17 File No. R11-3

Page 14 Scenario NRC0202 Rev. 0, 4/22/2002 SCENARIO EVENT FORM Event No:

I Brief

Description:

SWAP IN SERVICE CRD PUMPS POSITION TIME STUDENT ACTIVITIES US Direct PCO to place 'B' CRD pump in service and shutdown the 'A' CRD pump.

PCOP Implements OP-1 55-001, Section 3.1 0.

Directs Plant Operator to verify oil levels Direct Plant Operator to close 'B' discharge valve 146F014B Place 'B' CRD control switch to RUN Direct Plant Operator to slowly open 146F01 4B Verify proper CRD flow and pressure indications.

Place 'A' CRD control switch to STOP.

US Notify maintenance that 'B' CRD pump is in service.

Denotes Critical Task NOTES:

Form STCP-QA-612A

Page 15 Scenario NRC0202 Rev. 0, 4/22/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, II AND INSTRUCTOR'S PERSONAL NOTES Event No:

I Brief

Description:

SWAP IN SERVICE CRD PUMPS NOTE: Monitor P & ID RD1.

INSTRUCTOR ACTIVITY:

If directed to close 'B' CRD pump discharge valve 146F014B, Depress P-1:

[P-1] MRF RD155014 0 When directed to reopen 146F014B, Depress P-2:

[P-2] MRF RD1 55014 100 ROLE PLAY:

As Plant Operator at the CRD pumps: oil levels in the motor and speed increaser are normal.

Form STCP-QA-612A Rev. 1, (05/01)

Page 15 of 17 File No. R1 1-3

Page 16 Scenario NRC0202 Rev. 0, 4/22/2002 SCENARIO EVENT FORM Event No:

2 Brief

Description:

DECREASE POWER IOOMWe POSITION TIME STUDENT ACTIVITIES US Direct the power reduction.

Brief the crew for the upcoming reactivity evolution.

Direct implementation of Reactor Engineering Instru-tions in the CRC Book.

Direct implementation of GO-1 00-012, POWER MANEUVERS.

PCOM Decreases reactor power as directed by the US and CRC Book.

Plots power changes on the power to flow map.

PCOP Notifies GCC when the power reduction is complete.

US Makes notifications IAW OP-AD-002, STANDARDS FOR SHIFT OPERATIONS.

4 I

I4 I4

Denotes Critical Task

[NOTES:

Form STCP-QA-612A Rev. 1, (05101)

Page 16 of 17 File No. R11-3

Page 17 Scenario NRC0202 Rev. 0, 4/22/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, I

AND INSTRUCTOR'S PERSONAL NOTES Event No:

2 Brief

Description:

DECREASE POWER IOOMWe INSTRUCTOR-ACTIVITY:

After'B' CRD pump is in service call SSES as GCC and state a Minimum Generation Emergency is issued and SSES Unit 1 should decrease generation by 100 MWe as soon as possible.

ROLE PLAY:

As necessary.

Form STCP-QA-612A Rev. 1, (05/01)

Page 17 of 17 File No. R11-3

Page 18 Scenario NRC0202 Rev. 0, 4/22/2002 SCENARIO EVENT FORM Event No:

3 Brief

Description:

TRIP OF RFPT 'A' POSITION TIME STUDENT ACTIVITIES PCOM Report trip of 'A' RFP.

Reports RPV water level is decreasing and feedwater system response.

Implements AR-1 01-Al 0, RFPT 'A' TRIP.

Dispatches a Plant Operator to investigate the cause of the trip.

Refers to ON-145-001, determines no actions are applicable.

Directs Plant Operator to remove hydrogen injection to RFP 'A' using OP-1 45-002.

Implements AR-1 01-F1 1, RFP A BRG OIL LO PRESS.

US Directs implementation of ON-145-001, RPV WATER LEVEL MALFUNCTION.

Contacts FIN Team/maintenance to investigate the cause of the trip.

Make notifications IAW OP-AD-002, STANDARDS FOR SHIFT OPERATIONS.

PCOM Reports Recirc pump runback, Limiter #2.

Checks power to flow map; determines plant is not operating in a restricted region.

Implements ON-164-002, LOSS OF RECIRCULATION FLOW.

Selects a control rod to monitor for core flux oscillations.

US Directs performance of ON-164-002, LOSS OF RECIRCULATION FLOW.

Contacts Reactor Engineering for assistance.

Notifies Health Physics and Chemistry groups of power change.

Denotes Critical Task

[NOTES:

Form STCP-QA-612A Rev. 1, (05101)

Page 1 8 of 17 File No R11-3

Page 19 Scenario NRC0202 Rev. 0, 4/22/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY,

.I AND INSTRUCTOR'S PERSONAL NOTES I

Event No:

3 Brief

Description:

TRIP OF RFPT 'A' INSTRUCTOR-ACTIVITY:

When generator output has been reduced by 10OMWe insert a trip of RFPT 'A', Depress P-3:

[P-3] IMF FW145009A ROLE PLAY:

As Plant Operator sent 'A' RFP wait 2 mins. and report no abnormal conditions are visible around the pump or turbine.

As FIN Team or maintenance sent to 'A' RFP wait 10 minutes and report the turbine trip circuit is energized but the reason has not yet been identified. We will continue to investigate and let you know about any further developments.

As Reactor Engineering, report that you will run the Thermal Monitor and then come to the control room with any instructions or recommendations.

Form STCP-QA-612A Rev. 1, (05/01)

Page 19 of 17 File No. R11-3

Page 20 Scenario NRC0202 Rev. 0, 4/22/2002 SCENARIO EVENT FORM Event No:

4 Brief

Description:

RECIRC FLOW UNIT FAILURE DOWNSCALE POSITION TIME STUDENT ACTIVITIES PCOM Reports RPS half scram condition on Division 2.

Determines neutron monitoring caused the half scram.

Determines a flow unit has failed.

Implements ON-164-001, RECIRC DRIVE FLOW INSTRUMENT FAILURE.

Dispatches a Plant Operator to LRR to investigate to flow unit status.

US Directs implementation of ON-164-001, RECIRC DRIVE FLOW INSTRUMENT FAI LURE.

Contacts EWAC/maintenance to investigate the flow unit failure.

Directs bypassing 'D' flow unit on panel 1 C651 using the joystick.

Directs placing the 'D' flow unit mode switch to ZERO.

Directs resetting the division 2 RPS half scram signal.

Refers to T.S 3.3.1.1, RPS INSTRUMENTATION.

Make notifications IAW OP-AD-002, STANDARDS FOR SHIFT OPERATIONS.

PCOM Bypasses 'D' flow unit with the joystick as directed.

Directs the Plant Operator to place the mode switch to ZERO positions for 'D' flow unit.

Resets RPS half scram.

Denotes Critical Task

[NOTES:

D Form STCP-QA-612A Rev. 1, (05/01)

Page 20 of 17 File No. R11-3

Page 21 Scenario NRC0202 Rev. 0, 4/22/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

4 Brief

Description:

RECIRC FLOW UNIT FAILURE DOWNSCALE INSTRUCTOR-ACTIVITY:

When the plant is stable after the recirc flow runback insert the 'D' Recirc flow unit failure downscale, Depress P-4:

[P-4] IMF NM178012D

'D' RECIRC FLOW UNIT DNSC When directed to place the 'D' flow unit to ZERO in the LRR, Depress P-5:

[P-5J MRF NM178008 ZERO

'D' FLOW UNIT TO ZERO ROLE PLAY:

As Plant Operator sent to LRR Panel 1C608 wait 2 mins. report all flow unit mode switches are in operate and flow unit 'D' has downscale indication.

If asked about additional indications, the following exist:

Amber compare light is ON for flow units 'C' and 'D'.

Along the top of panel 1 C608:

White FLOW UNIT COMPARATOR lights are ON for 'C' and 'D' flow units.

Red UPSC THERM TRIP lights are ON for all Div 2 APRMs.

Red THERM FIRST lights are ON for all Div 2 APRMs.

Amber UPSC lights are ON for all Div 2 APRMs.

As FIN Team/maintenance acknowledge the direction to investigate the flow unit failure. No other feedback will be provided.

Form STCP-QA-612A Rev-1, (05/01)

Page 21 of 17 File No. R11-3

Page 22 Scenario NRC0202 Rev. 0, 4/22/2002 SCENARIO EVENT FORM Event No:

5 Brief

Description:

LOSS OF CRD FLOW WITH INOPERABLE ACCUMULATORS POSITION TIME STUDENT ACTIVITIES PCOP Reports trip of 'B' CRD pump.

Refer to AR-1 07-D02, CRD PUMP 'B' TRIP.

Implements ON-1 55-007, LOSS OF CRD SYSTEM FLOW.

Closes flow control valve FV-146FO02 using FC-C12-1 R600 in MANUAL.

Attempts to START 'A' CRD pump.

Reports 'A' CRD pump failed to start.

Dispatches a Plant Operator to check breakers IA20107 AND 1A20407.

Reports charging water header pressure.

PCOM Reports control rod accumulator trouble alarms.

Reports all trouble alarms are for withdrawn control rods.

Dispatches a Plant Operator to the HCU to report status.

US Directs implementation of ON-155-007, LOSS OF CRD SYSTEM FLOW.

Contacts FIN Team/maintenance to investigate the accumulator troubles.

Directs placing mode switch to S/D within 20 minutes when two or more accumulator are determined inoperable for withdrawn control rods with steam dome pressure >900 psig.

Refers to T.S. 3.1.5, Control Rod Accumulators.

Make notifications IAW OP-AD-002, STANDARDS FOR SHIFT OPERATIONS.

PCOM Places Mode Switch to Shutdown, informs US of failure to scram.

Denotes Critical Task l

NOTES:l Form STCP-QA-612A Rev. 1, (05/01)

Page 22 of 17 File No. R11-3

Page 23 Scenario NRC0202 Rev. 0, 4122/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

5 Brief

Description:

LOSS OF CRD FLOW WITH INOPERABLE ACCUMULATORS INSTRUCTOR-ACTIVITY:

NOTE: Before continuing the scenario insert the failure to scram, Depress P-6:

[P-6] bat RPB.ATWS-ELEC After RPS half scram is RESET insert a loss of CRD system flow and several control rod accumulator trouble alarms, Depress P-7:

[P-7] bat YPB.NRC0202A NOTE: Times for accumulator alarms are:

Rod 46-47 45 seconds Rod 38-39 2 minutes Rod 10-19 2 minutes 30 seconds Rod 14-23 3 minutes ROLE PLAY:

As Plant Operator sent to 'B' CRD pump breaker 1A20407 wait 2 mins. and report over current relay 50/51 has a target dropped.

As Plant Operator sent to 'A' CRD pump breaker 1A20107 wait 2 mins. report no abnormal conditions exist on the breaker.

As Plant Operator sent to HCUs for accumulator trouble alarms report pressures less than 900 psig for rod 46-47, rod 38-39, rod 10-19, and rod 14-23.

NOTE: In order to avoid a long time delay in candidate activities, make it clear that neither pump appears to be capable for return to service any time soon.

Form STCP-QA-612A Rev. 1, (05/01)

File No. R11-3 Page 23 of 17

Page 24 Scenario NRC0202 Rev. 0, 4/22/2002 SCENARIO EVENT FORM Event No:

6, 7 Brief

Description:

ATWS I SLC FAILURE POSITION TIME STUDENT ACTIVITIES PCOM Inserts manual scram via Scram Pushbuttons, reports continued failure to scram.

Initiates ARI, reports failure to scram via ARI.

US Enters EO-000-1 02, RPV CONTROL, exits EO-1 00-102 and enters EO-1 00-113, LEVEL POWER CONTROL.

Directs initiating SLC and inhibiting ADS.

PCOP Initiates SLC, notifies US of SLC system problems.

Inhibits ADS.

US Directs RPV level lowered to,-60" but >-161".

Directs establishing RPV level target band of -60" to -11 0".

Directs bypassing MSIV and CIG interlocks.

Directs overriding RCIC injection.

PCOM Lowers and controls RPV level to <-60" but >-161" using available injection systems (FW/Condensate).

Attempts to establish RPV level in target band of -60" to -11 o0.

PCOP Bypasses MSIV and CIG interlocks IAW OP-1 84-001, MAIN STEAM SYSTEM.

Denotes Critical Task NOTES:

I-l Form STCP-QA-612A Rev. 1, (05/01)

Page 24 of 17 File No. R11-3

Page 25 Scenario NRC0202 Rev. 0, 4/22/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

6, 7 Brief

Description:

ATWS / SLC FAILURE / MT TRIP / LOSS OF AUX BUSES IIA/11B INSTRUCTORACTIVITY:

Ensure event trigger activates to trip 'A' SLC pump 3 minutes after start.

IMF PM03:1P208A (El 3:00 0)

A SLC PUMP MOTOR SHORT CIRCUIT ROLE PLAY:

As NPO directed to investigate SLC pumps, wait -3 minutes and report the A pump is not running (do not give this report until the pump has tripped) and the motor appears to have some scorching; the B pump motor is running but the shaft is sheared.

Form STCP-QA-612A Rev. 1, (05/01)

Page 25 of 17 File No. R11-3

Page 26 Scenario NRC0202 Rev. 0, 4/22/2002 SCENARIO EVENT FORM Event No:

8,9,10 Brief

Description:

MT TRIP I RCIC SPEED CTL FAILURE / LOSS OF AUX BUSES lIA/IIB POSITION TIME STUDENT ACTIVITIES

US Directs control rods inserted IAW EO-1 00-113 Sheet 2, CONTROL ROD INSERTION.

Directs implementation of ES-158-001, DE-ENERGIZING SCRAM PILOT SOLENOIDS.

Directs venting of Scram Air Header.

Directs SLC injection with RCIC IAW ES-1 50-002.

PCOM Informs US of main turbine trip and TBV failure to open.

Recognizes/reports loss of feedwater, condensate and CW systems.

PCOM/P Directs Plant Operator to vent scram air header.

PCOP Reports Aux Buses 11A/11B are de-energized.

US Directs Electrical Maintenance to investigate Aux Bus problem.

PCOP Attempts to maintain level between -60" and -161" with RCIC.

Recognizes/reports RCIC speed control malfunction.

Recognizes/reports RPV level can no longer be maintained >-161".

Denotes Critical Task NOTES:

NOTE: US may not direct ES-1 50-002 due to RCIC speed control problems.

l Form STCP-QA-612A Rev. 1, (05/01)

Page 26 of 17 File No. R11-3

Page 27 Scenario NRC0202 Rev. 0, 4/22/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

8, 9,10 Brief

Description:

MT TRIP / RCIC SPEED CTL FAILURE / LOSS OF AUX BUSES IIA/IIB INSTRUCTOR ACTIVITY:

When RPV water level is lowered into the target band insert a trip of the main turbine, Depress P4:

[P-8] bat YPB.NRC0202B MAIN TURBINE TRIP NOTE: When main generator lockout occurs the Aux Buses 1 1A/11 B should fail to transfer and will de-energize and cause a loss of feedwater and condensate.

NOTE: The above file also deletes the Accumulator Fault malfunctions so that all rods can be fully inserted later in the scenario.

ROLE PLAY:

1. As Electrical Maintenance if directed to investigate Aux Bus breaker problem, wait -3 minutes and inform crew that a bus fault is present; you are continuing to investigate.

2. As NPO directed to vent the Scram Air Header, wait -3 minutes and report that you are unable to get the cap off of the 147007 valve's vent line and that the cap appears to be galled; you request Mechanical maintenance assistance.

3. As OSC/AUS directed to perform ES-150-002, acknowledge the direction and perform no further actions.

Form STCP-QA-612A Rev. 1, (05/01)

Page 27 of 17 File No. R11-3

Page 28 Scenario NRC0202 Rev. 0, 4/22/2002 SCENARIO EVENT FORM Event No:

8, 9,10 Brief

Description:

MT TRIP / RCIC SPEED CTL FAILURE /LOSS OF AUX BUSES IIA/IIB POSITION TIME STUDENT ACTIVITIES

US Directs all injection stopped and prevented except from RCIC.

PCOMIP Stops and prevents all injection except from RCIC.

US Enters EO-1 00-112, RAPID DEPRESSURIZATION.

Directs that Suppression Pool level is verified >5'.

Directs Rapid Depressurization by opening all ADS SRVs.

PCOM/P Verifies Suppression Pool level >5'.

Rapidly depressurizes reactor by opening ADS SRVs valves.

US Directs slowly restoring RPV level to -60" to -161" with LPCI.

PCOM/P Slowly restores RPV level to -60" to -161" with LPCI.

Denotes Critical Task

[

NOTES:

l1 Form STCP-QA-612A Rev. 1, (05/01)

Page 28 of 17 File No. R11-3

Page 29 Scenario NRC0202 Rev. 0, 4/22/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

8,9,10 Brief

Description:

MT TRIP / RCIC SPEED CTL FAILURE I LOSS OF AUX BUSES 11A/11B INSTRUCTOR ACTIVITY:

None.

ROLE PLAY:

As necessary.

Form STCP-QA-612A Rev. 1, (05/01)

Page 29 of 17 File No. R11-3

Page 30 Scenario NRC0202 Rev. 0, 4/22/2002 SCENARIO EVENT FORM Event No:

8,9,10 Brief

Description:

MT TRIP / RCIC SPEED CTL FAILURE I LOSS OF AUX BUSES IlA/IIB POSITION TIME STUDENT ACTIVITIES

PCOP Inserts control rods IAW EO-1 00-113 Sheet 2.

Coordinates ES-1 58-001 with AUS/NPO.

Verifies indications as Div 1 RPS fuses are pulled.

Verifies control rod insertion as Div 2 RPS fuses are pulled.

Verifies all rods fully inserted; informs US.

US Directs SLC injection terminated, restores ES-1 50-002.

Exits EO-1 00-113 Sheets 1 and 2; re-enters EO-1 00-102.

Directs establishing water level +13" to +54".

PCOM Establishes water level +13" to +54" with LPCI.

US Enters EO-1 00-1 03, PRIMARY CONTAINMENT CONTROL.

Directs both loop of RHR placed in Suppression Pool Cooling.

PCOM/P Places both loops of RHR in Suppression Pool Cooling IAW OP-149-005, RHR OPERATION IN THE SUPPRESSION POOL COOLING MODE.

Denotes Critical Task

[

NOTES:

Form STCP-QA-612A Rev. 1, (05/01)

Page 30 of 17 File No. RI1-3

Page 31 Scenario NRC0202 Rev. 0, 4/2212002 INSTRUCTOR ACTIVITIES, ROLE PLAY, I

AND INSTRUCTOR'S PERSONAL NOTES Event No:

Brief

Description:

8, 9,10 MT TRIP / RCIC SPEED CTL FAILURE I LOSS OF AUX BUSES IIA/M1B When RPV water level is restored >-161" following RD proceed with pulling RPS fuses.

ROLE PLAY:

As Operator dispatched to perform ES-158-001, wait -2 minutes and report that you are ready to pull the Div 1 RPS fuses.

INSTRUCTOR ACTIVITY:

Pull Div 1 RPS fuses, Depress P-9:

[P-9] bat RPB.ES158001A ES-158-001 DIV 1 FUSES PULLED ROLE PLAY:

As Operator call the control room and report you have completed pulling Div 1 RPS fuses and you are now going to the LRR to pull Div. 2 fuses at this time.

INSTRUCTOR ACTIVITY:

When RPV level is stabilized at <-60" but >-161" following Rapid Depressurization, pull Div 2 RPS fuses to complete ES-158-001, Depress P-10:

[P-10] bat RPB.ES158001B ES-158-001 DIV 2 FUSES PULLED ROLE PLAY:

As Operator, wait -2 minutes and report that RPS Div 2 fuses have been pulled and ES-158-001 is now completed.

TERMINATION CUE:

When all control rods are inserted and actions are in progress to restore RPV water level to +13" to +54",

the scenario may be terminated.

Form STCP-QA-612A Rev. 1, (05101)

Page 31 of 17 File No. R11-3

UNIT SUPERVISOR TURNOVER SHEET UNIT:

1 Date: July 30, 2002 SHIFT 1900 to 0700 SHIFT 0700 to 1900 Start End Start End MODE 1

POWER LEVEL 100 GENERATOR OUTPUT 1151 MWe MODE POWER LEVEL GENERATOR OUTPUT MWe

1.

HPCI is out of service for governor valve adjustments. The system will not be returned to service this shift.

2.

Perfrom a swap of CRD pumps to allow maintencance to record vibration data on 'B' CRD pump.

3.

A minimum generation alert has been issued for the PJM network.

4.

Unit 2 is in MODE 1 at 100% power EOL.

5.

Chemistry/Rx Engineering investigating Off Gas System spike observed during last Control Rod Exercising Surveillance COMMON:

Form OP-AD-003-7, Rev.3, DUPLEX, Page 1 of 2 (File Number R5-5)

PP&L-SUSQUEHANNA TRAINING CENTER SIMULATOR SCENARIO Scenario

Title:

NRC INITIAL LICENSE OPERATOR EXAMINATION Scenario Duration:

2 Hours Scenario Number: NRC0203 Revision/Date:

Rev 0, 4/2312002 Course:

PCO17, NRC Initial License Operator Examination Operational Activities:

1. Transfer SUB 10 to SUT 10

5. Loss of Instrument Air

2. Increase Reactor Power

6. Recirc Loop Suction Line Break

3. FW Flow Transmitter Failure Low

7. Auto ADS Logic Failure

4. Steam Leak Detection Failure i HPCI ISOL

8. HV-151-F015B Auto-Open Failure Prepared By:

Instructor Date Reviewed By:

6/oz Nucl rKa ions Training Supervisor Date Approved By:

Pet, 7-_2o9-0 Supervising Manager/Shift Servisor Date Form STCP-QA-612A Rev. 1, (05/01)

Page 1 of 27 File No. R11-3

Page 2 Scenario NRC0203 Rev. 0, 4/23/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 2 of 27 File No. R11-3

Page 3 Scenario NRC0203 Rev. 0, 4/23/2002 SCENARIO

SUMMARY

Unit 1 is 50% power, Unit 2 is MODE 4. Power ascension was suspended while maintenance performed an inspection of Start Up Transformer 10 following inadvertent fire system deluge actuation. Start Up Bus 10 is supplied from Start Up Bus 20 with the tie breaker OA1 0502 closed. Standby Liquid Control Pump 1 B is inoperable while maintenance investigates a high motor vibration. Maintenance has completed the inspection of Start Up Transformer 10, the crew will restore the electric plant line up to normal by transferring Start Up Bus 10 to Start Up Transformer 10.

The crew will continue with power ascension by pulling control rods and raise power -1 0%.

The 'B' feedwater flow transmitter fails low causing the feedwater level control system to raise RPV water level to z+44".The crew will perform Off-Normal procedures and transfer from 3 element to single element control with feedwater control being returned to automatic control. RPV water level should be restored to +35".

A failure in the Steam Leak Detection System causes the HPCI Steam Supply Outboard Isolation Valve HV-155-F003 to automatically close making the HPCI system inoperable. HPCI will not be restored.

After the Steam Leak Detection problem the Instrument air header will develop a leak. The leak will be unisolable and worsen over time. The crew will implement the Loss of Instrument Air Off-Normal procedure and manually scram the reactor before instrument air header pressure reaches 65 psig.

Following the manual scram and stabilization of plant parameters, a small Recirculation Loop suction line break will occur requiring the crew to enter and perform the action of the Primary Containment Control procedure. Shortly after the crew initiates Suppression Chamber Spray the leak will increase in size and will eventually require the crew to rapidly depressurize the RPV due to water level reaching TAF. The high Drywell temperature and depressurized plant conditions cause violation of the RPV Saturation temperature curve, requiring the crew to perform RPV Flooding. Fuel Zone water level may decrease below the useable value limit of -290" which also requires entry into RPV Flooding. The injection valve on the 'B' loop of RHR will fail to auto-open; the crew will be required to manually open the valve in order to achieve flooding pressure.

When RPV Flooding pressure has been achieved the scenario will be terminated.

Form STCP-QA-612A Rev. 1, (05/01)

File No. R11-3 Page 3 of 27

Page 4

Scenario NRC0203 Rev. 0, 4/23/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 4 of 27 File No. R11-3

Page 5

Scenario NRC0203 Rev. 0, 4/23/2002 l1 SCENARIO OBJECTIVES The USISS will:

1. Inform other shift members and plant management of changes in plant status, potential plant problems or limitations. (00.AD.131)

2. Implement appropriate portions of Reactivity Management and Controls program. (O0.AD.047)

3. Implement control of LCOs, TROs, and Safety Function Determination program. (0Q.AD.273)

4. Ensure that required actions per Technical Specifications are met when a LCO is not met. (O0.TS.002)

5. Implement Alarm Response procedures. (00.AR.005)

6. Implement Loss of Instrument Air. (18.ON.003)

7. Implement scram. (00.ON.018)

8. Implement RPV Control. (00.EO.026)

9. Implement Primary Containment Control. (0O.EO.027)

10. Implement Rapid Depressurization. (0O.EO.030)

11. Implement RPV Flooding. (OO.EO.032)

12. Ensure that required actions per Technical Specifications are met when a LCO is entered.

(OO.TS.003)

13. Shutdown the reactor when it is determined reactor safety is in jeopardy, or when operating parameters exceed any RPS setpoint and scram does not occur. (00.AD.131)

The PCOs will:

1. Perform overriding RHR injection. (49.OP.011)

2. Implement Alarm Response procedures. (O0.AR.005)

3. Perform LPCI injection through heat exchanger. (49.OP.013)

4. Perform RHR operation in Containment Spray Mode. (49.OP.005)

5. Perform automatic/manual startup of RCIC system. (51.OP.010)

6. Perform Division 1(2) response during automatic initiation. (51.OP.007)

7. Perform overriding CS injection. (51.OP.004)

8. Perform maximizing CRD flow. (55.OP.001)

9. Perform manual operation of ADS. (83.OP.001)

10. Perform Loss of Instrument Air. (18.ON.003)

11. Perform Scram. (00.ON.018)

12. Perform RPV Control. (0O.EO.026)

13. Perform Primary Containment Control. (0O.EO.027)

14. Perform Rapid Depressurization. (00.EO.030)

15. Perform RPV Flooding. (00.EO.032)

Form STCP-QA-612A Rev. 1, (05/01)

File No. R1 1-3 Page 5 of 27

Page 6 Scenaro NRC0203 Rev. 0, 4/23/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 6 of 27 File No. R11-3

Page 7

Scenario NRC0203 Rev. 0, 4/23/2002 CRITICAL TASKS l

Performs Rapid Depressurization when RPV level drops to -161".

Performs RPV Flooding when RPV water level becomes indeterminate by increasing injection flowrate to raise RPV pressure 81 psig above Suppression Chamber pressure.

Manually opens RHR F015B valve to inject to the RPV.

Denotes Simulator Critical Task Form STCP-QA-612A Rev. 1, (05/01)

File No. R11-3 Page 7 of 27

Page 8

Scenario NRC0203 Rev. 0, 4/23/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 8 of 27 File No. R1 1-3

Page 9

Scenaro NRC0203 Rev. 0, 4/23/2002 I~

SCENARIO REFERENCES

1. TRANSFER STARTUP BUS 10 TO STARTUP TRANSFORMER 10 OP-003-001 OP-AD-004 13.8KV COMMON ELECTRICAL EQUIPMENT OPERATIONS STANDARDS FOR ERROR AND EVENT PREVENTION

2. POWER ASCENSION CORE REACTIVITY CONTROL BOOK GO-100-002 PLANT STARTUP, HEATUP AND POWER OPERATION OP-AD-338 COMMUNICATION REQUIREMENTS FOR REACTIVITY MANIPULATIONS

3. FEEDWATER FLOW TRANSMITTER 'B' FAILS LOW ON-145-001 AR-101-B117 RPV LEVEL CONTROL SYSTEM MALFUNCTION RX WATER HI-LO LEVEL

4. STEAM LEAK DETECTION FAILURE / HPCI ISOLATION AR-1 14-C02 AR-1 14-FO5 AR-1 14-802 T.S. 3.5.1 T.S. 3.2.6 HPCI TURBINE TRIP SOLENOID ENERGIZED HPCI LEAK DETECTION LOGIC 'B' HI TEMP HPCI OUT OF SERVICE ECCS OPERATING PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION

5. LOSS OF INSTRUMENT AIR AR-124-AO1 AR-124-B01 ON-1 18-001 ON-100-101 INSTRUMENT AIR LOOP A LO PRESSURE INSTRUMENT AIR HEADER LO PRESSURE LOSS OF INSTRUMENT AIR SCRAM

6. RECIRC LOOP 'B' SUCTION LINE BREAK EO-000-102 EO-000-1 03 OP-149-004 AR-1 12-D03 AR-104-103 EO-100-112 EO-100-114 RPV CONTROL PRIMARY CONTRAINMENT CONTROL RHR OPERATION IN CONTAINMENT SPRAY MODE DW/SUPP CHAMBER HIILOW PRESSURE PRI CONTAINMENT HI.LOW PRESSURE RAPID DEPRESSURIZATION RPV FLOODING Form STCP-QA-612A Rev. 1, (05/01)

Page 9 of 27 File No. R11-3

Page 10 Scenario NRC0203 Rev. 0, 4/23/2002 Form STCP-QA-612A Rev. 1, (05101)

Page 10 of 27 File No. R11-3

Page 11 Scenario NRC0203 Rev. 0, 4/23/2002 SCENARIO SPECIAL INSTRUCTIONS

1. Initialize the simulator to IC-16, (170 for NRC Exam) Unit 1 at 50% power EOL. Unit 2 is 100% power EOL.

2. Set up the simulator for the scenario by performing the following:

a. Remove SUT 10 from service.

Supply SUB 10 from SUB 20 with the tie breaker OA10502 dosed.

Open SUT 10 MOAB 1R105.

Transfer 4KV buses to SUB 20.

b. Perform GO-100-002 step 6.71.

3. Type restorepref YPP.NRC0203; verify that the following pre-inserts and Program Button assignments.

Also verity that the Environment window shows 0 Event Trigger active:

MRF DB106723 OPEN BKR FOR 1 B SLC PUMP OPEN IMF MV06:HV151F015B RHR INJ F015B FAILS TO AUTO OPEN IMF RLI0:B21C1K5A DIV 1 ADS AUTO LOGIC FAILURE IMF RLI01 :B21 C1 K5B DIV 2 ADS AUTO LOGIC FAILURE

[P-1] IMF TR02:FTC321 N002B 0 0 2.5 FW FLOW XMTR 'B' FAILS LOW

[P-2] IMF TH02:TEE41N24B 350 0 74 TSH-E41-1N006B FAILS HIGH -HPCI AREA

[P-3] IMF IA11802 5 IA COMMON HEADER RUPTURE - 5%

[P-4] MMF IA1 1802 201A COMMON HEADER RUPTURE - 20%

[P-5] IMF RR16401 1 B 0.5 300 RECIRC LOOP 'B' SUCTION LINE BRK - 0.5%

[P-6] MMF RR16401IB 403000.5 RECIRC LOOP 'B' SUCTION LINE BRK-40%

[P-7] MMF RR164011B 5 120 40 RECIRC LOOP 'B' SUCTION LINE BRK-5%

4. Prepare a turnover sheet indicating:

a. Unit 1 is at 50% power, Unit 2 is at 100% power EOL.

b.

Power ascension on Unit 1 was suspended while maintenance performs an inspection of Startup Transformer 10 following inadvertent fire system deluge actuation.

c. Startup Transformer 1 0 has been out of service for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , 4KV ESS buses were transferred to Startup Bus 20.

d. Startup Bus 10 is supplied from Startup Bus 20 with the tie breaker OA10502 closed.

e. Maintenance has completed the inspection of Start Up Transformer 10, all permits have been cleared, restore the electric plant line up to normal by transferring Start Up Bus 10 to Start Up Transformer 10.

Form STCP-QA-612A Rev. 1, (05/01)

File No. R11-3 Page 11 of 27

Page 12 Scenario NRC0203 Rev. 0, 4/23/2002 SCENARIO SPECIAL INSTRUCTIONS Continued:

f. When the electric plant is returned to normal, continue with the power ascension starting at GO-100-002 step 6.72 and Start up rod sequence B-2 at step 538. Notify Reactor Engineering at 65%

reactbf power.

g. SLC pump 1 B is out of service while maintenance investigates high motor vibration.

5. Prepare an LCO sheet identifying that Startup Transformer 10 has been out of service for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

6. Prepare an LCO sheet identifying that SBLC has been out of service for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

K --.

Form STCP-QA-612A Rev. 1, (05/01)

Page 12 of 27 File No. R11-3

Page 13 Scenario NRC0203 Rev. 0, 4/23/2002 SCENARIO EVENT DESCRIPTION FORM Initial Conditions: Initialize the Simulator to IC-16. Place the Simulator to RUN. Ensure the Prooram Buttons are assigned as indicated on the Special Instructions sheet via the aPpropriate Preference File. Assign Shift positions.

Direct the start of the 5 minute panel walkdown.

EVENT TIME DESCRIPTION 1

TRANSFER SUB 10 TO SUT 10 2

CONTINUE POWER ASCENSION 3

FEEDWATER FLOW TRANSMITTER 'B' FAILS LOW 4

STEAM LEAK DETECTION FAILURE I HPCI ISOLATION 5

LOSS OF INSTRUMENT AIR 6

RECIRC LOOP 'B' SUCTION LINE BREAK 7

AUTO ADS LOGIC FAILURE 8

LOOP 'B' RHR INJECTION VALVE HV-151 F01 5B FAILS TO AUTO-OPEN Form STCP-QA-612A Rev. 1, (05/01)

Page 13 of 27 File No. R11-3

Page 14 Scenario NRC0203 Rev. 0, 4/23/2002 SCENARIO EVENT FORM Event No:

1 Brief

Description:

TRANSFER SUB 10 TO SUT 10 POSITION TIME STUDENT ACTIVITIES US Direct PCO to transfer Startup Bus 10 to Startup Transformer 10.

PCOP Implements OP-003-001, 13.8KV COMMON ELECTRICAL EQUIPMENT, Section 3.8 Closes MOAB 1 R1 05.

Places SU XFMR 10 TO BUS 10 SYNC SEL HS-00014 to ON.

Closes breaker OA10301.

Verifies Tie Breaker OA01 0502 OPENS.

Places SU XFMR 10 TO BUS 10 SYNC SEL HS-00014 to OFF.

Aligns all control switch flags to actual breaker position.

t I

S I

I A

I I

Denotes Critical Task NOTES:

Form STCP-QA-612A Rev. 1, (05/01)

Page 14 of 27 File No. R11-3

Page 15 Scenario NRC0203 Rev. 0, 4/23/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES l

Event No:

I Brief

Description:

TRANSFER SUB 10 TO SUT 10 INSTRUCTOR ACTIVITY:

None.

ROLE PLAY:

As necessary.

Form STCP-QA-612A Rev. 1, (05/01)

Page 15 of 27 File No. R11-3

Page 16 Scenario NRC0203 Rev. 0, 4/23/2002 SCENARIO EVENT FORM Event No:

2 Brief

Description:

CONTINUE POWER ASCENSION POSITION TIME STUDENT ACTIVITIES US Direct the power ascension.

Brief the crew for the upcoming power increase.

Direct implementation of Reactor Engineer Instruction in the CRC Book.

Direct the implementation of GO-1 00-102, PLANT STARTUP, HEATUP AND POWER OPERATION.

PCOM Increases reactor power as directed by the US and CRC Book.

Plots power change on the power to flow map.

Maintains Load Set =100 MWe above existing load.

PCOP Notifies GCC before the power increase begins.

US Makes notifications IAW OP-AD-002, STANDARDS FOR SHIFT OPERATIONS.

Denotes Critical Task NOTES:

Form STCP-QA-612A Rev. 1, (05/01)

Page 16 of 27 File No. R11-3

Page 17 Scenario NRC0203 Rev. 0, 4/23/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

2 Brief

Description:

CONTINUE POWER ASCENSION INSTRUCTOR ACTIVITY:

None.

ROLE PLAY:

As necessary Form STCP-QA-612A Rev. 1, (05/01)

Page 17 of 27 File No. R11-3

Page 18 Scenario NRC0203 Rev. 0, 4/23/2002 SCENARIO EVENT FORM Event No:

3 Brief

Description:

FEEDWATER FLOW TRANSMITTER 'B' FAILS LOW POSITION TIME STUDENT ACTIVITIES PCOM Reports AR-101-B17, RX WATER HI-LO LEVEL.

Reports RPV level has increased and is now controlling at = +45".

Recognizes/reports 'B' FW Flow indication is zero.

Us Directs actions of ON-145-001, RPV LEVEL CONTROL SYSTEM MALFUNCTION.

Directs placing FWLC in MAN, then Single Element, then back to AUTO to return RPV level to +35".

Directs l&C to investigate 'B' Feedwater Flow instrumentation failure.

Contacts Reactor Engineering for 'B' FW Flow instrument failure impact on core thermal power calculation.

Directs monitoring OG and MSL radiation levels due to reactor power spike.

PCOM Places Master FWLC Controller LIC-C32-1 R600 in MAN.

Places FWLC in Single Element by depressing Green pushbutton HS-1 06102.

Nulls Master FWLC Controller, places controller in AUTO, and slowly restore RPV level to +35".

PCOP Monitors OG and MSL radiation levels at 1 C600 as directed.

Denotes Critical Task

~NOTES:

]

Form STCP-QA-612A Rev. 1, (05/01)

Page 18 of 27 File No. R11-3

Page 19 Scenario NRC0203 Rev. 0, 4/23/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

3 Brief

Description:

FEEDWATER FLOW TRANSMITTER 'B' FAILS LOW INSTRUCTOR-ACTIVITY:

When reactor power is raised to z 60%, or when directed by Chief Examiner, insert a 'B' FW flow transmitter failure low, Depress P-1:

[P-1] IMF TR02:FTC321NO02B 0 0 2.5 ROLE PLAY:

1. As l&C sent to investigate 'B' FW Flow Instrumentation failure, wait 3 mins. and report the transmitter is failed and will require repair or replacement. I will provide a time estimate for repairs as soon as one is available.

2. As Reactor Engineering, report that I will run a Thermal Monitor and report the results as soon as they are available.

3. Note this event may be affected by the time schedule of the leading edge flow meter implementation schedule.

Form STCP-QA-612A Rev. 1, (05/01)

File No. R11-3 Page 19 of 27

Page 20 Scenario NRC0203 Rev. 0, 4/23/2002 SCENARIO EVENT FORM Event No:

4 Brief

Description:

STEAM LEAK DETECTION FAILURE / HPCI ISOLATION POSITION TIME STUDENT ACTIVITIES PCOP Reports AR-11 4-FO5, HPCI LEAK DETECT LOGIC B Hi TEMP.

Reports AR-114-C02, HPCI TURBINE TRIP SOLENOID ENERGIZED.

Reports AR-1 14-B05, HPCI OUT OF SERVICE.

Reports HPCI STM SUPPLY OB ISO valve HV-155-F003 is CLOSED.

l Reports PUMP SUCT FROM SUPP POOL valve HV-155-F42 is CLOSED.

Determines TSH-E41-1 N600B is tripped and indicates 3500F.

Dispatch a Plant Operator to HPCI Equipment Room to investigate potential high temperature condition using appropriate safety precautions.

US Contacts I&C to investigate TSH-E41-1 N600B.

Declares HPCI System inoperable.

Refers to T.S. 3.5.1, ECCS OPERATING - Condition 'D'.

Makes notifications lAW OP-AD-002, STANDARDS FOR SHIFT OPERATIONS.

Denotes Critical Task

[

NOTES:

0 Form STCP-QA-612A Rev. 1, (05/01)

Page 20 of 27 File No. R11-3

Page 21 Scenario NRC0203 Rev. 0, 4/23/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

4.

Brief

Description:

STEAM LEAK DETECTION FAILURE I HPCI ISOLATION INSTRUCTOR ACTIVITY:

When the Master FW Controller is restored to AUTO inert a Steam Leak Detection Failure and HPCI auto isolation, Depress P-2:

[P-2] IMF TH02:TEE411 N24B 350 0 74 ROLE PLAY:

1. As Plant Operator sent to investigate HPCI Equipment Area wait 2 mins. and report all conditions in the HPCI room are normal.

2. A l&C sent to investigate TE-E41-1 N600B acknowledge the direction to investigate, no further actions will be taken.

Form STCP-QA-612A Rev. 1, (05/01)

Page 21 of 27 File No. R11-3

Page 22 Scenario NRC0203 Rev. 0, 4/23/2002 SCENARIO EVENT FORM Event No:

5 Brief

Description:

LOSS OF INSTRUMENT AIR POSITION TIME STUDENT ACTIVITIES PCOP Reports lowering Instrument Air pressure.

Respond to AR-124-EO1, SERVICE AIR LO PRESS and AR-124-A01, INSTRUMENT AIR LOOP A LO PRESSURE.

Dispatches a Plant Operator to investigate IA system.

Implements ON-i 18-001, LOSS OF INSTRUMENT AIR.

US Enter ON-1 00-101, SCRAM and directs Scram Imminent Actions as air pressure decreases.

PCOP Shifts Aux Buses 11 A/i1 B to S/U Buses.

PCOM Reduces recirc flow to ; 65 Mlbm/hr.

Starts MSOP and TGOP.

US Directs PCOM to scram the reactor prior to IA header pressure reaching 65 psig.

PCOM Places Mode Switch to Shutdown.

Performs actions of ON-1 00-1 01, SCRAM.

Inserts SRMs and IRMs.

Trips Main Turbine at 150 MWe.

US Enters EO-1 00-102, RPV CONTROL.

Directs RPV level maintained + 13" to + 54" with available systems.

Directs RPV pressure stabilized <1087 psig.

Denotes Critical Task NOTES:l Form STCP-QA-612A Rev. 1, (05/01)

Page 22 of 27 File No. R11-3

Page 23 Scenario NRC0203 Rev. 0, 4/23/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

5 Brief

Description:

LOSS OF INSTRUMENT AIR INSTRUCTORACTIVITY:

When the crew has completed addressing Steam Leak Detection System Failure and HPCI Isolation insert an instrument air leak, Depress P-3:

[P-3] IMF IA118002 5 IA COMMON HEADER RUPTURE -5%

ROLE PLAY:

As Plant Operator sent to IA, wait 2 mins. and report that all IA and SA compressors are running, the SA cross tie appears to be operating normally but IA pressure is slowly decreasing. If asked, inform the crew that I will investigate the system for a possible leak.

INSTRUCTOR ACTIVITY:

When the US directs the crew to perform Scram Imminent Actions increase the severity of the rupture to 20%, Depress P4:

[P-4] MMF IA118002 20 IA COMMON HEADER RUPTURE - 20%

ROLE PLAY:

As Plant Operator sent to IA, report that I have located a large air leak at the common IA header piping just downstream of the receivers; I do not see any way to isolate the leak, and header pressure is dropping rapidly.

Form STCP-QA-612A Rev. 1, (05/01)

Page 23 of 27 File No. R11-3

Page 24 Scenario NRC0203 Rev. 0, 4/23/2002 SCENARIO EVENT FORM Event No:

6, 7 Brief

Description:

RECIRC LOOP 'B' SUCTION LINE BREAK I AUTO ADS LOGCIC FAILURE POSITION TIME STUDENT ACTIVITIES PCOP Reports increasing Drywell pressure and temperature.

US Enters EO-1 00-103, PRIMARY CONTAINMENT CONTROL.

Directs initiation of Suppression Chamber Sprays.

PCOP Sprays the Suppression Chamber IAW OP-149-004, RHR OPERATION IN CONTAINMENT SPRAY.

Reports rapidly decreasing RPV water level.

US Re-enters EO-1 00-1 02 due to high Drywell pressure.

Directs injection with available systems.

PCOP Attempts to maintain RPV water level + 13" to + 54" with RCIC.

Verifies initiations, isolations, and DG starts as directed.

Injects with available systems as directed.

Reports RPV water level is approaching/at - 161".

Reports failure of automatic ADS function.

US Directs rapid depressurization when RPV level drops to - 161".

When RPV level decreases to - 161", enters EO-1 00-1 12, RAPID DEPRESSURIZATION Directs opening of all ADS SRVs.

Denotes Critical Task NOTES:

Form STCP-QA-612A Rev. 1, (05/01)

Page 24 of 27 File No. R1 1-3

Page 25 Scenario NRC0203 Rev. 0, 4/23/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY,

.E AND INSTRUCTOR'S PERSONAL NOTES Event No:

6, 7 Brief

Description:

RECIRC LOOP 'B' SUCTION LINE BREAK I AUTO ADS LOGCIC FAILURE INSTRUCTOR ACTIVITY:

When the crew scrams the reactor and RPV water level is stable at + 13" to + 54", initiate a small break inside the primary containment, Depress P-5:

[P-5J IMF RR164011B 0.5 300 RECIRC LOOP B SUCTION LINE BREAK-.5%

When the crew has commenced Suppression Chamber Spray, increase the severity of the recirc loop rupture to 40%, Depress P-6:

[P-6] MMF RR164011B 40300 0.5 RECIRC LOOP B SUCTION LINE BREAK - 40%

ROLE PLAY:

As necessary.

Form STCP-QA-612A Rev. 1, (05/01)

Page 25 of 27 File No. R11-3

Page 26 Scenario NRC0203 Rev. 0, 4/23/2002 SCENARIO EVENT FORM Event No:

8 Brief

Description:

RHR F015B FAILS TO AUTO-OPEN POSITION TIME STUDENT ACTIVITIES

PCOP Rapidly depressurizes reactor by opening all ADS SRVs.

US Determines RPV water level instrumentation is no longer valid due to violation of the Saturation Curve.

Note 1 Recognizes that RPV water level cannot be determined due to violating the RPV Saturation Curve: Exits EO-100-102 and Enters EQ-1 00-114, RPV FLOODING.

Directs RPV Flooding when RPV water level becomes indeterminate by increasing injection flowrate to raise RPV pressure to 81 psid above Suppression Chamber pressure.

Note 2 Directs that injection be increased to maximum with available systems to raise reactor pressure to 81 psid above Suppression Chamber pressure.

PCOP Increases injection to maximum with available systems to raise reactor pressure to 81 psid above Suppression Chamber pressure.

Recognizes/reports RHR F01 5B failed to auto-open.

Manually opens RHR F01 5B to inject to the vessel.

Controls injection flowrate to maintain RPV Flooding Pressure.

Denotes Critical Task NOTES:

NOTE 1: Fuel Zone level may decrease <-290" requiring entry into RPV Flooding.

NOTE 2: Crew must terminate containment sprays and direct all ECCS flow to the RPV in order to establish RPV Flooding pressure.

I-.-

Form STCP-QA-612A Rev. 1, (05/01)

Page 26 of 27 File No. R11-3

Page 27 Scenario NRC0203 Rev. 0, 4/23/2002 Al INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES I

Event No:

8 Brief

Description:

RHR F015B FAILS TO AUTO-OPEN INSTRUCTOR ACTIVITY:

When the crew has commenced RPV flooding, decrease the size of the Recirc rupture to allow achieving flooding pressure, Depress P-7:

MMF RR16401 lB 5 12040 RECIRC LOOP B SUCTION LINE BREAK - 5%

ROLE PLAY:

As necessary.

TERMINATION CUE:

When RPV Flooding Pressure is established, the scenario will be terminated.

Form STCP-QA-612A Rev. 1, (05/01)

File No. R11-3 Page 27 of 27

UNIT SUPERVISOR TURNOVER SHEET UNIT:

1 Date: July 24. 2002 SHIFT 1900 to 0700 SHIFT 0700 to 1900 Start End Start End MODE 1

MODE POWER LEVEL 50 POWER LEVEL GENERATOR OUTPUT 503 MWe GENERATOR OUTPUT MWe

1. Power ascension on Unit 1 was suspended while maintenance performs an inspection of Start Up Transformer 10 following Inadvertent fire system deluge actuation.

2. Start Up TransfQrmer 10 has been out of service for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , 4 KV ESS buses were transferred to Start Up Bus 20.

3. Start Up Bus 10 is supplied from Statrt Up Bus 20 with breaker OA10502 closed.

Maintenance has completed the inspection of Start Up Transformer 10, all permits have been cleared.

Restorethe electric plant line up to normal bytransferring Start Up Bus 10 to Start Up Transformer 10 lAW OP-003-001 Section 3.8.

DO NOT transfer 4Kv buses to normal lineup until Maintenance calls back and and concurs with that activity.

5. When the electric plant is returned to normal, continue with the power ascension starting at GO-100-002 step 6.72 and Start up rod sequence B2 at step 538. Notify Reactor Engineering at 65% reactor power.

6. SLC pump 1B is out of service while maintenance investigates high motor vibration.

7.

Unit 2 is in MODE 1 at 100% power EOL.

COMMON:

Form OP-AD-003-7, Rev.3, DUPLEX, Page 1 of 2 ( File Number R5-5)

Y PP&L-SUSQUEHANNA TRAINING CENTER SIMULATOR SCENARIO Scenario

Title:

NRC INITIAL LICENSE OPERATOR EXAMINATION Scenario Duration:

2 Hours Scenario Number: NRC0204 Revision/Date:

Rev 0, 412412002 Course:

PCO17, NRC Initial License Operator Examination Operational Activities:

1. Secure RHRSW Pump 1A

5. Generator Lockout I Turbine Trip

2. RHRSW Rad Monitor Fails Upscale

6. RPS 'B' Failure to Trip I ATWS

3. Loss of Iso Phase Bus Duct Cooling

7. Squib Valves Fail

4. Power Reduction

8. 'A' EHC Pump Trip Prepared By:

Instructor Date Reviewed By:

/o2 Nucl erations Training Supervisor Date Approved By:

7-Za 9* go Supervising Manager/Shift Supftfisor Date Form STCP-QA-612A Rev. 1, (05/01)

Page 1 of 27 File No. R11-3

Page 2

Scenario NRC0204 Rev. 0, 4/24/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 2 of 27 File No. R11-3

Page 3

Scenario NRC0204 Rev. 0, 4/24/2002

-1 SCENARIO

SUMMARY

The scenario begins with Unit 1 at 90% power EOL and Unit 2 at 100% power EOL. EHC pump 1 B is out of service for breaker maintenance. RHR loop 'A' has just been secured from Suppression Pool Cooling and RHRSW pump is running for maintenance to record vibration data. The crew will shutdown 1A RHR SW pump._

Following shutdown of 1A RHRSW the RHRSW radiation monitor will fail upscale. The crew will direct Chemistry to obtain a grab sample of RHRSW to validate the indicated high radiation condition. The US will declare the RHRSW radiation detector inoperable and enter T.R. 3.11.1.5.

The in service Iso Phase Bus Cooling Fan will trip, investigation will determine repairs will take a minimum of 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months . Bus duct temperature will increase, the crew will decrease generator output to <19,000 amps lAW Alarm Response and Operating procedures.

After the generator output is reduced to <19,000 amps a main generator lockout trip will occur. A failure of RPS 'B' to trip will result in an Electrical ATWS and all control rods will fail to insert. ARI will not properly actuate, further inhibiting control rod insertion. When the crew will initiates SLC a failure of the squib valves to fire will prevent SLC injection. The crew will initiate action to inject boron with the RCIC system and inhibit ADS. The crew will decrease core power by lowering RPV water level to < -60" but > -161" using feedwater. A loss of EHC pump 1A will result in a loss of EHC hydraulic fluid pressure causing the TBVs to close; SRV operation will raise Suppression Pool Water temperature requiring the crew to enter Primary Containment Control procedure and maximize Suppression Pool Cooling. Actuation of SRVs will eventually cause Drywell pressure to increase > 1.72 psig resulting in a loss of Condensate and Feedwater injection due to initiation of Plant Aux Load Shed circuitry; the crew will restore and maintain RPV water level with HPCI and RCIC systems.

The crew will be unsuccessful at rod insertion by maximizing CRD and drifting control rods. Manually driving rods and venting the scram air header will be successful for rod insertion.

When all control rods have been inserted and actions are in progress to maximize Suppression Pool Cooling and restore RPV water level to +13" to +54" the scenario will be terminated.

Form STCP-QA-612A Rev. 1, (05/01)

File No. R 1 1-3 Page 3 of 27

Page 4 Scenaro NRC0204 Rev. 0, 4/24/2002 THIS PAGE IS INTNTJONAU..Y LEFT BLANK Form STCP-QA-612A Rev. 1, (05/01)

Page 4 of 27 File No. R1 1-3

Page 5 Scenario NRC0204 Rev. 0, 4/24/2002 l1 SCENARIO OBJECTIVES The USISS will:

1. Inform other shift members and plant management of changes in plant status, potential plant problems or limitations. (0O.AD.131)

2. Implement appropriate portions of reactivity management & control program. (00.AD.017)

3. Ensure that required actions per Technical Specifications are met when a LCO is not met.

(00.TS.002)

4. Implement control of LCOs, TROs, and Safety Function Determination Program. (00.AD.273)

5. Shutdown the reactor when it is determined Reactor safety is in jeopardy, or when operating parameters exceed any RPS setpoint and scram does not occur. (0Q.AD.031)

6. Implement Alarm Response procedures. (Q0.AR.005)

7. Implement Scram. (00.ON.018)

8. Implement ATWS. (00.ON.026)

9. Implement RPV Control. (00.EO.026)

10. Implement Level/Power Control. (00.EO-031)

11. Implement Primary Containment Control. (0O.EO.027)

12. Implement HPCI Suction Auto Transfer Bypass. (52.EO.009)

13. Implement Boron Injection with RCIC. (50.EO.009)

14. Implement RCIC Turbine Isolation and Trip Bypass. (50.EO.008)

The PCOs will:

1. Perform RHRSW System shutdown - Unit 1 Pump to Unit 1 Heat Exchanger. (16.OP.011)

2. Implement Alarm Response procedures. (00.AR.005)

3. Perform RHRSW Radiation Monitor Failure.

4. Perform Removal of Iso Phase Bus Duct Fan Motor From Service. (87.OP.002)

5. Perform a 10% power change with rods/recirc flow. (Q0.GO.012)

6. Perform maximizing CRD flow. (55.OP.001)

7. Perform initiation of Standby Liquid Control System. (53.OP.003)

8. Implement inhibiting ADS. (83.OP.005)

9. Implement Main Turbine Trip. (93.ON.006)

10. Implement Scram. (00.ON.018)

11. Implement ATWS. (00.ON.026

12. implement RPV Control. (00.EO.026)

13. Implement Level/Power Control. (00. EO-03 1)

14. Implement Primary Containment Control. (00.EO.027)

15. Perform normal operation of RHR in Suppression Pool Cooling mode. (49.OP.003)

16. Implement HPCI Suction Auto Transfer Bypass. (52.EO.009)

17. Implement Boron Injection with RCIC. (50.EO.009)

18. Implement RCIC Turbine Isolation and Trip Bypass. (50.EO.008)

Form STCP-QA-612A Rev. 1, (05/01)

File No. R11-3 Page 5 of 27

Page 6 Scenario NRC0204 Rev. 0, 4/24/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 6 of 27 File No. R11-3

Page 7 Scenario NRC0204 Rev. 0, 4/24/2002 CRITICAL TASKS Lowers RPV water level to <-60" but >-161" using available injection systems.

InsertsControl Rods lAW EO-100-1 13, Sheet 2, Control Rod Insertin.g Denotes Simulator Critical Task Form STCP-QA-612A Rev. 1, (05/01)

Page 7 of 27 File No. R11-3

Page 8

Scenaro NRC0204 Rev. 0, 4/24/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 8 of 27 File No. R11-3

Page 9 Scenario NRC0204 Rev. 0, 4/24/2002 1r SCENARIO REFERENCES 1.

1. SECURE RHRSW PUMP 1A OP-116-001 T.R. 3.8.2.1 OP-AD-004 RHR SERVICE WATER MOV THERMAL OVERLOAD PROTECTION - CONTINUOUS OPERATIONS STANDARDS FOR ERROR AND EVENT PREVENTION

2. RHRSW RAD MONITOR FAILS UPSCALE AR-109-FOl RHRSWA HI RADIATION

3. LOSS OF ISO PHASE BUS DUCT COOLING AR-106-G09 AR-106-H09 OP-1 87-001 ON-000-005 ISOPHASE BUS COOLER MOTOR TRIP ISO PHASE BUS PANEL 1C172 TROUBLE ISO PHASE BUS DUCT COOLING SYSTEM HOT WEATHER

4. POWER REDUCTION GO-100-012 POWER MANEUVERS CORE REACTIVITY CONTROL BOOK OP-AD-338 COMMUNICATION REQUIREMNETS FOR REACTIVITY MANIPULATIONS

5. GENERATOR LOCKOUT / TURBINE TRIP ON-100-101 EO-100-102 SCRAM RPV CONTROL

6. RPS 'B' FAILS TO TRIP / ATWS / SQUIB VALVES FAIL / A EHC PUMP TRIP OP-AD-002 EO-100-113 ES-1 50-002 ES-1 52-002 ES-1 50-001 ES-158-001-AR-106-103 EO-1 00-1 03 OP-1 49-005 STANDARDS FOR SHIFT OPERATIONS LEVEL POWER CONTROL / CONTROL ROD INSERTION BORON INJECTION WITH RCIC BYP HPCI SUCT SWAP BYP RCIC LO PRESS ISO DE-ENERGIZING SCRAM PILOT SOLENOIDS EHC HYD FLUID PUMP DSCH LO PRESS PRIMARY CONTAINMENT CONTROL RHR OPERATION IN SUPPRESSION POOL COOLING MODE Form STCP-QA-612A Rev. 1, (05/01)

Page 9 of 27 File No. R11-3

Page 10 Scenaro NRC0204 Rev. 0, 4/24/2002 Form STCP-QA-612A Rev. 1, (05101)

Page 10 of 27 File No. R11-3

Page 11 Scenario NRC0204 Rev. 0, 4/24/2002 l

SCENARIO SPECIAL INSTRUCTIONS

1. Set up the simulator for the scenario by performing the following:

a. Initialize the simulator to IC-20, both Units at 100% power EOL.

b. Insert rods to step 555, adjust TCF for -90% power.

c.

PlaceTA RHRSW pump in service per OP-I 16-001.

d. Place RHRSW radiation monitor in service.

e.

Place ESW I/S, start ESW pumps A & B.

f.

Place handswitch to STOP for 1 B EHC pump.

2. Take a snapshot to a saved IC.

3. Initialize the simulator to IC-1 65.

4. Type restorepref YPP.NRC0204; verify that the following pre-inserts and Program Button assignments.

Also verity that the Environment window shows 1 Event Trigger active:

MRF PMOII PM113B OUT IMF PM01:IPI13B IMF RP158007B IMF SLI53001A IMF SLI53001B IMF RL03:63X114725D1 IMF RL03:63X214725D1 TRG El BAAA26409 TRG El = MRF RD155023 0

[P-1] IMF TR02:RITS11216A

[P-2] IMF PM03:1KI09A

[P-3] DMF PM03:1KI09A

[P-4] IMF EG198004

[P-5] MRF RD155023 0

[P-6] IMF PM03: I P1 3A 1 B EHC PUMP BKR RACKED OUT 1B EHC BKR CONTROL POWER RPS'B FAIL TO TRIP SQUIB VLAVE 'A' FAIL SQUIB VLAVE 'A' FAIB ARI FAILURE ARI FAILURE EVENT TRIGGER - MODE SWITCH TO SHUTDOWN THROTTLE CRD MAN ISO CLOSED WHEN El IS TRUE IE+6 0 27 RHRSW RM 'A' FAIL UPSCALE ISO PHASE BUS DUCT COOLING FAN 'A' TRIP DELETE ISO PHASE BUS DUCT COOLING FAN 'A' TRIP GENERATOR LOCKOUT TRIP THROTTLE CRD MAN ISO CLOSED 1A EHC PUMP TRIP

[P-7] MRF HP152007 BYPASS ES-152-002, BYP HPCI SUCT SWAP

[P-8] bat RDB.VSAH VENT SCRAM AIR HEADER

[P-9] bat RDB.RSAH RESTORE SCRAM AIR HEADER Form STCP-QA-612A Rev. 1, (05/01)

Page 11 of 27 File No. R11-3

Page 12 Scenario NRC0204 Rev. 0, 4/24/2002 SCENARIO SPECIAL INSTRUCTIONS

5. Prepare a turnover sheet indicating:

a. Unit-I is at 90% power EOL, Unit 2 is at 100% power EOL.

b. 1 B EHC pump is out of service for breaker maintenance and will not be returned to service this shift.

c. RHR Loop 1A has just been secured from Suppression Pool Cooling and RHRSW pump 1A is running for vibration data. Vibration recording is complete, shutdown RHRSW.

d. ESW pumps A & B are in service to support Suppression Pool Cooling operation.

6. Prepare a TRO sheet for bypassing RHRSW overloads lAW OP-1 16-001.

7. Prepare an OD-7 for the current rod pattern.

8. Prepare an OP-AD-338, Attachment E "CONTROLLED SHUTDOWN / UNPLANNED POWER REDUCTION" form. Enter 65 in step S-3 and enter 555 in step S-4 3).

9. Prepare a modified page 1 of the Shutdown Control Rod Sequence 82 in the CRC Book. Remove rod steps 561 through 556 on page 01.

10. Insert the OD-7; OP-AD-338, Attachment E; and page 01 of the Shutdown Control Rod Sequence B2 into the CRC Book on the PCOs desk.

11. Prepare an OP-149-005, Attachment C entry for the Special Log Book for biocide injection. Indicate injection was performed 4 days previous to today, the exam date.

12. Make a copy of shift assignments.

Form STCP-QA-612A Rev. 1, (05/01)

Page 12 of 27 File No. R11-3

Page 13 Scenario NRC0204 Rev. 0, 4/24/2002 SCENARIO EVENT DESCRIPTION FORM Initial Conditions: Initialize the Simulator to IC-1 65. Place the Simulator to RUN. Ensure the Program Buttons are zignnd asz indicated on the p rinel InPztmctionn s-heet Pin thi P

nnrnnrinfa Pn.firPrnrm Mnl AeiiJP nn PIhPfifpjtin Direct the start of the 5 minute panel walkdown.

EVENT' TIME I

DESCRIPTION I

SECURE RHRSW PUMP 1A 2

RHRSW RAD MONITOR FAILS UPSCALE 3

LOSS OF ISO PHASE BUS DUCT COOLING 4

POWER REDUCTION 5

GENERATOR LOCKOUT I TURBINE TRIP 6

RPS 'B' FAILURE TO TRIP / ATWS 7

SQUIB VALVES FAIL 8

1A EHC PUMP TRIP Form STCP-QA-612A Rev. 1, (05/01)

Page 13 of 27 File No. R11-3

Page 14 Scenario NRC0204 Rev. 0, 4/24/2002 SCENARIO EVENT FORM Event No:

1 Brief

Description:

SECURE RHRSW PUMP 1A POSITION TIME STUDENT ACTIVITIES US Directs shutdown of 1A RHRSW pump.

Complies with T.R. 3.8.2.1, MOV THERMAL OVERLOAD PROTECTION -

CONTINUOUS.

PCOP Implements OP-116-001, RHR SERVICE WATER.

Verifies the last biocide injection date in the Special Log Book.

Notifies US to comply with T.R. 3.8.2.1.

Places motor overload bypass switch HS-1 121 OAIto TEST on 0C697.

Reduces RHRSW flow to 1500gpm by throttling closed HV-1 121 OA.

Stops RHRSW pump 1 P506A.

Closes HX Inlet valve HV-1 121 OA.

Closes HX Outlet valve HV-1 1215A.

After 2 minutes returns motor overload bypass switch HS-1 1210A1 to OPERATE on 0C697.

Ensures RHRSW pump Supply Fan 1V506A STOPS.

4 4

4.

4

4.

4 J.

4.

Denotes Critical Task NOTES:

I Form STCP-QA-612A Rev. 1, (05/01)

Page 14 of 27 File No. R11-3

Page 15 Scenario NRC0204 Rev. 0, 4/24/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

I Brief

Description:

SECURE RHRSW PUMP 1A INSTRUCTOR ACTIVITY:

None.

ROLE PLAY:

As necessary.

Form STCP-QA-612A Rev. 1, (05/01)

Page 15 of 27 File No. R11-3

Page 16 Scenario NRC0204 Rev. 0, 4/24/2002 SCENARIO EVENT FORM Event No:

2 Brief

Description:

RHRSW RAD MONITOR FAILS UPSCALE POSITION TIME STUDENT ACTIVITIES PCOP Reports alarm AR-1 09-F01, RHR SW A Hi RADIATION.

Refers to AR-1 09-F01, RHR SW A Hi RADIATION. -

Checks indication for RR-D12-1 R606 on 1C600.

Dispatches Plant Operator to check operation of indicator and trip unit RITS-1 1216A.

US Notify Chemistry to obtain grab sample.

Contact I&C to investigate RHRSW Rad Monitor problem.

Refers to T.R. 3.11.1.5, RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION.

Declares RHRSW Rad Monitor inoperable; enters Condition B or T.R. 3.11.1.5.

Make notifications IAW OP-AD-002, STANDARDS FOR SHIFT OPERATIONS.

Denotes Critical Task NOTES:

I II I]

Form STCP-QA-612A Rev 1, (05/01)

Page 16 of 27 File No. R11-3

Page 17 Scenario NRC0204 Rev. 0, 4/2412002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

2 Brief

Description:

RHRSW RAD MONITOR FAILS UPSCALE INSTRUCTOR ACTIVITY:

When 1A RHRSW pump is stopped wait -30 seconds and insert RHRSW radiation monitor failure upscale, Depress P-1.

[P-I] IMF TR02:RITS1216A 1 E+6 0 27 RHRSW RM 'A' FAIL UPSCALE ROLE PLAY:

As Chemistry contacted to obtain a grab sample of Unit 1 RHRSW acknowledge the request to obtain a grab sample. No further information will be provided.

As Plant Operator sent to the indicator and trip unit wait 2 mins. and report that high radiation condition is indicated.

As I&C acknowledge the request to investigate the RHRSW radiation monitor. No further information will be provided.

Form STCP-QA-612A Rev. 1, (05/01)

Page 17 of 27 File No. R11-3

Page 18 Scenario NRC0204 Rev. 0, 4/24/2002 SCENARIO EVENT FORM Event No:

3,4 Brief

Description:

LOSS OF BUS DUCT COOLING I REDUCE GENERATOR CURRENT <19,000 AMPS POSITION TIME STUDENT ACTIVITIES PCOM Reports alarm AR-106-G09, ISOPHASE BUS COOLER MOTOR TRIP.

Reports alarm AR-1 06-H09, ISO PHASE BUS PANEL 1C172 TROUBLE.

Verifies iso phase bus cooling fan tripped on PICSY format and/or indication lights on 11C668.

Dispatches a Plant Operator to check breaker 1 BI 01121 closed.

Directs plant Operator to reset breakeri B1 01121 thermal overloads.

Refers to OP-187-001, ISO PHASE BUS DUCT COOLING SYSTEM.

Directs plant Operator to monitor/report bus duct temperature.

Refers to ON-000-005, HOT WEATHER.

US Contacts FIN TEAM/Maintenance to investigate the loss of bus duct cooling.

Directs generator output lowered to <19,000 amps.

Contacts Reactor Engineering about the power reduction.

Directs power reduction using instructions from the CRC Book.

Makes notifications lAW OP-AD-002, STANDARDS FOR SHIFT OPERATIONS.

Notify Chemistry/Health Physics power changed by 15%.

Notify System Engineer to perform temperature trending and evaluation.

PCOM Reduces generator output to <19,000 amps as directed.

Plots power changes on the power to flow map.

Maintains core flow >65 mlbmlhr.

Implements GO-100-012, POWER MANEUVERS.

PCOP Notify GCC power reduction is required due to loss of Iso Phase Bus Duct Cooling.

Denotes Critical Task fNOTES:

]

Form STCP-QA-612A Rev. 1, (05/01)

Page 18 of 27 File No. R11-3

Page 19 Scenario NRC0204 Rev. 0, 4/24/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

3, 4 Brief

Description:

LOSS OF BUS DUCT COOLING I REDUCE GENERATOR CURRENT <19,000 AMPS INSTRUCTOR ACTIVITY:

1. When actions are complete for RHRSW Rad Monitor failure insert a loss of iso phase bus duct cooling, Depress P-2:

[P-2] IMF PM03:1KI09A ISO PHASE BUS DUCT COOLING FAN 'A' TRIP Monitor P&ID EC1 and/or LP1C172 for indications and alarm status.

2. If directed to reset the thermal overloads on breaker 1BlOl121, Depress P-3:

[P-3] DMF PM03:IK109A DELETE ISO PHASE BUS DUCT COOLING FAN 'A' TRIP then wait 15 seconds and trip the Iso Phase Bus Duct Cooling Fan, Depress P-2:

[P-2] IMF PM03:1K109A ISO PHASE BUS DUCT COOLING FAN 'A' TRIP ROLE PLAY:

As Plant Operator sent to 1C172 wait 2 mins. and report that the 'A' fan was selected as lead fan and it is not running. I have 3 annunciators in alarm:

HIGH BUS TEMPERATURE HIGH TEMPERATURE RETURN AIR LOW AIR SUPPLY NOTE:

High Bus Temperature setpoint is 180'F.

High Temperature Return Air setpoint is 1 85*F.

If temperature data is requested monitor P&ID ECI and report data as indicated.

As Plant Operator sent to breaker 1 B1 01121 wait 2 mins. and report the breaker is not tripped. If requested to reset the thermal overloads report they tripped almost immediately after resetting.

As maintenance sent to investigate the loss of bus duct cooling wait 5 mins. and report the cooling fan appears to be binding and the drive belts are showing abnormal wear. A minimum of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is required to repair/replace the cooling fan.

Form STCP-QA-612A Rev. 1, (05101)

File No. R11-3 Page 19 of 27

Page 20 Scenario NRC0204 Rev. 0, 4/24/2002 SCENARIO EVENT FORM Event No:

Brief

Description:

5,6,7,8 GENERATOR LOCKOUT TRIP / RPS 'B' FAIL TO TRIP / SQUIB VALVES FAIL /I1A EHC PUMP TRIP

POSITION, TIME STUDENT ACTIVITIES PCOM Reports scram condition and 'B' RPS failure to trip.

Places mode switch to SHUTDOWN.

Arms and depresses man scram initiation pushbuttons.

Reports failure of control rods to insert.

Inserts SRMs and IRMs.

Reports generator lockout and main turbine trip condition.

PCOP Initiates ARI, reports ARI has failed.

Ensures Isolations, Initiations, and Diesel Generator starts.

US Enters EO-100-012, RPV CONTROL and exits to EO-1 00-113, LEVEL POWER CONTROL.

Directs SLC initiated and ADS inhibited.

Directs insertion of control rods IAW EO-1 00-113 Sht. 2, CONTROL ROD INSERTION.

PCOP Initiates SLC, reports SLC is not injecting.

Inhibits ADS.

US Directs boron injection with RCIC lAW ES-1 50-002, BORON INJECTION WITH RCIC.

Directs lowering RPV water level to< - 60" but > - 161" with a target level band of -

60" to - 11 o0 with available systems.

Directs overriding HPCI and RCIC system injection.

Directs Bypassing MSIV and CIG interlocks.

Contacts maintenance to investigate SLC system problem.

Denotes Critical Task L NOTES:

Form STCP-QA-612A Rev. 1, (05/01)

Page 20 of 27 File No. R 1 1-3

Page 21 Scenario NRC0204 Rev. 0, 4/24/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

5, 6, 7, 8 Brief

Description:

GENERATOR LOCKOUT TRIP I RPS 'B' FAIL TO TRIP I SQUIB VALVES FAIL /1A EHC PUMP TRIP INSTRUCTOR ACTIVITY:

When the generator output is reduced to <19,000 amps insert a generator lockout, Depress P-4:

[P-4] IMF EG198004 GENERATOR LOCKOUT TRIP When the mode switch is placed to SHUTDOWN, verify that event trigger actuates to cause the CRD Pressure throttling valve manual isolation valve to fail closed preventing drifting control rods with CRD.

NOTE: If trigger El fails to actuate, Depress P-5 to cause the CRD Pressure throttling valve manual isolation valve to fail closed preventing drifting control rods with CRD.

[P-51 MRF RD155023 0 THROTTLE CRD MAN ISO CLOSED One minute after the mode switch is placed to SHUTDOWN insert a trip of 1A EHC pump, Depress P-6:

[P-6] IMF PM03:1PI13A 1A EHC PUMP TRIP ROLE PLAY:

As necessary.

Form STCP-QA-612A Rev. 1, (05/01)

Page 21 of 27 File No. R11-3

Page 22 Scenario NRC0204 Rev. 0, 4/24/2002 SCENARIO EVENT FORM Event No:

5, 6, 7, 8 Brief

Description:

GENERATOR LOCKOUT TRIP I RPS 'B' FAIL TO TRIP I SQUIB VALVES FAIL /1A EHC PUMP TRIP POSITION TIME STUDENT ACTIVITIES

PCOM Lowers RPV water level to <- 60" but > -161" using feedwater.

PCOP Overrides HPCI and RCIC to prevent injection.

Bypasses MSIV and CIG interlocks IAW OP-184-001, MAIN STEAM SYSTEM.

US Directs RPV pressure stabilized below 1087 psig with TBVs/SRVs.

PCOP Stabilizes pressure below 1087 psig with TBVs/SRVs.

US Directs maximizing CRD to drift control rods.

Directs venting the Scram Air Header.

Directs performance of ES-158-001, DE-ENERGIZING SCRAM PILOT SOLENOIDS.

l

Directs bypassing RSCS and RWM and establishing normal CRD system parameters to manually drive control rods.

PCOM Reports alarm AR-105-103, EHC HYD FLUID PUMP DSCH LO PRESS.

l Reports TBVs have CLOSED.

PCOMIP Directs Plant Operator to vent scram air header.

Maximizes CRD to drift control rods.

PCOM Bypasses RSCS and RWM; attempts to establish normal CRD system parameters for manual rod insertion.

l

Recognizes/reports inability to establish normal CRD system parameters but attempts manual rod insertion.

Denotes Critical Task

[ NOTES:

]

Form STCP-QA-612A Rev. 1, (05/01)

Page 22 of 27 File No. RII-3

Page 23 Scenario NRC0204 Rev. 0, 4/2412002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

5, 6, 7, 8 Brief

Description:

GENERATOR LOCKOUT TRIP I RPS 'B' FAIL TO TRIP / SQUIB VALVES FAIL INSTRUCTOR ACTIVITY:

NOTE:

Drywell pressure reaches 1.72 psig in -15 minutes.

Suppression Pool temperature reaches =150'F in 16 minutes.

ROLE PLAY:

As maintenance sent to investigate SLC failure report the pumps are operating but the discharge relief valves are lifting.

Form STCP-QA-612A Rev. 1, (05/01)

Page 23 of 27 File No. R11-3

Page 24 Scenario NRC0204 Rev. 0, 4/24/2002 SCENARIO EVENT FORM Event No:

5,6,7,8 Brief

Description:

GENERATOR LOCKOUT TRIP / RPS 'B' FAIL TO TRIP / SQUIB VALVES FAIL POSITION TIME STUDENT ACTIVITIES PCOM Inserts control rods lAW EO-1 00-113 Sht. 2, CONTROL ROD INSERTION.

i_

Reports manual control rod insertion is successful.

PCOP Reports Suppression Pool Water temperature exceeds 900F.

US Enter EO-1 00-103, Primary Containment Control when SPT exceeds 900F.

Directs maximizing Suppression Pool Cooling IAW OP-149-005, RHR OPERATION IN SUPPRESSION POOL COOLING MODE.

PCOP Places both loops of RHR in Suppression Pool Cooling IAW OP-149-005, RHR OPERATION IN SUPPRESSION POOL COOLING MODE.

PCOM Reports loss of Condensate and Feedwater when Drywell pressure exceeds 1.72 psig.

US Re-enters EO-1 00-1 13 when Drywell pressure exceeds 1.72 psig.

Directs RPV water level control with HPCI and RCIC; level band < - 60" but > - 161" with a target level band of - 60" to - 11 o0.

Directs performance of ES-152-002, BYPASS HPCI SUCT SWAP.

Directs performance of ES-1 50-001, BYPASS RCIC LO PRESS ISO.

Re-enters EO-100-103 when Drywell pressure exceeds 1.72 psig.

PCOM Verifies control rod insertion as the Scram Air Header is vented.

Verifies all rods fully inserted; informs US.

Denotes Critical Task NOTES:

Form STCP-QA-612A Rev. 1, (05/01)

Page 24 of 27 File No. R11-3

Page 25 Scenario NRC0204 Rev. 0, 4/24/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

5, 6, 7,8 Brief

Description:

GENERATOR LOCKOUT TRIP I RPS 'B' FAIL TO TRIP / SQUIB VALVES FAIL INSTRUCTORACTIVITY:

1. When ES-152-002 is requested, wait z1 minutes then Bypass the HPCI Suct Swap, Depress P-7:

[P-7] MRF HP152007 BYPASS ES-152-002, BYP HPCI SUCT SWAP

2. When Supp.Pool Water temperature reaches 150*F, or 15 minutes after the ATWS, vent the Scram Air Header, Depress P-8:

[P-8] bat RDB.VSAH VENT SCRAM AIR HEADER ROLE PLAY:

1. As Plant Operator sent to perform ES-152-002 report that the field portion for booting contacts is complete, you are at step 4.1.2 in ES-152-002.

2. As Plant Operator venting the Scram Air Header, inform the control room that you have closed/checked-closed 147002A/B and uncapped and opened 147007. Air has rushed out of the header and has now stopped.

Form STCP-QA-612A Rev. 1, (05/01)

Page 25 of 27 File No. R11-3

Page 26 Scenario NRC0204 Rev. 0, 4/24/2002 SCENARIO EVENT FORM Event No:

5,6,7,8 Brief

Description:

GENERATOR LOCKOUT TRIP / RPS 'B' FAIL TO TRIP / SQUIB VALVES FAIL POSITION TIME STUDENT ACTIVITIES US Directs restoration of scram air header.

Directs SLC injection terminated.

Exits EO-1 00-113 Sheets I and 2; re-enters EO-1 00-102.

Directs establishing RPV water level +13" to +54".

Directs stopping actions for ES-1 50-002, BORON INJECTION WITH RCIC.

Directs stopping actions for ES-1 58-001, DE-ENERGIZING SCRAM PILOT SOLENIODS.

PCOP Terminates SLC injection.

Directs Plant Operator to restore the scram air header.

Establishes RPV water level +13" to +54" with HPCI/RCIC.

US Reassess plant conditions Directs PCO to maximize Suppression Pool Cooling IAW EO-1 00-103

Denotes Critical Task NOTES:

I 11 Form STCP-QA-612A Rev. 1, (05/01)

Page 26 of 27 File No. R11-3

Page 27 Scenario NRC0204 Rev. 0, 4/24/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

5,6,7,8 Brief

Description:

GENERATOR LOCKOUT TRIP I RPS 'B' FAIL TO TRIP I SQUIB VALVES FAIL INSTRUCTOR ACTIVITY:

NOTE:

Monitor P&ID RD6 for status of venting/restoring Scram Air Header.

If directed to restore the Scram Air Header following venting, wait 2 mins. then, Depress P-9:

P-9] bat RDB.RSAH RESTORE SCRAM AIR HEADER ROLE PLAY:

As Plant Operator directed to restore the Scram Air Header, wait 2 mins. and report that you have closed and capped 147007 and re-opened 147002A, which was the supply valve that was previously open.

TERMINATION CUE:

When all control rods have been inserted and actions are in progress to maximize Suppression Pool Cooling and restore RPV water level to +13" to +54' the scenario will be terminated.

Form STCP-QA-612A Rev. 1, (05/01)

Page 27 of 27 File No. R11-3

UNIT SUPERVISOR TURNOVER SHEET UNIT:

1 Date: July 30, 2002 SHIFT 1900 to 0700 SHIFT 0700 to 1900 Start End Start End MODE 1

POWER LEVEL GENERATOR OUTPUT 90 1030 MWe MODE POWER LEVEL GENERATOR OUTPUT MWe

1. 1 B EHC pump is out of service for breaker maintenance and will not be returned to service this shift.

2. RHR Loop 'A' has just been secured from Suppression Pool Cooling and RHRSW pump 1A is running for vibration data.

Vibration recording is complete, shutdown RHRSW.

3. ESW pumps 'A' and 'B' are in service to support Suppression Pool Cooling operation.

4. Unit 2 is in MODE 1 at 100% power EOL.

5. Chemistry and RX Engineering investigating spike in Off Gas activity during last Control Rod Exercising Surveillance.

COMMON:

Form OP-AD-003-7, Rev.3, DUPLEX, Page 1 of 2 (File Number R5-5)

PP&L-SUSQUEHANNA TRAINING CENTER SIMULATOR SCENARIO Scenario

Title:

NRC INITIAL LICENSE OPERATOR EXAMINATION Scenario Duration:

2 Hours Scenario Number: NRC0205 Revision/Date:

Rev 0, 4127/2002 Course:

PCO17, NRC Initial License Operator Examination Operational Activities:

1. Power Reduction

5. Fuel Clad Failure

2. Shutdown lB Condensate Pump

6. MSL Leak Outside Primary Containment

3. NR Level Instrument Fail Upscale

7. 'D' MSL Failure to Isolate

4. Failure of RPS A to Trip Prepared By:

3L-4Ii Instructor Date Reviewed By:

W/13la t

Nuclea attions Training Supervisor Date Approved By:

z, z7fJ-A -g oZ9 zoot Supervising Manager/Shift ervisor Date Form STCP-QA-612A Rev. 1, (05/01)

Page 1 of 25 File No. RI1-3

Page 2 Scenario NRC0205 Rev. 0, 4/27/2002 Form STCP-QA-612A Rev. 1, (05/01).

Page 2 of 25 File No. R11-3

Page 3

Scenario NRC0205 Rev. 0, 4/27/2002 1

SCENARIO

SUMMARY

The scenario begins with Unit 1 at 100% power EOL and Unit 2 in MODE 4. 1 B CRD pump is out of service for breaker maintenance. Condensate pump 1 B has a possible ground, the crew will reduce reactor power to 80% and shutdown Condensate pump 1 B for inspection.

Following the shutdown of 1 B Condensate pump the 'A' Narrow Range Level instrument will fail upscale.

Feedwater level control system response will stabilize RPV water level at

+23" in automatic. The crew will implement an Off-Normal procedure to transfer RPV water level control from averaged level control to selected level control and return to automatic control of RPV water level.

Following the water level perturbation a fuel clad failure will result in Turbine Building area high radiation and increasing main steam line radiation. The crew will respond by decreasing reactor power, radiation levels will continue to rise requiring the crew to manually scram the reactor and manually close the MSIVs and drains. When the mode switch is placed to shutdown a failure to scram will occur when RPS 'A' fails to trip. The control rods will insert when the crew initiates ARI.

Following the scram a main steam line break will occur in the Turbine Building Steam Tunnel. The 'D' MSL failed to isolate resulting in a sustained release to the Turbine Building. Release rates from the Turbine Building Vent Stack will increase above the ALERT level requiring entry-into Radioactive Release Emergency Operating Procedure, EO-1 00-105. The crew will request performance of dose calculations and conduct a reactor cooldown at <100F/hr. When off-site dose calculations exceed the General Emergency level the crew will rapidly depressurize the reactor.

When the crew has performed Rapid Depressurization and actions are in progress to restore RPV water level to +13' to +54 " the scenario will be terminated.

Form STCP-QA-612A Rev. 1, (05/01)

Page 3 of 25 File No. R11-3

Page 4

Scenario NRC0205 Rev. 0, 4/2712002 Form STCP-QA-612A Rev. 1, (05/01)

Page 4 of 25 File No. R11-3

Page 5

Scenario NRC0205 Rev. 0, 4/2712002 SCENARIO OBJECTIVES The USISS will:

1. Inform other shift members and plant management of changes in plant status, potential plant problems or limitations. (00.AD. 131)

2. Shutdown-the reactor when it is determined Reactor safety is in jeopaFdy, or when operating parameters exceed any RPS setpoint and scram does not occur. (00.AD.131)

3. Ensure that required actions per Technical Specifications are met when a LCO is not met. (00.TS.002)

4. Implement Alarm Response Procedures. (00.AR.005)

5. Respond to a loss of level signal to FWLC. (45.ON.009)

6. Implement control of LCOs, TROs, and Safety Function Determination Program. (O0.AD.047)

7. Implement Fuel Clad Failure. (00.AR.006)

8. Respond to Main Steam Line Radiation. (83.AR.005)

9. Implement Abnormal Gaseous Radiation Release. (70.ON.003)

10. Implement Scram. (00.ON.018)

11. Implement ATWS. (00.ON.026)

12. Implement RPV Control. (00.EO.026)

13. Implement Secondary Containment Control. (00.EO.028)

14. Implement Radioactive Release Control. (00.EO.029)

15. Implement Rapid Depressurization. (00.EO.030)

The PCOs will:

1. Perform a 10% power change with rods/recirc flow. (00.GO.012)

2. Perform a shutdown of a Condensate pump. (44.OP.002)

3. Implement Alarm Response Procedures. (00.AR.005)

4. Respond to a loss of level signal to FWLC. (45.ON.009)

5. Implement Fuel Clad Failure. (00.AR.006)

6. Respond to Main Steam Line Radiation. (83.AR.005)

7. Implement Abnormal Gaseous Radiation Release. (70.ON.003)

8. Perform Scram. (00.ON.018)

9. Implement ATWS. (00.ON.026)

10. Perform RPV Control. (00.EO.026)

11. Perform Secondary Containment Control. (00.EO.028)

12. Perform Radioactive Release Control. (00.EO.029)

13. Implement Rapid Depressurization. (00.EO.030)

Form STCP-QA-612A Rev. 1, (05/01)

File No. R11-3 Page 5 of 25

Page 6 Scenario NRC0205 Rev. 0, 4/27/2002 Form STCP-QA-612A Rev. 1, (05(01)

Page 6 of 25 File No. R11-3

Page 7 Scenario NRC0205 Rev. 0, 4/2712002 CRITICAL TASKS l

Manually initiate ARI Performs Rapid Depressurization before EPB projected dose / dose rates reach General Emergency declaration criteria.

Denotes Simulator Critical Task.

Form STCP-QA-612A Rev. 1, (05/01)

Page 7 of 25 File No R11-3

Page 8 Scenario NRC0205 Rev. 0, 4/27/2002 U

Form STCP-QA-612A Rev. 1, (05/01)

Page 8 of 25 File No. R11-3

Page 9

Scenaro NRC0205 Rev. 0, 4/2712002 SCENARIO REFERENCES

1. POWER REDUCTION CORE REACTIVITY CONTROL BOOK OP-AD-338 COMMUNICATION REQUIREMENTS FOR REACTIVITY MANIPULATIONS GO-1 00-0f2 POWER MANEUVERS OP-AD-004 OPERATIONS STANDARDS FOR ERROR AND EVENT PREVENTION

2. SHUTDOWN 18 CONDENSATE PUMP OP-144-001 CONDENSATE AND FEEDWATER SYSTEM

3. NARROW RANGE INSTRUMENT FAILS UPSCALE AR-1011-B17 AR-101-A17 ON-145-001 T.S. 3.3.2.2 RX WATER HI-LO LEVEL RX WATER HI LEVEL RPV WATER LEVEL CONTROL SYSTEM MALFUNCTION FEEDWATER / MAIN TURBINE HIGH WATER LEVEL TRIP

4. RPS 'A' FAILURE TO TRIP ON-1 00-101 EO-100-102 SCRAM RPV CONTROL

5. FUEL CLAD FAILURE AR-111-C03 AR-101-C05 AR-101i-B05 ON-070-001 AR-01 5-E04 AR-i 11-803 AR-1 12-803 EO-100-104 EO-100-105 EO-100-112 EO-100-103 OP-149-005 MN STM LINE RAD MONITOR Hi RADIATION TURB BLDG AREA PANEL 1C605 HI RADIATION RX BLDG AREA PANEL 1C605 HI RADIATION ABNORMAL GASEOUS RADIATION RELEASE STACK MONITORING SYS 0C630/0C677 HI RADIATION MN STM LINE LEAK DETECTION HI TEMP MN STM LINE LEAK DETECTION Hi TEMP SECONDARY CONTAINMENT CONTROL RADIOACTIVITY RELEASE CONTROL RAPID DEPRESSURIZATION PRIMARY COMTAINMENT CONTROL RHR OPERATION IN SUPPRESSION POOL COOLING MODE Form STCP-QA-612A Rev. 1, (05/01)

Page 9 of 25 File No.. R11-3

Page 1 0 Scenario NRC0205 Rev. 0, 4/27/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 10 of 25 File No. R11-3

Page 1 1 Scenario NRC0205 Rev. 0, 4/27/2002

-1 SCENARIO SPECIAL INSTRUCTIONS

1. Initialize the simulator to IC-18, Unit 1 at 100% power EOL. Unit 2 in MODE 4.

2. Type restorepref YPP.NRC0205; verify that the following pre-inserts and Program Button assignments.

Also verty that the Environment window shows I Event Trigger active:

MRF PM131PI32B OUT 1B CRD PUMP BKR RACKED OUT IMF RP158007A RPS'A' FAILURE TO TRIP IMFAV06:HV141F022D 80 MSIV F022D BIND DURING MOTION IMF AV06:HVI41FO28D 80 MSIV F028D BIND DURING MOTION TRG El BAAA26409 EVENT TRIGGER MODE SWITCH IN SHUTDOWN TRG El = IMF MS1830089 0.9

'D' MSL LEAK IN TURBINE BUILDING

[P-1] IMF TR02:PDTC321 NO04A 600 Asls NR LEVEL 'A' FAILURE UPSCALE

[P-2J IMF RR179003 90 8:00 FUEL FAILURE 90 PINS

[P-3] bat YPB.NRC0205A RAMP TB SPING RELEASE RATES

4. Prepare a turnover sheet indicating:

a. Unit 1 is at 100% power EOL. Unit 2 is in MODE 4.

b. CRD pump 1 B is out of service for breaker maintenance, it is not expected to return this shift.

c. Condensate pump 1 B has a possible ground, you are to reduce reactor power to 80% and shutdown Condensate pump 1B for inspection.

5. Make a copy of shift assignments.

Form STCP-QA-612A Rev. 1, (05/01)

Page 11 of 25 File No. R1 1-3

Page 12 Scenario NRC0205 Rev. 0, 4/27/2002 Form STCP-QA-612A Rev. 1, (05/01)

Page 12 of 25 File No. R11-3

Page 13 Scenaro NRC0205 Rev. 0, 4/27/2002 SCENARIO EVENT DESCRIPTION FORM Initial Conditions: Initialize the Simulator to IC-1 8. Place the Simulator to RUN. Ensure the Program Buttons are assigned as indicated on the Special Instructions sheet via the appromiate Preference File. Assign Shift Dositions.

Direct the start of the 5 minute panel walkdown.

EVENT_-j TIME DESCRIPTION~

1 POWER REDUCTION 2

SHUTDOWN 1 B CONDENSATE PUMP 3

'A' NR LEVEL INSTRUMENT FAILS UPSCALE 4

FUEL CLAD FAILURE 5

RPS 'A' FAILURE TO TRIP I ATWS 6

MSL LEAK IN TURBINE BUILDING 7

'D' MSL FAILURE TO ISOLATE Form STCP-QA-612A Rev. 1, (05/01)

Page 13 of 25 File No. R11-3

Page 14 Scenario NRC0205 Rev. 0, 4/27/2002 SCENARIO EVENT FORM Event No:

1,2 Brief

Description:

POWER REDUCTION I SHUTDOWN lB CONDENSATE PUMP POSITION TIME STUDENT ACTIVITIES US Direct the power reduction.

Brief the crew for the upcoming reactivity evolution7-Direct implementation of Reactor Engineering Instructions in the CRC Book.

Direct implementation of GO-100-012, POWER MANEUVERS.

PCOM Decreases reactor power as directed by the US and CRC Book.

Plots power changes on the power to flow map.

PCOP Notifies GCC when the power reduction is started and ended.

US Makes notifications lAW OP-AD-002, STANDARDS FOR SHIFT OPERATIONS.

Notify Chemistry/Health Physics when reactor power changes by 15%.

Directs implementation of OP-144-001, CONDENSATE AND FEEDWATER SYSTEM.

PCOM Implements OP-144-001, CONDENSATE AND FEEDWATER SYSTEM.

Depress the STOP pushbutton for 1 B Condensate Pump.

Observes condensate header pressure on PICSY format.

Observes RPV water level and Feedwater System response.

US Notify WCC/Maintenance 1 B Condensate Pump is shutdown.

Denotes Critical Task NOTES:

Form STCP-QA-612A Rev. 1, (05/01)

Page 14 of 25 File No. R11-3

Page 15 Scenario NRC0205 Rev. 0, 4/27/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

1, 2 Brief

Description:

POWER REDUCTION / SHUTDOWN 1B CONDENSATE PUMP INSTRUCTOR ACTIVITY:

None.

ROLE PLAY:

As necessary.

Form STCP-QA-612A Rev. 1, (05/01)

Page 15 of 25 File No. R11-3

Page 16 Scenario NRC0205 Rev. 0, 4/27/2002 SCENARIO EVENT FORM Event No:

3 Brief

Description:

'A' NR LEVEL INSTRUMENT FAILS UPSCALE POSITION TIME STUDENT ACTIVITIES PCOM Reports alarms RX WATER HI-LO LEVEL and RX WATER HI LEVEL.

_Reports

'A' NR level reading +60" and average level is 33.5'.

Observes FWLC response to stabilize RPV water level.

Reports 'B' and 'C' NR level indication stabilizes at =22.5".

Reports 'A' Hi Water Level Trip green status light is ON.

Refers to AR-101-B17, RX WATER HI-LO LEVEL.

Refers to AR-1 01-Al 7, RX WATER Hi LEVEL.

Implement ON-145-001, RPV LEVEL CONTROL SYSTEM MALFUNCTION.

US Directs implementation of ON-145-001, RPV LEVEL CONTROL SYSTEM MALFUNCTION.

Contacts I&C to investigate 'A' NR level instrument failure.

Refers to T. S. 3.3.2.2; declares 'A' NR level channel inoperable, enter Condition A.

PCOM Places FW LEVEL CTLIDEMAND SIGNAL LIC-C32-1 R600 controller in MAN.

l Adjusts LIC-C32-1 R600 to restore RPV water level to =+ 35".

Selects level 'B' NR level signal input.

Transfers from Averaged to Selected level Nulls FW LEVEL CTIDEMAND LIC-C32-1R600 controller.

Place FW LEVEL CTL/DEMAND LIC-C32-1 R600 controller in AUTO.

Denotes Critical Task NOTES:

Form STCP-QA-612A Rev. 1, (05101)

Page 16 of 25 File No. R11-3

Page 17 Scenario NRC0205 Rev. 0, 4/27/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, HAND INSTRUCTOR'S PERSONAL NOTES Event No:

3 Brief

Description:

'A' NR LEVEL INSTRUMENT FAILS UPSCALE INSTRUCTOR ACTIVITY:

When 1 B Condensate Pump is shutdown insert 'A' NR level instrument failure upscale, Depress P-1:

[P-I] IMF TR02:PDTC321 NO04A 600 AsIs NR LEVEL 'A' FAILURE UPSCALE ROLE PLAY:

As l&C sent to investigate 'A' NR level problem wait 5 mins. and report the differential pressure transmitter is failed and must be replaced and calibrated. The repairs are expected to take approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Form STCP-QA-612A Rev. 1, (05/01)

Page 17 of 25 File No. R11-3

Page 18 Scenaro NRC0205 Rev. 0, 4/27/2002 SCENARIO EVENT FORM Event No:

4 Brief

Description:

FUEL CLAD FAILURE POSITION TIME STUDENT ACTIVITIES PCOM Reports alarm TURB BLDG AREA PANEL 1C605 HI RADIATION.

--Observes Turbine building area rad reading on PICSY.

l Reports SJAE RM and TB OFFGAS BYP AREA have rad levels increasing.

Refers to AR-1 01-C05, TURB BLDG AREA PANEL 1C605 HI RADIATION.

Evacuates Unit 1 TB of all non-essential personnel.

Contacts HP to perform HP-TP-441.

US Directs PCOP to monitor MSL and Offgas radiations levels on PICSY or panel 1 C600.

PCOP Report radiation levels are increasing for MSL and Offgas.

Reports alarm MN STM LINE RAD MONITOR HI RADIATION.

Refer to AR-1 1-C03, MN STM LINE RAD MONITOR HI RADIATION.

US Directs power reduction by reducing recirc flow.

May enter ON-1 00-101, SCRAM and direct scram imminent actions.

PCOM Reduces power/recirc flow as directed.

Performs scram imminent actions if directed.

PCOP Checks MSL and Offgas rad monitors for indication and trend.

Performs scram imminent actions if directed.

Denotes Critical Task lNOTES:.

Form STCP-QA-612A Rev. 1, (05/01)

Page 18 of 25 File No. R11-3

Page 19 Scenario NRC0205 Rev. 0, 4/27/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

4 Brief

Description:

FUEL CLAD FAILURE INSTRUCTOR ACTIVITY:

When FWLC master controller is restored to auto insert a fuel clad failure, Depress P-2:

[P-2] IMF RR179003 90 8:00 FUEL FAILURE 90 PINS NOTE:

Turbine building area high radiation alarm is received in -2 minutes.

Main steam line high radiation alarm is received in -4 minutes.

ROLE PLAY:

As necessary.

Form STCP-QA-612A Rev. 1, (05/01)

Page 19 of 25 File No. R11-3

Page 20 Scenario NRC0205 Rev. 0, 4/27/2002 SCENARIO EVENT FORM Event No:

Brief

Description:

4,5,6,7 FUEL CLAD FAILURE I RPS 'A' FAILURE TO TRIP I MSL LEAK INSIDE TURB BLDG I 'D' MSL FAILURE TO ISOLATE POSITION TIME STUDENT ACTIVITIES US Directs manually scramming reactor.

Enters ON-100-101, SCRAM.

PCOM Place the reactor mode switch to SHUTDOWN.

Recognizes/reports failure to scram.

Arms and depresses manual scram pushbuttons.

Inserts SRMs and IRMs.

US Enters EO-1 00-102, RPV CONTROL and Exits to EO-1 00-113, LEVEL POWER CONTROL.

Directs ARI initiation.

PCOP Initiates ARI.

Reports ARI has actuated.

PCOM Reports all control rods are fully inserted.

US Exits EO-1 00-113 and re-enters EO-1 00-102.

Directs closure of MSIVs and drains.

Directs RPV water level maintained +13" to +54".

Directs RPV pressure maintained <1087 psig with SRVs.

Directs PCOM to reset main generator lockouts.

Denotes Critical Task l NOTES:l Form STCP-QA-612A Rev. 1, (05/01)

Page 20 of 25 File No. R1 1-3

Page 21 Scenario NRC0205 Rev. 0, 4/2712002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

4,5, 6, 7 Brief

Description:

FUEL CLAD FAILURE I RPS 'A' FAILURE TO TRIP/ MSL LEAK INSIDE TURB BLDG I 'D' MSL FAILURE TO ISOLATE INSTRUCTOR ACTIVITY:

When the crew places the Mode Switch to SHUTDOWN, verify the Event Trigger activates to initiate a steam leak in the Steam Tunnel.

When the MSIVs and drains are closed increase TB release rates, Depress P-3:

[P-3] bat YPB.NRC0205A RAMP TB SPING RELEASE RATES ROLE PLAY:

As necessary.

Form STCP-QA-612A Rev. 1, (05/01)

Page 21 of 25 File No. R11-3

Page 22 Scenario NRC0205 Rev. 0, 4/27/2002 SCENARIO EVENT FORM Event No:

Brief

Description:

4,5,6, 7 FUEL CLAD FAILURE I RPS 'A' FAILURE TO TRIP/ MSL LEAK INSIDE TURB BLDG I 'D' MSL FAILURE TO ISOLATE POSITION TIME STUDENT ACTIVITIES PCOP Manually closes MSIVs and drains.

Reports 'D' MSL failed to isolate.

Verifies '0' MSL flow indication on 1 C652 indication FI-C32-1 R603D.

PCOM Reports alarm RX BLDG AREA PANEL 1 C605 Hi RADIATION.

Observes Reactor building area rad reading on PICSY.

Reports CRD N & S and RB SUMP AREA have rad levels increasing.

Refers to AR-i 01-B05, RX BLDG AREA PANEL 1 C605 Hi RADIATION.

Evacuates Unit 1 RB of all non-essential personnel.

Contacts HP to perform HP-TP-441.

US Enters EO-1 00-104, SECONDARY CONTAINEMNT CONTROL.

NOTE 1 Contacts maintenance for the MSIV failures in 'D' MSL.

PCOP Reports alarm STACK MONITORING SYS 0C630/0C677 HI RADIATION.

Checks SPING, reports increasing TB Stack Noble Gas and Iodine.

PCOP Reports alarms MN STM LINE LEAK DETECTION HI TEMP DIV 1 /2.

Verifies 1C614 temperature readings; reports high temperature in TB Steam Tunnel.

Denotes Critical Task NOTES:

I NOTE 1: A common error is Rapid Depressurization when the rad levels on elevations 645' and 719' increase to > max safe levels. There is no primary system discharging to any Secondary Containment area throughout this scenario.

Form STCP-QA-612A Rev. 1, (05/01)

Page 22 of 25 File No. RII-3

Page 23 Scenario NRC0205 Rev. 0, 4/27/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

Brief

Description:

4, 5,6, 7 FUEL CLAD FAILURE I RPS 'A' FAILURE TO TRIP/ MSL LEAK INSIDE TURB BLDG / 'D' MSL FAILURE TO ISOLATE INSTRUCTOR ACTIVITY:

None.

ROLE PLAY:

As necessary.

Form STCP-QA-612A Rev. 1, (05101)

Page 23 of 25 File No. R11-3

Page 24 Scenario NRC0205 Rev. 0, 4/27/2002 SCENARIO EVENT FORM Event No:

4, 5, 6, 7 Brief

Description:

FUEL CLAD FAILURE I RPS 'A' FAILURE TO TRIP/ MSL LEAK INSIDE TURB BLDG / 'D' MSL FAILURE TO ISOLATE POSITION TIME STUDENT ACTIVITIES US Enters EO-1 00-105, RADIOACTIVITY RELEASE when TB Iodine or NG release rate exceeds ALERT Level.

Request Off-Site Dose Calculations.

Directs reactor cooldown < 100IF/hr.

PCOP Initiates cooldown < 1O0F/hr using SRVs.

US Performs Rapid Depressurization before EPB projected dose/dose rate reaches the General Emergency declaration criteria.

Enter EO-i 00-1 12, RAPID DEPRESSUREIZATION Directs RPV rapid depressurization by opening all ADS valves.

PCOP Rapidly depressurizes the reactor by opening all ADS valves.

US Directs RPV level restored and maintained +13" to +54" with available systems.

Enters EO-1 00-1 03, PRIMARY CONTAINMENT CONTROL due to Suppression Pool temperature > 90°F.

Directs maximizing Suppression Pool Cooling.

PCOP Places both loops of Suppression Pool Cooling in service IAW OP-149-005, RHR OPERATION IN SUPPRESSION POOL COOLING MODE.

Denotes Critical Task NOTES:

Form STCP-QA-612A Rev. 1, (05/01)

Page 24 of 25 File No. R11-3

Page 25 Scenario NRC0205 Rev. 0, 4/27/2002 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:

Brief

Description:

4,5,6,7 FUEL CLAD FAILURE I RPS 'A' FAILURE TO TRIP/ MSL LEAK INSIDE TURB BLDG I 'D' MSL FAILURE TO ISOLATE INSTRUCTOR ACTIVITY:

None.

ROLE PLAY:

Approximately 5 minutes after the crew enters EO-1 00-105 and Off-Site Dose Calculations have been requested, report to the Control Room as the TSC Dose Calculator and provide the crew the attached MIDAS report.

NOTE: Off-Site dose is projected to reach 1.6 rem TEDE based on existing release rate and plant conditions.

TERMINATION CUE:

Rapid depressurization has been performed and actions are in progress to restore RPV water level to

+13" to +54".

Form STCP-QA-612A Rev. 1, (05/01)

Page 25 of 25 File No. R11-3

UNIT SUPERVISOR TURNOVER SHEET UNIT:

1 Date: July 30, 2002 SHIFT 1900 to 0700 SHIFT 0700 to 1900 Start End Start End MODE 1

POWER LEVEL.

GENERATOR OUTPUT 100 1150 MWe MODE POWER LEVEL GENERATOR OUTPUT MWe

1.

CRD pump I B is out of service for breaker maintenance, it is not expected to return this shift.

2.

Condensate pump 1 B has a possible ground, you are to reduce reactor power to 80% and shutdown 1 B Condensate Pump IB for inspection.

3.

Unit 2 is in MODE 4.

4. Chemistry and RX Engineering still investigating spike in Off Gas activity during last Control Rod Exercising surveillance.

COMMON:

Form OP-AD-003-7, Rev.3, DUPLEX, Page 1 of 2 (File Number R5-5)

ML022550317

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