Text

RB-2010-12-Draft Operating Test
	ML110450185
Person / Time
Site:	River Bend
Issue date:	12/10/2010
From:	; NRC Region 4
To:	; Entergy Corp
References
	Download: ML110450185 (242)
	v • d • e

Number: *RJPM-NRC-D10-A1 RIVER Revision: 00 BEND STATION Page 1 of 8 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

DETERMINE CORRECTED FUEL ZONE LEVEL INDICATION AND WHETHER OR NOT ADEQUATE CORE COOLING EXISTS REASON FOR REVISION:

NRC Exam JPM A1 PREPARE / REVIEW:

Angie Orgeron 1538 8/26/2010 Preparer KCN Date John Hedgepeth 0069 8/26/2010 Technical Review (SME) KCN Date Scott Shultz 0176 9/9/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC-D10-A1 TASK DESCRIPTION: Determine corrected fuel zone level indication and determine whether or not adequate core cooling exits.

TASK

REFERENCE:

2000090005005 K/A REFERENCE & RATING: 2.1.25 IR 3.9 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-NRC-D10-A1 Page 2 of 8

RJPM-NRC-D10-A1 SIMULATOR SETUP SHEET Task

Description:

Determine corrected fuel zone level indication and determine whether or not adequate core cooling exits.

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

RJPM-NRC-D10-A1 Page 3 of 8

RJPM-NRC-D10-A1 DATA SHEET References for Development: SOP-0001, Nuclear Boiler Instrumentation, Attachment 3 Required Materials: SOP-0001, Nuclear Boiler Instrumentation, Attachment 3 Required Plant Condition: None Task Standard Determine that RPV water level is below TAF and the adequate core cooling is not assured.

Applicable Objectives: RLP-STM-0051 Obj.5 Safety Related Task: Yes 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-NRC-D10-A1 Page 4 of 8

RJPM-NRC-D10-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:

The plant has experienced a LOCA.

Fuel Zone level indication is -210 inches RPV pressure is 250 psig.

Low pressure core spray is injecting at 2500 gpm.

Initiating Cue:

The CRS has directed you to use the fuel zone correction curve of SOP-0001 (Attachment 3) and determine whether level is above or below the top of active fuel and whether or not adequate core cooling is assured to support the decision on emergency depressurization.

RJPM-NRC-D10-A1

Denotes Critical Step Page 5 of 8

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

RJPM-NRC-D10-A1 PERFORMANCE STEP STANDARD S/U COMMENTS Plot fuel zone level indication on Candidate plotted -210 inches on y-axis of 1.

Attachment 3 of SOP-0001. Attachment 3 of SOP-0001.

Plot RPV pressure indication on Candidate plotted 250 psig on x-axis of Attachment 3 of SOP-0001 Attachment 3 of SOP-0001.

2.

Identify intersection of fuel zone Candidate identified the intersection of the fuel level and RPV pressure plots. zone level and RPV pressure lines as being BELOW TAF and circled on cue sheet.

Candidate determined that adequate core cooling

3. IS NOT ASSURED based on corrected level being below the minimum steam cooling reactor water level (MSCRWL) and circled on cue sheet.

Terminating Cue: Corrected level indication determined to be below the top of active fuel and adequate core cooling does not exist. Responses documented on cue sheet.

RJPM-NRC-D10-A1

Denotes Critical Step Page 6 of 8

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

RJPM-NRC-D10-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-NRC-D10-A1 Page 7 of 8

RJPM-NRC-D10-A1 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant has experienced a LOCA.

Fuel Zone level indication is -210 inches RPV pressure is 250 psig.

Low pressure core spray is injecting at 2500 gpm.

Initiating Cues: The CRS has directed you to use the fuel zone correction curve of SOP-0001 (Attachment 3) and determine whether level is above or below the top of active fuel and whether or not adequate core cooling is assured to support the decision on emergency depressurization.

Record your responses below.

Corrected Level is:

ABOVE TAF / BELOW TAF (Circle one)

Adequate Core Cooling:

IS ASSURED / IS NOT ASSURED (Circle one)

RJPM-NRC-D10-A1 Page 8 of 8

Number: *RJPM-NRC-D10-A2 RIVER Revision: 00 BEND STATION Page 1 of 11 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

USING A CORE MONITOR PRINT OUT, DETERMINE IF THERMAL LIMITS ARE IN SPEC.

REASON FOR REVISION:

NRC Exam JPM A2 PREPARE / REVIEW:

John Hedgepeth 0069 8-31-2010 Preparer KCN Date Angie Orgeron 1538 8-31-2010 Technical Review (SME) KCN Date Scott Dallas 1385 9-9-2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-A2 TASK DESCRIPTION: Using a core monitor print out, determine if thermal limits are in spec.

TASK

REFERENCE:

302001002001 K/A REFERENCE & RATING: 2.1.20 IR 4.6 TESTING METHOD: Simulate Actual Performance Performance X Control Simulator Classroom X Room COMPLETION TIME: 6 min.

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

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

RJPM-NRC-D10-A2 Page 2 of 11

RJPM-NRC-D10-A2 SIMULATOR SETUP SHEET Task

Description:

Using a core monitor print out, determine if thermal limits are in spec Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC-D10-A2 Page 3 of 11

RJPM-NRC-D10-A2 DATA SHEET References for Development: STP-000-0001, Daily Operations Logs GOP-0004, Single Loop Operation Required Materials: STP-000-0001, Daily Operations Logs GOP-0004, Single Loop Operation Attached POWERPLEX Core Performance Log Required Plant Condition: N/A Task Standard The information is recorded in step 113 and determination made that MFLCPR acceptance criteria is not met.

Applicable Objectives: RLP-STM-514, Obj. H5 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-NRC-D10-A2 Page 4 of 11

RJPM-NRC-D10-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 A Reactor Recirc Pump tripped from full power and GOP-0004, Single Loop Operation has been entered. Reactor Engineering has NOT implemented a new core monitoring system thermal limit deck for Single Loop Operation.

Initiating Cue:

The CRS has directed you to complete Step 113 of STP-000-0001, Data Sheet, with the attached Core Performance Log data and determine if acceptance criteria is met.

RJPM-NRC-D10-A2

Denotes Critical Step Page 5 of 11

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

RJPM-NRC-D10-A2 PERFORMANCE STEP STANDARD S/U COMMENTS STEP 113 NOTES Refered to administrative limits in GOP-0004 Step 3.4.

Power Distribution Limits shall be verified to be within the limits stated in Technical Specifications within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after Thermal Power is 23.8%

1.

of rated thermal power and once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

During Single Loop Operation, refer to GOP-0004 to determine if administrative limits are applicable.

GOP-0004 Step 3.4 During Single Loop Operation, an Used 0.980 Admin limit for MFLCPR and 0.79 administrative limit of 0.980 shall be for MAPRAT.

applied to MFLCPR and an administrative limit of 0.79 shall be

2. applied to MAPRAT while core flow is greater than 50% rated. The administrative limits may be removed once Reactor Engineering implements the appropriate core monitoring system thermal limit deck.

RJPM-NRC-D10-A2

Denotes Critical Step Page 6 of 11

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

RJPM-NRC-D10-A2 PERFORMANCE STEP STANDARD S/U COMMENTS Reviews Core Performance Log to Filled in Step 113 identifying MFLCPR at 0.988 CUE: As CRS, acknowledge obtain values for MFLPD, MAPRAT, as exceeding SLO administrative limit. MFLCPR exceeding limit.

___*__3. and MFLCPR for operating log Step 113. Notifies CRS of MFLCPR exceeding limit. NOTE: Reading being circled is NOT critical.

Terminating Cue: Step 113 of STP-000-0001, Data Sheet 1 completed and MFLCPR identified as exceeding limit.

KEY Acceptance Criteria met YES _______

NO ___X___

MLFPD Y/N MAPRAT Y / N MFLCPR Y / N RJPM-NRC-D10-A2

Denotes Critical Step Page 7 of 11

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

RJPM-NRC-D10-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-NRC-D10-A2 Page 8 of 11

RJPM-NRC-D10-A2 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The A Reactor Recirc Pump tripped from full power and GOP-0004 Single Loop Operation has been entered.

Reactor Engineering has NOT implemented a new core monitoring system thermal limit deck for Single Loop Operation.

Initiating Cues: The CRS has directed you to complete Step 113 of STP-000-0001, Data Sheet, with the attached Core Performance Log data and determine if acceptance criteria is met.

Acceptance Criteria met YES _______

NO _______

MLFPD Y/N MAPRAT Y / N MFLCPR Y / N RJPM-NRC-D10-A2 Page 9 of 11

RJPM-NRC-D10-A2 DAILY OPERATING LOGS Ste Instrument Night Limits Day p

No. Panel Numbers Panel Numbers 110 ENS-SWG1A P877 P877 Degraded (27/62-2A, B, C) and Under (27-1A, B, C) Volts Volts Voltage V-1EGSA08 V-1EGSA08 3740 VAC Relay Channel Check AND 111 ENS-SWG1B P877 4580 VAC P877 Degraded (27/62-2A, B, C) and Under (27-1A, B, C) Volts Volts Voltage V-1EGSB08 V-1EGSB08 Relay Channel Check 112 E22-S004 P601 P601 Degraded and Place E22B-S4, E22- Place E22B-S4, E22-ACB004 SYNC Undervoltage Relay ACB004 SYNC SWITCH in NRM/BUS.

Channel Check SWITCH in NRM/BUS.

Degraded 27/62-1, 2 Incoming Volts Incoming Volts 3740 VAC E22-R611 E22-R611 AND Undervoltage 4580 VAC 27-S1, 2, 3, 4 Running Volts Running Volts E22-R614 E22-R614 P601 P601 Place E22B-S4 in OFF (Key removed) Place E22B-S4 in OFF (Key removed)

Lined up by: _____________ Verified by: Lined up by: _____________ Verified by:

(Initials) (Initials) (Initials) (Initials) 113 Thermal Limits Core STEP 113 NOTES Power Power Distribution Limits shall be verified to be within the limits stated in Technical Specifications (LHGR) within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after Thermal Power is 23.8% of MFLPD rated thermal power and once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (Most limiting) thereafter.

(APLHGR)

MAPRAT During Single Loop Operation, Refer To GOP-(Most limiting) 0004 to determine if administrative limits are applicable.

(MCPR)

MFLCPR (Most limiting)

RJPM-NRC-D10-A2 Page 10 of 11

RJPM-NRC-D10-A2 POWERPLEX - III CORE PERFORMANCE LOG - OPS - 03FEB10 - 164555 B1-01-04 (02.11.03 @ 2100) GEOM=FULL PREDICT CALCULATION - UPD TDXEC PREV PCS Y RESTART 03FEB10 - 161100 POWER 2036.0 MWTH CYCLE EXP 10133.4 MWD/MT CMFLCPR .988 23-22 (67.0%) CORE EXP 23317.4 MWD/MT CMAPRAT .781 21-32-17 FLOW 45.4 MLB/HR PRESS 1015.0 PSIA CMFLPD .824 21-32-17 (53.7%) DHS 30.40 BTU/LB CMTPF 2.558 19-32-15 ELEC 719.6 MWE WFW 7.473 MLB/HR FCBB 1.879 2.46 FT ROD-LN 106.9 % TFW-A 383.7 DEG F P-PCS .000 17-34-18 K-EFF 1.0054 NON-EQ XE .00 P-PCFC -.252 35-10-10 CONTROL RODS SYMMETRIC, C.R. SEQUENCE: B-1, C.R. DENSITY: .070 04 08 12 16 20 24 28 32 36 40 44 48 52 53 -- -- -- -- -- -- -- 53 49 -- -- -- -- -- -- -- -- -- 49 45 -- -- -- -- -- - -- -- -- -- -- 45 KEY 41 -- -- -- -- 06 -- 12 -- 06 -- -- -- -- 41 R-MFLCPR 37 -- -- -- -- -- -- -- -- -- -- -- -- -- 37 M-MAPRAT 33 -- -- 10 P 24* -- -- -- 24 -- 10 -- -- 33 X-FDLRX 29 -- -- -- -- -- -- -- -- -- -- -- -- -- 29 P-PRECOND 25 -- -- 10 -- 24 -- -- -- 24 -- 10 -- -- 25 *-MULT 21 -- -- -- -- -- R- - 12 -- -- -- -- -- -- 21 17 -- -- -- -- 06 -- -- -- 17 -- -- -- -- 17 SUBST RODS 13 -- -- -- -- -- -- -- -- -- -- -- 13 09 -- -- -- -- -- -- -- -- -- 09 05 -- -- -- -- -- -- -- 05 04 08 12 16 20 24 28 32 36 40 44 48 52 THERMAL LIMIT DETAIL (TOP 5) AXIAL REL POWER MFLCPR LOC MAPRAT LOC MFLPD LOC TPF LOC LOC NOTCH RPOW

.988 23-22 .781 21-32-17 .824 21-32-17 2.558 19-32-15 25 .098

.961 27-22 .773 19-24-17 .763 19-32-17 2.461 21-34-15 24 00 .315

.938 21-28 .760 19-32-17 .751 19-24-17 2.438 23-48-04 23 02 .801

.925 15-22 .739 15-20-09 .746 29-48-04 2.376 35-12-04 22 04 1.007

.920 13-20 .737 13-26-21 .746 29-48-04 2.376 35-12-04 21 06 1.100 20 08 1.147 19 10 1.154 18 12 1.150 FUEL TYPE DETAIL AXIAL DISTRIBUTION DETAIL 17 14 1.146 MAX LHGR BATCH 16 16 1.189 TYPE LHGR LOC AVG EXP CORE -AVERAGE 15 18 1.189

----- ------- ------ POWER (PINER) -3.458 14 20 1.193 14 7.427 15-20-20 32.972 13 22 1.199 15 6.380 05-20-20 27.034 CORE-AVERAGE 12 24 1.184 16 5.005 05-30-20 27.375 EXPOSURE (INER) -10.915 11 26 1.179 17 7.140 19-22-17 20.836 10 28 1.180 18 8.616 19-28-17 26.561 09 30 1.178 19 9.622 21-32-15 28.341 08 32 1.166 20 9.045 21-28-17 12.792 07 34 1.149 21 10.185 19-32-17 12.224 06 36 1.124 05 38 1.100 04 40 1.071 03 42 .996 RADIAL RING 1 2 3 4 5 6 7 02 44 .780 RING REL POWER 1.07 1.26 1.29 1.20 1.21 1.13 .59 01 46 .204 RJPM-NRC-D10-A2 Page 11 of 11

Number: *RJPM-NRC-D10-A3 RIVER Revision: 0 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

IDENTIFY COMPONENTS AND SEQUENCE FOR A TAGOUT ON HVN-STR1B, TURBINE BUILDING PUMP 1A SUCTION STRAINER REASON FOR REVISION:

NRC Exam JPM A3 PREPARE / REVIEW:

John Hedgepeth 0069 8-31-2010 Preparer KCN Date Angela Orgeron 1538 8-31-2010 Technical Review (SME) KCN Date Scott Dallas 1385 9-9-2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC-D10-A3 TASK DESCRIPTION: IDENTIFY COMPONENTS AND SEQUENCE FOR A TAGOUT ON HVN-STR1B, TURBINE BUILDING PUMP 1A SUCTION STRAINER TASK

REFERENCE:

300095003001 K/A REFERENCE & RATING: 2.2.13 IR 4.1 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-NRC-D10-A3 Rev. 00 Page 2 of 9

RJPM-NRC-D10-A3 SIMULATOR SETUP SHEET Task

Description:

IDENTIFY COMPONENTS AND SEQUENCE FOR A TAGOUT ON HVN-STR1B, TURBINE BUILDING PUMP 1A SUCTION STRAINER Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC-D10-A3 Rev. 00 Page 3 of 9

RJPM-NRC-D10-A3 DATA SHEET References for Development: PID 22-14A, System P&ID SOP-0116, TURBINE AND RADWASTE BUILDING HVAC CHILLED WATER SYSTEM EN-OP-102 Protective and Caution Tagging Required Materials: PID 22-14A, System P&ID SOP-0116, TURBINE AND RADWASTE BUILDING HVAC CHILLED WATER SYSTEM (lineup section)

EN-OP-102 Protective and Caution Tagging Required Plant Condition: The plant is operating in Mode 1, maintenance requested that HVN-STR1B be tagged out to clean and inspect the strainer.

Task Standard Required components and sequence identified as listed on the attached answer key.

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-NRC-D10-A3 Rev. 00 Page 4 of 9

RJPM-NRC-D10-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 is operating in Mode 1. Maintenance requested that HVN-STR1B be tagged out to clean and inspect the strainer.

Initiating Cue:

The CRS has directed you to assist in preparing a tagout to clean and inspect HVN-STR1B.

A tagging official will enter the information you provide into the tagging computer.

RJPM-NRC-D10-A3 Rev. 00

Denotes Critical Step Page 5 of 9

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

RJPM-NRC-D10-A3 PERFORMANCE STEP STANDARD S/U COMMENTS Obtained PID 22-14A, System P&ID Obtains documents to develop tagout. CUE: Provide PID and SOP SOP-0116, TURBINE AND RADWASTE when requested.

BUILDING HVAC CHILLED WATER 1.

SYSTEM Identify components to be tagged and Student identified the proper components and

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

Terminating Cue: Tagout Form completed.

RJPM-NRC-D10-A3 Rev. 00

Denotes Critical Step Page 6 of 9

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

RJPM-NRC-D10-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-NRC-D10-A3 Rev. 00 Page 7 of 9

RJPM-NRC-D10-A3 Sequence Component ID Component Name Hang Position 1 1 HVN-P1B control switch HVN-P1B VENT CHILL STOP WATER PUMP 2 2 NNS-SWG1B ACB19 ACB19 TURB BLDG Racked out CHILLED WP MOT HVN-P1B 3 2 NHS-MCC1F BKR 3B CHILLED WATER PUMP off P1B DISCHARGE VALVE 4 3 HVN-MOV4B CHILLED WATER PUMP closed P1B DISCHARGE VALVE hand wheel 5 4 HVN-V2 TURB BLDG PUMP 1B closed HVN-P1B SUCTION 6 5 HVN-V18 TURB BLDG PUMP 1B Uncapped open SUCTION STRAINER HVN-STR1B DRAIN 7 6 HVN-V1216 TURB BLDG PUMP 1B Uncapped open HVN-P1B CASING VENT V16 ALTERNANTE VENT V-1217 OR 808 ALTERNATE DRAIN RJPM-NRC-D10-A3 Rev. 00 Page 8 of 9

RJPM-NRC-D10-A3 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is operating in Mode 1. Maintenance requested that HVN-STR1B be tagged out to clean and inspect the strainer.

Initiating Cues: The CRS has directed you to assist in preparing a tagout to clean and inspect HVN-STR1B.

A tagging official will enter the information you provide into the tagging computer.

Sequence Component ID Component Name Hang Position RJPM-NRC-D10-A3 Rev. 00 Page 9 of 9

Number: *RJPM-NRC-D10-A4 RIVER Revision: 00 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

PERFORM A DOSE ASSESSMENT AND DETERMINE IF RWP IS ACCEPTABLE REASON FOR REVISION:

NRC Exam JPM A4 PREPARE / REVIEW:

John Hedgepeth 0069 8-31-2010 Preparer KCN Date Angela Orgeron 1538 8-31-2010 Technical Review (SME) KCN Date Scott Shultz 0176 9-9-2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC-D10-A4 TASK DESCRIPTION: PERFORM A DOSE ASSESSMENT AND DETERMINE IF RWP IS ACCEPTABLE TASK

REFERENCE:

300157003001 K/A REFERENCE & RATING: Generic 2.3.7 3.5 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 15 min.

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

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

RJPM-NRC-D10-A4 Rev. 0 Page 2 of 10

RJPM-NRC-D10-A4 SIMULATOR SETUP SHEET Task

Description:

PERFORM A DOSE ASSESSMENT AND DETERMINE IF RWP IS ACCEPTABLE Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC-D10-A4 Rev. 0 Page 3 of 10

RJPM-NRC-D10-A4 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: Dose assessment and RWP adequacy determined.

Applicable Objectives: N/A 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-NRC-D10-A4 Rev. 0 Page 4 of 10

RJPM-NRC-D10-A4 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.

SPC-P1A will be placed in service this shift.

Initiating Cue:

Your shift will obtain pump bearing vibration readings.

It will take a maximum of 20 minutes to complete this activity.

RWP 2010-1032 has been written for this job.

General area dose levels are shown on the survey map. SPC-P1A is the north most pump in the room

Determine the expected dose to be received for this activity.

Determine if the RWP is adequate for the work to be performed.

RJPM-NRC-D10-A4 Rev. 0

Denotes Critical Step Page 5 of 10

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

RJPM-NRC-D10-A4 PERFORMANCE STEP STANDARD S/U COMMENTS Determine the expected dose to be Determined the dose that will be received is received for this activity.

1 0.32mR/min. or 6.4 for the activity.(accept 5-8mR)

Review RWP 2010-1032 and Determined that the RWP is adequate for this determine if the RWP is adequate activity

2. for the work to be performed.

Terminating Cue: Expected dose calculated and RWP determination made.

KEY Dose to be received for this activity 5 - 8 mR RWP is adequate RWP is NOT adequate RJPM-NRC-D10-A4 Rev. 0

Denotes Critical Step Page 6 of 10

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

RJPM-NRC-D10-A4 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-NRC-D10-A4 Rev. 0 Page 7 of 10

RJPM-NRC-D10-A4 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 07-14-2010 Prepared By: Keith Rockwood Job Supervisor:

Estimated Estimated Hours: Actual Dose: Actual Hours:

Dose: 8.00 100 mrem Buildings Elevations Rooms AB 70 SPC PUMP ROOM Radiological Conditions Description Value Unit Contact RP or review current survey maps See maps TASKS Task Description Status 1 Isolate and Tag out SPC pump 1A active 2 Remove and replace SPC pump 1A seal active 3 System return to service active 4 Obtain pump bearing vibration readings 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-NRC-D10-A4 Rev. 0 Page 8 of 10

RJPM-NRC-D10-A4 RADIOLOGICAL WORK PERMIT Task Number: 4 RWP No.: 20101032 Rev: 00 Task

Description:

Task Status: Active Obtain pump bearing vibration readings Estimated Dose: Estimated Hours: 0.3 Hi-Rad: NO Hot Particle: Locked Hi-Rad: NO Hi-Contamination:

NO NO Dose Alarm (mrem) 20.00 Dose Rate (mrem/hr) 50.00 Requirement Groups Requirement Descriptions ACCESS **CRITICIAL STEP** 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 N/A 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 >50 mrem/hr, contamination levels >5 mrad/hr beta/gamma or >

or = 1000 dpm/100cm2 (alpha)

RJPM-NRC-D10-A4 Rev. 0 Page 9 of 10

RJPM-NRC-D10-A4 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions:

The Plant is operating at 100% power.

SPC-P1A will be placed in service this shift.

Initiating Cue:

Your shift will obtain pump bearing vibration readings.

It will take a maximum of 20 minutes to complete this activity.

RWP 2010-1032 has been written for this job.

General area dose levels are shown on the survey map. SPC-P1A is the north most pump in the room

Determine the expected dose to be received for this activity.

Determine if the RWP is adequate for the work to be performed.

Dose to be received for this activity RWP is adequate RWP is NOT adequate RJPM-NRC-D10-A4 Rev. 0 Page 10 of 10

Number: *RJPM-NRC-D10-A5 RIVER Revision: 0 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

DETERMINE THE TIME TO 200oF AND IF FORCED CIRCULATION IS REQUIRED REASON FOR REVISION:

2010 NRC Exam JPM - SRO A5 PREPARE / REVIEW:

John Hedgepeth 0069 8/31/2010 Preparer KCN Date Angie Orgeron 1538 8/31/2010 Technical Review (SME) KCN Date Alfonso Croeze 0597 9/9/2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-A5 TASK DESCRIPTION: Determine the time to 200oF and if forced circulation is required TASK

REFERENCE:

400077004001 K/A REFERENCE & RATING: 2.1.25, 4.2 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-NRC-D10-A5 Page 2 of 10

RJPM-NRC-D10-A5 SIMULATOR SETUP SHEET Task

Description:

Determine the time to 200oF and if forced circulation is required Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC-D10-A5 Page 3 of 10

RJPM-NRC-D10-A5 DATA SHEET References for Development: OSP-0037, Shutdown Operations Protection Plan (SOPP) Rev.23 SOP-0003 REACTOR RECIRCULATION SYSTEM Required Materials: OSP-0037, Shutdown Operations Protection Plan (SOPP) Rev.23 (graphs only)

SOP-0003 REACTOR RECIRCULATION SYSTEM Required Plant Condition: N/A Task Standard Used OSP-0037 to determine the time to 200oF and made the determination regarding Recirc pumps in accordance with the attached key.

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-NRC-D10-A5 Page 4 of 10

RJPM-NRC-D10-A5 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:

You are currently in day 15 of a forced outage.

Shutdown cooling is being maintained by RHR B through the Heat Exchanger, recirculation pump A is tagged out for seal replacement that is expected to start next shift. Recirculation pump B is running in slow speed with the FCV at 94% open.

SPC-P1B is tagged out SPC-P1A and RHR-P1A are out of service due to electrical bus outage.

Reactor Water temperature is 130oF The water level in the Reactor is about 85 inches.

The first reactor head bolt will be de-tensioned within an hour.

Initiating Cue:

A bus fault has resulted in a loss of power to RHR B. The OSM has directed you to determine time to 200oF and if Reactor Recirc. Pump can be secured at this time.

RJPM-NRC-D10-A5

Denotes Critical Step Page 5 of 10

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

RJPM-NRC-D10-A5 PERFORMANCE STEP STANDARD S/U COMMENTS Determine which curve group to use. Used the information provided, determined that

1. Before Fuel Shuffle or After Fuel Fuel Movement has not started.

Shuffle.

Determine Reactor Water Level: Using the information provided that the reactor water level is about 85 inches.

36 inches

85 inches

2.

Main Steam Lines

Reactor Flange

Flooded Locate Day 15 on Attachment 9 page Determine from the graph that for Day 15, it will 4 of 32, Time to 200F curve before take 2.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (+ 0.05 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ) for temperature to

3. fuel shuffle for reactor water level rise from 110oF to 200oF about 85 inches and Rx water Temperature 110.

Use the appropriate Multiplier for an Determine from the table in the lower right of the Note: Because the initial initial temperature of 130oF graph that the multiplier for Temp 130oF is 0.77 temperature is closer to 200F it

4.

will take less time to get to 200F, so a multiplier is used.

5. Multiply 2.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months by 0.77 Answer range of 1.57 to 1.65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months is correct Determine that Recirc pump cannot be Time to 200oF is < 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months SOP-003 Section 6.0 NOTE

6.

secured.

RJPM-NRC-D10-A5

Denotes Critical Step Page 6 of 10

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

RJPM-NRC-D10-A5 Terminating Cue: Time to 200°F and recirculation limitations determined.

RJPM-NRC-D10-A5

Denotes Critical Step Page 7 of 10

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

RJPM-NRC-D10-A5 KEY Time to 200oF __1.57 to 1.65 hour7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months s___________

Can Recirc. Pump be secured? YES NO RJPM-NRC-D10-A5

Denotes Critical Step Page 8 of 10

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

RJPM-NRC-D10-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-NRC-D10-A5 Page 9 of 10

RJPM-NRC-D10-A5 JPM Task Conditions/Cues (Operator Copy)

You are currently in day 15 of a forced outage.

Initial Conditions:

Shutdown cooling is being maintained by RHR B through the Heat Exchanger, recirculation pump A is tagged out for seal replacement that is expected to start next shift. Recirculation pump B is running in slow speed with the FCV at 94% open.

SPC-P1B is tagged out SPC-P1A and RHR-P1A are out of service due to electrical bus outage.

Reactor Water temperature is 130oF The water level in the Reactor is about 85 inches.

The first reactor head bolt will be de-tensioned within an hour.

A bus fault has resulted in a loss of power to RHR B. The OSM has Initiating Cues:

directed you to determine time to 200oF and if Reactor Recirc. Pump can be secured at this time.

Time to 200oF ______________________

Can Recirc. Pump be secured? YES NO RJPM-NRC-D10-A5 Page 10 of 10

Number: *RJPM-NRC-D10-A6 RIVER Revision: 00 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

DETERMINE IF SHIFT STAFFING REQUIREMENTS ARE MET REASON FOR REVISION:

NRC Exam JPM A6 PREPARE / REVIEW:

Angie Orgeron 1538 8/26/2010 Preparer KCN Date John Hedgepeth 0069 8/26/2010 Technical Review (SME) KCN Date Alfonso Croeze 0597 9/9/2010 Operations Validation KCN Date Facility Reviewer approval via ES-301-3

Indexing Information

RJPM-NRC-D10-A6 TASK DESCRIPTION: Determine if shift staffing requirements are met.

TASK

REFERENCE:

300071003003 K/A REFERENCE & RATING: 2.1.5 IR 3.9 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 10 min.

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

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

RJPM-NRC-D10-A6 Page 2 of 9

RJPM-NRC-D10-A6 SIMULATOR SETUP SHEET Task

Description:

Determine if shift staffing requirements are met.

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

RJPM-NRC-D10-A6 Page 3 of 9

RJPM-NRC-D10-A6 DATA SHEET References for Development: EN-OP-115, Conduct of Operations Required Materials: EN-OP-115, Conduct of Operations Required Plant Condition: None Task Standard Determined that EN-OP-115 requirements are not met and that Stone must be the ATC operator.

Applicable Objectives: RLP-OPS-H0206 Obj 6, 7 Safety Related Task: No 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-NRC-D10-A6 Page 4 of 9

RJPM-NRC-D10-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 in Mode 1 at 100%. No significant evolutions are in progress.

Initiating Cue:

An operator scheduled for the next shift has called in to report that he will not be at work due to illness. The following individuals are scheduled for the shift and will be reporting as scheduled. Determine if minimum staffing requirements of EN-OP-115 are met and determine which of the operators must stand the at the controls (ATC) position.

Branscum OSM McLean CRS/STA Parker STA Stone NCO Coykendall NCO FBL Duncan Fully qualified SNEO FBM Howell Fully qualified SNEO FBM Dugar O, T, RW, R SNEO FBM Bordelon O,T,RW SNEO FBM Seymour O,T,R SNEO FBM RJPM-NRC-D10-A6

Denotes Critical Step Page 5 of 9

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

RJPM-NRC-D10-A6 PERFORMANCE STEP STANDARD S/U COMMENTS Compare available personnel and Candidate reviewed available personnel and EN-qualifications to EN-OP-115 OP-115 requirements and determine:

requirements. EN-OP-115 requirements are not

1) Requirements were not met. met due to only 2 NCOs being present. The assistant Ops

2) Stone must stand the ATC position. Manager may approve a deviation from this requirement since Technical Specification minimum

1. staffing is met.

Stone must stand the ATC position because Coykendall is the only Fire Brigade Leader. The Fire Brigade Leader may not stand the ATC position due to the potential of leaving the control room for fire response.

Terminating Cue: Candidate has determine that EN-OP-115 requirements are not met and that NCO Stone must stand the at the controls (ATC) position.

RJPM-NRC-D10-A6

Denotes Critical Step Page 6 of 9

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

RJPM-NRC-D10-A6 ANSWER KEY Initial Conditions: The plant is in Mode 1 at 100%. No significant evolutions are in progress.

Initiating Cues: An operator scheduled for the next shift has called in to report that he will not be at work due to illness. The following individuals are scheduled for the shift and will be reporting as scheduled.

Determine if minimum staffing requirements of EN-OP-115 are met and determine which operator must stand the at the controls (ATC) position.

Record your responses below.

Branscum OSM McLean CRS/STA Parker STA Stone NCO Coykendall NCO FBL Duncan Fully qualified SNEO FBM Howell Fully qualified SNEO FBM Dugar O, T, RW, R SNEO FBM Bordelon O,T,RW SNEO FBM Seymour O,T,R SNEO FBM McCartney O,T,RW SNEO FBM EN-OP-115 Requirements: MET / NOT MET ; (Select One)

ATC Operator: STONE RJPM-NRC-D10-A6

Denotes Critical Step

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

RJPM-NRC-D10-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-NRC-D10-A6 Page 8 of 9

RJPM-NRC-D10-A6 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is in Mode 1 at 100%. No significant evolutions are in progress.

Initiating Cues: An operator scheduled for the next shift has called in to report that he will not be at work due to illness. The following individuals are scheduled for the shift and will be reporting as scheduled.

Determine if minimum staffing requirements of EN-OP-115 are met and determine which operator must stand the at the controls (ATC) position.

Record your responses below.

Branscum OSM McLean CRS/STA Parker STA Stone NCO Coykendall NCO FBL Duncan Fully qualified SNEO FBM Howell Fully qualified SNEO FBM Dugar O, T, RW, R SNEO FBM Bordelon O,T,RW SNEO FBM Seymour O,T,R SNEO FBM McCartney O,T,RW SNEO FBM EN-OP-115 Requirements: MET / NOT MET (Select One)

ATC Operator ________________________

RJPM-NRC-D10-A6 Page 9 of 9

Number: *RJPM-NRC-D10-A7 RIVER Revision: 0 BEND STATION Page 1 of 8 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

REVIEW A TAGOUT OF LOS-STR1, TURBINE LUBE OIL SUCTION HEADER STRAINER REASON FOR REVISION:

2010 NRC Exam JPM A7 PREPARE / REVIEW:

John Hedgepeth 0069 8/31/2010 Preparer KCN Date Angie Orgeron 1538 8/31/2010 Technical Review (SME) KCN Date Alfonso croeze 0597 9/9/2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-A7 TASK DESCRIPTION: REVIEW A TAGOUT OF LOS-STR1, TURBINE LUBE OIL SUCTION HEADER STRAINER TASK

REFERENCE:

300095003001 K/A REFERENCE & RATING: 2.2.13 4.3 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 Yes (FAULTED):

RJPM-NRC-D10-A7 Page 2 of 8

RJPM-NRC-D10-A7 SIMULATOR SETUP SHEET Task

Description:

REVIEW A TAGOUT OF LOS-STR1, TURBINE LUBE OIL SUCTION HEADER STRAINER Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC-D10-A7 Page 3 of 8

RJPM-NRC-D10-A7 DATA SHEET References for Development: PID-16-03a PID-16-12A SOP-0012 Main Turbine Lube Oil System Required Materials: PID-16-03a PID-16-12A SOP-0012 Main Turbine Lube Oil System Required Plant Condition: N/A Task Standard Reviewed the prepared tagout and determined that it is not acceptable.

Applicable Objectives: ELP-OPS-CLR, Obj. 10 Safety Related Task: NA 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-NRC-D10-A7 Page 4 of 8

RJPM-NRC-D10-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:

A tagout has been developed to support the cleaning and inspecting of the turbine lube oil suction header strainer LOS-STR1.

Initiating Cue:

As part of your outage support activities you have been given a tagout to support the cleaning and inspecting of the turbine lube oil suction header strainer LOS-STR1 for approval. Review the tagout and determine if it should be approved, and if not, why.

RJPM-NRC-D10-A7

Denotes Critical Step Page 5 of 8

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

RJPM-NRC-D10-A7 PERFORMANCE STEP STANDARD S/U COMMENTS Review the turbine lube oil suction DO NOT APPROVE THE TAGOUT for the header strainer LOS-STR1 tagout for following reason:

1. approval.

1. The placement sequence for all tags is 1.

This is incorrect.

Terminating Cue: The candidate has made a determination of the inadequacy of the tagout.

KEY APPROVED DISAPPROVED If disapproved, WHY? The placement sequence for all tags is 1.

RJPM-NRC-D10-A7

Denotes Critical Step Page 6 of 8

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

RJPM-NRC-D10-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-NRC-D10-A7 Page 7 of 8

RJPM-NRC-D10-A7 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A tagout has been developed to support the cleaning and inspecting of the turbine lube oil suction header strainer LOS-STR1.

Initiating Cues: As part of your outage support activities you have been given a tagout to support the cleaning and inspecting of the turbine lube oil suction header strainer LOS-STR1 for approval. Review the tagout and determine if is should be approved, and if not, why.

APPROVED DISAPPROVED If disapproved, WHY? ___________________________________________________

RJPM-NRC-D10-A7 Page 8 of 8

Number: *RJPM-NRC-D10-A8 RIVER Revision: 0 BEND STATION Page 1 of 12 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

REVIEW A LIQUID RADWASTE RELEASE PERMIT ISSUED BY CHEMISTRY REASON FOR REVISION:

2010 NRC Exam JPM A8 PREPARE / REVIEW:

John Hedgepeth 0069 8/31/2010 Preparer KCN Date Angie Orgeron 1538 8/31/2010 Technical Review (SME) KCN Date Alfonso Croeze 0597 9/9/2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-A8 TASK DESCRIPTION: REVIEW A LIQUID RADWASTE RELEASE PERMIT ISSUED BY CHEMISTRY TASK

REFERENCE:

300174003002 K/A REFERENCE & RATING: 2.3.6 3.8 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-NRC-D10-A8 Page 2 of 12

RJPM-NRC-D10-A8 SIMULATOR SETUP SHEET Task

Description:

REVIEW A LIQUID RADWASTE RELEASE PERMIT ISSUED BY CHEMISTRY Required Power: N/A IC No.: N/A Notes: Administrative JPM that will be conducted in a classroom.

RJPM-NRC-D10-A8 Page 3 of 12

RJPM-NRC-D10-A8 DATA SHEET References for Development: CSP-0110 Radioactive Liquid Effluent Batch Discharge ADM-0054, Radioactive Liquid Effluent Batch Discharge Required Materials: CSP-0110 Radioactive Liquid Effluent Batch Discharge ADM-0054, Radioactive Liquid Effluent Batch Discharge Required Plant Condition: N/A Task Standard Reviewed the discharge permit and approved for discharge.

Applicable Objectives:

Safety Related Task: NA 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-NRC-D10-A8 Page 4 of 12

RJPM-NRC-D10-A8 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:

LWS-TK4D, Recovery Sample Tank, is ready for discharge. RMS-RE107 is operable.

Initiating Cue:

Chemistry has brought discharge permit 2010004 to you for authorization. Review the permit and either authorize it or determine why it should not be authorized. Explain your decision.

RJPM-NRC-D10-A8

Denotes Critical Step Page 5 of 12

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

RJPM-NRC-D10-A8 PERFORMANCE STEP STANDARD S/U COMMENTS Review the discharge permit for Discharge permit 2010004 should be authorized.

authorization.

All data is correct, no typographically errors

1.

The RMS-RE107 alarm and alert setpoints on page 1 and page three agree Terminating Cue: Discharge permit has been authorized by the SRO.

RJPM-NRC-D10-A8

Denotes Critical Step Page 6 of 12

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

RJPM-NRC-D10-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-NRC-D10-A8 Page 7 of 12

RJPM-NRC-D10-A8 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: LWS-TK4D, Recovery Sample Tank, is ready for discharge.

RMS-RE107 is operable.

Initiating Cues: Chemistry has brought discharge permit 2010004 to you for authorization. Review the permit and either authorize it or determine why it should not be authorized. Explain your decision.

RJPM-NRC-D10-A8 Page 8 of 12

EOI - RIVER BEND STATION RADIOACTIVE LIQUID EFFLUENT DISCHARGE PERMIT No.: 2010004 I. DISCHARGER AUTORHIZATION LWS-TK4: D LWS-P4: C Sample Date/Time: 08/31/2010 10:00 Recirculation Start Date/Time: 08/31/2010 07:35 LWS-FV197 Control Setpoint (Max.): 40 gpm Diluted Pre-Release ECL Fraction: 3.41E-02 (<1.000)

Calculated RMS-RE 107 Setpoints:

Alarm: 1.99E-03 uCi/ml Alert: 1.79E-03 uCi/ml CH.13

Background:

3.35E+03 cpm Blowdown Rate (Min.): > 2200 gpm Diluted Pre-Release Gaseous Act. 2.93E-07 uCi/ml (<2.00e-4)

Chemistry Authorization: _____Wayne Hillard_____ KCN: _1234 Date/Time: _8-31-2010 / 1700 Chemistry Authorization: __________N/A__________ KCN: __N/A__ Date/Time: __N/A______

(Two authorizations required when monitor inoperable)

SS/CRS Discharge Authorization: _______________________ KCN: ______ Date/Time: _____________

II. DISCHARGE RECORD Init. / KCN RMS-RE107 Source Check Completed: /

RMS-RE107 Sample Pump Started Running: /

Alarm Setpoint Entered: /

Alert Setpoint Entered: /

CH.13 Background Setpoint Entered: /

Sample Pump Operability Check: /

LWS-FE197 Operability Check: /

Valve Lineup Performed: /

Valve Lineup Verified: /

(Two verifications required only when monitor inoperable)

Date Time LWS-FE197 (gpm) CWS-FE113 (gpm) Init. / KCN Start:

Stop:

Total Tank Volume Released (gal) ___________________

RJPM-NRC-D10-A8 Page 9 of 12

EOI - RIVER BEND STATION RADIOACTIVE LIQUID EFFLUENT DISCHARGE PERMIT No.: 2010004 III. POST RELEASE DATA Composite Updated (ml) ________

Completed: / /

Signature KCN Date Reviewed: / /

Signature KCN Date Total Pages Attached_______________

RJPM-NRC-D10-A8 Page 10 of 12

LIQUID PRE-RELEASE PERMIT REPORT Permit 2010004 Number:

Release Point: 1 Radwaste System Release Mode: 2 Batch Status: P Pre-Release Comments:

= = PRE-RELEASE DATA = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =

=

Estimated start date / time ------------------------------------------------------------------- 08/31/10 10:20 Estimated end date / time -------------------------------------------------------------------- 08/31/10 17:35 Estimated release duration (minutes) ------------------------------------------------------------- 4.25E+02 Cooling Tower Blowdown flowrate (gpm) ------------------------------------------------------ 2.20E+03 Release volume (gal) -------------------------------------------------------------------------------- 1.70E+04 Release flowrate (gpm) ----------------------------------------------------------------------------- 4.00E+01 LWS-FV197 Control Setpoint (Max.) (gpm) ------------------------------------------------------------ 40 Diluted Pre-release ECL Fraction (<1.0) --------------------------------------------------------- 3.41E-02 RMS-RE107 Operable? ----------------------------------------------------------------------------- Operable Current Monitor Background (cpm) ------------------------------------------------------------- 3.47E+03 Lowest 10 Minute Trend Background (uCi/mL) ------------------------------------------------- 1.79E-06 Alarm Setpoint (uCi/mL) ---------------------------------------------------------------------------- 1.99E-03 Alert Setpoin (uCi/mL) ------------------------------------------------------------------------------ 1.79E-03 Channel-13 Background (cpm) -------------------------------------------------------------------- 3.35E+03 Tank ------------------------------------------------------------------------------------------------------------- D Pump ------------------------------------------------------------------------------------------------------------ C Recirculation Start Date ------------------------------------------------------------------ 08/31/2010 07:35 Sample Date -------------------------------------------------------------------------------- 08/31/2010 10:00 RJPM-NRC-D10-A8 Page 11 of 12

LIQUID PRE-RELEASE PERMIT REPORT Permit 2010004 Number:

Release Point: 1 Radwaste System Release Mode: 2 Batch Status: P Pre-Release

= = = NUCLIDE DATA (INITIAL) = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =

Undiluted Ratio Ratio Diluted Ratio Ration Nuclide uCi/ml EC to EC to 10*EC uCi/ml to EC to 10*EC MN-54 3.07E-07 3.00E- 1.02E-02 1.02E-03 5.48E- 1.83E- 1.83E-05 05 09 04 CO-60 7.53E-07 3.00E- 2.51E-01 2.51E-02 1.34E- 4.48E- 4.48E-04 06 08 03 Gamma 1.06E-06 2.61E-01 2.61E-02 1.89E- 4.66E- 4.66E-04 08 03 H-3 1.87E-02 1.00E- 1.87E+01 1.87E+00 3.34E- 3.34E- 3.34E-02 03 04 01 FE-55 6.04E-06 1.00E- 6.04E-02 6.04E-03 1.08E- 1.08E- 1.08E-04 04 07 03 Beta 1.87E-02 1.88E+01 1.88E+00 3.34E- 3.35E- 3.35E-02 04 01 XE-135 1.29E-05 2.00E- 6.45E-02 6.45E-03 2.30E- 1.15E- 1.15E-04 04 07 03 XE-133 3.46E-06 2.00E- 1.73E-02 1.73E-03 6.18E- 3.09E- 3.09E-05 04 08 04 O&EG 1.64E-05 8.18E-02 8.18E-03 2.92E- 1.46E- 1.46E-04 07 03 Total 1.87E-02 1.91E+01 1.91E+00 3.34E- 3.41E- 3.41E-02 04 01 RJPM-NRC-D10-A8 Page 12 of 12

Number: *RJPM-NRC-D10-A9 RIVER Revision: 0 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

DETERMINE PROTECTIVE ACTION RECOMMENDATIONS REASON FOR REVISION:

2010 NRC Exam JPM - A9 PREPARE / REVIEW:

John Hegdepeth 0069 8/31/2010 Preparer KCN Date Angie Orgeron 1538 8/31/2010 Technical Review (SME) KCN Date Alfonso Croeze 0597 9/9/2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-A9 TASK DESCRIPTION: Determine Protective Action Recommendations TASK

REFERENCE:

301016005003 K/A REFERENCE & RATING: 2.4.44 4.4 TESTING METHOD: Simulate Actual Performance Performance X Control Room Simulator Classroom X COMPLETION TIME: 15 min.

MAX TIME: 15 min JOB LEVEL: SRO TIME CRITICAL: Yes EIP CLASSIFICATION No REQUIRED:

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

RJPM-NRC-D10-A9 Page 2 of 10

RJPM-NRC-D10-A9 SIMULATOR SETUP SHEET Task

Description:

Determine Protective Action Recommendations.

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

RJPM-NRC-D10-A9 Page 3 of 10

RJPM-NRC-D10-A9 DATA SHEET References for Development: EIP-2-007, Protective Action Recommendation Guidelines Required Materials: EIP-2-007, Protective Action Recommendation Guidelines Required Plant Condition: N/A Task Standard: An upgraded Protective Action Recommendation has been issued within 15 minutes Applicable Objectives: EP-42.12, Obj. 11 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-NRC-D10-A9 Page 4 of 10

RJPM-NRC-D10-A9 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 loss of offsite power. Div III D/G did not start. RCIC tripped on over speed. Main steam tunnel temperature is above 200 deg. F. The Main plant exhaust activity level has been reading greater than the General Emergency level for 15 minutes.

Initiating Cue:

As acting Recovery Manager, dose projections and meteorological information were just handed to you. Complete a Notification of General Emergency short form and make Protective Action Recommendations.

THIS IS A TIME CRITICAL JPM RJPM-NRC-D10-A9

Denotes Critical Step Page 5 of 10

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

RJPM-NRC-D10-A9 PERFORMANCE STEP STANDARD S/U COMMENTS CUE: When requested, provide a Use (EIP-2-007) Attachments 1, 2, Start Time begins when the JPM Task Conditions copy of EIP-2-007 to candidate.

and 3 to formulate Protective Action / Cues is handed to the candidate Recommendations (PARs).

START TIME: ___________________

1. Candidate requested copy of EIP-2-007, Protective Action Recommendations.

Determines PARs are required. Candidate determined that a PAR is required

2. using Attachment 2, PAR Flowchart Block 1.

Protective Action Recommendations Candidate completed GE Short Form that Current Date/Time and Message must be developed within 15 minutes matches answer key using Attachment 3 Block Number are not required for of receipt of data. 1 and dose assessment and meteorological Satisfactory performance. This data. information is computer

3. generated.

TERMINATION TIME: _____________

Must be completed in 15 minutes or less Time to complete: ___________________

Terminating Cue: Notification of General Emergency short form completed.

RJPM-NRC-D10-A9

Denotes Critical Step Page 6 of 10

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

RJPM-NRC-D10-A9 ANSWER KEY PAR BLOCK # _____1___________________

Notification of General Emergency Time/Date: Current time / date Message:

This is River Bend Station A General Emergency was declared at Declaratio on Declaratio for n time n date AG 1-2 VALID reading on one or more radiation monitors in Table R1 that exceeds or is expected to exceed GENERAL EMERGENCY reading for greater than or equal to 15 minutes Wind from ___330___ Deg. At ___2.1___ MPH No Release PAR Reference Scenario No.: 5 Release BELOW federally approved operating limits Release ABOVE federally approved operating limits Authorized by:

Title:

RJPM-NRC-D10-A9 Page 7 of 10

RJPM-NRC-D10-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-NRC-D10-A9 Page 8 of 10

RJPM-NRC-D10-A9 JPM Task Conditions/Cues (Operator Copy)

The plant has experienced a loss of offsite power. Div III D/G did not Initial Conditions:

start. RCIC tripped on over speed. Main steam tunnel temperature is above 200 deg. F. The Main plant exhaust activity level has been reading greater than the General Emergency level for 15 minutes.

Initiating Cues: As acting Recovery Manager, dose projections and meteorological information were just handed to you. Complete a Notification of General Emergency short form and make Protective Action Recommendations.

THIS IS A TIME CRITICAL JPM DOSE ASSESSMENT for Emergency Containment Venting DOSE RATE CALCULATIONS TEDE Dose (REM): CDE Dose (REM) Thyroid:

Site Boundary 3.95E1 Site Boundary 6.02E-1 2 Miles 6.49E0 2 Miles 1.06E-1 5 Miles 9.08E-1 5 Miles 2.44E-2 10 Miles 2.02E-1 10 Miles 7.55E-3 Meteorological Data Wind Speed 2.1 mph Wind Direction 330 deg.

Delta T -0.8oF Stability Class D RJPM-NRC-D10-A9 Page 9 of 10

RJPM-NRC-D10-A9 JPM Task Conditions/Cues (Operator Copy)

PAR BLOCK # ________________________

Notification of General Emergency Time/Date: Current time / date Message:

This is River Bend Station A General Emergency was declared at Declaratio on Declaratio for n time n date AG 1-2 VALID reading on one or more radiation monitors in Table R1 that exceeds or is expected to exceed GENERAL EMERGENCY reading for greater than or equal to 15 minutes 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-NRC-D10-A9 Page 10 of 10

Number: *RJPM-NRC-D10-C1 RIVER Revision: 00 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

Defeat RWCU Level 2 and SLC Isolation Interlocks REASON FOR REVISION:

D 2010 NRC Exam JPM C1 PREPARE / REVIEW:

John Hedgepeth 0069 8-24-2010 Preparer KCN Date Angie Orgeron 1538 9-14-2010 Technical Review (SME) KCN Date Alfonso Croeze 0597 9-14-2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-C1 TASK DESCRIPTION: Defeat RWCU Level 2 and SLC Isolation Interlocks TASK

REFERENCE:

200087005001 K/A REFERENCE & RATING: 223002 A4.03 3.6 / 3.5 TESTING METHOD: Simulate Actual X

Performance 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 5 RJPM-NRC-D10-C1 Page 2 of 10

RJPM-NRC-D10-C1 SIMULATOR SETUP SHEET Task

Description:

Required Power:

IC No.:

Notes: NONE: This JPM is performed in the control room.

RJPM-NRC-D10-C1 Page 3 of 10

RJPM-NRC-D10-C1 DATA SHEET References for Development: EOP-005 ENCLOSURE 4 Required Materials: EOP-005 ENCLOSURE 4 Required Plant Condition: ANY Task Standard All four jumper locations identified.

Applicable Objectives: HLO-516, Obj. 1 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-NRC-D10-C1 Page 4 of 10

RJPM-NRC-D10-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, 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 in an ATWS condition and the turbine has tripped. Reactor pressure is not stable.

Initiating Cue: The CRS has directed you to install EOP-005 Enclosure 4 to defeat RWCU level 2 and SLC isolations.

RJPM-NRC-D10-C1

Denotes Critical Step Page 5 of 10

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

RJPM-NRC-D10-C1 PERFORMANCE STEP STANDARD S/U COMMENTS 3.1 Jumper kit No. 4 obtained from the Control Room OBTAIN EOP-0005 ENCL 4 jumper Emergency Locker

1.

kit from the Control Room Emergency Locker.

3.1.1 Inspected for four jumpers CUE: Inform the candidate that the

2. four jumpers are obtained.

INSPECT kit for 4 jumpers 3.2 N/A

3. DEFEAT the SLC Pump A isolation interlock as follows:

3.2.1 Located TB0033 in P623 TB0033 is in H13-P623 right side Location: H13-P623 of panel, 1st column of terminal

4. boards from panel door, 3rd Affected Terminal Board: TB0033 terminal board from top.

3.2.1.1 Terminal 1 on TB0033 and Terminal 2 on CUE: Inform the candidate that the TB0033 properly identified for jumper placement Jumper No. 1 jumper is installed.

5.

JUMPER Terminal 1 on TB0033 to Terminal 2 on TB0033 3.3 N/A 6 DEFEAT the SLC Pump B isolation interlock as follows:

RJPM-NRC-D10-C1

Denotes Critical Step Page 6 of 10

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

RJPM-NRC-D10-C1 PERFORMANCE STEP STANDARD S/U COMMENTS 3.3.1 Located TB0030 in P622 TB0030 is in H13-P622 right side Location: H13-P622 of panel, 2nd column of terminal 7 boards from the panel door, 6th Affected Terminal Board: TB0030 terminal board from top.

3.3.1.1 Terminal 1 on TB0030 and Terminal 2 on CUE: Inform the candidate that the TB0030 properly identified for jumper Jumper No. 2 jumper is installed.

8 placement.

JUMPER Terminal 1 on TB0030 to Terminal 2 on TB0030 3.4 N/A 9 DEFEAT the RWCU RPV Water Level 2 isolation interlocks as follows:

3.4.1 Located TB0023 in P691 Bay A Right side of bay, 2nd column of 10 Location: H13-P691 Bay A Affected terminal boards from bay door, 3rd Terminal Board: TB0023 terminal board from top 3.4.1.1 Terminal 12 on TB0023 and Terminal 13 on CUE: Inform the candidate that the TB0023 properly identified for jumper Jumper No. 3 jumper is installed.

11 placement.

JUMPER Terminal 12 on TB0023 to Terminal 13 on TB0023 3.4.2 Located TB0014 in P692 Bay A Right side of bay, 2nd column of 12 Location: H13-P692 Bay A Affected terminal boards from bay door, 6th Terminal Board: TB0014 terminal board from top RJPM-NRC-D10-C1

Denotes Critical Step Page 7 of 10

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

RJPM-NRC-D10-C1 PERFORMANCE STEP STANDARD S/U COMMENTS 3.4.2.1 Terminal 10 on TB0014 and Terminal 11 on CUE: Inform the candidate that the TB0014 properly identified for jumper Jumper No. 4 jumper is installed.

13 placement.

JUMPER Terminal 10 on TB0014 to Terminal 11 on TB0014 3.5 Requested direction from the CRS CUE: Inform the candidate that 14 Return RWCU to service as directed another operator will return by the CRS RWCU to service.

Terminating Cue: Four jumpers installed per EOP-005 enclosure #4 RJPM-NRC-D10-C1

Denotes Critical Step Page 8 of 10

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

RJPM-NRC-D10-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-NRC-D10-C1 Page 9 of 10

RJPM-NRC-D10-C1 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is in an ATWS condition and the turbine has tripped. Reactor pressure is not stable.

Initiating Cues: The CRS has directed you to install EOP-005 Enclosure 4 to defeat RWCU level 2 and SLC isolations.

RJPM-NRC-D10-C1 Page 10 of 10

Number: *RJPM-NRC-D10-C2 RIVER Revision: 00 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

Stuck open SRV fuse removal, SRV B21-F051B REASON FOR REVISION:

D 2010 NRC Exam JPM C2 PREPARE / REVIEW:

John Hedgepeth 0069 8-24-2010 Preparer KCN Date Angie Orgeron 1538 9-14-2010 Technical Review (SME) KCN Date Scott Dallas 1385 9-14-2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-C2 TASK DESCRIPTION: Stuck open SRV fuse removal, SRV B21-F051B TASK

REFERENCE:

400059004001, 400061004001 K/A REFERENCE & RATING: 239002 K2.01 2.8/3.2 239002 K4.08 3.6/3.7 239002 K5.01 3.4/3.5 239002 A4.01 4.4/4.4 TESTING METHOD: Simulate Actual X

Performance 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 3 RJPM-NRC-D10-C2 Page 2 of 9

RJPM-NRC-D10-C2 SIMULATOR SETUP SHEET Task

Description:

Required Power:

IC No.:

Notes: NONE: This JPM is performed in the control room.

RJPM-NRC-D10-C2 Page 3 of 9

RJPM-NRC-D10-C2 DATA SHEET References for Development: AOP-0035, Safety Relief Valve Stuck Open Required Materials: AOP-0035 Attachment 1, Safety Relief Valves Solenoid Circuit Fuses.

Required Plant Condition: ANY Task Standard Fuses required to be removed have been properly identified.

Applicable Objectives: RLP-OPS-AOP035 OBJ 7 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-NRC-D10-C2 Page 4 of 9

RJPM-NRC-D10-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:

SRV B21-F051B has opened.

Reactor pressure is normal

Immediate operator actions for AOP-0035 have been completed.

Reactor power is steady at 89%.

Attempts to close B21-RV-F051B from panels H13-P601 and H13-P631 have been unsuccessful.

Initiating Cue:

The CRS has directed you to deenergize the solenoids of SRV B21-RV-F051B, by pulling the applicable fuses listed in Attachment 1, Safety Relief Valves Solenoid Circuit Fuses of AOP-0035.

RJPM-NRC-D10-C2

Denotes Critical Step Page 5 of 9

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

RJPM-NRC-D10-C2 PERFORMANCE STEP STANDARD S/U COMMENTS 5.6 N/A IF the SRV is still open, THEN

1. deenergize the solenoids by pulling the applicable fuses listed in Attachment 1, Safety Relief Valves Solenoid Circuit Fuses.

5.6 Panel P628 Bay A has been properly located. H13-P628 Bay A, is located south

2. end control room, west side.

Locate H13-P628 Bay A 5.6 Fuse B21C-F81A has been properly identified for CUE: Inform the candidate that

3. Remove fuse B21C-F81A on fuse removal. the fuse has been removed.

block 9H13 5.6 Fuse B21C-F82A has been properly identified for CUE: Inform the candidate that removal. the fuse has been removed.

Remove fuse B21C-F82A on fuse block 9H14 If requested, after the fuses have

4. been removed, The ATC operator reports SRV B21-F051B is still open.

5.6 Panel P631 Bay A has been properly located. H13-P631 Bay A, is located south

5. end control room, east side.

Locate H13-P631 Bay A 5.6 Fuse B21C-F81B has been properly identified for CUE: Inform the candidate that removal.

6 Remove fuse B21C-F81B on fuse the fuse has been removed.

block 9H13 RJPM-NRC-D10-C2

Denotes Critical Step Page 6 of 9

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

RJPM-NRC-D10-C2 PERFORMANCE STEP STANDARD S/U COMMENTS 5.6 Fuse B21C-F82B has been properly identified for CUE: Inform the candidate that removal.

Remove fuse B21C-F82B on fuse the fuse has been removed.

block 9H14

7 If requested after the fuses have been removed, The ATC operator announces SRV B21-F051B has closed.

Terminating Cue: Four fuses for SRV B21-F051B removed per AOP-0035 RJPM-NRC-D10-C2

Denotes Critical Step Page 7 of 9

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

RJPM-NRC-D10-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-NRC-D10-C2 Page 8 of 9

RJPM-NRC-D10-C2 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: SRV B21-F051B has opened.

Reactor pressure is normal

Immediate operator actions for AOP-0035 have been completed.

Reactor power is steady at 89%.

Attempts to close B21-RV-F051B from panels H13-P601 and H13-P631 have been unsuccessful.

Initiating Cues: The CRS has directed you to deenergize the solenoids of SRV B21-RV-F051B, by pulling the applicable fuses listed in Attachment 1, Safety Relief Valves Solenoid Circuit Fuses of AOP-0035.

RJPM-NRC-D10-C2 Page 9 of 9

Number: *RJPM-NRC-D10-P1 RIVER Revision: 00 BEND STATION Page 1 of 8 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

LINE UP FIRE WATER PROTECTION SYSTEM FOR RPV INJECTION REASON FOR REVISION:

D 2010 NRC Exam JPM P1 PREPARE / REVIEW:

John Hedgepeth 0069 8-24-2010 Preparer KCN Date Angie Orgeron 1538 9-14-2010 Technical Review (SME) KCN Date Alfonso Croeze 0597 9-14-2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-P1 TASK DESCRIPTION: LINE UP FIRE WATER PROTECTION SYSTEM FOR RPV INJECTION EOP-005 ENCLOSURE 7 TASK

REFERENCE:

286001005004 K/A REFERENCE & RATING: 286000 K1.03 2.9 / 3.0 TESTING METHOD: Simulate Actual X

Performance Performance Control Simulator In-Plant x Room 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 8 RJPM-NRC-D10-P1 Page 2 of 8

RJPM-NRC-D10-P1 SIMULATOR SETUP SHEET Task

Description:

Required Power:

IC No.:

Notes: NONE: This JPM is performed in the plant.

RJPM-NRC-D10-P1 Page 3 of 8

RJPM-NRC-D10-P1 DATA SHEET References for Development: EOP-005 Enclosure 7 Required Materials: EOP-005 Enclosure 7 Required Plant Condition: ANY Task Standard Simulated opening the four required valves to inject with fire water.

Applicable Objectives: HLO-516 Objective 1 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-NRC-D10-P1 Page 4 of 8

RJPM-NRC-D10-P1 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:

While operating at 100 percent power the plant has experienced a scram. RCIC and HPCS have tripped, and efforts are in progress to restore RCIC. The diesel-powered fire water pumps are running. RHR A is in suppression pool cooling and RHR B is secured.

Initiating Cue:

The CRS has directed you to perform EOP-005 Enclosure 7 INJECTION INTO RPV WITH FIRE SYSTEM step 3.6 for the Fuel Building and Auxiliary Building ONLY.

RJPM-NRC-D10-P1

Denotes Critical Step Page 5 of 8

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

RJPM-NRC-D10-P1 PERFORMANCE STEP STANDARD S/U COMMENTS 3.6 N/A

1. OPEN (UNLOCK if necessary) the following Fire Protection/Service Water Inlet Valves.

(Fuel Bldg EL 74 ft. SW corner each side of Check Valve SWP-V973) 3.6.1 Opened FPW-V396 by turning the handwheel in CUE: Valve motion has stopped at FPW-V396, ISOLATION VALVE the counterclockwise direction until valve motion the open backseat and the valve

2.

FOR SWP BACKUP TO FUEL stopped. stem is fully extended.

BLDG HOSE RACKS 3.6.2 Unlocked and opened SWP-V971 by turning the CUE: Valve motion has stopped at

3. SWP-V971, DIV 2 STBY SWP TO handwheel in the counterclockwise direction until the open backseat and the valve FUEL BLDG FIRE PROT ISOL VLV valve motion stopped. stem is fully extended.

(Aux. Bldg EL 100 ft. crescent area NE corner each side of Check Valve SWP-V964) 3.6.1 Opened FPW-V321 by turning the handwheel in CUE: Valve motion has stopped at FPW-V321, SWP BACKUP TO RB the counterclockwise direction until valve motion the open backseat and the valve

4.

AND AUX BLDG HOSE RACKS stopped. stem is fully extended.

ISOLATION VALVE 3.6.2 Unlocked and opened SWP-V968 by turning the CUE: Valve motion has stopped at handwheel in the counterclockwise direction until

5. SWP-V968, SVCE WTR TO FIRE the open backseat and the valve valve motion stopped. stem is fully extended..

PROTECTION MAN ISOL VLV Terminating Cue: Four FPW to SWP valves have been opened per EOP-005 Enclosure 7 RJPM-NRC-D10-P1

Denotes Critical Step Page 6 of 8

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

RJPM-NRC-D10-P1 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-NRC-D10-P1 Page 7 of 8

RJPM-NRC-D10-P1 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: While operating at 100 percent power the plant has experienced a scram.

RCIC and HPCS have tripped, and efforts are in progress to restore RCIC. The diesel-powered fire water pumps are running. RHR A is in suppression pool cooling and RHR B is secured.

Initiating Cues: The CRS has directed you to perform EOP-005 Enclosure 7 INJECTION INTO RPV WITH FIRE SYSTEM step 3.6 for the Fuel Building and Auxiliary Building ONLY.

RJPM-NRC-D10-P1 Page 8 of 8

Number: *RJPM-NRC-D10-P2 RIVER Revision: 00 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

Restore RPS B Normal Power Supply REASON FOR REVISION:

D 2010 NRC Exam JPM P2 PREPARE / REVIEW:

John Hedgepeth 0069 8-24-2010 Preparer KCN Date Angie Orgeron 1538 9-14-2010 Technical Review (SME) KCN Date Alfonso Croeze 0597 9-14-2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-P2 TASK DESCRIPTION: Restore RPS B Normal Power Supply TASK

REFERENCE:

212004001004 K/A REFERENCE & RATING: 212000 K1.04, 3.4/3.6 212000 K2.01, 3.2/3.3 212000 A1.01, 2.8/2.9 212000 A2.01, 3.7/3.9 TESTING METHOD: Simulate Actual X

Performance Performance Control Simulator In-Plant X 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 Yes (FAULTED):

SAFETY FUNCTION 7 RJPM-NRC-D10-P2 Page 2 of 9

RJPM-NRC-D10-P2 SIMULATOR SETUP SHEET Task

Description:

Required Power:

IC No.:

Notes: NONE: This JPM is performed in the plant.

RJPM-NRC-D10-P2 Page 3 of 9

RJPM-NRC-D10-P2 DATA SHEET References for Development: SOP-0079, Reactor Protection System Required Materials: SOP-0079, Reactor Protection System Section 5.3 Required Plant Condition: Any Task Standard RPS M/G set running at rated voltage Applicable Objectives: RLP-STM-0508 OBJ 3f 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-NRC-D10-P2 Page 4 of 9

RJPM-NRC-D10-P2 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 at 100% power. Electrical maintenance has completed work on the RPS B MG set generator output breaker. RPS B Bus is being supplied from the Alternate Power Supply.

Initiating Cue:

The CRS has directed you to restore the B RPS MG set and close the appropriate breakers to make RPS Bus B ready to transfer to the Normal Supply, in accordance with SOP-0079, Reactor Protection System.

RJPM-NRC-D10-P2

Denotes Critical Step Page 5 of 9

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

RJPM-NRC-D10-P2 PERFORMANCE STEP STANDARD S/U COMMENTS 5.3.1.1 Closed NHS-MCC10B Breaker 1C by moving CUE: Breaker BKR 1C is closed.

At NHS-MCC10B, close BKR 1C, handle all the way to left.

1.

REACTOR PROT SYSTEM MOTOR GENERATOR SET 5.3.1.2.1 MOTOR ON pushbutton depressed as motor CUE: MG status lights above At MG Set Panel C71-S001B, depress generator comes up to proper voltage. motor control pushbuttons are the MOTOR ON pushbutton while

2. Green light OFF Red light ON observing the Motor Generator Set output voltmeter AND Generator Output voltage is rising.

5.3.1.2.2 Verify Motor Generator Set output voltmeter CUE: 15 minutes have elapsed IF the Motor Generator Set output stabilizes at 123.5 volts. and MG Set output voltmeter voltmeter does not increase to and indicates less than123.5 volts.

3. stabilize at >123.5 volts 5.3.1.2.2 ALTERNATE PATH MOTOR ON pushbutton depressed to reset the CUE: MG Set output voltmeter THEN depress the Motor Generator over excitation trip and allow the Motor indicates 125 volts.

4. Set MOTOR ON pushbutton to reset Generator Set to self-excite.

the over excitation trip and allow the Motor Generator Set to self-excite.

5.3.1.3 Generator Output Breaker on C71-S001B closed CUE: Generator Output Breaker by moving it to the upper position.

WHEN the MG Set output voltmeter is Closed.

5.

is 123.5 volts, THEN at C71-S001B, close the Generator Output Breaker.

RJPM-NRC-D10-P2

Denotes Critical Step Page 6 of 9

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

RJPM-NRC-D10-P2 PERFORMANCE STEP STANDARD S/U COMMENTS 5.3.1.4 EPA Breaker C71-S003B closed by rotating CUE: EPA Breaker C71-S003B breaker lever to the ON (fully counter-clockwise) EPA OUTPUT red light ON:

Close C71-S003B, MG SET LOAD position

6. BREAKER POWER SUPPLY OUTPUT -

Red light ON 5.3.1.5 EPA Breaker C71-S003D closed by rotating CUE: EPA Breaker C71-S003D breaker lever to the ON (fully counter-clockwise)

Close C71-S003D, RPS BUS B EPA OUTPUT red light ON position

7. NORMAL SUPPLY Breaker.

EPA INPUT - Red light ON 5.3.1.6 Verified targets on EPA breakers C71-S003B and CUE: All targets on EPA D are reset

8. Verify targets are reset on all EPA Breakers are reset.

breakers Terminating Cue: RPS MG Set B running with power available to transfer RPS B Bus to the Normal Supply.

RJPM-NRC-D10-P2

Denotes Critical Step Page 7 of 9

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

RJPM-NRC-D10-P2 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-NRC-D10-P2 Page 8 of 9

RJPM-NRC-D10-P2 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is at 100% power. Electrical maintenance has completed work on the RPS B MG set generator output breaker. RPS B Bus is being supplied from the Alternate Power Supply.

Initiating Cues: The CRS has directed you to restore the B RPS MG set and close the appropriate breakers to make RPS Bus B ready to transfer to the Normal Supply, in accordance with SOP-0079, Reactor Protection System.

RJPM-NRC-D10-P2 Page 9 of 9

Number: *RJPM-NRC-D10-P3 RIVER Revision: 00 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

MANUALLY STARTUP RHR B IN SUPPRESSION POOL COOLING FROM THE REMOTE SHUTDOWN PANEL REASON FOR REVISION:

D 2010 NRC Exam JPM P3 PREPARE / REVIEW:

John Hedgepeth 0069 8-24-2010 Preparer KCN Date Angie Orgeron 1538 9-9-2010 Technical Review (SME) KCN Date Alfonso Croeze 0597 9-9-2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-P3 TASK DESCRIPTION: Manually Startup RHR B in Suppression Pool Cooling from the Remote Shutdown Panel TASK

REFERENCE:

400075004001 K/A REFERENCE & RATING: 219000 K1.01, 3.8/3.9 K3.01, 3.9/4.1 K6.06, 3.7/3.7 A1.01, 4.0/4.0 A1.02, 3.5/3.5 A1.08, 3.7/3.6 A4.01, 3.8/3.7 A4.02, 3.7/3.5 A4.07, 3.5/3.4 295016 AK2.01, 4.4/4.5 AK2.02, 4.0/4.1 AA1.07, 4.2/4.3 AA2.04, 3.9/4.1 AA2.07, 3.2/3.4 TESTING METHOD: Simulate Actual X

Performance Performance Control Simulator In-Plant X Room COMPLETION TIME: 12 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: 5 RJPM-NRC-D10-P3 Page 2 of 9

RJPM-NRC-D10-P3 SIMULATOR SETUP SHEET Task

Description:

Required Power:

IC No.:

Notes: NONE: This JPM is performed in the plant.

RJPM-NRC-D10-P3 Page 3 of 9

RJPM-NRC-D10-P3 DATA SHEET References for Development: AOP-0031, Shutdown From Outside the Main Control Room Required Materials: AOP-0031, Shutdown From Outside the Main Control Room, Step 5.15 Required Plant Condition: Any Task Standard Simulated placing RHR B in the suppression pool cooling mode from RSS-PNL102 Applicable Objectives: RLP-OPS-AOP031, Obj. 4 and 6 RLP-OPS-0200, Obj. 3, 11 and 12 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-NRC-D10-P3 Page 4 of 9

RJPM-NRC-D10-P3 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 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. Reactor pressure is under control with SRVs.

Initiating Cue:

The CRS has directed you to place RHR B in Suppression Pool Cooling using AOP-0031, Shutdown From Outside the Main Control Room, Step 5.15. Standby Service water pumps B and D are in service.

RJPM-NRC-D10-P3

Denotes Critical Step Page 5 of 9

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

RJPM-NRC-D10-P3 PERFORMANCE STEP [SOP/ARP Step] STANDARD S/U COMMENTS 5.15.1 N/A CUE: RHR Heat Exchangers are Verify the RHR Heat Exchangers are being supplied by Standby Service 1.

being supplied by either Normal or Water per cue sheet.

Standby Service Water 5.15.2 E12-F068B, RHR HX A SVCE WTR RTN CUE: RHR B HX flow is 5500 throttled open. gpm Throttle E12-F068B, RHR HX B RED light ON

2. SVCE WTR RTN open to establish GREEN light ON required flow not to exceed 5800 gpm as indicated on SWP-FI64B, SSW RHR HX B FLOW.

5.15.3 E12-C002B, RHR PUMP B has been started.

CUE: RED light ON

3. Start E12-C002B, RHR PUMP B and perform the following: GREEN light OFF 5.15.3.1 Control switch for E12-F024B, RHR PUMP B CUE: RED light ON TEST RTN TO SUP PL placed in the open Open E12-F024B, RHR PUMP B GREEN light OFF

4. position.

TEST RTN TO SUP PL.

5.15.3.2 At ENS-SWG01B, pump running amps verified CUE: RHR B running amps are less than or equal to 91 amps At ENS-SWG01B, check pump 80 amps 5.

running amps are less than or equal to 91 amps RJPM-NRC-D10-P3

Denotes Critical Step Page 6 of 9

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

RJPM-NRC-D10-P3 PERFORMANCE STEP [SOP/ARP Step] STANDARD S/U COMMENTS 5.15.4 CUE: Inform the candidate that N/A Perform the following: this step will be completed by a

1. On EHS-MCC2E open the building operator.

following breakers:

Bkr 6A, E12-F073A HEAT EXCH A VENT SUPPR POOL VALVE Inform the candidate that step

6.

Bkr 6B, E12-F074A HEAT EXCH 5.15.4 is complete.

A VENT SUPPR POOL VALVE

2. Verify the following valves are closed:

1) In AUX Bldg 95 NW crescent area, E12-MOVF073A, RHR A HX DN STREAM VENT VALVE 5.15.5 E12-F064B, RHR PUMP B MIN FLOW TO SUP CUE: RHR flow is greater than PL verified closed. 1100 gpm

7. WHEN RHR flow exceeds 1100 gpm, RED light OFF THEN close E12-F064B, RHR PUMP GREEN light ON B MIN FLOW TO SUP PL.

Throttle E12-F048B, RHR HX B Control switch for E12-F048B, RHR HX B CUE: RED light OFF

8. BYPASS VALVE closed to obtain the BYPASS VALVE placed in the closed position.

GREEN light ON desired cooling.

Record data on Attachment 3, CUE: Another operator is Suppression Pool Water recording Data 8.

Temperature/Level Data Terminating Cue: .RHR B is in Suppression Pool Cooling per AOP-0031, Shutdown From Outside the Main Control Room, Step 5.15 RJPM-NRC-D10-P3

Denotes Critical Step Page 7 of 9

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

RJPM-NRC-D10-P3 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-NRC-D10-P3 Page 8 of 9

RJPM-NRC-D10-P3 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. Reactor pressure is under control with SRVs.

Initiating Cues: The CRS has directed you to place RHR B in Suppression Pool Cooling using AOP-0031, Shutdown From Outside the Main Control Room, Step 5.15. Standby Service water pumps B and D are in service.

RJPM-NRC-D10-P3 Page 9 of 9

Number: *RJPM-NRC-D10-S1 RIVER Revision: 00 BEND STATION Page 1 of 9 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

SHIFT STATOR COOLING WATER PUMPS REASON FOR REVISION:

D 2010 NRC Exam JPM S1 PREPARE / REVIEW:

John Hedgepeth 0069 8-24-2010 Preparer KCN Date Angie Orgeron 1538 9-8-2010 Technical Review (SME) KCN Date Tim Venable 0130 9-8-2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-S1 TASK DESCRIPTION: Shift stator cooling water pumps TASK

REFERENCE:

253010001001 K/A REFERENCE & RATING: 245000 A4.03 2.7 / 2.8 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 4 RJPM-NRC-D10-S1 Page 2 of 9

RJPM-NRC-D10-S1 SIMULATOR SETUP SHEET Task

Description:

Alternate Stator Cooling Water Pumps Required Power: Any IC No.: 177 Notes:

RJPM-NRC-D10-S1 Page 3 of 9

RJPM-NRC-D10-S1 DATA SHEET References for Development: SOP-020 Required Materials: SOP-020 Required Plant Condition: None Task Standard Returned to the previously running pump, following pump rotation due to out of spec parameters.

Applicable Objectives: RLP-STM-0123 Objective 3, 4 and 7 Safety Related Task: NO 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-NRC-D10-S1 Page 4 of 9

RJPM-NRC-D10-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, 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:

Stator Cooling Water Pump "A" is operating with normal system pressure and flow. The turbine building operator has verified that B Stator cooling water pump is ready to start.

Initiating Cue:

The CRS directs you to shift Stator Cooling Water pumps in accordance with SOP-020 section 5.2 RJPM-NRC-D10-S1

Denotes Critical Step Page 5 of 9

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

RJPM-NRC-D10-S1 PERFORMANCE STEP [SOP/ARP Step] STANDARD S/U COMMENTS 5.2.1 START pushbutton for GMC-SCPM-B depressed GMC-SCPM-B red light ON green light OFF

1. Depress idle GMC-SCPM-B, STATOR CLG WTR PUMP B START Pushbutton.

5.2.2 STOP pushbutton for GMC-SCPM-A depressed GMC-SCPM-A red light OFF green light ON

2. Depress previously running GMC-SCPM-A, STATOR CLG WTR PUMP A STOP Pushbutton.

5.2.3 STATOR COOLING WATER PRESS on GMC-PIEPR-15 determined to be less than 60 psig.

At H13-P870, observe pressure on GMC-PIEPR-15, STATOR

3. COOLING WATER PRESS. IF pressure does not stabilize at greater than 60 psig, THEN immediately return to original pump configuration.

5.2.1 ALTERNATE PATH START pushbutton for GMC-SCPM-A depressed GMC-SCPM-A red light ON green light OFF

4. Depress idle GMC-SCPM-A, STATOR CLG WTR PUMP A START Pushbutton.

RJPM-NRC-D10-S1

Denotes Critical Step Page 6 of 9

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

RJPM-NRC-D10-S1 PERFORMANCE STEP [SOP/ARP Step] STANDARD S/U COMMENTS STOP pushbutton for GMC-SCPM-B depressed 5.2.2 GMC-SCPM-B red light OFF green light ON

5. Depress previously running GMC-SCPM-B, STATOR CLG WTR PUMP B STOP Pushbutton.

Terminating Cue: Stator Cooling Water Pump "A" is operating with normal system pressure and flow.

RJPM-NRC-D10-S1

Denotes Critical Step Page 7 of 9

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

RJPM-NRC-D10-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-NRC-D10-S1 Page 8 of 9

RJPM-NRC-D10-S1 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: Stator Cooling Water Pump "A" is operating with normal system pressure and flow. The turbine building operator has verified that B Stator cooling water pump is ready to start.

Initiating Cues: The CRS directs you to shift Stator Cooling Water pumps in accordance with SOP-020 section 5.2 RJPM-NRC-D10-S1 Page 9 of 9

Number: *RJPM-NRC-D10-S2 RIVER Revision: 00 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

MANUALLY START LPCS - SUPPRESSION POOL TO SUPPRESSION POOL REASON FOR REVISION:

D 2010 NRC Exam JPM S2 PREPARE / REVIEW:

John Hedgepeth 0069 8-24-2010 Preparer KCN Date Angie Orgeron 1538 9-8-2010 Technical Review (SME) KCN Date Tim Venable 0130 9-8-2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-S2 TASK DESCRIPTION: Manually Start LPCS - Suppression Pool to Suppression Pool TASK

REFERENCE:

203007001001 K/A REFERENCE & RATING: 209001 A2.01 3.4/ 3.4 A3.01 3.6/ 3.6 A3.04 3.7/ 3.6 A4.01 3.8/ 3.6 A4.11 3.7/ 3.6 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: Yes ALTERNATE PATH Yes (FAULTED):

SAFETY FUNCTION 2 RJPM-NRC-D10-S2 Page 2 of 10

RJPM-NRC-D10-S2 SIMULATOR SETUP SHEET Task

Description:

Manually Start LPCS-Suppression Pool to Suppression Pool Required Power: Any IC No.: 245 Notes: LPCS pump will trip when flow increases to approximately 4000 GPM Build a trigger event with ADFLPCS .> 420 to a Trigger (420 #/sec = 3000 gpm)

Attach that Trigger to LPCS001(LPCS Pump Trip), no time delay or ramp RJPM-NRC-D10-S2 Page 3 of 10

RJPM-NRC-D10-S2 DATA SHEET References for Development: SOP-0032, Low Pressure Core Spray (Sys#205)

Required Materials: SOP-0032, Low Pressure Core Spray (Sys#205) section 4.2 Required Plant Condition: None Task Standard Started LPCS pump, responded to a pump trip and placed the system into standby lineup.

Applicable Objectives: RLP-STM-205 Obj #5 and 10 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-NRC-D10-S2 Page 4 of 10

RJPM-NRC-D10-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:

LPCS is in a normal Standby Lineup.

Initiating Cue:

The CRS has directed you to manually start the LPCS System @ 5000 gpm Suppression Pool to Suppression Pool, per SOP-0032 section 4.2, to place load on the diesel generator.

RJPM-NRC-D10-S2

Denotes Critical Step Page 5 of 10

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

RJPM-NRC-D10-S2 PERFORMANCE STEP STANDARD S/U COMMENTS 4.2.1 Cue: RP Notified

1. Notify Radiation Protection of impending system operation.

4.2.2 Pump breaker handle placed to the close position, Pump Running, red & white light only.

2. Start E21-C001, LPCS PUMP and perform the following.

4.2.2.1 Amps verified less than 157.

3. Check LPCS pump current is less than 157 amps as indicated on E21-C001, LPCS MOTOR AMPS.

4.2.2.2 Verified that E21-F011indicates full open, red light on

4. Verify E21-F011, LPCS MIN FLOW VLV TO SUPPRESSION POOL is open Verified Annunciator P601-19A-F07, DIV 1 4.2.2.3 ADS LOGIC LPCS/LPCI OPR PERMISSIVE alarms.

5. Check Annunciator P601-19A-F07, DIV 1 ADS LOGIC LPCS/LPCI OPR PERMISSIVE alarms.

RJPM-NRC-D10-S2

Denotes Critical Step Page 6 of 10

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

RJPM-NRC-D10-S2 PERFORMANCE STEP STANDARD S/U COMMENTS 4.2.3 Placed and held the control switch for, E21-F012, to OPEN, red light on, green light off

6. Open E21-F012, LPCS TEST RETURN VLV TO SUPPRESSION POOL 4.2.4 Verified that E21-F011, stroked full closed, Green light only

7. WHEN flow rises above 875 gpm, THEN verify E21-F011, LPCS MIN FLOW VLV TO SUPPRESSION POOL closes ALTERNATE PATH Implemented ARP-601-21-C08, SOP-0032 CUE: As CRS direct operator to Section 6 and Notifies CRS secure lineup per SOP-0032 Respond to the LPCS pump Trip by section 6.0.

8. referring to ARP-601-21-C08 and SOP-0032, Section 6. Allow time for candidate to review ARP for P601-21-C7 & C8 6.1 Verified normal reactor water level 9

Verify adequate core cooling is assured by two independent indications.

6.4.1 Placed the switch control for E21-F012 to CLOSE, red light off green light on

10 Close E21-F012, LPCS TEST RETURN VLV TO SUPPRESSION POOL RJPM-NRC-D10-S2

Denotes Critical Step Page 7 of 10

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

RJPM-NRC-D10-S2 PERFORMANCE STEP STANDARD S/U COMMENTS 4.2.1 Verified red light off green light on 11.

Verify Close E21-F005, LPCS INJECT ISOL VALVE.

6.5 Verified E21-F011, LPCS MIN FLOW VLV TO If Valve does not OPEN, Operator SUPPRESSION POOL opens, red light off ,green to take action per procedure

12. When flow losers below 875 gpm, light on.

then verify E21-F011, LPCS MIN FLOW VLV TO SUPPRESSION POOL opens 6.6 Verified E21-C002 running, red light only

13. If E21-C002, LPCS/RHR DIV I LINE FILL PUMP is not running, than start E21-C002 Terminating Cue: LPCS is shutdown per SOP-0032 RJPM-NRC-D10-S2

Denotes Critical Step Page 8 of 10

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

RJPM-NRC-D10-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-NRC-D10-S2 Page 9 of 10

RJPM-NRC-D10-S2 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: LPCS is in a normal Standby Lineup.

Initiating Cues: The CRS has directed you to manually start the LPCS System @ 5000 gpm Suppression Pool to Suppression Pool, per SOP-0032 section 4.2, to place load on the diesel generator.

RJPM-NRC-D10-S2 Page 10 of 10

Number: *RJPM-NRC-D10-S3 RIVER Revision: 00 BEND STATION Page 1 of 15 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

START DRYWELL LOW VOLUME PURGE REASON FOR REVISION:

D 2010 NRC Exam JPM S3 PREPARE / REVIEW:

John Hedgepeth 0069 8-24-2010 Preparer KCN Date Angie Orgeron 1538 9-8-2010 Technical Review (SME) KCN Date Scott Shultz 0176 9-8-2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-S3 TASK DESCRIPTION: Start Drywell Low Volume Purge per SOP-059 TASK

REFERENCE:

222015001001 K/A REFERENCE & RATING: 261000 A4.03 3.0 / 3.0 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 9 RJPM-NRC-D10-S3 Page 2 of 15

RJPM-NRC-D10-S3 SIMULATOR SETUP SHEET Task

Description:

Start Drywell Low Volume Purge per SOP-0059 Required Power: Mode 4 or 5 IC No.: 179 Notes: Set up an event trigger as follows:

ZDI2(437) != 0 DI_HVR-FN13 d 20 f stop RJPM-NRC-D10-S3 Page 3 of 15

RJPM-NRC-D10-S3 DATA SHEET References for Development: SOP-0059 Required Materials: SOP-0059 Required Plant Condition: Mode 4 or 5 Task Standard Low volume purge in service. Responded to the trip and placed high volume purge into service.

Applicable Objectives: RLP-STM-0403 Objective 2 and 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-NRC-D10-S3 Page 4 of 15

RJPM-NRC-D10-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: The plant is shutdown in Mode 4. The initial drywell entry will be performed on this shift. RP has requested the drywell to be purged for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to entry.

Initiating Cue: The CRS directs you to purge the drywell per SOP-0059 section 5.8. Steps 5.8.1 and 5.8.2 have been completed.

RJPM-NRC-D10-S3

Denotes Critical Step Page 5 of 15

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

RJPM-NRC-D10-S3 PERFORMANCE STEP STANDARD S/U COMMENTS NOTE: Steps 5.8.1 and 5.8.2 have been completed.

5.8.3 Verified

Verify the following dampers are open:

HVR-AOD164, UP STREAM HVR-AOD164 red light ON green light OFF ISOL SUPPLY

1.

HVR-AOD143, DN STREAM HVR-AOD143 red light ON green light OFF ISOL SUPPLY

HVR-AOD214, AUX/CONTMT HVR-AOD214 red light ON green light OFF BLDG EXH ISOL

HVR-AOD262, AUX/CONTMT HVR-AOD262 red light ON green light OFF BLDG EXH ISOL 5.8.4

HVR-AOV165 red light ON Open the following valves: green light OFF

HVR-AOV165, CONTMT SPLY

HVR-AOV123 red light ON OUTBD ISOL HVR-AOV165 control switch placed to open green light OFF

HVR-AOV123, CONTMT SPLY HVR-AOV123 control switch placed to open

HVR-AOV125 & 126 red INBD ISOL HVR-AOV125 & 126 control switch placed to lights ON green light OFF

HVR-AOV125 & 126, DW open

HVR-AOV147 & 148 red PURGE BACKUP ISOL lights ON green light OFF

2. HVR-AOV147 & 148 control switch placed to

HVR-AOV147 & 148, DW

HVR-AOV128 red light ON PURGE ISOL open green light OFF

HVR-AOV128, CONTMT RTN HVR-AOV128 control switch placed to open

HVR-AOV166 red light ON INBD ISOL green light OFF HVR-AOV166 control switch placed to open

HVR-AOV166, CONTMT RTN HVR-AOD225 control switch placed to open

HVR-AOD225 red light ON OUTBD ISOL green light OFF

HVR-AOD225, CONTMT/DW PURGE EXH ISOL RJPM-NRC-D10-S3

Denotes Critical Step Page 6 of 15

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

RJPM-NRC-D10-S3 PERFORMANCE STEP STANDARD S/U COMMENTS 5.8.5 Control switch for HVR-FN14 placed in the HVR-FN14 red light ON green Place HVR-FN14, CONTMT PURGE START position. light OFF FLT EXH FAN to START and verify the following:

HVR-AOD238, CONTMT PURGE HVR-AOD238 red light ON green

3. FLT SUCT opens. light OFF

HVR-AOD240, CONTMT FLT EXH FAN SUCT opens. HVR-AOD240 red light ON green light OFF 5.8.6 Control switch for HVR-FN13 placed in the HVR-FN13 red light ON green START position. light OFF Place HVR-FN13, LOW VOL

4. CONTMT PURGE to START and HVR-AOD236 red light ON green verify HVR-AOD236, LOW VOL FAN light OFF DISCH opens.

Report has been made to the CRS ALTERNATE PATH CUE: As the CRS, direct the candidate to secure the drywell Recognize and report the trip of HVR- low volume purge starting at step

5. FN14. 5.8.9 and start drywell high volume purge per SOP-059 section 5.7 using GTS-FN1A.

RJPM-NRC-D10-S3

Denotes Critical Step Page 7 of 15

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

RJPM-NRC-D10-S3 PERFORMANCE STEP STANDARD S/U COMMENTS 5.8.9 Control switch for HVR-FN14 placed in the HVR-FN14 red light OFF green STOP position. light ON Place HVR-FN14, CONTMT PURGE FLT EXH FAN to STOP and verify HVR-AOD238 red light OFF green

6. the following dampers close: light ON

HVR-AOD238, CONTMT PURGE FLT SUCT HVR-AOD240 red light OFF green

HVR-AOD240, CONTMT FLT light ON EXH FAN SUCT 5.8.10 Verified proper component alignment N/A NOTE Verify HVR-FN15, FLT6 DECAY Decay heat fan will not auto start HEAT REMOVAL starts and the due to the suction damper open for

7. following dampers open: less than 60 seconds.

HVR-AOD239, DECAY HEAT REMOVAL INTK

HVR-AOD241, DECAY HEAT REMOVAL DISCH RJPM-NRC-D10-S3

Denotes Critical Step Page 8 of 15

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

RJPM-NRC-D10-S3 PERFORMANCE STEP STANDARD S/U COMMENTS 5.8.11 HVR-AOV165 control switch placed to closed

HVR-AOV165 red light OFF Close the following valves: green light ON

HVR-AOV165, CONTMT SPLY HVR-AOV123 control switch placed to closed

HVR-AOV123 red light OFF OUTBD ISOL HVR-AOV125 & 126 control switch placed to green light ON

HVR-AOV123, CONTMT SPLY closed

HVR-AOV125 & 126 red light INBD ISOL OFF green light ON

HVR-AOV125 & 126, DW PURGE HVR-AOV147 & 148 control switch placed to

8. closed

HVR-AOV147 & 148 red light BACKUP ISOL OFF green light ON

HVR-AOV147 & 148, DW PURGE HVR-AOV128 control switch placed to closed

HVR-AOV128 red light OFF ISOL HVR-AOV166 control switch placed to closed green light ON

HVR-AOV128, CONTMT RTN

HVR-AOV166red light OFF INBD ISOL green light ON

HVR-AOV166, CONTMT RTN OUTBD ISOL 5.8.12 This step is N/A in mode 4 N/A Place administrative controls on the following control switches:

9.

HVR-AOV125 & 126, DW PURGE BACKUP ISOL

HVR-AOV147 & 148, DW PURGE ISOL RJPM-NRC-D10-S3

Denotes Critical Step Page 9 of 15

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

RJPM-NRC-D10-S3 PERFORMANCE STEP STANDARD S/U COMMENTS 5.8.13 This step is N/A in mode 4 N/A Close the following valves and install administrative controls:

HVR-AOV125-V1, DRYWELL SPLY OUTBD ISOL

10.

HVR-AOV126-V1, DRYWELL EXH AIR OUTBD ISOL

HVR-AOV147-V1, DRYWELL SPLY INBD ISOL

HVR-AOV148-V1, DRYWELL EXH AIR INBD ISOL 5.8.14 NOTE Step is N/A. N/A WHEN HVR-FN15, FLT6 DECAY HEAT REMOVAL has operated at Decay heat fan will not auto start least 30 minutes OR at the discretion due to the suction damper open for of the OSM/CRS, THEN place Filter less than 60 seconds.

Train Decay Heat Removal in standby by performing the following:

1. Place HVR-FN15, FLT6 DECAY HEAT REMOVAL in

11. STOP.

2. Verify HVR-AOD239, DECAY HEAT REMOVAL INTK closes.

3. Verify HVR-AOD241, DECAY HEAT REMOVAL DISCH closes.

4. Place HVR-FN15, FLT6 DECAY HEAT REMOVAL in AUTO.

RJPM-NRC-D10-S3

Denotes Critical Step Page 10 of 15

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

RJPM-NRC-D10-S3 PERFORMANCE STEP STANDARD S/U COMMENTS 5.8.15 HVR-AOD225 control switch has been placed to HVR-AOD225 green light ON red

12. Close HVR-AOD225, CONTMT/DW the closed position light OFF.

PURGE EXH ISOL.

5.7.1 This step is N/A in mode 4 N/A Release administrative controls and open the following valves:

HVR-AOV125-V1, DRYWELL SPLY OUTBD ISOL 13

HVR-AOV126-V1, DRYWELL EXH AIR OUTBD ISOL

HVR-AOV147-V1, DRYWELL SPLY INBD ISOL

HVR-AOV148-V1, DRYWELL EXH AIR INBD ISOL 5.7.2 This step is N/A in mode 4. N/A Release administrative controls on the following control switches:

14

HVR-AOV125 & 126, DW PURGE BACKUP ISOL

HVR-AOV147 & 148, DW PURGE ISOL 5.7.3 Verified proper component alignment HVR-AOD164 red light ON green Verify the following dampers are open:

light OFF

HVR-AOD164, UP STREAM ISOL 15 SUPPLY

HVR-AOD143, DN STREAM HVR-AOD143 red light ON green ISOL SUPPLY light OFF RJPM-NRC-D10-S3

Denotes Critical Step Page 11 of 15

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

RJPM-NRC-D10-S3 PERFORMANCE STEP STANDARD S/U COMMENTS 5.7.4 HVR-AOV165 control switch placed to open

HVR-AOV165 red light ON Open the following dampers and valves: green light OFF

HVR-AOV165, CONTMT SPLY HVR-AOV123 control switch placed to open

HVR-AOV123 red light ON OUTBD ISOL HVR-AOV125 & 126 control switch placed to green light OFF

HVR-AOV123, CONTMT SPLY open

HVR-AOV125 & 126 red light INBD ISOL ON green light OFF

HVR-AOV125 & 126, DW PURGE HVR-AOV147 & 148 control switch placed to open

HVR-AOV147 & 148 red light BACKUP ISOL ON green light OFF

HVR-AOV147 & 148, DW PURGE HVR-AOV128 control switch placed to open

16

HVR-AOV128 red light ON ISOL HVR-AOV166 control switch placed to open green light OFF

HVR-AOV128, CONTMT RTN

HVR-AOV166 red light ON INBD ISOL HVR-AOD245 control switch placed to open green light OFF

HVR-AOV166, CONTMT RTN OUTBD ISOL HVR-AOD162 control switch placed to open.

HVR-AOD245 red light ON

HVR-AOD245, CONTMT PURGE green light OFF TO SGT

HVR-AOD162 red light ON

HVR-AOD162, CONTMT PURGE green light OFF TO SGT 5.7.5 Start pushbutton has been depressed and held GTS-AOD1A red light ON green Start GTS-FN1A, SGT EXH FAN A by until HVR-AOD1A has fully opened and the GTS light OFF depressing the START Pushbutton and verify the following: fan has started.

1. GTS-AOD1A, SGT FILTER A GTS-FN1A red light ON green

17 SUCT ISOL opens. light OFF

2. GTS-FN1A, SGT EXH FAN A) starts. GTS-AOD3A red light ON green

3. GTS-AOD3A, SGT EXH FAN A) light OFF DISCH opens.

RJPM-NRC-D10-S3

Denotes Critical Step Page 12 of 15

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

RJPM-NRC-D10-S3 PERFORMANCE STEP STANDARD S/U COMMENTS 5.7.6 N/A NOTE: Annulus Mixing System IF an Annulus Mixing System Initiation should not initiate.

is received, THEN take action in 18 accordance with the associated annunciator Alarm Response Procedures.

5.7.7 HVR-FN8 control switch has been placed to the HVR-FN8 red light ON green Place HVR-FN8, HIGH VOL START position. light OFF CONTMT/DW PURGE to START and 19 verify HVR-AOD244, HIGH VOL FAN DISCH opens. HVR-AOD244 red light ON green light OFF 5.7.8 Candidate has dispatched an operator to verify CUE: As the building operator At AB 141 ft el, EJS-SWG2A(B), 480 breaker is in the closed position. accept the direction to verify the 20 V STANDBY SWITCHGEAR, verify breaker position and report that the breaker EJS-ACB033(073), GTS-H1A(B) is closed. breaker is closed.

5.7.9 Candidate has dispatched an operator to verify CUE: As the building operator Verify proper filter operation by proper local component differential pressure accept the direction to verify observing the following differential instruments. proper local component differential pressure and radiation indications:

pressure instruments.

GTS-FLT1A(B), SGT FILTER 21 TRAIN local component differential Candidate has verified that radiation indications are pressure instruments normal on RE-21A&B and 103. Radiation monitors have a color

RMS-RE21A&B, CONTMT status of GREEN.

PURGE ISOL

RMS-RE103, SGT FILTER EXH RAD MONITOR Terminating Cue: Drywell High Volume Purge is in service with GTS-FN1A and HVR-FN8 RJPM-NRC-D10-S3

Denotes Critical Step Page 13 of 15

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

RJPM-NRC-D10-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-NRC-D10-S3 Page 14 of 15

RJPM-NRC-D10-S3 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is shutdown in Mode 4. The initial drywell entry will be performed on this shift. RP has requested the drywell to be purged for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to entry.

Initiating Cues: The CRS directs you to purge the drywell per SOP-059 section 5.8. Steps 5.8.1 and 5.8.2 have been completed.

RJPM-NRC-D10-S3 Page 15 of 15

Number: *RJPM-NRC-D10-S4 RIVER Revision: 00 BEND STATION Page 1 of 11 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

ALTERNATE CONTROL ROD DRIVE PUMPS REASON FOR REVISION:

D 2010 NRC Exam JPM S4 PREPARE / REVIEW:

John Hedgepeth 0069 8-24-2010 Preparer KCN Date Angie Orgeron 1538 9-8-2010 Technical Review (SME) KCN Date Scott Dallas 1385 9-8-2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-S4 TASK DESCRIPTION: Alternate Control Rod Drive pumps TASK

REFERENCE:

201007001001 K/A REFERENCE & RATING: 201001 A1.01 3.1/2.9 A1.02 2.9/2.9 201001 A1.03 2.9/2.8 A3.02 2.8/2.8 201001 A3.03 2.7/2.7 A3.04 2.8/2.7 201001 A4.01 3.1/ 3.1 A4.04 3.1/ 3.0 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 1 RJPM-NRC-D10-S4 Page 2 of 11

RJPM-NRC-D10-S4 SIMULATOR SETUP SHEET Task

Description:

Alternate Control Rod Drive Pumps Required Power: Any IC No.: 179 Notes:

RJPM-NRC-D10-S4 Page 3 of 11

RJPM-NRC-D10-S4 DATA SHEET References for Development: SOP-0002, Section 5.1 Required Materials: SOP-0002, Section 5.1 Required Plant Condition: None Task Standard Alternate CRD pumps and respond to the tripped pump Applicable Objectives: RLP-STM-052 Obj #4 and 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-NRC-D10-S4 Page 4 of 11

RJPM-NRC-D10-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, 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:

CRD Pump "B" is operating with normal system pressure and flow. A CRD pump is off.

Initiating Cue:

The CRS directs you to shift CRD pumps in accordance with SOP-0002, Section 5.1.

RJPM-NRC-D10-S4

Denotes Critical Step Page 5 of 11

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

RJPM-NRC-D10-S4 PERFORMANCE STEP STANDARD S/U COMMENTS 5.1.1.1 Directed the building operator check CRD pump Cue: The building operator reports oil levels that the CRD pump oil levels are

1. Check that the oil level for CRD Pump normal A and its associated gear box is normal.

5.1.1.2 Directed the building operator to close Cue: The building operator reports C11-VF014A, CRD PMP A DISCH STOP that C11-VF014A, CRD PMP A

2. CHECK VLV. DISCH STOP CHECK VLV is Close C11-VF014A, CRD PMP A DISCH STOP CHECK VLV. now closed 5.1.1.3 Directed the building operator to vent the CRD Cue: The building operator reports Pump A casing using C11-VF109A, CRD PUMP that the CRD pump casing has

3. Vent the CRD Pump A casing using A CASING VENT VLV. been vented C11-VF109A, CRD PUMP A CASING VENT VLV.

5.1.1.4 Control switch for C11-C001AP, CRD AUX Red light on green light off OIL PUMP A rotated to the start position

4. Start C11-C001AP, CRD AUX OIL PUMP A.

Verified that the white light is illuminated.

5.1.1.5 White light on.

5.

Verify white light comes on for C11-C001A, CRD PUMP A.

RJPM-NRC-D10-S4

Denotes Critical Step Page 6 of 11

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

RJPM-NRC-D10-S4 PERFORMANCE STEP STANDARD S/U COMMENTS 5.1.1.6 Control switch for C11-C001A, CRD PUMP A Red light on green light off rotated to the start position

6. Start C11-C001A, CRD PUMP A AND immediately perform the following:

Directed the building operator to slowly, open 5.1.1.6. Cue: The building operator reports C11-VF014A, CRD PMP A DISCH STOP that the discharge valve has been Slowly, open C11-VF014A, CRD CHECK VLV.

7. slowly opened fully PMP A DISCH STOP CHECK VLV.

5.1.1.7 Directed the building operator to verify proper CUE: The building operator operation. reports that all pumps checks are

8. satisfactory.

Verify CRD Pump A is operating properly.

5.1.2. Verified proper flow on C11-R606, CRD HYDR 45gpm FLOW.

9. Check that CRD System flow has stabilized.

5.1.3.1 Directed the building operator to close C11- CUE: Report as the building VF014B, CRD PMP B DISCH STOP CHECK operator that C11-VF014B, CRD

10. Close C11-VF014B, CRD PMP B VLV. PMP B DISCH STOP CHECK DISCH STOP CHECK VLV. VLV is closed.

RJPM-NRC-D10-S4

Denotes Critical Step Page 7 of 11

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

RJPM-NRC-D10-S4 PERFORMANCE STEP STANDARD S/U COMMENTS 5.1.3.2. Placed the control switch for C11-C001B, CRD Red light OFF and green light ON.

11. Stop C11-C001B, CRD PUMP B. PUMP B to stop.

ALTERNATE PATH Recognized and reported to the CRS that the White light off, amber and green CRD pump has tripped lights on.

C11-C001B, CRD PUMP B trips CUE; as the CRS direct the

12. candidate to restore CRD-P1B discharge path, then start CRD-P1B per the ARP-P601-22 -A01 guidance.

5.1.5 Directed the building operator to slowly open CUE: Report as the building Slowly reopen C11-VF014B, CRD C11-VF014B, CRD PMP B DISCH STOP operator that C11-VF014B, CRD 13 PMP B DISCH STOP CHECK VLV CHECK VLV PMP B DISCH STOP CHECK for the pump which was stopped VLV is fully open.

1.(ARP-H13-P601/22/A01) N/A 14 At H13-P601, start the standby CRD Pump as follows:

1.a Placed the control switch for C11-C001BP, CRD Red light ON green light OFF Start Standby CRD Pump Aux Oil AUX OIL PUMP B to start

15 Pump C11-C001BP, CRD AUX OIL PUMP B.

1.b Placed Flow Controller C11-R600 to MANUAL 16 Place Flow Controller C11-R600 to MANUAL RJPM-NRC-D10-S4

Denotes Critical Step Page 8 of 11

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

RJPM-NRC-D10-S4 PERFORMANCE STEP STANDARD S/U COMMENTS 1.c Depressed the close push button to close C11-Close C11-R600, CRD R600, CRD HYDRAULICS FLOW 17 HYDRAULICS FLOW CONTROLLER C11-F001A/B.

CONTROLLER C11-F001A/B.

1.d Verified the white Control Power Light on for 18 Verify White Control Power Light on CRD Pump B to be started.

for CRD Pump to be started.

1.e Placed the control switch for C11-C001B, CRD Red light ON green light OFF

19 Start Standby Pump C11-C001B, PUMP B to start.

CRD PUMP B.

1.f Verified amps return to normal of less than 45 20 Verify amps return to normal of less amps.

than 45 amps.

1.g After system flow has dropped below 45 gpm WHEN system flow drops below 45 slowly throttled open Flow Controller C11-R600 gpm as indicated on C11-R606, CRD with the open push button to achieve 45 gpm.

21 HYDR FLOW, THEN slowly throttle open Flow Controller C11-R600 to achieve 45 gpm.

1.h After flow controller C11-R600 setpoint is nulled WHEN Flow Controller C11-R600 out, placed into AUTO.

22 setpoint is nulled out, THEN place to AUTO.

Terminating Cue: CRD-P1B restored per ARP-P601-22.

RJPM-NRC-D10-S4

Denotes Critical Step Page 9 of 11

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

RJPM-NRC-D10-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-NRC-D10-S4 Page 10 of 11

RJPM-NRC-D10-S4 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: CRD Pump "B" is operating with normal system pressure and . A CRD pump is off.

Initiating Cues: The CRS directs you to shift CRD pumps in accordance with SOP-0002, Section 5.1.

RJPM-NRC-D10-S4 Page 11 of 11

Number: *RJPM-NRC-D10-S5 RIVER Revision: 00 BEND STATION Page 1 of 12 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

Restoration of Offsite Power REASON FOR REVISION:

D 2010 NRC Exam JPM S5 PREPARE / REVIEW:

John Hedgepeth 0069 8-24-2010 Preparer KCN Date Angie Orgeron 1538 9-9-2010 Technical Review (SME) KCN Date Alfonso Croeze 0597 9-9-2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-S5 TASK DESCRIPTION: Restoration of Offsite Power TASK

REFERENCE:

400014004001 K/A REFERENCE & RATING: 262001 K1.03 3.4/3.8 262001 A1.02 3.1/3.5 262001 A1.03 2.9/3.1 A1.05 3.2/3.5 262001 A2.07 3.0/3.2 A4.05 3.3/3.3 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: Yes ALTERNATE PATH No (FAULTED):

SAFETY FUNCTION 6 RJPM-NRC-D10-S5 Page 2 of 12

RJPM-NRC-D10-S5 SIMULATOR SETUP SHEET Task

Description:

Required Power: Loss of Offsite Power IC No.: 180 Notes:

RJPM-NRC-D10-S5 Page 3 of 12

RJPM-NRC-D10-S5 DATA SHEET References for Development: AOP-0004, Loss of Offsite Power Required Materials: AOP-0004, Loss of Offsite Power, Section 5.16 Required Plant Condition: Plant shutdown, offsite power available, all three diesel generators running carrying their respective buses.

Task Standard Power has been restored to NPS and NNS busses.

Applicable Objectives: RLP-HLO-523 Obj. 11 and 12 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-NRC-D10-S5 Page 4 of 12

RJPM-NRC-D10-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 experienced a Loss of Offsite Power approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ago due to a grid fault. All required immediate and subsequent actions were carried out. All three diesel generators started and are carrying their respective buses. All other plant equipment operated as designed. There are no faults within the plant electrical distribution system and all protective relays have been reset and documented. The System Operator has reported that offsite power is available at the switchyard and he is ready for restoration to the plant.

Initiating Cue: The CRS directs you to restore offsite power to the plant (NPS and NNS Buses) in accordance with AOP-0004, Loss of Offsite Power, Section 5.16. Steps 5.16.1 thru 5.16.5 have already been completed.

RJPM-NRC-D10-S5

Denotes Critical Step Page 5 of 12

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

RJPM-NRC-D10-S5 PERFORMANCE STEP STANDARD S/U COMMENTS 5.16.6 N/A

1. At H13-P870, depress the LOCKOUT Pushbutton for the following pumps:

5.16.6 CCS-P1A LOCKOUT Pushbutton has been fully CCS-P1A control power white 2.

CCS-P1A, TPCCW PUMP 1A depressed light OFF 5.16.6 CCS-P1B LOCKOUT Pushbutton has been fully CCS-P1B control power white 3

CCS-P1B, TPCCW PUMP 1B depressed light OFF 5.16.6 CCS-P1C LOCKOUT Pushbutton has been fully CCS-P1C control power white 4

CCS-P1C, TPCCW PUMP 1C depressed light OFF 5.16.6 CCP-P1A LOCKOUT Pushbutton has been fully CCP-P1A control power white 5

CCP-P1A, RPCCW PUMP 1A depressed light OFF 5.16.6 CCP-P1B LOCKOUT Pushbutton has been fully CCP-P1B control power white 6

CCP-P1B, RPCCW PUMP 1B depressed light OFF 5.16.6 CCP-P1C LOCKOUT Pushbutton has been fully CCP-P1C control power white 7

CCP-P1C, RPCCW PUMP 1C depressed light OFF 5.16.6 GMC-SCPM-A LOCKOUT Pushbutton has been GMC-SCPM-A control power 8 GMC-SCPM-A, STATOR CLG WTR fully depressed white light OFF PUMP A 5.16.6 GMC-SCPM-B LOCKOUT Pushbutton has been GMC-SCPM-B control power 9 GMC-SCPM-B, STATOR CLG WTR fully depressed white light OFF PUMP B 5.16.6 TMB-HFPM-A LOCKOUT Pushbutton has been TMB-HFPM-A control power 10 TMB-HFPM-A, EHC PUMP A fully depressed white light OFF 5.16.6 TMB-HFPM-B LOCKOUT Pushbutton has been TMB-HFPM-B control power 11 TMB-HFPM-B, EHC PUMP B fully depressed white light OFF 5.16.7 N/A At H13-P808, Harris Panel, verify 12 lockout indication for the following pumps:

RJPM-NRC-D10-S5

Denotes Critical Step Page 6 of 12

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

RJPM-NRC-D10-S5 PERFORMANCE STEP STANDARD S/U COMMENTS 5.16.7 SWC-P1A has been selected and locked out. SWC-P1A BLUE light ON and 13 SWC-P1A LOCKOUT Lockout status light ON.

5.16.7 SWC-P1B has been selected and locked out. SWC-P1B BLUE light ON and 14 SWC-P1B LOCKOUT Lockout status light ON.

5.16. SWC-P1C has been selected and locked out. SWC-P1C BLUE light ON and 15 SWC-P1C LOCKOUT Lockout status light ON.

5.16.7 SWP-P7A has been selected and locked out. SWP-P7A BLUE light ON and 16 SWP-P7A LOCKOUT Lockout status light ON.

5.16.7 SWP-P7B has been selected and locked out. SWP-P7B BLUE light ON and 17 SWP-P7B LOCKOUT Lockout status light on.

5.16.7 SWP-P7C BLUE light ON and SWP-P7C has been selected and locked out.

18 SWP-P7C LOCKOUT Lockout status light ON.

5.16.8 N/A At H13-P680, close the Preferred 19 Station Service Transformer supply breakers as follows:

5.16.8.1 Placed PFD XFMR C & E SPLY SYNC Place PFD XFMR C & E SPLY 20 SELECTOR SWITCH to N. BUS position.

SYNC SELECTOR SWITCH to N.

BUS position.

5.16.8.2 YWC-20620 CLOSE pushbutton has been YWC-20620 red light ON and

21 Close YWC-20620 to energize PFD depressed green light OFF STA SVCE XFMR C & E.

RJPM-NRC-D10-S5

Denotes Critical Step Page 7 of 12

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

RJPM-NRC-D10-S5 PERFORMANCE STEP STANDARD S/U COMMENTS 5.16.8.3 Placed PFD XFMR C & E SPLY SYNC Place PFD XFMR C & E SPLY 22 SELECTOR SWITCH to S. BUS position.

SYNC SELECTOR SWITCH to S.

BUS position.

5.16.8.4 YWC-20610 CLOSE pushbutton has been YWC-20610 red light ON and

23 Close YWC-20610. depressed green light OFF 5.16.8.5 Placed PFD XFMR C & E SPLY SYNC 24 Place PFD XFMR C & E SPLY SELECTOR SWITCH to OFF SYNC SELECTOR SWITCH to OFF.

5.16.8.6 Placed PFD XFMR D & F SPLY SYNC Place PFD XFMR D & F SPLY 25 SELECTOR SWITCH to N. BUS position SYNC SELECTOR SWITCH to N.

BUS position.

5.16.8.7 YWC-20670 red light ON and YWC-20670 CLOSE pushbutton has been

26 Close YWC-20670 to energize PFD depressed green light OFF STA SVCE XFMR D & F.

5.16.8.8 Placed PFD XFMR D & F SPLY SYNC Place PFD XFMR D & F SPLY 27 SELECTOR SWITCH to ENJAY position.

SYNC SELECTOR SWITCH to ENJAY position.

5.16.8.9 YWC-20665 CLOSE pushbutton has been YWC-20665 red light ON and

28 Close YWC-20665. depressed green light OFF 5.16.8.10 Placed PFD XFMR D & F SPLY SYNC 29 Place PFD XFMR D & F SPLY SELECTOR SWITCH to OFF SYNC SELECTOR SWITCH to OFF.

RJPM-NRC-D10-S5

Denotes Critical Step Page 8 of 12

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

RJPM-NRC-D10-S5 PERFORMANCE STEP STANDARD S/U COMMENTS 5.16.9 N/A At H13-P808, close the Preferred 30 Station Transformer output breakers as follows:

5.16.9.1 Selected 13.8 KV on BUS A SYNC CHECK

31 Select 13.8 KV on BUS A SYNC DEFEAT Switch.

CHECK DEFEAT Switch.

5.16.9.2 NPS-ACB11 CLOSE pushbutton has been NPS-ACB11 red light ON and

32 Close NPS-ACB11, 13.8 KV PFD depressed green light OFF SUPPLY BRKR for NPS-SWG1 5.16.9.3 Selected OFF on BUS A SYNC CHECK 33 Select OFF on BUS A SYNC CHECK DEFEAT Switch.

DEFEAT Switch.

5.16.9.4 Selected 4.16 KV on BUS A SYNC CHECK

34 Select 4.16 KV on BUS A SYNC DEFEAT Switch.

CHECK DEFEAT Switch.

5.16.9.5 NNS-ACB07 red light ON and NNS-ACB07 CLOSE pushbutton has been

35 Close NNS-ACB07, 4160V PFD depressed green light OFF SUPPLY BRKR for NNS-SWG1A.

5.16.9.6 Selected OFF on BUS A SYNC CHECK 36 Select OFF on BUS A SYNC CHECK DEFEAT Switch.

DEFEAT Switch.

5.16.9.7 Selected 13.8 KV on BUS B SYNC CHECK

37 Select 13.8 KV on BUS B SYNC DEFEAT Switch.

CHECK DEFEAT Switch.

5.16.9.8 NPS-ACB27 CLOSE pushbutton has been NPS-ACB27 red light ON and

38 Close NPS-ACB27, 13.8 KV PFD depressed green light OFF SUPPLY BRKR for NPS-SWG1B.

RJPM-NRC-D10-S5

Denotes Critical Step Page 9 of 12

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

RJPM-NRC-D10-S5 PERFORMANCE STEP STANDARD S/U COMMENTS 5.16.9.9 Selected OFF on BUS B SYNC CHECK 39 Select OFF on BUS B SYNC CHECK DEFEAT Switch.

DEFEAT Switch.

5.16.9.10 Selected 4.16 KV on BUS B SYNC CHECK

40 Select 4.16 KV on BUS B SYNC DEFEAT Switch.

CHECK DEFEAT Switch.

5.16.9.11 NNS-ACB15 CLOSE pushbutton has been NNS-ACB15 red light ON and

41 Close NNS-ACB15, 4160V PFD depressed green light OFF SUPPLY BRKR for NNS-SWG1B.

5.16.9.12 Selected OFF on BUS B SYNC CHECK 42 Select OFF on BUS B SYNC CHECK DEFEAT Switch.

DEFEAT Switch.

Terminating Cue: Off site power has been restored to the NPS (13.8KV) and NNS (4.16KV) buses.

RJPM-NRC-D10-S5

Denotes Critical Step Page 10 of 12

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

RJPM-NRC-D10-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-NRC-D10-S5 Page 11 of 12

RJPM-NRC-D10-S5 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant experienced a Loss of Offsite Power approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ago due to a grid fault. All required immediate and subsequent actions were carried out. All three diesel generators started and are carrying their respective buses. All other plant equipment operated as designed.

There are no faults within the plant electrical distribution system and all protective relays have been reset and documented. The System Operator has reported that offsite power is available at the switchyard and he is ready for restoration to the plant.

Initiating Cues: The CRS directs you to restore offsite power to the plant (NPS and NNS Buses) in accordance with AOP-0004, Loss of Offsite Power, Section 5.16. Steps 5.16.1 thru 5.16.5 have already been completed.

RJPM-NRC-D10-S5 Page 12 of 12

Number: *RJPM-NRC-D10-S6 RIVER Revision: 00 BEND STATION Page 1 of 10 JOB PERFORMANCE MEASURE TRAINING PROGRAM:

JOB PERFORMANCE MEASURE LESSON PLAN:

Perform Rod Withdrawal Limiter Surveillance (>HPSP)

REASON FOR REVISION:

D 2010 NRC Exam JPM S6 PREPARE / REVIEW:

John Hedgepeth 0069 8-24-2010 Preparer KCN Date Angie Orgeron 1538 9-8-2010 Technical Review (SME) KCN Date Scott Shultz 0176 9-8-2010 Operations Validation KCN Date

Indexing Information

RJPM-NRC-D10-S6 TASK DESCRIPTION: Perform Rod Withdrawal Limiter Surveillance (>HPSP)

TASK

REFERENCE:

214001002001 K/A REFERENCE & RATING: 201005 A3.03 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 No (FAULTED):

SAFETY FUNCTION 7 RJPM-NRC-D10-S6 Page 2 of 10

RJPM-NRC-D10-S6 SIMULATOR SETUP SHEET Task

Description:

Perform Rod Withdrawal Limiter Surveillance (>HPSP)

Required Power: Greater than the HPSP IC No.: 177 Notes:

RJPM-NRC-D10-S6 Page 3 of 10

RJPM-NRC-D10-S6 DATA SHEET References for Development: STP-500-0704 Required Materials: STP-500-0704 Required Plant Condition: Greater than the HPSP Task Standard STP-500-0704 has been completed with reactor power above the high power setpoint.

Applicable Objectives: RLP-STM-0500 Objective 4, 12 and 20 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-NRC-D10-S6 Page 4 of 10

RJPM-NRC-D10-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, 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 power is above the HPSP.

Initiating Cue: The CRS has directed you to perform STP-500-0704 for control rod 16-17 per section 7.1 Initial Position 10 Final Position 14 RJPM-NRC-D10-S6

Denotes Critical Step Page 5 of 10

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

RJPM-NRC-D10-S6 PERFORMANCE STEP STANDARD S/U COMMENTS 7.1.1. Rod 16-17 verified to be in position 10 Rod 16-17 selected and position Verify the selected rod is in the start 10 displayed 1.

position recorded in Step 6.6. Record rod position.

7.1.2. N/A

2. On the ROD SELECT module, perform the following:

7.1.2.1 Depressed the DESELECT pushbutton and then DESELECT pushbutton

3. released. illuminated, then off.

Deselect the rod.

7.1.2.2 Rod 16-17 has been selected. Rod 16-17 selected and position Select the rod that corresponds to the 10 displayed

4.

rod coordinate position recorded in Step 6.6.

7.1.3. Withdraw pushbutton depressed.

Rod motion from position 10 to

5. Withdraw the rod two notches in the position 14 notch withdrawal mode.

7.1.4. CONTROL ROD WITHDRAWAL BLOCK CONTROL ROD alarm silenced and acknowledged.

Check Annunciator P680-07A-C01, WITHDRAWAL BLOCK alarm 6

CONTROL ROD WITHDRAWAL received.

BLOCK alarms.

RJPM-NRC-D10-S6

Denotes Critical Step Page 6 of 10

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

RJPM-NRC-D10-S6 PERFORMANCE STEP STANDARD S/U COMMENTS 7.1.5. Withdraw pushbutton depressed and verified no No change to rod position rod motion.

Check the rod withdrawal limiter stops

7 rod motion at the second notch by attempting to withdraw the rod a third notch and verifying the rod does not move.

7.3.1. N/A 8 On the ROD SELECT module, perform the following:

7.3.1.1 Depressed the DESELECT pushbutton and then DESELECT pushbutton 9 released.

Deselect the rod. illuminated, then off.

7.3.1.2 Rod 16-17 has been selected. Rod 16-17 selected and position 14 displayed 10 Select the rod that corresponds to the rod coordinate position recorded in Step 6.6.

7.3.2. CONTROL ROD WITHDRAWAL BLOCK CONTROL ROD alarm has been reset. WITHDRAWAL BLOCK alarm 11 Check Annunciator P680-07A-C01, CONTROL ROD WITHDRAWAL cleared.

BLOCK is clear.

7.3.3. Verified that rod 16-17 is at position 14 and Rod 16-17 is displayed at position recorded.

14 12 Verify the selected rod is in the final position recorded in Step 6.6. Record rod position RJPM-NRC-D10-S6

Denotes Critical Step Page 7 of 10

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

RJPM-NRC-D10-S6 PERFORMANCE STEP STANDARD S/U COMMENTS 7.3.4. Recorded as N/A 13 IF the rod is withdrawn to position 48, THEN perform a coupling check.

7.3.5. Requested independent verification of rod CUE: Inform the candidate that position.

the independent verification has 14 Verify the rod recorded in Step 6.6 is in the final position recorded in Step been completed.

6.6.

7.3.6. Notified the NCO of test completion CUE: Accept the notification as 15 the NCO Notify the NCO of test completion.

7.3.7. Notified the OSM/CRS of test completion CUE: Accept the notification as 16 Notify the OSM/CRS of test the CRS completion.

Terminating Cue: Rod Withdrawal Limiter verified per STP-500-0704 RJPM-NRC-D10-S6

Denotes Critical Step Page 8 of 10

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

RJPM-NRC-D10-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-NRC-D10-S6 Page 9 of 10

RJPM-NRC-D10-S6 JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: Reactor power is above the HPSP.

Initiating Cues: The CRS has directed you to perform STP-500-0704 for control rod 16-17 per section 7.1 Initial Position 10 Final Position 14 RJPM-NRC-D10-S6 Page 10 of 10

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station_______________ Scenario No.: __1____ Op-Test No.:

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 99% power. Preparing for down power for sequence exchange.

EOOS STATUS = 10 GREEN PROTECTED EQUIPMENT DIV I and RCIC DIV III work week. High Pressure Core Spray is available but not operable until the breaker functional is complete.

Turnover: Complete breaker functional per SOP on the High Pressure Core Spray breaker. The pre-start checks have been completed satisfactory. Lower power per GOP-5 Power Maneuvering and the approved reactivity control plan.

Event Malf. No. Event Event No. Type* Description 1 N Perform High Pressure Core Spray Pump Breaker Functional per SOP.

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

3 RCIC009 I (BOP,SRO) Spurious RCIC Isolation. (Technical Specifications)

RCIC007 E51-F063 RCIC Steam Supply Inboard Isolation Valve fails to auto close 4 B21005 I (SRO) B21-PTN078A RPV pressure transmitter fails low. (Technical Specifications) 5 GMC002A C Stator Cooling Pump A trips, Stby pump fails to AUTO start (BOP,SRO) requiring manual start.

GMC001B 6 GMC002B C (ATC,SRO) Second Stator Cooling Pump trips / Reactor Scram 7 RPS001A M (ALL) RPS Fails to Scram - All Signals 8 FWS004A C (ATC,SRO) Feedwater Master Controller output fails low 9 EHC002A C (ATC,SRO) Main Turbine Bypass Valves fail OPEN.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions: (5-8): (8) RCIC, E51-MOVF063, B21-PTN078A, Stator Cooling Pumps A & B, ATWS, FWS Controller, BPVs Malfunctions after EOP entry: (1-2) (2) FWS, BPVs Abnormal events: (2-4): (2) (AOP-3, AOP-1)

Major transients: (1-2): (1) ATWS EOPs entered: (1-2): (2)EOP-1, EOP-2 EOP contingencies: (0-2) (1) EOP-1A Critical tasks: (2-3) (2) Terminate FW injection, Begin control insertion.

Rev 01

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

Description:

Perform HPCS Pump Breaker Functional per SOP.

Cue: Turnover item.

Time Position Applicants Actions or Behavior Direct the BOP to start the HPCS pump per SOP-0030 section 5.4 with SRO suction lined up to the CST Perform HPCS Breaker Functional

Start the HPCS Pump and verify the following:

HPCS Pump motor current is less than or equal to 350 amps on E22-R616, HPCS PUMP MOTOR AMPS.

WHEN HPCS Pump discharge pressure rises above 300 psig on E22-R601, HPCS PUMP DISCH PRESSURE, THEN E22-F012, HPCS MIN FLOW VALVE TO SUPPRESSION POOL opens.

BOP

Trip E22-ACB02, HPCS PUMP SUPPLY BRKR.

WHEN HPCS Pump discharge pressure lowers below 300 psig on E22-R601,

HPCS PUMP DISCH PRESSURE, THEN verify E22-F012, HPCS MIN FLOW VALVE TO SUPPRESSION POOL closes.

Log completion of the breaker functional in the MCR Logs.

Notify SRO that the breaker functional is complete As the reactor building operator, if requested report that all pre-start ROLE PLAY checks are complete and SAT.

As the control building operator, if requested, report that the charging ROLE PLAY springs for High Pressure Core Spray pump motor breaker are charged.

When the High Pressure Core Spray breaker functional test is complete, SRO notify Work Management Center to exit the High Pressure Core Spray LCO.

Rev 01

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

Description:

Lower reactor power with control rods.

Cue: Turnover item.

Time Position Applicants Actions or Behavior Direct the power reduction per the reactivity Control Plan step 02 and 03 SRO Accept the direction for power reduction.

Insert control rods per the RCP

At H13-P680, on the ROD SELECT MODULE, select the rod to be moved.

Depress SELECTED GROUP button to check positions of control rods ATC within group are correct prior to movement

Check that a Rod Insert Block or Inhibit does not exist.

On H13-P680, depress and hold C11A-S314, INSERT Pushbutton until the IN indicator is lit or the start of rod motion is observed.

Check that the new rod notch position displayed is the next lowest even number.

Repeat the rod movement steps as needed to complete step 02 and 03 of ATC the RCP Report completion of the power reduction Rev 01

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

Description:

Spurious RCIC Isolation. (Technical Specifications) RCIC MOV63 fails to auto close Cue: RCIC Steam supply isolation annunciators on H13-P601. E51-F063 red light on, green light off.

Time Position Applicants Actions or Behavior Recognize and report the RCIC isolation due to high differential steam flow BOP

Accept the report SRO

Refer to Tech. Specs.

Request back panel reading Refer to the Alarm Response Procedure BOP Retrieve the requested back panel information As the back panel operator when requested, report that trip unit E31-ROLE PLAY ESN683A and B reads 138 inches and the trip red LED is on.

Report the back panel reading to the SRO BOP Report that E51-F063 did not isolate per the ARP Direct the BOP to perform AOP-0003 for the isolation signal SRO Direct the BOP to attempt to close E51-F063 Closes E51-F063 manually.

BOP Verifies that all other required isolation valves have closed per AOP-0003 Enters T.S. 3.5.3A and 3.3.6.1A SRO Notifies WMC to investigate the trip unit failure Makes the required notifications per OSP-046 Rev 01

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

Description:

B21-PTN078A RPV pressure transmitter fails low. (Technical Specifications)

Cue: Annunciator H13-P680-06-A5.

Time Position Applicants Actions or Behavior Recognize and report the failure of B21-PTN078A RPV pressure transmitter ATC Give the SRO a critical parameter report Refer to ARP-P680-06-A5 Accept the report SRO Refer to Tech. Specs.

Request back panel indication As the back panel operator when requested, report that B21-PTN078A ROLE PLAY reads 1250 psig. All other channels read normal for this power level Enters T.S. 3.3.1.1A SRO Contacts the WMC to investigate the transmitter failure Rev 01

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

Description:

Stator Cooling Pump A trips, Standby pump fails to AUTO start requiring manual start.

Cue: Annunciator H13-P870-54-D01.

Time Position Applicants Actions or Behavior Recognize and report the trip of Stator cooling water pump A.

Recognize and report the failure of Stator cooling water pump B to auto start.

BOP Manually start Stator cooling water pump B.

Refer to the Alarm Response procedure Direct the turbine building operator to perform running checks on pump B Accept the report from the BOP.

SRO Direct manual start of Stator cooling water pump B if not completed by the BOP.

Contact WMC to investigate the pump trip.

As the turbine building operator, accept the direction to investigate the trip of ROLE PLAY Stator cooling water pump A and perform running checks on pump B Rev 01

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

Description:

Second Stator Cooling Pump trips / Reactor Scram Cue: Annunciator H13-P870-54-D01.

Time Position Applicants Actions or Behavior Recognize and report the trip of Stator cooling water pump B BOP Recognize and report that a turbine runback is in progress ATC Accept report from the BOP / ATC SRO Direct the ATC to place the reactor mode switch to Shutdown due to the turbine runback Place the mode switch to shutdown Determine that all control rods did not fully insert Arm and depress all four manual scram pushbuttons ATC Determine that all control rods did not fully insert Arm and initiate Alternant Rod Insertion Determine that all control rods did not fully insert Give the SRO an ATWS report Rev 01

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

Description:

RPS Fails to Scram - All Signals Cue: Indication of control rods not fully inserted on H13-P680 Full Core Display.

Time Position Applicants Actions or Behavior Enter EOP-1 and transition to EOP-1A RPV control ATWS Direct EOP-1A actions

ATC trip both reactor recirc pumps

BOP terminate and prevent injection with HPCS

BOP inhibit ADS SRO

BOP install EOP-5 enclosures 16 and 24

ATC terminate injection with feedwater and lower reactor water level to -60 to -140

BOP initiate Standby liquid control system

BOP install EOP-5 enclosures 14 and 10

BOP maximize CRD cooling water flow Trip both reactor recirc pumps

Depress STOP, RECIRC PUMP BREAKER 5A.

ATC

Depress STOP, RECIRC PUMP BREAKER 5B.

TRIP LFMG BRKR 1A

TRIP LFMG BRKR 1B.

Terminate and prevent injection with High Pressure Core Spray

Override Injection / Initiate High Pressure Core Spray

Verify E22-F004 amber override light is lit.

BOP

Stop the High Pressure Core Spray pump.

Notify the SRO that injection from HPCS has been terminated and prevented.

Inhibit ADS BOP

Place Div I ADS key lock switch to INHIBIT

Place Div II ADS key lock switch to INHIBIT Install EOP-5 enclosures 16 and 24 BOP

Request the back panel operator to perform needed actions

Verify that IAS-MOV106 is open Rev 01

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

Description:

RPS Fails to Scram - All Signals continued Time Position Applicants Actions or Behavior Terminate injection with feedwater and lower reactor water level to -60 to

-140 ATC

Place the master RPV level controller into manual

Lower master controller output signal to 0 Initiate Standby liquid control system

Place SLC PUMP A(B) (NOT BOTH), control switch to RUN.

Verify the following:

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

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

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

Notify SRO of SLC injection status.

Verify IAS-MOV106 is Open.

Record SLC Tank Level gallons.

Install EOP-5 enclosures 14 and 10 BOP

Request the back panel operator to perform needed actions Enclosure 10 actions BOP

Determine if any rod motion has occurred

Direct the back panel operator to reinstall the fuses Enclosure 14 actions

Fully INSERT control rods by group, starting with Group 10, using IN ATC TIMER SKIP pushbutton. Skip control rods which do not fully INSERT.

Maximize CRD cooling water flow

Start C11-C001AP(BP), CRD AUX OIL PUMP A(B).

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

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

BOP

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

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

Verify IAS-MOV106 is Open.

Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 8 Page 9 of 10 Event

Description:

FWS Master Controller output fails low Cue: Output demand signal remains at 0 when OPEN pushbutton is depressed on Feedwater Master Controller.

Time Position Applicants Actions or Behavior Recognize and report the failure of the master controller ATC Place Feedwater level control valves A, B and C into manual Manually control reactor level within the given band of -60 to -140 Direct manual control of the feedwater level control valves SRO Rev 01

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

Description:

Main Turbine Bypass Valves fail OPEN.

Cue: Bypass Valve position indication FULL OPEN lights are illuminated when reactor pressure is below the established pressure setpoint.

Time Position Applicants Actions or Behavior Recognize and report the turbine bypass valves have failed open and ATC reactor pressure is lowering Direct the turbine building operator to secure the turbine bypass valve EHC pumps to close the bypass valves SRO Direct the BOP to close the MSIVs if reactor pressure lowers to 600 psig Rev 01

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station_______________ Scenario No.: __2____ Op-Test No.:

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1 75% power. Down power in progress. Feedwater pump C is shutdown.

EOOS STATUS 10 GREEN(9.8 GREEN when the FWS pump is tagged) PROTECTED EQUIPMENT DIV I work week DIV II protected.

Turnover: Perform STP-406-0201, DIVISION I FUEL BUILDING HVAC CHARCOAL FILTER A OPERABILITY TEST. Section 6.0 has been completed. Raise reactor power per GOP-005 Power Maneuvering. FWS P1C is off and due to be tagged and drained this shift.

Event Malf. No. Event Event No. Type* Description 1 N (BOP,SRO) Perform STP-406-0201 Division I Fuel Building HVAC Charcoal Filter A Operability Test 2 R (ATC) Raise reactor power with reactor recirculation flow.

3 ED004K C (SRO) Loss of NJS-LDC1K 480 VAC Load Center (Technical Specification).

4 RMS013A C (SRO) RMS-RE13A Control Building Local Intake Monitor fails upscale.(Technical Specification) 5 C (BOP,SRO) HVC-AOD51A Control Room Isolation damper fails to isolate, but can be manually isolated.

6 CNM004A C (ATC,SRO) Condensate pump A trip 7 WCS006 M (ALL) RWCU leak in the Main Steam Tunnel 8 WCS004 C(BOP,SRO) G33-MOVF004 RWCU Pumps Outboard Isolation valve fails to WCS005 automatically isolate.

G33-MOVF001 RWCU Pumps Inboard Isolation valve fails to automatically isolate but can be manually isolated.

9 MGEN003 C(ATC,SRO) Main Generator reverse power relay fails.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions: (5-8) (7) NJS-LDC1K, RMS-RE13A, HVC-AOD51A, CNM-P1A, RWCU leak, G33-MOVs, Main Turbine Malfunctions after EOP entry: (1-2) (2) G33-MOVs, Main Turbine Abnormal events: (2-4) (4) AOP-3, AOP-1, AOP-2, AOP-6 Major transients: (1-2) (1) Steam Tunnel leak EOPs entered: (1-2) (2) EOP-1, EOP-3 EOP contingencies: (0-2) (0)

Critical tasks: (2-3) (2) Isolate leak, Trip the main turbine Rev 01

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

Description:

Perform STP-406-0201 Division I Fuel Building HVAC Charcoal Filter A Operability Test Cue: Turnover item.

Time Position Applicants Actions or Behavior Direct the BOP to perform STP-406-0201 DIVISION I FUEL BUILDING SRO HVAC CHARCOAL FILTER A OPERABILITY TEST Perform STP-406-0201 DIVISION I FUEL BUILDING HVAC CHARCOAL FILTER A OPERABILITY TEST

At H13-P863/76B, record HVF-TI30A, CHARCOAL BED 2A INLET TEMP temperature.

Start HVF-FN3A, EXH FLTR TRAIN and record the time it was started.

Check HVF-AOD20A, FILTER 2A INLET opens.

Check HVF-AOD31A, FAN 3A DISCH opens.

Place the standby HVF-FN8A(B), FUEL BLDG EXH FAN A(B) Control Switch in STOP.

Stop the running HVF-FN8A(B), FUEL BLDG EXH FAN A(B).

BOP

Check HVF-AOD6A(B), FUEL BLDG EXH FAN A(B) DISCH closes.

Close HVF-AOD102, FUEL BLDG EXH FAN INLT.

Close HVF-AOD112, FUEL BLDG EXH FAN INLT.

Close HVF-AOD104, FUEL BLDG EXH ISOL.

Close HVF-AOD137, FUEL BLDG EXH ISOL.

Calculate required stop time.

Request Electrical Maintenance to take current readings on heater HVF-FLT2AH, FUEL BLDG FILTER TRAIN HEATER

Request Electrical Maintenance to take voltage readings on heater HVF-FLT2AH, FUEL BLDG FILTER TRAIN HEATER Report to the SRO that the filter train is in service per the STP.

As EM accept the direction to obtain amp and voltage readings per the STP.

ROLE PLAY As reactor building operator accept direction to perform running checks on the filter train Rev 01

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 reactor power with reactor recirculation flow.

Cue: Turnover item.

Time Position Applicants Actions or Behavior Direct power ascension from 74% to 80% per GOP-005 by raising reactor SRO recirc. flow.

Accept direction for power ascension.

Raise reactor power with reactor recirculation flow.

Verify B33-K603A(B), RECIRC LOOP A(B) FLOW CONTROL M/A Station is in MAN.

Determine which B33-K603A(B), RECIRC LOOP A(B) FLOW CONTROL is to be adjusted by observing Loop Flows on B33-R612A and B33-R612B. Both loops may have to be adjusted to obtain the desired Reactor Power while maintaining Loop Flow mismatch within specification.

Note the current B33-HYVF060A(B), FLOW CONTROL VALVE ATC position, generator load, MWt, APRMs and loop flows.

Raise Reactor Recirculation Flow by toggling momentarily B33-K603A(B) controller in the open direction using the slow detent while observing for a servo error deviation in the positive direction.

Verify the servo error returns to its previous position.

Observe B33-HYVF060A(B), FLOW CONTROL VALVE position, generator load, MWt, APRMs and loop flows for expected changes.

Repeat steps 5.9.1.2.2) through 5.9.1.2.7) until the desired Reactor Power Level is achieved.

Report to the SRO when 80% power level is reached Rev 01

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

Description:

Loss of NJS-LDC1K 480 VAC Load Center (Technical Specification).

Cue: Annunciator H13-P808-86-G07. NJS-ACB149 red light off, green light on.

Time Position Applicants Actions or Behavior Recognize and report Loss of NJS-LDC1K 480 VAC Load Center BOP Accept report of NJS-LDC1K 480 VAC Load Center failure.

SRO Direct ACR operator to investigate the loss of NJS-LDC 1K. 480 VAC Load BOP Center As the ACR operator when requested report that the supply breaker for ROLE PLAY NJS-LDC1K 480 VAC Load Center has an over current flag in and the 86 lock out device is tripped Contact the WMC to investigate the fault on NJS-LDC1K 480 VAC Load Center SRO Enter TRM 3.7.9.1 A Make required notifications per OSP-0046 Rev 01

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

Description:

RMS-RE13A Control Building Local Intake Monitor fails upscale.(Technical Specification)

Cue: Annunciator H13-P863-74-H03 and Digital Radiation Monitoring computer alarm.

Time Position Applicants Actions or Behavior Recognize and report the failure of RMS-RE13A Control Building Local Intake Monitor BOP Refer to the Alarm response Procedure for the alarms received.

Determine and report normal readings / status of RE13B Control Building Local Intake Monitor Accept the failure report Assign the performance of AOP-003 Automatic Isolations to the BOP SRO Enter Tech Spec 3.3.7.1 A and D Rev 01

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

Description:

HVC-AOD51A Control Room Isolation damper fails to isolate, but can be manually isolated.

Cue: HVC-AOD51A red light on, green light off with isolation signal present.

Time Position Applicants Actions or Behavior Recognize and report the failure of HVC-AOD51A Control Room Isolation damper to close BOP Close HVC-AOD51A Control Room Isolation damper per the AOP-003 or ARP actions.

Verify all other isolations have occurred and report to the SRO.

Enter Tech Spec 3.7.2 B (short term until AOD is closed)

SRO Contact WMC to investigate the failure of the radiation instrument and the failure to isolate.

Rev 01

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

Description:

CONDENSATE PUMP A TRIP Cue: Annunciator H13-P680-02-A03 Time Position Applicants Actions or Behavior Recognize and report that Condensate pump A has tripped.

ATC Give the SRO a critical parameter report Accept the report SRO Direct the ATC to perform AOP-006 Condensate and Feedwater failures Direct the ATC to verify pump shutdown per the SOP-007 Close the A condensate discharge valve.

ATC Rev 01

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

Description:

RWCU leak in the Main Steam Tunnel Cue: Annunciator H13-P680-19-A01,A03,B01,B03 Time Position Applicants Actions or Behavior Recognize and report high main steam tunnel temperature BOP Obtain back panel reading for steam tunnel temperature As the back panel operator when requested report MST temperature for ROLE PLAY the insight file - AAA top 40 Enter EOP-003 Secondary Containment control when the main steam tunnel temperature reaches max normal temperature of 135 deg F.

SRO Direct the ATC to place the reactor mode switch to shutdown when the MST temperature reaches 200 deg F.

Place the mode switch to shutdown ATC Give the SRO a scram report Direct a reactor level band of -20 to 51 with condensate and feedwater Direct a pressure band of 500 to 1090 psig with bypass valves and steam line drains until the MSIVs close.

SRO Then direct pressure control with SRVs and RCIC Direct performance of AOP-0001 Reactor Scram and AOP-0002 Turbine Generator trip to the ATC Direct the performance of AOP-0003 Automatic Isolations to the BOP Perform actions of AOP-0003 to verify all required isolations have BOP occurred.

Rev 01

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

Description:

G33-MOVF004 RWCU Pumps Outboard Isolation valve fails to automatically isolate.

G33-MOVF001 RWCU Pumps Inboard Isolation valve fails to automatically isolate but can be .

manually isolated.

Cue: Both valves indicate red light on, green light off with an isolation signal present.

Time Position Applicants Actions or Behavior Recognize and report MSIV isolation BOP Recognize and report the failure of G33-MOVF001 and F004 to isolate.

BOP Attempt to close G33-MOVF001 and F004 RWCU Pumps Isolation valves.

Report that G33-MOVF001 did close and G33-MOVF004 did not.

Direct BOP to obtain new reading for the MST temperature SRO Direct the BOP to place RHR into suppression pool cooling mode of operation As the back panel operator when requested report MST temperature for ROLE PLAY the insight file - AAA top 40 Inform the SRO of the new MST temperature Place RHR into suppression pool cooling

Verify the selected system is not required for adequate core 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.

BOP

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

Open/Verify Open E12-F024A(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 01

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

Description:

Main Generator reverse power relay fails.

Cue: YMC-20640 and YMC-20635 indicate red light on, green light off with Main Turbine TRIPPED indication lit.

Time Position Applicants Actions or Behavior Recognize and report that the generator did not trip on reverse power Perform action of AOP-0002 Turbine Generator trips

IF an automatic trip setpoint has been exceeded, THEN verify Main Turbine has tripped.

ATC

Verify Main Generator Output Breakers YMC-20640, 230KV GEN BKR and YMC-20635, 230KV GEN BKR are open.

Verify Exciter Field Breaker is open.

Direct actions of AOP-0002 if not already performed SRO Rev 01

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station_______________ Scenario No.: __3____ Op-Test No.:

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1, 100%, RCIC tagged out for pump repairs. EOOS STATUS 8.6 YELLOW.

DIV III protected. Non-Divisional work week Turnover: Perform STP-256-0202 Standby Cooling Tower Fan Operability. Perform OSP-0101 section 4.11.3 for the turning gear oil pump pressure switch replacement. Lower power to 85% per GOP-005 to support control rod sequence exchange.

Event Malf. No. Event Event No. Type* Description 1 N Perform OSP-0101 Turbine Generator Periodic Testing Section (SRO,ATC) 4.11.3 2 N Perform STP-256-0202 Division II Standby Cooling Tower Fans (SRO,BOP) Operability Test.

3 R(ATC) Lower reactor power to 85% with reactor recirculation flow.

4 C HVR-UC1A Containment Unit Cooler trips. (Technical (SRO,BOP) Specifications) 5 B21006B I (SRO) Level transmitter B21-LTN081A fails downscale (Technical Specifications).

6 CCP001B C CCP Component Cooling Water Pump B trips, CCP Component (SRO,BOP) Cooling Water Pump A fails to Auto start CCP004A ED001 M(ALL)

Station Blackout 7

Loss of offsite power EDG001A

Div 1 DG trips EDG002B

Div 2 DG fails to start 8 SWP004 C SWP-AOV599 Standby Cooling Tower Inlet Valve fails to auto (SRO,BOP) open.

9 HPCS003 C High Pressure Core Spray fails to automatically initiate (Pump only, (SRO,BOP) DG starts on LOP to require SWP-AOV599 actions).

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions: (5-8) (6) HVR UC, LTN081A, CCP, SBO, SWP-AOV599, HPCS Malfunctions after EOP entry: (1-2) (2) SWP-AOV599, HPCS Abnormal events: (2-4) (2) AOP-1, AOP-50 Major transients: (1-2) (1) SBO EOPs entered: (1-2) (2) EOP-1, EOP-2 EOP contingencies: (0-2) (1) Alternate Level Control Critical tasks: (2-3) (2) Open SWP-AOV599, Maintain Adequate Core Cooling with HPCS Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 1 Page 1 of 9 Event

Description:

Perform OSP-0101 Turbine Generator Periodic Testing Section 4.11.3 Cue: Turnover item.

Time Position Applicants Actions or Behavior Direct the ATC to perform OSP-0101 Turbine Generator Periodic Testing SRO section 4.11.3 as a post maintenance test for pressure switch replacement Perform OSP-0101 Turbine Generator Periodic Testing section 4.11.3

Verify the 5 BRG LIFT PUMP switches are in OFF/RESET.(depress the OFF/RESET push button)

Depress the MSOP LOW PRESS TEST START pushbutton.

Check TML-TGOP TURNING GEAR OIL PMP starts and the white OUTPUT PRESS light comes on.

Depress TML-TGOP TURNING GEAR OIL PMP OFF/RESET ATC pushbutton.

Check the white OUTPUT PRESS light goes off.

Depress the TML-TGOP TURNING GEAR OIL PMP AUTO pushbutton.

Place the 5 BRG LIFT PUMP switches in AUTO.

Report the completion of OSP-0101 Turbine Generator Periodic Testing section 4.11.3 Rev 01

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

Description:

Perform STP-256-0202 Division II Standby Cooling Tower Fans Operability Test Cue: Turnover item.

Time Position Applicants Actions or Behavior Direct the performance of STP-256-0202 Division II Standby Cooling SRO Tower Fans Operability Test Perform STP-256-202 Division II Standby Cooling Tower Fans Operability Test BOP

Check SWP-FN1B, SWP-FN1D, SWP-FN1F, SWP-FN1H, and SWP-FN1K Standby Cooling Tower #1 Fans green status lights are on.

Place SWP-FN1B, 1D, 1F, 1H, 1K STBY CLG TOWER #1 Fans bank hand switch to START and record time the last fan starts.

Check Standby Cooling Tower #1 Fans are operating by observing SWP-FN1B, SWP-FN1D, SWP-FN1F, SWP-FN1H, and SWP-FN1K red status lights are on.

WHEN the Standby Cooling Tower #1 Fans have operated for at least 15 minutes, THEN place SWP-FN1B, 1D, 1F, 1H, 1K STBY CLG TOWER #1 fans bank hand switch to STOP and record time.

Check Standby Cooling Tower #1 Fans are stopped by observing SWP-FN1B, SWP-FN1D, SWP-FN1F, SWP-FN1H, and SWP-FN1K green status lights are on.

Check SWP-FN1M, SWP-FN1P, SWP-FN1R, SWP-FN1T, and SWP-FN1V Standby Cooling Tower #1 Fans green status lights are on.

Place SWP-FN1M, 1P, 1R, 1T, 1V STBY CLG TOWER #1 Fans bank hand switch to START and record time the last fan starts.

Check Standby Cooling Tower #1 Fans are operating by observing SWP-FN1M, SWP-FN1P, SWP-FN1R, SWP-FN1T, and SWP-FN1V red status lights are on.

WHEN the Standby Cooling Tower #1 Fans have operated for at least 15 minutes, THEN place SWP-FN1M, 1P, 1R, 1T, 1V STBY CLG TOWER #1 Fans bank hand switch to STOP and record time Report the completion of STP-256-0202 Division II Standby Cooling Tower Fans Operability Test Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 1 Event No.: 3 Page 3 of 9 Event

Description:

Lower power to 85% to support control rod sequence exchange Cue: Turnover item.

Time Position Applicants Actions or Behavior Direct ATC to lower power with recirc flow to 85%

SRO Accept the direction Lower Reactor Power by lowering recirculation flow:

Verify B33-K603A(B), RECIRC LOOP A(B) FLOW CONTROL M/A Station is in MAN.

Determine which B33-K603A(B), RECIRC LOOP A(B) FLOW CONTROL is to be adjusted by observing Loop Flows on B33-R612A and B33-R612B. Both loops may have to be adjusted to obtain the desired Reactor Power while maintaining Loop Flow mismatch within specification.

ATC

Note the current B33-HYVF060A(B), FLOW CONTROL VALVE position, generator load, MWt, APRMs and loop flows.

Lower Reactor Recirculation Flow by toggling momentarily B33-K603A(B) controller in the closed direction using the slow detent while observing a servo error deviation in the negative direction.

Verify the servo error returns to its previous position.

Observe B33-HYVF060A(B), FLOW CONTROL VALVE position, generator load, MWt, APRMs and loop flows for expected changes.

Repeat steps until the desired Reactor Power Level is achieved.

Report the completion of power reduction Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 4 Page 4 of 9 Event

Description:

HVR-UC1A Containment Unit Cooler trips. (Technical Specifications)

Cue: Annunciator H13-P863-71A-H03. Amber light illuminated at HVR-UC1A breaker indication.

Time Position Applicants Actions or Behavior Recognize and report the trip of HVR-UC1A BOP Refer to alarm response procedure Accept the report SRO Direct the start of HVR-UC1C per the SOP When requested, as the reactor building operator report that there is an ROLE PLAY OC flag down for HVR-UC1A and the breaker indicates tripped.

Accept the direction to start HVR-UC1C BOP

Start the standby HVR-UC1A(B)(C), CONTMT UNIT CLR A(B)(C) and verify the applicable cooling water valve HVN-TV5A(B)(HVN-TV122) opens.

Report to the SRO when HVR-UC1C is started.

Enter Tech Spec 3.6.1.7 A SRO As EM / FIN accept the request to investigate HVR-UC1A ROLE PLAY Inform the SRO not to depress the STOP pushbutton until the investigation is complete.

Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 5 Page 5 of 9 Event

Description:

Level transmitter B21-LTN081A fails downscale (Technical Specifications).

Cue: Annunciator H13-P680-06A-A05.

Time Position Applicants Actions or Behavior Recognize and report that level transmitter B21-LTN081A failed ATC downscale Accept the report SRO Direct BOP to obtain back panel information As the back panel operator report that B21-ESN681 and 682 indicate ROLE PLAY downscale and the trip light is on Report the back panel indication to the SRO BOP Enter Tech Spec 3.3.6.1 A SRO Contact WMC to investigate the instrument failure Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 6 Page 6 of 9 Event

Description:

CCP Pump B trips, CCP Pump A fails to Auto start Cue: Annunciator H13-P870-55A-C04.

Time Position Applicants Actions or Behavior Recognize and report the trip of CCP-P1B BOP Start CCP-P1A per the ARP Refer to AOP-0011 Accept the report for the tripped CCP pump SRO Direct reference to AOP-0011 As the reactor building operator, report that nothing looks abnormal with B ROLE PLAY pump and post start checks are satisfactory for the A pump.

Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 7 Page 7 of 9 Event

Description:

Station Blackout Loss of offsite power Div 1 DG trips Div 2 DG fails to start Cue: Loss of control room lighting, various annunciators, Offsite power supply breakers indicate green lights on, red lights off. Div 1 DG amber trip light, Div 2 DG indicates standby conditions.

Time Position Applicants Actions or Behavior Recognize and report the loss of offsite.

ALL Place the reactor mode switch to Shutdown ATC Give a scram report to the SRO Recognize and report the status of the emergency diesel generators

Div I started and tripped BOP

Div II did not start Attempt to emergency start the Div II diesel generator Accept the scram report Enter EOP-001 RPV Control SRO

Direct a level band of -20 to 51 with HPCS

Direct a pressure band of 500 to 1090 psig with SRVs

Direct implementation of AOP-0050 Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 8 Page 8 of 9 Event

Description:

SWP-AOV599 Standby Cooling Tower Inlet Valve fails to auto open.

Cue: SWP-AOV599 green light on, red light off.

Time Position Applicants Actions or Behavior Implement action of AOP-050 Station Blackout

Verify SWP-P2C, STANDBY SERVICE WATER PUMP running.

Verify SWP-MOV40C, PUMP DISCH VALVE open.

BOP

Verify SWP-AOV599, STBY CLG TWR INLET, STATION BLACKOUT RETURN TO STBY COOLING TOWER open.

Dispatch an operator to attempt an emergency start of the Diesel Generators per Attachment 1 Rev 01

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

Description:

High Pressure Core Spray fails to automatically initiate (Pump only, DG starts on LOP to required SWP-AOV599 actions).

Cue: HPCS Initiation white light is off with Level <-43 inches or manual initiation signal present.

Time Position Applicants Actions or Behavior Recognize and report that the HPCS pump did not automatically start.

Manually start the HPCS pump.

Verify Annunciator P601-16A-G04, HPCS INJECTION LINE PRESSURE LOW, is not lit.

Arm and depress HPCS MANUAL INITIATION Pushbutton.

Verify HPCS PUMP running.

Verify E22-F004, HPCS INJECT ISOL VALVE, Opens.

BOP

Verify HPCS injection flow.

Verify E22-F012, HPCS MIN FLOW VALVE TO SUPPRESSIONPOOL, Closes.

WHEN DESIRED TO STOP INJECTION o If possible reset initiation by depressing E22A-S7 o Close E22-F004, HPCS INJECT ISOL VALVE Report that HPCS is running and injecting.

Rev 01

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station_______________ Scenario No.: __4____ Op-Test No.:

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: Mode 1, 50% power. Plant startup in progress. GOP-0001 Step G.29. (2 FWS pumps in service.) EOOS = 10 GREEN. Non-divisional work week. Division III is Protected Turnover: Remove RWCU F/D A from service per SOP. Start HDL pumps A & C. Then raise power to 55% per reactivity control plan Step 90. Hold at 55% until chemistry is adequate to Pump Forward.

Start RHR in Sup Pool Cooling lineup to support system flush.

Event Malf. No. Event Event No. Type* Description 1 N Remove RWCU F/D A from service (SRO,ATC) 2 N Start Heater Drain Pumps A & C in Recirc mode.

(SRO,BOP) 3 R(ATC) Raise power to 55% with control rods.

4 N Start RHR A Residual Heat Removal Pump in Suppression Pool (SRO,BOP) Cooling mode per SOP-0031 to support system flush to reduce dose rates in pump room.

5 RHR002A C RHR A Residual Heat Removal Pump trips. (Technical (SRO,BOP) Specifications) 6 Overides C (SRO) Containment Monitoring System H2 analyzer failure (Technical Specifications) 7 CNM006 M (ALL) Condensate filter high differential pressure. Total loss of feedwater.

RPS001B Reactor Scram. ARI inserts rods.

8 RCIC001 C Reactor Core Isolation Cooling pump turbine trips, but can be (SRO,BOP) manually reset for level control.

9 MSS111P C MSS-MOV111/112 MSR Steam Supply Valve fails to isolate (SRO,BOP) causing uncontrolled pressure drop.

MSS112P

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total Malfunctions: (5-8) (6) RHR A, CMS, CNM dp, RPS, RCIC, MSS Malfunctions after EOP entry: (1-2) (2) RCIC, MSS Abnormal events: (2-4) (2) AOP-1, AOP-2 Major transients: (1-2) (1) Loss of FW, HPCS injection valve failure EOPs entered: (1-2) (2) EOP-1, EOP-2 EOP contingencies: (0-2) (1) Alternate level control Critical tasks: (2-3) (2) Adequate core cooling with RCIC, Close MSIVs or MSS to avoid exceeding cooldown rate.

Rev 01

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

Description:

Remove RWCU Filter Demin A from service Cue: Turnover item.

Time Position Applicants Actions or Behavior Direct the ATC to remove RWCU Filter Demin from service per the SOP SRO section 5.4 Accept the direction to remove the RWCU Filter Demin from service.

ATC Direct the reactor building operator to perform section 5.4 of SOP-090.

As the reactor building operator when directed, inform the ATC that you ROLE PLAY are ready to perform step 5.4.2 of SOP-090.

Maintain a nearly constant system flow rate as indicated on G33-R609, RWCU INLET FLOW by simultaneously performing the following

Throttle G33-F044, RWCU F/D BYP open.

ATC

Throttle G36-FCR022A(B), F/D FLOW CONTROLLER G36-PNLP002 closed.(reactor building operator)

As the RB operator report that RWCU Filter Demin is out of service.

ROLE PLAY Rev 01

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

Description:

Start HDL Pumps A & C in Recirc mode.

Cue: Turnover item.

Time Position Applicants Actions or Behavior Direct the BOP operator to start HDL-P1A and C Heater Drain pumps in SRO recirc mode per SOP-010 Accept the direction to start Heater Drain Pumps BOP Perform SOP actions to start HDL-P1A and C Heater Drain pumps in recirc mode per SOP-010 Direct the turbine building operator to:

BOP

Close HDL-LV4A, 3RD PT A HTR DRAIN VLV per Attachment 6

Close HDL-LV4B, 3RD PT HTR B DRAIN VLV per Attachment 6 When requested as the TB operator in form the BOP that steps 4.3.1.1 ROLE PLAY and 4.3.1.2 are complete Verify the following Htr Drain Pump Suction Valves are open:

1) HDL-MOV53A, HTR DR PMP 1A SUCT

3) HDL-MOV53C, HTR DR PMP 1C SUCT Verify the following Heater Drain Pump Discharge Valves are closed:

1) HDL-MOV55A, HTR DR PMP 1A DISCH

3) HDL-MOV55C, HTR DR PMP 1C DISCH Open the following Cooling Water Valves:

BOP

1) CCS-AOV57A, PUMP A CLR ISOL VLV

3) CCS-AOV57C, PUMP C CLR ISOL VLV Verify the following Seal Water Valves are open:

1) CNA-AOV5A, PUMP A SEAL WTR VALVE

3) CNA-AOV5C, PUMP C SEAL WTR VALVE Direct the turbine building operator to vent the Heater drain Pump Seal per step 4.3.6.

As the TB operator when requested report that step 4.3.6 is complete ROLE PLAY Rev 01

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

Description:

Start HDL Pumps A & C in Recirc mode. (Cont.)

Time Position Applicants Actions or Behavior

Place HDL-FV20A, HTR DR PUMP 1A RECIRC FLOW CONTROLLER in MANUAL.

BOP

Open HDL-FV20A to 25% open

Open HDL-MOV58A, HTR DR PMP A VENT valve.

Direct the turbine building operator to perform step 4.3.9 As the TB operator when requested report that step 4.3.9 is complete ROLE PLAY

Start HDL-P1A, HTR DR PUMP 1A for Heater String A

Open HDL-MOV55A, HTR DR PMP 1A DISCH valve.

Throttle HDL-FV20A open to no more than 55% to prevent damage to piping and supports.

BOP

Close HDL-MOV58A, HTR DR PMP A VENT valve.

Place HDL-FV20B, HTR DR PUMP 1B RECIRC FLOW CONTROLLER in MANUAL.

Open HDL-FV20B to 25% open.

Direct the turbine building operator to perform step 4.3.15 As the TB operator when requested report that step 4.3.15 is complete ROLE PLAY and the pump is not rotating

Open HDL-MOV58C, HTR DR PMP C VENT valve.

BOP Direct the turbine building operator to perform step 4.3.18 As the TB operator when requested report that step 4.3.18 is complete ROLE PLAY

Start HDL-P1C HTR DR PUMP 1C for Heater String B.

Open HDL-MOV55C, HTR DR PMP 1C DISCH valve.

Throttle HDL-FV20B open to no more than 55% to prevent damage to BOP piping and supports.

Close HDL-MOV58C, HTR DR PMP C VENT valve Direct the turbine building operator to perform step4.3.23 Report to the SRO that HDL-P1A and C are in the recirc mode.

As the TB operator when requested report that step 4.3.23 is complete ROLE PLAY Rev 01

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

Description:

Raise power to 55% with control rods.

Cue: Turnover item.

Time Position Applicants Actions or Behavior Direct the ATC to raise reactor power with control rods per the reactivity SRO control plan Accept the direction to raise power With draw control rods 20-37, 36-37, 36-21 and 20-21 from position 06 to position 12.

Select the rod to be moved

Depress SELECTED GROUP button to check positions of control rods within group are correct prior to movement.

ATC

Check that a Rod Withdrawal Block or Inhibit does not exist.

Depress and hold C11A-S334, WITHDRAW Pushbutton until the IN indicator is lit or the start of rod motion is observed.

Check that the new rod notch position displayed is the next highest even number.

Repeat for all 4 control rods.

Report completion to the SRO.

Rev 01

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

Description:

Start RHR A in Suppression Pool Cooling mode per SOP-0031 to support system flush to reduce dose rates in pump room.

Cue: Turnover item.

Time Position Applicants Actions or Behavior Direct the BOP to start RHR pump A in the suppression pool cooling mode SRO per SOP-0031 Accept the direction Start RHR-A in suppression pool cooling mode

Verify RMS-RE15A is operable OR Chemistry grab sampling is being obtained on the RHR A Heat Exchanger.

On H13-P870, throttle open E12-F068A, RHR HX A SVCE WTR RTN to establish less than or equal to 5800 gpm flow as indicated on E12-R602A, RHR HX A SVCE WTR FLOW.

BOP

Start the E12-C002A, RHR PUMP A.

Open E12-F024A, RHR PUMP A TEST RTN TO SUP PL.

WHEN flow exceeds 1100 gpm, THEN verify E12-F064A, RHR PUMP A MIN FLOW TO SUP PL closes

Check running pump amps are less than or equal to 91 amps.

Throttle closed E12-F048A, RHR A HX BYPASS VALVE to obtain the desired cooling.

Report that RHR pump A is in the suppression pool cooling mode Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 5 Page 6 of 10 Event

Description:

Residual Heat Removal Pump A trips. (Technical Specifications)

Cue: Annunciator H13-P601-20A-E05 Time Position Applicants Actions or Behavior Recognize and report the Residual Heat Removal Pump A has tripped BOP Accept the report Direct the completion of the shutdown section of SOP-0031 SRO Enter Tech Spec 3.5.1 A (ECCS) and 3.6.2.3 A (SPC)

Contact WMC to investigate the trip of RHR pump A

Close E12-F024A, RHR PUMP A TEST RTN TO SUP PL.

Verify open the following:

o E12-F003A, RHR A HX OUTLET VALVE BOP o E12-F048A, RHR A HX BYPASS VALVE o E12-F064A, RHR PUMP A MIN FLOW TO SUP PL

On H13-P870, close E12-F068A, RHR HX A SVCE WTR RTN.

Report that Residual Heat Removal Pump A is shutdown Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 6 Page 7 of 10 Event

Description:

Containment Monitoring System H2 analyzer failure (Technical Specifications)

Cue: Annunciator H13-P808-83A-F04.

Time Position Applicants Actions or Behavior Recognize and report the loss of power to Containment Monitoring System BOP Accept the report SRO Enter TRM 3.3.14 A Contact WMC to investigate CMS power loss.

Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 7 Page 8 of 10 Event

Description:

Condensate filter high differential pressure. Total loss of feedwater. Reactor Scram. ARI inserts rods.

Cue: Rising pressure indicated on CND-PDI138 just prior to annunciator H13-P680-03A-B03, followed by amber trip indication on all 3 feedwater pumps.

Time Position Applicants Actions or Behavior Recognize and report that condensate differential pressure is rising ATC Accept the report SRO Direct the ATC to place the reactor mode switch to shutdown Place the reactor mode switch to S/D ATC Recognize that ARI initiation is required Give the SRO a scram report that includes ARI inserted the control rods Accept the report Enter EOP-001 RPV control

Direct a level band to the BOP of -20 to 51 with RCIC and HPCS SRO

Direct a pressure band the ATC of 500 to 1090 psig with bypass valves and steam line drains.

Assign AOP-001, 002 and 006 actions to the ATC Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 8 Page 9 of 10 Event

Description:

Reactor Core Isolation Cooling turbine trips, but can be manually reset for level control.

Cue: RCIC Trip and Throttle valve position indication green light on, red light off with initiation signal present.

Time Position Applicants Actions or Behavior Recognize and report a loss of all high pressure feed at the P680 panel ATC Direct the BOP to initiate Reactor Core Isolation Cooling SRO Accept the direction

Arm and depress, RCIC MANUAL INITIATION Pushbutton.

Verify the following:

o E51-F045, RCIC STEAM SUPPLY TURBINE STOP VALVE Opens.

o RCIC STEAM SUPPLY and EXHAUST DRAIN POT ISOLATION VALVES Close.

o E51-C002C, GLAND SEAL COMPRESSOR Starts.

o E51-F013, RCIC INJECT ISOL VALVE Opens.

BOP

Verify RCIC Turbine comes up to speed and stabilizes at 2300 - 4600 rpm.

Verify RCIC injection flow.

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

Adjust flow controller as required to achieve desired injection rate.

Recognize and report the Reactor Core Isolation Cooling turbine has tripped Recognize and report that HPCS injection valve has lost power.

Accept the report that RCIC has tripped SRO Direct the BOP to reset the RCIC turbine trip Accept the direction to reset RCIC BOP Direct the Reactor building operator to reset the RCIC turbine As the reactor building operator when requested inform the BOP that ROLE PLAY Reactor Core Isolation Cooling Turbine has been reset Restart RCIC to maintain given level band BOP Recognize and report that the High Pressure Core Spray injection valve BOP breaker has tripped Contact Work Management Center about the High Pressure Core Spray SRO injection valve.

Rev 01

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: Scenario No.: 4 Event No.: 9 Page 10 of 10 Event

Description:

MSS-MOV111/112 fails to isolate causing uncontrolled pressure drop.

Cue: MSS-MOV111/112 red lights off, green lights on following turbine trip.

Time Position Applicants Actions or Behavior Recognize and report that reactor pressure is lowering due to unknown ATC reasons Accept the report of reactor pressure lowering SRO Direct the BOP and ATC to investigate the pressure loss.

Recognize and report that the MSR steam supply valves did not respond BOP / ATC as designed Direct the closure of MSS-MOV111 and 112 MSR Steam Supply Valves SRO or MSIVs to avoid exceeding the cooldown rate.

Close the MSS-MOV111 and 112 MSR Steam Supply Valve or MSIVs BOP prior to exceeding the cooldown rate.

Rev 01

ML110450185

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