Text

RB-2010-04-Final Operating Test
	ML101530484
Person / Time
Site:	River Bend
Issue date:	04/12/2010
From:	Garchow S; Operations Branch IV
To:	; Entergy Operations
References
	50-458/10-04
	Download: ML101530484 (275)
	v • d • e

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 1 Op-Test No.: NRC Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1 100% power.

Turnover: Complete section 7.3 of STP-205-6301 for scheduled monthly performance. Complete STP-509-0101 MAIN TURBINE BYPASS SYSTEM VALVE CYCLE TEST for Bypass Valve #1 only. Post maintenance test for the ERIS point.

Event Malf. No. Event Event No. Type* Description 1 NA N Run Low Pressure Core Spray pump per STP-205-6301.

(BOP,SRO) 2 NA N Complete STP-509-0101 MAIN TURBINE BYPASS SYSTEM (ATC,SRO) VALVE CYCLE TEST 3 LPCS001 C Low Pressure Core Spray pump trip. (Technical Specifications)

(BOP,SRO) 4 CCS001A, C CCS Pump A trips, CCS Pump C fails to auto start. (Requires manual (BOP,SRO) start of standby pump per AOP-0012)

CCS003C 5 MSS005J C SRV B21-F047C fails open. (Technical Specifications)

(BOP,SRO)

Lower reactor <90% by lowering reactor recirculation flow.

R (ATC) 6 MSS001 M (All) Steam leak in the drywell on SRV closure. Manual scram or automatic scram on high drywell pressure.

7 HPCS003 C HPCS fails to automatically initiate. (After EOP entry)

(BOP,SRO) 8 MSC007 C (All) Drywell to Containment Leakage (After EOP entry).

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (7): LPCS trip, CCS A trip, CCS C fail, SRV open, Steak Leak, HPCS fail, DW to Cont Leakage.

Malfunctions after EOP entry (2): HPCS fail, DW to Cont Leakage Abnormal events (3): AOP-0012, AOP-0001, AOP-0002 Major transients (1): Steam Leak EOPs entered (2): EOP-0001, EOP-0002 EOP contingencies (1): Emergency depressurization Critical tasks (2): Close SRV (Cont. integrity), Open 7 ADS SRVs when PSP exceeded. (Cont integrity)

Rev 02

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

Description:

Run Low Pressure Core Spray pump per STP-205-6301.

Time Position Applicants Actions or Behavior Direct the performance of STP-205-6301 LPCS PUMP AND VALVE SRO OPERABILITY TEST May enter TS 3.5.1 Condition A on pump run.

Perform actions of STP-205-6301 BOP

Contact the reactor building operator to verify oil level in the upper and lower sight glasses is within the High and Low marks on the Upper and Lower sight glasses.

Contact the reactor building operator to verify that the suction pressure gauge is installed.

Start E21-C001, LPCS PUMP.

Check that E21-C001, LPCS Motor AMPS indicates less than 157 amps.

Check E21-F011, LPCS MIN FLOW VLV TO SUPPRESSION POOL, is open.

Throttle E21-F012, LPCS TEST RETURN VLV TO SUPPRESSION POOL to obtain a flow rate of 5050 gpm as indicated on E21-R600, LPCS PUMP FLOW.

Check E21-F011 is closed.

WHEN the LPCS pump has been running at stable reference conditions for at least 2 minutes, THEN perform the following:

Record pump flow as indicated on E21-R600 on Data Sheet 1.

ROLE PLAY As Reactor building operator :

When requested, report that the oil level is satisfactory for the LPCS pump and that the suction press gauge is installed.

Rev 02

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

Description:

Complete STP-509-0101 MAIN TURBINE BYPASS SYSTEM VALVE CYCLE TEST for Bypass Valve #1 only. Post maintenance test for the ERIS point.

Time Position Applicants Actions or Behavior SRO Direct the performance of STP-509-0101 ATC Perform the actions of STP-509-0101

In the BYPASS VALVE TEST STATUS group, depress the TESTING pushbutton momentarily.

Check the following occurs:

o The OFF light goes off.

o The TESTING light comes on.

o The READY light comes on.

Depress and hold the TEST BPV 1 pushbutton.

Check the following occur:

o The READY light goes off.

o The TEST BPV 1 light comes on.

o Small positive current change on C85AM4, 1 BYPASS VALVE SERVO CURRENT meter.

o BPV 1 is traveling smoothly in the open direction as indicated on C85AM5, 1 BYPASS VALVE POSITION meter.

o Annunciator P680-07A-A07, TURBINE BYPASS VALVE OPEN alarms.

o The Fast Acting Solenoid operates properly as BPV 1 opens.

Verify BPV 1 is full open by one of the following:

o C85AM5, 1 BYPASS VALVE POSITION o ERIS point C85EA012, BYPASS VALVE 1 POSITION.

o Only the FULL OPEN indicator light is on.

Only the FULL OPEN indicator light is on

Release the TEST BPV 1 pushbutton.

Check the following occur:

o Small negative current change on C85AM4, 1 BYPASS VALVE SERVO CURRENT meter.

o BPV 1 is traveling smoothly in the close direction as indicated on C85AM5, 1 BYPASS VALVE POSITION meter.

Verify BPV 1 is full closed by one of the following indications:

C85AM5, 1 BYPASS VALVE POSITION.

ERIS point C85EA012, BYPASS VALVE 1 POSITION.

Only the CLOSED indicator light is on.

Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 2 Page 3 of 10 Event

Description:

Complete STP-509-0101 MAIN TURBINE BYPASS SYSTEM VALVE CYCLE TEST for Bypass Valve #1 only. Post maintenance test for the ERIS point.

Time Position Applicants Actions or Behavior ATC

Only the CLOSED indicator light is on

Annunciator P680-07A-A07, TURBINE BYPASS VALVE OPEN clears.

The TEST BPV 1 light goes off.

The READY light comes on.

In the BYPASS VALVE TEST STATUS group, depress the OFF pushbutton.

Check the following occurs:

The TESTING light goes off.

The READY light goes off.

The OFF light comes on.

Notify OSM/CRS of the test completion.

Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 3 Page 4 of 10 Event

Description:

Low Pressure Core Spray pump trip. (Technical Specifications)

Time Position Applicants Actions or Behavior H13-P601/21A/C08 LPCS PUMP E21-C001 AUTO TRIP EVENT CUE

Recognize and report trip of LPCS pump.

BOP

Recognize and report LPCS pump low discharge line pressure

Contact operator to investigate LPCS pump trip locally.

Direct the closure of E21-MOVF012 LPCS test return valve.

SRO

Direct the actions of ARP

Close E21-MOVF012 LPCS test return valve.

BOP

Review ARP for required actions

Verify that E21-MOVF011 LPCS min. flow valve is closed

Request E21-PSN654 back panel pressure reading Enter Tech Spec 3.5.1 condition A (7 day LCO)

SRO Make required notifications per OSP-046 Possible actions if RHR-A low discharge pressure alarm is received:

Enter Tech Spec 3.5.1 condition C (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO)Two low pressure ECCS systems inop As operator sent to the LPCS pump:

ROLE PLAY Report no apparent problem with the pump.

As operator sent to the LPCS pump breaker:

Report that there is an over current relay flag and 86 device tripped.

As Back panel operator:

Report the discharge pressure the same as the ERIS pressure indication.

Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 4 Page 5 of 10 Event

Description:

CCS Pump A trips, CCS Pump C fails to auto start. (Requires manual start of standby pump per AOP-0012)

Time Position Applicants Actions or Behavior H13-P870/55A/E01 TURB CMPNT CLG WATER PUMP BRKR AUTO TRIP EVENT CUE

Recognize and report the trip of CCS-P1A TPCCW pump BOP

Start CCS-P1C due to failure to auto start

Review ARP for required actions

Direct entry into AOP-012 Loss of CCS for applicable actions SRO

Make notifications per OSP-046

Dispatch operators to investigate pump trip locally BOP

Dispatch operator to obtain local parameters for CCS-P1C

Review AOP-012 for applicable actions. Report none applicable.

As operator sent to the pump breaker:

ROLE PLAY Report an over current trip on CCS-P1A As operator sent to CCS-P1C:

Report all parameters normal Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 5 Page 6 of 10 Event

Description:

SRV B21-F047C fails open. (Technical Specifications)

Time Position Applicants Actions or Behavior EVENT CUE H13-P601/19A/A09 MAIN STEAM SAFETY RELIEF VALVE OPEN BOP / Recognize and report that SRV B21-F047C is open ATC SRO Direct implementation of AOP-035 Stuck Open SRV BOP Announce the following over the Gaitronics:

Attention in the plant. "Safety Relief Valve Open, all personnel evacuate the Containment. Personnel evacuate to WMC At H13-P601, place SORV control switch to OPEN.

WHEN reactor power is equal to or less than 90%, THEN attempt to close the open SRV as follows:

o At H13-P601, take the control switch to OFF.

o IF SRV remains open, THEN at H13-P601, take the control switch to OPEN and back to OFF.

IF SRV remains open, THEN at H13-P631, perform the following:

o Take the control switch to OPEN and back to OFF.

IF the SRV did not close, THEN take the control switch to OPEN and back to OFF.

ATC Reduce reactor power to equal to or less than 90% with recirc flow.

SRO Enter the following Tech Specs:

3.5.1 E ADS, 3.5.1 F ADS & ECCS, 3.6.2.1 S. Pool temp., 3.6.5.3. Drywell PCIV, TRM 3.4.4 A Open SRV Direct reference to AOP-007 Loss of Feedwater Heating Direct reference to AOP-024 Thermal Hydraulic Stability Controls Enter EOP-002 on Suppression Pool Level and Temperature when entry conditions are met.

ATC Refer to AOP-024 and 007.

Determine and report required entry into AOP-007 SRO Direct the actions of AOP-007.

Reduce recirculation flow until thermal power lowers by 20% (620 MWth) or 60% (50.7 Mlbm/hr) core flow is reached.

Direct suppression pool cooling with RHR with OSP-0053 ATTACHMENT 12 -

ESTABLISHING SUPPRESSION POOL COOLING NOTE: The SRV will close when the fuses are removed. Actions of AOP-007 may not be performed prior to SRV closure.

ATC Reduce recirculation flow until thermal power lowers by 20% (620 MWth) or 60% (50.7 Mlbm/hr) core flow is reached.

Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 5 Page 7 of 10 Event

Description:

SRV B21-F047C fails open. (Technical Specifications) Cont.

Time Position Applicants Actions or Behavior BOP If the SRV is still open, THEN deenergize the solenoids by pulling the applicable fuses listed in ATTACHMENT 1,SAFETY RELIEF VALVES SOLENOID CIRCUIT FUSES Perform actions of ATTACHMENT 12 - ESTABLISHING SUPPRESSION POOL COOLING (Time permitting)

Throttle E12-F068A(B), RHR HX A(B) SVCE WTR RTN, not to exceed 5800 gpm flow.

Start/Verify Running RHR PUMP A(B).

Verify E12-F042A(B), RHR PUMP A(B) LPCI INJECT ISOL VALVE, Closed.

Verify E12-F053A(B), RHR PUMP A(B) SDC INJECTION VALVE, Closed.

Open/Verify Open E12-FO24A(B), RHR PUMP A(B) TEST RTN TO SUP PL.

Verify E12-F064A(B), RHR PUMP A(B) MIN FLOW TO SUP PL, Closed.

Close E12-F048A(B), RHR A(B) HX BYPASS VALVE, when auto open signal has cleared.

Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 6 Page 8 of 10 Event

Description:

Steam leak in the drywell on SRV closure. Manual scram or automatic scram on high drywell pressure.

Time Position Applicants Actions or Behavior EVENT CUE H13-P808 / 84A / B07 DIV II DW PAM AREA RADN ALARM TEAM Recognize and report steam leak in the drywell SRO Direct the ATC to place the mode switch in Shutdown.

ATC Place the mode switch in shutdown Give SCRAM report to the SRO Trip Reactor Recirculation pumps due to loss of CCP.

o Perform the following:

Trip LFMG BRKR 2A and 2B o When pump coasts down to 0%, THEN Trip LFMG BRKR 1A and 1B SRO Enter EOP-001 Enter EOP-002 Direct a pressure control band of 500# to 1090#

Direct installation of Enclosure 20 to bypass drywell cooling interlocks Direct implementation of AOP-001 Reactor scram and AOP-002 Turbine /

Generator trips to the ATC Direct implementation of AOP-003 Automatic Isolations to the BOP BOP Perform Enclosure 20 actions.

VERIFY Normal Service Water pressure on SWP-PI124, SVCE SPLY HDR PRESSURE OR Standby Service Water pressure on SWP-PR50A(B), STBY CLG TOWER LVL & PUMP DISCH PRESS RECORDER is greater than Containment AND Drywell pressure on CMS-PR2A(B), DRYWELL PRESSURE PLACE Control Switches for all tripped Drywell Unit Coolers to OFF.

START DIV I AND II H2 Analyzers. (H13-P808)

IF any drywell temperature on CMS-TR41A or B, DRYWELL ATMOS TEMP (H13-P808) is or has been greater than 200 °F, THEN, notify the CRS/OSM that this enclosure cannot be completed.

CONT.

Perform the following:

OPEN the following valves: (H13-P870)

SWP-MOV4A DRYWELL UC SUPPLY SWP-MOV5A DRYWELL UC RETURN SWP-MOV4B DRYWELL UC SUPPLY SWP-MOV5B DRYWELL UC RETURN

VERIFY closed the following: (H13-P877)

EJS-ACB25 NHS-MCC102A SPLY BRKR

EJS-ACB66 NHS-MCC102B SPLY BRKR START Drywell Unit Coolers as directed by the CRS.

Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 6 Page 9 of 10 Event

Description:

Steam leak in the drywell on SRV closure. Manual scram or automatic scram on high drywell pressure.

Time Position Applicants Actions or Behavior SRO Direct reactor water level band of -20 to 51.

Direct enclosure 12 for expanded band BOP Perform actions of Enclosure 12 for the expanded reactor water level band (Instructor performed action).

Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 7/8 Page 10 of 10 Event

Description:

HPCS fails to automatically initiate. (After EOP entry)

Drywell to Containment Leakage (After EOP entry).

Time Position Applicants Actions or Behavior SRO

Recognize drywell leak into containment

Anticipate the need to Emergency Depressurize due to approaching the unsafe of the Pressure Suppression curve of EOP-002

Direct opening all steam drains and turbine bypass valves.

Direct override automatic injection from all low pressure ECCS systems.

ATC Fully open the main turbine steam bypass vales BOP

Open all available steam line drain valves.

Override all low pressure injection valves closed.

Recognize and report that HPCS did not auto initiate on the high drywell pressure.

SRO

Recognize entry into the unsafe region of the Pressure Suppression Curve.

Direct BOP to open 7 ADS/SRVs to Emergency Depressurize the reactor BOP Open 7 ADS / SRVs and report SRO Declare the reactor depressurized when reactor pressure falls below 46#

Rev 02

Number: *RSMS-OPS-NRC10-1 RIVER Revision: 01 BEND STATION Page 1 of 15 SIMULATOR SCENARIO TRAINING PROGRAM:

SIMULATOR TRAINING LESSON PLAN:

Steam Leak in Drywell with Steam Bypass to Containment REASON FOR REVISION:

New for 2010 NRC exam PREPARE / REVIEW:

John Hedgepeth 0069 02/03/2010 Preparer KCN Date Angela Orgeron 1538 2/24/2010 Technical Review (SME) KCN Date Joey Clark 0260 2/26/2010 Operations Management KCN Date (Evaluated scenarios only)

Facility Reviewer approval via ES-301-3, 301-4

Indexing Information

I. DESCRIPTION OF SCENARIO The scenario begins at 100% power.

Event 1: Complete section 7.3 of STP-205-6301 for scheduled monthly performance.

Event 2: Complete STP-509-0101 MAIN TURBINE BYPASS SYSTEM VALVE CYCLE TESTEvent 3: Low Pressure Core Spray pump trip. (Technical Specifications)

Event 4: CCS Pump A trips, CCS Pump C fails to auto start. (Requires manual start of standby pump per AOP-0012)

Event 5: SRV B21-F047C fails open.

Event 6: Steam leak in the drywell on SRV closure. Manual scram or automatic scram on high drywell pressure.

Event 7: Drywell to Containment Leakage II. TERMINAL OBJECTIVES

1. Recognize and respond to trip of LPCS pump.

2. Recognize and respond to a trip of CCS-P1A

3. Recognize and respond to a drywell steam leak (with and without Containment Bypass Leakage). Control RPV level and pressure per EOP-1. Control primary containment parameters per EOP-2.

4. Emergency Depressurize when containment pressure cannot be maintained in the safe zone of the PSP curve..

RSMS-OPS-NRC10-1 Rev. 02 Page 2 OF 15

IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL TRAINING EQUIPMENT STATUS REQUIRED DOCUMENTS CONDITION FOCUS IC #__237___ AOP-0035 Power: 100%

EOP-1, RPV Control Core: Xenon equilibrium EOP-2, Primary Containment Control Equipment OOS:

None STPs Due: STP-205-6301 LCOs: None Evolutions in progress: None.

Problem/Lit annunciators: None RSMS-OPS-NRC10-1 Rev. 02 Page 3 OF 15

V. GENERAL INSTRUCTIONS Event Number MFS-OR-REM-SCH Expected Operator Action Simulator Setup Setup

Verify CCS-P1A and CCS-P1B are running.

Malfunctions T1, LPCS001, LPCS PUMP TRIP T2, CCS001A, CCS-P1A PUMP TRIP CCS003C, CCS-P1C FAILS TO AUTO START T3, MSS005J, SRV B21-47C FAILS OPEN T7, MSS001, Ramp 15:00, Final Value 1000, Delay 10, STEAM LEAK IN THE DRYWELL T7, MSC007, Final Value 10, Delay 5:00 DRYWELL TO CONTAINMENT LEAKAGE HPCS003, HPCS FAILS TO AUTO INITIATE Remotes T4, MSS012, DIV II SRV SWITCH T5, MSS010, DIV I FUSES T6, MSS017, DIVII FUSES Event 0 RUN CREW: Conduct panel walkdown and assume the shift RSMS-OPS-NRC10-1 Rev. 02 Page 4 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Action Event 1 Complete section 7.3 of STP-205-6301 for scheduled SRO: Direct the performance of STP-205-6301 LPCS PUMP AND monthly performance. VALVE OPERABILITY TEST RO: Perform actions of STP-205-6301

Contact the reactor building operator to verify oil level in the upper and lower sight glasses is within the High and Low marks ROLE PLAY:

on the Upper and Lower sight glasses.

As Reactor building operator :

Contact the reactor building operator to verify that the suction When requested, report that the oil level is satisfactory pressure gauge is installed for the LPCS pump and that the suction press gauge is

Start E21-C001, LPCS PUMP.

installed.

Check that E21-C001, LPCS Motor AMPS indicates less than 157 amps.

Check E21-F011, LPCS MIN FLOW VLV TO SUPPRESSION POOL, is open.

Throttle E21-F012, LPCS TEST RETURN VLV TO SUPPRESSION POOL to obtain a flow rate of 5050 gpm as indicated on E21-R600, LPCS PUMP FLOW.

Check E21-F011 is closed.

WHEN the LPCS pump has been running at stable reference conditions for at least 2 minutes, THEN perform the following:

Record pump flow as indicated on E21-R600 on Data Sheet 1.

RSMS-OPS-NRC10-1 Rev. 02 Page 5 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Action Event 2 Complete STP-509-0101 MAIN TURBINE BYPASS SRO: Direct the performance of STP-509-0101 for bypass SYSTEM VALVE CYCLE TEST for Bypass valve #1 valve #1 only.

only for a post maintenance test on the ERIS point RO: Perform the actions of STP-509-0101 Notify OSM/CRS of the test completion.

Event 3 Low Pressure Core Spray pump trip. (Technical BOP Recognize and report trip of LPCS pump.

Specifications)

Recognize and report LPCS pump low discharge line pressure T1, LPCS PUMP TRIP. Contact operator to investigate LPCS pump trip locally.

RSMS-OPS-NRC10-1 Rev. 02 Page 6 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Action ROLE PLAY: As operator sent to the LPCS pump: SRO:

Direct the closure of E21-MOVF012 LPCS test return Report no apparent problem with the pump. valve.

As operator sent to the LPCS pump breaker:

Direct the actions of ARP Report that there is an over current relay flag and 86 device tripped. RO:

Close E21-MOVF012 LPCS test return valve.

As Back panel operator:

Review ARP for required actions Report the discharge pressure the same as the ERIS

Verify that E21-MOVF011 LPCS min. flow valve is pressure indication. closed

Request E21-PSN654 back panel pressure reading SRO:

Enter Tech Spec 3.5.1 condition A (7 day LCO)

Make required notifications per OSP-046

Possible actions if RHR-A low discharge pressure alarm is received:

Enter Tech Spec 3.5.1 condition C (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO)Two low pressure ECCS systems inop RSMS-OPS-NRC10-1 Rev. 02 Page 7 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Action Event 4 CCS Pump A trips, CCS Pump C fails to auto start. BOP

Recognize and report the trip of CCS-P1A TPCCW pump (Requires manual start of standby pump per AOP-0012)

Start CCS-P1C due to failure to auto start

Review ARP for required actions T2, Inserts trip of CCS-P1A SRO

Direct the review of AOP-012 Loss of CCS for applicable actions

Make notifications per OSP-046 ROLE PLAY: As operator sent to the pump breaker:

Report an over current trip on CCS-P1A BOP

Dispatch operators to investigate pump trip locally As operator sent to CCS-P1C:

Dispatch operator to obtain local parameters for CCS-Report all parameters normal P1C

Review AOP-012 for applicable actions. Report none applicable.

EVENT 5 SRV B21-F047C fails open. (Technical Specifications) BOP / Recognize and report that SRV B21-F047C is open T3, Fails open SRV 47C ATC SRO Direct implementation of AOP-035 Stuck Open SRV BOP Announce the following over the Gaitronics:

Attention in the plant. "Safety Relief Valve Open, all personnel evacuate the Containment. Personnel evacuate to WMC

At H13-P601, place SORV control switch to OPEN.

WHEN reactor power is equal to or less than 90%,

THEN attempt to close the open SRV as follows:

o At H13-P601, take the control switch to OFF.

o IF SRV remains open, THEN at H13-P601, take the control switch to OPEN and back to OFF.

T4, DIV II SRV SWITCH

IF SRV remains open, THEN at H13-P631, perform the following:

RSMS-OPS-NRC10-1 Rev. 02 Page 8 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Action o Take the control switch to OPEN and back to OFF.

o IF the SRV did not close, THEN take the control switch to OPEN and back to OFF.

ATC Reduce reactor power to equal to or less than 90% with recirc flow.

SRO Enter the following Tech Specs:

3.5.1 E ADS, 3.5.1 F ADS & ECCS, 3.6.2.1 S. Pool temp.,

3.6.5.3. Drywell PCIV, TRM 3.4.4 A Open SRV

Direct reference to AOP-007 Loss of Feedwater Heating

Direct reference to AOP-024 Thermal Hydraulic Stability Controls ATC

Refer to AOP-024 and 007.

Determine and report required entry into AOP-007 SRO

Direct the actions of AOP-007.

ATC

Reduce recirculation flow until thermal power lowers by 20% (620 MWth) or 60% (50.7 Mlbm/hr) core flow is reached.

NOTE: The SRV will close when the fuses are removed. Actions of AOP-007 may not be performed prior to SRV closure.

ATC Reduce recirculation flow until thermal power lowers by 20% (620 MWth) or 60% (50.7 Mlbm/hr) core flow is reached.

BOP IF the SRV is still open, THEN deenergize the solenoids by RSMS-OPS-NRC10-1 Rev. 02 Page 9 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Action T5, DIV I FUSES pulling the applicable fuses listed in ATTACHMENT 1,SAFETY RELIEF VALVES SOLENOID CIRCUIT T6, DIVII FUSES FUSES EVENT 6 Steam leak in the drywell on SRV closure. Manual TEAM Recognize and report steam leak in the drywell scram or automatic scram on high drywell pressure.

SRO Direct the ATC to place the mode switch in Shutdown.

T6, Steam leak in the drywell with bypass leakage ATC Place the mode switch in shutdown Give SCRAM report to the SRO SRO Enter EOP-001 Enter EOP-002 Direct a pressure control band of 500# to 1090#

Direct installation of Enclosure 20 to bypass drywell cooling interlocks Direct implementation of AOP-001 Reactor scram and AOP-002 Turbine / Generator trips to the ATC Direct implementation of AOP-003 Automatic Isolations to the BOP Direct suppression pool cooling with RHR with OSP-0053 ATTACHMENT 12 - ESTABLISHING SUPPRESSION POOL COOLING RSMS-OPS-NRC10-1 Rev. 02 Page 10 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Action BOP Perform actions of ATTACHMENT 12 -

ESTABLISHING SUPPRESSION POOL COOLING Throttle E12-F068A(B), RHR HX A(B) SVCE WTR RTN, not to exceed 5800 gpm flow.

Start/Verify Running RHR PUMP A(B).

Verify E12-F042A(B), RHR PUMP A(B) LPCI INJECT ISOL VALVE, Closed.

Verify E12-F053A(B), RHR PUMP A(B) SDC INJECTION VALVE, Closed.

Open/Verify Open E12-FO24A(B), RHR PUMP A(B)

TEST RTN TO SUP PL.

Verify E12-F064A(B), RHR PUMP A(B) MIN FLOW TO SUP PL, Closed.

Close E12-F048A(B), RHR A(B) HX BYPASS VALVE, when auto open signal has cleared.

Perform Enclosure 20 actions.

VERIFY Normal Service Water pressure on SWP-PI124, SVCE SPLY HDR PRESSURE OR Standby Service Water pressure on SWP-PR50A(B), STBY CLG TOWER LVL & PUMP DISCH PRESS RECORDER is greater than Containment AND Drywell pressure on CMS-PR2A(B), DRYWELL PRESSURE PLACE Control Switches for all tripped Drywell Unit Coolers to OFF.

START DIV I AND II H2 Analyzers. (H13-P808)

IF any drywell temperature on CMS-TR41A or B, DRYWELL ATMOS TEMP (H13-P808) is or has been greater than 200 °F, THEN, notify the CRS/OSM that this enclosure cannot be completed.

CONT.

RSMS-OPS-NRC10-1 Rev. 02 Page 11 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Action BOP Perform the following:

Cont. OPEN the following valves: (H13-P870)

SWP-MOV4A DRYWELL UC SUPPLY SWP-MOV5A DRYWELL UC RETURN SWP-MOV4B DRYWELL UC SUPPLY SWP-MOV5B DRYWELL UC RETURN VERIFY closed the following: (H13-P877)

EJS-ACB25 NHS-MCC102A SPLY BRKR

EJS-ACB66 NHS-MCC102B SPLY BRKR START Drywell Unit Coolers as directed by the CRS.

SRO Direct reactor water level band of -20 to 51.

Direct enclosure 12 for expanded band BOP Perform actions of Enclosure 12 for the expanded reactor water level band SRO

Recognize drywell leak into containment

Anticipate the need to Emergency Depressurize due to approaching the unsafe of the Pressure Suppression curve of EOP-002

Direct opening all steam drains and turbine bypass valves.

Direct override automatic injection from all low pressure ECCS systems.

RSMS-OPS-NRC10-1 Rev. 02 Page 12 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Action ATC Fully open the main turbine steam bypass valves BOP

Open all available steam line drain valves.

Override all low pressure injection valves closed.

Recognize and report that HPCS did not auto initiate on the high drywell pressure.

SRO

Recognize entry into the unsafe region of the Pressure Suppression Curve.

Direct BOP to open 7 ADS/SRVs to Emergency Depressurize the reactor BOP Open 7 ADS / SRVs and report SRO Declare the reactor depressurized when reactor pressure falls below 46#

When the FREEZE Termination Criteria are met, and/or at the direction of the floor instructor RSMS-OPS-NRC10-1 Rev. 02 Page 13 OF 15

VI. TERMINATION CRITERIA:

The reactor vessel has been depressurized (<46 psig)

Containment parameters addressed with an improving trend VII. CRITICAL TASKS

1. Close failed SRV (containment integrity)

2. Open 7 ADS / SRVs when PSP curve is exceeded.

RSMS-OPS-NRC10-1 Rev. 02 Page 14 OF 15

Offgoing OSM: Oncoming OSM: Off-Going Shift N D (Print) KCN (Print) KCN Date PART I - TO BE REVIEWED PRIOR TO ASSUMING THE SHIFT UNIT STATUS MODE 1 RX POWER 100%

EVOLUTIONS (COMPLETED / IN PROGRESS / PLANNED); GENERAL INFORMATION Complete section 7.3 of STP-205-6301 monthly performance. Establish reference conditions, then Complete STP-509-0101 MAIN TURBINE BYPASS SYSTEM VALVE CYCLE TEST for Bypass Valve #1 only. Post maintenance test for the ERIS point.

SIGNIFICANT LCO STATUS Required Short Term LCOs have been entered for STP-509-0101 (3.3.1.1 RPS Instrumentation; 3.3.4.1 EOC-RPT Instrumentation and 3.3.2.1 Control Rod Block Instrumentation)

EQUIPMENT STATUS EOOS = 10 GREEN DIV I Work Week Night Orders Standing Orders Board Walkdown Temp Alts (Signature: Oncoming OSM Review Completed) KCN RSMS-OPS-NRC10-1 Rev. 02 Page 15 OF 15

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 2 Op-Test No.: NRC Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1, 87% power. Plant startup is in progress. GOP-0001 complete through step G.41 Turnover: Swap level control input to FWLC to support I&C surveillance. Continue with power ascension with reactor recirculation flow per RE instructions.

Event Malf. No. Event Event No. Type* Description 1 NA N Swap Feedwater Level Control level input to alternate channel to (ATC,SRO) support I&C surveillance scheduled later today.

2 NA R (ATC) Raise power with reactor recirculation flow.

3 RCIC I Inadvertent initiation of RCIC. (Technical Specifications)

(BOP,SRO) 4 ED003B C Loss of NNS-SWG1B.

(BOP,SRO) 5 C Control Rod Drifts in. (AOP-0061). (Technical Specification)

(ATC,SRO)

At the examiners direction a second control rod drifts in. Manual Scram.

6 CRD0014 M (All) ATWS Hydraulic lock.

RPS001A 7 MGEN001 C (All) Main Turbine/Generator Trip (After EOP entry) 8 SLC002A C SLC A sheared coupling. (After EOP entry)

(BOP,SRO)

SLC001B SLC B suction valve fails to open. (After EOP entry)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (6):RCIC Initiation, NNS-SWG1B Loss, Rod Drift, ATWS, Turbine trip, SLC failures Malfunctions after EOP entry (2): Turbine Trip, SLC failure Abnormal events (2): AOP-0061, AOP-0001 Major transients (1): ATWS EOPs entered (2): EOP-0001, EOP-0002 EOP contingencies (1): EOP-0001A Critical tasks (2): Terminate injection to RPV, Begin inserting control rods Rev 02

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

Description:

Swap Feedwater Level Control level input to alternate channel to support I&C surveillance scheduled later today.

Time Position Applicants Actions or Behavior SRO Direct the swap of Feedwater Level Control level input signals per SOP-0009 REACTOR FEEDWATER SYSTEM ATC Swap to A feedwater level control signal per SOP-009

Ensure no deviation on C33-R600, FW REG VALVES MASTER FLOWCONTROLLER and place to MANUAL.

Swap the level control input by depressing either A or B on the RX LVL A/B SELECT Pushbutton.

Check for proper operation, then return C33-R600, FW REG VALVES MASTER FLOW CONTROLLER to AUTO as follows:

Adjust tape set 2 inches above actual vessel level and observe the deviation signal is positive.

Lower tape set 2 inches below actual vessel level and observe the deviation signal is negative.

Match tape set to actual vessel level in order to null the deviation signal.

WHEN the level signal is nulled, THEN depress the AUTO Pushbutton and check green light above the pushbutton is on.

Adjust C33-R600, FW REG VALVES MASTER FLOW CONTROLLER Tape Set to maintain the reactor level requested by the OSM/CRS.

Report the completion of level signal swap Rev 02

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

Description:

Raise power with reactor recirculation flow.

Time Position Applicants Actions or Behavior SRO Direct raising reactor power per the reactivity control plan.

ATC Raise reactor power with recirculation flow per the reactivity control plan.

Report completion of power change Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2 Event No.: 3 Page 3 of 9 Event

Description:

Inadvertent initiation of RCIC. (Technical Specifications)

Time Position Applicants Actions or Behavior EVENT CUE H13-P601/21A/E02 RCIC GLAND SEAL COMPRESSOR AUTO START BOP Recognize and report initiation of RCIC.

SRO

Direct BOP to determine if RCIC is needed for RPV level control by two independent means.

Direct BOP to trip RCIC

Direct BOP to determine if a loss of feedwater heating has occurred per AOP-007 BOP

Report normal RPV level indications

Depress the RCIC trip push button

Report to the SRO that RCIC is tripped

Refer to the ARP SRO

Enter Tech Spec 3.5.3 A (14 day LCO)

Contact Work Management Center o Notify WMC of RCIC initiation o Request maintenance support for RCIC o Request no work activities be performed on the HPCS system o Verify by administrative means High Pressure Core Spray System is OPERABLE.

Make notifications per OSP-46 ROLE PLAY Security officer will notify the control room team that he may have keyed his radio in the vicinity of H13-P629.

Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2 Event No.: 4 Page 4 of 9 Event

Description:

Loss of NNS-SWG1B.

Time Position Applicants Actions or Behavior EVENT CUE H13-P808/86/B06 NNS SWG1A OR 1B UNDERVOLTAGE.

BOP Recognize and report the loss of NNS-SWG1B Recognize and report the loss of CRD pump B due to the bus loss.

Direct SNEO to investigate NNS SWG1B locally.

Direct SNEO to investigate CRD pumps Direct SNEO to restore Turbine Building Chillers to service.

ATC Report High CRDM temperature alarm.

Direct SNEO to investigate high temperature locally Role Play As operators sent to local indications, report:

The CRDM recorder has 6 control rods above the alarm setpoint but below 350o F.

CRD pump A is ready to be started.

Provide steam tunnel temperature from InSight when requested.

SRO Contact Work Management Center to investigate bus loss.

Direct BOP to started CRD pump A per ARP-P601/22/A01 If 2 or more accumulator faults are received, then enter TS 3.5.1 Condition B.

BOP

Start Standby CRD Pump Aux Oil Pump C11-C001AP(BP), CRD AUX OIL PUMP A(B).

Place Flow Controller C11-R600 to MANUAL

Close C11-R600, CRD HYDRAULICS FLOW CONTROLLER C11-F001A/B.

Verify White Control Power Light on for CRD Pump to be started.

Start Standby Pump C11-C001A(B), CRD PUMP A(B).

Verify amps return to normal of less than 45 amps.

WHEN system flow drops below 45 gpm as indicated on C11-R606, CRD HYDR FLOW, THEN slowly throttle open Flow Controller C11-R600 to achieve 45 gpm.

WHEN flow controller C11-R600 setpoint is nulled out, THEN place to AUTO.

Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 2 Event No.: 5 Page 5 of 9 Event

Description:

Control Rod Drifts in. (AOP-0061). (Technical Specification)

At the examiners direction a second control rod drifts in. Manual Scram.

Time Position Applicants Actions or Behavior EVENT CUE H13-P680/07A/B02 CONTROL ROD DRIFT ATC

Recognize and report that control rod 08-13 is drifting in

Refer to ARP 680-07A Take actions per ARP:

On H13-P680, determine which rod(s) drifted by depressing the ROD DRIFT pushbutton and observing red lights on ROD POSITION DISPLAY.

Select the drifting rod(s) and apply a continuous insert signal.

WHEN the control rod is inserted to the full in position, THEN remove the continuous insert signal.

IF the CRD remains inserted, THEN perform actions for a Directional Control Valve (122) failure.

IF the rod drift was determined to be a failure of Directional Control Valve (122), THEN valve out the HCU per SOP-0002, Control Rod Drive Hydraulics for valve repair and Refer to Technical Specification 3.1.3.

SRO

Accept report of drifting control rod

Direct entry into AOP-0061 CONTROL ROD(S) MISPOSITIONED /

MALFUNCTION

Enter LCO 3.1.3 C for the drifting control rod ATC

Review immediate operator actions of AOP-0061

Recognize and report control rod 16-37 drifting in SRO Direct ATC to manually scram the reactor Rev 02

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

Description:

ATWS Hydraulic lock.

Time Position Applicants Actions or Behavior ATC

Place the reactor mode switch in the shut down position

Arm and depress all four manual scram push buttons

Arm and depress both ARI push buttons

Communicate ATWS report to the SRO SRO

Accept the ATWS report

Enter EOP-01A o Direct terminate and prevent injection from HPCS o Direct transfer of Recirc. Pumps to slow speed o Direct inhibiting the ADS system o Direct trip of the Recirc. Pumps o Direct installation of enclosures 16 and 24 o Direct maximizing CRD cooling water flow o Direct termination of injection from condensate and feedwater o Direct a reactor vessel level band of -60 to -140 o Direct RCIC to be tripped o Enter EOP-02 on suppression pool parameters BOP

Terminate and prevent injection from HPCS and report completion o Override Injection / Initiate HPCS o Verify E22-F004 amber override light is lit.

o STOP THE HPCS PUMP.

Inhibit the ADS system by placing the Div I and II inhibit switches to INHIBIT and report completion

Report the enclosure 16 and 24 have been installed (Instructor performed)

Maximize CRD cooling water flow and report completion o Start C11-C001AP(BP), CRD AUX OIL PUMP A(B).

o Verify C11-C001A(B), CRD PUMP A(B), white control power available light on.

o Start C11-C001A(B), CRD PUMP A(B).

o Place CRD HYDRAULICS FLOW CONTROLLER, in MANUAL and raise signal to 100%.

o Fully Open C11-F003, CRD DRIVE WATER PRESS CONTROL VALVE.

Depress the RCIC trip pushbutton and report RCIC tripped

Report Enclosure 12 installed (Instructor performed)

Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 6 Page 7 of 9 Event

Description:

ATWS Hydraulic lock.

ATC

Transfer Recirc. Pumps to slow speed and report completion o Depress both RECIRC PUMP A and B XFER TO LFMG pushbuttons simultaneously.

o Verify the following:

o LFMG BRKR 1A and 1B Close.

o RECIRC PUMP BREAKER 5A and 5B Open.

o LFMG BRKR 2A and 2B Close.

o Pump speeds stabilize near 450 RPM.

Trip both Recirc. Pumps and report completion o TRIP LFMG BRKR 2A.

o TRIP LFMG BRKR 2B.

o WHEN pump coasts down to 0% speed, THEN perform the following:

o TRIP LFMG BRKR 1A.

o TRIP LFMG BRKR 1B.

Terminate injection from condensate and feedwater and report completion o Place Master level controller in Manual o Lower the Master controller output signal to 0

Maintain a RPV water level band of -60 to -140

Perform actions of Enclosure 12 o VERIFY ARI is RESET o RESET the reactor SCRAM.

o VERIFY OPEN SCRAM DISCH VOL VENT VLVS (F010 &

180) AND SCRAM DISCH VOL DRAIN VLVS (F011 & F181)

Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 7 Page 8 of 9 Event

Description:

Main Turbine/Generator Trip (After EOP entry)

Time Position Applicants Actions or Behavior ATC Recognize and report main turbine / generator trip SRO Assign owners to AOP-001 Reactor Scram, AOP-002 Turbine generator trips and AOP-003 Automatic Isolations Direct reactor pressure control with steam line drains, turbine Bypass valves and SRVs as needed Direct a reactor pressure band of 950 and 1090 psig BOP Open all available steam line drains Adjust the manually open SRVS to maintain the turbine bypass valves open SRO Direct SLC injection Rev 02

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

Description:

SLC A sheared coupling. (After EOP entry)

SLC B suction valve fails to open. (After EOP entry)

Time Position Applicants Actions or Behavior SRO Direct SLC injection BOP Place SLC PUMP A(B) (NOT BOTH), control switch to RUN.

Verify the following:

1. SQUIB CONTINUITY A(B), light goes Off.

2. C41-F001A(B), SLC PUMP A(B) SUCT VLV, Opens.

3. C41-C001A(B), SLC PUMP A(B), Starts.

IF any required actions do not occur, THEN perform the following:

1. Place SLC PUMP A(B), control switch to STOP.

2. Repeat steps 1 and 2 for the Alternate pump.

Notify SRO of SLC injection status SRO Direct work control center to have the actions of Enclosure 15 for alternate SLC injection performed NOTE: After the scram has been reset with enclosure 12, remove the hydraulic ATWS ATC When the scram discharge volume high level alarm is reset insert a Manual Scram Recognize and report all control rods are inserted SRO Exit EOP-01A and enter EOP-01 Rev 02

Number: *RSMS-OPS-NRC10-2 RIVER Revision: 02 BEND STATION Page 1 of 14 SIMULATOR SCENARIO TRAINING PROGRAM:

SIMULATOR TRAINING LESSON PLAN:

RCIC Inadvertent Initiation - Rod Drift - Main Turbine Trip - ATWS - SLC Failure -

REASON FOR REVISION:

2010 NRC Exam PREPARE / REVIEW:

John Hedgepeth 0069 02/09/2010 Preparer KCN Date Angela Orgeron 1538 2/16/2010 Technical Review (SME) KCN Date Joey Clark 0260 2/26/2010 Operations Management KCN Date (Evaluated scenarios only)

Facility Reviewer approval via ES-301-3, 301-4

Indexing Information

I. DESCRIPTION OF SCENARIO The crew assumes the shift at 87% power, with plant start up in progress. The crew will swap Feedwater level control signal input to support an I&C surveillance. An inadvertent initiation of RCIC will occur. After the team has addressed RCIC, NNS-SWG1B will experience a fault resulting in a loss of the bus. The crew will be required to start CRD pump A. When the CRD pump swap is complete, a control rod will drift in. At the examiners direction a second control rod will drift in and a manual scram will be required. All rods will not insert and EOP-0001, RPV Control and EOP-0001A, RPV Control - ATWS are entered to control power, level and pressure. SLC will fail to initiate using the control switch. As level is lowered a trip of the Main Turbine will occur.

II. TERMINAL OBJECTIVES

1. Recognize and respond to an inadvertent initiation of RCIC..

2. Recognize and respond to a loss of NNS-SWG1B in accordance with plant procedures.

3. Recognize and respond to drifting control rod in accordance with plant procedures and Technical Specifications.

4. Recognize and respond to a Main Turbine trip and failure to scram in accordance with plant procedures.

III. PERFORMANCE OBJECTIVES A. Shift/Team

1. Recognize and respond to an inadvertent initiation of RCIC in accordance with plant procedures.

2. Recognize and respond to loss of NNS-SWG1B in accordance with plant procedures.

3. Recognize and respond to drifting control rod in accordance with plant procedures and Technical Specifications.

4. Recognize and respond to a Main Turbine trip and failure to scram in accordance with plant procedures.

RSMS-OPS-NRC10-2 Rev. 02 Page 2 OF 14

IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL TRAINING EQUIPMENT STATUS REQUIRED CONDITION FOCUS DOCUMENTS Power: 87%

AOP-0002, Main Turbine and Core: MOL, xenon equilibrium Generator Trips EOP-0001, RPV Control Equipment OOS: NONE EOP-0001A, RPV Control - STPs Due: NONE ATWS EOP-0002, Primary Containment LCOs: None Control Evolutions in progress: Plant start up RCP to raise power with recirc. flow Problem/Lit annunciators: N/A RSMS-OPS-NRC10-2 Rev. 02 Page 3 OF 14

V. GENERAL INSTRUCTIONS Event Number MFS/OR #/CAE Expected Operator Action Simulator Snapped to IC# 238 Setup Set up the following event trigger:

EVENT# 10 EVENT ACTION MGEN001, MAIN TURBINE TRIP COMMAND rrlnr = - 9.7 MALFUNCTIONS CRD014 90, CONTROL ROD HYDRAULIC LOCK-ATWS T-1 RCIC005, INADVERTENT INITIATION OF RCIC.

T-2 ED003B, NNS-SWG1B FAULT T-3 CRD0813 DRIFT IN d 2:00, CONTROL ROD 0813 FAILURES T-4 CRD1637 DRIFT IN, CONTROL ROD 1637 FAILURES SLC002A, SLC A SHEARED COUPLING SLC001B, SLC B SUCTION VALVE FALS TO OPEN REMOTE FUNCTIONS RSMS-OPS-NRC10-2 Rev. 02 Page 4 OF 14

Event Number MFS/OR #/CAE Expected Operator Action Event 1 NONE SRO Direct the swap of Feedwater Level Control level input Swap feedwater signals per SOP-0009 REACTOR FEEDWATER level control SYSTEM input signals ATC Swap to A feedwater level control signal per SOP-009 Report the completion of level signal swap Event 2 NONE SRO Direct raising reactor power per the reactivity control plan.

Raise reactor power with ATC Raise reactor power with recirculation flow per the Recirc. flow reactivity control plan.

Report completion of power change Event 3 T1 Inserts Inadvertent initiation of RCIC. BOP

Recognize and report initiation of RCIC.

SRO

Direct BOP to determine if RCIC is needed for RPV RCIC failure level control by two independent means.

Direct BOP to trip RCIC ROLE PLAY: As a Security officer, notify BOP

Report normal RPV level indications the control room team that you may have

Depress the RCIC trip push button inadvertently keyed your radio in the vicinity

Report to the SRO that RCIC is tripped of H13-P629.

Refer to the ARP SRO

Enter Tech Spec 3.5.3 A (14 day LCO)

Contact Work Management Center o Notify WMC of RCIC initiation o Request maintenance support for RCIC o Request not work activities be performed on the HPCS system o Verify by administrative means High Pressure Core Spray System is OPERABLE.

Make notifications per OSP-46 RSMS-OPS-NRC10-2 Rev. 02 Page 5 OF 14

Event Number MFS/OR #/CAE Expected Operator Action Event 4 T-2 NNS-SWG1B FAULT BOP Recognize and report the loss of NNS-SWG1B Recognize and report the loss of CRD pump B due to the Loss of bus loss.

NNS-SWG1B Direct SNEO to investigate NNS SWG1B locally.

Direct SNEO to investigate CRD pumps Direct SNEO to restore Turbine Building Chillers to service.

ATC Report High CRDM temperature alarm Direct SNEO to investigate high temperature locally Role Play As operators sent to local indications, report:

The CRDM recorder has 6 control rods above the alarm setpoint but below 350o F.

Provide steam tunnel temperature from InSight when requested.

SRO Contact Work Management Center to investigate bus loss.

Direct BOP to started CRD pump A per ARP-P601/22/A01 If 2 or more accumulator faults are received, then enter TS 3.5.1 Condition B.

RSMS-OPS-NRC10-2 Rev. 02 Page 6 OF 14

Event Number MFS/OR #/CAE Expected Operator Action BOP

Start Standby CRD Pump Aux Oil Pump C11-C001AP(BP), CRD AUX OIL PUMP A(B).

Place Flow Controller C11-R600 to MANUAL

Close C11-R600, CRD HYDRAULICS FLOW CONTROLLER C11-F001A/B.

Verify White Control Power Light on for CRD Pump to be started.

Start Standby Pump C11-C001A(B), CRD PUMP A(B).

Verify amps return to normal of less than 45 amps.

WHEN system flow drops below 45 gpm as indicated on C11-R606, CRD HYDR FLOW, THEN slowly throttle open Flow Controller C11-R600 to achieve 45 gpm.

WHEN flow controller C11-R600 setpoint is nulled out, THEN place to AUTO.

Event 5, 6, 7 T3 Control Rod Drift ATC

Recognize and report that control rod 08-13 is drifting and 8 in This will drift in control rod 08-13.

On H13-P680, determine which rod(s) drifted by Timing at chief depressing the ROD DRIFT pushbutton and observing examiners red lights on ROD POSITION DISPLAY.

discretion.

Select the drifting rod(s) and apply a continuous insert Rods drift, signal.

ATWS, turbine

WHEN the control rod is inserted to the full in trip and SLC position, THEN remove the continuous insert signal.

failure SRO

Direct entry into AOP-0061 CONTROL ROD(S)

MISPOSITIONED / MALFUNCTION

Enter LCO 3.1.3 C for the drifting control rod RSMS-OPS-NRC10-2 Rev. 02 Page 7 OF 14

Event Number MFS/OR #/CAE Expected Operator Action T4 Control Rod Drift ATC

Recognize and report control rod 16-37 drifting in SRO Direct ATC to manually scram the reactor This will drift in control rod 16-37 ATC

Place the reactor mode switch in the shut down position

Arm and depress all four manual scram push buttons

Arm and depress both ARI push buttons

Communicate ATWS report to the SRO SRO

Accept the ATWS report

Enter and take actions of EOP-01A o Direct terminate and prevent injection from HPCS o Direct transfer of Recirc. Pumps to slow speed o Direct inhibiting the ADS system o Direct trip of the Recirc. Pumps o Direct installation of enclosures 16 and 24 o Direct maximizing CRD cooling water flow o Direct termination of injection from condensate and feedwater o Direct a reactor vessel level band of -60 to -140 o Direct RCIC to be tripped o Enter EOP-02 on suppression pool parameters BOP

Terminate and prevent injection from HPCS and report completion

Inhibit the ADS system by placing the Div I and II inhibit switches to INHIBIT and report completion

Report the enclosure 16 and 24 have been installed

Maximize CRD cooling water flow and report completion

Depress the RCIC trip pushbutton and report RCIC tripped RSMS-OPS-NRC10-2 Rev. 02 Page 8 OF 14

Event Number MFS/OR #/CAE Expected Operator Action ATC

Transfer Recirc. Pumps to slow speed and report completion

Trip both Recirc. Pumps and report completion

Terminate injection from condensate and feedwater and report completion

Maintain a RPV water level band of -60 to -140

Perform actions of Enclosure 12 ATC Recognize and report main turbine / generator trip SRO Direct a reactor pressure band of 950 and 1090 psig BOP Open all available steam line drains Adjust the manually open SRVS to maintain the turbine bypass valves open SRO Direct SLC injection BOP Notify SRO of SLC injection status SRO Direct work control center to have the actions of Enclosure 15 for alternate SLC injection performed NOTE: After the scram has been reset with enclosure 12, remove the hydraulic ATWS ATC Recognize and report all control rods are inserted SRO Exit EOP-01A and enter EOP-01 When the FREEZE Termination Criteria are met, and at the direction of the floor instructor RSMS-OPS-NRC10-2 Rev. 02 Page 9 OF 14

VI. TERMINATION CRITERIA:

The exercise should be terminated when the performance objectives have been achieved or the operators are unable to diagnose and respond effectively to the scenario.

The following conditions provide an indication of performance objective achievement for this scenario; Critical Tasks are indicated by an *:

EOP-0001A, RPV Control - ATWS implemented

Lower RPV water level

Terminate and Prevent HPCS

Inhibit ADS

Pressure control established on SRVs and MSL Drains

Take action to reduce power to prevent exceeding Containment design limits

EOP-0002, Primary Containment Pressure Control implemented

All rods in RSMS-OPS-NRC10-2 Rev. 02 Page 10 OF 14

VII. REFERENCES A. Plant Procedures

1. AOP-0001, Reactor Scram

2. AOP-0002, Main Turbine and Generator Trips

3. AOP-0003, Automatic Isolations

4. EOP-0001, RPV Control

5. EOP-0001A, RPV Control - ATWS

6. EOP-0002 Primary Containment Control RSMS-OPS-NRC10-2 Rev. 02 Page 11 OF 14

Offgoing OSM: Oncoming OSM: Off-Going Shift N D (Print) KCN (Print) KCN Date PART I - TO BE REVIEWED PRIOR TO ASSUMING THE SHIFT UNIT STATUS MODE 1 RX POWER 87%

EVOLUTIONS (COMPLETED / IN PROGRESS / PLANNED); GENERAL INFORMATION Plant start up in progress per GOP-001. Complete through step G.41 Swap Feedwater level control input signal from B to A. Support for I&C, then Continue power ascension with Recirc. Flow at 2% per hour per RCP guidance SIGNIFICANT LCO STATUS None EQUIPMENT STATUS EOOS 10 / GREEN Night Orders Standing Orders Board Walkdown Temp Alts (Signature: Oncoming OSM Review Completed) KCN RSMS-OPS-NRC10-2 Rev. 02 Page 12 OF 14

CHANGE PLANNED PERFORMED COMMENTS APPROVAL STEP RCIS ROD FROM TO M PERF VER C RE SRO Instruction RE / SRO RE SRO COMMENTS Thermal limits &

preconditioning Run MON and review thermal limits and margin verified 049 preconditioning margin.

Currently below Record date / time the preconditioning state 050 28-21 08 10 I NA 051 28-37 08 10 I NA 052 20-29 08 10 I NA 053 36-29 08 10 I NA RSMS-OPS-NRC10-2 Rev. 02 Page 13 OF 14

Raising reactor power within guidance of EN-RE-205.

Ramp rate is ~4 % CTP / hr below the preconditioned state.

Ramp rate is ~1 % CTP / hr above the preconditioned state.

PLANNED PERFORMED CHANGE COMMENTS APPROVAL 054 Instruction Left @ ATC RE SRO Raise reactor power to 90% (2782 MWth), with recirc. Flow at 2% per hour 055 Instruction Left @ ATC RE SRO 056 Instruction Left @ ATC RE SRO 057 Instruction Left @ ATC RE SRO 058 Instruction Left @ ATC RE SRO 059 Instruction Left @ ATC RE SRO RSMS-OPS-NRC10-2 Rev. 02 Page 14 OF 14

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 3 Op-Test No.: NRC Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1, 70% power. Tech Spec required shutdown in progress due to expiration of TS 3.8.1 Condition B. Condition F entered 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ago. Must be in Mode 3 in 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . Div 2 Diesel Generator tagged out.

Turnover: GOP-0002 complete to Step 11. Remove FWS-P1A from service. Continue shutdown by driving control rods per RE instruction.

Event Malf. Event Event No. No. Type* Description 1 NA N Secure Feedwater Pump A per SOP-0009.

(BOP,SRO) 2 NA R (ATC) Reduce reactor power by control rod insertion.

3 B21001A I (CRS) RPV Level Instrument 004A fails downscale (Tech Requirement Manual) Fail instrument which is NOT selected.

4 RPS003A C Loss of RPS Bus A (SRO,BOP) 5 SASMO C SAS-MOV102 failed to automatically isolate. (Technical V102P (BOP,SRO) Specifications) 6 ED001 M (All) Loss of offsite power.

7 RCIC002 C RCIC fails to automatically initiate. (After EOP entry)

(BOP,SRO) 8 HPCS002 C E22-F004 fails to open. (After EOP entry)

(BOP,SRO)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (6):Level Instrument, RPS A, SAS-MOV102, LOP, RCIC, E22-F004 Malfunctions after EOP entry (2): RCIC, E22-F004 Abnormal events (2): AOP-0010, AOP-0004 Major transients (1): Loss of offsite power EOPs entered (1):EOP-0001, EOP-0002 EOP contingencies (1): Alternate Level Control Critical tasks (2):Reopen IAS-MOV106, Recover reactor water level.

Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 1 Page 1 of 8 Event

Description:

Secure Feedwater Pump A per SOP-0009.

Time Position Applicants Actions or Behavior SRO Direct the securing of Feedwater Pump A per SOP-0009.

BOP Perform actions to secure Feedwater Pump A per SOP-0009.

At H13-P680, place CNM-H/A68A, RX FWP 1A MIN FLOW FLOW CONTROLLER to MANUAL for the Reactor Feed Pump to be secured.

Open slowly FWR-FV2A, RX FWP 1A MIN FLOW VALVE using CNM-H/A68A, RX FWP 1A MIN FLOW FLOW CONTROLLER while monitoring Reactor Water Level.

IF desired to raise Reactor Water Level, THEN adjust C33-R600, MASTER FLOW CONTROLLER tape set to desired Reactor Water Level

IF the capability of meeting feed flow requirements with the remaining Feedwater Pumps is uncertain, THEN make a determination as follows:.

o Close FWS-MOV26A, RX FWP 1A DISCH VLV for the pump being shutdown.

o Verify the minimum flow valve for the pump being secured is open.

o Monitor Feed Flow/Steam Flow mismatch and RPV Level to insure remaining pump(s) can maintain level.

Stop FWS-P1A, RX FWP P1A

Verify CNM-H/A68A, RX FWP 1A MIN FLOW FLOW CONTROLLER is in AUTO for the Reactor Feed Pump that was secured.

IF Reactor Water Level was intentionally raised in Step 6.1.2, THEN adjust Reactor Water Level to desired level within normal level control band using C33-R600, MASTER FLOW CONTROLLER tape set.

Verify min flow valve closes 1 - 3 minutes after pump shutdown.

Verify FWS-MOV26A(B)(C), RX FWP P1A (B)(C) DISCH VLV is closed.

Role Play As Turbine building operator accept actions for feedwater pump shutdown as directed.

Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 2 Page 2 of 8 Event

Description:

Reduce reactor power by control rod insertion.

Time Position Applicants Actions or Behavior SRO Direct power reduction with control rods per the reactivity control plan.

ATC Insert control rods per the reactivity control plan

Insert control rod 28-37 from position 10 to position 06

Insert control rod 20-29 from position 10 to position 06

Insert control rod 36-29 from position 10 to position 06

Insert control rod 28-21 from position 10 to position 06 Report the completion of rod movement Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 3 Page 3 of 8 Event

Description:

RPV Level Instrument 004A fails downscale (Tech Requirement Manual)

Time Position Applicants Actions or Behavior ATC Recognize and report the failed level instrument SRO Direct reference to the ARP ATC Request I&C support per the ARP SRO Contact the work management center for I&C support.

Make notifications per OSP-46 Enter TRM 3.3.7.3 A( 7 day LCO) for the failed instrument ATC Direct the reactor building operator take A level instrument to OUT OF SERVICE locally.

Role Play As reactor building operator accept the direction to take the A level instrument to OOS Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 4/5 Page 4 of 8 Event

Description:

Loss of RPS Bus A SAS-MOV102 failed to automatically isolate. (Technical Specifications)

Time Position Applicants Actions or Behavior ATC Recognize and report the loss of RPS-A SRO Direct actions of AOP-10 loss of an RPS Bus ATC Report no single rod scram BOP Perform AOP-10 actions.

On H13-P610, place RPS A(B) POWER TRANSFER SWITCH to the AVAILABLE power source for RPS Bus A(B).

On H13-P601, depress the following to reset the isolation:

B21H-S33, INBD ISOLATION SEAL-IN RESET Pushbutton B21H-S32, OUTBD ISOLATION SEAL-IN RESET Pushbutton

At H13-P870, reopen the following isolation valves:

IAS-MOV106, INST AIR OUTBD ISOL CCP-MOV138, CONTMT SPLY OUTBD ISOL CCP-MOV142, RR PUMP CLG SUPPLY CCP-MOV143, RR PUMP CLG DN STREAM RTN CCP-MOV159, CONTMT RTN OUTBD ISOL

At H13-P669 and P671, Neutron Monitoring Cabinets, depress S1, RESET Pushbutton ATC or BOP

Place C71A-S5A, SCRAM RESET LOGIC A and C71A-S5C, SCRAM RESET LOGIC C in RESET BOP

Place control switches for all tripped Drywell Unit Coolers to OFF.

At H13-P877, close the following breakers:

o EJS-ACB09, NORM CHGR 1A SPLY BRKR o EJS-ACB25, NHS MCC102A SPLY BRKR

At H13-P870, reopen the following isolation valves:

o SWP-MOV4A, DRYWELL UC SUPPLY o SWP-MOV5B, DRYWELL UC RETURN o DFR-AOV102, RB FLOOR DR OUTBD ISOL o CNS-MOV125, CNDS MKUP OUTBD ISOL o FPW-MOV121, F-P WTR OUTBD ISOL o SAS-MOV102, SVCE AIR OUTBD ISOL o DER-AOV127, RB EQPT DR OUTBD ISOL o WCS-MOV172 BW TK DR OUTBD ISOL

Report to SRO that SAS-MOV102 failed to isolate

Attempt to manually close SAS-MOV102

Start additional Drywell Unit Coolers as needed per SOP-0060, Drywell Cooling.

Rev 01

Op-Test No.: Scenario No.: 3 Event No.: 4/5 Page 5 of 8 Event

Description:

Loss of RPS Bus A SAS-MOV102 failed to automatically isolate. (Technical Specifications)

Time Position Applicants Actions or Behavior BOP

At H13-P863, reopen the following isolation valves:

o HVN-MOV127, CHW SPLY OUTBD ISOL o HVN-MOV128, CHW RTN OUTBD ISOL

At H13-P863, perform the following to reset HVK-MOV10A, CHW SURGE TK A NORM MKUP:

o Place HVK-MOV10A, CHW SURGE TK A NORM MKUP Control Switch in CLOSE.

o Place HVK-MOV10A, CHW SURGE TK A NORM MKUP Control Switch in AUTO.

At H13-P808, reopen the following isolation valves:

o RCS-MOV61A, FCV A ACTUATOR LEAKOFF o RCS-MOV60A, FCV A RETURN ISOL VLV o RCS-MOV59A, FCV A CLOSING SPLY VLV o RCS-MOV58A, FCV A OPENING SPLY VLV

At H13-P601, reopen the following isolation valves:

o B33-F019, REACTOR WATER UP STREAM SAMPLE VLV o B33-F020, REACTOR WATER DN STREAM SAMPLE VLV o B21-F019, MSL WARMUP HDR OUTBD CONTMT ISOL VLV o B21-F067A, MSL A DRAIN VALVE o B21-F067B, MSL B DRAIN VALVE o B21-F067C, MSL C DRAIN VALVE o B21-F067D, MSL D DRAIN VALVE

Request SRO guidance for further system restoration / restart.

SRO

Enter EOP-03 for Annulus pressure high

Enter T.S. 3.6.1.3 for SAS-MOV102 failure to isolate

Direct Work Management Center to initiate actions to close and deactivate SAS-MOV102

May direct closure of SAS-MOV103.

Role Play As control building operator:

When requested to investigate RPS-M/G A failure, report no problem can be found visually.

Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 6/7/8 Page 6 of 8 Event

Description:

Loss of offsite power.

RCIC fails to automatically initiate. (After EOP entry)

E22-F004 fails to open. (After EOP entry)

Time Position Applicants Actions or Behavior ATC

Recognize and report reactor scram due to loss of offsite power

Place the reactor mode switch in shut down

Give scram report to the SRO SRO

Enter EOP-01direct level control with RCIC and HPCS

Direct a level band of 51 to -20

Direct pressure control with RCIC and SRVs

Direct a pressure band of 950# to 1090#

BOP Recognize and report the failure of HPCS to inject Event 7/8 Recognize and report the failure of RCIC to initiate Direct the Reactor building operator to manually open the HPCS injection valve Re-align HPCS suction to suppression pool or secure the HPCS pump.

If directed to align HPCS to Suppression Pool:

Close E22-F001, HPCS PUMP CST SUCTION VALVE

WHEN E22-F001 indicates dual indication, THEN open E22-F015, HPCS PUMP SUP PL SUCTION VALVE SRO Direct manual start and injection with RCIC Event 7 May direct alignment of HPCS to Suppression Pool BOP Manually start and inject with RCIC Event 7

Start E51-C002C, GLAND SEAL COMPRESSOR.

Open E51-F045, RCIC STEAM SUPPLY TURBINE STOP VALVE.

Verify the following valves are closed:

o E51-F025, RCIC STM SPLY DR POT UP STREAM ISOL VALVE o E51-F026, RCIC STM SUPLY DR POT DN STREAM ISOL VALVE o E51-F004, RCIC TURB EXH DR POT UP STREAM ISOL VALVE o E51-F005, RCIC TURB EXH DR POT DN STREAM ISOL VALVE

Verify E51-F019, RCIC MIN FLOW VLV TO SUPPRESSION POOL is open.

To inject into the vessel perform the following:

o Open E51-F013, RCIC INJECT ISOL VALVE.

SRO Direct WMC to assist with the HPCS injection valve failure Event 8 SRO Direct actions of AOP-004 LOSS OF OFFSITE POWER and AOP-016 LOSS OF STANDBY SERVICE WATER Rev 01

Op-Test No.: Scenario No.: 3 Event No.: 6/7/8 Page 7 of 8 Event

Description:

Loss of offsite power.

RCIC fails to automatically initiate. (After EOP entry)

E22-F004 fails to open. (After EOP entry)

Time Position Applicants Actions or Behavior ATC Perform actions of AOP-004 and AOP-016

Dispatch operator to locally monitor diesel generator operation per PEP-0026, Diesel Generator Operating Logs.

Verify initiation of the Standby Service Water System.

Verify SWP-MOV96B, NORM SVCE WTR RETURN is closed

Operate the following valves to isolate SSW Division II and place redundant SSW Division I in service:

CLOSE OPEN

SWP-MOV73B, HVR-UC5

SWP-MOV73A, HVR-UC5 SUPPLY SUPPLY

SWP-MOV74B, HVR-UC5

SWP-MOV74A, HVR-UC5 RETURN RETURN

SWP-MOV77B, HPCS D/G

SWP-MOV77A, HPCS D/G SUPPLY SUPPLY

SWP-MOV506B, HPCS D/G

SWP-MOV506A, HPCS D/G RETURN RETURN

SWP-MOV4B, DRYWELL UC

SWP-MOV4A, DRYWELL UC SUPPLY SUPPLY

SWP-MOV5B, DRYWELL UC

SWP-MOV5A, DRYWELL UC RETURN RETURN

SWP-MOV501B, RPCCW HX B

SWP-MOV501A, RPCCW HX A SUPPLY SUPPLY

SWP-MOV511B, RPCCW HX B

SWP-MOV511A, RPCCW HX A RETURN RETURN SRO

Direct installation of Enclosures 3 DEFEATING RCIC HIGH SUPPRESSION POOL WATER LEVEL SUCTION TRANSFER INTERLOCK and 33 DEFEATING RCIC HIGH AREA TEMPERATURE ISOLATION INTERLOCKS

Direct installation of Enclosure 20 DEFEATING DRYWELL COOLING ISOLATION INTERLOCKS

Enter EOP-002 on high Drywell temperature BOP Perform the actions of Enclosure 3

REMOVE relay E51A-K79 (back panel)

CLOSE E51-F031, RCIC PUMP SUP PL SUCTION VALVE

OPEN E51-F010, RCIC PUMP CST SUCTION VALVE Perform the actions of Enclosure 33 (request to the back panel operator)

Rev 01

Op-Test No.: Scenario No.: 3 Event No.: 6/7/8 Page 8 of 8 Event

Description:

Loss of offsite power.

RCIC fails to automatically initiate. (After EOP entry)

E22-F004 fails to open. (After EOP entry)

Time Position Applicants Actions or Behavior BOP Perform the actions of Enclosure 20

PLACE Control Switches for all tripped Drywell Unit Coolers to OFF.

PLACE the key lock switches in the EMERGENCY position (back panel)

START DIV I AND II H2 Analyzers.

OPEN the following valves:

o SWP-MOV4A DRYWELL UC SUPPLY o SWP-MOV5B DRYWELL UC RETURN

VERIFY closed the following:

o EJS-ACB25 NHS-MCC102A SPLY BRKR

START Drywell Unit Coolers as directed by the CRS.

SRO Direct operator to start all drywell unit coolers Role Play As Load Dispatcher when contacted report:

Unknown cause for the loss of power and at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months before power can be restored Rev 01

Number: *RSMS-OPS-NRC10-3 RIVER Revision: 01 BEND STATION Page 1 of 13 SIMULATOR SCENARIO TRAINING PROGRAM:

SIMULATOR TRAINING LESSON PLAN:

Loss of RPS, Loss of Offsite Power REASON FOR REVISION:

NRC 2010 exam PREPARE / REVIEW:

John Hedgepeth 0069 02/15/2010 Preparer KCN Date Angela Orgeron 1538 2/16/2010 Technical Review (SME) KCN Date Joey Clark 0260 2/26/2010 Operations Management KCN Date (Evaluated scenarios only)

Facility Reviewer approval via ES-301-3, 301-4

Indexing Information

I. DESCRIPTION OF SCENARIO The scenario begins at 70% power with Shutdown in progress due to expiration of T.S. 3.8.1 for Div II diesel generator. The crew will continue the plant shutdown per GOP-002. The crew will secure feed water pump A and lower power with control rods. RPV level instrument 004A will fail down scale and the SRO will enter TRM 3.3.7.3. A loss of RPS bus A will occur and SAS-MOV102 will fail to automatically or manually isolate. A loss of offsite power will occur causing a loss of Condensate pumps and Feedwater pumps.

HPCS injection valve will not open and will not open during the scenario. RCIC will fail to automatically start however it can be manually started.

II. TERMINAL OBJECTIVES

1. Recognize and respond to a Loss of RPS A in accordance with AOP-0010.

2. Recognize and respond to a complete loss of offsite power in accordance with plant procedures

3. Recognize and respond to the failure of the RPV level instrument.

4. Recognize and respond to the failure of HPCS and RCIC.

5. Establish safe and stable plant conditions following a loss of offsite power in accordance with Abnormal Operating Procedures, Emergency Operating Procedures, and other applicable plant procedures.

RSMS-OPS-NRC10-3 Rev. 01 Page 2 OF 13

III. PERFORMANCE OBJECTIVES A. Shift/Team

1. Recognize and respond to a Loss of RPS A in accordance with AOP-0010.

2. Recognize and respond to a complete loss of offsite power in accordance with plant procedures

3. Recognize and respond to the failure of the RPV level instrument.

4. Recognize and respond to the failure of HPCS and RCIC.

5. Establish safe and stable plant conditions following a loss of offsite power in accordance with Abnormal Operating Procedures, Emergency Operating Procedures, and other applicable plant procedures.

RSMS-OPS-NRC10-3 Rev. 01 Page 3 OF 13

IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL TRAINING EQUIPMENT STATUS REQUIRED CONDITION FOCUS DOCUMENTS IC # 240 Power: 70% REP-0051 Core: MOL, xenon equilibrium STP:

Equipment OOS: Div II D/G GOP 002 STPs Due: none LCOs: 3.8.1 Evolutions in progress: Plant shut down Problem/Lit annunciators:

RSMS-OPS-NRC10-3 Rev. 01 Page 4 OF 13

V. GENERAL INSTRUCTIONS Event Number MFS-OR-REM-SCH Expected Operator Action Simulator Setup Setup Lower reactor power to 70% using Recirc Flow.

Place Div II D/G in Maint.

MALFUNCTIONS T1 B21001, RPV LEVEL INSTRUMENT 004A FAIL DOWN SCALE T2 RPS003A, LOSS OF RPS A T3 ED001, LOSS OF OFFSITE POWER REMOTES T10, NIS001 -RESET APRM POWER SUPPLY S1 PUSHBUTTON OVERRIDES SASMOV102P 0, SAS-MOV102 POSITION Event 0 RUN Board walkdown and turnover RSMS-OPS-NRC10-3 Rev. 01 Page 5 OF 13

Event Number MFS-OR-REM-SCH Expected Operator Action Event 1 ROLE PLAY: As Turbine building SRO: Direct the securing of Feedwater Pump A per SOP-0009.

At the direction operator accept actions for feedwater pump RO: Perform actions to secure Feedwater Pump A per SOP-0009.

of the floor shutdown as directed.

instructor.

If requested, report HWC-AOV111A is closed for FWS-P1A.

Event 2 Continue power reduction SRO Direct power reduction with control rods per the reactivity At the direction control plan.

of the floor instructor. ATC Insert control rods per the reactivity control plan.

Report the completion of rod movement Event 3 RPV level instrument failure ATC Recognize and report the failed level instrument At the direction SRO Direct reference to the ARP of the floor instructor. ATC Request I&C support per the ARP SRO Contact the work management center for I&C support.

Make notifications per OSP-46 Enter TRM 3.3.7.3 A( 7 day LCO) for the failed instrument ROLE PLAY: As reactor building ATC Direct the reactor building operator take A level instrument operator accept the direction to take the A to OUT OF SERVICE locally.

level instrument to OOS RSMS-OPS-NRC10-3 Rev. 01 Page 6 OF 13

Event Number MFS-OR-REM-SCH Expected Operator Action Insert LO_FWS-RLAOOS-A ON ROLE PLAY: Report A OOS switch is in OOS.

Event 4/5 Loss of RPS A ATC Recognize and report the loss of RPS-A At the direction SRO Direct actions of AOP-10 loss of an RPS Bus of the floor instructor. ATC Report no single rod scram BOP Perform AOP-10 actions.

ROLE PLAY: As back panel operator take At H13-P669 and P671, Neutron Monitoring Cabinets, direction to reset the APRM power supplies. depress S1, RESET Pushbutton Insert trigger 10.

ATC Place C71A-S5A, SCRAM RESET LOGIC A and C71A-S5C, SCRAM RESET LOGIC C in RESET As control building operator: BOP Report to SRO that SAS-MOV102 failed to isolate When requested to investigate RPS-M/G A failure, report no problem can be found Start additional Drywell Unit Coolers as needed per SOP-visually. 0060, Drywell Cooling.

SRO Enter EOP-03 for Annulus pressure high Enter T.S. 3.6.1.3 for SAS-MOV102 failure to isolate Direct Work Management Center to initiate actions to close and deactivate SAS-MOV102 RSMS-OPS-NRC10-3 Rev. 01 Page 7 OF 13

Event Number MFS-OR-REM-SCH Expected Operator Action Event 6/7/8 T3, Inserts a Loss of Offsite Power ATC Recognize and report reactor scram due to loss of offsite At the direction power RCIC fails to automatically initiate. (After Place the reactor mode switch in shut down of the floor EOP entry) Give scram report to the SRO instructor.

E22-F004 fails to open. (After EOP entry) SRO Enter EOP-01direct level control with RCIC and HPCS Direct a level band of 51 to -20 Direct pressure control with RCIC and SRVs Direct a pressure band of 950# to 1090#

BOP Recognize and report the failure of HPCS to inject Recognize and report the failure of RCIC to initiate Direct the Reactor building operator to manually open the HPCS injection valve SRO Direct manual start and injection with RCIC BOP Manually start and inject with RCIC SRO Direct WMC to assist with the HPCS injection valve failure SRO Direct actions of AOP-004 LOSS OF OFFSITE POWER and AOP-016 LOSS OF STANDBY SERVICE WATER ATC Perform actions of AOP-004 and AOP-016 SRO Direct installation of Enclosures 3 DEFEATING RCIC HIGH SUPPRESSION POOL WATER LEVEL SUCTION TRANSFER INTERLOCK and 33 DEFEATING RCIC HIGH AREA TEMPERATURE ISOLATION INTERLOCKS RSMS-OPS-NRC10-3 Rev. 01 Page 8 OF 13

Event Number MFS-OR-REM-SCH Expected Operator Action ROLE PLAY:As Load Dispatcher when Direct installation of Enclosure 20 DEFEATING contacted report: DRYWELL COOLING ISOLATION INTERLOCKS Unknown cause for the loss of power and at Enter EOP-002 on high Drywell temperature least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months before power can be restored BOP Perform the actions of Enclosure 3 Perform the actions of Enclosure 33 Perform the actions of Enclosure 20 START Drywell Unit Coolers as directed by the CRS.

SRO Direct operator to start all drywell unit coolers When the FREEZE Termination Criteria are met, and at the direction of the floor instructor RSMS-OPS-NRC10-3 Rev. 01 Page 9 OF 13

VI. TERMINATION CRITERIA:

The exercise should be terminated when the performance objectives have been achieved or the operators are unable to diagnose and respond effectively to the scenario.

The following conditions provide an indication of performance objective achievement for this scenario; Critical Tasks are indicated by an asterisk:

RCIC initiated manually and level being controlled between 10 and 51 inches.

IAS-MOV106 reopened to avoid an unintended RPS actuation.

RPV pressure control.

EOP-1 implemented

EOP-2 implemented

AOP-0001 implemented

AOP-0002 implemented

AOP-0003 implemented

AOP-0004 implemented

AOP-0010 implemented RSMS-OPS-NRC10-3 Rev. 01 Page 10 OF 13

VII. REFERENCES A. Plant Procedures

1. EIP-2-001, Classification of Emergencies

2. EOP-1, RPV Control

3. EOP-2, Containment Control

4. GOP-0002, Shut Down

5. AOP-0001, Reactor Scram

6. AOP-0002, Main Turbine and Generator Trips

7. AOP-0003, Automatic Isolations

8. AOP-0004, Loss of Offsite Power

9. AOP-0008, Loss of Instrument Air

10. AOP-0010, Loss of One RPS Bus RSMS-OPS-NRC10-3 Rev. 01 Page 11 OF 13

Offgoing OSM: Oncoming OSM: Off-Going Shift N D (Print) KCN (Print) KCN Date PART I - TO BE REVIEWED PRIOR TO ASSUMING THE SHIFT UNIT STATUS MODE 1 RX POWER 70%

EVOLUTIONS (COMPLETED / IN PROGRESS / PLANNED); GENERAL INFORMATION Tech Spec required shut down in progress due to expiration of LCO 3.8.1. condition B Condition F entered 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ago. The plant must be in mode 3 in 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months .

GOP-002 complete to step 11 Remove FWS-P1A from service Continue plant shut down by rod insertion per RCP step #67 only, then contact RE.

SIGNIFICANT LCO STATUS Div II D/G 3.8.1 EQUIPMENT STATUS Div II D/G tagged out EOOS 9.5 / Green Night Orders Standing Orders Board Walkdown Temp Alts (Signature: Oncoming OSM Review Completed) KCN RSMS-OPS-NRC10-3 Rev. 01 Page 12 OF 13

CHANGE PLANNED PERFORMED COMMENT APPROVAL STEP RCIS ROD FROM TO M PERF VER C RE SRO 20-29 N/A 28-37 N/A 067 2,1 36-29 10 06 I N/A 28-21 N/A 12-21 N/A 20-45 N/A 068 2,3 44-37 10 06 I N/A 36-13 N/A 36-45 N/A 44-21 N/A 069 2,4 20-13 10 06 I N/A 12-37 N/A 04-29 N/A 28-53 N/A 070 2,2 52-29 10 06 I N/A 28-05 N/A RSMS-OPS-NRC10-3 Rev. 01 Page 13 OF 13

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 4 Op-Test No.: NRC Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 69% power Turnover: Rotate CCP pumps to support scheduled maintenance. Place CCP-P1A in service, secure CCP-P1C. Power ascension in progress. GOP-001 complete through G 41. Continue power ascension per the RCP at step 83.

Event Malf. No. Event Event No. Type* Description 1 NA N Rotate Reactor Plant Component Cooling Water Pumps.

(BOP,SRO) 2 NA R (ATC) Raise reactor power with control rods.

3 FWS006B C Feedwater pump B minimum flow valve fails open.

(ATC,SRO) 4 RHR008A C (SRO) Division I ECCS Line Fill pump trip (Technical Specifications) 5 RCS016 C Reactor Recirculation FCV B LVDT failure (Technical Specification)

(SRO,ATC) 6 NA C Gland steam evaporator outlet pressure control valve failure (BOP,SRO) 7 RCS001A M (All) Reactor Recirculation Loop A Rupture 8 ED004A C (All) Loss of NJS-LDC1A (After EOP entry) 9 RHR001B C RHR B Injection valve fails to open (After EOP entry).

(BOP,SRO)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions (6): Gland steam failure, FWS min flow valve, Line fill trip, LVDT failure, Loop Rupture, Inj valve failure.

Malfunctions after EOP entry (2): NJS-LDC1A, RHR B Inj Valve Abnormal events (2): AOP-0006, AOP-0061 Major transients (1): Loop Rupture EOPs entered (2): EOP-0001, EOP-0002 EOP contingencies (1): Alternate Level Control Critical tasks (2): Isolate leak, Restore level above TAF Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 1 Page 1 of 8 Event

Description:

Rotate Reactor Plant Component Cooling Water Pumps.

Time Position Applicants Actions or Behavior SRO Direct actions to rotate Reactor Plant Component Cooling Water Pumps BOP Perform actions to rotate Reactor Plant Component Cooling Water Pumps

Verify open CCP-V21, CCP-P1A SUCTION VALVE and CCP-V26, CCP-P1A DISCHARGE VALVE for the pump to be started.

Vent the pump via Pressure Indicator CCP-PI58A, VENT VALVES.

Start the standby CCP-P1A, RPCCW PUMP 1A.

Stop the desired CCP-P1C, RPCCW PUMP 1C.

Verify the white light for the secured pump remains on.

ROLE PLAY As reactor building operator, when requested:

Report CCP-P1A suction and discharge valves are open Report that the pump seals have been vented via CCP-PI58A BOP Report the completion of rotating Reactor Plant Component Cooling Water Pumps Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 2 Page 2 of 8 Event

Description:

Raise reactor power with control rods.

Time Position Applicants Actions or Behavior SRO Direct power ascension with control rods per the RCP ATC Withdraw control rods per the RCP

Control Rod 28-45 from position 12 to position 18

Control Rod 44-29 from position 12 to position 18

Control Rod 28-13 from position 12 to position 18

Control Rod 12-29 from position 12 to position 18 Verify plant response Report control rod movement is complete ROLE PLAY If requested, as RE:

Inform the SRO you will bring him the next step after the preconditioning delay.

Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: AUDIT Scenario No.: 4 Event No.: 3 Page 3 of 8 Event

Description:

Feedwater pump B minimum flow valve fails open.

Time Position Applicants Actions or Behavior EVENT CUE Turbine load reducing, FWS-P1A min. flow valve position indication indicates OPEN (red light only)

ATC Recognize and report the FWS-P1A feed water pump B min. flow valve is open.

SRO

Direct entry into AOP-006 CONDENSATE/FEEDWATER FAILURES

Refer to AOP-007 LOSS OF FEEDWATER HEATING ATC Perform actions to close FWR-FV2B from P680

IF any of the following flow control valves have failed, THEN attempt to take manual control

or isolate the flow control valve to control reactor vessel level:

FWR-FV2B, RX FWP B MIN FLOW VALVE isolated by closing FWR-V2, RFP B MIN FLOW MAN ISOL SRO Direct the closing of FWR-V2 RFP B MIN FLOW MAN ISOL ROLE PLAY As turbine building operator:

Accept the direction to isolate FWR-V2

After 5 minute delay, report that FWR-V2 is closed Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 4 Page 4 of 8 Event

Description:

Division I ECCS Line Fill pump trip (Technical Specifications)

Time Position Applicants Actions or Behavior EVENT CUE H13-P601/21A/H08 LPCS SYSTEM INOPERATIVE H13-P601/20A/H06 DIV I RHR SYSTEM INOPERATIVE SRO May direct starting RHR-A in suppression pool cooling mode.

BOP Perform actions of ARP:

RHR PUMP A DISCH PRESSURE HI/LOW O AT H13-P629, CHECK THE TRIP UNITS TO DETERMINE IF PRESSURE IS HIGH OR LOW.

o IF not able to maintain the system filled with the LPCS/RHR Div I Water Leg Pump, THEN rack out ENS-SWG1A ACB03, RHR PUMP A MOTOR BREAKER.

LPCS INJECTION LINE PRESSURE HI/LOW o Determine if pressure is high or low by observing trip units on H13-P629.

o IF unable to fill the system, THEN rack out the pump breaker ENS-SWG1A ACB08 AND Refer To Technical Specifications Section 3.5.1 or 3.5.2.

ROLE PLAY As back panel operator, when requested:

Report the RHR and or LPCS discharge pressure based on alarm setpoint.

SRO

Enter Tech Spec 3.5.1 A (7 day LCO) & C for ECCS (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months LCO)

Enter Tech Spec 3.6.2.3 A for suppression pool cooling (7 day LCO)

Direct that the pump breakers for LPCS and RHR-A be racked out

Make notifications per OSP-46 ROLE PLAY As control building operator: when directed accept the direction to rack out the LPCS and RHR-A pump breakers Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 5 Page 5 of 8 Event

Description:

Reactor Recirculation FCV B LVDT failure (Technical Specification)

Time Position Applicants Actions or Behavior EVENT CUE Lowering reactor power Lowering turbine load Lowering loop flow for B Recirc. Pump Lowering jet pump diff. pressure on loop B jet pumps ATC

Recognize and report lowering power due to B Recirc. Flow lowering

Recognize and report Recirc. Loop mismatch > 10%

SRO

Enter AOP-024 Thermal Hydraulic Stability Controls

Enter Tech Spec 3.4.1 A for loop flow mismatch (2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months LCO)

BOP/ATC Perform actions of actions of AOP-024

Determine power/flow region using RBS DUAL LOOP OPERATION POWER/FLOW MAPS

IF a malfunction of B33-HYV-F060A(B), FLOW CONTROL VALVE is suspected, THEN evaluate inhibiting motion of the affected valve through use of the HPU Shutdown Buttons.

IF entry into the Restricted Region is unexpected, THEN perform the following:

o Immediately exit this region by performing the following actions:

o Insert Control Rods using the Shutdown Control Rod Sequence Package or as specified by Reactor Engineering, OR o Raise recirculation flow by opening Recirc FCVs o Verify FCBB 1.0 within 15 minutes and once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter while in the Restricted Region. (SR 3.2.4.1)

Contact Reactor Engineering.

IF thermal power was changed by more than 15% of rated thermal power, THEN notify Chemistry to obtain samples required by Technical Requirements Manual TLCO 3.11.2.1, Gaseous Effluent-Dose Rate.

ATC May inhibit FCV motion by arming and depressing the B HPU shutdown push buttons.

SRO

Contact Chemistry for Tech Spec required sampling, TLCO 3.11.2.1

Contact RE to determine FCBB 1.0 (SR 3.2.4.1)

Contact WMC for I&C support for the FCV failure ROLE PLAY As RE when contacted:

Report FCBB 1.0 Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 6 Page 6 of 8 Event

Description:

Gland steam evaporator outlet pressure control valve failure Time Position Applicants Actions or Behavior EVENT CUE H13-P870/54A/E05 STEAM SEAL EVAP STEAM HEADER LOW PRESSURE BOP

Recognize and report low gland steam supply pressure

Refer to the alarm response procedure SRO

Accept the report

Direct actions of the ARP

Direct opening of TME-MOVS2 Gland Steam Supply PCV Bypass Valve

Direct the ATC to monitor and report main condenser vacuum

Contact WMC for maintenance support for the PCV failure BOP

Throttle open TME-MOVS2 Gland Steam Supply PCV Bypass Valve

Restore gland steam header pressure in the green band (~ 5 psig)

ATC Report value and trend of main condenser vacuum Rev 02

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 7/8/9 Page 7 of 8 Event

Description:

Reactor Recirculation Loop A Rupture Loss of NJS-LDC1A (After EOP entry)

RHR B Injection valve fails to open (After EOP entry).

Time Position Applicants Actions or Behavior ATC

Recognize and report Reactor scram

Place the reactor mode switch to shutdown

Give the scram report to the SRO SRO

Enter EOP-01

Direct a level band of 10 to 51

Direct ADS to be inhibited ATC

Recognize and report that Recirc. Loop A source of drywell leak

Attempt to isolate the Recirc. Loop by closing the pump suction and discharge valves

Recognize and report that power has been lost to Recirc A suction and discharge valves BOP / ATC Report power loss to NJS-LDC1A ATC Inject into the RPV with condensate and feedwater BOP

Place the ADS inhibit switches to the INHIBIT position

Report ADS is overridden

Recognize and report that RHR-B injection valve did not auto open on initiation signal

Recognize and report RPV water level < -162 SRO

Direct 7 ADS/SRVs to be opened

Direct installation of Enclosure 32 DEFEATING SDC INJECTION VALVES ISOLATION INTERLOCKS

Direct the cross tie of NJS-LDC1A/1B BOP

Report 7 ADS/SRVs are open

Perform actions for enclosure 32 o Perform back panel actions o OPEN E12-F053B, RHR PUMP B SDC INJECTION VALVE as directed by the CRS.

o OPEN E12-F053A, RHR PUMP A SDC INJECTION VALVE as directed by the CRS.

SRO Enter EOP-2 on Suppression pool level and temperature high Direct placing RHR into suppression pool cooling mode if available.

Rev 02

Op-Test No.: Scenario No.: 4 Event No.: 7/8/9 Page 8 of 8 Event

Description:

Reactor Recirculation Loop A Rupture Loss of NJS-LDC1A (After EOP entry)

RHR B Injection valve fails to open (After EOP entry).

Time Position Applicants Actions or Behavior BOP Take actions to place RHR-A into suppression pool cooling mode

Verify the selected system is not required for adequate core cooling.

Throttle E12-F068A, RHR HX A SVCE WTR RTN, not to exceed 5800 gpm flow.

Start/Verify Running RHR PUMP A.

Verify E12-F042A, RHR PUMP A LPCI INJECT ISOL VALVE, closed.

Verify E12-F053A, RHR PUMP A SDC INJECTION VALVE, closed.

Open/Verify Open E12-FO24A, RHR PUMP A TEST RTN TO SUP PL.

Verify E12-F064A, RHR PUMP A MIN FLOW TO SUP PL, Closed.

Close E12-F048A, RHR A HX BYPASS VALVE, when auto open signal has cleared.

ROLE PLAY As WMC: repot that NJS-LDC1A/1B is now cross tied SRO Direct the isolation of Recirc pump A suction and discharge valves ATC Take actions to isolate recirc. pump A

Verify Recirc Pump to be isolated is secured.

Isolate the appropriate loop as follows o Close B33-F067A, RECIRC PUMP A DISCH VLV.

o Close B33-F023A, RECIRC PUMP A SUCTION VLV.

o Close G33-F100, RWCU RECIRC A SUCT.

o Monitor affected recirc pump seal pressures for indications of over pressurization.

Rev 02

Number: *RSMS-OPS-NRC10-4 RIVER Revision: 02 BEND STATION Page 1 of 15 SIMULATOR SCENARIO TRAINING PROGRAM:

SIMULATOR TRAINING LESSON PLAN:

Plant S/U / Div I line fill trip / Recirculation Line Break / LOCA REASON FOR REVISION:

2010 NRC exam PREPARE / REVIEW:

John Hedgepeth 0069 02/15/2010 Preparer KCN Date Angela Orgeron 1538 2/16/2010 Technical Review (SME) KCN Date Joey Clark 0260 2/26/2010 Operations Management KCN Date (Evaluated scenarios only)

Facility Reviewer approval via ES-301-3, 301-4

Indexing Information

I. DESCRIPTION OF SCENARIO The scenario begins with the power ascension in progress, at 69% reactor power. The crew will rotate CCP pumps to support scheduled maintenance. Continue power ascension with control rod movement per the RCP. The Gland steam supply PCV will fail closed and the bypass valve will be used to restore supply pressure. Feedwater pump B minimum flow valve will fail open and cannot be closed from the control room. The min. flow valve will need to be isolated in the field. Division I ECCS line fill pump will trip, causing a low pressure condition in the discharge piping. The LPCS and RHR-A pump breakers will be required to be racked out. B Reactor Recirculation FCV LVDT will fail and cause the B FCV to close to minimum position. After the crew has addressed the FVC issue the A Recirc. Loop will rupture. The crew will respond using EOP-1 and EOP-2 to stabilize plant conditions, RPV Flooding may be required. The crew may attempt to isolate the leak, at which time they will discover that the rupture cannot be isolated. RPV water level will be restored using HPCS, CNM and RHR B.

II. TERMINAL OBJECTIVES

1. Recognize and respond to a FWS min. flow valve failure per AOP-006 Condensate and Feedwater Failures.

2. Recognize and respond to a line fill pump trip.

3. Recognize and respond to a Reactor Recirc. FCV LVDT failure.

4. Recognize and respond to a DBA LOCA by implementing EOP-1, EOP-2, and related plant procedures.

5. Stabilize and control Primary Containment Parameters following a DBA LOCA in accordance with EOP-2 and related plant procedures.

RSMS-OPS-NRC10-4 Rev. 02 Page 2 OF 15

III. PERFORMANCE OBJECTIVES A. Shift/Team

1. Recognize and respond to a FWS min. flow valve failure per AOP-006 Condensate and Feedwater Failures.

2. Recognize and respond to a line fill pump trip.

3. Recognize and respond to a Reactor Recirc. FCV LVDT failure.

4. Recognize and respond to a DBA LOCA by implementing EOP-1, EOP-2, and related plant procedures.

5. Stabilize and control Primary Containment Parameters following a DBA LOCA in accordance with EOP-2 and related plant procedures.

RSMS-OPS-NRC10-4 Rev. 02 Page 3 OF 15

IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL TRAINING EQUIPMENT STATUS REQUIRED CONDITION FOCUS DOCUMENTS IC #_244_ DBA LOCA Power:. 69%

EOP-1, RPV Control Core: MOL, xenon equilibrium Equipment NONE STPs Due: None LCOs: None Evolutions in progress: power ascension.

RSMS-OPS-NRC10-4 Rev. 02 Page 4 OF 15

V. GENERAL INSTRUCTIONS Event Number MFS-OR-REM-SCH Expected Operator Actions Simulator Setup EVENT TRIGGER T6 = RECIRC PUMP A MOV67A CONTROL SWITCH TO CLOSE Malfunctions T1, FWS006B, FEEDWATER PMP B MIN FLOW VLV FAILURE T2, RHR008A, DIV I LINE FILL PMP TRIP T3, RCS016, B RECIR LVDT FAILURE T4, TMEMOVS1P, 0%, GLAND STEAM SUPPLY HEADER ISOLATION VALVE T5, RCS001A, 100s, REACTOR RECIRC A LOOP RUPTURE T6, ED004A, 45d, delete time 1:00, NJS-LDC1A FAULT RHR001B, RHR B INJECTION VALVE FAILS TO OPEN Overrides T1, LO_FWR-FV2B-G, OFF, 45d, FWS-FV2B GREEN LIGHT T1, LO_FWR-FV2B-R, ON, 45d, FWS-FV2B RED LIGHT LO_TME-MOVS1-G, OFF, TME-MOVS1 GREEN RSMS-OPS-NRC10-4 Rev. 02 Page 5 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Actions LIGHT LO_TME-MOVS1-R, ON, TME-MOVS1 RED LIGHT REMOTES T10, ECCS003, RACK OUT, LPCS PUMP BREAKER T11, ECCS004, RACK OUT, RHR-A PUMP BREAKER Event 0 RUN CREW: Board walkdown/Turnover Event 1 Rotate CCP pumps, start A and secure C. SRO Direct actions to rotate Reactor Plant Component Cooling Water Pumps At the direction ROLE PLAY: As reactor building operator, when BOP Perform actions to rotate Reactor Plant Component of the floor requested: Cooling Water Pumps instructor. Report CCP-P1A suction and discharge valves are BOP Report the completion of rotating Reactor Plant open Component Cooling Water Pumps Report that the pump seals have been vented via CCP-PI58A RSMS-OPS-NRC10-4 Rev. 02 Page 6 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Actions Event 2 Withdraw control rods for rodline adjustment SRO Direct rodline adjustment with control rods per the RCP ATC With draw control rods per the RCP ROLE PLAY: If requested, as RE: Verify plant response Inform the SRO you will bring him the next step after Report control rod movement is complete the preconditioning delay.

Event 3 Feedwater pump B minimum flow valve fails open. ATC Recognize and report the FWS-P1A feed water pump B min. flow valve is open.

SRO Direct actions per the ARP Direct entry into AOP-006 CONDENSATE/FEEDWATER FAILURES Refer to AOP-007 LOSS OF FEEDWATER HEATING ATC Perform actions to close FWR-FV2B from P680

IF any of the following flow control valves have failed, THEN attempt to take manual control ROLE PLAY; As turbine building operator:

or isolate the flow control valve to control reactor

Accept the direction to isolate FWR-V2 vessel level:

After ten minute delay, report that FWR-V2 is

FWR-FV2B, RX FWP B MIN FLOW VALVE closed isolated by closing FWR-V2, RFP B MIN FLOW MAN ISOL SRO Direct the closing of FWR-V2 RFP B MIN FLOW MAN ISOL RSMS-OPS-NRC10-4 Rev. 02 Page 7 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Actions Event 4 Division I ECCS Line Fill pump trip BOP Recognize and report Div I line fill pump has tripped SRO May direct starting RHR-A in suppression pool cooling mode.

BOP Perform actions of ARP:

SRO Enter Tech Spec 3.5.1 A (7 day LCO) & C for ECCS (72 ROLE PLAY:As back panel operator, when hour LCO) requested: Enter Tech Spec 3.6.2.3 A for suppression pool cooling Report the RHR and or LPCS discharge pressure based (7 day LCO) on whether or not low pressure alarm is in when Direct that the pump breakers for LPCS and RHR-A be requested (RHR A alarms at 28 psig, LPCS alarms at racked out 12 psig). Make notifications per OSP-46 As control building operator: when directed accept the direction to rack out the LPCS and RHR-A pump breakers

After 5 minutes insert T10 to rack out LPCS

After 5 minutes insert T11 to rack out RHR-A Event 5 Reactor Recirculation FCV B LVDT failure ATC Recognize and report lowering power due to B Recirc.

Flow lowering Recognize and report Recirc. Loop mismatch > 10%

SRO Enter AOP-024 Thermal Hydraulic Stability Controls Enter Tech Spec 3.4.1 A for loop flow mismatch (2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months LCO)

ROLE PLAY: As RE when contacted: BOP/ATC Perform actions of actions of AOP-024 Report FCBB 1.0. ATC May inhibit FCV motion by arming and depressing the B HPU shutdown push buttons.

SRO Contact Chemistry for Tech Spec required sampling, TLCO 3.11.2.1 Contact RE to determine FCBB 1.0 (SR 3.2.4.1)

Contact WMC for I&C support for the FCV failure RSMS-OPS-NRC10-4 Rev. 02 Page 8 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Actions Event 6 Gland steam supply valve failure BOP

Recognize and report low Gland Steam supply pressure.

Refer to the Alarm Response procedure SRO

Accept report

Direct actions of the ARP

Direct opening of TME-MOVS2 Gland Steam Supply PCV Bypass valve

Direct the ATC to monitor and report main condenser vacuum values BOP

Throttle open TME-MOVS2 Gland Steam Supply PCV Bypass valve

Restore Gland steam supply header into the green band(~ 5 psig)

ATC Report value and trend of main condenser vacuum Event 7/8/9 Reactor Recirculation Loop A Rupture ATC

Recognize and report Reactor scram

Place the reactor mode switch to shutdown Loss of NJS-LDC1A

Give the scram report to the SRO RHR B Injection valve fails to open SRO

Enter EOP-01

Direct a level band of 10 to 51

Direct ADS to be inhibited ATC

Recognize and report that Recirc. Loop A source of drywell leak

Attempt to isolate the Recirc. Loop by closing the pump suction and discharge valves

Recognize and report that power has been lost to Recirc A suction and discharge valves RSMS-OPS-NRC10-4 Rev. 02 Page 9 OF 15

Event Number MFS-OR-REM-SCH Expected Operator Actions BOP

Place the ADS inhibit switches to the INHIBIT position

Report ADS is overridden

Recognize and report that RHR-B injection valve did not auto open on initiation signal

Recognize and report RPV water level < -162 SRO

Direct 7 ADS/SRVs to be opened

Direct installation of Enclosure 32

Direct the cross tie of NJS-LDC1A/1B ROLE PLAY: As WMC: report that NJS-LDC1A/1B BOP Report 7 ADS/SRVs are open is now cross tied SRO Enter EOP-2 on Suppression pool level and temperature high Direct placing RHR-A into suppression pool cooling mode Direct the isolation of Recirc pump A suction and discharge valves ATC Take actions to isolate recirc. pump A When the FREEZE Termination Criteria are met, and at the direction of the floor instructor RSMS-OPS-NRC10-4 Rev. 02 Page 10 OF 15

VI. TERMINATION CRITERIA:

The exercise should be terminated when the performance objectives have been achieved or the operators are unable to diagnose and respond effectively to the scenario.

The following conditions provide an indication of performance objective achievement for this scenario; Critical Tasks are indicated by an (*):

EOP-1 and EOP-2 properly entered when entry conditions are exceeded.

Emergency Depressurization properly entered due to low RPV level or suppression pool level high.

*Isolate the Recirc. Loop leak

Restore and maintain RPV water level above TAF RSMS-OPS-NRC10-4 Rev. 02 Page 11 OF 15

VII. REFERENCES A. Plant Procedures

1. EOP-1; RPV Control

2. EOP-2; Primary Containment Control

3. AOP-0001, Reactor Scram

4. AOP-0002, Turbine/Generator Trips

5. AOP-0003, Automatic Isolations RSMS-OPS-NRC10-4 Rev. 02 Page 12 OF 15

Offgoing OSM: Oncoming OSM: Off-Going Shift N D (Print) KCN (Print) KCN Date PART I - TO BE REVIEWED PRIOR TO ASSUMING THE SHIFT UNIT STATUS MODE 1 RX POWER 69%

EVOLUTIONS (COMPLETED / IN PROGRESS / PLANNED); GENERAL INFORMATION Rotate CCP pumps (Start A and secure C)

GOP-001 completed through G.41 Continue power ascension by performing rod line adjustment per RCP, step 83-86, then contact RE prior to proceeding.

SIGNIFICANT LCO STATUS None EQUIPMENT STATUS Night Orders Standing Orders Board Walkdown Temp Alts (Signature: Oncoming OSM Review Completed) KCN RSMS-OPS-NRC10-4 Rev. 02 Page 13 OF 15

PLANNED PERFORMED CHANGE COMMENTS APPROVAL STEP ROD FROM TO M PER VER CK RE SRO F

Instruction RE / SRO RE SRO COMMENTS Thermal limits &

preconditioning Run MON and review thermal limits and margin verified 082 preconditioning margin.

Currently below Record date / time the preconditioning state 083 28-45 12 18 I NA 084 44-29 12 18 I NA 085 28-13 12 18 I NA 086 12-29 12 18 I NA RSMS-OPS-NRC10-4 Rev. 02 Page 14 OF 15

Raising reactor power within guidance of EN-RE-205.

Ramp rate is ~4 % CTP / hr below the preconditioned state.

Ramp rate is ~1 % CTP / hr above the preconditioned state.

PLANNED PERFORMED CHANGE COMMENTS APPROVAL 087 Instruction Left @ ATC RE SRO Raise reactor power to 85% (2627 MWth), with recirc. Flow at 2% per hour RSMS-OPS-NRC10-4 Rev. 02 Page 15 OF 15

Number: *RJPM-NRC10-A1 RIVER Revision: 01 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

DETERMINE CONTAINMENT WATER LEVEL DURING CONTAINMENT FLOODING REASON FOR REVISION:

NRC Exam JPM A1 PREPARE / REVIEW:

John Hedgepeth 0069 10/28/2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Scott Dallas 1385 1/12/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-A1 TASK DESCRIPTION: Determine Containment Water Level During Containment Flooding.

TASK

REFERENCE:

200063005001 K/A REFERENCE & RATING: 2.1.25, 3.9/4.2 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 8 min.

MAX TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC10-A1 Page 2 of 9

RJPM-NRC10-A1 SIMULATOR SETUP SHEET Task

Description:

Determine Containment Water Level During Containment Flooding.

Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC10-A1 Page 3 of 9

RJPM-NRC10-A1 DATA SHEET References for Development: EOP-0005, Enclosure 23, Containment Water Level Determination.

Required Materials: EOP-0005, Enclosure 23, Containment Water Level Determination.

Required Plant Condition: None Applicable Objectives: HLO-516 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-A1 Page 4 of 9

RJPM-NRC10-A1 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

Containment Flooding is in progress in accordance with SAP-1. Suppression Pool level indication on panel H13-P808 is pegged upscale.

The CRS has directed you to determine Containment water level AND a correlated RPV water level using EOP-0005 Enclosure 23, Containment Water Level Determination. The following plant data has been obtained by completing Sections 3.1 and 3.2 of Enclosure 23:

Div II CMS-PI17B indicates 7.5 psig E51-R604 RCIC PUMP SUCTION PRESSURE indicates 30 psig E51-F031 RCIC PUMP SUP PL SUCTION VALVE is open Initiating Cue:

Complete EOP-0005, Enclosure 23, given the plant data from Division II CMS and E51-R604 for RCIC suction pressure to provide the CRS a Primary Containment water level AND a correlated RPV water level.

Report Containment water level from Enclosure 23 Figure 8 to the CRS as soon as it is obtained.

RJPM-NRC10-A1

Denotes Critical Step Page 5 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A1 PERFORMANCE STEP STANDARD S/U COMMENTS EOP Enclosure 23, Figure 8, Primary Figure 8 used to determine containment water CUE: When candidate reports Containment Water Level level at ~56 ft (+/-1 foot). level from Figure 8, request

1. Determination, to determine calculated value to confirm Figure Containment Water Level. Primary Containment water level reported to 8 value and use calculated value to CRS. determine RPV water level.

Confirms Primary Containment PCWL = [(ECCS Suction Press - CTMT Press) NOTE: [30-7.5)2.3]+4 = Level in Water Level from Figure 8 with 2.3] + 4. Determined containment water level to ft

2. calculation per Step 3.3. be 55.75 ft.

[(22.5)2.3]+4 = Level in ft

[51.75]+4 = 55.75 ft Uses Table 1 and calculated value of Used interpolation of Table 1 with the calculated containment water level to determine containment level (55.75 ft) to determine RPV

3. RPV water level. water level at -237 inches.

Terminating Cue: Primary Containment water level AND correlated RPV water level are provide to the CRS using EOP-0005, Enclosure 23.

RJPM-NRC10-A1

Denotes Critical Step Page 6 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A1 CONTAINMENT WATER LEVEL from FIG 8 55 to 57 feet CONTAINMENT WATER LEVEL CALCULATED 55 to 56.5 feet RPV WATER LEVEL (Based on calculated Containment water level) -246 to -228 inches RJPM-NRC10-A1 Page 7 of 9

RJPM-NRC10-A1 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-A1 Page 8 of 9

RJPM-NRC10-A1 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: Containment Flooding is in progress in accordance with SAP-1.

Suppression Pool level indication on panel H13-P808 is pegged upscale.

The CRS has directed you to determine Containment water level AND a correlated RPV water level using EOP-0005 Enclosure 23, Containment Water Level Determination.

The following plant data has been obtained by completing Sections 3.1 and 3.2 of Enclosure 23:

Div II CMS-PI17B indicates 7.5 psig

E51-R604 RCIC PUMP SUCTION PRESSURE indicates 30 psig

E51-F031 RCIC PUMP SUP PL SUCTION VALVE is open Initiating Cues: Complete EOP-0005, Enclosure 23, given the plant data from Division II CMS and E51-R604 for RCIC suction pressure to provide the CRS a Primary Containment water level AND a correlated RPV water level.

Report a value for Containment water level from Enclosure 23 Figure 8 to CRS as soon as it is obtained.

CONTAINMENT WATER LEVEL from FIG 8 ______________________

CONTAINMENT WATER LEVEL CALCULATED __________________

RPV WATER LEVEL (Based on calculated Containment water level) _________________

RJPM-NRC10-A1 Page 9 of 9

Number: *RJPM-NRC10-A2 RIVER Revision: 0 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

IDENTIFY REQUIRED TAGS AND HANGING SEQUENCE FOR SLC PUMP RELIEF VALVE REMOVAL AND REPLACEMENT REASON FOR REVISION:

NRC Exam JPM A2 PREPARE / REVIEW:

John Hedgepeth 0069 10/28/2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Scott Dallas 1385 01/18/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-A2 TASK DESCRIPTION: Identify Required Tags and Hanging Sequence For SLC Pump Relief Valve Removal and Replacement TASK

REFERENCE:

K/A REFERENCE & RATING: 2.2.13, 4.1 / 4.3 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 17 min.

MAX TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC10-A2 Rev. 00 Page 2 of 9

RJPM-NRC10-A2 SIMULATOR SETUP SHEET Task

Description:

Identify Required Tags and Hanging Sequence For SLC Pump A Relief Valve Removal and Replacement Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC10-A2 Rev. 00 Page 3 of 9

RJPM-NRC10-A2 DATA SHEET References for Development: PID 27-16A, System P&ID SOP-0028, Standby Liquid Control OSP-0038 Protective Tagging Guidelines Tech Spec. 3.2.1, SLC LCO Required Materials: PID 27-16A, System P&ID SOP-0028, Standby Liquid Control OSP-0038 Required Plant Condition: Mode 1, During the last performance of STP-0201-6310, SLC Quarterly Pump and Valve Operability Test, the SLC Pump Relief Valve C41-RVF0029A lifted and would not reseat.

Applicable Objectives: ELP-OPS-CLR Obj. C Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-A2 Rev. 00 Page 4 of 9

RJPM-NRC10-A2 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is operating in Mode 1. Maintenance has requested a tagout to replace the Pump Relief Valve C41-RVF029A Standby Liquid Control Pump 1A Header Press Relief Valve, which is expected to take 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to complete.

Initiating Cue:

The CRS has directed you to assist in preparing a tagout to replace the valve. The CRS requests that you provide the components and hang sequence for the tag out. Because of the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months LCO for both SLC Pumps out of service, the tagout must not INOP the B SLC pump. A tagging Official will enter the information you provide into the tagging computer.

RJPM-NRC10-A2 Rev. 00

Denotes Critical Step Page 5 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A2 PERFORMANCE STEP STANDARD S/U COMMENTS Obtains documents to develop Obtained PID for SLC and SOP-0028 CUE: Provide PID and SOP tagging. when requested.

1.

Identify components to be tagged and Student identified the proper components and NOTE: Test switch is not required.

2. the proper sequence. sequence as per the answer key below.

Terminating Cue: Manual Tagout Form completed.

RJPM-NRC10-A2 Rev. 00

Denotes Critical Step Page 6 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A2 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-A2 Rev. 00 Page 7 of 9

RJPM-NRC10-A2 Sequence Component ID Component Name Hang Position 1 C41-S1A SLC PUMP A control NEUTRAL KEY switch REMOVED 2 EHS-MCC2A BKR 2C STANDBY LIQUID OFF CONTROL PUMP A NOTE: Test switch is not required 3 3 C41-VF003A SLC PUMP A MANUAL UNLOCKED CLOSED DISCHARGE VLV 4 3 C41-VF002A SLC PUMP A SUCTION UNLOCKED CLOSED VALVE 5 4 SLS-V3000 SLC PUMP A SUCTION UNCAPPED OPEN STRAINER DRAIN VALVE 6 5 SLS-V27 OR SLC PUMP A SUCTION UNCAPPED OPEN SLS-V38 TEST CONNECTION NOTE: SLS-V38 may be used in lieu of SLS-V27.

RJPM-NRC10-A2 Rev. 00 Page 8 of 9

RJPM-NRC10-A2 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is operating in Mode 1. Maintenance has requested a tagout to replace the Pump Relief Valve C41-RVF029A Standby Liquid Control Pump 1A Header Press Relief Valve, which is expected to take 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to complete.

Initiating Cues: The CRS has directed you to assist in preparing a tagout to replace the valve. Because of the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months LCO for both SLC Pumps out of service, the tagout must not INOP the B SLC pump. A tagging Official will enter the information you provide into the tagging computer.

Sequence Component ID Component Name Hang Position RJPM-NRC10-A2 Rev. 00 Page 9 of 9

Number: *RJPM-NRC10-A3 RIVER Revision: 1 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

DETERMINATION OF H2 RECOMBINER SETTINGS REASON FOR REVISION:

NRC Exam JPM A3 PREPARE / REVIEW:

Angie Orgeron 1538 3/15/2010 Preparer KCN Date John Hedgepeth 0069 3/15/2010 Technical Review (SME) KCN Date Scott Shultz 0176 3/17/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-A3 TASK DESCRIPTION: DETERMINATION OF H2 RECOMBINER SETTINGS TASK

REFERENCE:

K/A REFERENCE & RATING: 2.1.23 / 4.3 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 10 min.

MAX TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC10-A3 rev. 01 Page 2 of 9

RJPM-NRC10-A3 SIMULATOR SETUP SHEET Task

Description:

DETERMINATION OF H2 RECOMBINER SETTINGS Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC10-A3 rev. 01 Page 3 of 9

RJPM-NRC10-A3 DATA SHEET References for Development: SOP-0040 STP-000-0001 Required Materials: SOP-0040 STP-000-0001 Historical Required Plant Condition: ANY Task Standard Required hydrogen recombiner settings have been determined.

Applicable Objectives: RLP-STM-0057 OBJ 25 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-A3 rev. 01 Page 4 of 9

RJPM-NRC10-A3 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant has experienced a LOCA with significant fuel damage. Containment hydrogen concentration is 3.8%.

Containment Pressure read at CMS-PR2A is 3.5 psig.

Prior to the LOCA, average containment temperature was 90°F.

Initiating Cue:

The CRS has directed you to determine the required hydrogen recombiner settings in accordance with SOP-0040 Steps 4.3.2 through 4.3.4.

RJPM-NRC10-A3 rev. 01

Denotes Critical Step Page 5 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A3 PERFORMANCE STEP STANDARD S/U COMMENTS

1. Read the Post-LOCA Containment From cue sheet, candidate determined Post Pressure from one of the LOCA containment pressure is 3.5 psig and Pre indications listed below and LOCA containment temperature is 90°F.

determine from plant operating records the Pre-LOCA Containment Temperature.

INDICATOR PANEL CMS-ES45A H13-P819 CMS-ES45B H13-P820 CMS-PR2A H13-P808

2. Determine Pressure Factor (Cp) Determined Cp = 1.19 to 1.21 using Attachment 5, Recombiner Power Correction Factor vs Containment Pressure Curve.

3. Determine the required Determined Recombiner Power Setting is 51.17 Recombiner Power Setting by to 52.03 KW.

multiplying the Reference Power, 43 KW, times Cp.

Terminating Cue: Recombiner setting determined to be 51.17 to 52.03 KW.

RJPM-NRC10-A3 rev. 01

Denotes Critical Step Page 6 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A3 RJPM-NRC10-A3 rev. 01

Denotes Critical Step Page 7 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A3 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-A3 rev. 01 Page 8 of 9

RJPM-NRC10-A3 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant has experienced a LOCA with significant fuel damage.

Containment hydrogen concentration is 3.8%.

Containment Pressure read at CMS-PR2A is 3.5 psig.

Prior to the LOCA, average containment temperature was 90°F.

Initiating Cues: The CRS has directed you to determine the required hydrogen recombiner settings in accordance with SOP-0040 Steps 4.3.2 through 4.3.4.

RJPM-NRC10-A3 rev. 01 Page 9 of 9

Number: RJPM-NRC10-A5 RIVER Revision: 01 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

GENERATE A MANUAL LCO TRACKING SHEET REASON FOR REVISION:

2010 NRC EXAM JPM - SRO A5 PREPARE / REVIEW:

Angie Orgeron 1538 3/16/2010 Preparer KCN Date John Hedgepeth 0069 3/16/2010 Technical Review (SME) KCN Date Alfonso Croeze 0597 3/17/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-A5 TASK DESCRIPTION: GENERATE A MANUAL LCO TRACKING SHEET TASK

REFERENCE:

K/A REFERENCE & RATING: Generic 2.1.18 3.8 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 20 min.

MAX TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC10-A5 Rev. 01 Page 2 of 10

RJPM-NRC10-A5 SIMULATOR SETUP SHEET Task

Description:

Generate a manual LCO Tracking Sheet Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC10-A5 Rev. 01 Page 3 of 10

RJPM-NRC10-A5 DATA SHEET References for Development: Technical Specifications OSP-0040, LCO TRACKING AND SAFETY FUNCTION DETERMINATION Required Materials: Technical Specifications OSP-0040, LCO TRACKING AND SAFETY FUNCTION DETERMINATION Required Plant Condition: N/A Task Standard: Generate a manual LCO Tracking Sheet.

Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-A5 Rev. 01 Page 4 of 10

RJPM-NRC10-A5 If In-Plant or In the Control Room:

Caution the Operator is NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

On April 16, 2010 at 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months the 171 airlock (JRB-DRA1, System #710) developed an air leak on the outer seal of the inner door. The plant is operating in Mode 1 at 100% power. The LCO module of eSoms is unavailable due to a system upgrade. The next available LCO number is 2010-068.

Initiating Cue:

Generate a manual LCO tracking sheet for this condition.

RJPM-NRC10-A5 Rev. 01

Denotes Critical Step Page 5 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A5 PERFORMANCE STEP STANDARD S/U COMMENTS Complete OSP-0040 Attachment 2 for LCO Status Sheet completed as indicated on JPM the 171 airlock. key.

1.

Terminating Cue: LCO Status Sheet completed for 171 airlock.

RJPM-NRC10-A5 Rev. 01

Denotes Critical Step Page 6 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A5 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-A5 Page 7 of 10

RJPM-NRC10-A5 ANSWER KEY RJPM-NRC10-A5 Page 8 of 10

RJPM-NRC10-A5 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: On April 16, 2010 at 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months the 171 airlock (JRB-DRA1, System #710) developed an air leak on the outer seal of the inner door.

The plant is operating in Mode 1 at 100% power.

The LCO module of eSoms is unavailable due to a system upgrade.

The next available LCO number is 2010-068.

Initiating Cues: Generate a manual LCO tracking sheet for this condition.

RJPM-NRC10-A5 Page 9 of 10

RJPM-NRC10-A5 RJPM-NRC10-A5 Page 10 of 10

Number: *RJPM-NRC10-A6 RIVER Revision: 01 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

DETERMINE PERSONNEL CALL-OUT AVAILABILITY REASON FOR REVISION:

NRC Exam JPM A6 PREPARE / REVIEW:

John Hedgepeth 0069 10/28/2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Terry Wymore 0523 1/18/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-A6 TASK DESCRIPTION: DETERMINE PERSONNEL CALL-OUT AVAILABILITY TASK

REFERENCE:

K/A REFERENCE & RATING: Generic 2.1.5 2.9 / 3.9 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 15 min.

MAX TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC10-A6 Rev. 01 Page 2 of 9

RJPM-NRC10-A6 SIMULATOR SETUP SHEET Task

Description:

DETERMINE PERSONNEL CALL-OUT AVAILABILITY.

Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC10-A6 Rev. 01 Page 3 of 9

RJPM-NRC10-A6 DATA SHEET References for Development: Nuclear Management Manual EN-OM-123 Fatigue Management Program Required Materials: Nuclear Management Manual EN-OM-123 Fatigue Management Program Required Plant Condition: None Task Standard: Determined proper call out per EN-OM-123 SECTION 5.2 Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-A6 Rev. 01 Page 4 of 9

RJPM-NRC10-A6 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The Plant is operating at 100% power.

A non-licensed operator has called in sick for night shift on 12-25-2009.

Your shift is below minimum staffing.

Initiating Cue:

You are the Control Room Supervisor.

Using the attached schedule report for Team B. Determine which operators are not available to work the night shift, without violating the work hour limits. Include the reason the operator would not be allowed to work.

All operators worked only the hours they were scheduled and no vacation is scheduled.

RJPM-NRC10-A6 Rev. 01

Denotes Critical Step Page 5 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A6 PERFORMANCE STEP STANDARD S/U COMMENTS Determine which operators are not Per EN-OM-123 SECTION 5.2: Student may also identify Clayton available to work the night shift Keown, due to scheduled to work Student identified (2) two operators that are not the night shift.

available to work the night shift.

1.

Shannon Deason, violate the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in 7 days

Orville McClure, violate 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Terminating Cue: Operators are identified.

RJPM-NRC10-A6 Rev. 01

Denotes Critical Step Page 6 of 9

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A6 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-A6 Rev. 01 Page 7 of 9

RJPM-NRC10-A6 Schedule Report for Operations / Team B 12/2009 - 01/2010 December Thu Fri Sat Sun Mon Tue Wed Thu Fri Sat Sun Mon Tue Wed Thu Fri Sat Sun Mon Tue Wed Thu 2009 12/10 12/11 12/12 12/13 12/14 12/15 12/16 12/17 12/18 12/19 12/20 12/21 12/22 12/23 12/24 12/25 12/26 12/27 12/28 12/29 12/30 12/31 Team B Adams, 0530 0530 0530 0530 0630 0630 0630 0630 1730 1730 1730 0530 0530 0530 John B. 1800 1800 1800 1800 1600 1600 1600 1600 0600 0600 0600 1800 1800 1800 Deason, 0530 0530 0530 0530 0530 0530 1730 1730 1730 1730 1730 1730 Shannon R. 1800 1800 1800 1800 1800 1800 0600 0600 0600 0600 0600 0600 Edwards, 0530 0530 0530 0530 0630 0630 1730 1730 1730 0530 0530 0530 Tommy S. 1800 1800 1800 1800 1600 1600 0600 0600 0600 1800 1800 1800 Fortenberry, 0530 0530 0530 0530 0630 0630 0630 0630 1730 1730 1730 0530 Jason 1800 1800 1800 1800 1600 1600 1600 1600 0600 0600 0600 1800 Gates, 0515 0525 0515 0515 0515 0515 0515 0515 1715 1715 1715 0515 0515 0515 Timothy W. 1815 1745 1745 1715 1745 1745 1745 1745 0545 0545 0545 1745 1745 1745 Kelley, 0530 0530 0530 0530 0630 0630 0630 0630 1730 1730 1730 1730 0530 0530 0530 Joshua T. 1800 1800 1800 1800 1600 1600 1600 1600 0600 0600 0600 0600 1800 1800 1800 Keown, 0530 0530 0600 1730 1730 1730 1730 1730 1730 1730 1730 0530 0530 0530 Clayton W. 1800 1800 1630 0600 0600 0600 0600 0600 0600 0600 0600 1800 1800 1800 McClure Jr, 1730 1730 0530 0530 0630 0630 0630 Orville G. 0600 0600 1800 1800 1630 1630 1630 McDaniel, 0515 0515 1715 1715 1715 Michael J. 1745 1745 0545 0545 0545 Motes, 0530 0530 0530 0530 0630 0630 0630 0630 1730 1730 1730 Scott R. 1800 1800 1800 1800 1600 1600 1600 1600 0600 0600 0600 Parker, 0515 0515 0515 0515 1715 1715 1715 Jerry L. 1745 1745 1745 1745 0545 0545 0545 Patterson, 0530 0530 0530 0530 0630 0630 0630 0630 1730 1730 1730 Guy D. 1800 1800 1800 1800 1600 1600 1600 1600 0600 0600 0600 RJPM-NRC10-A6 Rev. 01 Page 8 of 9

RJPM-NRC10-A6 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions:

The Plant is operating at 100% power.

A non-licensed operator has called in sick for night shift on 12-25-2009.

Your shift is below minimum staffing.

Initiating Cue:

You are the Control Room Supervisor.

Using the attached schedule report for Team B. Determine which operators are NOT available to work the night shift, without violating the work hour limits. Include the reason the operator would not be allowed to work.

All operators worked only the hours they were scheduled and no vacation is scheduled.

NOT AVAILABLE TO WORK NIGHT SHIFT 12-25-2009 RJPM-NRC10-A6 Rev. 01 Page 9 of 9

Number: RJPM-NRC10-A7 RIVER Revision: 01 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

DETERMINATION OF PLANT SAFETY INDEX (EOOS)

REASON FOR REVISION:

2010 NRC EXAM JPM - SRO A7 PREPARE / REVIEW:

John Hedgepeth 0069 10/28/2010 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Terry Wymore 0523 01/18/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-A7 TASK DESCRIPTION: Determination of Plant Safety Index (EOOS)

TASK

REFERENCE:

K/A REFERENCE & RATING: 2.2.17 2.6 / 3.8 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 20 min.

MAX TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC10-A7 Rev. 01 Page 2 of 10

RJPM-NRC10-A7 SIMULATOR SETUP SHEET Task

Description:

Determination of Plant Safety Index (EOOS)

Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC10-A7 Rev. 01 Page 3 of 10

RJPM-NRC10-A7 DATA SHEET References for Development: ADM-0096, Risk Management Program Implementation and On-Line Maintenance Risk Assessment, Rev. 302 Required Materials: ADM-0096, Risk Management Program Implementation and On-Line Maintenance Risk Assessment, Rev. 302 Required Plant Condition: N/A Task Standard: Plant risk index determined properly.

Applicable Objectives: RLP-LOR-EOOSPSA, ADM-0096 Obj. 2 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-A7 Rev. 01 Page 4 of 10

RJPM-NRC10-A7 If In-Plant or In the Control Room:

Caution the Operator is NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The EOOS Computer is down and it is not expected to be restored before the end of next shift. Current Conditions are:

1. 100% power, Mode 1, no AOP or EOP entry conditions

2. SWP-V173 and SWP-MOV-F055B are out of service for actuator rebuild

3. During Fuel Receipt 36 days ago, the Fuel Trailer damaged the seal on the Fuel Building 95 Truck Bay Door. Engineering has performed an Operability Assessment which has determined that this is an inoperable external flood barrier.

4. Division 1 Hydrogen Igniters are out of service due to supply breaker failure

5. SFC-P1A is out of service for pump replacement

6. RHR B is out of service for bearing replacement Initiating Cue:

Determine the Plant Safety Index, both number and color for the current conditions, and state possible contingency actions.

RJPM-NRC10-A7 Rev. 01

Denotes Critical Step Page 5 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A7 PERFORMANCE STEP STANDARD S/U COMMENTS Using ADM-0096 Attachment 5 SSW B, EDG B and RHR B are out of service. Note: SWP-V173 and SWP-MOV determine the Level 1 Out of Service F055B are out of service PSI value for EOOS unavailable. Plant Safety Index is 7.8 which per Note 2 causes SSW B out of service.

When SSW B is taken out of service EOOS, considers EDG B unavailable.

1. Additional contingencies may be driven by the System to avoid placing out of service concurrently column of the Level 1 table, these are not critical SFC-P1A does not affect PSI per Attachment 5 Using ADM-00096 Attachment 4 External Flood Barrier OOS for more than 30 The Division 1 Hydrogen determine the External Events and days (Attachment 4 - Table 4) Igniters OOS results in Yellow Level 2 SSC Risk Level (Color) color (Attachment 4 - Table 5)

Color: ORANGE Because the Level 2

2.

determination for External Flood Barrier is more conservative (dominating) the Risk color is driven by the Orange color RJPM-NRC10-A7 Rev. 01

Denotes Critical Step Page 6 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A7 PERFORMANCE STEP STANDARD S/U COMMENTS Using ADM-00096 Attachment 4 Contingency Actions: The contingency actions for determine the contingency actions. Hydrogen Igniters: Comply with

Assume equipment protected by Technical Specifications and barriers is OOS and comply with Minimize duration of Technical Specification requirements configuration are not critical

Install temporary barriers 3

Restore barrier to service

Return any OOS redundant train equipment to service Terminating Cue: Plant Safety Index number and color determines, contingency actions listed.

RJPM-NRC10-A7 Rev. 01

Denotes Critical Step Page 7 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A7 ANSWER KEY Plant Safety Index 7.8 Risk Level Orange Contingency Actions:

Assume equipment protected by barriers is OOS and comply with Technical Specification requirements

Install temporary barriers

Restore barrier to service

Return any OOS redundant train equipment to service RJPM-NRC10-A7 Rev. 01 Page 8 of 10

RJPM-NRC10-A7 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-A7 Rev. 01 Page 9 of 10

RJPM-NRC10-A7 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The EOOS Computer is down and it is not expected to be restored before the end of next shift. Current Conditions are:

1. 100% power, Mode 1, no AOP or EOP entry conditions

2. SWP-V173 and SWP-MOV55B are out of service for actuator rebuild

3. During Fuel Receipt 36 days ago, the Fuel Trailer damaged the seal on the Fuel Building 95 Truck Bay Door. Engineering has performed an Operability Assessment which has determined that this is an inoperable external flood barrier.

4. Division 1 Hydrogen Igniters are out of service due to supply breaker failure

5. SFC-P1A is out of service for pump replacement

6. RHR B is out of service for bearing replacement Initiating Cues: Determine the Plant Safety Index, both number and color for the current conditions, and state possible contingency actions.

PLANT SAFETY INDEX (EOOS) NUMBER: ______________

PLANT SAFETY INDEX COLOR: ______________________

POSSIBLE CONTINGENCY ACTIONS: _______________________________________________________

RJPM-NRC10-A7 Page 10 of 10

Number: *RJPM-NRC10-A8 RIVER Revision: 01 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

DETERMINE IF RWP IS ACCEPTABLE REASON FOR REVISION:

NRC Exam JPM A8 PREPARE / REVIEW:

John Hedgepeth 0069 10/28/2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Terry Wymore 0523 01/18/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-A8 TASK DESCRIPTION: DETERMINE IF RWP IS ACCEPTABLE TASK

REFERENCE:

K/A REFERENCE & RATING: Generic 2.3.7 3.5 / 3.6 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 15 min.

MAX TIME: N/A JOB LEVEL: SRO/RO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC10-A8 Rev. 01 Page 2 of 10

RJPM-NRC10-A8 SIMULATOR SETUP SHEET Task

Description:

DETERMINE IF RWP IS ACCEPTABLE.

Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC10-A8 Rev. 01 Page 3 of 10

RJPM-NRC10-A8 DATA SHEET References for Development: Nuclear Management Manual EN-RP-105 RADIOLOGICAL WORK PERMIT Required Materials: Nuclear Management Manual EN-RP-105 RADIOLOGICAL WORK PERMIT Required Plant Condition: None Task Standard: RWP adequacy determined.

Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-A8 Rev. 01 Page 4 of 10

RJPM-NRC10-A8 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The Plant is operating at 100% power.

RWCU pump 1A seal has failed. The pump has been secured and a tag out prepared.

Initiating Cue:

Your shift will isolate and drain the pump for the next shift to hang the tag out.

RWP 2010-1032 has been written for this job.

General area dose levels are: 75 mrem/hr. The job is estimated to take 1/2 hour.

Determine if the RWP is adequate for the work to be performed.

RJPM-NRC10-A8 Rev. 01

Denotes Critical Step Page 5 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A8 PERFORMANCE STEP STANDARD S/U COMMENTS Review RWP 2010-1032 and This RWP is not adequate due to Determined that system draining is not allowed determine if the RWP is adequate under this RWP the restrictions under

1. for the work to be performed. contamination control Terminating Cue: RWP determination made.

RJPM-NRC10-A8 Rev. 01

Denotes Critical Step Page 6 of 10

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A8 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-A8 Rev. 01 Page 7 of 10

RJPM-NRC10-A8 RADIOLOGICAL WORK PERMIT RWP

Title:

Replace pump seal on RWCU pump 1A RWP No.

20101032 Comments:

RWP type: RWP Status: Begin Date: Close On Date:

Specific Active 10-16-2009 Prepared By: Keith Rockwood Job Supervisor:

Estimated Estimated Hours: Actual Dose: Actual Hours:

Dose: 8.00 200 mrem Buildings Elevations Rooms AB 95 RWCU PUMP ROOM A Radiological Conditions Description Value Unit Contact RP or review current survey maps See maps TASKS Task Description Status 1 Isolate and Tag out RWCU pump 1A active 2 Remove and replace RWCU pump 1A seal active 3 System return to service active Requirement Groups Requirement Descriptions N/A Instructions 1: Pre-job briefing required.

Instructions 2:

Instructions 3:

Approver Title Name Date ALARA K ROCKWOOD 1/5/2010 JOB SUPERVISOR E COVINGTON 1/6/2010 RP SUPERVISOR W HOLLAND 1/7/2010 RJPM-NRC10-A8 Rev. 01 Page 8 of 10

RJPM-NRC10-A8 RADIOLOGICAL WORK PERMIT Task Number: 1 RWP No.: 20101032 Rev: 00 Task

Description:

Task Status: Active Tag out RWCU pump 1A Estimated Dose: 200 Estimated Hours: 3 Hi-Rad: NO Hot Particle: Locked Hi-Rad: YES Hi-Contamination:

NO YES Dose Alarm (mrem) 50.00 Dose Rate (mrem/hr) 300.00 Requirement Groups Requirement Descriptions ACCESS **CRITICIAL STEP** LHRA brief and RP approval required prior to entry CONTAMINATION CONTROL NO burning, welding, grinding, flapping, insulation removal, system breach, system draining or use of air tools allowed COVERAGE **CRITICIAL STEP** Continuous coverage per EN-RP-141 DOSIMETRY **CRITICIAL STEP** Periodically check your EAD. If an EAD alarm is received, place work in a safe condition and leave the area.

Whole body DLR and EAD required.

EXPOSURE CONTROL Low dose waiting areas will be discussed during the pre-job brief PROTECTIVE CLOTHING Single Anti-Cs are required if no kneeling or climbing is required.

RP INSTRUCTIONS **CRITICIAL STEP** STOP WORK CRITERIA: Dose rate >300 mrem/hr, contamination levels >5 mrad/hr beta/gamma or >

or = 1000 dpm/100cm2 (alpha)

RJPM-NRC10-A8 Rev. 01 Page 9 of 10

RJPM-NRC10-A8 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions:

The Plant is operating at 100% power.

RWCU pump 1A seal has failed. The pump has been secured and a tag out prepared.

Initiating Cue:

Your shift will isolate and drain the pump for the next shift to hang the tag out.

RWP 2010-1032 has been written for this job.

General area dose rate is 75 mRem / hour. The job is estimated to take 1/2 hour.

Determine if the RWP is adequate for the work to be performed.

RWP is adequate RWP is NOT adequate RJPM-NRC10-A8 Rev. 01 Page 10 of 10

Number: RJPM-NRC10-A9 RIVER Revision: 01 BEND STATION Page 1 of 11 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

CLASSIFY AN EMERGENCY REASON FOR REVISION:

2010 NRC EXAM JPM - SRO A9 PREPARE / REVIEW:

John Hedgepeth 0069 2/22/2010 Preparer KCN Date Angie Orgeron 1538 2/25/2010 Technical Review (SME) KCN Date Terry Wymore 0523 2/25/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-A9 TASK DESCRIPTION: CLASSIFY AN EMERGENCY TASK

REFERENCE:

K/A REFERENCE & RATING: 2.4.41 2.9 / 4.6 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X Classroom COMPLETION TIME: 20 min.

MAX TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION Yes REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

RJPM-NRC10-A9 Rev. 01 Page 2 of 11

RJPM-NRC10-A9 SIMULATOR SETUP SHEET Task

Description:

Classify an emergency Required Power: N/A IC No.: N/A Notes: This Administrative JPM may be conducted in the simulator in conjunction with Scenario 2 or in a classroom.

RJPM-NRC10-A9 Rev. 01 Page 3 of 11

RJPM-NRC10-A9 DATA SHEET References for Development: EIP-2-001 CLASSIFICATION OF EMERGENCIES Required Materials: EIP-2-001 CLASSIFICATION OF EMERGENCIES Required Plant Condition: N/A Applicable Objectives: RCBT-EP-SRORMED Obj. 16 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-A9 Rev. 01 Page 4 of 11

RJPM-NRC10-A9 If In-Plant or In the Control Room:

Caution the Operator is NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant has experienced a hydraulic lock ATWS. Current reactor power is 25%. Both SLC pumps have failed. Pressure is presently controlled with the bypass valves, steam drains and SRVs. Reactor water level is currently controlled with condensate and feedwater. There is no indication of fuel clad failure at this time. Suppression Pool temperature is 108°F and steady. Reactor water level is being maintained -60to -140.

Wind speed is 2 mph from 197 degrees.

Initiating Cue:

You are the Operations Shift Superintendent, classify the event, AND fill out the applicable notification short form.

RJPM-NRC10-A9 Rev. 01

Denotes Critical Step Page 5 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A9 PERFORMANCE STEP STANDARD S/U COMMENTS Consult EIP-2-001 Classification of Classified this event as a SITE AREA EAL SS3 Failure of Reactor

1. Emergencies for this event EMERGENCY. Protection System Complete the notification short form Short form for Site Area Emergency completed 2.

with proper and accurate information Terminating Cue: Emergency Plan is applied to classify the event as a Site Area Emergency and Site Area Emergency Short Form completed per attachment.

RJPM-NRC10-A9 Rev. 01

Denotes Critical Step Page 6 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A9 ANSWER KEY Notification of Site Area Emergency Time/Date: Message: 1 This is River Bend Station A Site Area Emergency was declared at Current on Current date for time SS3 Failure of Reactor Protection System Failure of reactor protection system to complete or initiate an automatic reactor scram once a reactor protection system setpoint has been exceeded and manual scram was not successful Wind from ____197__ Deg. At __2______ MPH 9 No Release No Protective Actions Required.

{ Release BELOW federally approved operating limits

{ Release ABOVE federally approved operating limits Authorized by: Candidate name

Title:

Emergency Director /

Recovery Manager RJPM-NRC10-A9 Rev. 01

Denotes Critical Step Page 7 of 11

^ Denotes Sequence Critical (must be performed after previous step marked ^)

RJPM-NRC10-A9 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-A9 Rev. 01 Page 8 of 11

RJPM-NRC10-A9 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant has experienced a hydraulic lock ATWS. Current reactor power is 25%. Both SLC pumps have failed. Pressure is presently controlled with the bypass valves, steam drains and SRVs. Reactor water level is currently controlled with condensate and feedwater. There is no indication of fuel clad failure at this time. Suppression Pool temperature is 108°F and steady. Reactor water level is being maintained -60to -140.

Wind speed is 2 mph from 197 degrees.

Initiating Cues: You are the Operations Shift Superintendent, classify the event, AND fill out the applicable notification short form.

Notification of General Emergency Time/Date: Message:

This is River Bend Station A General Emergency was declared at on for Wind from _________ Deg. At _________ MPH

{ No Release PAR Reference Scenario No.:

{ Release BELOW federally approved operating limits

{ Release ABOVE federally approved operating limits Authorized by:

Title:

RJPM-NRC10-A9 Rev. 01 Page 9 of 11

RJPM-NRC10-A9 Notification of Site Area Emergency Time/Date: Message:

This is River Bend Station A Site Area Emergency was declared at on for Wind from _________ Deg. At _________ MPH

{ No Release No Protective Actions Required.

{ Release BELOW federally approved operating limits

{ Release ABOVE federally approved operating limits Authorized by:

Title:

Notification of Alert Time/Date: Message:

This is River Bend Station A Site Area Emergency was declared at on for Wind from _________ Deg. At _________ MPH

{ No Release No Protective Actions Required.

{ Release BELOW federally approved operating limits

{ Release ABOVE federally approved operating limits Authorized by:

Title:

RJPM-NRC10-A9 Rev. 01 Page 10 of 11

RJPM-NRC10-A9 Notification of Unusual Event Time/Date: Message:

This is River Bend Station A Site Area Emergency was declared at on for Wind from _________ Deg. At _________ MPH

{ No Release No Protective Actions Required.

{ Release BELOW federally approved operating limits

{ Release ABOVE federally approved operating limits Authorized by:

Title:

RJPM-NRC10-A9 Rev. 01 Page 11 of 11

Number:

RJPM-NRC10-C1 RIVER Revision: 01 BEND STATION Page 1 of 8 JOB PERFORMANCE MEASURE TRAINING PROGRAM: HLO JOB PERFORMANCE MEASURE LESSON PLAN:

BYPASS MSR STEAM SUPPLY VALVES INTERLOCK REASON FOR REVISION:

New revision for 2010 NRC exam C1 PREPARE / REVIEW:

John Hedgepeth 0069 10-28-2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Terry Wymore 0523 01/18/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-C1 TASK DESCRIPTION: Bypass MSR Steam Supply Valves Interlock per EOP-005 Enclosure 5.

K/A REFERENCE & RATING: 239001 EK1.01, 3.4/3.4 239001 EK5.09, 3.4/3.5 239001 EA2.01, 3.8/3.9 239001 G013, 3.7/3.7 TASK

REFERENCE:

200037005001 TESTING METHOD: Simulate Performance: X Actual Performance:

Control Room: X Simulator: In-Plant:

COMPLETION TIME: 6 min.

MAX. TIME: N/A JOB LEVEL: RO / SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION 4 RJPM-NRC10-C1 rev 01 Page 2 of 8

RJPM-NRC10-C1 SIMULATOR SETUP SHEET Task

Description:

Bypass MSR Steam Supply Valves Interlock per EOP Enclosure 5 Required Power: N/A IC No.: N/A Notes: This JPM is to be simulated in the plant RJPM-NRC10-C1 rev 01 Page 3 of 8

RJPM-NRC10-C1 DATA SHEET References for Development: EOP-0005, Enclosure 5 Required Materials: EOP-0005, Enclosure 5 Required Plant Condition: Any Task Standard Relay 63B-MSSN17 removed and both jumpers installed per EOP-0005 Enclosure 5, Bypassing MSR Steam Supply Valves Interlock.

Applicable Objectives: HLO-516-00, Obj 5 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: None Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-C1 rev 01 Page 4 of 8

RJPM-NRC10-C1 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues, I may provide cues during the performance of this JPM, I may ask follow-up questions as part of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied, you should inform me when you have completed the task.

Initial Conditions:

A reactor scram has occurred after extended high power operations. A malfunction of the turbine bypass valves and low Suppression Pool level require use of alternate pressure control methods. Crew is operating using EOP-0001 Initiating Cue:

CRS directs installation of EOP-0005, Enclosure 5, Bypassing MSR Steam Supply Valves Interlock.

RJPM-NRC10-C1 rev 01 Page 5 of 8

RJPM-NRC10-C1 PERFORMANCE STEP STANDARD S/U COMMENTS

1. Obtain Jumper Kit No. 5 from the Control Jumper Kit No. 5 obtained from Control Room DO NOT remove the kit from the Room Emergency Locker. Emergency Locker Emergency Locker.

2. Inspect kit for two jumpers. Two jumpers located in Jumper Kit No 5.

3. Verify MSS-MOV111, MSR 1 STM SPLY MSS-MOV111 control switch verified in the CUE: Control switch is in the SHUTOFF, Control Switch is in CLOSE CLOSE Position CLOSE position, green light is Position on and red light is off

4. Verify MSS-MOV112, MSR 2 STM SPLY MSS-MOV112 control switch verified in the CUE: Control switch is in the SHUTOFF, Control Switches is in CLOSE CLOSE Position CLOSE position, green light is Position on and red light is off

5. Locate H13-P869 Bay D Panel H13-P869 located.

6. Remove Relay 63B-1MSSN17 Relay 63B-1MSSN17 in H13-P869 Bay D Relay 63B-1MSSN17 in H13-removed P869 Bay D, (Left row of agastat relays, 8th relay from top)

CUE: Relay is removed.

7. Jumper Terminal M3 on Relay Block Jumper correctly installed CUE: Jumper is installed.

63B-1MSSN17 to Terminal R3 on Relay Block 63B-1MSSN17

8. Jumper Terminal M4 on Relay Block Jumper correctly installed CUE: Jumper is installed.

63B-1MSSN17 to Terminal R4 on Relay Block 63B-1MSSN17

9. OPEN MSS-MOV111, MSR1 STM SPLY CRS informed that relay is removed and jumpers CUE: As CRS inform operator SHUTOFF AND MSS-MOV112, MSR2 STM installed. that another Operator will SPLY SHUTOFF as directed by the CRS. perform pressure control action with MSS-MOV111 and 112.

Terminating Cue: Relay 63B-MSSN17 removed and both jumpers installed per EOP-0005 Enclosure 5, Bypassing MSR Steam Supply Valves Interlock.

RJPM-NRC10-C1 rev 01 Page 6 of 8

RJPM-NRC10-C1 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-C1 rev 01 Page 7 of 8

RJPM-NRC10-C1 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A reactor scram has occurred after extended high power operations. A malfunction of the turbine bypass valves and low Suppression Pool level require use of alternate pressure control methods. Crew is operating using EOP-0001 Initiating Cues: CRS directs installation of EOP-0005, Enclosure 5, Bypassing MSR Steam Supply Valves Interlock.

RJPM-NRC10-C1 rev 01 Page 8 of 8

Number:

RJPM-NRC10-C2 RIVER Revision: 01 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM: HLO JOB PERFORMANCE MEASURE LESSON PLAN:

BYPASS A LOCAL POWER RANGE MONITOR (LPRM) DETECTOR REASON FOR REVISION:

New revision for 2010 NRC exam C2 PREPARE / REVIEW:

John Hedgepeth 0069 10-28-2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Scott Shultz 0176 01/18/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-C2 TASK DESCRIPTION: Bypass a Local Power Range Monitor (LPRM) Detector TASK

REFERENCE:

2153050101 K/A REFERENCE & RATING: 215005-K1.04, 3.6/3.6; K3.01, 4.0/4.0; K4.01, 3.7/3.7; A4.06, 3.6/3.8; G04,3.8/3.8; G07, 3.5/3.6 TESTING METHOD: Simulate Actual Performance X Performance Control X Simulator In-Plant Room COMPLETION TIME: 10 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

SAFETY FUNCTION: 7 RJPM-NRC10-C2 rev. 01 Page 2 of 11

RJPM-NRC10-C2 SIMULATOR SETUP SHEET Task

Description:

N/A Required Power: N/A IC No.: N/A Notes: This JPM is to be simulated in the plant RJPM-NRC10-C2 rev. 01 Page 3 of 11

RJPM-NRC10-C2 DATA SHEET References for Development: REP-0037, LPRM Operability Required Materials: REP-0037, LPRM Operability Required Plant Condition: Any Task Standard LPRM 2A-38-47 has been bypassed in accordance with REP-0037.

Applicable Objectives: RBS-STM-0503.00, Obj 18, 19, 20, 22, 23 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-C2 rev. 01 Page 4 of 11

RJPM-NRC10-C2 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

Reactor is in Mode 1 Initiating Cue:

LPRM 2A-38-47 has failed. The CRS has directed you to bypass it. (IAW REP-0037 section 4.1).

RJPM-NRC10-C2 rev. 01 Page 5 of 11

RJPM-NRC10-C2 PERFORMANCE STEP STANDARD S/U COMMENTS

1. Record the performance of the Operator has identified Attachment 2 of REP-applicable steps of section 4.1 on the 0037 (LPRM BYPASS SHEET)

LPRM BYPASS SHEET (Attachment 2)

2. Ensure that personnel bypassing an Candidate qualifies as a Licensed Operator.

LPRM satisfy ADM-0007 requirements for performing this procedure by being any of the following: Licensed Operator, Qualified STA, or Qualified I&C Technician.

3. Contact Reactor Engineering to Operator notified Reactor Engineering of the CUE: Acknowledge report to notify them of the intent to bypass an intent to bypass LPRM 2A-38-47 and Attachment bypass LPRM 2A-38-47 as LPRM, so Reactor Engineering can 2 initialed. Reactor Engineer.

evaluate potential to affect core monitoring functions.

4. Record the LPRM location and level LPRM 2A-38-47 recorded on Attachment 2 and on the LPRM BYPASS sheet. step initialed.

5. Using Attachment 1 as a guide, Operator has identified APRM H, records on determine the APRM channel Attachment 2, and initialed step.

associated with the LPRM.

6. Obtain permission from the Operator performs the following: CUE: Provide the following Operations Shift Manager (OSM) or

Requested permission from the OSM/CRS information to the operator the Control Room Supervisor (CRS) to bypass LPRM 2A-38-47 when requested.

prior to bypassing an LPRM.

Requested the ATC operator bypass

As OSM/CRS inform Request the OSM/CRS to have the APRM H. operator he has permission At-the-Controls (ATC) operator to bypass LPRM 2A-38-47.

bypass the affected APRM on 1H13- Canidate may request an P680 prior to manipulating any initial.

switches.

As ATC inform the operator that APRM H is bypassed.

RJPM-NRC10-C2 rev. 01 Page 6 of 11

RJPM-NRC10-C2 PERFORMANCE STEP STANDARD S/U COMMENTS

7. Have a qualified member of plant Operator requested a qualified member of plant CUE: Inform the operator that staff provide concurrence with the staff provide concurrence with the performance you are qualified and will performance of steps 4.1.8 - 4.1.17 of steps 4.1.8 - 4.1.17 provide concurrence with the required steps.

8. Verify that no more than 33 LPRM Operator verified the number of bypassed/failed CUE: Inform the operator that signals are bypassed. Record the LPRM signals and records information on there are no other number of bypassed LPRMs on the Attachment 2. bypassed/failed LPRM signals.

LPRM BYPASS SHEET.

9. Record the number of LPRMs that Operator placed the APRM METER FUNCTION CUE: Inform the operator that are in OPERATE by placing the SWITCH in the COUNT position and determined the meter reads 80% when the affected APRM METER that the 16 LPRMs assigned to APRM H are in APRM METER FUNCTION FUNCTION SWITCH in the OPERATE, when the meter reading of 80 has SWITCH is placed in the COUNT position. been dividing by 5. COUNT position.

There is one LPRM for every 5%

division. Operator has recorded 16 on the LPRM BYPASS

Divide the meter value by 5. SHEET.

Record the number on the LPRM BYPASS SHEET.

10. Determine if bypassing the LPRM Operator referenced step 3.2 of REP-0037 and will render its APRM inoperable per determined that APRM H will not be rendered step 3.2. inoperable by bypassing LPRM 2A-38-47.

11. Determine if bypassing the LPRM Operator referenced step 3.3 of REP-0037 and will render PBDS channel A or B determined that PBDS will not be rendered inoperable per step 3.3. inoperable by bypassing LPRM 2A-38-47.

RJPM-NRC10-C2 rev. 01 Page 7 of 11

RJPM-NRC10-C2 PERFORMANCE STEP STANDARD S/U COMMENTS

12. Using Attachment 1 as a guide, select Operator placed the LPRM SELECTOR NOTE: the candidate may the desired LPRM to be bypassed SWITCH in position 2 and the METER inform the ATC operator of with the LPRM SELECTOR FUNCTION SWITCH in position A. incoming alarm SWITCH and the METER CUE: LPRM SELECTOR FUNCTION SWITCH. Observe that SWITCH is in position 2 and the bypass light on the APRM panel the METER FUNCTION meter is not lit. SWITCH is in position A.

CUE: The bypass light is NOT lit.

13. Bypass the selected LPRM by Switch S1 of LPRM 2A-38-47 placed in the CUE: S1 is in the bypass placing the S1 switch of the LPRM in BYPASS position. position.

the BYPASS position

14. Observe that the bypass light on the Operator verified that the bypass light on the CUE: LPRM 2A-38-47 Bypass APRM panel meter is lit. Record on APRM Panel for LPRM 2A-38-47 is lit. light is lit.

LPRM BYPASS SHEET. Operator recorded the LPRM on LPRM BYPASS SHEET.

15. Determine the number of LPRMs that Operator placed the APRM METER FUNCTION CUE: When asked, inform the are in OPERATE by placing the SWITCH in the COUNT position and read 75%, operator that the meter reads METER FUNCTION SWITCH for determined that the number of LPRMs in 75% when the APRM METER the selected APRM on the panel OPERATE is 15. FUNCTION SWITCH is placed meter in the COUNT position. in the COUNT position.

There is one LPRM for every 5%

division.

Divide the meter value by 5.

Check that the number of LPRMs in OPERATE is one less than recorded on the LPRM BYPASS SHEET, step 4.1.9.

Record the number on the LPRM BYPASS SHEET.

RJPM-NRC10-C2 rev. 01 Page 8 of 11

RJPM-NRC10-C2 PERFORMANCE STEP STANDARD S/U COMMENTS

16. Using either an OD-3 edit or a 3D Operator verified that APRM H is reading CUE: Inform the operator that Monicore Core Power and Flow edit, within +/- 2% of RTP. APRM H is within +/- 2% of verify that the APRM reading is Rated Thermal Power.

within +/- 2% of rated thermal power (RTP) or adjust.

17. Request the OSM/CRS to have the Operator requested the OSM/CRS to have the CUE: Inform the operator after ATC return the affected APRM to ATC operator place APRM H back in service. being requested that the ATC service. operator has placed APRM H in service.

18. Record the date and WR/WO# (if Operator has recorded the date on the LPRM CUE; The WR# is 123456 applicable) on the LPRM BYPASS BYPASS SHEET The CRS will forward SHEET. documentation to the RE.

Terminating Cue: LPRM 2A-38-47 has been bypassed in accordance with REP-0037.

RJPM-NRC10-C2 rev. 01 Page 9 of 11

RJPM-NRC10-C2 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-C2 rev. 01 Page 10 of 11

RJPM-NRC10-C2 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: Reactor is in Mode 1 Initiating Cues: LPRM 2A-38-47 has failed, the CRS has directed you to bypass it. (IAW REP-0037, Section 4.1).

RJPM-NRC10-C2 rev. 01 Page 11 of 11

Number:

RJPM-NRC10-IP1 RIVER Revision: 00 BEND STATION Page 1 of 8 JOB PERFORMANCE MEASURE TRAINING PROGRAM: HLO JOB PERFORMANCE MEASURE LESSON PLAN:

VENT THE SCRAM AIR HEADER PER EOP-0005 REASON FOR REVISION:

New revision for 2010 NRC exam IP 1 PREPARE / REVIEW:

John Hedgepeth 0069 10-28-2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Scott Shultz 0176 01/08/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-IP 1 TASK DESCRIPTION: Vent the Scram Air Header per EOP-0005, Enclosure 11, Venting Scram Air Header TASK

REFERENCE:

201001005004 K/A REFERENCE & RATING: 295037 EK3.07, 4.2/4.3 295037EA1.05, 3.9/4.0 295037G06, 4.2/4.1 295037G12, 3.9/4.6 TESTING METHOD: Simulate Actual Performance X Performance Control Room Simulator In-Plant X COMPLETION TIME: 20 min.

MAX TIME: n/a JOB LEVEL: RO / SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH No (FAULTED):

SAFETY FUNCTION: 1 RJPM-NRC10-IP 1 Rev. 00 Page 2 of 8

RJPM-NRC10-IP 1 SIMULATOR SETUP SHEET Task

Description:

N/A Required Power: N/A IC No.: N/A Notes: This JPM task is to be simulated in the plant.

RJPM-NRC10-IP 1 Rev. 00 Page 3 of 8

RJPM-NRC10-IP 1 DATA SHEET References for Development: EOP-0005, Enclosure 11, Venting Scram Air Header Required Materials: EOP-0005, Enclosure 11, Venting Scram Air Header Required Plant Condition: This JPM task is to be simulated in the plant.

Task Standard: Scram air header vented in accordance with EOP-0005 Applicable Objectives: RBS-1-OJT-NLO-QC005.04, Task 201001005004 HLO-516 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-IP 1 Rev. 00 Page 4 of 8

RJPM-NRC10-IP 1 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues, I may provide cues during the performance of this JPM, I may ask follow-up questions as part of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied, you should inform me when you have completed the task.

Initial Conditions:

A scram condition has occurred but all control rods failed to insert and power is above 6%

Initiating Cue:

The CRS has instructed you to implement EOP-0005, Enclosure 11, VENTING SCRAM AIR HEADER, to insert control rods per Emergency Procedure EOP-0001A, RPV CONTROL - ATWS.

RJPM-NRC10-IP 1 Rev. 00 Page 5 of 8

RJPM-NRC10-IP 1 PERFORMANCE STEP STANDARD S/U COMMENTS

1. OBTAIN EOP-0005 ENCL 11 tool kit Key to emergency locker obtained and the tools CUE: Return tool kit to from Control Room Emergency Locker for EOP-0005, Enclosure 11 are identified. Emergency Locker INSPECT kit for the following:

1. One (1) Flashlight with batteries

2. Two (2) 10" Crescent wrenches

2. CLOSE C11-VF095 INSTR AIR C11-VF095 identified and closed CUE: Valve is closed SUPPLY TO SCRAM PILOT VALVES ISOL (Containment EL 114 ft AZ 195, to right of backup scram valves)

3. Remove test connection cap downstream Test connection cap downstream of C11-PT- CUE: Cap is removed of C11-PT-N052-V2 PILOT AIR N052-V2 removed.

HEADER PRESSURE TRANSMITTER TEST VALVE (above and left of backup scram valve)

4. OPEN C11-PT-N052-V2 PILOT AIR C11-PT-N052-V2 opened. CUE: Valve is open and air flow HEADER PRESSURE TRANSMITTER is present at test connection TEST VALVE Terminating Cue: Scram air header vented in accordance with EOP-0005, Enclosure 11 VENTING SCRAM AIR HEADER RJPM-NRC10-IP 1 Rev. 00 Page 6 of 8

RJPM-NRC10-IP 1 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-IP 1 Rev. 00 Page 7 of 8

RJPM-NRC10-IP 1 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A scram condition has occurred but all control rods failed to insert and power is above 6%

Initiating Cues: The CRS has instructed you to implement EOP-0005, Enclosure 11, VENTING SCRAM AIR HEADER, to insert control rods per Emergency Procedure EOP-0001A, RPV CONTROL - ATWS RJPM-NRC10-IP 1 Rev. 00 Page 8 of 8

RIVERBEND STATION Number:

RJPM-NRC10-IP2 Revision: 01 Page 1 of 8 TRAINING PROGRAM: HLO JOB PERFORMANCE MEASURE LESSON PLAN:

PLACE DIV. 1 STANDBY SERVICE WATER SYSTEM IN SERVICE FROM THE REMOTE SHUTDOWN PANEL REASON FOR REVISION:

New revision for 2010 NRC exam IP2 PREPARE / REVIEW:

John Hedgepeth 0069 10-28-2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Terry Wymore 0523 1/8/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-IP2 JPM NUMBER:

TASK DESCRIPTION: Place Div. 1 Standby Service Water System in service from the Remote Shutdown Panel (with SWP-P2A Pump Trip)

K/A REFERENCE & RATING: 264000 K6.07 (3.8/3.9) 295016 AK2.01 (4.4/4.5) AK2.02 (4.0/4.1)

TASK

REFERENCE:

400076004001 TESTING METHOD: Simulate Performance: X Actual Performance:

Control Room: Simulator: In-Plant: X COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): Yes SAFETY FUNCTION GROUP 8 RJPM-NRC10-IP2 Rev.01 Page 2 of 9

RJPM-NRC10-IP2 SIMULATOR SETUP SHEET Task

Description:

Place Div. 1 Standby Service Water System in service from the Remote Shutdown Panel (with SWP-P2A Pump Trip)

Required Power: N/A IC No.: N/A Notes: This JPM is to be performed in the Plant.

RJPM-NRC10-IP2 Rev.01 Page 3 of 9

RJPM-NRC10-IP2 DATA SHEET References for Development: AOP-0031, Shutdown From Outside Main Control Room Required Materials: AOP-0031, Shutdown From Outside Main Control Room Required Plant Condition: Any Task Standard: Division 1 Standby Service Water is in service.

Applicable Objectives: STM-200, Objectives H2, H3, H11, H12 HLO-537, Objective 7 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-IP2 Rev.01 Page 4 of 9

RJPM-NRC10-IP2 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues, I may provide cues during the performance of this JPM, I may ask follow-up questions as part of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied, you should inform me when you have completed the task.

Initial Conditions: The Control Room has been evacuated. The Reactor is in Hot Shutdown and control has been established at the Remote Shutdown Panel. There has been no fire. Normal Service Water is NOT available. Div III D/G is running.

Initiating Cue: The CRS has directed you to place the Division 1 Standby Service Water System in service from the appropriate Remote Shutdown Panel, per AOP-0031, step 5.14.5.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. On C61-P001, verify the following lights Verified both lights are on. CUE: Inform operator that both are on:

lights are on.

LOCAL SWP 1 EMERGENCY CONTROL ALIGNED

LOCAL SWP 2 EMERGENCY CONTROL ALIGNED On RSS-PNL101, BOP REMOTE

2. Placed SWP-P2A pump control switch to CUE: SWP-P2A Pump Status SHUTDOWN PNL, SWP-P2A, STBY START. RED light on, GREEN light off; SVCE WTR PUMP 2A and immediately, RED and GREEN light off.

NOTE: ALTERNATE PATH RJPM-NRC10-IP2 Rev.01 Page 5 of 9

RJPM-NRC10-IP2 PERFORMANCE STEP STANDARD S/U COMMENTS

3. On EGS-PNL4C, SWP-P2C, STANDBY Placed SWP-P2C pump control switch to CUE: SWP-P2C Pump Status SERVICE WATER PUMP START. RED light on, GREEN light off (Located in Div 3 Swgr Room, Control Building 116 el.)

4. Verify SWP-MOV40C STBY SVCE Verified SWP-MOV40C STBY SVCE WTR CUE: SWP-MOV40C STBY WTR PUMP DISCHARGE Valve opens. PUMP DISCHARGE Valve. Verifies valve has SVCE WTR PUMP DISCHARGE opened. Valve status RED light on, GREEN light off On RSS-PNL101(102),open the

5. On RSS-PNL101 placed SWP-MOV55A STBY CUE: SWP-MOV55A STBY appropriate SWP-MOV55A(B), STBY CLG TOWER 1 INLET valve control switch CLG TOWER 1 INLET Valve CLG TOWER 1(2) INLET. momentarily to OPEN (then released). Verifies status RED light on, GREEN light valve has opened. off.

Close both of the following valves: Placed SWP-MOV96A NORM SVCE WTR

6. CUE: SWP-MOV96A NORM

On RSS-PNL101, SWP-MOV96A, RETURN Valve control switch momentarily to SVCE WTR RETURN Valve NORMAL SVCE WTR RETURN CLOSE. Verified valve have closed. status RED light off, GREEN light on.

Placed SWP-MOV96B NORM SVCE WTR

On RSS-PNL102, SWP-MOV96B, RETURN Valve control switch momentarily to SWP-MOV96B NORM SVCE NORM SVCE WTR RETURN CLOSE. Verified valve have closed. WTR RETURN Valve status RED light off, GREEN light on.

RJPM-NRC10-IP2 Rev.01 Page 6 of 9

RJPM-NRC10-IP2 PERFORMANCE STEP STANDARD S/U COMMENTS

7. IF check valve leakage is excessive, Reported Div 1 SSW operating with P2C running CUE: As CRS acknowledges Div THEN locally, close the following valves: and requested CRS have Standby Cooling Tower 1 SSW in service with P2C SWP-MOV57A and SWP-MOV57B Basin Level monitored for excessive leakage running and request for Basin from Standby Service Water to Normal Service Level monitoring for leakage from NORMAL SERVICE WATER SUPPLY VALVES. Water System. SSW.

No leakage is indicated.

Terminating Cue: Division 1 Standby Service Water is in service.

RJPM-NRC10-IP2 Rev.01 Page 7 of 9

RJPM-NRC10-IP2 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

RJPM-NRC10-IP2 Rev.01 Page 8 of 9

RJPM-NRC10-IP2 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The Control Room has been evacuated. The Reactor is in Hot Shutdown and control has been established at the Remote Shutdown Panel. There has been no fire. Normal Service Water is NOT available. Div III D/G is running.

Initiating Cues: The CRS has directed you to place the Division 1 Standby Service Water System in service from the appropriate Remote Shutdown Panel, per AOP-0031, step 5.14.5.

RJPM-NRC10-IP2 Rev.01 Page 9 of 9

Number:

RJPM-NRC10-IP3 RIVER Revision: 00 BEND STATION Page 1 of JOB PERFORMANCE MEASURE TRAINING PROGRAM: HLO JOB PERFORMANCE MEASURE LESSON PLAN:

SHIFT CONTROL BUILDING CHILLED WATER IN THE STANDBY LOOP REASON FOR REVISION:

New revision for 2010 NRC exam IP 3 PREPARE / REVIEW:

John Hedgepeth 0069 10-28-2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Terry Wymore 0523 01/18/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information RJPM-NRC10-IP3

RJPM-NRC10-IP3 TASK DESCRIPTION: As Control Building Operator Alternate Control Building Chilled Water Pump and Chiller within the Standby Division.

K/A REFERENCE & RATING: 290003 K4.01 3.1/3.2 A4.01 3.2/3.2 TASK

REFERENCE:

291011001004 TESTING METHOD: Simulate Performance: X Actual Performance:

Control Room: Simulator: In-Plant: X COMPLETION TIME: 15 minutes MAX TIME: N/A JOB LEVEL: All TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION: 9 RJPM-NRC10-IP3 page 2 of 9

RJPM-NRC10-IP3 SIMULATOR SETUP SHEET Task

Description:

As Control Building Operator Alternate Control Building Chilled Water Pump and Chiller within the Standby Division.

Required Power: N/A IC No.: N/A Notes: This JPM is to be simulated in the plant RJPM-NRC10-IP3 page 3 of 9

RJPM-NRC10-IP3 DATA SHEET References for Development: SOP-0066, Plant and Control Building HVAC Chilled Water System, Section 5.3 Required Materials: SOP-0066, Plant and Control Building HVAC Chilled Water System, Section 5.3 Required Plant Condition: Any Task Standard Chilled Water lined up for 1HVK*CHL1C Applicable Objectives: STM-402, Objectives N4, N6 Safety Related Task: NA0 (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-IP3 page 4 of 9

RJPM-NRC10-IP3 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator: I will explain the initial conditions, and provide initiating cues, I may provide cues during the performance of this JPM, I may ask follow-up questions as part of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied, you should inform me when you have completed the task.

Initial Conditions: The operating HVK chiller has been in service for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . 1HVK-CHL1A (CONTROL BLDG CHILLER A) and 1HVK-P1A (CHILLED WATER PUMP) are lined up for standby operation.

The UO (Unit Operator) has placed 1HVK-CHL1A (CONTROL BLDG CHILLER A) in LOCKOUT and 1HVK-P1A (CHILLED WATER PUMP A) in STOP.

Initiating Cue: The CRS has directed you, as the Control Building Operator, to do the local lineup for placing Control Building HVK Chiller C, in standby with HVK-P1C Chilled Water Pump. SOP-0066 has been completed through Step 5.3.3.

PERFORMANCE STEP STANDARD S/U COMMENTS 1HVK-V35 has been unlocked and closed. CUE: HVK-V35 is closed.

1. Locally at the chiller, unlock and close the standby chiller inlet valve.

HVK-V35 1HVK-CHL1A INLET ISOL

2. Locally at the currently out of service chiller, open and lock the inlet valve. 1HVK-V39 placed in the open and locked CUE: HVK-V39 is open and

HVK-V39 1HVK-CHL1C INLET position locked.

ISOL RJPM-NRC10-IP3 page 5 of 9

RJPM-NRC10-IP3 PERFORMANCE STEP STANDARD S/U COMMENTS

3. Locally at the chiller being placed in NOTE standby, verify the following: Oil level may be lower than normal if service water temperature is low (approx. 65-75 °F).

a. Lube oil level is visible in the lower or Lube oil level verified. Cue: Lube oil level in upper sight upper sightglass. glass

b. Lube oil temperature is greater than or Lube oil temperature verified within limits Cue: Lube oil temp. 140 °F equal to 120°F and less than or equal to 155°F.

c. READY light is on. Ready verified lit Cue: Ready light is on.

d. SAFETY CIRCUIT light is on. Safety Circuit verified lit Cue: Safety Circuit light is on.

e. LOAD RECYCLE light is on Load Recycle lights verified lit. Cue: Load Recycle light is on.

f. Refrigerant visible in evaporator sight glass Refrigerant level verified Cue: Refrigerant is visible in the evaporator RJPM-NRC10-IP3 page 6 of 9

RJPM-NRC10-IP3 PERFORMANCE STEP STANDARD S/U COMMENTS

4. Contact the control room to perform Main Control Room contacted to perform steps CUE:

steps 5.3.7 thru 5.3.12. 5.3.7 thru 5.3.12. The control room reports that steps 5.3.7 thru 5.3.12 are complete.

5. When alternating DIV I Chiller only, then Note: Located on the back of on the back of 1EHS-MCC8A, perform the 1EHS-MCC8A.

following.

a. Place HVK-CHL1APL(CPL) , CHLD Switch 1HVK-CHL1CPL placed in the ON CUE: Switch 1HVK-CHL1CPL CPRSR LUBO for the standby chiller to position placed in the ON position ON

b. Place HVK-CHL1CPL(APL) for the out Switch 1HVK-CHL1APL placed in the OFF CUE: Switch 1HVK-CHL1APL of service chiller to OFF. position placed in the OFF position Terminating Cue: Chilled Water lined up for 1HVK-CHL1C.

RJPM-NRC10-IP3 page 7 of 9

RJPM-NRC10-IP3 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): NLO / RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-IP3 page 8 of 9

RJPM-NRC10-IP3 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The operating HVK chiller has been in service for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1HVK-CHL1A (CONTROL BLDG CHILLER A) and 1HVK-P1A (CHILLED WATER PUMP) are lined up for standby operation.

The UO (Unit Operator) has placed 1HVK-CHL1A (CONTROL BLDG CHILLER A) in LOCKOUT and 1HVK-P1A (CHILLED WATER PUMP A) in STOP.

Initiating Cues: The CRS has directed you, as the Control Building Operator, perform the local lineup for placing Control Building HVK Chiller C, in standby with HVK-P1C Chilled Water Pump. SOP-0066 has been completed through Step 5.3.3.

RJPM-NRC10-IP3 page 9 of 9

Number:

RJPM-NRC10-S1 RIVER Revision: 00 BEND STATION Page 1 of JOB PERFORMANCE MEASURE TRAINING PROGRAM: HLO JOB PERFORMANCE MEASURE LESSON PLAN:

PERFORM CONTROL ROD OPERABILITY CHECK WITH ROD OVER-TRAVEL REASON FOR REVISION:

New revision for 2010 NRC exam S1 PREPARE / REVIEW:

John Hedgepeth 0069 10-28-2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Terry Wymore 0523 01/12/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-S1 TASK DESCRIPTION: Perform Control Rod Operability Check With Rod Over-Travel K/A REFERENCE & RATING: 201003 K4.02 3.8/3.9 A3.01 3.7/3.6 K5.07 3.3/3.6 G04 3.5/3.6 A1.01 3.7/3.8 G07 3.6/3.6 A2.02 3.7/3.8 TASK

REFERENCE:

201024001001 201001002001 TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: Simulator: X In-Plant:

COMPLETION TIME: 10 minutes MAX TIME: N/A JOB LEVEL: ALL TIME CRITICAL: NO EIP CLASSIFICATION REQUIRED: NO PRA RISK DOMINATE: NO ALTERNATE PATH (FAULTED): YES SAFETY FUNCTION: 1 RJPM-NRC10-S1 rev 00 Page 2 of 8

RJPM-NRC10-S1 SIMULATOR SETUP SHEET Task

Description:

Perform control rod operability check with rod over-travel.

Required Power: Any IC No.: 231 Notes: Before start of JPM enter the following at the instructor console:

Rod 16-29 Failure (Rod Uncoupled)

RJPM-NRC10-S1 rev 00 Page 3 of 8

RJPM-NRC10-S1 DATA SHEET References for Development: STP-052-0101 REP-0051 Required Materials: STP-052-0101 Required Plant Condition: Reactor at power, steady state >27%

Task Standard Control rod operability check for 16-29 completed in accordance with STP-052-0101 Applicable Objectives: HLO-004 Obj. #6 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-S1 rev 00 Page 4 of 8

RJPM-NRC10-S1 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues, I may provide cues during the performance of this JPM, I may ask follow-up questions as part of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied, you should inform me when you have completed the task.

Initial Conditions:

Reactor at power, steady state.

Initiating Cue:

The CRS has directed you to perform control rod operability check on control rod 16-29 per STP-052-0101 PERFORMANCE STEP STANDARD S/U COMMENTS

1. Print out an OD-7 of present control OD-7 printed out. CUE: Provide OD-7 to student rod positions.

2. Select control rod 16-29. Control rod 16-29 selected, position 48 displayed on full core display.

3. Insert Control Rod to position 46 Control rod inserted one notch; to position 46 and None and verify position indication changes. position indication change verified.

4. Withdraw Control Rod to position 48 Control rod withdrawn to position 48 and None and verify position indication changes position indication change verified.

RJPM-NRC10-S1 rev 00 Page 5 of 8

RJPM-NRC10-S1 PERFORMANCE STEP STANDARD S/U COMMENTS

5. Perform coupling check for control Withdraw signal applied to control rod. Control rod. rod over travel annunciator acknowledged.

6. Notify CRS of uncoupled rod. CRS notified. Cue: As CRS direct the operator to take the actions of ARP-P680 C02

7. Determine uncoupled rod by ROD UNCOUPLED pushbutton depressed and depressing the ROD UNCOUPLED and observe red light noted for rod 16-29 red lights.

8. Attempt to recouple rod by driving Control rod inserted one notch; to position 46 and in to Position 46 and withdrawing to Position 48. position indication change verified.

Control rod withdrawn to position 48 and position indication change verified.

9. Check the success of recoupling by Withdraw signal applied to control rod. Control Cue: As CRS acknowldge the attempting to withdraw beyond position 48. rod over travel annunciator acknowledged. report for uncoupled rod, reference

a. IF rod was successfully coupled, THEN note in to REP-0051 and T.S. 3.1.3.

Control Room Logbook.

b. IF rod was not successfully coupled, THEN Refer To REP-0051, Reactivity Control and Control Rod Movement and Technical Specification 3.1.3.

10. Notify Reactor Engineer of any Notified the CRS to contact Reactor Engineer for Cue: As CRS acknowldge the failure of control rods to recouple. the control rod failure to recouple. report to contact R.E.

11. Printout another OD-7 of final control OD-7 printed out. None rod position.

Terminating Cue: Control rod operability check for 16-29 completed in accordance with STP-052-0101.

RJPM-NRC10-S1 rev 00 Page 6 of 8

RJPM-NRC10-S1 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-S1 rev 00 Page 7 of 8

RJPM-NRC10-S1 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: Reactor at power, steady state Initiating Cues: The CRS has directed you to perform control rod operability check on control rod 16-29 per STP-052-0101 RJPM-NRC10-S1 rev 00 Page 8 of 8

Number:

RJPM-NRC10-S2 RIVER Revision: 01 BEND STATION Page 1 of 12 JOB PERFORMANCE MEASURE TRAINING PROGRAM: HLO JOB PERFORMANCE MEASURE LESSON PLAN:

START ARC PUMP WITH SEPARATOR LEVEL ALARM REASON FOR REVISION:

New revision for 2010 NRC exam S2 PREPARE / REVIEW:

John Hedgepeth 0069 10-28-2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Scott Dallas 1385 01/12/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-S2 TASK DESCRIPTION: Start ARC pump TASK

REFERENCE:

255006001001 K/A REFERENCE & RATING: 256000 A2.02, A4.04 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 10 minutes MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH Yes (FAULTED):

Safety Function : 2 RJPM-NRC10-S2 rev. 01 Page 2 of 12

RJPM-NRC10-S2 SIMULATOR SETUP SHEET Task

Description:

Start an ARC pump with separator level alarm Required Power: Any IC No.: 233 Notes: Insert level alarm for ARC-P1A 10 seconds after pump has been started. ARC-P1A start push button = ZDI 1 (464) != 0.

RJPM-NRC10-S2 rev. 01 Page 3 of 12

RJPM-NRC10-S2 DATA SHEET References for Development: SOP-0025, P870-52 ALARM RESPONSE Required Materials: SOP-0025, P870-52 ALARM RESPONSE Required Plant Condition: Any Task Standard ARC-P1B started and running normally..

Applicable Objectives: RBS-STM-125, Obj 6 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-S2 rev. 01 Page 4 of 12

RJPM-NRC10-S2 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The plant is starting up after a refuel outage. Condenser vacuum must be established to continue the plant start up per GOP-001 PLANT STARTUP.

Initiating Cue:

The CRS has directed you to start ARC-P1A AIR REMOVAL PUMP, per SOP-0025 CONDENSER AIR REMOVAL SYSTEM step 4.1.

The pre-job brief has been completed and the Turbine building operator is in the field ready to start ARC-P1A.

RJPM-NRC10-S2 rev. 01 Page 5 of 12

RJPM-NRC10-S2 PERFORMANCE STEP STANDARD S/U COMMENTS

1. Notify Radiation Protection to post Radiation Protection notified to post the area CUE: As RP acknowledge the the area around the Condenser Air around the air removal pumps. request to post the area around the Removal Pumps. air removal pumps and inform the student that the area is already posted

2. IF time permits, THEN fill the Turbine building operator was directed to fill the CUE: As the Turbine Building discharge silencer line loop seal via loop seal via ARC-V51. operator, report that the loop seal ARC-V51, DISCHARGE has been filled.

SILENCER DRAIN LINE LOOP SEAL FILL VALVE.

3. Verify RMS-RE125 or RMS-RE126, Verified that RMS-125 or 126 is operating via MAIN PLANT STACK is operating DRMS Display. Status of GREEN on the DRMS per SOP-0086, Digital Radiation display.

Monitoring (SYS #511).

4. At TB, 123 ft el, HVT-PNL162, start Turbine building operator was directed to start CUE: As the Turbine Building HVT-FLT1, IODINE FILTRATION HVT-FLT1 per SOP-0064. operator, report that HVT-FLT1 is UNIT per SOP-0064, Turbine running per SOP-0064.

Building HVAC System

5. At TB, 95 ft el, open MWS-V155, Turbine building operator was directed to open CUE: As the Turbine Building MAKEUP WATER SUPPLY TO MWS-V155 MAKEUP WATER SUPPLY TO operator, report that MWS-V155 is ARC-LCV9A for the Condenser Air ARC-LCV9A open.

Removal Pump to be started.

RJPM-NRC10-S2 rev. 01 Page 6 of 12

RJPM-NRC10-S2 PERFORMANCE STEP STANDARD S/U COMMENTS

6. At TB, 95 ft el, verify the separator Turbine building operator was directed to verify CUE: As the Turbine Building water level is visible in ARC-LG6A, the separator water level is visible in ARC-LG6A operator, report that the water SEPARATOR A LEVEL SIGHT level is visible in ARC-LG6A GLASS for the Condenser Air Removal Pump to be started.

7. IF performing a controlled plant NONE This step will be N/A. initial shutdown, THEN verify the conditions are a plant start-up.

discharge silencer line loop seal is filled via ARC-V51, DISCHARGE N/A SILENCER DRAIN LINE LOOP SEAL FILL VALVE.

At H13-P870, start ARC-P1A COND ARC-P1A START push button was depressed, AIR REMOVAL PUMP and verify ARC-P1A verified started, ARC-P2A verified the following: started and ARC-AOV3A verified open.

1. ARC-P2A, RECIRC SEAL WTR

8.

PUMP starts.

2. ARC-AOV3A, COND AIR REM PUMP A SUCT VALVE opens.

Acknowledge alarm AIR DISCH Alarm acknowledged and CRS notified. CUE: As the CRS, direct the SEP/SIL SP1A LEVEL HIGH/LOW. operator to take actions per the

9. Notify CRS or alarm and refer to ARP.

ARP-P870-52A-F03 Check level locally to determine Turbine building operator directed to determine CUE: As turbine building whether level is high or low as whether level is high or low as indicated on operator, report that the sight glass 10 indicated on ARC-LG6A. ARC-LG6A. is completely full.

RJPM-NRC10-S2 rev. 01 Page 7 of 12

RJPM-NRC10-S2 PERFORMANCE STEP STANDARD S/U COMMENTS IF level is high, THEN perform the Turbine building operator directed to crack CUE: As turbine building operator following: open ARC-V13, SEPARATOR DRAIN report that ARC-V13

a. Return level to normal by VALVE and return level to normal. SEPARATOR DRAIN VALVE cracking open ARC-V13, has been cracked 50% open for 20 SEPARATOR DRAIN VALVE. May also close MWS-V155. minutes and level has not returned

b. IF it is necessary to maintain to normal.

pump running, THEN manually If theMWS-V155 was requested 11 control level by throttling closed closed then provide the following MWS-V155, MAKEUP WATER cue.

INLET VALVE. CUE: MWS-V155 MAKEUP WATER INLET VALVE is closed and level has not returned to normal.

IF the condition can not be corrected CRS notified that ARC-P1A sight glass level is CUE: As CRS direct student to and level restored to normal, THEN high and cannot be returned to normal. secure the ARC-P1A per SOP-shut down the ARC-P1A, COND 0025 and start ARC-P1B 12 AIR REMOVAL PMP A, and initiate corrective actions.

At H13-P870, stop ARC-P1A, Stop push button depressed for ARC-P1A.

COND AIR REMOVAL PUMP and Verified that ARC-P2A has stopped and ARC-verify the following: AOV3A has closed

1. ARC-P2A, RECIRC SEAL

13 WTR PUMP A stops.

2. ARC-AOV3A, AIR REM PUMP A SUCT VALVE closes.

RJPM-NRC10-S2 rev. 01 Page 8 of 12

RJPM-NRC10-S2 PERFORMANCE STEP STANDARD S/U COMMENTS IF both Condenser Air Removal This step will be N/A Pumps are to be shut down, THEN at TB, 123 ft el, HVT-PNL162 stop 14 HVT-FLT1, IODINE FILTRATION N/A UNIT per SOP-0064, Turbine Building HVAC System.

At TB, 95 ft el, close MWS-V155, Turbine building operator was directed to close CUE: As the Turbine Building MAKEUP WATER SUPPLY TO MWS-V155 MAKEUP WATER SUPPLY TO operator, report that MWS-V155 is 15 ARC-LCV9A for the idle Condenser ARC-LCV9A closed.

Air Removal Pump(s).

16 Notify Radiation Protection to post This step may be N/A due previous notification. CUE: As RP acknowledge the the area around the Condenser Air request to post the area around the Removal Pumps. Radiation Protection notified to post the area air removal pumps and inform the around the air removal pumps. student that the area is already posted 17 IF time permits, THEN fill the This step may be N/A due previous actions. CUE: As the Turbine Building discharge silencer line loop seal via operator, report that the loop seal ARC-V51, DISCHARGE Turbine building operator was directed to fill the has been filled.

SILENCER DRAIN LINE LOOP loop seal via ARC-V51.

SEAL FILL VALVE.

18 Verify RMS-RE125 or RMS-RE126, This step may be N/A due previous actions.

MAIN PLANT STACK is operating per SOP-0086, Digital Radiation Verified that RMS-125 or 126 is operating via Monitoring (SYS #511). DRMS Display. Status of GREEN on the DRMS display.

RJPM-NRC10-S2 rev. 01 Page 9 of 12

RJPM-NRC10-S2 PERFORMANCE STEP STANDARD S/U COMMENTS 19 At TB, 123 ft el, HVT-PNL162, start This step may be N/A due previous actions. CUE: As the Turbine Building HVT-FLT1, IODINE FILTRATION operator, report that HVT-FLT1 is UNIT per SOP-0064, Turbine Turbine building operator was directed to start running per SOP-0064.

Building HVAC System HVT-FLT1 per SOP-0064.

20 At TB, 95 ft el, open MWS-V156, Turbine building operator was directed to open CUE: As the Turbine Building MAKEUP WATER SUPPLY TO MWS-V156 MAKEUP WATER SUPPLY TO operator, report that MWS-V156 is ARC-LCV9B for the Condenser Air ARC-LCV9B open.

Removal Pump to be started.

21 At TB, 95 ft el, verify the separator Turbine building operator was directed to verify CUE: As the Turbine Building water level is visible in ARC-LG6B, the separator water level is visible in ARC-LG6B operator, report that the water SEPARATOR A LEVEL SIGHT level is visible in ARC-LG6B GLASS for the Condenser Air Removal Pump to be started.

At H13-P870, start ARC-P1B COND ARC-P1B START push button was depressed, AIR REMOVAL PUMP and verify ARC-P1B verified started, ARC-P2B verified the following: started and ARC-AOV3B verified open.

1. ARC-P2B, RECIRC SEAL WTR

22 PUMP starts.

2. ARC-AOV3B, COND AIR REM PUMP B SUCT VALVE opens.

Contact Mechanical Maintenance to Contacted Mechanical Maintenance to check and CUE: As MM accept the direction check and adjust the packing on the adjust the packing on the ARC-P1B to check and adjust the ARC-P1B 23 ARC-P1B COND AIR REMOVAL packing.

PUMP.

Terminating Cue: ARC-P1B started after ARC-P1A has been started and secured.

RJPM-NRC10-S2 rev. 01 Page 10 of 12

RJPM-NRC10-S2 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-S2 rev. 01 Page 11 of 12

RJPM-NRC10-S2 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is starting up after a refuel outage. Condenser vacuum must be established to continue the plant start up per GOP-001 PLANT STARTUP.

Initiating Cues: The CRS has directed you to start ARC-P1A AIR REMOVAL PUMP, per SOP-0025 CONDENSER AIR REMOVAL SYSTEM step 4.1.

The pre-job brief has been completed and the Turbine building operator is in the field ready to start ARC-P1A.

RJPM-NRC10-S2 rev. 01 Page 12 of 12

Number:

RJPM-NRC10-S3 RIVER Revision: 01 BEND STATION Page 1 of 8 JOB PERFORMANCE MEASURE TRAINING PROGRAM: HLO JOB PERFORMANCE MEASURE LESSON PLAN:

SHIFT MAIN EHC PUMPS WITH LOW PRESSURE REASON FOR REVISION:

New revision for 2010 NRC exam S3 PREPARE / REVIEW:

John Hedgepeth 0069 10-28-2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Scott Dallas 1385 01/12/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-S3 TASK DESCRIPTION: Shift main EHC pumps TASK

REFERENCE:

SOP-0014 K/A REFERENCE & RATING: 241000 A2.06, A3.04, A4.10 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 10 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH Yes (FAULTED):

SAFETY FUNCTION: 3 RJPM-NRC10-S3 Rev. 01 Page 2 of 8

RJPM-NRC10-S3 SIMULATOR SETUP SHEET Task

Description:

Shift main EHC pumps Required Power: Any IC No.: 232 Notes: none RJPM-NRC10-S3 Rev. 01 Page 3 of 8

RJPM-NRC10-S3 DATA SHEET References for Development: SOP-0014 Required Materials: SOP-0014 Required Plant Condition: Any Task Standard TMB-HFPM-B, EHC PUMP B started and then secure.

Applicable Objectives: STM-509 Obj. 8 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-S3 Rev. 01 Page 4 of 8

RJPM-NRC10-S3 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

Reactor is in Mode 1 Initiating Cue:

The CRS has directed you to swap to B main EHC pumps per SOP-0014 for normal equipment rotation.

RJPM-NRC10-S3 Rev. 01 Page 5 of 8

RJPM-NRC10-S3 PERFORMANCE STEP STANDARD S/U COMMENTS

1. Start TMB-HFPM-B, EHC PUMP B. Start push button depressed CUE: If requested, verify the local sump level is normal.

2. Check the EHC PUMP B DISCH Verified that the B discharge pressure light White light ON PRESS white light is on. stays lit.

NOTE Allow at least 30 seconds for the standby pump to pick up, prime and expel possible air

3. Notify CRS that EHC FLUID Informed CRS of indication for EHC system CUE: As CRS direct the operator PUMP TROUBLE alarm is received. to perform ARP actions (H13-P870/54A/H01)

4. Dispatch an operator to determine the Turbine building operator dispatched to the EHC CUE: As turbine building operator cause of the pump trouble alarm. pump report that EHC pump B discharge pressure is about 100# higher than EHC pump A.

5. Check the differential pressure on Plant Process computer point TMBPC03 status is CUE: Inform student that the PPC Process Computer Point(TMBPC03) verified. point indication reads HI

6. Notify CRS of EHC system status CRS notified of HI discharge filter differential CUE: As CRS direct the operator pressure to secure EHC-P1B

7. Secure TMB-HFPM-B, EHC PUMP Stop push button depressed for EHC-P1B, Red B. light off and Green light on.

Terminating Cue: TMB-HFPM-B, EHC PUMP B started and then secure.

RJPM-NRC10-S3 Rev. 01 Page 6 of 8

RJPM-NRC10-S3 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-S3 Rev. 01 Page 7 of 8

RJPM-NRC10-S3 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: Reactor is in Mode 1 Initiating Cues: The CRS has directed you to swap to B main EHC pumps per SOP-0014 for normal equipment rotation.

RJPM-NRC10-S3 Rev. 01 Page 8 of 8

Number:

RJPM-NRC10-S4 RIVER Revision: 01 BEND STATION Page 1 of 8 JOB PERFORMANCE MEASURE TRAINING PROGRAM: HLO JOB PERFORMANCE MEASURE LESSON PLAN:

START OF SPC / ADHR REASON FOR REVISION:

New revision for 2010 NRC exam S4 PREPARE / REVIEW:

John Hedgepeth 0069 10-28-2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Scott Dallas 1385 01/12/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-S4 TASK DESCRIPTION: Start of SPC / ADHR K/A REFERENCE & 223001 A3.03, A3.4, A3.3 RATING:

TASK

REFERENCE:

220004001001 TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: Simulator: X In-Plant:

COMPLETION TIME: 15 minutes MAX TIME: N/A JOB LEVEL: ALL TIME CRITICAL: NO EIP CLASSIFICATION NO REQUIRED:

PRA RISK DOMINATE: NO ALTERNATE PATH NO (FAULTED):

SAFETY FUNCTION:: 5 RJPM-NRC10-S4 Rev 01 Page 2 of 8

RJPM-NRC10-S4 SIMULATOR SETUP SHEET Task

Description:

Start of SPC / ADHR Required Power: Any IC No.: 233 Notes: NONE RJPM-NRC10-S4 Rev 01 Page 3 of 8

RJPM-NRC10-S4 DATA SHEET References for Development: SOP-0140 Required Materials: SOP-0140 Required Plant Condition: Any Task Standard ADHR back in service per SOP-0140 Applicable Objectives: STM-656 Obj. 2 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-S4 Rev 01 Page 4 of 8

RJPM-NRC10-S4 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues, I may provide cues during the performance of this JPM, I may ask follow-up questions as part of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied, you should inform me when you have completed the task.

Initial Conditions:

Start-up, Mode 2 <5 % power. SPC/ADHR was secured to support a swap of the RPS system power supply. RPS swap is complete.

Initiating Cue:

The CRS has directed you to restart SPC-P1B per SOP-140 starting at step 5.6.7. SPC cooling is not required. SPC demin will be placed in service at a later time.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. WHEN it is desired to restart the NONE system, THEN perform the following:

2. IF SPC/ADHR was secured for swap RHS-AOV62, 63 and 64 opened with the control of RPS power supplies, THEN open switches.

the following as directed by the OSM/CRS:

RHS-AOV62, SPC SUCTION VALVE

RHS-AOV63, SPC SUCTION VALVE

RHS-AOV64, SPC DISCH VALVE RJPM-NRC10-S4 Rev 01 Page 5 of 8

RJPM-NRC10-S4 PERFORMANCE STEP STANDARD S/U COMMENTS

3. At AB 70 ft el, Racquetball Room, Reactor building operator directed to open SPC- CUE: Reactor building operator open SPC-V3B, SPC PUMP B V3B reports that SPC-V3B is open.

DISCHARGE VALVE.

4. IF Annunciator P601-20A-F02, SPC Operator verified the alarm is not lit.

SYSTEM NOT FULL, alarms, THEN vent per Step 5.2.12.

5. Start SPC-P1B, SPC PUMP 1B. Control switch for SPC-P1B placed to START

6. Check open SPC-AOV25, SPC Flow verified greater than or equal to 200 gpm on PUMP MINIMUM FLOW VALVE, SPC-FI32 as indicated by flow indication on SPC-FI32, SPC TOTAL FLOW.

7. Throttle open SPC-AOV20, SPC SPC-AOV20 throttled open to 1500 to 2250 gpm FILTER DEMIN BYPASS VALVE as read on SFC-FI32 to greater than 1500 gpm and less than or equal to 2250 gpm as indicated on SPC-FI32, SPC TOTAL FLOW.

8. WHEN SPC-AOV25 closes, as SPC-AOV20 adjusted back to 1500 to 2250 gpm indicated by a drop in flow on SPC- as read on SFC-FI32 FI32, SPC TOTAL FLOW, THEN adjust SPC-AOV20 to obtain system flow greater than 1500 gpm and less than 2250 gpm as indicated on SPC-FI32, SPC TOTAL FLOW.

9. IF required for cooling, THEN adjust NONE CUE: ADHR is not required for SPC-AOV16, SPC HX DISCH VLV, cooling at this time.

to obtain the desired cooling rate.

10. IF placing SPC filter-demineralizer in NONE CUE: The filter demin will remain service, THEN Go To Section 6.4. out of service at this time.

Terminating Cue: ADHR back in service per SOP-0140 RJPM-NRC10-S4 Rev 01 Page 6 of 8

RJPM-NRC10-S4 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-S4 Rev 01 Page 7 of 8

RJPM-NRC10-S4 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: Start-up, Mode 2 <5 % power. SPC/ADHR was secured to support a swap of the RPS system power supply. RPS swap is complete.

Initiating Cues: The CRS has directed you to restart SPC-P1B per SOP-140 starting at step 5.6.7. SPC cooling is not required. SPC demin will be placed in service at a later time.

RJPM-NRC10-S4 Rev 01 Page 8 of 8

Number: *RJPM-NRC10-S5 RIVER Revision: 01 BEND STATION Page 1 of 12 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

CCP VALVE QUARTERLY STROKE TEST REASON FOR REVISION:

2010 NRC Exam JPM S5 PREPARE / REVIEW:

John Hedgepeth 0069 11/18/2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Terry Wymore 0523 01/12/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-S5 TASK DESCRIPTION: CCP Valve Quarterly Stroke Test Surveillance TASK

REFERENCE:

208007001001 277007001001 K/A REFERENCE & RATING: 400000 K1.01, 3.2/3.3 400000 A4.01, 3.1/3.2 295018 AK3.07, 3.1/3.2 295018 AA1.01, 3.3/3.4 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator X In-Plant COMPLETION TIME: 15 min.

MAX TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION No REQUIRED:

PSA RISK DOMINATE: No ALTERNATE PATH Yes (FAULTED):

SAFETY FUNCTION: 8 RJPM-NRC10-S5 Rev 01 Page 2 of 12

RJPM-NRC10-S5 SIMULATOR SETUP SHEET Task

Description:

CCP Valve Quarterly Stroke Test Surveillance (STP-115-6301).

Required Power: Any IC No.: 231 Notes: Malfunctions to trip of all Normal Service Water Pumps are setup to be inserted by Trigger 1. Initiate Trigger 1 when stroke test time has been recorded for CCP-MOV16A, JPM Step 11.

RJPM-NRC10-S5 Rev 01 Page 3 of 12

RJPM-NRC10-S5 DATA SHEET References for Development: STP-115-6301, Div 1 Reactor Plant Component Cooling Water Quarterly Valve Operability Test Required Materials: STP-115-6301, Div 1 Reactor Plant Component Cooling Water Quarterly Valve Operability Test Stopwatch Required Plant Condition: N/A Applicable Objectives:

Safety Related Task: (If K/A less than 3.0)

Control Manipulations: N/A Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-S5 Rev 01 Page 4 of 12

RJPM-NRC10-S5 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues. I may provide cues during the performance of this JPM, and I may ask follow-up questions as part of this JPM. When you have completed the task successfully, the objective for this JPM will be satisfied, and you should inform me when you have completed this task.

Initial Conditions:

The Plant is operating at rated conditions with no equipment out of service.

Initiating Cue:

The CRS directs you to complete STP-115-6301, Div 1 Reactor Plant Component Cooling Water Quarterly Valve Operability Test, starting at Step 7.4.

Steps 7.1 through 7.3 have been completed by the Reactor Building Operator.

The CRS has designated you as the dedicated operator to maintain Div I Standby Service Water System availability during the surveillance testing, per Step 7.4.1 RJPM-NRC10-S5 Rev 01 Page 5 of 12

RJPM-NRC10-S5 PERFORMANCE STEP STANDARD S/U COMMENTS Establish a dedicated operator(s) per CUE: As CRS acknowledge LCO

1. entry for Standby Service water ADM-0096 in order to maintain Div I Standby Service Water System and Emergency Diesel Generator.

availability during testing throughout this section. The dedicated operator(s) will establish communications with the Main Control Room to perform the following functions: In the Main Control Room:

Place the SWP-P2A, STBY SVCE Reviews step and initials step completion WTR PUMP 2A (LOCKOUT)

Switch in RESET upon the Loss of Normal Service Water, Loss of CCP and/or directed by the OSM/CRS.

Place the SWP-P2C, STBY SVCE WTR (LOCKOUT) Switch in RESET upon the Loss of Normal Service Water, Loss of CCP and/or directed by the OSM/CRS RJPM-NRC10-S5 Rev 01 Page 6 of 12

RJPM-NRC10-S5 PERFORMANCE STEP STANDARD S/U COMMENTS Place the STBY SVCE WTR TEST

1. (DIV 1) to OFF upon the Loss of (contd) Normal Service Water, Loss of CCP and/or directed by the OSM/CRS.

Reviews step and initials step completion.

Place the RPCCW DIV 1 TEST to OFF upon the Loss of Normal Service Water, Loss of CCP and/or directed by the OSM/CRS.

Prohibit the initiation of Standby RPCCW DIV 1 TEST Switch placed in TEST NOTE: Will receive alarm P870-

2. 55A-G04, DIVISION 1 RPCCW Service Water, isolation of RPCCW, position and trip of the CRD Pumps, by SYSTEM INOPERATIVE performing the following:

Place RPCCW DIV 1 TEST Switch in TEST.

Place the STBY SVCE WTR TEST STBY SVCE WTR TEST (Div 1) Switch placed NOTE: Will receive alarm P870-

3. (Div 1) Switch in TEST. in TEST position. 55A-H07, DIVISION 1 STBY SERVICE WTR INOPERATIVE Place SWP-P2A, STBY SVCE WTR SWP-P2A, STBY SVCE WTR PUMP 2A

4. PUMP 2A in LOCKOUT. LOCKOUT pushbutton depressed. (P870)

RJPM-NRC10-S5 Rev 01 Page 7 of 12

RJPM-NRC10-S5 PERFORMANCE STEP STANDARD S/U COMMENTS Place SWP-P2C, STBY SVCE WTR SWP-P2C, STBY SVCE WTR PUMP 2C NOTE: Will receive alarm P601-

5. in LOCKOUT LOCKOUT pushbutton depressed. (P601) 18A-B01, DIV 3 STBY SVCE WATER SYSTEM INOPERATIVE Close and time CCP-MOV130, Stop watch started when control switch has been 6.

LOOP A DN STREAM RETURN moved to close and stopped when CCP-MOV130 Closed.

Green light ON Red light OFF Record closing stroke time, full Closing time for CCP-MOV130 recorded on data

7. stroke exercise result, and valve sheet at 28.9 seconds (+/- 4.3 seconds) acceptance determination for CCP-MOV130 on Data Sheet 1.

Close and time CCP-MOV335, Stop watch started when control switch has been

8. LOOP A UP STREAM RETURN. moved to close and stopped when CCP-MOV335 Closed.

Green light ON Red light OFF Record closing stroke time, full Closing time for CCP-MOV335 recorded on data

9. stroke exercise result, and valve sheet at 29.6 seconds (+/- 4.4 seconds) acceptance determination for CCP-MOV335 on Data Sheet 1.

RJPM-NRC10-S5 Rev 01 Page 8 of 12

RJPM-NRC10-S5 PERFORMANCE STEP STANDARD S/U COMMENTS Close and time CCP-MOV16A, Stop watch started when control switch has been

10. RPCCW LOOP A SUPPLY. moved to close and stopped when CCP-MOV16A Closed.

Green light ON Red light OFF Record closing stroke time, full Closing time for CCP-MOV16A recorded on data NOTE: ALTERNATE PATH

11. stroke exercise result, and valve sheet at 29.2 seconds (+/- 4.3 seconds) acceptance determination for CCP- NOTE: The following will alarm MOV16A on Data Sheet 1. ~15 seconds apart:

P870-55A-H04, RPCCW TO DIV 1 EXTREME LOW PRESSURE P870-55A-G07, DIVISION 1 STBY SERVICE WATER LOW PRESSURE P870-55A-D07, DIV 1 STBY SERVICE WTR VALVE MISALIGNMENT Place the SWP-P2A, STBY SVCE SWP-P2A, STBY SVCE WTR PUMP 2A CUE: As CRS, if candidate

12. WTR PUMP 2A (LOCKOUT) (LOCKOUT) Switch placed in RESET reports loss of NSW, direct Switch in RESET upon the Loss of taking action of the dedicated Normal Service Water, Loss of CCP. SWP-P2A Starts (P870) operator per STP.

Green light OFF Red light ON RJPM-NRC10-S5 Rev 01 Page 9 of 12

RJPM-NRC10-S5 PERFORMANCE STEP [STP Step] STANDARD S/U COMMENTS Place the SWP-P2C, STBY SVCE SWP-P2C, STBY SVCE WTR PUMP 2C

13. WTR (LOCKOUT) Switch in (LOCKOUT) Switch placed in RESET RESET upon the Loss of Normal Service Water, Loss of CCP. SWP-P2C Starts (P601)

Green light OFF Red light ON Place the STBY SVCE WTR TEST STBY SVCE WTR TEST (DIV 1) placed to OFF

14. (DIV 1) to OFF upon the Loss of Normal Service Water, Loss of CCP. Normal Service Water Isolation Valves SWP-MOV57A and SWP-MOV96A Close (P870)

Green light ON Red light OFF Standby Cooling Tower Inlet SWP-MOV55A opens Green light OFF Red light ON Place the RPCCW DIV 1 TEST to RPCCW DIV 1 TEST placed to OFF NOTE: No valves should

15. OFF upon the Loss of Normal reposition when this switch is Service Water, Loss of CCP. removed from TEST because the vital loop isolation valves were closed as part of the STP.

Terminating Cue: Div I Standby Service Pumps SWP-P2A and SWP-P2C operating with NSW supply and return valves closed.

RJPM-NRC10-S5 Rev 01 Page 10 of 12

RJPM-NRC10-S5 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-S5 Rev 01 Page 11 of 12

RJPM-NRC10-S5 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The Plant is operating at rated conditions with no equipment out of service.

Initiating Cues: The CRS directs you to complete STP-115-6301, Div 1 Reactor Plant Component Cooling Water Quarterly Valve Operability Test, starting at Step 7.4.

Steps 7.1 through 7.3 have been completed by the Reactor Building Operator.

The CRS has designated you as the dedicated operator to maintain Div I Standby Service Water System availability during the surveillance testing, per Step 7.4.1 RJPM-NRC10-S5 Rev 01 Page 12 of 12

Number:

RJPM-NRC10-S6 RIVER Revision: 01 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM: HLO JOB PERFORMANCE MEASURE LESSON PLAN:

SHUTDOWN DIVISION I EMERGENCY DIESEL GENERATOR (EG1A)

REASON FOR REVISION:

New revision for 2010 NRC exam S6 PREPARE / REVIEW:

John Hedgepeth 0069 10-28-2009 Preparer KCN Date Angela Orgeron 1538 2-15-2010 Technical Review (SME) KCN Date Scott Dallas 1385 01/12/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC10-S6 JPM NUMBER: JPM-309-01 Rev 05 TASK DESCRIPTION: Shutdown Division I Emergency Diesel Generator (EG1A)

K/A REFERENCE & RATING: 264000 A4.04, 3.7/3.7 264000 A1.09, 3.0/3.1 264000 A2.02, 3.1/3.1 264000 A2.03, 3.4/3.4 264000 A4.01, 3.3/3.4 264000 A4.04, 3.7/3.7 264000 K4.07, 3.3/3.4 264000 G07, 3.6/3.8 264000 G09, 3.8/3.9 264000 G13, 3.5/3.7 TASK

REFERENCE:

264015001001 TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: Simulator: X In-Plant:

COMPLETION TIME: 15 min.

MAX. TIME: N/A JOB LEVEL: All TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION: 6 RJPM-NRC10-S6 Rev 01 Page 2 of 9

RJPM-NRC10-S6 SIMULATOR SETUP SHEET Task

Description:

Shutdown Division I Emergency Diesel Generator (EG1A)

Required Power: Any IC No.: 232 Notes: 1. Require Div I EDG to be running in parallel with the Normal Supply.

2. Have loaded to approx. 2000 kw.

3. Use the emergency start pushbutton on P877 to start the diesel.

Then depress the emergency start reset push button to setup the diesel for this JPM. If the local start remote function is used, the diesel will restart if the stop reset push buttons are depressed on P877.

RJPM-NRC10-S6 Rev 01 Page 3 of 9

RJPM-NRC10-S6 DATA SHEET References for Development: SOP-0053, Standby Diesel Generator and Auxiliaries Required Materials: SOP-0053 Section 6.1, Shutdown of EGS-EG1A STANDBY DIESEL GENERATOR from the Control Room.

Required Plant Condition: Div I EDG is running in parallel with the Normal Supply per SOP-0053 for a post maintenance run.

Task Standard: EGS-EG1A STANDBY DIESEL GENERATOR secured per SOP-0053 Applicable Objectives: REQ-334-00, Obj 3 HLO-037-05 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: None Items marked with an "*" are required to be performed, and are Critical Steps, failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory". Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

Items marked with an "^" are required to be performed in the sequence described, if not performed in the sequence described, appropriate cues other than described in the body of the JPM may be required to provide proper feedback.

RJPM-NRC10-S6 Rev 01 Page 4 of 9

RJPM-NRC10-S6 If In-Plant or In the Control Room:

Caution the Operator NOT to MANIPULATE the controls, but make clear what they would do if this were not a simulated situation.

Read to the Operator:

I will explain the initial conditions, and provide initiating cues, I may provide cues during the performance of this JPM, I may ask follow-up questions as part of this JPM. When you complete the task successfully, the objective for this JPM will be satisfied, you should inform me when you have completed the task.

Initial Conditions:

Div I EDG is running in parallel with the Normal Supply per SOP-0053 for a post maintenance run.

Initiating Cue:

The CRS has directed you to unload and secure the Division I Emergency Diesel Generator from the control Room in accordance with SOP-0053 Section 6.1.

RJPM-NRC10-S6 Rev 01 Page 5 of 9

RJPM-NRC10-S6 PERFORMANCE STEP STANDARD S/U COMMENTS

1. Reduce load with the STBY DIESEL Load reduced to approximately 175 kw and This may be done per Attachment GENERATOR A GOVERNOR to reactive load is reduced to no less than 0 KVARs 6 guidance for KW vs. Vars.

approximately 175 Kw and reactive load to This step is not critical if no less than 0 KVAR using the STBY Governor Control is later adjusted DIESEL GENERATOR A VOLTAGE to 60 Hz. No less than 0 KVAR REGULATOR CONT. means minimum, but not less than 0 KVAR.

2. Allow diesel cylinder temperatures to Cylinder temperatures stablized CUE: Ten minutes have elapsed stabilize and the cylinder temperatures have stablized.

3. Trip ENS-ACB07, STBY D/G A OUTPUT ENS-ACB07 open; green light is on and red light BRKR. is off

4. Adjust the EG1A STANDBY DIESEL DG frequency at 60 Hz. This step is not critical if load was frequency to 60 Hz, using the STBY reduced to 175 kw in the previous DIESEL GENERATOR A GOVERNOR steps.

CONTROL

5. Depress the STBY DIESEL ENGINE A STBY DIESEL ENGINE A EMERGENCY Failure to press the Emergency EMERGENCY START RESET START RESET Pushbutton depressed Start Reset Pushbutton will cause Pushbutton EDG to restart. This step is not critical if performed in later steps.

6. Allow the diesel to run unloaded for DG runs unloaded for approximately 2 minutes CUE: Two minutes has elapsed.

approximately 2 minutes

7. Depress the STBY DIESEL ENGINE A Both STBY DIESEL ENGINE A STOP CUE: Inform the operator that STOP Pushbuttons simultaneously Pushbuttons simultaneously depressed the DG is coasting down.

RJPM-NRC10-S6 Rev 01 Page 6 of 9

RJPM-NRC10-S6 PERFORMANCE STEP STANDARD S/U COMMENTS

8. Open the Turbocharger Prelube Valve Turbocharger Prelube Valve opened within 1 CUE: As diesel operator report immediately after depressing the STOP minute after STOP pushbuttons depressed. that the EGO-V3006A, prelube Pushbuttons. EGO-V3006A valve is open.

9 WHEN the engine has stopped, THEN Diesel operator directed to depress the STOP CUE: Diesel operator reports that depress STBY DIESEL ENGINE A STOP RESET pushbutton on EGS-PNL3A. ENGINE the STOP RESET push button has RESET pushbutton. CONTROL PANEL. been depressed.

10 At EGS-PNL3A, depress the STOP Diesel operator directed to depress the STOP CUE: Diesel operator reports that pushbutton for HVP-FN2A, STBY VENT pushbutton for HVP-FN2A, STBY VENT FAN HVP-FN2A, STBY VENT FAN FAN. has been stopped.

11 WHEN the Turbocharger has coasted to a Diesel operator directed to close the prelube CUE: Diesel operator reports that stop, THEN close EGO-V3006A, TURBO valve when the diesel has coasted to a stop. the diesel has coasted to a stop and MANUAL PRELUBE SHUTOFF. the prelube valve is closed.

CUE: Diesel operator will continue with steps 6.1.10 to 6.1.13.

Terminating Cue: Diesel Generator shutdown in accordance with SOP-0053.

RJPM-NRC10-S6 Rev 01 Page 7 of 9

RJPM-NRC10-S6 VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO No. of Attempts:

Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Note: An "Unsatisfactory" requires comments and remedial training.

Evaluator's Signature: Date:

RJPM-NRC10-S6 Rev 01 Page 8 of 9

RJPM-NRC10-S6 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: Div I EDG is running in parallel with the Normal Supply per SOP-0053 for a post maintenance run.

Initiating Cues: The CRS has directed you to unload and secure the Division I Emergency Diesel Generator from the control Room in accordance with the SOP 0053 Section 6.1.

RJPM-NRC10-S6 Rev 01 Page 9 of 9

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