ML070380304

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Draft - Section a Operating Exam (Folder 2)
ML070380304
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 11/22/2006
From: Vanwyen T
Exelon Generation Co
To: Todd Fish
Operations Branch I
Sykes, Marvin D.
Shared Package
ML060800089 List:
References
Download: ML070380304 (56)
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Text

EXELON NUCLEAR Nuclear Generation Group OJTlTPE MATERIAL COVERSHEET APPROVALS:

Signature /Title Date Signature I Title Date Signature / Title Date Signature I Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

SOC. SEC. NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: I PlMS CODE:

4- . SignaturelDate I PlMS ENTRY: I 2007 NRC JPM RO AD-CO1 (2005 RO-DW Temp Monitoring) Page 1 of 5

TEMPORARY CHANGE FORM LOG

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-4.

CODE NO.: PLOR-XXXC REV. NO.: 001 TITLE: MANUALLY CALCULATE DRYWELL BULK AVERAGE TEMPERATURE -

ALTERNATE PATH (Failed Temperature Points) 2.

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2007 NRC JPM RO AD-CO1 (2005 RO-DW Temp Monitoring) Page 2 of 5

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: WA: G2.1.7 URO: 3.7 SRO: 4.4 TASK DESCRIPTI0N: MANUALLY CALCULATE DRYWELL BULK AVERAGE TEMPERATURE - ALTERNATE PATH (Failed Temperature Points)

A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.
2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.
3. JPM Performance
a. Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).
b. When performing ln-Plant JPMs, no equipment will be operated without Shift Management approval.
4. Satisfactory performance of this JPM is accomplished if:
a. The task standard is met.
b. JPM completion time requirement is met.
1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.
2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.
5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

2007 NRC JPM RO AD-CO1 (2005RO-DW Temp Monitoring) Page 3 of 5

B. TOOLS AND EQUIPMENT I. RT-0-40C-530-2, Drywell Temperature Monitoring L--

2. RT-0-40C-530-2, Data Sheet 1 with temperature values filled in with points 137 and 139 indicated as out of service and point 136 reading 132.4F C. REFERENCES
1. RT-0-40C-530-2, Rev. 5, Drywell Temperature Monitoring D. TASK STANDARD
1. Satisfactory task completion is indicated when the operator has determined that Drywell Temperature requires entry into ON-I 20, High Drywell Temperature.
2. Estimated time to complete: 20 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to *** using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Unit 2 is experiencing a small steam leak into primary containment.
2. TI-80146, the drywell bulk average temperature indication, has failed.
3. Another operator has completed taking the temperatures required for Data Sheet 1 of RT-0-40C-500-2, Drywell Temperature Monitoring.

G. INITIATING CUE The Control Room Supervisor directs you to perform RT-0-40C-530-2, Drywell Temperature Monitoring, beginning with step 6.2.1, and report any required actions.

2007 NRC JPM RO AD-COI (2005RO-DW Temp Monitoring) Page 4 of 5

H. PERFORMANCE CHECKLIST STEP NO STEP 1 ACT STANDARD 1 Review the provided, partially complete, P Candidate reviews the ST and ST to determine where to begin in the ST. determines that all steps are signed off up to step 6.2.1.

  • 2 Review Data Sheet 1 and recognize that P Recognize that the calculation of Bulk all of the temperature points in Zone Average temperature is INVALID. Place Number 4 are out of service (Step 6.2.1). an N/A in step 6.2.1.

3 Record the instrument used on the blank P Record TI-2501, Point 136 in the provided in step 6.2.2.1. Instrument Used blank provided in step 6.2.2. I then initial the step in the SAT column.

  • 4 Record the value of TI-2501, Point 136 in P Record 132.4 in the blanks provided the provided blanks in steps 6.2.2.1 and before the first OFin steps 6.2.2.1 and 6.2.2.2. 6.2.2.2.
  • 5 Calculate approximate Drywell Bulk P Calculate 132.4F + 10°F = 142.4F.

Average Temperature as indicated in step Record 142.4 in the blank provided in 6.2.2.2. step 6.2.2.2, then initial the step in the SAT column.

Complete verification of Drywell Bulk P Initial the UNSAT Black Box beside Step Average Temperature less than 140°F. 6.2.3.

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Report ON-120 High Drywell P Report to the CRS that ON-I20 should be Temperature entry condition. entered due to Approximate Drywell Bulk Average Temperature greater than 140°F.

As an evaluator, ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites)AND procedures.

Under ACT P - must perform S - must simulate I. TERMINATING CUE

  • /

When the candidate informs the Control Room Supervisor of the ON-120, High Drywell Temperature, entry condition, the evaluator will then terminate the exercise.

2007 NRC JPM RO AD-CO1 (2005 RO-DW Temp Monitoring) Page 5 of 5

TASK CONDITIONS/PREREQUISlTES Unit 2 is experiencing a small steam leak into primary containment.

2. TI-80146, the drywell bulk average temperature indication, has failed.
3. Another operator has completed taking the temperatures required for Data Sheet Iof RT-0-4OC-500-2, Drywell Ternperature Monitori ng.

INITIATING CUE The Control Room Supervisor directs you to perform RT-0-40C-530-2, DrywelI Tem perature Monitoring, beginning with step 6.2.1 , and report any required actions.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

- . j APPROVALS:

Signature I Title Date Signature /Title Date Signature /Title Date Signature I Title Date T A P P R O V E D FOR USE:

Signature I Title Date I EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

SOC. SEC. NO. COMPLETION DATE:

Training Review for Completeness: 1 PlMS CODE: I

-d SignaturelDate I I

ENTRY: I 2007 NRC JPM RO AD-C02 (New-Reactor Coolant Leakage Test} Page 1 of 6

TEMPORARY CHANGE FORM LOG

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CODE NO.: PLOR-XXXC REV. NO.:

TITLE: PERFORM REACTOR COOLANT LEAKAGE SURVEILLANCE 1.

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W' 2007 NRC JPM RO AD-C02 (New-Reactor Coolant Leakage Test) Page 2 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 8 WA: G2.1.25 URO: 2.8 SRO: 3.1 TASK DESCRIPTION: PERFORM REACTOR COOLANT LEAKAGE SURVEILLANCE A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.
2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.
3. JPM Performance
a. Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).
b. When performing ln-Plant JPMs, no equipment will be operated without Shift Management approval.
4. Satisfactory performance of this JPM is accomplished if:
a. The task standard is met.
b. JPM completion time requirement is met.

I) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.
5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

v 2007 NRC JPM RO AD-C02 (New-Reactor Coolant Leakage Test) Page 3 of 6

B. TOOLS AND EQUIPMENT

1. Copy of ST-0-020-560-2, Rev. 12, Reactor Coolant Leakage Test with hand-written

, / . . . -< data already filled in on Data Sheet 1 (use Attachment 2 of this JPM for exact values)

2. Calculator C. REFERENCES
1. ST-0-020-560-2, Rev. 12, Reactor Coolant Leakage Test D. TASK STANDARD
1. Satisfactory task completion is indicated when reactor coolant leakage has been calculated using Data Sheet 1 of ST-0-020-560-2 Reactor Coolant Leakage Test.
2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to calculate reactor coolant leakage using ST-0-020-560-2 Reactor Coolant Leakage Test. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISlTES C-

1. Unit 2 is at 100% power.
2. The Unit 2 Drywell Sump Monitoring System is operable.
3. Unit 2 Drywell Floor Drain Sump valves and pumps are lined up in accordance with SO 20C. 1.A, Floor Drain Sumps Startup and Normal Operation.

I

4. Unit 2 Drywell Equipment Drain Sump valves and pumps are lined up in accordance with SO 20C.1.D, Equipment Drain Sumps Startup and Normal Operation.
5. A 0 2A.16-2 Manual Adjustment of Recirculation Pump Seal Second Stage Pressure has NOT been performed.
6. The previous we6ks last six 4-hour flow data readings of Drywell Floor and Equipment Drain Sumps has been entered on Data Sheet 1 of ST-0-020-560-2,Reactor Coolant Leakage Test.
7. The current 4-hour Drywell Floor Drain and Equipment Drain sump integrator reading has already been documented on Data Sheet 1 of ST-0-020-560-2,Reactor Coolant Leakage Test.

G. INITIATING CUE The Control Room Supervisor directs you to determine the Unit 2 reactor coolant leakage flow rate by performing steps 6.1 through 6.4 of ST-0-020-560-2,Reactor Coolant Leakage Test.

.-+

2007 NRC JPM RO AD-C02 (New-Reactor Coolant Leakage Test) Page 4 of 6

H. PERFORMANCE CHECKLIST STEP ACT STANDARD Cue: Hand the Examinee the hard P copy of ST-0-020-560-2,yReactor Coolant Leakage Test with Data Sheet I data filled in by hand from Attachment 2 of this JPM.

~

Calculate and record Drywell Floor Drain P Subtract the latest Floor Drain Sump 4-hour integrator difference. Integrator reading from the previous 4-hour reading. Place a 0 in column (a) of Data Sheet 1.

Calculate and record Drywell Floor Drain P Divide the number from column (a) of flow in gallons per minute. Data Sheet 1 by 12. Place a 0 in column (b) of Data Sheet 1.

Calculate and record the Drywell Floor P Add the six flow numbers from Column Drain 24-hour running average flow. (b) and divide by 6. Place a 0 in column (c) of Data Sheet 1.

i

  • 6 Record 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> running average flow Drywell Floor Drain for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago.

Calculate and record the Drywell Floor Ip P Record a 0 in column (d) of Data Sheet 1.

Subtract column (d) from column (c) on Drain 24-hour running average difference. Data Sheet 1. Place a 0 in column (e) on Data Sheet 1.

  • 7 Calculate and record Equipment Floor P Subtract the latest Equipment Drain Drain 4-hour integrator difference. Sump integrator reading from the previous 4-hour reading. Place a 19 in column (9 of Data Sheet 1.
  • 8 Calculate and record Drywell Equipment P Divide the number from column (9 of Drain flow in gallons per minute. Data Sheet Iby 12. Place a 1.58 in column (9) of Data Sheet 1.
  • 9 Calculate and record Total Drywell P Add the six Equipment Drain numbers Leakage. from column (b) to the six Equipment Drain numbers from column (9) of Data Sheet 1.

Divide the above number by 6 and place a I .38 in column (h) of Data Sheet 1.

2007 NRC JPM RO AD-C02 (New-Reactor Coolant Leakage Test) Page 5 of 6

STEP ACT STANDARD

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L-I *IO Verify the following data is acceptable: P Verify all data is below the specified limits and initial All Data Within Accep Crit Column (b) is 5 5.0 gpm Column of Data Sheet1 as SAT.

Column (e) is 5 2.0 gpm Column (h) is 5 25.0 gpm

~~

As an evaluator, ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under ACT P - must perform S - must simulate I. TERMINATING CUE When step 6.4 of ST-0-020-560-2,Reactor Coolant Leakage Test has been completed the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

2007 NRC JPM RO AD-C02 (New-Reactor Coolant Leakage Test) Page 6 of 6

TASK CONDITIONS/PREREQUBITES

1. Unit 2 is at 100% power.
2. The Unit 2 Drywell Sump Monitoring System is operable.
3. Unit 2 Drywell Floor Drain Sump valves and pumps are lined up in accordance with SO 20C.l.A, Floor Drain Sumps Startup and Normal Operation.
4. Unit 2 Drywell Equipment Drain Sump valves and pumps are lined up in accordance with SO 20C.l.D, Equipment Drain Sumps Startup and Normal Operation.
5. A 0 2A.16-2 Manual Adjustment of Recirculation Pump Seal Second Stage Pressure has NOT been performed.

. - 6. The previous weeks last six 4-hour flow data readings of Drywell Floor and Equipment Drain Sumps has been L A -

entered on Data Sheet 1 of ST-0-020-560-2,Reactor Coolant Leakage Test.

7. The current 4-hour Drywell Floor Drain and Equipment Drain sump integrator reading has already been documented on Data Sheet 1 of ST-0-020-560-2,Reactor Coolant Leakage Test.

INITIATING CUE The Control Room Supervisor directs you to determine the Unit 2 reactor coolant leakage flow rate by performing steps 6.1 through 6.4 of ST-0-020-560-2,Reactor Coolant Leakage L- Test .

EXELON NUCLEAR Nuclear Generation Group OJTlTPE MATERIAL COVERSHEET APPROVALS:

Signature I Title Date Signature /Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

SOC. SEC. NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: I PlMS CODE:

v Signatu re/Date I I

ENTRY:

I 2007 NRC JPM RO AD-EC (PLOR205C Rev000) Page 1 of 6

TEMPORARY CHANGE FORM LOG

.v' CODE NO.: PLOR-20% REV. NO.:

TITLE: Prepare a Partial Procedure 2.

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2007 NRC JPM RO AD-EC (PLOR205C Rev000) Page 2 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 3421130302 / PLOR-20% WA: 2.2.11 URO: 2.5 SRO: 3.4 TASK DESCRIPTION: PreDare a Partial Procedure A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.
2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.
3. JPM Performance
a. Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).
b. When performing ln-Plant JPMs, no equipment will be operated without Shift Management approval.
4. Satisfactory performance of this JPM is accomplished if:
a. The task standard is met.
b. JPM completion time requirement is met.
1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.
2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.
5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

2007 NRC JPM RO AD-EC (PLOR205C Rev000) Page 3 of 6

B. TOOLS AND EQUIPMENT

1. A blank copy of ST-0-010-401-2, Rev. 0, RHR Manual Isolation Valves Remote

\ .-+ Position Indication Verification C. REFERENCES

1. HU-AA-104-101, Rev. 0, Procedure Use and Adherence
2. AD-PB-101-1003, Rev. 5, Temporary Changes To Approved Documents And Partial Procedure Use
3. ST-0-010-401-2, Rev. 0, RHR Manual Isolation Valves Remote Position Indication Verification D. TASK STANDARD I. Satisfactory task completion is indicated when the candidate has correctly prepared ST-0-010-401-2, RHR Manual Isolation Valves Remote Position Indication Verification as a partial for the completion of Post Maintenance Testing on the B RHR Loop Manual Isolation Valve.
2. Estimated time to complete: 15 minutes Non-Time Critical

. E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to prepare a partial procedure for Post Maintenance Testing of the B RHR Loop Manual Isolation Valve using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDIT10NSIPREREQ UISITES

1. Unit 2 is in an outage.
2. The plant is in Mode 4.
3. Work has been performed on HV-2-10-081B, RHR Loop B Manual Isolation Valve.
4. Maintenance has completed repairs on the valve and it is ready for Post Maintenance Testing.

2007 NRC JPM RO AD-EC (PLOR205C Rev000) Page 4 of 6

G. INITIATING CUE

.LAThe Control Room Supervisor directs you to prepare a Partial Procedure using ST-0-010-401-2, RHR Manual Isolation Valves Remote Position Indication Verification to complete Post Maintenance Testing of the HV-2-10-081B, in accordance with HU-AA-104-101 and AD-PB-101-1003. Submit the completed partial procedure for review and approval to the SQR.

\+--

2007 NRC JPM RO AD-EC (PLOR205C Rev000) Page 5 of 6

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1 Obtain a copy of the procedure. P A copy of ST-0-010-401-2 is obtained.

  • 2 Enter the word PARTIAL on the first P The word PARTIAL is entered on the page of the procedure. front page.
  • 3 Record the reason for the partial and P Candidate writes words that indicate the whether additional testing is required to partial is being used as Post Maintenance fuIfilI surveiIlance test requirements. Test and that it will meet the surveillance requirements for the position indication of the B manual isolation valve.
  • 4 Indicate changes to Section 6.0, Steps 6.1.2 through 6.1.5 should be Performance Steps, those steps of the marked N/A.

procedure that are not required to be performed.

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5 Indicate changes to Section 7.0, Step 7.1.1 should be marked N/A.

Procedure Completion, those steps of the procedure that are not required to be performed.

6 Indicate changes to Data Sheet 1 those P Information for HV-2-10-081A on Data steps of the procedure that are not Sheet 1 should be marked N/A.

required to be performed.

Submit the partial for approval. P Candidate will give evaluator the marked up procedure for approval.

(Cue: Accept partial for approval.)

As an evaluator ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under ACT P - must perform S - must simulate I. TERMINATING CUE When the candidate submits the Partial Procedure for approval, the evaluator will then terminate the exercise.

2007 NRC JPM RO AD-EC (PLOR205C Rev000) Page 6 of 6

TASK CONDITIONS/PREREQUlSlTES I. Unit 2 is in an outage.

2. The plant is in Mode 4.
3. Work has been performed on HV-2-10-081B, RHR Loop B Manual Isolation Valve.
4. Maintenance has completed repairs on the valve and it is ready for Post Maintenance Testing.

INITIATING CUE The Control Room Supervisor directs you to prepare a Partial Procedure using ST-0-010-401-2, RHR Manual Isolation Valves Remote Position Indication Verification to complete Post Maintenance Testing of the HV-2-10-081B, in accordance with HU-AA-104-101 and AD-PB-IOI-1003. Submit the completed partial procedure for review and approval to the SQR.

EXELON NUCLEAR Nuclear Generation Group OJTITPE MATERIAL COVERSHEET APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

SOC. SEC. NO. COMPLETION DATE:

Training Review for Completeness: PlMS CODE:

PlMS ENTRY:

Signature/Date 2007 NRC JPM RO AD-EP (PLOR217C Rev001) Page 1 of 6

TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-217C REV. NO.: 002 TITLE: PERFORM PERSONNEL NOTIFICATIONS DURING A SECURITY THREAT 1.

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2007 NRC JPM RO AD-EP (PLOR217C Rev001) Page 2 of 6

PECO NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2008550401 / PLOR-217C WA: 2.1.8 URO: 3.8 SRO: 3.6 TASK DESCRIPTION: Perform Actions For A Security Emergency In Accordance With SE-23 A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.
2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.
3. JPM Performance
a. Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).
b. When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.
4. Satisfactory performance of this JPM is accomplished if:
a. The task standard is met.
b. JPM completion time requirement is met.
1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.
2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.
5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

2007 NRC JPM RO AD-EP (PLOR217C Rev001) Page 3 of 6

B. TOOLS AND EQUIPMENT I. SE-23, Response to Security Threats

. I

2. Ensure the radio in the Simulator is selected to Ops Channel 1.

C. REFERENCES

1. SE-23, Rev. 13, Response to Security Threats D. TASK STANDARD
1. Satisfactory completion of this task is indicated when the Security Threat Announcements have been properly completed.
2. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, make the Security Threat announcement in accordance with SE-23, Response to Security Threats. I will describe the initial conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISlTES

.-. 1. Peach Bottom Atomic Power Station is currently experiencing an Aircraft Probable (Airborne Threat - Probable) security threat.

2. The operating crew is executing SE-23, Response to Security Threats.

G. INITIATING CUE The Control Room Supervisor directs you to make the site announcements in accordance with step 3.3.5 of SE-23, Response to Security Threats.

2007 NRC JPM RO AD-EP (PLOR217C Rev001) Page 4 of 6

H. PERFORMANCE CHECKLIST STEP NO ACT STANDARD

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1 Obtain a copy of SE-23, Response to P Candidate obtains a copy of SE-23, Security Threats. Response to Security Threats and references step 3.3.5.

(Cue: this procedure may be provided by the examiner.)

2 Determine that Script #2 of SE-23 P Candidate selects Script #2 of SE-23 Attachment 1 is the correct script for Attachment 1 due to initial conditions Airborne Threat - Probable. being an Aircraft Probable security threat.

3 Activate the station alert tone. P Candidate activates the station alert tone by depressing the red push button beside (Cue: the alert tone is activated.) the plant page handset at least once, preferably twice.

The steps to make the announcement over the plan page and the radio systems may be completed either sequentially or simultaneously.

  • 4 Make the announcement over the plant P Candidate depresses the page handset page. pushbutton and states, Attention all personnel, attention all personnel. An airborne threat has been determined to exist at the station and a Rapid Evacuation has been ordered.

Operators in excess of minimum staffing requirements muster at the upper North parking lot. Fire Brigade obtain protective gear and muster at the upper North parking lot. All personnel at Unit 1 assemble at the Atom Road Parking lot. ERO members and all other site personnel assemble at the Upper North parking lot. I repeat, an airborne threat has been determined to exist at the station and a Rapid Evacuation has been ordered. Operations in excess of minimum staffing requirements muster at the upper North parking lot. Fire Brigade obtain protective gear and muster at the Upper North parking lot. All personnel at Unit 1 assemble at the Atom Road parking lot. ERO members and all other site personnel assemble at the Upper North parking lot.

4 2007 NRC JPM RO AD-EP (PLOR217C Rev001) Page 5 of 6

STEP ACT STANDARD

-_ 5 Make the announcement over the radio P Candidate depresses the radio system. transmitter pushbutton and states, Attention all personnel, attention all personnel.

(Cue: Acknowledge announcement.) An airborne threat has been determined to exist at the station and a Rapid Evacuation has been ordered. Operators in excess of minimum staffing requirements muster at the upper North parking lot. Fire Brigade obtain protective gear and muster at the upper North parking lot. All personnel at Unit 1 assemble at the Atom Road Parking lot. ERO members and all other site personnel assemble at the Upper North parking lot. I repeat, an airborne threat has been determined to exist at the station and a Rapid Evacuation has been ordered. Operations in excess of minimum staffing requirements muster at the upper North parking lot. Fire Brigade obtain protective gear and muster at the Upper North parking lot. All personnel at Unit 1 assemble at the Atom Road parking lot. ERO members and all other site personnel assemble at the Upper North parking lot.

a Report to the Control Room Supervisor P Report that the Security Threat that the announcement has been made. announcement has been completed.

(Cue: acknowledge report.)

9 As an evaluator, ensure that you have P Positive Control Established.

positive control of all exam material provided to examinees (Task Conditions/PrerequisitesAND procedures).

Under ACT P - must perform S - must simulate TERMINATING CUE:

When the candidate reports that the Security Threat announcements are complete, the evaluator may then terminate the exercise.

2007 NRC JPM RO AD-EP (PLOR217C Rev001) Page 6 of 6

TASK CONDlTlONS/PREREQUlSlTES w

1. Peach Bottom Atomic Power Station is currently experiencing an Aircraft Probable (Airborne Threat - Probable) security threat.
2. The operating crew is executing SE-23, Response to Security Threats.

INITIATING CUE The CRS directs you to make the site announcements in accordance with step 3.3.5 of SE-23, Response to Security Threats.

EXELON NUCLEAR Nuclear Generation Group OJTlTPE MATERIAL COVERSHEET

'd APPROVALS:

Signature / Title Date Signature /Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature /Title Date EFFECTIVE DATE: i f NAME: ISSUE DATE:

Last First M.I.

SOC. SEC. NO. COMPLETION DATE:

COMMENTS:

Training Review for Completeness: PlMS CODE:

C' Signature/Date I ENTRY:

TEMPORARY CHANGE FORM LOG 2007 NRC JPM SRO AD-CO1 (SRO AJPM l-Evaluate Shift Staffing) Page 1 of 7

CODE NO.: PILT-ADMINOOO REV. NO.:

.W' TITLE: EVALUATE SHIFT STAFFING I.

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2007 NRC JPM SRO AD-CO1 (SRO AJPM 1-Evaluate Shift Staffing) Page 2 of 7

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE

.u POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: X WA: Generic 2.1.4 URO: 2.3 SRO: 3.4 TASK DESCRIPTI0N: Knowledge of shift staffing requirements A. NOTES TO EVALUATOR:

I. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.
3. JPM Performance
a. Control Room JPMs are designed to be performed in the simulator. If a u

Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b. When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.
4. Satisfactory performance of this JPM is accomplished if:
a. The task standard is met.
b. JPM completion time requirement is met.
1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.
2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.
5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

2007 NRC JPM SRO AD-CO1 (SRO AJPM I-Evaluate Shift Staffing) Page 3 of 7

B. TOOLS AND EQUIPMENT

1. None

,L-/* c REFERENCES

1. OP-PB-101-111, Rev. 6, Peach Bottom Operations Department
2. OP-AA-105-101, Rev.9, Administrative Process for NRC License and Medical Requirements
3. LS-AA-119, Rev. 4, Overtime Controls
4. OPM-P-30, Rev. 0, Reactor Operator Staffing Policy
5. OPM-P-40, Rev. 1, Peach Bottom Operations Overtime Policy D. TASK STANDARD
1. Satisfactory task completion is indicated when the Work Execution Center Supervisor has chosen an appropriately qualified individual that will not exceed overtime requirements to replace the disqualified operator, in accordance with approved procedures.
2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform the steps necessary to ensure that your shift is appropriately staffed. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. Both units are operating at full power conditions.
2. Unit #2 is expected to do a load drop later this morning to facilitate investigation of air inleakage on the Main Condenser.
3. Shift crew PSOI has just assumed the watch and you are the Work Execution Center Supervisor.
4. The shift is staffed as indicated on the Shift Attendance Briefing Sheet.

G. INITIATING CUE As the PSOI Work Execution Center Supervisor, using appropriate procedures and the Shift Attendance Briefing Sheet, determine if shift manning requirements are being met.

2007 NRC JPM SRO AD-CO1 (SRO AJPM I-Evaluate Shift Staffing) Page 4 of 7

H. PERFORMANCE CHECKLIST G STANDARD NO STEP ACT CUE: Provide the candidate with Hand the candidate the Shift Attendance Attachment 2 of this JPM. Briefing Sheet (Attachment 2 of this JPM).

CUE: When the candidate has had time to review Attachment 2, tell him/her that you are with Regulatory Assurance and that you have just been informed that Gary Johnsons NRC medical examination expired yesterday.

I Obtain a copy of OP-AA-105-101, Obtains a copy of OP-AA-105-101, Administrative Process for NRC Administrative Process for NRC License an License and Medical Requirements Medical Requirements.

and review/utilize the correct section of the procedure.

~~

  • 2 Evaluate the impact of Gary Using OP-AA-105-101, Administrative Proc Johnsons medical qualification for NRC License and Medical Requirements expiring and determine that he must steps 4.4.4 and/or 4.4.5,determines Gary be removed from licensed duties. Johnson must be removed from licensed du until such time as a satisfactory medical exa can be completed.

3 Determine if shift staffing P May refer to:

requirements are met.

0 OPM-P-30, Reactor Operator Staffin PoIicy, 0 Technical Specification 5.2, 0 OP-PB-101-1 I1, Peach Bottom Operations Department Directs the fourth RO to relieve Gary Johnst the Unit 3 Reactor Operator.

Determines the minimum staffing requireme are now met with three (3) Reactor Operato May reassign a Shift Supervisor use Gar Johnson to fill Shift Emergency Communica position vacated by moving 4h RO.

2007 NRC JPM SRO AD-CO1 (SRO AJPM I-Evaluate Shift Staffing) Page 5 of 7

STEP NO STEP ACT STANDARD CUE: As the Shift Manager state that for the impending load drop, four (4) Reactor Operators are needed in the Control Room and no more are available on shift.

Request the WECS to determine which RO to call-out for the remainder of the shift.

~~ ~

4 Call-out of a qualified Reactor P May refer to the following procedures:

3perator.

OPM-P-40, Peach Bottom Operations CUE: As the Shift Clerk, hand the Overtime Policy candidate Attachment 3 of this JPM, the RO Active 0 LS-AA-119, Overtime Controls License Call-out List.

Requests a copy of the RO Active License Call-out List from the Shift Clerk.

5 Determine which of the qualified P May refer to Technical Specification 5.2 and/or, Reactor Operators on the list is LS-AA-119, Overtime Controls.

available without exceeding LS-AA-119 limitations. Determines that M. Ames is the only Reactor Operator on the supplied list that can be called out for the full twelve ( I 2) hours without exceeding procedural and Technical Specification limitations.

6 As an evaluator ensure that you P Positive control established.

have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites)

AND procedures.

Under ACT P - must perform S - must simulate 2007 NRC JPM SRO AD-CO1 (SRO AJPM I-Evaluate Shift Staffing) Page 6 of 7

I. TERMINATING CUE:

When the Work Execution Center Supervisor has chosen an appropriately qualified individual

-4 to replace the disqualified operator, that will not exceed LS-AA-119 overtime requirements, the evaluator will terminate the exercise.

J. SPECIAL INSTRUCTIONS:

The following Attachments are provided as described in the above steps:

1. Task Cue Sheet.
2. Shift Attendance Briefing Sheet.
3. RO Active License Call-out List.

u.

2007 NRC JPM SRO AD-CO1 (SRO AJPM 1-Evaluate Shift Staffing) Page 7 of 7

TASK CONDITIONS/PREREQUISlTES

,W I. Both units are operating at full power conditions.

2. Unit #2 is expected to do a load drop later this morning to facilitate investigation of air in-leakage on the Main Condenser.
3. PSOl has just assumed the watch and you are the Work Execution Center Supervisor.
4. The shift is staffed as indicated on the Shift Attendance Briefing Sheet.

INITIATING CUE As the PSOl Work Execution Center Supervisor (WECS), using appropriate procedures and the Shift Attendance Briefing Sheet, determine if shift manning requirements are being met.

EXELON NUCLEAR Nuclear Generation Group OJTlTPE MATERIAL COVERSHEET

-\.-,.-

APPROVALS:

Signature / Title Date Signature / Title Date Signature I Title Date

---. ,( Signature /Title Date EFFECTIVE DATE: I I NAME: ISSUE DATE:

Last First M.I.

SOC. SEC. NO. COMPLETION DATE:

Training Review for Completeness: I PlMS CODE: I I

Signature/Date I ENTRY:

2007 NRC JPM SRO AD-C02 (PLOR218C Rev000) Page 1 of 6

TEMPORARY CHANGE FORM LOG i/CODE NO.: PLOR-218C REV. NO.:

TITLE: EVALUATE A P I EDIT AND TAKE CORRECTIVE ACTION FOR A THERMAL LIMIT VIOLATION 2.

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EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE J&

POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2830150401 / PLOR-218C WA: 295014AA2.04 URO: 4.1 SRO: 4.4 TASK DESCRI PTI0N: Resolve Thermal Limits A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.
2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.
3. JPM Performance
a. Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).
b. When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.
4. Satisfactory performance of this JPM is accomplished if:
a. The task standard is met.
b. JPM completion time requirement is met.

I) For non-time critical JPMs, completion within double the estimated time (listed in paragraph 0.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.
5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

B. TOOLS AND EQUIPMENT

1. None 4C. REFERENCES
1. GP-13, Rev 20, Resolution of Thermal Limit Violations
2. GP-5, Rev 63, Power Operations D. TASK STANDARD
1. Satisfactory task completion is indicated when the SRO has authorized a power reduction using control rods only, in accordance with the approved procedure.
2. Estimated time to complete: 10 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to review the initial 3D Monitor Case (PI) Edit following the previous shifts power ascension. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISlTES

1. Reactor power is currently stable at 100%.
2. The previous shift raised reactor power from 90% to 100% following a rod pattern adjustment, in accordance with GP-5, Power Operations.
3. Shift turnover has been completed, all required log entries have been completed and you have assumed the duties of the Control Room Supervisor.
4. The official 3D Monitor Case (PI) Edit is being run at this time to assess the recently completed reactor power ascension.
5. The Plant Monitoring System (PMS) is operable.
6. 3D MONICORE is operable.

G. INITIATING CUE As the Control Room Supervisor, review the official 3D Monitor Case (PI) Edit to ensure reactor core limits have been preserved during the recent power ascension.

H. PERFORMANCE CHECKLIST G

NO STEP ACT STANDARD CUE: Provide the Student with the official 3D Monitor Case (PI) Edit (which is Attachment 2 of this JPM).

  • I Review the official 3D P I Edit to Determines MFLCPR is greater than 1.OOO in ensure Core Thermal Limits are one location (19-20).

within specified limits.

2 Obtain a copy and enter GP-13, Reviews GP-13 prerequisites.

Resolution of Thermal Limit Violations. Reviews procedure NOTES prior to step 3.1 O f GP-13.

  • 3 Determine requirements to restore Determines the MFLCPR limit must be restored MFLCPR limit. to within limits within two (2) hours or thermal power must be reduced to less than 25% RTP within the next four (4) hours.

Make immediate notification of core Immediately informs:

conditions. 0 Shift Management 0 Reactor Engineers CUE: Role-play as the Shift Reports that the MFLCPR limit has been Manager as necessary. exceeded and that it must be restored to within limits within two (2) hours or thermal power must be reduced to less than 25% RTP within the next four (4) hours.

CUE: Role-play as the Reactor Engineer as necessary. Recommends power reduction with flow to reduce MFLCPR to 0.980, IAW GP-5.

Requests Reactor Engineering assistance with returning MFLCPR to below its limit.

As an evaluator ensure that you Positive control established.

have positive control of all exam material provided to the examinee (Task Conditions/PrerequisitesAND procedures).

Under ACT P - must perform S - must simulate iJ,>

I. TERMINATING CUE:

When the CRS has determined that entry into GP-13 AND a reactor power reduction is required in accordance with GP-13 (and GP-5), the evaluator may terminate the exercise.

TASK CONDlTlONS/PREREQUlSlTES

%4 I. Reactor power is currently stable at 100%.

2. The previous shift raised reactor power from 90% to 100% following a rod pattern adjustment, in accordance with GP-5, Power Operations.
3. Shift turnover has been completed, all required log entries have been completed and you have assumed the duties of the Control Room Supervisor.
4. The official 3D Monitor Case (PI) Edit is being run at this time to assess the recently completed reactor power ascension.
5. The Plant Monitoring System (PMS) is operable.
6. 3D MONICORE is operable.

INITIATING CUE As the Control Room Supervisor, review the official 3D Monitor Case (PI) Edit to ensure reactor core limits have been preserved during the recent power ascension.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET W

APPROVALS:

Signature / Title Date Signature /Title Date Signature / Title Date Signature / Title Date II APPROVED FOR USE:

EFFECTIVE DATE:

Signature /Title I I Date

~ ~

NAME: ISSUE DATE:

Last First M.I.

SOC. SEC. NO. COMPLETION DATE:

Training Review for Completeness: PlMS CODE:

PlMS ENTRY:

-- SignatureIDate 2007 NRC JPM SRO AD-RC (New-90 Hour Log) Page Iof 5

TEMPORARY CHANGE FORM LOG

- 4 CODE NO.: PLOR-XXXC REV. NO.:

TITLE: REVIEW AND APPROVE PRIMARY CONTAINMENT PURGENENT ISOLATION VALVE CUMMULATIVE HOUR LOG 1.

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2007 NRC JPM SRO AD-RC (New-90 Hour Log) Page 2 of 5

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: WA: 2.3.9 URO: 2.5 SRO: 3.4 TASK DESCRlPTION: Knowledge of the process for performing a containment purae.

A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.
2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.
3. JPM Performance
a. Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).
b. When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.
4. Satisfactory performance of this JPM is accomplished if:
a. The task standard is met.
b. JPM completion time requirement is met.
1) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.
2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.
5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

2007 NRC JPM SRO AD-RC (New-90 Hour Log) Page 3 of 5

6. TOOLS AND EQUIPMENT
1. Calculator L/
2. Copy of RT-0-007-560-2, Primary Containment PurgeNent Isolation Valve Cumulative Hour Log.
3. A calculation error made on Data Sheet 1 such that Accumulated Total Time Since Beginning of Calendar Year is greater than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />, with the procedure completed to indicate total time is less than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> (use Attachment 2 of this JPM for exact values).

C. REFERENCES

1. RT-0-007-560-2, Rev. 4, Primary Containment PurgeNent Isolation Valve Cumulative Hour Log.

D. TASK STANDARD I. Satisfactory task completion is indicated when the Shift Management review has been completed, the calculation error on Data Sheet 1 identified, and the total accumulated time a purgehent valve is open has been determined to be greater than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />.

2. Estimated time to complete: 15 minutes Non-Time Critical E. DIRECTIONS TO EXAMINEE b-When given the initiating cue, perform necessary steps to review the Primary Containment PurgeNent Isolation Valve Cumulative Hour Log. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F. TASK CONDITIONS/PREREQUISITES

1. The Primary Containment PurgeNent Isolation Valve Cumulative Hour Log for Unit 2 (RT-0-007-560-2) has been completed.
2. The Accumulated Total Time Since Beginning of Year is greater than 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Shift Management has been notified as required by Step 6.1.6.

G. INITIATING CUE You are the Work Control Supervisor. Perform the Plant Staff review and approval of RT-O-007-560-2, Primary Containment PurgeNent Isolation Valve Cumulative Hour Log.

2007 NRC JPM SRO AD-RC (New-90 Hour Log) Page 4 of 5

H. PERFORMANCE CHECKLIST STEP NO STEP ACT STANDARD 1 Cue: Hand the Examinee a completed copy of RT-0-007-560-2, Primary Containment PurgeNent Isolation Valve Cumulative Hour Log with Data Sheets 1 and 2 data filled in by hand from Attachment 2 of this JPM.

2 Review RT-0-007-560-2 for P Verifies all procedure steps, Data Sheet completeness. 1, and Data Sheet 2 have been completed satisfactorily.

3 Verify calculations. P Performs all calculations that were done on Data Sheet 1 to verify they are correct and properly recorded.

~

  • 4 Recognize calculation error. P Recognizes calculation error on Data Sheet 1 (second row for Flow Path Open Total Time column should be 17 Hr, 4 Min versus 5 Hr, 4 Min); and determines the Accumulated Total Time Since Beginning of Year is 93 Hr, 22 Min versus 81 Hr, 22 Min.

5 Notify Shift Management of unsatisfactory P Reports to Shift Manager and/or Control test results. Room Supervisor that the Accumulated Total Time Since Beginning of Year is (Cue: Acknowledge report.) greater than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />.

6 As an evaluator, ensure that you have P Positive control established.

positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under ACT P - must perform S - must simulate I. TERMINATING CUE When the review of RT-0-007-560-2 has been completed, the calculation error on Data Sheet 1 identified, and the total accumulated time a purgehent valve is open has been determined to be greater than 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />, the evaluator will terminate the exercise.

2007 NRC JPM SRO AD-RC (New-90 Hour Log) Page 5 of 5

TASK CONDITIONS/PREREQUISITES

  • L/

I. The Primary Containment PurgeNent Isolation Valve Cumulative Hour Log for Unit 2 (RT-0-007-560-2) has been completed.

2. The Accumulated Total Time Since Beginning of Year is greater than 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.

Shift Management has been notified as required by Step 6.1.6.

INITIATING CUE You are the Work Control Supervisor. Complete the Plant Staff review and approval of RT-0-007-560-2, Primary Containment PurgeNent Isolation Valve Cumulative Hour Log.

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date 11I APPROVED FOR USE:

EFFECTIVE DATE:

Signature I Title I I Date NAME: ISSUE DATE:

Last First M.I.

SOC. SEC. NO. COMPLETION DATE:

1 II Training Review for Completeness:

I PlMS CODE:

I i_/

l SignatureIDate I I

ENTRY: I 2007 NRC JPM SRO AD-EP (PLOR215C Rev001) Page 1 of 7

TEMPORARY CHANGE FORM LOG CODE NO.: PLOR-215C REV. NO.: 002 TITLE: REVIEW AND AUTHORIZE ISSUANCE OF THYROID BLOCKING AGENT (KI)

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2007 NRC JPM SRO AD-EP (PLOR215C Rev001) Page 2 of 7

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE: Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR: 2007560502 / PLOR-21% WA: G2.3.10 URO: 2.9 SRO: 3.3 TASK DESCRIPTION: REVIEW AND AUTHORIZE ISSUANCE OF THYROID BLOCKING AGENT (KI)

A. NOTES TO EVALUATOR:

1. An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.
2. System cues included in the performance checklist are to be provided to the examinee when no system response is available.
3. J PM Performance
a. Control Room JPMs are designed to be performed in the simulator. If a Control Room JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).
b. When performing In-Plant JPMs, no equipment will be operated without Shift Management approval.
4. Satisfactory performance of this JPM is accomplished if:
a. The task standard is met.
b. JPM completion time requirement is met.

I) For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2) For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.
5. The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

.-./

2007 NRC JPM SRO AD-EP (PLOR215C Rev001) Page 3 of 7

6. TOOLS AND EQUIPMENT
1. EP-AA-113, Personnel Protective Actions

=--j

2. EP-AA-113-F-03, Thyroid Blocking Agent Authorization Form completed with the exception of the Station Emergency Director authorization.
3. Worker history descriptions.

C. REFERENCES

1. EP-AA-112-100-F-01, Rev. F, Shift Emergency Director Checklist
2. EP-AA-I 13, Rev. 7, Personnel Protective Actions
3. EP-AA-I 13-F-03, Rev. 6, Thyroid Blocking Agent Authorization D. TASK STANDARD
1. Satisfactory completion of this task is indicated when the Emergency Director has reviewed and denied the issuance of Thyroid Blocking Agent.
2. Estimated time to complete: 20 minutes Non-Time Critical v

E. DIRECTIONS TO EXAMINEE When given the initiating cue, review the information provided including the Thyroid Blocking Agent Authorization and make the decision as to whether to authorize the issuance of Thyroid Blocking Agent. I will describe the initial conditions and provide you access to the materials required to complete this task.

F. TAS K CONDITI0NS/PREREQUISITES

1. Unit 2 experienced a major transient that resulted in a General Emergency declaration.
2. A release is in progress.
3. There is no loss (or potential loss) of the Fuel Clad Barrier.
4. Field Monitoring Teams have been mobilized by the Shift Dose Assessor
5. Iodine air samples have been completed and a Committed Dose Equivalent (CDE)

Thyroid Dose has been calculated and verified. Total CDE Thyroid Dose is expected to be 30 Rem.

  • d 2007 NRC JPM SRO AD-EP (PLOR215C Rev001) Page 4 of 7
6. Due to concerns for the exposure the Field Monitoring Teams may receive, EP-AA-113-F-03, Thyroid Blocking Agent Authorization Forms, have been completed and L/ reviewed/approved by the Radiation Protection Manager.

G. INITIATING CUE As the Shift Emergency Director, review the attached Thyroid Blocking Agent Authorization Form (EP-AA-113-F-03) for authorization.

v 2007 NRC JPM SRO AD-EP (PLOR215C Rev001) Page 5 of 7

H. PERFORMANCE CHECKLIST I

I, I I NO STEP 1

I STEP Obtain a copy of EP-AA-113, Personnel ACT P

STANDARD The examinee obtains the current Protective Actions. revision of EP-AA-113, Personnel Protective Actions.

2 Use Section 4.4 of the procedure for KI P The examinee references section 4.4 of assessment. EP-AA-113.

IF the Operator requests to review the KI calculation, inform the Operator that the EP-MA-110-100-F-02 form is not currently available, but it has been verified and is accurate.

  • 3 Recognize that the conditions for issuing P Examinee determines the conditions for KI are not currently met. Step 4.4.1 .I .A are NOT met due to:

0 Condition 1: there is not a loss or potential loss of the Fuel Clad Barrier.

0 Condition 2: the projected iodine thyroid exposure will be < 50 Rem CDE.

Examinee determines the conditions for Step 4.4.1 . I .B are NOT since this applies to onsite workers, and:

0 Condition 1: there is not a loss or potential loss of the Fuel Clad Barrier.

0 Condition 2: the projected iodine thyroid exposure will be < 50 Rem CDE.

4 Determine that Thyroid Blocking Agent Recognize and report that KI should not (KI) should not be issued. be issued.

(Cue: Acknowledge report.)

  • 5 Deny authorizing the issuance of Thyroid The examinee does not sign EP-AA-113-Blocking Agent. F-03, Thyroid Blocking Agent Authorization Form.

(Cue: Acknowledge denial.)

2007 NRC JPM SRO AD-EP (PLOR215C Rev001) Page 6 of 7

STEP ACT STANDARD

~ ~ ~ ~~

As an evaluator, ensure that you have P Positive Control Established.

positive control of all exam material provided to the examinees (Task Conditions/Prerequisites AND procedures.

Under ACT P - must perform S - must simulate TERMINATING CUE:

When the examinee has determined the conditions for issuing KI are not met and EP-AA-113-F-03 Thyroid Blocking Agent Authorization Form is returned without authorization, the evaluator may terminate the exercise.

w 2007 NRC JPM SRO AD-EP (PLOR215C Rev001) Page 7 of 7

TASK CONDITIONS/PREREQUISlTES I. Unit 2 experienced a major transient that resulted in a General Emergency declaration.

2. A release is in progress.
3. There is no loss'(or potential loss) of the Fuel Clad Barrier.
4. Field Monitoring Teams have been mobilized by the Shift Dose Assessor.
5. Iodine air samples have been completed and a Committed Dose Equivalent (CDE) Thyroid Dose has been calculated and verified. Total CDE Thyroid Dose is expected to be 30 Rem.
6. Due to concerns for the exposure the Field Monitoring Teams may receive, EP-AA-I 13-F-03, Thyroid Blocking Agent Authorization Forms, have been completed and reviewedlapproved by the Radiation Protection Manager.

INITIATING CUE As the Shift Emergency Director, review the attached Thyroid Blocking Agent Authorization Form (EP-AA-113-F-03) for authorization.

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