ML12074A058

Initial Exam 2011-302 Draft Administrative Jpms

ML12074A058
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: ML12074A058 (143)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Examination: October 2011 Examination Level: RO El SRO Operating Test Number: 2 Administrative Topic Tvne

• Describe activity to be performed (See Note) Code Al-I Determine License Status 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as Conduct of Operations M,R medical requirements, no-solo operation, maintenance of active license status, 10CFR55 etc.

Al-2 RCS Deboration Calculation.

2. 1.25 Ability to interpret reference materials, such as Conduct of Operations M, R graphs, curves, tables, etc. 3.9 / 4.2 41.10 / 45.12

/43.5 A.2 Independent Verification of I-Sl-68-32 Calculation.

Equipment Control N,R 2.2.12 Knowledge of surveillance procedures. 3.7/4.1 41.10/45.13 A.3 Determine Potential Dose During Valve Alignment.

Radiation Control M,R 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. 3.2/3.741.12 /

43.4 /45.10 A.4 Evaluate Changing Plant Conditions and Determine if REP Classification Upgrade is Emergency Procedures Required.

M R Plan 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation. 2.7/4.541.10 / 43.5 / 45.11 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; <4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 SRO Admin JPM Summary Al-i The applicant 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. The applicant indicates that the replacement operator must report for work no later than 0225, to meet the two hour requirement of Technical Specification Section 5.5.2, Unit Staffing.

A.l-2 Applicant determines that it will take 229.5 minutes to reduce RCS boron concentration from 52 ppm to 38 ppm after performing SO1-62.04, CVCS Purification System, Appendix B, RCS Deboration Calculation.

A.2 The applicant performs an Independent Verification of i-SI-68-32, Reactor Coolant System Water Inventory Balance, Appendix A, Manual Performance of RCS Water Inventory Balance, using the data provided. The applicant evaluates results of the calculation and enters Technical Specification LCO 3.4.13, RCS Operational LEAKAGE, Condition A.

A.3 The applicant determines total dose which an individual would receive while aligning i-FCV ii to be 360 367 mrem. When added to the total dose received for the year, the applicant

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determines that the administrative dose limit (1000 mrem) will be exceeded.

A.4 The applicant determines that an upgrade from an ALERT to a GENERAL EMERGENCY is required. The applicant prepares forms for emergency notification. The applicant evaluates conditions and initiates Protective Action Recommendations, Recommendation 2.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Examination: October 2011 Examination Level: RO SRO LI Operating Test Number: 2 Administrative Topic Type

• Describe activity to be performed (See Note) Code A.1-1 Determine License Status.

2.1.4 Knowledge of individual licensed operator

. responsibilities related to shift staffing, such as Conduct of Operations M,R medical requirements, ho-solo operation, maintenance of active license status, I OCFR55, etc.

A.1-2 RCS Deboration Calculation.

Conduct of Operations M,R 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.9/4.2 41.10/45.12

/43.5 A.2 Hand Calculation of Reactor Coolant System Water Inventory Balance.

Equipment Control M,R 2.2.12 Knowledge of surveillance procedures. 3.7/4.1 41.10/45.13 A.3 Determine Potential Dose During Valve Alignment.

Radiation Control M,R 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. 3.2/3.741.12 /

43.4 /45.10 Emergency Procedures!

N/A N/A Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; <4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 RO Admin JPM Summary Al-i The applicant is provided with historical data for four operators and must determine each operators license status. The applicant determines that Operator A, B and D do NOT meet the criteria for assuming shift.

A.i-2 Applicant determines that it will take 229.5 minutes to reduce RCS boron concentration from 52 ppm to 38 ppm after performing SO 1-62.04, CVCS Purification System, Appendix B, RCS Deboration Calculation.

A.2 The applicant performs 1-SI-68-32, Reactor Coolant System Water Inventory Balance, Appendix A, Manual Performance of RCS Water Inventory Balance, using the data provided in the Applicant Data Sheets. Based on the results of the calculation, the applicant determines that the UNIDENTIFIED leakage limits have been exceeded.

A.3 The applicant determines total dose which an individual would receive while aligning i-FCV ii to be 360 367 mrem. When added to the total dose received for the year, the applicant

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determines that the administrative dose limit (1000 mrem) will be exceeded.

A.4 N/A

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-10 NRC Exam A.1-1 SRO Determine License Status

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-10 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, 10CFR55, 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-119-SPP-10.0-001

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: /

NAME SIGNATURE DATE COMMENTS

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-10 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. 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, CB!ICE 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 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?

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-10 NRC Exam 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 1 OAC.

10/04/11 Worked 0700-1 900 shift in the Taciciinq Office.

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

10/06/11 Worked 0700-1 900 shift as Unit 1 OAC. Called for Fitness for Duty Random Test.,

and was absent from the Control Room for 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

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

OPERATOR B License was active on October 1, 2011.

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

10/02/1 Worked 0700-1 900 shift in the TaQQincI Office.

10/03/1 Worked 0700-1 900 shift as Unit 1 CR0.

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

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

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

OPERATOR C License was inactive on October 1, 2011 10/05/11 thru 10/09/11 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the Unit 1 OAC and completed all requirements for license reactivation.

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

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

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-10 NRC Exam STEPISTANDARD 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 the operator did not UNSAT work the required qualified 5 twelve hour shifts in a license position during the previous quarter. The shift on 10/06/11 DOES NOT count due to the 2.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> absence. OPDP-1 0, Section 3.2.4.B states Absences from the Control Room for extended periods (i.e., Fitness-for-Duty testing) will not count towards shift functions.

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

COMMENTS:

STEP 2: Determine the Active I Inactive status of Operator B license. CRITICAL STEP STANDARD:

SAT Applicant determines the license is Inactive because the operator did not work the required 5 twelve hour shifts in a license position during the UNSAT previous quarter.

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

COMMENTS:

PAGE 5 OF 9

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-10 NRC_Exam STEPISTANDARD SAT/UNSAT STEP 3: Determine the Active I Inactive status of Operator C license. CRITICAL STEP STANDARD:

SAT Applicant determines the license is Active because the license was reactivated in the previous quarter, including working 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the UNSAT direction of the Unit 1 OAC. The operator has also worked 4 twelve hour shifts in a license position during the quarter.

Step is critical to ensure an operator with an active license is called in to replace the ill OAC to 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 6 OF 9

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 SRO 2011-10 NRC_Exam STEP/STANDARD SAT/U NSAT 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 RO UNSAT 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

COMMENTS:

END OF TASK STOP TIME PAGE 7 OF 9

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 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?

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?

A.1-1 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 OAC.

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

10/04/11 Worked 0700-1 900 shift in the TaQainQ Office.

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

10/06/11 Worked 0700-1 900 shift as Unit I OAC. Called for Fitness for Duty Random Test.,

and was absent from the Control Room for 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

11/14/11 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 in the TaciciinQ Office.

10/03/11 Worked 0700-1 900 shift as Unit 1 CR0.

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

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

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

OPERATOR C License was inactive on October 1, 2011 10/05/1 1 thru 10/09/1 1 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the Unit 1 OAC and completed all reciuirements for license reactivation.

11/12/11 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 1 OAC.

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

A.1-1 SRO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO 2011-10 NRC Exam A.1-1 RO Determine License Status

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.l-l RO 2011-10 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: 41.10/43.2 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: 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

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-l RO 2011-10 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:

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.

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

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

10/04/1 1 Worked 0700-1900 shift in the Tagging Office.

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

10/06/1 1 Worked 0700-1900 shift as Unit 1 OAC. Called for Fitness for Duty Random Test., and was absent from the Control Room for 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

11/14/11 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.

1 0/02/1 1 Worked 0700-1900 shift in the Tagging Office.

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

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

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

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

Operator C License was inactive on October 1, 2011 10/05/1 1 thru 10/09/1 1 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the Unit 1 OAC and completed all requirements for license reactivation.

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

11/13/11 Worked 0700-1900 shift as Unit 1 OAC.

1 1/15/1 1 Worked 0700-1900 shift as Unit 1 OAC.

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

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE Al-l RO 2011-10 NRC Exam Table continued on next page.

License was active on October 1, 2011.

10/07/11 Worked 0700-1900 shift as Unit 1 OAC.

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

10/09/11 Worked 0700-1900 shift as Unit 1 OAC.

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

10/11/11 Worked 0700-1 900 shift as Unit 1 OAC. Absent from MCR for 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> to complete required General Employee Training.

INITIATING CUES:

1. 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO 2011-10 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 the operator did not UNSAT work the required qualified 5 twelve hour shifts in a license position during the previous quarter. The shift on 10/06/11 DOES NOT count due to the 2.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> absence. OPDP-1 0, Section 3.2.4.B states Absences from the Control Room for extended periods (i.e., Fitness-for-Duty testing) will not count towards shift functions.

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

COMMENTS:

STEP 2.: Determine the Active I Inactive status of Operator B license. CRITICAL STEP STANDARD:

SAT Applicant determines the license is Inactive because the operator did not work the required 5 twelve hour shifts in a license position during the UNSAT previous quarter.

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

COMMENTS:

PAGE 5 OF 8

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-1 RO 2011-10 NRC Exam STE P/STAN DARD SAT/U N SAT STEP 3.: Determine the Active / Inactive status of Operator C license. SAT STANDARD: UNSAT Applicant determines the license is Active because the license was reactivated in the previous quarter, including working 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the Unit I OAC. The operator has also worked 4 twelve hour shifts in a license position during the quarter.

COMMENTS:

STEP 4.: Determine the Active / Inactive status of Operator D license. CRITICAL STEP STANDARD:

SAT Applicant determines the license is Inactive because the operator did not work the required qualified 5 twelve hour shifts in a license position during UNSAT the previous quarter. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> time to attend the pre-job brief on 10/08/11 does count as actively performing the functions of an operator.

Howerver, the 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> spent completing required general employee training on 10/11/11 does NOT count as actively performing the functions of an operator.

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

COMMENTS:

END OF TASK STOP TIME PAGE 6 OF 8

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

INITIAL CONDITIONS:

Four Reactor Operators have the following history:

1. All four obtainted 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.

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

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

10/04/11 Worked 0700-1900 shift in the Tagging Office.

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

10/06/11 Worked 0700-1900 shift as Unit 1 OAC. Called for Fitness for Duty Random Test., and was absent from the Control Room for 2.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

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

Operator B License was active on October 1, 2011.

10/01/11 Worked 0700-1900 shift as Unit 1 OAC.

10/02/1 1 Worked 0700-1900 shift in the Tagging Office.

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

10/05/1 1 Worked 0700-1900 shift as Unit 1 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 10/05/11 thru 10/09/11 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the Unit 1 OAC and completed all requirements for license reactivation.

11/12/11 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 1 OAC.

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

Table continued on next page.

A.1-1 RO

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

Operator D License was active on October 1, 2011.

10/07/1 1 Worked 0700-1900 shift as Unit 1 OAC.

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

10/09/1 1 Worked 0700-1900 shift as Unit 1 OAC.

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

10/11/11 Worked 0700-1900 shift as Unit 1 OAC. Absent from MCR for 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to complete required General Employee Training.

INITIATING CUE:

1. You are to determine which if any of the Reactor Operators is NOT etigible to work the Unit 1 OAC position on the 0700 1900 shift on January, 31, 2012.

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A.1-1 RO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 2011-10 NRC Exam A1-2 Perform RCS Deboration Calculation

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 2011-10 NRC Exam EVALUATION SHEET Task: Perform RCS Deboration Calculation.

Alternate Path: n/a Facility JPM #:

Safety Function: n/a

Title:

KIA 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:

SOI-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 229.5 (acceptable range 229-230) minutes to reduce RCS boron concentration from 52 ppm to 38 ppm after performing SO1-62.04, 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

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 2011-10 NRC Exam ToolslEguipmentlProcedures Needed:

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

• Tl-59, Boron Tables, Rev. 7

• 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.

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 52 ppm.

3. Current RCS temperature is 575°F.

4. Mixed Bed A contains fresh, unborated resin.

5. Maximum Mixed Bed (MB) flow per SOI-62M4, 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 38 ppm.

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

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 2011-10 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:

or V

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

V = ROS Volume at operating temperature (gals)

T = Time (minutes)

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:

PAGE 5 OF 7

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.1-2 2011-10 NRC Exam

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

SAT STANDARD:

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

(Acceptable Range 87813 87814 gallons)

-

COMMENTS:

STEP 4: [4] PERFORM the following calculation to estimate time in CRITICAL service: STEP SAT STANDARD: UNSAT 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 229.5 minutes.

(Acceptable range 229 230 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 6 OF 7

• WBN CVCS Purification System SOl-62.04 Unit I Rev. 0057 Page 97 of 103 Appendix B (Page I ofi)

RCS Deboration Calculation

[ INDICATE Mixed Bed for which this Calculation is being performed (CHECK ONLY ONE.)

Mixed Bed A X OR Mixed Bed B 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:

QT V

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

V = RCS Volume at operating temperature (gals)

T = Time (minutes)

RECORD current RCS Temperature:

575 RCS Temp RECORD RCS Volume (V) based on current RCS Temp using Tl-59 (first page of App D through App N, as appropriate.)

87813.5 RCS Volume PERFORM the following calculation to estimate time in service:

-In (Cr/Co) V -In ( 38 ppm! 52 ppm) 87813.5 gals Time =

Q 120 gpm Time = 229.5 minutes

[5] RECORD Mixed Bed Run times for which this Calculation is being performed (Times can be obtained from Attachment 1 for the associated demin).

1 2 3 4 5 6 7 8 Run time Total time Initials

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 52 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 SOl-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 38 ppm.

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

A.1-2

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A2SRO 2011-10 NRC Exam A.2 SRO Independent Verification of 1-Sl-68-32 Calculation

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-10 NRC Exam EVALUATION SHEET Task: Independent Verification of 1-SI-68-32 Calculation.

Alternate Path: n/a Facility JPM #: Modified Safety Function: n/a

Title:

Equipment Control KIA 2.2.12 Knowledge of surveillance procedures.

Rating(s): 3.7/4.1 CFR: 41.10/45.13 Evaluation Method: Simulator In-Plant Classroom X

References:

1-51-68-32, Reactor Coolant System Water Inventory Balance, Rev. 14.

Task Number: RO-068-Sl-68-32-001

Title:

Perform a Reactor Coolant System Inventory Balance.

Task Standard: The applicant:

1.) Performs an Independent Verification of 1-SI-68-32, Reactor Coolant System Water Inventory Balance, Appendix A, Manual Performance of RCS Water Inventory Balance, using the data provided and identifies that the RCDT Leakage was incorrectly calculated.

2.) Evaluates results of the calculation and enters Technical Specification LCO 3.4.13, RCS Operational LEAKAGE, Condition A.

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

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-10 NRC Exam Tools/EguipmentlProcedures Needed:

• Marked-up copy of 1-Sl-68-32, Reactor Coolant System Water Inventory Balance, Rev. 14.

• Calculator

• Steam Tables 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.2 SRO 2011-10 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. Unit I is in Mode I at 100% power.

2. 1-Sl-68-32, Reactor Coolant System Water Inventory Balance, performance is req UI red.

3. The ICS Computer program RCSWIB is unreliable.

4. 1-Sl-68-32 Appendix A, Manual Performance of RCS Water Inventory Balance, has been completed through step 5.

5. An initial data set was entered at 1800 and a second data set was entered at 1900 on I-Sl-68-32 Appendix B, RCS Water Inventory Balance Data Sheet.

6. Appendix C, RCS Water Inventory Balance Calculations, has been performed by an extra operator assigned to the shift.

INITIATING CUES:

1. As the Unit SRO, you are to complete an independent verification of the manual calculation of RCS inventory balance using the data provided.

2. Evaluate the results of your calculation and determine which, if any, Technical Specification ACTIONS are applicable.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-10 NRC Exam I STEPISTANDARD SAT/UNSAT START TIME:

NOTE Throughout this Appendix, INITIAL indicates the data is to be taken from first data set recorded in Appendix B and FINAL indicates data is to be taken from the last data set recorded in Appendix B. A copy of this Appendix is required to be completed each time RCS leakage is calculated.

STEP 1: [1] CALCULATE elapsed time (AT) as follows: CRITICAL STEP STANDARD:

SAT Applicant determines the elapsed time to be 60 minutes by performing the appropriate calculation. UNSAT Step is critical since an incorrect calculation of the elapsed time will result in an incorrect calculation of leak rates.

STEP 2: [2] CONVERT INITIAL and FINAL PZR PRESSURE units of CRITICAL measure to psia as follows: STEP STANDARD: SAT Applicant determines the Initial and Final PZR pressures to be 2250 UNSAT psia.

Step is critical since an incorrect calculation of the initial and final pressures will result in an incorrect calculation PZR water inventory.

COMMENTS:

PAGE 5 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-10 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: [3] CALCULATE VCT Leakage as follows: CRITICAL STEP STANDARD:

SAT Applicant determines VCT leakage to be 1.03 gpm.

(Acceptable range 1.0-1.3 gpm) UNSAT Step is critical since an incorrect calculation of the VCT leakage will result in an incorrect calculation of overall leakage rates.

COMMENTS:

STEP 4: [4] CALCULATE Pressurizer (PZR) Leakage as follows: CRITICAL STEP

[4.1] RECORD INITIAL and FINAL PZR PRESSURE in table below using values calculated in Step [2]. SAT

[4.2] RECORD INITIAL and FINAL PZR LEVEL in table below UNSAT using values recorded in Appendix B.

[4.3] DETERMINE and RECORD INITIAL and FINAL PZR Vf (volume of water) and Vg (volume of steam) at INITIAL and FINAL PZR PRESS (Step [2]) using ASME Steam Tables (Table 2, Properties of Saturated Steam and Saturated Water).

STANDARD:

Applicant enters the appropriate data from the Steam Tables into the table.

Step is critical since an incorrect calculation of the VCT leakage will result in an incorrect calculation of overall leakage rates.

COMMENTS:

PAGE 6 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-10 NRC Exam STEP/STANDARD I SAT/UNSAT STEP 5: [4] CALCULATE Pressurizer (PZR) Leakage as follows: CRITICAL (Continued) STEP

[4.4] CALCULATE INITIAL PZR VOLUME as follows: SAT STANDARD: UNSAT Applicant performs the calculation and determines Initial PZR volume to be 4972.5 gallons.

(Acceptable range 4944.2 5003.4 gallons)

-

Step is critical since an incorrect calculation of the PZR initial volume will result in an incorrect calculation of PZR and overall leakage rates.

COMMENTS:

STEP 6: [4] CALCULATE Pressurizer (PZR) Leakage as follows: CRITICAL (Continued) STEP

[4.5] CALCULATE FINAL PZR VOLUME as follows: SAT STANDARD: UNSAT Applicant performs the calculation and determines Final PZR volume to be 4834.4 gallons.

(Acceptable range 4808.9 4862.5 gallons)

-

Step is critical since an incorrect calculation of the PZR final volume will result in an incorrect calculation of PZR and overall leakage rates.

COMMENTS:

PAGE 7 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-10 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: [4] CALCULATE Pressurizer (PZR) Leakage as follows: CRITICAL (Continued) STEP

[4.6] CALCULATE PZR Leakage as follows: SAT STANDARD: UNSAT Applicant performs calculation and determines PZR leakage to be 2.3 gpm.

(Acceptable range 2.25 2.35 gpm)

-

Step is critical since an incorrect calculation of the PZR leakage rate will result in an incorrect calculation of the overall leakage rate.

COMMENTS:

STEP 8: [5] IF RCS TEMP FINAL is NOT equal to RCS TEMP INITIAL, SAT THEN UNSAT STANDARD:

Applicant determines RCS temperature did not change so this step and its sub steps are not applicable. Applicant marks Step 5 and its sub-steps as N/A.

COMMENTS:

PAGE 8 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-10 NRC Exam STEP/STANDARD SAT/U NSAT STEP 9: [6] CALCULATE Total RCS Leakage as follows: CRITICAL STEP STANDARD:

SAT Applicant adds VCT Leakage of 1.03 gpm to PZR Leakage of 2.3 gpm and determines Total RCS Leakage to be 3.33 gpm. UNSAT (Acceptable range 3.25 3.4 gpm)

-

Step is critical since an incorrect calculation of Total RCS Leakage will result in an incorrect evaluation of RCS Leakage.

COMMENTS:

STEP 10: [7] CALCULATE Leakage to Pressurizer Relief Tank (PRT) as SAT follows:

UNSAT STANDARD:

Applicant determines there is no change in the PRT level and leakage to the PRT is 0 gpm.

COMMENTS:

PAGE 9 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-10 NRC Exam STEP/STANDARD [ SATIUNSAT STEP 11: [8] CALCULATE Leakage to Reactor Coolant Drain Tank CRITICAL (RCDT) as follows: STEP STANDARD: SAT Applicant determines from Tl-4 Part II that initial RCDT volume is equal UNSAT to 80 gallons, and that final RCDT volume is 140 gallons. The leakage to the RCDT is calculated at 1.0 gpm.

Applicant determines that the RO entered the incorrect value for the initial RCDT level (21 gallons), resulting in a value of 2 gpm.

Step is critical since an incorrect calculation will result in an incorrect evaluation of RCS leakage.

COMMENTS:

STEP 12: [9] CALCULATE Identified Leakage as follows: CRITICAL STEP STANDARD:

SAT Applicant performs adds Leakage to PRT of 0 gpm to the Leakage to RCDT of I gpm and Total SG Leakage of 0 gpm and determines that UNSAT Identified Leakage is 1.0 gpm.

Applicant determines that the RO entered the incorrect value for the Leakage to RCDT of 2 gpm.

Step is critical since an incorrect calculation will result in an incorrect evaluation of RCS leakage.

COMMENTS:

PAGE 10 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 SRO 2011-10 NRC Exam STEP/STANDARD [ SATIUNSAT STEP 13: [10] CALCULATE Unidentified Leakage as follows: CRITICAL STEP STANDARD: SAT Applicant subtracts the Identified leakage of 1.0 gpm from the Total RCS UNSAT Leakage of 3.33 gpm determines that Unidentified Leakage is 2.33 gpm.

(Acceptable range 2.25 2.4 gpm)

-

Applicant determines that the previous error made by the RO resulted in an Unidentified Leakage of 1.33 gpm.

Step is critical since an incorrect calculation will result in an incorrect evaluation of RCS leakage.

COMMENTS:

STEP 14: [11] RECORD Total RCS Leakage (Step [63), Identified Leakage CRITICAL (Step [9]) and Unidentified Leakage (Step [10]) on Appendix STEP B in the last column that data is recorded. SAT STANDARD: UNSAT Applicant records values in the appropriate column on Appendix B.

Applicant determines that the Unidentified Leakage Rate does not meet Acceptance Criteria, and determines that Technical Specification 3.4.13, Action A is applicable and leakage rate must be reduced to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Step is critical to ensure that the proper Technical Specification is entered and the appropriate Action is performed.

COMMENTS:

END OF TASK STOP TIME PAGE 11 OF 12

AflFAIM IDrfI VV WBN Unit I Water Inventory Balance Page2of32 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of RevisionlChange Rev 9 08/12/04 2, 8-1 1, 18 Non-intent change. Incorporated Operations comments related to PER 64091 and other enhancements. Required 1-LCV-62-1 18 (1-HS-62-1 18A) to be in VCT position during test. 50.59 review is NOT required.

Rev 10 07/25/06 2, 23 Corrected UNID for Pressurizer Cold Cal instrument 1-Ll-68-321. 50.59 review is NOT required.

Rev 11 11/24/06 2,4, 13,29 Updated RCS volume in temperature correction calculation based on DCN 51754.

Rev 12 12/12/06 2, 8, 1 1 Added notes relative to zinc addition (DCN 52122).

Rev 13 03/05/10 All This procedure has been converted from Word 95 to Word XP using Rev 12 by the conversion team. A line by line verification, including minor editorial and formatting corrections, was performed by the preparer. Clarifications related to procedure revisions were made to the Precautions and Limitations. A 10CFR5O.59 screening review is not required for this revision.

Rev 14 01/24/11 2, 31 Added Note to Appendix C allowing Total RCS Leakage to conservatively be set equal to Unidentified Leakage under certain unusual conditions. A IOCFR5O.59 screening review or evaluation is not required for this revision since it implements requirements of the Technical Specifications.

NRC LXAM FAATFRAL

P 4[ 1? 4*

L

______L.i.

WBN Reactor Coolant System I -SI-68-32 Unit I Water Inventory Balance Rev. 0014 Page 3 of 32 Table of Contents

1.0 INTRODUCTION

4 1.1 Purpose 4 1.2 Scope 4 1.3 Frequency and Conditions 4

2.0 REFERENCES

6 2.1 Performance References 6 2.2 Developmental References 6 3.0 PRECAUTIONS AND LIMITATIONS 7 4.0 PREREQUISITE ACTIONS 9 4.1 PreliminaryActions 9 4.2 Approvals and Notifications 10 4.3 Field Preparations 10 5.0 ACCEPTANCE CRITERIA 12 6.0 PERFORMANCE 13 7.0 POST PERFORMANCE ACTIVITIES 17 8.0 RECORDS 18 8.1 QARecords 18 8.2 Non-QA Records 18 Appendix A: Manual Performance of RCS Water Inventory Balance 19 Appendix B: RCS Water Inventory Balance Data Sheet 21 Appendix C: RCS Water Inventory Balance Calculations 24 Source Notes 32

WBN AD MTN-WM KEY Reactor Coolant System I -Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page4of32

1.0 INTRODUCTION

1.1 Purpose This Instruction provides detailed steps to perform a Reactor Coolant System (RCS) water inventory balance.

1.2 Scope 1.2.1 Operability Test to be Performed Operations that could affect RCS water inventory (makeup and sampling) are terminated and the RCS is stabilized. With the RCS stable, parameters such as temperature, pressure, and associated tank levels are measured at one hour or greater intervals. When at least two sets of data have been collected, identified and unidentified leakages are calculated using the rate of change between the data sets.

Then, the calculated leakage rates are compared to values in Technical Specification Limiting Condition for Operation (LCO) 3.4.13 to determine RCS 4

operability.

1.2.2 Surveillance Requirements Fulfilled and Modes NOTES

1) TSR 3.4.13.1 is applicable in Modes 3 and 4 after 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of steady state operation have been achieved.

2) Steady state operation is defined as RCS temperature stable within +/- 0.3°F.4 Performance of this SI fully implements Technical Specifications Requirements 3.4.13.1.

TECHNICAL SPECIFICATION SECTION APPLICABLE MODES PERFORMANCE MODES 3.4.13.1 1,2,3, 4(See Notes) 1,2,3,4 LcQ 3.4.15, AcTI0N-A.1 1,2,3,4 1,2,3,4 Lco 3.4.15, ACTION-B.1.2 1,2,3,4 1,2,3,4 1.3 Frequency and Conditions A. This Instruction is required to be performed at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the unit is in Mode I or 2 during steady state operation and in Mode 3 or 4 after 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of steady state operation has been achieved.

NR( LXAM MATERIAL

WBN AD MI-N Reactor Coolant4il6832 Unit I Water Inventory Balance Rev. 0014 Page5of32 1.3 Frequency and Conditions (continued)

B. This Instruction is required to be performed within one hour of receiving an alarm and confirming leakage in a flow path with no indicators.

2 Leakage by any of the following will be indicated by an alarm in the control room: Leakage across the SIS cold-leg and hot-leg check valves is detected by pressure transmitters, leakage across the cold-leg accumulators check valves is detected by increase in accumulator inventory, steam generator tube leakage is indicated by radiation monitors, leakage past RHR injection check valves is detected by pressure transmitters, RCS leakage into CCS is detected by radiation monitors.

2 C. This Instruction is required to be performed once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for LCO 3.4.15 Action-A.1 or LCO 3.4.15 Action-B.1.2 iRC XAM MAERAL

WBN AReactor DM[WJ Coolant S Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page6of32

2.0 REFERENCES

2.1 Performance References A. ASME Steam Tables.

B. SOl-77.O1, Waste Disposal System.

C. Tl-4, Part II, Plant Curve Book, Tank Curves, Turbine Curves.

2.2 Developmental References 2.2.1 TVA Procedures A. SPP-2.6, Computer Software Control.

2.2.2 TVA Drawings A. 1-47W809-1 B. 1-47W809-2 C. 1-47W813-1 D. 1-47W830-1 2.2.3 Other A. N3-68-4001, Reactor Coolant System.

B. Regulatory Guide 1.45, Reactor Coolant Pressure Boundary Leakage Detection System.

C. Unit I Technical Specification Section 3.4.13.

Nr FXAMMATERA

WBN ADM[NJRM-KEY Reactor Coolant System 1-SI-68-32 Unit I Water Inventory Balance Rev. 0014 Page 7 of 32 3.0 PRECAUTIONS AND LIMITATIONS The final RCS temperature must be within +/- 0.3°F of the initial RCS temperature or the final data is VOID and must be retaken.

The final RCS power level must be within +/- 1 .0% of the initial RCS power level or the final data is VOID and must be retaken.

Makeup to the Volume Control Tank (VCT) is isolated and VCT level is expected to decrease during this SI. If VCT level falls to 20% or low VCT level alarm annunciates before final data is recorded, makeup to the VCT will be required and the test will have to be voided and reperformed.

The Reactor Coolant Drain Tank (RCDT) pumps are placed in PULL-TO-LOCK with 1-FCV-68-310, PRT DRAIN, closed. At the same time, RCDT and Pressurizer Relief Tank (PRT) levels are expected to increase. If PRT or RCDT high level alarm annunciates before final data is recorded, pump-down of the PRT or RCDT will be required and the test will have to be voided and reperformed.

Instruments such as PZR pressure and level or any other instruments used by the RCS Inventory Program that are removed from service during the performance of this SI will cause the quality to be bad on the final data sheet.

Any revisions to this SI will require coordination with the Computer Engineering Group to change the SI revision level displayed on the ICS Water Inventory Balance screen.

Any revisions or modifications to this procedure that affect the water inventory balance calculation or that could affect the ICS software will require a Computer Software Service Request (SSR) per SPP-2.6 to make the applicable software changes to the ICS Water Inventory Balance.

If any of the following events occur during performance of Section 6.0 the data is VOID and the test must be restarted after initial conditions are reestablished:

Any instrument or computer data point used to obtain initial data is NOT available for final data.

Emergency boration.

Diversion of letdown to the hold up tanks.

Makeup from any source.

Change in primary side purification demineralizers or filter lineup.

Failure to accumulate data for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

F CFXAM 1 AATER A L

WBN ADM[NJ-M-K Reactor Coolant System Y

E1-SI-68-32 Unit I Water Inventory Balance Rev. 0014 Page 8 of 32 3.0 PRECAUTIONS AND LIMITATIONS (continued)

Restarting the primary water pumps if they were stopped before the initial data was collected.

Sampling the RCS or making chemical additions to the RCS (with the exception of RCS Zinc Injection).

PRT or RCDT operations that affect tank levels.

Operating with VCT level near the divert setpoint of 63% may cause erratic readings due to diversion of letdown to the HUT (which is NOT accounted for in the calculations). Reducing VCT level to less than 60% before initiating performance will minimize the possibility of errors in the calculations.

To ensure that test results are as accurate as possible, the test should NOT begin until at least 30 minutes following evolutions such as dilution, boration, or rod movement.

Zinc injection, as implemented by DCN 52122, is limited to a maximum of 8 ml per minute (about 0.002 gpm). This amount of inventory increase is NOT detectable within the methodology of this procedure.

/ XAMMATFRAL

ArrjnM IDr,1 k3V WBN Reactor Coolant System 1-SI-68-32 Unit I Rev 0014 Data Package: Page Date TODAY 4.0 PREREQUISITE ACTIONS 4.1 Preliminary Actions RECORD start date and time on Surveillance Task Sheet. LRM IF required, THEN OBTAIN an RWP. LRM jiF in Mode 3 or 4, THEN SETUP trend block on the Plant computer to monitor Thot approximately every 30 minutes. N/A IF steady state conditions are maintained for any continuous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, THEN PERFORM this instruction. N/A MAKE log entry at end of each 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period if NOT at steady state (+/- 0.3°F). N/A RECORD present plant operating mode: 1 OBTAIN the most recent Steam Generator (SG) Leakage from Chemistry. LRM RECORD the most recent Steam Generator Leakage obtained from Chemistry in the appropriate column below, AND CALCULATE Total SG Leakage (in gpm) as follows:

SG Leakage Reported as TOTAL SG Leakage Reported as INDIVIDUAL Total SG SG1 SG2 SG3 SG4 Leakage = Leakage + Leakage + Leakage + Leakage Total SG Leakage = 0 gpd 0

= gpd + 0 gpd + 0 gpd+ 0 gpd Total SG Leakage = 0 gpd (sum of above)

Total SG Total SG Leakage (god) 0 gpçj Leakage (gpm) = 1440 mm/day = 1440 mm/day = 0 gpm Total SG Leakage = 0 gpm LRM DAH Performed CV I,EXAM M 1 EFJA1

!XflFAIM flDFii Ptrni WBN Reactor Coolant System I -SI-68-32 Unit I Water Inventory Balance Rev. 0014 Page 10 of 32 Data Package: Page Date TODAY 4.2 Approvals and Notifications OBTAIN Operations approval on Surveillance Task Sheet to perform this Instruction. LRM 4.3 Field Preparations ENSURE VCT level is such that neither makeup NOR diversion to the HUT is anticipated during performance of this Instruction. LRM IF Reactor Coolant Drain Tank (RCDT) level is such that an automatic pump-down may occur during the performance of this procedure, THEN PERFORM SOl-77.O1 as required to reduce RCDT level to the LO-level cutoff. LRM RECORD as-found position of the following handswitches, AND PLACE the following handswitches in their required position:

AS-FOUND REQUIRED HANDSWITCH DESCRIPTION POSITION POSITION INITIALS 1-HS-77-4A REACTOR COOLANT PULLTO LOCK PULL TO LOCK LRM DRTKPUMPA 1-HS-77-6A RCDT PUMP B PULL TO LOCK PULL TO LOCK LRM NOTIFY Chemistry Lab that RCS water inventory balance is being performed and they are NOT to make any chemical additions to the RCS (with the exception of RCS Zinc Injection)

OR take any samples from the RCS. LAM i C LXA A MATERIAl

AThMM IA VV WBN Unit I Water Inventory Balance Rev. 0014 PagelIol32 Data Package: Page Date TODAY 43 Field Preparations (continued)

RECORD as-found position of the following valves and handswitches, AND PLACE the following valves and handswitches in their required position.

AS-FOUND REQUIRED VALVE DESCRIPTION POSITION POSITION INITIALS 1-LCV-77-415 RCDT DRAIN LEVEL CONTROL CLOSED CLOSED LRM 1-HS-62-118A LETDOWN DIVERT TO HUT VCT VCT LRM 1-FCV-62-128 BA BLENDER TO VCT INLET P-AUTO CLOSED CLOSED LRM MAKEUP INJECTION VLV FLOW P-AUTO 1-FCV-62-144 CLOSED CLOSED CONTROL LRM EMERGENCY BORATION FLOW 1-FCV-62-138 CLOSED CLOSED CONTROL VALVE LRM ESTABLISH communications between test performer in the Main Control Room and test performer stationed at 1-Ll-77-1

[O-PNL-276-L2, EL 692, CDL A8-S]. LRM XAM AATF RIAL

WBN Reactor Coolant System 1-Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Pagel2of32 Data Package: Page Date 5.0 ACCEPTANCE CRITERIA A. Technical Specification acceptance criteria for RCS leakage is shown below:

1. No pressure boundary leakage.

NOTE Negative unidentified leakage may be considered acceptable if at least one hour of additional data is collected and unidentified leakage is more positive than -0.10 gpm OR total leakage is less than or equal to 1.0 gpm.

3

2. 1 gpm unidentified leakage.

3. 10 gpm identified leakage.

B. If Acceptance Criteria stated above is NOT met, the SRO is to be notified as soon as possible that LCO 3.4.13 may be applicable and an investigation into the source of leakage is to be initiated.

I C XAAMA1ERA1

tinr/HM IFi1 WBN Reactor Coolant System I -SI-68-32 Unit I Water Inventory Balance Rev. 0014 Page 13 of 32 Data Package: Page Date TODAY 6.0 PERFORMANCE 1i) ENSURE precautions and limitations in Section 3.0 have been reviewed. LRM ENSURE prerequisite actions in Section 4.0 have been met. LRM ENSURE reactor power and RCS temperature are stable and have varied less than the limits shown below during the last 30 minutes:

PARAMETER VARIATION LIMITS Reactor power +/- 1.0%

Mode 1 & 2 Tavg +/-0.3°F Mode 3 & 4 ThOt +/- 0.3°F LRM

\-

RCS parameters must remain stable during performance of remaining steps in this Section.

IF Plant Computer Program RCSWIB is unavailable, THEN MARK Steps 6.0[5] through 6.0[18] in this Section NIA, AND PERFORM Appendix A. LRM Values displayed on the computer screen are color coded to indicate QUALITY of the data point. Values that appear BLUE are BAD QUALITY (NOT reliable). Final readings will appear BLUE until computed.

Step 6.0[1 1] provides action to be taken when a data point has BAD QUALITY. This action should be taken anytime (during this SI) a data point has BAD QUALITY.

DISPLAY Plant Computer Program RCSWIB screen using the RCSWIB TURN ON Code (TOC) OR the BOP menu touch screen N/A NGFXAMMA RAL

WBN ADM[N J-RM-KEY Reactor Coolant System 1-SI-68-32 Unit I Water Inventory Balance Rev. 0014 Pagel4of32 Data Package: Page Date TODAY 6M PERFORMANCE (continued)

Steps 6.O[6]and 6.O[7]will clear the RCSWIB program to allow a new performance to be started with Step 6.O[8]

IF RCSWIB prompt says READY FOR FINAL READINGS?

(YIN), THEN ENTER Y, AND, when prompted, ENTER RCDT level (%) from 1-LI-77-1 [O-PNL-276L2]. N/A IF RCSWIB prompt says PRINT

SUMMARY

SHEET/DATA PACKAGE? (YIN), THEN ENTER N. N/A IF RCSWIB prompt says START OR CONTINUE CALC.?

(SIC), THEN ENTER S. N/A ENTER Steam Generator leakage (gpm) from Section 4.1 [6]. N/A ENTER RCDT level (%) from 1-LI-77-1 [O-PNL-276-L2]. N/A IF any value shown on the computer display is BLUE, THEN 1 1 MARK remaining steps in this Section N!A, AND PERFORM Appendix A, OR SELECT another data point associated with the parameter in question, THEN REPLACE the BAD QUALITY data point using the substitute value function on the single point menu screen prior to initiating and finalizing the RCSWIB program, AND EXPLAIN in Remarks Section of Surveillance Task Sheet. N/A r

FXAM iT i

1 N

WBN ADM[N-J PM-KEY Reactor Coolant System I -Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page 15 of 32 Data Package: Page Date TODAY 6.0 PERFORMANCE (continued)

The RCSWIB prompt READY FOR FINAL READINGS? (YIN) will display at the top of the screen until Y is entered. Operators may exit the program to perform other tasks and return to this prompt by starting RCSWIB program as described in Step 6.O[5]. All data is retained and the programs clock keeps track of elapsed time WAIT at least one hour (optimum time is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) N/A ENSURE RCSWIB prompt says READY FOR FINAL Y\

READINGS? (Y/N), AND ENTER Y. N/A After RCDT level is entered, the RCSWIB program collects values from additional data points and calculates Total Leakage, Identified Leakage, and Unidentified Leakage.

ENTER RCDT level (%) from 1-Ll-77-1, [O-PNL-276-L2]. N/A IF UNIDENTIFIED LEAKAGE is less than 0 gpm (negative N , THEN 3

leakage)

ENSURE RCSWIB prompt says PRINT

SUMMARY

SHEET/DATA PACKAGE? (Y/N), AND ENTER N. N/A WHEN RCSWIB prompt says START OR CONTINUE CALC.? (S/C), THEN ENTER C. N/A WAIT at least one hour from the last time data was collected. N/A ENSURE RCSWIB prompt says READY FOR FINAL READINGS?, (Y/N), AND ENTERY. N/A ENTER RCDT level (%) from 1-Ll-77-1, [0-PNL-276-L2]. N/A XAM\AA1ERAI

WBN Unit I Water Inventory Balance Rev. 0014 Page 16 of 32 Data Package: Page Date TODAY 6.0 PERFORMANCE (continued)

REPEAT Steps 6.0[15.1] through 6.0[1 5.5] UNTIL one of the following conditions exists:

A. UNIDENTIFIED LEAKAGE is more positive than

-0.10 gpm.

B. TOTAL LEAKAGE is less than or equal to 1.0 gpm.

C. SI is aborted because A or B above cannot be met before plant conditions, e.g. makeup to VCT or pump down of RCDT, require action that would invalidate test results. N/A IF SI is aborted per Step 6.0[15.6]C, THEN NOTIFY UNIT SRO and/or cognizant System Engineer that an investigation to determine the source of inleakage to the RCS must be initiated.

3 N/A ENSURE RCSWIB prompt says PRINT

SUMMARY

SHEET/DATA PACKAGE? (YIN), AND ENTER Y. N/A PRESS ENTER to obtain printout at default printer. N/A ATTACH printout to the data package of this SI. N/A

[19] IF UNIDENTIFIED LEAKAGE is greater than 1 gpm, THEN NOTIFY UNIT SRO and/or cognizant System Engineer that an investigation to determine any miscellaneous identified leakage (i.e., other than leakage to the PRT, RCDT or SG tube leakage) from the RCS must be initiated.

[20] IF MISCELLANEOUS IDENTIFIED LEAKAGE is found and determined to cause failure of the SI, THEN RECORD the source and amount of MISCELLANEOUS IDENTIFIED LEAKAGE on the computer printout/data sheet.

[21] VERIFY Acceptance Criteria is met.

XAM M/LRIA

AflFMM IDIA VZV WBN Unit I Water Inventory Balance 32 Data Package: Page Date 7.0 POST PERFORMANCE ACTIVITIES

[1] RETURN the following valves and handswitches to their as-found position listed in Step 4.3[5], AND VERIFY valve and handswitch position:

VALVE DESCRIPTION INITIALS IV 1-LCV-77-415 RCDT DRAIN LEVEL CONTROL N/A 1-HS-62-118A LETDOWN DIVERT TO HUT 1-FCV-62-128 BA BLENDER TO VCT INLET N/A MAKEUP INJECTION VLV FLOW I FCV 62 144

-

N/A

- CONTROL EMERGENCY BORATION FLOW I FCV 62 138

-

- CONTROL VALVE

[2] PLACE the following handswitches in their as-found position listed in Section 4.3[3]:

HANDSWITCH DESCRIPTION AS-FOUND POSITION INITIALS 1-HS-77-4A REACT COOLANT DR TK PUMP A 1-HS-77-6A RCDT PUMP B

[3] RECORD completion time and date on Surveillance Task Sheet.

[4] NOTIFY SM/UNIT SRO that this SI is complete.

XA! 1 MATER A L

WBN React 68-32 Unit I Water Inventory Balance 0014 Page 18 of 32 8.0 RECORDS 8.1 QA Records The Data Package is a QA record, is handled in accordance with the Document Control and Records Management Program, and contains the following:

A. Completed parts of Sections 4.0, 6.0 and 7.0.

B. Section 5.0.

C. Completed Appendixes A and B.

D. Surveillance Task Sheet.

E. Other sheets added during the performance.

8.2 Non-QA Records None NF F/AM MATRAL

WBN Unit I Water Inventory Balance Page 19 of 32 Appendix A (Page 1 of 2)

Manual Performance of RCS Water Inventory Balance Data Package: Page Date TODAY 1.0 MANUAL PERFORMANCE OF RCS WATER INVENTORY BALANCE F)

OBTAIN controlled copy of TI-4, Part II pages that show graphs of volume vs. indicated level for Pressurizer Relief Tank (PRT) and Reactor Coolant Drain Tank (RCDT). LRM RECORD initial RCS data per Appendix B. LAM WAIT at least one hour (optimum is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />). LRM RECORD another set of RCS data per Appendix B. LAM CALCULATE RCS leakage per Appendix C. 4 LAM Additional copies of Appendix C may be used to perform independent verification.

PERFORM independent verification of Appendix C.

IV

[7] IF unidentified leakage is less than 0 gpm (negative leakage)

,

3 THEN

[7.1] WAIT at least one hour from the last time data was collected.

[7.2] RECORD another set of RCS data per Appendix B.

[7.3] CALCULATE RCS leakage per Appendix C. 4

[7.4] PERFORM independent verification of Appendix C.

IV

[7.5] REPEAT Steps 1.0[7.1J through 1.0[7.5] UNTIL one of the following conditions exists:

A. Unidentified leakage rate is more positive than

-0.10 gpm.

B. Total RCS leakage is less than or equal to 1.0 gpm.

NRC :XAM MAT ERAI

WBN A-fl-M-[N-J--P-!\

Reactor Coolant System 6832 K-Unit I Water Inventory Balance Rev. 0014 Page2Oof32 Appendix A (Page 2of2)

Data Package: Page Date 1.0 MANUAL PERFORMANCE OF RCS WATER INVENTORY BALANCE (continued)

C. SI is aborted because A or B above cannot be met before plant conditions (e.g. makeup to VCT, pump down of RCDT) require action that would invalidate test results.

[7.6] IF SI is aborted per Stepi .O[7.5}C THEN NOTIFY SM/Unit SRO and br cognizant System Engineer that an investigation to determine the source of inleakage to the RCS must be initiated.

3

[8] GO TO Step 6.O[19].

NFC XA\i MITFRiAL

WBN Reactor Coolant System 1-Sl-68-32 Unit 1 Water Inventory Balance Rev. 0014 Page 21 of 32 Appendix B (Page 1 of 3)

RCS Water Inventory Balance Data Sheet Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE DATA SHEET NOTES

1) Time for each data set is the time of day when the first instrument is read. Recording each data set as quickly as possible will ensure an accurate relationship between parameters. Additional copies of Appendix A may be used as required.

2) Only one instrument should be used for each parameter and the same instrument must be used for each data set. Instruments NOT used should be marked NIA for each data set.

2nd 3rd 4th 5th PARAMETER INSTRUMENT [PANEL] INITIAL DATA SET DATA SET DATA SET DATA SET DATA SET TIME N/A 1800 1900 LO1I2A 40  % 36.8  %  %  %  %

VCT LEVEL 1-LI-62-129A [1-M-6] N/A  % N/A  %  %  %  %

1-PI-68-342A < 1700 psi N/A psig N/A psig psig psig psig 1-PI-68-340A[1-M-5] N/A psig N/A psig psig psig psig P0480A 2235.3 psig 2235.3 psig psig psig psig PRESSURIZER 1-PR-68-340 [1-M-5] N/A psig N/A psig psig psig psig PRESSURE P0481A N/A psig N/A psig psig psig psig 1-PI-68-322 [1-M-5] N/A psig N/A psig psig psig psig P0483A N/A psig N/A psig psig psig psig

WBN Reactor Coolant System 1-SI-68-32 Unit I Water Inventory Balance Rev. 0014 Page 22 of 32 Appendix B (Page 2 of 3)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE DATA SHEET (continued) 2nd 3rd 4th 5th PARAMETER INSTRUMENT [PANEL] INITIAL DATA SET DATA SET DATA SET DATA SET DATA SET 1-LI-68-321 < 350°F N/A  % N/A  %  %  %  %

1-LI-68-320 [1-M-4j N/A  % N/A  %  %  %  %

L0482A 60.25  % 58.0  %  %  %  %

PRESSURIZER 1LI-68-335A [1-M-4] N/A N/A

%  %  %  %  %

L0481A N/A  % N/A  %  %  %

1.-LI-68-339A [1-M-4] N/A  % N/A  %  %  %  %

L0480A N/A  % N/A  %  %  %  %

1-TI-68-2E [1-M-5] N/A N/A °F °F °F °F TO439AThOt<530°F N/A N/A °F °F °F °F T0460A 586.2 °F 586.2 °F °F °F °F RCS TEMPERATURE T0440A N/A °F N/A °F °F °F °F T0420A N/A °F N/A °F °F °F °F TO400A N/A °F N/A °F °F °F °F

WBN Reactor Coolant System 1-Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page 23 of 32 Appendix B (Page 3 of 3)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE DATA SHEET (continued) 2nd 3rd 4th 5th PARAMETER INSTRUMENT[PANEL] INITIAL DATA SET DATA SET DATA SET DATA SET DATA SET 1-NI-41 [1-M-4] 99*5  % 995  %  %  %  %

REACTOR l-NI-42 N/A  % N/A  %  %  %  %

POWER 1-NI-43 N/A  % N/A  %  %  %  %

1-NI-44 N/A  % N/A  %  %  %  %

1-LI-68-300 [1-M-4] N/A  % N/A  %  %  %  %

PRT LEVEL L0485A 59  % 59  %  %  %  %

RCDT LEVEL 1-Ll-77-1 [0-PNL-276-L2] 21  % 38  %  %  %  %

DATA SET RECORDED BY LRM LRM TOTAL RCS LEAKAGE N/A (Appendix C Step 1 .0[6])

IDENTIFIED LEAKAGE (Ace cr11: 10 gpm) N/A 2.0 (Appendix C Step 1 .O[9])

UNIDENTIFIED LEAKAGE ,

(Ace Crit: I gpm) N/A (Appendix C Step I .0[1 0]) SRO determines that the value of 1 gpm should have been entered here.

SRO determines that the value of 2.33 gpm should have been entered here.

WBN Unit I Water Inventory Balance Peof 32 Appendix C (Page 1 of 8)

RCS Water Inventory Balance Calculations Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS Throughout this Appendix, INITIAL indicates the data is to be taken from first data set recorded in Appendix B and FINAL indicates data is to be taken from the last data set recorded in Appendix B. A copy of this Appendix is required to be completed each time RCS leakage is calculated.

CALCULATE elapsed time (AT) as follows:

AT = FINAL TIME INITIAL TIME

-

AT= 1900 - 1800 AT= 60 mm LRM 1st cv CONVERT INITIAL and FINAL PZR PRESSURE units of measurement to psia as follows:

I PARAMETER I INITIAL I FINAL

= 2235.3 psig + 14.7 = 2235.3 psig + 14.7 PZR L PRESS

= 2250 psia = 2250 psia LRM I St cv

[Jp FxcM 1VAThRAL

AAIM DFA VV WBN Reactor Coolant System 1-SI-68-32 Unit I Water Inventory Balance Rev. 0014 Page 25 of 32 Appendix C (Page 2 of 8)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE VCT Leakage as follows:

(INITIAL VCT LEVEL FINAL VCT LEVEL) x 19.27 gal/%

-

VCT Leakage

= AT (Step 1.0[1])

40  % - 36.8  %) x 19.27 gaII%

VCT Leakage =

60 mm VCT Leakage = 1.03 gpm LAM 1St CV CALCULATE Pressurizer (PZR) Leakage as follows: 4

.1 RECORD INITIAL and FINAL PZR PRESSURE in table below using values calculated in Step 1 .O[2]. LAM RECORD INITIAL and FINAL PZR LEVEL in table below using values recorded in Appendix B. LRM DETERMINE and RECORD INITIAL and FINAL PZR Vf (volume of water) and Vg (volume of steam) at INITIAL and FINAL PZR PRESS (Step 1.O[2]) using ASME Steam Tables (Table 2, Properties of Saturated Steam and Saturated Water).

STEP PARAMETER INITIAL FINAL 1.0[4.1] PZR PRESS 2250 psia 2250 psia I .0[4.2] PZR LEVEL 60.25  % 58  %

PZR Vf 0.02698 /Ibm 3

ft 0.02698 /Ibm 3

ft 1.0[4.3]

PZR Vg 0.157 /Ibm 3

ft 0.157 /Ibm 3

ft LAM Ii? XAiA MATFRA

WBN Reactor Coolant Unit I Water Inventory Balance Rev. 0014 Page26of32 Appendix C (Page3of8)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE INITIAL PZR VOLUME as follows: 4 INITIAL PZR 3

X0 01605 VOLUME - Vf Vg )

INITIAL PZR 60.25 ° + 100 60.25 %) 2galft 3

((

VOLUME - 0.02698 ft/Ibm 0.157 /lbm 3

ft %1bm INITIAL PZR = 4972.64 gallons VOLUME LRM 1 St CV CALCULATE FINAL PZR VOLUME as follows: 5 FINAL PZR = irPZRLVL u100_PZRLVLx 3 16.73ft O 1 48

.

7 1

a 5 I X0 01605 VOLUME Vf Vg  % 3 ft FINAL PZR 58  %)(100 58 3

%))(2a1ft

= ((

VOLUME 0.02698 /lbm 3

ft 0.157 /lbm 3

ft %lbm FINAL PZR = 4834.51 gallons VOLUME LRM 1 st CV EXAM MAT RAL

WBN Reactor Coolant System KEY I -Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page 27 of 32 Appendix C (Page 4 of 8)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE PZR Leakage as follows:

INITIAL PZR VOLUME FINAL PZR VOLUME PZR Leakage = (Stepl.O[4.4]) - (Step 1.O[4.5])

AT (Stepl.O[1])

4972.64 gallons - 4834.51 gallons PZR Leakage =

60 mm PZR Leakage 2.3 gpm LRM 1st CV IF RCS TEMP FINAL is NOT equal to RCS TEMP INITIAL ,

4 THEN RECORD INITIAL and FINAL PZR PRESSURE in table below using values calculated in Step I .O[2] N/A RECORD INITIAL and FINAL RCS TEMPERATURE in table below using values recorded in Appendix B. N/A DETERMINE and RECORD INITIAL and FINAL RCS SPECIFIC VOLUME in table below using PZR PRESSURE, RCS TEMPERATURE and ASME Steam Tables (Table 3, Properties of Superheated Steam and Compressed Water). N/A XiFA IA/TF RA

AflFiHM IDIi1 vIzv WBN Unit I Water Inventory Balance ev 0014 Page 28 of 32 Appendix C (Page 5 of 8)

Data Package: Page Date TODAY to RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE INITIAL and FINAL RCS DENSITY as follows, AND RECORD in table below:

1 RCS DENSITY =

RCS SPECIFIC VOLUME STEP PARAM INITIAL FINAL PZR 1.O{5.1] psia psia PRESS RCS 1 .O[5.2] °F TEMP RCS 1.O[5.3] SPECIFIC /Ibm 3

ft /Ibm 3

ft VOLUME RCS 1.O[5.4] 3 Ibm/ft 3 Ibm/ft DENSITY N/A 1st CV CALCULATE RCS Temperature Correction as follows:

(InitiaiRCSDensityFinaiRCSDensity)X 1O9O2ftX 7.48O5 X O.O16O5---

3 Temp Corr = ft ibm AT (Step 1.O[1])

6 ibm Ibm ga1 1308 92 ft 3 Temp Corr = ft3J ibm mm Temp Corr =

N/A 1st CV iG EXAM \ATLPA

WBN I Rea 68-32 Unit I Wate r Inventory Balance 0014 Page 29 of 32 Appendix C (Page 6 of 8)

Data Package: Page Date TODAY tO RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE Total RCS Leakage as follows:

Total RCS Leakage = VCT Leakage (Step 1 .O[3]) +

PZR Leakage (Step [1 .O[4]) + Temp Corr (Step 1 .O[5} or 0)

Total RCS Leakage = 1.03 gpm + 2.3 gpm + 0 gpm Total RCS Leakage = 3.33 gpm LRM 1st CV CALCULATE Leakage to Pressurizer Relief Tank (PRT) as follows:

CONVERT INITIAL and FINAL PRT LEVEL from percent

(%) to gallons using TI-4, Part II, AND RECORD the converted PRT LEVELS in Step 1 .0[7.2]. LRM CALCULATE Leakage to PRT using the following equation:

(Final PRT LVL Initial PRT LVL

Leakage to PRT =

AT(Stepl.O{1])

Leakage to PRT =

(I 8250 gallons 8250 gallons 60 mm Leakage to PRT = 0 gpm LRM 1st CV I RC XA A I AM ER IAL

WBN A-JM-KEY Reactor Coolant System I -Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page 30 of 32 Appendix C (Page7of8)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE Leakage to Reactor Coolant Drain Tank (RCDT) as follows:

CONVERT INITIAL and FINAL RCDT LEVEL from percent (%) to gallons using TI-4, Part II, AND RECORD the converted RCDT LEVELS in Step I .O[8.2]. LRM CALCULATE Leakage to RCDT using the following SRO identifies that 80 gal should have been equation: entered here

= Final RCDT LVL Initial RC9L

Leakage to RCDT (Step l.O[/

140 gal gal Leakage to RCDT =

60 mm Leakage to RCDT gpm LRM I St E.N4N%%%

4

=

identifies that 1 gpm CV should have been CALCULATE Identified Leakage as follows: entered here Identified Leakage = Leakage to PRT (StepA.O[7]) +

Leakage to RCDT (Step I .O[8J) +

Total SG Leakage (Step 4.1 [6]

Identified Leakage = 0 gpm + gpm + 0 gpm Identified Leakage = 1.0 gpm LRM 1st CV I

XArA MATE RAL

WBN

° $ J-JQM- Iy-Sl-68-32 Reactor Coolant System Unit I Water Inventory Balance Rev. 0014 Page 31 of 32 Appendix C (Page 8 of 8)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE Unidentified Leakage as follows:

Unidentified Leakage = Total RCS Leakage (Step I .O[6]) -

Identified Leakage (Step 1 .D[9])

Unidentified Leakage = 3.33 gpm - 2.0 gpm Unidentified Leakage = () gpm LRM SRO identifies that 1 gpm 1st SRO identifies that 233 should have been gpm should have been / entered here CV entered here The value of Total RCS Leakage recorded in Appendix B by the following step should conservatively be set equal to the value of Unidentified Leakage IF the value of Identified Leakage is negative AND there is a well-understood reason for the negative value of Identified Leakage. Such a situation could arise if there is known external leakage from the PRT and/or the RCDT which is causing a corresponding decrease in tank level (i.e., tank out-leakage). A notation should be added to Appendix B if the value of Total RCS Leakage is set equal to Unidentified Leakage based on the reasoning in this NOTE.

RECORD Total RCS Leakage (Step 1 .O[6]), Identified Leakage (Step 1.O[9]) and Unidentified Leakage (Stepl.O[1O]) on Appendix B in the last column that data is recorded. LRM r p I - $

fJiEV!

WBN ADM-[NJ Reactor Coolant S Unit I Water Inventory Balance Rev. 0014 Page32of32 Source Notes (Page 1 ofl)

Implementing Requirements Statement Source Document Statement Primary to Secondary leakage is NCO 850404138 1 limited to 1 gpm. [Reference to this Watts Bar SER (NUREG-0847) source note on page 13 is deleted by Pages 15-18 Revision 8, which incorporates Tech Spec Change WBN-TS-99-014.]

A water inventory balance must be NCO 850404025 2 performed within one hour of receiving Watts Bar SER (NUREG-0847) an alarm and confirming leakage in a Pages 5-7 flow path with no indicators.

Steps to take when negative NRC Inspection Report 50-327 3 unidentified leakage is calculated. NOV 50-327, 328/89-16-02 RCS leakage should NOT be NRC Inspection Report 50-39OIFI 4 measured using the reactor sump. 390/85-22-01 Correction factors for PZR level need to be traceable. RCS temperature correction factor must be calculated for any change in initial and final RCS temperature.

The pressurizer (PZR) mass volume WBPER960017 5 (initial and final) should be obtained by adding the vapor space volume and the liquid space volume together.

11 Ia - /J M ii r: L

RCS Operational LEAKAGE 3.413 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4,13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. 1 gpm unidentified LEAKAGE;

c. 10 gpm identified LEAKAGE; and

d. 150 gallons per day primary-to-secondary LEAKAGE through any one steam generator (SG).

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational LEAKAGE Al Reduce LEAKAGE to within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> not within limits for reasons limits.

other than pressure boundary LEAKAGE or primary-to-secondary LEAKAGE.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not met. AND OR B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Pressure boundary LEAKAGE exists.

OR Primary-to-secondary LEAKAGE not within limit.

Watts Bar-Unit 1 3.4-30 Amendment 38, 65

RCS Operational LEAKAGE 3.413 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 NOTE

1. Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.

2. Not applicable to primary-to-secondary LEAKAGE.

Verify RCS operational LEAKAGE is within limits by 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> performance of RCS water inventory balance.

SR 3.4.13.2 NOTE Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.

Verify primary-to-secondary LEAKAGE is less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or equal to 150 gallons per day through any one SG.

Watts Bar-Unit 1 3.4-3 1 Amendment 65

RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. 1 gpm unidentified LEAKAGE;

c. 10 gpm identified LEAKAGE; and

d. 150 gallons per day primary-to-secondary LEAKAGE through any one steam generator (SG).

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational LEAKAGE Al Reduce LEAKAGE to within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> not within limits for reasons limits.

other than pressure boundary LEAKAGE or primary-to-secondary LEAKAGE.

B. Required Action and 8.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not met.

OR 8.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Pressure boundary LEAKAGE exists.

OR Primary-to-secondary LEAKAGE not within Iimit Watts Bar-Unit 1 3.4-30 Amendment 38, 65

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 -------- ---

NOTE 1 Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.

2. Not applicable to primary-to-secondary LEAKAGE.

Verify RCS operational LEAKAGE is within limits by 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> performance of RCS water inventory balance.

SR 3.4.13.2 NOTE Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.

Verify primary-to-secondary LEAKAGE is less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or equal to 150 gallons per day through any one SG.

Watts Bar-Unit 1 3.4-3 1 Amendment 65

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

INITIAL CONDITIONS:

1. Unit I is in Mode I at 100% power.

2. 1-S1-68-32, Reactor Coolant System Water Inventory Balance, performance is requi red.

3. The ICS Computer program RCSWIB is unreliable.

4. 1-SI-68-32 Appendix A, Manual Performance of RCS Water Inventory Balance, has been completed through step 5.

5. An initial data set was entered at 1800 and a second data set was entered at 1900 on 1-Sl-68-32 Appendix B, RCS Water Inventory Balance Data Sheet.

6. Appendix C, RCS Water Inventory Balance Calculations, has been performed by an extra operator assigned to the shift.

INITIATING CUES:

I. As the Unit SRO, you are to complete an independent verification of the manual calculation of RCS inventory balance using the data provided.

2. Evaluate the results of your calculation and determine which, if any, Technical Specification ACTIONS are applicable.

A.2 SRO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-10 NRC Exam A.2 RO Hand Calculation of Reactor Coolant System Water Inventory Balance

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-10 NRC Exam EVALUATION SHEET Task: Hand Calculation of Reactor Coolant System Water Inventory Balance.

Alternate Path: n/a Facility JPM #: Modified Safety Function: n/a

Title:

Equipment Control KIA 2.2.12 Knowledge of surveillance procedures.

Rating(s): 3.7/4.1 CFR: 41.10/45.13 Evaluation Method: Simulator InPlant Classroom X

References:

1-Sl-68-32, Reactor Coolant System Water Inventory Balance, Rev. 14.

Task Number: RO-068-SI-68-32-001

Title:

Perform a Reactor Coolant System Inventory Balance.

Task Standard: The applicant:

1.) Performs 1-S1-68-32, Reactor Coolant System Water Inventory Balance, Appendix A, Manual Performance of RCS Water Inventory Balance, using the data provided in the Applicant Data Sheets.

2.) Evaluates results of the calculation and determines that the UNIDENTIFIED leakage limits have been exceeded.

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

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-10 NRC Exam Tools/Equipment/Procedures Needed:

• Marked-up copy of 1-SI-68-32, Reactor Coolant System Water Inventory Balance, Rev. 14.

• Calculator

• Steam Tables 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.2 RO 2011-10 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. Unit I is in Mode I at 100% power.

2. 1-S1-68-32, Reactor Coolant System Water Inventory Balance, performance is required.

3. The ICS Computer program RCSWIB is unreliable.

4. 1-SI-68-32 Appendix A, Manual Performance of RCS Water Inventory Balance, has been completed through step 4.

5. An initial data set was entered at 1800 and a second data set was entered at 1900 on 1-S1-68-32 Appendix B, RCS Water Inventory Balance Data Sheet.

6. You are an extra operator assigned to the shift.

INITIATING CUES:

1. The Unit SRO has directed you to complete 1-SI-68-32, Appendix C, RCS WATER INVENTORY BALANCE CALCULATIONS, using the data provided.

2. After completion of 1-SI-68-32, Appendix C, RCS WATER INVENTORY BALANCE CALCULATIONS, report your results to the Unit SRO.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-10 NRC Exam I STEP/STANDARD I SAT/UNSAT START TIME:

NOTE Throughout this Appendix, INITIAL indicates the data is to be taken from first data set recorded in Appendix B and FINAL indicates data is to be taken from the last data set recorded in Appendix B. A copy of this Appendix is required to be completed each time RCS leakage is calculated.

STEP 1: [1] CALCULATE elapsed time (z\T) as follows: CRITICAL STEP STANDARD:

SAT Applicant determines the elapsed time to be 60 minutes by performing the appropriate calculation. UNSAT Step is critical since an incorrect calculation of the elapsed time will result in an incorrect calculation of leak rates.

STEP 2: [2] CONVERT INITIAL and FINAL PZR PRESSURE units of CRITICAL measure to psia as follows: STEP STANDARD: SAT Applicant determines the Initial and Final PZR pressures to be 2250 UNSAT psia.

Step is critical since an incorrect calculation of the initial and final pressures will result in an incorrect calculation PZR water inventory.

COMMENTS:

PAGE 5 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-10 NRC Exam STEPISTANDARD [ SATIUNSAT STEP 3: [3] CALCULATE VCT Leakage as follows: CRITICAL STEP STANDARD:

SAT Applicant determines VCT leakage to be 1.03 gpm.

(Acceptable range 1.0 1.03 gpm)

- UNSAT Step is critical since an incorrect calculation of the VCT leakage will result in an incorrect calculation of overall leakage rates.

COMMENTS:

STEP 4: [4] CALCULATE Pressurizer (PZR) Leakage as follows: CRITICAL STEP

[4.1] RECORD INITIAL and FINAL PZR PRESSURE in table below using values calculated in Step [2]. SAT

[4.2] RECORD INITIAL and FINAL PZR LEVEL in table below UNSAT using values recorded in Appendix B.

[4.3] DETERMINE and RECORD INITIAL and FINAL PZR Vf (volume of water) and Vg (volume of steam) at INITIAL and FINAL PZR PRESS (Step [2]) using ASME Steam Tables (Table 2, Properties of Saturated Steam and Saturated Water).

STANDARD:

Applicant enters the appropriate data from the Steam Tables into the table.

Step is critical since an incorrect calculation of the VCT leakage will result in an incorrect calculation of overall leakage rates.

COMMENTS:

PAGE 6 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-10 NRC Exam STEP/STANDARD I SATIUNSAT STEP 5: [4] CALCULATE Pressurizer (PZR) Leakage as follows: CRITICAL (Continued) STEP

[4.4] CALCULATE INITIAL PZR VOLUME as follows: SAT STANDARD: UNSAT Applicant performs the calculation and determines Initial PZR volume to be 4972.5 gallons.

(Acceptable Range 4944.2 5003.4 gallons)

-

Step is critical since an incorrect calculation of the PZR initial volume will result in an incorrect calculation of PZR and overall leakage rates.

COMMENTS:

STEP 6: [4] CALCULATE Pressurizer (PZR) Leakage as follows: CRITICAL (Continued) STEP

[4.5] CALCULATE FINAL PZR VOLUME as follows: SAT STANDARD: UNSAT Applicant performs the calculation and determines Final PZR volume to be 4834.4 gallons.

(Acceptable range 4808.9 4862.5 gallons)

-

Step is critical since an incorrect calculation of the PZR final volume will result in an incorrect calculation of PZR and overall leakage rates.

COMMENTS:

PAGE 7 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-10 NRC Exam

[ STEP/STANDARD SATIUNSAT STEP 7: [4] CALCULATE Pressurizer (PZR) Leakage as follows: CRITICAL (Continued) STEP

[4.6] CALCULATE PZR Leakage as follows: SAT STANDARD: UNSAT Applicant performs calculation and determines PZR leakage to be 2.3 gpm.

(Acceptable range 2.25 2.35 gpm)

-

Step is critical since an incorrect calculation of the PZR leakage rate will result in an incorrect calculation of the overall leakage rate.

COMMENTS:

STEP 8: [5] IF RCS TEMP FINAL is NOT equal to RCS TEMP INITIAL, SAT THEN UNSAT STANDARD:

Applicant determines RCS temperature did not change so this step and its sub steps are not applicable. Applicant marks Step 5 and its sub-steps as N/A.

COMMENTS:

PAGE 8 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-10 NRC Exam

[ STEP/STANDARD SAT/UNSAT STEP 9: [6] CALCULATE Total RCS Leakage as follows: CRITICAL STEP STANDARD:

SAT Applicant adds VCT Leakage of 1.03 gpm to PZR Leakage of 2.3 gpm and determines Total RCS Leakage to be 3.33 gpm. UNSAT (Acceptable range 3.25 3.4 gpm)

-

Step is critical since an incorrect calculation of Total RCS Leakage will result in an incorrect evaluation of RCS Leakage.

COMMENTS:

STEP 10: [7] CALCULATE Leakage to Pressurizer Relief Tank (PRT) as SAT follows:

UNSAT STANDARD:

Applicant determines there is no change in PRT level and leakage to the PRT isO gpm.

COMMENTS:

PAGE 9 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-10 NRC Exam STEPISTANDARD [ SAT/UNSAT STEP 11: [8] CALCULATE Leakage to Reactor Coolant Drain Tank CRITICAL (RCDT) as follows: STEP STANDARD: SAT Applicant determines from TI-4 Part II that initial RCDT volume is equal UNSAT to 80 gallons, and that final RCDT volume is 140 gallons. The leakage to the RCDT is calculated at 1.0 gpm. (Acceptable range 0.9- 1.1 gpm)

Step is critical since an incorrect calculation will result in an incorrect evaluation of RCS leakage.

COMMENTS:

STEP 12: [9] CALCULATE Identified Leakage as follows: CRITICAL STEP STANDARD:

SAT Applicant performs adds Leakage to PRT of 0 gpm to the Leakage to RCDT of 1 gpm and Total SG Leakage of 0 gpm and determines that UNSAT Identified Leakage is 1.Ogpm. (Acceptable range 0.9- 1.1 gpm)

Step is critical since an incorrect calculation will result in an incorrect evaluation of RCS leakage.

COMMENTS:

PAGE 10 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.2 RO 2011-10 NRC Exam STEP/STANDARD SAT/UNSAT I STEP 13: [10] CALCULATE Unidentified Leakage as foHows: CRITICAL STEP STANDARD: SAT Applicant subtracts the Identified leakage of 1.0 gpm from the Total RCS UNSAT Leakage of 3.33 gpm determines that Unidentified Leakage is 2.33 gpm.

(Acceptable range 2.25 2.4 gpm)

-

Step is critical since an incorrect calculation will result in an incorrect evaluation of RCS leakage.

COMMENTS:

STEP 14: [11] RECORD Total RCS Leakage (Step [6]), Identified Leakage CRITICAL (Step [9]) and Unidentified Leakage (Step [10]) on Appendix STEP B in the last column that data is recorded.

SAT STANDARD:

UNSAT Applicant records values in the appropriate column on Appendix B.

Applicant determines that the Unidentified Leakage Rate does not meet Acceptance Criteria, and reports values to the SRO.

Step is critical to ensure that the proper information is provided to the SRO to evaluate Technical Specifications.

COMMENTS:

END OF TASK STOP TIME PAGE 11 OF 12

ADM{N JPM KEY I !/i Watts Bar Nuclear Plant Unit I Surveillance Instruction I-S 1-68-32 Reactor Coolant System Water Inventory Balance Revision 0014 Quality Related Level of Use: Continuous Use Effective Date: 01-24-201 1 Responsible Organization: SNE, System Eng NSSS

-

Prepared By: Nicholas C. Horning Approved By: Stephen M. Partch r

I

AflIiHM A 1

F L

WBN Reactor Coolant System 1-Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page 2 of 32 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of RevisionlChange Rev 9 08/12/04 2, 8-11, 18 Non-intent change. Incorporated Operations comments related to PER 64091 and other enhancements. Required 1-LCV-62-118 (1 -HS-62-1 I 8A) to be in VCT position during test. 50.59 review is NOT required.

Rev 10 07/25/06 2, 23 Corrected UNID for Pressurizer Cold Cal instrument 1-LI-68-321. 50.59 review is NOT required.

Rev 11 11/24/06 2,4, 13, 29 Updated RCS volume in temperature correction calculation based on DCN 51754.

Rev 12 12/12/06 2, 8, 11 Added notes relative to zinc addition (DCN 52122).

Rev 13 03/05/10 All This procedure has been converted from Word 95 to Word XP using Rev 12 by the conversion team. A line by line verification, including minor editorial and formatting corrections, was performed by the preparer. Clarifications related to procedure revisions were made to the Precautions and Limitations A 10CFR5O.59

.

screening review is not required for this revision.

Rev 14 01/24/11 2, 31 Added Note to Appendix C allowing Total RCS Leakage to conservatively be set equal to Unidentified Leakage under certain unusual conditions. A IOCFR5O.59 screening review or evaluation is not required for this revision since it implements requirements of the Technical Specifications.

G If \,1 MATEF IAL

I WBN React 68-32 Unit I Water Inventory Balance 0014 Page 3 of 32 Table of Contents

1.0 INTRODUCTION

4 1.1 Purpose 4 1.2 Scope 4 1.3 Frequency and Conditions 4

2.0 REFERENCES

6 2.1 Performance References 6 2.2 Developmental References 6 3.0 PRECAUTIONS AND LIMITATIONS 7 4.0 PREREQUISITE ACTIONS 9 4.1 Preliminary Actions 9 4.2 Approvals and Notifications 10 4.3 Field Preparations 10 5.0 ACCEPTANCE CRITERIA 12 6.0 PERFORMANCE 13 7.0 POST PERFORMANCE ACTIVITIES 17 8.0 RECORDS 18 8.1 QARecords 18 8.2 Non-QA Records 18 Appendix A: Manual Performance of RCS Water Inventory Balance 19 Appendix B: RCS Water Inventory Balance Data Sheet 21 Appendix C: RCS Water Inventory Balance Calculations 24 Source Notes 32 IRC [XAI MA1ERI- L

WBN Unit I Water Inventory Balance Page4of32

1.0 INTRODUCTION

1.1 Purpose This Instruction provides detailed steps to perform a Reactor Coolant System (RCS) water inventory balance.

1.2 Scope 1.2.1 Operability Test to be Performed Operations that could affect RCS water inventory (makeup and sampling) are terminated and the RCS is stabilized. VMth the RCS stable, parameters such as temperature, pressure, and associated tank levels are measured at one hour or greater intervals. When at least two sets of data have been collected, identified and Unidentified leakages are calculated using the rate of change between the data sets.

Then, the calculated leakage rates are compared to values in Technical Specification Limiting Condition for Operation (LCO) 3.4.13 to determine RCS 4

operability.

1.2.2 Surveillance Requirements Fulfilled and Modes NOTES

1) TSR 3.4.13.1 is applicable in Modes 3 and 4 after 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of steady state operation have been achieved.

2) Steady state operation is defined as RCS temperature stable within +/- 0.3°F.

4 Performance of this SI fully implements Technical Specifications Requirements 3.4.13.1.

TECHNICAL SPECIFICATION SECTION APPLICABLE MODES PERFORMANCE MODES 3.4.13.1 1,2,3, 4(See Notes) 1,2,3,4 LCO 3.4.15, ACTION-A.1 1, 2, 3,4 1, 2, 3, 4 LCO 3.4.15, ACTION-B.1.2 1,2,3,4 1,2,3,4 1.3 Frequency and Conditions A. This Instruction is required to be performed at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the unit is in Mode 1 or 2 during steady state operation and in Mode 3 or 4 after 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of steady state operation has been achieved.

FT X/IA MA T PAL

WBN Unit I Water Inventory Balance Rev. 0014 Page 5 of 32 1.3 Frequency and Conditions (continued)

B. This Instruction is required to be performed within one hour of receiving an alarm and confirming leakage in a flow path with no indicators.

2 Leakage by any of the following will be indicated by an alarm in the control room: Leakage across the SIS cold-leg and hot-leg check valves is detected by pressure transmitters, leakage across the cold-leg accumulators check valves is detected by increase in accumulator inventory, steam generator tube leakage is indicated by radiation monitors, leakage past RHR injection check valves is detected by pressure transmitters, RCS leakage into CCS is detected by radiation monitors.

2 C. This Instruction is required to be performed once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for LCO 3.4.15 Action-A.1 or LCO 3.4.15 Action-B.1.2 Nr , XAM MA iRA[

WBN ADM[N JP M KEY Reactor Coolant System 1-Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page 6 of 32 20 REFERENCES 2.1 Performance References A. ASME Steam Tables.

B. SOl-77.O1, Waste Disposal System.

C. Tl-4, Part II, Plant Curve Book, Tank Curves, Turbine Curves.

2.2 Developmental References 2.2.1 TVA Procedures A. SPP-2.6, Computer Software Control.

2.2.2 TVA Drawings A. 1-47W809-1 B. l-47W809-2 C. l-47W813-l D. 1-47W830-1 2.2.3 Other A. N3-68-4001, Reactor Coolant System.

B. Regulatory Guide 1.45, Reactor Coolant Pressure Boundary Leakage Detection System.

C. Unit I Technical Specification Section 3.4.13.

i<AM AfA

WBN 68-32 Reacr Unit I Wate Inventory Balance 0014 Page 7 of 32 3M PRECAUTIONS AND LIMITATIONS The final RCS temperature must be within +/- 0.3°F of the initial RCS temperature or the final data is VOID and must be retaken.

The final RCS power level must be within +/- 1.0% of the initial RCS power level or the final data is VOID and must be retaken.

Makeup to the Volume Control Tank (VCT) is isolated and VCT level is expected to decrease during this SI. If VCT level falls to 20% or low VCT level alarm annunciates before final data is recorded, makeup to the VCT will be required and the test will have to be voided and reperformed.

The Reactor Coolant Drain Tank (RCDT) pumps are placed in PULL-TO-LOCK with 1-FCV-68-310, PRT DRAIN, closed. At the same time, RCDT and Pressurizer Relief Tank (PRT) levels are expected to increase. If PRT or RCDT high level alarm annunciates before final data is recorded, pump-down of the PRT or RCDT will be required and the test will have to be voided and reperformed.

Instruments such as PZR pressure and level or any other instruments used by the RCS Inventory Program that are removed from service during the performance of this SI will cause the quality to be bad on the final data sheet.

Any revisions to this SI will require coordination with the Computer Engineering Group to change the SI revision level displayed on the ICS Water Inventory Balance screen.

Any revisions or modifications to this procedure that affect the water inventory balance calculation or that could affect the ICS software will require a Computer Software Service Request (SSR) per SPP-2.6 to make the applicable software changes to the ICS Water Inventory Balance.

If any of the following events occur during performance of Section 6.0 the data is VOID and the test must be restarted after initial conditions are reestablished:

Any instrument or computer data point used to obtain initial data is NOT available for final data.

Emergency boration.

Diversion of letdown to the hold up tanks.

Makeup from any source.

Change in primary side purification demineralizers or filter lineup.

Failure to accumulate data for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

F C XAM MATERIA

WBN AD-M1-NJRM--KEY Reactor Coolant System 1-SI-68-32 Unit I Water Inventory Balance Rev. 0014 Page 8of32 3.0 PRECAUTIONS AND LIMITATIONS (continued)

Restarting the primary water pumps if they were stopped before the initial data was collected.

Sampling the RCS or making chemical additions to the RCS (with the exception of RCS Zinc Injection).

PRT or RCDT operations that affect tank levels.

Operating with VCT level near the divert setpoint of 63% may cause erratic readings due to diversion of letdown to the HUT (which is NOT accounted for in the calculations). Reducing VCT level to less than 60% before initiating performance will minimize the possibility of errors in the calculations.

To ensure that test results are as accurate as possible, the test should NOT begin until at least 30 minutes following evolutions such as dilution, boration, or rod movement.

Zinc injection, as implemented by DON 52122, is limited to a maximum of 8 ml per minute (about 0.002 gpm). This amount of inventory increase is NOT detectable within the methodology of this procedure.

N XAMMATFHA

i AflI\ilIM 1rIv1F1 ii-i-r FZM WBN Reactor Coolant System 1-Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page 9 of 32 Data Package: Page Date TODAY 4.0 PREREQUISITE ACTIONS 4.1 Preliminary Actions RECORD start date and time on Surveillance Task Sheet. LRM IF required, THEN OBTAIN an RWP. LRM IF in Mode 3 or 4, THEN SETUP trend block on the Plant computer to monitor Th t 0

approximately every 30 minutes. N/A IF steady state conditions are maintained for any continuous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, THEN PERFORM this instruction. N/A MAKE log entry at end of each 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period if NOT at steady state (+/- 0.3°F). N/A RECORD present plant operating mode: 1 OBTAIN the most recent Steam Generator (SG) Leakage from Chemistry. LRM RECORD the most recent Steam Generator Leakage obtained from Chemistry in the appropriate column below, AND CALCULATE Total SG Leakage (in gpm) as follows:

SG Leakage Reported as TOTAL SG Leakage Reported as INDIVIDUAL TotalSG SG1 SG2 SG3 SG4 Leakage = Leakage + Leakage + Leakage ÷ Leakage Total SG Leakage = 0 gpd 0 Leakage = gpd ÷ 0 gpd + 0 gpd+ 0 gpd Total SG Leakage = 0 gpci (sum of above)

Total SG Total SG Leakage (gpd) 0 gpç Leakage (gpm) = 1440 mm/day = 1440 mm/day = 0 gpm Total SG Leakage = 0 gpm LRM DAH Performed CV Jr !AAMATLRIAI

I AnriHMFrTr III WBN Reactor Coolant System 1-Sl-68-32 Unit I Water Inventory Balance Rev. 0014 PagelOof32 Data Package: Page Date TODAY 4.2 Approvals and Notifications j) OBTAIN Operations approval on Surveillance Task Sheet to perform this Instruction. LRM 4.3 Field Preparations ENSURE VCT level is such that neither makeup NOR diversion to the HUT is anticipated during performance of this Instruction. LRM

) IF Reactor Coolant Drain Tank (RCDT) level is such that an automatic pump-down may occur during the performance of this procedure, THEN PERFORM SOI-77.O1 as required to reduce RCDT level to the LO-level cutoff. LRM I) RECORD as-found position of the following handswitches, AND PLACE the following handswitches in their required position:

AS-FOUND REQUIRED HANDSWITCH DESCRIPTION POSITION POSITION INITIALS 1-HS-77-4A REACTOR COOLANT PULL TO LOCK PULL TO LOCK LRM DRTKPUMPA 1-HS-77-6A RCDT PUMP B PULL TO LOCK PULL TO LOCK LRM NOTIFY Chemistry Lab that RCS water inventory balance is being performed and they are NOT to make any chemical additions to the RCS (with the exception of RCS Zinc Injection)

OR take any samples from the RCS. LRM I C LXAMM/i

!flI1flM DIA vIv WBN Reactor Coolant System I SI 68 32 Unit I Water Inventory Balance 7?V. 0014 Pagellof32 Data Package: Page Date TODAY 4.3 Field Preparations (continued)

RECORD as-found position of the following valves and handswitches, AND PLACE the following valves and handswitches in their required position.

AS-FOUND REQUIRED VALVE DESCRIPTION POSITION POSITION I NITIALS 1-LCV-77-415 RCDT DRAIN LEVEL CONTROL CLOSED CLOSED LRM 1-HS-62-118A LETDOWN DIVERT TO HUT VCT VCT LRM 1-FCV-62-128 BA BLENDER TO VCT INLET P-AUTO CLOSED LRM CLOSED MAKEUP INJECTION VLV FLOW P-AUTO 1-FCV--62-144 CLOSED CLOSED CONTROL LRM EMERGENCY BORATION FLOW 1-FCV-62-138 CLOSED CLOSED CONTROL VALVE LRM ESTABLISH communications between test performer in the Main Control Room and test performer stationed at 1-LI-77-1

[O-PNL-276-L2, EL 692, COL A8-S]. LRM XAM AATLRAL

1*

WBN Reactor Coolant System j1-Sl-68-32 Unit 1 Water Inventory Balance Rev. 0014 Pagel2of32 Data Package: Page Date 5.0 ACCEPTANCE CRITERIA A. Technical Specification acceptance criteria for RCS leakage is shown below:

1. No pressure boundary leakage.

NOTE Negative unidentified leakage may be considered acceptable if at least one hour of additional data is collected and unidentified leakage is more positive than -0.10 gpm OR total leakage is less than or equal to 1.0 gpm.

3

2. 1 gpm unidentified leakage.

3. 10 gpm identified leakage.

B. If Acceptance Criteria stated above is NOT met, the SRO is to be notified as soon as possible that LCO 3.4.13 may be applicable and an investigation into the source of leakage is to be initiated.

JR YAM MAI ERIAL

AflI1IM PIi1 WBN Reactor Coolant System 1-Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page 13 of 32 Data Package: Page Date TODAY 6.0 PERFORMANCE ENSURE precautions and limitations in Section 3.0 have been reviewed. LAM

? ENSURE prerequisite actions in Section 4.0 have been met. LAM ENSURE reactor power and RCS temperature are stable and have varied less than the limits shown below during the last 30 minutes:

PARAMETER VARIATION LIMITS Reactor power +/- 1.0%

M de &2 Tavg +/-0.3°F Mode 3 & 4 Thot +/- 0.3°F LAM RCS parameters must remain stable during performance of remaining steps in this Section.

IF Plant Computer Program RCSWIB is unavailable, THEN MARK Steps 6.0[5] through 6.0[18] in this Section NIA, AND PERFORM Appendix A. LRM N

I4&

Values displayed on the computer screen are color coded to indicate QUALITY of the data point. Values that appear BLUE are BAD QUALITY (NOT reliable). Final readings will appear BLUE until computed.

Step 6.0[1 1] provides action to be taken when a data point has BAD QUALITY. This action should be taken anytime (during this SI) a data point has BAD QUALITY.

DISPLAY Plant Computer Program RCSWIB screen using the RCSWIB TURN ON Code (TOC) OR the BOP menu touch screen N/A I Ifr XAM MATERA

WBN AMTNJRM-KEY Reactor Coolant System 1-SI-68-32 Unit I Water Inventory Balance Rev. 0014 Page 14 of 32 Data Package: Page Date TODAY 6.0 PERFORMANCE (continued)

N Steps 6.O[6}and 6.O[7]wilI clear the RCSWIB program to allow a new performance to be started with Step 6.O[8]

IF RCSWIB prompt says READY FOR FINAL READINGS?

(YIN), THEN ENTER Y, AND, when prompted, ENTER RCDT level (%) from 1-LI-77-1 [O-PNL-276-L2]. N/A IF RCSWIB prompt says PRINT

SUMMARY

SHEET/DATA PACKAGE? (Y/N), THEN ENTER N. N/A IF RCSWIB prompt says START OR CONTINUE CALC.?

(S/C), THEN ENTERS. N/A ENTER Steam Generator leakage (gpm) from Section 4.1[6}. N/A ENTER RCDT level (%) from 1-LI-77-1 [O-PNL-276-L2]. N/A IF any value shown on the computer display is BLUE, THEN MARK remaining steps in this Section NIA, AND PERFORM Appendix A, OR SELECT another data point associated with the parameter in question, THEN REPLACE the BAD QUALITY data point using the substitute value function on the single point menu screen prior to initiating and finalizing the RCSWIB program, AND EXPLAIN in Remarks Section of Surveillance Task Sheet. N/A XAM 1AATFRIA

WBN -Sl-68-32 Unft 1 Water Inventory Balance Rev. 0014 Data Package: Page Date TODAY 60 PERFORMANCE (continued)

The RCSWIB prompt READY FOR FINAL READINGS? (YIN) will display at the top of the screen until Y is entered. Operators may exit the program to perform other tasks and return to this prompt by starting RCSWIB program as described in Step 6.O[5]. All data is retained and the programs clock keeps track of elapsed time WAIT at least one hour (optimum time is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) N/A ENSURE RCSWIB prompt says READY FOR FINAL READINGS? (YIN), AND ENTERY. N/A After RCDT level is entered, the RCSWIB program collects values from additional data points and calculates Total Leakage, Identified Leakage, and Unidentified Leakage.

ENTER RCDT level (%) from 1-LI-77-1, [O-PNL-276-L2]. N/A IF UNIDENTIFIED LEAKAGE is less than 0 gpm (negative

, THEN 3

leakage)

I I ENSURE RCSWIB prompt says PRINT

SUMMARY

SHEET/DATA PACKAGE? (Y/N), AND ENTER N. N/A WHEN RCSWIB prompt says START OR CONTINUE CALC.? (S/C), THEN ENTER C. N/A WAIT at least one hour from the last time data was collected. N/A ENSURE RCSWIB prompt says READY FOR FINAL READINGS?, (Y/N), AND ENTERY. N/A ENTER RCDT level (%) from l-LI-77-l, [0-PNL-276-L2]. N/A AL I IA

WBN ADM[N Reactor Coolant 68-32 Unit 1 Water Inventory Balance 0014 Page 16 of 32 Data Package: Page Date TODAY 6.0 PERFORMANCE (continued)

REPEAT Steps 6.0[15.1] through 6.0[15.5] UNTIL one of the following conditions exists:

A. UNIDENTIFIED LEAKAGE is more positive than

-0.10 gpm.

B. TOTAL LEAKAGE is less than or equal to 1.0 gpm.

C. SI is aborted because A or B above cannot be met before plant conditions, e.g. makeup to VCT or pump down of RCDT, require action that would invalidate test results. N/A IF SI is aborted per Step 6.0[15.6]C, THEN NOTIFY UNIT SRO and/or cognizant System Engineer that an investigation to determine the source of inleakage to the RCS must be initiated.

3 N/A ENSURE RCSWIB prompt says PRINT

SUMMARY

SHEET/DATA PACKAGE? (YIN), AND ENTERY. N/A PRESS ENTER to obtain printout at default printer. N/A ATTACH printout to the data package of this SI. N/A

[19] IF UNIDENTIFIED LEAKAGE is greater than I gpm, THEN NOTIFY UNIT SRO and/or cognizant System Engineer that an investigation to determine any miscellaneous identified leakage (i.e., other than leakage to the PRT, RCDT or SG tube leakage) from the RCS must be initiated.

[20] IF MISCELLANEOUS IDENTIFIED LEAKAGE is found and determined to cause failure of the SI, THEN RECORD the source and amount of MISCELLANEOUS IDENTIFIED LEAKAGE on the computer printout/data sheet.

[21] VERIFY Acceptance Criteria is met.

NrLXAM AA1RAI

LkflrAM 1PM L(V fTVUUF V WBN Reactor Coolant System I -SI-68-32 Unit 1 Water Inventory Balance Rev. 0014 Page 17 of 32 Data Package: Page Date 7.0 POST PERFORMANCE ACTIVITIES

[1] RETURN the following valves and handswitches to their as-found position listed in Step 4.3[5], AND VERIFY valve and handswitch position:

VALVE DESCRIPTION INITIALS IV 1-LCV-77-415 RCDT DRAIN LEVEL CONTROL N/A 1 -HS-62-1 1 8A LETDOWN DIVERT TO HUT 1-FCV-62-128 BA BLENDER TO VCT INLET N/A MAKEUP INJECTION VLV FLOW I FCV 62 144

-

N/A

- CONTROL EMERGENCY BORATION FLOW 1 FCV 62 138

- CONTROL VALVE

[2] PLACE the following handswitches in their as-found position listed in Section 4.3[3]:

HANDSWITCH DESCRIPTION AS-FOUND POSITION INITIALS 1-HS-77-4A REACT COOLANT DR TK PUMP A 1-HS-77-6A RCDT PUMP B

[3] RECORD completion time and date on Surveillance Task Sheet.

[4] NOTIFY SM/UNIT SRO that this SI is complete.

X\A MA CRIAL

WBN AD-M1-N-J RM-KEY Reactor Coolant System 1-Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page 18 of 32 8.0 RECORDS 8.1 QA Records The Data Package is a QA record, is handled in accordance with the Document Control and Records Management Program, and contains the following:

A. Completed parts of Sections 4.0, 6.0 and 7.0.

B. Section 5.0.

C. Completed Appendixes A and B.

D. Surveillance Task Sheet.

E. Other sheets added during the performance.

8.2 Non-QA Records None PC F XAM M/IEhJAI

WBN ADM[N-JRM-KEY Reactor Coolant System l-Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page 19 of 32 Appendix A (Page 1 of 2)

Manual Performance of RCS Water Inventory Balance Data Package: Page Date TODAY 1.0 MANUAL PERFORMANCE OF RCS WATER INVENTORY BALANCE OBTAIN controlled copy of TI-4, Part II pages that show graphs of volume vs. indicated level for Pressurizer Relief Tank (PRT) and Reactor Coolant Drain Tank (RCDT). LRM RECORD initial RCS data per Appendix B. LRM WAIT at least one hour (optimum is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />). LRM RECORD another set of RCS data per Appendix B. LRM CALCULATE RCS leakage per Appendix C. 4 NOTE Additional copies of Appendix C may be used to perform independent verification.

[6] PERFORM independent verification of Appendix C.

lv

[7] IF unidentified leakage is less than 0 gpm (negative leakage)

,

3 THEN

[7.1] WAIT at least one hour from the last time data was collected.

[7.2] RECORD another set of RCS data per Appendix B.

[7.3] CALCULATE RCS leakage per Appendix C. 4

[7.4] PERFORM independent verification of Appendix C.

IV

[7.5] REPEAT Steps 1.0[7.1] through 1.0[7.5] UNTIL one of the following conditions exists:

A. Unidentified leakage rate is more positive than

-0.10 gpm.

B. Total RCS leakage is less than or equal to 1.0 gpm.

EXAM M/V MAL

I WBN 6832 ADM[N-JRMKX Reactor Coolant System Unit I Water Inventory Balance Rev. 0014 Page2Oof32 Appendix A (Page2of2)

Data Package: Page Date 1.0 MANUAL PERFORMANCE OF RCS WATER INVENTORY BALANCE (continued)

C. SI is aborted because A or B above cannot be met before plant conditions (e.g. makeup to VCT, pump down of RCDT) require action that would invalidate test results.

[7.6] IF SI is aborted per Stepi .O[7.5]C THEN

,

NOTIFY SM/Unit SRO and br cognizant System Engineer that an investigation to determine the source of inleakage to the RCS must be initiated.

3

[8] GO TO Step 6.O[19}.

XAM rAA1:RI\I

WBN Reactor Coolant System 1-Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page 21 of 32 Appendix B (Page 1 of 3)

RCS Water Inventory Balance Data Sheet Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE DATA SHEET NOTES

1) Time for each data set is the time of day when the first instrument is read. Recording each data set as quickly as possible will ensure an accurate relationship between parameters. Additional copies of Appendix A may be used as required.

2) Only one instrument should be used for each parameter and the same instrument must be used for each data set. Instruments NOT used should be marked NIA for each data set.

2nd 3rd 4th 5th PARAMETER INSTRUMENT [PANEL] INITIAL DATA SET DATA SET DATA SET DATA SET DATA SET TIME N/A 1800 1900 LO112A 40  % 36.8  %  %  %  %

VCT LEVEL 1-LI-62-129A [1-M-6] N/A  % N/A  %  %  %  %

1-PI-68-342A < 1700 psi N/A psig N/A psig psig psig psig 1-PI-68-340A[1-M-5] N/A psig N/A psig psig psig psig P0480A 2235.3 psig 2235.3 psig psig psig psig PRESSURIZER 1-PR-68-340 [1-M-5] N/A psig N/A psig psig psig psig PRESSURE P0481A N/A psig N/A psig psig psig psig 1-PI-68-322 [1-M-5] N/A psig N/A psig psig psig psig P0483A N/A psig N/A psig psig psig psig

WBN Reactor Coolant System 1-Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page 22 of 32 Appendix B (Page 2 of 3)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE DATA SHEET (continued) 2nd 3rd 4th 5th PARAMETER INSTRUMENT [PANEL] INITIAL DATA SET DATA SET DATA SET DATA SET DATA SET 1-LI-68-321 < 350°F N/A  % N/A  %  %  %  %

1-LI-68-320 [1-M-4j N/A N/A  %  %  %  %

L0482A 60.25  % 58.0  %  %  %  %

PRESSURIZER N/A 1-LI-68-335A [1-M-4]  % N/A  %  %  %  %

L0481A N/A  % N/A  %  %  %  %

1-LI-68-339A [1-M-4] N/A  % N/A  %  %  %  %

L0480A N/A  % N/A  %  %  %  %

1-TI-68-2E [1-M-5] N/A N/A °F °F °F °F T0439A Thot < 530°F N/A N/A °F °F °F °F T0460A 586.2 586.2 °F °F °F °F RCS TEMPERATURE T0440A N/A °F N/A °F °F °F °F T0420A N/A °F N/A °F °F °F °F TO400A N/A °F N/A °F °F °F

WBN Reactor Coolant System 1-51-68-32 Unit I Water Inventory Balance Rev. 0014 Page 23 of 32 Appendix B (Page3of3)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE DATA SHEET (continued) 2nd 3rd 4th 5th PARAMETER INSTRUMENT [PANEL] INITIAL DATA SET DATA SET DATA SET DATA SET DATA SET 1-NI-41 [1-M4] 99.5  % 99.5  %  %  %  %

REACTOR 1-NI-42 N/A  % N/A  %  %  %  %

POWER 1-NI-43 N/A  % N/A  %  %  %  %

1-NI-44 N/A  % N/A  %  %  %  %

1-LI-68-300 [1-M-4j N/A  % N/A  %  %  %  %

PRT LEVEL L0485A 59  % 59  %  %  %  %

RCDT LEVEL 1-LI-77-1 [O-PNL-276-L2] 21  % 38  %  %  %  %

DATA SET RECORDED BY LRM LRM TOTAL RCS LEAKAGE N/A (Appendix C Step 1 .O[6])

IDENTIFIED LEAKAGE (Acc Crit: <10 gpm) N/A 1.0 (Appendix C Step 1 .0[9j)

UNIDENTIFIED LEAKAGE (Acc Crit: 1 gpm) N/A 2.33 (Appendix C Step 1.0[10])

WBN ADMTN-JP-M-KEY Reactor Coolant System 1-Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Appendix C (Page 1 of 8)

RCS Water Inventory Balance Calculations Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS Throughout this Appendix, INITIAL indicates the data is to be taken from first data set recorded in Appendix B and FINAL indicates data is to be taken from the last data set recorded in Appendix B. A copy of this Appendix is required to be completed each time RCS leakage is calculated.

CALCULATE elapsed time (AT) as follows:

AT = FINAL TIME INITIAL TIME

-

AT= 1900 1800 AT = 80 mm LRM 1st cv CONVERT INITIAL and FINAL PZR PRESSURE units of measurement to psia as follows:

I PARAMETER I INITIAL I FINAL I 2235.3 psig + 14.7 = 2235.3 psig + 14.7 PZR PRESS 2250 2250 I

psia = psia LRM 1st cv i C, E X \FiI fA :RA

AflIi1IM rm-i -r ID\JI vv WBN Reactor Coolant System 1-SI-68-32 Unit I Water Inventory Balance Rev. 0014 Page 25 of 32 Appendix C (Page 2 of 8)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE VCT Leakage as follows:

(INITIAL VCT LEVEL FINAL VCT LEVEL) x 1927 gaII%

-

VCT Leakage =

AT (Step 1.0[1])

=

40  % - 36.8  %) x 19.27 gal/%

VCT Leakage 60 mm VCT Leakage = 1.03 gpm LRM 1 St CV CALCULATE Pressurizer (PZR) Leakage as follows: 4

.1 RECORD INITIAL and FINAL PZR PRESSURE in table below using values calculated in Step 1.O[2]. LRM RECORD INITIAL and FINAL PZR LEVEL in table below using values recorded in Appendix B. LRM DETERMINE and RECORD INITIAL and FINAL PZR Vf (volume of water) and Vg (volume of steam) at INITIAL and FINAL PZR PRESS (Step 1.O[2]) using ASME Steam Tables (Table 2, Properties of Saturated Steam and Saturated Water).

STEP PARAMETER INITIAL FINAL 1.0[4.1] PZR PRESS 2250 psia 2250 psia 1 .0[4.2] PZR LEVEL 60.25  % 58  %

PZR Vf 0.02698 /Ibm 3

ft 0.02698 /Ibm 3

ft 1 .0[4.3]

PZR V9 0.157 /Ibm 3

ft 0.157 /lbm 3

ft LRM MC X/ A MATERIAL

WBN w Reactor Coolant System jSI-68-32 Unitl Water Inventory Balance Rev. 0014 Page 26 of 32 Appendix C (Page3of8)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE INITIAL PZR VOLUME as follows: 4 INITIAL PZR = ((PZRLVL 100P ZRLVL))x(16.73ft 3 001605 4

.

7

)(

a 5

o l) 8

)+(

VOLUME  % 3 ft INITIAL PZR 60.25  % 100 60.25 % (2a1ft)

VOLUME )+( 0.157

- J.02698 /lbm 3

ft ft /lbm 3 %lbm INITIAL PZR = 4972.64 gallons VOLUME LRM 1st CV CALCULATE FINAL PZR VOLUME as follows: 5 FINAL PZR PZRLVL 1 00_PZRLVL))x(1 6.73ft 3

74805 )X 0.01605

)X(

VOLUME Vf Vg  % 3 ft FINAL PZR 58  % 100 58  % (2a1ft)

=(( )+

VOLUME 0.02698 ft

/lbm 3 0.157 ft/1bm %lbm FINAL PZR = 4834.51 gallons VOLUME LRM 1st CV H! XA A A1

WBN Unit I Water Inventory Balance Rev. 0014 Page 27 of 32 Appendix C (Page4of8)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE PZR Leakage as follows:

INITIAL PZR VOLUME FINAL PZR VOLUME PZR Leakage = (Stepl.O[4.4]) - (Step 1.O[4.5])

AT (Stepl.O[1])

4972.64 gallons - 4834.51 gallons PZR Leakage =

60 mm PZR Leakage 2.3 gpm LRM 1st CV IF RCS TEMP FINAL is NOT equal to RCS TEMP INITIAL ,

4 THEN RECORD INITIAL and FINAL PZR PRESSURE in table below using values calculated in Step 1 .O[2] N/A RECORD INITIAL and FINAL RCS TEMPERATURE in table below using values recorded in Appendix B. N/A DETERMINE and RECORD INITIAL and FINAL RCS SPECIFIC VOLUME in table below using PZR PRESSURE, RCS TEMPERATURE and ASME Steam Tables (Table 3, Properties of Superheated Steam and Compressed Water). N/A Hr XPM\ilA ERA

AflMM IDIA I.(V WBN Reactor Coolant System 1-Sl-68-32 Unit I Water Inventory Balance Rev. 0014 Page 28 of 32 Appendix C (Page 5of8)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE INITIAL and FINAL RCS DENSITY as follows, AND RECORD in table below:

1 RCS DENSITY =

RCS SPECIFIC VOLUME STEP PARAM INITIAL FINAL PZR 1.O[5.1j psia psia PRESS RCS 1.O[5.2] °F °F TEMP RCS 1.O[5.3] SPECIFIC /Ibm 3

ft /Ibm 3

ft VOLUME RCS 1 .O[5.4j 3 Ibm/ft 3 Ibm/ft DENSITY N/A 1st CV CALCULATE RCS Temperature Correction as follows:

(InitialRCS Density FinalRCSDensity)X 1 0902ft 3 X 7.4805 X 0.01 605--

Temp Corr = ft ibm zT (Step 1.O[1])

I ibm 1308 ga1 ibm 92 ft 3 Temp Corr = 3 ft ft3J ibm mm Temp Corr =

N/A 1st CV F

XAM FA rJ Al

WBN AMReactor Coolant System PM-KEY 1-SI-68-32 Unit I Water Inventory Balance Rev. 0014 Page 29 of 32 Appendix C (Page6of8)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE Total RCS Leakage as follows:

Total RCS Leakage = VCT Leakage (Step 1 .O[3]) +

PZR Leakage (Step [1 .O[4}) + Temp Corr (Step I .O[5] or 0)

Total RCS Leakage = 1.03 gpm + 2.3 gpm + 0 gpm Total RCS Leakage = 3.33 gpm LRM 1st CV CALCULATE Leakage to Pressurizer Relief Tank (PRT) as follows:

CONVERT INITIAL and FINAL PRT LEVEL from percent

(%) to gallons using Tl-4, Part II, AND RECORD the converted PRT LEVELS in Step I .0[7.2]. LRM CALCULATE Leakage to PRT using the following equation:

(Final PRT LVL Initial PRT LVL

Leakage to PRT = I zXT(Stepl.0[1])

8250 gallons 8250 gallons Leakage to PRT = I 60 mm Leakage to PRT = 0 gpm LRM 1st CV FXAMMK ERA

WBN 6832 Uniti Water Inventory Balance 0014 Page 30 of 32 Appendix C (Page7of8)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE Leakage to Reactor Coolant Drain Tank (RCDT) as follows:

CONVERT INITIAL and FINAL RCDT LEVEL from percent (%) to gallons using Tl-4, Part II, AND RECORD the converted RCDT LEVELS in Step 1 .O[8.2]. LRM CALCULATE Leakage to RCDT using the following equation:

Final RCDT LVL Initial RCDT LVL Leakage to RCDT

-

z\T (Step 1.O[1])

= 140 gal 80 gal Leakage to RCDT 60 mm Leakage to RCDT = 1.0 gpm LRM I at CV CALCULATE Identified Leakage as follows:

Identified Leakage = Leakage to PRT (Step 1 .O[7]) +

Leakage to RCDT (Step I .O[8]) +

Total SG Leakage (Step 4.1 [6]

Identified Leakage = 0 gpm + 1.0 gpm + 0 gpm Identified Leakage = 1.0 gpm LRM 1st CV I XAM MAERIA

WBN A-DN-[N-J P M-Reactor Coolant System Sl-68-32 1

Unit I Water Inventory Balance Rev. 0014 Page 31 of 32 Appendix C (Page8of8)

Data Package: Page Date TODAY 1.0 RCS WATER INVENTORY BALANCE CALCULATIONS (continued)

CALCULATE Unidentified Leakage as follows:

Unidentified Leakage = Total RCS Leakage (Step 1 .O[6]) -

Identified Leakage (Step I .O[9J)

Unidentified Leakage = 3.33 gpm - 10 gpm Unidentified Leakage = 2.33 gpm LRM I St cv The value of Total RCS Leakage recorded in Appendix B by the following step should conservatively be set equal to the value of Unidentified Leakage IF the value of Identified Leakage is negative AND there is a well-understood reason for the negative value of Identified Leakage. Such a situation could arise if there is known external leakage from the PRT and/or the RCDT which is causing a corresponding decrease in tank level (i.e., tank out-leakage). A notation should be added to Appendix B if the value of Total RCS Leakage is set equal to Unidentified Leakage based on the reasoning in this NOTE.

RECORD Total RCS Leakage (Step I .O[6]), Identified Leakage (Step I.O[9]) and Unidentified Leakage (Stepl.O[1O]) on Appendix B in the last column that data is recorded. LRM XA u1A1EIAI

WBN tor Coolant System 68-32 Uniti 0014 32 of 32 Source Notes (Page 1 ofl)

Implementing Requirements Statement Source Document Statement Primary to Secondary leakage is NCO 850404138 limited to I gpm. [Reference to this Watts Bar SER (NUREG-0847) source note on page 13 is deleted by Pages 15-18 Revision 8, which incorporates Tech Spec Change WBN-TS-99-0 14.]

A water inventory balance must be NCO 850404025 2 performed within one hour of receiving Watts Bar SER (NUREG-0847) an alarm and confirming leakage in a Pages 5-7 flow path with no indicators.

Steps to take when negative NRC Inspection Report 50-327 3 unidentified leakage is calculated. NOV 50-327, 328/89-16-02 RCS leakage should NOT be NRC Inspection Report 50-3901F1 4 measured using the reactor sump. 390/85-22-01 Correction factors for PZR level need to be traceable. RCS temperature correction factor must be calculated for any change in initial and final RCS temperature.

The pressurizer (PZR) mass volume WBPER9600I7 5 (initial and final) should be obtained by adding the vapor space volume and the liquid space volume together.

XAV1 MM rAL

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

CONDITIONS:

1. Unit I is in Mode I at 100% power.

2. I-SI-68-32, Reactor Coolant System Water Inventory Balance, performance is required.

3. The ICS Computer program RCSWIB is unreliable.

4. 1-Sl-68-32 Appendix A, Manual Performance of RCS Water Inventory Balance, has been completed through step 4.

5. An initial data set was entered at 1800 and a second data set was entered at 1900 on 1-Sl-68-32 Appendix B, RCS Water Inventory Balance Data Sheet.

6. You are an extra operator assigned to the shift.

INITIATING CUES:

3. The Unit SRO has directed you to complete 1-Sl-68-32, Appendix C, RCS WATER INVENTORY BALANCE CALCULATIONS using the data provided.

4. Report the results of the surveillance to the Unit SRO.

A.2 RO

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

INITIAL CONDITIONS:

1. Unit I is in Mode I at 100% power.

2. 1-SI-68-32, Reactor Coolant System Water Inventory Balance, performance is required.

3. The ICS Computer program RCSWIB is unreliable.

4. 1-SI-68-32 Appendix A, Manual Performance of RCS Water Inventory Balance, has been completed through step 4.

5. An initial data set was entered at 1800 and a second data set was entered at 1900 on 1-Sl-68-32 Appendix B, RCS Water Inventory Balance Data Sheet

6. You are an extra operator assigned to the shift.

INITIATING CUES:

1. The Unit SRO has directed you to complete I-S1-68-32, Appendix C, RCS WATER INVENTORY BALANCE CALCULATIONS, using the data provided.

2. After completion of 1-SI-68-32, Appendix C, RCS WATER INVENTORY BALANCE CALCULATIONS, report your results to the Unit SRO.

A.2 RO

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 2011-10 NRC Exam A.3 Determine Potential Total Dose for Valve Alignment.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 2011-10 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 K/A 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 determines total dose which an individual would receive while aligning 1-FCV-63-11 to be 361 -364 mrem. When added to the total dose received for the year, the applicant states that the administrative dose limit 1000 mrem) will be exceeded.

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

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 2011-10 NRC Exam ENSURE the applicant has a copy of the survey map for elevation 713 areas of interest.

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. 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.

PAflF OF lfl

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 2011-10 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: (TOmr to 8.Omr)

Pen Room to STEP (l2OmrIhr)(O.5min)(hrI6Omin) 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: (8lmrto 82mr)

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

Step is critical to avoid exceeding dose limits.

COMMENTS:

PAGE 4 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 2011-10 NRC Exam EXAMINER: Some rounding of numbers is allowed as long as the examinee follows

sound mathematical standards. The acceptable total range is 361 to 364 mrem.

STEP 2: Calculate the total exposure received while performing the CRITICAL task. STEP STANDARD: SAT Individual doses received are added up. UNSAT 7.92 mr + 2 mr + 75 mr + 90 mr + 81.67 mr + 106.67 mr = 363.26 mr.

Rounding values:

Low: 7.0 + 2 + 75 + 90 + 81 + 106.0 = 361 mr High: 8 + 2+75 + 90 + 82 + 107 = 364 mr Acceptable Range 361 - - 364 mrem Step is critical to avoid exceeding dose limits.

COMMENTS:

PAGE 5 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.3 2011-10 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) + 363.26 mr (total dose for this job) = 1063.26 m rem.

Acceptable range of answer 1061 mrem to 1064 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 361 to 364 mrem. Total is 1061 to 1064 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 6 OF 10

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.

• 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: 70 8.0 mr

-

Pen Room to STEP (l2Omr/hr)(0.5min)(2hr/60min) x 2(trips) 2 mr OFF PAD and back Range: N/A Hot Spot and back (2700mr/hr)(50sec)(min/60sec)(hr/6Omin) 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 Total 363.26 mr Range: 361 - 364 mr Accept 360 to 364 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 1061 1064 mrem).

-

PAGE 7 OF 10

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

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.

A.3

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

SURVEY DATA:

• I -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.

• General Area Dose rates are listed on the survey map.

RESULTS:

A.3

APPLICANT DATA SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) general area 4:

1-44 1000 mr/hr general area 120 mr/hr 1 general area A /8 1-FCV-63-8 350 mr;hr 1-FCV-63-1 1

• 1-FCV-72-40 2700 mr/hr 900 mr/hr general area 320 mr/hr Hot Spot general area general area Li Sora,, inJ ,4qA

.:

270

/

Q y, COflffo/

U t No. 4

\.

A.3

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 2011-10 NRC Exam A.4 Determine if conditions warrant a Follow-up Report or Upgrade based on changing conditions.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 2011-10 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-JPMSO81A Safety Function: n/a

Title:

2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.

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

References:

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

EPIP-3 ALERT, Rev. 33.

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.4 2011-10 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:

TREAT THIS AS A RADIOLOGICAL EMERGENCY DRILL

1. A Drill is being conducted during which 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 failed to reclose.

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.

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 to make notifications to appropriate personnel.

3. This JPM contains time critical elements.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 2011-10 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 pCi/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 S/G 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 4 OF 6

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A.4 2011-10 NRC Exam STEPISTANDARD I SAT/UNSAT 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 Appendix B .PROTECTIVE ACTION RECOMMENDATIONS, flowchart and determines Recommendation 2 is required.

Applicant completes Appendix A, TVA Initial Notification Form For Site Area Emergency, within 10 minutes after the declaration is made.

Critical elements that must appear on Appendix A form:

Item I - Marked as a Drill Item 3- EAL Designators 1.1.2 L, 1.23 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 I, 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 5 OF 6

WBN Emergency Plan Classification Logic EPIP-1 UnitO Rev. 0035 PagelOof5l Attachment I (Page 1 of 4)

Fission Product Barrier Matrix (Modes 1-4)

FISSION PRODUCT BARRIER MATRIX (Modes 1-4) 1.1 Fuel Clad 1.2 RCS 1.3 Containment SYSTEM DEGRADATION 2.1 Loss of Instrumentation 2.6 RCS Identified Leakage 2.2 Loss of Function/Communication 2.7 Uncontrolled Cool Down 2.3 Failure of Reactor Protection 2.8 Turbine Failure 2.4 Fuel Clad Degradation 2.9 Technical Specification 2.5 RCS Unidentified Leakage 2.10 Safety Limit LOSS OF POWER 3.1 Loss of AC (Power Ops) 3.2 Loss of AC (Shutdown) 3.3 Loss of DC HAZARDS and SED JUDGMENT 4.1 Fire 4.3 Flammable Gas 4.5 Control Room 4.2 Explosion 4.4 Toxic Gas Evacuation Table 4-1 Table 4-2 4.6 Security Figure 4-A Figure 4-B 4.7 SED Judgment DESTRUCTIVE PHENOMENON 5.1 Earthquake 5.4 River Level High 5.2 Tornado 5.5 River Level Low 5.3 Aircraft/Projectile 5.6 Watercraft Crash Crash Figure 5-A Table 5-1 SHUTDOWN SYSTEM DEGRADATION 6.1 Loss of Shutdown Systems 6.2 Loss of AC (Shutdown) 6.3 Loss of DC (Shutdown)

RADIOLOGICAL 7.1 Gaseous Effluent 7.3 Radiation Levels 7.2 Liquid Effluent 7.4 Fuel Handling Table 7-1 Table 7-2 Figure 7-A

WBN Emergency Plan Classification Logic EPIP-1 Unit 0 Rev. 0035 Page 11 of5l Attachment I (Page 2 of 4)

UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY and GENERAL INTRUSIONIINTRUDER: Suspected hostile individual present in a protected EMERGENCY: (see SED Judgment 4.7). area without authorization.

BOMB: An explosive device (See EXPLOSION). ODCM: Offsite Dose Calculation Manual.

CIVIL DISTURBANCE: A group of twenty (20) or more persons violently ORANGE PATH: Monitoring of one or more CSF5 by FR-0 which indicates protesting station operations or activities at the site. that the CSF(s) is under severe challenge.

CREDIBLE SITE-SPECIFIC -The determination is made by WBN senior plant PROJECTILE: An Object ejected, thrown, or launched towards a plant management through use of information found in the Safeguards structure. The source of the projectile may be onsite or offsite. Damage is Contingency Plan. sufficient to cause concern regarding the integrity of the affected structure or the operability or reliability of safety equipment contained therein.

CRITICAL-SAFETY FUNCTION (CSFs): A plant safety function required to prevent significant release of core radioactivity to the environment. There are PROTECTED AREA: Encompasses all owner controlled areas within the six CSF5: Sub-criticality, Core Cooling, Heat Sink, Pressurized Thermal security protected area fence as shown on Figure 4-A.

Shock, Integrity (Containment) and Inventory (RCS).

RED PATH: Monitoring of one or more CSF5 by the FR-0 which indicates EVENT: Assessment of an EVENT commences when recognition is made that the CSF(s) is under extreme challenge; prompt operator action is that one or more of the conditions associated with the event exist. Implicit in required.

this definition is the need for timely assessment, i.e. within 15 minutes.

RUPTURED: (Steam Generator) Existence of primary to secondary leakage EXCLUSION AREA BOUNDARY (EAB): The demarcation of the area of a magnitude greater than charging pump capacity.

surrounding the WBN units in which postulated FSAR accidents will not result in population doses exceeding the criteria of 10 CFR Part 100. Refer to SABOTAGE: Deliberate damage, misalignment, or mis-operation of plant equipment with the intent to render the equipment inoperable.

Figure 7-A.

EXPLOSION: A rapid, violent, unconfined combustion or a catastrophic SECURITY CONDITION- Any Security Event as listed in the approved security contingency plan that constitutes a threat/compromise to site failure of pressurized equipment that potentially imparts significant energy to security, threat/risk to site personnel, or a potential degradation to the level of near-by structures and materials.

safety of the plant. A SECURITY CONDITION does not involve a HOSTILE EXTORTION: An attempt to cause an action at the station by threat of force. ACTION.

FAULTED: (Steam Generator) Existence of secondary side leakage (i.e., SIGNIFICANT TRANSIENT: An UNPLANNED event involving one or more steam or feed line break) that results in an uncontrolled decrease in steam ofthefollowing: (1)Anautomaticturbine runback> 15%thermal reactor generator pressure or the steam generator being completely depressurized. power; (2) Electrical load rejection > 25% full electrical load; (3) Reactor Trip or (4) Safety Injection System Activation.

FIRE: Combustion characterized by heat and light. Source of smoke such as slipping drive belts or overheated electrical components do not SITE PERIMETER: Encompasses all owner controlled areas in the constitute fires, Observation of flame is preferred but is NOT required if large immediate site environs as shown on Figures 4-A and 7-A.

quantities of smoke and heat are observed.

STRIKE ACTION: A work stoppage within the PROTECTED AREA by a FLAMMABLE GAS: Combustible gases maintained at concentrations less body of workers to enforce compliance with demands made on TVA. The than the LOWER EXPLOSIVE LIMIT (LEL) will not explode due to ignition. STRIKE ACTION must threaten to interrupt normal plant operations.

HOSTAGE: A person(s) held as leverage against the station to ensure that TOXIC GAS: A gas that is dangerous to life or limb by reason of inhalation or demands will be met by the station. skin contact (e.g., chlorine),

HOSTILE ACTION: An act toward a nuclear power plant or its personnel that UNPLANNED: An event or action that is not the expected result of normal includes the use of violent force to destroy equipment, take hostages, and/or operations, testing, or maintenance. Events that result in corrective or intimidates the licensee to achieve an end. This includes attack by air, land, mitigative actions being taken in accordance with abnormal or emergency or water; using guns, explosives, projectiles, vehicles, or other devices used procedures are UNPLANNED.

to deliver destructive force. Other acts that satisfy the overall intent may be included. HOSTILE ACTION should NOT be construed to include acts of civil UNPLANNED: (With specific regard to radioactivity releases) A release of radioactivity is UNPLANNED if the release has not been authorized by a disobedience or felonious acts that are not part of a concerted attack on the Discharge Permit (DP). Implicit in this definition are unintentional releases, nuclear power plant. Non-terrorism-based EAL5 should be used to address unmonitored releases, or planned releases that exceed a condition specified such activities, (e.g., violent acts between individuals in the owner controlled on the DP, e.g., alarm setpoints, minimum dilution flow, minimum release area.)

times, maximum release rates, and/or discharge of incorrect tank.

HOSTILE FORCE: Individual(s) involved with a HOSTILE ACTION. One or more individuals who are engaged in a determined assault, overtly or by VALID: An indication or report or condition is considered to be VALID when it stealth and deception, equipped with suitable weapons capable of killing, is conclusively verified by (1) an instrument channel check, or (2) indications on related or redundant indicators, or (3) by direct observation by plant maiming, or causing destruction.

personnel. Implicit in this definition is the need for timely assessment, i.e.,

INEFFECTIVE: The specified restoration action(s) does not result in a within 15 minutes.

reduction in the level of severity of the RED PATH condition within 15 minutes from identification of the Core Cooling CSF Status Tree RED PATH. VISIBLE DAMAGE: Damage to equipment that is readily observable without A reduction in the level of severity is an improvement in the applicable measurements, testing, or analyses. Damage is sufficient enough to cause concern regarding the continued operability or reliability of affected safety parameters, e.g., Increasing Trend in Reactor Vessel Water Level (Full RVLIS) and/or Decreasing Trend on Core Thermocouple Temperatures. structure, system, or component. Example damage includes: deformation due to heat or impact, denting, penetration, rupture, cracking, and/or paint INITIATING CONDITIONS: Plant Parameters, radiation monitor readings or blistering. Surface blemishes (e.g., paint chipping, scratches) should NOT be personnel observations that identify an Event for purposes of Emergency included.

Plan Classification.

VITAL AREA: Is any area within the PROTECTED AREA which contains equipment, systems, devices, or material, the failure, destruction, or release of which could directly or indirectly endanger the public health and safety by exposure to radiation.

WBN Emergency Plan Classification Logic EPIP-1 UnitO Rev. 0035 Page 12 of 51 Attachment I (Page 3 of 4)

I. Critical Safety Function Status 1. Critical Safety Function Status

.)* Potential LOSS I** Potential LOSS Core Cooling Red (FR-Cl) Core Cooling Orange Not Applicable Pressurized Thermal Shock (FR-C.2) Red (FR-P.1)

OR OR Heat Sink Red (FR-Hi) Heat Sink Red (FR-Hi)

(RHR Not in Service) (RHR Not in Service)

-OR -OR

2. PrimaJQQlar Activity Level 2. RCS LeakE /LOCA I. Potential LOSS LOSS Potential LOSS RCS sample activity is applicable RCS Leak results in Loss of Non Isolatable RCS Leak Greater Than 300 pCi/gm subcooling (<65°F Exceeding The Capacity of dose equivalent iodine-131 Indicated), [85°F ADV] One Charging Pump (CCP)

(

In the Normal Charging Alignment.

OR RCS Leakage Results In Entry Into E-i

-OR- -OR-inrnr Tfl I-li ()ii1 Avr 3. Stea or Tube Rupture LOSS Potential LOSS

• Potential LOSS Greater Than 1200°F Greater Than 727°F 7 SGTR that results in a ot Applicable safety injection actuation OR Entry into E-3

-OR- ------ -OR

4. Reactor Vessel Water Level 4. Reactor Vessel Water Level

.}* Potential LOSS I1* Potential LOSS Not Applicable VALID RVLIS level <33% VALID RVLIS level <33% Not Applicable (No RCP running) (No RCP Running)

-OR-

5. Containment Radiation Monitors LOSS Potential_LOSS VALID reading increase of Not Applicable Greater Than:

293 R/hr On i-RM-90-271 -OR-and 272 OR 261 R/hr On i-RM-90-273 and 274 (see instruction note 5)

-OR-

6. Site Emergency Director Judgment 5. Site Emergency Director Judgment Any condition that, in the Judgment of the SM/SED, Any condition that, in the Judgment of the SM/SED, Indicates Loss or Potential Loss of the Fuel Clad Barrier Indicates Loss or Potential Loss of the RCS Barrier Comoarable to the Conditions Listed Above. Comoarable to the Conditions Listed Above.

WBN Emergency Plan Classification Logic EPIP-1 UnitO Rev. 0035 Page 13 of 51 Attachment I (Page4of4) 1.3._ CNTMT Barrier Modes: 1,2,3,4 I 1. Critical SafE Function Status INSTRUCTIONS LOSS Potential LOSS NOTE:

Not Applicable Containment (FR-Z.1) Red A condition is considered to be MET if; in the OR judgment of the Site Emergency Director the Actions of FR-C.1 (Red condition will be MET imminently (i.e., within Ito Path) are INEFFECTIVE 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in the absence of a viable success path).

S (i.e.: core TCs trending up) The classification shall be made a soon as this determination is made.

-OR- 1. In the matrix to the left, review the INITIATING 0

2. Containment Pressure/Hydrogen CONDITIONS in all columns and identify which, N if any, INITIATING CONDITIONS are MET.

y.1* Potential LOSS Circle these CONDITIONS. P Rapid unexplained Containment Hydrogen 2. For each of the three barriers, identify if any R decrease following initial Increases to >4% by LOSS or Potential LOSS INITIATING 0 increase volume CONDITIONS have been MET. D 2 3. If a CSF is listed as an INITIATING U Containment pressure or Pressure >2.8 PSIG CONDITION; the respective status tree criteria C Sump level Not increasing (Phase B) with < One full will be monitored and used to determine the T (with LOCA in progress) train of Containment spray EVENT classification for the Modes listed on the

-OR- B classification flowchart.

A

3. Containment Isolation Status 4. Compare the barrier losses and potential losses R

I.* Potential LOSS to the EVENTS below and make the appropriate R

declaration.

Containment Isolation is Not Applicable

5. Containment High Range Radiation Monitors Incomplete (when required) E (HRRM5) are temperature sensitive and can be AND a Release Path to the R affected by both temperature induced currents Environment Exists and insulation resistance temperature effects. M

-OR- Following the initial increase in containment A

4. Containment Bypass temperature the HRRM monitors can give T 1 Potential LOSS erratic indication for up to 1 minute. Steady R RUPTURED S/G is also Unexplained VALID state temperature effects on cable insulation resistance for the HRRM signal cable is

(

FAULTED outside CNTMT i,crease in area or x OR vntilation RAD monitors in dependent on containment temperature and could result in a shift in monitor output U Prolonged (>4 Hours) afras adjacent to CNTMT I Secondary Side release (pith LOCA in progress) indication. With a containment excursion temperature to 327 °F (HELB), the output of outside CNTMT from a S/G / the HRRMs could potentially have up to a 25 with a SGTL > T/S Limits /

R/hr indicated offset for duration of 10 minutes

-OR-until the containment air return fans are started

5. Signi can adioactivity in Containment and temperature starts to reduce. (Caution:

Potential LOSS Should the containment air return fans not Not Applicable VALID Reading increase of start, containment temperatures could Greater Than: remain elevated resulting in potential 5290 R/hr on l-RM-90-271 false HRRM indicated readings).

and 1-RM-90-272 EVENTS OR UNUSUAL EVENT ALERT 4710 R/hron 1-RM-90-273 Loss or Potential LOSS of Any LOSS or Potential and 1-RM-90-274 Containment Barrier LOSS of Fuel Clad barrier OR (see instruction note 5) Any LOSS or Potential

-OR- LOSS of RCS barrier

6. Site Emergency Director Judgment Any condition that, in the Judgment of the SM/SED, SITE AREA Indicates Loss or Potential Loss of the CNTMT Barrier LOSS or Potential LOSS q( LOSS of any two barriers \

Comparable to the Conditions Listed Above. any two barriers aridPotPotential LOSS,!

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

TVA Initial Notification Form For General Emergency CRITICAL Event Repeat This is an Actual Event

- -

rhisisSED atts Bar has declared a GENERAL EMERGENCY affecting Unit I CRITICAL EAL Designator(s): 1.1.2 L(OSS) / 1.2.3 L(OSS) I 1.3.4 L(OSS)

CRITICAL Brief Description of the Event: Concurrent with a 100 pm SG tube rupture on SG 1, RCS Activity is 340 microcurries/gram dose equivalent 1-131, and a SG 1 safety valve is failed open.

Radiological Conditions: (Check one under both Airborne and Liquid column.)

Airborne Releases Offsite Liquid Releases Offsite

)( Minor releases within federally approved limits D Releases above federally approved limits 1 1 )E( Minor releases within federally approved limits D Releases above federally approved limits 1 1

)(Tech Release information not known J2 Release information not known j Specs) ( Tech Specs)

CRITICAL Event Declared: Time: TIME Date: TODAY

, The Meteorological Conditions are: (Use 46 meter data from the Met Tower)

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

D Recommendation 1

• WIND FROM °

• Recommendation 2 EVACUATE LISTED SECTORS P (Mark) R VACUATE 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.

CONSlDER issuance of Potassium Iodide CONSlDER issuance of Potassium in accordance with the State Plan. I 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, A-i, B-i, C-i, D-i,

><

A-3, -4, D-2, -3, -4, -5, -6, -7, -8, -9 A-3, D-2, -4, -5 Ai, Bi, Ci, D1, 111170 Ai, Bi, CI, Di, 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, 171-230 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, 231-270 A-i, B-i, C-i, D-l, B-2, -3, -4, -5, C-2, -3, B-2, -4, C-2 A-lB-iC-iD-i, 271-325 A-i, B-i, C-i, D-i, B-2,-3,C-2,-3,-4,-5,-6,-ll 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 D Recommendation 3

• SHELTER all sectors. CONSIDER issuance of Potassium Iodide in accordance with the State Plan.

cAX this form to CECC Director at 5-751-1 682 or ODS at 5-751-8620 or TEMA at 9-1-615-242-9635.

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

WBN General Emergency EPIP-5 UnitO Rev. 0038 Page 18 of 21 Appendix B (Page 1 of 1)

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

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

EMERGEN DEREDP CONTINUE ASSESSMENT

} Modify protective actions based on available

] plant and field monitoring information.

Locate and evaluate localized hot spots.

Is there a short term controlled release whereas near NO plant areas cannot be evacuated before plume arrival?

(see Note 2) At or beyond he t

Zes,is YES / Projected OR N( NO)

S Measured Dose greater than Table 1 limits?

RECOMMENDATION 3 1ZeEPZ RECOMMENDATION I ,/RECOMMENDATION 2 EVACUATE 2 miles radius EVACUATE 2 miles radius and 10 miles downwind and 5 miles downwind AND AND SHELTER remainder of \ SHELTER remainder of /

10 mile EPZ 10 mile EPZ I

TABLE I Protective Action Guides (PAG)

TYPE LIMIT Measured 3.9 E-6 micro Ci/co of Iodine 131 or I 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. A Drill is being conducted during which 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 SO #1 opened and failed to reclose.

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.

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 to make notifications to appropriate personnel.

3. This JPM contains time critical elements.

A.4