ML023020126

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Final - Section a Operating
ML023020126
Person / Time
Site: Beaver Valley
Issue date: 09/30/2002
From: Hynes C
FirstEnergy Nuclear Operating Co
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-334/02-301, ES-C-1 50-334/02-301
Download: ML023020126 (51)


Text

JOB PERFORMANCE MEASURE Form ES-C-1 (R8, S1)

Appendix C Task No: 0481-006-03-013 Facility: BVPS UNIT 1 JPM No: 2002 NRC Ala RO Task

Title:

Shift Relief And Turnover K/A

Reference:

2.1.3 (3.0)

NRC Examiner:

Examinee: ______________

Date:

Facility Evaluator: N/A Method of testing:

Actual Performance X Simulated Performance: _____

Simulator: X Plant:

Classroom:

READ TO THE EXAMINEE initiating cues.

Iwill explain the initial conditions, which steps to simulate or discuss, and providemeasure will be When you complete the task successfully, the objective for this job performance satisfied.

Initial Conditions: The Unit is operating at 100% power. You are the oncoming day shift Reactor Operator. You have just completed relief turnover with the offgoing RO with the exception of completing the control board checklist. The IPC is out of service.

Task Standard: 1OST-48.3A, Control Board Checklist completed and error identified.

Required Materials: None General

References:

1OST-48.3A, Control Board Checklist, Rev. 10 Handout: 1OST-48.3A (marked up copy)

Initiating Cue: In accordance with 1OST-48.3A, Control Board Checklist, verify the equipment in Section III, ESF Pump Control Switches by performing a control board walkdown and report your results.

Time Critical Task: NO Validation Time: 20 minutes

Page 2 of 6 Form ES-C-1 (R8, S)

Appendix C JOB PERFORMANCE MEASURE 2002 NRC Ala RO Shift Relief And Turnover Simulator Setup Information

C cc t--i imp Qiý Appendix C Page3or 6 VUll[

PERFORMANCE INFORMATION Shift Relief And Turnover 2002 NRC Ala RO (Denote Critical Steps with an asterisk)

Performance Step 1: Complete Initial Conditions section of procedure.

Standard: Candidate initials Step IV.1 to begin performance of the OST.

Comments:

  • Performance Step 2: Verify ESF Pump Control Switches are in their required positions.

Standard: Candidate identifies that 1QS-P-1 A is not in the AUTO position as designated in the Control Board Checklist.

Evaluator Note: Ifasked, inform the Candidate that the Plant Operator will investigate.

Comments:

Performance Step 3: Assign a Deviation Number in the Shift Check Block.

(Step V.2)

Standard: Candidate assigns a Deviation Number for the identified deficiency and records the number in the Shift Check Block.

Comments:

Appendix C Page 4 of 6 Form ES-C-1 (R8, Si)

PERFORMANCE INFORMATION Shift Relief And Turnover 2002 NRC Ala RO Performance Step 4: Consult Acceptance Critieria.

(Step 11.1)

Standard: Candidate refers to Acceptance Criteria and informs the Unit Supervisor of the identified deficiency.

CUE: The Unit Supervisor will review and disposition the deviations.

Comments:

Terminating Cue: The evaluation is complete when the Candidate reports the error in the plant alignment of the Control Board Checklist.

Appendix C Page 5 of 6 Form ES-C-1 (R8, S1)

VERIFICATION OF COMPLETION Shift Relief And Turnover 2002 NRC Ala RO JPM No.: 2002 NRC Ala RO Examinee's Name:

Examiner's Name:

Date performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

Date:

Signature:

Examiner's

Appendix C Page 6 of 6 Form ES-C-1 (R8, Si)

JPM CUE SHEET 2002 NRC Ala RO INITIAL CONDITIONS: The Unit is operating at 100% power. You are the oncoming day shift Reactor Operator. You have just completed relief turnover with the offgoing RO with the exception of conducting the control board walkdown. The IPC is out of service.

INITIATING CUE: In accordance with 1 OST-48.3A, Control Board Checklist, verify the equipment in Section III, ESF Pump Control Switches by performing a control board walkdown and report your results.

Appendix C JOB PERFORMANCE MEASURE Form ES-C-1 (R8, S)

Facility: BVPS UNIT 1 Task No: 1300-001-03-023 Task

Title:

Shift Relief And Turnover JPM No: 2002 NRC Ala SRO K/A

Reference:

2.1.3 (3.4)

Examinee: NRC Examiner: ________

Facility Evaluator: N/A Date:

Method of testing:

Simulated Performance: Actual Performance X Classroom: X Simulator: Plant:

READ TO THE EXAMINEE I will explain the initial conditions, which steps 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: The Unit is operating at 100% power. You are the oncoming day shift Unit Supervisor. The RO has completed shift relief turnover including the Control Board Checklist. The IPC is out of service.

Task Standard: Verify the Control Board Checklist OST is correctly completed in accordance with 1 OST-48.3A and errors identified.

Required Materials: None General

References:

1OST-48.3A, Control Board Checklist, Rev. 10 Handout: 1OST-48.3A (marked up copy)

Initiating Cue: As the Unit Supervisor perform a review of 1 OST-48.3A, Control Board Checklist for acceptability and report your results.

Time Critical Task: NO Validation Time: 15 minutes

Appendix C Page 2 of 5 Form ES-C-1 (R8, Si)

JOB PERFORMANCE MEASURE Shift Relief and Turnover 2002 NRC Ala SRO Simulator Setup Information

- - fl a Inn fl4 Appendix C Page 3 of 5 F-orm E-U- I k,-n, b 1)

PERFORMANCE INFORMATION Shift Relief and Turnover 2002 NRC Ala SRO (Denote Critical Steps with an asterisk)

Evaluator Note: Provide the Candidate with a marked copy of 1OST-48.3A, Control Board Checklist.

  • Performance Step: Reviews procedure for acceptability.

Standard: Candidate identifies the following errors:

"* Item II.b [MOV-1 RC-516] is not checked in the 08 - 16 Shift Check Block.

"* Item IV.2 [MOV-1 RW-11 6A] is not checked in the 08 - 16 Shift Check Block.

"* Item IV.40 does not list Deviation Number #2 in the Shift Check Block for MOV-1 RC-537 being in the CLOSED position.

Comments:

  • Performance Step: Refers to Acceptance Criteria to determine required action.

Standard: Candidate reports that the OST was not satisfactorily completed and that the Acceptance Criteria is not met.

CUE: The Shift Manager will review and disposition the identified deviations.

Comments:

Terminating Cue: The evaluation is complete when the Candidate reports the errors identified to the Shift Manager.

Appendix C Page 4 of 5 Form ES-C-1 (R8, Si)

VERIFICATION OF COMPLETION Shift Relief And Turnover 2002 NRC Ala SRO JPM No.: 2002 NRC Ala SRO Examinee's Name:

Examiner's Name:

Date performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

Appendix C Page 5 of 5 Form ES-C-1 (R8, Si)

JPM CUE SHEET 2002 NRC Ala SRO INITIAL CONDITIONS: The Unit is operating at 100% power. You are the oncoming day shift Unit Supervisor. The RO has completed shift relief turnover including the Control Board Checklist. The IPC is out of service.

INITIATING CUE: As the Unit Supervisor perform a review of 1 OST-48.3A, Control Board Checklist for acceptability and report your results.

Appendix C JOB PERFORMANCE MEASURE Form ES-C-1 (R8, Si)

Facility: BVPS UNIT 1 Task No: 0011-006-01-013 Task

Title:

Perform Shutdown Margin Calculation JPM No: 2002 NRC Alb RO K/A

Reference:

2.1.25 (2.8)

Examinee: NRC Examiner:__ ______

Facility Evaluator: N/A Date:

Method of Testing:

Simulated Performance: Actual Performance X Classroom: X Simulator: Plant:

READ TO THE EXAMINEE I will explain the initial conditions, which steps 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: The Unit is at 100% power. All control rods are at 225 steps.

Control rod "F10" is INOPERABLE (immovable and untrippable).

Core age is 8,300 MWD/MTU with a boron concentration of 1200 ppm. RCS Tavg is stable at 576 0 F. Annunciator [A4-46], Tavg Deviation From Tref is 'OFF'.

Task Standard: Correctly calculate shutdown margin in accordance with 1OST-49. 1.

Required Materials: Calculator Cycle 15 Curves CB-21, CB-24A, 24B & 24C General

References:

1OST-49.1, Shutdown Margin Calculation (Plant Critical), Rev. 6 Handout: 1OST-49.1 (marked up copy attached)

Initiating Cue: The Unit Supervisor directs you to perform 1OST-49.1 to calculate shutdown margin and report your results.

Time Critical Task: NO Validation Time: 20 minutes

Appendix C Page 2 of 6 Form ES-C-1 (R8, Si)

JOB PERFORMANCE MEASURE Perform Shutdown Margin Calculation 2002 NRC Alb RO Simulator Setup Information Setup: None required.

Appendix C Page 3 of 6 Form ES-C-1 (R8, S1)

PERFORMANCE INFORMATION Perform Shutdown Margin Calculation 2002 NRC Alb RO (Denote critical steps with an asterisk)

Evaluator Note: Provide the Candidate with a copy of 1 OST 49.1, Cycle 15 Curves and a calculator.

Allow the Candidate to complete the calculation and then report the results.

Performance Step: Enter Test Preparation Data (Section VII.A).

Standard: Candidate initials Step VII.A. 1 (plant in Mode 1, Tavg < 50 F above Tref, A4-46 OFF) from information given in Initial Conditions.

Candidate N/A's Step VII.A.2 (Mode 2 condition).

Candidate enters the following information in Data Sheet 1:

"* Control Bank "D" is at 225 steps (Step A.4).

"* Reactor power is 100% (Step A.5).

"* Number of Immovable or Untrippable Rods is 1 (Step A.6).

Candidate N/A's step VII.A.7 (greater than 1 immovable rod).

Comments:

Appendix C Page 4 of 6 Form ES-C-1 (R8, Sl)

PERFORMANCE INFORMATION Perform Shutdown Margin Calculation 2002 NRC Alb RO

  • Performance Step: Calculate shutdown margin (Section VII.B & Data Sheet 1).

Evaluator Note: Refer to Data Sheet 1 Answer Key to verify the calculation is correct.

Standard: Candidate determines and enters the following data:

  • ARO TBW for 8,000 MWD/MTU = 7.016 %Ak/k (Step B.1 .a)
  • IRW = 0 pcm and 0 %Ak/k from CB-24A (Step B.1.b)
  • TBW minus IBW = 7.016 %Ak/k (Step B.1 .c)
  • 90% Current TBW = 6.314 %Ak/k (Step B.1 .d)
  • 90% TBW minus Stuck Rod Worth = 3.085 %Ak/k (Step B.3)
  • RCS boron concentration = 1200 ppm (Step B.4.a)
  • Power Defect from CB-21 = 1800 pcm & 1.8 %Ak/k (Step B.4.b & c)
  • Power Defect + Operating temperature band margin = 1.8 & 2.05

%Ak/k (Step B.4.d)

Comments:

Terminating Cue: When the Candidate completes the shutdown margin calculation, the evaluation for this JPM is complete.

Appendix C Page 5 of 6 Form ES-C-1 (R8, S1)

VERIFICATION OF COMPLETION Perform Shutdown Margin Calculation 2002 NRC Alb RO JPM No.: 2002 NRC Alb RO Examinee's Name:

Examiner's Name:

Date performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's signature and date:

Appendix C Page 6 of 6 Form ES-C-1 (R8, Si)

JPM CUE SHEET 2002 NRC Alb RO INITIAL CONDITIONS: The Unit is at 100% power. All control rods are at 225 steps.

Control rod "F10" is INOPERABLE (immovable and untrippable).

Core age is 8,300 MWD/MTU with a boron concentration of 1200 ppm. RCS Tavg is stable at 5760 F. Annunciator [A4-46], Tavg Deviation From Tref is 'OFF'.

INITIATING CUE: The Unit Supervisor directs you to perform 1 OST-49.1 to calculate shutdown margin and report your results.

Appendix C JOB PERFORMANCE MEASURE Form ES-C-1 (R8, S1)

Facility: BVPS UNIT 1 Task No: 1340-007-03-023 Task

Title:

Review Shutdown Margin Calculation JPM No: 2002 NRC Al b SRO K/A

Reference:

2.1.25 (3.1)

Examinee: NRC Examiner:

Facility Evaluator: N/A Date:

Method of Testing:

Simulated Performance: ____

Actual Performance X Classroom: X Simulator: Plant:

READ TO THE EXAMINEE I will explain the initial conditions, which steps 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: The Unit is at 100% power. All control rods are at 225 steps.

Control rod "F10" is INOPERABLE (immovable and untrippable).

Core age is 8,300 MWD/MTU with a boron concentration of 1200 ppm. RCS Tavg is stable at 576 0 F.

Task Standard: Verify shutdown margin calculation and determine that Acceptance Criteria is not met in accordance with 1OST-49.1 Required Materials: Calculator Cycle 15 Curves CB-21, CB-24A, 24B & 24C General

References:

1OST-49.1, Shutdown Margin Calculation (Plant Critical), Rev. 6 Handout: 1OST-49.1 (marked up copy)

Initiating Cue: The Shift Manager requests you to perform a review of 1OST-49.1 to verify that the Acceptance Criteria is met. Report your results when completed.

Time Critical Task: NO Validation Time: 20 minutes

Appendix C Page 2 of 6 Form ES-C-1 (R8, Si)

JOB PERFORMANCE MEASURE Review Shutdown Margin Calculation 2002 NRC Al b SRO Simulator Setup Information

Appendix C Page 3 of 6 Form ES-C-1 (R8, Sl)

PERFORMANCE INFORMATION Review Shutdown Margin Calculation 2002 NRC Al b SRO (Denote critical steps with an asterisk)

Evaluator Note: Provide the Candidate with a copy of 1OST 49.1, Cycle 15 Curves and a calculator.

Allow the Candidate time to review the calculation and refer to the Acceptance Criteria before reporting the results.

Performance Step: Complete Test Preparation Data (Step VII.A).

Standard: Candidate verifies the plant is in Mode 1 and Tavg is less than 5°F above Tref from Initial Conditions.

Candidate verifies Step VII.A.2 is N/A (Mode 2 condition).

Candidate verifies the following information in Data Sheet 1:

"* Control Bank 'D' is at 225 steps (Step VII.A.4).

"* Reactor power is 100% (Step VII.A.5).

"* Number of Immovable or Untrippable Rods is 1 (Step VII.A.6).

Candidate verifies Step VII.A.7 is N/A (more than 1 immovable rod).

Comments:

Performance Step: Review shutdown margin calculation (Step VII.B).

Standard: Candidate identifies the following errors on Data Sheet 1:

"* Values in 4.c are incorrect (1600 vs. 1800 and 1.6 vs. 1.8)

"* Values in 4.d are incorrect (1.6 vs. 1.8 and 1.85 vs. 2.05)

"* Values in 5 are incorrect (1.85 vs. 2.05 and 1.235 vs. 1.035)

Evaluator Note: If asked, inform the Candidate to correct any errors in the calculation and complete the remainder of the OST.

Comments:

Appendix C Page 4 of 6 Form ES-C-1 (R8, Si)

PERFORMANCE INFORMATION Review Shutdown Margin Calculation 2002 NRC Al b SRO

  • Performance Step: Test Completion (Section VII.C).

Standard: Candidate determines that the Acceptance Criteria (SDM > 1.77% Ak/k) is not met and informs the Shift Manager of the test results.

CUE: Inform the Candidate as the Shift Manager that Reactor Engineering has been contacted to reverify the shutdown margin calculation.

Comments:

Terminating Cue: When the Candidate informs the Shift Manager of the results of the calculation, the evaluation for this JPM is complete.

Appendix C Page 5 of 6 Form ES-C-1 (R8, Si)

VERIFICATION OF COMPLETION Review Shutdown Margin Calculation 2002 NRC Al b SRO JPM No.: 2002 NRC Al b SRO Examinee's Name:

Examiner's Name:

Date performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's signature and date:

Appendix C Page 6 of 6 Form ES-C-1 (R8, S1)

JPM CUE SHEET 2002 NRC Al b SRO INITIAL CONDITIONS: The Unit is at 100% power. All control rods are at 225 steps.

Control rod "F10" is INOPERABLE (immovable and untrippable).

Core age is 8,300 MWD/MTU with a boron concentration of 1200 1200 ppm. RCS Tavg is stable at 576 0 F.

INITIATING CUE: The Shift Manager requests you to perform a review of 1OST-49.1 to verify that the Acceptance Criteria is met. Report your results when completed.

Appendix C JOB PERFORMANCE MEASURE Form ES-C-1 (R8, Si)

Facility: BVPS UNIT 1 Task No: 0481-020-03-013 Task

Title:

Prepare A Clearance Tagout JPM No: 2002 NRC A2 RO K/A

Reference:

2.2.13 (3.6)

Examinee: NRC Examiner:

Facility Evaluator: N/A Date:

Method of Testing:

Simulated Performance: ____

Actual Performance X Classroom: X Simulator: Plant:

READ TO THE EXAMINEE I will explain the initial conditions, which steps 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: The Unit is operating at 100% power with all systems in their normal operating alignment. A tagout section has been prepared to isolate [1CH-P-2B], Boric Acid Transfer Pump for maintenance.

Task Standard: Correctly identify all tagout section errors.

Required Materials: None General

References:

NPDAP 3.4, Rev. 14 1OM-7.3.B and 7.3.C 1OM Figure 7-3, Rev. 12 Handout: 1OM Figure 7-3 1OM-7.3.B and 7.3.C Initiating Cue: The Unit Supervisor directs you to review the tagout section for correct selection of clearance points.

Time Critical Task: NO Validation Time: 15 minutes

Appendix C Page 2 of 5 Form ES-C-1 (R8, Si)

JOB PERFORMANCE MEASURE Prepare a Clearance Tagout 2002 NRC A2 RO I I Simulator Setup Information

Appendix C Page 3 of 5 Form ES-C-1 (R8, S1)

PERFORMANCE INFORMATION Prepare A Clearance Tagout 2002 NRC A2 RO (Denote Critical Steps with an asterisk)

NOTE: This task is normally performed using the NOMS clearance computer and signed electronically. For the purpose of this JPM, inform the Candidate to report the results of the tagout review in place of signing the tagout form.

Evaluator Note: Provide Candidate with a copy of the JPM Handout (Tagout forms and 1 OM Fig. 7-3) and 1 OM-7.3.B and 7.3.C.

  • Performance Step 1: Review tagout section for accuracy and completeness.

Standard: Candidate verifies that appropriate clearance points are selected.

Candidate identifies and reports the following tagout errors:

"* Valve [1 CH-80] is incorrectly listed in the OPEN position in the Place Configuration Section (correct position is SHUT).

" Valve [1 CH-99] is listed in the SHUT position in the Restoration Section (correct position is LOCKED SHUT).

" 480V breaker is incorrectly listed as MCC-1 -El 1-B in the Equipment ID Section (correct breaker is MCC-1-E12-B).

Evaluator Note: If the Candidate asks for direction following identification of the first error, direct the Candidate to review the remainder of the tagout section.

Comments:

Terminating Cue: When the Candidate reports the results of the tagout section review the evaluation for this JPM is complete.

Appendix C Page 4 of 5 Form ES-C-1 (R8, Si)

VERIFICATION OF COMPLETION Prepare A Clearance Tagout 2002 NRC A2 RO JPM No.: 2002 NRC A2 RO Examinee's Name:

Examiner's Name:

Date performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

Appendix C Page 5 of 5 Form ES-C-1 (R8, Si)

JPM CUE SHEET 2002 NRC A2 RO INITIAL CONDITIONS: The Unit is operating at 100% power with all systems in their normal operating alignment. A tagout section has been prepared to isolate [1 CH-P-2B], Boric Acid Transfer Pump for maintenance.

INITIATING CUE: The Unit Supervisor directs you to review the tagout section for correct selection of clearance points.

Appendix C JOB PERFORMANCE MEASURE Form ES-C-1 (R8, Si)

Facility: BVPS UNIT 1 Task No: 1300-027-03-023 Task

Title:

Evaluate Removing Eguipment From Service JPM No: 2002 NRC A2 SRO K/A

Reference:

2.2.17 (3.5)

Examinee: NRC Examiner: ________

Facility Evaluator: N/A Date:

Method of Testing:

Simulated Performance: ____

Actual Performance X Classroom: X Simulator: Plant:

READ TO THE EXAMINEE I will explain the initial conditions, which steps 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: The Unit is in Mode 1. 1 EE-EG-1, Emergency Diesel Generator is scheduled to be tagged out for maintenance and removed from service within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Additionally, the FIN Team has requested permission to tagout and troubleshoot 1 MS-465, Turbine Driven AFW Pump Trip & Throttle Valve. The valve will be left open during troubleshooting. The work is expected to take 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to complete. All other plant equipment is operable. A Reactor Safety Engineer is not available.

Task Standard: Correctly determine which equipment may be removed from service in accordance with NPDAP 7.12 and/or Technical Specifications.

Required Materials: NPDAP 7.12, Rev. 11 Unit 1 Technical Specifications General

References:

NPDAP 7.12, Non-Outage Planning, Scheduling, and Risk Assessment, Rev. 11 Unit 1 Technical Specifications Handout: None Initiating Cue: For the given plant conditions, determine which maintenance activities can be authorized to proceed and report your results.

Time Critical Task: NO Validation Time: 10 minutes

Appendix C Page 2 of 5 Form ES-C-1 (R8, S1i)

JOB PERFORMANCE MEASURE Perform On-Line Risk Assessment 2002 NRC A2 SRO Simulator Setup Information Setup: None required.

j

Appendix C Page 3 of 5 Form ES-C-1 (R8, 1)

PERFORMANCE INFORMATION Perform On-Line Risk Assessment 2002 NRC A2 SRO (Denote critical steps with an asterisk)

  • Performance Step 1: Correctly determine the maintenance activities that can be authorized to proceed.

Standard: Candidate determines that [1 EE-EG-1], Emergency Diesel Generator No. 1 and the Turbine Driven AFW Pump cannot be simultaneously removed from service.

Evaluator Note: Reference NPDAP 7.12, Attachment 8, Item 4 under Main and Auxiliary Feedwater.

Comments:

Terminating Cue: When the Candidate reports the results of the determination, the evaluation for this JPM is complete.

Appendix C Page 4 of 5 Form ES-C-1 (R8, Si)

VERIFICATION OF COMPLETION Perform On-Line Risk Assessment 2002 NRC A2 SRO JPM No.: 2002 NRC A2 SRO Examinee's Name:

Examiner's Name:

Date performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's signature and date:

Appendix C Page 5 of 5 Form ES-C-1 (R8, S-1)

JPM CUE SHEET 2002 NRC A2 SRO INITIAL CONDITIONS: The Unit is in Mode 1. 1 EE-EG-1, Emergency Diesel Generator is scheduled to be tagged out for maintenance and removed from service within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Additionally, the FIN Team has requested permission to tagout and troubleshoot [1 MS-465], Turbine Driven AFW Pump Trip & Throttle Valve. The valve will be left open during troubleshooting. The work is expected to take 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to complete. All other plant equipment is operable. A Reactor Safety Engineer is not available.

INITIATING CUE: For the given plant conditions, determine which maintenance activities can be authorized to proceed and report your results.

Appendix C JOB PERFORMANCE MEASURE Form ES-C-1 (R8, Si)

Facility: BVPS UNIT 1 Task No: N/A Task

Title:

Determine Low Dose Area JPM No: 2002 NRC A3 RO/SRO K/A

Reference:

2.3.10 (2.6/3.3)

Examinee: NRC Examiner: ________

Facility Evaluator: N/A Date:

Method of Testing:

Simulated Performance: X Actual Performance _

Classroom: X Simulator: Plant:

READ TO THE EXAMINEE I will explain the initial conditions, which steps 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: The Unit is at 100% power. A void has developed in the suction line to 1CH-P-1A, High Head Safety Injection Pump. The line is to be drained and vented to reduce the size of the void. As the PAB Operator, the Unit Supervisor directs you to go to the 1A Charging Pump room to operate valve 1 CH-36, Charging Pump 1A Suction Vent.

Task Standard: Determine the area inside the pump cubicle having the lowest dose rate.

Required Materials: Charging Pump Cubicle Survey Map General

References:

1/2-ADM-1 630, Radiation Worker Practices, Rev. 3 Handout: Radiation Survey Map 102182 Initiating Cue: While waiting for direction from the Unit Supervisor to operate the valve, (Unit Supervisor will communicate via a cell phone) where will you stand to minimize the dose and why?

Time Critical Task: NO Validation Time: 10 minutes

Appendix C Page 2 of 5 Form ES-C-1 (R8, Si)

JOB PERFORMANCE MEASURE Determine Low Dose Area 2002 NRC A3 RO/SRO Simulator Setup Information

Appendix C Page 3 of 5 Form ES-C-1 (R8, Si)

PERFORMANCE INFORMATION Determine Low Dose Area 2002 NRC A3 RO/SRO (Denote critical steps with an asterisk)

  • Performance Step 1: Obtain survey map.

Standard: Candidate indicates obtaining survey map for the 1A charging pump.

CUE: How would you determine the low dose area if requested to standby to operate 1 CH-36.

Evaluator Note: After Candidate indicates obtaining the survey map, provide the attached survey map. Inform the Candidate this is the latest survey map for the room.

Comments:

  • Performance Step 2: Determine low dose area.

Standard: Candidate determines the area on the motor end of the pump has the lowest dose (2 mR/hr.).

Evaluator Note: If necessary, inform the Candidate that the US will communicate via a cell phone and provide direction to operate the vent valve.

Comments:

Terminating Cue: When Candidate determines the low dose area, the evaluation for this JPM is complete.

Appendix C Page 4 of 5 Form ES-C-1 (R8, S1)

VERIFICATION OF COMPLETION Determine Low Dose Area 2002 NRC A3 RO/SRO JPM No.: 2002 NRC A3 RO/SRO Examinee's Name:

Examiner's Name:

Date performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's signature and date:

Appendix C Page 5 of 5 Form ES-C-1 (R8, Si)

JPM CUE SHEET 2002 NRC A3 RO/SRO INITIAL CONDITIONS: The Unit is at 100% power. A void has developed in the suction line to 1CH-P-1A, High Head Safety Injection Pump. The line is to be drained and vented to reduce the size of the void. As the PAB Operator, the Unit Supervisor directs you to go to the 1A Charging Pump room to operate valve 1 CH-36, Charging Pump 1 A Suction Vent.

INITIATING CUE: While waiting for direction from the Unit Supervisor to operate the valve, (Unit Supervisor will communicate via a cell phone) where will you stand to minimize the dose and why?

REACTOR POWER I 00 SURVE YDAT DATE 30-

- TIE 0_ 00 SURVEY BY . 1 CHARGING PUMP PIT "A" BADGEs 4con 1 RwP,, cP# 101- 11Q19 E-5*0 4.

2 INST. TYPE INST TYPE OTHER

  • ALL AREAS ARE POSTED ,I_

SR 4

_ SRO lz0

-UNLESS OTHERWISE NOTED MAP 102182

" CIRCLED NUMBERS ARE RADIATION LEVELS IN mR/hr, 3 " NUMBERS ARE SMEAR LOCATIONS. *1

- ALL SMEARS ARE LESS THAN OOOdpmf&[OOcm 2 9-N.07-7 8

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Appendix C JOB PERFORMANCE MEASURIE Form I--u-1 ,Ho, b)

Facility: BVPS UNIT 1 Task No: N/A Task

Title:

Emergency Plan Administrative Questions (RO) JPM No: 2002 NRC A4 RO K/A

Reference:

2.4.29 (2.6) 2.4.39 (3.3)

Examinee: NRC Examiner:

Facility Evaluator: N/A Date:

Method of Testing:

Simulated Performance: Actual Performance X Classroom: X Simulator: Plant:

READ TO THE EXAMINEE I will explain the initial conditions, which steps 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: N/A Task Standard: Both questions answered correctly (minimum 80%).

Required Materials: None General

References:

EPP/IP 1.1, Notifications, Rev. 30 EPP/IP 1.5, Operations Support Center (OSC) Activation, Operation and Deactivation, Rev. 14 Handout: None Initiating Cue: N/A Time Critical Task: NO Validation Time: 10 minutes

Appendix C Page 2 of 7 Form ES-C-1 (R8, Si)

JOB PERFORMANCE MEASURE Emergency Plan Administrative Questions (RO) 2002 NRC A4 RO Simulator Setup Information Setup: None required.

Appendix C Page 3 of 7 Form ES-C-1 (R8, S-1)

PERFORMANCE INFORMATION Emergency Plan Administrative Questions (RO) 2002 NRC A4 RO QUESTION #1 Closed Reference A Site Area Emergency has been declared at Unit 1.

State the time requirement for Initial Notification and the methods by which the notifications can be made.

Appendix C Page 4 of 7 Form ES-C-1 (RB, Si)

PERFORMANCE INFORMATION Emergency Plan Administrative Questions (RO) 2002 NRC A4 RO QUESTION #2 Closed Reference Describe the location of the Operations Support Center and the Alternate Operations Support Center and when each must be activated.

Appendix C Page 5 of 7 Form ES-C-1 (R8, Si)

PERFORMANCE INFORMATION Emergency Plan Administrative Questions (RO)

IE'%J 2002 NRC A4 RO Question #1 A Site Area Emergency has been declared at Unit 1.

State the time requirement for Initial Notification and the methods by which the notifications can be made.

ANSWER:

Initial Notifications are to be made within 15 minutes of the event declaration. Official notification is made by telephone or radio.

Grading Criteria:

  • This question is worth 50% of the overall grade with the following breakdown:

+ 15 minute time requirement (30%)

  • Notification by telephone (10%) or radio (10%)

Appendix C Page 6 of 7 Form ES-C-1 (R8, S1)

PERFORMANCE INFORMATION Emergency Plan Administrative Questions (RO) 2002 NRC A4 RO Question #2 AI KEY Describe the location of the Operations Support Center and the Alternate Operations Support Center and when each must be activated.

ANSWER:

The OSC is located above the Control Rooms in Outage Central. The OSC is required to be activated within 60 minutes of the declaration of an Alert classification, or at the direction of the Emergency Director.

The Alternate OSC is located below the Unit 1 Control Room in the Process Instrumentation and Rod Position Instrumentation Area. The Alternate OSC is activated in the event the OSC becomes uninhabitable or access to it is restricted.

Grading Criteria:

  • This question is worth 50% of the overall grade with the following breakdown:
  • OSC location and activation requirement (25%)

+ Alternate OSC location and activation requirement (25%)

Appendix C Page 7 of 7 Form ES-C-1 (RS, Si)

VERIFICATION OF COMPLETION Emergency Plan Administrative Questions (RO) 2002 NRC A4 RO JPM No.: 2002 NRC A4 RO Examinee's Name:

Examiner's Name:

Date performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's signature and date:

Appendix C JOB PERFORMANCE MEASURE Form ES-C-1 (H8, S1)

Facility: BVPS UNIT 1 Task No: 1350-004-03-023 Task

Title:

EPP Classification JPM No: 2002 NRC A4 SRO K/A

Reference:

2.4.41 (4.1)

Examinee: NRC Examiner:

Facility Evaluator: N/A Date:

Method of Testing:

Simulated Performance: Actual Performance X Classroom: Simulator: X Plant:

READ TO THE EXAMINEE I will explain the initial conditions, which steps 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: The simulator scenario just completed.

Task Standard: The proper EPP classification is made within 15 minutes.

Required Materials: None General

References:

EPP/I-1A, Recognition and Classification of Emergency Conditions I Rev. 1 Handouts None Initiating Cue: Classify the events in the scenario just completed in accordance with EPP/I-1A, Recognition and Classification of Emergency Conditions.

Critical Task: YES Validation Time: 10 minutes per classification

Appendix C Page 2 of 5 Form ES-C-1 (R8, Si)

JOB PERFORMANCE MEASURE EPP Classification 2002 NRC A4 SRO Simulator Setup Information

Appendix C Page 3 of 5 Form ES-C-1 (R8, S1)

PERFORMANCE INFORMATION EPP Classification 2002 NRC A4 SRO (Denote critical steps with an asterisk)

I Evaluator Note: The Candidate is being evaluated on classifying the scenario events just completed.

  • Performance Step 1: Classify the event in accordance with the Emergency Plan.

Standard: Candidate properly classifies the event within 15 minutes.

Scenario #11: Site Area Emergency classification based on EPP/I-1 a, Tab 1.2.4 and 1.3.4.

Scenario #2: Alert classification based on EPP/I-1 a, Tab 1.2.3.

Scenario #3: Alert classification based on EPP/I-1 a, Tab 2.3.

Scenario #4: Site Area Emergency classification based on EPP/I-la, Tab 2.3.

Scenario #5: Site Area Emergency classification based on EPP/1-la, Tab 1.1.1 and 1.2.1.

Comments:

Terminating Cue: When the Candidate classifies the event, the evaluation for this JPM is complete.

Appendix C Page 4 of 5 Form ES-C-1 (R8, S1)

VERIFICATION OF COMPLETION EPP Classification 2002 NRC A4 SRO JPM No.: 2002 NRC A4 SRO Examinee's Name:

Examiner's Name:

Date performed:

Facility Evaluator:

Number of attempts:

Time to complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's signature and date:

Appendix C Page 5 of 5 Form ES-C-1 (R8, Si)

JPM CUE SHEET 2002 NRC A4 SRO INITIAL CONDITIONS: The simulator scenario just completed.

INITIATING CUE: Classify the events in the scenario just completed in accordance with EPP/I-1A, Recognition and Classification of Emergency Conditions.