Text

RBS - Init Exam - 02/2003 - Draft Operating Exam
	ML030640611
Person / Time
Site:	River Bend
Issue date:	12/10/2002
From:	Persons R; Entergy Operations
To:	; Office of Nuclear Reactor Regulation
References
	-RFPFR, 50-458/03-301
	Download: ML030640611 (258)
	v • d • e

RBS JOB PERFORMANCE MEASURE ES-301 RO Admin Topic No. A.1.1 JPM NUMBER: 976-03 Rev. 0, ADMIN TASK DESCRIPTION: Complete Daily Log Verification of Power Distribution Limits during Single Loop Operation.

K/A REFERENCE & RATING: 2.1.19 (3.0/3.0)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: X Simulator: X In-Plant: X COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP NA Prepared by: Roger Persons 0862 12/04/02 KCN DATE:

Ops Validation: Joseph Clark 0260 12/10/02 KCN DATE:

Approved by: Mike Wagner 0035 12/10/02 KCN DATE:

JPM-97603.00 Page 1 of 7

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Complete Daily Log Verification of Power Distribution Limits during Single Loop Operation.

Required Power: NA IC No.: NA Notes: Administrative JPM that does not require simulator.

JPM-97603.00 Page 2 of 7

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: STP-000-0001, Daily Operating Logs GOP-0004, Single Loop Operation Required Materials: STP-000-0001, Daily Operating Logs, Data Sheet 1 GOP-0004, Single Loop Operation Required Plant Condition: 60% Power Applicable Objectives: HLO-, Objectives Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-97603.00 Page 3 of 7

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: The 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 114 of STP-000-0001, Data Sheet 1 with the attached Core Performance Log data.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. STEP 114 NOTES Refer to administrative limits in GOP-0004 Step 3.4. CUE: Reactor Engineering has not implemented the appropriate core Power Distribution Limits shall be verified to monitoring system thermal limit deck.

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% 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.

JPM-97603.00

Denotes Critical Step Page 4 of 7

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

2. GOP-0004 Step 3.4 CUE: If asked as CRS, Reactor Engineering has not implemented the During Single Loop Operation, an appropriate core monitoring system administrative limit of 0.980 shall be applied thermal limit deck.

to MFLCPR and an administrative limit of Uses 0.980 Admin limit for MFLCPR and 0.79 for 0.79 shall be applied to MAPRAT while MAPRAT.

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.

3. Reviews Core Performance Log to obtain Fills in Step 114 identifying MAPRAT at 0.811as CUE: As CRS, acknowledge values for MFLPD, MAPRAT, and exceeding SLO administrative limit. MAPRAT exceeding limit.

MFLCPR for operating log Step 114.

Notifies CRS of MAPRAT exceeding limit.

Terminating Cue: Step 114 of STP-000-0001, Data Sheet 1 completed and MAPRAT identified as exceeding limit.

JPM-97603.00

Denotes Critical Step Page 5 of 7

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-97603.00 Page 6 of 7

RBS JOB PERFORMANCE MEASURE 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 114 of STP-000-0001, Data Sheet 1 with the attached Core Performance Log data.

Terminating Cue: Step 114 of STP-000-0001, Data Sheet 1 completed.

JPM-97603.00 Page 7 of 7

RBS JOB PERFORMANCE MEASURE ES-301 RO Admin Topic No. A.1.2 JPM NUMBER: 201-03 Rev. 0, ADMIN TASK DESCRIPTION: Determine Fuse Removal Required for SLC Squib A and Effects on Control Room Status Indication.

K/A REFERENCE & RATING: 2.1.24 (2.8/3.1)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: X Simulator: X In-Plant:

COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP NA Prepared by: Roger Persons 0862 12/09/02 KCN DATE:

Ops Validation: Joseph Clark 0260 12/10/02 KCN DATE:

Approved by: Mike Wagner 0035 12/10/02 KCN DATE:

JPM-20103.00 Page 1 of 7

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Determine the effects of a failed component on system operation.

Required Power: NA IC No.: NA Notes: Administrative JPM that does not require simulator.

JPM-20103.00 Page 2 of 7

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: GE Elementary 828E234AA Required Materials: GE Elementary 828E234AA Required Plant Condition: 100% Power Applicable Objectives: HLO-542, Objectives 4 & 5 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-20103.00 Page 3 of 7

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: Maintenance requires the A SLC Squib Valve C41-F004A to be de-energized.

Initiating Cue: The CRS has directed you to do the following:

1. Determine the fuses (by identifying number) that must be removed to de-energized Squib Valve C41-F004A.

2. Provide the exact physical location of the fuses by panel and terminal board.

3. Identify the impact of fuse removal on Control Room front panel indication and/or alarm status.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Locates correct plant electrical print. Locates fuses on GE Elementary 828E234AA

2. Identifies Fuse Numbers and physical States Fuses F2 and F3 in Panel P632, Terminal location. Board TB0010.

JPM-20103.00

Denotes Critical Step Page 4 of 7

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. Identifies impact of fuse removal on Control States fuse removal will:

Room indication and/or alarm status.

De-energize squib continuity white light on P601.

Energize (or turn on) the Amber postage stamp Loss of Continuity to Squib Valve A or Loss of Power.

Standby Liquid System A Inoperative annunciator will alarm.

Terminating Cue: Provided fuse identification, location and impact on Control Room front panel indications and/or alarms.

JPM-20103.00

Denotes Critical Step Page 5 of 7

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-20103.00 Page 6 of 7

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: Maintenance requires the A SLC Squib Valve C41-F004A to be de-energized.

Initiating Cues: The CRS has directed you to do the following:

1. Determine the fuses (by identifying number) that must be removed to de-energized Squib Valve C41-F004A.

2. Provide the exact physical location of the fuses by panel and terminal board.

3. Identify the impact of fuse removal on Control Room front panel indication and/or alarm status.

Terminating Cue: Provided fuse identification, location and impact on Control Room front panel indications and/or alarms.

JPM-20103.00 Page 7 of 7

RBS JOB PERFORMANCE MEASURE ES-301 RO Admin Topic No. A.2 JPM NUMBER: 204-08, Rev. 0 ADMIN TASK DESCRIPTION: Perform Independent Verification of A RHR Heat Exhanger tagout K/A REFERENCE & RATING: 2.2.13 (3.6/3.8)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: Simulator: X In-Plant:

COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): Yes SAFETY FUNCTION GROUP NA Prepared by: Roger Persons 0862 12/05/02 KCN DATE Ops Validation: Joseph Clark 0260 12/10/02 KCN DATE Approved by: Mike Wagner 0035 12/10/02 KCN DATE JPM-20408.00 Page 1 of 6

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Perform Independent Verification of A RHR Heat Exhanger tagout.

Required Power: NA IC No.: 148 Notes: 1. Close E12-F003A RHR A HX Outlet Valve and place switch cover tag for the Inlet Valve on the control switch

2. Close E12-F047A RHR A HX Inlet Valve and place switch cover tag for the Outlet Valve on the control switch

3. Close and tag remaining P601 control switches per attached Clearance form.

JPM-20408.00 Page 2 of 6

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: ADM-0076, Verfication Program ADM-0027, Protective Tagging Required Materials: Tagging Sheet for RHR A Heat Exchanger Clearance RB-00-0326 Required Plant Condition: Any Applicable Objectives: HLO-201, Objective 2 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-20408.00 Page 3 of 6

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: A Clearance has been authorized for the A RHR Heat Exhanger. The RHR system component lineup has been completed and the tags have been hung.

Initiating Cue: The CRS has given you the attached tagging sheet and directed you to perform an Independent Verification of the tags on P601 for the A RHR Heat Exchanger Clearance RB-00-0326.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Verifies tags on P601 Section 21 for the A Verifies all tagged components are in the proper CUE: As CRS, direct operator to RHR Heat Exhanger Clearance. position and the tag numbers match the tag sheet. remove the incorrectly placed tags and return them to you.

Identifies incorrect placement of RHR HX Inlet Valve and Outlet Valve tags. NOTE: It is satisfactory for the candidate to remove the tags and Informs CRS of tagging discrepancy. deliver them to the CRS when informing you of the tagging error.

2. Removes incorrectly placed tags. Incorrectly placed tags removed and given to CRS CUE: As CRS, direct operator to for disposition. initiate a Condition Report for the tagging error Terminating Cue: Independent verification has been completed and incorrectly placed tags removed.

JPM-20408.00

Denotes Critical Step Page 4 of 6

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-20408.00 Page 5 of 6

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A Clearance has been issued for the A RHR Heat Exhanger.

The RHR system component lineup has been completed and the tags are hung.

Initiating Cues: The CRS has given you the attached tagging sheet and directed you to perform an Independent Verification of the tags on P601 for the A RHR Heat Exhanger Clearance RB-00-0326.

Terminating Cue: Independent Verification of P601 portion of the A RHR Heat Exhanger Clearance has been completed.

JPM-20408.00 Page 6 of 6

RBS JOB PERFORMANCE MEASURE ES-301 RO Admin Topic No. A.3 JPM NUMBER: 001-01, Rev. 0 ADMIN TASK DESCRIPTION: Entry and Exit from Controlled Access Area Including Entry Into A Contamination Zone.

K/A REFERENCE & RATING: 2.3.1 (2.6/3.0) 2.3.4 (2.5/3.1)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: X Actual Performance: X Control Room: Simulator: In-Plant: X COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO & SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP NA Prepared by: Roger Persons 0862 12/06/02 KCN DATE:

Ops Validation: Joseph Clark 0260 12/10/02 KCN DATE:

Approved by: Mike Wagner 0035 12/10/02 KCN DATE:

JPM-00101.00 Page 1 of 8

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Entry and Exit from Controlled Access Area Including Entry Into A Contamination Zone.

Required Power: NA IC No.: NA Notes: Administrative JPM that will be conducted in the plant in conjunction with other JPMs performed in the CAA.

JPM-00101.00 Page 2 of 8

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: EOI Rad Worker Training Required Materials: Standard personal safety equipment for entry into CAA RWP and Survey Map for entering Contamination Area Required Plant Condition: Any Applicable Objectives: RWT01 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-00101.00 Page 3 of 8

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

NOTE: Explain to the Candidate that you will be observing and grading the radiological practices performed by the candidate during the entry, activities inside the CAA, and exit of the CAA.

Inform the candidate part of the JPM will involve entry into a contamination zone . ACTUAL ENTRY WILL NOT BE REQUIRED.

Initial Conditions: With the plant at power, .

Initiating Cue: The CRS has directed you to enter a Contamination Zone to reposition a valve.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Informs the Health Physics Candidate may review the survey map and determine NOTE: The Evaluator may be Technician/Supervisor at the HP desk at only single PCs are required OR may discuss with required to discuss the entry in CAA entrance that part of his Job will involve HP Desk. Either is acceptable. There is NO pre- private with the Health Physics entry into the area around the fuel pool heat Job brief required to enter a Contamination Area. personnel this is only a test and the exchangers OR reviews the survey map and operator will NOT be entering the determines the area is a contamination area. High Contamination Area.

Per the RWP 2002-1002 entry into contamination areas requires single PCs and NO Pre-Job Brief.

JPM-00101.00

Denotes Critical Step Page 4 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

2. Obtain Electronic Alarming Dosimeter (EAD) Candidate will obtain an EAD and insert the EAD NOTE: The RWP Number will be from the rack outside the CAA entranceand into the activation slot and SCAN the bar code on his either 2002-1002 or 2002-1005 activate at the access turnstile using TLD and follow instructions on the screen. Entering either RWP number is acceptable appropriate Radiation Work Permit (RWP) RWP number and answering the questions on the dependent on the candidates number, and enters CAA when access is computer fields of the access terminal. Once all fields authorization.

granted. have been entered appropriately access is granted.

3. Dons personal safety equipment as required Hard hat, safety glasses and ear plugs worn where inside the CAA. required in the CAA.

4. While in CAA the candidate observes and While in CAA the candidate observes and adheres to NOTE: None of the areas for the adheres to ALL applicable Postings and ALL applicable Postings and entry requirements. JPMs should access any High entry requirements. Radiation Areas or Contamination Areas.

5. Exiting of the CAA the candidate enters the Candidate clears PCM-1 Monitor and exits. NOTE: If candidate shows radon control point area and enters a PCM-1 contamination portions of apparel Monitor. such as hard hat may be left with Health Physics for decay.

6. If hand carried materials were carried into the Candidate will place hand carried items in the TCM CAA they will be cleared through the Tool for counting.

Contamination Monitor (TCM).

7. After clearing the PCM-1 the candidate exits Candidate clears Portal Monitor and exits.

through the Portal Monitor.

JPM-00101.00

Denotes Critical Step Page 5 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

8. Deactivates Merlin Guerlin at terminal at final Candidate will deactivate his EAD and return it to exit of session. Health Physics rack.

Terminating Cue: Entry and egress from CAA completed.

JPM-00101.00

Denotes Critical Step Page 6 of 8

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-00101.00 Page 7 of 8

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: With the plant at power, Initiating Cues: The CRS has directed you to enter a Contamination Zone to reposition a valve.

Terminating Cue: Entry and egress from CAA completed.

JPM-00101.00 Page 8 of 8

RBS JOB PERFORMANCE MEASURE ES-301 RO Admin Topic No. A.4 JPM NUMBER: 940-02, Rev. 1 ADMIN TASK DESCRIPTION: Make Required EP Notifications K/A REFERENCE & RATING: 2.4.39 (3.3/3.1) 2.4.43 (2.8/3.5)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: X Actual Performance:

Control Room: Simulator: X In-Plant:

COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP NA Prepared by: Roger Persons 0862 12/05/02 KCN DATE:

Ops Validation: Fred Hurst 0628 12/09/02 KCN DATE:

Approved by: Mike Wagner 0035 12/10/02 KCN DATE:

JPM-94002.01 Page 1 of 7

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Make Required EP Notifications Required Power: NA IC No.: NA Notes: Ensure the ESP-COMM computer is setup with Station in control Simulator.

JPM-94002.01 Page 2 of 7

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: EIP-2-006, Notifications Required Materials: EIP-2-006, Notifications Completed Short Notification Message Form Required Plant Condition: Any Applicable Objectives: EP-23, Objective 1 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-94002.01 Page 3 of 7

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: An ongoing fire on the 116 elevation of the Control Building has damaged both Control Building Filter trains. The Fire Brigade Leader expects to have the fire extinguished within the next 20 minutes. The Shift Manager/Emergency Director has just classified this event as a Site Area Emergency. The normal communicator was incapacitated by smoke from the fire.

Initiating Cue: The CRS has provided you the Short Notification Form and directed you to make the required notifications to state and local authorities per EIP-2-006, Notifications. [NOTE: Message transmittal should be SIMULATED.]

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Verify Station in Control is appropriate. Station in Control Simulator NOTE: Computer will be set up with station in control Simulator.

2. Click on Start Event button Start Event screen opens.

3. Select Drill Status Drill Status selected.

4. Click OK

5. Select Site Area Emergency from Site Area Emergency selected.

Classification pull-down menu.

JPM-94002.01

Denotes Critical Step Page 4 of 7

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

6. Requests Emergency Director Review Requested CUE: As Emergency Director verify Site Area Emergency information from short form.

7. Click on transmit Window to choose Group opens. Terminate the JPM Terminating Cue: Notifications made to state and local authorities for Site Area Emergency.

JPM-94002.01

Denotes Critical Step Page 5 of 7

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-94002.01 Page 6 of 7

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: An ongoing fire on the 116 elevation of the Control Building has damaged both Control Building Filter trains.

The Fire Brigade Leader expects to have the fire extinguished within the next 20 minutes.

The Shift Manager/Emergency Director has just classified this event as a Site Area Emergency.

The normal communicator was incapacitated by smoke from the fire.

Initiating Cues: The CRS has provided you the Short Notification Form and directed you to make the required notifications to state and local authorities per EIP-2-006, Notifications. [NOTE: Message transmittal should be SIMULATED.]

Terminating Cue: Notifications made to state and local authorities for Site Area Emergency.

JPM-94002.01 Page 7 of 7

RBS JOB PERFORMANCE MEASURE ES-301 SRO Admin Topic No. A.1.1 JPM NUMBER: 053-07, Rev. 1 ADMIN TASK DESCRIPTION: Perform Calculations Per GOP-0004 For Entering Single Loop Operation K/A REFERENCE & RATING: 2.1.7 (3.7/4.4)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: Simulator: X In-Plant:

COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP NA Prepared by: Roger Persons 0862 12/05/02 KCN DATE:

Ops Validation: Joseph Clark 0260 12/10/02 KCN DATE:

Approved by: Mike Wagner 0035 12/10/02 KCN DATE:

JPM-05307.01 Page 1 of 7

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Perform Calculations Per GOP-0004 For Entering Single Loop Operation Required Power: 60%

IC No.: 139 Notes: Loop B Flow recorder pen on C51-R614 is failed downscale requiring use of Group Point B33NA007 or 8 for Flow Calculation.

Ensure Steam Tables are available JPM-05307.01 Page 2 of 7

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: GOP-0004, Single Loop Operation, Attachment 1 Required Materials: GOP-0004, Single Loop Operation, Attachment 1 Required Plant Condition: 60% Power Applicable Objectives: HLO-, Objectives Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-05307.01 Page 3 of 7

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

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

Initiating Cue: The CRS has directed you to complete Step 4 of GOP-0004, Attachment 1.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Within one hour of entering Single Loop Operation, verify the following:

Thermal Power is less than or equal to 79%

Rated Thermal Power (2400 MWTH)

Determines power to be 60% +/-1%.

_______CMWTH=___________% <79%

3039 (TSR 3.4.1.1.2)

2. AND Verifies both Recirc FCV M/A Stations in MANUAL.

At H13-P680, B33-HYVF060A and B33-HYVF060B, FLOW CONT VALVE, AMBER lights ON.

is in LOOP MANUAL. (TSR 3.4.1.1.3)

JPM-05307.01

Denotes Critical Step Page 4 of 7

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. Total loop flow in running loop is less than 33 NA Step 1. Obtain flow from C51-R614, LOOP NOTE: Loop B Flow recorder pen kgpm using one of the following methods A/B FLOW RECORDER, for the operating loop. on C51-R614 is failed downscale (N/A method not used): (TSR 3.4.1.1.1) requiring use of Group Point B33NA007 or 8 for Flow Calculation.

4. Use computer point for the operating loop (LOOP A - B33NA005 or B33NA006; LOOP B - B33NA007 or B33NA008) and convert from mlbm/hr to kgpm using the following formula:

______ x _______ x (124.68) = _______

(flow) (sv) (kgpm) Determines flow to be 30 kgpm where flow = loop flow from computer point in mlbm/hr.

sv = specific volume from steam tables (Vf)

(dependent on loop temp) in ft3/lbm.

Terminating Cue: Step 4 of GOP-0004, Attachment 1 is completed.

JPM-05307.01

Denotes Critical Step Page 5 of 7

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-05307.01 Page 6 of 7

RBS JOB PERFORMANCE MEASURE 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.

Initiating Cues: The CRS has directed you to complete Step 4 of GOP-0004, Attachment 1.

Terminating Cue: Step 4 of GOP-0004, Attachment 1 is completed.

JPM-05307.01 Page 7 of 7

RBS JOB PERFORMANCE MEASURE ES-301 SRO Admin Topic No. A.1.2 JPM NUMBER: 256-04, Rev. 0 ADMIN TASK DESCRIPTION: Complete LCO Status Sheet for Inoperative Div.1 Standby Diesel Generator.

K/A REFERENCE & RATING: 2.1.12 (2.9/4.0)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: X Simulator: X In-Plant: X COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP NA Prepared by: Roger Persons 0862 12/08/02 KCN DATE:

Ops Validation: Joseph Clark 0260 12/12/02 KCN DATE:

Approved by: Mike Wagner 0035 12/12/02 KCN DATE:

JPM-25604.00 Page 1 of 7

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Complete LCO Status Sheet for Inoperative Div.1 Standby Diesel Generator.

Required Power: NA IC No.: NA Notes: Administrative JPM that does not require simulator.

JPM-25604.00 Page 2 of 7

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: OSP-0040, LCO Tracking And Safety Function Determination Program Tech Spec 3.8.1, AC Sources - Operating Required Materials: LCO Status Sheet Technical Specifications Required Plant Condition: Mode 1 Applicable Objectives: HLO-408, Objective 2 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-25604.00 Page 3 of 7

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: The leak in the Service Water supply to the Division 1 Standby Diesel Generator has been discovered and isolated at 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months today.

The Division 1 Standby Diesel Generator has been declared inoperable. No other Technical Specification LCOs exist at this time.

Restoration of Service Water to the Diesel is expected to take about 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Initiating Cue: Complete attached LCO Status Sheet LCO No.03-016 for the Inoperative Division1 Standby Diesel Generator.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Complete LCO Status Sheet Blocks 5, 6, Completes LCO Status Sheet Blocks 5, 6, and 8 per and 8. attached LCO Status Sheet.

2. Provide a brief description of the Completes LCO Status Sheet Block 10 per attached Condition(s) entered. All conditions that LCO Status Sheet.

must be entered due to the inoperability should be documented.

JPM-25604.00

Denotes Critical Step Page 4 of 7

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. Provide the Required Actions if the TS/TRM Completes LCO Status Sheet Block 11 per attached LCO is not met. LCO Status Sheet.

4. Record the Completion Time associated with Completes LCO Status Sheet Block 12 per attached each Required Action. LCO Status Sheet.

5. When an LCO is entered for a system Completes LCO Status Sheet Blocks 13 through 15 designated as a support system in Attachment per attached LCO Status Sheet.

1, Support - Supported LCO Matrix of this procedure, evaluate the operability of the supported system. If T.S. 3.0.6 is to be used to prevent entering Conditions and Required Actions for supported systems, perform an evaluation per T.S. 5.5.10 to ensure that no loss of safety function exists.

Terminating Cue: LCO Status Sheet LCO No.03-016 for the Inoperative Division1 Standby Diesel Generator completed.

JPM-25604.00

Denotes Critical Step Page 5 of 7

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-25604.00 Page 6 of 7

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The leak in the Service Water supply to the Division 1 Standby Diesel Generator has been discovered and isolated at 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months today.

The Division 1 Standby Diesel Generator has been declared inoperable.

No other Technical Specification LCOs exist at this time.

Restoration of Service Water to the Diesel is expected to take about 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Initiating Cues: Complete attached LCO Status Sheet LCO No.03-016 for the inoperative Division1 Standby Diesel Generator.

Terminating Cue: LCO Status Sheet LCO No.03-016 for the Inoperative Division1 Standby Diesel Generator completed.

JPM-25604.00 Page 7 of 7

RBS JOB PERFORMANCE MEASURE ES-301 SRO Admin Topic No. A.2 JPM NUMBER: 204-09, Rev. 0 ADMIN TASK DESCRIPTION: Perform Review and Authorization of HPCS Tagout K/A REFERENCE & RATING: 2.2.13 (3.6/3.8)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: X Simulator: X In-Plant: X COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): Yes SAFETY FUNCTION GROUP NA Prepared by: Roger Persons 0862 12/05/02 KCN DATE:

Ops Validation: Joseph Clark 0260 12/12/02 KCN DATE:

Approved by: Mike Wagner 0035 12/12/02 KCN DATE:

JPM-20409.00 Page 1 of 6

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Perform review and authorization of HPCS tagout Required Power: NA IC No.: NA Notes: Administrative JPM that does not require simulator.

JPM-20409.00 Page 2 of 6

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: ADM-0027, Protective Tagging Required Materials: Tagging Sheet for HPCS Clearance LCO Status Sheet for LPCS Inop Required Plant Condition: 100% Power Applicable Objectives: HLO-201, Objective 8 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-20409.00 Page 3 of 6

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: The plant is in Mode 1. The Tagging Official hands you, the CRS, a clearance for authorization to remove HPCS from service to perform a required maintenance item.

Initiating Cue: As CRS, review and authorize the attached tagout for HPCS, RB-02-0136, current LCOs attached.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Reviews tagout against LCO status Requests LCO Status information.

information.

2. Determines authorization of tagout. Does not authorize tagout based on RCIC inoperability Terminating Cue: Review completed and not authorized based on LPCS inoperability.

JPM-20409.00

Denotes Critical Step Page 4 of 6

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-20409.00 Page 5 of 6

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is in Mode 1.

The Tagging Official hands you, the CRS, a clearance for authorization to remove HPCS from service to perform a required maintenance item.

Initiating Cues: As CRS, review and authorize the attached tagout for HPCS, RB-02-0136, current LCOs attached.

Terminating Cue: Review and authorization of HPCS, RB-02-0136 completed.

JPM-20409.00 Page 6 of 6

RBS JOB PERFORMANCE MEASURE ES-301 SRO Admin Topic No. A.3 JPM NUMBER: 001-01, Rev. 0 ADMIN TASK DESCRIPTION: Entry and Exit from Controlled Access Area Including Entry Into A Contamination Zone.

K/A REFERENCE & RATING: 2.3.1 (2.6/3.0) 2.3.4 (2.5/3.1)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: X Actual Performance: X Control Room: Simulator: In-Plant: X COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO & SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP NA Prepared by: Roger Persons 0862 12/06/02 KCN DATE:

Ops Validation: Joseph Clark 0260 12/10/02 KCN DATE:

Approved by: Mike Wagner 0035 12/10/02 KCN DATE:

JPM-00101.00 Page 1 of 8

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Entry and Exit from Controlled Access Area Including Entry Into A Contamination Zone.

Required Power: NA IC No.: NA Notes: Administrative JPM that will be conducted in the plant in conjunction with other JPMs performed in the CAA.

JPM-00101.00 Page 2 of 8

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: EOI Rad Worker Training Required Materials: Standard personal safety equipment for entry into CAA RWP and Survey Map for entering Contamination Area Required Plant Condition: Any Applicable Objectives: RWT01 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-00101.00 Page 3 of 8

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

NOTE: Explain to the Candidate that you will be observing and grading the radiological practices performed by the candidate during the entry, activities inside the CAA, and exit of the CAA.

Inform the candidate part of the JPM will involve entry into a contamination zone . ACTUAL ENTRY WILL NOT BE REQUIRED.

Initial Conditions: With the plant at power, .

Initiating Cue: The CRS has directed you to enter a Contamination Zone to reposition a valve.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Informs the Health Physics Candidate may review the survey map and determine NOTE: The Evaluator may be Technician/Supervisor at the HP desk at only single PCs are required OR may discuss with required to discuss the entry in CAA entrance that part of his Job will involve HP Desk. Either is acceptable. There is NO pre- private with the Health Physics entry into the area around the fuel pool heat Job brief required to enter a Contamination Area. personnel this is only a test and the exchangers OR reviews the survey map and operator will NOT be entering the determines the area is a contamination area. High Contamination Area.

Per the RWP 2002-1002 entry into contamination areas requires single PCs and NO Pre-Job Brief.

JPM-00101.00

Denotes Critical Step Page 4 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

2. Obtain Electronic Alarming Dosimeter (EAD) Candidate will obtain an EAD and insert the EAD NOTE: The RWP Number will be from the rack outside the CAA entranceand into the activation slot and SCAN the bar code on his either 2002-1002 or 2002-1005 activate at the access turnstile using TLD and follow instructions on the screen. Entering either RWP number is acceptable appropriate Radiation Work Permit (RWP) RWP number and answering the questions on the dependent on the candidates number, and enters CAA when access is computer fields of the access terminal. Once all fields authorization.

granted. have been entered appropriately access is granted.

3. Dons personal safety equipment as required Hard hat, safety glasses and ear plugs worn where inside the CAA. required in the CAA.

4. While in CAA the candidate observes and While in CAA the candidate observes and adheres to NOTE: None of the areas for the adheres to ALL applicable Postings and ALL applicable Postings and entry requirements. JPMs should access any High entry requirements. Radiation Areas or Contamination Areas.

5. Exiting of the CAA the candidate enters the Candidate clears PCM-1 Monitor and exits. NOTE: If candidate shows radon control point area and enters a PCM-1 contamination portions of apparel Monitor. such as hard hat may be left with Health Physics for decay.

6. If hand carried materials were carried into the Candidate will place hand carried items in the TCM CAA they will be cleared through the Tool for counting.

Contamination Monitor (TCM).

7. After clearing the PCM-1 the candidate exits Candidate clears Portal Monitor and exits.

through the Portal Monitor.

JPM-00101.00

Denotes Critical Step Page 5 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

8. Deactivates Merlin Guerlin at terminal at final Candidate will deactivate his EAD and return it to exit of session. Health Physics rack.

Terminating Cue: Entry and egress from CAA completed.

JPM-00101.00

Denotes Critical Step Page 6 of 8

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-00101.00 Page 7 of 8

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: With the plant at power, Initiating Cues: The CRS has directed you to enter a Contamination Zone to reposition a valve.

Terminating Cue: Entry and egress from CAA completed.

JPM-00101.00 Page 8 of 8

RBS JOB PERFORMANCE MEASURE ES-301 SRO Admin Topic No. A.4 JPM NUMBER: 980-01, Rev. 0 ADMIN TASK DESCRIPTION: Determine Protective Action Recommendations K/A REFERENCE & RATING: 2.4.44 (2.1/4.0)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: X Simulator: X In-Plant: X COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP NA Prepared by: Roger Persons 0862 12/07/02 KCN DATE:

Ops Validation: Joseph Clark 0260 12/10/02 KCN DATE:

Approved by: Mike Wagner 0035 12/10/02 KCN DATE:

JPM-98001.00 Page 1 of 7

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Determine Protective Action Recommendations Required Power: NA IC No.: NA Notes: Administrative JPM that does not require simulator.

JPM-98001.00 Page 2 of 7

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: EIP-2-007, Protective Action Recommendation Guidelines Required Materials: EIP-2-007, Protective Action Recommendation Guidelines Required Plant Condition: Shutdown with release in progress Applicable Objectives: EP-42.12, Objective 11 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-98001.00 Page 3 of 7

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: A General Emergency has been declared due to a release in progress following a large break LOCA inside containment. Minimum Protective Action Recommendations were issued. Due to the combination of Hydrogen Concentration and Containment pressure, Emergency Containment Venting is now required.

Initiating Cue: As acting Recovery Manager, determine the appropriate Protective Action Recommendations and complete a Notification of General Emergency short form using the attached dose projections and meteorological information.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Use (EIP-2-007) Attachments 1, 2, and 3 to Uses EIP-2-007 Attachment 2 to evaluate and formulate Protective Action Attachment 3 to determine PAR scenario number.

Recommendations (PARs).

2. Determines upgraded PARs are required. PAR upgraded to Scenario 19 and Notification short form completed.

Terminating Cue: Notification of General Emergency short form completed.

JPM-98001.00

Denotes Critical Step Page 4 of 7

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-98001.00 Page 5 of 7

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A General Emergency has been declared due to a release in progress following a large break LOCA inside containment.

Minimum Protective Action Recommendations were issued.

Due to the combination of Hydrogen concentration and Containment pressure, Emergency Containment Venting is now required.

Initiating Cues: As acting Recovery Manager, determine the appropriate Protective Action Recommendations and complete a Notification of General Emergency short form using the attached dose projections and meteorological information.

Terminating Cue: Notification of General Emergency short form completed.

JPM-98001.00 Page 6 of 7

RBS JOB PERFORMANCE MEASURE DOSE ASSESSMENT for Emergency Containment Venting DISTANCE DOSE RATE CALCULATIONS TEDE Dose (REM): CEDE Dose (REM)

Site Boundary 3.95E1 Site Boundary 6.02E-1 2 Miles 6.49E0 2 Miles 1.06E-1 5 Miles 1.08E0 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° Delta T -0.8°F Stability Class D JPM-98001.00 Page 7 of 7

RBS JOB PERFORMANCE MEASURE ES-301 RO/SRO-I and SRO-U Systems JPM No. B.1.1 JPM NUMBER: 053-08, Rev. 0 TASK DESCRIPTION: Restart Recirculation Pump A in Fast Speed Following Trip at Power (with Suction Temperature Alarm Before Start)

K/A REFERENCE & RATING: 202001 K1.10 (2.8/2.8) A4.10 (3.3/3.4)

A2.21 (3.3/3.7) A4.01 (3.7/3.7) 202002 K4.02 (3.0/3.0)

TASK

REFERENCE:

202008001001 TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: Simulator: X In-Plant:

COMPLETION TIME: 15 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): Yes SAFETY FUNCTION GROUP 1 Prepared by: Roger Persons 862 12/02/02 KCN DATE:

Ops Validation: Steve Fiore 0124 12/07/02 KCN DATE:

Approved by: Mike Wagner 0035 12/09/02 KCN DATE:

JPM-05308.00 Page 1 of 8

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Restart Recirculation Pump A in Fast Speed Following Trip at Low Power (with Suction Temperature Alarm Before Start)

Required Power: 38%

IC No.: 148 Notes: Insert Annunciator Override, P680_04a:c_2, t1 Turn down intensity on PMS screens at P680 to simulate it being out of service.

JPM-05308.00 Page 2 of 8

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: SOP-0003, Reactor Recirculation System (SYS #053)

Required Materials: SOP-0003, Reactor Recirculation System (SYS #053)

Required Plant Condition: 38% Power Applicable Objectives: STM-053, Objectives H11 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-05308.00 Page 3 of 8

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: The A Reactor Recirc Pump tripped during a plant startup. The plant has been in GOP-0004 Single Loop Operation for the last six hours. GOP-0004, Attachement 1 was completed. The cause of the trip has been determined and the A Reactor Recirc Pump is ready to be started. Attachment 2, Return to Two Loop Operation has been completed through Step 2 and the Recirculation Pump Startup in SOP-0003 has been completed through Step 4.10. An extra Control Room Operator is standing by to provide temperature reading from P614 since PMS is out of service.

Initiating Cue: The CRS has directed you to complete restarting the idle Recirculation Pump A per SOP-0003, Reactor Recirculation.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Depress B33-C001A(B), RECIRC PUMP RELEASE pushbutton depressed. PUSH TO LOCK button releases A(B) MOTOR BREAKER 5A(B) and Annunciatior P680-04A-E01, RELEASE pushbutton on the STOP/PUSH RECIRC PUMP A AUTO TO LOCK control switch. TRANSFER CIRCUIT INOP clears.

2. Verify B33-C001A(B) PUMP A(B) MOT BRKR 4A is closed.

BRKR 4A(B) is closed. RED light ON, GREEN light OFF JPM-05308.00

Denotes Critical Step Page 4 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. Depress B33-C001A(B) PUMP A(B) MOT BRKR 3A is closed. NOTE: As soon as Breaker 3A is BRKR 3A(B) CLOSE pushbutton. closed, activate trigger t1 to insert RED light ON, GREEN light OFF override P680_04a:c_2 to initiate P680-04A-C02 alarm.

4. Silence and acknowledge annunciator P680- Annunciator P680-04A-C02, silenced and NOTE: ALTERNATE PATH 04A-C02, RECIRC PUMP A TEMP acknowledged.

INTERLOCK ACTUATED.

5. Requests P614 status of vessel drain and P614 temperatures requested. CUE: At P614, cause of alarm is recirc loop suction temperatures. Loop Suction ?T 51°F.

6. Verify B33-F023A, RECIRC PUMP A Both valves are open. CUE: Time compression used to SUCTION VLV and B33-F067A, RECIRC move 10 minutes forward. At P614, RED lights ON, GREEN lights OFF PUMP A DISCH VLV are open. the Loop Suction ?T is now 40°F.

7. Close C11-F024A, RX RECIRC PMP A Contacts Reactor Building Operator to close C11- CUE: Reactor Building Operator SEAL PURGE LINE ISOL VLV. F024A. has closed C11-F024A NOTE: Alarm P680-04A-C02 C11-F024A is closed. clears.

8. Reopen C11-F024A immediately prior to Contacts Reactor Building Operator to open C11- CUE: Reactor Building Operator starting the recirc pump F024A. has opened C11-F024A.

C11-F024A is open.

JPM-05308.00

Denotes Critical Step Page 5 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

9. Resets annunciator P680-04A-C02, Annunciator P680-04A-C02, reset.

RECIRC PUMP A TEMP INTERLOCK ACTUATED.

10. IF one pump is operating in FAST SPEED B33-C001A RECIRC PUMP A MOTOR AND the idle pump is to be operated in BREAKER 5A closed and pump running.

FAST SPEED, THEN depress the B33-C001A RECIRC PUMP A MOTOR Breaker 5A closed.

BREAKER 5A control switch for the Recirc RED lights ON, GREEN lights OFF Pump to be started and perform the following:

Starting current dies back down to running current.

1) Verify B33-C001A RECIRC PUMP A MOTOR BREAKER 5A closes.

2) Check for a surge on B33-R609A, PUMP A AMPS as the Recirc Pump accelerates to full speed of 1800 RPM.

JPM-05308.00

Denotes Critical Step Page 6 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

11. Monitor Recirc Pump A and Jet Pump Monitors Pump DP and JP Loop A Total Flow Operation at the following:

1) Pump A Diff Press on B33-R605A, PUMP A DP.

2) JP Loop A Total Flow on B33-R612A, TOTAL FLOW.

3) The following seal flow annunciators are clear:

Annunciators cleared (were not alarming during

Annunciator P680-04A- evolution).

C05, RECIRC PUMP A SEAL CLG WATER LOW FLOW

Annunciator P680-04A-E05, RECIRC PUMP A SEAL STAGING HIGH/LOW FLOW Terminating Cue: Reactor Recirc Pump A is running at Fast Speed.

JPM-05308.00

Denotes Critical Step Page 7 of 8

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-05308.00 Page 8 of 9

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The A Reactor Recirc Pump tripped during a plant startup.

The plant has been in GOP-0004 Single Loop Operation for the last six hours.

GOP-0004, Attachement 1 was completed.

The cause of the trip has been determined and the A Reactor Recirc Pump is ready to be started.

Attachment 2, Return to Two Loop Operation has been completed through Step 2 and the Recirculation Pump Startup in SOP-0003 has been completed through Step 4.10.

An extra Control Room Operator is standing by to provide temperature reading from P614 since PMS is out of service.

Initiating Cues: The CRS has directed you to complete restarting the idle Recirculation Pump A per SOP-0003, Reactor Recirculation.

Terminating Cue: Reactor Recirc Pump A is running at Fast Speed.

JPM-05308.00 Page 9 of 9

RBS JOB PERFORMANCE MEASURE ES-301 RO/SRO-I Systems JPM No. B.1.2 JPM NUMBER: 501-03, Rev. 0 TASK DESCRIPTION: Transfer from Startup Feedwater Level Controller to the Master Feedwater Level Controller K/A REFERENCE & RATING: 259002 K5.01 (3.1/3.10) A4.03 (3.8/3.6)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: Simulator: X In-Plant:

COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP 2 Prepared by: Roger Persons 0862 12/01/02 KCN DATE:

Ops Validation: Steve Fiore 0124 12/07/02 KCN DATE:

Approved by: Mike Wagner 0035 12/09/02 KCN DATE:

JPM-50103.00 Page 1 of 8

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Transfer from Startup Feedwater Level Controller to the Master Feedwater Level Controller.

Required Power: 10%

IC No.: 145 Notes: A FWREG Valve in service 1 ELEM/3 ELEM pushbutton in 1 ELEM Startup Level Controller in operation set at 36 inches JPM-50103.00 Page 2 of 8

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: SOP-0009, Reactor Feedwater System (SYS #107)

Required Materials: SOP-0009, Reactor Feedwater System (SYS #107)

Required Plant Condition: Plant startup at 10% power Applicable Objectives: STM-107B, Objectives H2, H3, H5, and H9 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-50103.00 Page 3 of 8

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: A plant startup is in progress and reactor power is 10%. RPV level is being maintained with the Startup Level Controller. One Reactor Feed Pump and one Condensate Pump in operation. FWREG Valve A is in service.

Initiating Cue: The CRS has directed you to transfer from the Startup Level Controller to the Master Level Controller to control level at 36 inches.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Check feedwater flow is approximately 10% Feedwater flow ~10% or 1.31 x 106 lbm/hr or 1.31 x 106 lbm/hr.

2. Verify 1 ELEM is selected on the SINGLE 1 ELEM selected.

ELEMENT THREE ELEMENT SELECT Switch JPM-50103.00

Denotes Critical Step Page 4 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. Place C33-R600, FW REG VALVES Tape Set 2 inches above actual level, deviation signal MASTER FLOW CONTROLLER in positive AUTO as follows:

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

4. 2. Lower tape set 2 inches below actual Tape Set 2 inches above actual level, deviation signal vessel level and observe the deviation negative signal is negative.

5. 3. Match tape set to actual vessel level Tape Set to match actual level.

in order to null the deviation signal.

6. 4. Depress the AUTO Pushbutton and GREEN light on, YELLOW light off.

check the green light above the pushbutton is on.

7. Place C33-R602, START UP FWREG YELLOW light on, GREEN light off.

VALVE FLOW CONTROLLER in MANUAL.

8. Use the manual CLOSE Pushbutton on C33-FV002 closed, level maintained.

C33-R602, START UP FWREG VALVE FLOW CONTROLLER to close C33-FV002, START UP FWREG Valve while ensuring reactor level is maintained by the Master Level Controller.

JPM-50103.00

Denotes Critical Step Page 5 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

9. Adjust C33-R600, FW REG VALVES Tape Set to 36 inches.

MASTER FLOW CONTROLLER Tape Set to maintain the reactor level requested by the OSS/CRS.

Terminating Cue: Master Level Controller in AUTO and Single Element Control with Tape Set for 36 inches.

JPM-50103.00

Denotes Critical Step Page 6 of 8

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-50103.00 Page 7 of 8

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A plant startup is in progress and reactor power is 10%.

RPV level is being maintained with the Startup Level Controller.

One Reactor Feed Pump and one Condensate Pump in operation.

FWREG Valve A is in service.

Initiating Cues: The CRS has directed you to transfer from the Startup Level Controller to the Master Level Controller to control level at 36 inches.

Terminating Cue: Master Level Controller in AUTO and Three Element Control with Tape Set for 36 inches.

JPM-50103.00 Page 8 of 8

RBS JOB PERFORMANCE MEASURE ES-301 RO/SRO-I Systems JPM No. B.1.3 and SRO-U JPM No. B.1.2 JPM NUMBER: 109-05, Rev. 0 TASK DESCRIPTION: Open Inboard MSIVs After Closure During Plant Startup K/A REFERENCE & RATING: 239001 K4.09 (3.3/3.3) A4.01 (4.2/4.0)

A4.01 (3.2/3.2)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: Simulator: X In-Plant:

COMPLETION TIME: 15 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP 2 Prepared by: Roger Persons 0862 12/01/02 KCN DATE:

Ops Validation: Joseph Clark 0260 12/10/02 KCN DATE:

Approved by: Mike Wagner 0035 12/10/02 KCN DATE:

JPM-10905.00 Page 1 of 8

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Open Inboard MSIVs After Closure During Plant Startup Required Power: 2%

IC No.: 146 Notes: Requires an additional operator/instructor to maintain RPV water level and silence any annunciators during evolution.

JPM-10905.00 Page 2 of 8

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: SOP-0011, Main Steam System (SYS #109)

Required Materials: SOP-0011, Main Steam System (SYS #109)

Required Plant Condition: Plant startup at Point of Adding Heat, ~600 psig Applicable Objectives: STM-109, Objective H7 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-10905.00 Page 3 of 8

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: The Inboard MSIVs were closed during a plant startup. The heatup and pressurization will continue when the MSIVs are reopened.

Initiating Cue: The CRS has directed you to open the Inboard MSIVs using SOP-0011, beginning at Step 4.2.10.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Verify closed the following: All listed valves are closed.

B21-MOVF021, MSL WARMUP GREEN light ON HDR COND DRAIN BYP VALVE RED light OFF

B21-AOVF033, MSL WARMUP HDR COND DRAIN VALVE

B21-MOVF068, MSL DRAIN HDR COND DRAIN BYP VALVE

B21-AOVF069, MSL DRAIN HDR COND DRAIN VALVE JPM-10905.00

Denotes Critical Step Page 4 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

2. Verify open the following: All listed valves are open.

B21-MOVF016, MSL WARMUP RED light ON HDR INBD CONTMT ISOL VLV GREEN light OFF

B21-MOVF019, MSL WARMUP HDR OUTBD CONTMT ISOL VLV

B21-MOVF085, MSL WARMUP HDR SHUTOFF VALVE

3. Open slowly B21-MOVF020, MSL B21-MOVF020 slowly opened.

WARMUP HDR SUPPLY VALVE to equalize pressure across the inboard MSIVs.

4. Monitor differential pressure across the Monitors differential pressure. PROCEDURE NOTE: Opening inboard MSIVs using the following: an MSIV can cause a Reactor water level transient. Slowly opening the

C33-R605, REACTOR MSIV using the OPEN/SLOW PRESSURE TEST position and intermittent

MSS-PI101, MAIN STEAM release of the TEST Pushbutton can HEADER PRESSURE mitigate the level transient.

JPM-10905.00

Denotes Critical Step Page 5 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

5. WHEN differential pressure across the All MSIV switches in AUTO after differential NOTE: May use OPEN/SLOW inboard MSIVs is less than or equal to 50 pressure is less than or equal to 50 psid. TEST to slowly open MSIVs or psid, THEN place the following switches in place control switch in AUTO, either AUTO to open the inboard MSIVs: is satisfactory.

B21-AOVF022A, MSL A INBD MSIV

B21-AOVF022B, MSL B INBD MSIV

B21-AOVF022C, MSL C INBD MSIV

B21-AOVF022D, MSL D INBD MSIV

6. Check inboard MSIVs are open. All Inboard MSIVs are open.

RED light ON GREEN light OFF

7. On H13-P622, observe the indicating lights Requests backpanel indication for inboard MSIV CUE: On P622, indicating lights and and ammeters to confirm the energization of solenoids. ammeters confirm both solenoids on both solenoids on each inboard MSIV. each Inboard MSIV are energized.

Terminating Cue: All Inboard MSIVs are open.

JPM-10905.00

Denotes Critical Step Page 6 of 8

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-10905.00 Page 7 of 8

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The Inboard MSIVs were closed during a plant startup.

The heatup and pressurization will continue when the MSIVs are reopened.

Initiating Cues: The CRS has directed you to open the Inboard MSIVs using SOP-0011, beginning at Step 4.2.10.

Terminating Cue: All Inboard MSIVs are open.

JPM-10905.00 Page 8 of 8

RBS JOB PERFORMANCE MEASURE ES-301 RO/SRO-I Systems JPM No. B.1.4 JPM NUMBER: 203-07, Rev. 0 TASK DESCRIPTION: Shutdown HPCS following Spurious Automatic Initiation (with Line Fill Pump Trip)

K/A REFERENCE & RATING: 209002 K1.03 (3.0/3.0) K4.01 (2.9/3.0)

A3.01 (3.3/3.3) A4.01 (3.7/3.7)

A4.07 (2.8/2.8)

TASK

REFERENCE:

206016001001 TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: Simulator: X In-Plant:

COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): Yes SAFETY FUNCTION GROUP 4 Prepared by: Roger Persons 862 12/01/02 KCN DATE:

Ops Validation: Steve Fiore 0124 12/07/02 KCN DATE:

Approved by: Mike Wagner 0035 12/09/02 KCN DATE:

JPM-20307.00 Page 1 of 8

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Shutdown HPCS following Spurious Automatic Initiation (with Line Fill Pump Trip)

Required Power: 100%

IC No.: 151 Notes:

1. Insert manual scram and complete AOP-0001 immediate actions.

2. Manually initiate HPCS.

3. Establish RPV level at 35 inches.

4. Setup trigger t1 to initiate HPCS Line Fill Pump Trip JPM-20307.00 Page 2 of 8

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: SOP-0030, High Pressure Core Spray (SYS #203)

Required Materials: SOP-0030, High Pressure Core Spray (SYS #203)

ARP-P601-16A Required Plant Condition: 100% Power Applicable Objectives: STM-203, Objectives H4 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-20307.00 Page 3 of 8

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: The plant is operating at rated conditions and HPCS spuriously initiated. Adequate core cooling is assured and was verified by two independ means. RPV level is stable and the ATC is standing by to shutdown HPCS.

Initiating Cue: The CRS has directed you to coordinate with the ATC and shutdown HPCS returning it to standby lineup.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Verify E22A-S2, HPCS MANUAL Collar in DISARM position (rotated fully counter-INITIATION collar is in the DISARM clockwise).

position.

2. Depress E22A-S7, HPCS INITIATION White light above RESET pushbutton off.

RESET Pushbutton and check the white light goes off.

JPM-20307.00

Denotes Critical Step Page 4 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. Verify the following valves are closed: Listed valves are closed.

E22-F023, HPCS TEST RETURN VLV TO SUPPRESSION POOL

E22-F010, HPCS TEST BYPASS VLV TO CST

E22-F011, HPCS TEST RETURN VALVE TO CST

E22-F004, HPCS INJECT ISOL Informs ATC he will be securing HPCS injection VALVE flow.

4. WHEN flow lowers below 625 gpm on E22- E22-F012 opens below 625 gpm (following pump R603, HPCS FLOW, THEN verify trip in Step 6).

E22-F012, HPCS MIN FLOW VALVE TO SUPPRESSION POOL opens.

5. IF E22-PC003, HPCS LINE FILL PUMP E22-PC003 running.

is not running, THEN start E22-PC003.

6. Trip E22-ACB02, HPCS PUMP SUPPLY E22-ACB02 open BRKR.

JPM-20307.00

Denotes Critical Step Page 5 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

7. WHEN HPCS Pump discharge pressure E22-F012 closed. NOTE: As pressure drops below lowers below 300 psig on E22-R601, HPCS 100 psig, insert malfunction PUMP DISCH PRESSURE, THEN verify HPCS003 with t1 to trip Line Fill E22-F012, HPCS MIN FLOW VALVE Pump.

TO SUPPRESSION POOL closes.

NOTE: ALTERNATE PATH

8. Silence and acknowledge annunciator P601- Annunciator P601-16A-G04 silenced and 16A-G04, HPCS INJECTION LINE acknowledged PRESSURE LOW.

9. Attempt to start the HPCS LINE FILL Attempts start, Fill Pump remains tripped. NOTE: ARP-P601-16A-G04 from PUMP if not running. here on.

10. IF unable to start the HPCS LINE FILL Communicates ARP recommendation to CRS. CUE: CRS directs placing HPCS in PUMP, THEN consider placing HPCS in Suppression Pool to Suppression operation as following: Pool recirc mode.

11. 1. Close the E22-F001, HPCS PUMP E22-F001 closed.

CST SUCTION VALVE.

12. 2. Open the E22-F015, HPCS PUMP E22-F015 open.

SUP PL SUCTION VALVE.

13. 3. Start the HPCS Pump and verify HPCS Pump running and E22-F012 open E22-F012, HPCS MIN FLOW VALVE TO SUPPRESSION POOL opens.

JPM-20307.00

Denotes Critical Step Page 6 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

14. 4. Throttle open E22-F023, HPCS Flow on E22-F603, 2000 - 3000 gpm CUE: Evaluator terminates JPM TEST RETURN VLV TO SUPPRESSION POOL to achieve flow of 2000 - 3000 gpm as indicated on E22-F603.

Terminating Cue: HPCS Pump running in Suppression Pool to Suppression Pool recirc mode.

JPM-20307.00

Denotes Critical Step Page 7 of 8

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions :

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-20307.00 Page 8 of 8

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is operating at rated conditions and HPCS spuriously initiated.

Adequate core cooling is assured and was verified by two independ means.

RPV level is stable and the ATC is standing by to shutdown HPCS.

Initiating Cues: The CRS has directed you to coordinate with the ATC and shutdown HPCS returning it to standby lineup.

Terminating Cue: HPCS Pump shutdown in Standby Mode.

JPM-20307.00 Page 9 of 8

RBS JOB PERFORMANCE MEASURE ES-301 RO/SRO-I JPM No. B.1.5 JPM NUMBER: 309-05, Rev. 0 TASK DESCRIPTION: Parallel Offsite Power With Div 1 EDG Supplying ENS-SWG1A.

K/A REFERENCE & RATING: 264000 A2.01 (3.5/3.6) A2.05 (3.6/3.6)

A4.02 (3.4/3.4) 295003 AA1.02 (4.2/4.3)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: Simulator: X In-Plant:

COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: Yes ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP 6 Prepared by: Roger Persons 0862 12/01/02 KCN DATE:

Ops Validation: Joseph Clark 0260 12/10/02 KCN DATE:

Approved by: Mike Wagner 0035 12/10/02 KCN DATE:

JPM-30905.00 Page 1 of 7

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Parallel Offsite Power With Div 1 EDG Supplying ENS-SWG1A.

Required Power: Cold Shutdown following a Loss of Offsite Power IC No.: 140 Notes:

JPM-30905.00 Page 2 of 7

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: AOP-0004, Loss of Offsite Power SOP-0053, Standby Diesel Generator and Auxiliaries (SYS#309)

Required Materials: SOP-0053, Standby Diesel Generator and Auxiliaries (SYS#309)

Required Plant Condition: 0% power following LOP Applicable Objectives: STM-053S, Objectives H12 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-30905.00 Page 3 of 7

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: A Loss of Offsite Power has occurred with the plant in cold shutdown. AOP-0004, Loss of Offsite Power was entered and all required actions taken. Plant conditions are stable and Offsite power is being restored to the plant per AOP-0004, Section 5.16.

AOP-0004 has been completed through Step 5.16.11.

Initiating Cue: The CRS has directed you to parallel Offsite Power to the ENS-SWG1A per SOP-0053 using the normal supply breaker ACB06.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. IF ENS-ACB06(26), NORMAL SUPPLY REMOTE SYNC SW to NORM.

BRKR is to be closed, THEN place the REMOTE SYNC SW to NORM.

2. Adjust diesel voltage, as observed on V- RUNNING VOLTAGE to approximately 1- 2 volts 1RUN-1SYDA(B)01, RUNNING above V-1IN-1SYDA(B)01, INCOMING VOLTAGE to approximately 1- 2 volts VOLTAGE.

above V-1IN-1SYDA(B)01, INCOMING VOLTAGE using the STBY DIESEL GENERATOR A(B) VOLTAGE REGULATOR CONT.

JPM-30905.00

Denotes Critical Step Page 4 of 7

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. Adjust diesel speed, using the STBY SYNCHROSCOPE indicator is rotating slowly in the DIESEL GENERATOR A(B) SLOW direction.

GOVERNOR CONTROL, to bring the frequency within the range of grid frequency.

Adjust speed so the SY-1-SYDA(B)01, STBY BUS A(B) SYNCHROSCOPE indicator is rotating slowly in the SLOW direction (counterclockwise).

4. WHEN the synchroscope indicator is moving NORMAL SUPPLY BRKR closed.

slowly in the SLOW direction AND the RED light ON synchroscope indicator is 5 minutes to 2 minutes before the 12 o'clock position, GREEN light OFF THEN close the desired feeder breaker, ENS-ACB06(26), NORMAL SUPPLY BRKR or ENS-ACB04(24), ALTERNATE SUPPLY BRKR. Verify the red breaker closed light comes ON. If not, return the breaker handswitch to TRIP.

5. As soon as diesel load has stabilized, return REMOTE SYNC SW returned to OFF the REMOTE SYNC SW to OFF and shutdown Standby Diesel Generator per Section 6.1 of this procedure.

Terminating Cue: Offsite Power paralleled with ENS-SWG1A.

JPM-30905.00

Denotes Critical Step Page 5 of 7

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-30905.00 Page 6 of 7

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A Loss of Offsite Power has occurred with the plant in cold shutdown. AOP-0004, Loss of Offsite Power was entered and all required actions taken.

The plant is stable and Offsite power is available.

Electrical power from Offsite is being returned to station busses.

Initiating Cues: The CRS has directed you to parallel Offsite Power to the ENS-SWG1A per SOP-0053 using the normal supply breaker ACB06.

Terminating Cue: Offsite Power paralleled with ENS-SWG1A.

JPM-30905.00 Page 7 of 7

RBS JOB PERFORMANCE MEASURE ES-301 RO/SRO-I Systems JPM No. B.1.6 JPM NUMBER: 500-02, Rev. 0 TASK DESCRIPTION: Bypass Control Rod position information in RACS Cabinets K/A REFERENCE & RATING: 214000 A4.01 (3.2/3.3) 201005 K1.05 (3.5/3.5) A2.02 (2.8/3.2)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: X Actual Performance:

Control Room: X Simulator: In-Plant:

COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP 7 Prepared by: Roger Persons 0862 12/01/02 KCN DATE:

Ops Validation: Robert Peek 0546 12/07/02 KCN DATE:

Approved by: Mike Wagner 0035 12/09/02 KCN DATE:

JPM-50002.00 Page 1 of 7

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Bypass Control Rod position information in RACS Cabinets Required Power: NA IC No.: NA Notes: This JPM is to be performed in the Main Control Room.

JPM-50002.00 Page 2 of 7

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: SOP-0071, Rod Control and Information System (SYS

500)

Required Materials: SOP-0071, Rod Control and Information System (SYS

500)

Required Plant Condition: Any Applicable Objectives: STM-500, Objective H14 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-50002.00 Page 3 of 7

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: A reactor startup is in progress. Due to failed Rod Position Indication channels on Control Rod 24-17, the RC&IS Pattern Controller has initiated a Control Rod Withdrawal Block. In order to continue the startup, it is necessary bypass Control Rod 24-17 in the RACS Cabinets.

Initiating Cue: The CRS has directed you to bypass both Rod Position Indication channels for Control Rod 24-17 in the RACS Cabinets..

PERFORMANCE STEP STANDARD S/U COMMENTS

1. On Attachment 5, Full Core Map, determine Obtains address for CR 24-17 as X coordinate = NOTE: Key must be obtained to the binary numbers corresponding to the 00010 and Y coordinate = 00110 open plexiglass covers in RACS.

column (X) and the row (Y) coordinates for covers need NOT be opened.

the rod to be bypassed.

2. On H13-P651, Rod Bypass File A3, enter Demonstrates entering X coordinate = 00010 and Y NOTE: Inform candidate, plexiglass the address obtained above into the Bypass coordinate = 00110 using Ident Select Switches covers need NOT be opened.

Cards Ident Select Switches of one bypass card.

JPM-50002.00

Denotes Critical Step Page 4 of 7

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. On H13-P652, Rod Bypass File A3, enter Demonstrates entering X coordinate = 00010 and Y the same address as Step 5.10.2 into the coordinate = 00110 using Ident Select Switches Bypass Cards Ident Select Switches of one bypass card.

4. On H13-P651, Rod Bypass File A3, place Demonstrates placing BYPASS SWITCH in CUE: BYPASS SWITCH in the BYPASS SWITCH in the BYPASSED BYPASSED position BYPASSED Position on the effected card.

5. On H13-P652, Rod Bypass File A3, place Demonstrates placing BYPASS SWITCH in CUE: BYPASS SWITCH in the BYPASS SWITCH in the BYPASSED BYPASSED position BYPASSED Position on the effected card.

6. Check that the BYPASSED LED comes on Requests ATC to check POSITION BYP. LED ON CUE: As ATC at P680, GREEN for the correct Control Rod. for Control Rod 22-17 on P680. POSITION BYP. LED is ON for Control Rod 22-17.

7. Direct a second technically qualified operator Requests verification from second operator. CUE: JPM is terminated.

to verify the Control Rod position information is bypassed correctly.

Terminating Cue: Both Rod Position Indication channels in the RACS for Control Rod 24-17 are bypassed.

JPM-50002.00

Denotes Critical Step Page 5 of 7

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-50002.00 Page 6 of 7

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A reactor startup is in progress.

Due to failed Rod Position Indication channels on Control Rod 24-17, the RC&IS Pattern Controller has initiated a Control Rod Withdrawal Block.

In order to continue the startup, it is necessary bypass Control Rod 24-17 in the RACS Cabinets.

Initiating Cues: The CRS has directed you to bypass both Rod Position Indication channels for Control Rod 24-17 in the RACS Cabinets.

Terminating Cue: Both Rod Position Indication channels in the RACS for Control Rod 24-17 are bypassed.

JPM-50002.00 Page 7 of 7

RBS JOB PERFORMANCE MEASURE ES-301 RO/SRO-I Systems JPM No. B.1.7 SRO-U JPM No. B.1.3 JPM NUMBER: 403-03, Rev. 3 TASK DESCRIPTION: Place the Drywell in High Volume Purge Using Standby Gas Treatment Train A.

K/A REFERENCE & RATING: 261000 K1.01 (3.4/3.6) K1.02 (3.0/3.4)

A4.01 (3.2/4.0) A4.03 (3.0/3.0) 288000 A2.04 (3.7/3.8) A4.01 (3.1/2.9) 272000 A1.01 (3.2/3.2)

TASK

REFERENCE:

2223120101 TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: Simulator: X In-Plant:

COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP 9 Prepared by: Roger Persons 0862 12/02/02 KCN DATE:

Ops Validation: Steve Fiore 0124 12/07/02 KCN DATE:

Approved by: Mike Wagner 0035 12/09/02 KCN DATE:

JPM-40303.03 Page 1 of 9

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Place the Drywell in High Volume Purge Using Standby Gas Treatment Train A.

Required Power: 0%, Cold Shutdown Mode 4 IC No.: 147 Notes:

1. Remove HOLD Tags from dampers HVR-AOV125 & 126 and HVR-AOV147 &148 P863.

2. imf RMS-RE103, 2.00 E-7

3. Caution statement does not allow operation of the Drywell Purge valves in Modes 1, 2 or 3.

JPM-40303.03 Page 2 of 9

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: SOP-0059, Containment HVAC System (SYS #403)

Required Materials: SOP-0059, Containment HVAC System (SYS #403)

Required Plant Condition: Cold Shutdown Mode 4 Applicable Objectives: STM-403, Objectives H2, H7, and H8 STM-257, Objectives H3, H5, H6, and H7 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-40303.03 Page 3 of 9

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: The plant is shutdown and depressurized in Mode 4. Drywell Purge is required prior to opening the Drywell for maintenance access.

Administrative controls on HVR-AOV125 & 126, DW PURGE BACKUP ISOL and HVR-AOV147 & 148, DW PURGE ISOL have been released and the HOLD tags on P863 removed.

Initiating Cue: The CRS has directed you to place the Reactor Building HVAC in Drywell High Volume Purge using Standby Gas Treatment Train A, GTS-FN1A using SOP-0059, begining at Step 5.7.3.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Verify the following dampers are open: Both dampers are open. CUE: If requested, confirm that the plant is in MODE 4.

HVR-AOD164, UP STREAM ISOL SUPPLY

HVR-AOD143, DN STREAM ISOL SUPPLY JPM-40303.03

Denotes Critical Step Page 4 of 9

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

2. Open the following dampers and valves: All listed dampers are open.

HVR-AOV165, CONTMT SPLY OUTBD ISOL

HVR-AOV123, CONTMT SPLY INBD ISOL

HVR-AOV125 & 126, DW PURGE BACKUP ISOL

HVR-AOV147 & 148, DW PURGE ISOL

HVR-AOV128, CONTMT RTN INBD ISOL

HVR-AOV166, CONTMT RTN OUTBD ISOL

HVR-AOD245, CONTMT PURGE TO SGT

HVR-AOD162, CONTMT PURGE TO SGT JPM-40303.03

Denotes Critical Step Page 5 of 9

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. Start GTS-FN1A(B), SGT EXH FAN A(B) Standby Gas Treatment GTS-FN1A START by depressing the START Pushbutton and pushbutton depressed.

verify the following:

1. GTS-AOD1A(B), SGT FILTER A(B) SUCT ISOL opens.

2. GTS-FN1A(B), SGT EXH FAN A(B) starts.

3. GTS-AOD3A(B), SGT EXH FAN A(B) DISCH opens.

4. IF an Annulus Mixing System Initiation is Monitor P863 for annunciators NOTE: Annulus Mixing will not received, THEN take action in accordance receive and initiation signal.

with the associated annunciator Alarm Response Procedures.

5. Place HVR-FN8, HIGH VOL Demonstrates raising Lever and releasing Lever when CUE: Engine has started.

CONTMT/DW PURGE to START and engine has started..

verify HVR-AOD244, HIGH VOL FAN DISCH opens.

JPM-40303.03

Denotes Critical Step Page 6 of 9

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

6. Verify proper filter operation by observing CUE: Reactor Building Operator the following differential pressure and responds that he will check GTS radiation indications: Dispatch Reactor Building Operator to check GTS Filter Train A local indications

GTS-FLT1A(B), SGT FILTER Filter Train A local indications.

TRAIN local component differential pressure instruments Monitor radiation indications CUE: Radiation monitors are

RMS-RE21A&B, CONTMT operating and reading less than PURGE ISOL ALERT alarm values with no

RMS-RE103, SGT FILTER EXH unexpected trends RAD MONITOR Terminating Cue: Drywell High Volume Purge is in progress using Standby Gas Treatment Train A, GTS-FN1A.

JPM-40303.03

Denotes Critical Step Page 7 of 9

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-40303.03 Page 8 of 9

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant is shutdown and depressurized in Mode 4.

Drywell Purge is required prior to opening the Drywell for maintenance access.

Administrative controls on HVR-AOV125 & 126, DW PURGE BACKUP ISOL and HVR-AOV147 & 148, DW PURGE ISOL have been released and the HOLD tags on P863 removed.

Initiating Cues: The CRS has directed you to place the Reactor Building HVAC in Drywell High Volume Purge using Standby Gas Treatment Train A, GTS-FN1A using SOP-0059, begining at Step 5.7.3.

Terminating Cue: Drywell High Volume Purge is in progress using Standby Gas Treatment Train A, GTS-FN1A.

JPM-40303.03 Page 9 of 9

RBS JOB PERFORMANCE MEASURE ES-301 RO/SRO-I and SRO-U Systems JPM No. B.2.1 JPM NUMBER: 800-21, Rev. 1 TASK DESCRIPTION: Establish Emergency Containment Venting per EOP Enclosure 21 K/A REFERENCE & RATING: 223002 K1.10 (3.1/3.2) K4.08 (3.3/3.7) 50000 EK1.01 (3.3/3.9)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: X Actual Performance:

Control Room: X Simulator: In-Plant: X COMPLETION TIME: 15 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP 5 Prepared by: Roger Persons 0862 12/03/02 KCN DATE:

Ops Validation: Robert Peek 0546 12/07/02 KCN DATE:

Approved by: Mike Wagner 0035 12/09/02 KCN DATE:

JPM-80021.01 Page 1 of 9

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Establish Emergency Containment Venting per EOP Enclosure 21 Required Power: NA IC No.: NA Notes: This JPM is to be performed in the Main Control Room and the Plant.

JPM-80021.01 Page 2 of 9

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: EOP-0005, Enclosure 21, Emergency Containment Venting and Defeating Containment Vent Path Isolation Interlocks Required Materials: EOP-0005, Enclosure 21, Emergency Containment Venting and Defeating Containment Vent Path Isolation Interlocks Key to Control Room Emergency Locker Required Plant Condition: Any Applicable Objectives: HLO-516, Objective 1 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-80021.01 Page 3 of 9

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: A large break LOCA has occurred in the Drywell. Containment pressure is 12 psig and Containment Hydrogen concentration cannot be maintained in the Safe Zone of the Hydrogen Deflagration Overpressure Limit (HDOL). Normal Containment Vent and Purge, Hydrogen Mixing and the Hydrogen Recombiners have been secured. EOP-0005, Enclosure 16, Defeating Containment Instrument Air Isolation Interlocks has been installed.

Initiating Cue: The CRS has directed you install EOP-0005, Enclosure 21, Emergency Containment Venting and Defeating Containment Vent Path Isolation Interlocks.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. OBTAIN EOP-0005 ENCL 21 jumper kit Obtains jumper kit.

from the Control Room Emergency Locker.

2. INSPECT kit for 2 jumpers Kit contains two jumpers.

JPM-80021.01

Denotes Critical Step Page 4 of 9

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. DEFEAT isolation interlocks as follows: Locates P852 Bay E and describes installation of CUE: Jumper No.1 installed.

1. Location:1H13*P852 Bay E(left side Jumper No. 1.

of bay)

Affected Terminal Boards:

TB0175 (5th row of terminal boards from door, 2nd board from top)

TB0317(2nd row of terminal boards from door, top terminal board)

Jumper No. 1 JUMPER Terminal 12 on TB0175 to Terminal 2 on TB0317 JPM-80021.01

Denotes Critical Step Page 5 of 9

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

4. 2. Location: 1H13*P952 Bay A Locates P952 Bay A and describes installation of CUE: Jumper No.2 installed.

Jumper No. 2.

Affected Relay: 45-1HVRB20 (2nd row of relays from top, 4th relay from left)

Jumper No. 2 JUMPER Terminal M1 on Relay Block 45-1HVRB20.

to Terminal R1 on Relay Block 45-1HVRB20.

5. OPEN 1HVR*AOV128 CONTMT RTN At P863, demonstrates opening 1HVR*AOV128 CUE: CRS directs you to open INBD ISOL as directed by the CRS. 1HVR*AOV128.

CUE: 1HVR*AOV128 RED light on, GREEN light off

6. VENT Primary Containment as follows: Obtains ENCL 21 Key. CUE: BYPASS SWITCH in BYPASSED

1. OBTAIN EOP-0005 ENCL 21 key, one (1) for CPP-PNL102.

7. 2. VERIFY the Annulus Mixing System Describes Annulus Mixing System configuration with CUE: Annulus Mixing in operation in operation with flow to SGTS. flow to SGTS. with flow to SGTS.

JPM-80021.01

Denotes Critical Step Page 6 of 9

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

8. 3. VERIFY the SGTS in operation with Verifies SGTS flow to Main Plant Stack. CUE: SGTS is aligned to Main flow to the main plant exhaust duct. Plant Stack.

9. 4. VERIFY 1IAS*MOV107 INST Verifies both MOVs are open. CUE: 1IAS*MOV107 and AIR SHUTOFF VALVE AND 1IAS*MOV106 both have RED 1IAS*MOV106 INST AIR light on, GREEN light off OUTBD ISOL are open (1H13*P870)

10. 5. VERIFY 1HVR*AOV128 Verifies AOV is open. CUE: 1HVR*AOV128 RED light CONTMT RTN INBD ISOL is on, GREEN light off open (1H13*P863).

11. 6. OPEN 1HVR-AOD127 CONTMT Demonstrates opening 1HVR-AOD127 CUE: 1HVR-AOD127 RED light PURGE RTN ISOL (1H13*P863). on, GREEN light off.

12. 7. OPEN 1CPP*MOV105 H2 Locates panel, opens door with key and CUE: CPP*MOV105 RED light PURGE FAN DISCH VALVE TO demonstrates opening CPP*MOV105 on, GREEN light off..

ANNULUS at 1CPP-PNL102 (171 ft Aux Bldg East Side, Containment Purge FLT 6/HVR FAN 14 Room).

Terminating Cue: EOP-0005, Enclosure 21 installation has been completed and the Containment is being vented.

JPM-80021.01

Denotes Critical Step Page 7 of 9

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-80021.01 Page 8 of 9

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A large break LOCA has occurred in the Drywell.

Containment pressure is 12 psig and Containment Hydrogen concentration cannot be maintained in the Safe Zone of the Hydrogen Deflagration Overpressure Limit (HDOL).

Normal Containment Vent and Purge, Hydrogen Mixing and the Hydrogen Recombiners have been secured.

EOP-0005, Enclosure 16, Defeating Containment Instrument Air Isolation Interlocks has been installed.

Initiating Cues: The CRS has directed you install EOP-0005, Enclosure 21, Emergency Containment Venting and Defeating Containment Vent Path Isolation Interlocks.

Terminating Cue: EOP-0005, Enclosure 21 installation has been completed and the Containment is being vented.

JPM-80021.01 Page 9 of 9

RBS JOB PERFORMANCE MEASURE ES-301 RO/SRO-I and SRO-U Systems JPM No. B.2.2 JPM NUMBER: 200-08, Rev. 0 TASK DESCRIPTION: Place Div. 1 Standby Service Water System in service from the Remote Shutdown Panel (with SWP-P2A Pump Trip)

K/A REFERENCE & RATING: 264000 K6.07 (3.8/3.9) 295016 AK2.01 (4.4/4.5) AK2.02 (4.0/4.1)

TASK

REFERENCE:

400076004001 TESTING METHOD: Simulate Performance: X Actual Performance:

Control Room: Simulator: In-Plant: X COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): Yes SAFETY FUNCTION GROUP 6 Prepared by: Roger Persons 862 12/01/02 KCN DATE:

Ops Validation: Robert Peek 0546 12/07/02 KCN DATE:

Approved by: Mike Wagner 0035 12/09/02 KCN DATE:

JPM-20008.00 Page 1 of 7

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Place Div. 1 Standby Service Water System in service from the Remote Shutdown Panel (with SWP-P2A Pump Trip)

Required Power: N/A IC No.: N/A Notes: This JPM is to be performed in the Plant.

JPM-20008.00 Page 2 of 7

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: AOP-0031, Shutdown From Outside Main Control Room Required Materials: AOP-0031, Attachment 1, AOP Step Detailed Instructions Required Plant Condition: Any Applicable Objectives: STM-200, Objectives H2, H3, H11, H12 HLO-537, Objective 7 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-20008.00 Page 3 of 7

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: The Control Room has been evacuated. The Reactor is in Hot Shutdown and control has been established at the Remote Shutdown Panel. There has been no fire. Normal Service Water is NOT available.

Initiating Cue: The CRS has directed you to place the Division 1 Standby Service Water System in service by starting SWP-P2A (preferred) or SWP-P2C from the appropriate Remote Shutdown Panel.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. On C61-P001, verify both LOCAL SWP Both lights on. CUE: Inform operator that both EMERGENCY CONTROL ALIGNED lights are on.

Lights are on.

2. On RSS-PNL101,start SWP-P2A SWP-P2A tripped (or started and tripped). CUE: SWP-P2A Pump Status RED light on, GREEN light off; and immediately, RED light off, GREEN light on.

NOTE: ALTERNATE PATH JPM-20008.00

Denotes Critical Step Page 4 of 7

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. On EGS-PNL4C, start SWP-P2C SWP-P2C started. CUE: SWP-P2C Pump Status RED light on, GREEN light off

4. Verify SWP-MOV40C STBY SVCE WTR SWP-MOV40C STBY SVCE WTR PUMP CUE: SWP-MOV40C STBY PUMP DISCHARGE Valve opens. DISCHARGE Valve open SVCE WTR PUMP DISCHARGE Valve status RED light on, GREEN light off

5. Open SWP-MOV55A STBY CLG SWP-MOV55A STBY CLG TOWER 1 INLET CUE: SWP-MOV55A STBY CLG TOWER 1 INLET open TOWER 1 INLET Valve status RED light on, GREEN light off.

6. Close SWP-MOV96A and B NORM SVC SWP-MOV96A and B NORM SVCE WTR CUE: SWP-MOV96A and B WTR RETURN Valves RETURN Valves closed NORM SVCE WTR RETURN Valves status RED lights off, GREEN lights on.

7. CUE: No excessive leakage has been identified.

Terminating Cue: Division 1 Standby Service Water is in service.

JPM-20008.00

Denotes Critical Step Page 5 of 7

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-20008.00 Page 6 of 7

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The Control Room has been evacuated.

The Reactor is in Hot Shutdown and control has been established at the Remote Shutdown Panel.

There has been no fire.

Normal Service Water is NOT available.

Initiating Cues: The CRS has directed you to place the Division 1 Standby Service Water System in service by starting SWP-P2A (preferred) or SWP-P2C from the appropriate Remote Shutdown Panel.

Terminating Cue: Division 1 Standby Service Water is in service.

JPM-20008.00 Page 7 of 7

RBS JOB PERFORMANCE MEASURE ES-301 RO/SRO-I JPM No. B.2.3 JPM NUMBER: 251-01, Rev. 1 TASK DESCRIPTION: Emergency Start of Diesel Fire Pump FPW-P1A K/A REFERENCE & RATING: 286000 K4.05 (3.7/3.8) K5.05 (3.0/3.1)

A2.08 (3.2/3.3) A3.01 (3.4/3.4)

A4.06 (3.4/3.4) 295031 EA1.08 (3.8/3.9)

TASK

REFERENCE:

286018001004/286020004004 TESTING METHOD: Simulate Performance: X Actual Performance:

Control Room: Simulator: In-Plant: X COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: Yes ALTERNATE PATH (FAULTED): Yes SAFETY FUNCTION GROUP 8 Prepared by: Roger Persons 0862 12/01/02 KCN DATE:

Ops Validation: Robert Peek 0546 12/07/02 KCN DATE:

Approved by: Mike Wagner 0035 12/09/02 KCN DATE:

JPM-25101.01 Page 1 of 7

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Emergency Start of Diesel Fire Pump FPW-P1A Required Power: N/A IC No.: N/A Notes: This JPM is to be performed in the Plant.

JPM-25101.01 Page 2 of 7

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: SOP-0037, Fire Protection Water System Operating Procedure Required Materials: SOP-0037, Cover - Page 6 and Pages 8 - 11 Required Plant Condition: Any Applicable Objectives: STM-250, Objectives H4 and N7 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-25101.01 Page 3 of 7

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: The plant has experienced a Station Blackout with Diesel Fire Pump FPW-P1B tagged out. It is now necessary to inject into the RPV with Fire Water due to a failure of RCIC. Diesel Fire Pump FPW-P1A failed to auto start and attempts to start it from the Auxiliary Control Room have been unsuccessful. The Outside Operator is starting the Diesel Driven Air Compressor.

Initiating Cue: The CRS has directed you to locally start Diesel Fire Pump FPW-P1A.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. Place the selector switch on controllerFPW- Locates selector switch and demonstrates placing it in MST1A, DIESEL FIRE PUMP 1A the MANUAL 1 or MANUAL 2 position.

CONTROLLER in MANUAL 1 or MANUAL 2.

2. Depress and hold local START pushbutton Locates START pushbutton and demonstrates CUE: No response from FPW-P1A for 15 seconds or until engine starts for the depressing and holding for 15 seconds. engine starter.

following:

NOTE: ALTERNATE PATH

FPW-P1A, DIESEL DRIVEN FIRE PUMP A JPM-25101.01

Denotes Critical Step Page 4 of 7

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. Open FPW-SOV19A(B),FUEL SUPPLY Locates knurled knob for FPW-SOV19A and CUE: SOV19A is open.

SOLENOID by turning the knurled manual demonstrates turning knob clockwise.

knob clockwise or IN to open the solenoid.

4. Throttle open FPW-V179, FPW-P1A(B) Demonstrates operation of valve handwheels to CUE: Cooling water pressure is 40 ENGINE COOLING SYSTEM BYPASS throttle open valves to establish cooling water supply psig.

VALVE and FPW-V3009, FPW-P1A(B) pressure <50 psig ENGINE COOLING SYSTEM BYPASS VALVE in the cooling water supply piping.

5. Engage starter per the following: Demonstrates raising Lever and releasing Lever when CUE: Engine has started.

engine has started..

1) Raise the Lever on either of the two starter contactors.

2) Release the Lever as soon as the engine starts.

Terminating Cue: Diesel Fire Pump FPW-P1A is started.

JPM-25101.01

Denotes Critical Step Page 5 of 7

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-25101.01 Page 6 of 7

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: The plant has experienced a Station Blackout with Diesel Fire Pump FPW-P1B tagged out.

It is now necessary to inject into the RPV with Fire Water due to a failure of RCIC.

Diesel Fire Pump FPW-P1A failed to auto start and attempts to start it from the Auxiliary Control Room have been unsuccessful.

The Outside Operator is starting Diesel Air Compressor, IAS-C4.

Initiating Cues: The CRS has directed you to locally start Diesel Fire Pump FPW-P1A.

Terminating Cue: Diesel Fire Pump FPW-P1A is started.

JPM-25101.01 Page 7 of 7

RBS JOB PERFORMANCE MEASURE Backup JPM No. B.1.1 JPM NUMBER: 209-02, Rev. 3 TASK DESCRIPTION: Shutdown RCIC Following Automatic Initiation K/A REFERENCE & RATING: 217000 A4.01 (3.7/3.7) A4.02 (3.9/3.9)

A4.03 (3.4/3.3)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: Simulator: X In-Plant:

COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP 4 Prepared by: Roger Persons 0862 12/04/02 KCN DATE:

Ops Validation: Steve Fiore 0124 12/07/02 KCN DATE:

Approved by: Mike Wagner 0035 12/09/02 KCN DATE:

JPM-20902.03 Page 1 of 9

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Shutdown RCIC following Automatic Initiation Required Power: 100%

IC No.: 150 Notes:

JPM-20902.03 Page 2 of 9

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: SOP-0035, Reactor Core Isolation Cooling (SYS #209)

Required Materials: SOP-0035, Reactor Core Isolation Cooling (SYS #209)

Required Plant Condition: 100%

Applicable Objectives: STM-209, Objectives H4 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-20902.03 Page 3 of 9

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: A spurious automatic initiation of RCIC has occurred. RHR A has been placed in Suppression Pool Cooling.

Initiating Cue: The CRS has directed you to coordinate with the ATC and shutdown RCIC returning it to Standby Mode.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. When automatic RCIC operation is no longer desired perform the following: Gland Seal Compressor started.

RED light ON Place E51-C002C GLAND SEAL COMPRESSOR to start. GREEN light OFF

2. Depress RCIC INITIATION RESET White light above RESET pushbutton off.

Pushbutton and check the white light goes OFF.

JPM-20902.03

Denotes Critical Step Page 4 of 9

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. If RCIC flow to RPV is to be reduced, Cue: As CRS, RCIC is not required perform the following: for RPV injection.

Open E51-F059 RCIC TEST RETURN VLV TO CST. Throttle E51-F022 RCIC TEST BYPASS VLV TO CST as required to control injection flow rate to RPV.

WHEN RCIC is no longer required, THEN shut down RCIC per Section6. Alerts ATC he is going to trip RCIC.

4. Depress E51A-S17, RCIC TURBINE TRIP Pushbutton depressed and turbine trips.

pushbutton

5. Verify E51-MOVC002, RCIC TRIP & Trip and Throttle Valve is closed.

THROTTLE VALVE POSITION indicates RED light ON closed.

GREEN light OFF

6. Verify RCIC speed lowering as indicated on RCIC speed lowering E51-C002-1, RCIC TURB SPEED.

JPM-20902.03

Denotes Critical Step Page 5 of 9

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

7. Reset any RCIC Initiation signals as follows: Verifies white light is off.

Depress the RCIC INITIATION RESET pushbutton.

Verify RCIC INITIATION RESET white light is off.

8. Close E51-F045, RCIC STEAM SUPPLY E51-F045 is closed.

TURBINE STOP VALVE and verify the GREEN light ON following are open:

RED light OFF

E51-F025, RCIC STM SPLY DR POT UP STREAM ISOL VALVE All listed valves are open.

E51-F026, RCIC STM SUPLY DR POT DN STREAM ISOL VALVE RED light ON

E51-F004, RCIC TURB EXH DR GREEN light OFF POT UP STREAM ISOL VALVE

E51-F005, RCIC TURB EXH DR POT DN STREAM ISOL VALVE JPM-20902.03

Denotes Critical Step Page 6 of 9

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

9. Verify the following are closed: All listed valves are closed.

E51-F013, RCIC INJECT ISOL GREEN light ON VALVE RED light OFF

E51-F022, RCIC TEST BYPASS VLV TO CST

E51-F059, RCIC TEST RETURN VLV TO CST

E51-F019, RCIC MIN FLOW VLV TO SUPPRESSION POOL

10. Close E51-C002, RCIC TRIP & E51-C002 Operator closed.

THROTTLE VALVE OPERATOR. GREEN light ON RED light OFF

11. Open E51-C002 and verify RCIC TRIP & E51-C002 open.

THROTTLE VALVE POSITION red light RED light ON is on.

GREEN light OFF

12. Verify E51-R600, RCIC PUMP FLOW E51-R600 set to 600 gpm.

FLOW CONTROLLER HVYC002 in AUTO and set to 600 gpm.

Terminating Cue: RCIC is shutdown in Standby Mode.

JPM-20902.03

Denotes Critical Step Page 7 of 9

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-20902.03 Page 8 of 9

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A spurious automatic initiation of RCIC has occurred.

RHR A has been placed in Suppression Pool Cooling.

Initiating Cues: The CRS has directed you to coordinate with the ATC and shutdown RCIC returning it to Standby Mode.

Terminating Cue: RCIC is shutdown in Standby Mode.

JPM-20902.03 Page 9 of 9

RBS JOB PERFORMANCE MEASURE Backup JPM No. B.1.2 JPM NUMBER: 800-20, Rev. 4 TASK DESCRIPTION: Bypass Drywell Cooling Isolation Interlocks per EOP Enclosure 20 K/A REFERENCE & RATING: 223001 A2.10 (3.6/3.8) 295028 EK2.04 (3.6/3.8) EA1.03 (3.9/3.9)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: Actual Performance: X Control Room: Simulator: X In-Plant:

COMPLETION TIME: 10 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): Yes SAFETY FUNCTION GROUP 5 Prepared by: Roger Persons 0862 12/06/02 KCN DATE Ops Validation: Steve Fiore 0124 12/07/02 KCN DATE Approved by: Mike Wagner 0035 12/09/02 KCN DATE JPM-80020.04 Page 1 of 8

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Bypass Drywell Cooling Isolation Interlocks per EOP Enclosure 20 Required Power: 0%, Steam Leak in Drywell IC No.: 149 Notes: Insert malfunction MSS01, 80 gpm leak for slow rising Drywell temperature.

When candidate begins performing Step 3 of JPM, raise leak to 250 gpm.

JPM-80020.04 Page 2 of 8

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: EOP-0005, Enclosure 21, Emergency Containment Venting and Defeating Containment Vent Path Isolation Interlocks Required Materials: EOP-0005, Enclosure 21, Emergency Containment Venting and Defeating Containment Vent Path Isolation Interlocks Key to Control Room Emergency Locker Required Plant Condition: Any Applicable Objectives: HLO-516, Objective 1 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-80020.04 Page 3 of 8

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: A steam leak exists in the Drywell resulting in a LOCA BOP Isolation on High Drywell Pressure. With Drywell temperature above 180°F, EOP-2 Step DWT-3 states, Operator All available drywell cooling , defeating isolation interlocks (ENCL 20) if necessary.

Initiating Cue: The CRS has directed you to install EOP-0005, Enclosure 20, Defeating Drywell Cooling Isolation Interlocks.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. OBTAIN EOP-0005 ENCL 20 keys (2). Obtains keys from EOP ENCL key cabinet.

2. VERIFY Normal Service Water pressure on Normal Service Water pressure is greater than 1-SWP-PI124 (H13*P870) OR Standby Containment and Drywell pressure.

Service Water pressure on 1SWP*PR50A(B) (H13*P870) is greater than Containment pressure and Drywell pressure on 1CMS*PR2A(B) (H13*P808).

JPM-80020.04

Denotes Critical Step Page 4 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

3. PLACE Control Switches for all tripped Control switches for all Drywell Unit Coolers in NOTE: At this time, simulator Drywell Unit Coolers to OFF. (H13*P863) OFF. operator raises the leak to 250 gpm causing Drywell temperature to rise above 200°F before candidate performs Step 6.

4. PLACE the following keylock switches in the Both switches in EMERGENCY and RED lights NOTE: In the simulator the keylock EMERGENCY position AND VERIFY the ON. switches are located on the back of red lights illuminate. Panels P863 and P870.

Switch Name Panel No.

DW CLG ISOL INTLK BYP H13-P851 DW CLG ISOL INTLK BYP H13-P852

5. START DIV I AND II H2 Analyzers. Both H2 Analyzers started.

(H13*P808) RED light ON GREEN light OFF JPM-80020.04

Denotes Critical Step Page 5 of 8

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

6. IF any drywell temperature, as indicated on Notes drywell temperature on CMS-TR41A is CUE: As CRS, acknowledge CMS-TR41A/B (1H13*P808) is greater >200°F. Enclosure cannot be completed.

than 200 degrees F THEN, notify the CRS/OSS that this enclosure cannot be Notifies CRS that enclosure cannot be completed.

completed.

Terminating Cue: EOP-0005, Enclosure 20 installation has been terminated due to drywell temperature >200°F.

JPM-80020.04

Denotes Critical Step Page 6 of 8

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-80020.04 Page 7 of 8

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A steam leak exists in the Drywell resulting in a LOCA BOP Isolation on High Drywell Pressure.

With Drywell temperature above 180°F, EOP-2 Step DWT-3 states, Operator All available drywell cooling , defeating isolation interlocks (ENCL

20) if necessary.

Initiating Cues: The CRS has directed you to install EOP-0005, Enclosure 20, Defeating Drywell Cooling Isolation Interlocks.

Terminating Cue: EOP-0005, Enclosure 20 installation has been completed.

JPM-80020.04 Page 8 of 8

RBS JOB PERFORMANCE MEASURE Backup JPM No. B.2.1 JPM NUMBER: 700-09, Rev. 3 TASK DESCRIPTION: Respond To A Fire Outside The Main Control Room By Verifying SFC Vavle Position (SFC cooling Upper Pools.

K/A REFERENCE & RATING: 233000 A2.11 (3.6/3.8) 600000 AK3.04 (2.8/3.4)

TASK

REFERENCE:

TESTING METHOD: Simulate Performance: X Actual Performance:

Control Room: Simulator: In-Plant: X COMPLETION TIME: 20 minutes MAX. TIME: N/A JOB LEVEL: RO/SRO TIME CRITICAL: No EIP CLASSIFICATION REQUIRED: No PRA RISK DOMINATE: No ALTERNATE PATH (FAULTED): No SAFETY FUNCTION GROUP 9 Prepared by: Roger Persons 0862 12/04/02 KCN DATE:

Ops Validation: Robert Peek 0546 12/07/02 KCN DATE:

Approved by: Mike Wagner 0035 12/09/02 KCN DATE:

JPM-70009.03 Page 1 of 7

RBS JOB PERFORMANCE MEASURE SIMULATOR SETUP SHEET Task

Description:

Respond To A Fire Outside The Main Control Room By Verifying SFC Vavle Position (SFC cooling Upper Pools.

Required Power: NA IC No.: NA Notes: This JPM is to be performed in the plant.

JPM-70009.03 Page 2 of 7

RBS JOB PERFORMANCE MEASURE DATA SHEET References for Development: AOP-0052, Fire Outside The Main Control Room In Areas Containing Safety Related Equipment, Attachment 6

Required Materials: AOP-0052, Fire Outside The Main Control Room In Areas Containing Safety Related Equipment, Attachment 6

Required Plant Condition: Shutdown with Fire Applicable Objectives: HLO-544, Objective 6 Safety Related Task: (If K/A less than 3.0)

Control Manipulations: NA Items marked with an "*" are required to be performed, and are Critical Steps , failure to successfully complete a Critical Step requires the JPM to be evaluated as "Unsatisfactory".

Comments describing the reason for failure are required in the comments section of the Verification of Completion sheet.

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

JPM-70009.03 Page 3 of 7

RBS JOB PERFORMANCE MEASURE If In-Plant or In the Control Room:

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

Read to the Operator:

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

Initial Conditions: A fire is burning in the D-Tunnel Cable Chase (EL 70). SFC is being used to cool the Upper Pools.

Initiating Cue: The CRS has directed you to complete AOP-0052, Attachment 6, Verification Of SFC Valve Position, Step 1.

PERFORMANCE STEP STANDARD S/U COMMENTS

1. At CB, 95 ft el, EHS-MCC8A, open the Breakers 3B and 1B open EHS-MCC8A is located on the 95 following: El. Of the Control Building in the Div.

1 Switchgear Room.

BKR 3B, SFC-MOV119 CONTMT FUEL POOL INLET ISOL VALVE

BKR 1B SFC-MOV122 CONTMT OUTBOARD ISOL VALVE TO COOLING PMP.

JPM-70009.03

Denotes Critical Step Page 4 of 7

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

RBS JOB PERFORMANCE MEASURE PERFORMANCE STEP STANDARD S/U COMMENTS

2. At AB, east, 141 ft el, EHS-MCC2B, open Breaker 1B is open EHS-MCC2B is located on the 141 Breaker 1B, SFC-MOV120 RETURN TO El. of the Aux. Bldg East Side.

COOLING CONTMT INBD ISOLATION.

At Containment, 133 ft el, Az 180°, verify

3. SFC-MOV120 is open. Cue: As CRS, RCIC is not required SFC-MOV120 RETURN TO COOLING for RPV injection.

CONTMT INBD ISOLATION is open.

4. Verify SFC-MOV119, CONTMT FUEL SFC-MOV119 is open. SFC-MOV119 and 120 are located POOL INLET ISOL VALVE is open. in the Fuel Bldg, 137 El, in the room at the top of the ladder on the southeast end of the Spent Fuel Pool.

This room requires a high radiation door key for entry. Entry need not be made.

5. Verify SFC-MOV122, CONTMT SFC-MOV122 is open.

OUTBOARD ISOL VALVE TO COOLING PMP is open.

Terminating Cue: AOP-0052, Attachment 6, Step 1 is completed.

JPM-70009.03

Denotes Critical Step Page 5 of 7

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

RBS JOB PERFORMANCE MEASURE VERIFICATION OF COMPLETION Operator: SSN:

Evaluator: KCN:

Date: License (Circle one): RO / SRO Follow-up Questions:

Follow-up Question Response:

Time to complete JPM: minutes Comments / Feedback:

RESULT: Satisfactory / Unsatisfactory Evaluator's Signature: Date:

JPM-70009.03 Page 6 of 7

RBS JOB PERFORMANCE MEASURE JPM Task Conditions/Cues (Operator Copy)

Initial Conditions: A fire is burning in the D-Tunnel Cable Chase (EL 70).

SFC is being used to cool the Upper Pools.

Initiating Cues: The CRS has directed you to complete AOP-0052, Attachment 6, Verification Of SFC Valve Position, Step 1.

Terminating Cue: AOP-0052, Attachment 6, Step 1 is completed.

JPM-70009.03 Page 7 of 7

G1.41.19 (Job Book No.)

RIVER BEND STATION NUCLEAR TRAINING DEPARTMENT LICENSE OPERATOR SIMULATOR TRAINING

TPP-7-009 (CROSS REFERENCE)

EXAM SCENARIO NUMBER

R-SIS-18.0 (DOC. NO.)

TOPIC

Loss of RPS A / IAS-MOV106 fails to Open / Steam Leak/Rupture in the Drywell AVERAGE DURATION

1.0 HOUR PREPARED BY: Roger Persons / 0862 Date: 11/15/02 INSTRUCTOR / KCN REVIEWED BY: Mike Wagner / 0035 Date 11/22/02 TECHNICAL REVIEW / KCN VALIDATED BY: Joseph Kelley / 1410 Date 11/25/02 OPERATIONS CRS / KCN

Indexing Information

I. DESCRIPTION OF SCENARIO The crew assumes the shift at 28% power. Reactor Feed Pump FWS-P1A Lube System is started by the UO and the ATC raises power with control rods. Reactor pressure transmitter B21-N078A fails high causing a half-scram condition which remains while maintenance works to restore the transmitter. A failure of the C MSL flow instrument causes a low level alarm condition accompanied by a Recirc FCV Runback.

Once the ATC recovers from the FCV Runback, a loss of RPS Bus A occurs due to a trip of RPS MG Set A.

After transferring RPS Bus A to its alternate power supply, the UO will reset the Containment Isolation logic and find that the IAS-MOV106 the containment isolation valve for Instrument Air will not open. Prior to the Inboard MSIVs closing the Crew should initiate a manual scram.

RPS will fail to scram but the manual initiation of ARI will result in all control rods inserting.

Upon closure of the Inboard MSIVs a small (40 gpm) steam leak is initiated in the Drywell causing an isolation and ECCS initiation on High Drywell Pressure. The crew will enter EOP-1 and EOP-2. After EOP entry, the leak will propagate to a Main Steam Line Rupture. This will require the crew to declare that RPV level cannot be determined and enter contingency procedure EOP-4, RPV Flooding.

II. TERMINAL OBJECTIVES

1. Recognize and respond to a trip of one RPS MG Set in accordance with plant procedures.

2. Recognize and respond to a failure to scram in accordance with plant procedures.

3. Establish safe and stable plant conditions following a steam line break inside the Drywell in accordance with plant procedures.

R-SIS-18.0 PAGE 2 OF 20

III. PERFORMANCE OBJECTIVES A. CRS (SRO)

1. Direct the response to a trip of RPS MG Set A in accordance with AOP-0010, Loss of One RPS Bus.

2. Direct the response to a failure of IAS-MOV106 to re-open in accordance with AOP-0001, Reactor Scram.

3. Direct the response to high Drywell pressure/temperature and coordinate the implementation of EOP-1, RPV Control and EOP-2, Primary Containment Control.

4. Direct the response to loss of RPV level indication in accordance with EOP-1 and EOP-4, RPV Flooding.

5. Declare Site Area Emergency due to inability to determine RPV level.

B. ATC (RO)

1. Respond to a trip of RPS MG Set A in accordance with AOP-0010, Loss of One RPS Bus.

2. Respond to a reactor scram condition in accordance with AOP-0001, Reactor Scram.

3. Respond to a Main Turbine trip in accordance with AOP-0002, Main Turbine and Generator Trips.

4. Respond to a high Drywell and Containment pressure and temperature as directed.

5. Respond to loss of RPV level indication in accordance with EOP-1 and EOP-4, RPV Flooding as directed.

R-SIS-18.0 Page 3 OF 20

C. UO (RO)

1. Respond to a trip of RPS MG Set A in accordance with AOP-0010, Loss of One RPS Bus.

2. Respond to a failure of IAS-MOV106 to reopen in accordance with AOP-0001, Reactor Scram

3. Respond to a high Drywell and Containment pressure and temperature as directed.

4. Respond to HPCS failure to auto start and manually start.

5. Respond to a high Drywell pressure isolation in accordance with AOP-0003, Automatic Isolations.

6. Respond to loss of RPV level indication in accordance with EOP-1 and EOP-4, RPV Flooding as directed.

R-SIS-18.0 Page 4 OF 20

IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL TRAINING EQUIPMENT STATUS REQUIRED CONDITION FOCUS DOCUMENTS GOP-0001, Plant Startup Power: 28%

AOP-0006, Condensate / Core: MOL, xenon equilibrium Feedwater Failures AOP-0010, Loss of One RPS Bus Equipment OOS:

APRM B - Failed power supply EOP-0001, RPV Control

Normal Service Water Pump SWP-P7A - Bearing EOP-0002, Primary Containment

RFP FWS-P1B - Lube oil leak Control

Three LPRMs Bypassed:

EOP-0004, RPV Flooding 22-31D, 22-47A,46-15C STPs Due:

None LCOs:

3.3.1.1 and TR 3.3.2.1 for APRM B Evolutions in progress:

Continue with plant startup

CR 24-49 @ notch 16 R-SIS-18.0 Page 5 OF 20

V. GENERAL INSTRUCTIONS Event Number MFS/OR #/CAE Expected Operator Action Simulator Setup Snapped to IC# 141 PLANT CONFIGURATION: P808 Harris Panel, verify only blue status light on for SWP-P7A

P680, bypass APRM B

P870, all Lube Oil Pump switches for RFPs A and B in STOP INSTRUCTOR STATION COMMANDS:

TRIGGERS: (All set to FALSE) t1, Reactor pressure instrument failure t2, FWLC Steam Flow Channel C failure NOTE: t3 also inserts RPS Failure to scram - auto signals and manually with 2 t3, RPS MG Set A output breaker trip second time delay from loss of RPS bus. Also inserts switch override to t4, Resets NI DC power supplies keep IAS-MOV106 closed with 10 second time delay.

t5, Initiates steam leak in Drywell t6, Initiates steam line break in Drywell R-SIS-18.0 Page 6 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Simulator Setup MALFUNCTIONS:

Continued

NMS012B, APRM D failed downscale

HPCS003, HPCS Pump Fails to Auto start

B21005 t1, Reactor pressure transmitter B21-N078A fails upscale

FWS014 t2, Steam flow Channel C to FWLC fails downscale

RPS003A t3, RPS MG Set A Output breaker trips

RPS001B, d00:02, t3, Failure to SCRAM Auto

RPS001C, d00:02, t3, Failure to SCRAM Manual

MSS001, 250, r6:00, t4, Drywell Steam Leak

MSS002 t5, Steam Line Rupture in Drywell R-SIS-18.0 Page 7 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Simulator Setup REMOTE FUNCTIONS:

Continued

NIS001, RESET, t4, NI Cabinet 20 VDC Power Supplies

LPRMRB22-31d, BYPASS

LPRMRB22-47a, BYPASS

LPRMRB46-15c, BYPASS LAMP OVERRIDES:

LO_MSS155-G, OFF, P870-54C Mn Stm Sply to SSE Isol MOV green light

LO_TME-MOVS8-R, OFF, P870-54C SSE Press Cont Isol Vlv red light

LO_SW-N22-G, OFF, SWP-P7A green status light

LO_SW-N22-B, ON, SWP-P7A blue status light METER OVERRIDES:

AO_C33-R603, 0, t2, Main Steam Line C Flow Meter R-SIS-18.0 Page 8 OF 20

Event Number MFS/OR #/CAE Expected Operator Action ANNUNCIATOR OVERRIDES:

P870_53a:d_5, OFF, LP FW HTR STRING A LOW WATER LEVEL SWITCH OVERRIDES:

DI_IAS-MOV106, d00:10, t3, CLOSE FREEZE Event 0 RUN CREW: Board Walkdown and Turnover R-SIS-18.0 Page 9 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 1

Description:

Unit Operator is directed by CRS to start FWS-P1A Reactor Feed Pump Lube Oil System. Using SOP-0009, Reactor Feedwater System the UO starts the FWS-P1A Reactor Feed Pump Lube Oil System from P870 coordinating with ATC.

R-SIS-18.0 Page 10 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 1 ROLE PLAY : CRS: Directs UO to start FWS-P1A Lube Oil System When the crew As Turbine Building SNEO, when UO: Using SOP-0009, SECTION 4.1 for FWS-P1A:

has assumed the requested, report FWS-P1A RFP/Motor Starts AC Aux. Oil Pump, (ATC) Verifies pressure normal light shift and at the Oil Reservoir level is normal (midrange lit direction of the on FWL-LI19A.

lead examiner Stops AC Aux. Oil Pump Starts DC Aux. Oil Pump, (ATC) Verifies pressure normal light lit Stops DC Aux. Oil Pump Starts Gear Increaser AC Aux. Oil Pump, (ATC) Verifies pressure normal light lit Stops Gear Increaser AC Aux. Oil Pump ATC: Depresses Lube Oil System Start on P680 and verifies both system pressure normal lights are lit ROLE PLAY :

UO: Places DC and Gear Increaser AC Aux. Oil Pumps in AUTO As Turbine Building SNEO, when requested, report proper oil flow through Reports FWS-P1A Lube Oil System started to CRS pump, motor bearings and gear increaser.

Event 2

Description:

CRS directs ATC to Raise reactor power by control rod withdrawal.

R-SIS-18.0 Page 11 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 2 CRS: Directs ATC to raise power per GOP-0001 to 35% using control rods.

ATC: Withdraws Control Rods per approved Rod Movement Sequence Package Monitors RC&IS indications for rod withdrawals Performs coupling checks on rods withdrawn to notch 48 R-SIS-18.0 Page 12 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 3

Description:

Reactor Pressure Transmitter B21-N078A fails upscale resulting in a half-scram. With the instrument failed upscale, the half-scram cannot be reset.

CRS refers to Tech Specs and determines in LCO 3.3.1.1.

Event 3 t1, Inserts malfunction B21005 ATC: Reports half scram caused by High Reactor Pressure trip in RPS A to CRS When directed by lead examiner. Refers to ARP-P680-06A-A05, RPS-A TRIP REACTOR VESSEL HIGH PRESSURE ROLE PLAY: Diagnoses/recognizes pressure transmitter failure As Back Panel Operator, if requested, Confirm half scram and no control rods inserted and reports to report backpanel RPS pressure CRS instruments all four channels reading 1040 psig.

ROLE PLAY: CRS: Consults Tech Spec Section 3.3.1.1, RPS Instrumentation As I &C Maintenance/WMC, Determines LCO Action A applies and trip system in trip acknowledge request to investigate failure condition met of B21-N078A.

Directs I & C Maintenance investigate of instrument failure R-SIS-18.0 Page 13 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 4

Description:

Steam Flow Channel C to FWLC fails downscale. The resulting steam flow/feed flow mismatch lowers level rapidly below the low level alarm point but will stabilize well above the low level scram.

Event 4 t2, Inserts malfunction FWS014 and override ATC: As level lowers, refers to ARP-P680-03A-B08, REACTOR AO_C33-R603C HIGH/LOW WATER LEVEL and/or AOP-0006, When directed Condensate/Feedwater Failures by lead examiner.

Diagnoses/identifies steam flow channel failure May elect any of the following to restore level to normal band:

- Adjust Master Level Control setpoint.

- Master Level Control to 1 ELEMENT

- transfer Master Level Control to MANUAL ROLE PLAY: Refers to ARP-P680-04A-A03 & A09, FCV A/B RUNBACK RFP TRIP As I &C Maintenance/WMC, acknowledge request to investigate failure When directed by CRS restores Recirc FCVs from runback of Steam Flow Channel C.

Adjusts both LOOP FLOW CONTROL stations to zero limiter error

Resets Cavitation interlocks

Adjusts both LOOP FLOW CONTROL stations to return FCVs to maximum position R-SIS-18.0 Page 14 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 5

Description:

RPS MG Set A output breaker trips. Outboard containment isolation for Instrument Air fails to re-open after RPS bus is re-energized and containment isolations reset.

Critical Tasks: 1. Initiate ARI Event 5 t3, Inserts RPS003A trip of RPS A MG set ATC/CRS: Recognize loss of RPS bus A output breaker When directed CRS: Direct implementation of AOP-0010, Loss of One RPS Bus by lead examiner.

Direct investigation of the loss of RPS bus A UO: When directed, transfer RPS bus A to alternate power Reset CRVICS depressing both RESET pushbuttons on P601 Recognize failure of IAS-MOV106 to open on P870 and report to CRS Continue AOP-0010 actions, as directed by CRS ROLE PLAY : CRS: Direct implementation of AOP-0001 and AOP-0002 for impending Inboard MSIV closure scram.

As Back Panel Operator, when requested, reset the Neutron Monitoring Cabinet ATC: When directed, Insert manual scram or insert following auto power supply. scram.

Irf_NIS001 RESET Initiate ARI to cause control rod insertion and report failure of RPS to CRS R-SIS-18.0 Page 15 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 6

Description:

A small leak develops when the Inboard MSIVs close. After entering EOP-1 and EOP-2 for High Drywell temperature and pressure, the leak propagates into a Main Steam Line rupture inside containment. This results in RPV pressure and Drywell temperature conditions outside the safe zone of the RPV Saturation Curve in EOP Caution 1. RPV level can no longer be determined and EOP-4 RPV Flooding must be entered.

Critical Tasks: 1. Recognize loss of level indication and enter EOP-4, RPV Flooding Event 6 t4, Inserts MSS001 Steam Leak in the ATC/CRS: Recognize loss of RPS bus A Drywell When directed CRS: Direct implementation of AOP-0010, Loss of One RPS Bus by lead examiner.

Direct investigation of the loss of RPS bus A t5, Inserts MSS002 Steam Line Rupture in Determine no LCO required actions per Tech Spec 3.3.8.2 the Drywell (After EOP Entry)

(RPS Electric Power Monitoring)

UO: When directed, transfer RPS bus A to alternate power Reset CRVICS depressing both RESET pushbuttons Recognize failure of IAS-MOV106 to open and report to CRS Continue AOP-0010 actions as directed by CR Event 6 contd CRS: Direct implementation of AOP-0001 and AOP-0002 for impending Inboard MSIV closure scram.

Enters EOP-1 if RPV level lowers to Level 3 following scram.

ATC: When directed, Insert manual scram or insert following auto scram.

Initiate ARI to cause control rod insertion and report failure of RPS to CRS R-SIS-18.0 Page 16 OF 20

Event Number MFS/OR #/CAE Expected Operator Action ROLE PLAY: If a leakage report is CRS: Enters (or re-enters) EOP-1, Drywell pressure >1.68 psid requested give the leakage values that Enters EOP-2 on Drywell temperature >145°F are shown in monitored parameters Leak_report. Directs actions to control RPV level and containment parameters When requested report Drywell Unit Direct implementation of AOP-0003, Automatic Isolations Cooler Drain flow is pegged high.

UO/ATC: Implement EOP-1 as directed Verify ECCS/ESF automatic actions Remove HPCS003 When directed, inhibit ADS actuation CRS: Recognize rapidly rising Drywell temperature/pressure, ROLE PLAY: Acknowledge requests for Suppression Pool temperature/level, and rapidly lowering RPV EOP Enclosure installation. level from steam line rupture.

Install EOP Enclosures with Remote Recognizes loss of RPV level indication and directs transition to Functions as necessary. EOP-4, RPV Flooding.

Report EOP Enclosure installation UO/ATC: Implement EOP-4 as directed completed based on appropriate time Establish Minimum RPV Flooding pressure intervals.

Event 7

Description:

The HPCS Pump fails to auto start on High Drywell pressure. Identifying the failure and attempting manual control will successfully start the pump.

Critical Tasks: 1. Recognize HPCS failure to auto start and manually start for small steam leak in Drywell.

R-SIS-18.0 Page 17 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 7 UO: Verifies ECCS automatic operation following steam leak in Drywell Recognizes failure of HPCS pump to auto start, manually starts HPCS pump Reports failure/status to CRS Termination FREEZE CRS: Determines Emergency Classification as Site Area Emergency Criteria are met per EIP-2-001, EAL 1 (if not previously declared during and concurrence scenario) of the Lead Examiner R-SIS-18.0 Page 18 OF 20

VI. TERMINATION CRITERIA:

1. All control rods inserted by ARI.

2. Injecting with all available injection sources to achieve Minimum RPV Flooding pressure.

IX. QUANTITATIVE

SUMMARY

Total Malfunctions 5 Reactor pressure transmitter failure, Steam flow transmitter failure, Loss of RPS Bus, Steam leak in Drywell, Steam line break in Drywell, Failure of E21-MOVF005 Malfunctions after EOP entry 2 Steam Line Break and LPCS Injection Valve failure Abnormal Events 2 FWLC problem (AOP-0006), Loss of RPS Bus (AOP-0010)

Major Transients 1 Small break/Large break LOCA EOPs entered 2 EOP-1, EOP-2 EOP Contingencies used 1 EOP-4, Sheet 4, RPV Flooding Simulator Run Time 60 Minutes EOP Run Time 30 Minutes Critical Tasks 3 Tech Specs Exercised Yes 3.3.1.1, RPS Instrumentation R-SIS-18.0 Page 19 OF 20

VII. REFERENCES A. Plant Procedures

1. GOP-0001, Plant Startup

2. SOP-0009, Reactor Feedwater

3. ARP-P680-06A-A05

4. ARP-P680-03A-B08

5. ARP-P680-04A-A03 & A09

6. AOP-0001, Reactor Scram

7. AOP-0002, Main Turbine and Generator Trips

8. AOP-0003, Automatic Isolations

9. AOP-0006, Condensate/Feedwater Failures

10. AOP-0010, Loss of One RPS Bus

11. EOP-1, RPV Control

12. EOP-2, Primary Containment Control

13. EOP-4, Contingencies

14. EIP-2-001, Classification of Emergencies

15. Technical Specifications R-SIS-18.0 Page 20 OF 20

Offgoing OSS: Oncoming OSS: Off-Going Shift N D (Print) KCN (Print) KCN

? ?

Date PART I - TO BE REVIEWED PRIOR TO ASSUMING THE SHIFT UNIT STATUS MODE 1 RX POWER 28%

EVOLUTIONS (COMPLETED / IN PROGRESS / PLANNED); GENERAL INFORMATION Completed GOP-0001 through Section G, Step 20. On Step 50 of Control Rod Movement Sequence.

A lube oil leak was found on RFP FWS-P1B last shift. FWS-P1B lube oil system has been shutdown.

Maintenance and WMC generating MAI and clearance for FWS-P1B lube oil leak.

RFP FWS-P1A was shutdown earlier last shift to repair CCS leak lube oil cooler. MAI was complete, clearance has been released and tags remove. Turbine Bldg Operator standing by at FWS-P1A for lube oil system startup.

APRM B is bypassed with a failed power supply. Three LPRMs are bypassed 22-31D,22-47A, 46-15C.

Normal Service Water Pump SWP-P7A is tagged out for bearing replacement.

Start RFP FWS-P1A lube oil system. Raise power to 35% to continue plant startup.

SIGNIFICANT LCO STATUS Tracking LCO for APRM B EQUIPMENT STATUS APRM B power supply failed and bypassed. Condensate Full-Flow Filtration is bypassed.

SWP-P7A tagged out for bearing replacement.

? ? ? ?

Night Orders Standing Orders Board Walkdown Temp Alts (Signature: Oncoming OSS Review Completed) KCN R-SIS-18.0 PAGE 21 OF 20

G1.41.19 (Job Book No.)

RIVER BEND STATION NUCLEAR TRAINING DEPARTMENT LICENSE OPERATOR SIMULATOR TRAINING

TPP-7-009 (CROSS REFERENCE)

EXAM SCENARIO NUMBER

R-SIS-16.0 (DOC. NO.)

TOPIC

SORV / Steam Leak in Drywell / Loss of Offsite Power AVERAGE DURATION

1.0 HOUR PREPARED BY: Roger Persons / 0862 Date: 11/15/02 INSTRUCTOR / KCN REVIEWED BY: Mike Wagner / 0035 Date 11/22/02 TECHNICAL REVIEW / KCN VALIDATED BY: Joseph Kelley / 1410 Date 11/25/02 OPERATIONS CRS / KCN

Indexing Information

I. DESCRIPTION OF SCENARIO The crew assumes the shift at 100% power. The Unit Operator will place RHR A into Suppression Pool Cooling in preparation for RCIC testing. An LPRM Upscale causes APRM F to reach its Upscale Thermal Trip and causes a half-scram. After the half-scram is reset a Heater Drain Pump Overload condition requires shutdown of the pump and start of the alternate pump.

SRV-F047C fails and sticks open. The crew responds by lower power with recirc flow and implementing AOP-0035 to shut the SRV. The SRV closes when control power fuses are removed.

The closure of SRV-F047C will initiate a 100 gpm steam leak in the Drywell. The crew will manually scram and enter EOP-1 and EOP-2 for Drywell conditions. After the scram, when the Generator output breaker opens on reverse power, a Loss of Offsite Power occurs. The crew enters AOP-0004, Loss of Offsite Power.

II. TERMINAL OBJECTIVES

1. Recognize and respond to a Stuck Open SRV in accordance with plant procedures.

2. Recognize and respond to a Steam Leak in the Drywell in accordance with plant procedures.

3. Recognize and respond to a Loss of Offsite Power in accordance with plant procedures.

4. Establish safe and stable plant conditions following a steam line break inside the Drywell in accordance with plant procedures.

R-SIS-16.0 PAGE 2 OF 21

III. PERFORMANCE OBJECTIVES A. CRS (SRO)

1. Direct the response to SRV-F047C opening in accordance with AOP-0035, Stuck Open SRV.

2. Direct the response to high Drywell pressure/temperature and coordinate the implementation of EOP-1, RPV Control and EOP-2, Primary Containment Control.

3. Direct the response to Loss of Offsite Power in accordance with AOP-0004, Loss of Offsite Power.

4. Declare an ALERT Emergency Classification due to a reactor coolant leak greater than 50 gpm.

B. ATC (RO)

1. Respond to APRM F Upscale from LPRM Upscale in accordance with P680 ARPs.

2. Respond to a Heater Drain Pump Overload in accordance with ARPs.

3. Respond to SRV-F047C opening in accordance with AOP-0035, Stuck Open SRV

4. Initiate a Manual Scram in accordance with AOP-0001, Reactor Scram.

5. Respond to a Main Turbine trip in accordance with AOP-0002, Main Turbine and Generator Trips.

6. Respond to high Drywell pressure/temperature in accordance with EOP-1, RPV Control and EOP-2, Primary Containment Control, as directed.

7. Respond to Loss of Offsite Power in accordance with AOP-0004, Loss of Offsite Power, as directed.

R-SIS-16.0 Page 3 OF 21

C. UO (RO)

1. Respond to to SRV-F047C opening in accordance with AOP-0035, Stuck Open SRV.

2. Respond to Manual Scram in accordance with AOP-0001, Reactor Scram

3. Respond to a high Drywell pressure and temperature as directed.

4. Respond to a high Drywell pressure isolation in accordance with AOP-0003, Automatic Isolations.

5. Respond to Loss of Offsite Power in accordance with AOP-0004, Loss of Offsite Power, as directed.

R-SIS-16.0 Page 4 OF 21

IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL TRAINING EQUIPMENT STATUS REQUIRED CONDITION FOCUS DOCUMENTS GOP-0005, Power Maneuvering Power: 100%

AOP-0035, Stuck Open SRV Core: MOL, xenon equilibrium AOP-0007, Loss of Feedwater Equipment OOS:

Heater

CRD Pump A tagged out AOP-0009, Loss of Normal

APRM A - INOP Service Water AOP-0004, Loss of Offsite Power STPs Due:

None EOP-1, RPV Control LCOs:

EOP-2, Primary Containment

3.3.1.1 and TR 3.3.2.1 for APRM A Control Evolutions in progress:

Operation at rated conditions R-SIS-16.0 Page 5 OF 21

V. GENERAL INSTRUCTIONS Event Number MFS/OR #/CAE Expected Operator Action Simulator Setup Snapped to IC# 144 PLANT CONFIGURATION:

On P680, bypass APRM A Verify all status indication lights for CRD Pump A are extinguished.

Taggout CRD Pump A Place danger tag switch covers on control switches for CRD Pump A and its Auxiliary Oil Pump.

INSTRUCTOR STATION COMMANDS:

TRIGGERS: (All set to FALSE) t1, LPRM Upscale and rod scram t2, Bypass LPRM 0615D t3, Heater Drain Pump Overload t4, SRV F047C stuck open t5, SRV F047C Div 2 switch OFF t6, SRV F047C A fuses pulled t7, SRV F047C B fuses pulled and Leak in Drywell initiated.

t8, Loss of Offsite Power R-SIS-16.0 Page 6 OF 21

Event Number MFS/OR #/CAE Expected Operator Action Simulator Setup MALFUNCTIONS:

Continued

NMS012A, APRM A Fails Downscale

CRD001A, CRD A Pump Trip

LPRMUP0615D t1, LPRM 0615D fails Upscale

MSS005J t4, SRV F047C Fails Open

MSS006J t4, SRV F047C Sticks Open

MSS001, 100, r5:00, t7, Steam Leak in the Drywell

ED001 t8, Loss of Offsite Power

EDG003, HPCS DG Failure to Start REMOTE FUNCTIONS:

LPRMRB0615d, BYPASS, t2, LPRM Bypass, 0615d

MSS012, CLOSE, t5, Operate SRV B Solenoid Switches

LPRMRB22-31d, BYPASS

LPRMRB22-47a, BYPASS

LPRMRB46-15c, BYPASS R-SIS-16.0 Page 7 OF 21

Event Number MFS/OR #/CAE Expected Operator Action Simulator Setup LAMP OVERRIDES:

Continued

LO_MSS155-G, OFF, P870-54C Mn Stm Sply to SSE Isol MOV green light

LO_TME-MOVS8-R, OFF, P870-54C SSE Press Cont Isol Vlv red light

LO_C11-CRDPA-G 601-22C, OFF, CRD Pump A Green Light

LO_C11-CRDPA-R 601-22C, OFF, CRD Pump A Red Light

LO_C11-C001AP-G 601-22C, OFF, CRD Aux Oil Pump A Green Light

LO_C11- C001AP-R 601-22C, OFF, CRD Aux Oil Pump A Red Light

LO_B21-AB1-A601-19B, ON, t6, ADS A Logic Power Failure (Postage Stamp)

LO_B21-F047C-R-601-19C, OFF, t6, SRV F047C Red Light

LO_B21-F047C-G-601-19C, OFF, t6, SRV F047C Green Light

LO_B21-BB1-A601-19B, ON, t7, ADS B Logic Power Failure (Postage Stamp)

LO_B21-ACF047C-R-601-19C, OFF, t7, SRV F047C Accoustic Monitor Red Light R-SIS-16.0 Page 8 OF 21

Event Number MFS/OR #/CAE Expected Operator Action ANNUNCIATOR OVERRIDES:

P870_53a:d_5 OFF, LP FW HTR STRING A LOW WATER LEVEL

P680_2a:e_8 ON t3, HTR DR PUMP 1HDL-P1D OVERLOAD

P601_19a:b_8 ON t6, DIV 1 ADS/SRV INOPERATIVE

P601_19a:b_11 ON t7, DIV 2 ADS/SRV INOPERATIVE SWITCH OVERRIDES:

NONE FREEZE Event 0 RUN CREW: Board Walkdown and Turnover R-SIS-16.0 Page 9 OF 21

Event Number MFS/OR #/CAE Expected Operator Action Event 1

Description:

Unit Operator is directed by the CRS to place RHR A into Suppression Pool Cooling.

Event 1 CRS: Directs UO to place RHR A into Suppression Pool Cooling When the crew UO: Using SOP-0031 has assumed the Throttles open SWP-F068 to obtain ~5800 gpm thru RHR A shift and at the Heat Exchanger (P870) direction of the Lead Examiner Starts RHR Pump A (P601)

Opens RHR Test Return to Suppression Pool (P601)

Verifies RHR Pump Min Flow Valve closes (P601)

Closes RHR HX Bypass Valve (P601)

R-SIS-16.0 Page 10 OF 21

Event Number MFS/OR #/CAE Expected Operator Action Event 2

Description:

ATC responds APRM F Upscale and half-scram caused by LPRM 0615D failure upscale.

Event 2 t1, Inserts malfunction LPRMUP0615D, ATC: Refers to ARP-680-06A-C03 LPRM 0615D fails Upscale.

When directed Diagnoses/recognizes APRM F upscale caused by LPRM by Lead upscale.

Examiner Locates failed LPRM with RCIS (P680)

Reports to CRS.

CRS: Consults RPS Instrumentation TS R-SIS-16.0 Page 11 OF 21

Event Number MFS/OR #/CAE Expected Operator Action ROLE PLAY : CRS: Directs ATC to bypass APRM F and reset half-scram As Reactor Engineer, when requested, Directs RE to bypass LPRM report LPRM has failed upscale and ATC: When directed, bypasses APRM F and resets half-scram (P680) request APRM F bypassed. Bypasses LPRM 0615D and reports to CRS.

t2, LPRMRB0615d, BYPASS, Bypasses CRS: Directs ATC to place APRM F back in service LPRM 0615d ATC: When directed, places APRM F back in service (P680)

Event 3

Description:

ATC responds to Heater Drain Pump P1D Overload.

Event 3 t3, Inserts override P680_2a:e_8 ON, to ATC: Refers to ARP-680-02A-E08. Starts HDL-P1C and stops initiate annunciator HTR DR PUMP 1HDL- HDL-P1D per SOP-0010, 5.1 When directed P1D OVERLOAD by Lead Starts HDL-P1C (P680)

Examiner Opens HDL-P1C discharge valve (P680)

Closes HDL-P1D discharge valve (P680)

Remove P680_2a:e_8 ON Stops HDL-P1D (P680)

R-SIS-16.0 Page 12 OF 21

Event Number MFS/OR #/CAE Expected Operator Action ROLE PLAY: CRS: Directs WMC investigate HDL-P1D overload As Electrical Maintenance/WMC, acknowledge request to investigate HDL-P1D overload condition.

Event 4

Description:

SRV F047C fails open and sticks open. Per AOP-0035, ATC lowers power to at least 90%. Attempts to close SRV with control switches are unsuccessful. When both sets of logic power fuses are pulled, the SRV closes. SRV closure initiates a small steam leak in the Drywell.

Critical Tasks: 1. Close SRV F047C.

R-SIS-16.0 Page 13 OF 21

Event Number MFS/OR #/CAE Expected Operator Action Event 4 t4, Inserts malfunctions MSS005J, SRV CRS: Directs crew response per AOP-0035 F047C Fails Open and MSS006J, SRV When directed UO: Places SRV F051G in OPEN (P601)

F047C Sticks Open by lead examiner.

ATC: Lowers reactor power to <90% with recirc flow (P680)

UO: Attempts to close SRV by placing control switch in CLOSE, then returns it to OPEN then back to CLOSE (P601)

ROLE PLAY : CRS/UO: Requests closure attempts using back panel control switch As Backpanel Operator, when requested, places SRV F047C control switches to CLOSE, to OPEN and back to CLOSE.

t5, Places backpanel SRV switch to CLOSE ATC/UO: Monitor indications for SRV closing (P680/P601)

ROLE PLAY :

As Backpanel Operator, when requested, CRS/UO: Requests closure attempts by fuse removal from back panel removes SRV F047C Div 1 control power ATC/UO: Monitor indications for SRV closing (P680/P601) fuses 15A and 16A first, then Div 2 control power fuses 15B and 16B.

t6, Removes SRV Div 1 fuses ATC/UO: Monitor indications for SRV closing (P680/P601) t7, Removes SRV Div 2 fuses and Recognize SRV F047C closure initiates steam leak in Drywell CRS: Refers to Technical Specification for SRV operability Event 5

Description:

Steam leak develops in the Drywell when SRV closes. Reactor is manually scrammed as Drywell pressure approaches scram setpoint.

R-SIS-16.0 Page 14 OF 21

Event Number MFS/OR #/CAE Expected Operator Action Event 5 t7, Inserts malfunction MSS001, 100 gpm CRS: Directs implementation of AOP-0001 and AOP-0002 before Steam Leak in the Drywell automatic scram on High Drywell Pressure.

ROLE PLAY: If a leakage report is CRS: Directs manual scram before High Drywell Pressure Auto scram.

requested give the leakage values that Directs implementation of EOP-1 RPV Control entered on High are shown in monitored parameters Drywell Pressure.

Leak_report.

Enters EOP-2 on High Drywell Temperature When requested report Drywell Unit Cooler Drain flow is pegged high. ATC: When directed, Inserts manual scram and completes AOP-0001 and AOP-0002 actions.

ROLE PLAY: Acknowledge requests for EOP Enclosure installation. UO: Verifies ECCS automatic operation for High Drywell Pressure.

Install EOP Enclosures with Remote Functions as necessary.

Report EOP Enclosure installation completed based on appropriate time intervals.

R-SIS-16.0 Page 15 OF 21

Event Number MFS/OR #/CAE Expected Operator Action Event 6

Description:

Following the scram, when the Generator output breaker opens on reverse power, a Loss of Offsite Power occurs. The crew enters AOP-0004, Loss of Offsite Power.

Event 6 ED001 t8, Loss of Offsite Power CRS: Directs implementation of AOP-0004.

When directed UO: Initiates RCIC if directed.

by lead examiner.

Verifies Diesel Generator Auto Starts R-SIS-16.0 Page 16 OF 21

Event Number MFS/OR #/CAE Expected Operator Action Event 7

Description:

Following the Loss of Offsite Power the HPCS Diesel fails to Auto start. The UO must start the Diesel to make HPCS injection available.

Critical Tasks: 1. Starts HPCS Diesel.

Event 7 Remove malfunction EDG003, HPCS DG UO: HPCS Diesel failure to start and reports to CRS Failure to Start.

Attempts start from P601 to start diesel.

Termination FREEZE CRS: Determines Emergency Classification as ALERT per EIP-2-001, Criteria are met EAL 2 (if not previously declared during scenario) and concurrence of the Lead Examiner VI. TERMINATION CRITERIA:

1. All Emergency Diesel Generators operating.

2. RPV level maintained by HPCS and or RCIC operation.

3. RPV pressure controlled by manual SRV operation.

4. Containment parameters stabilized.

R-SIS-16.0 Page 17 OF 21

R-SIS-16.0 Page 18 OF 21 IX. QUANTITATIVE

SUMMARY

Total Malfunctions 6 LPRM upscale failure, SRV fails open and sticks open, Steam leak in Drywell, Loss of Offsite Power, Failure of Div 3 EDG to start Malfunctions after EOP entry 2 Loss of Offsite Power, Division 3 EDG Start Failure Abnormal Events 2 SORV (AOP-0035)

Loss of Offsite Power (AOP-0004)

Major Transients 1 Steam Leak in Drywell, Loss of Offsite Power EOPs entered 2 EOP-1, RPV Control; EOP-2, Primary Containment Control EOP Contingencies used 0 Simulator Run Time 60 Minutes EOP Run Time 30 Minutes Critical Tasks 2 Tech Specs Exercised Yes 3.3.1.1, RPS Instrumentation, 3.5.1 SRV R-SIS-16.0 PAGE 19 OF 21

VII. REFERENCES A. Plant Procedures

1. GOP-0005, Power Maneuvering

2. SOP-0031, Residual Heat Removal

3. SOP-0010, MSR and FW Heater Extraction Steam and Drains

4. ARP-P680-06A-C03

5. ARP-P680-02A-E08

6. AOP-0001, Reactor Scram

7. AOP-0002, Main Turbine and Generator Trips

8. AOP-0003, Automatic Isolations

9. AOP-0004, Loss of Offsite Power

10. AOP-0007, Loss of Feedwater Heater

11. AOP-0035, Stuck Open SRV

12. EOP-1, RPV Control

13. EOP-2, Primary Containment Control

14. EIP-2-001, Classification of Emergencies

15. Technical Specifications R-SIS-16.0 Page 20 OF 21

Offgoing OSS: Oncoming OSS: Off-Going Shift N D (Print) KCN (Print) KCN

? ?

Date PART I - TO BE REVIEWED PRIOR TO ASSUMING THE SHIFT UNIT STATUS MODE 1 RX POWER 100%

EVOLUTIONS (COMPLETED / IN PROGRESS / PLANNED); GENERAL INFORMATION Steady state rated power operation per GOP-0005.

Trip throttle valve maintenance was completed on RCIC on the previous shift.

CRD Pump A is tagged out for pump seal repairs.

APRM A is bypassed. I & C Maintenance is troubleshooting its flow unit.

Preparations are being made for RCIC testing scheduled this shift.

Place RHR A in Suppression Pool Cooling.

SIGNIFICANT LCO STATUS Tracking LCO for APRM A LCO 3.5.1 for RCIC EQUIPMENT STATUS APRM A bypassed Condensate Full-Flow Filtration is bypassed CRD Pump A tagged out

? ? ? ?

Night Orders Standing Orders Board Walkdown Temp Alts (Signature: Oncoming OSS Review Completed) KCN R-SIS-16.0 Page 21 OF 21

R-SIS-16.0 Page 22 OF 21

G1.41.19 (Job Book No.)

RIVER BEND STATION NUCLEAR TRAINING DEPARTMENT LICENSE OPERATOR SIMULATOR TRAINING

TPP-7-009 (CROSS REFERENCE)

EXAM SCENARIO NUMBER

R-SIS-17.0 (DOC. NO.)

TOPIC

Loss of Vacuum / Turbine Control Failure / Loss of Feedwater AVERAGE DURATION

1.0 HOUR PREPARED BY: Roger Persons / 0862 Date: 11/15/02 INSTRUCTOR / KCN REVIEWED BY: Mike Wagner / 0035 Date 11/22/02 TECHNICAL REVIEW / KCN VALIDATED BY: Joseph Kelley / 1410 Date 11/25/02 OPERATIONS CRS / KCN

Indexing Information

I. DESCRIPTION OF SCENARIO The crew assumes the shift at 85% power. Unit Operator is directed by the CRS to remove RHR B from Suppression Pool Cooling. Using SOP-0031, RHR System, the UO secures Suppression Pool Cooling and returns it to standby lineup. ATC responds to an APRM D Upscale failure. Using ARP ATC recognizes single control rod scram.

A loss of TPCCW to Reactor Feed Pump FWS-P1C Gear Increaser Lube Oil Cooler requires securing FWS-P1C. An electrical fault causes a loss of NNS-SWG2B. As a result, two condenser circ water pumps are lost and condenser vacuum begins to lower. The Crew will enter AOP-0005 and lower power to maintain vacuum.

EHC Governor Fails Low closing Control Valves. ATC initiates manual scram when BPVs are full open and RPV pressure begins rising.

Following the scram a total loss of feedwater occurs as a result of FCV200 closure. One of the Turbine Bypass Valves sticks open causing an excessive cooldown rate after the scram. The crew should close the MSIVs to control cooldown rate.

The UO must restore RCIC following an overspeed trip.

II. TERMINAL OBJECTIVES 1.

R-SIS-17.0 PAGE 2 OF 19

III. PERFORMANCE OBJECTIVES A. CRS (SRO) 1.

B. ATC (RO) 1.

R-SIS-17.0 Page 3 OF 19

C. UO (RO)

1. .

2.

R-SIS-17.0 Page 4 OF 19

IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL TRAINING EQUIPMENT STATUS REQUIRED CONDITION FOCUS DOCUMENTS GOP-0005, Power Maneuvering Power: 85%

AOP-0061, Mispositioned Control Core: MOL, xenon equilibrium Rod(s)

AOP-0007, Loss of Condenser Equipment OOS:

Vacuum

HPCS tagged out AOP-0009, Loss of Normal

APRM B - INOP Service Water AOP-0006, Condensate / STPs Due:

Feedwater Failures

None EOP-1, RPV Control LCOs:

EOP-2, Primary Containment

3.3.1.1 and TR 3.3.2.1 for APRM B Control Evolutions in progress:

Return to rated conditions R-SIS-17.0 Page 5 OF 19

V. GENERAL INSTRUCTIONS Event Number MFS/OR #/CAE Expected Operator Action Simulator Setup Snapped to IC# 143 PLANT CONFIGURATION:

P680, bypass APRM B Place taggout switch covers on HPCS Injection Valve and HPCS Pump control switches. Verify all status lights HPCS Pump and Injection valve are

P601, HPCS OOS Switch to ON extinguished.

P601, Place RHR B in Suppression Pool Cooling INSTRUCTOR STATION COMMANDS:

TRIGGERS:

t1, APRM D fails Upscale and Control Rod 2017 scram t2, High Temperature Alarm on RFP C Gear Increaser Lube Oil t3, NNS-SWG2B Bus Fault t4, EHC fault closes Turbine CVs NOTE: t5 should be set to actuate on RPV Level 3 t5, CFFF Bypass FCV200 closes t6, RCIC Overspeed trip locally reset R-SIS-17.0 Page 6 OF 19

Event Number MFS/OR #/CAE Expected Operator Action Simulator Setup MALFUNCTIONS:

Continued

HPCS001, HPCS Pump Trip

RCIC003B, t1, RCIC Speed Controller Fails High

CRDM3213, Single Control Rod Scram

CRD001A, Trip of CRD Pump P1A

MGEN001 Main Generator Trip REMOTE FUNCTIONS:

LPRMRB22-31d, BYPASS

LPRMRB22-47a, BYPASS

LPRMRB46-15c, BYPASS LAMP OVERRIDES:

LO_MSS155-G, OFF, P870-54C Mn Stm Sply to SSE Isol MOV green light

LO_TME-MOVS8-R, OFF, P870-54C SSE Press Cont Isol Vlv red light R-SIS-17.0 Page 7 OF 19

Event Number MFS/OR #/CAE Expected Operator Action Simulator Setup ANNUNCIATOR OVERRIDES:

Continued SWITCH OVERRIDES:

FREEZE Event 0 RUN CREW: Board Walkdown and Turnover R-SIS-17.0 Page 8 OF 19

Event Number MFS/OR #/CAE Expected Operator Action Event 1

Description:

Unit Operator is directed by the CRS to remove RHR B from Suppression Pool Cooling. Using SOP-0031, RHR System, the UO secures Suppression Pool Cooling and returns it to standby lineup.

Event 1 CRS: Directs UO to remove RHR B from Suppression Pool Cooling When the crew UO: Using SOP-0031:

has assumed the Closes RHR Pump B Test Return to Suppression Pool (P601).

shift and at the direction of the Stops RHR Pump B (P601).

lead examiner Verifies minimum flow and HX outlet valves open (P601).

Opens RHR B HX Bypass valve (P601).

Closes RHR HX B Service Water Return (P870).

R-SIS-17.0 Page 9 OF 19

Event Number MFS/OR #/CAE Expected Operator Action Event 2

Description:

ATC responds to an APRM D Upscale failure. Using ARP ATC recognizes single control rod scram.

Event 2 t1, Inserts malfunction NMS011D, APRM D ATC: ARP-P680-06A-B03:

failure Upscale and CRDM3213, Single Verify half scram (P680).

Control Rod Scram Compare channel with other APRMs (P680).

Verify proper core flow (P680).

Bypass APRM D on CRS direction (P680).

Reset half scram on CRS direction (P680).

ARP-P680-05A-A10:

Identify scrammed rod using RCIS (P680).

Report scrammed rod to CRS.

CRS: AOP-0061, Mispositioned Control Rod(s) SECTION 5.1 Perform MON calculation Notify RE for control rod pattern recovery directions Document and initiate a CR R-SIS-17.0 Page 10 OF 19

Event Number MFS/OR #/CAE Expected Operator Action Event 3

Description:

Loss of TPCCW to Reactor Feed Pump FWS-P1C Gear Increaser Lube Oil Cooler requiring shutdown of FWS-P1C.

Event 3 t2, Inserts override OR_P680_3a:d-6, to ATC: ARP-P680-03A-D02, RX FWP 1C GEAR INCREASER initiate annunciator RX FWP 1C GEAR HIGH TEMP When directed INCREASER HIGH TEMP by lead examiner. Direct NEO to verify lineup and TPCCW to LO cooler.

Upon notification of failure of Temp. Control Valve and temp rapidly trending to 190ºF go to SOP-0009 for P1C shutdown.

SOP-0009, Reactor Feedwater System, SECTION 6.1 Close discharge valve on P1C (P680).

Verify min flow valve for P1C opens (P680).

Monitor SF/FF mismatch and RPV Level to verify capability of remaining RFPs (P680).

Stop Reactor Feed Pump P1C (P680).

R-SIS-17.0 Page 11 OF 19

Event Number MFS/OR #/CAE Expected Operator Action Event 4

Description:

An electrical fault causes a loss of NNS-SWG2B. As a result, two condenser circ water pumps are lost and condenser vacuum begins to lower. The Crew will enter AOP-0005 and lower power to maintain vacuum.

R-SIS-17.0 Page 12 OF 19

Event Number MFS/OR #/CAE Expected Operator Action Event 4 t3, Inserts malfunction ED003E, Loss of 1. ATC: AOP-0005, Loss of Condenser Vacuum/Circ Water NNS-SWG2B Pump Trip When directed a. Verify CWS Pump Discharge Valves for tripped pumps by lead examiner. close (P808).

b. Isolate the B Condenser Water box per SOP-0006 when <70% power

2. SOP-0006, Circ Water, Cooling Tower and Vacuum Priming, SECTION 6.4

a. Close both 1B Condenser water box outlet valves (P808).

b. Close both 1B Condenser water box inlet valves (P808).

3. AOP-0009, Loss of Normal Service Water

a. Verify standby Normal Service Water Pump P1C started ATC:

1. AOP-0005, Loss of Condenser Vacuum/Circ Water Pump Trip

a. Reduce power with Recirc flow to maintain Condenser vacuum =23 in Hg (P680).

Continue to reduce power per the Shutdown Reactivity Control Plan (P680).

Event 5

Description:

EHC Governor Fails Low closing Control Valves. ATC initiates manual scram when BPVs are full open and RPV pressure begins rising.

R-SIS-17.0 Page 13 OF 19

Event Number MFS/OR #/CAE Expected Operator Action Event 5 t4, Inserts malfunction EHC006A, EHC 1. AOP-0001, Reactor Scram Governor Fails Low and 12 seconds after the a. Immediate Operator Actions.

When directed b. Subsequent Operator Actions.

scram, inserts CNM006, CFFF Bypass Valve by lead examiner. 2. AOP-0002, Turbine Trip FCV200 Fails Shut

a. Immediate Operator Actions.

b. Subsequent Operator Actions.

3. AOP-0006, Condensate/Feedwater Failures

a. Immediate Operator Actions.

b. Subsequent Operator Actions.

R-SIS-17.0 Page 14 OF 19

Event Number MFS/OR #/CAE Expected Operator Action Event 6

Description:

One of the Turbine Bypass Valves sticks open causing an excessive cooldown rate after the scram. The crew should close the MSIVs to control cooldown rate.

Critical Tasks: 1. Close MSIVs to prevent excessive cooldown.

Event 6 t5, Inserts EHC002C No. 1 Turbine Bypass ATC: Recognize failure of Bypass valve to close on pressure below Valve Fails open pressure set.

When directed by lead examiner. CRS: Directs UO to close MSIVs UO: When directed, closes MSIVs R-SIS-17.0 Page 15 OF 19

Event Number MFS/OR #/CAE Expected Operator Action Event 7

Description:

Following the Loss of Feed scram RCIC will trip on Overspeed.

Critical Tasks: 1. Recover RCIC and inject into RPV to Control Level.

Event 7 t6, Inserts malfunction RCIC001, RCIC trip UO: Recognizes RCIC trip and reports to CRS after start Attempts to reset trip throttle.

Has Building Operator reset trip throttle locally.

Starts RCIC.

Termination FREEZE CRS: Determines no Emergency Classification required per EIP-2-001.

Criteria are met and concurrence of the Lead Examiner R-SIS-17.0 Page 16 OF 19

VI. TERMINATION CRITERIA:

1. RCIC recovered and injecting into RPV.

2. RPV level and pressure stabilized.

IX. QUANTITATIVE

SUMMARY

Total Malfunctions 5 Malfunctions after EOP entry 2 Abnormal Events 2 Major Transients 1 EOPs entered 2 EOP-1, EOP-2 EOP Contingencies used 1 Simulator Run Time 60 Minutes EOP Run Time 30 Minutes Critical Tasks 3 Tech Specs Exercised Yes 3.3.1.1, RPS Instrumentation R-SIS-17.0 Page 17 OF 19

VII. REFERENCES A. Plant Procedures

1. GOP-0005, Power Maneuvering

2. SOP-0009, Reactor Feedwater

3. ARP-P680-06A-A05

4. ARP-P680-03A-B08

5. ARP-P601-19A-F05

6. AOP-0001, Reactor Scram

7. AOP-0002, Main Turbine and Generator Trips

8. AOP-0003, Automatic Isolations

9. AOP-0006, Condensate/Feedwater Failures

10. EOP-1, RPV Control

11. EOP-2, Primary Containment Control

12. Technical Specifications R-SIS-17.0 Page 18 OF 19

Offgoing OSS: Oncoming OSS: Off-Going Shift N D (Print) KCN (Print) KCN

? ?

Date PART I - TO BE REVIEWED PRIOR TO ASSUMING THE SHIFT UNIT STATUS MODE 1 RX POWER 85%

EVOLUTIONS (COMPLETED / IN PROGRESS / PLANNED); GENERAL INFORMATION Rod sequence exchange completed last shift. Reactivity Control Plan completed, at Target Rod Pattern.

RHR B is in Suppression Pool Cooling following RCIC testing completed on the previous shift. RCIC is back in service.

HPCS is tagged out for motor oil replacement.

APRM C is bypassed. I & C maintenance is replacing its averaging amplifier card.

Three LPRMs are bypassed: 22-31D,22-47A, 46-15C Suppression pool temperatures are normal following RCIC testing completed on the previous shift.

Secure Suppression Pool Cooling. Raise power to 92% using Recirc flow per GOP-0005 then notify RE.

SIGNIFICANT LCO STATUS Tracking LCO for APRM C LCO 3.5.1 for HPCS EQUIPMENT STATUS APRM B bypassed Condensate Full-Flow Filtration is bypassed HPCS INOP and tagged out

? ? ? ?

Night Orders Standing Orders Board Walkdown Temp Alts (Signature: Oncoming OSS Review Completed) KCN R-SIS-17.0 PAGE 19 OF 19

G1.41.19 (Job Book No.)

RIVER BEND STATION NUCLEAR TRAINING DEPARTMENT LICENSE OPERATOR SIMULATOR TRAINING

TPP-7-009 (CROSS REFERENCE)

EXAM SCENARIO NUMBER

R-SIS-15.0 (DOC. NO.)

TOPIC

Single Loop Ops / Loss of Feed Heater / Turbine Trip ATWS AVERAGE DURATION

1.0 HOUR PREPARED BY: Roger Persons / 0862 Date: 11/15/02 INSTRUCTOR / KCN REVIEWED BY: Mike Wagner / 0035 Date 11/22/02 TECHNICAL REVIEW / KCN VALIDATED BY: Joseph Kelley / 1410 Date 11/25/02 OPERATIONS CRS / KCN

Indexing Information

I. DESCRIPTION OF SCENARIO A plant shutdown is in progress from 61% power in Single Loop Operation when the crew assumes the shift. The UO removes Suppression Pool Cleanup from service as part of GOP-0004, Shutdown from Single Loop Operation. ATC inserts control rods for plant shutdown.

The B Feedwater Reg Valve fails open requiring the ATC to take it out of service by closing its isolation MOV. The UO operator responds to a CRD pump trip by placing the other CRD pump in service.

The E5A Low Pressure Feedwater heater tube ruptures causing a high level condition in the heater. At the Extreme High Level, a turbine runback to 70% is initiated which terminates before affecting the Turbine Control Valves. It also isolates the A Feedwater Heater String and opens the 25% flow bypass causing a significant loss of feedwater heating.

A generator trip causes a turbine trip with a failure to scram (Hydraulic ATWS). The crew will enter EOP-1A RPV Control - ATWS from EOP-1, RPV Control. EOP-2, Primary Containment Control will be entered on high suppression pool temperature.

II. TERMINAL OBJECTIVES

1. Recognize and respond to feedwater regulating valve failure in accordance with plant procedures.

2. Recognize and respond to a CRD pump trip in accordance with plant procedures.

3. Recognize and respond to a loss of feedwater heating in accordance with plant procedures.

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

5. Establish safe and stable plant conditions following a Hydraulic ATWS in accordance with plant procedures.

R-SIS-15.0 PAGE 2 OF 20

III. PERFORMANCE OBJECTIVES A. CRS (SRO)

1. Direct plant shutdown in accordance with GOP-0004

2. Direct the response to feedwater heater tube leak with AOP-0007, Loss of Feedwater Heater.

3. Direct the response to a failure to scram and coordinate implementation of EOP-1A, RPV Control - ATWS

4. Direct the response to high Suppression Pool temperature and coordinate the implementation of EOP-2, Primary Containment Control.

5. Declare a Site Area Emergency due to the ATWS condition.

B. ATC (RO)

1. Respond to a Feedwater Reg. Valve failure in accordance with ARP.

2. Respond to a APRM flow unit downscale failure in accordance with ARP

3. Respond to Feedwater Heater Tube Failure in accordance with ARPs and AOP-0007

4. Respond to Generator trip in accordance with AOP-0002, Main Turbine and Generator Trips.

5. Respond to failure to scram controlling RPV level as directed.

R-SIS-15.0 Page 3 OF 20

C. UO (RO)

1. Respond to a trip of CRD pump in accordance with ARP.

2. Respond to a high Suppression Pool temperature as directed.

3. Respond to a failure to scram as directed.

R-SIS-15.0 Page 4 OF 20

IV. INITIAL CONDITIONS/SHIFT TURNOVER INITIAL TRAINING EQUIPMENT STATUS REQUIRED CONDITION FOCUS DOCUMENTS GOP-0004, Single Loop Operation Power: 61%

AOP-0006, Condensate / Core: MOL, xenon equilibrium Feedwater Heater AOP-0007, Loss of Feedwater Equipment OOS:

Heater

Reactor Recirculation Pump A tripped - Investigating AOP-0002, Turbine and Generator

APRM A - INOP Trips

TPCCW Pump CCS - P1C - Motor replacement

Three LPRMs Bypassed:

EOP-1, RPV Control 22-31D, 22-47A,46-15C EOP-1A, RPV Control - ATWS STPs Due:

None EOP-2, Primary Containment Control LCOs:

3.3.1.1 and TR 3.3.2.1 for APRM A Evolutions in progress:

Plant shutdown R-SIS-15.0 Page 5 OF 20

V. GENERAL INSTRUCTIONS Event Number MFS/OR #/CAE Expected Operator Action Simulator Setup Snapped to IC# 142 PLANT CONFIGURATION: At Step 2 of SHUTDOWN Control Rod Movement Sequence

P680, bypass APRM A Place Danger tag switch cover on CCS-P1C RESET/LOCKOUT Pushbutton.

P870, CCS-P1C, Lockout PB Verify all indicating lights for CCS-P1C and its discharge valve CCS-MOV15C are extinguished.

INSTRUCTOR STATION COMMANDS:

TRIGGERS: (All set to FALSE) t1, FWRV F001B Fails Open t2, CRD Pump A trip t3, APRM F Flow Converter Fails Downscale NOTE: t4 also inserts Hydraulic ATWS.

t4, FW Heater E5A Tube Leak t5, Main Generator Trip t6, Trip of SLC Pump A t7, Trip of SLC Pump B t12, Removes SPC Demineralizer from service t13, Opens RHS-V3022 RHR C Test Return Line Isolation Valve R-SIS-15.0 Page 6 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Simulator Setup MALFUNCTIONS:

Continued

FWS007B t1, Feedwater Reg Valve B failure open

CRD001A t2, Trip of CRD Pump P1A

NMS015F t3, APRM F flow reference signal failure downscale

FWS011 t4, E5A Feedwater Heater tube leak

MGEN001 t5, Main Generator Trip

RPS001A t4, Hydraulic ATWS REMOTE FUNCTIONS:

RPS008, IN, Single Loop APRM Scram and Rod Block

NIS013, NORMAL, PBDS A Bypass

NIS016, NORMAL, PBDS B Bypass

LPRMRB22-31d, BYPASS

LPRMRB22-47a, BYPASS

LPRMRB46-15c, BYPASS R-SIS-15.0 Page 7 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Simulator Setup LAMP OVERRIDES:

Continued

LO_MSS155-G, OFF, P870-54C Mn Stm Sply to SSE Isol MOV green light

LO_TME-MOVS8-R, OFF, P870-54C SSE Press Cont Isol Vlv red light

LO_CCS-P1C-G, OFF, P870-55C CCS Pump P1C green light

LO_C41-F001B-R 601-18B, ON t7, SLC Pump B Suction Valve Red Light

LO_C41-F001B-G 601-18B, OFF t7, SLC Pump B Suction Valve Green Light

LO_C41-A2-A 601-18B, ON t7, C41-C001B or F001B Ovld (Postage Stamp)

LO_C41-F001A-R 601-19B, ON t6, SLC Pump A Suction Valve Red Light

LO_C41-F001A-G 601-19B, OFF t6, SLC Pump A Suction Valve Green Light

LO_C41-AA2-A 601-19B, ON t6, C41-C001A or F001A Ovld (Postage Stamp)

R-SIS-15.0 Page 8 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Simulator Setup ANNUNCIATOR OVERRIDES:

Continued

P870_53a:d_5, OFF, LP FW HTR STRING A LOW WATER LEVEL SWITCH OVERRIDES:

DI_C41-C001A 601-19B, STOP, t6, SLC A Pump Switch

DI_C41-C001B 601-18B, STOP, t7, SLC B Pump Switch FREEZE Event 0 RUN CREW: Board Walkdown and Turnover R-SIS-15.0 Page 9 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 1

Description:

Unit Operator is directed by the CRS to remove SPC from service. Using SOP-0140, SPC/ADHR System, coordinating with the Reactor Building Operator, the UO secures SPC.

Event 1 ROLE PLAY : CRS: Directs UO to remove SPC from Service When the crew As Reactor Building Operator in UO: Using SOP-0140, directs building operators to remove SPC has assumed the Racquetball Room, when requested, Filter/Demin.

shift and at the coordinate with Radwaste to remove SPC direction of the Filter/Demineralizer from service.

lead examiner t12, Removes SPC Demin from service UO: Stops SPC-P1B (P601)

Closes the following valves (P601):

SPC-AOV62 SPC-AOV63 SPC-AOV64 SPC-AOV20 ROLE PLAY : E12-MOVF021 As Reactor Building Operator, when Verifies SPC-AOV16 closed (P870) directed, Open RHS-V3022.

Directs Reactor Building Operator to open RHS-V3022 t13, Opens RHS-V3022 RHR C Test Return Line Isolation Valve R-SIS-15.0 Page 10 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 2

Description:

CRS directs ATC to lower reactor power by control rod insertion for plant shutdown per GOP-0004.

Event 2 CRS: Directs ATC to lower power using control rods.

ATC: Inserts Control Rods per SHUTDOWN Control Rod Movement Sequence Monitors RC&IS during rod insertions R-SIS-15.0 Page 11 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 3

Description:

ATC responds to B Feedwater Reg Valve failing open.

Event 3 t1, Inserts malfunction FWS007B, Feedwater ATC: Refers to AOP-0006, Condensate/Feedwater Failures Reg Valve B fails open Diagnoses/Recognizes failure of FWRV(P680)

Transfers FWRV M/A station to Manual (P680)

Attempts to manually close FWRV (P680)

Closes FWS-MOV27B to isolate FWRV (P680)

R-SIS-15.0 Page 12 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 4

Description:

The operating CRD Pump Trips. ATC monitors RC&IS for accumulator faults and rod drifts while UO starts the standby CRD Pump.

Event 4 t2, Inserts malfunction CRD001A, Trip of UO: ARP-P601-22A-A01, CRD PUMP A OR B AUTO TRIP CRD Pump P1A.

When directed Start standby oil pump (P601).

by lead examiner.

Place CRD Flow Controller to MANUAL (P601).

Close CRD Flow Control Valve (P601).

Start Standby CRD Pump (P601).

Reopen CRD Flow Control Valve (P601).

Place CRD Flow Controller to AUTO (P601).

R-SIS-15.0 Page 13 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 5

Description:

APRM F flow reference signal fails downscale. This results in a half-scram. After determining the cause of the APRM F Upscale trip, the half-scram can be reset after bypassing APRM F.

Event 5 t3, Inserts malfunction NMS015F, APRM F ATC: Diagnose/Recognize Flow channel downscale (P680) flow reference signal failure downscale When directed Refers to ARP-P680-06A-A03 by lead examiner.

When directed by CRS, bypass APRM F (P680).

When directed by CRS, reset half-scram (P680).

R-SIS-15.0 Page 14 OF 20

Event Number MFS/OR #/CAE Expected Operator Action ROLE PLAY: CRS: Consults Tech Spec Section 3.3.1.1, RPS Instrumentation As I &C Maintenance/WMC, acknowledge request to investigate failure of APRM F flow unit.

Event 6

Description:

A tube failure in E5A feedwater heater causes isolation of the A LP feedwater heater string. The 25% bypass isolation valve MOV136 opens as the LP heater string isolates. Crew must enter AOP-0007, Loss of Feedwater Heater and evaluate feedwater temperature change to determine if use of AOP-0007 Single Loop Map is required. The AOP-0007 Power-to-Flow map would have plant in the Restricted Region (cannot raise flow in single operating recirc loop any further).

ATC may be directed by CRS to insert control rods per SHUTDOWN Control Rod Movement Sequence anticipating entry into Restricted Zone of power-to-flow map in AOP-0007.

R-SIS-15.0 Page 15 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 6 t4, Inserts malfunction FWS011, E5A ATC: AOP-0007, Loss of Feedwater Heating Feedwater Heater tube leak and RPS001A When directed Monitor feedwater temperatures (P680).

Hydraulic ATWS.

by lead examiner.

Confirm/monitor turbine runback to < 70% load (P680).

Confirm turbine load within limits (P680).

Verifies LP FW Heater String isolation and bypass (P680).

If directed by CRS, Reduce power with Control Rods using SHUTDOWN Control Rod Movement Sequence.

Event 7

Description:

A Main Generator Trip causes a Turbine Trip. None of the control rods insert on the automatic scram and ARI fails to insert any control rods. CRS enters EOP-1, RPV Control and transitions to EOP-1A, RPV Control - ATWS.

Critical Tasks: 1. Inhibit ADS

2. Terminate and prevent HPCS injection into the RPV R-SIS-15.0 Page 16 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 7 t5, Inserts MGEN001 Main Generator Trip ATC: Recognize failure of control rods to insert and initiates ARI.

When directed Reports ATWS conditions to CRS.

by lead examiner.

Completes applicable immediate and subsequent operator actions for AOP-0001 and AOP-0002 When directed, lowers RPV level by terminating feedwater flow.

Stabilizes RPV level at CRS direction.

ROLE PLAY: Acknowledge requests for CRS: Enters EOP-1, transitions to EOP-1A and directs implementation EOP Enclosure installation. of EOP-2 Install EOP Enclosures with Remote UO: Inhibits ADS, terminates and prevents HPCS injection Functions as necessary.

When directed, maximizes CRD drive pressure to drift rods in Report EOP Enclosure installation When directed, initiates SLC injection completed based on appropriate time intervals. When directed, controls RPV pressure with manual SRV operation When directed, installs EOP Enclosure 16.

When directed, places RHR in Suppression Pool cooling.

Event 8

Description:

SLC Pump started for ATWS trips after it starts. UO should monitoring system to verify proper operation, recognize trip and start alternate SLC Pump.

Critical Tasks: 1. Place alternate SLC Pump in service injecting to RPV.

R-SIS-15.0 Page 17 OF 20

Event Number MFS/OR #/CAE Expected Operator Action Event 8 t6, Inserts Overrides for SLC Pump C41- UO: Recognizes SLC Pump A trip and reports to CRS P1A trip Start alternate SLC Pump t7, Inserts Overrides for SLC Pump C41-Verifies proper operation P1B trip Termination FREEZE CRS: Determines Emergency Classification as Site Area Emergency Criteria are met per EIP-2-001, EAL 7 (if not previously declared during and concurrence scenario) of the Lead Examiner R-SIS-15.0 Page 18 OF 20

VI. TERMINATION CRITERIA:

1. Reactor power below APRM downscales and lowering.

2. RPV pressure and level stable.

3. SLC injection in progress.

IX. QUANTITATIVE

SUMMARY

Total Malfunctions 6 FWREG valve failure, CRD Pump Trip, Feedwater heater tube leak, Generator trip, Hydraulic ATWS, SLC Pump trip Malfunctions after EOP entry 1 SLC pump trip Abnormal Events 2 FWLC problem (AOP-0006), Loss of Feedwater Heater (AOP-0007)

Major Transients 1 Turbine Trip ATWS EOPs entered 2 EOP-1A, EOP-2 EOP Contingencies used 1 EOP-1A Level/Power Control Simulator Run Time 60 Minutes EOP Run Time 30 Minutes Critical Tasks 3 Tech Specs Exercised Yes 3.3.1.1, RPS Instrumentation R-SIS-15.0 Page 19 OF 20

VII. REFERENCES A. Plant Procedures

1. GOP-0004, Single Loop Operation

2. SOP-0140, Suppression Pool Cleanup

3. ARP-P601-22A-A01

4. AOP-0001, Reactor Scram

5. AOP-0002, Main Turbine and Generator Trips

6. AOP-0003, Automatic Isolations

7. AOP-0006, Condensate/Feedwater Failures

8. AOP-0007, Loss of Feedwater Heater

9. AOP-0024, Thermal Hydraulic Stability Controls

10. EOP-1, RPV Control

11. EOP-1A, RPV Control - ATWS

12. EOP-2, Primary Containment Control

13. EIP-2-001, Classification of Emergencies

14. Technical Specifications R-SIS-15.0 Page 20 OF 20

Offgoing OSS: Oncoming OSS: Off-Going Shift N D (Print) KCN (Print) KCN

? ?

Date PART I - TO BE REVIEWED PRIOR TO ASSUMING THE SHIFT UNIT STATUS MODE 1 RX POWER 61%

EVOLUTIONS (COMPLETED / IN PROGRESS / PLANNED); GENERAL INFORMATION Plant shutdown in progress from Single Loop Operation following trip of Recirc Pump A last shift.

GOP-0004 Attachment 1 completed and since decision to shutdown, completed through Step 4 of , Shutdown from Single Loop Operation. Heating steam to MSRs has been secured and the SSE has been transferred to Main Steam supply. RFP FWS-P1A and CP CNM-P1A have been secured.

Electrical Maintenance and WMC preparing investigation of Reactor Recirculation Pump A trip.

APRM A bypassed with failed Upscale trip unit. Three LPRMs bypassed: 22-31D,22-47A, 46-15C.

CCS - P1C is tagged out for motor replacement.

Building Operators have been briefed and are standing by to remove SPC from service.

Continue plant shutdown with rod insertion. At Step 2 of SHUTDOWN Control Rod Movement Sequence.

SIGNIFICANT LCO STATUS Tracking LCO for APRM A EQUIPMENT STATUS Recirc Pump A tripped, cause being investigated. Condensate Full-Flow Filtration is bypassed.

APRM A Upscale trip unit failed and bypassed.

CCS - P1C tagged out for motor replacement.

? ? ? ?

Night Orders Standing Orders Board Walkdown Temp Alts (Signature: Oncoming OSS Review Completed) KCN R-SIS-15.0 PAGE 21 OF 20

R-SIS-15.0 Page 22 OF 20

ML030640611

Text

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

REFERENCE:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

SUMMARY

Description:

Description:

Description:

Description:

Description:

Description:

Description:

SUMMARY

Description:

Description:

Description:

Description:

Description:

Description:

Description:

SUMMARY

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description: