Text

Initial Exam 2011-302 Final Administrative Jpms
	ML12074A184
Person / Time
Site:	Watts Bar
Issue date:	04/29/2011
From:	; Operator Licensing and Human Performance Branch
To:	; Tennessee Valley Authority
References
	50-390/11-302
	Download: ML12074A184 (94)
	v • d • e

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO 2011-12 NRC Exam FINAL SUBMITTAL A.1-1 RO Determine License Status PAGE 1 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO 2011-12 NRC Exam Task: Determine License Status Active / Inactive Alternate Path: N/A Facility JPM #: None Safety Function: 2.1

Title:

Conduct of Operations KIA 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 1 OCFR55, etc.

Rating(s): 3.3/3.8 CFR: 41.10 I 43.2 Evaluation Method: Simulator In-Plant Classroom X*

References:

OPDP-1 0, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions Rev. 3 Task Number: RO-1 1 9-PAI-2.07-001

Title:

Maintain active NRC License Task Standard: Applicant determines that Reactor Operators A, B, and D are Inactive and are NOT able to assume shift.

Validation Time: 15 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS PAGE2OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO 2011-12 NRC Exam ToolslEguipmentlProcedures Needed:

NRC REFERENCE DISK.

NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.

PAGE 3 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO 2011-12 NRC Exam DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task, return the handout sheet I provided you.

INITIAL CONDITIONS:

Four Reactor Operators have the following history:

1. All four obtained a license in 2009, have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years.

2. None of the 4 has worked any shift since December 1, 2011.

3. Active/Inactive status and time on shift since October 1, 2011 is as follows for each of the Reactor Operators:

OPERATORA License was acti,e on October 1, 2011 10/02/11 Worked 0700-1900 shift as Unit I OAC.

10/03/11 Worked 0700-1900 shift as Unit 1 OAC.

10/04/11 Worked 0700-1900 shift as Unit I OAC.

10/05/11 Worked 0700-1900 shift as Unit 1 OAC. Was absent from the Control Room for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to provide a statement associated with a HU event.

10/06/11 Worked 1900-0700 shift as Unit 1 OAC.

OPERATOR B License was active on October 1, 2011.

10/01/11 Worked 0700-1 900 shift as Unit 1 CR0.

10/02/11 Worked 0700-1900 shift as Unit 1 OAC.

10/03/11 Worked 0700-1900 shift as Unit 1 CR0. Attended a Licensed Operator Requalification Class for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at the Training Center, to make up for a class missed due to illness.

10/05/11 Worked 0700-1900 shift as Unit I OAC.

10/14/11 Worked 1900-0700 shift as Unit 1 OAC.

11/02/11 Worked 0700-1 900 shift in the Tagging Office.

PAGE4OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO 2011-12 NRC Exam OPERATOR C License was inactive on October 1, 2011 Completed Appendix A of OPDP-1 0 on 10/09/11.

11/10/11 Worked 0700-1 900 shift as Unit 1 OAC.

11/13/11 Worked 0700-1 900 shift as Unit 1 OAC.

11/15/11 Worked 0700-1 900 shift as Unit I OAC.

11/21/11 Worked 1900-0700 shift as Unit 1 OAC.

OPERATOR 0 License was inactive on October 1, 2011 10/07/11 Worked 0700-1900 shift as Unit 1 OAC.

10/08/11 Worked 0700-1900 shift as Unit I OAC. Absent from the Control Room for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to attend a pre-job brief for a sensitive evolution.

10/09/11 Worked 0700-1900 shift as Unit I OAC.

10/10/11 Worked 0700-1900 shift as Unit 1 OAC.

10/11/11 Worked 0700-1900 shift as Unit 1 OAC. Completed NANTeI TVA Specific GET CBT modules in the Shift Managers Office for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

INITIATING CUES:

You are to determine if each of the Reactor Operators is eligible to work the Unit I OAC position on the 0700 1900 shift on January, 31, 2012, and why.

PAGE 5011

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO 2011-12 NRC Exam STEPISTANDARD SATIUNSAT START TIME:

STEP 1.: Determine the Active I Inactive status of Operator A license. CRITICAL STEP STANDARD: SAT Applicant determines the license is INACTIVE because: UNSAT operator DID NOT work the required qualified 5 twelve hour shifts in a license position during the previous quarter.

The shift on 10/05/11 DOES NOT count due to the 3.0 hour0 days 0 hours 0 weeks 0 months absence.

The 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to provide a statement associated with a HU event does not count as licensed duties.

Step is critical to ensure an operator with an inactive license does not perform license duties.

COMMENTS:

PAGE6OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO 2011-12 NRC Exam STE PISTAN DARD SATIU NSAT STEP 2.: Determine the Active I Inactive status of Operator B license. CRITICAL STEP STANDARD:

SAT Applicant determines the license is INACTIVE because:

UNSAT The operator DID NOT work the required 5 twelve hour shifts in a license position during the previous quarter.

The 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months time spent at the Training Center attending the missed Licensed Operator Requalification class DOES NOT count as licensed duties.

The shift in the Tagging Office DOES NOT count as licensed duties.

Step is critical to ensure an operator with an inactive license does not perform license duties.

COMMENTS:

PAGE 7011

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO 2011-12 NRC Exam STE P/STANDARD SAT/U NSAT STEP 3.: Determine the Active I Inactive status of Operator C license. CRITICAL STEP STANDARD:

SAT Applicant determines the license is ACTIVE because:

UNSAT Completion of OPDP-10, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions, Appendix A, Return to Active Status Checklist, on 10/09/11 satisfies the requirements for returning to active status.

Per OPDP-10, 3.2.4.K:

The licensee that stands forty (40) hours under instruction and regains active license status is not required to stand five (5) 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts (or seven (7) eight hour shifts) in the calendar quarter that the license was reactivated.

The licensee must stand five (5) 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts (or seven (7) eight hour shifts) in the next calendar quarter to maintain an active license.

Step is critical to ensure an operator with an inactive license does not perform license duties.

COMMENTS:

PAGE 8011

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO 2011-12 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4.: Determine the Active / Inactive status of Operator D license. CRITICAL STEP STANDARD:

SAT Applicant determines the license is INACTIVE because:

UNSAT The operator DID NOT work the required qualified 5 twelve hour shifts in a license position during the previous quarter.

On 10/08/11, the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months time to attend the pre-job brief COUNTS as actively performing the functions of an operator, so all of the hours for the shift are courted.

Completing NANTeI TVA Specific GET CBT training modules in the Shift Managers Office for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months DOES NOT count as licensed duties. Credit towards license maintenance would not be given for this period.

Step is critical to ensure an operator with an inactive license does not perform license duties.

COMMENTS:

END OF TASK STOP TIME PAGE9OF 11

A.1-1 RO Handout Package for Applicant

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Four Reactor Operators have the following history:

1. All four obtained a license in 2009, have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years.

2. None of the 4 has worked any shift since December 1, 2011.

3. Active/Inactive status and time on shift since October 1, 2011 is as follows for each of the Reactor Operators:

OPERATOR A License was active on October 1, 2011 10/02/11 Worked 0700-1900 shift as Unit 1 OAC.

10/03/11 Worked 0700-1 900 shift as Unit I OAC.

10/04/11 Worked 0700-1 900 shift as Unit I OAC.

10/05/11 Worked 0700-1 900 shift as Unit I OAC. Was absent from the Control Room for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to provide a statement associated with a HU event.

10/06/11 Worked 1900-0700 shift as Unit I OAC.

OPERATOR B License was active on October 1, 2011.

10/01/11 Worked 0700-1900 shift as Unit I CR0.

10/02/11 Worked 0700-1900 shift as Unit I OAC.

10/03/11 Worked 0700-1900 shift as Unit 1 CR0. Attended a Licensed Operator Requalification Class for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at the Training Center, to make up for a class missed due to illness.

10/05/11 Worked 0700-1900 shift as Unit 1 OAC.

10/14/11 Worked 1 900-0700 shift as Unit 1 OAC.

11/02/11 Worked 0700-1900 shift in the Tagging Office.

A.1-1 RO

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

OPERATOR C License was inactive on October 1, 2011 Completed Appendix A of OPDP-1 0 on 10/09/11 11/10/11 Worked 0700-1 900 shift as Unit I OAC.

11/13/11 Worked 0700-1 900 shift as Unit I OAC.

11/15/11 Worked 0700-1 900 shift as Unit I OAC.

11/21/11 Worked 1900-0700 shift as Unit I OAC.

OPERATOR D License was inactive on October 1, 2011 10/07/11 Worked 0700-1900 shift as Unit I OAC.

10/08/11 Worked 0700-1900 shift as Unit I OAC. Absent from the Control Room for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to attend a pre-job brief for a sensitive evolution.

10/09/11 Worked 0700-1900 shift as Unit I OAC.

10/10/11 Worked 0700-1 900 shift as Unit 1 OAC.

10/11/11 Worked 0700-1 900 shift as Unit I OAC. Completed NANTeI TVA Specific GET CBT modules in the Shift Managers Office for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

INITIATING CUES:

You are to determine if each of the Reactor Operators is eligible to work the Unit 1 OAC position on the 0700- 1900 shift on January, 31, 2012, and why.

A.1-1 RO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-12 NRC Exam FINAL SUBMITTAL Al-I SRO Determine License Status PAGE 1 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-12 NRC Exam EVALUATION SHEET Task: Determine License Status.

Alternate Path: n/a Facility JPM #: New Safety Function: 2.1

Title:

Conduct of Operations K/A 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 1 OCFR55, etc.

Rating(s): 3.3/3.8 CFR: 41.10/43.2 Evaluation Method: Simulator In-Plant Classroom X*

References:

OPDP-1, Conduct of Operations, Rev. 19.

OPDP-1 0, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions, Rev. 3.

WBN Technical Specifications Section 5.2.2, Unit Staff.

Task Number: SRO-1 1 9-SPP-1 0.0-001

Title:

Authorize the call-in of personnel.

Task Standard: The applicant:

1) Determines that Operator C is the only RO with an ACTIVE license available for call-in, and that the SRO is eligible to assume the RO position.

2) States that, per Technical Specification Section 5.5.2, replacement must report for work no later than 0225, to meet the two hour requirement of Tech Spec 5.2.2.b.

Validation Time: 15 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: I NAME SIGNATURE DATE COMMENTS PAGE 2 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-12 NRC Exam ToolslEguipmentlProcedures Needed:

NRC REFERENCE DISK.

NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.

PAGE 3 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-12 NRC Exam DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit I is operating at 100% power with the following 1900-0700 shift positions manned on January, 31, 2012:

Shift Manager, SM Unit Supervisor, US Shift Technical Advisor, STA (non-licensed)

Operator at the Controls, OAC Control Room Operator, CR0 Outside Nuclear Assistant Unit Operator, OS NAUO Auxiliary Building Nuclear Assistant Unit Operator, AB NAUO Turbine Building Nuclear Assistant Unit Operator, TB NAUO Control Building/Ice Nuclear Assistant Unit Operator, CBIICE NAUO Condensate Demineralizer Nuclear Assistant Unit Operator, COND Dl

2. At 0025, the Operator at the Controls (OAC) becomes violently ill, requiring medical assistance and immediate transport to a hospital.

INITIATING CUE:

You are the US, and are to determine:

1. Which, if any, of the following available operators is eligible to call in to replace the OAC and why?

a. Three Reactor Operators with the following history:

1.) The three obtained a license in 2009, have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years.

2.) None of the ROs have worked any shift since December 1, 2011.

3.) The Active/Inactive status and time on shift since October 1, 2011 for each of the Reactor Operators is provided in the table on the next page.

b. An SRO (Instant) who was issued his license on January 29, 2012.

2. If a replacement operator was called in to meet minimum shift staffing, what is the latest time allowed by procedure for the replacement to assume shift?

PAGE4OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-12 NRC Exam OPERATOR A License was actie on October 1. 2011 10/02/11 Worked 0700-1900 shift as Unit I OAC.

10/03/11 Worked 0700-1900 shift as Unit I OAC.

10/04/11 Worked 0700-1900 shift as Unit I OAC.

10/05/11 Worked 0700-1900 shift as Unit 1 OAC. Was absent from the Control Room for 3hours to provide a statement associated with a HU event.

10/06/11 Worked 1900-0700 shift as Unit 1 OAC.

OPERATOR B License was active on October 1, 2011.

10/01/11 Worked 0700-1 900 shift as Unit 1 OAC.

10/02/11 Worked 0700-1900 shift as Unit I CR0. Attended a Licensed Operator Requalification Class for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at the Training Center, to make up for a class missed due to illness.

10/03/11 Worked 0700-1900 shift as Unit 1 CR0.

10/05/11 Worked 0700-1900 shift as Unit I OAC.

10/14/11 Worked 1900-0700 shift as Unit 1 OAC.

11/02/11 Worked 0700-1900 shift in the Tagging Office.

OPERATOR C License was inactive on October 1, 2011 Completed Appendix A of OPDP-1 0 on 10/09/11.

11/12/11 Worked 0700-1 900 shift as Unit I OAC.

11/13/11 Worked 0700-1900 shift as Unit I OAC.

11/15/11 Worked 0700-1900 shift as Unit I OAC.

11/21/11 Worked 1900-0700 shift as Unit I OAC.

PAGE 5 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-12 NRC Exam STEP/STANDARD SAT/UNSAT START TIME:

STEP 1: Determine the Active / Inactive status of Operator A license. CRITICAL STEP STANDARD: SAT Applicant determines the license is INACTIVE because: UNSAT The operator DID NOT work the required qualified 5 twelve hour shifts in a license position during the previous quarter.

The shift on 10/05/11 DOES NOT count due to the 3.0 hour0 days 0 hours 0 weeks 0 months absence.

The 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to provide a statement associated with a HU event does not count as licensed duties.

Step is critical to ensure an operator with an inactive license does not perform license duties.

COMMENTS:

PAGE6OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-12 NRC_Exam STEPISTANDARD SATIUNSAT STEP 2: Determine the Active I Inactive status of Operator B license. CRITICAL STEP STANDARD:

SAT Applicant determines the license is INACTIVE because:

UNSAT The operator DID NOT work the required 5 twelve hour shifts in a license position during the previous quarter.

The 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months time spent at the Training Center attending the missed Licensed Operator Requalification class DOES NOT count as licensed duties.

_The shift in the Tagging Office DOES NOT count as licensed duties.

Step is critical to ensure an operator with an inactive license does not perform license duties.

COMMENTS:

PAGE 7 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-12 NRC Exam STEPISTANDARD SATIUNSAT STEP 3: Determine the Active / Inactive status of Operator C license. CRITICAL STEP STANDARD:

SAT Applicant determines the license is ACTIVE because:

UNSAT Completion of OPDP-1 0, License Status Maintenance, Reactivation and Proficiency for Non-Licensed Positions, Appendix A, Return to Active Status Checklist, on 10/09/11 satisfies the requirements for returning to active status.

Per OPDP-10, 3.2.4.K:

The licensee that stands forty (40) hours under instruction and regains active license status is not required to stand five (5) 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts (or seven (7) eight hour shifts) in the calendar quarter that the license was reactivated.

The licensee must stand five (5) 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts (or seven (7) eight hour shifts) in the next calendar quarter to maintain an active license.

Step is critical to ensure an operator with an inactive license does not perform license duties.

COMMENTS:

STEP 4: Determine the status of the newly licensed SRO. CRITICAL STEP STANDARD:

SAT Applicant determines the license is ACTIVE, and that the SRO may fill either an RO or SRO position. UNSAT Step is critical to ensure an operator with an active license is called in to replace the ill OAC to perform license duties.

COMMENTS:

PAGE 8 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.l-l SRO 2011-12 NRC Exam STEP/STANDARD 1 SATIUNSAT STEP 5: Determine the latest time that the replacement operator may CRITICAL assume the shift. STEP STANDARD: SAT Applicant determines the operator selected as the replacement (either UNSAT RD C or the SRO) must report for work no later than 0225, to meet the two hour requirement of Tech Spec 5.2.2.b.

Step is critical to ensure an operator with an active license reports for work within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

COMMENTS:

END OF TASK STOP TIME PAGE9OF 11

Al-I SRO Handout Package for Applicant

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. Unit I is operating at 100% power with the following 1900-0700 shift positions manned on January, 31, 2012:

Shift Manager, SM Unit Supervisor, US Shift Technical Advisor, STA (non-licensed)

Operator at the Controls, OAC Control Room Operator, CR0 Outside Nuclear Assistant Unit Operator, OS NAUO Auxiliary Building Nuclear Assistant Unit Operator, AB NAUO Turbine Building Nuclear Assistant Unit Operator, TB NAUO Control Buildingllce Nuclear Assistant Unit Operator, CBIICE NAUO Condensate Demineralizer Nuclear Assistant Unit Operator, COND DI

2. At 0025, the Operator at the Controls (OAC) becomes violently ill, requiring medical assistance and immediate transport to a hospital.

INITIATING CUE:

You are the US, and are to determine:

1. Which, if any, of the following available operators is eligible to call in to replace the OAC?

a. Three Reactor Operators with the following history:

1.) The three obtained a license in 2009, have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years.

2.) None of the ROs have worked any shift since December 1, 2011.

3.) The Activellnactive status and time on shift since October 1, 2011 for each of the Reactor Operators is provided in the table on the next page.

b. An SRO (Instant) who was issued his license on January 29, 2012.

2. If a replacement operator was called in to meet minimum shift staffing, what is the latest time allowed by procedure for the replacement to assume shift?

Al-I SRO

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

OPERATOR A License was active on October 1, 2011.

10/02/11 Worked 0700-1900 shift as Unit 1 QAC.

10/03/11 Worked 0700-1 900 shift as Unit 1 OAC.

10/04/11 Worked 0700-1 900 shift as Unit 1 OAC.

10/05/11 Worked 0700-1900 shift as Unit 1 OAC. Was absent from the Control Room for 3hours to orovide a statement associated with a HU event.

10/06/11 Worked 1900-0700 shift as Unit 1 OAC.

OPERATOR B License was active on October 1, 2011 10/01/11 Worked 0700-1 900 shift as Unit 1 OAC.

10/02/11 Worked 0700-1 900 shift as Unit 1 CR0. Attended a Licensed Operator Requalification Class for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months at the Training Center, to make up for a class missed due to illness.

10/03/11 Worked 0700-1900 shift as Unit 1 CRC.

10/05/11 Worked 0700-1 900 shift as Unit 1 OAC.

10/14/11 Worked 1900-0700 shift as Unit 1 OAC.

1 1/02/11 Worked 0700-1 900 shift in the Taqqinq Office.

OPERATOR C License was inactive on October 1, 2011 Completed Appendix A of OPDP-1 0 on 10/09/1 1.

11/12/11 Worked 0700-1900 shift as Unit 1 OAC.

11/13/11 Worked 0700-1 900 shift as Unit 1 CAC.

11/15/11 Worked 0100-1900 shift as Unit 1 OAC.

11/21/11 Worked 1900-0700 shift as Unit 1 OAC.

Al-I SRO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A1-2 RO & SRO 2011-12 NRC Exam FINAL SUBMITTAL A.1-2 Perform RCS Deboration Calculation PAGE 1 OF 8

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO & SRO 2011-12 NRC Exam EVALUATION SHEET Task: Perform RCS Deboration Calculation.

Alternate Path: n/a Facility JPM #: 12-2009 Audit Exam (Modified)

Safety Function: n/a

Title:

!ui& 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Rating(s): 3.9 / 4.2 CFR: 41.10 /43.5 /45.12 Evaluation Method: Simulator In-Plant Classroom X*

References:

SOl-62.04, CVCS Purification System, Rev. 57.

Tl-59, Boron Tables, Rev. 7.

Task Number: RO-062-Tl-59-001

Title:

Perform boron concentration change calculations.

Task Standard: Applicant determines that it will take 225.6 (acceptable range 225-226) minutes to reduce RCS boron concentration from 49 ppm to 36 ppm after performing SOl-62.04, CVCS Purification System, Appendix B, RCS Deboration Calculation.

Validation Time: 10 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS PAGE 2 OF 8

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO & SRO 2011-12 NRC Exam Tools/Eciuipmentlprocedures Needed:

The following information will be handed out to each applicant:

A blank copy of SOl-62.04, CVCS Purification System, Appendix C, RCS Deboration Calculation, Rev. 57.

NRC REFERENCE DISK.

Calculator

NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.

PAGE 3 OF 8

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO & SRO 2011-12 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. The unit is in Mode 1, coasting down prior to refueling.

2. Current RCS CB is 49 ppm.

3. Current RCS temperature is 575°F.

4. Mixed Bed A contains fresh, unborated resin.

5. Maximum Mixed Bed (MB) flow per SOI-62.04, CVCS Purification System, will be used during this evolution.

6. You are an extra operator.

INITIATING CUES:

1. The Unit SRO has directed you to perform SOI-62.04, CVCS Purification System, Appendix B,RCS Deboration Calculation, to estimate the time that CVCS Mixed Bed Demineralizer A must be in service in order to reduce RCS boron concentration to 36 ppm. Show all work.

2. Report the results of your calculation to the Unit SRO.

PAGE 4 OF 8

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO & SRO 2011-12 NRC Exam STEPISTANDARD SATIUNSAT START TIME:

STEP 1: [1] INDICATE Mixed Bed for which this calculation is being SAT performed (CHECK ONLY ONE.)

UNSAT Mixed Bed A OR Mixed Bed B STANDARD:

From INITIAL CONDITIONS, the applicant checks Mixed Bed A.

COMMENTS:

NOTE This calculation is based on the Mixed Bed being a fresh unborated bed, all letdown flow being directed through the mixed bed being placed in service, and the following:

OT V

Cf Co Where: Cf = Final Boron Concentration Co = Initial Boron Concentration Q = Mixed Bed Flow Rate (Letdown Flow in gpm)

V = ROS Volume at operating ternpera:ure (gals)

T = Time (minutes)

PAGE 5 OF 8

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO & SRO 2011-12 NRC Exam STEPISTANDARD SAT/UNSAT STEP 2: [2] RECORD current RCS Temperature: CRITICAL STEP STANDARD:

SAT From INITIAL CONDITIONS, applicant records 575°F as the current RCS temperature. UNSAT COMMENTS:

STEP 3: [3] RECORD RCS Volume (V) based on current RCS Temp CRITICAL using Tl-59 (first page of App D through App N, as STEP appropriate.)

SAT STANDARD:

Applicant locates TI-59, and selects Appendix L, and records 87813.5 UNSAT as the RCS volume.

(Acceptable Range 87813 87814 gallons)

COMMENTS:

PAGE 6 OF 8

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 RO & SRO 2011-12 NRC Exam

[ STEPISTANDARD STEP 4: [4] PERFORM the following calculation to estimate time in CRITICAL service: STEP SAT

-in ( ppm! ppm)

STANDARD:

Applicant enters letdown flow of 120 gpm, since the INITIAL CONDITIONS requires letdown flow to be at maximum, and RCS volume of 87813.5 gallons. Applicant calculates time of 225.6 minutes.

(Acceptable range 225-226 minutes)

Applicant reports the results of the calculation to the Unit Supervisor.

EVALUATORS CUE: When the applicant reports the result of the calculation to the Unit Supervisor, acknowledge using repeat back.

State that another operator will complete Step 5 of Appendix B.

COMMENTS:

END OF TASK STOP TIME PAGE 7 OF 8

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. The unit is in Mode I coasting down prior to refueling.

2. Current RCS CB is 49 ppm.

3. Current RCS temperature is 575°F.

4. Mixed Bed A contains fresh, unborated resin.

5. Maximum Mixed Bed (MB) flow per SOI-62.04, CVCS Purification System, will be used during this evolution.

6. You are an extra operator.

INITIATING CUES:

I. The Unit SRO has directed you to perform SOI-62.04, CVCS Purification System, Appendix B, RCS Deboration Calculation, to estimate the time that CVCS Mixed Bed Demineralizer A must be in service in order to reduce RCS boron concentration to 36 ppm. Show all work.

2. Report the results of your calculation to the Unit SRO.

A.1.2 RO & SRO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-12 NRC Exam FINAL SUBMITTAL A.2 RO Perform a Clearance without use of eSOMS Computer.

Page 1 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-12 NRC Exam EVALUATION SHEET Task: Perform a Clearance without use of eSOMS Computer.

Alternate Path: n/a Facility JPM #: New Safety Function: 2.2

Title:

Equipment Control KIA 2.2.13 Knowledge of tagging and clearance procedures.

Rating(s): 4.2/4.3 CFR: 41.10/45.13 Evaluation Method: Simulator In-Plant Classroom X

References:

1.) 1-47W859-1, Mechanical Flow Diagram Component Cooling Water, Rev. 50.

2.) NPG-SPP-10.2, Clearance Procedure to Safely Control Energy, Rev. I 3.) TVA 17984 [11-2005]. CLEARANCE TAG LIST AND OPERATIONAL STEPS.

Task Number: RO-119-NOMS-010

Title:

Enter/edit devices held for active clearances.

Task Standard: The applicant:

1.) Identifies the handswitches, breakers and their required positions to electrically clear the C-S CCS pump in preparation for maintenance.

2). Identifies the components and positions required to isolate, vent and drain a section of piping in preparation for repair of the C-S CCS pump discharge check valve.

3.) Identifies the proper sequence of isolation of components, specifically that the discharge and suction valves will be isolated first, then the vent and drain valves will be opened.

Validation Time: 45 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner:

NAME SIGNATURE DATE COMMENTS Page2oflO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-12 NRC Exam Tools/EguipmentlProcedures Needed:

ELECTRICAL PRINTS:

1-45W749-1, WIRING DIAGRAMS 480V SHUTDOWN BD IA 1-A SINGLE LINE, Rev 1-45W749-IA, WIRING DIAGRAMS 480V SHUTDOWN BD 2A1-A SINGLE LINE, Rev 1-45W749-2, WIRING DIAGRAMS 480V SHUTDOWN BD 1A2-A SINGLE LINE, Rev 54.

1-45W749-2A, WIRING DIAGRAMS 480V SHUTDOWN BD 2A2-A SINGLE LINE, Rev 1-45W749-3, WIRING DIAGRAMS 480V SHUTDOWN BD IBI-B SINGLE LINE, Rev 1-45W749-3A, WIRING DIAGRAMS 480V SHUTDOWN BD 2B1-B SINGLE LINE, Rev 1-45W749-4, WIRING DIAGRAMS 480V SHUTDOWN BD 1B2-B SINGLE LINE, Rev 1-45W749-4A, WIRING DIAGRAMS 480V SHUTDOWN BD 2B2-B SINGLE LINE, Rev 1-45W760-70-1, WIRING DIAGRAMS COMPONENT COOLING SYSTEM SCHEMATIC DIAGRAMS, Rev 1-45W760-70-2, WIRING DIAGRAMS COMPONENT COOLING SYSTEM SCHEMATIC DIAGRAMS Rev 19.

MECHANICAL PRINTS 1-47W859-1, FLOW DIAGRAM COMPONENT COOLING SYSTEM, Rev.50.

1-47W859-2, FLOW DIAGRAM COMPONENT COOLING SYSTEM, Rev.36.

1-47W859-3, FLOW DIAGRAM COMPONENT COOLING SYSTEM, Rev.22.

1-47W859-4, FLOW DIAGRAM COMPONENT COOLING SYSTEM, Rev.25.

TVA 17984 [11-2005) Clearance Tag List and Operational Steps, filled out for removing the C-S CCS pump electrically.

BLANK TVA 17984 [11-2005) Clearance Tag List and Operational Steps.

NRC REFERENCE DISK.

NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.

Page 3 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-12 NRC Exam DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit I is in Mode4.

2. The I B-B CCS pump is aligned per SOI-70.01, Section 8.1 to supply B Train loads.

3. The C-S CCS pump was shut down due to a LARGE LEAK on 0-CKV-070-504 (C-S pump discharge check valve).

4. The eSOMS Clearance System computer program is NOT available.

INITIATING CUES:

Using the references provided, prepare a clearance sheet of components to be tagged on WA 17984 [11-2005], Clearance Tag List and Operational Steps, to de energize and isolate the C-S CCS pump for repairs to be made to the leaking check valve 0-CHK-070-504.

NOTE: Complete the first, third, fourth, and fifth columns on WA 17984

[11-2005], Clearance Tag List and Operational Steps.

Page 4 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-12 NRC Exam START TIME:

STEP 1: Applicant identifies components that must be operated to support CRITICAL maintenance on O-CKV-070-504. Applicant enters data in the STEP Equipment ID, Equipment Description, Equipment Location Column.

SAT STANDARD:

UNSAT The applicant completes Column I of the WA 17984 [11-2005] form provided:

_1-HS-70-51A, CCS PMP C-S ALT ACB, 0-M-27B

_2-HS-70-51A, CCS PMP C-S NORM ACB, 0-M-27B

_0-BRK-70-51A, NORMAL FDR FOR CCS PUMP C-S (0-PMP-70-51),

480V SD BD 2B2-B CI2D

_0-BRK-70-51B, ALT FOR FOR CCS PUMP C-S (0-PMP-70-51),

480V SD BD 1A2-A CI3B

_0-ISV-70-505, CCS PUMP C-S DISCHARGE ISOLATION VALVE, A3S171 3

_0-ISV-70-503, CCS PUMP C-S SUCTION ISOLATION, A2S1713 0-VTV-70-506, CCS PUMP C-S DISCHARGE VENT, A3S1713 AND/OR 0-VTV-70-718, CCS PUMP C-S CASING VENT, A2S/713 0-DRV-70-720, CCS PUMP C-S CASING DRAIN, A2S/713 AND/OR

_0-DRV-70-721, CCS PUMP C-S CASING DRAIN, A2S/713 Step is critical to correctly isolate the electrical and mechanical portions of the system prior to work being performed.

COMMENTS:

Page 5oflO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-12 NRC Exam EXAMINER: Control power fuses are NOT REQUIRED to be pulled. Per NPG-SPP-1O.2, Clearance Procedure to Safely Control Energy, Requirement 0. states, Control power circuits shall be tagged if (1) the work is on the control circuit, (2) the proximity of the work is near the energized control circuii, or (3) there exists a possibility of grounding the control circuit. Control power fuses are NOT REQUIRED to be addressed to satisfy the CRITICAL STEP.

STEP 2: Applicant identifies components that must be operated tosupport CRITICAL maintenance on O-CKV-070-504. Applicant enters data in the STEP Tag Type Column.

SAT STANDARD:

UNSAT The applicant completes Column 3 of the TVA 17984 [11-2005] form provided:

The applicant enters DANGER in the Tag Type Column for the pump handswitches, the pump breakers, and the pump suction and discharge valves.

The applicant may enter either DANGER or VENTIDRAIN NO TAG for the vent and drain valves.

Step is critical to correctly isolate and depressurize the portion of the system prior to work being performed.

COMMENTS:

Page 6 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-12 NRC Exam STEP 3: Applicant identifies the sequence that the components must be CRITICAL operated to support maintenance on O-CKV-070-504. Applicant STEP enters data in the Place Seq. Column.

STANDARD: SAT The applicant completes Column 4 of the WA 17984 [11-2005]

UNSAT form by entering the following sequence ( ) for operation of the following components:

1-HS-70-51A, CCS PMP C-S ALT ACB, O-M-27B (1)

2-HS-70-51A, CCS PMP C-S NORM ACB, O-M-27B (1)

O-BRK-70-51A, NORMAL FDR FOR CCS PUMP C-S (O-PMP-70-51),

480V SD BD 2B2-B C/2D (2)

O-BRK-70-51 B, ALT FDR FOR CCS PUMP C-S (O-PMP-70-51), 480V SD BD 1A2-A C/3B (2)

O-ISV-70-505, CCS PUMP C-S DISCHARGE ISOLATION VALVE, A3S1713 (3)

_O-ISV-70-503, CCS PUMP C-S SUCTION ISOLATION, A2S1713 (3)

O-VTV-70-506, CCS PUMP C-S DISCHARGE VENT, A3S1713 (4)

ANDIOR O-VTV-70-71 8, CCS PUMP C-S CASING VENT, A25171 3 (4)

O-DRN-70-720, CCS PUMP C-S CASING DRAIN, A251713 (4)

ANDIOR O-DRN-70-721, CCS PUMP C-S CASING DRAIN, A251713 (4)

Step is critical to correctly de-energize, isolate and depressurize the portion of the system prior to work being performed.

NOTE: Sequence variations are allowed as long as the sequence does not result in opening a drain or vent valve prior to the suction and discharge valves being isolated.

COMMENTS:

Page 7 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-12 NRC Exam STEP 4: Applicant identifies position that each listed component must be CRITICAL placed in to allow maintenance to be performed on 0-CKV-070- STEP 504 SAFELY. Applicant enters the correct position in the Place Config. Column.

STANDARD: SAT The applicant completes Column 5 of the WA 17984 [11-2005] UNSAT form by listings the following POSITION for each of the following components:

1-HS-70-51A, CCS PMP C-S ALT ACB, 0-M-27B, PULL-TO-LOCK, or STOP, PTL or PTL 2-HS-70-51A, CCS PMP C-S NORM ACB, 0-M-27B, PULL-TO-LOCK, or STOP, PTL or PTL 0-BRK-70-51A, NORMAL FDR FOR CCS PUMP C-S (0-PMP 51), 480V SD SD 2B2-B CI2D, DISCONNECTED or RACKED OUT.

0-BRK-70-51 B, ALT FDR FOR CCS PUMP C-S (0-PMP-70-51),

480V SD BD 1A2-A CI3B, DISCONNECTED or RACKED OUT.

0-ISV-70-505, CCS PUMP C-S DISCHARGE ISOLATION VALVE, A3S1713, CLOSED.

0-ISV-70-503, CCS PUMP C-S SUCTION ISOLATION, A2S1713, CLOSED.

CCS PUMP C-S DISCHARGE VENT, A3S1713 OPEN.

AND/OR 0-VTV-70-718, CCS PUMP C-S CASING VENT, A251713 OPEN.

0-DRN-70-720, CCS PUMP C-S CASING DRAIN, A2S1713 OPEN.

AND/OR 0-DRN-70-721, CCS PUMP C-S CASING DRAIN, A2S1713 OPEN.

Step is critical to correctly de-energize, isolate and depressurize the portion of the system prior to work being performed.

NOTE: Sequence variations are allowed as long as the sequence does not result in opening a drain or vent valve prior to the suction and discharge valves being isolated.

COMMENTS:

END OF TASK STOPTIME -

PageS of 10

Tennessee Valley Authority Clearance Tag List and Operational Steps Clearance Sheet I Clearance No. I Page of Apparatus: Isolate and Repair Leak on 0-CHK-70-504, CCS PUMP C-S DISCHARGE CHECK VALVE.

Equipment ID Place. Place. Restore Restore nd 2 1 s t Equipment Description Tag Serial Tag Place. Place. let Rest. Restore As left Tag Notes Equipment Location No. Type Seq. Config. Verifier Verifier Seq. Config. Confg. Verifier Verifier 1-HS-70-51A STOP, Dan g er 1 PULL-To-LOCK CCS PMP C-S ALT ACB 0-M-27B i STOP, 2HS40-51A Dan g er PULL-TO CCS PP C-S NORM ACB O-M-27B 0BKR705 I A Danger 2 DISCONNECTED NORM FDR FOR CCS PUMP C-S 480V SD BD 2B2-R CI2D 0-BKR70-51 B DISCONNECTED Danger 2 ALT FOR FOR CCS PUMP C-S 480V SD BD 1A2-A C/3B -

0-ISV-70-505 Danger 3 CLOSED CCS PUMP C-S DISCH ISOL VLV A3S/7i 3 0-ISV-V0-503 Danger 3 CLOSED CCS IUMP C-S SUCTION ISOL VLV A2S/7i 3 0-VTV-70-506 Danger 4 OPEN CCS PUMP C-S DISCHARGE VENT A3S/713 0V1V70718 Danger 4 OPEN CCSFUMPC-SCASINGVENT A2S/7fl 3

- o_9lJ7o_72o Danger 4 OPEN CCS P!JMP C-S CASING DRAIN A2S1713 -

- o_vw_70.721 Danger OPEN 4

CCS PUMP C-S CASING DRAIN A2S/713 -

OPTIONAL, NOT CRITICAL CRITICAL TO TAG EITHER DRAIN VALVE OPEN TVA 17984 [11-2005]

A.2 RO Handout Package for Applicant A.2 RO

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. Unit I is in Mode 4.

2. The lB-B CCS pump is aligned per SOI-70.O1, Section 8.1 to supply B Train loads.

3. The C-S CCS pump was shut down due to a LARGE LEAK on O-CKV-070-504 (C-S pump discharge check valve).

4. The eSOMS Clearance System computer program is NOT available.

INITIATING CUES:

Using the references provided, prepare a clearance sheet of components to be tagged on WA 17984 [11-2005], Clearance Tag List and Operational Steps, to de energize and isolate the C-S CCS pump for repairs to be made to the leaking check valve 0-CKV-070-504.

NOTE: Complete the first, third, fourth, and fifth columns on WA 17984

[11-2005], Clearance Tag List and Operational Steps.

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WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A2 SRO 2011-12 NRC Exam FINAL SUBMITTAL A.2 SRO Perform a Clearance without use of eSOMS Corn puter.

Paa1 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-12 NRC Exam EVALUATION SHEET Task: Perform a Clearance without use of eSOMS Computer.

Alternate Path: n/a Facility JPM #: New Safety Function: 2.2

Title:

Equipment Control KIA 2.2.13 Knowledge of tagging and clearance procedures.

Rating(s): 4.2/4.3 CFR: 41.10/45.13 Evaluation Method: Simulator In-Plant Classroom X*

References:

1.) 1-47W859-l, Mechanical Flow Diagram Component Cooling Water, Rev. 50.

2.) NPG-SPP-10.2, Clearance Procedure to Safely Control Energy, Rev. I 3.) TVA 17984 [11-2005]. CLEARANCE TAG LIST AND OPERATIONAL STEPS.

Task Number: RD-i 1 9-NOMS-Ol 0

Title:

Enter/edit devices held for active clearances.

Task Standard: The applicant:

1.) Identifies the handswitches, breakers and their required positions to electrically clear the C-S CCS pump in preparation for maintenance.

2). Identifies the components and positions required to isolate, vent and drain a section of piping in preparation for repair of the C-S CCS pump discharge piping.

3.) Identifies the proper sequence of isolation of components, specifically that the discharge and suction valves will be isolated first, then the vent and drain valves will be opened.

4.) Determines that LCD 3.7.7 must be entered for the current plant conditions.

This is required since the 2B-B CCS pump does will not start automatically from a Safety Injection signal.

Validation Time: 45 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS Paae 2 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-12 NRC Exam ToolslEguipment/Procedures Needed:

ELECTRICAL PRINTS:

1-45W749-1, WIRING DIAGRAMS 480V SHUTDOWN BD IAI-A SINGLE LINE, Rev 1-45W749-IA, WIRING DIAGRAMS 480V SHUTDOWN BD 2A1-A SINGLE LINE, Rev 1-45W749-2, WIRING DIAGRAMS 480V SHUTDOWN BD 1A2-A SINGLE LINE, Rev 54.

1-45W749-2A, WIRING DIAGRAMS 480V SHUTDOWN BD 2A2-A SINGLE LINE, Rev 1-45W749-3, WIRING DIAGRAMS 480V SHUTDOWN BD IBI-B SINGLE LINE, Rev 1-45W749-3A, WIRING DIAGRAMS 480V SHUTDOWN BD 2B1-B SINGLE LINE, Rev 1-45W749-4, WIRING DIAGRAMS 480V SHUTDOWN BD 1B2-B SINGLE LINE, Rev 1-45W749-4A, WIRING DIAGRAMS 480V SHUTDOWN BD 2B2-B SINGLE LINE, Rev 1-45W760-70-1, WIRING DIAGRAMS COMPONENT COOLING SYSTEM SCHEMATIC DIAGRAMS, Rev 1-45W760-70-2, WIRING DIAGRAMS COMPONENT COOLING SYSTEM SCHEMATIC DIAGRAMS Rev 19.

MECHANICAL PRINTS 1-47W859-1, FLOW DIAGRAM COMPONENT COOLING SYSTEM, Rev.50.

1-47W859-2, FLOW DIAGRAM COMPONENT COOLING SYSTEM, Rev.36.

1-47W859-3, FLOW DIAGRAM COMPONENT COOLING SYSTEM, Rev.22.

1-47W859-4, FLOWDIAGRAM COMPONENT COOLING SYSTEM, Rev.25.

TVA 17984 [11-20051 Clearance Tag List and Operational Steps, filled out for removing the C-S CCS pump electrically.

BLANK TVA 17984 [11-20051 Clearance Tag List and Operational Steps.

NRC REFERENCE DISK.

NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.

nf 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-12 NRC Exam DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unitl isinModel.

2. The 2B-B CCS pump is in service, supplying B Train loads.

3. A large leak has developed on the C-S CCS pump discharge between 0-CHK-070-504 Discharge Check valve and O-ISV-70-505, Discharge isolation valve.

4. The eSOMS Clearance System computer program is NOT available.

INITIATING CUES:

1. Using the references provided, manually prepare a WA 17984 [11-2005], Clearance Tag List and Operational Steps, to de-energize and isolate the C-S CCS pump for repairs to be made to the leak on the discharge piping between 0-CHK-070-504 check valve and 0-ISV-70-505.

NOTE: Complete the first, third, fourth, and fifth columns on WA 17984

[11-2005], Clearance Tag List and Operational Steps.

2. What, if any, Technical SpecificationslTechnical Requirements must be entered due to the failure of the C-S CCS pump? Why?

pnp 4 nf 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-12 NRC Exam START TIME:

STEP 1: Applicant identifies components that must be operated to support CRITICAL maintenance on O-CHK-070-504. Applicant enters data in the STEP Equipment ID, Equipment Description, Equipment Location Column. SAT STANDARD: UNSAT The applicant completes Column I of the WA 17984 [11-2005] form provided:

_1-HS-70-51A, CCS PMP C-S ALT ACB, 0-M-27B

_2-HS-70-51A, CCS PMPC-S NORM ACB, 0-M-27B

_0-BRK-70-51A, NORMAL FDR FOR CCS PUMP C-S (0-PMP-70-51),

480V SD BD 2B2-B CI2D

_0-BRK-70-51B, ALT FOR FOR CCS PUMP C-S (0-PMP-70-51),

480V SD BD 1A2-A CI3B

_0-ISV-70-505, CCS PUMP C-S DISCHARGE ISOLATION VALVE, A3SI71 3

_0-ISV-70-503, CCS PUMP C-S SUCTION ISOLATION, A2S/713 0-VTV-70-506, CCS PUMP C-S DISCHARGE VENT A3S/713 Optional

_0-VTV-70-718, CCS PUMP C-S CASING VENT, A2S/713

_0-DRN-70-720, CCS PUMP C-S CASING DRAIN, A2S/713 AND/OR

_0-DRN-70-721, CCS PUMP C-S CASING DRAIN, A2S/713 Step is critical to correctly isolate the electrical and mechanical portions of the system prior to work being performed.

COMMENTS:

PAGE 5011

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-12 NRC Exam EXAMINER: Control power fuses are NOT REQUIRED to be pulled. Per NPG-SPP-1O.2, Clearance Procedure to Safely Control Energy, Requirement 0. states, Control power circuits shall be tagged if (1) the work is on the control circuit, (2) the proximity of the work is near the energized control circuit, or (3) there exists a possibility of grounding the control circuit.

Control power fuses are NOT REQUIRED to be addressed to satisfy the CRITICAL STEP.

STEP 2: Applicant identifies components that must be operated to support CRITICAL maintenance on O-CHK-070-504. Applicant enters data in the STEP Tag Type Column.

SAT STANDARD:

UNSAT The applicant completes Column 3 of the WA 17984 [11-2005] form provided:

The applicant enters DANGER in the Tag Type Column for each of the components.

Step is critical to correctly isolate and depressurize the portion of the system prior to work being performed.

COMMENTS:

PAGE6OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-12 NRC Exam STEP 3: Applicant identifies the sequence that the components must be CRITICAL operated to support maintenance on O-CHK-070-504. Applicant STEP identifies enters data in the Place Seq. Column.

STANDARD:

SAT The applicant completes Column 4 of the WA 17984 [11-2005]

form by entering the following sequence ( ) for operation of the UNSAT following components:

1-HS-70-51A, CCS PMP C-S ALT ACB, O-M-27B (1) 2-HS-70-51A, CCS PMP C-S NORM ACB, O-M-27B (1)

O-BRK-70-51A, NORMAL FDR FOR CCS PUMP C-S (O-PMP-70-51),

480V SD BD 2B2-B C/2D (2)

O-BRK-70-51 B, ALT FDR FOR CCS PUMP C-S (O-PMP-70-51), 480V SD BD 1A2-A C/3B (2)

O-ISV-70-505, CCS PUMP C-S DISCHARGE ISOLATION VALVE, A3S171 3 (3)

O-ISV-70-503, CCS PUMP C-S SUCTION ISOLATION, A251713 (3) 0-VTV-70-506, CCS PUMP C-S DISCHARGE VENT A3S/713 (4)OPTIONAL O-VTV-70-718, CCS PUMP C-S CASING VENT, A2S1713 (4)

O-DRN-70-720, CCS PUMP C-S CASING DRAIN, A2S1713 (4)

AND/OR O-DRN-70-721, CCS PUMP C-S CASING DRAIN, A2S1713 (4)

Step is critical to correctly de-energize, isolate and depressurize the portion of the system prior to work being performed.

NOTE: Sequence variations are allowed as long as the sequence does not result in opening a drain or vent valve prior to the suction and discharge valves being isolated.

COMMENTS:

PAGE 7011

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-12 NRC Exam STEP 4: Applicant identifies position that each listed component must be CRITICAL placed in to allow maintenance to be performed on 0-CHK-070- STEP 504 SAFELY. Applicant enters the correct position in the Place Config. Column.

SAT STANDARD:

The applicant completes Column 5 of the P/A 17984 [11-2005] UNSAT form by listings the following POSITION for each of the following components:

_1-HS-70-51A, CCS PMP C-S ALT ACB, 0-M-27B, PULL-TO-LOCK, or STOP, PTL or PTL

_2-HS-70-51A, CCS PMP C-S NORM ACB, 0-M-27B, PULL-TO-LOCK, or STOP, PTL or PTL

_0-BRK-70-51A, NORMAL FDR FOR CCS PUMP C-S (0-PMP 51), 480V SD BD 2B2-B CI2D, DISCONNECTED or RACKED OUT.

_0-BRK-70-51 B, ALT FDR FOR CCS PUMP C-S (0-PMP-70-51),

480V SD BD 1A2-A C/3B, DISCONNECTED or RACKED OUT.

0-ISV-70-505, CCS PUMP C-S DISCHARGE ISOLATION VALVE, A3S/713, CLOSED.

0-ISV-70-503, CCS PUMP C-S SUCTION ISOLATION, A2S1713, CLOSED.

O-VTV-70-506, CCS PUMP C-S DISCHARGE VENT A3S/713 OPEN. (OPTIONAL) 0-VTV-70-718, CCS PUMP C-S CASING VENT, A2S1713 OPEN.

0-DRN-70-720, CCS PUMP C-S CASING DRAIN, A2S1713 OPEN.

AND/OR 0-DRN-70-721, CCS PUMP C-S CASING DRAIN, A251713 OPEN.

Step is critical to correctly de-energize, isolate and depressurize the portion of the system prior to work being performed.

NOTE: Sequence variations are allowed as long as the sequence does not result in opening a drain or vent valve prior to the suction and discharge valves being isolated.

COMMENTS:

PAGE 8011

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A2 SRO 2011-12 NRC Exam STEP 5: Applicant responds to the question What, if any, Technical CRITICAL Specifications/Technical Requirements must be entered due to STEP the failure of the C-S CCS pump? Why?

SAT STANDARD:

UNSAT The applicant evaluates the plant configuration due to the failure of the C-S CCS pump and enters LCO 3.7.7, COMPONENT COOLING SYSTEM.

The B Train is INOPERABLE since the 2B-B CCS pump does not have an automatic start on an SI signal.

NOTE: When the C-S CCS pump is OPERABLE, running the 2B-B CCS pump does not require entry into LCO 3.7.7, since the C-S CCS pump would start and supply flow to B Train equipment on a SI signal. If the I B-B CCS pump had been aligned, entry into LCO 3.7.7 would not be required.

COMMENTS:

ENDOFTASK STOP TIME PAGE9OF 11

Tennessee Valley Authority Clearance Tag List and Operational Steps Clearance Sheet j Clearance No. Page of Apparatus: Isolate and Repair Leak on 0-CHK-70-504, CCS PUMP C-S DISCHARGE CHECK VALVE.

Equipment ID Place. Place. Restore Restore fld 2 nd 2

Equipment Description Tag Serial Tag Place. Place. Rest. Restore As left Tag Notes Equipment Location No. Type Seq. Config. Verifier Verifier Seq. Config. Confg. Verifier Verifier 1-kS-7o-51A STOP, Dan g er 1 PULL-TO-LOCK CCS PMP C-S ALTACB 0-M-27B 2-HS-70-51A 1 STOP, D

CCS PMP C-S NORM ACB LOCK O-M-27B 0BKR7051A Danger 2 DISCONNECTED NORM FDR FOR CCS PUMP C-S 48V SD RD 2R2-B C/2D 0-KR-70-51 B DISCONNECTED Danger 2 ALT FDR FOR CCS PUMP C-S 48cV SD BD 1A2-A CI3B 0-ISV-70-505 Danger 3 CLOSED CcS PUMP C-S DISCH ISOL VLV A33/71 3 0-IV-70-503 Danger 3 CLOSED CCS PUMP C-S SUCTION ISOL VLV A2S/71 3 0-VTV-70-506 Danger 4 OPEN CCS PUMP C-S DISCHARGE VENT A3S/713 O-VTV-70-718 Danger 4 OPEN CCS PUMP C-S CASING VENT AZSI71 3

- ovw_7o.72o Danger 4 OPEN COS PUMP C-S CASING DRAIN A2/71 3

- OrlV_7O.721 Danger 4 OPEN CS PUMP C-S CASING DRAIN A281713

OPTIONAL NOTCRITICAL **CRITICALTOTAG EITHER DRAIN VALVEOPEN WA 17984 [11-2005]

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. Unit I is in Mode 1.

2. The 2B-B CCS pump is in service, supplying B Train loads.

3. A large leak has developed on the C-S CCS pump discharge between 0-CHK-070-504 Discharge Check valve and 0-ISV-70-505, Discharge isolation valve.

4. The eSOMS Clearance System computer program is NOT available.

INITIATING CUES:

1. Using the references provided, manually prepare a WA 17984 [II-2005], Clearance Tag List and Operational Steps, to de-energize and isolate the C-S CCS pump for repairs to be made to the leak on the discharge piping between 0-CHK-070-504 check valve and 0-ISV-70-505.

NOTE: Complete the first, third, fourth, and fifth columns on WA 17984

[11-2005], Clearance Tag List and Operational Steps.

2. What, if any, Technical SpecificationslTechnical Requirements must be entered due to the failure of the C-S CCS pump? Why?

A.2 SRO

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WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO 2011-12 NRC Exam FINAL SUBMITTAL A.3 RO Determine Potential Total Dose for Valve Alignment.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO 2011-12 NRC Exam EVALUATION SHEET Task: Determine Potential Total Dose For Valve Alignment.

Alternate Path: n/a Facility JPM #: 3-OT-JPMADA.3-1 Safety Function: n/a

Title:

Radiation Control KIA 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

Rating(s): 3.2/3.7 CFR: 41.12 I 43.4/ 45.10 Evaluation Method: Simulator In-Plant Classroom X*

References:

Task Number: AUO-119-SSP-5.01 -001

Title:

Control Personal Radiation Exposure Task Standard: The applicant determines:

1. The total dose which an individual would receive while aligning 1 -FCV-63-1 1 to be 369.5-372.5 mrem.

2. That, when added to the total dose received for the year, the administrative dose limit of 1000 mrem will be exceeded (1069.5 to 1072.5 mrem.)

Validation Time: 20 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: 1 NAME SIGNATURE DATE COMMENTS

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO 2011-12 NRC Exam Tools/EguipmentlProcedures Needed:

A3 RO Applicant Data Sheets I through 3.

NRC REFERENCE DISK

Calculator

NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.

PA(F flE 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO 2011-12 NRC Exam DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task, return the handout sheet I provided you.

INITIAL CONDITIONS:

1. A survey map is available for elevation 713 of the auxiliary building, showing dose rates and projected travel times to reach 1-FCV-63-11 and open it manually.

2. RADCON personnel are currently unavailable to provide assistance.

INITIATING CUES:

1. You have been directed to perform the alignment of 1-FCV-63-11.

2. Your total dose for the year to date is 700 mr.

3. Calculate your estimated total dose to perform this job using the attached survey map.

4. Determine if you can perform this job without exceeding your administrative dose limit. Show all work.

PA(F 4 flP 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO 2011-12 NRC Exam START TIME:

EXAMINER: If the applicant asks if this is a planned special exposure, respond that the applicant should read initiating cues.

Examinee must calculate 2 way travel time through all transit areas. Allowable ranges are shown where applicable STEP 1: Calculate exposure during transit through the sample room CRITICAL and penetration room to the valve and return. STEP STANDARD: SAT Sample Room (475mr/hr)(O.5min)( hr/6Omin) x 2(trips) = 7.92 mr UNSAT Allowable range: (7.5 mr to 8.5 mr)

Pen Room to STEP (l2Omr/hr)(O.5min)(hr/6Omin) x 2(trips) 2 mr OFF PAD Allowable range: N/A Hot Spot (2700mr/hr)(5Osec)(min/6Osec)(hr/6Omin) x 2(trips) = 75 mr Allowable range: N/A Past BIT (900mr/hr)(3min)(hr/6Omin) x 2(trips) = 90 mr Allowable range: N/A Transit to valve (350mr/hr)(7min)(hr/6Omin) x 2(trips) = 81.67 mr Allowable range: (81 mr to 82mr)

Operate valve (320mr/hr)(2Omin)(hr/6Omin) x 1(trip) = 106.67 mr Allowable range: (1 06.Omr to 1 O7mr)

STEP OFF PAD (l2Omr/hr)(4min)(hr/6Omin) 1(trip) = 8 mr during exit Allowable range: N/A Step is critical to avoid exceeding dose limits.

COMMENTS:

PAGE 5 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO 2011-12 NRC Exam EXAMINER: Some rounding of numbers is allowed as long as the examinee follows sound mathematical standards. The acceptable total range is 369.5 to 372.5 mrem.

STEP 2: Calculate the total exposure received while performing the CRITICAL task. STEP STANDARD: SAT Individual doses received are added up. UNSAT 7.92mr + 2mr + 75mr + 9Omr + 81 .67mr + 106.67mr + 8mr = 371.26 mr.

Rounding values:

Low: 7.5 + 2 + 75 + 90 + 81 + 106.0 + 8 = 369.5 mr High: 8.5 + 2+75 + 90 + 82 + 107 + 8 = 372.5 mr Acceptable Range 369.5 to 372.5 mrem Step is critical to avoid exceeding dose limits.

COMMENTS:

PAGE6OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 RO 2011-12 NRC Exam STEP 3. Applicant calculates his/her total estimated exposure. CRITICAL STEP STANDARD:

SAT Total dose calculated in previous step is added to applicants total dose for the year: UNSAT 700 mr (total dose to date) + 371.26 mr (total dose for this job) 1071.26 m rem.

Acceptable range of answer 1069.5 mrem to 1072.5 mrem.

Critical step to calculate dose accurately in order to avoid exceeding dose limits.

COMMENTS:

STEP 4: Applicant determines admin dose limit will be exceeded if the CRITICAL job is performed. Applicant notifies supervisor of findings, STEP stating that admin dose limit will be exceeded.

SAT STANDARD:

UNSAT Admin dose limit for the year is 1000 mrem. Potential dose received is 369.5 to 372.5 mrem Total is 1069.5 mrem to 1072.5 mrem, exceeding admin limit.

CUE: When notified of applicants findings, acknowledge report using repeat back, and state that this JPM is completed. Have applicant turn in all paperwork & calculations.

Step is critical to avoid exceeding administrative dose limits.

COMMENTS:

END OF TASK STOP TIME PAGE 7011

KEY DO NOT HAND TO APPLICANT SURVEY DATA:

1-FCV 63-11 is shown on the Survey map.

Travel time from the sample room door thru the sample room is 30 seconds.

Travel time from the sample room door thru the penetration room to the step off pad is 30 seconds.

Travel time from the step off pad past the Hot Spot to the lower radiation area around the BIT is 50 seconds due to obstructions in the area.

Travel time from the BIT area into the piping area is 180 seconds.

Travel time thru the piping area to the valve is 420 seconds.

Estimated time at valve is 20 minutes.

Estimated time at the STEP OFF pad during exit is 4 minutes.

General Area Dose rates are listed on the survey map.

RESULTS:

Sample Room and (475mr/hr)(0.5min)(hr/60min) x 2(trips) 7.92 mr back Range: 7.5 8.5 mr Pen Room to STEP (l2Omr/hr)(0.5min)(hr/60min) x 2(trips) 2 mr OFF PAD and back Range: N/A Hot Spot and back (2700mr/hr)(50sec)(min/60sec)(hr/60min) x 75 mr 2(trips)

Range: N/A Past BIT and back (900mr/hr)(3min)(hr/60min) x 2(trips) 90 mr Range: N/A Transit to valve and (350mr/hr)(7min)(hr/60min) x 2(trips) 81.67 mr back Range: 81 - 82 mr Operate valve (320mr/hr)(20min)(hr/60min) x 1(trip) 106.67 mr Range: 106- 107 mr STEP OFF PAD (l2Omr/hr)(4min)(hr/60min) x 1(trip) 8 mr during exit Range: N/A Total 371.26mr Range: 369.5 372.5 mr Accept 369.5 to 372.5 mrem as dose expected to perform task.

When added to current dose for the year of 700 mr, the administrative dose limit of 1000 mrem WILL BE EXCEEDED (total 1069.5 1072.5 mrem).

PAGE 8011

APPLICANT DATA SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

SHEET I OF 3 INITIAL CONDITIONS:

I. A survey map is available for elevation 713 of the auxiliary building, showing dose rates and projected travel times to reach 1-FCV-63-11 and open it manually.

2. RADCON personnel are currently unavailable to provide assistance.

INITIATING CUES:

I. You have been directed to perform the alignment of I-FCV-63-11.

2. Your total dose for the year to date is 700 mr.

3. Calculate your estimated total dose to perform this job using the attached survey map.

4. Determine if you can perform this job without exceeding your administrative dose limit. Show all work.

k3RO

APPLICANT DATA SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

SHEET2OF3 SURVEY DATA:

1 -FCV 63-11 is shown on the Survey map.

Travel time from the sample room door thru the sample room is 30 seconds.

Travel time from the sample room door thru the penetration room to the step off pad is 30 seconds.

Travel time from the step off pad past the Hot Spot to the lower radiation area around the BIT is 50 seconds due to obstructions in the area.

Travel time from the BIT area into the piping area is 180 seconds.

Travel time thru the piping area to the valve is 420 seconds.

Estimated time at valve is 20 minutes.

Estimated time at the STEP OFF pad during exit is 4 minutes.

General Area Dose rates are listed on the survey map.

RESULTS:

A.3RO

APPLICANT DATA SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

SHEET3OF3 1000 mr/hr ED general area IL V

(A 120 mr/hr general area II.,-.

.,.. b 1 -FCV-63-8 1 -FCV-7240 350 mr/hr 1-FCV-63-1 1 2700 nir hr 900 mrhr general area 320 mr/hr I. Hot Spot general area cieneral area U 80,0,7

a ))

i?j 0

Yo/me confo1 oop No. 4 A.3 RO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 SRO 2011-12 NRC Exam FINAL SUBMITTAL A.3 SRO Determine Potential Total Dose for Valve Alignment.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 SRO 2011-12 NRC Exam EVALUATION SHEET Task: Determine Potential Total Dose For Valve Alignment.

Alternate Path: n/a Facility JPM #: 3-OT-JPMADA.3-1 Safety Function: n/a

Title:

Radiation Control KIA 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

Rating(s): 3.2/3.7 CFR: 41.12 / 43.4 / 45.10 Evaluation Method: Simulator In-Plant Classroom X*

References:

Task Number: AUO-119-SSP-5.01-001

Title:

Control Personal Radiation Exposure Task Standard: The applicant

1. Determines total dose which an individual would receive while aligning 1-FCV-63-1 1 to be 369.5 372.5 mrem. When added to the total dose received for the year, the applicant states that the administrative dose limit 1000 mrem) will be exceeded.

2. States that the RCTP-1 05-1, Administrative Dose Level Extension (TVA 40757) must be filled out and approved by the Radiation Protection Manager, in order for the assigned AUO to perform the task.

Validation Time: 30 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 SRO 2011-12 NRC Exam ToolslEguipmentlProcedures Needed:

A.3 SRO Applicant Data Sheets I through 3.

NRC REFERENCE DISK

Calculator

NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.

flP 19

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 SRO 1

A 2011-12 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task, return the handout sheet I provided you.

INITIAL CONDITIONS:

1. An outage is in progress on Unit 1. A surveillance test is required to be performed on 1-FCV-63-11, requiring it to be stroked (closed-open-closed).

2. A survey map is available for elevation 713 of the auxiliary building, showing dose rates and projected travel times to reach 1-FCV-63-11 and open it manually.

3. RADCON personnel are currently unavailable to provide assistance.

4. The AUO assigned the task has received 700 mr year-to-date.

INITIATING CUES:

1. Based on the data provided, determine:

a. The dose projected to be received by the assigned AUO during performance of the surveillance on 1-FCV-63-11.

b. The assigned AUOs total annual dose expected after the surveillance is corn plete.

2. Would administrative actions be required to allow the assigned AUO to complete the task? If so, what is required.?

PA(F d flP 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 SRO 2011-12 NRC Exam START TIME:

EXAMINER: If the applicant asks if this is a planned special exposure, respond that the applicant should read initiating cues.

Examinee must calculate 2 way travel time through all transit areas. Allowable ranges are shown where applicable STEP 1: Calculate exposure during transit through the sample room CRITICAL and penetration room to the valve and return. STEP STANDARD: SAT Sample Room (475mr/hr)(O.5min)( hrl6Omin) x 2(trips) = 7.92 mr UNSAT Allowable range: (7.5 mr to 8.5 mr)

Pen Room to STEP (l2Omr/hr)(O.5min)(hr/6Omin) x 2(trips) 2 mr OFF PAD Allowable range: N/A Hot Spot (2600mr/hr)(5Osec)(min/6Osec)(hr/6Omin) x 2(trips) 75 mr Allowable range: N/A Past BIT (900mr/hr)(3min)(hr/6Omin) x 2(trips) 90 mr Allowable range: N/A Transit to valve (350mr/hr)(7min)(hr/6Omin) x 2(trips) 81.67 mr Allowable range: (81 mr to 82mr)

Operate valve (320mr/hr)(2Omin)(hr/6Omin) x 1(trip) = 106.67 mr Allowable range: (106.Omr to lO7mr)

STEP OFF PAD (l2Omr/hr)(4min)(hr/6Omin) 1(trip) = 8 mr during exit Allowable range: N/A Step is critical to avoid exceeding dose limits.

COMMENTS:

PAGE 5 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 SRO 2011-12 NRC Exam EXAMINER: Some rounding of numbers is allowed as long as the examinee follows sound mathematical standards. The acceptable total range is 369.5 to 372.5 mrem.

STEP 2: Calculate the total exposure received while performing the CRITICAL task. STEP STANDARD: SAT Individual doses received are added up. UNSAT 7.92mr + 2mr + 75mr + 9Omr + 81 .67mr + 1 06.67mr + 8mr = 371.26 mr.

Rounding values:

Low: 7.5 + 2 + 75 + 90 + 81 + 106.0 + 7 = 369.5 mr High: 8.5 + 2+ 75 + 90 + 82 + 107 + 8 = 372.5 mr Acceptable Range 369.5 372.5 mrem Step is critical to avoid exceeding dose limits.

COMMENTS:

PAGE6OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 SRO 2011-12 NRC Exam STEP 3. Applicant total estimated exposure for the assigned AUO. CRITICAL STEP STANDARD:

SAT Total dose calculated in previous step is added to applicants total dose for the year: UNSAT 700 mr (total dose to date) + 371.26 mr (total dose for this job) = 1071.26 mrem.

Acceptable range of answer 1069.5 mrem to 1072.5 mrem.

Critical step to calculate dose accurately in order to avoid exceeding dose limits.

COMMENTS:

STEP 4: Applicant determines admin dose limit will be exceeded if the CRITICAL job is performed. Applicant notifies examiner of findings, STEP stating that admin dose limit will be exceeded.

SAT STANDARD:

UNSAT Admin dose limit for the year is 1000 mrem. Potential dose received is 369.5 to 372.5 mrem. Total is 1069.5 to 1072.5 mrem, which is above the TVA annual administrative limit.

Step is critical to avoid inadvertently exceeding administrative dose limits.

COMMENTS:

PAGE 7012

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 SRO 2011-12 NRC Exam STEP 5: Applicant responses to the Question, Would administrative CRITICAL actions be required to allow the assigned AUO to complete STEP the task? If so, what is required?

SAT STANDARD:

UNSAT The applicant determines that in order for the assigned AUO to go above TVA annual administrative dose limit, NPG-SPP-05.1, Radiological Controls, Section 3.4.1 .F would have to be applied. (See reference supplied.)

The applicant must state that RCTP-1 05-1, Administrative Dose Level Extension (TVA 40757) form must be completed and approved by the Radiation Protection Manager for greater than 1 rem (or 3 rem LDE, or 10 rem SDE).

CUE: When notified of applicants findings, acknowledge report using repeat back, and state that this JPM is completed. Have applicant turn in all paperwork & calculations.

Step is critical to avoid exceeding NRC dose limits.

COMMENTS:

END OF TASK STOP TIME PAGE 8 OF 12

KEY DO NOT HAND TO APPLICANT SURVEY DATA:

1-FCV 63-11 is shown on the Survey map.

Travel time from the sample room door thru the sample room is 30 seconds.

Travel time from the sample room door thru the penetration room to the step off pad is 30 seconds.

Travel time from the step off pad past the Hot Spot to the lower radiation area around the BIT is 50 seconds due to obstructions in the area.

Travel time from the BIT area into the piping area is 180 seconds.

Travel time thru the piping area to the valve is 420 seconds.

Estimated time at valve is 20 minutes.

Estimated time at the STEP OFF pad during exit is 4 minutes.

General Area Dose rates are listed on the survey map.

RESULTS:

Sample Room and (475mrIhr)(O.5min)(hr/6Omin) x 2(trips) 7.92 mr back Range: 7.5 8.5 mr Pen Room to STEP (l2Omr/hr)(0.5min)(hr/60min) x 2(trips) 2 mr OFF PAD and back Range: N/A Hot Spot and back (2600mrIhr)(5osec)(minl6osec)(hrl60min) x 75 mr 2(trips)

Range: N/A Past BIT and back (900mr/hr)(3min)(hr/60min) x 2(trips) 90 mr Range: N/A Transit to valve and (350mr/hr)(7min)(hr/60min) x 2(trips) 81.67 mr back Range: 81 - 82 mr Operate valve (320mr/hr)(2omin)(hr/6omin) x 1(trip) 106.67 mr Range: 106 - 107 mr STEP OFF PAD (l2Omr/hr)(4min)(hr/6Omin) x 1(trip) 8 mr during exit Range: N/A Total 371.26 mr Range: 369.5 372.5 mr Accept 369.5 to 372.5 mrem as dose expected to perform task.

When added to current dose for the year of 700 mr, the administrative dose limit of 1000 mrem WILL BE EXCEEDED (total 1069.5 1072.5 mrem).

PAGE 9 OF 12

APPLICANT DATA SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

SHEET I OF 3 INITIAL CONDITIONS:

1. An outage is in progress on Unit 1. A surveillance test is required to be performed on 1-FCV-63-11, requiring it to be stroked (closed-open-closed).

2. A survey map is available for elevation 713 of the auxiliary building, showing dose rates and projected travel times to reach 1-FCV-63-11 and open it manually.

3. RADCON personnel are currently unavailable to provide assistance.

4. The AUO assigned the task has received 700 mr year-to-date.

INITIATING CUES:

1. Based on the data provided, determine:

a. The dose projected to be received by the assigned AUO during performance of the surveillance on I -FCV-63-1 1.

b. The assigned AUOs total annual dose expected after the surveillance is complete.

2. Would administrative actions be required to allow the assigned AUO to complete the task? If so, what is required?

A.3SRO

APPLICANT DATA SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

SHEET2OF3 SURVEY DATA:

1 -FCV 63-11 is shown on the Survey map.

Travel time from the sample room door thru the sample room is 30 seconds.

Travel time from the sample room door thru the penetration room to the step off pad is 30 seconds.

Travel time from the step off pad past the Hot Spot to the lower radiation area around the BIT is 50 seconds due to obstructions in the area.

Travel time from the BIT area into the piping area is 180 seconds.

Travel time thru the piping area to the valve is 420 seconds.

Estimated time at valve is 20 minutes.

Estimated time at the STEP OFF pad during exit is 4 minutes.

General Area Dose rates are listed on the survey map.

RESULTS:

A3 SRO.

APPLICANT DATA SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

SHEET3OF3 AAIjL4L 7

L1 Q475mr/hr general area 120 mr/hr genera] area s.op 1000 mr/hr general area V

-1 F ED IA

.,Y_

i -FCV-63--8 -r -r f-I L T i -

1 -FCV-72-40 350 mr/hr 1-FCV-63-1 1 2700 mrihr 900 mr/hr genera] area 320 mr/hr I. Hot Spot general area general area Soan inj. - ..y.*.*.

as 1;A

/7 : /

2 70* U /ame

%. N Con frol L Nczz?

1 No. 4 \:..\

A3 SRO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4SRO 2011-12 NRC Exam FINAL SUBMITTAL A4SRO Determine if conditions warrant a Follow-up Report or Upgrade based on changing conditions.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4SRO 2011-12 NRC Exam EVALUATION SHEET Task: Determine if conditions warrant a Follow-up Report or Upgrade based on changing conditions.

Alternate Path: n/a Facility JPM #: Modified 3-OT-JPMSO8IA Safety Function: n/a

Title:

KIA 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.

Rating(s): 2.7/4.5 CFR: 41.10 / 43.5 I 45.11 Evaluation Method: Simulator In-Plant Classroom X*

References:

EPIP-1 Emergency Plan Classification Flowpath, Rev. 35.

EPIP-3 Alert, Rev. 33.

EPIP-4, Site Area Emergency, Rev. 32.

EPIP-5 General Emergency, Rev. 38.

Task Number: SRO-113-EPIP-001

Title:

Classify emergency events requiring Emergency Plan Implementation.

Task Standard: The applicant:

1) Determines that an upgrade from an ALERT to a GENERAL EMERGENCY is required.

2) Prepares forms for emergency notification as indicated on the attached key.

3) Initiates Protective Action Recommendations, Recommendation 2.

Validation Time: 25 minutes Time Critical: Yes X No Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner:

NAME SIGNATURE DATE COMMENTS

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4SRO 2011-12 NRC Exam Tools/EguipmentlProcedures Needed:

The following information will be handed out to each SRO applicant:

1. EPIP-1, Emergency Plan Classification Logic, MARKED UP for the ALERT condition described in the INITIAL CONDITIONS.

2. EPIP-3, Alert, Appendix A, TVA Initial Notification Form For Alert, FILLED OUT for the Alert condition described in the INITIAL CONDITIONS.

3. A blank copy of EPIP-3, Alert, Appendix C, Alert Follow-up Notification Form, Page 20 of 20.

3. Blank copies of the following EPIP-4, Site Area Emergency, forms:

a. Appendix A, TVA Initial Notification Form For Site Area Emergency, Page 19 of 21.

b. Appendix B, TVA Initial Classification Form For Site Area Emergency, Page 20 of 21.

c. Appendix C, Site Area Emergency Follow-Up Notification Form, Page 21 of 21.

4. Blank copies of the following EPIP-5, General Emergency, forms:

a. Appendix A, TVA Initial Notification Form For General Emergency, Page 17 of 21.

b. Appendix B, Protective Action Recommendations, Page 19 of 21.

c. Appendix C, TVA Initial Notification Form For General Emergency, Page 19 of 21.

d. Appendix D, General Emergency Follow-Up Notification Form, Page 20 of 21.

e. Appendix E, Contact Information for State and Local Notifications, Page 21 of 21.

NRC REFERENCE DISK.

NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4SRO 2011-12 NRC Exam DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

TREA T THIS AS A RADIOLOGICAL EMERGENCY DRILL

1. Unit I was at 90% RTP when the crew manually initiated a Reactor Trip and Safety Injection due to a SGTR on SG #1 of approximately 100 gpm.

2. An ALERT was declared 15 minutes ago, and EPIP-3, Alert has been implemented.

3. The Shift Technical Advisor NOW reports the following conditions exist on Unit 1:

a. One Safety Valve on SG #1 opened and cannot be closed or isolated.

b. The Chemistry Supervisor reports RCS activity is 340 uCilgram dose equivalent 1-131.

c. All Status Trees are GREEN except for FR-H.5, Steam Generator Low Level, which is YELLOW due to levelin SG #1 at 50% wide range.

d. Atmospheric conditions indicate the wind is from 90 degrees at 10 mph.

e. The SGTR on SG #1 continues at approximately 100 gpm.

INITIATING CUES:

1. As the SED, you are to evaluate current plant conditions and decide the appropriate actions.

2. Once your decision is made, fill out the appropriate forms as necessary.

NOTIFICATIONS ARE NOT REQUIRED.

3. This JPM contains time critical elements.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4SRO 2011-12 NRC Exam STEPISTANDARD SATIUNSAT START TIME:

STEP 1: Refers to EPIP-1 to determine level of classification required CRITICAL for the events in progress. STEP STANDARD: SAT Applicant refers to EPIP-1, Section 1, Fission Product Barrier Matrix. UNSAT Applicant determines that the following conditions exist:

1.1.2 Loss, RCS sample activity is greater than 300 iCi/gm dose equivalent 1-131 1 .2.3 Loss, SGTR that results in a safety injection actuation OR entry into E-3.

1.3.4 Loss, RUPTURED S/G is also FAULTED outside CNTMT OR Prolonged (>4 Hours) Secondary Side release outside CNTMT from a SIG with a SGTL > T/S Limits.

Based on Emergency Class Criteria, the applicant determines the need to upgrade to a General Emergency, based on the loss of 3 barriers.

Criteria to meet the critical step is for the EALs to be correctly identified and the declaration made within 15 minutes.

EXAMINER: RECORD time that declaration was made:_________

COMMENTS:

PAGE 5 OF 7

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4SRO 2011-12 NRC Exam STEP/STANDARD SATIUNSAT EXAMINER: Completed copies of EPIP-5, General Emergency, Appendix A and B for this JPM are included and marked EXAM MATERIAL KEY. -

STEP 3: INITIATES EPIP-5, GENERAL EMERGENCY Appendix A, CRITICAL TVA Initial Notification Form For Site Area Emergency, and STEP Appendix B.PROTECTIVE ACTION RECOMMENDATIONS.

SAT STANDARD:

UNSAT Applicant evaluates EPIP-5, Appendix B, PROTECTIVE ACTION RECOMMENDATIONS, flowchart and determines Recommendation 2 is required.

Applicant completes EPIP-5, Appendix A, TVA Initial Notification Form For General Emergency, within 10 minutes after the declaration is made.

Critical elements that must appear on Appendix A form:

Item 3 EAL Designators

- - 1.1.2 L, 1.2.3 L, 1.3.4 L Item 4. - Brief Description of Event Events that occurred, in the words of the applicant. Concurrent with a 100 gpm SG tube rupture on SG 1, RCS Activity is 340 microcurries/gram dose equivalent 1-131, and a SG I safety valve is failed open.

Item 6. Time that applicant declared the event and the date.

Item 8. - Recommendation 2 selected with wind direction 69-110 and associated Sectors selected.

EXAMINER: RECORD time that appendices are completed:

COMMENTS:

END OF TASK STOP TIME PAGE 6 OF 7

WBN General Emergency EPIP-5 Unit 0 Rev. 0038 Page 17 of 21 Appendix A (Page 1 ofl)

TVA Initial Notification Form For General Emergency 2 Ths is an Actual Event Repeat This is an Actual Event jrhls[sSED ails Bar has declared a GENERAL EMERGENCY affecting Unit 1 CRITICAL EAL Designator(s): 1.1.2 L(OSS) / 1.2.3 L(OSS) / 1.3.4 L(OSS) CRITICAL Description of the Event: Concurrent with a 100 qpm SG tube rupture on SG 1, RCS Activity is 340 N

microcurries/gram dose equivalent 1-131, and a SG 1 safetyvalve is failed open. CRITICAL Radiological Conditions: (Check one under both Airborne and Liquid column.)

Airborne Releases Offsite Liquid Releases Offsite Either of the 2 indicated items is acceptable Either of the 2 indicated items is acceptable Minor releases within federally approved limits 1 Minor releases within federally approved limits 1

0. Releases above federally approved limits 1 0 Releases above federally approved limits 1 Release information not known j4 Release informatiOn not known (Tech Specs) (Tech Specs)

Event Declared: Time: TIME Date: TODAY CRITICAL The Meteorological Conditions are: (Use 46 meter data from the Met Tower)

Wind Direction is FROM: 90 degrees Wind Speed: 10 m.p.h Provide Protective Action Recommendation: (Check 1, 2 or 3, and mark wind direction.) CRITICAL 0 Recommendation I

WIND FROM °

Recommendation 2

EVACUATE LISTED SECTORS F (Mark) R EVACUATE LISTED SECTORS (2 mile Radius and 10 miles downwind) E E (2 mile radius and 5 mile downwind)

SHELTER remainder of 10 mile EPZ. C C SHELTER remainder of 10 mile EPZ.

CONSIDER issuance of Potassium Iodide CONSlDER issuance of Potassium in accordance with the State Plan. 1 2 Iodide in accordance with the State Plan.

A-i, B-i, C-i, D-i, 26-68 A-i, B-i, C-i, D-i, C-7, -9, D-2, -4, -5, -6, -7, -8, -9 C-7, D-2, -4, -5 A-i, B-i, C-i, D-i,69-110 A-i, B-i, C-i, D-1, A-3, -4, D-2, -3, -4, -5, -6, -7, -8, -9 >< A-3, D-2, -4, -5 A-i,B-i,C-i,D-1, iii-i70 A-i,B-i,C-i,D-i, A-2, -3, -4, -5, -6, -7, D-2, -3, -5, -6 A-2, -3, D-2, -5 A-i, B-i, C-i, D-i, i7i-230 A-i, B-i, C-i, D-i, A-2, -3, -5, -6, -7, B-2, -3, -4, -5, C-2 A-2, -3, B-2, -4, C-2 A-i, B-i, C-i, D-i, 23i-270 A-i, B-i, C-i, D-i, B-2, -3, -4, -5, C-2, -3, B-2, -4, C-2 A-i, B-i, C-i, D-i, 271-325 A-i, B-i, C-i, D-i, B-2,-3,C-2,-3,-4,-5,-6,-ii B-2,C-2,-4,-5, A-i, B-i, C-i, D-i, 326-25 A-i, B-i, C-i, D-i, C-2, -4, -5, -6, -7, -8, -9, -10, -ii, D-4, -9 C-2, -4, -5, -7, -8, D-4 0 Recommendation 3 SHELTER all sectors. >CONSIDER issuance of Potassium Iodide in accordance with the State Plan.

c9AX this form to CECC Director at 5-751-1682 or ODS at 5-75i-8620 or TEMA at 9-i-6i5-242-9635.

?I Call ODS or TEMA to ensure accuracy of the information provided.

WBN General Emergency EPIP-5 UnitO Rev. 0038 Pagel8of2l Appendix B (Pagelofi)

Protective Action Recommendations If conditions are unknown utilizing the flowchart, then answer is NO.

N A short term release is defined as a release that does not exceed a 15 minute duration.

GENERAL EMERGENC DECLARED jCONTINUE ASSESSMENT

Modify protective actions based on available plant and field monitoring information.

Locate and evaluate localized hot spats.

Is there a short term controlled release whereas near NO plant areas cannot be evacuated before RECOMMENDATION I RECOMMENDATION 2 EVACUATE 2 miles radius and 10 miles downwind 7 EVACUATE 2 miles radius and 5 miles downwind AND AND SHELTER remainder of \ SHELTER remainder of /

lOmileEPZ 10mleEPZ I I TABLE I Protective Action Guides (PAG)

TYPE LIMIT Measured 3.9 E-6 micro Ci/cc of Iodine 131 or 1 REM per hour External Dose Projected I REM TEDE or 5 REM Thyroid CDE

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

TREAT THIS AS A RADIOLOGICAL EMERGENCY DRILL

1. Unit I was at 90% RTP when the crew manually initiated a Reactor Trip and Safety Injection due to a SGTR on SG #1 of approximately 100 gpm.

2. An ALERT was declared 15 minutes ago, and EPIP-3, Alert has been implemented.

3. The Shift Technical Advisor NOW reports the following conditions exist on Unit 1:

a. One Safety Valve on SG #1 opened and cannot be closed or isolated.

b. The Chemistry Supervisor reports RCS activity is 340 uCilgram dose equivalent 1-131.

c. All Status Trees are GREEN except for FR-H.5, Steam Generator Low Level, which is YELLOW due to level in SG #1 at 50% wide range.

d. Atmospheric conditions indicate the wind is from 90 degrees at 10 mph.

e. The SGTR on SG #1 continues at approximately 100 gpm.

INITIATING CUES:

1. As the SED, you are to evaluate current plant conditions and decide the appropriate actions.

2. Once your decision is made, fill out the appropriate forms as necessary.

NOTIFICATIONS ARE NOT REQUIRED.

3. This JPM contains time critical elements.

A.4SRO

ML12074A184

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