ML092160347

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2009 Kewaunee Administered Operating Test
ML092160347
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 01/14/2009
From: Johnson S
Dominion Energy Kewaunee
To:
NRC/RGN-III
References
Download: ML092160347 (352)


Text

KEWAUNEE POWER STATION ADMINISTERED OPERATING TEST APRIL 13-22, 2009 INCLUDES ALL ADMINISTRATIVE JPMs, ALL CONTROL ROOM JPMs, ALL IN-PLANT JPMs ALL ADMINISTERED SCENARIOS

JOB PERFORMANCE MEASURE (JPM)

SITE: KPS JPM TITLE: Perform NIS High Flux at Shutdown Alarm Test from Refueling Daily Checklist JPM NUMBER: RO-053-JP04A REV. A RELATED PRA None INFORMATION:

TASK NUMBER(S) / 0530040101 / Perform the Refueling Daily Checklist TASK TITLE(S):

K/A NUMBERS: 2.1.36 RO / SRO Imp 3.0 / 4.1 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 10 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: RO, SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /s 1/14/09 Instructor Date Validated by: Stephen Johnson /s 01/22/2009 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /s 02/10/09 Training Supervisor Date Retention: Life of plant insurance policy + 10 years Retain in: Training Program File Form NTP-6331 Rev. A Date: JAN 19 2006 Page 1 of 8

RO-053-JP04A, Perform NIS High Flux at Shutdown Alarm Test from Refueling Daily Checklist, Rev. A INITIAL CONDITIONS:

  • You are the Reactor Operator.
  • The plant is in REFUELING Mode.
  • The Daily Surveillances using N-FH-53D, Refueling Daily Checklist, is in progress.
  • N-FH-53D is complete up through, and including step 2.9.4.
  • An AO is stationed in containment to assist in completing the surveillance.

THE STEPS IN THIS JPM SHOULD BE: PERFORMED THIS TASK IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

Perform the remaining steps of N-FH-53D, section 2.9.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Retention: Life of plant insurance policy + 10 years Retain in: Training Program File Form NTP-6331 Rev. A Date: JAN 19 2006 Page 2 of 8

RO-053-JP04A, Perform NIS High Flux at Shutdown Alarm Test from Refueling Daily Checklist, Rev. A Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y/Yes below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 N-FH-53-CLD, step 5.2.9.5.a:

Critical: No ESTABLISH communications with an individual in Containment.

Standard:

Contacts AO in Containment using phone, or gaitronics.

Evaluator Note:

Each Step of this procedure has a SECOND OPERATOR signoff. Inform the performer that for each step the SECOND OPERATOR will provide confirmation based on the actions taken by the performer. If necessary provide a CUE to the performer after each step performance that the SECOND OPERATOR has signed the step.

The FIRST OPER is normally in phone (PCS) contact with the person in the Containment.

Evaluator Cue: Acknowledge contact and report standing by on 626 elevation inside Containment.

SECOND OPERATOR verifies your action and initials step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Retention: Life of plant insurance policy + 10 years Retain in: Training Program File Form NTP-6331 Rev. A Date: JAN 19 2006 Page 3 of 8

RO-053-JP04A, Perform NIS High Flux at Shutdown Alarm Test from Refueling Daily Checklist, Rev. A Performance Step: 2 N-FH-53-CLD, step 5.2.9.5.b:

Critical: Yes PERFORM plant announcement for start of High Flux at Shutdown Alarm Test.

Standard: Make announcement for starting High Flux at Shutdown Alarm Test using the gaitronics.

Evaluator Cue: SECOND OPERATOR verifies your action and initials step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 N-FH-53-CLD, step 5.2.9.5.c.1: At N-31 or N-32, PERFORM the following:

Critical: Yes POSITION Level Trip switch to BYPASS.

Standard:

On N-31 Source Range NIS drawer, Level Trip switch placed to BYPASS position.

Evaluator Note:

When the switch is taken to BYPASS the following will occur:

  • On N-31 drawer, LEVEL TRIP BYPASS bistable light comes ON.
  • Annunciator 47033-L, NI SYSTEM SR/IR TRIP BYPASSED, (SER1675) alarms.
  • Status Light 44906, N31 SR TRIP BYPASSED, comes ON.

Evaluator Cue: (Prior to operator taking action) As Unit Supervisor direct that N-31 should be the channel used for the test.

SECOND OPERATOR verifies your action and initials step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Retention: Life of plant insurance policy + 10 years Retain in: Training Program File Form NTP-6331 Rev. A Date: JAN 19 2006 Page 4 of 8

RO-053-JP04A, Perform NIS High Flux at Shutdown Alarm Test from Refueling Daily Checklist, Rev. A Performance Step: 4 N-FH-53-CLD, step 5.2.9.5.c.2: At N-31 or N-32, PERFORM the following:

Critical: No ROTATE Level Adjust potentiometer fully counter-clockwise.

Standard: Verify/rotate Level Adjust potentiometer for N-31 to the fully counter-clockwise position.

Evaluator Cue: SECOND OPERATOR verifies your action and initials step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 N-FH-53-CLD, step 5.2.9.5.c.3: At N-31 or N-32, PERFORM the following:

Critical: Yes POSITION Operation Selector switch to LEVEL ADJUST.

Standard: N-31 Operation Selector switch taken to LEVEL ADJUST position.

Evaluator Note:

When the switch is taken to LEVEL ADJUST the following will occur:

  • On N-31 drawer, CHANNEL ON TEST bistable light comes ON.
  • Annunciator 47033-M, NI SYSTEM CHANNEL IN TEST, (SER1676) alarms.
  • The N-31 indication drops to the bottom of scale.

Evaluator Cue: SECOND OPERATOR verifies your action and initials step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Retention: Life of plant insurance policy + 10 years Retain in: Training Program File Form NTP-6331 Rev. A Date: JAN 19 2006 Page 5 of 8

RO-053-JP04A, Perform NIS High Flux at Shutdown Alarm Test from Refueling Daily Checklist, Rev. A Performance Step: 6 N-FH-53-CLD, step 5.2.9.5.c.3: At N-31 or N-32, PERFORM the following:

Critical: Yes ROTATE Level Adjust potentiometer clockwise until High Flux at Shutdown Alarm actuates.

Standard: Level Adjust potentiometer for N-31 is rotated clockwise until High Flux at Shutdown Alarm is actuated as indicated by:

  • HIGH FLUX AT SHUTDOWN bistable on N31 drawer comes ON.
  • Annunciator 47032-O, SR FLUX AT SHUTDOWN HIGH, (SER1669) alarms.

Evaluator Note:

Normal reading for N-31 in this condition is 14 cps.

The HIGH FLUX AT SHUTDOWN actuates at approximately 35 cps.

Evaluator Cue:

SECOND OPERATOR verifies your action and initials step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 N-FH-53-CLD, step 5.2.9.5.d:

Critical: No CHECK High Flux at Shutdown Alarm in Containment ACTUATED.

Standard:

Contact AO in Containment and check that High Flux at Shutdown Alarm in Containment is actuated.

Evaluator Cue:

On phone, You hear alarm in background.

As AO, Acknowledge contact and report Containment alarm is actuated.

SECOND OPERATOR verifies your action and initials step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Retention: Life of plant insurance policy + 10 years Retain in: Training Program File Form NTP-6331 Rev. A Date: JAN 19 2006 Page 6 of 8

RO-053-JP04A, Perform NIS High Flux at Shutdown Alarm Test from Refueling Daily Checklist, Rev. A Performance Step: 8 N-FH-53-CLD, step 5.2.9.5.e.1: WHEN High Flux at Shutdown Alarm test Critical: Yes complete, THEN PERFORM the following:

ROTATE Level Adjust potentiometer fully counterclockwise.

Standard: Rotate Level Adjust potentiometer for N-31 to the fully counterclockwise position.

Evaluator Note: The HIGH FLUX AT SHUTDOWN condition clears when the reset value is reached during this operation and the following will clear:

  • HIGH FLUX AT SHUTDOWN bistable on N31 drawer.
  • Annunciator 47032-O, SR FLUX AT SHUTDOWN HIGH, (SER1669).

Evaluator Cue: On phone, You hear background noise stop.

If required, AO reports Containment alarm clears.

SECOND OPERATOR verifies your action and initials step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 9 N-FH-53-CLD, step 5.2.9.5.e.2: WHEN High Flux at Shutdown Alarm test Critical: Yes complete, THEN PERFORM the following:

POSITION Operation Selector switch to Normal.

Standard: N-31 Operation Selector switch taken from LEVEL ADJUST to NORMAL position.

Evaluator Note:

When the switch is taken to Normal the following will occur:

  • On N-31 drawer, CHANNEL ON TEST bistable light will clear.
  • Annunciator 47033-M, NI SYSTEM CHANNEL IN TEST, (SER1676) will clear.
  • N31 indication will return to normal position for neutron level.

Evaluator Cue: SECOND OPERATOR verifies your action and initials step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Retention: Life of plant insurance policy + 10 years Retain in: Training Program File Form NTP-6331 Rev. A Date: JAN 19 2006 Page 7 of 8

RO-053-JP04A, Perform NIS High Flux at Shutdown Alarm Test from Refueling Daily Checklist, Rev. A Performance Step: 10 N-FH-53-CLD, step 5.2.9.5.e.3: WHEN High Flux at Shutdown Alarm test Critical: Yes complete, THEN PERFORM the following:

POSITION Level Trip switch to NORMAL.

Standard:

On N-31 Source Range NIS drawer, Level Trip switch placed to NORMAL position.

Evaluator Note:

When the switch is taken to NORMAL the following will occur:

  • On N-31 drawer, LEVEL TRIP BYPASS bistable light clears.
  • Annunciator 47033-L, NI SYSTEM SR/IR TRIP BYPASSED, (SER1675) clears.
  • Status Light 44906, N31 SR TRIP BYPASSED, clears.

Evaluator Cue:

SECOND OPERATOR verifies your action and initials step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 11 N-FH-53-CLD, step 5.2.9.5.f:

Critical: No PERFORM plant announcement for completion of High Flux at Shutdown Alarm Test.

Standard: Make announcement for completion High Flux at Shutdown Alarm Test using the gaitronics.

Evaluator Cue: SECOND OPERATOR verifies your action and initials step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When the operator has completed announcement of end of the High Flux at Shutdown Alarm Test, This JPM is complete.

Stop Time:

Retention: Life of plant insurance policy + 10 years Retain in: Training Program File Form NTP-6331 Rev. A Date: JAN 19 2006 Page 8 of 8

JOB PERFORMANCE MEASURE (JPM)

SITE: KPS JPM TITLE: Review completed N-FH-53 CLD, Daily Refueling Checklist JPM NUMBER: SO-119-JP04A REV. A RELATED PRA None INFORMATION:

TASK NUMBER(S) / 1190040302 / Maintain the Shift Logs TASK TITLE(S):

K/A NUMBERS: 2.1.36 RO / SRO Imp 3.0 / 4.1 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: Other: X Classroom Lab:

Time for Completion: 10 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /S 1/29/09 Instructor Date Validated by: Andy Fahrenkrug /S 2/10/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /S 2/10/09 Training Supervisor Date Page 1 of 7

SO-119-JP04A, Review completed N-FH-53 CLD, Daily Refueling Checklist, Rev. A INITIAL CONDITIONS:

  • You are the Shift Manager.
  • The plant is in REFUELING Mode.
  • Fuel is in the reactor
  • The Daily Surveillances using N-FH-53D, Refueling Daily Checklist, has been completed one hour following DAY SHIFT turnover.

THE STEPS IN THIS JPM SHOULD BE: PERFORMED THIS TASK IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

Perform review of the completed of N-FH-53D, Refueling Daily Checklist.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Page 2 of 7

SO-119-JP04A, Review completed N-FH-53 CLD, Daily Refueling Checklist, Rev. A JPM PERFORMANCE INFORMATION Required Materials: N-FH-53-CLD completed with FIRST & SECOND OPERATOR signatures. Step 2.6.2 will have a value of 4.2 GPM; and, Step 2.18.2 will be missing the SECOND OPER initials.

KPS Technical Requirements Manual (COLR) available ORT-MISC-003 ATTACHMENT A Table 4 (page 4) - 2 copies One completed for previous shifts showing 38.4 min run time for Day and Night Shift.

ORT-MISC-003 ATTACHMENT A Table 8 (page 7) - Rx Cavity Sump Pump completed with Minutes Run reading 76.8 and Total Gal Pumped reading 3456.0 General

References:

N-FH-53-CLD, Rev. 26 OP-KW-ORT-MISC-003, Rev. 1 Task Standards: N-FH-53-CLD review completed and the two errors identified.

Start Time:

Performance Step: 1 N-FH-53-CLD, All appropriate steps have FIRST OPER blanks filled in with initials Critical: No SJ.

Standard:

Check all FIRST OPER blanks filled in with expected initials for steps 1.1 through 4.5 for BT-3B, inclusive, with the following exceptions, which are blank:

  • 2.8.3.c.1.A through 2.8.3.c.1.D
  • 2.10.2.a through 2.10.2.e Evaluator Cue:

For Step 1.1, if asked to provide N-FH-53-CLC, N-FH-53-CLC is on file and correctly completed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 3 of 7

SO-119-JP04A, Review completed N-FH-53 CLD, Daily Refueling Checklist, Rev. A Performance Step: 2 N-FH-53-CLD, All appropriate steps have SECOND OPER blanks filled in with Critical: No initials AF with the exception of step 2.18.2 Standard:

Check all SECOND OPER blanks filled in with expected initials for steps 1.1 through 2.18.2, and for steps 2.19 through 4.5 for BT-3B, with the following exceptions, which are blank:

  • 2.8.3.c.1.A through 2.8.3.c.1.D
  • 2.10.2.a through 2.10.2.e Evaluator Note:

Step 2.18.2 is supposed to have been completed during performance of the procedure but was not. This is a CRITICAL step for identification and correction and is covered in a later Performance Step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 N-FH-53-CLD, Steps 1.2 (3), 1.3 (2), 2.1, 2.6.1 and 2.6.2 Critical: No Steps with blanks for data filled in with data or numbers appropriate to plant conditions Standard:

Check steps 1.2, 1.3, 2.1, 2.6.1 and 2.6.2 to ensure appropriate numbers are filled in blanks.

Evaluator Note:

The COLR for Cycle 29 Rev. 1, 2.12 identifies the minimum Refueling Boron Concentration as 2500 ppm.

Chemistry provides the updated RCS, RHR and SFP boron concentrations.

Reactor Cavity Sump Leakage and Leak rate will be taken from OP-KW-ORT-MISC-003, ATTACHMENT A, Table 4 - Reactor Cavity Sump Pump Run Time Shift Record, and Table 8, Total Sump Pumped History.

Step 2.6.2 has an incorrect value listed and as listed is above the allowed value. This is a CRITICAL step for identification and correction and is covered in Performance Step 6.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 7

SO-119-JP04A, Review completed N-FH-53 CLD, Daily Refueling Checklist, Rev. A Performance Step: 4 N-FH-53-CLD, Steps 2.4.1, 2.4.2, 2.8.c.1, 2.8.3.c.8, 2.8.3.c.9, 2.9.3, 2.9.4, 2.10.1, Critical: No 2.10.2, 2.14 and 2.16.

Steps with choices are circled for the appropriate condition or action depending on plant conditions.

Standard: Check steps below are circled as appropriate for plant conditions to indicate to action or non-action (NA) taken:

2.4.1 - OPERABLE circled.

2.4.2 - NA circled.

2.8.3.c.1 - NA circled.

2.8.3.c.8 - NA circled.

2.8.3.c.9 - STARTED circled.

2.9.3 - ALARM SET circled.

2.9.4 - NA circled.

2.10.1 - APPLIES circled.

2.10.2 - NA circled.

2.14 - NA circled.

2.16 - NORMAL circled.

4.1 - CC SYS INTACT TO RXCP A/B circled. (4 locations)

Evaluator Cue: For steps 1.2 and 1.3 if asked about boron concentration, The values for Reactor Cavity, RHR system, and SFP boron concentrations are current as reported by Chemistry.

For step 2.1 if asked about the Containment Integrity Tagout, The listed Tagout #

is correct for Containment Integrity Tagout.

Evaluator Cue: Check steps below are circled as appropriate for plant conditions to indicate to action or non-action (NA) taken:

2.4.1 - OPERABLE circled.

2.4.2 - NA circled.

2.8.3.c.1 - NA circled.

2.8.3.c.8 - NA circled.

2.8.3.c.9 - STARTED circled.

2.9.3 - ALARM SET circled.

2.9.4 - NA circled.

2.10.1 - APPLIES circled.

2.10.2 - NA circled.

2.14 - NA circled.

2.16 - NORMAL circled.

4.1 - CC SYS INTACT TO RXCP A/B circled. (4 locations)

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 5 of 7

SO-119-JP04A, Review completed N-FH-53 CLD, Daily Refueling Checklist, Rev. A Performance Step: 5 N-FH-53-CLD, Step 2.6.2 Critical: Yes Record latest leak rate 4.2 gpm <3 gpm Standard: Identify that listed value of 4.2 gpm is above the allowable leak rate of < 3 gpm.

Correct value to read between 2.3 to 2.5 gpm OR direct FIRST OPER and SECOND OPER to correct and verify value reads between 2.3 to 2.5 gpm (line out and initial incorrect data) when correct information is provided.

Evaluator Note:

A Condition Report (CR) is required for this error. The Performer may identify this requirement at this time (NOT Critical). If so, cue, A CR has been completed.

Evaluator Cue:

As FIRST OPER state, The value I looked up had the leak rate at 2.4 gpm. I must have written it down wrong. If requested, provide ORT-MISC-003 ATTACHMENT A Table 4 (2 pages) and Table 8 information which supports the total leakage value and the 24-hour leak rate value of 2.4.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 6 N-FH-53-CLD, Step 2.18.2:

Critical: Yes Charcoal Filters (2) in service (Bypass CLOSED) IN SERVICE:

SECOND OPER initial blank Standard: Identify that SECOND OPER failed to initial blank for Step 2.18.2.

Direct SECOND OPER to correct error and initial blank.

Evaluator Note:

A Condition Report (CR) is required for this error. The Performer may identify this requirement at this time (NOT Critical). If so, cue, A CR has been completed.

Evaluator Cue:

As SECOND OPER, I forgot to initial the block. I have confirmed that the charcoal filters are in service with Bypass Damper CLOSED.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 6 of 7

SO-119-JP04A, Review completed N-FH-53 CLD, Daily Refueling Checklist, Rev. A Performance Step: 7 N-FH-53-CLD Critical: No PERFORMED BY blanks.

Standard:

Check that both FIRST OPER and SECOND OPER have completed a PERFORMED BY section, with the name, signature, initials and date blanks filled in.

Evaluator Note:

The DATE will be filled-in with CURRENT DATE. If asked by the Performer indicate that this means todays date is listed in those blanks.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 8 N-FH-53-CLD, Critical: No Shift Manager blank.

Standard: Complete the SHIFT MANAGER blanks by filling in:

  • (Performer) Name
  • Signature
  • Date Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When the performer has completed review of material, This JPM is complete.

Stop Time:

Page 7 of 7

JOB PERFORMANCE MEASURE (JPM)

SITE: KPS JPM TITLE: Perform Independent Verification of SI Valve Lineup JPM NUMBER: RO-033-JP05C REV. B RELATED PRA None INFORMATION:

TASK NUMBER(S) / 0330050101 / Perform a Pre-Start Checklist of the Safety Injection System TASK TITLE(S): 1190180301 / Perform a Independent Verification K/A NUMBERS: 2.1.29 RO / SRO Imp 4.1 / 4.0 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 8 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: RO, SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /s 1/14/09 Instructor Date Validated by: Stephen Johnson /s 01/22/2009 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /s 02/10/09 Training Supervisor Date Page 1 of 7

RO-033-JP05C, Perform Independent Verification of SI Valve Lineup, Rev. B INITIAL CONDITIONS:

  • You are the second NCO.
  • A plant startup is in progress at Step 5.4.5.b of OP-KW-GOP-103, STARTUP FROM RHR TO HOT SHUTDOWN (ESTABLISH SI valve alignment prior to exceeding 1,000 psig per N-SI-33-CL.).
  • The Reactor Operator has just completed the Control Room Switches portion of N-SI-33-CL, Appendix A, SI Valve Lineup Prior To Exceeding 1000 psig.

THE STEPS IN THIS JPM SHOULD BE: PERFORMED THIS TASK IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

The Unit Supervisor directs you to complete the SECOND OPERATOR actions for the Control Room Switches.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Page 2 of 7

RO-033-JP05C, Perform Independent Verification of SI Valve Lineup, Rev. B JPM PERFORMANCE INFORMATION Required Materials: N-SI-33-CL, Appendix A with FIRST OPERATOR section completed, except for the SI-300B/MV-32112 RWST Supply to RHR Pump B which is left BLANK.

General

References:

N-SI-33, Rev. 31 OP-KW-GOP-103, Rev. 2 Task Standards: Second Operator initials complete for correct items. BOTH incorrect items identified and reported.

Start Time:

NOTE: Critical steps are marked with a Y/Yes below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 N-SI-33-CL, APPENDIX A: Control Room Switches Critical: No Safety Injection Pump A AUTO Standard:

Blank under SECOND OPER for SI Pump A initialed.

Evaluator Note:

The order in which the items are addressed is not important. They are listed in the same order as the Appendix.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 N-SI-33-CL, APPENDIX A: Control Room Switches Critical: No Safety Injection Pump B AUTO Standard:

Blank under SECOND OPER for SI Pump B initialed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 3 of 7

RO-033-JP05C, Perform Independent Verification of SI Valve Lineup, Rev. B Performance Step: 3 N-SI-33-CL, APPENDIX A: Control Room Switches Critical: No SI-20A/MV32091 Accumulator A Isolation OPEN/AUTO Standard:

Blank under SECOND OPER for SI-20A initialed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 N-SI-33-CL, APPENDIX A: Control Room Switches Critical: No SI-20B/MV32096 Accumulator B Isolation OPEN/AUTO Standard:

Blank under SECOND OPER for SI-20B initialed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 N-SI-33-CL, APPENDIX A: Control Room Switches Critical: Yes SI-11A/MV32092 Safety Injection to Loop A Cold Leg OPEN/AUTO Standard: Identify SI-11B as CLOSED. Blank under SECOND OPER for SI-11A NOT initialed.

Evaluator Cue: As UNIT SUPERVISOR acknowledge report and direct completion of the remainder of the list.

Discrepancy will be addressed when the list is completed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 7

RO-033-JP05C, Perform Independent Verification of SI Valve Lineup, Rev. B Performance Step: 6 N-SI-33-CL, APPENDIX A: Control Room Switches Critical: No SI-11B/MV32097 Safety Injection to Loop B Cold Leg OPEN/AUTO.

Standard:

Blank under SECOND OPER for SI-11B initialed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 N-SI-33-CL, APPENDIX A: Control Room Switches Critical: No SI-9A/MV32094 Safety Injection to RCS Cold Legs OPEN/MP Standard:

Blank under SECOND OPER for SI-9A initialed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 8 N-SI-33-CL, APPENDIX A: Control Room Switches Critical: No SI-9B/MV32095 Safety Injection to Reactor Vessel OPEN/MP Standard: Blank under SECOND OPER for SI-9B initialed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 5 of 7

RO-033-JP05C, Perform Independent Verification of SI Valve Lineup, Rev. B Performance Step: 9 N-SI-33-CL, APPENDIX A: Control Room Switches Critical: No SI-300A/MV32111 RWST Supply to RHR Pump A OPEN/MP Standard: Blank under SECOND OPER for SI-300A initialed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 10 N-SI-33-CL, APPENDIX A: Control Room Switches Critical: Yes SI-300B/MV32112 RWST Supply to RHR Pump B OPEN/MP Standard:

Identify FIRST OPER has not initialed blank for SI-300B. Blank under SECOND OPER for SI-300B NOT initialed.

Evaluator Cue: As UNIT SUPERVISOR acknowledge report and direct completion of the remainder of the list.

Discrepancy will be addressed when the list is completed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 11 N-SI-33-CL, APPENDIX A: Control Room Switches Critical: No SI-302A/MV32100 RHR Pump A Injection to Reactor Vessel OPEN/AUTO Standard: Blank under SECOND OPER for SI-302A initialed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 6 of 7

RO-033-JP05C, Perform Independent Verification of SI Valve Lineup, Rev. B Performance Step: 12 N-SI-33-CL, APPENDIX A: Control Room Switches Critical: No SI-302B/MV32101 RHR Pump B Injection to Reactor Vessel OPEN/AUTO Standard: Blank under SECOND OPER for SI-302B initialed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 13 N-SI-33-CL, APPENDIX A: Control Room Switches Critical: No PERFORMED BY ______________________ DATE____________

Standard: Signs and dates PERFORMED BY blanks.

Evaluator Note: This may NOT occur if the operator reports completion of the steps he could perform and notes the two items need to be resolved for completion.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When lineup checklist is returned to the UNIT SUPERVISOR: This JPM is complete.

Stop Time:

Page 7 of 7

JOB PERFORMANCE MEASURE (JPM)

SITE: KPS JPM TITLE: Review SP-033-065, Reactor Coolant Chemistry Surveillance, Results JPM NUMBER: SO-119-JP19A REV. B RELATED PRA None INFORMATION:

TASK NUMBER(S) / 1190190302 / Apply Technical Specifications during plant operations TASK TITLE(S):

K/A NUMBERS: 2.1.34 RO / SRO Imp 2.7 / 3.5 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: Other: X Classroom Lab:

Time for Completion: 10 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson 03/30/09 Instructor Date Validated by: Andrew Fahrenkrug 03/24/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans Training Supervisor Date Page 1 of 8

SO-119-JP19A, Review SP-033-065, Reactor Coolant Chemistry Surveillance, Results, Rev. B INITIAL CONDITIONS:

  • You are the Shift Manager.
  • The plant has been operating at 100% power for the past 30 days.
  • Today is 4/XF/2009.

THE STEPS IN THIS JPM SHOULD BE: PERFORMED THIS TASK IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

Perform review of Form SP-37-065-1.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Page 2 of 8

SO-119-JP19A, Review SP-033-065, Reactor Coolant Chemistry Surveillance, Results, Rev. B JPM PERFORMANCE INFORMATION Required Materials: Form SP-37-065-1, With 6 blocks worth of information completed (3 samples of pertinent values). Under 4/XF, the value for CHLORIDE will exceed the allowable steady-state value of 0.15 ppm. The value will be listed as 160.8 ppb.

KPS Technical Specifications General

References:

SP-37-065, Rev. X CY-KW-040-001, Rev. 1 KPS Technical Specifications Task Standards: Form SP-37-065-1 reviewed and the ACTIONS of Technical Specification 3.1.e.2 and 3.1.e.3 identified.

Start Time:

NOTE: Critical steps are marked with a Y/Yes below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Page 3 of 8

SO-119-JP19A, Review SP-033-065, Reactor Coolant Chemistry Surveillance, Results, Rev. B Performance Step: 1 Form SP-37-065-1, All appropriate steps have blanks filled in.

Critical: No Standard:

Check all blanks filled in with expected information for:

  • Week of - [4/XA/2009 to 4/XG/2009]
  • Most recent E - [1.314]
  • Most recent 91 / E - [64.26]
  • Sample Date - [3/30/2009]
  • All listed blanks under 4/XF Sample Date, except for Tritium [line out]; Shift Manager.

Evaluator Note:

Chemistry procedure CY-KW-040-001, Primary Chemistry Sample Specifications, provides ACTION levels in response to off-normal Chemistry values. When chloride values exceed 50 ppb, ACTION Level 1 is entered. This would require a Condition Report (CR or AR). This is the reason the AR filed blank is checked YES and the number listed. The action stated is, Actions to be taken if a parameter exceeds the Action Level 1 value: Efforts shall be made to bring the parameter to below the Action Level 1 within 7 days.

Evaluator Cue:

If asked about the Condition Report (AR) listed for 4/XB and 4/XD: This CR was written to address Chemistry entering ACTION LEVEL 1 for Chloride.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 Form SP-37-065-1, Sample Date 4/XF Critical: No Coolant Activity (µCi/ml)

Standard:

Determine value is acceptable in accordance with Technical Specification 3.1.c.1.B

[Value is less than or equal to Most Recent 91 / E]

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 8

SO-119-JP19A, Review SP-033-065, Reactor Coolant Chemistry Surveillance, Results, Rev. B Performance Step: 3 Form SP-37-065-1, Sample Date 4/XF Critical: No Dose Equivalent I-131 (µCi/gram)

Standard:

Determine value is acceptable in accordance with Technical Specification 3.1.c.1.A

[Value is less than or equal to 1.0 µCi/gram.]

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 Form SP-37-065-1, Sample Date 4/XF Critical: No Flouride (ppb).

Standard: Determine value is acceptable in accordance with Technical Specification 3.1.e.1.C [Value is less than or equal to 150 ppb (0.15 ppm).]

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 5 of 8

SO-119-JP19A, Review SP-033-065, Reactor Coolant Chemistry Surveillance, Results, Rev. B Performance Step: 5 Form SP-37-065-1, Sample Date 4/XF Critical: Yes Chloride (ppb).

Standard: Determine value is NOT acceptable in accordance with Technical Specification 3.1.e.1.B [Value is NOT less than or equal to 150 ppb (0.15 ppm).]

Determine the Technical Specification ACTIONs required:

  • 3.1.e.2 - Corrective Action shall be taken immediately
  • 3.1.e.3 - If concentrations of any contaminants cannot be controlled within the transient limits of TS 3.1.e.1 above (1.50 ppm) or returned to steady-state limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then the reactor shall be brought to the COLD SHUTDOWN condition, utilizing normal operating procedures, and the cause shall be ascertained and corrected.

Evaluator Note:

A Condition Report (CR or AR as listed on Form SP-37-065) is required for this condition. The Performer may identify this requirement at this time (Item is covered in Performance Step 11). If so, cue, CR CR0YYYYY has been completed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 6 Form SP-37-065-1, Sample Date 4/XF Critical: No Oxygen (ppb).

Standard:

Determine value is acceptable in accordance with Technical Specification 3.1.e.1.A [Value is less than or equal to 100 ppb (0.10 ppm).]

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 6 of 8

SO-119-JP19A, Review SP-033-065, Reactor Coolant Chemistry Surveillance, Results, Rev. B Performance Step: 7 Form SP-37-065-1, Sample Date 4/XF Critical: No Boron (ppm).

Standard:

Check boron value filled in and consistent with previous listings.

Evaluator Note:

Boron limit only applies when while loading and unloading fuel from the reactor, or during Reactor Vessel Head removal.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 8 Form SP-37-065-1, Sample Date 4/XF Critical: No Tritium (µCi/mL)

Standard:

Tritium Sampling is NOT listed [lined out]

Evaluator Note:

Tritium sampling is required only once per week, usually Wednesday.

There is no specific limit for RCS tritium concentration.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 9 Form SP-37-065-1, Sample Date 4/XF Critical: No Chemistry Tech.

Standard:

Check Chemistry Tech. initials in blank.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 7 of 8

SO-119-JP19A, Review SP-033-065, Reactor Coolant Chemistry Surveillance, Results, Rev. B Performance Step: 10 Form SP-37-065-1, Sample Date 4/XF Critical: No Shift Manager Standard: Complete the SHIFT MANAGER blanks by filling in initials.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 11 Form SP-37-065-1, Sample Date 4/XF Critical: Yes AR filed checkbox and AR # blank Standard: Identify that NO checkbox is incorrectly marked for 4/XF date One line and initial NO checkbox mark AND YES checkbox checked.

Identify that use of NA is inappropriate.

One line and initial NA AND CR# (AR#) listed.

Evaluator Note:

A Condition Report (CR or AR as listed on Form SP-37-065) is required for this condition. The Performer may identify this requirement at this time. If so, cue, CR CR0YYYYY has been completed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When the performer has completed filling Form SP-37-065-1 for 4/XF date, This JPM is complete.

Stop Time:

Page 8 of 8

JOB PERFORMANCE MEASURE (JPM)

SITE: KPS JPM TITLE: Perform a Manual Calorimetric / Heat Balance Using SP-87-125 JPM NUMBER: RO-087-JP01B REV. A RELATED PRA None INFORMATION:

TASK NUMBER(S) / 0870010201 / Perform Shift Instrument Channel Checks - Operating TASK TITLE(S):

K/A NUMBERS: 2.2.44 RO / SRO Imp 4.2 / 4.4 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 20 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: RO, SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /s 1/15/09 Instructor Date Validated by: Stephen Johnson /s 01/22/2009 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /s 02/10/09 Training Supervisor Date PERFORMANCE RESULTS: SAT: UNSAT:

Page 1 of 11

RO-087-JP01B, Perform a Manual Calorimetric / Heat Balance Using SP-87-125, Rev. A INITIAL CONDITIONS:

  • You are the Reactor Operator.
  • The plant is operating at 100% steady-state power.
  • PPCS Calorimetric Program is NOT functioning, and OP-KW-AOPCP-001, Abnormal Plant Process Computer System, ATTACHMENT A is being performed by the crew.
  • ARTO is NOT available.
  • Access to the KPS Network is NOT available.

THE STEPS IN THIS JPM SHOULD BE: PERFORMED THIS TASK IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

The Unit Supervisor directs you to complete a calorimetric per section 6.7.3 of SP 87-125, Shift Instrument Channel Checks - Operating.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Page 2 of 11

RO-087-JP01B, Perform a Manual Calorimetric / Heat Balance Using SP-87-125, Rev. A JPM PERFORMANCE INFORMATION Required Materials: SP-87-125.

General

References:

SP-87-125, Rev. 97 OP-KW-AOP-CP-001, Rev. 2, ATTACHMENT A Task Standards:

Start Time:

NOTE: Critical steps are marked with a Y/Yes below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Page 3 of 11

RO-087-JP01B, Perform a Manual Calorimetric / Heat Balance Using SP-87-125, Rev. A Performance Step: 1 SP-87-125, Step 6.7.3.a Critical: Yes On ATTACHMENT A, RECORD data from Operations - Protected 1, SP-87-125 Data OR the Yokogawa recorders R average indications from Control Board meters.

Standard:

On PPCS Main Screen, click the following to get to the Operations - Protected 1, SP-87-125 Data:

  • Button for AREA/GROUP DISPLAYS
  • (List #) 1. OPERATIONS -PROTECTED 1
  • (List #) 3. SP87-125 DATA Record data on ATTACHMENT A:
  • FX51OG OR T0418A (SG A FW Temp) [434.9ºF OR 434.89ºF]
  • P8021G (SG A Pressure) [768.4 psig]
  • FX800G (SG A FW Flow) [3833.4 to 3833.5 Klbm/hr]
  • F0508K (SG A Blowdown Flow) [40 gpm]
  • FX61OG OR T0438A (SG B FW Temp) [434.9ºF OR 434.87ºF]
  • P8022G (SG B Pressure) [757.8 psig]
  • FX900G (SG B FW Flow) [3907.1 to 3907.2 Klbm/hr]
  • F0509K (SG B Blowdown Flow) [40 gpm]

Evaluator Note:

The performer may choose to review Initial Conditions (Section 1.0), Precautions and Limitations (Section 2.0), and General Instructions (Section 4.0) prior to performing steps.

The NOTEs at the beginning of Step 6.7 state:

Operations - Protected 1, SP-87-125 Data may be used in place of, and is preferable to, Yokogawas and Control Board meters for obtaining data.

Yokogawas may be used in place of, and are preferable to, Control Board meters for obtaining data.

Evaluator Cue:

As Unit Supervisor, Use the preferred source for data information.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 11

RO-087-JP01B, Perform a Manual Calorimetric / Heat Balance Using SP-87-125, Rev. A Performance Step: 2 SP-87-125, Step 6.7.3.b: CALCULATE Reactor Thermal Output Using Enthalpy Critical: Yes per ATTACHMENT B.

1. OBTAIN enthalpy values for FW temperature by using RD 1.6 OR Steam Tables Standard:

Fill in the blanks for the enthalpy value of the FW temperature (hf at the temp) from either RD 1.6 or Steam Tables:

  • Header A _________ BTU/LBM [413.32 to 413.67]
  • Header B _________ BTU/LBM [413.30 to 413.67]

Evaluator Note:

The following values are calculated from either RD 1.6 or Steam Table hf values for the feedwater temperature:

RD 1.6 Interpolate

  • Header A - Page 21 Steam Pressure 750-775 psig): 434.9 [413.67 BTU/LB] OR 434.89 (between 434.8 and 434.9) [413.66 BTU/LB]
  • Header B - Page 21 Steam Pressure 750-775 psig): 434.9 [413.67 BTU/LB] OR 434.87 (between 434.8 and 434.9) [413.64 BTU/LB]

Steam Table interpolation

  • Header A - For FW temperature 434.9 or 434.89 interpolate hf between 432ºF (410.12 BTU/LB) and 436ºF (414.55 BTU/LB) to calculate values of 413.33 BTU/LB and 413.32 BTU/LB, respectively.
  • Header B - For FW temperature 434.9 or 434.87 interpolate hf between 432ºF (410.12 BTU/LB) and 436ºF (414.55 BTU/LB) to calculate values of 413.33 BTU/LB and 413.30 BTU/LB, respectively.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 5 of 11

RO-087-JP01B, Perform a Manual Calorimetric / Heat Balance Using SP-87-125, Rev. A Performance Step: 3 SP-87-125, Step 6.7.3.b: CALCULATE Reactor Thermal Output Using Enthalpy Critical: Yes per ATTACHMENT B.

2. OBTAIN enthalpy values for SG Pressure by using RD 1.6 OR Steam Tables Standard:

Fill in the blanks for the enthalpy value of the SG pressure (hg at the pressure) from either RD 1.6 or Steam Tables:

  • SG A _________ BTU/LBM [1199.80 to 1199.83]
  • SG B _________ BTU/LBM [1200.08 to 1200.14]

Evaluator Note:

The following values are calculated from either RD 1.7 or Steam Table hg values for the SG pressure:

RD 1.6 Interpolate

  • Header A - Page 1 Steam Pressure between 765 and 770 psig):

Interpolate for 768.4 psig to calculate between given values of 1199.9 BTU/LB and 1199.8 BTU/LB and determine 1199.83 BTU/LB.

  • Header B - Page 1 Steam Pressure between 755 and 760 psig):

Interpolate for 757.8 psig to calculate between given values of 1200.2 BTU/LB and 1200.1 BTU/LB and determine 1200.14 BTU/LB.

Steam Table interpolation includes changing form psig to psia:

  • Header A - For steam pressure 783.1 / 783.4 psia interpolate hg between 780 and 820 psia to calculate values between 1199.9 BTU/LB and 1198.7 BTU/LB, respectively.
  • Header B - For steam pressure 772.5 / 772.8 psia interpolate hg between 740 and 780 psia to calculate values between 1200.9 BTU/LB and 1199.9 BTU/LB, respectively.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 6 of 11

RO-087-JP01B, Perform a Manual Calorimetric / Heat Balance Using SP-87-125, Rev. A Performance Step: 4 SP-87-125, Step 6.7.3.b: CALCULATE Reactor Thermal Output Using Enthalpy Critical: Yes per ATTACHMENT B.

1. CALCULATE MWt output for SG A:

MWt(A) = (FW Flow) K-LBM/HR x [(ho(A) - hi(A)) BTU/LBM] / 3413 K-BTU/MW-HR Standard:

Determine the MWt for SG A from the calculation using the recorded and computed data. [883.00 to 883.40]

Evaluator Note:

Calculation range is based upon use of highest and lowest values for FW flows and the use of RD or Steam Table values.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 SP-87-125, Step 6.7.3.b: CALCULATE Reactor Thermal Output Using Enthalpy Critical: Yes per ATTACHMENT B.

2. CALCULATE MWt output for SG B:

MWt(B) = (FW Flow) K-LBM/HR x [(ho(B) - hi(B)) BTU/LBM] / 3413 K-BTU/MW-HR Standard:

Determine the MWt for SG B from the calculation using the recorded and computed data. [900.30 to 900.75]

Evaluator Note:

Calculation range is based upon use of highest and lowest values for FW flows and the use of RD or Steam Table values.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 7 of 11

RO-087-JP01B, Perform a Manual Calorimetric / Heat Balance Using SP-87-125, Rev. A Performance Step: 6 SP-87-125, Step 6.7.3.b: CALCULATE Reactor Thermal Output Using Enthalpy Critical: Yes per ATTACHMENT B.

5. CALCULATE Blowdown Correction:

Blowdown Correction = 0.0758 MWt/GPM x (Blowdown Flow A + Blowdown Flow B) GPM Standard:

Determine the MWt for Blowdown Correction from the calculation using the recorded data. [6.06]

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 SP-87-125, Step 6.7.3.b: CALCULATE Reactor Thermal Output Using Enthalpy Critical: Yes per ATTACHMENT B.

6. CALCULATE Reactor Thermal Output:

RTO = MWt(A) + MWt(B) - Blowdown Correction - 7.11 MW Standard:

Determine the MWt for Reactor Thermal Output from the calculation using the recorded data. [1770.13 to 1770.98]

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 8 of 11

RO-087-JP01B, Perform a Manual Calorimetric / Heat Balance Using SP-87-125, Rev. A Performance Step: 8 SP-87-125, Step 6.7.3.c Critical: Yes RECORD Reactor Thermal Output from ATTACHMENT B on ATTACHMENT A and SP-87-125, Step 6.7.3.b: CALCULATE Reactor Thermal Output Using Enthalpy per ATTACHMENT B.

7. RECORD Reactor Thermal Output on ATTACHMENT A Standard: Reactor Thermal Output recorded in MWt box on ATTACHMENT A.

Evaluator Note: Action to copy the RTO to ATTACHMENT A is a step on ATTACHMENT B. It is also repeated as a step 6.7.3.c in the body of the procedure.

ATTACHMENT A Reactor Thermal Output directs the performer to circle the method for determining the RTO. The bottom line should be circled to indicate the RTO was determined by Calculation. Circling the method is NOT a critical action.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 9 SP-87-125, Step 6.7.3.b: CALCULATE Reactor Thermal Output Using Enthalpy Critical: No per ATTACHMENT B.

8. Performed By:

Standard: Fill in the Performed By: blanks by printing name and signature.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 9 of 11

RO-087-JP01B, Perform a Manual Calorimetric / Heat Balance Using SP-87-125, Rev. A Performance Step: 10 SP-87-125, Step 6.7.3.d Critical: Yes CALCULATE AND RECORD Reactor Power Level per ATTACHMENT A.

[Reactor Thermal Output x 100] / 1772 MWt Standard:

Determine the % power for Reactor Power level from the calculation using the recorded data.

Reactor Power Level recorded in % box on ATTACHMENT A. [99.89 to 99.94]

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 11 SP-87-125, Step 6.7.3.d Critical: No ATTACHMENT A: Date and time; Performed By:

Standard: Fill in the Date: and Time: blanks by printing current date and time, respectively.

Fill in the Performed By: blanks by printing name and signature.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 12 SP-87-125, Step 6.7.3.e Critical: No IF Heat Balance Calculation results will be used for Nuclear Power Range Daily Calibration, THEN RECORD Reactor Power Level on "Instrument Channel Checks and Nuclear Power Range Daily Calibration" data sheet.

Standard: Determine step does NOT apply.

Evaluator Cue: As Unit Supervisor, This surveillance is being performed hourly as directed by AOP-CP-001 ATTACHEMNT A; Not for the NIS calibration.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 10 of 11

RO-087-JP01B, Perform a Manual Calorimetric / Heat Balance Using SP-87-125, Rev. A Performance Step: 13 SP-87-125, Step 6.7.3.f Critical: No ATTACH completed copies of ATTACHMENT A, ATTACHMENT B and ATTACHMENT C to this procedure.

Standard: Attach completed ATTACHMENT A and ATTACHMENT B to Procedure SP 125.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When SP-75-125 is returned to the UNIT SUPERVISOR: This JPM is complete.

Stop Time:

Page 11 of 11

JOB PERFORMANCE MEASURE (JPM)

SITE: KPS JPM TITLE: Determine Appropriate Actions For System Operations With Inoperable Equipment JPM NUMBER: SO-119-JP19B REV. B RELATED PRA Diesel Generator is ranked the 1st system for importance to At-Power CDF & LERF.

INFORMATION: SI is ranked the 11th system for importance to At-Power CDF & 3rd for LERF.

TASK NUMBER(S) / 1190190302 / Apply Technical Specifications during plant operations TASK TITLE(S):

K/A NUMBERS: 2.2.44 RO / SRO Imp 4.2 / 4.4 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 10 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson 03/30/09 Instructor Date Validated by: Stephen Johnson 03/25/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans Training Supervisor Date Page 1 of 6

SO-119-JP19B, Determine Appropriate Actions For System Operations With Inoperable Equipment, Rev. B INITIAL CONDITIONS:

  • You are the Shift Manager.
  • The plant operating at 100% power.
  • All initial operator actions for the plant conditions have been taken.

THE STEPS IN THIS JPM SHOULD BE: PERFORMED THIS TASK IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

Determine the applicable Technical Specifications and the ACTIONS required based on the plant conditions.

NOTE: The sampling of SI Accumulators requires Containment entry. Use of the Personnel Door Lock requires leak rate surveillance to ensure seals functioning (TS 1.0.g / 4.4.b). If asked about leak test during JPM performance, provide CUE: Leak rate tests have been satisfactorily completed.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Form NTP-6331 Rev. A Date: JAN 19 2006 Page 2 of 6

SO-119-JP19B, Determine Appropriate Actions For System Operations With Inoperable Equipment, Rev. B JPM PERFORMANCE INFORMATION Required Materials: KPS Technical Specifications General

References:

KPS Technical Specifications OP-KW-NOP-DGM-001B, Rev. 3; N-SI-33, Rev. 31 Task Standards: Identify that SI Accumulator cannot be restored until DG B return to OPERABLE. TS ACTION for Accumulator applies as most limiting - TS 3.3.a.2.B, 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO Start Time:

NOTE: Critical steps are marked with a Y/Yes below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Identify plant conditions:

Critical: No Standard:

Determine the following:

Evaluator Cue:

If asked about DG B: DG B has been out of service for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for fuel pump replacement. The expected outage time for the DG is not known at this time. All required surveillances have been completed up to the current time.

Annunciator 47024-A (pressure) and 47024-B (level) has just actuated, and SI Accumulator A level has occurred due to recent Chemistry sampling.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 3 of 6

SO-119-JP19B, Determine Appropriate Actions For System Operations With Inoperable Equipment, Rev. B Performance Step: 2 Diesel Generator B TS:

Critical: Yes 3.7.a The reactor shall not be made critical unless all of the following requirements are satisfied:

7. Both diesel generators are OPERABLE. The two underground storage tanks combine to supply at least 35,000 gallons of fuel oil for either diesel generator and the day tanks for each diesel generator contain at least 1,000 gallons of fuel oil.

LCO 3.7.b During power operation or recovery from inadvertent trip, any of the following conditions of inoperability may exist during the time intervals specified. If OPERABILITY is not restored within the time specified, then within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action shall be initiated to achieve HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

2. One diesel generator may be inoperable for a period not exceeding 7 days provided within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, either:

A. Determine the OPERABLE diesel generator is not inoperable due to common cause failure, or B. Perform surveillance requirement TS 4.6.a.1.A on the OPERABLE diesel generator 3.7.c When its normal or emergency power source is inoperable, a system, train or component may be considered OPERABLE for the purpose of satisfying the requirements of its applicable LIMITING CONDITION FOR OPERATION, provided:

1. Its corresponding normal or emergency power source is OPERABLE; and
2. Its redundant system, train, or component is OPERABLE.

Standard:

1. Identify 7-day LCO period with DG B inoperable.
2. Affects Train B equipment OPERABILITY in that Train B Electrical Distribution system supplied via the RAT must be OPERABLE, AND Train A required equipment must be OPERABLE.

Evaluator Note:

Item 2 of the STANDARD need NOT be directly identified at the time the DG TS is identified, but will be implicitly addressed in correct identification of actions as stated in PERFORMANCE STEP 4.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 4 of 6

SO-119-JP19B, Determine Appropriate Actions For System Operations With Inoperable Equipment, Rev. B Performance Step: 3 SI Accumulator TS:

Critical: Yes 3.3.a Accumulators

1. The reactor shall not be made critical unless the following conditions are satisfied, except for LOW POWER PHYSICS TESTING and except as provided by TS 3.3.a.2.

A. Each accumulator is pressurized to at least 700 psig and contains 1250 ft3 +/- 25 ft3 of water with a boron concentration of at least 2400 ppm, and is not isolated.

LCO 3.3.a.2 During power operation or recovery from an inadvertent trip, the following conditions of inoperability may exist during the time interval specified:

B. One accumulator may be inoperable for a reason other than TS 3.3.a.2.A [Boron conc < 2400 ppm] for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Standard:

1. Determine SI Accumulator A is inoperable due to level less than 40% on LT-938 channel and less than 36% on LT-939 channel. [Volume is < 1225 ft3]
2. Identify 24-hour LCO to restore SI Accumulator A volume with level 40.21%

(LT-938) and 36.61% (LT-939).

Evaluator Note:

The required Technical Specification level in % can be found in either ARP 47024-B, 3.4 Comments or N-SI-33, ATTACHMENT B Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 5 of 6

SO-119-JP19B, Determine Appropriate Actions For System Operations With Inoperable Equipment, Rev. B Performance Step: 4 Determine corrective actions to restore system OPERABILITY.

Critical: Yes Standard: Determine correct course of action:

1. Restore DG B to OPERABLE AND refill SI Accumulator A to within TS limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (to prevent unit backdown).

OR

2. If 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> elapses (in current condition), then initiate a unit backdown and:
a. Achieve HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. Achieve HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c. Achieve COLD SHUTDOWN within an additional 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

(This timeline is to be met until DG B is restored to OPERABLE and SI Accumulator A is refilled to within TS limits.)

Evaluator Note: With DG B inoperable application of TS 3.7.c is NOT allowed for using an SI Pump to fill the accumulator. An SI Pump used for filling the accumulator is inoperable during the time of filling. The other SI Pump is also inoperable (due to 3.7.c) during this time.

Wording provided by performer does not have to exactly match that given in the STANDARD as log as the action and key times are addressed.

Evaluator Cue: Cue as necessary to elicit plan of action: (Suggested cues)

What is required if the component is NOT restored to OPERABLE within the listed time?

How would the component be restored?

What is required to allow restoration of the component? (i.e., Diesel Generator must be returned to service.)

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When the performer has reported the identified the actions he/she identifies as required, This JPM is complete.

Stop Time:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 6 of 6

JOB PERFORMANCE MEASURE (JPM)

SITE: KPS JPM TITLE: Don and Remove Class 2 Protective Clothing JPM NUMBER: RO-119-JP12A REV. B RELATED PRA None INFORMATION:

TASK NUMBER(S) / 1190120301 / Demonstrate an understanding of the responsibilities and TASK TITLE(S): requirements for the Nuclear Control Operator K/A NUMBERS: 2.3.7 RO / SRO Imp 3.5 / 3.6 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: Other: X Classroom /

Lab:

Time for Completion: 20 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: AO / RO / SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson 03/30/09 Instructor Date Validated by: Stephen Johnson 03/25/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans Training Supervisor Date Page 1 of 11

RO-119-JP12A, Don and Remove Class 2 Protective Clothing, Rev. B INITIAL CONDITIONS:

  • You are an extra operator on shift.
  • Conditions require local action by the operator in a contaminated area.
  • The RWP-XX provides coverage for this task.
  • Class 2 Protective Clothing is specified in the RWP to include: 1 pair PCs (coveralls); Glove liners, Rubber gloves; Shoe covers; Rubber footwear, and Head cover (hood).
  • All actions required prior to dressing out have been completed including obtaining TLD and dosimetry; and, logging into the RCA Access System.
  • The clothes you are currently wearing will meet the identified modesty garments required underneath the Class 2 Protective Clothing.

THE STEPS IN THIS JPM SHOULD BE: PERFORMED THIS TASK IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

Complete dress out in the specified Protective Clothing for entry into and exit from the contaminated area.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Page 2 of 11

RO-119-JP12A, Don and Remove Class 2 Protective Clothing, Rev. B Performance Step: 1 RP-KW-001-005, Step 5.2.2:

Critical: No COLLECT protective clothing required by the RWP from the storage racks.

Standard:

Obtain the following:

  • 1 pair PCs (coveralls)
  • 1 set of glove liners
  • 1 set of rubber gloves
  • 1 pair of shoe covers
  • 1 pair rubber footwear
  • 1 head cover (hood)

Evaluator Note:

The designated dressout area will be supplied with a selection of dressout items including labcoats which are designated for Class 1 Protective Clothing.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 RP-KW-001-005, Step 5.2.3:

Critical: No INSPECT articles of protective clothing for rips, cuts, proper fit, and general integrity prior to donning the articles of protective clothing selected.

Standard:

Inspect all selected Protective Clothing for

  • Rips or cuts
  • Fit
  • General integrity Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 3 of 11

RO-119-JP12A, Don and Remove Class 2 Protective Clothing, Rev. B Performance Step: 3 RP-KW-001-005, Step 5.2.4:

Critical: Yes DON shoe covers over your shoes, as appropriate.

Standard:

Place shoe covers over shoes.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 RP-KW-001-005, Step 5.2.5:

Critical: Yes DON a pair of glove liners Standard: Place cotton glove (liners) over each hand.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 11

RO-119-JP12A, Don and Remove Class 2 Protective Clothing, Rev. B Performance Step: 5 RP-KW-001-005, Step 5.2.6:

Critical: Yes DON a pair of coveralls as follows:

a. STEP into the coveralls making sure that the tops of the shoe covers are inside the pant legs.
b. INSERT arms into the sleeves of the coveralls.

Standard:

Don coveralls:

  • Tops of shoe covers are inside the coverall pant legs.
  • The zipper on the coveralls is zipped all the way up Evaluator Note:

The zipper may not be zipped all the way prior to the completion of the dressout to allow access to TLD and dosimetry.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 6 RP-KW-001-005, Step 5.2.7:

Critical: Yes DON a second pair of shoe covers (i.e., rubber overshoes, plastic shoe covers).

Standard:

Rubber shoe covers placed over first set of shoe covers.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 5 of 11

RO-119-JP12A, Don and Remove Class 2 Protective Clothing, Rev. B Performance Step: 7 RP-KW-001-005, Step 5.2.8:

Critical: Yes DON a pair of rubber gloves over the disposable glove liners, pulling the cuffs up over the sleeves of the coveralls.

Standard:

Rubber glove placed on each hand:

  • Over glove liners.

Evaluator Note:

The coveralls are equipped with oversleeves that can be pulled down over the outer-most set of gloves.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 8 RP-KW-001-005, Step 5.2.9:

Critical: No PULL outer sleeves of coveralls over rubber gloves.

Standard:

Outer sleeve of coverall pulled down over outer-most (rubber) glove opening for each sleeve.

Evaluator Note:

The coveralls are equipped with oversleeves that can be pulled down over the outer-most set of gloves.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 6 of 11

RO-119-JP12A, Don and Remove Class 2 Protective Clothing, Rev. B Performance Step: 9 RP-KW-001-005, Step 5.2.10:

Critical: Yes DON head cover. This is normally a hard hat, but may include additional items (e.g., hood) if required by RWP.

Standard:

Hood is placed on head with bottom draped over coveralls.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 10 RP-KW-001-005, Step 5.2.11:

Critical: No Unless otherwise directed by HP, PLACE dosimetry on upper torso with TLD and ED or DRD within one hands width of each other.

Standard: Dosimetry and TLD placed on upper torso within one hands width.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 11 RP-KW-001-005, Step 5.2.12:

Critical: No ENSURE that proper respiratory equipment is available, if required by the RWP Standard:

Respiratory Equipment is NOT required by RWP.

Evaluator Cue:

When dressout is complete: Proceed to the indicated work area.

After entry into work area: All work is complete. Exit the work area removing the protective clothing.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 7 of 11

RO-119-JP12A, Don and Remove Class 2 Protective Clothing, Rev. B Performance Step: 12 RP-KW-001-005, Step 5.3.1.b:

Critical: Yes REMOVE the outer layer of protective clothing (e.g., shoe covers, gloves, hood, plastics) prior to proceeding to a frisking station.

REMOVE outer shoe covers.

  • PLACE the outer shoe covers into the appropriate container.

Standard:

Remove outer shoe covers and place in plastic bin.

Maintain body positioned to avoid first step-off pad.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 13 RP-KW-001-005, Step 5.3.1.c:

Critical: Yes REMOVE the outer layer of protective clothing (e.g., shoe covers, gloves, hood, plastics) prior to proceeding to a frisking station.

To prevent the spread of contamination, REMOVE the rubber gloves by grasping the cuff and pulling downward toward the fingers and turning the glove inside out at the same time.

  • PLACE the rubber gloves into the appropriate container.

Standard:

Remove rubber gloves by rolling inside-out from cuff and place in plastic bin.

Maintain body positioned to avoid first step-off pad.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 8 of 11

RO-119-JP12A, Don and Remove Class 2 Protective Clothing, Rev. B Performance Step: 14 RP-KW-001-005, Step 5.3.1.d:

Critical: Yes REMOVE the outer layer of protective clothing (e.g., shoe covers, gloves, hood, plastics) prior to proceeding to a frisking station.

IF worn, THEN REMOVE the hood or skull cap by turning it inside out.

  • ASSURE that while removing the hood or skull cap, no parts of the head are touched by the glove liners.
  • PLACE the hood or skull cap in the appropriate container.

Standard:

Remove hood from bottom turning inside-out without touching the glove liners to head, and place hood in plastic bin.

Maintain body positioned to avoid first step-off pad.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 15 RP-KW-001-005, Step 5.3.1.e:

Critical: No REMOVE the outer layer of protective clothing (e.g., shoe covers, gloves, hood, plastics) prior to proceeding to a frisking station.

IF Respiratory equipment was used, THEN REMOVE as follows:

Standard:

N/A (Respiratory equipment NOT used.)

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 9 of 11

RO-119-JP12A, Don and Remove Class 2 Protective Clothing, Rev. B Performance Step: 16 RP-KW-001-005, Step 5.3.1.f:

Critical: Yes REMOVE the outer layer of protective clothing (e.g., shoe covers, gloves, hood, plastics) prior to proceeding to a frisking station.

REMOVE the coveralls as follows:

  • IF wearing draw string type coveralls, THEN UNTIE the drawstring at the neck of the coveralls to expand the neck opening.
  • IF wearing zip up type coveralls, THEN UNZIP coveralls.
  • GRASP the shoulders and PULL down so that the sleeves are turned inside out and REMOVE the hands from the sleeves.
  • ROLL the coveralls downward from the waist while raising the feet, and PULL the legs off over the shoe covers.
  • PLACE the coveralls into the proper container.

Standard:

Remove coveralls:

  • Unzip
  • Remove from top by turning sleeves inside-out
  • Roll coverall downward from waist; lift and extract each leg
  • Place in plastic bin marked for Ortex.

Maintain body positioned to avoid first step-off pad.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 10 of 11

RO-119-JP12A, Don and Remove Class 2 Protective Clothing, Rev. B Performance Step: 17 RP-KW-001-005, Step 5.3.1.g:

Critical: Yes REMOVE the outer layer of protective clothing (e.g., shoe covers, gloves, hood, plastics) prior to proceeding to a frisking station.

REMOVE the shoe covers.

  • PLACE the shoe covers into the appropriate container.

Standard:

1. Step onto first step-off pad.
2. Remove shoe cover and place in plastic bin.
3. As each shoe cover is removed, place unprotected foot onto second step-off pad.

Maintain body positioned to avoid having potentially contaminated material (i.e., shoe covers) over the second step-off pad.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 18 RP-KW-001-005, Step 5.3.1.h:

Critical: Yes REMOVE the outer layer of protective clothing (e.g., shoe covers, gloves, hood, plastics) prior to proceeding to a frisking station.

REMOVE the glove liners.

  • PLACE the glove liners into the appropriate container.

Standard:

Remove glove liners by rolling inside-out from cuff and place in plastic bin.

Maintain body positioned on second step-off pad.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When the performer has completed removing protective clothing, This JPM is complete.

Stop Time:

Page 11 of 11

JOB PERFORMANCE MEASURE (JPM)

SITE: KPS JPM TITLE: Review Emergency Exposure Authorization JPM NUMBER: SO-119-JP66A REV. A RELATED PRA None INFORMATION:

TASK NUMBER(S) / 1190660302 / Control Emergency Radiation to achieve ALARA TASK TITLE(S):

K/A NUMBERS: 2.3.7 RO / SRO Imp 3.5 / 3.6 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: Other: X Classroom Lab:

Time for Completion: 10 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /S 1/28/09 Instructor Date Validated by: Andy Fahrenkrug /S 02/10/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /S 02/10/09 Training Supervisor Date Page 1 of 8

SO-119-JP66A, Review Emergency Exposure Authorization, Rev. A INITIAL CONDITIONS:

  • You are the Shift Manager / Emergency Director.
  • An accident has occurred at the plant.
  • A SITE AREA EMERGENCY has been declared.
  • Radiation levels are elevated in the Aux Building.
  • The task is to CLOSE SI-8A and SI-8B to stop leakage past SI-38, SI Pmp 1A/1B Disch X-Connect Line Drain, that is threatening to flood the RHR Pits.
  • Two individuals have volunteered for the job.
  • Emergency Exposure Authorizations and an Emergency Radiation Work Permit have been prepared.

THE STEPS IN THIS JPM SHOULD BE: PERFORMED THIS TASK IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

Review Forms EPIPF-AD-11-04, Emergency Exposure Authorization, and EPIPF-AD-11-01, Emergency Radiation Work Permit, for approval.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Page 2 of 8

SO-119-JP66A, Review Emergency Exposure Authorization, Rev. A JPM PERFORMANCE INFORMATION Required Materials: Form EPIPF-AD-11-01 completed through the APPROVAL blocks except for E.D blank. Form EPIPF-AD-11-04 (2) for two individuals completed up to the Emergency Director Approval block which is blank.

General

References:

EPIP-AD-11, Rev. 22 Task Standards: Approval of the Forms EPIPF-AD-11-01 and EPIPF-AD-11-04 is withheld since the exposure exceeds that allowable for the protection of valuable property.

Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y/Yes below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

NOTE: The Performance Steps of this JPM are arranged to match the layout of procedure EPIP-AD-11.

This procedure provides guidance related to requirements related to Emergency Radiation Controls but is not required to be performed step-by-step. Therefore, the Performance Steps amy be addressed in any order.

Performance Step: 1 EPIP-AD-11, 5.1.1 Critical: No The requirements of the Health Physics Procedures shall be applicable during all radiological emergencies with the following exceptions:

5.1.1.1 Exceptions authorized by the Radiological Protection Director (RPD) or Emergency Director (ED).

5.1.1.2 Exceptions documented and authorized using Emergency Radiation Work Permit, Form EPIPF-AD-11-01.

5.1.1.3 Exceptions outlined in this procedure.

Standard:

  • Recognize the authority of Emergency Director
  • Determine Form EPIPF-AD-11-01 is exception to normal HP Procedures.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 3 of 8

SO-119-JP66A, Review Emergency Exposure Authorization, Rev. A Performance Step: 2 EPIP-AD-11, 5.1.2 Critical: No For RCA entries, if any 10CFR20 dose limit is likely to be exceeded, an Emergency Radiation Work Permit, Form EPIPF-AD-11-01, shall be completed. Otherwise, use an existing Radiation Work Permit (RWP) or fill out a RWP in accordance with NAD-08.03, Radiation Work Permit.

Standard:

Determine that Form EPIPF-AD-11-01 is being used since dose limits are likely to exceed 10CFR20 dose limit(s).

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 EPIP-AD-11, 5.1.3 Critical: No A PRIORITY ENTRY can be used for quick action to expedite the entry of emergency response personnel into the RCA in accordance with EPIP-RET-02D, Emergency Radiation Entry Controls and Implementation and should NOT exceed 10CFR20 dose limits.

Standard:

Determine condition is not PRIORITY ENTRY.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 8

SO-119-JP66A, Review Emergency Exposure Authorization, Rev. A Performance Step: 4 EPIP-AD-11, 5.1.4 Critical: No For any task where an exposure greater than 10CFR20 dose limits is likely, an Emergency Exposure Authorization, Form EPIPF-AD-11-04, shall be completed. All exposures which could exceed 10CFR20 dose limits shall be approved by the ED.

Standard: Determine Form EPIPF-AD-04 is to be completed, and if exposures which could exceed 10CFR20 dose limits, approval by the ED (Performer) is required.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 Form EPIPF-AD-11-04 , Emergency Exposure Authorization Critical: No Emergency Exposure Authorization blocks completed through RPD recommendation Standard:

Determine that blanks are completed for form(s):

  • Individual Name, SS# and age
  • Reason for exposure. [Wording for task involving protection of valuable property.]
  • Estimated Dose values listed TEDE, LDE and SDE/TODE
  • Authorized Emergency Dose values listed. [Values listed are from life-saving section of table 5.1b, EPIP-AD-11.
  • Individual signature and date
  • RPO/Shift HP signature and date Evaluator Note:

Two Form EPIPF-AD-11-04 forms are provided for the two individuals that will be performing the task in plant. Each Form reads the same except for the Individual name, SS# and age. It does not matter which form (or both) is reviewed to determine the error identified in the next PERFORMANCE STEP.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 5 of 8

SO-119-JP66A, Review Emergency Exposure Authorization, Rev. A Performance Step: 6 Form EPIPF-AD-11-04 , Emergency Exposure Authorization Critical: Yes Qualitative evaluation of information.

Standard:

1. Determine values for Authorized Emergency Dose are those for Emergency workers exposure should be controlled below these levels when their mission involves life saving or protection of large populations.
2. Determine task is for mission involves protecting valuable property.
3. Refuse to / does not sign ED Authorization on either Form EPIPF-AD-11-04 since the Authorized Emergency Dose values are greater than the recommended for the task of protecting valuable property.
4. Identify the correct limits for Authorized Emergency Dose from Form EPIPF-AD-11-04 (Emergency Exposure Guidelines: 3) or EPIP-AD-11, Table 5.1b second row.
  • SDE/TODE - 100 Rem (< 100 Rem)

Evaluator Cue:

If Performer identifies error(s) in Authorized Emergency Dose values, but does not identify/report the CORRECT values, What are the proper dose limits?

If Form EPIPF-AD-11-04 reviewed first and Performer indicates NO further action, Continue with review of the Emergency Radiation Work Permit.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 6 of 8

SO-119-JP66A, Review Emergency Exposure Authorization, Rev. A Performance Step: 7 Form EPIPF-AD-11-01 , Emergency Radiation Work Permit Critical: No Emergency Radiation Work Permit blocks completed through RPD Approval.

Standard:

Determine that blanks are completed for form:

  • Date Prepared
  • Effective Dates
  • System No. [33]
  • Estimated Dose
  • Estimated Man-hours
  • Job Description and location [Wording for task involving protection of valuable property.]
  • Assigned Workers Name, TLD Init
  • Contact Radiation
  • Gen Area Radiation
  • Contamination Levels
  • Instrument Used and Serial Number
  • Individual Requirements marked [ Dosimetry, TLD Badge, Coveralls, Hood/Cap, Shoe Covers, Glove Liners, Rubber Gloves]
  • Special Instructions [Action based on condition]
  • Work Supervisor Approval signature
  • RPD Approval signature Evaluator Note:

The following will not be marked or indicated: DCR No., MWR No., Lab Coat, Paper Suit, Plastic Suit, Any Respiratory requirements.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 7 of 8

SO-119-JP66A, Review Emergency Exposure Authorization, Rev. A Performance Step: 8 Form EPIPF-AD-11-01, Emergency Radiation Work Permit Critical: Yes ED Approval Standard:

Emergency Radiation Work Permit not signed for authorization based on review of Form EPIPF-AD-11-04, Emergency Exposure Authorization, errors.

Evaluator Note:

The review of the two Emergency Exposure Authorization forms should occur prior to approval of the Emergency Radiation Work Permit to ensure the ASSIGNED WORKERS are properly identified and authorized.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When the performer has completed review of Forms EPIPF-AD-11-04 and EPIPF-AD-11-01, This JPM is complete.

Stop Time:

Page 8 of 8

JOB PERFORMANCE MEASURE (JPM)

SITE: KPS JPM TITLE: Make protective action recommendations for emergency event escalation (General Emergency with evaluated release.)

JPM NUMBER: SO-119-JP05A REV. D RELATED PRA N/A INFORMATION:

TASK NUMBER(S) / 1190050502 / Make protective action recommendations for emergency event TASK TITLE(S): escalation (General Emergency with evaluated release.)

2.4.38 (CFR 43.5 / 45.11) SRO 4.4 K/A NUMBERS:

2.4.44 (CFR 43.5 / 45.13) SRO 4.4 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: Other: X Lab:

Time for Completion: 12 Minutes Time Critical: Yes Alternate Path / Faulted: No TASK APPLICABILITY: SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson 03/30/2009 Instructor Date Validated by: Andy Fahrenkrug 03/24/2009 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans Training Supervisor Date Page 1 of 10

SO-119-JP05A, Make protective action recommendations for emergency event escalation (General Emergency with evaluated release.), Rev. D NOTE:

When ready to begin covering Initial Conditions, provide the examinee with the following:

  • Completed Form EPIPF-AD-07-01 for SITE AREA EMERGENCY If performed in the Simulator, DO NOT provide the following, otherwise also provide:
  • Copy of EPIP-AD-02
  • Copy of EPIP-AD-19
  • Blank copy of Form EPIPF-CR-01-01 A blank Form EPIPF-AD-07-01 is included with JPM but should only be provided when the examiner has located the forms.

Page 2 of 10

SO-119-JP05A, Make protective action recommendations for emergency event escalation (General Emergency with evaluated release.), Rev. D INITIAL CONDITIONS:

  • You are the Shift Manager, acting as the Emergency Director.
  • A Steam Generator Tube Rupture has occurred in the S/G B. One Safety Relief Valve on S/GB has opened and cannot be closed. Additionally, the RCS coolant has high activity due to suspected fuel damage prior to the event.
  • The steam release rate is 3.5 x 105 lbm/hr.
  • The current Emergency classification is SITE AREA EMERGENCY with Planned Protective Action Recommendation of NONE.
  • 10 minutes ago the RP Supervisor has provided the verified initial dose estimation for the next 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

3/4 Total Effective Dose Equivalent - 1.5 REM up to 1.7 miles down wind.

3/4 Thyroid dose - 6 REM up to 2.9 miles down wind 3/4 Projected Maximum dose to Emergency Team workers is expected to be 1.7 REM TEDE and 6.8 REM to all other organs.

  • The event classification has just been changed to a General Emergency (RG1.2) based on the dose assessments rates in the EAL Matrix.
  • Wind direction is currently from 128 degrees. The wind speed is currently 20 MPH, Stability class B.

Adverse meteorological conditions do not exist. Weather conditions are clear with no changes expected over the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

  • No other emergencies in the local area
  • EPIP-AD-02 and EPIPF-CR-01-01 are in use, and have directed you to EPIP-AD-19, Determining Protective Action Recommendations.
  • EPIP-AD-19 step 5.1.4 is being performed.
  • Radiation Monitors R-40 and R-41 are reading 100 R/hr and 110 R/hr, respectively.
  • Core Exit Thermocouple maximum temperatures are 600ºF.

THIS TASK IS TIME CRITICAL.

INITIATING CUES:

Complete form EPIPF-AD-07-01 including determination of a default PAR as directed in EPIP-AD-19 for the given conditions.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Form NTP-6331 Rev. A Date: JAN 19 2006 Page 3 of 10

SO-119-JP05A, Make protective action recommendations for emergency event escalation (General Emergency with evaluated release.), Rev. D JPM PERFORMANCE INFORMATION Required Materials: EPIP-AD-19 EPIP-AD-02 Form EPIPF-AD-07-01 (Completed & filled out for SAE)

Form EPIPF-AD-07-01 (Blank)

Form EPIPF-CR-01-01 Emergency Action Level Matrix Rev 4 General

References:

Emergency Action Level Matrix Rev 4 EPIP-AD-02, Emergency Class Determination, Rev. AS (45)

EPIP-AD-19, Determining Protective Action Recommendations, Rev. 26 Form EPIPF-AD-07-01 Rev 28, Event Notice-NARS Form Form EPIPF-CR-01-01 Rev. 5, EMERGENCY DIRECTOR (CR) CHECKLIST Task Standards: Complete Form EPIPF-AD-07-01 including recommended PAR, Evacuate ALL sectors (360º) out to 2 mile and Evacuate downwind sectors P,Q,R out to 5 miles, within 12 min (as per EPIP-AD-19, default PAR for non-adverse meteorology.)

Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Obtain form EPIP-AD-07-01 EVENT NOTIFICATION Nuclear Accident Critical: Yes Reporting System Form (NARS)

Standard: Obtain correct form Evaluator Note: When forms are located, Provide copy of blank EPIPF-AD-07-01 Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 4 of 10

SO-119-JP05A, Make protective action recommendations for emergency event escalation (General Emergency with evaluated release.), Rev. D Performance Step: 2 Box 1: Check box for Emergency Classification Change Critical: No Standard: Box 1: Check box for Emergency Classification Change.

Evaluator Note: Box 1 IS NOT graded during EP exercises. Reference DNAP-2605 Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 Box 2: Check Box for Status Critical: Yes Standard: Box 2: Either box checked (Box for Drill [B] OR Box for Actual Event [A])

Evaluator Note: Box 2 IS graded during EP exercises and must be marked [B]. Reference DNAP-2605 Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 Box 3: Check Box for Kewaunee Critical: No Standard: Box 3: Check Box for Kewaunee Evaluator Note: Box 3 IS NOT graded during EP exercises. Reference DNAP-2605 Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 5 of 10

SO-119-JP05A, Make protective action recommendations for emergency event escalation (General Emergency with evaluated release.), Rev. D Performance Step: 5 Box 4: Check box for General Emergency Critical: Yes Standard: Box 4: Check box for General Emergency Evaluator Note: Box 4 IS graded during EP exercises. Reference DNAP-2605 Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 6 Box 5: Check box [A] Classification Critical: Yes Box 5: Enter JPM start time and current date for classification Box 5: Enter RG1.2 for EAL#

Standard: Box 5: Check box [A] Classification (c) Box 5: Enter JPM Start time and current date for Classification (c) Box 5: Enter RG1.2 for EAL#

CUE If asked what time to enter. Use the START TIME of the JPM and TODAYs DATE.

Evaluator Note: The following items in Box 5 ARE graded during EP exercises. Reference DNAP-2605:

  • Classification Time
  • Classification Date EAL #
  • Par Change Time
  • Par Change Date
  • Recovery/Termination Time
  • Recovery/Termination Date Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 6 of 10

SO-119-JP05A, Make protective action recommendations for emergency event escalation (General Emergency with evaluated release.), Rev. D Performance Step: 7 Box 6: Check box [B2] OCCURRING Critical: Yes Standard: Box 6: Check box [B2] OCCURRING Evaluator Note: Box 6 IS graded during EP exercises. Reference DNAP-2605 Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 8 Box 7: Check box [B] AIRBORNE Critical: No Standard: Box 7: Check box [B] AIRBORNE Evaluator Note: Box 7 IS NOT graded during EP exercises. Reference DNAP-2605 Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 9 Complete block 8, Wind Direction.

Critical: Yes Standard: (c) 1. Write 128 in FROM Blank in Block 8.

2. Circle P Q R in Downwind Sector section in Block 8.

Evaluator Note: Box 8 wind direction IS graded during EP exercises. Minor discrepancies in wind direction need not count as a missed notification provided the discrepancy would not result in an incorrect PAR. Reference DNAP-2605 Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 7 of 10

SO-119-JP05A, Make protective action recommendations for emergency event escalation (General Emergency with evaluated release.), Rev. D Performance Step: 10 Complete block 9. Wind Speed.

Critical: Yes Standard: (c) 1. Write value 20 in Miles/Hr blank in Block 9.

2. Circle B for Stability Class in Block 9.

Evaluator Note: Box 9 wind speed value IS graded during EP exercises. Minor discrepancies in wind speed need not count as a missed notification provided the discrepancy would not result in an incorrect PAR. Reference DNAP-2605 Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 11 Reference EPIP-AD-19 Protective Action Guidelines for PAR determination.

Critical: No Standard: Refer to EPIP-AD-19 Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 12 EPIP-AD-19, step 5.1.4.b Critical: No Determine Initial Protective Action Recommendation.

Standard: Determine for General Emergency, with NO adverse meteorology, is

  • Evacuate ALL sectors (360º) out to __2__ miles, AND
  • evacuate downwind sectors __P, Q, R__ out to _ 5 __ miles Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 8 of 10

SO-119-JP05A, Make protective action recommendations for emergency event escalation (General Emergency with evaluated release.), Rev. D Performance Step: 13 Complete Block 10, Protective Action Recommendations Critical: Yes Standard: (c) 1. Check (B) EVACUATE BOX in Block 10 (c) 2. On the line with box (B) Write ALL in the blank before the word SECTORS.

(c) 3. On the line with box (B) Write 2 in the blank before the word MILES.

(c) 4. On the line below box (B) but above Box (C) write P, Q, R in the blank before the word OUT.

(c) 5. On the line below box (B) but above Box (C) write 5 in the blank before the word MILES.

Evaluator Note: All of Box 10 IS graded during EP exercises. Reference DNAP-2605 Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 14 Complete EPIPF-AD-07-01, Block 11 ADDITIONAL INFORMATION.

Critical: Yes Standard: (c) 1. Block contains general description of event that accurately gives conditions.

2. Initial PAR.

(c)

Evaluator Note: Box 11 IS graded during EP exercises. There must be a description of the event which accurately describes the event and can be understood by recipient(s). Reference DNAP-2605.

If classifying an event, THEN at a minimum briefly describe the EAL being implemented (refer to EAL initiating Condition for guidance). IF making a PAR change, THEN write NONE PAR Change or other applicable information related to the PAR. Ref EPIPF-07-01 page 3.

Wording does not have to exactly match as long as the EVENT and PAR are accurately described.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 9 of 10

SO-119-JP05A, Make protective action recommendations for emergency event escalation (General Emergency with evaluated release.), Rev. D Performance Step: 15 Complete Approval Signature EPIPF-AD-07-01, EVENT NOTICE Critical: No Standard: 1. Sign Approval Signature blank

2. Write current date and time in Date/Time Approved blanks
3. Circle Emergency Director.

Evaluator Note: The approval signature, date, time and circle of the emergency director IS NOT graded during EP exercises. Reference DNAP-2605 Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: THIS COMPLETES THIS JPM Stop Time:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 10 of 10

JOB PERFORMANCE MEASURE (JPM)

SITE: KPS JPM TITLE: Operate Safety Injection System in the Recirc Mode JPM NUMBER: RO-E01-JP041 REV. D RELATED PRA INFORMATION:

TASK NUMBER(S) / E010040501 / Perform a Transfer to Containment Sump Recirculation TASK TITLE(S):

K/A NUMBERS: 011EA1.11, RO/SRO IMP 4.2/4.2 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 20 Minutes Time Critical: YES Alternate Path / Faulted: YES TASK APPLICABILITY: RO/SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /s 03/27/09 Instructor Date Validated by: Stephen Johnson /s 03/24/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /s Training Supervisor Date Page 1 of 13

RO-E01-JP041, Operate Safety Injection in the Recirc Mode, Rev. D INITIAL CONDITIONS:

1. You are the Reactor Operator.
2. A large break LOCA has occurred.
3. RCS pressure is at Containment pressure.
4. RWST level is at approximately 27%.

THIS JPM CONTAINS TIME CRITICAL ELEMENTS.

INITIATING CUES (IF APPLICABLE):

You are directed by the Unit Supervisor to align SI system for recirculation using ES-1.3, Transfer to Containment Sump Recirculation, starting at step 12.

INFORM the evaluator when you have completed the task.

Do you have any questions before we begin? - Answer any questions Page 2 of 13

RO-E01-JP041, Operate Safety Injection in the Recirc Mode, Rev. D JPM PERFORMANCE INFORMATION Required Materials: ES-1.3 marked complete through and including Step 11.

General

References:

GNP-05.16.06, Rev. 7 (ATTACHMENT A)

ES-1.3 Transfer to Containment Sump Recirculation, Rev. 31 Task Standards: Train A RHR transferred to containment sump recirculation and flow established.

Start Time:

NOTE: Critical steps are marked with a Yes below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Step 12. VERIFY Train A Injection Flow:

Critical No a. SI Pump A - Running and Pump Amps Indicate Flow or

b. RHR Pump A - Running and Flow Indicated
  • FI-626 Standard: VERIFY SI pump A, red light ON, green light OFF.

AND VERIFY SI pump A current meter indicates amps.

OR VERIFY RHR pump A, red light ON, green light OFF.

AND VERIFY RHR flow meter FI-626 indicates flow.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 Step 13.a Critical No ALIGN Train B RHR Pump for Recirculation:

CHECK Containment Sump B Supply to RHR Pump B - OPEN

  • SI-350B Standard: CHECK red light ON, green light OFF.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 3 of 13

RO-E01-JP041, Operate Safety Injection in the Recirc Mode, Rev. D Performance Step: 3 Step 13.b Critical No ALIGN Train B RHR Pump for Recirculation:

CLOSE RWST Supply to RHR Pump B

  • SI-300B Standard: POSITION control switch for SI-300B to CLOSE.

VERIFY green light ON, red light OFF.

Evaluator Note: Step is NOT critical since Train B RHR Pump fails to start later.

The approximate stroke time for this valve is 2 minutes.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 Step 13.c Critical No ALIGN Train B RHR Pump for Recirculation DO NOT CONTINUE until RWST Supply to RHR Pump B is closed

  • SI-300B Standard: Do not continue until SI-300B is closed with green light ON and red light OFF.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 13

RO-E01-JP041, Operate Safety Injection in the Recirc Mode, Rev. D Performance Step: 5 Step 13.d Critical No ALIGN Train B RHR Pump for Recirculation:

OPEN Containment Sump B Supply to RHR Pump B

  • SI-351B Standard: Take SI-351B to OPEN.

VERIFY red light ON, green light OFF.

Evaluator Note: Step is NOT critical since Train B RHR Pump fails to start later.

The approximate stroke time for this valve is 2 minutes.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 6 Step 13.e Critical No ALIGN Train B RHR Pump for Recirculation:

CLOSE RHR Heat Exchanger B Flow CV

  • RHR-8B Standard: POSITION RHR-8B Hand Station flow controller to 100% CLOSE.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 5 of 13

RO-E01-JP041, Operate Safety Injection in the Recirc Mode, Rev. D Performance Step: 7 Step 13.f Critical No ALIGN Train B RHR Pump for Recirculation:

START RHR Pump B Standard: POSITION RHR pump B C/S to START/AUTO.

OBSERVE RHR Pump B red light OFF, green light ON and white light ON.

Perform Response Not Obtained and go to step 16 for aligning Train A RHR using alternate method.

Evaluator Note: Starting RHR Pump is NOT critical but attempting to start does provide the operator the CUE to apply RNO for aligning Train A Alternate Path.

Performance: SATISFACTORY UNSATISFACTORY Comments:

NOTE: The BOOTH OPERATOR will check RWST level and when directed by EVALUATOR (TIME COMPRESSION statement completed), INSERT Remote Function SI131 (RWST Level) set to 10%. When value has changed to 10%, then DELETE SI131.

Performance Step: 8 Step 16.a Critical No ALIGN Train A RHR Using Alternate Method:

TIME CRITICAL START: CHECK RWST Level - LESS THAN or EQUAL to 10%

Standard: Checks RWST level indication 10%.

When RWST level indication is 10%, continues actions of procedure.

Evaluator Note:

The TIME CRITICAL portion of the JPM begins at the point when RWST level is less than or equal to 10%. Record the time above when the OPERATOR acknowledges that RWST is less than nor equal to 10%.

Evaluator Cue: After operator notes that RNO directs DO NOT CONTINUE then inform operator, TIME COMPRESSION - RWST level is now 10%.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 6 of 13

RO-E01-JP041, Operate Safety Injection in the Recirc Mode, Rev. D Performance Step: 9 Step 16.b Critical No ALIGN Train A RHR Using Alternate Method:

VERIFY SI Pump A - Running Standard: Checks SI pump A running:

Red light ON, Green light OFF.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 10 Step 16.c Critical No ALIGN Train A RHR Using Alternate Method:

STOP SI Pump B Standard: Verify SI pump B stopped.

Green light ON, Red light OFF Evaluator Note: SI Pump B was stopped at Step 4.b Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 7 of 13

RO-E01-JP041, Operate Safety Injection in the Recirc Mode, Rev. D Performance Step: 11 Step 16.d Critical Yes ALIGN Train A RHR Using Alternate Method:

STOP both RHR Pumps

  • RHR Pump B Standard: Position RHR pump A C/S to Stop/Auto.

Green light ON, Red light OFF.

Evaluator Note: Stopping RHR Pump A is critical prior to performing Step 16.g where the suction from the RWST to RHR Pump A is isolated. If NOT stopped Pump would be operating without adequate suction source.

RHR Pump B was stopped at Step 4.c and failed to start at Step 13.f.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 12 Step 16.e Critical No ALIGN Train A RHR Using Alternate Method:

STOP Both ICS pumps

  • ICS Pump B Standard: Position ICS pump A C/S in Stop/Auto.

Green light ON, Red light OFF.

Evaluator Note: This action maximizes time to reaching RWST level less than 4%.

ICS Pump B was stopped at Step 8.b.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 8 of 13

RO-E01-JP041, Operate Safety Injection in the Recirc Mode, Rev. D Performance Step: 13 Step 16.f Critical No ALIGN Train A RHR Using Alternate Method:

CHECK Containment Sump B Supply to RHR Pump A - OPEN

  • SI-350A Standard: VERIFY red light ON, green light OFF.

Evaluator Note: SI-350A was opened in Step 7.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 14 16.g Critical Yes ALIGN Train A RHR Using Alternate Method:

CLOSE RWST Supply to RHR Pump A

  • SI-300A Standard: POSITION control switch for SI-300A to CLOSE.

VERIFY green light ON, red light OFF.

Evaluator Note: The approximate stroke time for this valve is 2 minutes.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 15 Step 16.h Critical No ALIGN Train A RHR Using Alternate Method:

DO NOT CONTINUE until RWST Supply TO RHR Pump A is closed

  • SI-300A Standard: Do not continue until SI-300A is closed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 9 of 13

RO-E01-JP041, Operate Safety Injection in the Recirc Mode, Rev. D Performance Step: 16 Step 16.i Critical Yes ALIGN Train A RHR Using Alternate Method:

OPEN Containment Sump B Supply to RHR Pump A

  • SI-351A Standard: Position control switch for SI-351A to OPEN.

VERIFY red light ON, green light OFF.

Evaluator Note: The approximate stroke time for this valve is 2 minutes.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 17 Step 16.j Critical No ALIGN Train A RHR Using Alternate Method:

CLOSE RHR Heat Exchanger A Flow CV

  • RHR-8A Standard: POSITION RHR-8A Hand Station flow controller to 100% CLOSE.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 10 of 13

RO-E01-JP041, Operate Safety Injection in the Recirc Mode, Rev. D Performance Step: 18 Step 16.k Critical Yes ALIGN Train A RHR Using Alternate Method:

START RHR Pump A Standard: POSITION RHR pump A C/S to START/AUTO.

  • VERIFY RHR Pump A red light ON, green light OFF.
  • VERIFY RHR Pump A Motor Current meter pegs high then returns to nominal amps. (Not critical)

OR

  • VERIFY RHR Pump A Disch Press meter PI-626 indicates 100-175 psig.

(Not critical)

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 19 Step 17.a Critical No VERIFY Train A RHR Recirculation Flow CHECK RCS pressure - LESS THAN 270 PSIG [300 PSIG]

Standard: OBSERVE RCS WR pressure indicator PI-420 or Yokogowa recorder 42556 pressure less than 270 psig.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 11 of 13

RO-E01-JP041, Operate Safety Injection in the Recirc Mode, Rev. D Performance Step: 20 Step 17.b Critical Yes VERIFY Train A RHR Recirculation Flow TIME CRITICAL STOP: TROTTLE RHR Heat Exchanger A Flow CV as necessary to maintain RHR recirculation flow at 1500 GPM Standard: ESTABLISH at least 500 gpm recirculation flow with RHR pump A:

  • Throttle open RHR-8A.
  • Maintain flow at least 1500 gpm. (Not critical)

Time from RWST level at 10% to RHR flow greater than or equal to 500 gpm is equal to or less than 8.7 minutes.

Evaluator Note:

The TIME CRITICAL portion of the JPM ends at the point when RHR recirculation flow is established at greater than 500 gpm. Record the time above when the OPERATOR acknowledges that RWST is less than nor equal to 10%. The difference between this time and that recorded in Performance Step 8 must be equal to or less than 8.7 minutes (8 min, 42 sec). Time Stop (Step 21) ________ -

Time Start (Step 8) ___________ = _______________

Using ES-1.1 ATTACHMENT A, Required SI Flow Versus Time After Trip, at 30 minutes following the trip (0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) 230 gpm of SI flow is required for heat removal. Based upon this and the range for RHR flow indicator (FI-626), 500 gpm is selected as the value for minimum ECCS recirculation flow, while the procedure directs establishing 1500 gpm flow.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 12 of 13

RO-E01-JP041, Operate Safety Injection in the Recirc Mode, Rev. D Performance Step: 21 Step 17.c Critical No GO TO Step 20 Standard: Go to Step 20.

Evaluator Note: Step 20 directs, CHECK Running RHR PUMPS - NOT CAVITATING.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When transition has been made to Step 20, Check Running RHR PUMPS - NOT CAVITATING, CUE: This JPM is complete.

Stop Time:

Page 13 of 13

JOB PERFORMANCE MEASURE (JPM)

SITE: Kewaunee Power Station JPM TITLE: Depressurize the RCS during Cooldown JPM NUMBER: RO-036-JP25A REV. B RELATED PRA INFORMATION:

TASK NUMBER(S) / 0360250101 / Operate the Pressurizer Pressure Control System to control TASK TITLE(S): pressure during a cooldown K/A NUMBERS: 010A1.07 RO/SRO Imp 3.7 / 3.7 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 10 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: RO/SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /s 03/27/09 Instructor Date Validated by: Stephen Johnson /s 03/24/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /s Training Supervisor Date Page 1 of 5

RO-036-JP25A, Depressurize the RCS during Cooldown, Rev. B INITIAL CONDITIONS:

1. You are the Reactor Operator.
2. The plant has begun a cooldown and depressurization from HOT SHUTDOWN conditions.
3. RCS pressure is to be maintained within limitations of RD-11.1 during cooldown by adjusting PRZR Spray Master Controller setpoint as continuous action directed in Step 5.2.6 of OP-KW-GOP-203, SHUTDOWN FROM HOT SHUTDOWN TO RHR.
4. OP-KW-GOP-203 is currently in progress at Step 5.2.17, INITIATE RCS depressurization to 925-975 psig.

THIS JPM IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

The US directs you to continue the RCS depressurization by performing Steps 5.2.17 and 5.2.18.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Page 2 of 5

RO-036-JP25A, Depressurize the RCS during Cooldown, Rev. B JPM PERFORMANCE INFORMATION Required Materials:

GOP-203, marked up through step 5.2.16, including Prerequisites and Precautions and Limitations RD 11.1.1 graph General

References:

OP-KW-GOP-203, Rev. 4 RD 11.1.1 Rev. 04/30/07 Task Standards:

RCS pressure between 1950 and 1975 psig with safety injection blocked AND RCS pressure and temperature maintained within limits of RD 11.1.1.

Start Time:

NOTE: Critical steps are marked with a Y or Yes below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 GOP-203, Step 5.2.17 Critical Yes INITIATE RCS depressurization to 925-975 psig.

Standard: Lower PRZR Spray Master Controller setpoint to lower PRZR (RCS) pressure.

Evaluator Note:

The operator should rotate the setpoint dial clockwise to lower the desired pressure setpoint, and verify PS-1B opens to lower PRZR pressure.

Pressurizer pressure may be monitored using the recorder 42301 and/or indicators PI-429, PI-430, PI-431 and PI-449A until PRZR pressure reaches 1700 psig.

Below 1700 psig, wide range RCS pressure is monitored on PI-419, PI-420 and/or recorder 42556.

The rate of pressure decrease is NOT significant as long as temperature-pressure is maintained within limits of RD11.1.1.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 3 of 5

RO-036-JP25A, Depressurize the RCS during Cooldown, Rev. B Performance Step: 2 GOP-302, Step 5.2.18.a Critical No WHEN RCS pressure is 1950-1975 psig, THEN PERFORM the following to block safety injection:

VERIFY permissive status light 44905 1101, Pressurizer Perm Block SI, ON.

Standard: Check Permissive Status Light 44905-1101, PRESSURIZER PERM BLOCK SI, lit.

Evaluator Note: Annunciator 47024-E, SI ACMTR A/B ISOLATION VALVE ABNORMAL, alarms when RCS pressure falls below 2000 psig (SER0919 - LOCK OPEN ACCUMULATOR VALVES). This is an expected alarm for RCS conditions.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 GOP-302, Step 5.2.18.b Critical Yes WHEN RCS pressure is 1950-1975 psig, THEN PERFORM the following to block safety injection:

POSITION Safety Injection Train A Block/Unblock switches to BLK.

Standard: Safety Injection Train A Block/Unblock control switch taken to BLK position and released to neutral (center) position.

Evaluator Note: The Safety Injection Train A/B Block/Unblock switches are on MCC just above the ICS section.

BOTH switches MUST be operated to BLK in order to satisfactorily block the low PRZR pressure SI and low steam line pressure SI signals.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 5

RO-036-JP25A, Depressurize the RCS during Cooldown, Rev. B Performance Step: 4 GOP-302, Step 5.2.18.c Critical Yes WHEN RCS pressure is 1950-1975 psig, THEN PERFORM the following to block safety injection:

POSITION Safety Injection Train B Block/Unblock switches to BLK.

Standard: 1. Safety Injection Train B Block/Unblock control switch taken to BLK position and released to neutral (center) position.

2. Pressurizer SI signal BLOCKED when Permissive Status Light 44905-1102, PRESSURIZER SI BLOCKED after BOTH Safety Injection Block /Unblock switches operated.

Evaluator Note: The Safety Injection Train A/B Block/Unblock switches are on MCC just above the ICS section.

BOTH switches MUST be operated to BLK in order to satisfactorily block the low PRZR pressure SI and low steam line pressure SI signals.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 GOP-302, Step 5.2.18.d Critical No WHEN RCS pressure is 1950-1975 psig, THEN PERFORM the following to block safety injection:

VERIFY permissive status light, 44905 1102, Pressurizer SI Blocked, ON.

Standard: Checks Permissive Status Light 44905-1102, PRESSURIZER SI BLOCKED, lit.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When RCS pressure is lowered to between 1950 and 1975 psig and actions to block Pressurizer SI signal have been taken per GOP-302 step 5.2.18: This JPM is complete.

Stop Time:

Page 5 of 5

JOB PERFORMANCE MEASURE (JPM)

SITE: Kewaunee Power Station JPM TITLE: Shutdown RHR for At Power Operation JPM NUMBER: RO-034-JP06A REV. B RELATED PRA N/A INFORMATION:

TASK NUMBER(S) / 0340060101 / Shutdown the Residual Heat Removal System for At Power TASK TITLE(S): Operation 004A4.01 RO/SRO Imp: 3.6 / 3.4 K/A NUMBERS:

2.1.23 RO/SRO Imp: 4.3 / 4.4 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 15 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: RO/SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /s 03/27/09 Instructor Date Validated by: Stephen Johnson /s 03/24/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /s Training Supervisor Date Page 1 of 11

RO-034-JP06A, Shutdown RHR for At Power Operation, Rev. B INITIAL CONDITIONS:

  • You are the Reactor Operator.
  • The plant is heating up from COLD SHUTDOWN to HOT SHUTDOWN.
  • RHR is being shutdown as directed by OP-KW-GOP-103, STARTUP FROM RHR TO HOT SHUTDOWN (Step 5.3.1.b), and in accordance with N-RHR-34, Residual Heat Removal System Operation.
  • N-RHR-34 sections 2.0, Precautions and Limitations and 3.0, Initial Conditions have been reviewed and completed.

THIS JPM IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

The US directs you to shutdown the RHR system using N-RHR-34, Section 4.3, Shutdown of RHR System for At Power Operation.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Page 2 of 11

RO-034-JP06A, Shutdown RHR for At Power Operation, Rev. B JPM PERFORMANCE INFORMATION Required Materials: N-RHR-034 with section 2.0 marked and all of section 3.0 initialed.

GOP-103 marked-up through step 5.3.1.a, including Prerequisites and Precautions and Limitations.

General

References:

N-RHR-034, Rev. 71 OP-KW-GOP-103, Rev. 2 Task Standards:

RHR aligned for recirculation cooldown with RHR-8A and RHR-8B open and RHR-11 closed.

Start Time:

NOTE: Critical steps are marked with a Yes below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 N-RHR-34, Step 4.3.1 Critical No (CR/L) CLOSE the following:

  • RHR-210, RHR/CVC Inlet Isolation
  • RHR-211, RHR/CVC Outlet Isolation Standard:

Contact AO to close RHR-210 and RHR-211.

Receive report from AO that RHR-210 and RHR-211 are closed.

Initial 1st blank in INITIALS column.

Evaluator Note:

Closing these valves isolates the 2 in. line from RHR Hx A outlet to CVCS letdown line upstream of the LTDN Hx (RHR Cleanup).

RHR-210 and RHR-211 were previously closed during performance of OP-KW-GOP-102 at step 5.5.7, when establishing a bubble in the PRZR.

Evaluator Cue:

As AO; Acknowledge request. [TIME COMPRESSION] Report back that RHR-210 and RHR-211 are closed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 3 of 11

RO-034-JP06A, Shutdown RHR for At Power Operation, Rev. B Performance Step: 2 N-RHR-34, Step 4.3.2 Critical No STATION an operator at Component Cooling Hx to monitor outlet temperature.

Standard: Contact AO to monitor CCW Hx outlet temperature.

Evaluator Cue: As AO, acknowledge request.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 N-RHR-34, Step 4.3.3 Critical Yes CLOSE the following:

  • RHR-8A/CV-31114, RHR Flow Control Hx A Outl
  • RHR-8B/CV-31115, RHR Flow Control Hx B Outl Standard: RHR-8A controller dial rotated fully counter-clockwise to 100 position, RHR-8A controller output indicator pointer is at CLOSE (100) indication.

AND RHR-8B controller dial rotated fully counter-clockwise to 100 position, RHR-8B controller output indicator pointer is at CLOSE (100) indication.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 11

RO-034-JP06A, Shutdown RHR for At Power Operation, Rev. B Performance Step: 4 N-RHR-34, Step 4.3.4 Critical Yes POSITION RHR-101/CV-31116, RHR Flow Control Bypass to MAN.

1. ADJUST RHR-101 to 5-10% OPEN.

Standard: Check RHR-101 controller switch in MAN.

RHR-101 output meter reads at or between 5 (second mark from left) and 10 (third mark from left).

Evaluator Note: RHR-101 is normally operated in MAN.

Annunciator 47021-G, RHR TO RCS COOLDOWN FLOW LOW, may alarm as RHR flow falls below 1250 gpm. This is an expected alarm for these plant conditions.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 N-RHR-34, Step 4.3.5 Critical No IF both RHR Pumps are running, THEN STOP one RHR Pump as follows:

Standard: Determine both RHR Pumps running and mark APPLIES.

Evaluator Cue: As Unit Supervisor: RHR Pump A is to remain running. Stop RHR Pump B Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 5 of 11

RO-034-JP06A, Shutdown RHR for At Power Operation, Rev. B Performance Step: 6 N-RHR-34, Step 4.3.5.1 Critical No IF both RHR Pumps are running, THEN STOP one RHR Pump as follows:

IF RHR Pump A is operating AND is NOT required, THEN PERFORM the following:

Standard: Determine step does NOT apply and mark NA.

Evaluator Cue: (If not given before), As Unit Supervisor: RHR Pump A is to remain running. Stop RHR Pump B.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 N-RHR-34, Step 4.3.5.2 Critical No IF both RHR Pumps are running, THEN STOP one RHR Pump as follows:

IF RHR Pump B is operating AND is NOT required, THEN PERFORM the following:

Standard: Determine step applies and mark APPLIES.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 6 of 11

RO-034-JP06A, Shutdown RHR for At Power Operation, Rev. B Performance Step: 8 N-RHR-34, Step 4.3.5.2.a Critical Yes IF both RHR Pumps are running, THEN STOP one RHR Pump as follows:

IF RHR Pump B is operating AND is NOT required, THEN PERFORM the following:

POSITION Residual Heat Removal Pump B control switch to STOP/AUTO.

Standard: Take RHR Pump B control switch to STOP position and allow to return to AUTO position.

Observe RHR Pump B red light OFF; green light lit.

Evaluator Note:

Operator may also check other indications for pump stopping such as amps at ZERO (MTR CURRENT 41336); May also observe SI ACTIVE Status Light 44910-0207, RHR PUMP B ON, NOT lit Annunciator 47021-G, RHR TO RCS COOLDOWN FLOW LOW, may alarm (reflash) as RHR flow falls below 1250 gpm. This is an expected alarm for these plant conditions.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 7 of 11

RO-034-JP06A, Shutdown RHR for At Power Operation, Rev. B Performance Step: 9 N-RHR-34, Step 4.3.5.2.b Critical No IF both RHR Pumps are running, THEN STOP one RHR Pump as follows:

IF RHR Pump B is operating AND is NOT required, THEN PERFORM the following:

(CR/L) IF Pump Pit Fan Coil Unit is operating, THEN STOP RHR Pump B Pump Pit Fan Coil Unit.

Standard: Direct AO to locally stop RHR Pump B Pump Pit Fan Coil Unit.

Observe RHR Pump B Pump Pit Fan Coil Unit green light lit; red light OFF on MCC; and/or observe SI ACTIVE Status Light 44910-0307, RHR PUMP FAN COIL B ON, NOT lit.

Initial 1st blank in INITIALS column. (Not Critical)

Evaluator Note:

The BOOTH OPERATOR will stop RHR Pump B Pump Pit FCU by entering REMOTE FUNCTION CH104 (to TOGGLE then back to AUTO).

Evaluator Cue: As AO acknowledge and report stopping RHR Pump B Pump Pit Fan Coil Unit.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 10 N-RHR-34, Step 4.3.6 Critical No IF solid, THEN REDUCE LD-10/CV-31099 Letdown Cont Pressure setpoint to maintain RCS NR Pressure (PI-420).

Standard: Determine step does NOT apply and mark NA.

Evaluator Note: The operator may check recorder 42302 and PRZR level instruments LI-426, LI-427, LI-428 to determine PZRZ liquid level does exist with a stem bubble.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 8 of 11

RO-034-JP06A, Shutdown RHR for At Power Operation, Rev. B Performance Step: 11 N-RHR-34, Step 4.3.7 Critical Yes CLOSE RHR-11/MV-32118, RHR Discharge To RCS Loop B.

Standard: Take RHR-11 control switch to CLOSE position and release to center.

Observe RHR-11 Green light lit; red light out.

Evaluator Note: In accordance with the NOTE prior to the step, the Operator may observe an increase in letdown flow as indicated on FI-134. (See next Performance Step.)

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 12 N-RHR-34, Step 4.3.7 NOTE Critical No Closing RHR-11 will cause an increase in letdown flow.

Standard: Adjust LD-10 setpoint upward (increase pressure) to lower flow and maintain Przr level.

Evaluator Note: Annunciator 47045-K, LETDOWN FLOW HIGH, will alarm if letdown flow rises above 90 gpm.

The operator may adjust LD-10 prior to closing RHR-11 to prevent exceeding 90 gpm letdown flow.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 9 of 11

RO-034-JP06A, Shutdown RHR for At Power Operation, Rev. B Performance Step: 13 N-RHR-34, Step 4.3.8 Critical Yes OPEN the following:

  • RHR-8A
  • RHR-8B Standard: RHR-8A controller dial rotated fully clockwise to 0 position, RHR-8A controller output indicator pointer is at OPEN (0) indication.

AND RHR-8B controller dial rotated fully clockwise to 0 position, RHR-8B controller output indicator pointer is at OPEN (0) indication.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 14 N-RHR-34, Step 4.3.9 Critical No IF RHR System boron concentration has NOT been obtained within the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, THEN REQUEST Chemistry obtain boron concentration for RHR System.

Standard: Determine RHR System boron concentration NOT required to be obtained and mark NA.

Evaluator Cue: As Unit Supervisor: Chemistry had sampled the RHR system on the previous shift (less than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />).

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 10 of 11

RO-034-JP06A, Shutdown RHR for At Power Operation, Rev. B Performance Step: 15 N-RHR-34, Step 4.3.10 Critical No RECIRCULATE RHR System until RHR Heat Exchanger Outlet Temperatures are less than 200°F (TI-12075 and 12076 locally).

Standard: Direct AO to locally monitor RHR Hx Outlet Temperatures (for reading less than 200ºF)

Determine system needs to be in recirculation.

Evaluator Cue: As AO acknowledge request. (If directed to provide local temperature readings:

[TIME COMPRESSION - 5 minutes]: TI-12075 reads 275ºF and TI-12076 reads 280ºF.)

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When the operator determines recirculation is to be continued until RHR Hx Outlet temperatures cool less than 200°F: This JPM is complete.

Stop Time:

Page 11 of 11

JOB PERFORMANCE MEASURE (JPM)

SITE: Kewaunee Power Station JPM TITLE: Rapid Power Reduction to Approximately 570 MWe JPM NUMBER: RO-054-JP061 REV. D RELATED PRA None INFORMATION:

TASK NUMBER(S) / 0540060101 / Change Turbine and Generator Load TASK TITLE(S):

K/A NUMBERS: 045 2.1.23 RO 3.9 / SRO 4.0 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: x EVALUATION LOCATION: In-Plant: Control Room:

Simulator: x Other:

Lab:

Time for Completion: 15 Minutes Time Critical: NO Alternate Path / Faulted: YES TASK APPLICABILITY: RO/SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /s 03/27/09 Instructor Date Validated by: Stephen Johnson /s 03/24/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /s Training Supervisor Date Page 1 of 6

RO-054-JP061, Rapid Power Reduction to Approximately 570 MWe, Rev. D INITIAL CONDITIONS:

1. You are the BOP Operator
2. The turbine is selected to TURBINE MANUAL due to cycling noted on the turbine control valves when in OPER AUTO.
3. The Unit Supervisor has directed a load backdown to LESS THAN OR EQUALTO 570 MWe at 1% per minute.
4. Actions of OP-KW-AOP-GEN-002, Rapid Power Reduction, are in progress.
5. AOP-GEN-002 Steps 1 through 9 have been completed.
6. A normal boration using AOP-GEN-002 Attachment G has been completed and Tave is being monitored by the RO.
7. Initial Tave was 571.7ºF.

THIS JPM IS NOT TIME CRITICAL.

INITIATING CUES:

You have been directed to complete the load reduction to LESS THAN OR EQUALTO 570 MWe beginning at Step 10 of AOP-GEN-002.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Form NTP-6331 Rev. A Date: JAN 19 2006 Page 2 of 6

RO-054-JP061, Rapid Power Reduction to Approximately 570 MWe, Rev. D JPM PERFORMANCE INFORMATION Required Materials: AOP-GEN-002 marked up through step 9.

General

References:

OP-KW-AOP-GEN-002, Rapid Power Reduction, Rev. 2 Task Standards: Reduce turbine load to at or below 570 MWe using the CV DOWN pushbutton in accordance with OP-KW-AOP-GEN-002, Rapid Power Reduction.

Start Time:

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 AOP-GEN-002, Step 10 Critical: No Check Turbine - NOT on Valve Position Limiter.

Standard: Check VALVE POS LIMIT green light NOT lit.

Determine TURBINE MODE TURBINE MANUAL amber light lit.

Evaluator Note: Turbine comes off VPL when TURBINE MANUAL operation is selected. This mode of operation is given in the Initial Conditions.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 AOP-GEN-002, Step 11.a Critical: No Check Turbine load reduction desired.

Standard: Determine turbine load reduction is desired.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 3 of 6

RO-054-JP061, Rapid Power Reduction to Approximately 570 MWe, Rev. D Performance Step: 3 AOP-GEN-002, Step 11.b Critical: No Check Turbine MODE - OPER AUTO.

Standard: Determine turbine control is in TURBINE MANUAL.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 AOP-GEN-002, Step 11.e Critical: No Check either of the following:

1. Rapid Boration per ATTACHMENT E in progress OR
2. Immediate Turbine load reduction required.

Standard: Determine neither condition applies.

Evaluator Cue: As Unit Supervisor, Immediate load reduction is NOT required. (Load reduction is per Operations Management request).

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 AOP-GEN-002, Step 11.e (RNO)

Critical: No When Tave lowers by greater than 1.0ºF due to boration, THEN GO TO Step 12.

Standard: Monitor Tave (Recorder 42554) and when Tave lowers to or below 570.7ºF, and then proceed with turbine load reduction.

Evaluator Note: The initial conditions have Tave more than 1ºF below Tref. Operator should check recorder 42554, TAVE - TREF, and determine Tave is adequately below Tref for initiating load reduction.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 4 of 6

RO-054-JP061, Rapid Power Reduction to Approximately 570 MWe, Rev. D Performance Step: 6 AOP-GEN-002, Step 12.a Critical: No Check Turbine MODE - OPER AUTO.

Standard: Determine turbine control is in TURBINE MANUAL.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 AOP-GEN-002, Step 12.a (RNO)

Critical: Yes Intermittently PRESS CV DOWN pushbutton. GO TO Step 12.c.

Standard: Load decrease using CV DOWN pushbutton until load is equal to or less than 570 MWe with the following constraints:

  • Load reduction is performed in discrete steps of at least 3 steps.
  • Periodic pressing of the CV DOWN pushbutton is used.

Evaluator Note: The CV DOWN pushbutton is located in the TURBINE CV MANUAL CONTROL section of the turbine control panel.

The operator may remain at this step (12) until load reduction is completed. The procedure is NOT normally performed by a single individual and the Unit Supervisor would follow to ensure all appropriate steps performed.

The rate of 1%/minute is equivalent to 6 MWe/minute.

Evaluator Cue: As Unit Supervisor, Maintain approximately 1% per minute load rate.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 5 of 6

RO-054-JP061, Rapid Power Reduction to Approximately 570 MWe, Rev. D Performance Step: 8 AOP-GEN-002, Step 12.c and d Critical: No Maintain MVAR out loading during power reduction at 0-150 MVAR.

Maintain boration flow rate and power reduction rate as necessary to maintain plant requirements:

  • I
  • Rod Insertion Limits
  • Tave within 4ºF of Tref Standard: MVAR loading maintained between 0 MVAR and 150 MVAR during load reduction.

Monitors load rate to maintain Tave within 4ºF of Tref.

Evaluator Note: MVAR loading is maintained by adjusting the GENERATOR #1 VOLTAGE ADJUSTER.

The operator may remain at this step (12) until load reduction is completed. The procedure is NOT normally performed by a single individual and the Unit Supervisor would follow to ensure all appropriate steps performed. The RO is responsible for monitoring I and RIL. With rods in AUTO, the stated limit for temperature difference will Not be exceeded if load is reduced in as described in Performance Step 7.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When Operator reports turbine load adjustment complete: THIS JPM IS COMPLETE.

Stop Time:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 6 of 6

JOB PERFORMANCE MEASURE (JPM)

SITE: KPS JPM TITLE: Restore Normal Emergency Bus Lineup Following Blackout JPM NUMBER: RO-039-JP09A REV. F RELATED PRA Loss of Offsite Power: 4% contribution to CDF; 5% contribution to LERF INFORMATION: 8th Most Important System - 4160 V AC Distribution TASK NUMBER(S) / 0390090401 / Respond to a Bus 5 or 6 Voltage LOW Condition TASK TITLE(S):

K/A NUMBERS: 062A2.12 RO 3.2 / SRO 3.6 and 062A4.07 RO 3.1 / SRO 3.1 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 12 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: RO/SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /s 03/27/09 Instructor Date Validated by: Stephen Johnson /s 03/24/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /s Training Supervisor Date Page 1 of 13

RO-039-JP09A, Restore Normal Emergency Bus Lineup Following Blackout, Rev. F INITIAL CONDITIONS:

  • You are the Balance of Plant Operator.
  • The plant had experienced a blackout, and ECA-0.0 was entered.
  • Power to the substation has been restored as directed in OP-KW-NOP-SUB-002, Restoration of Off-site Power.

INITIATING CUES (IF APPLICABLE):

The Unit Supervisor directs you to shift Bus 5 power supply from DG A to TAT per OP-KW-AOP-EHV-005 ATTACHMENT A.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Page 2 of 13

RO-039-JP09A, Restore Normal Emergency Bus Lineup Following Blackout, Rev. F JPM PERFORMANCE INFORMATION Required Materials: OP-KW-AOP-EHV-005 General

References:

OP-KW-AOP-EHV-005, Rev 0 ECA-0.0, Rev 39; OP-KW-NOP-SUB-002, Rev. 0 Task Standards:

Bus 5 powered from the TAT, and DG A shutdown and in-service.

Start Time:

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From DG A to Critical: No TAT Step A1.a:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

a. Announce via Gaitronics
  • Attention in the plant, Attention in the plant.

Shifting 4160 Volt power supplies, Stand Clear of Bus 5 Shifting 4160 Volt power supplies, Stand Clear of Bus 5 Standard: Make Plant Announcement Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 3 of 13

RO-039-JP09A, Restore Normal Emergency Bus Lineup Following Blackout, Rev. F Performance Step: 2 AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From DG A to Critical: No TAT Step A1.b:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

b. VERIFY BKR 1-501 43 SWITCH in MAN Standard: Bkr 1-501 43 Switch is in MAN Evaluator Note: This switch is placed in MAN as directed by NOP-SUB-002 when restoring offsite power to switchyard.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From DG A to Critical: Yes TAT Step A1.c:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

c. Position BKR 1-501 SYNC SWITCH to ON.

Standard: Bkr 1-501 Sync Switch is in ON.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 13

RO-039-JP09A, Restore Normal Emergency Bus Lineup Following Blackout, Rev. F Performance Step: 4 AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From DG A to Critical: No TAT Step A1.d:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

d. LOG Diesel Generator A INOPERABLE Standard: States need to log DG A INOPERABLE.

Evaluator Cue: As Unit Supervisor, state the Reactor Operator will log DG A INOPERABLE Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: Yes DG A to TAT Step A1.e:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

e. Locally SET Governor Droop Setting to 30 Standard: Contact EO to Set DG A Governor Speed Droop to 30.

Evaluator Cue: As EO, acknowledge and state that DG A Governor Speed Droop is set to 30.

Evaluator Note: The Booth Operator will use REMOTE FUNCTION EG105, DIESEL A DROOP PARALLEL SETTING 0UNIT/30PAR, Remote Value selection 30+PAR to set droop to 30.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 5 of 13

RO-039-JP09A, Restore Normal Emergency Bus Lineup Following Blackout, Rev. F Performance Step: 6 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: Yes DG A to TAT Step A1.f:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

f. Locally position Parallel-Unit switch to PARALLEL.

Standard: Contacts EO to Set DG A Parallel-Unit switch to PARALLEL position.

Evaluator Cue: As EO, acknowledge and state that DG A Parallel Unit Switch is in PARALLEL.

Evaluator Note: The Booth Operator will use REMOTE FUNCTION EG105, DIESEL A DROOP PARALLEL SETTING 0UNIT/30PAR, Remote Value selection 30+PAR to set switch to PARALLEL. (This was already selected by the Booth Operator action from Performance Step 6)

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: Yes DG A to TAT Step A1.g:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

g. ADJUST diesel generator voltage with Voltage Control switch until Incoming and Running voltages are matched.

Standard: Voltage on Incoming meter and voltage on Running meter are equal +/- 2 volts.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 6 of 13

RO-039-JP09A, Restore Normal Emergency Bus Lineup Following Blackout, Rev. F Performance Step: 8 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: Yes DG A to TAT Step A1.h:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

h. ADJUST Diesel Generator speed with Speed Control switch until Synchroscope rotates slowly (4 - 6 rpm) in FAST (clockwise) direction.

Standard: Synchroscope is rotating slowly (2 - 10 rpm) in FAST (clockwise) direction.

Evaluator Cue: If necessary, Synchroscope is rotating at 5 rpm.

Evaluator Note: It has been noted that adjusting DG speed to within 4 to 6 rpm on the Synchroscope in the Simulator is extremely difficult as the Speed Control switch does not respond well to fine adjustment. Therefore after several adjustments have been made and speed is the 2 to 10 rpm, the above cue should be used.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 9 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: Yes DG A to TAT Step A1.i:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

i. VERIFY Incoming and Running voltages matched.

Standard: Voltage Control switch for DG A operated, if necessary, until voltage on Incoming meter and voltage on Running meter are equal +/- 2 volts.

Evaluator Note: Step is not critical if operation of Voltage Control switch operation NOT required.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 7 of 13

RO-039-JP09A, Restore Normal Emergency Bus Lineup Following Blackout, Rev. F Performance Step: 10 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: Yes DG A to TAT Step A1.j:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

j. VERIFY Synchroscope rotating slowly in the FAST direction.

Standard: Speed Control switch for DG A operated, if necessary, until Synchroscope is rotating slowly (2 - 10 rpm) in FAST (clockwise) direction Evaluator Cue: If necessary, Synchroscope is rotating at 5 rpm.

Evaluator Note:

Step is not critical if operation of Speed Control switch operation NOT required.

It has been noted that adjusting SG speed to within 4 to 6 rpm on the Synchroscope in the Simulator is extremely difficult as the Speed Control switch does not respond well to fine adjustment. Therefore after several adjustments have been made and speed is the 2 to 10 rpm, the above cue should be used .

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 8 of 13

RO-039-JP09A, Restore Normal Emergency Bus Lineup Following Blackout, Rev. F Performance Step: 11 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: Yes DG A to TAT Step A1.k:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

k. At 1157 oclock close Bkr 1-501
1. WHEN syncroscope passes 12 oclock position, THEN release the breaker
2. IF Bkr 1-501 did NOT close, THEN REPEAT Steps A1.g thru A1.k Standard: 1. Brk 1-501 Control Switch taken to CLOSE with Synchroscope needle indicating between 1155 and 1200 on meter.
2. Brk 1-501 closed with red light lit.

Evaluator Note:

Performer should check:

1. Tertiary Aux XFMR power meter reads on-scale.
2. Tertiary Aux XFMR current meter reads on-scale Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 12 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: No DG A to TAT Step A1.l:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

l. Slowly REDUCE DG load to 200-300 KW AND reactive load to 120-190 KVAR.

Standard: 1. Speed Control switch operated (to LOWER) until load reads between 200 and 300 KW on power meter 4461103.

2. Voltage Control switch operated (to LOWER) until reactive load reads between 120 and 190 KVAR on react pwr meter 4461104 Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 9 of 13

RO-039-JP09A, Restore Normal Emergency Bus Lineup Following Blackout, Rev. F Performance Step: 13 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: Yes DG A to TAT Step A1.m:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

m. Open Bkr 1-509, DG A To Bus 5.

Standard: 1. Brk 1-509 Control Switch taken to TRIP.

2. Brk 1-509 open with green light lit.

Evaluator Note:

Performer should check:

1. DG A power meter power meter reads ZERO KW.
2. DG A reactive power meter power meter reads ZERO KVAR.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 14 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: No DG A to TAT Step A1.n:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

n. ADJUST diesel generator voltage to 4200 volts.

Standard: Operates Voltage Control switch for DG A until voltage indicates between 4000 and 4400 on DG A Voltage meter 4461102.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 10 of 13

RO-039-JP09A, Restore Normal Emergency Bus Lineup Following Blackout, Rev. F Performance Step: 15 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: No DG A to TAT Step A1.o:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

o. ADJUST diesel generator frequency to 59 Hz.

Standard: Operates Speed Control switch for DG A until frequency indicates between 58.8 and 59.2 on DG A Frequency meter 4461101.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 16 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: No DG A to TAT Step A1.p:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

p. OPERATE Diesel Generator A unloaded for greater than or equal to 5 minutes Standard: Determines DG has run unloaded for at least 5 minutes.

Evaluator Cue: After performer notes that DG is required to be run for at least 5 minutes unloaded, state, FIVE minutes has elapsed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 11 of 13

RO-039-JP09A, Restore Normal Emergency Bus Lineup Following Blackout, Rev. F Performance Step: 17 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: Yes DG A to TAT Step A1.q:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

q. Stop Diesel Generator A and POSITION control switch to AUTO.

Standard: 1. Place Diesel Engine A control switch to STOP.

2. DG A stopped with control switch in AUTO and green light lit.

Evaluator Note:

Performer should check when control switch taken to STOP:

  • DG A Frequency 4461101 goes to bottom of scale.
  • DG A Voltage 4461102 goes to bottom of scale.
  • DG A Speed 44611204 goes to ZERO.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 18 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: Yes DG A to TAT Step A1.r:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

r. POSITION Bkr 1-501 43 switch to AUTO.

Standard: Bkr 1-501 43 Switch is in AUTO.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 12 of 13

RO-039-JP09A, Restore Normal Emergency Bus Lineup Following Blackout, Rev. F Performance Step: 19 OP-KW-AOP-EHV-005 ATTACHMENT A, Shifting Bus 5 Power Supply From Critical: No DG A to TAT Step A1.s:

A1. WHEN TAT is restored, THEN SHIFT Bus 5 power supply to TAT as follows:

s. POSITION Bkr 1-501 sync switch to OFF.

Standard: Bkr 1-501 sync switch is in OFF.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When action OP-KW-AOP-EHV-005 ATTACHMENT A Step A1.s complete: This completes this JPM.

Stop Time:

Page 13 of 13

JOB PERFORMANCE MEASURE (JPM)

SITE: Kewaunee Power Station JPM TITLE: Realign Containment Sampling from R-21 JPM NUMBER: RO-045-JP08A REV. E RELATED PRA INFORMATION:

TASK NUMBER(S) / 0450050101 / Perform Containment Gaseous Monitoring using R-21 TASK TITLE(S):

K/A NUMBERS: 073A4.02 RO/SRO Imp: 3.7 / 3.7 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 10 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: RO/SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /s 03/27/08 Instructor Date Validated by: Stephen Johnson /s 03/24/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /s Training Supervisor Date Page 1 of 7

RO-045-JP08A, Realign Containment Sampling from R-21, Rev. E INITIAL CONDITIONS:

  • You are the Reactor Operator.
  • R-21, Cntmt Sys Vent Monitor, is aligned to Containment.
  • The AO has been briefed on the task and is standing by to perform actions as necessary.

THIS JPM IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

The Unit Supervisor directs you to align R-11/12, Cntmt Air Particulate Monitor, to Containment using N-RM-45, Radiation Monitoring System, step 4.2.13.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Form NTP-6331 Rev. A Date: JAN 19 2006 Page 2 of 7

RO-045-JP08A, Realign Containment Sampling from R-21, Rev. E JPM PERFORMANCE INFORMATION Required Materials:

N-RM-45, verified to latest revision and Sections 2.0 and 3.0 marked.

General

References:

N-RM-45, Rev 54.

Task Standards:

R-11/R-12 aligned to containment air sampling with R-11/R-12 Sample Pump running.

Start Time:

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 N-RM-45, 4.2.13.a.

Critical No RESTORE Containment Gaseous Monitoring From R-21 to R-11/12 as follows:

VERIFY R-11/12 Sample Pump OFF.

Standard: Determine R-11/R-12 Sample Pump Off.

Evaluator Note: On MCV the operator will observe the following for R-11/R-12 Pump Control:

  • R-11/R-12 Pump Control switch in OFF/RESET position
  • Green light lit, red light out above control switch
  • FLOW HIGH/LOW amber light lit to right of control switch
  • Annuncitor 47013-A, RAD MONITOR SAMPLING FLOW HIGH / LOW lit with SER point 0390 active.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 3 of 7

RO-045-JP08A, Realign Containment Sampling from R-21, Rev. E Performance Step: 2 N-RM-45, 4.2.13.b.

Critical Yes (SEQ-1)

RESTORE Containment Gaseous Monitoring From R-21 to R-11/12 as follows:

STOP R-21 Sample Pump.

Standard:

Place control switch for R-21 Pump Control to OFF/RESET position.

Evaluator Note:

The operator will observe the following:

  • Green light lit, red light out above control switch
  • FLOW HIGH/LOW amber light lit to right of control switch
  • Annuncitor 47013-A, RAD MONITOR SAMPLING FLOW HIGH / LOW alarms with SER point 0396 active Evaluator Cue: If required cue operator to continue with actions of identified procedure.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 4 of 7

RO-045-JP08A, Realign Containment Sampling from R-21, Rev. E Performance Step: 3 N-RM-45, 4.2.13.c. through 4.2.13.h Critical Yes (SEQ-2)

RESTORE Containment Gaseous Monitoring From R-21 to R-11/12 as follows:

Locally CLOSE AS-16.

Locally CLOSE AS-11.

Locally OPEN AS-31-1.

Locally OPEN AS-4.

Locally OPEN AS-15.

Locally OPEN AS-10.

Standard:

Contact Aux Operator to align the identified valves as listed above.

Receive report from Aux Operator that valves are in correct position.

Evaluator Note: Steps 4.2.13.c through 4.2.13.h are local actions and may be directed to be performed (sequentially) at one time by the operator or individually. Use check boxes in front of valve step if the Performer directs positioning the valves individually.

This step is Critical since the failure to direct alignment will result in NO flow path to the R11/12 Sample Pump.

BOOTH OPERATOR will change Remote Function RM101 to VENT to realign valves from R-21 sampling CNTMT to R-11/12 and align R-21 to normal vent sampling.

Evaluator Cue: As AO: Acknowledge request to align valve(s) and then report [TIME COMPRESSION] valve(s) is/are in open/closed position.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 5 of 7

RO-045-JP08A, Realign Containment Sampling from R-21, Rev. E Performance Step: 4 N-RM-45, 4.2.13.i.

Critical No RESTORE Containment Gaseous Monitoring From R-21 to R-11/12 as follows:

START R-21 Sample Pump.

Standard:

Place control switch for R-21 Pump Control to ON position.

Evaluator Note:

The operator will observe the following:

  • Green light out, red light lit above control switch
  • FLOW HIGH/LOW amber light out to right of control switch
  • SER point 0396 clears Starting R-21 Sample Pump is not Critical since other radiation monitors are normally measuring Plant Vent exhaust. (ODCM Table 3.2)

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 N-RM-45, 4.2.13.j.

Critical Yes (SEQ-3)

RESTORE Containment Gaseous Monitoring From R-21 to R-11/12 as follows:

START R-11/12 Sample Pump.

Standard:

Place control switch for R-11/12 Pump Control to ON position.

Evaluator Note:

The operator will observe the following:

  • Green light out, red light lit above control switch
  • FLOW HIGH/LOW amber light out to right of control switch
  • SER point 0390 and annunciator 47013-A, RAD MONITOR SAMPLING FLOW HIGH / LOW clear Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 6 of 7

RO-045-JP08A, Realign Containment Sampling from R-21, Rev. E Performance Step: 6 N-RM-45, 4.2.13.k.

Critical No RESTORE Containment Gaseous Monitoring From R-21 to R-11/12 as follows:

VERIFY R-11/12 and R-21 Flow High/Low light OFF.

Standard: Checks :

  • R-11/R-12 Pump Control FLOW HIGH/LOW amber light out to right of control switch.
  • R-21 Pump Control FLOW HIGH/LOW amber light out to right of control switch.

Evaluator Note: This may have been check when the sample pumps were started above.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 N-RM-45, 4.2.13.l.

Critical No RESTORE Containment Gaseous Monitoring From R-21 to R-11/12 as follows:

NOTIFY Radiation Protection containment air sampling is returned to R-11/12.

Standard: Contacts Radiation Protection and notifies them containment gaseous sampling is aligned to R-11/12 OR Notifies Unit Supervisor that Radiation Protection needs to be notified that R-11/12 is now aligned for containment gaseous sampling.

Evaluator Cue: If contacted as Radiation Protection: Acknowledge report.

If notified as Unit Supervisor: I will contact Radiation Protection to report R-11/12 aligned for containment gaseous sampling.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When notification requirements are addressed (Step 4.2.13 completed): This JPM is complete.

Stop Time:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 7 of 7

JOB PERFORMANCE MEASURE (JPM)

SITE: Kewaunee Power Station JPM TITLE: Respond to Trip of Circulating Water Pump JPM NUMBER: RO-004-JP031 REV. B RELATED PRA N/A INFORMATION:

TASK NUMBER(S) / 0040030501 / Respond to Low Condenser Vacuum due to loss of TASK TITLE(S): Circulating Water K/A NUMBERS: 051AA2.02 RO/SRO Imp: 3.9 / 4.1 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 3 Minutes Time Critical: No Alternate Path / Faulted: Yes TASK APPLICABILITY: RO/SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /s 03/27/09 Instructor Date Validated by: Stephen Johnson /s 03/27/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /s Training Supervisor Date Page 1 of 7

RO-004-JP031, Respond to Trip of Circulating Water Pump, Rev. B NOTE: Do NOT allow the JPM Performer to review any procedures prior to starting task.

INITIAL CONDITIONS:

  • You are currently the ONLY Nuclear Control Operator in the At-The-Controls area.
  • Plant power is stable.

THIS JPM IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

Annunciators 47082-D, BUS 4 FEEDER BKR TRIP, and 47083-D, BUS 4 FEEDER BKR OVERLOAD, are about to actuate.

Perform the immediate operator actions for the condition associated with the alarms.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions NOTE: Circ Water Pump B will trip 2 seconds after the Simulator is taken to RUN.

Page 2 of 7

RO-004-JP031, Respond to Trip of Circulating Water Pump, Rev. B JPM PERFORMANCE INFORMATION Required Materials:

None General

References:

OP-KW-AOP-GEN-001, Rev. 3, ATTACHMENT E Task Standards:

Both Circulating Water Pumps tripped, reactor tripped and E-0 Step 1 complete.

Start Time:

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 AOP-GEN-001, ATTACHMENT E, E1.

Critical No CHECK Loss Of Circulating Water Flow:

  • Turbine latched AND
  • NO CW Pumps Standard: Determine loss of Circ Water flow has occurred.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 AOP-GEN-001, ATTACHMENT E, E2.a Critical No CHECK If Standby CW Pump Should Be Started:

CHECK annunciator 47051-M, CW PUMPS LOW LOW LEVEL TRIP, - CLEAR Standard: Determine 47051-M annunciator clear.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 3 of 7

RO-004-JP031, Respond to Trip of Circulating Water Pump, Rev. B Performance Step: 3 AOP-GEN-001, ATTACHMENT E, E2.b Critical No CHECK If Standby CW Pump Should Be Started:

CHECK annunciator 47051-N, CW PUMPS FLOOD LEVEL TRIP, - CLEAR.

Standard: Determine 47051-N annunciator clear.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 AOP-GEN-001, ATTACHMENT E, E2.c Critical No CHECK If Standby CW Pump Should Be Started:

CHECK forebay level - GREATER THAN 64%

Standard: Determine forebay level is greater than 64%.

Evaluator Note: Forebay level is read on MVA on meter 41551 Forebay Level.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 7

RO-004-JP031, Respond to Trip of Circulating Water Pump, Rev. B Performance Step: 5 AOP-GEN-001, ATTACHMENT E, E2.d Critical No CHECK If Standby CW Pump Should Be Started:

START standby circulating water pump CW Pump 1A.

Standard:

Take control switch for CW Pump 1A from PULLOUT to STOP.

Take control switch for CW Pump1A to START and release.

Determine CW Pump 1A failed to start/tripped.

Evaluator Note:

Normally this action would be critical; however, since the Pump trips upon start, it is NOT critical that this action be performed if the operator addresses the RNO for failure of the standby pump to start.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 6 AOP-GEN-001, ATTACHMENT E, E2.d.1 RNO Critical Yes PERFORM the following:

Manually TRIP Reactor.

Standard: Depress the REACTOR TRIP pushbutton on MCB or MCA.

Evaluator Note: The operator may review the actions of AOP-GEN-001 before proceeding to or beyond this point.

Evaluator Cue: As US, if required, concur with identified actions.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 5 of 7

RO-004-JP031, Respond to Trip of Circulating Water Pump, Rev. B Performance Step: 7 AOP-GEN-01, ATTACHMENT E, E2.d.2 RNO Critical No PERFORM the following:

GO TO E-0, REACTOR TRIP OR SAFETY INJECTION.

Standard: Determine need to perform E-0 Immediate Operator Actions Evaluator Cue: If identified by operator, as Unit Supervisor: Perform immediate actions of E-0.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 8 E-0 Step 1.a Critical No VERIFY Reactor Trip:

CHECK reactor trip and bypass breakers - ALL OPEN.

Standard: Determine and report reactor trip and bypass breakers open.

Evaluator Note:

Operator will check the Reactor Trip Breaker A red light OUT green light lit for A and B Reactor Trip Breakers on VBB.

Operator will check neither red nor green light lit on Bypass A and Bypass B (normal condition).

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 6 of 7

RO-004-JP031, Respond to Trip of Circulating Water Pump, Rev. B Performance Step: 9 E-0 Step 1.b Critical No VERIFY Reactor Trip:

CHECK Reactor - SUBCRITICAL

  • Reactor power - LESS THAN 5%
  • Neutron flux - STABLE OR DECREASING Standard: Determine and report
  • Reactor NI power less than 5% for PR NIS - MCB meters NI-41B through NI-44B; NI drawer indicators N41A through N44A on MVB; NR-45 recorder.
  • Neutron flux decreasing on MCB Intermediate Range SUR meters NI-35D and NI-36D, OR Source Range SUR meters NI-31D and NI-32D.

Report reactor tripped.

Evaluator Cue: As Unit Supervisor: Acknowledge reactor trip.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When reactor trip has been verified (Completion of E-0 step 1): This JPM is complete.

Stop Time:

Page 7 of 7

JOB PERFORMANCE MEASURE (JPM)

SITE: Kewaunee Power Station JPM TITLE: Perform Boration Of The RWST JPM NUMBER: RO-035-JP23A REV. C RELATED PRA None INFORMATION:

TASK NUMBER(S) / 0350230101 / Perform a Manual Makeup to the SFP, RWST, VCT, or CVCS TASK TITLE(S): Holdup Tanks K/A NUMBERS: 004A4.12 RO/SRO Imp: 3.8 / 3.3 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: Perform: X EVALUATION LOCATION: In-Plant: Control Room:

Simulator: X Other:

Lab:

Time for Completion: 20 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: RO/SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson 03/30/09 Instructor Date Validated by: Stephen Johnson 03/24/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans Training Supervisor Date Page 1 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C INITIAL CONDITIONS:

  • You are the Reactor Operator.
  • The plant is at 100% power.
  • Chemistry reports have indicated lowering boron concentration in the RWST.
  • The source of the inleakage has been identified and corrected.
  • Operations Management has decided to raise the born concentration of the RWST.

THIS JPM IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

The US directs you directs you to add 36 gallons of boric acid to the RWST at the rate of 12 gpm using OP-KW-NOP-CVC-001, Boron Concentration Control, Section 5.10.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Page 2 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C JPM PERFORMANCE INFORMATION Required Materials:

Copy of NOP-CVC-001 Completed NOP-CVC-001, ATTACHMENT F showing 36 gallons of boric acid required.

General

References:

OP-KW-NOP-CVC-001, Rev. 13 Task Standards:

36 gallons of boron added to RWST from CVC Makeup System.

Start Time:

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 NOP-CVC-001 Critical No Review of PREREQUISITES Standard: Reviews and initials PREREQUISITE steps 3.1 and 3.2 Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 2 NOP-CVC-001 Critical No Review of PRECAUTIONS AND LIMITATIONS Standard: Reviews and initials PRECAUTIONS AND LIMITATIONS steps 4.1 through 4.13 Evaluator Cue: If required, inform operator that all P&Ls are satisfied.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 3 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 3 NOP-CVC-001, Step 5.10.1 Critical No VERIFY current plant conditions will NOT require an automatic makeup for the anticipated duration of this addition.

Standard: Determine plant is in steady-state condition.

Check VCT level (LI-112 and LI-141B) stable and above 18% such that makeup would not be required during performance of boration to RWST.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 4 NOP-CVC-001, Step 5.10.2 Critical No IF desired to add inventory to the RWST without diluting OR borating the RWST, THEN CALCULATE Boric Acid and Rx Makeup totalizer settings using ATTACHMENT C.

Standard: Determine step does NOT apply since boration is desired.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 NOP-CVC-001, Step 5.10.3 Critical No IF desired to raise RWST boron concentration, THEN CALCULATE Boric Acid totalizer setting using ATTACHMENT F.

Standard: Refer to ATTACHMENT F.

Evaluator Note: A completed ATTACHMENT F should be provided to operator.

Evaluator Cue: ATTACHMENT F has been previously completed, verified, and supports adding 36 gallons boric acid.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 6 NOP-CVC-001, Step 5.10.4 Critical No IF desired to lower RWST boron concentration, THEN CALCULATE Makeup Water Totalizer setting using ATTACHMENT H.

Standard: Determine step does NOT apply since boration is desired.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 NOP-CVC-001, Step 5.10.5 Critical Yes Position Reactor Makeup Mode Selector to MANUAL Standard: Places Reactor Makeup Mode Selector to MANUAL position.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 5 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 8 NOP-CVC-001, Step 5.10.6 Critical Yes SET Boric Acid Totalizer to the number of gallons required as determined on:

0.0 gallons for lowering RWST boron concentration.

OR Value determined using ATTACHMENT F OR Value determined using ATTACHMENT C Standard: On Boric Acid Totalizer:

  • Depress black pushbutton at 44559/YIC-110 and lifts red cover,
  • Rotate thumbwheels so as to read 000360 as read from left (36.0).
  • Lower red cover.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 6 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 9 NOP-CVC-001, Step 5.10.7 Critical Yes SET Makeup Totalizer to either:

50 gallons less than the number of gallons of makeup water required on ATTACHMENT H.

OR 50 gallons less than the number of gallons of makeup water required on ATTACHMENT C OR to 0 gallons, if using ATTACHMENT F Standard: On Rx Makeup Totalizer:

  • Depress black pushbutton at 44560/YIC-111 and lifts red cover,
  • Rotate thumbwheels so as to read 000000 as read from left (ZERO).
  • Lower red cover.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 10 NOP-CVC-001, Step 5.10.8 Critical No VERIFY CVC-403/CV-31092, Boric Acid To Blender, hand controller set to provide makeup at desired rate.

Standard: Rotate CVC-403 Controller setpoint dial to 12.0 (+/- 0.2)

Evaluator Note: Although the desired flow rate is given, it is not critical for the operator to set this value exactly as it will only affect the amount of time taken to complete the boration.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 7 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 11 NOP-CVC-001, Step 5.10.9 Critical No VERIFY MU-1022/CV-31095, Blender Control Rx Mu Flow, hand controller set at 60 gpm.

Standard: Check MU-1022 Controller setpoint dial to 60.0 (+/- 2.0)

Evaluator Note: MU-1022 Controller Setpoint dial is normally set to 60.0. Makeup flow is NOT used for control during this evolution.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 12 NOP-CVC-001, Step 5.10.10 Critical Yes Locally OPEN the following to establish blender flowpath:

  • CVC-410, Blended Makeup To Alternate Services Isol
  • CVC-412, Blended Makeup To Refueling Water Storage Tank Isol Standard: Contact AO and direct him to OPEN CVC-410 and CVC-412.

Receive report from AO that CVC-410 and CVC-412 are OPEN.

Evaluator Note: The BOOTH OPERATOR will enter REMOTE FUNCTION CV165 to 100 to open CVC-410, and CV120 to open CVC-412.

Evaluator Cue:

As Auxiliary Operator: Acknowledge request, and then report CVC-410 and CVC-412 are open.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 8 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 13 NOP-CVC-001, Step 5.10.11 Critical No IF maximum flow rate is required, THEN VERIFY the following setpoints:

  • CVC-403 hand controller set at 15.0
  • MU-1022 hand controller set at 80.0 Standard: Determine step does NOT apply.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 14 NOP-CVC-001, Step 5.10.12 Critical Yes POSITION Reactor Makeup Control switch to START.

Standard: Reactor Makeup Control switch taken to START position and allowed to return to center with red flag present.

Evaluator Note: Operator should observe that red light for Reactor Makeup Control lights and green light extinguishes. Other items that may be observed are included in next Performance Step.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 9 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 15 NOP-CVC-001, Step 5.10.13 Critical No VERIFY makeup flow to RWST.

Standard: Observe the following:

  • CVC-403, Boric Acid to Blender, throttles as indicated by red and green lights lit
  • CVC-408, BA Blender to Charging Pumps, and CVC-406, BA Blender to VCT, remain CLOSED
  • VCT level on LI-112 and LI141B remains stable.
  • Recorder 42552 red pen indicates BA flow at selected rate (12 gpm)

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 10 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 16 NOP-CVC-001, Step 5.10.14 Critical No During manual makeup, VERIFY proper boron concentration as follows:

  • CVCS BA & MU flow recorder
  • Recorder 42552 red pen reading the desired BA flow rate (12 gpm)
  • Recorder 42552 green pen reading ZERO
  • BA Totalizer counter readings going up
  • Rx Makeup Totalizer counter reading NOT changing.
  • Boric Acid Tank levels LI-106, 172, 190, 196, 102, 171, 189, and 197 changing together at approximately 0.4%/min for total of 1.2% level change.

Evaluator Note:

The rate of change and total amount of change for BA tanks is based on the information provided in AOP-CVC-001, Emergency Boration, Attachment B, 360 gallons (12% combined level) from the BATs Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 11 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 17 NOP-CVC-001, Step 5.10.15 Critical No IF low flow to a single BA transfer pump is suspected during parallel pump operation, THEN PERFORM the following:

Throttle OPEN CVC-712A and CVC-172B during the evolution. .

Standard:

Determine OPENING of CVC-712A and CVC-712B NOT required based on adequate BA flow.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 12 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 18 NOP-CVC-001, Step 5.10.16 Critical YES, if makeup IF required to manually stop makeup, THEN PERFORM the following:

stopped prior to 36 gallons a. POSITION Reactor Makeup Control switch to STOP

b. IF CVC-403 is OPEN, THEN CLOSE CVC-403
c. IF required to continue makeup, THEN PERFORM the following:
1. POSITION CVC-403 control switch to AUTO.
2. POSITION Reactor Makeup Control switch to START
3. VERIFY makeup flow reestablished to RWST Standard:

If manual makeup is stopped prior to endpoint of 36 gallons:

  • Reactor Makeup switch is taken to STOP with green flag and green light only lit.
  • CVC-403 switch is placed in CLOSE position If makeup is restarted the following steps are critical:
  • Reactor Makeup Control switch taken to START position and allowed to return to center with red flag present.
  • CVC-403 control switch is placed to AUTO position and throttling of CVC-403 is observed
  • Makeup flow is verified:
1. Boric Acid Transfer Pumps start and run
2. CVC-408, BA Blender to Charging Pumps, and CVC-406, BA Blender to VCT, remain CLOSED
3. VCT level on LI-112 and LI-141B remains stable.
4. Recorder 42552 red pen indicates BA flow at selected rate
5. Boric Acid totalizer counter is counting up.

Evaluator Note:

It is not expected that this step will be performed, but if boration is manually stopped prior to 36 gallons added, then reestablishing makeup to the RWST is critical.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 13 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 19 NOP-CVC-001, Step 5.10.17.a Critical Yes WHEN required makeup has been achieved, THEN PERFORM the following:

IF CVC-403 is OPEN, THEN CLOSE CVC-403.

Standard:

If red light for CVC-304 is lit, place CVC-304 control switch to CLOSE position and observe red light extinguishes when valve closes.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 20 NOP-CVC-001, Step 5.10.17.b Critical No WHEN required makeup has been achieved, THEN PERFORM the following:

VERIFY auto stop of Makeup System.

Standard: Observe the following:

a. Reactor Makeup Control switch green light lit and red light out.
b. Boric Acid Transfer Pumps stop
c. Recorder 42552 red pen indicates BA flow at ZERO
d. Boric Acid totalizer counter stops counting.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 14 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 21 NOP-CVC-001, Step 5.10.17.

Critical No WHEN required makeup has been achieved, THEN PERFORM the following:

c. At 44559/YIC-110, Boric Acid Totalizer, VERIFY correct quantity added
d. PRESS black pushbutton at 44559/YIC-110 AND VERIFY totalizer output window resets to all zeros
e. Under red shutter, SET 44559/YIC-110 totalizer setting to 00000.0 Standard: On Boric Acid Totalizer:
  • Determine approximately 36 gallons BA added by change in BA Totalizer counter
  • Press black pushbutton at 44559/YIC-110
  • Verify ZEROs displayed on counter
  • Lift red cover,
  • Rotate thumbwheels so as to read 00000.0.
  • Lower red cover.

Evaluator Note:

Action is not critical since the totalizer does not affect operation of makeup system in AUTO (to VCT).

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 15 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 22 NOP-CVC-001, Step 5.10.17.

Critical No WHEN required makeup has been achieved, THEN PERFORM the following:

f. At 44560/YIC-111, Rx Makeup Totalizer, VERIFY correct quantity added
g. PRESS black pushbutton at 44560/YIC-111 AND VERIFY totalizer output window resets to all zeros Standard: On Rx Makeup Flow Totalizer:
  • Determine NO makeup flow at Rx Makeup Totalizer counter
  • Depress black pushbutton at 44560/YIC-111.
  • Verify ZEROs displayed on counter.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 23 NOP-CVC-001, Step 5.10.18 Critical No FLUSH fill line with Reactor makeup water as follows:

a. VERIFY MU-1002 hand controller set to provide makeup at 60 gpm.

Standard: Check MU-1022 Controller setpoint dial to 60.0 (+/- 2.0)

Evaluator Note:

Flush of line is NOT required but is desired to ensure all 36 gpm of BA is flushed to RWST.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 16 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 24 NOP-CVC-001, Step 5.10.18 Critical No FLUSH fill line with Reactor makeup water as follows:

b. SET RX Makeup Totalizer to 50 Standard: On Rx Makeup Flow Totalizer:
  • Lift red cover,
  • Rotate thumbwheels so as to read 000050.
  • Lower red cover.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 25 NOP-CVC-001, Step 5.10.18 Critical No FLUSH fill line with Reactor makeup water as follows:

c. POSITION Reactor Makeup Control switch to START.

Standard:

Reactor Makeup Control switch taken to START position and allowed to return to center with red flag present.

Observe the following:

  • Recorder 42552 red pen reading 0.0 the desired BA flow rate (ZERO gpm)
  • Recorder 42552 green pen reading the desired Makeup flow rate (~ 60 gpm)
  • BA Totalizer counter reading NOT changing
  • Rx Makeup Totalizer counter reading going up.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 17 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 26 NOP-CVC-001, Step 5.10.19 Critical No WHEN flush is complete, THEN RESET Rx Makeup Totalizer as follows:

a. VERIFY expected quantity added.
b. At 445560/YIC-111, Rx makeup Totalizer, VERIFY correct quantity added.
c. PRESS black pushbutton at 445560/YIC-111 AND VERIFY totalizer output window resets to all zeros.

Standard: On Rx Makeup Totalizer:

  • Determine approximately 50 gallons Makeup water added by change in Rx Makeup Totalizer counter
  • Press black pushbutton at 44560/YIC-111
  • Verify ZEROs displayed on counter Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 27 NOP-CVC-001, Step 5.10.20 Critical Yes CLOSE CVC-410 Standard: Contact AO and direct him to CLOSE CVC-410.

Receive report from AO that CVC-410 is closed and independent verification performed.

Evaluator Note: The BOOTH OPERATOR will change REMOTE FUNCTION CV165 to 0 to close CVC-410.

Evaluator Cue:

As Auxiliary Operator: Acknowledge request, and then report CVC-410 is closed. Report that Independent Verification is performed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 18 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 28 NOP-CVC-001, Step 5.10.21 Critical Yes CLOSE CVC-412 Standard: Contact AO and direct him to CLOSE CVC-412.

Receive report from AO that CVC-412 is closed and independent verification performed.

Evaluator Note: The BOOTH OPERATOR will change REMOTE FUNCTION CV120 to close CVC-412.

Evaluator Cue:

As Auxiliary Operator: Acknowledge request, and then report CVC-412 is closed. Report that Independent Verification is performed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 29 NOP-CVC-001, Step 5.10.22 Critical No VERIFY CVC-403 control switch in AUTO.

Standard:

Place CVC-403 control switch to AUTO position.

Evaluator Note:

This is a portion required to return the makeup system to normal operations but is NOT required to complete the task of makeup to the RWST for raising boron concentration.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 19 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 30 NOP-CVC-001, Step 5.10.23 Critical No VERIFY CVC-403/CV31092 hand controller set for current RCS boron concentration.

Standard:

Determine setting for current RCS boron concentration:

  • Use Operator Aid 96-3, RMW Blender Flow Curves
  • Determine required Boric Acid Flow at intersection of RED curve (60 gpm @

8.0 w%) and current RCS boron concentration.

  • Set CVC-403 hand controller setpoint dial to determined value +/- 0.2.

Evaluator Note:

For Cycle 100% power MOC the RCS boron concentration is 967 ppm. 967 ppm intersects the RED curve at approximately 4.6 at rated boric acid flow. CVC-403 had controller setpoint would then be set to approximately 4.4-4.8 to establish the desired blended flow during automatic makeup.

This is a portion required to return the makeup system to normal operations but is NOT required to complete the task of makeup to the RWST for raising boron concentration.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 20 of 21

RO-035-JP23A, Perform Boration Of The RWST, Rev. C Performance Step: 31 NOP-CVC-001, Step 5.10.24 Critical No POSITION Reactor Makeup Mode Selector switch to AUTO Standard:

Reactor Makeup Mode Selector switch taken to AUTO position.

Evaluator Note:

This is a portion required to return the makeup system to normal operations but is NOT required to complete the task of makeup to the RWST for raising boron concentration.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 32 NOP-CVC-001, Step 5.10.24 Critical No POSITION Reactor Makeup Mode Selector switch to START Standard:

Reactor Makeup Control switch taken to START position and allowed to return to center with red flag present.

Check the Reactor Makeup Mode Selector switch red light lit and green light off.

Evaluator Note:

This is a portion required to return the makeup system to normal operations but is NOT required to complete the task of makeup to the RWST for raising boron concentration.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When the Makeup System is aligned for normal operations at step 5.10.25: This JPM is complete.

Stop Time:

Page 21 of 21

JOB PERFORMANCE MEASURE (JPM)

SITE: Kewaunee Power Station JPM TITLE: Align Alternate Instrument Header To Containment With A Fire In A Dedicated Zone JPM NUMBER: RO-E07-JP013 REV. D RELATED PRA N/A INFORMATION:

TASK NUMBER(S) / E070010501 / Respond To A Fire In A Dedicated Fire Zone TASK TITLE(S):

K/A NUMBERS: 067 2.1.30 RO/SRO Imp 4.4 / 4.0 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: X Perform:

EVALUATION LOCATION: In-Plant: X Control Room:

Simulator: Other:

Lab:

Time for Completion: 10 Minutes Time Critical: NO Alternate Path / Faulted: YES TASK APPLICABILITY: RO/SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /S 01/26/09 Instructor Date Validated by: Stephen Johnson /S 01/08/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /S 02/10/09 Training Supervisor / Facility Rep Date Page 1 of 5

RO-E07-JP013, Align Alternate Instrument Header To Containment With A Fire In A Dedicated Zone, Rev. C JPM BRIEFING/TURNOVER Read to Examinee:

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

You may use any approved reference materials normally available including logs. Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

AOP and EOP Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

If this JPM is performed on the simulator, the JPM administrator should only give cues that are not indicated on the simulator. If simulator indication is sufficient to indicate the completion of a step, the JPM administrator should not have to give a cue to the trainee to continue the evolution.

1. Human Performance attributes should be visible. The student may use STAR and or request Peer Checks.
2. If peer checks are requested, the Instructor should reply - Peer Check Acknowledged. The instructor will acknowledge use of the human performance tool and not validate the proper component manipulation.

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • You are Control Operator B.
  • The plant has been tripped due to a fire in a dedicated fire zone.
  • OP-KW-AOP-FP-003, FIRE IN DEDICATED FIRE ZONE, is being performed.
  • You have been dispatched to perform AOP-FP-003, ATTACHMENT B.
  • ATTACHMENT B has been completed through step B14.
  • You have an Emergency Key Ring and two-way radio.
  • It has been determined that the air accumulators inside containment are depleted.

THE STEPS IN THIS JPM SHOULD BE: SIMULATED THIS JPM IS NOT TIME CRITICAL.

INITIATING CUES (IF APPLICABLE):

Implement step B15 ATTACHMENT B of AOP-FP-003.

Page 2 of 5

RO-E07-JP013, Align Alternate Instrument Header To Containment With A Fire In A Dedicated Zone, Rev. C JPM PERFORMANCE INFORMATION Required Materials: AOP-FP-003, ATTACHMENT B marked up with procedure placekeeping (circle/slash) for steps B1 through B14.

General

References:

OP-KW-AOP-FP-003, Fire In Alternate Fire Zone, Rev. 1 Task Standards: Alternate Instrument Air Header to Containment aligned with IA-101 CLOSED, and both IA-101-1 and IA-310 open.

Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 AOP-FP-003 ATTACHMENT B, step B15 Critical No (CAS) Check Air Accumulators for Valves Located Inside Containment NOT Depleted.

Standard: Determine that Air Accumulators in containment are depleted.

Evaluator Note: Given in Initial Conditions that air accumulators are depleted.

Evaluator Cue: If contacted as control room operator: Valve operation of valves in containment indicate that air accumulators are depleted.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 3 of 5

RO-E07-JP013, Align Alternate Instrument Header To Containment With A Fire In A Dedicated Zone, Rev. C Performance Step: 2 AOP-FP-003 ATTACHMENT B, step B15.a RNO Critical Yes When air accumulators for valves located inside Containment depleted, THEN ALIGN the Alternate Instrument Air Header to Containment as follows:

In BAST Room, LOOSEN jam nut on handwheel for IA to Cntmt Isol IA-101.

Standard: Jam nut has been rotated counter-clockwise to free handwheel.

Evaluator Note: The valve is located in the Boric Acid Tank room along the west wall. A ladder will be required to operate IA-101 and jam nut on valve operator. The nearest ladders are located outside the BAST room on elevation 626 to the north-east by the wall of the Hot Tool Crib.

Examinee will need a wrench in order to loosen the jam nut. There is a wrench hanging on the wall near the valve.

Valve handwheel will NOT operate until handwheel is free (jam nut loosened).

Evaluator Cue: (If actual use of ladder NOT desired) When ladder is located, cue, You have obtained the ladder.

When examinee indicates wrench location, cue, The wrench has been obtained.

When examinee indicates jam nut operation, cue, Nut is loosened and screw threads are visible between nut and operator.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 AOP-FP-003 ATTACHMENT B, step B15.b RNO Critical Yes When air accumulators for valves located inside Containment depleted, THEN ALIGN the Alternate Instrument Air Header to Containment as follows:

Locally CLOSE IA-101.

Standard: Rotate handwheel clockwise until valve is closed.

Evaluator Cue:

(As clockwise handwheel operation is indicated) The handwheel rotates until NO further motion occurs.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 5

RO-E07-JP013, Align Alternate Instrument Header To Containment With A Fire In A Dedicated Zone, Rev. C Performance Step: 4 AOP-FP-003 ATTACHMENT B, step B15.c RNO Critical Yes When air accumulators for valves located inside Containment depleted, THEN ALIGN the Alternate Instrument Air Header to Containment as follows:

In BAST Room, OPEN Ded & Alt Hdr to Cntmt Isol, IA-101-1.

Standard: Rotate handwheel counter-clockwise until IA-101-1 is open.

Evaluator Note: The valve is located in the Boric Acid Tank room along the west wall.

Evaluator Cue:

(As counter-clockwise handwheel operation is indicated) The handwheel rotates until NO further motion occurs. The valve stem rises during operation.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 AOP-FP-003 ATTACHMENT B, step B15.d RNO Critical Yes When air accumulators for valves located inside Containment depleted, THEN ALIGN the Alternate Instrument Air Header to Containment as follows:

In ICS Pump Area, OPEN Alternate IA Hdr to Cntmt Isol, IA-310.

Standard: Rotate handwheel counter-clockwise until IA-310 is open.

Evaluator Note:

The valve is located behind the support I-beam just north of ICS Pump A.

Evaluator Cue:

(As counter-clockwise handwheel operation is indicated) The handwheel rotates until NO further motion occurs. The valve stem rises during operation.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When operator has completed the step to align the alternate IA header to Containment: This completes this JPM.

Stop Time:

Page 5 of 5

JOB PERFORMANCE MEASURE (JPM)

SITE: KPS JPM TITLE: Operate and Monitor the Post-LOCA Hydrogen Control System JPM NUMBER: AO-018-JP01A REV. C RELATED PRA None INFORMATION:

TASK NUMBER(S) / 0180010104 / Startup the Post-LOCA Hydrogen Control System for TASK TITLE(S): Hydrogen Dilution of Containment with Instrument Air Available K/A NUMBERS: 028A1.01 RO/SRO Imp 3.4 / 3.8 (028) 2.1.30 - RO/SRO Imp 4.4 / 4.0 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: X Perform:

EVALUATION LOCATION: In-Plant: X Control Room:

Simulator: Other: X Simulator DSP Lab:

Time for Completion: 13 Minutes Time Critical: No Alternate Path / Faulted: No TASK APPLICABILITY: RO, SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson /s 01/13/09 Instructor Date Validated by: Andrew Fahrenkrug /s 02/11/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans /s 02/12/09 Training Supervisor Date Page 1 of 6

RO-035-JP27A, Test Charging Pump C From Dedicated Shutdown Panel, Rev. B JPM BRIEFING/TURNOVER Read to Examinee:

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

You may use any approved reference materials normally available including logs. Make all written reports, oral reports, and log entries as if the evolution is actually being performed.

AOP and EOP Immediate Actions are required to be performed from memory. After completing immediate action steps without using the procedure, you may then use any approved reference materials.

If this JPM is performed on the simulator, the JPM administrator should only give cues that are not indicated on the simulator. If simulator indication is sufficient to indicate the completion of a step, the JPM administrator should not have to give a cue to the trainee to continue the evolution.

1. Human Performance attributes should be visible. The student may use STAR and or request Peer Checks.
2. If peer checks are requested, the Instructor should reply - Peer Check Acknowledged. The instructor will acknowledge use of the human performance tool and not validate the proper component manipulation.

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

INITIAL CONDITIONS:

  • You are the Auxiliary Operator.
  • A LOCA has occurred.
  • Chemistry has reported Containment hydrogen concentration has reached 1.0% by volume.
  • The crew has decided to implement N-RBV-18C, Post-LOCA Hydrogen Control, to reduce hydrogen concentration.
  • A copy of N-RBV-18C has been provided.
  • All procedural PRECAUTIONS AND LIMITATIONS and Initial Conditions are currently satisfied.
  • Instrument Air system is available.

THE STEPS IN THIS JPM SHOULD BE: SIMULATED THIS TASK IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

The Unit Supervisor has directed you to the Train B Hydrogen Dilution of Containment per N-RBV-18C, section 4.1.1.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Page 2 of 6

AO-018-JP01A, Operate and Monitor the Post-LOCA Hydrogen Control System, Rev. C JPM PERFORMANCE INFORMATION NOTE: Review GNP-05.16.06, ATTACHMENT A for Time Dependent Operator Actions. If the JPM addresses one of these tasks and the JPM is determined to be time critical or contain time critical performance steps, then GNP-05.16.06 will be included in the General References below. [OTH 12765]

Required Materials: N-RBV-18C General

References:

N-RBV-18C, Rev. K Task Standards: Instrument air aligned for Train B Containment dilution with flow adjusted to approximately 25 scfm.

Start Time:

NOTE: When providing Evaluator Cues to the examinee, care must be exercised to avoid prompting the examinee. Typically cues are only provided when the examinees actions warrant receiving the information (i.e. the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a Y/Yes below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 N-RBV-18C, step 4.1.1.a.1: Locally OPEN SA-7003B/MV-32148, Hydrogen Critical: Yes Dilution to Containment:

REMOVE sealing device from SA-7003B LOCAL/REMOTE switch.

Standard: SA-7003 LOCAL/REMOTE switch tie-wrap cut or undone.

SA-7003 LOCAL/REMOTE switch sealing device removed.

Evaluator Note: Panel with SA-7003B controls is located on 606 elev. of the Auxiliary Building. The panel is located on the south wall at the east end of the CC Heat Exchangers area.

Sealing device is a cover plate over the switch that is secured by a tie-wrap.

Evaluator Cue: Sealing device has been removed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 3 of 6

AO-018-JP01A, Operate and Monitor the Post-LOCA Hydrogen Control System, Rev. C Performance Step: 2 N-RBV-18C, step 4.1.1.a.2: Locally OPEN SA-7003B/MV-32148, Hydrogen Critical: Yes Dilution to Containment:

REMOVE sealing device from SA-7003B control switch.

Standard: SA-7003 control switch tie-wrap cut or undone.

SA-7003 control switch sealing device removed Evaluator Note: Sealing device is a cover plate over the switch that is secured by a tie-wrap.

Evaluator Cue:

Sealing device has been removed.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 N-RBV-18C, step 4.1.1.a.3: Locally OPEN SA-7003B/MV-32148, Hydrogen Critical: Yes Dilution to Containment:

POSITION SA-7003B LOCAL/REMOTE switch to LOCAL.

Standard:

Switch is taken to LOCAL position.

Evaluator Cue: Initially, Switch is as you see it (in REMOTE position).

When switch operation indicated, Switch is in LOCAL position.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 4 of 6

AO-018-JP01A, Operate and Monitor the Post-LOCA Hydrogen Control System, Rev. C Performance Step: 4 N-RBV-18C, step 4.1.1.a.4: Locally OPEN SA-7003B/MV-32148, Hydrogen Critical: Yes Dilution to Containment:

OPEN SA-7003B.

Standard: Take control switch from AUTO to OPEN.

Verify valve open with red light ON and green light OFF.

Evaluator Cue: Initially, Switch is as you see it (in AUTO position).

When switch operation from AUTO to OPEN is indicated, Switch goes to OPEN and red light goes on; green light goes off.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 N-RBV-18C, step 4.1.1.b.1: ESTABLISH Instrument Air flow to Containment :

Critical: Yes OPEN IA-1002B, Instrument Air Supply - Post LOCA Hydrogen.

Standard: IA-1002B knife handle is moved from the horizontal position (perpendicular to piping) to the vertical position (parallel to piping).

Evaluator Note: The valve is located on the 606 elev. of the Auxiliary Building in the Train A Main Steam Penetration area. The valve is located in the south corner past the SG A PORV platform next to the Shield Building wall.

Evaluator Cue: Initially, (Knife) handle is as you see it (perpendicular to the piping).

When valve handle operation is indicated, Valve handle is now in the vertical position.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Page 5 of 6

AO-018-JP01A, Operate and Monitor the Post-LOCA Hydrogen Control System, Rev. C Performance Step: 6 N-RBV-18C, step 4.1.1.b.2: ESTABLISH Instrument Air flow to Containment :

Critical: Yes OPEN IA-1001B/CV-31392, Post LOCA Air Supply Control Valve, and ESTABLISH 25 SCFM air flow as indicated by FI-18238, Post LOCA Instrument Air Supply flow indication.

Standard: Rotate counterclockwise the knob on top of IA-1001B until FI18238 indication reads approximately 25 scfm.

Evaluator Note: The control valve knob is accessible from and the flow meter can be read from the SG A PORV platform in the Train A Main Steam Penetration area.

Evaluator Cue: Initially, The valve is closed and the flow meter reads ZERO.

When operation indicated, The knob rotates counter-clockwise. When flow meter is checked indicate flow (plug float) reads about 20 scfm.

When further operation indicated, The knob rotates counter-clockwise. When flow meter is checked indicate flow reads about 25 scfm.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When the operator indicates the air flow is adequate, This JPM is complete.

Stop Time:

Page 6 of 6

JOB PERFORMANCE MEASURE (JPM)

SITE: Kewaunee Power Station JPM TITLE: Operate The Emergency Borate Valve Locally JPM NUMBER: AO-035-JP011 REV. D RELATED PRA INFORMATION:

TASK NUMBER(S) / 0350010504 / Perform an Emergency Boration TASK TITLE(S):

K/A NUMBERS: 024AA1.17 RO/SRO Imp 3.9/3.9 2.1.30 RO/SRO Imp 4.4 / 4.0 APPLICABLE METHOD OF TESTING:

Discussion: Simulate/walkthrough: X Perform:

EVALUATION LOCATION: In-Plant: X Control Room:

Simulator: Other:

Lab:

Time for Completion: 10 Minutes Time Critical: No Alternate Path / Faulted: Yes TASK APPLICABILITY: AO/RO/SRO Additional signatures may be added as needed.

Developed by: Stephen Johnson 03/30/09 Instructor Date Validated by: Stephen Johnson 03/25/09 Validation Instructor Date (See JPM Validation Checklist, Attachment 1)

Approved by: Terry Evans Training Supervisor Date Page 1 of 6

AO-035-JP011, Operate The Emergency Borate Valve Locally, Rev. D INITIAL CONDITIONS:

  • You are the Auxiliary Operator
  • An Emergency Condition exists
  • The plant has just tripped from 100% power
  • CVC-440/MV-32127, Emergency Boration To Charging Pumps, has failed to operate from the Control Room
  • CVC-403, CVC-408 and CVC-405 failed to operate.

THE STEPS IN THIS JPM SHOULD BE: SIMULATED THIS TASK IS NOT TIME CRITICAL INITIATING CUES (IF APPLICABLE):

The RO directs you to locally OPEN CVC-440/MV-32127, Emergency Boration To Charging Pumps, per AOP-CVC-001, ATTACHMENT A beginning at Step A4.

INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK Do you have any questions before we begin? - Answer applicable questions Form NTP-6331 Rev. A Date: JAN 19 2006 Page 2 of 6

AO-035-JP011, Operate The Emergency Borate Valve Locally, Rev. D JPM PERFORMANCE INFORMATION Required Materials:

OP-KW-AOP-CVC-001, Rev. 1, ATTACHMENT A General

References:

OP-KW-AOP-CVC-001, Rev. 1 Task Standards:

CVC-302, RWST Emergency Suction Isol, is OPEN locally and CVC-3, Charging Pump Suction Line X-Connect, is closed locally.

Start Time:

NOTE: Critical steps are marked with a Y below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 AOP-CVC-001, ATTACHMENT A, A4.

Critical No Locally OPERATE declutch lever to DISENGAGE motor and ENGAGE handwheel.

Standard:

DEPRESS the valve de-clutching lever.

Slowly rotate handwheel until the handwheel engages.

Evaluator Note:

CVC-440 location: South of SI Pumps, boric acid blender area.

Evaluator Cue:

Once actions are simulated properly state: Declutch lever latches in place.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 3 of 6

AO-035-JP011, Operate The Emergency Borate Valve Locally, Rev. D Performance Step: 2 AOP-CVC-001, ATTACHMENT A, A5.

Critical No Locally OPERATE handwheel to OPEN CVC-440.

Standard:

TURN CVC-440 handwheel in the counter-clockwise direction to attempt to OPEN valve.

Evaluator Cue: Once simulated properly state: The handwheel freely turns and valve stem position does NOT change. (The valve will not open)

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 3 AOP-CVC-001, ATTACHMENT A, A6.

Critical No NOTIFY Control Room CVC-440 is OPEN.

Inform the Control Room CVC-440 will not open.

Standard: Contact and report to Control Room Operator that CVC-440 will not open.

Evaluator Cue:

As Control Room Operator: Acknowledge report and then direct operator to perform Step 5.b, RESPONSE NOT OBTAINED of AOP-CVC-001.

(For Step 5.b.1 RNO), Charging Pump A is running.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 4 of 6

AO-035-JP011, Operate The Emergency Borate Valve Locally, Rev. D Performance Step: 4 AOP-CVC-001, Step 5.b.2 RNO Critical Yes Locally open CVC-302, RWST Emergency Suction Isol.

Standard: Rotate handwheel counter-clockwise until CVC-302 is open.

Evaluator Note: Valve is located in the Aux Bldg 586 elevation in the Charging Pump room along the south wall between Charging Pumps B and C.

Evaluator Cue: (As counter-clockwise handwheel operation is indicated) The handwheel rotates until NO further motion occurs. The valve stem rises during operation.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 5 Inform the Control Room CVC-302 is open.

Critical No Standard:

Contact and report to Control Room Operator that CVC-302 is open.

Evaluator Cue:

As Control Room Operator: Acknowledge report, and then direct operator to locally close CVC-3, Charging Pump Suction Line X-Connect.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 5 of 6

AO-035-JP011, Operate The Emergency Borate Valve Locally, Rev. D Performance Step: 6 AOP-CVC-001, Step 5.b.3 RNO Critical Yes Locally CLOSE CVC-3, Charging Pump Suction Line X-Connect.

Standard: Rotate handwheel clockwise until CVC-3 is closed.

Evaluator Note: Valve is located in the Aux Bldg 586 elevation in the Charging Pump room along the south wall between Charging Pumps B and C.

Evaluator Cue: (As clockwise handwheel operation is indicated) The handwheel rotates until NO further motion occurs. The valve stem lowers during operation.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Performance Step: 7 Inform the Control Room CVC-302 is closed.

Critical No Standard: Contact and report to Control Room Operator that CVC-3 is close.

Evaluator Cue: As Control Room Operator: Acknowledge report.

Performance: SATISFACTORY UNSATISFACTORY Comments:

Terminating Cues: When RWST to Charging Pump local alignment complete (Completion of AOP-CVC-001 step 5.b.3 RNO): This JPM is complete.

Stop Time:

Form NTP-6331 Rev. A Date: JAN 19 2006 Page 6 of 6

Simulator Exercise Guide Job Aid Page 1 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SITE: Kewaunee Power Station PROGRAM: Reactor Operator Program/Senior Reactor Operator Program PROGRAM No.

COURSE: 2009 NRC License Exam Course #: ROI-06-SE-SC01

/ SOI-06-SE-SC01 Total Time 2 Hours Prepared by: Andrew Fahrenkrug /S 01/28/09 Printed Name Instructors Signature Date Reviewed by: Steve Johnson /S 01/30/09 (Optional) Printed Name Simulator Development Checklist Date Instructor Signature Reviewed by: Andrew Fahrenkrug /S 01/23/09 (Optional) Printed Name Simulator Validation Checklist Signature Date Approved by: Terry Evans /S 02/10/09 Printed Name Training Manager Date Approved by:

Mark Goolsbey /S 02/12/09 Printed Name Facility Representative Date

Simulator Exercise Guide Job Aid Page 2 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A REQUIREMENTS Goal of Training: Evaluate the operators response and performance to the following events:

  • High Turbine Vibrations and Rapid Plant Backdown.
  • Reactivity Manipulations
  • Failure of P-485, 1st Stage Turbine Impulse Pressure, during a power reduction (Passive Failure).
  • Failure of SG B narrow range level instrument, LT-471 controlling channel.
  • Failure of SI Pump B to Auto Start with a valid ESF signal, SI Pump A has no power
  • SRO/US analysis of plant conditions for Technical Specification application

Simulator Exercise Guide Job Aid Page 3 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A Learning Objectives: While responding as the RO/BOP satisfactorily MEET the performance requirements in TR-AA-400 for the following competencies

a. Understand and Interpret Annunciator and Alarm Signals
b. Diagnose Events and Conditions based on Signals and Reading
c. Understand Plant and System Response
d. Comply with and Use Procedures and Technical Specifications
e. Operate the Control Board
f. Communicate and Interact with Other Crew Members (RO4-06-SED01.002) ROI-06-SE-SC01.001 / SOI-06-SE-SC01.001 While responding as the US satisfactorily MEET the performance requirements in TR-AA-400 for the following competencies
a. Understand and Interpret Annunciator and Alarm Signals
b. Diagnose Events and Conditions based on Signals and Reading
c. Understand Plant and System Response
d. Comply with and Use Procedures and Technical Specifications
e. Operate the Control Board
f. Communicate and Interact with Other Crew Members
g. Direct Shift Operations
h. Comply with and Use Technical Specifications (RO4-06-SED01.003) SOI-06-SE-SC01.002 As the US DETERMINE the appropriate event classification in accordance with EPIP-AD-02,Emegency Classification Determination. This objective will be completed at the end of the scenario and may be waived at the lead evaluators discretion SOI-06-SE-SC01.003.

Prerequisites: Enrolled in current ILT class and recommended by station management to take an NRC license exam Training Resources: Simulator KPS Exam Team Member NRC Examiners

Simulator Exercise Guide Job Aid Page 4 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A

References:

OP-KW-GOP-307, Hold at Power Greater than 35%

ARP-47051-U, Turbine Vibration High ARP 47054-T,Turbinre Oil Cooler Temp High/Low OP-KW-AOP-GEN-002, Rapid Power Reduction OP-AA-100 Conduct of Operations OP-AP-300 Reactivity Management N-TB-54, Turbine and Generator Operation NOP-CRD-001, Control Rod Drive System OP-KW-CVC-001, Boron Concentration Control N-HD-11, Heater and Moisture Separator Drain and Bleed Steam System AOP-MISC-001, Response to Instrument Failure TLA-15, RMS Above Normal 47012-B, Radiation Indication Alert 47011-B, Radiation Indication High 47031-Q, Containment Sump A Level High 47031-P, Containment Sump A Level Hi-H AOP-RM-001, Abnormal Radiation Monitor AOP-RC-001,Reactor Coolant Leak OP-KW-OSP-RCS-001, Reactor Coolant System Leak Rate Check AOP-GEN-001, Operator Immediate Actions AOP-MISC-001, Response to Instrument Failure 47043-C, Pressurizer Control Press Abnormal 47043-D, PRZR Pressure Low 47043-E, Pressurizer Level Deviation 47043-F, PRZR Level Low 47091-G Bus 5 Lockout 47091-H Bus 5 Voltage Low E-0, Reactor Trip or Safety Injection E-1, Loss of Reactor or Secondary Coolant

Simulator Exercise Guide Job Aid Page 5 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A Commitments: Per Outline submitted to NRC for 2009 Operating exam Evaluation Method: Dynamic Simulator Historical Record: Initial Issue Operating Experience: Not required for evaluations Related PRA Initiating Event with Core Damage Frequency:

Information:

Total CDF/LERF (4.8E-5/yr)/(6.5E-06/yr)

Small Break LOCA percentage of CDF/LERF (2%)/(0%)

Transient with Feed water Available percentage of CDF/LERF (19%)/(7%)

Other percentage of CDF/LERF (3%)/(2%)

Important Components:

System CDF Importance Rank LERF Importance Rank EDG 1st 1st SI 12th 3rd EHV 7th 12th AFW 3rd 2nd RCS 12th 9th CDF Post Event Important Operator Actions None LERF Post Event Important Operator Actions None

Simulator Exercise Guide Job Aid Page 6 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A OVERVIEW INITIAL CONDITIONS:

1. Standard IC-12 (100% power MOL)
2. The following equipment is OOS:
a. TD AFW Pump: Auxiliary Lube Oil Pump Overhaul per CMP-05B-03
b. NI Channel N43: Failed and removed from service per AOP-GEN-MISC-001 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago
c. Standard cycle OOS items

Simulator Exercise Guide Job Aid Page 7 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A QUANTITIVE ATTRIBUTES Event Malf. Event Event No. No. Type*

Description Preload SI05B C Failure to Auto Start, SI Pump 1B RX222 Preload 579.8 I PT-485 HP Turbine Impulse Pressure fails as-is (~ 579.6 psig)

TU03A, Turbine Bearing High Temperature (Front Bearing) [Turbine 1 40 C (BOP) High Vibrations, Bearing #1]

N Load backdown due to turbine high vibrations R Power reduction due to turbine high vibrations PT-485, Turbine First Stage Pressure instrument fails as-is RX222 affecting steam dumps and auto rod control (Tref) during 2 579.8 I (Both) backdown RC08 RCS System Leaks. 15 gpm RCS leak develops at RCS Loop A 3 0.5 C (RO) RHR line tap.

FW207 LT-471 SG B level transmitter 24046 Yellow. SG B controlling 4 0, 1:00 I (BOP) level channel fails low over 60 seconds RC03A Loss of Coolant - Hot Leg (1A). RCS leak becomes small break 5 0.2 M (Both) LOCA resulting in reactor trip and Safety Injection Loss of 4160 (Bus 1-5). Bus 5 lockout resulting in loss of Train A 6 ED08E C (BOP) ECCS/ESF equipment. DG starts on SI signal Failure to Auto Start, SI Pump B requiring manual start of SI 7 SI05B C (RO) Pump

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

Simulator Exercise Guide Job Aid Page 8 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A Malfunctions:

Before EOP Entry:

1. Turbine High Vibrations, Bearing #1
2. PT-485, Turbine first stage pressure failure
3. RCS Loop A Hot Leg Leak
4. LT-471, SG B controlling level channel failure After EOP Entry:
1. Small Break LOCA
2. Bus 5 Lockout at time of reactor trip
3. SI Pump B failure to auto start Abnormal Events:
1. Turbine High Vibrations, Bearing #1
2. PT-485, Turbine first stage pressure failure
3. RCS Loop A Hot Leg Leak
4. LT-471, SG B controlling level channel failure Major Transients:
1. Small Break LOCA, Reactor Trip with Bus 5 Lockout at time of reactor trip and failure of SI Pump B to auto start

Simulator Exercise Guide Job Aid Page 9 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A Critical Tasks:

1) Manual Start of SI Pump B a) SAFETY SIGNIFICANCE: No safety injection with a LOCA in progress b) CUE No SI pumps running with indications of a LOCA and SI required.

c) MEASURABLE PERFORMANCE INDICATOR: Evaluator observes the crew recognizing the need to manually start SI pump B and observes the RO starting SI Pump B before transitioning from E-0 or stopping RXCP Pumps d) PERFORMANCE FEEDBACK: SI Pump B running with SI flow indicated

2) A EDG to PULLOUT a) SAFETY SIGNIFICANCE: Degrade Emergency Power Capacity by allowing the EDG to run without service water b) CUE: A EDG running without service water. SI signal and BUS 5 lockout c) MEASURABLE PERFORMANCE INDICATOR: Crew places A EDG to pullout before damage to EDG as indicated by a mechanical lockout on EDG A d) PERFORMANCE FEEDBACK: A EDG stopped
3) : STOP RXCPs a) SAFETY SIGNIFICANCE: The purpose of tripping the RXCPs during SBLOCA accident conditions is to prevent unnecessary depletion of the RCS water inventory through at the break in the RCS which could lead to severe core uncovery if the RXCPs were tripped for some reason later in the accident.

b) CUE: RXCPs running during small break LOCA and Subcooling less than 15 °F [37 °F] with at least one SI pump running and capable of delivering flow.

c) MEASURABLE PERFORMANCE INDICATOR: Crew Stops RXCPs before transitioning from E-0 and after verifying at least one SI pump is running and capable of delivering flow d) PERFORMANCE FEEDBACK: RXCPs stopped

Simulator Exercise Guide Job Aid Page 10 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SEQUENCE OF EVENTS:

Event 1: At the direction of the Lead Examiner, Turbine Bearing High Temperature/High Vibration.

Turbine Bearing High Temperature on Bearing #1 results in increased turbine vibration. Alarm 47051-U, TURBINE VIBRATION HIGH, actuates. The ARP will direct the crew to lower turbine load to reduce vibration level. Engineering will report that the condition appears to be caused by a steam imbalance and recommends a power reduction to 90% within 20 minutes. The US will direct the load reduction using AOP-GEN-002, Rapid Load Reduction. The RO will perform a boration and monitor reactivity parameters for the load reduction. The BOP will manipulate the turbine controls and monitor secondary plant parameters during the load reduction. Vibrations will lower and stabilize as load is reduced.

Event 2: Passive failure, inserted at the start of the scenario, PT-485 fails as-is when turbine power is at 100%.

Turbine first stage pressure fails as-is, PT-485. The instrument is stuck when the crew takes the shift; passive failure. Tref will remain constant during the load reduction. Tave-Tref meter will not be consistent with other plant indications, PPCS will alarm for P-486/P-485 deviation and rod motion will not be consistent with expectations for a rapid power reduction. The crew will diagnose the failure of the instrument. The US will direct entry into OP-KW-AOP-MISC-001, Response to Instrument Failure. The RO will be required to take manual rod control and insert rods as necessary to maintain Tave. Steam Dump control is also affected as steam dumps will not respond correctly to high RCS Tave since with Tref elevated. The BOP will be required to place steam dump controls to STEAM PRESSURE mode. Actions for manual rod control and steam dumps are directed by OP-KW-AOP-MISC-001, Response to Instrument Failure.

Event 3: At direction of Lead Examiner, RCS Hot Leg Leak of 15-20 gpm.

A RCS leak of approximately 15 to 20 gpm will develop on the RCS Loop A Hot Leg at the RHR piping weld. Containment humidity and pressure will rise. The speed of charging pump in AUTO will increase to maintain PRZR level on program. Containment sump A level will rise and annunciators 47031-Q, Containment Sump A Level High and 47031-P, Containment Sump A Level Hi-HI will activate. The crew will diagnose a RCS leak and per ARPs OP-KW-ARP-47031-Q, Containment Sump A Level High, and OP-KW-ARP-47031-P, Containment Sump A Level Hi-Hi, and the US will direct entry into OP-KW-AOP-RC-001, Reactor Coolant Leak. The crew will stabilize the plant and determine a leak rate. Technical Specification 3.1.d.1.B limits unidentified leakage to 1 gpm. ACTION statement 3.1.d.2 requires the leakage be reduced to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. ACTION statement 3.1.d.3 requires action to achieve HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within an additional 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, if the time limit of 3.1.d.2 is exceeded. EAL classification SU5.1, Unidentified or pressure boundary leakage > 10 gpm.

Simulator Exercise Guide Job Aid Page 11 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A Event 4: At direction of Lead Examiner, LT-471 SG B control level channel fails low from current value.

Steam Generator B controlling level channel (LT-471) will fail low (from 44%) over 60 seconds. The failure will result in an increase in feed flow to Steam Generator B. Steam Generator B level and feed flow alarms will rise and alert the BOP to the abnormal condition. Per OP-KW-AOP-GEN-001, Immediate Operator Actions (for abnormal SG level), the BOP will take FW-7B to manual and maintain SG level between 30%

and 50%. The crew will transition to OP-KW-AOP-MISC-001, Response to Instrument Failure, to address the failed channel. Technical Specification 3.5.b is addressed. Table TS 3.5-2, item 12 (Lo-Lo SG water level reactor trip) is verified satisfied with the two other level channels (LT-472 & LT-473) for SG B OPERABLE. Table TS 3.5-3, items 4.a and 5.a (SG Lo-Lo level AFW auto start) is verified satisfied with the two other level channels for SG B OPERABLE. TS Table 3.3-4, item 4.a (Hi-Hi SG level FW Isolation) level of redundancy is not satisfied until the bistable for Hi-Hi SG Level associated with LT-471 is tripped.

This requires implementation TS 3.5.c to place the plant in hot shutdown. The note in OP-KW-AOP-MISC-001 defines the time requirement as soon as practical in TS 3.5.c as using the time requirements of TS 3.0.c. The crew has one hour to trip the Hi-Hi SG level bistable associated with LT-471 or commence a plant shutdown to hot shutdown. TS 3.0.c time requirements are within one hour action shall be taken to place the plant in a mode in which the specification does not apply by placing it, as applicable, in: Hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, at least hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Event 5: At direction of Lead Examiner, RCS leak becomes a SBLOCA exceeding charging capacity.

The RCS leak worsens and becomes a small-break LOCA exceeding charging capability. A reactor trip and safety injection will occur. RXCPs will be stopped using the E-0 Foldout Page RXCP Trip Criteria when subcooling and SI injection capability conditions are satisfied. (NOTE: Event 7 involves NO SI Pumps running and no SI flow when SI flow should occur. Tripping RXCPs should NOT occur until after SI Pump B is started.) EAL escalation FA1, ALERT: Any Loss or any potential loss of either the fuel clad or RCS (Table F-1). Table F-1 Fission product barrier reference table: RCS Barrier, Potential Loss, RCS leak rate un-isolable > 60 gpm the capacity of charging pump in normal charging mode.

Event 6: Initiated with Reactor Trip, Bus 5 Lockout due to ground fault.

At the time of the reactor trip, Bus 5 will lockout due to ground fault. This will remove power from the Train A Safeguards (ECCS/ESF) equipment. DG A will start on the Safety Injection signal but will run with no cooling water supplied from Service Water System. The BOP operator will stop DG A and place its control switch in PULLOUT using ARP OP-KW-ARP-47091-G, Bus 5 Lockout, to prevent damage to DG A.

Event 7: Initiated with SBLOCA, SI Pump B fails to auto start.

SI Pump B will fail to auto start on the Safety Injection. This will result NO SI Pumps running for the small break LOCA. The RO will start SI Pump B as directed in E-0 while performing ATTACHMENT A (NOTE:

The step may be brought forward using guidance of UG-0 and started when the failure to run is noted.)

Scenario Termination:

The crew will continue the actions of E-0 to ensure Safeguards equipment is operating as required.

Diagnosis will be made of an RCS leak and transition will be made to E-1. Termination of the scenario will be made at the lead evaluators discretion after the crew transitions to E-1.

Simulator Exercise Guide Job Aid Page 12 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A TASKS Task Number Task Title SRO Tasks:

1190190302 Apply Technical Specifications During Plant Operations 1190030502 Determine Emergency Classification 1190070502 Coordinate the Implementation of the IPEOPs A030010402 Perform a Rapid Power Reduction Demonstrate an understanding of the responsibility and requirements for the Control Room 1190330302 Supervisor RO Tasks:

0540030401 Respond to Abnormal Turbine Vibration Annunciator 0540110401 Respond to a Failure to a P-485 Instrument Failure A030010401 Perform a Rapid Power Reduction 0360030401 Respond to an unidentified RCS leak 0450090401 Respond to an abnormal condition with R-11 containment particulate monitor 0450100401 Respond to an abnormal condition with R-12 containment gas monitor 1190020001 Demonstrate and understanding of sensors and detectors Transfer Feedwater Control from Automatic to Manual Control during Abnormal Feedwater 05A0030401 System Operation 0390060401 Respond to a Bus 5 or 6 Lockout 0100010401 Respond to abnormal Diesel Generator Operation A(B)

E010010501 Respond to a loss of Primary or Secondary coolant E000010501 Respond to a Reactor Trip Condition with Safety Injection 1190110301 Operate the plant IAW technical specifications 0350070101 Operate the Charging and Volume Control System during Steady State Conditions 0350230101 Control the RCS Boron Concentration by the use of Boration 0360180101 Stop a RXCP

Simulator Exercise Guide Job Aid Page 13 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A __

SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

1. INITIAL CONDITIONS:
  • Standard IC-12
  • Mode: Operating
  • Exposure: 10, 000 MWD/MTU
  • Power: 99.5%
  • Boron: (CB): 968 ppm
  • Temperature 572ºF
  • Pressure: 2236
  • Xenon: EQU
  • Rods: ARO
  • Generator: 601 MWe
2. SIMULATOR SETUP: 1. Reset to IC# 12 and go to run The following forms are needed during the 2. Insert DVD for recording
3. Remove T/D AFW Pump from SERVICE scenario and are to be placed in the booth. by aligning the following equipment and placing tags on the equipment
  • MS-102 - PULLOUT No Additional Material Need For Booth Operator
  • MS100A - CLOSE
4. Position the following switches to N43 channel o Upper Section switch on Detector Current Comparator

Simulator Exercise Guide Job Aid Page 14 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Shift Manager Status board information o Lower Section switch on Detector Current Comparator Equipment OOS o Rod Stop Bypass switch on T/D AFW Pump for Aux Lube Oil Pump Miscellaneous Control and Overhaul TS 3.4.b.4.A. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO. Indicating Panel N43 Failed and Removed from Service per o Power Mismatch Bypass switch on MISC-001 at XX:XX (four hours prior to the Miscellaneous Control and start of the scenario) TS Table 3.5-2 item 2, Indication Panel 5, and 6 condition are met. o Comparator Channel Defeat switch on Comparator And Rate drawer 3.1.a.5.A.1 D For PR-2A Seat Leakage.

PR-1A closed with Power Available o N43A drawer Control Power breaker to OFF Standard Cycle OOS items 5. Position AS-31/AS-35, R-11 and R-12 Remarks Sample return to return to the containment.

Protected train = A 6. OPEN and Run CAEP file. ILT Risk CDF/LERF= Yellow SEE01.cae. After file has run for one minute close CAE file.

SPER / WRs 7. Verify the following Status Lights are lit:

None PR N43 P8 (44907-0403) o PR N43 P10 (44907-0503) o PR N43 Low Range Hi Flux (44907-0603) o PR N43 Hi Range Hi Flux (44907-0703) o Loop B OTT (44907-0507) o PR N43 Hi Flux Rate (44907-0803) o N43 Rod Stop bypassed (44906-0601) o Loop B Chan 3 OTT (44904-0202)

Simulator Exercise Guide Job Aid Page 15 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS GENERAL 8. Verify the following annunciator lights are lit:

Consecutive days of operation ___30____ o OTT High (47033-C)

G-1 Closed (indicate date last month) JD o OTT Channel RNBACK/RDSTP xxx Alert (47041-R) o Power Range Positive Rate Channel Burn up 10,000 MWD/MTU Alert (47032-K)

Sirens Lost Coverage % __0__ o Power Range Negative Rate Channel Alert (47032-J)

Sirens OOS __0__ o Power Range High Flux (47031-M)

RCS and Pressurizer boron = 968 ppm o Power Range Detector Voltage Low (47033J)

All other entries are standard

9. Verify the Instructor Station Summary IAW instructions at the beginning of the input summary in this SEG
10. Second verification of the Instructor IAW instructions at the beginning of the input summary in this SEG
11. Start the Monitor File using the NRC Extended Value Monitor File.
12. COMPLETE Simulator Exam Setup Checklist NOTE: If called to the Control Room then wear the badge identifying who you are.

Simulator Exercise Guide Job Aid Page 16 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

3. PRE-SCENARIO:

a) IF this is the first simulator scenario of the week, THEN review the Simulator Differences List with the crew.

b) Provide crew with:

  • Turnover sheets and plant information
  • Copy of CMP-05B-03 c) Cover Simulator Scenario Briefing Sheet in Job Aid 04-01 with the crew
  • Inform the crew that the Lead Evaluator will take response for the Shift Manager. They will acknowledge communications, but their acknowledgment does not mean agreement or disagreement.

d) Brief the crew IAW NUREG 1021 Appendix E (Simulator Test Guidelines) e) Lead Evaluator perform a Pre-Job brief per Job Aid 04-03

Simulator Exercise Guide Job Aid Page 17 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

4. TURNOVER: PROVIDE Shift Turnover When Crew enters the simulator than begin (All) Walk down control boards~ 5 minutes Information. recording on the DVD.

After ~5 minute walk down of boards by the crew. Give the crew the shift.

Shift Direction:

Maintain 100% power.

Simulator Exercise Guide Job Aid Page 18 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

5. SCENARIO:

EVENT 1: HIGH TURBINE VIBRATIONS Human Performance Tools: Procedure Compliance, Clear Communications, Peer Checking Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely controlling plant evolutions, Teamwork Component BOP After the crew takes the shift and directed When directed by the Lead Evaluator insert CREW by the Lead Examiner. TU03A, Front TRIGGER 1 .

Bearing High Temperature will be inserted. Respond to and Diagnose an increase Verify that TU03A, Front Bearing High in turbine vibration above the alert set It will take ~ 2.5 minutes for 47041-U to inserts point, as indicated by the following:

alarm.

Verify RX222, PT-485 HP Turbine Impulse - 47051-U TURBINE VIBRATION Press is preloaded HIGH. (approximately 2 minutes Turbine bearings 1, 2, & 3 vibrations will all from start of event) increase. Only Bearing #1 will alarm.

- Turbine Supervisory panel (HU Tool Clear Communications) indicates increase in bearing Vibrations on the #1 bearing will max out at vibrations.

8 mils for this failure. The crew will - T2051A Turb BRG #1 Metal commence a back down based on Temp (approximately 4 minutes Engineering recommendation. At after the start of the event approximately 95% power the vibrations will begin to lower.

No transient should be in progress at this US Direct implementation of ARP 47051-U time.

NOTE: Max vibrations will be 8 mils on BOP CHECK Turbine Vibrations < 13 mils bearing #1 US CHECK Turbine Load > 90%

Simulator Exercise Guide Job Aid Page 19 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS No transient should be in progress at this US VERIFY no transient in progress to time. stop.

Operator Fundamental: Crew should be BOP MONITOR the Turbine Supervisory monitoring all bearing temperatures for any Panel increase to 13 mils, required trip NOTE: The US should contact SM and ask ROLE: SM (if contacted by the US) US REDUCE Turbine Load to Reduce engineering to investigate. If the crew Turbine Vibration decides to reduce turbine load at this time REQUEST: Acknowledge high turbine turbine vibrations will decrease with load vibrations and contact WWC/Engineering decrease. If the crew only monitors the turbine and does not start a load reduction, RESPOND: Wait 5 minutes and direct the 10 minutes or at the direction of the Lead US to perform a back down to 90% in the Examiner. next 20 minutes.

ROLE: SM (if NOT contacted by the US)

RESPOND: Wait 10 minutes from the start of the event then, inform the US you were contacted by Engineering and direct the US to perform a back down to 90% in the next 20 minutes.

ROLE: EO CREW DIRECT EO to locally monitor Turbine for abnormalities.

NOTE: The crew may call the EO to the Control Room to brief and give a copy of the ARP.

REQUEST: Locally Monitor the Turbine and inform of Bearing #1 high vibrations RESPONSE: Acknowledge knowledge direction to locally monitor the turbine.

Simulator Exercise Guide Job Aid Page 20 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: SM US Contact SM REQUEST: Acknowledge high vibrations on turbine RESPONSE: Acknowledge the Turbine Bearing problem. After 10 minutes inform US that you were contacted by Engineering.

They recommend a 10% power reduction in 20 minutes and you agree with Engineerings recommendation.

Role: EO CREW Direct EO to locally check Turbine REQUEST: Locally check Turbine Lube Oil Lube Oil Temperatures 106-1100F Temperatures

  • TI-12065, Turbine oil cooler outlet
  • TI-12065, Turbine oil cooler outlet temperature temperature
  • TI-12371, Turbine #6 bearing oil
  • TI-12371, Turbine #6 bearing oil temperature temperature RESPONSE: Acknowledge direction, after 3 minutes report
  • TI-12065, Turbine oil cooler outlet temperature 1090F
  • TI-12371, Turbine #6 bearing oil temperature 1060F

Simulator Exercise Guide Job Aid Page 21 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: EO CREW Direct EO to check Turbine Seal Oil REQUEST: Locally check Turbine Seal Oil Temperatures Temperatures

  • Air Side and H2 Side Seal Oil
  • Air Side and H2 Side Seal Oil Temperature 110-1220F Temperature 110-1220F 3/4 TI-12333 3/4 TI-12333 3/4 TI-12334 3/4 TI-12334
  • Air Side and H2 Side Seal Oil
  • Air Side and H2 Side Seal Oil Temperatures 3-50F greater than #6 Temperatures 3-50F greater than #6 bearing oil temperature bearing oil temperature 3/4 TI-12371 3/4 TI-12371 RESPONSE: Acknowledge direction. Then after 5 minutes report that 3/4 TI-12333 = 1120F 3/4 TI-12334 = 1130F 3/4 TI-12371 is 40F greater than # 6 bearing oil temperature

Simulator Exercise Guide Job Aid Page 22 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Power Reduction per AOP-GEN-002 Normal BOP Reactivity RO If the crew elects to VPL down then 47042- If the crew reduces power by use of the US Review AOP-GEN-002 for power Q, Control bank Low limit may come in. VPL then manually insert TRIGGER 30 to reduction.

change malfunction TU003A to a ramp from 40 to 20 over 10 minutes Operator Fundamental - Teamwork The EO/AO may be called to the control US DETERMINE loading rate.Should be room for a brief. If so acknowledge any 1% per minute according the table.

direction given. But add no other information US Should delay the Brief until after load reduction in order to reduce vibrations.

(CAS) US/RO VERIFY Rods in Auto Human Performance: Peer Checking & US/RO DETERMINE reactivity plan Procedure Compliance Operator Fundamental: Precisely Controlling Plant evolutions The crew should use a standard reactivity plan.

A crew brief should be performed for the back down and reactivity plan. All reactivity calculations and manipulations must be peer checked IAW standards.

(CAS) US/RO BORATE the RCS per Attachment G RO SET Boric Acid Totalizer to required quantity RO PLACE CVC-403 hand controller in manual

Simulator Exercise Guide Job Aid Page 23 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO SET CVC-403 hand controller setpoint to 15 RO SET CVC-403 hand controller output to 65 RO POSITION Reactor Makeup Mode Selector switch to BORATE RO POSITION Reactor Makeup Control switch to START RO ADJUST boric acid flowrate as required to null deviation meter RO/BOP PLACE all Pressurizer heaters on (CAS) US/RO CONTROL Charging and Letdown Flow to maintain RCS inventory If the VPL was used to reduce load then the BOP TAKE turbine off VPL crew proceeds.

(CAS) US/BOP PREPARE for Turbine Load ReductionImmediate Load reduction is required.

VERIFY that trigger 30 inserts and TU03A US/BOP PERFORM Turbine Load changes to a ramp from 40 to 20 over 10 Reduction minutes when the power reduction is started ROLE: DEMI (CAS)US INFORM DEMI of Power REQUEST: Informing Power Reduction Reduction RESPONSE: Acknowledge Power Reduction.

(CAS) RO CHECK Rod Position (CAS) RO CONTROL Tave-Tref Deviation

Simulator Exercise Guide Job Aid Page 24 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US REVIEW of SER points (CAS) US/RO/BOP VERIFY Control Systems operating in Automatic.

Simulator Exercise Guide Job Aid Page 25 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 2: PT-485 Fails AS-IS Human Performance Tools: Clear Communications, Self Checking, Peer Checking Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely Controlling Plant Evolutions Instrument Failure RO & BOP Operator Fundamental - closely monitoring CREW Recognizes PT-485 is failed as-is plant conditions based on turbine load reduction and no change in PT-485, and Tref not changing during the down power Human Performance Clear Communications - PO487G, PPCS point P486 Deviation in alarm US Direct implementation of AOP-MISC-001 Attachment M Human Performance- Self Checking and US/RO POSITION Control Rod Bank Peer Checking Selector to MAN Human Performance- Self Checking and US/BOP SHIFT steam dumps to Steam Peer Checking Pressure Mode Operator Fundamental - Precisely US/RO REFER to RD 11.3.4.1 for RCS controlling plant evolutions Tavg versus % Plant Power ROLE: SM US Inform SM of failure REQUEST: Inform failure of PT-485 as-is.

Ask for WWC/IC help RESPONSE: Acknowledge failure of PT-485 as-is and request for assistance DELAY: None

Simulator Exercise Guide Job Aid Page 26 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 3: RCS Loop Hot Leg Leak Human Performance Tools: Procedure Compliance, Questioning Attitude Operator Fundamentals: Teamwork, Closely monitoring plant Conditions, Understand plant design and theory Component RO Technical Specification SRO Crew may implement ARP-47031-Q or When directed by the Lead Evaluator insert Annunciators:

ARP-47031-P which will direct a transition TRIGGER 3 .

to AOP-RC-001 TLA-15, RMS Above Normal Verify that RC08, Reactor Coolant System ARP 47012-B, 47011-B, and TLA-15 will Leaks inserts 47012-B, Radiation Indication Alert direct the crew to AOP-RM-001 47011-B, Radiation Indication High 47031-Q, Containment Sump A Level High Operator Fundamental - Understanding 47031-P, Containment Sump A Level Hi-Hi Plant Design and Theory/Closely monitoring plant conditions ROLE: SM/HP Parameters Identified by Crew REQUEST: Survey the (_____) area based

  • Containment humidity rising on radiation monitor R-XX indications.

RESPONSE: Acknowledge request for

  • Charging Speed increasing survey, you will call back when the
  • PRZR level lowering slowly survey(s) are completed.

DELAY: None

  • Containment Pressure Rising.
  • Rad Monitors Increasing

Simulator Exercise Guide Job Aid Page 27 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ACTIONS of AOP-RM-001 (CAS)US/BOP CHECK if personnel should be evacuated Operator Fundamental: Teamwork Human Performance: Procedure Use and Adherence During the crews performance of the ARPs/AOPs the US should call a brief to ensure crew is aligned and develop plan to execute both AOP-RM-001 and AOP-RC-001.

US/BOP CHECK radiation monitors none failed downscale ACTIONS for R-2 BOP CHECK R-2 ACTIONS for R-7 BOP CHECK R-7 ACTIONS for R-11 BOP POSITION paper drive to FAST for 15 seconds, then to OPERATE BOP CHECK R-11 indication lowering

Simulator Exercise Guide Job Aid Page 28 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS BOP VERIFY the following dampers and valves close

  • TAV-12, Cntmt Purge/Vent Supply
  • RBV-2, Cntmt Purge/Vent Supply B
  • RBV-5, Cntmt Purge/Vent Exhaust
  • RBV-3, Cntmt Purge/Vent Exhaust B
  • LOCA-2B, Post LOCA H2 Cntmt Vent Isol B ACTIONS for R-12 BOP CHECK R-12 radiation levels normal BOP VERIFY the following dampers and valves close
  • TAV-12, Cntmt Purge/Vent Supply
  • RBV-2, Cntmt Purge/Vent Supply B
  • RBV-5, Cntmt Purge/Vent Exhaust
  • RBV-3, Cntmt Purge/Vent Exhaust B
  • SA-7003B, Hydrogen dilution to Cntmt LOCA-2B, Post LOCA H2 Cntmt Vent Isol B

Simulator Exercise Guide Job Aid Page 29 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS CREW Recognizes RCS leak based on the above indications alarm US Direct implementation of AOP-RC-001 US/RO CHECK RHR not in service for RCS cool down (CAS)US/RO CHECK Reactor Trip NOT required Based on current plant conditions the (CAS)US/RO CHECK PRZR Level Stable AUTO charging pump should keep up with or Trending to Program Level the leakage.

(CAS)US/RO CHECK PRZR Pressure Stable at or trending to desired pressure US/RO VERIFY Automatic Makeup Control NOTE: Steps 6-21 are diagnostic and may US/RO/BOP CHECK Steam Generator be performed in any order Tubes Intact US/RO CHECK Component Cooling System Intact US/RO/BOP CHECK RXCP #1 Seal Leakoff Normal/Stable US/RO CHECK Annunciators RXCP Standpipe High/Low - Clear

Simulator Exercise Guide Job Aid Page 30 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: AO CREW Direct AO to Check Charging Pump REQUEST: Acknowledge direction to check Leakage normal charging pump leakage normal RESPONSE: After delay report all charging pump leakage is normal.

DELAY: 5 minutes US/RO DETERMINE if Leak is on RXCP Seal Injection Lines US/RO DETERMINE if leak is on Letdown Line US/RO DETERMINE if leak is on Charging Line R-2, R-7, R-11, R-12, R-21, and US/RO/BOP CHECK RCS Intact Inside containment humidity should not be stable Containment or normal, o US/RO Check R-2, R-7 Normal and Stable o US/BOP CHECK containment humidity Normal and Stable o US/RO CHECK R-11, R21 Normal o US/RO CHECK R-12 Normal and Stable o US DIRECT SM to Consult with RP to perform a containment entry

Simulator Exercise Guide Job Aid Page 31 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US Direct the implementation of OSP-RCS-001 Technical Specification 3.1.d.1.B limits US DETERMINE if Plant Shutdown is unidentified leakage to 1 gpm. ACTION required statement 3.1.d.2 requires the leakage be reduced to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. o US RCS Operational leakage does ACTION statement 3.1.d.3 requires action NOT comply with TS 3.1.d. RCS to achieve HOT SHUTDOWN within 6 Operational Leakage hours and COLD SHUTDOWN within an additional 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, if the time limit of 3.1.d.2 is exceeded.

EAL classification SU5.1, Unidentified or pressure boundary leakage > 10 gpm.

ROLE: SM US INFORM SM of need to shutdown REQUEST: Inform of need to shutdown because of RCS leakage.

RESPOND: Acknowledge RCS leak rate and need to shutdown will consult with station management DELAY: None

Simulator Exercise Guide Job Aid Page 32 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 4: Steam Generator B controlling Level Channel LT-471 Fails Low Human Performance Tools: Procedure Compliance Operator Fundamentals: Closely Monitoring Plant Conditions Instrument BOP Technical Specification SRO ARP 47062-D, 47062-E and 47064-D will When directed by the Lead Evaluator insert Annunciators:

direct the manual control of FW-7B and TRIGGER 5 .

direct transition to AOP-MISC-001 47062-D, S/G B Program Level Deviation Verify that FW207 LT-471 SG B Level Transmitter 24046 Yellow inserts 47062-E, S/G B Bypass CV Level Deviation 47064-D, S/G B Level Low Operator Fundamentals: Closely BOP Identify B Steam Generator level Monitoring Plant Conditions changing Human Performance Tools: Procedure US/BOP Implement the Immediate action of Compliance AOP-GEN-001 BOP CHECK B Steam Generator Narrow Range Level - Stable at Program o SHIFT FW-7B SG Feedwater flow controller to MANUAL o THROTTLE FW-7B to maintain SG Narrow Range Level stable between 33 and 50%

Simulator Exercise Guide Job Aid Page 33 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS BOP CHECK Initiating Event - Instrument Failure o Identity failure of LT-471 US Direct the implementation of AOP-MISC-001 US/BOP VERIFY Immediate action of Steam Generator Level Control failure per AOP-GEN-001 are complete US/BOP VERIFY B Steam Generator Feed Regulating Bypass Valve controller is in MANUAL US/BOP RESTORE B Steam Generator level to 44%

ROLE: SM US Inform SM of LT-471 failure REQUEST: Inform of failure of LT-471 and request WWC/IC support RESPOND: Acknowledge failure of LT-471 and the required I&C support DELAY: None US DIRECT I&C to perform corrective maintenance on LT-471

Simulator Exercise Guide Job Aid Page 34 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Table TS 3.5-2, item 12 (Lo-Lo SG water US REFER to TS 3.5.b.

level reactor trip) is verified satisfied with the two other level channels (LT-472 & LT-473) for SG B OPERABLE. Table TS 3.5-3, items 4.a and 5.a (SG Lo-Lo level AFW auto start) is verified satisfied with the two other level channels for SG B OPERABLE.

TS Table 3.3-4, item 4.a (Hi-Hi SG level FW Isolation) level of redundancy is not satisfied until the bistable for Hi-Hi SG Level associated with LT-471 is tripped. This requires implementation TS 3.5.c to place the plant in hot shutdown. The note in OP-KW-AOP-MISC-001 defines the time requirement as soon as practical in TS 3.5.c as using the time requirements of TS 3.0.c.

The crew has one hour to trip the Hi-Hi SG level bistable associated with LT-471 or commence a plant shutdown to hot shutdown.

US DIRECT I&C check existing bistable status to ensure a Reactor trip will not occur

Simulator Exercise Guide Job Aid Page 35 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 5: RCS Leak become a SMALL BREAK LOCA Major RO & BOP EVENT 6: BUS 1-5 Lockout when Reactor Trip Breakers Open Component BOP EVENT 7: SI Pump B fails to Auto start Component RO Human Performance Tools: Clear Communications, Self Checking, Procedure use and Adherence Operator Fundamentals: Closely Monitoring Plant Conditions, Conservative Decision Making, Precisely Controlling Plant Evolutions A INVALID CFS RED path is possible if When directed by the Lead Evaluator insert Annunciators for RCS Leak feed flow is reduced < 210 gpm AND TRIGGER 7.

only the level of the B Steam 47031-P, Containment Sump A Level Hi-Hi Verify that RC03A Loss of Coolant Accident Generator is greater than 4% [13%]

- Hot Leg (1A) inserts 47031-Q, Containment Sump A Level High (adverse containment)

Verify that SI05B Failure to Auto Start, SI 47043-C, Pressurizer Control Press Pump 1B already inserted Abnormal Gaitronics does NOT work with the loss 47043-D, PRZR Pressure Low of Bus 1-5 until the power supply has 47043-E, Pressurizer Level Deviation been shifted.

47043-F, PRZR Level Low Operator Fundamentals: Closely RO reports that not maintaining PRZR level Monitoring Plant Conditions, Precisely with letdown isolated and charging Controlling Plant Evolutions maximized - or - may report that VCT level Human Performance Tools: Clear cannot be maintained.

Communications

Simulator Exercise Guide Job Aid Page 36 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human Performance Tools: Clear US DIRECT Manual tripping of the reactor Communications and implementation of E-0 VERIFY that BLIND TRIGGER 29 activates US/RO MANUALLY TRIP the Reactor to insert malfunction ED08E Loss of 4160 V Bus 1-5 when the reactor trip breakers open.

RO VERIFY Reactor Trip BOP VERIFY Turbine Trip Verify Bus 5 Lockout occurred BOP VERIFY bus 5 or 6 has Power Operator Fundamentals: Closely RO CHECK if SI is actuated Monitoring Plant Conditions SI is actuated but NO SI Pumps are running

Simulator Exercise Guide Job Aid Page 37 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human Performance Tools:, Self Checking RO VERIFY automatic actions using ATTACHMENT A CRITICAL TASK - Manual Start of SI Pump B o CHECK both SI Pumps Running SAFETY SIGNIFICANCE: No safety o START SI Pump B injection with a LOCA in progress CUE No SI pumps running with indications of a LOCA and SI required.

MEASURABLE PERFORMANCE INDICATOR: Evaluator observes the crew recognizing the need to manually start SI pump B and observes the RO starting SI Pump B before transitioning from E-0 or stopping RXCP Pumps PERFORMANCE FEEDBACK: SI Pump B running with SI flow indicated

Simulator Exercise Guide Job Aid Page 38 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RXCP trip criteria actions SHOULD NOT be US/RO/BOP IDENTIFY RXCP Trip Criteria carried out until an SI pump is running per Foldout Page o IDENTIFY 1 SI pump Running Operator Fundamentals: Precisely o IDENTIFY RCS subcooling based Controlling Plant Evolutions on CETs <15ºF [37°F]

Human Performance Tools:, Procedure o IDENTIFY Operator controlled use and Adherence cooldown NOT in progress Critical Task: STOP RXCPs o RO STOP and PLACE SAFETY SIGNIFICANCE: The BOTH RXCPs in PULLOUT purpose of tripping the RXCPs during SBLOCA accident conditions is to prevent unnecessary depletion of the RCS water inventory through at the break in the RCS which could lead to severe core uncovery if the RXCPs were tripped for some reason later in the accident.

CUE: RXCPs running during small break LOCA and Subcooling less than 15°F [37°F] with at least one SI pump running and capable of delivering flow.

MEASURABLE PERFORMANCE INDICATOR: Crew Stops RXCPs before transitioning from E-0 and after verifying at least one SI pump is running and capable of delivering flow PERFORMANCE FEEDBACK: RXCPs stopped

Simulator Exercise Guide Job Aid Page 39 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/BOP Recognize EDG A is running without SW.

o US Direct the implementation of ARP-47091-G BOP VERIFY Bus 5 Breakers Tripped and Locked out BOP POSITION Bus 5 voltage Restoring Mode Selector to MAN Human Performance Tools:, Self Checking BOP POSITION Diesel Generator 1A control switch to PULLOUT Critical Task: A EDG to PULLOUT SAFETY SIGNIFICANCE: Degrade Emergency Power Capacity by allowing the EDG to run without service water CUE: A EDG running without service water. SI signal and BUS 5 lockout MEASURABLE PERFORMANCE INDICATOR: Crew places A EDG to pullout before damage to EDG as indicated by a mechanical lockout on EDG A PERFORMANCE FEEDBACK: A EDG stopped

Simulator Exercise Guide Job Aid Page 40 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: EO RO Verify Feedwater Isolation REQUEST: Locally close FW-12A, If FW-12A will not close then close FW-6A or FW-8A AND FW-9A or FW-11A RESPONSE: Acknowledge request, wait 5 minutes insert TRIGGER 9 and report FW-12A is closed locally ROLE: AO RO VERIFY Containment and Containment REQUEST: Close CC-654 Ventilation Isolation RESPONSE: Acknowledge request wait 3 minutes and report CC-654.

AFW pump A is not running due to Bus 1-5 (CAS)US/BOP VERIFY AFW Pumps Lockout Running o BOP Verify AFW Pump B running (CAS)US/BOP CHECK AFW Pump Discharge Pressures US/BOP VERIFY Secondary Heat Sink US/RO CHECK RXCP Seal Cooling Normal (CAS)US/RO/BOP VERIFY RCS Temperature Control US/RO CHECK Pressurizer PORVs -

BOTH Closed

Simulator Exercise Guide Job Aid Page 41 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/RO CHECK Pressurizer Spray Valves Closed US/RO CHECK If RXCPs should remain running - None running US/RO/BOP INITIATE monitoring CSF Status Trees US/BOP CHECK if any SG Faulted US/RO/BOP CHECK if Steam Generator tubes are intact US/RO/BOP CHECK if RCS is intact inside of containment o Transition to E-1

Simulator Exercise Guide Job Aid Page 42 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EAL Determination shall be conducted SRO/US identify the current EAL at the as a JPM for the SRO by an examiner if END of the scenario using the EAL matrix .

required Correct Classification is ALERT, FA1 Emergency Plan Student may refer to EPIP-AD-02 to assist in EAL determination

  • A classification of Alert will be determined due to the RCS leak rate greater than 60 gpm. EAL FA1 for Loss of 1 Barrier (Table F-1)
  • Table F-1 Fission Product Barrier Reference Table o RCS Barrier - LOSS - Item 2 RCS leak rate greater than makeup capacity as indicated by a loss of subcooling margin.

Note: EAL SU5.1 during initial RCS leak

Simulator Exercise Guide Job Aid Page 43 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

6. SCENARIO END: a. FREEZE simulator at direction of Lead Examiner Termination of the scenario will be made at the lead evaluators discretion after the b. STOP DVD recorder. IF this is the crew transitions to E-1. last session of the week, THEN FINALIZE the DVD (optional)
c. Ensure all EXAM material is collected
7. POST-SCENARIO:
a. ENSURE simulator problems encountered during the scenario are documented IAW site specific process.
b. ENSURE training attendance is documented on, Training Attendance Report.

Simulator Exercise Guide Job Aid Page 44 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A VERIFICATION INSTRUCTIONS These Malfunctions/Remotes/Overrides/Blind triggers SHALL be verified by two independent checkers prior to the start of the scenario after running the ILT-09-SEE01cae file INPUT

SUMMARY

Delay Ramp Event Severity Relative Description Time Time Trigger Or Value Final Value Order MALFUNCTIONS 47034-O SER1670 Source Range High Flux At Shutdown Alarm Blocked 00:00:00 00:00:00 Preload Block Block

  • SER0966 47043-P Bank D Rod Withdrawal High Limit 00:00:00 00:00:00 Preload Block Block
  • SER0642 47093-H Bus 5 RAT Source Breaker 1-503 43 Control Switch in Manual 00:00:00 00:00:00 Preload Block Block
  • SI05B Failure to Auto Start, SI Pump 1B 00:00:00 00:00:00 Preload False True 5 RX222 PT-485 HP Turbine Impulse Press 00:00:00 00:00:00 Preload 579.8 579.8 1 TU03A Turbine Bearing High Temperature (Front Bearing) 00:00:00 00:00:00 1 0 40 1 RC08 Reactor Coolant System Leaks 00:00:00 00:00:00 3 0 0.5 2 FW207 LT-471 SG B Level Transmitter 24046 Yellow 00:00:00 00:01:00 5 44 0 3 RC03A Loss of Coolant Accident - Hot Leg (1A) 00:00:00 00:00:00 7 0 0.2 4
  • Denotes Malfunctions that preload with ALL IC loads

Simulator Exercise Guide Job Aid Page 45 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A INPUT

SUMMARY

Delay Ramp Event Severity Relative Description Time Time Trigger Or Value Final Value Order REMOTE FUNCTIONS RP141 407C-OVER TEMPERATURE TRIP NORMAL/TRIP 00:00:00 00:00:00 Preload Norm Trip Preload RP142 407D-ROD STOP NORMAL/TRIP 00:00:00 00:00:00 Preload Norm Trip Preload IA101 AIR COMPRESSOR 1C LOCAL CONTROL AUTO/OFF/ON 00:00:00 00:00:00 Preload Auto Off Preload OVERRIDES MVC DO-44910-0804 FW TO S/G A FW12A CLOSED 00:00:00 00:00:00 9 Off On 5 MCA DO-46113-G MS-100A 00:00:00 00:00:00 Preload Off Off Preload MCA DO-46114-G MS-100B 00:00:00 00:00:00 Preload Off Off Preload MVA DO-44561-C-COUNT CVCS TOTALIZER COUNT 00:00:00 00:00:00 Preload Off Off Preload

Simulator Exercise Guide Job Aid Page 46 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A BLIND TRIGGERS (GUN SYMBOL)

Event #29 Event Action: hwzrpg5622==1.0 Command: IMF ed08e Trigger activates on reactor trip breaker train A opening and will insert ED08E loss of 4160 Volt to bus 1-5 Event #30 Event Action: hwztcs1s12==1.0 Command: IMF tu03a 20 00:10:00 40 Modify Malfunction TU03A to Decrease as Power Decreases. Activates upon depression of the Main Turbine GO Button

Simulator Exercise Guide Job Aid Page 47 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A CAEP FILE ILT-09-SEE01.cae IMF SI05B 00:00:00 N/A N/A N/A True 5 IMF RX222 579.8 00:00:00 N/A N/A N/A 579.8 1 IMF TU03A (1) 40 00:00:00 N/A N/A N/A 40 1 IMF RC08 (3) .5 00:00:00 N/A N/A N/A 0.5 2 IMF FW207 (5) 0 60 44 00:00:00 N/A N/A N/A 0 3 IMF RC03A (7) .2 00:00:00 N/A N/A N/A 0.2 4 IRF RP141 TRIP 00:00:00 N/A N/A N/A TRIP Preload IRF RP142 TRIP 00:00:00 N/A N/A N/A TRIP Preload IOR DO-44910-0804 (9) ON 00:00:00 N/A N/A N/A ON 5 IOR DO-46113-G OFF 00:00:00 N/A N/A N/A OFF Preload IRO DO-46114-G OFF 00:00:00 N/A N/A N/A OFF Preload IRF IA101 OFF 00:00:00 N/A N/A N/A OFF Preload IOR DI-46412-CLOSE ON 00:00:00 N/A N/A N/A ON Preload DOR DI-46412-CLOSE 00:00:16 N/A N/A N/A N/A N/A IOR DO-44561-C-COUNT OFF 00:00:00 N/A N/A N/A OFF Preload TRGSET 30 HWZTCS1S12==1.0 00:00:00 N/A N/A N/A N/A N/A TRG 30 IMF TU03A 20 00:10:00 40 00:00:00 N/A N/A N/A 40 1 TRGSET 29 HWZPG5622==1.0 00:00:00 N/A N/A N/A N/A N/A TRG 29 IMF ED08E 00:00:00 N/A N/A N/A TRUE 5

Simulator Exercise Guide Job Aid Page 48 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SIMULATOR SCENARIO DEVELOPMENT CHECKLIST Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

Yes No

1. The scenario contains objectives for the desired tasks and relevant Human Performance Tools.
2. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.
3. Plant PRA initiating events, important equipment, and important tasks are identified.
4. Turnover information includes a Daily At Power Risk Assessment provided by the PRA Group.
5. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.
6. The Scenario Guide includes responses for all communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices.
7. The scenario includes related industry experience. Not Required for Evaluations
8. Training elements and specific Human Performance elements are addressed in the Scenario Critique Guide to be used by the Critique Facilitator. The Critique Guide includes standards for expected performance.
9. Any identified Critical Tasks possesses the following elements (NUREG-1021):
  • Essential to safety with adverse consequences or significant degradation,
  • Cue(s) prompt the Operator to respond.
  • Defined and measurable performance indicators.
  • Performance feedback.

The use of N/A is allowed for item 9 only if this is NOT an evaluated scenario.

10. Technical Specifications including Limiting Conditions for Operation, reactivity briefings, and Emergency-Plan entries are addressed as appropriate.

Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

Simulator Exercise Guide Job Aid Page 49 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A SIMULATOR EXERCISE VALIDATION CHECKLIST Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

Yes No

1. The desired initial condition(s) could be achieved.
2. All malfunctions and other instructor interface items were functional and responded to support the simulator Scenario.
3. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.
4. All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.
5. During the simulator scenario, observed changes corresponded to expected plant response.
6. Did the scenario satisfy the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence?
7. The simulator is capable of being used to satisfy learning or examination objectives without exceptions, significant performance discrepancies, or deviation from the approved scenario sequence.
8. Any identified Critical Tasks possesses the following elements (NUREG-1021):
  • Essential to safety with adverse consequences or significant degradation,
  • Cue(s) prompt the Operator to respond.
  • Defined and measurable performance indicators.
  • Performance feedback.

The use of N/A is allowed for item 8 only if this is NOT an evaluated scenario.

Discrepancies noted (Check none or list items in comments field) None Comments:

Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

Simulator Exercise Guide Job Aid Page 50 of 50 SEG# ROI-06-SE-SC01/SOI-06-SE-SC01 Rev: A Applied & Implemented All Information Passed on to All Any Knowledge or Performance Corrective Actions if TS/TRM (PP-1) Identified All Applicable Correctly Crew Members (i.e., briefs) Deficiencies Required As Time Allowed 3.1.d.1.B Yes No Yes No Yes No 3.1.d.2 Yes No Yes No Yes No 3.1.d.3 Yes No Yes No Yes No 3.5.b Yes No Yes No Yes No Table TS 3.5-2, Yes No Yes No Yes No item 12

. Table TS 3.5-3, Yes No Yes No Yes No item 4.a

. Table TS 3.5-3, Yes No Yes No Yes No item 5.a TS Table 3.3-4, Yes No Yes No Yes No item 4.a TS 3.5.c Yes No Yes No Yes No TS 3.0.c Yes No Yes No Yes No EALs All Information Passed on to All Any Knowledge or Performance Corrective Actions if Identified All Applicable Classified & Notified Timely (EP Group) Crew Members (i.e., briefs) Deficiencies Required SU5.1 Yes No Yes No Yes No FA1 Yes No Yes No Yes No Yes No Yes No Yes No Yes No Yes No Yes No Yes No Yes No Yes No Yes No Yes No Yes No Any Knowledge or Performance Corrective Actions if Procedure Compliance (PP-3) Applied & Implemented Correctly As Time Allowed Deficiencies Required Yes No Yes No Yes No Yes No Yes No Yes No Any Knowledge or Performance Corrective Actions if Human Performance Errors (PP-2) Identify All HU Errors or Potential HU Errors Deficiencies Required Identify All Operator Fundamental Errors Or Potential Operator Fundamental Any Knowledge or Performance Corrective Actions if Operator Fundamentals Errors Deficiencies Required

Simulator Exercise Guide Job Aid Page 1 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SITE: Kewaunee Power Station PROGRAM: Reactor Operator Program/Senior Reactor Operator Program PROGRAM No.

COURSE: 2009 NRC License Exam Course #: ROI-06-SE-SC02

/ SOI-06-SE-SC02 Total Time 2.0 Hours Prepared by: Andrew Fahrenkrug /S 1/29/09 Printed Name Instructors Signature Date Reviewed by: Steve Johnson /S 01/29/09 (Optional) Printed Name Simulator Development Checklist Date Instructor Signature Reviewed by: Andrew Fahrenkrug /S 1/22/09 (Optional) Printed Name Simulator Validation Checklist Signature Date Approved by: Terry Evans /S 02/10/09 Printed Name Training Manager Date Approved by:

Mark Goolsbey /S 02/12/09 Printed Name Facility Representative Date

Simulator Exercise Guide Job Aid Page 2 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A REQUIREMENTS Goal of Training: Evaluate crew response and performance for the following events:

  • Controlling channel for PRZR fails high, PT-431 (Blue Channel)
  • Normal Power Reduction
  • Reactivity Manipulations
  • Steam Line Break in Containment
  • Failure of B AFW Pump to Automatically Start after receiving a valid start signal
  • Failure of the ICS system to initiate with a valid Hi-Hi containment pressure signa
  • SRO/US analysis of plant conditions for Technical Specification application

Simulator Exercise Guide Job Aid Page 3 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A Learning Objectives: While responding as the RO/BOP satisfactorily MEET the performance requirements in TR-AA-400 for the following competencies

a. Understand and Interpret Annunciator and Alarm Signals
b. Diagnose Events and Conditions based on Signals and Reading
c. Understand Plant and System Response
d. Comply with and Use Procedures and Technical Specifications
e. Operate the Control Board
f. Communicate and Interact with Other Crew Members (RO4-06-SED01.002) ROI-06-SE-SC02.001 / SOI-06-SE-SC02.001 While responding as the US satisfactorily MEET the performance requirements in TR-AA-400 for the following competencies
a. Understand and Interpret Annunciator and Alarm Signals
b. Diagnose Events and Conditions based on Signals and Reading
c. Understand Plant and System Response
d. Comply with and Use Procedures and Technical Specifications
e. Operate the Control Board
f. Communicate and Interact with Other Crew Members
g. Direct Shift Operations
h. Comply with and Use Technical Specifications (RO4-06-SED01.003) SOI-06-SE-SC02.002 As the US DETERMINE the appropriate event classification in accordance with EPIP-AD-02,Emegency Classification Determination. This objective will be completed at the end of the scenario and may be waived at the lead evaluators discretion SOI-06-SE-SC02.003 Prerequisites: Enrolled in current ILT class and recommended by station management to take an NRC license exam Training Resources: Simulator KPS Exam Team Member NRC Examiners

Simulator Exercise Guide Job Aid Page 4 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A

References:

47041-C Pressurizer Pressure 2385 47043-C Pressurizer Control Pressure Abnormal 47043-D Pressurizer Pressure Low 47043-J Charging Pump in Auto High/Low Speed 47044-F ICCMS Panel Trouble AOP-GEN-001, Operator Immediate Actions AOP-MISC-001, Response to Instrument Failure OP-KW-GOP-307, Hold at Power Greater than 35%

OP-AA-100 Conduct of Operations OP-AP-300 Reactivity Management N-TB-54, Turbine and Generator Operation NOP-CRD-001, Control Rod Drive System OP-KW-CVC-001, Boron Concentration Control N-HD-11, Heater and Moisture Separator Drain and Bleed Steam System 47051-P SW Header Pressure Low 47052-Q Turbine Bldg SW Isolation Alert 47092-I Bus 5 Feeder Bkr Trip 47093-I Bus 5 Feeder Bkr Overload AOP-SW-001, Abnormal Service Water System Operation 47031-Q, Containment Sump A Level 47031-P, Containment Sump A Level HI-HI E-0. Reactor Trip or Safety Injection 47021-F, Containment Spray Actuated E-2, Faulted Steam Generator Isolation E-1, Loss of Reactor of Secondary Coolant

Simulator Exercise Guide Job Aid Page 5 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A Commitments: Per Outline submitted to NRC for 2009 Operating exam Evaluation Method: Dynamic Simulator Historical Record: Initial Issue Operating Experience: Not required for evaluations Related PRA Initiating Event with Core Damage Frequency:

Information:

Total CDF/LERF (4.8E-5/yr)/(6.5E-06/yr)

Transient with Feed water Available percentage of CDF/LERF (19%)/(7%)

Other percentage of CDF/LERF (3%)/(2%)

Important Components:

System CDF Importance Rank LERF Importance Rank RPS 6th 7th AFW 3rd 2nd CDF Post Event Important Operator Actions Operator Fails to Cool Down and Depressurize the RCS LERF Post Event Important Operator Actions Operator Fails to Cool Down and Depressurize the RCS Operator Fails to Isolate 1 of 2 Steam Generators

Simulator Exercise Guide Job Aid Page 6 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A OVERVIEW INITIAL CONDITIONS:

1. Standard IC-12 (100% power (MOL)
2. The following equipment is OOS:
a. TD AFW Pump: Auxiliary Lube Oil Pump Overhaul per CMP-05B-03
b. NI Channel N43: Failed and removed from service per AOP-GEN-MISC-001 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago
c. B Emergency Diesel Generator is OOS for Oil Leak
d. Standard cycle OOS items

Simulator Exercise Guide Job Aid Page 7 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A QUANTITIVE ATTRIBUTES Event Malf. Event Event No. No. Type*

Description RX203 Failure of Pressurizer Pressure Instrument, Controlling Channel 1 100% I (RO) (BLUE) 2 N Load Reduction requested by ATC for Line Work 2 R Power Reduction as requested by ATC SW05A 3 99% C (BOP) SW pump 1A1 trip on over current 3 SW06D C (BOP) Failure to Auto Start SW pump 1B2 MS02A 0.1-

.03% M (Both) over 10 4 minutes Main Steam Line Break Inside containment, Header A 5 RD11A C (BOP) Failure Train A Reactor Trip Breakers to Open 5 RD11B C (BOP) Failure Train B Reactor Trip Breakers to Open 6 FW16B C (BOP) Failure B AFW pump to Auto Start 7 CS03A C (RO) Failure to Auto Start ICS pump A 7 CS03B C (RO) Failure to Auto Start ICS pump B

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

Simulator Exercise Guide Job Aid Page 8 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A Malfunctions:

Before EOP Entry:

1. PT-431 Pressurizer Pressure Instrument failure
2. SW Pump 1A1 Trip
3. SW Pump 1B2 failure to auto start
4. Steam Leak Inside of Containment After EOP Entry:
1. Small Main Steam Line break in Containment with ATWS
2. AFW Pump B failure to auto start
3. ICS failure to initiate Abnormal Events:
1. PT-431 Pressurizer Pressure Instrument failure
2. SW Pump 1A1 Trip
3. SW Pump 1B2 failure to auto start
4. AFW Pump B failure to auto start
5. ICS failure to initiate Major Transients:
1. Small Main Steam Line break in Containment with ATWS

Simulator Exercise Guide Job Aid Page 9 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A Critical Tasks:

1. Open Bus 33 and 43 Feed Breakers:
a. SAFETY SIGNIFICANCE: Required to remove power from Rod Drive MG Set A/B to drop control rods and shutdown the reactor
b. CUE: Reactor did not automatically trip on rate and Reactor trip push buttons on the operator panels did not work
c. MEASURABLE PERFORMANCE INDICATOR:
1) Evaluator observes the BOP opening Bus 33 and 43 feeder breakers during immediate actions of E-0.
d. PERFORMANCE FEEDBACK: Rods Insert and Reactor Power < 5% and decreasing NOTE: GNP-05.16.06 Attachment A section 8, isolation of feed flow to a faulted S/G, the 10 minutes time criteria applies to a MSLB inside containment of design basis size and is not applicable to this scenario.

NOTE: E-0 background document specifies that while isolating AFW flow to the faulted S/G, AFW flow to the intact S/G must be maintained Until level is >5% in order to maintain a secondary heat sink.

NOTE: GNP-05.16.06 Attachment A section 4, Restore AFW flow to steam generators following any design basis accident, time requirement is 10 minutes.

NOTE: T.S. bases 3.4 adequate heat removal is provided by one AFW pump and S/G safeties.

NOTE: If A AFW pump is running, the preferred sequence of critical tasks is to start B AFW pump prior to isolating feed flow to A S/G (E-0 background). As long as total feed flow does not decrease to less than 210 gpm for greater than 10 minutes with both S/G NR levels <5%, the two critical tasks of starting B AFW pump and Isolating Feed flow to S/G A can be performed in any order

2. Start AFW pump B and establish feed flow greater than 210 gpm to S/G B from AFW pump B with both S/G levels less than 5% NR.
a. SAFETY SIGNIFICANCE: Maintain Heat Sink Available.
b. CUE: TD & AFW Pump B not running with indications of faulted S/G A
c. MEASURABLE PERFORMANCE INDICATOR: AFW pump B running and feed establish to S/G B from AFW pump B. Loss of Feed Flow to S/G does not exceed 10 minutes while S/G Narrow range level in both S/Gs is less than 5%
d. PERFORMANCE FEEDBACK: AFW pump B running, delivering feed flow to S/G B as indicated by AFW header B flow greater than 210 gpm and AFW pump B discharge header pressure

Simulator Exercise Guide Job Aid Page 10 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A

3. Isolate Feed Flow faulted S/G A
a. SAFETY SIGNIFICANCE: Prevent excessive RCS cooldown by isolating AFW flow to the faulted S/G as soon as it is identified
b. CUE: Excessive RCS cooldown, Steam Flow Indication, Steam Generator Depressurizing
c. MEASURABLE PERFORMANCE INDICATOR: AFW crossover valve AFW-10A or AFW-10B CLOSED, and AFW flow control valve AFW-2A CLOSED, before or during faulted SG feed isolation step in E-2
d. PERFORMANCE FEEDBACK: Zero flow indication on AFW header A and no main feed water flow.
4. Establish ICS Flow to containment
a. SAFETY SIGNIFICANCE: Containment pressure > 23 psig ICS is required to reduce containment pressure
b. CUE: Containment Pressure > 23 psig and ICS has not actuated
c. MEASURABLE PERFORMANCE INDICATOR: Flow Path Established for at least one train of ICS and ICS Pump started in the train that the flow path was established for. As indicated by flow from the ICS Pump
d. PERFORMANCE FEEDBACK: At least one ICS Pump running and delivering flow. Containment Pressure lowering..

Simulator Exercise Guide Job Aid Page 11 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SEQUENCE OF EVENTS:

Event 1: At the direction of the Lead Examiner, PT-431 Pressurizer Pressure (Blue) Channel fail high.

Controlling channel for PRZR pressure fails high, PT-431(Blue Channel). The failure will cause PRZR and RCS pressure to drop as PRZR heaters turn off and PRZR spray valves open (PS-1A & PS-1B). The RO will manually shut the spray valves per OP-KW-AOP-GEN-001, Immediate Operator Actions. The US will direct transition to OP-KW-AOP-MISC-001, Response To Instrument Failure. Per OP-KW-AOP-MISC-001 the RO will select an operable PRZR pressure channel for PRZR pressure control and input to the PRZR pressure recorder. The US will evaluate Technical Specifications (TS) and tripping bistables. TS for the plant transient are 3.10.l for RCS pressure and 3.10.n for DNBR parameters. TS for failed pressurizer pressure instrument PT-431 include table 3.5-2 item #5-OTT, table 3.5-2 item #7-Low Pressurizer Pressure, table 3.5-2 item #8-High Pressurizer Pressure, and table 3.5-3 item #1d-Pressurizer Low Pressure. All TS requirements for continued operation will be met.

Event 2: At direction of Lead Examiner, ATC requests 6% (36 MWe) back down.

ATC will contact KPS requesting a 36 MWe back down (6%) in the next 90 minutes for emergent transmission line work on Q-303, Q-303 hot. The back down is to ensure post trip grid contingencies are met. The US will direct the back down per OP-KW-GOP-307 section 5.2. The RO will use NOP-CVC-001and NOP-CRD-001 to control reactivity as directed by the standard reactivity plan. The BOP will lower Turbine Load per N-TB-54.

Event 3: At direction of Lead Examiner, SW Pump 1A1 trips and SW Pump 1B2 fails to auto start.

After the 6% back down is complete, service water pump 1A1 will trip and service water pump 1B2 will fail to auto start. The BOP will manually start service water pump 1B2 per OP-KW-ARP-47051-P. After Completion of the ARP the crew will perform AOP-SW-001 to verify system operation. Per TS 3.7.c the crew identifies in TS 3.0.c for two trains of equipment listed in TRM 3.3.1 as OOS. TRM 3.3.1 when a train of service water is declared inoperable then the following administrative limiting conditions for operations apply: TS 3.3.e for an inoperable service water system, TS 3.7.b.2 for an inoperable emergency diesel generator, TS 3.3.d for an inoperable component cooling train, TS 3.3.b for an inoperable safety injection train, TS 3.3.c for an inoperable containment fan coil units train, TS 3.3.b for an inoperable residual heat removal train, and TS 3.4.b for an inoperable auxiliary feed water train. Three trains of AFW inoperable apply TS 3.4.b.2, when the Reactor Coolant Temperature is > 3500F, if three auxiliary Feedwater trains are discovered to be inoperable, initiate immediate action to restore one auxiliary Feedwater train to operable status and suspend all Limiting Conditions For Operations requiring mode changes until one auxiliary Feedwater train is restored to operable status.

Event 4: At direction of Lead Examiner, small steam leak in containment initiates.

A small steam line break in containment will build over 10 minutes. Containment Pressure will slowly build to 3.6 psi causing a Reactor Trip and SI signal to be generated. The crew should decide to manually trip the reactor. TS 3.6.d, if the internal pressure of the reactor containment vessel exceeds 2 psi, the condition shall be corrected within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or the reactor shall be placed in a subcritical condition.

Simulator Exercise Guide Job Aid Page 12 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A Event 5: Automatic reactor trip fails, ATWS.

Automatic reactor trip will fail. The operators will attempt to manually trip the reactor with the push buttons on the control boards, this will fail. Rod insertion will be successful when the BOP de-energizes bus 33 and 43 from the control room. The break size will increase when rods are inserted. EAL Classification SA2.1 ALERT. Failure of reactor protection system instrumentation to complete or initiate an automatic reactor trip once a reactor protection system set point has been exceeded and a manual reactor trip was successful.

Event 6: AFW Pump B fails to auto start.

B AFW pump will fail to Auto Start. The BOP will have to manually start AFW pump B to establish AFW flow and isolate feed flow to the faulted SG A.

Event 7: ICS fails to initiate on Hi-Hi containment pressure.

Failure of ICS to initiate on Hi-Hi containment pressure. The RO will identify containment pressure greater than 23 psi (ICS set point) and ICS has failed to initiate. Manual Pushbuttons will not initiate ICS. The RO will have to perform ICS valve alignment and manually start ICS pumps per Attachment A of E-0.

Scenario Termination:

The crew will continue the actions of E-0 and upon a diagnosis of Faulted SG A transition to E-2.

Termination of the scenario will be after the crew transitions from E-2 to E-1 and/or and the direction of the Lead Examiner.

Simulator Exercise Guide Job Aid Page 13 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A TASKS Task Number Task Title SRO Tasks:

1190190302 Apply Technical Specifications During Plant Operations 1190030502 Determine Emergency Classification 1190070502 Coordinate the Implementation of the IPEOPs Demonstrate an understanding of the responsibility and requirements for the Control Room 1190330302 Supervisor RO Tasks:

0360420401 Respond to a Pressurizer Control Press Abnormal Annunciator 0360410401 Respond to Pressurizer Pressure Low Annunciator 0500020401 Respond to ICCMS Panel Trouble Annunciator 0020070401 Respond to a SW Header Pressure Low Condition 0020080401 Respond to a SW Header Pressure Low Annunciator 0390130401 Respond to a Bus 5(6) Feeder Bkr Overload Annunciator 0390160401 Respond to a Bus 5(6) Feeder Bkr Trip Annunciator 0300040401 Respond to a Containment Sump A High Level 0060100401 Respond to a Steam Gen A(B) pressure low annunciator 1190020001 Demonstrate and understanding of sensors and detectors E000010501 Respond to a Reactor Trip Condition with Safety Injection E020010501 Perform a Faulted SG Isolation 1190110301 Operate the plant IAW technical specifications 0350070101 Operate the Charging and Volume Control System during Steady State Conditions 0350230101 Control the RCS Boron Concentration by the use of Boration

Simulator Exercise Guide Job Aid Page 14 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A __

SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

1. INITIAL CONDITIONS:
  • Standard IC-12
  • Mode: Operating
  • Exposure: 10,000 MWD/MTU
  • Power: 99.5% 1770.4MWth
  • Boron: (CB): 968 ppm
  • Temperature 572ºF
  • Pressure: 2236
  • Xenon: EQU
  • Rods: ARO
  • Generator: 601MWe
2. SIMULATOR SETUP: 1. Reset to IC# 12 and go to run The following forms are needed during the 2. Insert DVD for recording
3. Remove T/D AFW Pump from SERVICE scenario and are to be placed in the booth. by aligning the following equipment and placing tags on the equipment
  • MS-102 - PULLOUT No Additional Material Need For Booth Operator
  • MS100A - CLOSE

Simulator Exercise Guide Job Aid Page 15 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Shift Manager Status board information 4. Position the following switches to N43 channel Equipment OOS o Upper Section switch on Detector T/D AFW Pump for Aux Lube Oil Pump Current Comparator Overhaul TS 3.4.b.4.A. 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO. o Lower Section switch on Detector N43 Failed and Removed from Service per Current Comparator MISC-001 at XX:XX (four hours prior to the o Rod Stop Bypass switch on start of the scenario) TS Table 3.5-2 item 2, Miscellaneous Control and 5, and 6 condition are met. Indicating Panel EDG B declared OOS @ xxxx (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> o Power Mismatch Bypass switch on before scenario) due to oil leak. Expected Miscellaneous Control and return to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Technical Indication Panel Specification 3.7.b.2, 7 day LCO o Comparator Channel Defeat switch (Unplanned Failure) on Comparator And Rate drawer 3.1.a.5.A.1 For PR-2A leakage. PR-1A o N43A drawer Control Power breaker closed with Power Available to OFF

5. Position AS-31/AS-35, R-11 and R-12 Standard Cycle OOS items Sample return to return to the containment.
6. OPEN and Run CAEP file. ILT SEE02.cae. After file has run for one Remarks minute close CAE file.
7. Verify the following Status Lights are lit:

Protected train = A PR N43 P8 (44907-0403)

Risk CDF/LERF= RED, Unplanned Entry o PR N43 P10 (44907-0503)

Because of B EDG Failure. o PR N43 Low Range Hi Flux (44907-SPER / WRs 0603)

None o PR N43 Hi Range Hi Flux (44907-0703) o Loop B OTT (44907-0507) o PR N43 Hi Flux Rate (44907-0803)

Simulator Exercise Guide Job Aid Page 16 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS GENERAL o N43 Rod Stop bypassed (44906-0601)

Consecutive days of operation ___30____ o Loop B Chan 3 OTT (44904-0202)

G-1 Closed (indicate date last month) JD 8. Verify the following annunciator lights xxx are lit:

o OTT High (47033-C)

Burn up 10,000 MWD/MTU o OTT Channel RNBACK/RDSTP Sirens Lost Coverage % __0__ Alert (47041-R) o Power Range Positive Rate Channel Sirens OOS __0__ Alert (47032-K)

RCS and Pressurizer boron = 968 ppm o Power Range Negative Rate Channel Alert (47032-J)

All other entries are standard o Power Range High Flux (47031-M) o Power Range Detector Voltage Low (47033J)

9. Remove B EDG from Service as follows
  • Place EDG B CS in Pullout
  • Place Yellow Caution Tag on EDG B
  • Place BKR 1-603 in Pullout
  • Place Yellow Caution Tag on BKR 1-603
10. Verify the Instructor Station Summary IAW instructions at the beginning of the input summary in this SEG
11. Second verification of the Instructor Station Summary IAW instructions at the beginning of the input summary in this SEG
12. Start the Monitor File using the NRC Extended Value Monitor File

Simulator Exercise Guide Job Aid Page 17 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

13. COMPLETE Simulator Exam Setup Checklist.

NOTE: If called to the Control Room then wear the badge identifying who you are.

Simulator Exercise Guide Job Aid Page 18 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

3. PRE-SCENARIO:

a) IF this is the first simulator scenario of the week, THEN review the Simulator Differences List with the crew.

b) Provide crew with:

  • Turnover sheets and plant information
  • Copy of CMP-05B-03 c) Cover Simulator Scenario Briefing Sheet in Job Aid 04-01 with the crew
  • Inform the crew that the Lead Evaluator will take response for the Shift Manager. They will acknowledge communications, but their acknowledgment does not mean agreement or disagreement.

d) Brief the crew IAW NUREG 1021 Appendix E (Simulator Test Guidelines) e) Lead Evaluator perform a Pre-Job brief per Job Aid 04-03

Simulator Exercise Guide Job Aid Page 19 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

4. TURNOVER: PROVIDE Shift Turnover When Crew enters the simulator than begin (All) Walk down control boards~ 5 minutes Information. recording on the DVD.

After ~5 minute walk down of boards by the crew. Give the crew the shift.

Maintain 100% power Repairs Underway to return both TD AFW pump and B EDG ASAP

Simulator Exercise Guide Job Aid Page 20 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

5. SCENARIO:

EVENT 1:Controlling Channel Pressurizer Pressure PT-431 (Blue Channel) Fails High Human Performance Tools: Procedure Compliance, Clear Communications, Peer Checking Operator Fundamentals: Closely Monitoring Plant Conditions, Knowledge of Plant Design and Theory Instrument RO Technical Specification SRO When directed by the Lead Evaluator insert Annunciators:

TRIGGER 1 47041-C Pressurizer Pressure 2385 Verify that RX203, PT-431 PRZ Press inserts 47043-C Pressurizer Control Pressure Abnormal 47043-D Pressurizer Pressure Low 47043-J Charging Pump in Auto High/Low Speed 47044-F ICCMS Panel Trouble

Simulator Exercise Guide Job Aid Page 21 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamentals: Closely CREW Respond to and diagnose Blue Monitoring Plant Conditions, Knowledge of channel Pressurizer pressure failing high.

Plant Design and Theory Determine need to enter AOP-GEN-001 or ARP 47041-C.

Human Performance Tools: Clear Communications ARP 47041-C Pressurizer Pressure 2385, will direct the crew to close spray valves, de-energize pressurizer heaters and transition to AOP-MISC-001 ARP 47043-C Pressurizer Control Pressure Abnormal, will direct the crew to remove the failed channel if it effects Pressurizer Pressure Control with the PRZR Pressure Channel Selector Switch ARP 47043-D Pressurizer Pressure Low, will direct the crew to the immediate actions of AOP-GEN-001 if a spray valve is open ARP 47043-J Charging Pump in Auto High/Low Speed, will direct the crew to adjust the speed of the charging pump ARP 47044-F ICCMS Panel Trouble, will direct the crew to restore pressure.

AOP-GEN-001 will direct the crew to close spray valves and transition to AOP-MISC-001

Simulator Exercise Guide Job Aid Page 22 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human Performance Tools: Procedure RO CHECK Pressurizer Spray valves Compliance Closed

  • If pressure < 2260 psig, then manually close PS-1A and PS-1B RO CHECK Initiating Event - Failed Instrument Recognize PT-431 as failed US Direct transition to and implementation of AOP-MISC-001 Human Performance Tools: Procedure US/RO VERIFY Immediate actions for Compliance Pressurizer Spray Valve Open per AOP-GEN-001 have been completed Human Performance Tools. Peer Checking US/RO POSITION PRZR Pressure Control Channel Selector switch to a position that does NOT use PT-431 Human Performance Tools. Peer Checking US/RO POSITION PRZR Pressure Recorder Input Selector switch to an operable Channel.

RO RESTORE RCS Pressure 2220-2250 psig Human Performance Tools. Peer Checking US/RO RETURN Pressurizer Spray Valves to AUTO ROLE: SM US inform SM of PT-431 failure RESPONSE: Acknowledge failure of PT-431 US DIRECT I&C to perform corrective maintenance on PT-431

Simulator Exercise Guide Job Aid Page 23 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS TS for the plant transient are 3.10.l for RCS US REFER to TS 3.5.b.

pressure and 3.10.n for DNBR parameters COLR 2.11 pressure shall be > 2217 psig PT-431 control board and > 2219 psig computer indication

  • Table 3.5-2 item #5-OTT (May be entered depending upon crew
  • Table 3.5-2 item #7-Low Pressurizer response time for failed instrument) Pressure
  • Table 3.5-2 item #8-High Pressurizer TS for failed pressurizer pressure Pressure instrument PT-431 include table 3.5-2 item
  • Table 3.5-3 item #1d-Pressurizer Low
  1. 5-OTT, table 3.5-2 item #7-Low Pressure Pressurizer Pressure, table 3.5-2 item #8-High Pressurizer Pressure, and table 3.5-3 All Requirements will be met for T.S.

item #1d-Pressurizer Low Pressure. All TS requirements for continued operation will be met. DNBR T.S.

  • 3.10.l for RCS Pressure
  • 3.10.n for DNBR Parameters
  • COLR 2.11 pressure shall be > 2217 psig control board and > 2219 psig computer indication

Simulator Exercise Guide Job Aid Page 24 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 2: ATC requests a 36 MWe back down in 90 minutes due to emergent work Human Performance Tools: Procedure Compliance, Clear Communications, Peer Checking, Self Checking Operator Fundamentals: Closely Monitoring Plant Conditions, Team work, Precisely Controlling Plant Evolutions, Knowledge of Plant Design and Theory Normal BOP Reactivity RO ROLE: MNO US Implement and direct GOP-307 REQUEST: Informed by ATC that a 36 MWE back down in the next 90 minutes is required to facilitate emergent transmission line work on Q-303. Back down the plant 36 MWE at a speed of 1/2% per minute in the next 60 minutes to ensure post trip grid contingencies are met.

Operator Fundamentals: Team work, US/RO PERFORM reactivity estimate Precisely Controlling Plant Evolutions The crew should use a standard reactivity plan.

A crew brief should be performed for the back down and reactivity plan. All reactivity calculations and manipulations must be peer checked IAW standards.

US/BOP REDUCE load per N-TB-54

Simulator Exercise Guide Job Aid Page 25 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human Performance Tools: Peer Checking US/RO PERFORM reactivity adjustments using NOP-CRD-001 and NOP-CVC-001 N-CRD-49 has been replaced by NOP-CRD-001 US DETERMINE unloading rate - 1/2% per minute as directed by management Human Performance Tools: Peer Checking US/RO DETERMINE rate and magnitude of boration Boration should be conducted per Standard Reactivity Plan Operator Fundamentals: Knowledge of US/RO ESTIMATE expected change in Plant Design and Theory Rod Position, boron Concentration, and Reactor Thermal Power Human Performance: Peer Checking RO ADJUST CVC-403 to required flow rate Human Performance: Peer Checking RO SET Boric acid Totalizer Human Performance: Peer Checking RO POSITION Reactor Makeup Mode Selector to BORATE CREW should wait until boron affects Tave US/RO POSITION Reactor Makeup Control prior to starting the back down. switch to START ROLE: AO RO VERIFY Boric Acid tack recirculation valves closed REQUEST: Acknowledge order to verify CVC-712A and CVC-712B closed RESPONSE: After 3 minutes report both valves are closed.

Human Performance: Self Checking RO VERIFY correct amount of boric acid added on Boric Acid Totalizer RO RESET Boric Acid Totalizer to zero

Simulator Exercise Guide Job Aid Page 26 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO POSITION CVC-406 to close RO PEFORM 20 gallon flush RO ADJUST MU-1022 to required flow rate RO SET Rx Makeup Totalizer RO POSITION Reactor Makeup Mode Selector to ALT DIL RO CLOSE CVC-406 US/RO POSITION Reactor Makeup Control switch to START RO SET CVC-403 RO VERIFY MU-1022 set to 60 gpm Human Performance: Peer Checking RO POSITION Rector Makeup Mode Selector switch to auto Human Performance: Peer Checking RO POSITION Reactor Makeup Control switch to start Human Performance: Self Checking RO VERIFY correct amount of dilution/flush Rx Makeup Totalizer Operator Fundamentals: Closely (CAS)US/BOP MAINTAIN Valve Pos Limit Monitoring Plant Conditions, Precisely as close as reasonable possible above Controlling Plant Evolutions actual turbine load BOP SET the setter to the desired load 1/2% per minute as directed by Plant BOP SET required loading rate at 1/2% per Management minute

Simulator Exercise Guide Job Aid Page 27 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: DEMI US Inform DEMI of back down REQUEST: Inform of backdown RESPONSE: Acknowledge back down DELAY: None Human Performance Tools: Peer Checking BOP PRESS Go pushbutton Crew may energizer Pressurizer heaters per 47043-C Operator Fundamentals: Closely BOP MAINTAIN reactive load within limits Monitoring Plant Conditions of Figure 5 BOP ADJUST heater drain pump speed to maintain equal loading US/BOP WHEN planned power level is reached, STOP load decrease per N-TB-54

Simulator Exercise Guide Job Aid Page 28 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 3: SW Pump 1A1 trips and 1B2 fails to start Human Performance Tools: Procedure Compliance, Clear Communications, Peer Checking, Self Checking Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely controlling plant evolutions, Teamwork, Knowledge of Plant Design and Theory Component BOP Technical Specification SRO Power reduction must be complete and the When directed by the Lead Evaluator insert Annunciators:

turbine in hold prior to inserting TRIGGER 3 TRIGGER 3 due to a reduced amount of SW required at 47051-P SW Header Pressure Low Verify that SW05A Timed/Instantaneous a lower power level. 47052-Q Turbine Bldg SW Isolation Alert Overcurrent, SW Pump A1 insert Verify that SW06D Failure to Auto Start, SW 47092-I Bus 5 Feeder Bkr Trip Pump 1B2 is preloaded 47093-I Bus 5 Feeder Bkr Overload Operator Fundamentals: Closely CREW Respond to and diagnose Low Monitoring Plant Conditions, Knowledge of Service Water Pressure.

Plant Design and Theory Human Performance Tools: Clear Communications

Simulator Exercise Guide Job Aid Page 29 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human Performance Tools: Procedure US Direct implementation of ARP-47051-P Compliance Crew may perform 47092-I which will direct starting SW Pump 1B2 then REFER to Tech Spec section 3.3 Crew may perform 417093-I which will direct transition to A-SW-02 (AOP-SW-001)

Crew may perform 47052-Q after completion of 47051-P doing this will result in RESETTING of Turbine Building SW ESF Isolation US/BOP CHECK both SW headers > 72 psig Human Performance. Peer Checking and ROLE: EO US/BOP CHECK SW header B pressure >

Self Checking 78 psig - NO REQUEST: SW pump 1A1 tripped and 1B2 was started. Check SW pump 1B2 for o BOP VERIFY SW pump 1B2 normal conditions on startup and investigate running the trip of SW pump 1A1 RESPONSE: Acknowledge the request wait 5 minutes and report the following: SW Pump 1B2 local indication is normal on startup. SW Pump 1A1 motor is hot to the touch and breaker has over current flag US Direct and implement transition to AOP-SW-001 BOP CHECK forebay level > 42%

Simulator Exercise Guide Job Aid Page 30 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: AO/EO (CAS) CREW Direct EO and AO to locally check SW system INTACT and equipment REQUEST: Acknowledge direction to cooled by SW NORMAL inspect the SW system and equipment cooled RESPONSE: After 15 minutes report SW system intact and equipment normal BOP CHECK both SW headers > 72 pisg BOP CHECK SW header isolation valves open ROLE: AO/EO (CAS) CREW Direct AO and EO to check headers in Aux building, Screenhouse REQUEST: Acknowledge direction to inspect the SW system RESPONSE: After 10 minutes report requested SW header intact BOP CHECK annunciator 47051-N clear BOP CHECK SW pressure on Turb Bldg header > 82.5 psig BOP CHECK SW to Turb Bldg Hdr valve one open (CAS)BOP CHECK SW Header Supply to Jockey pump > 60 psig BOP CHECK SW Header A > 60 psig BOP CHECK SW-10A Open BOP CHECK SW Header B > 60 psig BOP CHECK SW-10B Open

Simulator Exercise Guide Job Aid Page 31 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS BOP CHECK SW header in Containment intact BOP CHECK BOTH SW Headers > 86 psig BOP CHECK Turbine Bldg SW Air Acmtr Alarms clear BOP CHECK SW Header A operating BOP CHECK SW Header B operating BOP VERFIY turbine building header operating US REFER for addition guidance o N-SW-02 o EP Implementing Procedures o Tech Specs o PI-KW-200 o GNP 11-08-04

Simulator Exercise Guide Job Aid Page 32 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Per TS 3.7.c the crew identifies in TS 3.0.c US Hold Crew Brief and Refer to Technical for two trains of equipment listed in TRM Specifications 3.3.1 as OOS. TRM 3.3.1 when a train of T.S.

service water is declared inoperable then the following administrative limiting

3. T.S 3.3.d an inoperable containment fan coil units train, TS 3.3.b for an inoperable residual 4. T.S 3.3.b heat removal train, and TS 3.4.b for an
5. T.S 3.4.b.2 inoperable auxiliary feed water train. Three trains of AFW inoperable apply TS 3.4.b.2, 6. T.S 3.4.b.3 when the Reactor Coolant Temperature is >

3500F, if three auxiliary Feedwater trains 7. T.S 3.0.c are discovered to be inoperable, initiate immediate action to restore one auxiliary Feedwater train to operable status and suspend all Limiting Conditions For Operations requiring mode changes until one auxiliary Feedwater train is restored to operable status. Power reduction should begin, but cannot go below 2% (mode change). TS 3.4.b.3 reactor power shall not be increased above 1673 MWt

Simulator Exercise Guide Job Aid Page 33 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 4: Small Steam Line Break in Containment Human Performance Tools: Procedure Compliance, Clear Communications, Peer Checking, Self Checking Operator Fundamentals: Conservative Decision Making, Closely Monitoring Plant Conditions, Precisely controlling plant evolutions, Teamwork, Knowledge of Plant Design and Theory Major RO/BOP Technical Specification SRO PPCS Containment Pressure alarms will When directed by the Lead Evaluator insert Annunciators reach setpoint approximately 5 minutes TRIGGER 5 after insertion of the steam leak 47031-Q, Containment Sump A Level High Verify that MS02A Main Steam Line ~7.5 minutes after start of event Rupture Inside Containment (1A) inserts 47031-P, Containment Sump A Level HI-HI Verify FW16B Failure to Auto Start, AFW ~8 minutes after start of event Pump 1B is preloaded PPCS Alarms N1901G, Nuclear Thermal Mismatch P0946A, Containment Pressure 1.5 psig P0948A, Containment Pressure 1.5 psig P0950A, Containment Pressure 1.5 psig P1004A, Containment Pressure 1.5 psig Indications A Steam Generator Steam Flow will Start to Decrease Containment Pressure and Humidity will rise A Loop Temperatures Starting changing Tavg Decreases & Power Increases

Simulator Exercise Guide Job Aid Page 34 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamentals: Closely Monitoring CREW Diagnose and respond to steam Plant Conditions leak in containment The crew should decide to manually trip the Verify that RD11A Reactor Trip Breaker A US Direct tripping the reactor and reactor. TS 3.6.d, if the internal pressure of Fails to Open on Trip Sign is preloaded transitioning to E-0 the reactor containment vessel exceeds 2 Verify that RD11B Reactor Trip Breaker B psi, the condition shall be corrected within 8 Fails to Open on Trip Sign is preloaded hours or the reactor shall be placed in a subcritical condition.

A valid Reactor Trip and SI signal will generated at a containment pressure of 3.6 psig

Simulator Exercise Guide Job Aid Page 35 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 5: Failure of Reactor Trip Breakers to OPEN (ATWS)

Human Performance Tools: Procedure Compliance, Self Checking Operator Fundamentals: Closely Monitoring Plant Conditions Component BOP Human Performance: Clear RO Attempts to trip the reactor, reports the Communications reactor did NOT trip BOP Attempt to trip the reactor from the turbine panel, reports the reactor did NOT trip Human Performance: Self Checking, When the rods are inserted VERIFY that BOP OPEN bus 33 and 43 Supply Procedure Compliance that MS02A Main Steam Line Rupture Breakers Inside Containment (1A) inserts with an CRITICAL TASK: Open Bus 33 and 43 initial valve of 5 , a final value of 20 and a Feed Breakers. ramp of 5 minutes SAFETY SIGNIFICANCE: Required to remove power from Rod Drive MG Sets to drop control rods and shutdown the reactor CUE: Reactor did not automatically trip on rate and Reactor trip push buttons on the operator panels did not work MEASURABLE PERFORMANCE INDICATOR: Evaluator observes the BOP opening Bus 33 feeder breaker during immediate actions of E-0.

PERFORMANCE FEEDBACK: Rods Insert and Reactor Power < 5% and decreasing

Simulator Exercise Guide Job Aid Page 36 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: AO CREW Dispatch AO to locally open Reactor Trip and Bypass Breakers REQUEST: Open Reactor Trip and Bypass Breakers RESPONSE: Acknowledge Direction. Wait 2 minutes then remove the malfunctions RD11A and RD11B by inserting TRIGGER 7 and TRIGGER 9..

RO VERIFY Reactor Trip Operator Fundamentals: Closely BOP VERIFY Turbine Trip Monitoring Plant Conditions Manual trip of the turbine will be required if the containment has not reached 3.6 psig BOP CHECK 4160V Emergency AC Buses one energized RO CHECK if SI is Actuated

Simulator Exercise Guide Job Aid Page 37 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 6: Failure of B AFW pump to AUTO Start with Faulted Steam Generator A Inside Containment Human Performance Tools: Procedure Compliance, Clear Communications, Self Checking Operator Fundamentals: Closely Monitoring Plant Conditions, Precisely controlling plant evolutions, Teamwork Component BOP Operator Fundamentals: Closely Monitoring Plant Conditions, Teamwork BOP - Reports foldout page criteria met for Human Performance: Clear SG A which appears to be faulted.

Communications

Simulator Exercise Guide Job Aid Page 38 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamental: Precisely (CAS)US/RO VERIFY AFW pump running Controlling Plant Evolutions o BOP CHECK AFW pump A running Human Performance: Clear Communications and Self Checking o BOP CLOSE AFW-2A CRITICAL TASK: Start AFW pump B and o BOP START AFW pump A establish feed flow greater than 210 gpm to when SI sequencer complete S/G B from AFW pump B with both S/G levels less than 5% NR. o BOP CHECK AFW pump B running SAFETY SIGNIFICANCE: Maintain o BOP CLOSE AFW-2B Heat Sink Available.

o BOP START AFW pump B when SI sequencer complete CUE: TD AFW & AFW Pump B not running with indications of faulted S/G A

MEASURABLE PERFORMANCE INDICATOR: AFW pump B running and feed establish to S/G B from AFW pump B. Loss of Feed Flow to S/G does not exceed 10 minutes while S/G Narrow range level in both S/Gs is less than 5%

PERFORMANCE FEEDBACK: AFW pump B running, delivering feed flow to S/G B as indicated by AFW header B flow greater than 210 gpm and AFW pump B discharge header pressure

Simulator Exercise Guide Job Aid Page 39 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS NOTE: This critical task does not have to US Directs BOP to isolate feed flow to be accomplished until the SG feed isolation SG A per the foldout page step of E-2 Faulted SG Isolation Criteria - If any SG is Operator Fundamental: Precisely faulted (pressure decreasing in an Controlling Plant Evolutions uncontrolled manner or completely Human Performance: Clear depressurized) AND remaining SG is intact, Communications and Self Checking THEN the following may be performed:

o ISOLATE all feed flow to faulted SG CRITICAL TASK: Isolate Feed Flow faulted S/G A o MAINTAIN total feed flow greater than 210 gpm until narrow range SAFETY SIGNIFICANCE: Prevent level in at least one SG is greater excessive RCS cooldown by isolating than 5%[13%]

AFW flow to the faulted S/G as soon as it is identified BOP Actions Close AFW-10A or AFW-10B CUE: Excessive RCS cooldown, Steam Flow Indication, Steam Generator Close AFW-2A Depressurizing (The Operators may chose to turn off A AFW pump at this time but it is not MEASURABLE PERFORMANCE required)

INDICATOR: AFW crossover valve US/BOP MAINTAIN feed flow > 210 gpm AFW-10A or AFW-10B CLOSED, and AFW flow control valve AFW-2A BOP THROTTLE AFW-2B to maintain >

CLOSED, before or during faulted SG 210 gpm feed flow feed isolation step in E-2 PERFORMANCE FEEDBACK: Zero flow indication on AFW header A and no main feed water flow.

Simulator Exercise Guide Job Aid Page 40 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Crew should recognize ADVERSE (CAS)US/BOP CHECK all running AFW CONTAINMENT criteria of the foldout page pump discharge pressure > 1000 psig US/BOP VERIFY Secondary heat sink o BOP VERIFY total AFW flow > 210 gpm o BOP THROTTLE open AFW-2A and/or AFW-2B to maintain > 210 gpm

Simulator Exercise Guide Job Aid Page 41 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 7: Failure of ICS to Auto Initiate with Valid Containment Hi-Hi pressure Signal Human Performance Tools: Procedure Compliance, Clear Communications, Self Checking Operator Fundamentals: Closely Monitoring Plant Conditions, Teamwork Component RO Human Performance Tools: Procedure Verify CS03A Failure to Auto Start, ICS Pump RO VERIFY automatic actions of SI using Compliance, Clear Communications, Self 1A preloaded ATTACHMENT A Checking Verify CS03B Failure to Auto Start, ICS Pump Operator Fundamentals: Closely 1B preloaded Monitoring Plant Conditions, Teamwork (CAS)RO CHECK Containment spray NOT required o RO CHECK Containment pressure remained < 23 psig - NO RO CHECK Annunciator 47021-F lit

Simulator Exercise Guide Job Aid Page 42 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Manual initiation of Containment Spray will RO IF containment spray has NOT NOT work (Push Buttons) actuated THEN manually ACTUATE containment spray CRITICAL TASK: Establish ICS Flow to containment SAFETY SIGNIFICANCE:

Containment pressure > 23 psig ICS is required to reduce containment pressure CUE: Containment Pressure > 23 psig and ICS has not actuated MEASURABLE PERFORMANCE INDICATOR: Flow Path Established for at least one train of ICS and ICS Pump started in train that the flow path was established as indicated by flow from the ICS Pump PERFORMANCE FEEDBACK: At least one ICS Pump running and delivering flow. Containment Pressure lowering..

RO VERIFY all Containment spray pump discharge valves open Human Performance: Self Checking: Verify the following TRIGGERS are RO OPEN ICS-5A Containment spray activated deleting the following pump A Discharge Valve OVERRIDES 27 MCC DO-46351-G ICS-5A 28 MCC DO-46351-R ICS-5A 29 MCC DI-46351-Close ICS-5A

Simulator Exercise Guide Job Aid Page 43 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human Performance: Self Checking Verify the following TRIGGERS are RO OPEN ICS-6A Containment spray activated deleting the following pump A Discharge Valve OVERRIDES 21 MCC DO-46352-G ICS-6A 22 MCC-DO-46352-R ICS-6A 23 MCC DI-46352-Close ICS-6A Human Performance: Self Checking Verify the following TRIGGERS are RO OPEN ICS-5B Containment spray activated deleting the following pump B Discharge Valve OVERRIDES 24 MCC DO-46353-G ICS-5B 25 MCC DO-46353-R ICS-5B 26 MCC DI-46353-Close ICS-5B Human Performance: Self Checking Verify the following TRIGGERS are RO OPEN ICS-6B Containment spray activated deleting the following pump B Discharge Valve OVERRIDES 18 MCC-DO-46354-G ICS-6B 19 MCC-DO-46354-R ICS-6B 20 MCC-DI-46354-Close ICS-6B Human Performance: Self Checking RO VERIFY ISC Pumps running o RO START ICS Pump A o RO START ICS Pump B RO VERIFY both Caustic Additive valves open

Simulator Exercise Guide Job Aid Page 44 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human Performance: Self Checking Verify the following TRIGGERS are RO OPEN CI-1001A Caustic Additive to activated deleting the following Containment Spray Valve OVERRIDES 15 MCC-DI-46401-Close CI-1001A 16 MCC DO-46401-R CI-1001A 17 MCC DO-46401-G CI-1001A Human Performance: Self Checking Verify the following TRIGGERS are RO OPEN CI-1001B Caustic Additive to activated deleting the following Containment Spray Valve OVERRIDES 12 MCC DI-46402-Close CI-1001B 13 MCC DO-46402-R CI-1001B 14 MCC DO-46402-G CI-1001B US/RO CHECK RXCP Seal Cooling Normal (CAS)US/RO/BOP VERIFY RCS Temperature Control US/RO CHECK Pressurizer PORVs BOTH Closed US/RO CHECK Pressurizer Spray Valves Closed US/RO CHECK If RXCPs should remain running US/RO/BOP INITIATE monitoring CSF Status Trees Diagnose Steam Generator A as FAULTED US/BOP CHECK if any SG Faulted o Transition to E-2

Simulator Exercise Guide Job Aid Page 45 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS US/BOP VERIFY MSIV and Bypass valves are closed RO/BOP should diagnose Steam Generator US/BOP CHECK if any Steam Generator is B being INTACT NOT Faulted RO/BOP should diagnose/confirm diagnosis US/BOP IDENTIFY faulted Steam of Steam Generator A being FAULTED Generator US/BOP ISOLATE feed to faulted SG o BOP VERIFY the following valves closed o FW-12A o FW-7A o FW-10A o AFW-10A o AFW-2A o BOP STOP AFW Pump A and place in PULLOUT US/BOP ISOLATE Steam from faulted Steam Generator

  • Verify SG Blowdown Isolation Valves Closed
  • Verify SG Sample Isolation Valves Closed
  • CLOSE Seam Supply to T/D AFW Pump - MS-100A BOP CHECK CST > 20%

Simulator Exercise Guide Job Aid Page 46 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: Chemistry US/RO/BOP CHECK secondary radiation normal REQUEST: Sample steam generator and report activity RESPOND: Acknowledge request, stating results will take approximately 30 minutes.

US/BOP STABILIZE RCS temperature

  • Check Condenser Steam Dump Available
  • VERIFY Intact SG PORV controller in AUTO - SD-3B
  • SET Intact SG PORV controller to saturation pressure for faulted RCS loop cold leg temperature - SD-3B US TRANSITION to E-1

Simulator Exercise Guide Job Aid Page 47 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EAL Determination shall be conducted SRO/US identify the current EAL at the as a JPM for the SRO by an examiner if END of the scenario using the EAL matrix .

required Correct Classification is ALERT, SA2.1 1

  • A classification of Alert will be determined due to Failure of RPS to Student may refer to EPIP-AD-02 to assist Trip the Reactor and Manual Trip was in EAL determination successful from the control room (SA2.1)

Simulator Exercise Guide Job Aid Page 48 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

6. SCENARIO END: a. FREEZE simulator at direction of Lead Examiner.

Transition from E-2 to E-1 and/or and the direction of the Lead Examiner. b. STOP DVD recorder. IF this is the last session of the week, THEN FINALIZE the DVD (optional)

c. Ensure all EXAM material is collected
7. POST-SCENARIO:
a. ENSURE simulator problems encountered during the scenario are documented IAW site specific process.
b. ENSURE training attendance is documented on, Training Attendance Report.
c. SOLICIT/COLLECT trainee feedback

Simulator Exercise Guide Job Aid Page 49 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A VERIFICATION INSTRUCTIONS These Malfunctions/Remotes/Overrides/Blind triggers SHALL be verified by two independent checkers prior to the start of the scenario after running the ILT-09-SEE02.cae file

Simulator Exercise Guide Job Aid Page 50 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A INPUT

SUMMARY

Delay Ramp Event Severity Relative Description Time Time Trigger Or Value Final Value Order MALFUNCTIONS 47034-O SER1670 Source Range High Flux At Shutdown Alarm Blocked 00:00:00 00:00:00 Preload Block Block

  • SER0966 47043-P Bank D Rod Withdrawal High Limit 00:00:00 00:00:00 Preload Block Block
  • SER0642 47093-H Bus 5 RAT Source Breaker 1-503 43 Control Switch in Manual 00:00:00 00:00:00 Preload Block Block
  • RD11A Reactor Trip Breaker A Fails to Open on Trip Sign Preload False True 4 RD11B Reactor Trip Breaker B Fails to Open on Trip Sign Preload False True 4 NI05C Improper Power Range Channel Response (N43) Preload 1.1 100 Preload RX203 PT-431 PRZ Press 1 0 2500 1 SW05A Timed/Instantaneous Overcurrent, SW Pump A1 3 0 99 2 SW06D Failure to Auto Start, SW Pump 1B2 Preload False True 2 MS02A Main Steam Line Rupture Inside Containment (1A) 00:10:00 5 0 0.3 3 SER0172 47021-F Containment Spray Actuated Preload Block Block 4 CS03A Failure to Auto Start, ICS Pump 1A Preload False True 4 CS03B Failure to Auto Start, ICS Pump 1B Preload False True 4 FW16B Failure to Auto Start, AFW Pump 1B Preload False True 5
  • Denotes Malfunctions that preload with ALL IC loads REMOTE FUNCTIONS RP141 407C-OVER TEMPERATURE TRIP NORMAL/TRIP 00:00:00 00:00:00 Preload Norm Trip Preload RP142 407D-ROD STOP NORMAL/TRIP 00:00:00 00:00:00 Preload Norm Trip Preload

Simulator Exercise Guide Job Aid Page 51 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A INPUT

SUMMARY

Delay Ramp Event Severity Relative Description Time Time Trigger Or Value Final Value Order IA101 AIR COMPRESSOR 1C LOCAL CONTROL AUTO/OFF/ON 00:00:00 00:00:00 Preload Auto Off Preload OVERRIDES MCC DI-46351-Close ICS-5A 00:00:00 00:00:00 Preload Off On 6 MCC DO-46351-R ISC-5A 00:00:00 00:00:00 Preload Off Off 6 MCC DO-46351-G ISC-5A 00:00:00 00:00:00 Preload Off On 6 MCC DI-46352-Close ICS-6A 00:00:00 00:00:00 Preload Off On 6 MCC-DO-46352-R ICS-6A 00:00:00 00:00:00 Preload Off Off 6 MCC DO-46352-G ICS-6A 00:00:00 00:00:00 Preload Off On 6 MCC DI-46353-Close ICS-5B 00:00:00 00:00:00 Preload Off On 6 MCC DO-46353-R ICS-5B 00:00:00 00:00:00 Preload Off Off 6 MCC DO-46353-G ICS-5B 00:00:00 00:00:00 Preload Off On 6 MCC-DI-46354-Close ICS-6B 00:00:00 00:00:00 Preload Off On 6 MCC-DO-46354-R ICS-6B 00:00:00 00:00:00 Preload Off Off 6 MCC-DO-46354-G ICS-6B 00:00:00 00:00:00 Preload Off On 6 MCC DI-467471-01-Initiate Cntmt Spray Train A Start 00:00:00 00:00:00 Preload Off Off 6 MCC DI-467474-01-Initiate Cntmt Spray Train B Start 00:00:00 00:00:00 Preload Off Off 6 MCC DO-46401-G CI-1001A 00:00:00 00:00:00 Preload Off On 6 MCC DO-46401-R CI-1001A 00:00:00 00:00:00 Preload Off Off 6 MCC-DI-46401-Close CI-1001A 00:00:00 00:00:00 Preload Norm Norm 6 MCC DO-46402-G CI-1001B 00:00:00 00:00:00 Preload Off On 6

Simulator Exercise Guide Job Aid Page 52 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A INPUT

SUMMARY

Delay Ramp Event Severity Relative Description Time Time Trigger Or Value Final Value Order MCC DO-46402-R CI-1001B 00:00:00 00:00:00 Preload Off Off 6 MCC DI-46402-Close CI-1001B 00:00:00 00:00:00 Preload Norm Norm 6 MCA DO-46113-G MS-100A 00:00:00 00:00:00 Preload Off Off Preload MCA DO-46114-G MS-100B 00:00:00 00:00:00 Preload Off Off Preload MVA DO-44561-C-COUNT CVCS TOTALIZER COUNT 00:00:00 00:00:00 Preload Off Off Preload BLIND TRIGGERS (GUN SYMBOL)

Event# 12 Event Action: hwzcst6401(2)==1.0 Command: DOR DI-46402-Close Trigger activates on CI-1001A switch operation providing indication of valve opening Event# 13 Event Action: hwzcst6401(2)==1.0 Command: DOR DO-46402-R Trigger activates on CI-1001A switch operation providing indication of valve opening Event# 14 Event Action: hwzcst6401(2)==1.0 Command: DOR DO-46402-G Trigger activates on CI-1001A switch operation providing indication of valve opening Event# 15 Event Action: hwzcst6401(1)==1.0 Command: DOR DI-46401-Close Trigger activates on CI-1001B switch operation providing indication of valve opening Event# 16 Event Action: hwzcst6401(1)==1.0 Command: DOR DO-46401-R Trigger activates on CI-1001B switch operation providing indication of valve opening Event# 17 Event Action: hwzcst6401(1)==1.0 Command: DOR DO-46401-G Trigger activates on CI-1001B switch operation providing indication of valve opening

Simulator Exercise Guide Job Aid Page 53 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A INPUT

SUMMARY

Delay Ramp Event Severity Relative Description Time Time Trigger Or Value Final Value Order Event# 18 Event Action: hwzcst5254(2)==1.0 Command: DOR DO-46354-G Trigger activates on ICS-6B switch operation providing indication of valve opening Event# 19 Event Action: hwzcst5254(2)==1.0 Command: DOR DO-46354-R Trigger activates on ICS-6B switch operation providing indication of valve opening Event# 20 Event Action: hwzcst5254(2)==1.0 Command: DOR DI-46354-Close Trigger activates on ICS-6B switch operation providing indication of valve opening Event# 21 Event Action: hwzcst5254(1)==1.0 Command: DOR DO-46352-G Trigger activates on ICS-6A switch operation providing indication of valve opening Event# 22 Event Action: hwzcst5254(1)==1.0 Command: DOR DO-46352-R Trigger activates on ICS-6A switch operation providing indication of valve opening Event# 23 Event Action: hwzcst5254(1)==1.0 Command: DOR DI-46352-Close Trigger activates on ICS-6A switch operation providing indication of valve opening Event# 24 Event Action: hwzcst5153(2)==1.0 Command: DOR DO-46353-G Trigger activates on ICS-5B switch operation providing indication of valve opening Event# 25 Event Action: hwzcst5153(2)==1.0 Command: DOR DO-46353-R Trigger activates on ICS-5B switch operation providing indication of valve opening Event# 26 Event Action: hwzcst5153(2)==1.0 Command: DOR DI-46353-Close Trigger activates on ICS-5B switch operation providing indication of valve opening

Simulator Exercise Guide Job Aid Page 54 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A INPUT

SUMMARY

Delay Ramp Event Severity Relative Description Time Time Trigger Or Value Final Value Order Event# 27 Event Action: hwzcst5153(1)==1.0 Command: DOR DO-46351-G Trigger activates on ICS-5A switch operation providing indication of valve opening Event# 28 Event Action: hwzcst5153(1)==1.0 Command: DOR DO-46351-R Trigger activates on ICS-5A switch operation providing indication of valve opening Event# 29 Event Action: hwzcst5153(1)==1.0 Command: DOR DI-46351-Close Trigger activates on ICS-5A switch operation providing indication of valve opening Event #30 Event Action: hwzedxg48a(5)==1.0&&hwzedxg48a(2)==1.0 Command: IMF MS02a 20 00:05:00 5 Trigger activates on rod insertion and will increase MS02A Main Steam Line Rupture Inside Containment (1A)

Simulator Exercise Guide Job Aid Page 55 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A CAEP FILE ILT-09-SEE02.cae PAGE 1 IMF RD11A 00:00:00 N/A N/A N/A True 4 IMF RD11B 00:00:00 N/A N/A N/A True 4 IMF NI05C 00:00:00 N/A N/A N/A 1.1 Preload IMF RC203 (1) 2500 00:00:00 N/A N/A N/A 2500 1 IMF SW05A (3) 99 00:00:00 N/A N/A N/A 99 2 IMF MS02A (5) .3 00:10:00 .1 00:00:00 N/A N/A N/A .3 3 TRG 7 DMF RD11A 00:00:00 N/A N/A N/A N/A 4 TRG 9 DMF RD11B 00:00:00 N/A N/A N/A N/A 4 IMF SER01720 00:00:00 N/A N/A N/A Block 6 IMF CS03A 00:00:00 N/A N/A N/A True 6 IMF CS03B 00:00:00 N/A N/A N/A True 6 IOR DI-46351-Close ON 00:00:00 N/A N/A N/A On 6 IOR DO-46351-R OFF 00:00:00 N/A N/A N/A Off 6 IOR DO-46351-G ON 00:00:00 N/A N/A N/A On 6 IOR DI-46352-Close ON 00:00:00 N/A N/A N/A On 6 IOR DO-46352-R OFF 00:00:00 N/A N/A N/A Off 6 IOR DO-46352-G ON 00:00:00 N/A N/A N/A On 6 IOR DI-46353-Close ON 00:00:00 N/A N/A N/A On 6 IOR DO-46353-R OFF 00:00:00 N/A N/A N/A Off 6 IOR DO-46353-G ON 00:00:00 N/A N/A N/A On 6

Simulator Exercise Guide Job Aid Page 56 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A IOR DI-46354-Close ON 00:00:00 N/A N/A N/A On 6 IOR DO-46354-R OFF 00:00:00 N/A N/A N/A Off 6 IOR DO-46354-G ON 00:00:00 N/A N/A N/A On 6 IOR DI-467471-01-Initiate OFF 00:00:00 N/A N/A N/A Off 6 IOR DI-467474-01-Initiate OFF 00:00:00 N/A N/A N/A Off 6 IMF FW16B 00:00:00 N/A N/A N/A True 5 TARGET 30 hwzedxg48a(5)==1.0&&hwzedxg48z(2)==1.0 00:00:00 N/A N/A N/A N/A 4 TRG 30 IMF MS02A 20 00:05:00 5 00:00:00 N/A N/A N/A 20 4 CAEP FILE ILT-09-SEE02.cae PAGE 2 TRGSET 29 hwzcst5153(1)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 29 DOR DI-46351-CLOSE 00:00:00 N/A N/A N/A N/A 6 TRGSET 28 hwzcst5153(1)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 28 DOR DO-46351-R 00:00:00 N/A N/A N/A N/A 6 TRGSET 27 hwzcst5153(1)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 27 DOR DO-46351-G 00:00:00 N/A N/A N/A N/A 6 TRGSET 26 hwzcst5153(2)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 26 DOR DI-46353-CLOSE 00:00:00 N/A N/A N/A N/A 6 TRGSET 25 hwzcst5153(2)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 25 DOR DO-46353-R 00:00:00 N/A N/A N/A N/A 6 TRGSET 24 hwzcst5153(2)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 24 DOR DO-46353-G 00:00:00 N/A N/A N/A N/A 6 TRGSET 23 hwzcst5254(1)==1.0 00:00:00 N/A N/A N/A N/A 6

Simulator Exercise Guide Job Aid Page 57 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A TRG 23 DOR DI-46352-CLOSE 00:00:00 N/A N/A N/A N/A 6 TRGSET 22 hwzcst5254(1)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 22 DOR DO-46352-R 00:00:00 N/A N/A N/A N/A 6 TRGSET 21 hwzcst5254(1)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 21 DOR DO-46352-G 00:00:00 N/A N/A N/A N/A 6 TRGSET 20 hwzcst5254(2)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 20 DOR DI-46354-CLOSE 00:00:00 N/A N/A N/A N/A 6 TRGSET 19 hwzcst5254(2)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 19 DOR DO-46354-R 00:00:00 N/A N/A N/A N/A 6 TRGSET 18 hwzcst5254(2)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 18 DOR DO-46354-G 00:00:00 N/A N/A N/A N/A 6 IRF RP141 TRIP 00:00:00 N/A N/A N/A Trip Preload IRF RP142 TRIP 00:00:00 N/A N/A N/A Trip Preload CAEP FILE ILT-09-SEE02.cae PAGE 3 IOR DO-46401-G ON 00:00:00 N/A N/A N/A On 6 IOR DO-46401-R OFF 00:00:00 N/A N/A N/A Off 6 IOR DI-46401-Close ON 00:00:00 N/A N/A N/A On 6 IOR DO-46402-G ON 00:00:00 N/A N/A N/A On 6 IOR DO-46402-R OFF 00:00:00 N/A N/A N/A Off 6 IOR DI-46402-Close ON 00:00:00 N/A N/A N/A On 6 TRGSET 17 hwzcst6401(1)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 17 DOR DO-46401-G 00:00:00 N/A N/A N/A N/A 6

Simulator Exercise Guide Job Aid Page 58 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A TRGSET 16 hwzcst6401(1)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 16 DOR DO-46401-R 00:00:00 N/A N/A N/A N/A 6 TRGSET 15 hwzcst6401(1)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 15 DOR DI-46401-CLOSE 00:00:00 N/A N/A N/A N/A 6 TRGSET 14 hwzcst6401(2)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 14 DOR DO-46402-G 00:00:00 N/A N/A N/A N/A 6 TRGSET 13 hwzcst6401(2)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 13 DOR DO-46402-R 00:00:00 N/A N/A N/A N/A 6 TRGSET 12 hwzcst6401(2)==1.0 00:00:00 N/A N/A N/A N/A 6 TRG 12 DOR DI-46402-CLOSE 00:00:00 N/A N/A N/A N/A 6 IOR DO-46113-G OFF 00:00:00 N/A N/A N/A Off Preload IRO DO-46114-G OFF 00:00:00 N/A N/A N/A Off Preload CAEP FILE ILT-09-SEE02.cae PAGE 4 IRF IA101 OFF 00:00:00 N/A N/A N/A Off Preload IOR DI-46412-CLOSE ON 00:00:00 N/A N/A N/A On Preload DOR DI-46412-CLOSE 00:00:20 N/A N/A N/A N/A Preload IOR DO-44561-C-COUNT OFF 00:00:00 N/A N/A N/A Off Preload

Simulator Exercise Guide Job Aid Page 59 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SIMULATOR SCENARIO DEVELOPMENT CHECKLIST Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

Yes No

1. The scenario contains objectives for the desired tasks and relevant Human Performance Tools.
2. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.
3. Plant PRA initiating events, important equipment, and important tasks are identified.
4. Turnover information includes a Daily At Power Risk Assessment provided by the PRA Group.
5. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.
6. The Scenario Guide includes responses for all communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices.
7. The scenario includes related industry experience. Not Required for Evaluations
8. Training elements and specific Human Performance elements are addressed in the Scenario Critique Guide to be used by the Critique Facilitator. The Critique Guide includes standards for expected performance.
9. Any identified Critical Tasks possesses the following elements (NUREG-1021):
  • Essential to safety with adverse consequences or significant degradation,
  • Cue(s) prompt the Operator to respond.
  • Defined and measurable performance indicators.
  • Performance feedback.

The use of N/A is allowed for item 9 only if this is NOT an evaluated scenario.

10. Technical Specifications including Limiting Conditions for Operation, reactivity briefings, and Emergency-Plan entries are addressed as appropriate.

Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

Simulator Exercise Guide Job Aid Page 60 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A SIMULATOR EXERCISE VALIDATION CHECKLIST Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

Yes No

1. The desired initial condition(s) could be achieved.
2. All malfunctions and other instructor interface items were functional and responded to support the simulator Scenario.
3. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.
4. All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.
5. During the simulator scenario, observed changes corresponded to expected plant response.
6. Did the scenario satisfy the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence?
7. The simulator is capable of being used to satisfy learning or examination objectives without exceptions, significant performance discrepancies, or deviation from the approved scenario sequence.
8. Any identified Critical Tasks possesses the following elements (NUREG-1021):
  • Essential to safety with adverse consequences or significant degradation,
  • Cue(s) prompt the Operator to respond.
  • Defined and measurable performance indicators.
  • Performance feedback.

The use of N/A is allowed for item 8 only if this is NOT an evaluated scenario.

Discrepancies noted (Check none or list items in comments field) None Comments: None Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

Simulator Exercise Guide Job Aid Page 61 of 61 SEG# ROI-06-SE-SC02/SOI-06-SE-SC02 Rev: A Applied & Implemented All Information Passed on to All Any Knowledge or Performance Corrective Actions if TS/TRM (PP-1) Identified All Applicable Correctly Crew Members (i.e., briefs) Deficiencies Required As Time Allowed T.S. 3.10.l Yes No Yes No Yes No T.S. 3.10.n Yes No Yes No Yes No T.S. Table 3.5-2 Yes No Yes No Yes No item #5-OTT T.S. Table 3.5-2 item #8-High Yes No Yes No Yes No Pressurizer Pressure T.S. Table 3.5-3 item #1d-Yes No Yes No Yes No Pressurizer Low Pressure COLR 2.11 Yes No Yes No Yes No T.S. 3.7.c Yes No Yes No Yes No TRM 3.3.1 Yes No Yes No Yes No T.S. 3.3.e Yes No Yes No Yes No T.S 3.7.b.2 Yes No Yes No Yes No T.S 3.7.b.2 Yes No Yes No Yes No T.S 3.3.d Yes No Yes No Yes No T.S 3.3.b Yes No Yes No Yes No T.S 3.4.b.2 Yes No Yes No Yes No T.S 3.4.b.3 Yes No Yes No Yes No T.S 3.0.c Yes No Yes No Yes No TS 3.6.d Yes No Yes No Yes No EALs All Information Passed on to All Any Knowledge or Performance Corrective Actions if Identified All Applicable Classified & Notified Timely (EP Group) Crew Members (i.e., briefs) Deficiencies Required SA2.1 Yes No Yes No Yes No Yes No Yes No Yes No Any Knowledge or Performance Corrective Actions if Procedure Compliance (PP-3) Applied & Implemented Correctly As Time Allowed Deficiencies Required Yes No Any Knowledge or Performance Corrective Actions if Human Performance Errors (PP-2) Identify All HU Errors or Potential HU Errors Deficiencies Required Identify All Operator Fundamental Errors Or Potential Operator Fundamental Any Knowledge or Performance Corrective Actions if Operator Fundamentals Errors Deficiencies Required

Simulator Exercise Guide Job Aid Page 1 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SITE: Kewaunee Power Station PROGRAM: Reactor Operator Program/Senior Reactor Operator Program PROGRAM No.

COURSE: 2009 NRC License Exam Course #: ROI-06-SE-SC03

/ SOI-06-SE-SC03 Total Time 2 Hours Prepared by: Andrew Fahrenkrug /S 02/02/09 Printed Name Instructors Signature Date Reviewed by: Steve Johnson /S 02/07/09 (Optional) Printed Name Simulator Development Checklist Date Instructor Signature Reviewed by: Andrew Fahrenkrug /S 01/23/09 (Optional) Printed Name Simulator Validation Checklist Signature Date Approved by: Terry Evans /S 02/10/09 Printed Name Training Manager Date Approved by:

Mark Goolsbey /S 02/12/09 Printed Name Facility Representative Date

Simulator Exercise Guide Job Aid Page 2 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A REQUIREMENTS Goal of Training: Evaluate crew response and performance for the following events:

  • PRZR PORV PR-2B Fails OPEN at 10%
  • SG A pressure Transmitter fails High, PT-468: SG PORV OPENS and A SG level will rise.
  • A SG Tube Leak
  • Rapid Power Reduction
  • Reactivity Manipulations
  • Shifting Electrical Buses
  • A SG Tube Rupture
  • Failure of MSIVs to close
  • Failure of Normal Spray Valves to Operate
  • SRO/US analysis of plant conditions for Technical Specification application

Simulator Exercise Guide Job Aid Page 3 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A Learning Objectives: While responding as the RO/BOP satisfactorily MEET the performance requirements in TR-AA-400 for the following competencies

a. Understand and Interpret Annunciator and Alarm Signals
b. Diagnose Events and Conditions based on Signals and Reading
c. Understand Plant and System Response
d. Comply with and Use Procedures and Technical Specifications
e. Operate the Control Board
f. Communicate and Interact with Other Crew Members (RO4-06-SED01.002) ROI-06-SE-SC03.001 / SOI-06-SE-SC03.001 While responding as the US satisfactorily MEET the performance requirements in TR-AA-400 for the following competencies
a. Understand and Interpret Annunciator and Alarm Signals
b. Diagnose Events and Conditions based on Signals and Reading
c. Understand Plant and System Response
d. Comply with and Use Procedures and Technical Specifications
e. Operate the Control Board
f. Communicate and Interact with Other Crew Members
g. Direct Shift Operations
h. Comply with and Use Technical Specifications (RO4-06-SED01.003) SOI-06-SE-SC03.002 As the US DETERMINE the appropriate event classification in accordance with EPIP-AD-02,Emegency Classification Determination. This objective will be completed at the end of the scenario and may be waived at the lead evaluators discretion SOI-06-SE-SC03.003 Prerequisites: Enrolled in current ILT class and recommended by station management to take an NRC license exam Training Resources: Simulator KPS Exam Team Member NRC Examiners

Simulator Exercise Guide Job Aid Page 4 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A

References:

GOP-105, Startup From Hot Standby To 35% Power 47042-A, PRESSURIZER PORV OPEN 47042-B, PRESSURIZER PORV DISCHARGE TEMP HIGH 47041-B, PRESSURIZER SAFETY DISCH TEMP HIGH 47043-C, Pressurizer Control Press Abnormal 47043-D, PRZR Pressure Low 47044-L, RX Makeup Boric Acid Deviation AOP-GEN-001, Operator Immediate Actions 47061-C, S/G A FEED FLOW EXCESSIVE TLA-10 SG TILTS AOP-MISC-001, Response to Instrument Failure TLA-15, RMS Above Normal 47011-B, Radiation Indication High 47012-B Radiation Indication Alert AOP-GEN-002, Rapid Power Reduction AOP-RC-004, Steam Generator Tube Leak 47042-G ,Auctioneered Tave-Tref Deviation 47042-F, Pressurizer LVL Letdown ISOL & Heaters Off N-EHV-39, 4160V AC Supply And Distribution System Operation E-0, Reactor Trip or Safety Injection E-3, Steam Generator Tube Rupture ECA-3.1, SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired KPS Technical Specifications

Simulator Exercise Guide Job Aid Page 5 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A Commitments: Per Outline submitted to NRC for 2009 Operating exam Evaluation Method: Dynamic Simulator Historical Record: Initial Issue Operating Experience: Not required for evaluations Related PRA Initiating Event with Core Damage Frequency:

Information:

Total CDF/LERF (4.8E-5/yr)/(6.5E-06/yr)

Stuck Open PORV percentage of CDF/LERF (2%)/(1%)

Steam Generator Tube Rupture percentage of CDF/LERF (10%)/(28%)

Transient with Feed water Available percentage of CDF/LERF (19%)/(7%)

Other percentage of CDF/LERF (3%)/(2%)

Important Components:

System CDF Importance Rank LERF Importance Rank None CDF Post Event Important Operator Actions Operator Fails to Limit SI Flow and refill RWST Operator Fails to Cool Down and Depressurize RCS LERF Post Event Important Operator Actions Operator Fails to Limit SI Flow and refill RWST Operator Fails to Cool Down and Depressurize RCS Operator Fails to Isolate 1 of 2 Steam Generators

OVERVIEW INITIAL CONDITIONS:

1. Special IC-91 (27.3%)
2. The following equipment is OOS:
a. Emergency Boric Acid Totalizer

Simulator Exercise Guide Job Aid Page 7 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A QUANTITIVE ATTRIBUTES Event Malf. Event Event No. No. Type*

Description RC10B 1 10% C (RO) PR-2B Fails Open 2 RX213 I (BOP) SG A pressure transmitter fails high SG02A 3 .3% C (Both) Small SG A tube leak < 1 gpm R (RO) Reactor Shutdown N (BOP) Plant Shutdown SG01A 4 20% M (Both) SGTR A SG 5 MS08A C (BOP) Failure of MS-1A to Close 5 MS08B C (BOP) Failure of MS-1B to Close 6 Override C (RO) Failure of Spray Valve PS-1A to Operate 6 Override C (RO) Failure of Spray Valve PS-1B to Operate

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

Simulator Exercise Guide Job Aid Page 8 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A Malfunctions:

Before EOP Entry:

1. PRZR PORV (PR-2B) fails open at 10%
2. PT-468 A SG pressure transmitter fails high
3. SG A small tube leak After EOP Entry:
1. SG A tube rupture
2. MSIVs fail to close
3. PRZR spray valves fail to open Abnormal Events:
1. PRZR PORV (PR-2B) fails open at 10%
2. PT-468 A SG pressure transmitter fails high
3. SG A small tube leak Major Transients:
1. SGTR, Reactor Trip, Safety Injection - MSIVs fail to close

Simulator Exercise Guide Job Aid Page 9 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A Critical Tasks:

Stop Feedwater to A Steam Generator within 10 minutes of A Steam Generator Rupture if minimum level requirements are met 5% [13%].

SAFETY SIGNIFICANCE:

Mitigate ruptured steam generator overfill and dose consequences, minimize the potential of radiological release from overfill. Min level required to maintain water level above the U-Tubes in order to promote thermal stratification to prevent ruptured steam generator depressurization CUE:

SG A Level rising in an uncontrolled manner or abnormal radiation and SG A narrow range level is > 5%

MEASURABLE PERFORMANCE INDICATOR:

BOP Closes AFW-10A or AFW-10B if the Turbine Driven AFW pump is not running. Close AFW-10A if TD AFW pump is running. Close AFW -2A PERFORMANCE FEEDBACK:

A AFW header flow indicates zero

Simulator Exercise Guide Job Aid Page 10 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SEQUENCE OF EVENTS:

Event 1: At the direction of the Lead Examiner, PRZR PORV (PR-2B) fails open at 10%.

The RO will perform the immediate operator actions of AOP-GEN-001 to shut the PRZR PORV Block Valve (PR-1B) and PRZR PORV (PR-2B). TS for the plant transient are 3.10.l for RCS pressure and 3.10.n for DNBR parameters. TS 3.1.a.5.A.2 for the failed PRZR PORV: PORV inoperable for reasons other than seat leakage within one hour either restore the PORV to operable status or close the associated block valve and remove power from the block valve. Restore the PORV to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or action shall be initiated to achieve hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The crew will pursue opening the breaker for PR-1B while the scenario continues. For information only: EAL SU5.2 Event 2: At the direction of the Lead Examiner, PT-468 A SG pressure transmitter fails high over 60 seconds.

The A SG PORV will open and A SG level will rise above program level. The BOP will perform the immediate operator actions of AOP-GEN-001 and place FW-7A in manual and close SD-3A. After closure of the A SG PORV The US will direct entry into AOP-MISC-001, Response To Instrument Failure. The BOP will restore SG level to 44%, defeat the steam pressure instrument and return FW-7A to auto. FW-7A will be in automatic control prior to the next event.

Event 3: At the direction of the Lead Examiner, SG A develops a small tube leak of ~ 500 gpd (0.35 gpm) over 5 minutes.

The crew will diagnose the indications and determine that a rapid power reduction and plant shutdown is required per AOP-RC-004, SG Tube Leak. The US will coordinate the actions of AOP-GEN-002, Rapid Power Reduction to shut down the plant while implementing AOP-RC-004, SG Tube Leak. The RO will borate the RCS per AOP-GEN-002 during the power reduction. The BOP will perform turbine load reduction and shift 4160 VAC buses from the MAT to the RAT per N-EHV-39. TS 3.1.d.1.D for RCS operational leakage: When the average RCS temperature is > 2000F Operational leakage shall be limited to 150 gallons per day primary to secondary leakage through any one steam generator. TS 3.1.d.3 If the limits contained in TS3.1.d.1 for pressure boundary or primary to secondary leakage are exceed. Or the time limit contained in TS 3.1.d.2 is exceeded, then initiate action to achieve hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within an additional 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Event 4: After the BOP has shifted 4160V Buses from the MAT to the RAT and at the direction of the Lead Examiner, SG A tube leak develops into a SGTR.

The SGTR will generate a Reactor Trip and SI signal. The US will direct entry into E-0. The crew will perform the immediate actions of E-0. The RO will manually SI on decreasing PRZR level. The BOP will isolate feed to ruptured SG A either in E-0 or E-3 after SG A narrow range level is greater than 5%. The crew will progress through E-0 and transition to E-3. For information only: EAL classification FA1, ALERT: Any Loss or any potential loss of either the fuel clad or RCS (Table F-1). Table F-1 Fission product barrier reference table: RCS Barrier, Loss, SGTR that results in ECCS (SI) actuation.

Simulator Exercise Guide Job Aid Page 11 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A Event 5: MSIVs fail to close.

The MSIVs will fail to close during the steam isolation step of the ruptured SG A in E-3. Manual attempts to close MSIVs will also fail. The BOP will set Steam Dump manual controller (HC-484) to 1050 psig and steam dumps to steam pressure mode. Direction will be given to locally isolate the main steam header.

The US will direct the BOP to use the intact SG B PORV to control RCS temperature and cooldown.

After determining that the ruptured SG A can not be isolated from the intact SG B a transition to ECA-3.1 will be made.

Event 6: Pressurizer spray valves fail to operate.

When required to depressurize to restore PRZR level in ECA-3.1 the spray valves will fail to operate and the crew will have to depressurize using a PRZR PORV.

Scenario Termination:

The scenario will terminate after the crew has progressed in ECA-3.1 to the determination if one SI pump should be stopped.

Simulator Exercise Guide Job Aid Page 12 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A TASKS Task Task Title Number SRO Tasks:

1190190302 Apply Technical Specifications During Plant Operations 1190030502 Determine Emergency Classification 1190070502 Coordinate the Implementation of the IPEOPs A030010402 Perform a Rapid Power Reduction 1190620302 Respond to Steam Generator Tube Leak Demonstrate an understanding of the responsibility and requirements for the Control Room 1190330302 Supervisor RO Tasks:

0360420401 Respond to a Pressurizer Control Press Abnormal Annunciator 0360410401 Respond to Pressurizer Pressure Low Annunciator 0360240401 Respond to Pressurizer PORV OPEN Annunciator Transfer Feedwater Control from Automatic to Manual Control during Abnormal Feedwater 05A0030401 System Operation Shift a Steam Flow or Feed Flow Channel Selector during Abnormal Feedwater System 05A0040401 Operation Transfer Feedwater Control From Manual to Automatic During Normal Feedwater System 05A0100101 Operation 1190250301 Respond to a S/G Tube Leak 0450130401 Respond to an Abnormal Condition with R-15, Air Ejector Exhaust Monitor 0450170401 Respond to an Abnormal Condition with R-19, S/G Blowdown Liquid Monitor A030010401 Perform a Rapid Power Reduction 1190020001 Demonstrate and understanding of sensors and detectors E000010501 Respond to a Reactor Trip Condition with Safety Injection E030010501 Respond to a Steam Generator Tube Rupture

Simulator Exercise Guide Job Aid Page 13 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A 1190110301 Operate the plant IAW technical specifications 0350070101 Operate the Charging and Volume Control System during Steady State Conditions 0350230101 Control the RCS Boron Concentration by the use of Boration

Simulator Exercise Guide Job Aid Page 14 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A __

SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

1. INITIAL CONDITIONS:
  • Special IC-91
  • Mode: Power Operation
  • Exposure: BOL
  • Power: 27.3%
  • Boron: (CB): 2042 ppm
  • Temperature: 552.4 oF
  • Pressure: 2235 psig
  • Xenon: Increasing
  • Rods: D @ 151 steps
  • Generator: 123 Mwe Shift Directions:

Chemistry hold at 30% Reactor power (Step 5.2.18 of GOP105 (473MWt)

2. SIMULATOR SETUP: 1. RESET to IC# 91 and go to RUN The following forms are needed during the 2. INSERT DVD for recording
3. OPEN AND RUN ILT-09-SEE03.cae.

scenario and are to be placed in the booth. After file has run CLOSE CAE file.

4. VERIFY the Instructor Station Summary IAW instructions at the beginning of the input summary in this SEG
5. SECOND VERIFICATION of the Instructor Station Summary IAW instructions at the beginning of the input summary in this SEG

Simulator Exercise Guide Job Aid Page 15 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Shift Manager Status board information 6. Start the Monitor File using the NRC Extended Value Monitor File.

Equipment OOS

7. COMPLETE Simulator Exam Setup
  • Emergency boric acid totalizer Checklist Remarks Protected train = Train A NOTE: If called to the Control Room then wear the badge identifying who you Risk CDF/LERF= Green are.

SPER / WRs None

Simulator Exercise Guide Job Aid Page 16 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS GENERAL Consecutive days of operation ___1____

G-1 Closed (yesterday) JD xxx Burn up 150 MWD/MTU Sirens Lost Coverage % __0__

Sirens OOS __0__

RCS and Pressurizer boron = 2042 ppm All other entries are standard

Simulator Exercise Guide Job Aid Page 17 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

3. PRE-SCENARIO:

a) IF this is the first simulator scenario of the week, THEN review the Simulator Differences List with the crew.

b) Provide crew with

  • Turnover sheets and plant information
  • Marked up Copy of GOP-105
  • Reactivity Plan c) Cover Simulator Scenario Briefing Sheet in Job Aid 04-01 with the crew
  • Inform the crew that the Lead Evaluator will take response for the Shift Manager. They will acknowledge communications, but their acknowledgment does not mean agreement or disagreement.

d) Brief the crew IAW NUREG 1021 Appendix E (Simulator Test Guidelines) e) Lead Evaluator perform a Pre-Job brief per Job Aid 04-03

Simulator Exercise Guide Job Aid Page 18 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

4. TURNOVER: PROVIDE Shift Turnover When Crew enters the simulator than begin (All) Walk down control boards~ 5 minutes Information. recording on the DVD.

Chemistry Hold @ 30% Reactor Power:

Step 5.2.18 of GOP-105 After ~5 minute walk down of boards by the crew. Give the crew the shift.

Simulator Exercise Guide Job Aid Page 19 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

5. SCENARIO:

EVENT 1: PRZR PORV (PR-2B) fails open at 10%

Human Performance Tools: Procedure Compliance, Clear Communications, Peer Checking, Self Checking Operator Fundamentals: Knowledge of Plant design and Theory, Teamwork Component RO Technical Specification SRO Lead evaluator direct Booth Instructor to When directed, initiate Event 1 by activating Annunciators:

initiate Event 1. Trigger 1.

47042-A, PRESSURIZER PORV OPEN 47042-B, PRESSURIZER PORV DISCHARGE TEMP HIGH 47041-B, PRESSURIZER SAFETY DISCH TEMP HIGH For Information Only: EAL SU5.2, Identified leakage > 25 gpm, due to PRZR 47043-C, Pressurizer Control Press PORV opening. Applicability of EAL SU5.2 Abnormal is based on total time the PRZR PORV was open and unisolated and the change in PRT 47043-D, PRZR Pressure Low level.

Board Indications:

PRZR PORV (PR-2B) red open light lit PRZR/RCS pressure decreasing Operator Fundamentals: Knowledge of CREW Identifies lowering PRZR pressure Plant Design and Theory RO Identifies open PRZR PORV (PR-2B)).

Simulator Exercise Guide Job Aid Page 20 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human performance: Self Checking, Peer RO Performs immediate actions of AOP-Checking, Procedure Use and Adherence GEN-001

  • Check Pressurizer Pressure GREATER THAN 2315 PSIG (NO)
  • CHECK Both PORVs - CLOSED (NO)
  • Place PRZR PORV Block Valve PR-1B control switch to close
  • Place PRZR PORV PR-2B control switch to close Operator Fundamental: Teamwork US Verify immediate actions of AOP-GEN-001 complete T.S. 3.1.a.5.A.2; PORV inoperable for US Hold Brief and evaluate T.S.

reasons other than seat leakage w/n one hour either restore PORV to operable status Instrument Failure or close associated block valve and remove T.S. 3.1.a.5.A.2 power from block valve. Restore PORV to operable status w/n 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or initiate 72 Hour LCO action to achieve HSB w/n 6 hrs and HSD w/n following 6 hrs.

TS for the plant transient are 3.10.l for RCS DNBR (If crew responds quickly pressure pressure and 3.10.n for DNBR parameters may not lower to COLOR Value)

COLOR 2.11 pressure shall be > 2217 psig T.S. 3.10.I control board and > 2219 psig computer indication T.S. 3.10.n COLOR 2.11

Simulator Exercise Guide Job Aid Page 21 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: SM/WCC US Inform SM or WCC need to remove power for PR-1B within one hour REQUEST: Remove Power from PR-1B RESPONSE: Will purse removing power and inform when completed.

DELAY: After 30 minutes INSERT TRIGGER 9 and report that power has removed from PR-1B For Information Only: EAL SU5.2, Identified leakage > 25 gpm, due to PRZR PORV opening. Applicability of EAL SU5.2 is based on total time the PRZR PORV was open and unisolated and the change in PRT level.

Simulator Exercise Guide Job Aid Page 22 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 2: PT-468 A SG pressure transmitter fails high over 60 seconds Human Performance Tools: Procedure Compliance, Clear Communications, Peer Checking, Self Checking Operator Fundamentals: Precisely Controlling Plant Parameters, Knowledge of Plant design and Theory, Teamwork, Closing Monitoring Plant Conditions Component BOP Technical Specification SRO Lead evaluator direct Booth Instructor to When directed, initiate Event 2 by activating Annunciators:

initiate Event 2. Trigger 3.

47061-C, S/G A FEED FLOW EXCESSIVE FW-7A will be in automatic control prior to (Depending on when the crew recognizes the next event. ROLE: WWC and/or I&C the problem and takes action)

REQUEST: Request support for failed TLA-10, SG TILTS transmitter.

Board Indications RESPONSE: Support as requested.

A SG level increasing above program Note: The operators may perform actions Reactor Thermal Increasing for SD-3A first.

SG PORV SD-3A Red Light Lit

Simulator Exercise Guide Job Aid Page 23 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamental: Closely Monitoring BOP SG A narrow range level not Plant Conditions maintaining on program.

Human performance: Self Checking, Clear BOP Performs immediate actions of AOP-Communications, Procedure Compliance, GEN-001 to place FW-7A in MAN Peer Checking If SG level is changing in an uncontrolled manner then PERFORM the following Operator Fundamental: Precisely Controlling Plant Parameters, Teamwork SHIFT affected SG Feedwater Flow Controller to Manual.

FW-7A THROTTLE affected SG Feedwater control valve to maintain SG narrow range level stable between 33% and 50%

FW-7A Operator Fundamental: Closely Monitoring BOP Identifies SD-3A Open Plant Conditions BOP Performs immediate actions of AOP-GEN-001 to Shut SD-3A Check Steam Generator PORVs BOTH CLOSED (NO SD-3A OPEN)

If SG pressure < 1005 psig than STOP SG PORV Flow Manually CLOSE SD-3A Operator Fundamental: Closely Monitoring BOP Identifies PT-468 failing high Plant Conditions, Knowledge of Plant Design and Theory

Simulator Exercise Guide Job Aid Page 24 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS The US may remove the failed instrument US Hold Brief to for entry to AOP-MISC-001 from service and place FW-7A in automatic before addressing T.S Actions for AOP-MISC-001 US If failed steam pressure channel is an input to a SG PORV VERIFY Immediate Actions of AOP-GEN-001 are complete Place affected SG PORV to Manual (SD-3A)

Adjust SG PORV as necessary to control SG Pressure at desired value BOP Restore A SG narrow range level to 44%

BOP Defeat the failed channel input by selecting the alternate steam flow channel on the associated steam flow channel selector switch BOP When SG level is restored to normal and steam flow and feed flow are matched then place the affected SG feed regulating valve to automatic. (FW-7A)

Simulator Exercise Guide Job Aid Page 25 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Note: Bistables will not be tripped during ROLE: WWC and/or I&C US Contact SM/WWC/IC to perform the scenario REQUEST: Support for failed transmitter. corrective action on failed instrument May Request to perform SP-47-316E for checking for Red Channel Failed Bistables May Request IC support for Tripping Bistables at this time RESPONSE: Support as requested It will take about 45 minutes to get the paper work together for the SP-47-316E.

Will take about 45 minutes to get an IC Tech to the control Room to Trip Bistables

Simulator Exercise Guide Job Aid Page 26 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS T.S. 3.5.b - For online testing or in the US Refer to T.S. 3.5.b event if failure of a subsystem Affected T.S., No Action Statements.

instrumentation channel, plant operation shall be permitted to continue at rated Table TS 3.5-2 Item 16 power in accordance with tables TS 3.5-2 through TS 3.5-5 Table TS 3.5-3 Item 1c Table TS 3.5-2 Item 16 Table TS 3.5-4 Item 2a Stem Flow/Feedwater Flow Mismatch: Table TS 3.5-4 Item 2b No Channels 2, No Channels to Trip 1, Minimum Operable Channels 1 Table TS 3.5-3 Item 1c Low Steam Pressure/Line: No Channels 3, No Channels to Trip 2, Minimum Operable Channels 2 Table TS 3.5-4 Item 2a Hi-Hi Steam Flow with Safety Injection: Channels 2/loop, No Channels to Trip 1, Minimum Operable Channels 1 Table TS 3.5-4 Item 2b Hi Steam Flow and 2 of 4 Lo-Lo Tavg with Safety Injection: Channels 2/loop, No Channels to Trip 1, Minimum Operable Channels 1 After FW-7A has been returned to Automatic, the next event may be initiated.

Simulator Exercise Guide Job Aid Page 27 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 3: SG A develops a small tube leak of ~ 500 gpd (0.35 gpm) over 5 minutes Human Performance Tools: Task Preview. Procedure Compliance, Clear Communications, Peer Checking, Self Checking Operator Fundamentals: Precisely Controlling Plant Parameters, Knowledge of Plant design and Theory, Teamwork, Closing Monitoring Plant Conditions Component RO/BOP Reactivity RO Normal BOP Technical Specification SRO Lead evaluator, WHEN FW-7A has been When directed, initiate Event 3 by activating Annunciators:

returned to AUTO, THEN direct Booth Trigger 5.

TLA-15, RMS Above Normal Instructor to initiate Event 3.

47011-B, Radiation Indication High 47012-B Radiation Indication Alert Note: Annunciator 47011-B and 47012-B will Alarm after the Tube Leak has been active for awhile Board Indications:

N-16 for A SG rising Human Performance: Clear Communications - During Evolution many parameters and control must be coordinated, clear communications within the crew is critical.

Operator Fundamental: The Crew must function efficiently as a team to complete procedure in a timely manner.

Simulator Exercise Guide Job Aid Page 28 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS NOTE: ARP 47033-35, Step 1 contains an ROLE: Radiation Protection Crew perform Actions of ARP.

OR statement that if used, directs RP to PURPOSE: Notified of possible primary to If Alarm is due to R-15 then Go To E-O-14 perform radiation surveys and the secondary leakage (AOP-RC-004) implementation of AOP-RM-001. Also note Survey the area of SG A.

that ARP 47033-35, Step 1 references A- OR RM-45, which has been replaced by AOP- RESPONSE: ACKNOWLEDGE RM-001 communication. CONSULT with control DIRECT Radiation Protection to Survey the room concerning survey requirements Area and Go To A-RM-45 (AOP-RM-001)

DELAY: If requested to survey the area of SG A, wait 10 minutes then report that SG A has elevated counts. If asked SG B counts are normal.

NOTE: If the crew implements AOP-RM- ROLE: NAO Crew may choose to implement AOP-001 they should direct the NAO to close RM-001, Abnormal Radiation Monitoring HS-17 and RP to perform radiation surveys. PURPOSE: Close HS-17 per AOP-RM- System If the crew doesnt implement AOP-RM-001 001, Steps 16 and 20 RNO b.1.b they should NOT direct the NAO to close Step 16 and/or 20 RNO b.1.b. DIRECT HS-17. HS-17 will be closed later in AOP- RESPONSE: REPORT HS-17 CLOSED Equipment Operator to CLOSE HS-17 RC-004 at Step 15.

DELAY 10 minutes NOTE: ARP 47033-35 directs US Announces entry into AOP-RC-004 per implementation of E-0-14 which has been ARP direction replaced by AOP-RC-004.

ROLE: OMOC AOP-RC-004 REQUEST: Inform of SG Tube leak (CAS)US Determine reactor trip NOT RESPONSE: Acknowledge SG Tube Leak required

  • PRZR level > 3%
  • Reactor Critical

Simulator Exercise Guide Job Aid Page 29 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: SM/WWC AOP-RC-004 REQUEST: Inform of SG tube leak & ask for assistance (CAS) US/RO Determine PZR level stable RESPONSE: Acknowledge SG tube leak or trending to program level. As leak and will get people ASAP increase during the scenario US direct RNO actions upon report of PRZR level lowering

  • Increase charging to maximum
  • Turn on all PRZR heaters
  • With report from that level is stable or increasing, control charging as necessary to maintain PRZR level at program US/RO Verify Automatic Makeup Control Note: The crew may contact the SM to ROLE: Chemistry AOP-RC-004 contact Chemistry for the R-15 count rate REQUEST: Estimate R-15 count rate for US Determine S/G leak Rate that equates to 100gpd. If so then as then 100 gpd leak using most recent results from wait 5minutes and report that the estimated CHEM-59.003 per AOP-RC-004, (CY-KW-R-15 count rate for 100gpd is 3172 cpm 059-003) Step 4.a RNO a.1 RESPONSE: ACKNOWLEDGE communication. INFORM operator that it will take approximately 5 minutes to estimate R-15 count rate (time it will take to locate the form)

DELAY: After 5 minutes report that 100 gpd leakage equates to 3172 cpm on R-15

Simulator Exercise Guide Job Aid Page 30 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Note: While waiting for the response from ROLE: Chemistry US evaluates T.S. for the plant transient:

chemistry the US may use this time to REQUEST: Count rate on R-15 for 150 gpd review T.S.

  • 3.1.d.1.D for RCS operational RESPONSE: R-15 count rate for 150 gpd leakage T.S. 3.1.d.1.D; When RCS Tavg is > 2000F, 4758 cpm operational leakage shall be limited to 150 gpd primary to secondary leakage through DELAY: 5 minutes any one SG. If primary to secondary leakage limit exceed, then initiate action to achieve HSD w/n 6 hrs and CSD w/n additional 30 hrs.

Action Level 3 includes 1 hr clock to 50% AOP-RC-004 reactor power and 2 hr clock once reactor CREW determines leakage > 100 gpd power gets to 50% to get to HSD. No credit is given for getting to 50% in < 1 hr. US/CREW determine Action Level 3 required based on R-19 increase > 5%

Human Performance: Task Preview AOP-RC-004/AOP-GEN-002 Note: Chemistry/RP/EO/AO will not be US Perform the following:

available for the shift brief. Task brief for action level 3 using Note: The US may take this time to review Attachment B of AOP-RC-004 & AOP-GEN-AOP-GEN-002 and incorporated required 002 brief in AOP-GEN-002 into brief required Distribute Field Copies of AOP-RC-004 and per AOP-RC-004 AOP-GEN-002 Note: The US may at this time review and perform initial steps of AOP-GEN-002

Simulator Exercise Guide Job Aid Page 31 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Note: Since starting at 27% the US should AOP-RC-004 realize that the desired loading rate is (CAS)US Coordinates load decrease at 1%/min, NOT 3%. Per Step 17 of AOP-RC-1%/min per AOP-GEN-002 while continuing 004.

AOP-RC-004.

The US may request concurrence for establishing initial loading rate at 1%/min instead of the 3% per min stated in Step 11.d.1 of AOP-RC-004. RESPONSE:

Acknowledge Human Performance: Procedure Compliance Operator Fundamental: Teamwork, Precisely Controlling Plant parameters AOP-GEN-002 CREW Make plant announcement AOP-GEN-002 (CAS) US Directs RO to VERIFY rods in AUTO Human Performance: Peer CheckingAll AOP-GEN-002 reactivity calculations must be peer US/RO Estimate required boron to be checked added standard reactivity plan Human Performance: Peer Checking AOP-GEN-002 (CAS) RO Borate RCS at Maximum rate per Attachment G

Simulator Exercise Guide Job Aid Page 32 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS AOP-GEN-002 US Direct Placing All PRZR Heaters ON AOP-GEN-002 (CAS)RO Control Charging and Letdown Flow to Maintain RCS Inventory per CVC-002 AOP-GEN-002 BOP Gen Turbine NOT on VPL

  • Disengage VPL o Verify CV tracking meter nulled o PRESS the Turbine Manual Pushbutton o PRESS the OPER AUTO Pushbutton Note: Per AOP-GEN-002 Step 35 the AOP-GEN-002 Turbine Load Reduction is Stopped at 5%.

(CAS) BOP Prepare for Turbine Load Reduction

  • Check Turbine Load Reduction Desired
  • Check Turbine Mode - OPER AUTO
  • SET Setter to Desired Turbine Load 5% (25-35 MWe)
  • Set Loading Rate to 1%/min

Simulator Exercise Guide Job Aid Page 33 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human Performance: Peer Checking BOP When Tave has lowered by 1ºF then perform load reduction by pressing GO Pushbutton

  • Maintain MVARs 0-150 MVAR Operator Fundamental: Teamwork, Closing AOP-GEN-002 Monitoring Plant Parameters, Precisely RO/BOP Control Boration Flow and power Controlling Plant Parameters reduction as necessary to maintain plant requirements
  • I
  • Rod Insertion Limits
  • Tave within 4ºF of Tref ROLE: DEMI AOP-GEN-002 (CAS) US Inform DEMI of Power Reduction REQUEST: Inform of Load Reduction RESPONSE: Acknowledge DELAY: None AOP-GEN-002 (CAS) US/RO Check Rod Position above alarm set points and RIL

Simulator Exercise Guide Job Aid Page 34 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamental: Closing Monitoring AOP-GEN-002 Plant Parameters (CAS) RO Control Tave/Tref Deviation

  • Verify Control Rods move as necessary to restore Tavg/Tref deviation
  • Check Status light Load Loss 10 PCT Rate: NOT LIT
  • Check Tavg > 540ºF AOP-GEN-002 CREW Review SER points Operator Fundamental: Closing Monitoring AOP-GEN-002 Plant Parameters (CAS) RO/BOP Verify Control Systems Operating in Automatic
  • S/G Level Control
  • PRZR Level Control
  • PRZR Pressure Control AOP-GEN-002 (CAS) ADJUST Heater Drain Pump Speed as necessary to Maintain Equal Loading

Simulator Exercise Guide Job Aid Page 35 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: Chemistry AOP-RC-004 (CAS) CREW determine leaking SG REQUEST: Sample SGs and perform accelerated count to determined leaking SG

  • Direct Chemistry to sample SGs and per AOP-RC-004, Step 12.a. perform accelerated count RESPONSE: ACKNOWLDEGE communication. IF SG sample valves are isolated, THEN REQUEST the sample valves be overridden OPEN.

DELAY: After 30 minutes REPORT A SG activity significantly > B SG activity and that the leak appears to be in A SG.

ROLE: Radiation Protection AOP-RC-004 CREW Direct RP to survey SGBD CIC Ion REQUEST: Survey SGBD CIC Ion Exchange Resin Column Exchange Resin Column per AOP-RC-004, Step 12.b RESPONSE: ACKNOWLEDGE communication.

DELAY: After 4 minutes REPORT that the leak appears to be in SG A due to higher background radiation readings on the SGBD CIC Ion Exchange Resin Column of SG A.

AOP-RC-004/AOP-GEN-002 BOP verifies SGBD isolated per AOP-RC-004 and AOP-GEN-002 step 24

Simulator Exercise Guide Job Aid Page 36 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: Equipment Operator AOP-RC-004/AOP-GEN-002 (CAS) US/BOP Minimize Condenser REQUEST: CLOSE MU-2A per AOP-RCS- Hotwell level per AOP-RC-004 and per 004, Step 14.a AOP-GEN-002 Step 25 RESPONSE: ACKNOWLEDGE direction.

After delay insert TRIGGER 11 and report MU-2A closed.

DELAY: 3 minutes ROLE: Equipment Operator REQUEST: Bypass makeup water plant heater per AOP-RCS-004, Step 14.d RESPONSE: ACKNOWLEDGE direction.

DELAY: 5 minutes later REPORT that the makeup water heater has been bypassed per NOP-MUP-001 ROLE: Equipment Operator AOP-RC-004/AOP-GEN-002 (CAS) US/BOP directs minimizing REQUEST: Minimize secondary secondary system contamination per AOP-contamination per AOP-RCS-004, Step 15 RCS-004. and per AOP-GEN-002 step 26 RESPONSE: ACKNOWLEDGE direction DELAY: 10 minutes later REPORT completion

Simulator Exercise Guide Job Aid Page 37 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: EO AOP-RC-004/AOP-GEN-002 (CAS) BOP Locally Align Heating Steam REQUEST: OPEN HS-5000B, CLOSE HS- Systems Drains to Condenser:

5000A & HS-5001A

  • Locally OPEN HS-5000B RESPONSE: HS-5000B OPEN and HS-5000A and HS-5001A are CLOSED
  • Locally CLOSE HS-5000A

Simulator Exercise Guide Job Aid Page 38 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamental: Closely Monitoring ROLE: AO N-EHV-39 Plant Parameters, Precisely Controlling REQUEST: Check Breaker 1-101, RAT to BOP Transfer Bus 1 from the MAT to the Plant Parameters Bus 1, OPEN and Racked IN RAT RESPONSE: Breaker 1-101, RAT to Bus 1

  • Check Power available from RAT OPEN and Racked IN.
  • Check Breaker 1-101, RAT to Bus 1, Human Performance: Procedure Compliance, Self Checking DELAY: 3 minutes OPEN and Racked IN
  • GAI-TRONICS Plant Announcement
  • POSITION BKR 1-101 Sync Switch to ON
  • VERIFY Incoming and Running Voltage Within 8 volts
  • CHECK Synchroscope indicator within 3.33 minutes (20º) of 12:00
  • WHEN sources are in Sync THEN CLOSE BKR 1-101
  • VERIFY the following o BKR 1-101 red light LIT o Indication of Load Shift between running and incoming sources
  • POSITION Bkr 1-104 to TRIP
  • VERIFY the following o Bkr 1-104 green light LIT o Decrease on Main Aux XFMR Winding Y megawatt and kiloamp indicators
  • POSITION BKR 1-101 Sync Switch to OFF

Simulator Exercise Guide Job Aid Page 39 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamental: Closely Monitoring ROLE: AO N-EHV-39 Plant Parameters, Precisely Controlling REQUEST: Check Breaker 1-201, RAT to BOP Transfer Bus 2 from the MAT to the Plant Parameters Bus 2, OPEN and Racked IN RAT RESPONSE: Breaker 1-201, RAT to Bus 2

  • Check Power available from RAT OPEN and Racked IN.
  • Check Breaker 1-201, RAT to Bus 2, Human Performance: Procedure Compliance, Self Checking DELAY: 3 minutes OPEN and Racked IN
  • GAI-TRONICS Plant Announcement
  • POSITION BKR 1-201 Sync Switch to ON
  • VERIFY Incoming and Running Voltage Within 8 volts
  • CHECK Synchroscope indicator within 3.33 minutes (20º) of 12:00
  • WHEN sources are in Sync THEN CLOSE BKR 1-201
  • VERIFY the following o BKR 1-201 red light LIT o Indication of Load Shift between running and incoming sources
  • POSITION Bkr 1-204 to TRIP
  • VERIFY the following o Bkr 1-104 green light LIT o Decrease on Main Aux XFMR Winding Y megawatt and kiloamp indicators
  • POSITION BKR 1-201 Sync Switch to OFF

Simulator Exercise Guide Job Aid Page 40 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamental: Closely Monitoring ROLE: EO N-EHV-39 Plant Parameters, Precisely Controlling REQUEST: Check Breaker 1-307, RAT to BOP Transfer Bus 3 from the MAT to the Plant Parameters Bus 3, OPEN and Racked IN RAT RESPONSE: Breaker 1-307, RAT to Bus 3

  • Check Power available from RAT OPEN and Racked IN.
  • Check Breaker 1-307, RAT to Bus 3, Human Performance: Procedure Compliance, Self Checking DELAY: 2 minutes OPEN and Racked IN
  • GAI-TRONICS Plant Announcement
  • POSITION BKR 1-307 Sync Switch to ON
  • VERIFY Incoming and Running Voltage Within 8 volts
  • CHECK Synchroscope indicator within 3.33 minutes (20º) of 12:00
  • WHEN sources are in Sync THEN CLOSE BKR 1-307
  • VERIFY the following o BKR 1-307 red light LIT o Indication of Load Shift between running and incoming sources
  • OPEN Bkr 1-301
  • VERIFY the following o Bkr 1-301 green light LIT o Decrease on Main Aux XFMR Winding X megawatt and kiloamp indicators
  • POSITION BKR 1-307 Sync Switch to OFF

Simulator Exercise Guide Job Aid Page 41 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamental: Closely Monitoring ROLE: EO N-EHV-39 Plant Parameters, Precisely Controlling REQUEST: Check Breaker 1-407, RAT to BOP Transfer Bus 4 from the MAT to the Plant Parameters Bus 4, OPEN and Racked IN RAT RESPONSE: Breaker 1-407, RAT to Bus 4

  • Check Power available from RAT OPEN and Racked IN.
  • Check Breaker 1-407, RAT to Bus 4, Human Performance: Procedure Compliance, Self Checking DELAY: 2 minutes OPEN and Racked IN
  • GAI-TRONICS Plant Announcement
  • POSITION BKR 1-407 Sync Switch to ON
  • VERIFY Incoming and Running Voltage Within 8 volts
  • CHECK Synchroscope indicator within 3.33 minutes (20º) of 12:00
  • WHEN sources are in Sync THEN CLOSE BKR 1-407
  • VERIFY the following o BKR 1-407 red light LIT o Indication of Load Shift between running and incoming sources
  • OPEN Bkr 1-401
  • VERIFY the following o Bkr 1-401 green light LIT o Decrease on Main Aux XFMR Winding X megawatt and kiloamp indicators
  • POSITION BKR 1-407 Sync Switch to OFF

Simulator Exercise Guide Job Aid Page 42 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS ROLE: EO AOP-GEN-002 REQUEST: Locally Shutdown Turbine Oil US/BOP Locally shutdown Turbine Oil Reservoir Conditioner:

The Control Room Operator May Request

  • Check Available Resources permit that the EO come to the control room or shutdown of Turbine Oil Conditioner perform Step 29 of AOP-GEN-002 as time
  • CLOSE Oil Reservoir Over Flow TD-permits 310 RESPONSE: Acknowledge direction to
  • STOP Turbine Oil and Circulating Locally Shutdown Turbine Oil Reservoir.

Pump DELAY: Will not be completed by the END

  • CLOSE Conditioner Discharge To of the scenario.

Reservoir TD-301 AOP-GEN-002 (CAS) RO Check P-2 LIT

  • NO - Continue Load Reduction
  • YES - Stop Turbine Load Reduction POSITION Control Rod Bank Selector in MANUAL MAINTAIN Tavg within 1.5ºF of Tref The Scenario is Not Validated for shifting Steam Dumps to Steam Pressure Mode at this time. It is intended that the next event be initiated prior to shifting steam dumps.

Shifting steam dumps is a BOP action.

Simulator Exercise Guide Job Aid Page 43 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 4: SG A tube leak develops into a SGTR Human Performance Tools: Clear Communications, Procedure Use and Adherence, Focus Brief Operator Fundamentals: Closing Monitoring Plant Conditions Major RO/BOP Human Performance: Clear When directed, initiate Event 4 by activating RO recognizes PRZR and VCT level Communications - Clear report of the Trigger 7. lowering and charging flow increasing, and parameters and use of three part reports same to US.

communications US/RO implement AOP-RC-004, (CAS)

Operator Fundamental: Closely Monitoring Step 2 RNO, when PRZR level is no longer Plant Parameters - Recognition of stable at or trending to program level changing PRZR level and VCT level Lead evaluator, WHEN the BOP has shifted 4160V Buses from the MAT to the RAT (AOP-GEN-002, Step 19.b), THEN direct Booth Instructor to initiate Event 4.

CUE:

  • PRZR and VCT level lowering
  • Charging pump speed increasing

Simulator Exercise Guide Job Aid Page 44 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Human Performance: Procedure Use and RO increases charging pump speed and Adherence - The Operator should initially starts second charging pump to establish maximize charging and then reduce speed maximum charging flow in later steps to maintain PRZR Level RO reports that PRZR level continues to NOTE: Two charging pumps are running at lower.

this time. The RO should place the charging US/RO isolate letdown.

pump in AUTO to MANUAL and increase charging to maximum for diagnosis steps

  • LD-2 SHUT that follow.
  • LD-4A SHUT
  • LD-4B SHUT
  • LD-4C SHUT
  • LD-300 SHUT CREW recognizes that a manual trip is required, cannot maintain PRZR/VCT level.

Human Performance: Focus Brief - Ensure US Focus brief for the crew to inform of the crew is aligned with actions tripping and going to E-0 NOTE: The magnitude of the SGTR increases upon reactor trip.

For Information Only: EAL classification FA1, Any Loss or potential loss of either fuel clad or RCS (Table F-1). Table F-1:

SGTR that results in SI actuation.

US directs manual reactor trip and SI RO Manually Trip the reactor and Verify Reactor Trip BOP Verify Turbine Trip

Simulator Exercise Guide Job Aid Page 45 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS BOP Check 4160V Emergency AC Buses at least one energized. Bus 5 or Bus 6 RO verifies that SI has initiated or manually initiates SI on lowering PRZR pressure and level.

Critical Task: Stop Feedwater to A Steam RECORD TIME FEED FLOW ISOLATED BOP once A SG NR level > 5%, isolates Generator within 10 minutes of A Steam TO SG A _____________________ feed to ruptured SG A either in E-0 using Generator Rupture if minimum level FOP or E-3 requirements are met 5% [13%].

SAFETY SIGNIFICANCE: Mitigate Time of Reactor Trip - Time Feed Flow ruptured steam generator overfill and dose Isolated=_____________

consequences, minimize the potential of radiological release from overfill. Min level required to maintain water level above the U-Tubes in order to promote thermal Time S/G A Narrow range level > 5%

stratification to prevent ruptured steam generator depressurization _______________________

CUE: SG A Level rising in an uncontrolled manner or abnormal radiation and SG A narrow range level is > 5%

MEASURABLE PERFORMANCE INDICATOR: BOP Closes AFW-10A or AFW-10B if the Turbine Driven AFW pump is not running. Close AFW-10A if TD AFW pump is running. Close AFW -2A PERFORMANCE FEEDBACK: A AFW header flow indicates zero

Simulator Exercise Guide Job Aid Page 46 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO - Performs Attachment A by direction from the SRO.

(CAS) US/BOP VERIFY AFW pumps Running (CAS) US/BOP AFW discharge pressure >

1000psig US/BOP Verify Secondary Heat Sink US/CREW RXCP Seal Cooling (CAS) US/CREW VERIFY RCS Temperature Control

  • RCS Cold Leg temperatures

<5470F and

  • Stop Dumping Steam
  • If SG pressure less than 1005 psig Then VERIFY SG PORV CLOSED
  • CLOSE MS-1A, MS-2A, MS-1B, MS-2B if RCS temperature continues to lower US/RO Check PRZR PORVs - Both Closed US/RO Check PRZR Spray Valves Closed US/ RO Check if RXCPS should remain running

Simulator Exercise Guide Job Aid Page 47 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS STA Monitor CSF Status Trees US/RO Check If any SG is Faulted US Check If Steam Generator Tubes are Intact

  • Crew Identify a Ruptured S/G.
  • Verify Attachment A complete
  • Crew Brief
  • Transition to E-3 E-3 (CAS) US/RO Check If RXCPs should remain running
  • RXCPs - Any Running
  • Subcooling > 15ºF [37ºF]

ROLE: Radiation Protection CREW Identify Ruptured Steam Generator REQUEST: Support surveys as requested

ROLE: Chemistry REQUEST: Sample SGs as requested RESPONSE: Acknowledge request Note: The only action in this step left to be (CAS) US/BOP - Check if Feed Flow to completed at this time, should be to take Ruptured Steam Generator should be the A AFW pump to pullout. stopped

  • Place A AFW pump to Pullout

Simulator Exercise Guide Job Aid Page 48 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 5: MSIVs Fail to CLOSE Human Performance Tools Self Checking Operator Fundamentals: Understanding Plant Design and Theory Component BOP The MSIVs have been preloaded to fail to US Directs isolating steam flow from SG A close Note: There is no procedural direction to BOP Determines MS-1A will NOT close.

locally close MSIVs.

ROLE: NAO REQUEST: Directed to locally close MSIVs RESPONSE: Acknowledge request DELAY: After 3 minutes report that MSIVs will NOT close locally.

BOP Determines MS-1B will NOT close BOP Sets Steam Dump manual controller (HC-484) to 1050 psig.

BOP shifts steam dumps to steam pressure mode.

Simulator Exercise Guide Job Aid Page 49 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS Operator Fundamental: Understanding ROLE: NAO US Directs local isolation of MS header per Plant Design and Theory - The US should E-3, Attachment C.

understand that Attachment C does not REQUEST: Directed to locally isolate MS isolate SG A from SG B header per E-3, Attachment C.

RESPONSE: Acknowledge request.. Insert Trigger 13, wait delay time and report action complete DELAY: 15 minutes US Directs BOP to use intact SG B PORV to control RCS temperature and cooldown.

Transition from E-3 to ECA-3.1 US determines that SG A can NOT be isolated from SG B AND directs transition to ECA-3.1 ECA-3.1 Human Performance: Self Checking RO reset SI Human Performance: Self Checking RO reset CI BOP Check Instrument Air to Containment Established

  • IA-101 Open
  • Reactor Building Header Pressure >

60 psig (CAS) BOP Check All AC Buses Energized by Off-Site Power RO Place all PRZR heater control switches to OFF

Simulator Exercise Guide Job Aid Page 50 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS (CAS) US Check if Containment Spray Should be Stopped - NO ICS pumps running Note: Feed Flow to Ruptures SG A was BOP Check Ruptured SG A level >

previously stopped 5%[13%]

  • Stop feed flow to Ruptured SG A Human Performance Self Checking - (CAS) RO Check If RHR Pumps Should be Pumps are placed in AUTO not Pullout Stopped
  • RHR pumps running in SI injection mode
  • RCS pressure > 270 psig[300psig]

AND Stable or Increasing

  • Stop RHR Pumps aligned for SI Injection Mode and PLACE in AUTO ROLE: Chemistry US Initiate Evaluation of Plant Status
  • Check Aux Building Radiation REQUEST: Perform EPIP-RET-03C. Levels Normal
  • Chemistry to perform the following RESPONSE: Acknowledge request. No per EPIP-RET-03C, Post Accident further action is required Operation of the High Radiation Sample Room:

o Start up Containment Hydrogen Monitoring System o Sample containment recirculation sump for pH o Sample RCS for boron and activity

  • Start Additional Plant Equipment to assist as necessary

Simulator Exercise Guide Job Aid Page 51 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS RO Establish charging flow RO Align Charging pump suction to the RWST

  • OPEN CVC-301
  • Maintain Total Feed Flow > 210 gpm until intact Steam Generator Narrow Range Level > 5%[13%]
  • Control Feed Flow to Maintain Intact Steam Generator Narrow Range Level 22%-50%

(CAS) BOP Maintain All Running AFW Pumps Discharge Pressures > 100 psig

  • Throttle AFW-2A BOP Initiate RCS Cooldown to Cold Shutdown
  • Cooldown rate < 100ºF/hr
  • RHR system not in service for cooldown

Simulator Exercise Guide Job Aid Page 52 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS NOTE: IF A SG NR level increases to > ROLE: Emergency Director (CAS) US Check if Subcooled Recovery 88% during the scenario, THEN the crew Appropriate will contact the ED to determine if ECA-3.2 REQUEST: A SG NR level is > 88%.

  • RWST Level > 56% -- Yes should be implemented. Should ECA-3.2 be implemented?
  • Check Rupture SG Narrow Range RESPONSE: It is not necessary to Level < 88%[85%]

implement ECA-3.2 at this time.

RO Check RCS Subcooling > 15ºF RO Check ECCS pump Status

  • SI pumps ANY Running

Simulator Exercise Guide Job Aid Page 53 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EVENT 6: Pressurizer spray valves fail to operate Human Performance Tools Self Checking Operator Fundamentals: Precisely Controlling Plant Parameters, Closely Monitoring Plant Conditions Component RO RO Check PRZR Level Greater than 22%[34%] - No RO Depressurize using Normal Spray US/RO Depressurize using ONE PRZR PORV Operator Fundamental: Precisely RO When PRZR Level > 22%[34%] then Controlling Plant Parameters, Closely STOP RCS Depressurization Monitoring Plant Conditions Human Performance: Self Checking RO Check If one RXCP Should be Started

  • Check RXCPs Both Stopped\
  • Stop RXCP A and place in PULLOUT US Determine if one SI pump should be stopped
  • Check SI Pumps - Both Running
  • Determine Required subcooling o 24ºF[78ºF]
  • Check RCS subcooling > required subcooling
  • Check PRZR Level > 22%[34%]
  • Stop one SI pump and Place in AUTO

Simulator Exercise Guide Job Aid Page 54 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS EAL Determination shall be conducted SRO/US identify the current EAL at the as a JPM for the SRO by an examiner if END of the scenario using the EAL matrix .

required Correct Classification is ALERT, FA1 Student may refer to EPIP-AD-02 to assist Emergency Plan in EAL determination

  • For Information Only: EAL classification FA1, Any Loss or potential loss of either fuel clad or RCS (Table F-1). Table F-1: SGTR that results in SI actuation Note EAL SU5.2 during initial SG tube leak when in excess of 25 gpm

Simulator Exercise Guide Job Aid Page 55 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SCENARIO TIME LINE FLOOR INSTRUCTOR BOOTH INSTRUCTOR STUDENTS

6. SCENARIO END: a. FREEZE simulator at direction of floor instructor.

Terminate the scenario after the crew has progressed in ECA-3.1 to determining if one b. STOP DVD recorder. IF this is the SI pump should be stopped (Step 20) OR at last session of the week, THEN the lead evaluators discretion. FINALIZE the DVD (optional)

c. Ensure all EXAM material is collected
7. POST-SCENARIO:
a. ENSURE simulator problems encountered during the scenario are documented IAW site specific process.
b. ENSURE training attendance is documented on, Training Attendance Report.
c. SOLICIT/COLLECT trainee feedback

Simulator Exercise Guide Job Aid Page 56 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A VERIFICATION INSTRUCTIONS These Malfunctions/Remotes/Overrides/Blind triggers SHALL be verified by two independent checkers prior to the start of the scenario after running the ILT-09-SEE03.cae file

Simulator Exercise Guide Job Aid Page 57 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A INPUT

SUMMARY

Delay Event Severity Final Description Time Ramp Time Trigger Or Value Value Relative Order MALFUNCTIONS SER0642 47093-H Bus 5 RAT Source Breaker 1-503 43 Control Switch in 00:00:00 00:00:00 Preload Block Block

  • Manual SER1670 47034-O Source Range High Flux At Shutdown Alarm Blocked 00:00:00 00:00:00 Preload Block Block
  • MS08A MSIV A Fails Open (MS-1A) 00:00:00 00:00:00 Preload TRUE TRUE 1 MS08B MSIV B Fails Open (MS-1B) 00:00:00 00:00:00 Preload TRUE TRUE 1 RC10B Pressurizer PORV PR-2B Fails Open (PCV-430) 00:00:00 00:00:00 1 0 10 2 RX213 PT-468 S/G A Pressure (A PORV and SGWLC Density Comp) 00:00:00 00:01:00 3 0 1400 3 SG02A Steam Generator Tube Leak, Inlet Tubesheet Lo-Volume (1A) 00:00:00 00:05:00 5 0 0.7 4 SG01A Steam Generator Tube Leak, Inlet Tubesheet Hi-Volume (1A) 00:00:00 00:00:00 7 0 8 5
  • Denotes Malfunctions that preload with ALL IC loads REMOTE FUNCTIONS IA101 Air Compressor 1C Local Control Auto/Off/CS 00:00:00 00:00:00 Preload Off Off 1 FW185 MU-2A, Condenser Makeup From CST 00:00:00 00:00:00 11 100 0 request MS105 MS200A1 RHTR 1A Steam Supply Valve 00:00:00 00:00:00 13 open close request MS106 MS200B1 RHTR 1B Steam Supply Valve 00:00:00 00:00:00 13 open close request MS107 MS200A2 RHTR 2A Steam Supply Valve 00:00:00 00:00:00 13 open close request MS108 MS200B2 RHTR 2B Steam Supply Valve 00:00:00 00:00:00 13 open close request FW101 Hogging Jet Inlet Valves (AR-100/MS-400) 00:00:00 00:00:00 13 close close request

Simulator Exercise Guide Job Aid Page 58 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A INPUT

SUMMARY

Delay Event Severity Final Description Time Ramp Time Trigger Or Value Value Relative Order FW102 Main Air Ejector Valves (AR-2/MS-500) 00:00:00 00:00:00 13 open close request OVERRIDES MVA DO-44561-C-COUNT CVCS TOTALIZER COUNT 00:00:00 00:00:00 Preload OFF OFF 1 MCC DI-43304-02-AUTO PS-1B 00:00:00 00:00:00 29 AUTO AUTO 6 MCC DI-43304-02-MAN-BAL PS-1B 00:00:00 00:00:00 29 AUTO AUTO 6 MCC DI-43304-01-AUTO PS-1A 00:00:00 00:00:00 29 AUTO AUTO 6 MCC DI-43304-01-MAN-BAL PS-1A 00:00:00 00:00:00 29 AUTO AUTO 6 MCC AI-43304-02-R2 PS-1B BAL ADJ 00:00:00 00:00:00 29 0 100 6 MCC AI-43304-01-R2 PS-1A BAL ADJ 00:00:00 00:00:00 29 0 100 6 MCC DI-46413-CLOSE PR-1B 00:00:00 00:00:00 9 OFF ON Requested MCC DI-46413-OPEN PR-1B 00:00:00 00:00:00 9 OFF OFF Requested MCC DI-46413-R PR-1B 00:00:00 00:00:00 9 OFF OFF Requested MCC DI-46413-G PR-1B 00:00:00 00:00:00 9 OFF OFF Requested

Simulator Exercise Guide Job Aid Page 59 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A BLIND TRIGGERS (GUN SYMBOL)

Event #29 Event Action: hwzrpg5622==1.0 Trigger activates on reactor trip breaker train A opening and will prevent the Pressurizer Spray valves from operating Event #30 Event Action: hwzrpg5622==1.0 Command: IMF sg01a 20 60 75 Trigger activates on reactor trip breaker train A opening and will cause the SGTR in A SG to become worse

Simulator Exercise Guide Job Aid Page 60 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A CAEP FILE ILT-09-SEE03.cae page 1 IRF IA101 OFF N/A N/A N/A N/A N/A N/A IOR DO-44561-C-COUNT OFF N/A N/A N/A N/A N/A N/A imf 08a N/A N/A N/A N/A N/A N/A imf 08b N/A N/A N/A N/A N/A N/A imf rc10b (1)10 N/A N/A N/A N/A N/A N/A imf rx213 (3) 1400 60 1000 N/A N/A N/A N/A N/A N/A imf sg02a (5) .7 00:05:00 0 N/A N/A N/A N/A N/A N/A imf sg01a (7) 8 N/A N/A N/A N/A N/A N/A ior di-43304-02-auto (29) off N/A N/A N/A N/A N/A N/A ior di-43304-02-man-bal (29) on N/A N/A N/A N/A N/A N/A ior di-43304-01-auto (29) off N/A N/A N/A N/A N/A N/A ior di-43304-01-man-bal (29) on N/A N/A N/A N/A N/A N/A ior di-43304-02-r2 (29) 100 N/A N/A N/A N/A N/A N/A ior di-43304-01-r2 (29) 100 N/A N/A N/A N/A N/A N/A trgset 30 hwzrpg5622==1.0 N/A N/A N/A N/A N/A N/A trg 30 imf sg01a 20 60 75 N/A N/A N/A N/A N/A N/A trgset 29 hwzrpg5622==1.0 N/A N/A N/A N/A N/A N/A ior di-46413-close (9) 1 N/A N/A N/A N/A N/A N/A ior di-46413-open (9) 0 N/A N/A N/A N/A N/A N/A irf fw185 (11) 0 N/A N/A N/A N/A N/A N/A

Simulator Exercise Guide Job Aid Page 61 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A CAEP FILE ILT-09-SEE03.cae page 2 irf ms105 (13) close N/A N/A N/A N/A N/A N/A irf ms106 (13) close N/A N/A N/A N/A N/A N/A irf ms107 (13) close N/A N/A N/A N/A N/A N/A irf ms108 (13) close N/A N/A N/A N/A N/A N/A irf fw101 (13) close N/A N/A N/A N/A N/A N/A irf fw102 (13) close N/A N/A N/A N/A N/A N/A

Simulator Exercise Guide Job Aid Page 62 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SIMULATOR SCENARIO DEVELOPMENT CHECKLIST Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

Yes No

1. The scenario contains objectives for the desired tasks and relevant Human Performance Tools.
2. The scenario content adequately addresses the desired tasks, through simulator performance, instructor-led training freezes, or both.
3. Plant PRA initiating events, important equipment, and important tasks are identified.
4. Turnover information includes a Daily At Power Risk Assessment provided by the PRA Group.
5. The scenario contains procedurally driven success paths. Procedural discrepancies are identified and corrected before training is given.
6. The Scenario Guide includes responses for all communications to simulated personnel outside the Control Room, based on procedural guidance and standard operating practices.
7. The scenario includes related industry experience. Not Required For Evaluations
8. Training elements and specific Human Performance elements are addressed in the Scenario Critique Guide to be used by the Critique Facilitator. The Critique Guide includes standards for expected performance.
9. Any identified Critical Tasks possesses the following elements (NUREG-1021):
  • Essential to safety with adverse consequences or significant degradation,
  • Cue(s) prompt the Operator to respond.
  • Defined and measurable performance indicators.
  • Performance feedback.

The use of N/A is allowed for item 9 only if this is NOT an evaluated scenario.

10. Technical Specifications including Limiting Conditions for Operation, reactivity briefings, and Emergency-Plan entries are addressed as appropriate.

Developer and Reviewer: Once checklist is completed and deficiencies are corrected, sign the cover page.

Simulator Exercise Guide Job Aid Page 63 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A SIMULATOR EXERCISE VALIDATION CHECKLIST Mark with an X Yes or No for any of the following. If the answer is No, include an explanation after the item.

Yes No

1. The desired initial condition(s) could be achieved.
2. All malfunctions and other instructor interface items were functional and responded to support the simulator Scenario.
3. All malfunctions and other instructor interface items were initiated in the same sequence described within the simulator scenario.
4. All applicable acceptance criteria were met for procedures that were used to support the simulator scenario.
5. During the simulator scenario, observed changes corresponded to expected plant response.
6. Did the scenario satisfy the learning or examination objectives without any significant simulator performance issues, or deviations from the approved scenario sequence?
7. The simulator is capable of being used to satisfy learning or examination objectives without exceptions, significant performance discrepancies, or deviation from the approved scenario sequence.
8. Any identified Critical Tasks possesses the following elements (NUREG-1021):
  • Essential to safety with adverse consequences or significant degradation,
  • Cue(s) prompt the Operator to respond.
  • Defined and measurable performance indicators.
  • Performance feedback.

The use of N/A is allowed for item 8 only if this is NOT an evaluated scenario.

Discrepancies noted (Check none or list items in comments field) None Comments: None Validator: Sign the cover page only after noted discrepancies are corrected or compensatory actions are taken to ensure quality training.

Simulator Exercise Guide Job Aid Page 64 of 64 SEG# ROI-06-SE-SC03/SOI-06-SE-SC03 Rev: A Applied & Implemented All Information Passed on to All Any Knowledge or Performance Corrective Actions if TS/TRM (PP-1) Identified All Applicable Correctly Crew Members (i.e., briefs) Deficiencies Required As Time Allowed T.S. 3.1.a.5.A.2 Yes No Yes No Yes No T.S. 3.10.I Yes No Yes No Yes No T.S. 3.10.n Yes No Yes No Yes No COLR 2.11 Yes No Yes No Yes No T.S. 3.5.b Yes No Yes No Yes No Table TS 3.5-2 Yes No Yes No Yes No Item 16 Table TS 3.5-3 Yes No Yes No Yes No Item 1c Table TS 3.5-4 Yes No Yes No Yes No Item 2a Table TS 3.5-4 Yes No Yes No Yes No Item 2b 3.1.d.1.D Yes No Yes No Yes No EALs All Information Passed on to All Any Knowledge or Performance Corrective Actions if Identified All Applicable Classified & Notified Timely (EP Group) Crew Members (i.e., briefs) Deficiencies Required SU5.2 Yes No Yes No Yes No FA1 Yes No Yes No Yes No Yes No Yes No Yes No Any Knowledge or Performance Corrective Actions if Procedure Compliance (PP-3) Applied & Implemented Correctly As Time Allowed Deficiencies Required Yes No Yes No Any Knowledge or Performance Corrective Actions if Human Performance Errors (PP-2) Identify All HU Errors or Potential HU Errors Deficiencies Required Identify All Operator Fundamental Errors Or Potential Operator Fundamental Any Knowledge or Performance Corrective Actions if Operator Fundamentals Errors Deficiencies Required