Text

Initial Examination 09/2004 - Draft Operating Exam
	ML050340094
Person / Time
Site:	Columbia
Issue date:	09/10/2004
From:	; NRC Region 4
To:	Parrish J; Energy Northwest
Shared Package
ML040840180	List: ML050240347; ML050330226; ML050330272; ML050330287; ML050330300; ML050330365; ML050330438; ML050340094; ML050690424;
References
	50-397/04-301
	Download: ML050340094 (193)
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Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM - SA1#2, rev 0 INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE INADVERTENT CRITICALITY ACTIONS LESSON TITLE MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Steve Garchow (NRC) DATE 9/10/04 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Page 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM - SA1#2, rev 0 Facility: CGS Task No: RO-0559 Task

Title:

Determine Actions for Job Performance Measure No: SA1#2 Criticality outside of ECP K/A

Reference:

2.1.7 3.7/4.4 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Actual Performance: Perform Page 2

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM - SA1#2, rev 0 JPM SETUP INFORMATION Initial Conditions: A plant startup is in progress. PPM 3.1.2 has been completed through step 5.2.3.

Task Standard: The task will be completed successfully when criticality is recognized and the correct actions have been identified.

Required Materials: Marked up copy of PPM 3.1.2 Reactor Plant Startup General

References:

PPM 3.1.2 Reactor Plant Startup, rev 43, page 20 - 22 Initiating Cue: As the RO you are second checking reactor conditions during the startup. You note the following conditions:

Reactor Power 20,000 cps and increasing Period 118 seconds and stable Control rod position 26-55 @ pos 14 There has been no control rod motion for the past 3 minutes.

Inform the SM of any actions required for these conditions Time Critical Task: NO Validation Time: 8 min.

Simulator ICs: N/A Malfunctions/Remote N/A Triggers:

Overrides: N/A Special Setup N/A Instructions:

Page 3

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM - SA1#2, rev 0 PERFORMANCE INFORMATION START TIME:

Critical Step: YES

Performance Step: 1 Standard: Determine from given conditions that the reactor is critical prior to the Minimum Critical Position given.

Comment:

SAT / UNSAT Critical Step: YES

Performance Step: 2 Standard: Identify the requirement to:

- Stop control rod withdrawal *

- Insert control rods in reverse order *

- Ask the SNE to provide a rod pattern that will maintain reactor subcritical

Comment:

SAT / UNSAT THE EXAMINEE SHOULD ANNOUNCE THE TERMINATION POINT OF THE JPM AT THIS POINT.

JPM TERMINATION TIME:

JPM START TIME: -

JPM COMPLETION TIME:

Page 4

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM - SA1#2, rev 0 VERIFICATION OF COMPLETION JPM Number: Determine Actions for Criticality outside of ECP SA1#2 NEW ADMIN JPM Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Completed:

Page 5

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM - SA1#2, rev 0 JPM INFORMATION CARD HAND THE STUDENT INFORMATION CARD TO THE EXAMINEE READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiation cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Task Standard: The task will be completed successfully when criticality is recognized and the correct actions have been identified.

Required Materials: Marked up copy of PPM 3.1.2 Reactor Plant Startup Safety Equipment: N/A General

References:

PPM 3.1.2 Reactor Plant Startup, rev 43, page 20 - 22 Time Critical Task: NO Initial Conditions: A plant startup is in progress. PPM 3.1.2 has been completed through step 5.2.3.

INITIATING CUE As the CRS you are second checking reactor conditions during the startup. You note the following conditions:

Reactor Power 20,000 cps and increasing Period 118 seconds and stable Control rod position 26-55 @ pos 14 There has been no control rod motion for the past 3 minutes. Inform the SM of any actions required for these conditions INFORMATION BELOW THIS LINE NOT SHARED WITH EXAMINEE Task Number: RO-0559 Validation Time: 8 min.

NUREG 1123

Reference:

2.1.7 3.7/4.4 Time Critical: NO Location: ADMIN Performance Method: PERFORM Prepared/Revised by: M. Westergren Revision Date:1/12/99 Page 6

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM - SA1#2, rev 0 STUDENT INFORMATION Initial Conditions: A plant startup is in progress. PPM 3.1.2 has been completed through step 5.2.3.

INITIATING CUE As the CRS you are second checking reactor conditions during the startup. You note the following conditions:

Reactor Power 20,000 cps and increasing Period 118 seconds and stable Control rod position 26-55 @ pos 14 There has been no control rod motion for the past 3 minutes. Inform the SM of any actions required for these conditions Page 7

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE DETRMINE THE OPERABILITY OF THE SLC SYSTEM MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY S. Hutchison DATE 6/20/04 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

DETERMINE THE OPERABILITY OF THE SLC SYSTEM MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

ADMIN JPM SIMULATOR SETUP NEEDED.

Special Setup Instructions:

ADMIN JPM SIMULATOR SETUP NEEDED.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0163-M-TS Validation Time: 10 Prerequisite Training: N/A Time Critical: NO PPM

Reference:

OSP-INST-H101 Location: Simulator/Classroom NUREG 1123 Ref: 2.1.12 2.9/4.0 Performance Method: Perform Page 1 of 4

DETERMINE THE OPERABILITY OF THE SLC SYSTEM JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL The plant is operating at 100% power.

CONDITIONS:

INITIATING CUE: The CRO has just given you a copy of OSP-INST-H101, Shift and Daily Instrument Checks (MODES 1, 2, & 3) for day shift review.

Evaluate steps 54, 55, and 56 to determine if SLC is operable.

Notify the CRS with your answer.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Determines SLC From step 54 determines the need to S/U Operability from temp. use Att. 9.7 for comparison.

Using ATT. 9.7, determines SLC S/U concentration/temperature is outside of the acceptable region.

From step 56 determines the need to S/U use Att. 9.8 for comparison.

Using Att. 9.8 determines SLC Tank S/U volume is acceptable.

Notifies the CRO that SLC is NOT S/U*

operable.

Termination Criteria: Student informs CRS that SLC in NOT operable.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 2 of 4

DETERMINE THE OPERABILITY OF THE SLC SYSTEM RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time

/ NA COMMENTS:

Evaluator's Signature: Date:

Page 3 of 4

DETERMINE THE OPERABILITY OF THE SLC SYSTEM STUDENT JPM INFORMATION CARD Initial Conditions:

The plant is operating at 100% power.

Cue:

The CRO has just given you a copy of OSP-INST-H101, Shift and Daily Instrument Checks (MODES 1, 2, & 3) for day shift review.

Evaluate steps 54, 55, and 56 to determine if SLC is operable.

Notify the CRS with your answer.

Page 4 of 4

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE TAGOUT CRD-P-1A USING MANUAL FORMS MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Steve Hutchison DATE 6/28/04 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

TAGOUT CRD-P-1A USING THE MANUAL FORMS MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

NO SETUP NEEDED, ADMIN JPM Special Setup Instructions:

NO SETUP NEEDED, ADMIN JPM JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-0695 Validation Time: 30 Minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

OI-12 ATT. 2 Location: TABLE TOP NUREG 1123 Ref: 2.2.13 3.6/3.8 Performance Method: PERFORM Page 1 of 5

TAGOUT CRD-P-1A USING THE MANUAL FORMS JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL SOMS is out of service and will not be available for the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . CRD-P-1A CONDITIONS: must be tagged out for a gearbox oil change.

INITIATING CUE: Using the Manual Clearance Order Process per OI-12, tag out CRD-P-1A for a gearbox oil change.

Give the CRS the Manual Clearance Order forms when completed.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Perform all non-critical Applies initial conditions & P/L, steps IAW current completes steps IAW procedure. S/U procedure.

Tags the control switch on Using an Equipment tag, tags CRD-P601 for CRD-P-1A. RMS-S3A for CRD-P-1A in the S/U*

CENTER AFTER STOP position.

Tags the closing fuses for Using a Danger Tag, tags E-FUSE-CRD-P-1A. SM7/F6/1/2 fuses REMOVED. S/U*

Tags the trip fuses for Using a Danger Tag, E-FUSE-CRD-P-1A. SM7/F5/1/2 fuses REMOVED. S/U*

Tags the 4160 breaker for Using a Danger Tag, tags CRD-CB-CRD-P-1A. P1A for CRD-P-1A RACKED OUT. S/U*

Note: The discharge valve, CRD-V-14A is shown as closed on the tagout form. Because the tagout is for a gearbox oil change, the discharge valve has no safety significance and is optional on the manual taggout. It is satisfactory to include it on the tagout, or to leave it off.

Termination Criteria: Student presents the Manual Clearance Order Forms to the CRS.

RECORD TERMINATION TIME: _________

Page 2 of 5

TAGOUT CRD-P-1A USING THE MANUAL FORMS

Items are Critical Steps Comments Element Standard Sat/Unsat Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 5

TAGOUT CRD-P-1A USING THE MANUAL FORMS RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Manual Tag out for CRD-P-1A completed per OI-12.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5

TAGOUT CRD-P-1A USING THE MANUAL FORMS STUDENT JPM INFORMATION CARD Initial Conditions:

SOMS is out of service and will not be available for the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

CRD-P-1A must be tagged out for a gearbox oil change.

Cue:

Using the Manual Clearance Order Process per OI-12, tag out CRD-P-1A for a gearbox oil change.

Give the CRS the Manual Clearance Order forms when completed.

Page 5 of 5

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE VALVE LINEUP RWP MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Steve Garchow (NRC) DATE 9/10/04 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

TAGOUT CRD-P-1A USING THE MANUAL FORMS MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

NO SETUP NEEDED, ADMIN JPM Special Setup Instructions:

NO SETUP NEEDED, ADMIN JPM JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: Standard Safety Items Required for Entering the Plant Task Number: RO-0695 Validation Time: 12 Minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

Location: TABLE TOP NUREG 1123 Ref: 2.3.1 2.6/3.0 Performance Method: PERFORM Page 1 of 7

TAGOUT CRD-P-1A USING THE MANUAL FORMS JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL The reactor is operating at 100 percent and all systems are operating normally.

CONDITIONS:

INITIATING CUE: Because it is suspected that one of the valves for EDR-HX-2 is partially closed, the Shift Manager needs to have the EDR-HX-2 valve lineup inspected. These valves are located at the north end of EDR-HX-2.

As part of his decision making process, he has requested you to provide him with the following information as per ALARA Task: WO 00DK27 48 43.

What is the RWP number that will be used to do this inspection?

Based on the most recent HP information, what is the highest general area dose rate that can be expected around this component?

What type of radiation area is this?

Will the person following up on this problem have to enter a contaminated area to do the inspection?

Without any HP extensions or other approvals, what would the maximum allowable stay time be for this task? (Use the highest general dose rate for your determination and assume you have 100 mrem for the current quarter and year.)

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Page 2 of 7

TAGOUT CRD-P-1A USING THE MANUAL FORMS

Items are Critical Steps Comments Element Standard Sat/Unsat CUE: Cue response of simulated actions based on procedure and student actions.

CUE: While the candidate may use any reference available in the plant for this JPM, he/she may not request assistance from HP personnel. Because no high radiation area entry will be made for this JPM, no HP briefing is required.

CUE: Ask the candidate to record the requested information on the CUE card provided with this JPM.

CUE: The candidate will have to begin the sign in process at the Access Point to get the RWP up on the computer screen. Once the RWP information is obtained, instruct the candidate to abort the sign in process. If the candidate actually signs on to the RWP, ENSURE he/she signs back off again.

Perform all non-critical Applies initial conditions & P/L, steps IAW current completes steps IAW procedure. S/U procedure.

Reviews the RWP for the Goes to the RCA Access Point referenced ALARA task computer and inputs the ALARA S/U number. task number.

Reviews RWP 30001192 02 S/U*

CUE: Instruct the candidate to abort the sign in process once the RWP has been reviewed.

Determines the maximum general area dose is up to 250 mREM/hr. S/U*

Determines it is a high radiation area.

S/U*

Reviews survey map Locates the hard copy survey map showing EDR-HX-2. (Rx 422 South S/U Side)

Determines that the individual will not have to enter a contaminated area S / U*

to perform this task.

Calculates the maximum Determines the maximum stay time stay time. is 24 minutes. (100 mrem setpoint S / U*

on ED / 250 mrem dose rate = .4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months = 24 minutes)

Termination Criteria: When the candidate states all required information has been provided to the Shift Manager.

Page 3 of 7

TAGOUT CRD-P-1A USING THE MANUAL FORMS

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 4 of 7

TAGOUT CRD-P-1A USING THE MANUAL FORMS RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Provides the following information to the Shift Manager: RWP

30001192 02, highest general area dose is 250 mrem/hr, it is a high radiation area, a contaminated area need not be entered for the inspection, and the stay time is 24 minutes.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 12 Minutes / NA COMMENTS:

Page 5 of 7

TAGOUT CRD-P-1A USING THE MANUAL FORMS Evaluator's Signature: Date:

Page 6 of 7

TAGOUT CRD-P-1A USING THE MANUAL FORMS STUDENT JPM INFORMATION CARD Initial Conditions:

The reactor is operating at 100 percent and all systems are operating normally.

Cue:

Because it is suspected that one of the valves for EDR-HX-2 is partially closed, the Shift Manager needs to have the EDR-HX-2 valve lineup inspected. These valves are immediately adjacent to the north end of EDR-HX-2.

As part of his decision making process, he has requested you to provide him with the following information as per ALARA Task:

WO 00DK27 48 43.

What is the RWP number that will be used to do this inspection?

What is the highest general area dose rate that can be expected around this component?

What type of radiation area is this?

Will the person following up on this problem have to enter a contaminated area to do the inspection?

Without any RP extensions and/or approvals, what would the maximum allowable stay time be for this task? (Use the highest general dose rate for your determination and assume you have 100 mrem for the current quarter and year.)

No entries into a high radiation area will be made during this JPM.

Page 7 of 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Columbia Generating Station Task No:

Task

Title:

Complete an INOP Job Performance Measure No:

Equipment/LCO/RFO Status Sheet K/A

Reference:

2.1.18 2.9/3.0 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing: PERFORM Actual Performance: SIMULATOR NOTES: Provide the candidate with a blank INOP EQUIP/LCO/RFO STATUS SHEET and INOP EQUIP/LCO/RFO LOG sheet.

Page 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM SETUP INFORMATION Initial Conditions: CGS is operating at 90 percent power with no equipment out of service with the exception of the LAN Operations Log System computer.

Task Standard: Complete an INOP EQUIP/:LCO/RFO Status Sheet and make a corresponding log entry per PPM 1.3.1.

Required Materials: A copy of attachments 6.4 and 6.5 of PPM 1.3.1.

General

References:

PPM 1.3.1, rev 62, pages 84/85 Tech Specs and LCS.

Initiating Cue: At 1045, I&C notified the Shift Manager (by telephone) that follow-up troubleshooting on an ADS problem has determined ADS switch MS-RMS-ADS12A, ADS DIV 1 INHIBIT, has failed. Their testing indicates the contacts for S12A have failed in the NORMAL position and do not open when the switch is placed in the INHIBIT position. As a result, placing the switch in the INHIBIT position will not inhibit or reset ADS Channel A logic. The I&C technicians have not discussed this with anyone other than the SM and will generate a PER and WR later today after they discuss it with their supervisor.

The Shift Manager has directed you to complete an INOP EQUIP/LCO/RFO Status Sheet and make the corresponding Log entry for this situation. Provide him with the Status and Log Entry Sheets when completed so they can be put on the LAN when it becomes available.

Time Critical Task: NO Validation Time: 30 Minutes Simulator ICs: N/A Malfunctions/Remote N/A Triggers:

Overrides: N/A Special Setup None Page 2

Appendix C Job Performance Measure Form ES-C-1 Worksheet Instructions:

Page 3

Appendix C Job Performance Measure Form ES-C-1 Worksheet PERFORMANCE INFORMATION START TIME:

Critical Step:

Performance Step: 1 PPM 1.3.1, rev 62, page 84 Performance Step: 2 PPM 1.3.1, rev 62, page 85 Task Standard: Complete the referenced forms as shown in the attached. The candidates form does not have to be verbatim, however it shall be technically consistent with the attached.

The critical steps for this JPM are correctly identifying the LCS number (1.3.5.2) and the INOP time/date (1045 and todays date).

Comments:

SAT / UNSAT THE EXAIMINEE SHOULD ANNOUNCE THE TERMINATION POINT OF THE JPM AT THIS POINT.

JPM TERMINATION TIME:

JPM START TIME: -

JPM COMPLETION TIME:

Page 4

Appendix C Job Performance Measure Form ES-C-1 Worksheet VERIFICATION OF COMPLETION JPM Number: Complete an INOP Equipment/LCO/RFO Status Sheet NEW JPM - ADMIN Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Page 5

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM INFORMATION CARD HAND THE STUDENT INFORMATION CARD TO THE EXAMINEE READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiation cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Task Standard: Complete the referenced forms as shown in the attached. The candidates form does not have to be verbatim, however it shall be technically consistent with the attached.

The critical steps for this JPM are correctly identifying the LCS number (1.3.5.2) and the INOP time/date (1045 and todays date).

Required Materials: A copy of attachments 6.4 and 6.5 of PPM 1.3.1.

Tech Specs and LCS Safety Equipment: N/A General

References:

PPM 1.3.1, Conduct of Operations Technical Specifications Licensee Controlled Specifications (LCS)

Time Critical Task: No Initial Conditions: CGS is operating at 90 percent power with no equipment out of service with the exception of the LAN Operations Log System computer.

INITIATING CUE At 1045, I&C notified the Shift Manager (by telephone) that follow-up troubleshooting on an ADS problem has determined ADS switch MS-RMS-ADS12A, ADS DIV 1 INHIBIT, has failed. Their testing indicates the contacts for S12A have failed in the NORMAL position and do not open when the switch is placed in the INHIBIT position.

As a result, placing the switch in the INHIBIT position will not inhibit or reset ADS Channel A logic. The I&C technicians have not discussed this with anyone other than the SM and will generate a PER and WR later today after they discuss it with their Page 6

Appendix C Job Performance Measure Form ES-C-1 Worksheet supervisor.

The Shift Manager has directed you to complete an INOP EQUIP/LCO/RFO Status Sheet and make the corresponding Log entry for this situation. Provide him with the Status and Log Entry Sheets when completed so they can be put on the LAN when it becomes available EXAMINER CUE: Provide the candidate with a blank Status Sheet and Log Sheet for this JPM.

INFORMATION BELOW THIS LINE NOT SHARED WITH EXAMINEE Task Number: Validation Time: 30 minutes NUREG 1123

Reference:

2.1.18 2.9/3.0 Time Critical: No Location: SIMULATOR Performance Method: PERFORM Prepared/Revised by: S Garchow (NRC) Revision Date: New JPM Page 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet STUDENT INFORMATION Initial Conditions: CGS is operating at 90 percent power with no equipment out of service with the exception of the LAN Operations Log System computer.

INITIATING CUE At 1045, I&C notified the Shift Manager (by telephone) that follow-up troubleshooting on an ADS problem has determined ADS switch MS-RMS-ADS12A, ADS DIV 1 INHIBIT, has failed. Their testing indicates the contacts for S12A have failed in the NORMAL position and do not open when the switch is placed in the INHIBIT position.

As a result, placing the switch in the INHIBIT position will not inhibit or reset ADS Channel A logic. The I&C technicians have not discussed this with anyone other than the SM and will generate a PER and WR later today after they discuss it with their supervisor.

The Shift Manager has directed you to complete an INOP EQUIP/LCO/RFO Status Sheet and make the corresponding Log entry for this situation. Provide him with the Status and Log Entry Sheets when completed so they can be put on the LAN when it becomes available.

Page 8

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE INTERPRET EWDS MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY S. Hutchison DATE 6/20/04 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

INTERPRET EWDS MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

ADMIN JPM NO SIMULATOR SETUP NEEDED.

Special Setup Instructions:

ADMIN JPM NO SIMULATOR SETUP NEEDED.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: None Validation Time: 5 min.

Prerequisite Training: N/A Time Critical: NO PPM

Reference:

EWD 80E001 Location: Simulator NUREG 1123 Ref: 2.1.24 2.8/3.1 Performance Method: Perform Page 1 of 6

INTERPRET EWDS JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL The plant is operating at power. ROA-FN-1A has to be started for operability CONDITIONS: following maintenance.

INITIATING CUE: The plant is operating at power. ROA-FN-1A has to be started for operability following maintenance. The following scenario occurs:

The breaker for the fan has been racked in and the EO has notified the control room he is ready for a start.

The CRO notices that the green STOP/OFF indication at the control switch is off. Thinking the light bulb is burned out; the CRO places the control switch for ROA-FN-1A to start.

The EO reports the breaker closes by sound and the manual indicators but there is no closed indication on the lights on the breaker door.

The CRO also notes there is no closed/running indication in the control room.

The CRO places the control switch in the TRIP position.

Nothing happens, the fan continues to run.

All light bulbs have been verified as good.

Using EWD 80E001, explain why there are no indicating lights for ROA-FN-1A and why it did not trip.

Page 2 of 6

INTERPRET EWDS

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

Demonstrate on EWD Using EWD 80E001, demonstrate 80E001 the reason for the the following:

indications in the Initiating Cue. 1. Since there was no breaker indication locally or in the control room and the fan would not trip with the control switch the trip fuses FO4-1 and FO4-2 S/U*

(either or both) are blown or not installed correctly.

Termination Criteria: Student informs CRS that the trip fuses are bad/blown, which prevents both the light indications and tripping of the fan.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 6

INTERPRET EWDS RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Indications for the start of ROA-FN-1A are explained correctly using EWD 80E-001 Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 5 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 6

INTERPRET EWDS STUDENT JPM INFORMATION CARD Initial Conditions:

The plant is operating at power. ROA-FN-1A has to be started for operability following maintenance.

Cue:

The plant is operating at power. ROA-FN-1A has to be started following maintenance for operability. The following scenario occurs:

The breaker for the fan has been racked in and the EO has notified the control room he is ready for a start.

The CRO notices that the green STOP/OFF indication at the control switch is off. Thinking the light bulb is burned out; the CRO places the control switch for ROA-FN-1A to start.

The EO reports the breaker closes by sound and the manual indicators but there is no closed indication on the lights on the breaker door.

The CRO also notes there is no closed/running indication in the control room.

The CRO places the control switch in the TRIP position.

Nothing happens, the fan continues to run.

All light bulbs have been verified as good.

Using EWD 80E001, explain why there are no indicating lights for ROA-FN-1A and why it did not trip.

Page 5 of 6

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE VERIFY CLEARANCE ORDER FOR CORRECT VALVE LINEUP MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY S. Hutchison DATE 6/23/04 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

VERIFY CLEARANCE ORDER FOR CORRECT VALVE LINEUP MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

ADMIN JPM, NO SETUP NEEDED Special Setup Instructions:

ADMIN JPM, NO SETUP NEEDED JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: Copy of clearance order. Safety Items: N/A Task Number: RO-N-1157 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 1.3.64 step 3.9.1 Location: SIMULATOR/PLANT/TABLE TOP NUREG 1123 Ref: 2.2.13 3.6/3.8 Performance Method: PERFORM Page 1 of 5

VERIFY CLEARANCE ORDER FOR CORRECT VALVE LINEUP JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL The Aux Boiler is in operation to supply seal steam for the main turbine.

CONDITIONS:

The Aux Boiler Feedpump, CO-P-2B has a broken discharge flange and must be repaired.

The work is expected to last into the next shift.

Clearance Order D-CO-P-2B -010 is ready for review.

INITIATING CUE: You are directed to review Clearance Order D-CO-P-2B -010 using the supplied M513.

Notify the Shift Manager when you have found two (2) mistakes with this Clearance Order.

Page 2 of 5

VERIFY CLEARANCE ORDER FOR CORRECT VALVE LINEUP

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Perform all non-critical Applies initial conditions & P/L, steps IAW current completes steps IAW procedure. S/U procedure.

Clearance Order is The Clearance Order is reviewed reviewed for correctness. against M513 and the following S/U*

mistakes are identified:

CO-V-10 (CO-P-2B discharge) is open instead of closed.

CO-V-27B or CO-V-31B (CO-Note: CO-V-711B is used for a vent path and must be closed when returning the system to service.

Therefore, it is correct as listed on the return status as closed.

Termination Criteria: Student informs the Shift Manage of the above mistakes found in the Clearance Order.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 5

VERIFY CLEARANCE ORDER FOR CORRECT VALVE LINEUP RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Validation/Critical JPM Completion 10 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5

VERIFY CLEARANCE ORDER FOR CORRECT VALVE LINEUP STUDENT JPM INFORMATION CARD Initial Conditions:

The Aux Boiler is in operation to supply seal steam for the main turbine.

The Aux Boiler Feedpump, CO-P-2B has a broken discharge flange and must be repaired.

The work is expected to last into the next shift.

Clearance Order D-CO-P-2B -010 is ready for review.

Cue:

You are directed to review Clearance Order D-CO-P-2B -010 using the supplied M513.

Notify the Shift Manager when you have found two (2) mistakes with this Clearance Order.

Page 5 of 5

Appendix C Admin Job Performance Measure Form ES-C-1 Worksheet SA3JPMreplacement Facility: Columbia Generating Station Task No:

Task

Title:

Calculate Projected dose. Job Performance Measure No:

SA.3JPRMreplacement K/A

Reference:

2.3.11 2.7/3.2 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Perform - Simulator Page 1 Sa3jpmreplacement

Appendix C Admin Job Performance Measure Form ES-C-1 Worksheet SA3JPMreplacement JPM SETUP INFORMATION Initial Conditions: The plant was operating at 100% power when a transient occurred. The reactor scrammed 30 minutes ago. The following conditions exist:

Wind Speed - 14 mph

Wind Direction - from 62°

A release is underway from the Radwaste Building with Radwaste HVAC flowrate of 83,000 scfm.

WEA-RIS-14 indicates 1.92E5 cpm.

The release is expected to last 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Task Standard: Projected dose is calculated to correctly using QEDPS.

Required Materials: A computer terminal with QEDPS General PPM 13.8.1 rev. 25 pages 5, 6, & 7

References:

Initiating Cue: The plant was operating at 100% power when a transient occurred. The reactor scrammed 30 minutes ago. The following are the current conditions:

Wind Speed - 14 mph

Wind Direction - from 62°

A release is underway from the Radwaste Building with Radwaste HVAC flowrate of 83,000 scfm.

WEA-RIS-14 indicates 1.92E5 cpm.

The release is expected to last 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Stability class = E You are directed to calculate a projected dose using QEDPS.

Notify the CRS when you have completed the dose projection with the results.

Time Critical Task: NO Page 2 Sa3jpmreplacement

Appendix C Admin Job Performance Measure Form ES-C-1 Worksheet SA3JPMreplacement Validation Time: 15 minutes Simulator ICs: N/A Malfunctions/Remot N/A e Triggers:

Overrides: N/A Special Setup N/A Instructions:

Page 3 Sa3jpmreplacement

Appendix C Admin Job Performance Measure Form ES-C-1 Worksheet SA3JPMreplacement PERFORMANCE INFORMATION START TIME:

Critical Step: Yes Performance Step: 1 4.2.1: Turn on computer equipment as needed.

Standard: Equipment is on and ready for software start.

Comment:

SAT / UNSAT Critical Step: Yes Performance Step: 2 4.2.2: Start QEDPS by double clicking on QEDPS Icon.

Standard: Double click on the icon.

Comment:

SAT / UNSAT Critical Step: Yes Performance Step: 3 4.2.2.b: Select Radwaste Building Low Range Monitor, WEA-RIS-14..

Standard: Radwaste Low Range (WEA-RIS-14) Monitor selected.

Comment:

SAT / UNSAT Page 4 Sa3jpmreplacement

Appendix C Admin Job Performance Measure Form ES-C-1 Worksheet SA3JPMreplacement Critical Step: Yes Performance Step: 4 4.2.2.b: Enter 1.92E5 for the monitor reading.

Standard: Enter 1.92E5 for the monitor reading.

Comment:

SAT / UNSAT Critical Step: Yes Performance Step: 5 4.2.3.a: Enter 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months for the release duration.

Standard: Enter 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months for the release duration.

Comment:

SAT / UNSAT Critical Step: Yes Performance Step: 6 4.2.3.b: Enter 30 min for time since reactor shutdown.

Standard: Enter 30 min for time since reactor shutdown.

Comment:

SAT / UNSAT Critical Step: Yes Performance Step: 7 4.2.4: Enter meteorological data:

Wind Speed - 14 mph Wind Direction - 62° Stability Class - E Standard: Enters correctly as above.

Comment:

SAT / UNSAT Page 5 Sa3jpmreplacement

Appendix C Admin Job Performance Measure Form ES-C-1 Worksheet SA3JPMreplacement Critical Step: YES Performance Step: 8 4.2.5: Select RUN.

Standard: Run selected to run the program.

Comment:

SAT / UNSAT Critical Step: No Performance Step: 9 4.2.6: Select Print for paper output.

CUE: If candidate give the results verbally, instruct him to print the output.

Standard: Results printed.

Comment:

SAT / UNSAT THE EXAMINEE SHOULD ANNOUNCE THE TERMINATION POINT OF THE JPM AT THIS POINT.

JPM TERMINATION TIME:

JPM START TIME: -

JPM COMPLETION TIME:

Page 6 Sa3jpmreplacement

Appendix C Admin Job Performance Measure Form ES-C-1 Worksheet SA3JPMreplacement VERIFICATION OF COMPLETION JPM Number: SA.3JPM replacement Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Page 7 Sa3jpmreplacement

Appendix C Admin Job Performance Measure Form ES-C-1 Worksheet SA3JPMreplacement JPM INFORMATION CARD HAND THE STUDENT INFORMATION CARD TO THE EXAMINEE READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiation cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Task Standard: Projected dose is calculated to correctly using QEDPS.

Required Materials: A computer terminal with QEDPS Safety Equipment: N/A General PPM 13.8.1 rev. 25

References:

Time Critical Task: No Initial Conditions: The plant was operating at 100% power when a transient occurred. The reactor scrammed 30 minutes ago. The following conditions exist:

Wind Speed - 14 mph

Wind Direction - from 62°

A release is underway from the Radwaste Building with Radwaste HVAC flowrate of 83,000 scfm.

WEA-RIS-14 indicates 1.92E5 cpm.

The release is expected to last 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Page 8 Sa3jpmreplacement

Appendix C Admin Job Performance Measure Form ES-C-1 Worksheet SA3JPMreplacement INITIATING CUE The plant was operating at 100% power when a transient occurred. The reactor scrammed 30 minutes ago. The following conditions exist:

Wind Speed - 14 mph

Wind Direction - from 62°

A release is underway from the Radwaste Building with Radwaste HVAC flowrate of 83,000 scfm.

WEA-RIS-14 indicates 1.92E5 cpm.

The release is expected to last 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Stability class = E You are directed to calculate a projected dose using QEDPS.

Provide the CRS with the QEDPS printout with the results of your dose projections.

INFORMATION BELOW THIS LINE NOT SHARED WITH EXAMINEE Task Number: Validation Time: 15 minutes NUREG 1123

Reference:

2.3.11 Time Critical: No 2.7/3.2 Location: Simulator Performance Method: Perform Prepared/Revised by: S Hutchison Revision Date: 9/21/02 Page 9 Sa3jpmreplacement

Appendix C Admin Job Performance Measure Form ES-C-1 Worksheet SA3JPMreplacement STUDENT INFORMATION Initial Conditions: The plant was operating at 100% power when a transient occurred. The reactor scrammed 30 minutes ago. The following are the current conditions:

Wind Speed - 14 mph

Wind Direction - from 62°

A release is underway from the Radwaste Building with Radwaste HVAC flowrate of 83,000 scfm.

WEA-RIS-14 indicates 1.92E5 cpm.

The release is expected to last 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

INITIATING CUE The plant was operating at 100% power when a transient occurred.

The reactor scrammed 30 minutes ago. The following conditions exist:

Wind Speed - 14 mph

Wind Direction - from 62°

A release is underway from the Radwaste Building with Radwaste HVAC flowrate of 83,000 scfm.

WEA-RIS-14 indicates 1.92E5 cpm.

The release is expected to last 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Stability class = E You are directed to calculate a projected dose using QEDPS.

Provide the CRS with the QEDPS printout with the results of your dose projection.

Page 10 Sa3jpmreplacement

Appendix C Admin Job Performance Measure Form ES-C-1 Worksheet SA3JPMreplacement Page 11 Sa3jpmreplacement

Appendix C Job Performance Measure Form ES-C-1 Worksheet INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE CLASSIFY THE EP EVENT MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Steve Hutchison DATE 4/14/04 REVISED BY Steve Garchow (NRC) DATE 9/10/04 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Page 1

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Columbia Generating Station Task No: SRO-0233-P-PLA Task

Title:

Classify the Emergency and Job Performance Measure No:

PAR K/A

Reference:

2.4.41 2.3/4.1 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing: PERFORM Actual Performance: SIMULATOR NOTE: This JPM will be done after the performance of the dynamic scenarios run on day 1 and 2 of the 2004 ILC EXAM. The simulator will be frozen following the scenario and the classification will be based on the existing conditions.

NOTE: This JPM will only be performed on day 2 for those SRO candidates that did not complete it on day 1.

Page 2

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM SETUP INFORMATION Initial Conditions: CGS has experienced the plant event you have just performed.

Task Standard: Correctly classify the plant event as indicated on the Columbia Generating Station Classification Notification Form as shown in the attached. Note on day one there are three possible answer keys as follows:

1. If RPV level decreases to less than -161 than it is a Site Area Emergency based on 2.1.S.1.

2. If RPV level remains greater than -161 and the SRO declares there was a fire in the EDG room than it is an Alert based on 9.2.A.1 due to a fire in the EDG room.

3. If RPV level remains greater than -161 and the SRO does not declare a fire in EDG room than there is no EP classification.

On day two the EP classification is a site area emergency based on 2.2.S.1 based on an ATWS with reactor power remaining above 5 percent.

Required Materials: Columbia Generating Station Classification Notification Form General

References:

PPM 13.1.1, rev 32, page 14 PPM 13.2.2, rev 14, page 8 Initiating Cue: As the Shift Manager, you are directed to complete a Columbia Generating Station Classification Form and make a PAR based on the scenario you just completed. Base your classification on the highest EP level reached during the scenario. You have 15 minutes to provide me with your completed form and PAR.

Time Critical Task: 15 minutes Validation Time: 10 Minutes Simulator ICs: N/A Malfunctions/Remote N/A Triggers:

Overrides: N/A Page 3

Appendix C Job Performance Measure Form ES-C-1 Worksheet Special Setup This JPM will be done after the performance of all day 1 and day Instructions: 2 scenarios. For day 2 it will only be performed for those SROs that did not perform this JPM on day 1. The simulator will be frozen following the scenario and the classification will be based on the highest EP level reached during the scenario.

Page 4

Appendix C Job Performance Measure Form ES-C-1 Worksheet PERFORMANCE INFORMATION Start Time:

Critical Step: YES Performance Step: 1 PPM 13.1.1, rev 32, page 14 Performance Step: 2 PPM 13.2.2, rev 14, page 8 Standard: Correctly classify the plant event as indicated on the Columbia Generating Station Classification Notification Form as shown in the attached. Note on day one there are three possible answer keys as follows:

1. If RPV level decreases to less than -161 than it is a Site Area Emergency based on 2.1.S.1.

2. If RPV level remains greater than -161 and the SRO declares there was a fire in the EDG room than it is an Alert based on 9.2.A.1 due to a fire in the EDG room.

3. If RPV level remains greater than -161 and the SRO does not declare a fire in EDG room than there is no EP classification.

On day two the EP classification is a site area emergency based on 2.2.S.1 based on an ATWS with reactor power remaining above 5 percent.

Comments:

SAT / UNSAT THE EXAIMINEE SHOULD ANNOUNCE THE TERMINATION POINT OF THE JPM AT THIS POINT.

JPM TERMINATION TIME:

JPM START TIME: -

JPM COMPLETION TIME:

Page 5

Appendix C Job Performance Measure Form ES-C-1 Worksheet VERIFICATION OF COMPLETION JPM Number: Classify the Emergency and PAR NEW JPM - ADMIN Examinees Name:

Examiners Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Page 6

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM INFORMATION CARD HAND THE STUDENT INFORMATION CARD TO THE EXAMINEE READ TO THE EXAMINEE:

I will explain the initial conditions, which steps to simulate or discuss, and provide initiation cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Task Standard: Correctly classify the plant event as indicated on the Columbia Generating Station Classification Notification Form as shown in the attached. Note on day one there are three possible answer keys as follows:

1. If RPV level decreases to less than -161 than it is a Site Area Emergency based on 2.1.S.1.

2. If RPV level remains greater than -161 and the SRO declares there was a fire in the EDG room than it is an Alert based on 9.2.A.1 due to a fire in the EDG room.

3. If RPV level remains greater than -161 and the SRO does not declare a fire in EDG room than there is no EP classification.

On day two the EP classification is a site area emergency based on 2.2.S.1 based on an ATWS with reactor power remaining above 5 percent.

Required Materials: One Columbia Generating Station Classification Notification Form (CNF)

Safety Equipment: N/A General

References:

PPM 13.1.1, rev 32, page 14 PPM 13.2.2, rev 14, page 8 Time Critical Task: 15 minutes Initial Conditions: CGS has experienced the plant event you have just performed.

INITIATING CUE As the Shift Manager, you are directed to complete a Columbia Generating Station Page 7

Appendix C Job Performance Measure Form ES-C-1 Worksheet Classification Form and make a PAR based on the scenario you just completed. Base your classification on the highest EP level reached during the scenario. You have 15 minutes to provide me with your completed form and PAR.

INFORMATION BELOW THIS LINE NOT SHARED WITH EXAMINEE Task Number: SRO-0233-P-PLA Validation Time: 10 NUREG 1123

Reference:

2.4.41 2.3/4.1 Time Critical: 15 minutes Location: SIMULATOR Performance Method: PERFORM Prepared/Revised by: S Garchow (NRC) Revision Date: 8/29/2004 Page 8

Appendix C Job Performance Measure Form ES-C-1 Worksheet CANDIDATE JPM INFORMATION Initial Conditions: CGS has experienced the plant event you have just performed.

INITIATING CUE As the Shift Manager, you are directed to complete a Columbia Generating Station Classification Form and make a PAR based on the scenario you just completed. Base your classification on the highest EP level reached during the scenario. You have 15 minutes to provide me with your completed form and PAR.

Page 9

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE BYPASS CONTROL RODS ON RSCS (SIMULATOR)

LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

OJT Guide PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

Student Handout PQD Code Rev. No.

JPM PQD Code Rev. No.

Check off Sheet PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY STAFF DATE 9/92 REVISED BY Steve Garchow (NRC) DATE 08/16/04 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

None JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0134 Validation Time: 20 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

PPM 2.1.5 Section 5.2 Rev. 10 Location: Simulator NUREG 1123 Ref: 201004 A4.01 (3.4/3.5) Performance Method: Perform Page 1 of 4 LR000196 Rev.5

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL The SRO has verified bypassing control rod 50-19 is in compliance with Technical CONDITIONS: Specifications. The Shift Manager has given permission to bypass this control rod.

No control rods are currently bypassed.

INITIATING CUE: The CRS has directed you to bypass control rod 50-19 in the RSCS cabinet per steps 1 through 10 of PPM 2.1.5. Inform the CRS when you have bypassed control rod 50-19. CONTROL MANIPULATIONS WILL NOT BE PERFORMED. ALL ACTIONS AND STEPS WILL BE SIMULATED.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of actions based on procedure and student actions.

CUE: There are no control rods currently bypassed.

CUE: The rod sequence in effect is as reflected on P-601.

CUE: All indications are as reflected by the simulator as this JPM is performed.

NOTE: Reactor power may be at any level, including shutdown, for the performance of this JPM.

Perform all non-critical steps Applies initial conditions & P/L, IAW current procedure. completes steps IAW procedure. S/U Determine control rods that are Depresses the rod bypass pushbutton (if currently bypassed. not already selected) on P-601 to display all bypassed rods.

CUE: Step 4 (Record and initial verifications in the control room log) is to be simulated (i.e. locate the log and state what would be entered). The entry would be the total number of control rods is three or less and are in compliance with BPWS. Note that the candidate may instead chose to enter reactor power has been verified to be greater than 10%.

NOTE: The simulator does not require a key to open the door for P-659.

Open cabinet door Obtain the cabinet key and open door for cabinet P659.

Determines RSCS binary Determines RSCS binary equivalent X equivalent. and Y coordinates are 01110 and 01100 S/U utilizing Attachment 6.1.

Page 2 of 4 LR000196 Rev.5

Items are Critical Steps Comments Element Standard Sat/Unsat Selects control rod 50-19 to be Places toggle switches as follows:

bypassed using binary code. X0 = 0, and Y0 = 0 X1 = 1, and Y1 = 1 X2 = 1, and Y2 = 1 S/U*

X3 = 1, and Y3 = 0 X4 = 0, and Y4 = 0 CUE: Provide independent verification of rod toggle switch positions - Inform candidate the toggle switches are in the correct position.

Bypasses control rod 50-19. Places the BYPASSED/NOT BYPASSED Toggle Switch in the S/U*

BYPASSED position.

Verifies correct rod is bypassed The switch on P-603 is positioned to ROD BYPASSED position and the rod bypassed indicator light on the full core S/U display for rod 50-19 is verified.

Termination Criteria: Student informs CRS that control rod 50-19 is bypassed.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 4 LR000196 Rev.5

RESULTS OF JPM:

BYPASS CONTROL RODS ON RSCS Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

Control Rod 50-19 indicates it is bypassed in RSCS when verified on P-601 per PPM 2.1.5.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 20 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 4 LR000196 Rev.5

STUDENT JPM INFORMATION CARD Initial Conditions:

The SRO has verified bypassing control rod 50-19 is in compliance with Technical Specifications.

The Shift Manager has given permission to bypass this control rod.

No control rods are currently bypassed.

Cue:

The CRS has directed you to bypass control rod 50-19 in the RSCS cabinet per PPM 2.1.5.

Inform the CRS when you have bypassed control rod 50-19.

Page 5 of 4 LR000196 Rev.5

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RPV DEPRESSURIZATION LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

OJT Guide PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

Student Handout PQD Code Rev. No.

JPM PQD Code Rev. No.

Check off Sheet PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Steve Garchow (NRC) DATE 6/04 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Reactor shutdown Special Setup Instructions:

Reactor initial pressure is about 675 psig.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: Validation Time: 20 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

PPM 3.2.1 Section 5.6 Rev. 47 Location: Simulator NUREG 1123 Ref: 241000 A3.08 (3.3/3.2) Performance Method: Perform Page 1 of 5 LR000196 Rev.5

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL The plant is being shutdown and reactor pressure is approximately 675 psig. Section CONDITIONS: 5.4 of procedure 3.2.1 has been completed.

INITIATING CUE: The CRS has directed you to continue the plant shutdown using section 5.6 of procedure 3.2.1, Normal plant shutdown. You are to perform steps 5.6.5 through 5.6.8. Logging of RPV temperature and pressure will be performed by another operator.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of actions based on procedure and student actions.

Perform all non-critical steps Applies initial conditions & P/L, IAW current procedure. completes steps IAW procedure. S/U Initiate RPV Cooldown Obtains procedure PPM 3.2.1, Section 5.6. S/U Examiner Cue: Inform candidate step 5.6.6, Logging of RPV temperature and pressure, is being performed by another licensed operator.

Initiate a pressure setpoint Verify PRESS SETPOINT AUTO Mode change in PRESS SETPOINT is lit. S/U AUTO Mode Depress PRESS SETPOINT PSI S/U pushbutton.

Verify PRESS SETPOINT PSI S/U pushbutton light is lit Verify the current pressure setpoint S/U appears in the display and display demand window Enter the desired pressure setpoint with S / U*

the numerical keyboard Verify the desired pressure setpoint S/U appears in the display demand window Depress ENTER S/U Verify the old pressure setpoint remains S/U in the DISPLAY window Verify the HOLD light is lit S/U Depress PRESS RATE, PSI/MIN S/U Page 2 of 5 LR000196 Rev.5

Items are Critical Steps Comments Element Standard Sat/Unsat Verify PRESS RATE, PSI/MIN light is S/U lit Verify PRESS SETPOINT PSI light is S/U extinguished Verify the current selected pressure S/U setpoint rate of change appears in the display window Depress the PRESS SETPOINT PSI S / U*

pushbutton to display the new pressure setpoint and current value in the display window.

Depress GO S/U Verify the GO light backlights, the S/U HOLD light goes out, and the GO light go out when the new setpoint is reached.

Verify the steam supply pressure S/U responds as the display value changes Perform at 650 psig Bypass MSIV low vacuum Obtains keys 51, 52, 71, 72 for the S/U interlock bypass switches Place the condenser low vacuum S / U*

switches in bypass :

MS-RMS-S24A

MS-RMS-S24C

MS-RMS-S24B

MS-RMS-S24D Verify Annunciators Verify main condenser vacuum trip S/U bypass annunciators are lit:

P601-A11-6.2

P601-A12-2.2 Termination Criteria: Student informs CRS that step 5.6.8 of procedure PPM 3.2.1, Normal Plant Shutdown has been completed.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedures and remaining JPM pages may be discarded.

Page 3 of 5 LR000196 Rev.5

RESULTS OF JPM:

RPV DEPRESSURIZATION Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

A plant cooldown using the main turbine bypass valves has been established and the MSIV Low Vacuum Isolations have been bypassed per Steps 5.6.5 through 5.6.8 of procedure PPM 3.2.1, Normal Plant Shutdown.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 20 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5 LR000196 Rev.5

STUDENT JPM INFORMATION CARD Initial Conditions:

The plant is being shutdown for an outage.

Reactor pressure is approximately 675 psig.

Section 5.4 of procedure 3.2.1 has been completed.

Cue:

The CRS has directed you to continue the RPV cooldown by performing section 5.6 of procedure 3.2.1, Normal Plant Shutdown. You are to perform, as required, steps 5.6.5 through 5.6.8. Logging of RPV pressure and temperature will be performed by another operator.

Inform the CRS when you have completed step 5.6.8 of procedure 3.2.1.

Page 5 of 5 LR000196 Rev.5

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE ABN-FIRE/APPENDIX R FIRE AREA RC-13 ATTACHMENT LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

OJT Guide PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

Student Handout PQD Code Rev. No.

JPM PQD Code Rev. No.

Check off Sheet PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Steve Garchow (NRC) DATE 6/04 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

None JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: Validation Time: ? Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

ABN-FIRE, Attachment 7.1, Location: HVAC Equipment Room 1 Section RC-13, Revision 6 NUREG 1123 Ref: 600000 AK3.04 (2.8/3.4) Performance Method: Simulate Page 1 of 4 LR000196 Rev.5

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL The plant is shutdown because of a serious on-site fire that has affected some CONDITIONS: appendix R instrumentation.

INITIATING CUE: The CRS has directed you to complete section RC-13 of attachment 7.1 of procedure ABN-FIRE. CONTROL MANIPULATIONS WILL NOT BE PERFORMED. ALL ACTIONS AND STEPS WILL BE SIMULATED.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Perform all non-critical steps Applies initial conditions & P/L, IAW current procedure. completes steps IAW procedure. S/U Goes to local panel Goes to West HVAC Chase (RW 525) via RW 501 entrance to the cable chase then up the ladder to RW 525.

CUE:

Pull fuses Removes fuses TB-F04, TB-F08, TB-F10, TB-F11, TB-F12, TB-F14 S/U Stop Fan Stop fan WMA-FN-53B S /U CUE: The CRS wants fan WMA-FN-53A shutdown. Do not cover fire damper WMA-FD-57.

Stop Fan Stop fan WMA-FN-53A S /U RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 2 of 4 LR000196 Rev.5

RESULTS OF JPM:

ABN-FIRE/APPENDIX R FIRE AREA RC-13 ATTACHMENT Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

Fuses removed, and fans WMA-FN-53A and B shutdown per ABN-FIRE.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 3 of 4 LR000196 Rev.5

STUDENT JPM INFORMATION CARD Initial Conditions:

The plant is shutdown because of a serious on-site fire that has affected some appendix R instrumentation.

Cue:

The CRS has directed you to complete section RC-13 of attachment 7.1 of procedure ABN-FIRE.

Inform the CRS when you have completed section RC-13 of attachment 1 of procedure ABN-Fire.

CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

ALL ACTIONS AND STEPS WILL BE SIMULATED.

Page 4 of 4 LR000196 Rev.5

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE JET PUMP OPERABILITY SURVEILLANCE (CONTROL ROOM)

LESSON TITLE (FAULTED)

LESSON LENGTH 0.5 hr MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

OJT Guide PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

Student Handout PQD Code Rev. No.

JPM PQD Code Rev. No. 0 Check off Sheet PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Steve Garchow (NRC) DATE 7/2004 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

NA Special Setup Instructions:

Provide candidate with procedure OSP-RRC-D701, including the attachments. The jet pump dP evaluation found in Attachment 10.1 should be filled in for candidate use. The completed attachment is provided as a part of this JPM.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.

Tools/Equipment: Handheld calculator similar to the Safety Items: Standard items used to access the one used in the control room. plant.

Task Number: Validation Time: 30 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

OSP-RRC-D701 Rev. 8 Location: Control Room NUREG 1123 Ref: 202001A.1.02 (3.4/3.4) Performance Method: Perform Page 1 of 5 LR000162 Rev. 6

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL The plant is operating in a normal lineup at 100 percent power.

CONDITIONS:

INITIATING CUE: The CRS has directed you to perform surveillance procedure OSP-RRC-D701, Jet Pump Operability and Recirculation Loop Flow Mismatch. Sections 7.5, 7.6, 7.7 will not be performed and step 7.1.3 should be NAd. Note that another reactor operator has already recorded jet pump dP data in Attachment 10.1. The plant Process Computer is inoperable due to a faulty power supply. Inform the CRS when the surveillance has been completed and provide him/her with all completed paperwork/forms.

THE PERFORMANCE OF THIS JPM WILL BE PERFORMED. CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of actions based on procedure and student actions Perform all non-critical steps Applies initial conditions & P/L, IAW current procedure. completes steps IAW procedure. S/U Examiner Cues:

Provide the candidate with a calculator

Provide the candidate with the partially completed surveillance procedure.

Data recorded should be at or near 100 percent reactor power.

Determines correct procedure Performs section 7.2.3 and 7.2.4 for section. Normal Two Loop Operation S/U Examiner Cue: Surveillance steps 7.2.1 and 7.2.2 should be NAd due to the process computer being INOP.

Reviews data. Checks the NO box contained in step S / U*

7.2.3.b Records data. Records data as indicated for steps S/U 7.2.3.c, d, and e Records data Records date for recirc loop flows S/U Evaluates data. Checks the YES box for steps 7.2.3.f, g, S /U*

and h.

Records data. Records data in step 7.4.2 S/U Page 2 of 5 LR000162 Rev. 6

Items are Critical Steps Comments Element Standard Sat/Unsat Evaluates data Verifies loop flow mismatch is LE 2086 S / U*

gpm.

Communicates Informs the CRS the surveillance has been completed satisfactorily. The S/U candidate should report the anomaly with jet pump 7.

Cue:

Termination Criteria: Student informs CRS that the surveillance has been completed.

RECORD TERMINATION TIME: _________

Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 5 LR000162 Rev. 6

JET PUMP dP EVALUATION LOOP A PERCENT % DEVIATION MAX. ALLOWED MIN. ALLOWED JP1 37 - 9.76 % 15.20 - 24.80 JP2 40 - 2.44 % 16.88 - 23.12 JP3 41 0% 19.77 - 20.23 JP4 40 - 2.44 % 19.69 - 20.31 JP5 41 0% 27.61 - 12.39 JP6 43 + 4.88 % 22.27 - 17.73 JP7 49 + 19.51 % 19.43 - 20.57 JP8 42 + 2.44 % 21.52 - 18.48 JP9 40 - 2.44 % 19.48 - 20.52 JP10 37 - 9.76% 18.15 - 21.85 SUM 410 AVG=SUM/10 SUM/10 SUM/10 41

(=SUM/10)

LOOP B PERCENT % DEVIATION MAX. ALLOWED MIN. ALLOWED JP11 41 - 1.68 % 18.03 - 21.97 JP12 37 - 11.27 % 12.68 - 27.32 JP13 41 - 1.68 % 16.65 - 23.35 JP14 39 - 6.47 % 15.28 - 24.72 JP15 45 + 7.91 % 25.46 - 14.54 JP16 46 + 10.31 % 25.51 -14.49 JP17 43 + 3.12 % 18.82 - 21.18 JP18 39 + 6.47 % 23.49 - 16.51 JP19 43 + 3.12 % 25.39 -14.61 JP20 43 + 3.12 % 18.69 - 21.31 SUM 417 AVG=SUM/10 41.7

(=SUM/10)

Page 4 of 5 LR000162 Rev. 6

RESULTS OF JPM:

PREPARE FOR EMERGENCY WETWELL VENTING (JET PUMP OPERABILITY SURVEILLANCE)

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

Performs Jet Pump Operability and Recirculation Loop Flow Mismatch surveillance in accordance with OSP-RRC-D701. All appropriate sections of the surveillance are correctly filled out including the cover page. The candidate informs the CRS the surveillance passed.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used Validation/Critical JPM Completion for JPM (Initial Box) Time Time 30 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 5 of 5 LR000162 Rev. 6

STUDENT JPM INFORMATION CARD Initial Conditions:

The plant is operating at indicated power and the daily Jet Pump Operability and Recirculation Loop Flow Mismatch, OSP-RRC-D701, is due.

Cue:

The CRS has directed you to complete sections 7.1 and 7.2 of procedure OSP-RRC-D701, Jet Pump Operability and Recirculation Loop Flow Mismatch. Sections 7.5, 7.6, 7.7 will not be performed.

Note that another reactor operator has already recorded jet pump dP data in Attachment 10.1. The plant Process Computer is inoperable due to a faulty power supply. Inform the CRS when sections 7.1 and 7.2 have been completed and provide him with all completed paperwork/forms.

THE PERFORMANCE OF THIS JPM WILL BE PERFORMED. CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

Page 6 of 5 LR000162 Rev. 6

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RAISE SUPPRESSION POOL LEVEL USING HPCS SYSTEM (SIM)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LR000153 Rev. No. 6 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Staff DATE 8/92 REVISED BY Steve Garchow (NRC) DATE 8/31/04 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

RAISE SUPPRESSION POOL LEVEL USING HPCS SYSTEM MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Any IC Insert MAL-RHR001 with a severity of 8400 (Suppression pool leak at RHR loop A suction)

Special Setup Instructions:

After initializing to the desired IC, place the simulator in RUN. From the action window, select MAL and then RHR001. Place the severity of the malfunction to 8400. Allow the simulator to run until Suppression Pool level is approximately -4 inches. Clear the malfunction. If this JPM will be run more than once during the day, snapshot this setup.

Advance the Wetwell Level Recorders to hide the induced level transient.

Ensure RHR-V-4A is closed and tagged.

JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0713 Validation Time: 10 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 5.5.23 rev 4 Location: SIMULATOR NUREG 1123 Ref: 209002A4.09 (3.4/3.5) Performance Method: PERFORM Page 1 of 5 LR000 Rev.0

RAISE SUPPRESSION POOL LEVEL USING HPCS SYSTEM JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL Fatigue cracking of RHR Loop A suction has caused a suppression pool leak with a CONDITIONS: suppression pool level at -3.4 inches. HPCS is in a normal standby lineup with no initiation signal present. RHR-V-4A has been closed.

INITIATING CUE: PPM 5.2.1 has been entered due to low Suppression Pool Level. You have been directed by the CRS to raise Suppression Pool level using the HPCS system per PPM 5.5.23. Notify the CRS when Suppression Pool Level has been returned to 0 inches and HPCS-P-1 is closed.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Verify Pump Suction From Ensures HPCS-V-1, Pump Suction S/U CST, is open. From CST, is open.

Start HPCS-P-1 and ensure Starts HPCS-P-1 and ensures S / U*

Minimum Flow Bypass HPCS-V-12, HPCS-P-1 Minimum valve opens. Flow Bypass, opens. Critical Step If HPCS Service Water Starts HPCS-P-2. S/U Pump, is not running, then start.

Ensure Service Water Ensures SW-V-29, Service Water S/U Pump Discharge, opens. Pump Discharge, opens.

Note: HPCS initiation signal is NOT present, override of HPCS-V-23 is not necessary Open Test Bypass To Opens HPCS-V-23, Test Bypass To S / U*

Suppression Pool and Suppression Pool to a maximum of Critical Step adjust flow as necessary to 7175 GPM to fill the suppression a maximum of 7175 GPM. pool.

Ensure HPCS-V-12 closes. Ensures HPCS-V-12 closes. S/U Page 2 of 5 LR000 Rev.0

RAISE SUPPRESSION POOL LEVEL USING HPCS SYSTEM

Items are Critical Steps Comments Element Standard Sat/Unsat Monitor suppression pool Monitors suppression pool level S/U level When suppression pool When suppression pool level reaches S / U*

level reaches zero inches, zero inches, then closes HPCS-V-23. Critical Step then close HPCS-V-23.

Ensure HPCS-V-12 opens Ensures HPCS-V-12 opens S/U Refer to Attachment 6.1 Removes contact boot previously and remove contact boot installed on HPCS-RLY-K3. N/A previously installed on HPCS-RLY-K3.

If HPCS is not required for Stops HPCS-P-1 and ensures injection, then stop HPCS-V-12 closes. S/U HPCS-P-1 and ensure HPCS-V-12 closes.

Termination Criteria: Student informs CRS that Suppression Pool level is 0 inches and HPCS-P-1 is shutdown.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 5 LR000 Rev.0

RAISE SUPPRESSION POOL LEVEL USING HPCS SYSTEM RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

Suppression Pool Level is returned to 0 inches (+ or - 1 inch) in accordance with PPM 5.5.23.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 10 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5 LR000 Rev.0

RAISE SUPPRESSION POOL LEVEL USING HPCS SYSTEM STUDENT JPM INFORMATION CARD Initial Conditions:

Fatigue cracking of RHR Loop A suction has caused a suppression pool leak with a suppression pool level at -3.4 inches HPCS is in a normal standby lineup with no initiation signal present.

RHR-V-4A has been closed.

Cue:

PPM 5.2.1 has been entered due to low Suppression Pool Level.

You have been directed by the CRS to raise Suppression Pool level using the HPCS system per PPM 5.5.23.

Notify the CRS when Suppression Pool Level has been returned to 0 inches and HPCS-P-1 is shutdown.

Page 5 of 5 LR000 Rev.0

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE REMOVE DECAY HEAT FROM SGTS CARBON BED (SIM)

LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

OJT Guide PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

Student Handout PQD Code Rev. No.

JPM PQD Code LR000180 Rev. No. 2 Check off Sheet PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ken Elliott DATE 10/95 REVISED BY S Hutchison DATE 6/26/04 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Insert necessary commands to cause SGT carbon Bed High Temperature.

Special Setup Instructions:

Ensure high temperature alarm is in and temperature indicates GT alarm setpoint.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0380 Validation Time: 9 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

ABN-SGT-TEMP/RAD rev. 0 Location: Simulator NUREG 1123 Ref: 261000 A4.03 (3.0/3.0) Performance Method: Perform Page 1 of 4 LR000180 Rev.2

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL SGT Train A charcoal adsorber bed has experienced steadily increasing temperature.

CONDITIONS: It is believed that the increase is NOT due to a fire. All Div. 1 and 2 SGT components have been verified to be in normal standby lineup. HP and OPS 2 are stationed at the A SGT Unit. SGT Train B is in service as required by ABN-SGT-TEMP/RAD.

INITIATING CUE: The CRS has directed you to respond to the SGT A system charcoal adsorber high temperature using ABN-SGT-TEMP/RAD at step 4.2.

Inform the CRS when flow has been established in SGT Train A at 4000 scfm.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions VERIFY SGT-V-1A is Verifies SGT-V-1A is CLOSED CLOSED (Inlet From Containment).

VERIFY SGT-V-5A1 and Verifies SGT-V-5A1 and SGT-V-5A2 are CLOSED SGT-V-5A2 are CLOSED (Exhaust to Stack).

VERIFY SGT-V-2A is Verifies SGT-V-2A is OPEN OPEN (Inlet from Reactor Building).

VERIFY SGT-V-3A2 is Verifies SGT-V-3A2 is OPEN OPEN (Fan Inlet).

IF possible, STATION an Notifies HP.

HP technician near SGT to MONITOR for airborne (This is given in the cue) contamination/smoke.

Otherwise, N/A.

Cue: Hp is stationed as required.

OPEN SGT-V-4A1 Opens SGT-V-4A1 S / U*

(Exhaust to Reactor Critical Step Building).

Page 2 of 4 LR000180 Rev.2

Items are Critical Steps Comments Element Standard Sat/Unsat PLACE Places SGT-EHC-1A1control S / U*

SGT-EHC-1A1control switch to ON Critical Step switch to ON (Main Heater).

VERIFY SGT-FN-1A1 Verifies SGT-FN-1A1 starts starts within 10 seconds within 10 seconds after the Main after the Main Heaters Heaters energize.

energize.

IF the SGT system is Notifies the SRO that SGT A is required to be operable, inop.

THEN DECLARE the SGT train inoperable in the Plant Logging System.

Cue: Acknowledge that SGT A is inop and that it will be entered in the inop log.

Place SGT-DPIC-1A1 in Places SGT-DPIC-1A1 in S / U*

MANUAL, MANUAL, Critical Step AND AND ADJUST the flow rate to Adjusts the flow rate to approximately 4000 CFM approximately 4000 CFM as as indicated by indicated by SGT-FR-2A1.

SGT-FR-2A1.

Termination Criteria: The candidate notifies the SRO when the flow is approximately 4000 (+ o

- 20 %) CFM..

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 4 LR000180 Rev.2

RESULTS OF JPM:

REMOVE DECAY HEAT FROM SGT CARBON BED Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

Actions have been completed per ABN-SGT-TEMP/RAD Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critica JPM Completion JPM (Initial Box) Time Time 9 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 4 LR000180 Rev.2

STUDENT JPM INFORMATION CARD Initial Conditions:

SGT Train A charcoal adsorber bed has experienced steadily increasing temperature.

It is believed that the increase is NOT due to a fire.

All Div. 1 and 2 SGT components have been verified to be in normal standby lineup.

HP and OPS 2 are stationed at the A SGT Unit.

SGT Train B is in service as required by ABN-SGT-TEMP/RAD.

Cue:

The CRS has directed you to respond to the SGT A system charcoal adsorber high temperature using ABN-SGT-TEMP/RAD at step 4.2.

Inform the CRS when flow has been established in SGT Train A at 4000 scfm.

Page 5 of 4 LR000180 Rev.2

Material verified current prior to use.

Initials_______

Date:________

INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE RESTORATION OF RPS ELECTRICAL ALIGNMENT TO NORMAL (FAULTED)

LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

OJT Guide PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

Student Handout PQD Code Rev. No.

JPM PQD Code Rev. No.

Checkoff Sheet PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Dan Hughes DATE 4/14/95 REVISED BY Steve Garchow (NRC) DATE 06/16/04 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

None Special Setup Instructions:

Have procedure PPM 2.7.6 including the attachments ready to provide to candidate.

JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

Evaluator and student shall use the current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.

Tools/Equipment: None. Safety Items: None Task Number: EO-0158 Validation Time: 20 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

PPM 2.7.6 Rev. 18 Location: Plant NUREG 1123 Ref: 212000A2.01 (3.7/3.9) Performance Method: Simulate Page 2 of 6 LR000251 Rev. 8

JPM CHECKLIST PROCEDURE Verify the revision number of procedure copies for evaluator and student. If the VALIDATION procedure revision is different from that listed on the JPM, the critical tasks must be verified. The evaluator copy may be used for marking step completion and comments.

INITIAL RPS Division A is energized from the alternate source of power. The RPS A MTR CONDITIONS: GEN MG-1 supply breaker (RPS-DISC-7A1B) on MC-7A is closed.

INITIATING CUE: The CRS has directed you to place the A RPS motor generator and associated EPA breakers in service in accordance with PPM 2.7.6 section 5.3. You are to complete this procedure through step 5.3.6. The division will be restored to a normal lineup following the post maintenance test.

Inform the CRS when the GENERATOR A FEED white power available indicating light on H13-P610 is illuminated.

The performance of this task is simulated. Control manipulations will not be performed.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and operator actions Performs all non-critical Applies initial conditions & P/L, steps IAW current completes steps IAW procedure. S/U procedure.

Locates Procedure Locates procedure PPM 2.7.6 in the control room.

CUE: When the candidate locates PPM 2.7.6, provide him/her with a For Information Only copy for JPM use.

Obtains Keys. Obtains EPA breaker keys # 166 S/U

& 168.

NOTE: If the keys are not obtained when in the control room getting the procedure, it is not necessary to return to the control room. Have the candidate verbalize the location of the keys. (The keys are located in the key locker located on the wall to the left of the Shift Managers office door.)

CUE: After Checks MG Power Supply Verifies RPS-DISC-7A1B is Given as candidate locates closed. closed in the the correct initial breaker, inform conditions him/her it is Page 3 of 6 LR000251 Rev. 8

Items are Critical Steps Comments Element Standard Sat/Unsat closed.

CUE: Green Starts the RPS MG set a. Ensure the MOTOR OFF S/U light is lit. (green) indicating light is illuminated.

S/U CUE: The output b. Ensure RPS-CB-MG1, breaker is open. Generator Output breaker, is open.

c. Hold RPS-RMS- S/U MG1/START, MOTOR ON, pushbutton depressed.

S/U CUE: The green

d. Ensure the MOTOR OFF light goes out and (green) indicating light the red light extinguishes and the MOTOR comes on.

ON (red) indicating light illuminates.

S/U

e. When RPS-MG-1 has come up to speed, release RPS-RMS-MG1/START pushbutton.

NOTE: MOTOR ON pushbutton doubles as an Over Voltage Trip Reset pushbutton.

S/U

f. If voltage is not indicated at rated speed, momentarily depress RPS-RMS-MG1/START, MOTOR ON, pushbutton to reset the overvoltage trip. S/U CUE: The g. Ensure RPS-VM-MG1A voltage stabilizes voltage stabilizes at at 120 VAC. *120 VAC.

CUE: The output Closes the RPS MG output At RPS-MG-1 panel, places S/U breaker is closed. breaker GENERATOR OUTPUT breaker in ON (pushed up)

Page 4 of 6 LR000251 Rev. 8

Items are Critical Steps Comments Element Standard Sat/Unsat Obtain required Electrical S/U Closes EPAs Protection Assembly (EPA) breaker keys, numbers 166 and 168, from the Control Room key locker.

5.3.3 In RPS-MG2 Room, close EPA breaker RPS-EPA- S / U*

3A as follows:

a. Ensure breaker keylock CUE: Switch S-1 switch S-1 is in the is in the normal NORMAL position.

position. S/U CUE: S-2 is in b. Ensure breaker keylock the OPER switch S-2 is in the OPER position. position. S/U CUE: The c. Ensure the POWER IN POWER IN indicator is illuminated.

S/U indicator is lit.

d. IF any of the following CUE: Inform indicators are not operator that all extinguished, THEN S / U*

indicators are rotate keylock switch S-2 extinguished to the RESET position and except return to OPER.

UNDERFREQUE Otherwise, N/A.

NCY.

OVERVOLTAGE

UNDERVOLTAGE

UNDERFREQUENCY

POWER OUT Page 5 of 6 LR000251 Rev. 8

Items are Critical Steps Comments Element Standard Sat/Unsat

e. Ensure the following S/U CUE: Inform indicators are operator that all extinguished:

indicators are extinguished.

OVERVOLTAGE

UNDERVOLTAGE

UNDERFREQUENCY

POWER OUT Page 6 of 6 LR000251 Rev. 8

Items are Critical Steps Comments Element Standard Sat/Unsat

f. Reset EPA breaker RPS- S/U EPA-3A by opening it fully.

CUE: RPS-EPA- g. Close the EPA breaker S / U*

3A is closed. RPS-EPA-3A.

CUE: The h. Ensure POWER OUT POWER OUT indicator is illuminated. S/U indicator is lit.

NOTE: EPA breakers are designed such that the undervoltage lights for RPS-EPA breakers may illuminate indicating an undervoltage condition without activating the undervoltage trip circuit.

i. IF the UNDERVOLTAGE light is illuminated and the The UNDER- breaker is closed, THEN VOLTAGE light initiate a work request to is not lit. evaluate. Otherwise, N/A.

NOTE: EPA breakers use key S/U numbers 166 and 168.

5.3.4 In RPS-MG2 Room, close EPA breaker RPS-EPA- S / U*

3C as follows:

CUE: S-1 is in a. Ensure breaker keylock S/U the NORMAL switch S-1 is in the position. NORMAL position.

S/U CUE: S-2 is in b. Ensure breaker keylock the OPER switch S-2 is in the position. OPER position.

Page 7 of 6 LR000251 Rev. 8

Items are Critical Steps Comments Element Standard Sat/Unsat Termination Criteria: Operator informs the CRS that the EPA breakers are closed.

RECORD TERMINATION TIME: _________

Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. Marked Up procedure and remaining JPM pages may be discarded.

Page 8 of 6 LR000251 Rev. 8

RESULTS OF JPM RESTORATION OF RPS ELECTRICAL ALIGNMENT TO NORMAL Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: EPA breakers are closed.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial box) Time Time

? Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 9 of 6 LR000251 Rev. 8

STUDENT JPM INFORMATION CARD Initial Conditions:

RPS Division A is being powered from the alternate power supply.

The RPS transfer switch is in the ALT A position.

Maintenance has completed their work on the RPS A MTR GEN MG-1.

The RPS A MTR GEN MG-1 supply breaker (RPS-DISC-7A1B) on MC-7A is closed.

Cue:

The CRS has directed you to place the A RPS motor generator and associated EPA breakers in service in accordance with PPM 2.7.6. You are to complete this procedure through step 5.3.7. RPS will be restored to a normal electrical lineup following the post maintenance test.

Inform the CRS when the GENERATOR A FEED white power available indicating light on H13-P610 is illuminated.

THE PERFORMANCE OF THIS JPM IS SIMULATED.

CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

Page 10 of 6 LR000251 Rev. 8

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE STARTUP A REACTOR FEED PUMP LESSON LENGTH 0.5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

OJT Guide PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

Student Handout PQD Code Rev. No.

JPM PQD Code LR000232 Rev. No. 9 Checkoff Sheet PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY L. Monroe DATE 04/13/95 REVISED BY M. Evosevich DATE 10/13/98 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Superintendent

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

IC-5 Special Setup Instructions:

Shutdown the A RFP per PPM 2.2.4 Section 5.10 by performing only the following steps in sequence:

- Transfer RFW-SC-601A to MDEM

- Trip the RFP by placing the Turbine Emergency Trip/Reset switch to Trip

- Lower RFW-SC-601A until the MIN light illuminates

- Close RFW-V-102A

- Open MS-V-105A

- Open BS-V-17A

- Reset RFW A Trip

- Ensure RFT-P-MOPA ON

- Ensure RFT-P-EOPA OFF Verify the following:

- RPV level is stable

- The A RFP is on the turning gear

- The turning gear C/S is ON

- COND-V-149 is open JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

The evaluator and student shall use the current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0371 Validation Time: 30 min.

Prerequisite Training: N/A Time Critical: No PPM

Reference:

PPM 2.2.4 Rev. 26 Location: Simulator NUREG 1123 Ref: 259001A4.02 (3.9/3.7) Performance Method: Perform JPM CHECKLIST Page 1 of 4 LR000232.JPM Rev. 9

PROCEDURE Verify the revision number of procedure copies for evaluator and student. If the procedure VALIDATION revision is different from that listed on the JPM, the critical tasks must be verified. The evaluator copy may be used for marking step completion and comments.

INITIAL A reactor startup is in progress and a feed pump must be started. Both of the RFPs are fully CONDITIONS: operational. CPU A is in service.

You have been directed by the CRS to perform a start of the A RFP in accordance with INITIATING CUE: PPM 2.2.4. The procedure has been completed to Section 5.6, step 5.6.2. Inform the CRS when RFP A is in service maintaining level in accordance with PPM 2.2.4.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and operator actions Performs all non-critical steps Applies initial conditions & P/L, IAW current procedure. completes steps IAW procedure. S/U Opens pump discharge. Opens RFW-V-102A S / U*

CUE: If asked cue operator that the turning gear is not wired up.

Checks status of speed Ensures RFW-SC-601A is in MDVP at S / U*

controller 0% and the MIN indicator is illuminated.

Rolls the turbine. Using RFW-SC-601A, increases speed S / U*

to 800 rpm.

Ensures turning gear Ensures the Turning Gear disengages. S / U*

disengages.

Transfers speed controller Depresses the MDEM pushbutton and S / U*

increases turbine speed to 1000 rpm.

Cue: Turbine has rolled for greater than 30 minutes.

Cue: Turbine was not jacked using minimum flow.

Increases turbine speed. Using RFW-SC-601A, increases speed S / U*

to 1800 rpm.

Closes bypass valve Closes COND-V-149 S / U*

Adjusts turbine speed. Using RFW-SC-601A, adjusts turbine S / U*

speed to maintain proper 10 valve position.

Termination Criteria: Operator informs the CRS that RFP A is in service and maintaining level in accordance with PPM 2.2.4.

RECORD TERMINATION TIME: _________

Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time. Marked Up procedure and remaining JPM pages may be discarded.

Page 2 of 4 LR000232.JPM Rev. 9

RESULTS OF JPM:

STARTUP A REACTOR FEED PUMP Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: A feed pump is maintaining RPV level.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used Validation/Critical JPM Completion for JPM Time Time 30 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 3 of 4 LR000232.JPM Rev. 9

STUDENT JPM INFORMATION CARD Initial Conditions: A reactor startup is in progress and a feed pump must be started. Both of the RFPs are fully operational. CPU A is in service.

Cue:

You have been directed by the CRS to perform a start of the A RFP in accordance with PPM 2.2.4. The procedure has been completed to Section 5.6, step 5.6.2. Inform the CRS when RFP A is in service maintaining level in accordance with PPM 2.2.4.

Page 4 of 4 LR000232.JPM Rev. 9

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE SHIFTING SHUTDOWN COOLING LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

OJT Guide PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

Student Handout PQD Code Rev. No.

JPM PQD Code Rev. No.

Check off Sheet PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Steve Garchow (NRC) DATE 6/04 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Normal shutdown IC - see special setup instructions Special Setup Instructions:

RHR-RMS-FCV/64A is danger tagged. RHR-42-7BA7B breaker is open. RRC-V-67A is closed.

SW-P-1A is running. Reactor pressure is less than 100 psig. There is less than 80 degree differential between the A RHR heat exchanger outlet and the RRC-P-1A suction. Reactor vessel level is +80 inches. SW-P-1A is in operation.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: Validation Time: ? Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

SOP-RHR-SDC, Section 5.8, Location: Simulator Revision 3 NUREG 1123 Ref: 205000 A4.09 (3.1/3.1) Performance Method: Perform Page 1 of 5 LR000196 Rev.5

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL The plant is shutdown for a refueling outage. RRC-P-1A is shutdown and RRC-P-CONDITIONS: 1B is operating. Service water pump 1A is in service.

INITIATING CUE: The CRS has directed you to shift shutdown cooling from loop B to RHR loop A using section 5.8 of procedure SOP-RHR-SDC. You are to perform, as required, steps 5.8.1 through 5.8.27. Inform the CRS when you have completed step 5.8.27 of SOP-RHR-SDC.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Perform all non-critical steps Applies initial conditions & P/L, IAW current procedure. completes steps IAW procedure. S/U Examiner Cues:

There is no degraded core condition.

There is no reactor recirc pump (RRC) start planned

The reactor has been shutdown for 30 days

Step 5.8.1 -

Section 5.5, Securing RHR Loop B Shutdown Cooling, has been completed Close Valve Close RHR-V-6B S/U Open Valve Open RHR-V-4B S /U Verify Verify RRC-V-67B is Open S /U Page 2 of 5 LR000196 Rev.5

Items are Critical Steps Comments Element Standard Sat/Unsat Verify Verify RRC-V-23B is Open S /U Examiner Cue:

Step 5.8.9 has been waived by the CRS based on ALARA considerations Verify Verify RHR-V-4A is Closed S /U Verify Verify RHR-V-6A is Open S /U Verify Verify RHR-V-8 is Open S /U Verify Verify RHR-V-9 is Open S /U Verify Verify RRC-V-67A or RRC-V-23A is closed Verify Verify the differential temperature between RHR Heat Exchanger outlet and RRC-P-1A suction is less than 80 degrees Close Valve Close RHR-V-48A S /U Throttle Open Valve Throttle Open RHR-V-48A for 8 S /U seconds.

Close Valve Close RHR-V-3A S /U Start Pump Start RHR-P-2A S /U Open Valve Immediately Open RHR-V-53A S /U Throttle Valve Throttle RHR-V-48A to obtain flow of S /U about 3000 gpm Throttle Valve Throttle RHR-V-48A to obtain flow of S /U GT 5400 gpm.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 5 LR000196 Rev.5

RESULTS OF JPM:

SHIFTING SHUTDOWN COOLING Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

RHR loop A is in service providing shutdown cooling.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5 LR000196 Rev.5

STUDENT JPM INFORMATION CARD Initial Conditions:

The plant is shutdown for a refueling outage.

RRC-P-1A is secured.

RRC-P-1B is operating.

Section 5.5 of SOP-RHR-SDC is complete.

Reactor vessel level is +80 inches.

Cue:

The CRS has directed you to shift shutdown cooling from loop B to loop A using section 5.8 of procedure SOP-RHR-SDC. You are to perform, as required, steps 5.8.1 through 5.8.27.

Inform the CRS when you have completed step 5.8.27 of SOP-RHR-SDC.

Page 5 of 5 LR000196 Rev.5

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE START AN RRC PUMP WITH THE REACTOR AT POWER (FAULTED)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code ????? Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Steve Hutchison DATE 4/14/04 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

TITLE MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

IC-14 or special IC created for JPM set.

Special Setup Instructions:

Trip RRC-P-1A, open breakers CB-RRA, CB-RPT4A, CB-RPT3A, and allow conditions to stabilize.

JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: RO-0061-N-RRC Validation Time: ??

Prerequisite Training: N/A Time Critical: NO PPM

Reference:

SOP-RRC-START rev. 0 Location: Simulator NUREG 1123 Ref: 202001A4.01 (3.7/3.7) Performance Method: Perfrom Page 1 of 4 LR000 Rev.0

TITLE JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL The plant was operating at 99% power when RRC-P-1A tripped. The cause has CONDITIONS: been corrected and RRC-P-1A is ready for a start.

The SNE is in the control room and has evaluated Core Maximum Peaking Factor and RPV inlet temperater as satifactory per PPM 9.3.12. A startup plan is in place.

RRC seal purge has been in service GT 30 minutes.

INITIATING CUE: The CRS has directed you to start RRC-P-1A per SOP-RRC-START section 5.1 step 5.1.2.

Notify the CRS when RRC-P-1A has been started and is operating at 15 Hz.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Perform all non-critical Applies initial conditions & P/L, steps IAW current completes steps IAW procedure. S/U procedure.

Lowers operating loop Lower and maintain the operating drive flow loop drive flow at approximatelyh S/U*

20,800 gpm.

Closes RRC-P-1A but tie Places control switch for Breaker breaker CB-RRA to the CLOSE postion. S/U*

Closes RRC-P-1A motor Places control switch for Breaker interlock breaker CB-RPT4A to the CLOSE postion. S/U*

Closes RRC-P-1A motor Places control switch for Breaker interlock breaker CB-RPT3A to the CLOSE postion. S/U*

Ensures temperatures are Verifies temperatures are within the within limits limits of OSP-RRC-C103 - Pen 1 & S/U*

2 on RRC-TR-650 is LE 50°.

Starts RRC-P-1A Momentarily pushes the ASD Pushbutton to start the pump. S/U*

Page 2 of 4 LR000 Rev.0

TITLE

Items are Critical Steps Comments Element Standard Sat/Unsat Verifies speed of RRC-P- Stops the pump by pressing the ASD 1A STOP pushbutton when the pump S/U*

speed does not reach 15 hz LE 50 seconds.

S/U*

Termination Criteria: Student informs CRS that RRC-P-1A has been tripped due to inadequate speed.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 4 LR000 Rev.0

TITLE RESULTS OF JPM:

PUT YOUR JPM TITLE HERE Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 4 LR000 Rev.0

TITLE STUDENT JPM INFORMATION CARD Initial Conditions:

The plant was operating at 99% power when RRC-P-1A tripped. The cause has been corrected and RRC-P-1A is ready for a start.

The SNE is in the control room and has evaluated Core Maximum Peaking Factor and RPV inlet temperater as satifactory per PPM 9.3.12. A startup plan is in place.

RRC seal purge has been in service GT 30 minutes.

Cue:

The CRS has directed you to start RRC-P-1A per SOP-RRC-START section 5.1 step 5.1.2.

Notify the CRS when RRC-P-1A has been started and is operating at 15 Hz.

Page 5 of 4 LR000 Rev.0

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE VENT CRD OVERPISTON AREA FOR ROD INSERTION (PLANT)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

OJT Guide PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

Student Handout PQD Code Rev. No.

JPM PQD Code LR000258 Rev. No. 12 Check off Sheet PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Donald Hughes DATE 4/95 REVISED BY Jim Redwine DATE 10/29/02 TECHNICAL REVIEW BY Pat Bagan (Signature on File) DATE 10/24/01 INSTRUCTIONAL REVIEW BY Jim Redwine (Signature on File) DATE 10/23/01 APPROVED BY Randy Guthrie (Signature on File) DATE 10/25/01 Operations Training Manager

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

N/A JPM Instructions:

Verify the current procedure against the JPM. If the procedure is a different revision than listed in the JPM, ensure the critical steps still match. If the critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0683, EO-1443 Validation Time: 8 minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 5.5.11 Rev. 4 Location: PLANT NUREG 1123 Ref: 295037EA1.05 (3.9/4.0) Performance Method: SIMULATE Page 1 of 5 LR000258 Rev. 12

JPM CHECKLIST PROCEDURE Regarding procedure copies for evaluator and student, if the procedure revision is VALIDATION different from that listed on the JPM, verify that the critical task steps are the same.

Evaluator copy may be used for marking step completion, and comments.

INITIAL A scram has been initiated. All rods are NOT fully inserted. Reactor pressure is 930 CONDITIONS: psig, stable. Health Physics is standing by, ready to support the work.

Communications have been established between the control room and the HCUs.

INITIATING CUE: The CRS has directed you to vent control rod 26-31 over-piston area in accordance with PPM 5.5.11. Inform the CRS when Rod 26-31 venting has commenced.

THE PERFORMANCE OF THIS JPM WILL BE SIMULATED. CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Obtain continuous HP coverage prior to venting.

Using Att. 6.3 selects S/U*

correct row if HCUs for control rod 26-31. Critical Step Establish communications between the HCUs and the control room.

Ensure leather gloves are worn to prevent burns.

Connect CRD vent hose to EDR drain.

At the HCU close CRD-V- S/U*

102 withdraw vent isolation. Critical Step Page 2 of 5 LR000258 Rev. 12

Items are Critical Steps Comments Element Standard Sat/Unsat Caution: Pressurized water could be trapped behind dragon vent valve plugs and cause personal injury or contamination.

Remove the bottom and S/U*

end plugs from CRD-V-102A withdraw vent valve Critical Step Connect CRD vent hose to S/U*

the bottom of CRD-V-102A, withdraw vent Critical Step valve.

Caution: Opening CRD-V-102A may eject the valve and cause severe personal injury.

Open CRD-V-102A ONE S/U*

turn.

Critical Step Inform the SRO of the results.

Termination Criteria: Student informs CRS that rod 26-13 venting has commenced.

RECORD TERMINATION TIME: _________

Transfer the following information to the Results of JPM page: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time.

The marked up procedure and remaining JPM pages may be discarded.

Page 3 of 5 LR000258 Rev. 12

RESULTS OF JPM:

VENT CRD OVERPISTON AREA FOR ROD INSERTION Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Control rod 26-31 over-piston area vented per PPM 5.5.11.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 8 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5 LR000258 Rev. 12

STUDENT JPM INFORMATION CARD Initial Conditions:

A scram has been initiated

All rods are NOT fully inserted

Reactor pressure is 930 psig, stable

Health Physics is standing by, ready to support the work

Communications have been established between the control room and the HCUs.

Cue:

The CRS has directed you to vent control rod 26-31 over-piston area in accordance with PPM 5.5.11.

Inform the CRS when Rod 26-31 venting has commenced.

THE PERFORMANCE OF THIS JPM WILL BE SIMULATED.

CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

Page 5 of 5 LR000258 Rev. 12

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE PREPARE FOR EMERGENCY WETWELL VENTING LESSON TITLE (HIGH H2 AND O2 CONCENTRATIONS (CONTROL ROOM)

LESSON LENGTH 0.5 MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

OJT Guide PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

Student Handout PQD Code Rev. No.

JPM PQD Code LR000162 Rev. No. 6 Check off Sheet PQD Code Rev. No.

Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Larry Monroe DATE 10/21/94 REVISED BY Ron Hayden DATE 10/01/01 TECHNICAL REVIEW BY Pat Bagan (Signature on File) DATE 10/24/01 INSTRUCTIONAL REVIEW BY Jim Redwine (Signature on File) DATE 10/17/01 APPROVED BY Randy Guthrie (Signature on File) DATE 10/25/01 Operations Training Manager

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

NA JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The instructor should mark off steps as they are completed, note comments, and transfer the comments to the results of JPM page.

Tools/Equipment: Flashlight, if required Safety Items: High voltages inside panels Task Number: RO-0690 Validation Time: 20 Minutes Prerequisite Training: N/A Time Critical: NO PPM

Reference:

PPM 5.5.20 Rev. 5 Location: Control Room NUREG 1123 Ref: 295024GA.12 (3.9/4.5) Performance Method: Simulate Page 1 of 5 LR000162 Rev. 6

JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL A LOCA has occurred coincident with a loss of Off Site power. Parameters now CONDITIONS: indicate that Primary Containment integrity may be challenged due to potentially flammable atmosphere in containment. The Reactor Building is inaccessible.

INITIATING CUE: The CRS has directed you to use SGT B to emergency vent the wetwell per PPM 5.5.20 due to high H2 and O2 concentrations. Inform the CRS when Wetwell Venting has been initiated. THE PERFORMANCE OF THIS JPM WILL BE SIMULATED.

CONTROL MANIPULATIONS WILL NOT BE PERFORMED.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions Perform all non-critical steps Applies initial conditions & P/L, IAW current procedure. completes steps IAW procedure. S/U Obtains screwdriver, tape, and jumpers.

CUE: The tools should be located but need not be taken to the affected panels.

Override Inlet From Lifts and tapes the gray (top) lead on Containment isolation logic. terminal 16 of TM-K2-1-09 at H13-P891 Bay 1. S / U*

CUE: Inform candidate the selected lead is lifted and taped.

Prevent B SGT Lead and Lag Places SGT-EHC-1B-2 to PTL at H13-Heater and Fan Operation. P811.

S / U*

At H13-P892 Bay 1:

Lifts/tapes the gray lead on term. 10 TM-K1-1-18.

Lifts/tapes the gray lead on term. 4 TM-K1-1-20.

Lifts/tapes the gray lead on term. 5 TM-K1-1-20.

CUE: Inform candidate each of the leads is lifted and taped.

CUE: CAUTION - K2-21/23 terminal strip cover SHOULD NOT BE REMOVED FOR JPM Override wetwell exhaust Overrides CEP-V-3A by installing outboard isolation logic. jumper between terminal 6 and 7 on TM-K1-4-7 at H13-P892 Bay 4. S/U*

Page 2 of 5 LR000162 Rev. 6

Items are Critical Steps Comments Element Standard Sat/Unsat CUE: Inform candidate the jumper is installed where the candidate indicated.

Override wetwell exhaust Overrides CEP-V-4A by installing inboard isolation logic. jumper between terminal 14 and 15 S/U*

on TB H28 at H13-P813.

CUE: If student checks, cue CEP-V-11 green light is lit, SGT-V-2B red light is lit, and SGT-V-3B-1 red light is lit.

CUE: Each of the valves operated below have a red position indicator light lit after the candidate operates the valve.

Open Exhaust to stack. Opens SGT-V-5B-2.

S/U*

Open inlet from Containment. Opens SGT-V-1B.

S/U*

Opens WW Exh Outbd Isol. Opens CEP-V3A.

S/U*

Opens WW Exh Inbd Isol. Opens CEP-V4A S/U*

Termination Criteria: Student informs CRS that Wetwell Venting has been initiated.

RECORD TERMINATION TIME: _________

Transfer to JPM Results Page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 5 LR000162 Rev. 6

RESULTS OF JPM:

PREPARE FOR EMERGENCY WETWELL VENTING (HIGH H2 AND O2 CONCENTRATIONS)

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

Initiates Emergency Wetwell Venting via SGT Train B in accordance with PPM 5.5.20.

Overall Evaluation Exam Code SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used Validation/Critical JPM Completion for JPM (Initial Box) Time Time 20 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 5 LR000162 Rev. 6

STUDENT JPM INFORMATION CARD Initial Conditions:

A LOCA has occurred coincident with a loss of Off Site power. Parameters now indicate that Primary Containment integrity may be challenged due to potentially flammable atmosphere in containment.

The Reactor Building is inaccessible.

Cue:

The CRS has directed you to use SGT B to emergency vent the wetwell per PPM 5.5.20 due to high H2 and O2 concentrations.

Inform the CRS when Wetwell Venting has been initiated.

The performance of this JPM will be simulated.

Control manipulations will NOT be performed.

Page 5 of 5 LR000162 Rev. 6

INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE TRANSFER SM-1 FROM TR-N TO TR-S (SIM) (FAULTED)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code LR001515 Rev. No. 0 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/01/01 REVISED BY DATE TECHNICAL REVIEW BY Pat Bagan DATE 10/24/01 INSTRUCTIONAL REVIEW BY Jim Redwine DATE 10/17/01 APPROVED BY Randy Guthrie DATE 10/25/01 Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

TRANSFER SM-1 FROM TR-N TO TR-S MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

Any IC where SM-1 is powered from N1-1 breaker.

Special Setup Instructions:

BKR-EPS038 CB-N1/1 Fail to Auto Trip JPM Instructions:

Verify Current Procedure against JPM and ensure procedure critical steps match if procedure is different revision than listed in JPM. If critical steps have changed, the JPM should be revised.

The evaluator and student shall use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: None Safety Items: None Task Number: RO-0414-N-AC Validation Time: 5 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

PPM 2.7.1A Section 5.6 Rev. 13 Location: Simulator NUREG 1123 Ref: 262001A4.04(3.6/3.6) Performance Method: Perform Page 1 of 4

TRANSFER SM-1 FROM TR-N TO TR-S JPM CHECKLIST PROCEDURE Procedure copies for evaluator and student, if procedure revision is different from VALIDATION that listed on JPM, critical tasks reverified. Evaluator copy may be used for marking step completion, and comments.

INITIAL A plant shutdown is in progress. All conditions, limitations, and prerequisites for this CONDITIONS: evolution are completed.

INITIATING CUE: The CRS has directed you to transfer SM-1 from the Normal transformer to the Startup transformer. Inform the CRS when SM-1 is being powered from the Startup transformer.

Items are Critical Steps Comments Element Standard Sat/Unsat RECORD START TIME: __________

CUE: Cue response of simulated actions based on procedure and student actions At H13-P842 (Bd. F), At H13-P842 (Bd. F), ensures the S/U ensure the white Lockout white Lockout TR-S Lockout TR-S Lockout Rly 86TS Rly 86TS light for Startup light for Startup Transformer (TR-S) is illuminated.

Transformer (TR-S) is illuminated.

Ensure the CB-S1 white Ensures the CB-S1 white S/U LOCKOUT CIRCUIT LOCKOUT CIRCUIT AVAIL light AVAIL light and green and green tripped light are tripped light are illuminated.

illuminated.

Ensure the green position Ensures the green position flag is S/U flag is being displayed in being displayed in the CB-S1 control the CB-S1 control switch switch window.

window.

Ensure the CB-N1/1 white Ensures the CB-N1/1 white S/U LOCKOUT CIRCUIT LOCKOUT CIRCUIT AVAIL light AVAIL light and red closed and red closed light are illuminated.

light are illuminated.

Place the CB-S1 Sync Places the CB-S1 Sync Selector S/U*

Selector switch in the switch in the MANUAL position. Critical step MANUAL position.

Page 2 of 4

TRANSFER SM-1 FROM TR-N TO TR-S

Items are Critical Steps Comments Element Standard Sat/Unsat Check voltage present on Checks voltage present on both S/U both incoming and running incoming and running buses (not buses (not required to be required to be matched).

matched).

NOTE: The blue sync permit light for CB-S1 is illuminated from the initiation of closure until closure actually occurs.

NOTE: CB-N1/1 should be manually tripped if it does not trip at the time of CB-S1 closure.

Place the CB-S1 control Places the CB-S1 control switch to S/U*

switch to the CLOSE the CLOSE position. Critical step position.

Ensure CB-S1 closes. Ensures CB-S1 closes.

Ensure CB-N1/1 auto trips Recognizes that breaker CB-n1/1 S/U*

at time of breaker CB-S1 does not opene. Critical step closure. Manually trip Manually trips CB-N1/1 when it CB-N1/1 if it does not auto does not auto trip.

trip.

Place the CB-N1/1 control Ensures a green flag is displayed in S/U switch to the TRIP position the CB-N1/1 control switch window.

and ensure a green flag is displayed in the CB-N1/1 control switch window.

Termination Criteria: Student informs CRS that SM-1 is being powered from TR-S.

RECORD TERMINATION TIME: _________

Transfer to Results of JPM page the following information: Procedures validated prior to use; Comments from marked up evaluators procedure copy; Unsatisfactory critical tasks; Total JPM time; Marked Up procedure and remaining JPM pages may be discarded.

Page 3 of 4

TRANSFER SM-1 FROM TR-N TO TR-S RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

SM-1 power supply has been transferred from N1-1 to TR-S per PPM 2.7.1A..

Overall Evaluation Exam Code LR001515 SAT / UNSAT (Circle One)

Verified Procedure #/Rev. Used for Validation/Critical JPM Completion JPM (Initial Box) Time Time 5 Minutes / NA COMMENTS:

Evaluator's Signature: Date:

Page 4 of 4

TRANSFER SM-1 FROM TR-N TO TR-S STUDENT JPM INFORMATION CARD Initial Conditions:

A plant shutdown is in progress. All conditions, limitations, and prerequisites for this evolution are completed.

Cue:

The CRS has directed you to transfer SM-1 from the Normal transformer to the Startup transformer.

Inform the CRS when SM-1 is being powered from the Startup transformer.

Page 5 of 4

Appendix D Scenario Outline Form ES-D-1 Facility: COLUMBIA Final Scenario No. 2 Op-Test No.: 1 Examiners: _________________________Operators: __________________________

Plant Status: The reactor has been operating at 100% power for the last 131 days except for a few minor downpowers for control rod adjustments. Control rod xx-yy is selected per step xx of the rod pull sheet. Thirty days remain until the start of the next refueling outage. Reactor water cleanup pump RWCU-P-1A was isolated and tagged out of service at 0345 this morning to repair a leak on the pump shaft. Mechanical maintenance completed the work near the end of the previous shift, the tags have been lifted, and the pump needs to be run for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months as a post maintenance test. SRV MS-RV-5B has a high tail pipe temperature alarm and engineering is working on developing a troubleshooting plan.

Turnover: Maintain reactor power at 100%. Place RWCU-P-1A in service per PPM 2.2.3 and run the pump for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The procedure was started by the previous crew and they completed steps 5.9.1 though step 5.9.3.

The 40 minute run has been completed. Completing this procedure should be done expeditiously because RWCU-P-1B also needs to have the shaft seals adjusted. Perform control rod surveillance OSP-CRD-W701, Control Rod Exercise for Fully Withdrawn Control Rods. Closely monitor SRV MS-RV-5B for increased leakage.

Scenario: This scenario includes two normal evolutions (shifting RWCU pumps and performing control rod overtravel surveillances), two component failures (RWCU pump seal failure/trip and a control rod overtravel), one instrument failure (Main Steam Line flow element fails high) and one main event. The main event is initiated with a ground fault on the Division 3 4160 volt bus supply breaker that causes a fire in the Division Page 1

Appendix D Scenario Outline Form ES-D-1 3 auxiliary transformer and a loss of the Division 3 4160 bus (SM-4).

This ultimately causes a trip of the main transformer. The auto transfer to the startup transformer fails to occur and consequently, all non-safety related AC power is lost. (Electrical power can be restored manually.)

The RCIC turbine overspeeds on startup and there is a loss of all high pressure injection systems. One SRV fails open.

Eve Malf. No. Event Type Event Description nt No.

1. Initiated by N Place RWCU-P-1A in service and turnover (BOP) secure RWCU-P-1B.

T=0

2. Initiated by N (RO) Perform rod over travel surveillance turnover OSP-CRD-W701.

T=0

3. Trigger 1 C (RO) The third rod tested fails the overtravel surveillance. The control rod is T>>15 min recoupled.

4. Trigger 2 I (SRO, Main steam line flow instrument MS-T~25 BOP) DPIS-10B fails high.

5. Trigger 2 C RWCU-P-1A trips.

(BOP)

T>>35 min

6. Trigger 3 M (All) SM-2 and SM-4 ground fault alarms and loss of SM-4 (51N and 59 relays T=45 min trip).

7. Trigger 4 M (All) Normal Aux Power TR-N1 fire alarm.

T=50 min

8. Trigger 5 M (All) Supply breaker to TR-N1 interbus transformer will not open.

T=0 min

9. Trigger 6 C Auto transfer switch is disabled.

Page 2

Appendix D Scenario Outline Form ES-D-1 T=0 min (BOP)

10. Trigger M (All) Trip of the main transformer TR-M1 on ground fault (neutral current).

T = 55 min

11. Trigger 8 C (All) RCIC turbine over speed trip on startup. (Loss of all high pressure T = 0 min injection systems.)

12. C One SRV fails open.

(BOP)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 3

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

Description:

Place RWCU-P-1A in service and shutdown RWCU-P-1B.

This event is initiated by the turnover sheet. The event endpoint occurs when the B pump is shutdown.

Time Position Applicants Actions or Behavior T=0 SRO Directs the BOP to complete placing RWCU-P-1A in service and securing the B pump per PPM 2.2.3, section 5.9, RWCU, starting with step 5.9.4.

BOP Carries out actions of PPM 2.2.3, starting with step 5.9.4:

When RWCU-P-1A has run on its Discharge Bypass valve for 40 minutes, open RWCU-V-13A and ensure normal pump flow indicated by an increase on RWCU-FI-609.

Secure RWCU-P-1B and ensure RWCU system flow is normal on RWCU-FI-609.

Close RWCU-V-13B for the previously running pump.

Place the RWCU Demineralizers in service per Section 5.14. (Local activity)

Reports to the CRS RWCU-P-1B is in service.

Page 4

Appendix D Scenario Outline Form ES-D-1 COMM ENTS:

Page 5

Appendix D Scenario Outline Form ES-D-1 Event No. 2

Description:

Perform control rod over travel surveillance for 3 control rods.

This event is initiated by the turnover sheet. The end point occurs when the third control rod fails the over travel test.

Critical Task for this event:

Time Position Applicants Actions or Behavior T=0 SRO Directs RO to perform OSP-CRD-W701, Control Rod Exercise of Fully Withdrawn Control Rods If available, obtain a control rod position printout. NA (Provided)

RO Select a control rod to be moved and initial on Attachment 9.1 of OSP-CRD-W701.

(Provided)

A second licensed operator or STA/SNE is to verify the correct control rod is selected and initial Attachment 9.1.

Insert the control rod one notch (to notch 46) as indicated on Four-Rod display.

Verify the indicated control rod position changes during control rod movement.

If the rod position is not available or is lost, withdraw the rod to its original position. Record this condition on Attachment 9.3 and exercise the rod per Step 7.6.

Page 6

Appendix D Scenario Outline Form ES-D-1 Continuously withdraw the control rod one notch (to notch 48) as indicated on the Four-Rod display.

Verify the indicated control rod position changes during control rod movement.

NOTE: A valid coupling integrity check requires the ROD OVERTRAVEL annunciator (H13-P603-A7-1.8) not received when a continuous withdrawal signal is applied to the control rod drive.

Simulator Cue: The ROD OVERTRAVEL alarm is recieved on the third rod tested.

Verify coupling integrity of the control rod.

Verify position 48 is illuminated or verify the FULL OUT indicating light is illuminated.

For control rods that were highlighted per step 7.4 re-perform steps 7.5.9 and 7.5.10 to promote the restoration of cooling. NA Initial on Attachment 9.2 for each control rod that has been exercised satisfactorily.

A second licensed Operator or STA is to verify the correct final control rod position after the settle function light has extinguished.

Initial on Attachment 9.2.

Record any difficulties while performing this exercise on Attachment 9.3. This may include double Page 7

Appendix D Scenario Outline Form ES-D-1 notches, failure to notch, or increase drive water pressure required.

Repeat Steps 7.5.2 through 7.5.14 for all rods to be exercised.

If available, obtain a control rod position printout and compare it with Step 7.5.1. Notify the CRS/SM and STA of any discrepancies.

CAUTION: If any rod is accidently inserted more than one notch, the rod should be withdrawn one notch at a time to avoid overnotching on the withdrawal.

Page 8

Appendix D Scenario Outline Form ES-D-1 Event No. 3

Description:

A control rod fails the rod over travel surveillance.

This event is initiated by the procedure addressed in Event #2. The event endpoint occurs when the control rod is recoupled and restored to the original position.

Time Position Applicants Actions or Behavior RO N o tify th e S h ift M a n a g e r a n d S h ift E n g in e e r o f th e co ntro l rod o ve r tra v e l a la rm .

T=20 SRO D irec ts t h e R O t o in s e r t t h e a ffe c te d c o n tro l ro d to p o sitio n 0 0 to a c c o m p lish re c o u p lin g .

RO In se rt s t h e c o n tr o l ro d to a tte m p t r e c o u p lin g .

Simulator Cue: The control rod is recoupled on the first attempt.

SRO D irec ts R O to w i th d ra w r o d to n o tc h 4 8 to d e te rm in e if th e ro d h a s b e e n re c o up le d .

RO R e p o rts to C R S c o n tro l ro d is re c o up le d .

COMMENTS:

Page 9

Appendix D Scenario Outline Form ES-D-1 Event No. 4

Description:

Main steam line flow instrument MS-DPIS-10B fails high.

Time Position Applicants Actions or Behavior BOP Reports MSIV Half Trip System B Alarm and that MS-DPIS-10B has failed upscale.

SRO Refers to TS 3.3.6.1.A and is required to place channel B in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

COMMENTS:

Page 10

Appendix D Scenario Outline Form ES-D-1 Event No. 5

Description:

RWCU-P-1A trips.

The event endpoint occurs when RWCU-P-1B is in service.

Time Position Applicants Actions or Behavior BOP Reports that RWCU-P-1A has tripped.

SRO Directs BOP to perform a quick restart of pump 1B BOP 1. Open RWCU-V-1 and RWCU-V-4.

2. If in Mode 4 or 5, place LD-RMS-S6A and LD-RMS-S6B in the TEST position at H13-P632 and H13-P642.

NA

3. Ensure RWCU-V-104 is closed.

NOTE: Perform Steps 5.17.4 and 5.17.5 simultaneously.

4. Place the control switch for RWCU-P-1B in START and hold in this position.

Page 11

Appendix D Scenario Outline Form ES-D-1

5. Open RWCU-V-44, Demineralizer Bypass until the RWCU Pump Flow Low alarm clears (approximately 70 gpm).

6. Let the RWCU-P-1B control switch spring return to the AUTO position.

7. Contact the Radwaste Control Room to place filter demineralizers in service, per Section 5.14.

8. If required, place LD-RMS-S6A and LD-RMS-S6B in the NORMAL position, after System Flow has stabilized and RWCU Differential Flow Alarm is cleared. NA COMMENTS:

Page 12

Appendix D Scenario Outline Form ES-D-1 Event No. 6 Main Event

Description:

SM-2 and SM-4 ground fault alarms and loss of SM-4 (51N and 59 relays trip). Breaker N1-2 fails to open.

This event is initiated with TRIGGER 6. The event endpoint occurs when the main event scenario is terminated.

Time Position Applicants Actions or Behavior BOP Reports HPCS SYSTEM UNDERVOLTAGE/HPCS SYSTEM GROUND Alarms and loss of SM-4 SRO Refers to procedure ABN-ELEC-SM2/SM4 time permitting.

Directs EO to check status of SM-2 and SM-4 trip relays COMMENTS: This event is continued in Event No. 11.

Page 13

Appendix D Scenario Outline Form ES-D-1 Events No. 7/8: Normal Aux Power Transformer TR-N1 fire alarm and normal supply breaker to SM-2, N1-2, fails to trip open.

Description:

This trigger is initiated 2 minutes after event 6 is triggered. The event endpoint occurs when the scenario is terminated.

Critical Task for this event:

Time Position Applicants Actions or Behavior COMMENTS: See Event No. 11 for description.

Page 14

Appendix D Scenario Outline Form ES-D-1 Event No. 9/10: Trip of the main transformer, TR-M1, with a failure of the electrical auto transfer.

Description:

On the loss of the main transformer TR-N1, there is a failure to auto transfer to off-site power. Off-site power can be manually restored by closing the appropriate circuit breakers.

The event endpoint occurs when the main event scenario is terminated.

Time Position Behavior BOP *Restores electrical power from off-site sources.

COMMENTS: This event is continued in Event No. 11.

Page 15

Appendix D Scenario Outline Form ES-D-1 Event No. 11: RCIC turbine over speed trip on startup. (Loss of all high pressure injection systems.) One SRV fails open after initial opening.

Description:

Note: The applicants actions are described assuming the MSIVs are closed and power has been restored from off-site power.

The event endpoint occurs when RPV level and pressure are stable.

Time Position Applicants Actions or Behavior SRO Enters EOP 5.1.1 and directs:

BOP Opens SRVs until RPV pressure drops to 945 psig. (P-3)

BOP *Stabilize RPV pressure below 1060 psig with SRVs. (P-5)

Reports one SRV will not close.

RO Takes SCRAM immediate actions BOP/RO Verifies all isolations, ECCS initiations, and EDGs have started (L-1)

SRO *Directs the MSIVs re-opened. (P-5)

BOP *Takes necessary actions to reopen MSIVs: (P-5)

Starts a circ water pump Starts a mechanical vacuum pump (hogger)

Opens MSIV bypass valves After pressure has been equalized, opens MSIVs RO *Places RPV pressure control on the main turbine bypass valves. (P-5)

BOP Restores and maximizes CRDH flow (L-3/8)

RO/BOP *Restores RPV level with reactor feedpump and/or condensate booster pumps (depending on RPV pressure) (L-3/6/8)

COMMENTS:

Page 16

Appendix D Scenario Outline Form ES-D-1 SCENARIO ENDPOINT: The endpoint is when RPV pressure and level are stable and/or being recovered.

Page 17

Appendix D Scenario Outline Form ES-D-1 SRO TURNOVER INFORMATION The plant has been at 100% power for the last 131 days except for a few minor downpowers.

Reactor water cleanup pump RWCU-P-1A was isolated and tagged out of service at 0345 this morning to repair a leak on the pump shaft. Mechanical maintenance completed the work near the end of the previous shift, the tags have been lifted, and the pump needs to be run for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months as a post maintenance test. Place RWCU-P-1A in service per PPM 2.2.3, RWCU, and run the pump for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . PPM 2.2.3 was started by the previous crew and they completed steps 5.9.1 though step 5.9.3.

The procedurally required 40 minute run for pump 1A has been completed. Completing this procedure should be done expeditiously because RWCU-P-1B also needs to have the shaft seals adjusted.

Perform control rod surveillance OSP-CRD-W701, Control Rod Exercise for Fully Withdrawn Control Rods, for rods xx-yy, xx-yy, and xx-yy.

SRV MS-RV-5B has a high tail pipe temperature alarm and engineering is working on developing a troubleshooting plan. Closely monitor SRV MS-RV-5B for increased leakage.

Page 18

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 Facility: Columbia Scenario Set No: 1 Scenario No: 5 Examiners: _______________ Operators: _______________

Initial conditions: Plant is at approximately 20% with the main turbine generator synchronized and a startup in progress. Reactor feedwater control is in 3 element on feedpump speed control.

Turnover: RCC-P-1A is OOS for motor replacement. BPA is selling power to CA. and power should be increased as soon as possible following turnover. The reactivity brief has been given and the power increase is to begin immediately.

Event Timeline Event Event Description No. Type*

1. T=0 N Power increase with rods to 24%.

SRO RO

2. T=5 I LPRM 08-41A fails upscale.

ALL TRG-1

3. T=15 C Failure of RB exhaust fan requires entry into PPM 5.3.1.

SRO BOP TRG-2

4. I Failure of RFW-LIC-600 to manual.

SRO RO OVERRIDE TO MANUAL DURING POWER INCREASE.

5. T=30 M Loss of SL-81 results in a loss of RCC and subsequent trip of RWCU, RRC, and a manual reactor scram.

ALL TRG 3

6. M Failure of enough rods to insert such that reactor power is GT 5%.

ALL Active at the beginning of the scenario.

7. C SLC fails - neither squib valve fires.

SRO RO Active at the beginning of the scenario.

8. Termination Cue: Power is being controlled with level less than LL>

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 Event No. 1

==

Description:==

Power reduction in preparation to take the unit off line.

This event is initiated by the Control Room Supervisor.

Time Position Applicants Actions or Behavior T=0 when SRO Directs RO to increase reactor power to 24% per PPM 3.1.2 step 5.8.8.

crew assumes shift RO Withdraws control rods to continue the startup per PPM 3.1.2.

Closely monitors reactor power during rod withdrawal.

Verifies prior to each rod movement:

correct rod selected correct start/stop position BOP Monitors plant conditions COMMENTS: Rod pull starts at RWM group (TBD).

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 Event No. 2

==

Description:==

LPRM 08-41A fails upscale.

The event is initiated by TRIGGER 1 during the control rod withdrawal approximately 5 minutes following Time Position Applicants Actions or Behavior T=5 RO Acknowledges the LPRM UPSCALE annunciator and announces to the SRO.

Refers to ARP 4.603.A8 and identifies the upscale LPRM as08-41A.

SRO Directs BOP to the back panel to read the output of the affected LPRM.

BOP Using the function and selector switches at P608 and determine that 08-41A is greater than 100 watts/cm2.

Inform the SRO of the upscale reading.

SRO Direct that the affected LPRM be bypassed per PPM 9.3.4 Failed or Drifting LPRMs.

BOP Using PPM 9.3.4:

Notify the SRO to check Tech Spec Table 3.3.1.1-1 to ensure APRM operability.

Gets permission from the SRO prior to bypassing the APRM as required by PPM 9.3.4.

Bypasses both APRM A and LPRM 08-41A at P608.

Notify the SRO that the LPRM is bypassed.

SRO Ensure APRM A indicates within 1/2% of CTP (CGS Admin Requirement per PPM 9.3.4) prior to directing the BOP to un-bypass the APRM.

BOP Return APRM A to service.

COMMENTS:

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 Event No. 3

==

Description:==

Loss of REA-FN-1B resulting in a high reactor building pressure and entry into EOP Secondary Containment Control, 5.3.1.

This event is MANUALLY initiated with TRIGGER 2 approximately 15 minutes following the start of the scenario..

Critical Task for this event: Directs or takes action to maintain Secondary Containment Pressure negative with regards to outside pressure Time Position Applicants Actions or Behavior T=15 BOP Reports the receipt of the Secondary Containment P High alarm and notes that it is a possible EOP entry.

Goes to the back panel (P812) to investigate the cause of the abnormal condition in secondary containment.

Reports that REA-FN-1B has tripped and that Reactor Bldg. pressure is positive on REA-DPR-1A(B).

SRO Enters EOP 5.3.1, Secondary Containment Control, based on Reactor Bldg. pressure at or above 0 H2O BOP Refers to the annunciator response procedures (PPM 4.812.R2, 9-1)

Attempts to start REA-FN-1A, Rx Bldg. Exhaust Fan (fan will not start)

If neither reactor bldg. exhaust fan can be started:

Immdiately secures Rx Bldg. Inlet Fan (ROA-FN-1B)

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 Closes ROA-V-1 & 2, REA-V-1 & 2 (Inlet and Outlet dampers)

Starts A train of SGT to maintain Rx Bldg. Pressure negative Refers to PPM 2.3.5, SGT System, to verify steps taken to start SGT.

Notifies Chemistry to monitor Rx Bldg Refers to ODCM 6.1.2.1 and LCS 1.3.3.1 (the examinee should inform the SRO that this procedure makes reference to these, it is not expected for the RO/BOP to enter these)

Refers to ABN-HVAC, HVAC Trouble Procedure, (all applicable actions have already been carried out in the Annunciator Response Procedure)

Ensures Rx Bldg. pressure is maintained negative (monitors back panel or Secondary Containment P High annunciator on P602)

May send an equipment operator to investigate the loss of fan 1B and check the start of fan 1A Cue: If asked to investigate the loss of REA-FN-1B, report that there is no apparent cause identified in your visual inspection. If requested to do pre or post fan start checks on REA-FN-1A or SGT, report that the checks are satisfactory RO Monitors plant Continues with plant shutdown (see event 1)

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 SRO May exit EOP 5.3.1, Secondary Containment Control when Rx Bldg.

Pressure is restored and with shift manager permission Cue: When asked, as the Shift Manager, for permission to exit the EOP 5.3.1, provide permission to exit since the entry condition has cleared and no emergency exists.

COMMENTS:

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 Event No. 4

==

Description:==

Failure of RFW-LIC-600 to manual.

The event is initiated shortly after the power increase is started.

Note: Override RFW-LIC-600 to manual.

Time Position Applicants Actions or Behavior T=5 RO Notes that reactor level is no longer tracking during the power increase and notifies the SRO.

Notes that RFW-LIC-600 has gone to manual and tells the SRO.

Operates RFW-LIC-600 in manual to maintain reactor level.

May refer to ABN-LEVEL and/or PPM 4.603.A8 drop 3-7 depending on conditions when the failure is noticed.

SRO May refer to ABN-LEVEL and/or PPM 4.603.A8 drop 3-7 depending on conditions when the failure is noticed.

Should direct the RO to attempt to place RFW-LIC-600 back in AUTO.

(Authority to operate equipment given in PPM 1.3.1)

RO Places RFW-LIC-600 in auto.

COMMENTS:

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 Event No. 5

==

Description:==

Overcurrent on SL-81 causes BKR 8-81 to trip open.

This event is MANUALLY initiated by TRIGGER 3 ,at approximately 30 minutes following the start of the scenario, and after the crew has exited EOP 5.3.1, Secondary Containment Control, or at the direction of the lead examiner.

Time Position Applicants Actions or Behavior T=30 BOP Announces loss of SL-81 due to the trip of BKR 8-81.

Refers to PPM 4.800.C5. drop 1-5:

Announce monitoring of drywell temperature and pressure.

Refer to ABN-RCC.

Note: The BOP operator must recognize that there is a complete loss of RCC due to the loss of power to RCC-P-1B and 1C with 1A out of service.

SRO Refers to ABN-RCC:

Directs the RO to scram the reactor.

Directs the BOP operator to stop both RRC Pumps.

Directs the BOP operator to stop RWCU-P-1A/B, close RWCU-V-4, and throttle open RWCU-V-104.

Directs the BOP operator to place all RCC pumps in PTL.

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 RO Scrams the reactor as directed and gives the scram report of Power, Pressure, and Level, noting an ATWS (hydraulic) condition.

Takes the immediate scram actions from PPM 3.3.1:

Place the Mode Switch in SHUTDOWN.

Monitor reactor power, pressure and level.

Verify all control rods have inserted and since they did not insert, depress the manual scram pushbuttons and initiate ARI.

Insert SRMs and IRMs.

Comments:

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 Event No. 6

==

Description:==

Hydraulic ATWS This event is setup at the beginning of the scenario and occurs automatically.

Critical Task for this event:

1. Enters PPM 5.1.2 and maintains power with level controlled less than LL.

Time Position Applicants Actions or Behavior RO Announce EOP entry into PPM 5.1.1 on reactor level or the ATWS.

Takes immediate scram actions:

MS to SHUTDOWN Monitor Power, Pressure, and Level Verify all CRs have not fully inserted.

Depress the manual scram pushbuttons Initiate ARI.

Insert SRMs and IRMs.

SRO Enters PPM 5.1.1 and directs/verifies that the Mode Switch has been placed in SHUTDOWN and enters the Level, Pressure and Power leg concurrently and exits PPM 5.1.1 via the Power leg to PPM 5.1.2 RPV Control ATWS.

Directs BOP to:

Verify all appropriate isolations and initiations have occurred.

Verify pressure is being maintained by the main turbine/bypass valves and if not, maintain pressure 800# to 1000# with SRVs.

Directs RO to:

Ensure both RRC Pumps are off.

Initiate both SLC pumps before WW temp reaches 110°F.

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 RO Takes actions as directed:

Stop both RRC Pumps if not already off.

Initiate both SLC pumps before WW temp reaches 110°F.

Announce that the SLC Squib valves did not fire and SLC is NOT injecting into the core.

SRO Direct the BOP operator to bypass the MSIV isolation interlocks per PPM 5.5.6.

Call OPS 3 on the radio and align firewater to the air compressors.

Note: Agree as Ops 3 to align firewater to the air compressors. 2 minutes after being called as OPS 3 activate triggers 23 and 24 to align FW to the air compressors.

SRO Direct the RO to:

Stop and prevent all injection into the RPV except by Boron injection systems, RCIC, and CRD.

Lower level to a band less than -65 inches but greater than -183 inches. Record the upper limit as LL.

Maintain level as directed from LL to -183 inches with outside the shroud injection systems listed in Table 5.

BOP Takes actions as directed:

Using PPM 5.5.6, bypass the MSIV isolation interlocks.

SRO Directs BOP operator to Perform PPM 5.5.10 and appropriate steps of 5.5.11 for a hydraulic ATWS, Tabs B, F, and G.

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 BOP Takes actions as directed:

Performs PPM 5.5.10 Override ARI Logic.

Performs Tabs B, F, and G of PPM 5.5.11 to:

Reset, Scram, Reset Drive control rods Vent the overpiston area COMMENTS:

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 Event No. 7

==

Description:==

Both SLC Squib valves fail to fire and will not operate.

Note: This failure is discussed under Event #6.

Time Position Applicants Actions or Behavior COMMENTS:

Termination cue for this scenario: Level has been reduced by stopping and preventing injection too less than LL and power is controlled by the evolution.

Critical Task for this event: Reactor power is being controlled at less than 5% with reactor level below LL.

When this task is completed, the scenario can be terminated at the discretion of the Lead Examiner.

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 SRO TURNOVER INFORMATION Initial conditions: Plant is at approximately 20% with the main turbine generator synchronized and a startup in progress. Reactor feedwater control is in 3 element on feedpump speed control.

Turnover: RCC-P-1A is OOS for motor replacement. BPA is selling power to CA.

and power should be increased as soon as possible following turnover.

The reactivity brief has been given and the power increase is to begin immediately.

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 SPECIAL SETUP

1. Ensure RCC-P-1A is racked out and tagged out.

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 Facility: Columbia Scenario Set No: 1 Scenario No: 10 Examiners: _______________ Operators: _______________

Initial conditions: The crew assumes the shift with the reactor at 90% power.

Turnover Information: HPCS-P-1 is OOS for motor bearing replacement. It is expected to be returned to service in two days. Tech. Spec. 3.5.1, condition B, was entered four hours ago. A reactivity brief for the power increase has been held and power is to be increased to 100% immediately following shift turnover.

Event Timeline Event Event Description No. Type*

1. T=0 N Increase power with flow.

SRO RO

2. T=5 I APRM-A fails upscale Tech Spec SRO RO TRG 1

3. T=7 C DEH-P-1A shaft break with a fail to auto start of DEH-P-1B.

SRO BOP TRG 2

4. T=10 C ASD Channel A2 alarm and fault ALL TRG 3

5. T=20 C ASD UPS trouble alarm ALL TRG 4

6. T=20 C Trip of E-PP-ASD1/4 and ASD CH A1 and B1 fault which results in a ALL manual scram by the crew.

TRG 5

7. T=30 M OBE and RHR-B Suction Break with a trip of both RFW pumps.

ALL TRG 6

8. T=31 C RCIC trips on initiation and cannot be re-started ALL Automatic upon RCIC initiation.

9. Termination cue: The scenario can be terminated when the ED has been performed and reactor level is being controlled in the band from

+13 inches to +54 inches.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 Event No. 1

==

Description:==

increase reactor power with flow to 100% power.

Time Position Applicants Actions or Behavior SRO T=0 Directs the RO to increase reactor power to 100% power with RRC flow at the rate of 10 mwe/minute.

RO Increases reactor power with RRC flow as directed.

BOP Monitors plant equipment.

COMMENTS:

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 Event No. 2

==

Description:==

APRM-C fails upscale.

This event is triggered with TRIGGER 1 5 minutes following the start of the scenario.

Time Position Applicants Actions or Behavior T=5 RO Reports APRM-A upscale and a 1/2 scram on RPS-A.

Refers to ARP and recommends; Consider bypassing APRM-A.

Refer to TS 3.3.1.1. LCS 1.3.2.1, and 1.3.3.1 Verify no rods have scrammed.

Recommend resetting the 1/2 scram Verify Scram Group Lights are illuminated.

Verify Backup Scram Lights have extinguished.

SRO Acknowledges the report.

Refers to Tech Specs and LCS and determines there are no regulatory requirements with this failure.

Directs RO to bypass APRM-A.

Directs RO to reset the 1/2 scram.

Directs BOP to make announcement to stop all testing and maintenance with a potential for generating a trip in the unaffected channel.

Calls PSRO/WC BOP Makes announcement to stop all testing and maintenance with a potential for generating a trip in the unaffected channel.

RO Bypasses the APRM.

Resets the 1/2 scram.

COMMENTS:

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 Event No. 3

==

Description:==

DEH-P-1A shaft breaks with a failure of DEH-P-1B to auto start.

This event is triggered with TRIGGER 2 approximately 7 minutes following the start of the scenario.

Time Position Applicants Actions or Behavior BOP Announce the loss of pressure to DEH Verify the start of the backup pump, and when it does not start, manually start DEH-P-1B.

Verify pressure returns to normal.

Note: When the operator places the control switch for DEH-P-1B in start, delete the override for the control switch for DEH-P-1A.

SRO Acknowledges report.

Directs BOP to take actions as directed in the ARP.

Directs OPS 3 to check system for indications of failure.

Notifies PSRO/WC.

Cue: Call back as OPS 3 with the information that the shaft on DEH-P-1A is sheared.

RO Monitors reactor; Power Pressure Level BOP Verifies system operation per PPM 2.5.1.

Sends OPS 3 to verify lineup in ARP.

Refers to ABN-DEH-LEAK.

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 COMMENTS:

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 Event No. 4

==

Description:==

ASD Channel A2 alarm and fault.

This event is triggered with TRIGGER 3 10 minutes following the start of the scenario.

Time Position Applicants Actions or Behavior RO Reports ASD 1A/2 alarm and Fault alarms.

Verifies trip of channel ASD1 A/2.

Ensures RRC-P-1A has runback to 51 Hz.

Reports power decrease due to runback.

Checks ASD video Display Unit for source of alarm.

Sends OPS4 to investigate @ ASD BLD SRO Directs actions per ARPs.

Cue: Using the telephone, call x2242 and report as OPS4 that there is a GTO freeze alarm on Channel A2.

SRO Directs actions per ARP for high delta flow.

Directs RO to match RRC loop flows.

Enters Tech. Spec. 3.4.1.

Tech. Spec. 3.4.1 flow mismatch is applicable until flows are matched.

Notifies PSRO/WC RO Reduces RRC-P-1B speed to 51 Hz.

Performs PPM OSP-RRC-D701, Jet Pump Operability and RRC loop Flow mismatch.

COMMENTS:

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 Event No. 5

==

Description:==

ASD UPS trouble alarm.

This event is imitated with TRIGGER 4 20 minutes following the start of the scenario and should be initiated when RRC loop flows are matched.

Time Position Applicants Actions or Behavior RO Reports ASD UPS Trouble Alarm and refers to ARP.

SRO Directs actions per ARP for ASD UPS Trouble.

Refers to ABN-ASD-INV RO Sends OPS4 to investigate.

Notifies PSRO/WC.

Cue: Thirty seconds after Trigger 4 is activated, call x2242 and report as OPS4 that there is arching and sparking coming from E-PP-ASD 1 / 4.

COMMENTS:

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 Event No. 6

==

Description:==

Trip of E-PP-ASD1/4 and ASD CH A1 and B1 fault.

This event is activated by TRIGGER 5 and is activated 45 seconds after the preceding report from OPS 4.

Time Position Applicants Actions or Behavior Cue: 45 seconds after the report from OPS4 activate Trigger 3, trip of E-PP-ASD1/4 and ASD CH A1 and B1 fault.

RO Reports both ASD Channels A1 and B1 are in alarm.

Reports that both RRC pumps have tripped.

Reports reactor scram.

SRO Directs RO to perform PPM 3.3.1Reactor Scram.

RO Takes immediate scram actions:

MS to SHUTDOWN Monitor Power, Pressure, and Level Verify all CRs have not fully inserted.

Insert SRMs and IRMs.

Reports EOP entry condition on RPV Level into PPM 5.1.1 and loss of feedwater due to reactor high level.

SRO Enters PPM 5.1.1 and directs:

RO to restore and maintain reactor level to the band of +13 inches to +54 inches and continue in PPM 5.3.1 with RCIC or reset 1 feedpump and restart.

BOP to verify all isolations and initiations and to monitor pressure on the turbine BPVs less than 1060 psig

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 RO Reports the trip of RCIC.

Resets feedpump and returns level to the band directed and performs actions of PPM 3.3.1.

BOP Reports initiations and isolations sat and monitors pressure.

COMMENTS:

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 Event No. 7 and 8.

==

Description:==

OBE and RHR-B Suction Break This event is initiated by TRIGGER 6 approximately 30 minutes following the start of the scenario.

Time Position Applicants Actions or Behavior Cue: As OPS1, call the control room on the radio and report that you felt severe shaking/

movement in the turbine building.

BOP Reports OBE annunciator and goes to the back to Bd. L.

Reports indications from Bd. L.

SRO Directs actions for earthquake.

Directs plant tours to determine damage.

RO Reports Suppression Pool level lowering.

Reports the trip of both feed pumps.

Reports RHR B Room level Hi EOP entry.

SRO Enters PPM 5.2.1 on low SP level and directs actions per ABN-FLOODING.

Enters PPM 5.3.1 on RHR B room level Hi.

Directs OPS2 to investigate water level in RHR B room.

Determines that RHR B is not operational due to flooding.

May direct the RO to close RHR-V-4B in an attempt to isolate the leak.

Directs pulling of RHR-P-2B control power fuses.

RO If directed, closes RHR-V-4B.

Reports continued lowering trend on Suppression Pool level.

SRO Determines that Suppression Pool level will not be able to be maintained above 192.

Determines Emergency Depressurization is required.

Enters PPM 5.1.3 and directs 7 ADS SRVs open.

Re-enters PPM 5.5.1 concurrently with 5.1.3.

Cue: 2 minutes after being called to reset RCIC, report that RCIC will not reset.

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 RO Opens 7 ADS SRVs to depressurize the reactor.

SRO Directs injection with systems to return RPV level to +13 to +54.

RO Returns RPV level to band as directed.

Comments:

This scenario will be terminated when the reactor has been emergency depressurized and RPV level is stable/increasing.

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 SRO TURNOVER INFORMATION Initial conditions: The crew assumes the shift with the reactor at 90% power.

Turnover Information: HPCS-P-1 is OOS for motor bearing replacement. It is expected to be returned to service in two days. Tech. Spec. 3.5.1, condition B, was entered four hours ago. A reactivity brief for the power increase has been held and power is to be increased to 100% immediately following shift turnover.

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 SETUP INFORMATION

1. Ensure HPCS-P-1 is racked out and tagged out.

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