ML17165A495

Watts Bar 2013-302 Final Administrative JPMs

ML17165A495
Person / Time
Site:	Watts Bar
Issue date:	06/14/2017
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
Download: ML17165A495 (150)

Text

NRCEXAM2013302AdministrativeJPM1 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1 NRC EXAM 2013-302 Page 2 of 15 EVALUATION SHEET Task: PERFORM SOI-62.01, "BORON CONCENTRATION CONTROL," APPENDIX C, "CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS)." Alternate Path: n/a Facility JPM #: Safety Function: 2.1 Title: Conduct of Operations K/A 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-62.02, "Boron Concentration Control," Rev. 56. TI-59, "Boron Tables," Rev. 7. Task Number: RO-062-SOI-62-017 Title: Perform manual makeup to the Volume Control Tank. Task Standard: The applicant performs SOI-62.02, "Boron Concentration Control," Appendix C, "CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS)," and calculates: 1.) The total VCT addition to be 367 +/- 1 gallon.

2.) The BA flow rate to be 10.60 gpm. (10.729 gpm is acceptable, if applicant elects to perform conservative calculation.) 3.) The amount of BA to be entered into the BA integrator to be 48 gallons +/- 1 gallon. 4.) The amount of PW to be entered into the PW integrator to be 318 gallons +/- 1 gallon. Validation Time: 25 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 1 NRC EXAM 2013-302 Page 3 of 15 Tools/Equipment/Procedures Needed: A copy of the NRC REFERENCE DISK. A copy of SOI-62.02, "Boron Concentration Control," Appendix C, "CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS)," for each applicant. *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 1 NRC EXAM 2013-302 Page 4 of 15 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. 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 1 is at 100% power, MOL conditions.

2. AUTO MAKEUP is currently out-of-service.

3. VCT level has decreased, and is now stable at 22%.

4. RCS Boric Acid Concentration is 915 ppm.

5. BAT Boric Acid Concentration is 6900 ppm.

6. REACTINW computer program is NOT AVAILABLE. INITIATING CUES: Using SOI-62.02, "Boron Concentration Control," Appendix C, "CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS)," you are to determine the following:

1. Total volume to raise VCT level from 22% to 41%.

2. Boric acid flow rate to be used during the manual makeup.

3. Amount of boric acid to be added.

4. Amount of primary water to be added.

Notify the Examiner when you have completed the calculation.

UNLESS DIRECTED OTHERWISE BY THE PROCEDURE, ROUND ALL CALCULATIONS TO 3 DECIMAL PLACES WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1 NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 5 of 15 START TIME: _______ STEP 1: [1] OBTAIN the following data for use in the HAND CALCULATION: [1.1] Current RCS Boric Acid Concentration.

[1.2] Current BAT Boric Acid Concentration.

[1.3] B-10 Depletion Value from Reactivity Management Briefing Sheet [1.4] Current VCT Level

[1.5] Desired VCT Level STANDARD: Applicant correctly transposes the data from the INITIAL CONDITIONS and INITIATING CUES portion to the APPLICANT HANDOUT SHEET. Applicant refers to the Reactivity Management Briefing Sheet and determines the B-10 depletion to be 0 PPM [1.1] Current RCS Boric Acid Concentration: 915 ppm [1.2] Current BAT Boric Acid Concentration: 6900 ppm [1.3] B-10 Depletion Value from Reactivity Management Briefing Sheet: 0 from Cycle 12 MOL Reactivity Briefing Book. [1.4] Current VCT Level: 22% [1.5] Desired VCT Level: 41% COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1 NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 6 of 15 EXAMINER: Step 2 allows for the entry of 1.0 for a conservative calculation. This value is also acceptable. Remaining steps which are affected by this difference are calculated each of the values. STEP 2: [2] CALCULATE BAT Boric Acid Concentration Ratio (BACR): 6820 ppm ÷ Step 2.0[1.2]ppm =_________ (ENTER 1.0 for BACR following a reactor shutdown or for a conservative calculation). STANDARD: Applicant determines that the BACR is 0.988. (Rounded from 0.988405) 6820PPM / 6900 PPM = 0.988405 OR Applicant elects to perform the conservative calculation and enters a value of 1.0. Step is critical since the BACR affects a later calculation of the BA Blender Flow Rate setting. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1 NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 15 STEP 3: [3] CALCULATE B-10 corrected boron concentration: __________-______________=____________ PPM STEP 2.0[1.1] STEP 2.0[1.3] B-10 corrected boron STANDARD: Applicant adds 915 PPM and 0 PPM and calculates the B-10 corrected boron concentration to be 915 PPM. Step is critical since the B-10 value affects a later calculation of the BA Blender Flow Rate setting. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT STEP 4: [4] CALCULATE total VCT addition volume needed for desired level. STANDARD: Applicant calculates the total VCT additional volume to be 367 GAL. 41%-22% x 19.3 GAL/% = 366.7 GAL, rounded to 367 GAL. Step is critical since the change in level is the basis for the remainder of the calculation. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1 NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 8 of 15 NOTE Corrected Boric Acid Flow Rate in Step 2.0[5] should be obtained from TI-59, Appendix C for the B-10 corrected boron value calculated in Step 2.0[3]. STEP 5: [5] CALCULATE 1-FC-62-139, BA TO BLENDER FCV-62-140 CONTROL, flow setpoint. STANDARD: Applicant refers to TI-59, "Boron Tables," Appendix C, Reactor Coolant Boron Concentration Vs. Automatic Makeup Flow Rate Primary Water Flow of 70 GPM With 4% Boric Acid," Page 20. 10.796 - 10.661 = 0.135 / 2 = 0.068 + 10.661 = 10.7285 rounded to 10.729 Applicant performs an interpolation and determines that the corrected boric acid flow rate for 915 PPM is 10.729 GPM. Applicant multiplies 10.729 times 0.988 and determines that the BA to Blender Flow is 10.600 GPM (Rounded from 10.600252). OR Applicant multiplies 10.729 times 1.0 and determines that the BA to Blender Flow is 10.729 GPM Step is critical since the flow rate determination affects the total amount of boric acid which will be added. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1 NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 9 of 15 STEP 6: [6] CALCULATE TOTAL flow rate. STANDARD: Applicant adds 10.600 GPM to 70 GPM to determine the TOTAL FLOW RATE to be 80.600 GPM. OR Applicant adds 10.729 GPM to 70 GPM to determine the TOTAL FLOW RATE to be 80.729 GPM. Step is critical since the flow rate determination affects the total amount of boric acid which will be added. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT STEP 7: [7] CALCULATE [Y] BA Fraction. STANDARD: Applicant divides 10.600 GPM by 80.600 GPM and determines the BA Fraction to be 0.132 (Rounded from 0.131513648.) OR Applicant divides 10.729 GPM by 80.729 GPM and determines the BA Fraction to be 0.133 (Rounded from 0.132901436.) Step is critical since the flow rate determination affects the total amount of boric acid which will be added. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1 NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 10 of 15 STEP 8: [8] CALCULATE 1-FQ-62-139, BA BATCH COUNTER Setting. STANDARD: Applicant multiplies 0.132 times 367 GALs and determines the Boric Acid Batch Counter Setting to be 48 GAL (Rounded from 48.44 GAL.). OR Applicant multiplies 0.133 times 367 GALs and determines the Boric Acid Batch Counter Setting to be 49 GAL (Rounded from 48.811 GAL.). Step is critical since the flow rate determination affects the total amount of boric acid which will be added. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT NOTE Corrected Boric Acid Flow Rate in Step 2.0[5] should be obtained from TI-59, Appendix C for the B-10 corrected boron value calculated in Step 2.0[3].

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1 NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 11 of 15 STEP 9: [9] CALCULATE [Z] PW Fraction. STANDARD: Applicant divides 70 GPM by 80.600 GPM and determines the PW Fraction to be 0.868. OR Applicant divides 70 GPM by 80.729 GPM and determines the PW Fraction to be 0.867. Step is critical since the flow rate determination affects the total amount of primary water which will be added. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1 NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 12 of 15 STEP 10: [10] CALCULATE 1-FQ-62-142, PW BATCH COUNTER Setting. STANDARD: Applicant multiplies 0.868 times 367 GAL and determines the Primary Water Batch Counter Setting to be 319 GAL (Rounded from 318.556 GAL.). OR Applicant multiplies 0.867 times 367 GAL and determines the Primary Water Batch Counter Setting to be 318 GAL (Rounded from 318.189 GAL.). Acceptable Range 318 +/- 1 GAL Step is critical since the flow rate determination affects the total amount of primary water which will be added. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT STEP 11: Notify the Unit Supervisor that SOI-62.02, "Boric Concentration Control," Appendix C, "CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS)." STANDARD: Applicant notifies the Unit Supervisor that the calculation is complete and ready for review. COMMENTS:

END OF TASK ___ SAT ___ UNSAT

STOP TIME ________

Page 13 of 15 1 KEY DO NOT HAND TO APPLICANT WBN Unit 1 Boron Tables TI-59 Rev. 0007 Page 20 of 105 Appendix C (Page 3 of 7) Reactor Coolant Boron Concentration Vs. Automatic Makeup Flow Rate Primary Water Flow of 70 GPM With 4% Boric Acid BORON CONCENTRATION BORIC ACID FLOW RATE (gpm)BORON CONCENTRATIONBORIC ACID FLOW RATE (gpm) 810 9.332 1010 12.036 820 9.463 1020 12.176 830 9.594 1030 12.317 840 9.726 1040 12.458 850 9.858 1050 12.600 860 9.991 1060 12.742 870 10.124 1070 12.884 880 10.258 1080 13.027 890 10.392 1090 13.171 900 10.526 1100 13.315 910 10.661 1110 13.460 920 10.796 1120 13.605 930 10.932 1130 13.750 940 11.069 1140 13.896 950 11.206 1150 14.043 960 11.343 1160 14.190 970 11.481 1170 14.338 980 11.619 1180 14.486 990 11.757 1190 14.635 1000 11.897 1200 14.784

Page 14 of 15 1 Handout Package for Applicant APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 1 INITIAL CONDITIONS: 1. Unit 1 is at 100% power, MOL conditions.

2. AUTO MAKEUP is currently out-of-service.

3. VCT level has decreased, and is now stable at 22%.

4. RCS Boric Acid Concentration is 915 ppm.

5. BAT Boric Acid Concentration is 6900 ppm.

6. The "REACTINW" computer program is NOT AVAILABLE. INITIATING CUES: Using SOI-62.02, "Boron Concentration Control," Appendix C, "CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS)," you are to determine the following:

1. Total volume to raise VCT level from 22% to 41%.

2. Boric acid flow rate to be used during the manual makeup.

3. Amount of boric acid to be added.

4. Amount of primary water to be added.

Notify the Examiner when you have completed the calculation.

UNLESS DIRECTED OTHERWISE BY THE PROCEDURE, ROUND ALL CALCULATIONS TO 3 DECIMAL PLACES

NRCEXAM2013302AdministrativeJPM2R WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 R NRC EXAM 2013-302 EVALUATION SHEET Task: DETERMINE AFW PUMP REQUIREMENTS. Alternate Path: n/a Facility JPM #: New Safety Function: n/a Title: Conduct of Operations. K/A 2.1.32 Ability to explain and apply system limits and precautions. Rating(s): 2.7/3.5 CFR: 41.10/43.2/45.12 Evaluation Method: Simulator In-Plant Classroom X

References:

GOI-7, "Generic Equipment Operating Guidelines," Rev. 50. Task Number: RO-003-SOI-3.02-006 Title: Manually startup the motor driven Auxiliary Feedwater pumps. Task Standard: The applicant determines: 1.) No starting limitations have been violated based on GOI-7, "Generic Equipment Operating Guidelines." 2.) 1B-B MD AFW Pump may be started immediately, or at any time after 2125. The 1A-A MD AFW pump cannot be restarted on October 15, 2013. 3.) Electrical Maintenance (EM) must be notified to perform 2500-volt megger, bridge, and dc high-potential tests after the 1B-B AFW pump tripped by instantaneous overcurrent relay operation. 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 2 R NRC EXAM 2013-302 DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. 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: The following is the "run" history for 1A-A MD AFW pump and 1B-B MD AFW pump on October 15, 2013:

Pump Start Time Shutdown Time Run Time (minutes) 1A-A 0115 0137 0205 0220 0310 0335 0818 0845 1130 1215 1400 1445 1B-B 0230 0255 0350 0410 0535 0615 1545 1620 1950 2025 Each of the listed pump starts resulted in a normal start. Current time is 2125.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 R NRC EXAM 2013-302 INITIATING CUE:

Part 1 Evaluate the Auxiliary Feedwater pump start history provided and determine:

1. If any starting limitations have been violated.

2. The pump(s) allowed to be started an additional time on October 15, 2013. Part 2 If an instantaneous overcurrent relay operation occurs on the next Auxiliary Feedwater Pump start, what motor testing is required to be performed?

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 R NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 5 0F 9 START TIME: _______ Part 1 STEP 1: Applicant determines that no starting limitations have been violated based on GOI-7, "Generic Equipment Operating Guidelines." STANDARD: From GOI-7, "Generic Equipment Operating Guidelines," Section 5.2.5, "Motor Operating and Starting Limitations." [3] IF NO Nameplate data exists, THEN USE the following generic guidelines for starting motors: A. Two starts in succession, coasting to rest between starts with the motor initially at ambient temperature; or B. One start with the motor initially at normal operating temperature. [4] APPLY the following limitations to motors greater than/equal to 200 hp following any start under either condition in Step 5.2.5[3] above: A. Allow the motor to cool for 20 minutes while running at normal or no load; OR B. Allow the motor to cool for 45 minutes while standing idle before each additional restart is attempted. Applicant locates GOI-7, "Generic Equipment Operating Guidelines," Page 28 NOTE, which states that "The Auxiliary Feedwater Pump motor is limited to six starts per day and the Condenser Circulating Water Pump motor is limited to eight starts per day." The applicant determines that 1A-A MD AFW Pump has been started 6 times today, and 1B-B MD AFW Pump has been started 5 times today. COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 R NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 6 0F 9 STEP 2: Applicant determines that the 1B-B MD AFW Pump may be started immediately, or at 2125. Applicant determines the 1A-A MD AFW pump cannot be restarted on October 15, 2013. STANDARD: Applicant determines that the 1B-B MD AFW Pump may be started at 2125 or any time thereafter. Step is critical to ensure the correct AFW Pump started without violating starting duty limits. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

Part 2 STEP 3: Applicant addresses the question If an instantaneous overcurrent relay operation occurs on the next Auxiliary Feedwater Pump start, what motor testing is required to be performed? STANDARD: Applicant determines that Electrical Maintenance (EM) must be notified to perform 2500-volt megger, bridge, and dc high-potential tests after a 6,900-volt motor has been tripped by relay operation. Step is critical since the specified tests are required to prove that the 1A-A AFW pump motor has not been damaged. COMMENTS:

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

PAGE 7 0F 9 2 R KEY DO NOT HAND TO APPLICANT 2-R KEY Part 1 Evaluate the Auxiliary Feedwater pump start history provided and determine:

1. If any starting limitations have been violated. The applicant evaluates the data provided and determines that there were NO starting limitations violated. 2. The pump(s) allowed to be started an additional time on October 15, 2013. The applicant determines that the 1B-B AFW pump may be started at 2125 or any time thereafter on October 15, 2013. Part 2 If an instantaneous overcurrent relay operation occurs on the next Auxiliary Feedwater Pump start, what motor testing is required to be performed? From GOI-7, "Generic Equipment Operating Guidelines," Section 5.2,5, "Motor Operating and Starting Limitations," Item [6]

NOTIFY Electrical Maintenance (EM) to perform 2500-volt megger, bridge, and dc high-potential tests after a 6,900-volt motor has been tripped by relay operation. This is done to determine whether the motor (or, in some cases, the motor cable) is suitable for service.

WBN Unit 0, 1, & 2 Generic Equipment Operating Guidelines GOI-7 Rev. 0050 Page 28 of 75 5.2.5 Motor Operating and Starting Limitations (continued) CAUTION The Auxiliary Feed Pump motor is limited to six starts per day and the Condenser Circulating Water Pump motor is limited to eight starts per day. NOTE The life of a motor is affected by the number of start attempts made on an individual motor. Most squirrel-cage motors are "rotor critical," and the stator temperature rise will NOT reflect excessive temperature rise in the rotor squirrel cage caused by excessive starting duty. [2] START motors greater than/equal to 200 hp once when at ambient or once when at operating temperature, THEN START motors per Nameplate data for any additional starts. [3] IF NO Nameplate data exists, THEN USE the following generic guidelines for starting motors: A. Two starts in succession, coasting to rest between starts with the motor initially at ambient temperature; or B. One start with the motor initially at normal operating temperature. [4] APPLY the following limitations to motors greater than/equal to 200 hp following any start under either condition in Step 5.2.5[3] above: A. Allow the motor to cool for 20 minutes while running at normal or no load; OR B. Allow the motor to cool for 45 minutes while standing idle before each additional restart is attempted. [5] IF a motor stalls during a starting attempt, THEN CORRECT the conditions which caused the motor to stall, AND EXAMINE the motor thoroughly for damage caused by overheating before an additional restart is attempted. The rotor squirrel cage should be examined visually and tested electrically.

WBN Unit 0, 1, & 2 Generic Equipment Operating Guidelines GOI-7 Rev. 0050 Page 29 of 75 5.2.5 Motor Operating and Starting Limitations (continued) NOTES 1) Severe damage to the motor and the auxiliary electrical system can be sustained by attempting to start a motor that already has a faulted stator winding. 2) If it is determined by an SRO that plant safety requires the restart of the motor, an exception to the limitations below may be made. [6] NOTIFY Electrical Maintenance (EM) to perform 2500-volt megger, bridge, and dc high-potential tests after a 6,900-volt motor has been tripped by relay operation. This is done to determine whether the motor (or, in some cases, the motor cable) is suitable for service. [7] NOTIFY EM to perform megger and bridge tests after a 480V motor (greater than/equal to 100 horsepower) has been tripped by protective relays or devices. This is done to determine whether the motor is suitable for service unless it can be determined that the motor was tripped because of overloading. When the trip out is apparently the result of overloading, the motor and the driven equipment should be inspected visually before attempting to restart the motor. 5.2.6 Auxiliary Power System Transformer Loading NOTE Yellow lines are placed on transformer primary and secondary ammeters to indicate nameplate loading (primary feeds to multiple transformers are NOT marked). Red lines are placed on the ammeters to indicate maximum transformer loading. [1] MAINTAIN loadings at or below the yellow line on all transformers having associated ammeters, AND NOTIFY the Shift Manager (SM) of any transformer loaded above the yellow line.

PAGE 8 0F 9 2 R Handout Package for Applicant APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 2 R INITIAL CONDITIONS: The following is the "run" history for 1A-A MD AFW pump and 1B-B MD AFW pump on October 15, 2013: Pump Start Time Shutdown Time Run Time (minutes) 1A-A 0115 0137 0205 0220 0310 0335 0818 0845 1130 1215 1400 1445

1B-B 0230 0255 0350 0410 0535 0615 1545 1620 1950 2025 Each of the listed pump starts resulted in a normal start. Current time is 2125. INITIATING CUE:

Part 1 Evaluate the Auxiliary Feedwater pump start history provided and determine:

1. If any starting limitations have been violated.

2. The pump(s) allowed to be started an additional time on October 15, 2013. Part 2 If an instantaneous overcurrent relay operation occurs on the next Auxiliary Feedwater Pump start, what motor testing is required to be performed?

NRCEXAM2013302AdministrativeJPM2S WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 S NRC EXAM 2013-302 EVALUATION SHEET Task: DETERMINE AFW PUMP START REQUIREMENTS. Alternate Path: n/a Facility JPM #: New Safety Function: n/a Title: Conduct of Operations. K/A 2.1.32 Ability to explain and apply system limits and precautions. Rating(s): 2.7/3.5 CFR: 41.10/43.2/45.12 Evaluation Method: Simulator In-Plant Classroom X

References:

GOI-7, "Generic Equipment Operating Guidelines," Rev. 50. LCO 3.7.5, Auxiliary Feedwater (AFW) System, Amendment 91. Task Number: RO-003-SOI-3.02-006 Title: Manually startup the motor driven Auxiliary Feedwater pumps. Task Standard: The applicant determines: 1. NO motor start limitations have been violated based on the history provided. 2. 1B-B AFW pump can be started at 2125 on October 15, 2013. The 1A-A AFW pump cannot be restarted on October 15, 2013. 3. Electrical Maintenance (EM) must be notified to perform 2500-volt megger, bridge, and dc high-potential tests after the 1B-B AFW pump tripped by instantaneous overcurrent relay operation. 4. LCO 3.7.5, Auxiliary Feedwater (AFW) System, Action B is applicable, and the 1B-B AFW pump must be declared INOPERABLE, and restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. 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 2 S NRC EXAM 2013-302 DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. 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: The following is the "run" history for 1A-A MD AFW pump and 1B-B MD AFW pump on October 15, 2013:

Pump Start Time Shutdown Time Run Time (minutes) 1A-A 0115 0137 0205 0220 0310 0335 0818 0845 1130 1215 1400 1445 1B-B 0230 0255 0350 0410 0535 0615 1545 1620 1950 2025 Each of the listed pump starts resulted in a normal start. Current time is 2125.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 S NRC EXAM 2013-302 INITIATING CUES: Part 1 Evaluate the Auxiliary Feedwater pump start history provided and determine:

1. If any starting limitations have been violated.

2. The pump(s) allowed to be started an additional time on October 15, 2013. Part 2 Unit 1 is in Mode 2 when the 1A-A MD AFW Pump trips on instantaneous overcurrent relay operation when started. 1.) What testing must be performed on the 1A-A MD AFW Pump motor as a result of the trip? 2.) What actions are required to be taken to comply with Tech Specs?

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 S NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 5 0F 11 START TIME: _______ Part 1 STEP 1: Applicant determines that no starting limitations have been violated based on GOI-7, "Generic Equipment Operating Guidelines." STANDARD: From GOI-7, "Generic Equipment Operating Guidelines," Section 5.2.5, "Motor Operating and Starting Limitations." [3] IF NO Nameplate data exists, THEN USE the following generic guidelines for starting motors: A. Two starts in succession, coasting to rest between starts with the motor initially at ambient temperature; or B. One start with the motor initially at normal operating temperature. [4] APPLY the following limitations to motors greater than/equal to 200 hp following any start under either condition in Step 5.2.5[3] above: A. Allow the motor to cool for 20 minutes while running at normal or no load; OR B. Allow the motor to cool for 45 minutes while standing idle before each additional restart is attempted. Applicant locates GOI-7, "Generic Equipment Operating Guidelines," Page 28 NOTE, which states that "The Auxiliary Feedwater Pump motor is limited to six starts per day and the Condenser Circulating Water Pump motor is limited to eight starts per day." The applicant determines that 1A-A MD AFW Pump has been started 6 times today, and 1B-B MD AFW Pump has been started 5 times today. COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 S NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 6 0F 11 STEP 2: Applicant determines that the 1B-B MD AFW Pump may be started immediately, or at 2125. Applicant determines the 1A-A MD AFW pump cannot be restarted on October 15, 2013. STANDARD: Applicant determines that the 1B-B MD AFW Pump may be started at 2125 or any time thereafter. Step is critical to ensure the correct AFW Pump started without violating starting duty limits. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2 S NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 7 0F 11 Part 2 STEP 3: Applicant addresses the question Unit 1 is in Mode 2 when the 1A-A MD AFW Pump trips on instantaneous overcurrent relay operation when started. 1.) What testing must be performed on the 1A-A MD AFW Pump motor as a result of the trip? STANDARD: Applicant determines that Electrical Maintenance (EM) must be notified to perform 2500-volt megger, bridge, and dc high-potential tests after a 6,900-volt motor has been tripped by relay operation. Step is critical since the specified tests are required to prove that the 1A-A AFW pump motor has not been damaged. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

STEP 4: Applicant addresses the question. 2.) What actions are required to be taken to comply with Tech Specs? STANDARD: Applicant refers to LCO 3.7.5, and determines that CONDITION B applies. Step is critical since the compliance with Tech Specs is a requirement of the plant license. COMMENTS:

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

PAGE 8 0F 11 2 S KEY DO NOT HAND TO APPLICANT 2-S KEY Part 1 Evaluate the Auxiliary Feedwater pump start history provided and determine:

1. If any starting limitations have been violated. The applicant evaluates the data provided and determines that there were NO starting limitations violated. 2. The pump(s) allowed to be started an additional time on October 15, 2013. The applicant determines that the 1B-B AFW pump may be started at 2125 or any time thereafter on October 15, 2013. Part 2 Unit 1 is in Mode 2 when the 1A-A MD AFW Pump trips on instantaneous overcurrent relay operation when started. 1.) What testing must be performed on the 1A-A MD AFW Pump motor as a result of the trip? From GOI-7, "Generic Equipment Operating Guidelines," Section 5.2,5, "Motor Operating and Starting Limitations," Item [6]

NOTIFY Electrical Maintenance (EM) to perform 2500-volt megger, bridge, and dc high-potential tests after a 6,900-volt motor has been tripped by relay operation. This is done to determine whether the motor (or, in some cases, the motor cable) is suitable for service. 2.) What actions are required to be taken to comply with Tech Specs? Applicant refers to LCO 3.7.5, and determines that CONDITION B applies. B. One AFW train inoperable in MODE 1, 2 or 3 for reasons other than Condition A. Restore AFW train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 10 days from the discovery of failure to meet the LCO.

WBN Unit 0, 1, & 2 Generic Equipment Operating Guidelines GOI-7 Rev. 0050 Page 28 of 75 5.2.5 Motor Operating and Starting Limitations (continued) CAUTION The Auxiliary Feed Pump motor is limited to six starts per day and the Condenser Circulating Water Pump motor is limited to eight starts per day. NOTE The life of a motor is affected by the number of start attempts made on an individual motor. Most squirrel-cage motors are "rotor critical," and the stator temperature rise will NOT reflect excessive temperature rise in the rotor squirrel cage caused by excessive starting duty. [2] START motors greater than/equal to 200 hp once when at ambient or once when at operating temperature, THEN START motors per Nameplate data for any additional starts. [3] IF NO Nameplate data exists, THEN USE the following generic guidelines for starting motors: A. Two starts in succession, coasting to rest between starts with the motor initially at ambient temperature; or B. One start with the motor initially at normal operating temperature. [4] APPLY the following limitations to motors greater than/equal to 200 hp following any start under either condition in Step 5.2.5[3] above: A. Allow the motor to cool for 20 minutes while running at normal or no load; OR B. Allow the motor to cool for 45 minutes while standing idle before each additional restart is attempted. [5] IF a motor stalls during a starting attempt, THEN CORRECT the conditions which caused the motor to stall, AND EXAMINE the motor thoroughly for damage caused by overheating before an additional restart is attempted. The rotor squirrel cage should be examined visually and tested electrically.

WBN Unit 0, 1, & 2 Generic Equipment Operating Guidelines GOI-7 Rev. 0050 Page 29 of 75 5.2.5 Motor Operating and Starting Limitations (continued) NOTES 1) Severe damage to the motor and the auxiliary electrical system can be sustained by attempting to start a motor that already has a faulted stator winding. 2) If it is determined by an SRO that plant safety requires the restart of the motor, an exception to the limitations below may be made. [6] NOTIFY Electrical Maintenance (EM) to perform 2500-volt megger, bridge, and dc high-potential tests after a 6,900-volt motor has been tripped by relay operation. This is done to determine whether the motor (or, in some cases, the motor cable) is suitable for service. [7] NOTIFY EM to perform megger and bridge tests after a 480V motor (greater than/equal to 100 horsepower) has been tripped by protective relays or devices. This is done to determine whether the motor is suitable for service unless it can be determined that the motor was tripped because of overloading. When the trip out is apparently the result of overloading, the motor and the driven equipment should be inspected visually before attempting to restart the motor. 5.2.6 Auxiliary Power System Transformer Loading NOTE Yellow lines are placed on transformer primary and secondary ammeters to indicate nameplate loading (primary feeds to multiple transformers are NOT marked). Red lines are placed on the ammeters to indicate maximum transformer loading. [1] MAINTAIN loadings at or below the yellow line on all transformers having associated ammeters, AND NOTIFY the Shift Manager (SM) of any transformer loaded above the yellow line.

AFW System3.7.5 Watts Bar-Unit 1 3.7-11 Amendment 55

3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System

LCO 3.7.5 Three AFW trains shall be OPERABLE.

---

NOTE---------------------------------------------------

Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4. ---------------------------------------------------------------------------------------------------------

APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

ACTIONS

---

NOTE---------------------------------------------------------------- LCO 3.0.4.b is not applicable when entering MODE 1. ----------------------------------------------------------------------------------------------------------------------------------------

CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to turbine driven AFW pump inoperable.

A.1 Restore steam supply to OPERABLE status.

7 days

AND 10 days from discovery of failure to meet the LCO

B. One AFW train inoperable in MODE 1, 2 or 3 for reasons other than Condition A.

B.1 Restore AFW train to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

AND 10 days from discovery of failure to meet the LCO (continued)

AFW System3.7.5 Watts Bar-Unit 1 3.7-12

ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time for Condition A or B not met.

OR Two AFW trains inoperable in MODE 1, 2, or 3.

C.1 Be in MODE 3.

AND C.2 Be in MODE 4.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> D. Three AFW trains inoperable in MODE 1, 2, or 3.

D.1 -----------------NOTE----------------

LCO 3.0.3 and all other LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status. -----------------------------------------

Initiate action to restore one AFW train to OPERABLE status.

Immediately

E. Required AFW train inoperable in MODE 4.

E.1 Initiate action to restore AFW train to OPERABLE status.

Immediately

AFW System3.7.5 Watts Bar-Unit 1 3.7-13 Amendment 13

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each AFW manual, power operated, and automatic valve in each water flow path, and in both steam supply flow paths to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

31 days SR 3.7.5.2 -----------------------------NOTE-------------------------------

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after 1092 psig in the steam generator. --------------------------------------------------------------------

Verify the developed head of each AFW pump at the flow test point is greater than or equal to the required developed head.

31 days on a STAGGERED TEST BASIS

SR 3.7.5.3 ------------------------------NOTE------------------------------

Not applicable in MODE 4 when steam generator is relied upon for heat removal. --------------------------------------------------------------------

Verify each AFW automatic valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

18 months (continued)

AFW System3.7.5 Watts Bar-Unit 1 3.7-14 Amendment 13

SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.7.5.4 --------------------------------NOTES---------------------------- 1. Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after 1092 psig in the steam generator.

2. Not applicable in MODE 4 when steam generator is relied upon for heat removal. ----------------------------------------------------------------------

Verify each AFW pump starts automatically on an actual or simulated actuation signal.

18 months SR 3.7.5.5 Verify proper alignment of the required AFW flow paths by verifying flow from the condensate storage tank to each steam generator.

Prior to entering MODE 2 after initial fuel loading and whenever unit has been in MODE 5 or 6 for 30 days PAGE 9 0F 11 2 S Handout Package for Applicant APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 2 S INITIAL CONDITIONS: The following is the "run" history for 1A-A MD AFW pump and 1B-B MD AFW pump on October 15, 2013:

Pump Start Time Shutdown Time Run Time (minutes) 1A-A 0115 0137 0205 0220 0310 0335 0818 0845 1130 1215 1400 1445

1B-B 0230 0255 0350 0410 0535 0615 1545 1620 1950 2025 Each of the listed pump starts resulted in a normal start. Current time is 2125.

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 2 S INITIATING CUES: Part 1 Evaluate the Auxiliary Feedwater pump start history provided and determine:

1. If any starting limitations have been violated.

2. The pump(s) allowed to be started an additional time on October 15, 2013. Part 2 Unit 1 is in Mode 2 when the 1A-A MD AFW Pump trips on instantaneous overcurrent relay operation when started. 1.) What testing must be performed on the 1A-A MD AFW Pump motor as a result of the trip? 2.) What actions are required to be taken to comply with Tech Specs?

NRCEXAM2013302AdministrativeJPM3R WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R NRC EXAM 2013-302 PAGE 2 OF 10 EVALUATION SHEET Task: REVIEW 1-SI-0-4, "MONTHLY SURVEILLANCES." Alternate Path: n/a Facility JPM #: A.2 2010-08 NRC Exam (Modified) Safety Function: 2.2 Title: Equipment Control K/A 2.2.12 Knowledge of surveillance procedures. Rating(s): 3.7/4.1 CFR: 45.10/45.13 Evaluation Method: Simulator In-Plant Classroom X

References:

1-SI-0-4, "Monthly Surveillances," Rev. 29. Task Number: RO-113-GEN-004 Title: Perform surveillance tests. Task Standard: The applicant reviews a completed 0-SI-4, "Monthly Surveillance," and determines that the following 5 ITEMS are exceeding MCD limits OR have exceeded specified values: 1. ITEM 4: 1-PI-1-1C, SG 1 Press, is exceeding its MCD value. 2. ITEM 7: 1-PI-68-336C PZR PRESS is exceeding its MCD value. 3. ITEM 13: 1-TI-68-43C LOOP 3 HL TEMP is exceeding its MCD value. 4. ITEM 25: 1-FI-68-93C CHARGING FLOW is within its MCD value, but exceeding the 20 gpm limit of NOTE (32). 5. ITEM 29: 1-PI-62-81C LP LETDOWN PRESS is exceeding its MCD value. The applicant indicates that the following actions are required (in no particular order) for each of the 5 items identified: 1. SM/Unit SRO must be notified of each item that exceeds limits.

2. A Work Order (WO) or Service Request (SR) must be prepared for each item that exceeds limits. 3. ITEM 25 requires a calibration of 1-FI-68-93C CHARGING FLOW. Validation Time: 25 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 3 R NRC EXAM 2013-302 PAGE 3 OF 10 Tools/Equipment/Procedures Needed: Marked up copy of 1-SI-0-4, "Monthly Surveillances," Pages 46, 47, 51, and 54 included in the 3 R Handout Package for Applicant portion of this JPM. NRC REFERENCE DISK. *NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R NRC EXAM 2013-302 PAGE 4 OF 10 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. 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. The Unit is in Mode 1, with no LCO entries at this time. 2. You are the Unit Operator responsible for the review of a partial performance of 1-SI-0-4, "Monthly Surveillances," Appendix D, "Remote Shutdown and PAM Channel Check Data Sheet," pages 46, 47, 51 and 54. INITIATING CUES: You are to review the data entered on pages provided to you from Appendix D, list the actions required to be taken to address any deviations found. RAISE YOUR HAND to inform the EXAMINER when you have completed your review and your list of actions has been developed.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 5 0F 10 START TIME: _______ EXAMINERS CUE: 1-SI-0-4, Appendix D, pages 46, 47, 51, and 54 are attached as the key to this JPM. Values which fall outside the MCD are circled on the key, and actions to be taken for each item are listed STEP 1: Item 4 (Page 46), values for SG 1 Pressure. STANDARD: Applicant evaluates data provided and determines that the readings in the Main Control Room (1-M-3) and the Auxiliary Control Room (1-L-10) for 1-PI-1-2A and 1-PI-1-1C are outside the channel check MCD of 80 psig. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

STEP 2. Item 7 (Page 47), value for 1-PI-68-336C PZR PRESS. STANDARD: Applicant evaluates data provided and determines that the reading for 1-PI-68-336C in the Auxiliary Control Room (1-L-10) is outside the channel check MCD of 50 psig. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 6 0F 10 STEP 3. Item 13 (Page 51), values for 1-TI-68-43C LOOP 3 HL TEMP. STANDARD: Applicant evaluates data provided and determines that the reading for 1-TI-68-43C in the Auxiliary Control Room (1-L-10) is outside the channel check MCD of 30F. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 4: Item 25 (Page 54), value for 1-FI-62-93A CHARGING FLOW. STANDARD: Applicant evaluates data provided and determines that the reading for 1-FI-62-93C in the Auxiliary Control Room (1-L-10) is within the channel check MCD of 40 psig, but exceeds the 20 gpm value given in NOTE (32). Per Note (32) If channel deviation is greater than 20 gpm, action shall be initiated to calibrate the flow instrumentation W.O. number shall be recorded in REMARKS. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

STEP 5: Item 29 (Page 54), value for 1-PI-62-81C LP LETDOWN PRESS. STANDARD: Applicant evaluates data provided and determines that the reading for 1-PI-62-81C in the Auxiliary Control Room (1-L-10) exceeds the 30 psig MCD value. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 R NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 7 0F 10 STEP 6: Applicant reports items that are out-of-limits per 1-SI-0-4.

STANDARD:

The applicant indicates that the following actions are required (in no particular order) for each of the 5 items identified: 1. SM/Unit SRO must be notified of each item that exceeds limits. 2. A Work Order (WO) or Service Request (SR) must be prepared for each item that exceeds limits. COMMENTS:

___ SAT

___ UNSAT

STOP TIME ________

PAGE 8 0F 10 3 R KEY DO NOT HAND TO APPLICANT

PAGE 9 0F 10 3 R Handout Package for Applicant APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 3 R INITIAL CONDITIONS: 1. The Unit is in Mode 1, with no LCO entries at this time. 2. You are the Unit Operator responsible for the review of a partial performance of 1-SI-0-4, "Monthly Surveillances," Appendix D, "Remote Shutdown and PAM Channel Check Data Sheet," pages 46, 47, 51 and 54. INITIATING CUES: You are to review the data entered on pages provided to you from Appendix D, list the actions required to be taken to address any deviations found. RAISE YOUR HAND to inform the EXAMINER when you have completed your review and your list of actions has been developed.

NRCEXAM2013302AdministrativeJPM3S WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 S NRC EXAM 2013-302 Page 2 of 13 EVALUATION SHEET Task: DETERMINE RISK LEVEL, CDF AND LERF MULTIPLIERS USING EOOS SOFTWARE. Alternate Path: n/a Facility JPM #: New Safety Function: 2.2 Title: Equipment Control. K/A 2.2.14 Knowledge of the process for controlling equipment configuration or status. Rating(s): 3.9/4.3 CFR: 41.10/43.3/45.13 Evaluation Method: Simulator In-Plant Classroom X

References:

NPG-SPP-09.11.1, "Equipment Out of Service (EOOS) Management," Rev. 6. WBN EOOS Computer Program Task Number: STA-119-SPP-9.11-001 Title: Determine Risk for Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) using EOOS software. Task Standard: The applicant determines: 1. Removing the 1A-A Diesel Generator from service in the WBN EOOS program results in a CDF of 4.36, a LERF of 4.57, and RISK remains GREEN for CDF and LERF. 2. Removing the 2B-B ERCW Strainer from service in addition to the 1A-A Diesel Generator in the WBN EOOS program results in a CDF of 25.9, Risk changes to ORANGE, and the LERF changes to 8.1, and Risk changes to YELLOW. 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 3 S NRC EXAM 2013-302 Page 3 of 13 Tools/Equipment/Procedures Needed: Laptop Computer with WBN EOOS installed. NRC REFERENCE DISK. *NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK. SPECIAL INSTRUCTIONS After each applicant performs this JPM, ENSURE that the 1A-A Diesel Generator and the 2B-B ERCW Strainer are returned to service in the WBN EOOS program, and that the "Calculate Risk Measures" icon is pressed. These actions will return the CDF and LERF Multiplier values to 1.0, and the RISK COLOR to GREEN.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 S NRC EXAM 2013-302 Page 4 of 13 DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. 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: Unit 1 is in MODE 1, 100% power. INITIATING CUES: You are to use the EOOS computer program to complete the following tasks. LOG IN INFORMATION: USERNAME "ops" and PASSWORD "opseoos."

PART 1 The 1A-A Diesel Generator has just been reported to have failed its surveillance, and you are to determine the RISK COLOR, Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) Multiplier which result from removing the 1A-A Diesel Generator from service. Enter the values for CDF and LERF, and CIRCLE the appropriate color. CDF = LERF = RISK COLOR GREEN

YELLOW

ORANGE

RED (circle one) RISK COLOR GREEN

YELLOW

ORANGE

RED (circle one) Part 2 on next page WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 S NRC EXAM 2013-302 Page 5 of 13 PART 2 A problem has developed that has rendered the 2B-B ERCW Strainer inoperable. You are to determine the RISK COLOR, the RISK COLOR, Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) Multiplier which result from removing the 1A-A Diesel Generator and the 2B-B ERCW Strainer from service. Enter the values for CDF and LERF, and CIRCLE the appropriate color. CDF = LERF = RISK COLOR GREEN

YELLOW

ORANGE

RED (circle one) RISK COLOR GREEN

YELLOW

ORANGE

RED (circle one)

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 S NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 6 of 13 START TIME: _______ STEP 1: From appropriately installed location, access EOOS for the desired plant and unit.

STANDARD:

Applicant locates a copy of the WBN EOOS program on the computer. COMMENTS:

___ SAT

___ UNSAT

STEP 2: Log in using the assigned User Name and Password which are available from the Corporate PRA Group.

STANDARD:

Applicant enters the appropriate user name and password to log in to the EOOS program. COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 S NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 13 STEP 3: Remove the 1A-A Diesel generator from service in the WBN EOOS program.

STANDARD: Applicant locates the 1A-A Diesel Generator on the EOOS screen.

Applicant selects the 1A-A Diesel Generator and uses the mouse to enter the related drop down menu.

Applicant selects "Take Item OOS' using the mouse.

Applicant ensures 1A-A DG appears in the "Active Items" window.

COMMENTS:

___ SAT

___ UNSAT

STEP 4: Ensure the list of components/FEGs out of service matches the current unit configuration or make updates as necessary.

STANDARD: Applicant ensures 1A-A DG appears in the "Active Items" window.

COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 S NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 8 of 13 STEP 5: Calculate Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) Multiplier for the unit configuration using EOOS (Calculate Risk Measure(s) Button).

STANDARD: Applicant locates the Calculate Risk Measures ICON (resembles a calculator) and selects the icon using the mouse.

Applicant writes down the Core Damage Frequency multiplier 4.36 and indicates the RISK is GREEN.

Applicant writes down the Large Early Release Frequency multiplier 4.57 and indicates the RISK is GREEN.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

STEP 6: Part 2. Removes the 2B-B ERCW Strainer from service in the WBN EOOS program.

STANDARD: Applicant locates the "2B-B Strainer" under the ERCW system on the EOOS screen.

Applicant selects the "2B-B Strainer" and uses the mouse to enter the related drop down menu.

Applicant selects "Take Item OOS' using the mouse.

Applicant ensures 2B-B ERCW Strainer appears in the "Active Items" window, in addition to the 1A-A Diesel Generator.

COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3 S NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 9 of 13 STEP 7: Calculate Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) Multiplier for the unit configuration using EOOS (Calculate Risk Measure(s) Button).

STANDARD:

Applicant locates the Calculate Risk Measures ICON (resembles a calculator) and selects the icon using the mouse.

Applicant writes down the Core Damage Frequency multiplier 25.9 and indicates the RISK is ORANGE.

Applicant writes down the Large Early Release Frequency multiplier 8.1 and indicates the RISK is YELLOW.

COMMENTS:

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

3 S Key DO NOT HAND TO APPLICANT NRC EXAM MATERIAL JPM 3 - S KEY PART 1 The 1A-A Diesel Generator has just been reported to have failed its surveillance, and you are to determine the RISK COLOR, Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) Multiplier which result from removing the 1A-A Diesel Generator from service. Enter the values for CDF and LERF, and CIRCLE the appropriate color. CDF = 4.36 LERF =4.57 RISK COLOR GREEN YELLOW ORANGE

RED (circle one) RISK COLOR GREEN YELLOW ORANGE

RED (circle one) PART 2 A problem has developed that has rendered the 2B-B ERCW Strainer inoperable. You are to determine the RISK COLOR, the RISK COLOR, Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) Multiplier which result from removing the 1A-A Diesel Generator and the 2B-B ERCW Strainer from service. Enter the values for CDF and LERF, and CIRCLE the appropriate color. CDF = 25.9 LERF =8.1 RISK COLOR GREEN

YELLOW

ORANGE

RED (circle one) RISK COLOR GREEN

YELLOW

ORANGE

RED (circle one) 3 S Handout Package for Applicant APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 3 S INITIAL CONDITIONS: Unit 1 is in MODE 1, 100% power. INITIATING CUES: You are to use the EOOS computer program to complete the following tasks. LOG IN information: USERNAME "ops" and PASSWORD "opseoos."

PART 1 The 1A-A Diesel Generator has just been reported to have failed its surveillance, and you are to determine the RISK COLOR, Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) Multiplier which result from removing the 1A-A Diesel Generator from service. Enter the values for CDF and LERF, and CIRCLE the appropriate color. CDF = LERF = RISK COLOR GREEN

YELLOW

ORANGE

RED (circle one) RISK COLOR GREEN

YELLOW

ORANGE

RED (circle one)

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 3 S PART 2 A problem has developed that has rendered the 2B-B ERCW Strainer inoperable. You are to determine the RISK COLOR, the RISK COLOR, Core Damage Frequency (CDF) and Large Early Release Frequency (LERF) Multiplier which result from removing the 1A-A Diesel Generator and the 2B-B ERCW Strainer from service. Enter the values for CDF and LERF, and CIRCLE the appropriate color. CDF = LERF = RISK COLOR GREEN

YELLOW

ORANGE

RED (circle one) RISK COLOR GREEN

YELLOW

ORANGE

RED (circle one)

NRCEXAM2013302AdministrativeJPM4R WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 R NRC EXAM 2013-302 PAGE 2 OF 9 EVALUATION SHEET Task: CALCULATE STAY TIME FOR EMERGENCY EXPOSURE Alternate Path: n/a Facility JPM #: Modified Safety Function: 2.3 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:

EPIP-15, Emergency Exposure Guidelines," Rev. 15. Task Number: AUO-119-SSP-5.01-001 Title: Control personnel radiation exposure. Task Standard: The applicant: 1. Calculates the total dose received performing the assigned tasks to be 19.8 Rem TEDE and 180 REM to the hands. (Acceptable Range 19.6 - 19.8, Hands 180 REM). 2. Determines the additional requirements contained in EPIP-15, Emergency Exposure Guidelines," Section 3.1.4, "Post Exposure Evaluations," are to be applied to the AB AUO. 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 4 R NRC EXAM 2013-302 PAGE 3 OF 9 Tools/Equipment/Procedures Needed: NRC REFERENCE DISK Calculator NOTE: This JPM is designed to be performed in a classroom with a computer and the NRC REFERENCE DISK available for each applicant WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 R NRC EXAM 2013-302 PAGE 4 OF 9 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. 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. A loss of coolant accident is in progress. 2. Automatic swap over to the containment sump has failed to occur. 3. In order to establish and maintain a safe shutdown, the TSC has recommended that the Auxiliary Building AUO be dispatched to perform the following tasks: # TASK TIME DOSE RATE 1 Go to task performance area. 9 minutes 2 Rem/hr 2 Manually open 1-FCV-63-72, CNTMT SUMP TO RHR PMP A SUCT. 36 minutes 32 Rem/hr TEDE 300 Rem/hr to HANDS 3 Return from task performance area. 9 minutes 2 Rem/hr 4. Authorization to exceed occupational dose limits to enable transfer to the containment sump has been approved by the Shift Manager (SED) for the Auxiliary Building AUO. INITIATING CUES:

The Auxiliary Building (AB) AUO has completed Tasks 1, 2 and 3 in the time listed.

You are to determine: 1. The exposure expected to be received by the AB AUO during the completion of Tasks 1 through 3 2. What additional requirements, if any, will be in effect after the AB AUO performs the task? -

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 R NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 5 of 9 START TIME: _______ STEP 1: Determine dose received performing Tasks 1through 3. STANDARD: Applicant calculates dose to complete Task 1 as:

9 min. /60 min/hr x 2 Rem/hr = 0.3 Rem. Acceptable Range 0.3 Rem. Applicant calculates dose to complete Task 2 TEDE as: 36 min./60 min/hr. X 32 Rem/hr = 19.2 Rem Acceptable Range 19 to 19.2 Rem. Applicant calculates dose to complete Task 2 HAND DOSE as: 36 min./60 min/hr. X 300 Rem/hr = 180 Rem Acceptable Range 180 Rem. Applicant calculates dose to complete Task 3 as: (SAME CALCULATION AND DOSE AS Task 1, or 0.3 Rem.) Total for Tasks 1, 2 and 3 is 19.8 Rem TEDE Acceptable Range 19.6 - 19.8 Rem. Total for Tasks 2 is 180 Rem To the Extremities (Hands) Acceptable Range 180 Rem. Step is critical to determine the total dose for the assigned tasks, and to determine that the Emergency Dose Limits are NOT exceeded. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 R NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 6 of 9 STEP 2: What additional requirements, if any, will be in effect after the AB AUO performs the task? STANDARD: From EPIP-15. 3.1.4 POST-EXPOSURE EVALUATIONS A. Personnel receiving emergency or accident exposures should be restricted from further occupational exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance. B. An exposure evaluation shall be performed to determine the individual dose. RP shall conduct post exposure dose assessments for exposed individuals, with particular attention to determining the adequacy of administrative dosimeter correction factors for TEDE doses resulting from internal and external exposures. This evaluation should be based on observed area dose rates, airborne activity measurements, and dosimetry results. The evaluation shall be documented in an appropriate format and filed with the individual's exposure records. Appropriate reports shall be submitted to RP and the US NRC. C. Any exposures above 5 Rem TEDE shall be reported to a TVA physician or designee. It is the responsibility of the physician to determine appropriate medical evaluations and required care. Cross reference guidance is in EPIP- 10. Step is critical to determine the restrictions associated with the dose received, even though the Emergency Dose limit of 25 Rem is not exceeded. COMMENTS:

END OF TASK CRITICAL TASK ___ SAT ___ UNSAT STOP TIME ________

4 R KEY DO NOT HAND TO APPLICANT WBN Unit 0 Emergency Exposure Guidelines EPIP-15 Rev. 0015 Page 7 of 16 3.1.4 POST-EXPOSURE EVALUATIONS A. Personnel receiving emergency or accident exposures should be restricted from further occupational exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance. B. An exposure evaluation shall be performed to determine the individual dose. RP shall conduct post exposure dose assessments for exposed individuals, with particular attention to determining the adequacy of administrative dosimeter correction factors for TEDE doses resulting from internal and external exposures. This evaluation should be based on observed area dose rates, airborne activity measurements, and dosimetry results. The evaluation shall be documented in an appropriate format and filed with the individual's exposure records. Appropriate reports shall be submitted to RP and the US NRC. C. Any exposures above 5 Rem TEDE shall be reported to a TVA physician or designee. It is the responsibility of the physician to determine appropriate medical evaluations and required care. Cross reference guidance is in EPIP-10. 3.1.5 EMERGENCY DOSE EXTENSIONS A. In REP emergency situations, planned doses to radiological workers can be extended beyond the TVA administrative limits to the 10 CFR 20 regulatory limits. 3.1.6 ADDITIONAL INSTRUCTIONS A. Refer to Appendix A and B of this procedure.

4 R Handout Package for Applicant APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 4 R INITIAL CONDITIONS: 1. A loss of coolant accident is in progress. 2. Automatic swap over to the containment sump has failed to occur. 3. In order to establish and maintain a safe shutdown, the TSC has recommended that the Auxiliary Building AUO be dispatched to perform the following tasks: # TASK TIME DOSE RATE 1 Go to task performance area. 9 minutes 2 Rem/hr 2 Manually open 1-FCV-63-72, CNTMT SUMP TO RHR PMP A SUCT. 36 minutes 32 Rem/hr TEDE 300 Rem/hr to HANDS 3 Return from task performance area. 9 minutes 2 Rem/hr 4. Authorization to exceed occupational dose limits to enable transfer to the containment sump has been approved by the Shift Manager (SED) for the Auxiliary Building AUO. INITIATING CUES:

The Auxiliary Building (AB) AUO has completed Tasks 1, 2 and 3 in the time listed.

You are to determine: 1. The exposure expected to be received by the AB AUO during the completion of Tasks 1 through 3 2. What additional requirements, if any, will be in effect after the AB AUO performs the task?

NRCEXAM2013302AdministrativeJPM4S WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 S NRC EXAM 2013-302 PAGE 2 OF 10 EVALUATION SHEET Task: DETERMINE REQUIREMENTS FOR AUTHORIZING EMERGENCY EXPOSURE. Alternate Path: n/a Facility JPM #: Modified 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:

EPIP-15, "Emergency Exposure Guidelines," Rev. 15. Task Number: AUO-119-SSP-5.01-001 Title: Control personnel radiation exposure. Task Standard: The applicant determines: 1. The exposure expected to be received by the AB AUO during the completion of Tasks 1 through 3 to be 19.8 REM TEDE and 180 REM Extremities. 2. The Shift Manager as the SED must authorize the exposure in writing using EPIP-15, "Emergency Exposure Guidelines," Appendix B, "Authorization to Exceed Occupational Dose Limits Form." 3. Determines the additional requirements contained in EPIP-15, Emergency Exposure Guidelines," Section 3.1.4, "Post Exposure Evaluations," are to be applied to the AB AUO. 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 4 S NRC EXAM 2013-302 PAGE 3 OF 10 Tools/Equipment/Procedures Needed: NRC REFERENCE DISK Calculator NOTE: This JPM is designed to be performed in a classroom with a computer and the NRC REFERENCE DISK available for each applicant WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 S NRC EXAM 2013-302 PAGE 4 OF 10 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. 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. A loss of coolant accident is in progress. 2. Automatic swap over to the containment sump has failed to occur.

3. In order to establish and maintain a safe shutdown, the TSC has recommended that the Auxiliary Building AUO be dispatched to perform the following tasks: # TASK TIME DOSE RATE 1 Go to task performance area. 9 minutes 2 Rem/hr 2 Manually open 1-FCV-63-72, CNTMT SUMP TO RHR PMP A SUCT. 36 minutes 32 Rem/hr TEDE 300 Rem/hr to HANDS 3 Return from task performance area. 9 minutes 2 Rem/hr INITIATING CUES: You are the Site Emergency Director and are to determine: 1. The exposure expected to be received by the AB AUO during the completion of Tasks 1 through 3 2. The specific approval required for the expected exposure to the AB AUO 3. What additional requirements, if any, will be in effect after the AB AUO performs the task? -

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 S NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 5 of 10 START TIME: _______ STEP 1: The exposure expected to be received by the AB AUO during the completion of Tasks 1 through 3. STANDARD: Applicant calculates dose to complete Task 1 as: 9 min. /60 min/hr x 2 Rem/hr = 0.3 Rem. Applicant calculates dose to complete Task 2 TEDE as: 36 min./60 min/hr. X 32 Rem/hr = 19.2 Rem Acceptable Range 19 to 19.2 Rem. Applicant calculates dose to complete Task 2 HAND DOSE as: 36 min./60 min/hr. X 300 Rem/hr = 180 Rem Acceptable Range is 180 Rem. Applicant calculates dose to complete Task 3 as: (SAME CALCULATION AND DOSE AS Task 1, or 0.3 Rem.)

9 min. /60 min/hr x 2 Rem/hr = 0.3 Rem. The TOTAL for all of the tasks (Tasks 1, 2 and 3) is 19.8 Rem TEDE Acceptable Range 19.6 - 19.8 Rem. Total to the Extremities (Hands) is 180 Rem Acceptable Range is 180 Rem. Step is critical to determine the total dose for the assigned tasks, and to determine that the Emergency Dose Limits are NOT exceeded. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 S NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 6 of 10 STEP 2: Determine that the SITE EMERGENCY DIRECTOR is the ONLY person that can authorize the Emergency Exposure. STANDARD: From EPIP-15, Section 3.0, INSTRUCTIONS. A. The Site Emergency Director (SED) is the only individual responsible for authorizing Emergency dose limits in excess of TVA Administrative dose limits and 10 CFR 20.1201. Appendix A and B shall be used to provide written authorization. The applicant determines that EPIP-15, APPENDIX B, General Instructions for Emergency Exposures, Page 4 Authorization To Exceed Occupational Dose Limits Form is required for written authorization. Step is critical to determine the authorization associated with the dose received. COMMENTS:

CRITICAL TASK ___ SAT ___ UNSAT WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4 S NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 10 STEP 3: What additional requirements, if any, will be in effect after the AB AUO performs the task? STANDARD: From EPIP-15. 3.1.4 POST-EXPOSURE EVALUATIONS A. Personnel receiving emergency or accident exposures should be restricted from further occupational exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance. B. An exposure evaluation shall be performed to determine the individual dose. RP shall conduct post exposure dose assessments for exposed individuals, with particular attention to determining the adequacy of administrative dosimeter correction factors for TEDE doses resulting from internal and external exposures. This evaluation should be based on observed area dose rates, airborne activity measurements, and dosimetry results. The evaluation shall be documented in an appropriate format and filed with the individual's exposure records. Appropriate reports shall be submitted to RP and the US NRC. C. Any exposures above 5 Rem TEDE shall be reported to a TVA physician or designee. It is the responsibility of the physician to determine appropriate medical evaluations and required care. Cross reference guidance is in EPIP- 10. Step is critical to determine the restrictions associated with the dose received. COMMENTS:

END OF TASK CRITICAL TASK ___ SAT ___ UNSAT STOP TIME ________

Page 8 of 10 4 S KEY

DO NOT HAND TO APPLICANT WBN Unit 0 Emergency Exposure Guidelines EPIP-15 Rev. 0015 Page 5 of 16 3.0 INSTRUCTIONS NOTE Specific definitions as used in this procedure are contained in Appendix D. A. The Site Emergency Director (SED) is the only individual responsible for authorizing Emergency dose limits in excess of TVA Administrative dose limits and 10 CFR 20.1201. Appendix A and B shall be used to provide written authorization. NOTE As defined by the emergency situation, this approval may be relayed verbally and documented later. B. The Radiation Protection (RP) Group is responsible for completing Appendix B-1, "Authorization to Exceed Occupational Dose Limits," obtaining the Site Emergency Director's approval and will perform radiological surveys or other assessments to estimate the radiation doses. C. In all cases, the site RP Manager shall be informed of any emergency exposure immediately so that a determination of the total quarterly exposure can be made. Based on the results of the determination, the worker may be restricted from further dose.

WBN Unit 0 Emergency Exposure Guidelines EPIP-15 Rev. 0015 Page 6 of 16 3.1 EXPOSURE LIMITATIONS 3.1.1 ACTIONS FOR LIFE SAVING OR PROTECTION OF THE PUBLIC A. For immediate activities up to 25 Rem which are necessary to: 1. Save Human Life. For lifesaving operations situations may occur in which a dose in excess of 25 Rem would be required. It is not possible to prejudge the risk that one person should be allowed to take to save the life of another. However, persons undertaking an emergency mission in which the dose would exceed 25 Rem to the whole body should do so only on a voluntary basis and with full awareness of the risks involved. 2. Restore equipment necessary to maintain critical safety functions or to establish and maintain a safe shutdown, 3. Prevent or Mitigate a release of radioactivity to the environment for which off-site protective measures may be required. For these activities, the TEDE of personnel directly involved shall not exceed 25 Rem. This limit is applicable only if actions establishing adequate or equivalent protection, with less dose, are not readily available. B. Limit for lens of eye is 75 Rem, or three (3) times the TEDE value. C. Limit for any other organ (including skin and body extremities) is 250 Rem, or ten (10) times the TEDE value. 3.1.2 ACTIONS FOR IMMEDIATE REPAIR OR TO PREVENT THE FAILURE OF EQUIPMENT A. For activities performed on an immediate basis to prevent the failure of equipment necessary to protect the public health and safety, the TEDE of personnel directly involved shall not exceed 10 Rem. This limit is applicable only if actions establishing adequate or equivalent protection, with a less dose consequence, are not readily available. B. Limit for lens of eye of 30 Rem, three (3) times the TEDE limit. C. Limit for any other organ (including skin and body extremities) of 100 Rem, or ten (10) times the TEDE limit. 3.1.3 INTERNAL EXPOSURE (EMERGENCY WORKERS) A. Guidelines for internal exposure controls of WBN emergency workers are provided in Appendix C.

WBN Unit 0 Emergency Exposure Guidelines EPIP-15 Rev. 0015 Page 7 of 16 3.1.4 POST-EXPOSURE EVALUATIONS A. Personnel receiving emergency or accident exposures should be restricted from further occupational exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance. B. An exposure evaluation shall be performed to determine the individual dose. RP shall conduct post exposure dose assessments for exposed individuals, with particular attention to determining the adequacy of administrative dosimeter correction factors for TEDE doses resulting from internal and external exposures. This evaluation should be based on observed area dose rates, airborne activity measurements, and dosimetry results. The evaluation shall be documented in an appropriate format and filed with the individual's exposure records. Appropriate reports shall be submitted to RP and the US NRC. C. Any exposures above 5 Rem TEDE shall be reported to a TVA physician or designee. It is the responsibility of the physician to determine appropriate medical evaluations and required care. Cross reference guidance is in EPIP-10. 3.1.5 EMERGENCY DOSE EXTENSIONS A. In REP emergency situations, planned doses to radiological workers can be extended beyond the TVA administrative limits to the 10 CFR 20 regulatory limits. 3.1.6 ADDITIONAL INSTRUCTIONS A. Refer to Appendix A and B of this procedure.

WBN Unit 0 Emergency Exposure Guidelines EPIP-15 Rev. 0015 Page 13 of 16 Appendix B (Page 4 of 4) Authorization To Exceed Occupational Dose Limits Form The persons listed below are authorized to exceed the TVA dose limits for the whole body and extremities during the evaluation or mitigation of an emergency situation. Emergency limits are in excess of 10 CFR 20.1201 limits. The persons listed below acknowledge they have volunteered for this assignment, and have been briefed on the emergency situation, and have been made aware of possible consequences of the estimated radiation dose(s). Hand carry or FAX to the TSC for SED Signature NAME EMPLOYEE ID# SIGNATURE DOSE LIMIT (REM) 1 2 3 4 5 6 7 8 9 10 RP Survey No. (If Applicable): Emergency Location(s) Estimated Doses Remarks: Prepared by: Authorized by: Site Emergency Director Hand carry or FAX to the OSC after SED signs.

Page 9 of 10 4 S

Handout Package for Applicant APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 4 S INITIAL CONDITIONS: 1. A loss of coolant accident is in progress. 2. Automatic swap over to the containment sump has failed to occur.

3. In order to establish and maintain a safe shutdown, the TSC has recommended that the Auxiliary Building AUO be dispatched to perform the following tasks: # TASK TIME DOSE RATE 1 Go to task performance area. 9 minutes 2 Rem/hr 2 Manually open 1-FCV-63-72, CNTMT SUMP TO RHR PMP A SUCT. 36 minutes 32 Rem/hr TEDE 300 Rem/hr to HANDS 3 Return from task performance area. 9 minutes 2 Rem/hr INITIATING CUES: You are the Site Emergency Director and are to determine: 1. The exposure expected to be received by the AB AUO during the completion of Tasks 1 through 3 2. The specific approval required for the expected exposure to the AB AUO 3. What additional requirements, if any, will be in effect after the AB AUO performs the task?

NRCEXAM2013302AdministrativeJPM5 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5 NRC EXAM 2013-302 Page 2 of 11 EVALUATION SHEET Task: CLASSIFY THE EVENT. Alternate Path: n/a Facility JPM #: A.4-1 SRO (2009-11 NRC EXAM) Safety Function: 2.4 Title: Emergency Procedures / Plan K/A 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation. Rating(s): 2.5/3.3 CFR: 41.10 / 43.5 / 45.11 Evaluation Method: Simulator In-Plant Classroom X*

References:

EPIP-1 "Emergency Plan Classification Flowpath", Rev. 37. EPIP-2, "Notification of Unusual Event," Rev. 31.

EPIP-3 "Alert", Rev. 37.

EPIP-4, "Site Area Emergency," Rev. 35. EPIP-5 "General Emergency", Rev. 41. Task Number: SRO-119-SPP-3.5-001 Title: Determine when immediate notifications are required and make notifications to the NRC or other Regulatory Agencies as appropriate. Task Standard: The applicant : 1.) Within 15 minutes, classifies the event as a GENERAL EMERGENCY per EALs 1.1.2 Loss, 1.2.2, Potential Loss and 1.3.2 Loss. 2.) INITIATES EPIP-5, "GENERAL EMERGENCY" Appendix A, "General Emergency Initial Notification Form," and completes: a. Item 3. - EAL Designators - 1.1.2 Loss, 1.2.2, Potential Loss and 1.3.2 Loss. b. Item 4. - Brief Description of the Event - Fuel Clad barrier breach, with a concurrent loss of coolant greater than the capacity of the CCP and indications of a LOCA Outside Containment. (Applicant description will vary) c. Item 5. - Radiological Conditions - EITHER "Minor releases within federally approved limits" OR "Release Information not known" checked or otherwise indicated on form. d, Item 6. - Time that applicant declared the event and the date. e. Item 7. - Meteorological Conditions. Wind Speed and direction correctly entered. (15 mph and 125 degrees). f. Item 8. - Recommendation 2 selected, and the proper area to be evacuated indicated on the form (110-170 degrees indicated). 3.) INITIATES EPIP-5, "GENERAL EMERGENCY" Appendix H, "Initial - Protective Action Recommendations," and determines that RECOMMENDATION 2 is applicable. Validation Time: 20 minutes Time Critical: Yes X No ==============================================================================================

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5 NRC EXAM 2013-302 Page 3 of 11 EVALUATION SHEET 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 5 NRC EXAM 2013-302 Page 4 of 11 Tools/Equipment/Procedures Needed: NRC REFERENCE DISK. *NOTE: This JPM is designed to be performed in a classroom with procedures available to the applicant via a laptop computer loaded with the NRC REFERENCE DISK. EXAMINER: Multiple copies of each of the following forms will be available for use by the applicants: EPIP-2, "Notification of Unusual Event," Appendix A, "Notification of Unusual Event Initial Notification Form," and Appendix B, "State of Tennessee Notification." EPIP-3, "Alert," Appendix A, "Alert Notification Form," and Appendix B, "State of Tennessee Notification." EPIP-4, "Site Area Emergency," Appendix A, "Site Area Emergency Initial Notification Form," and Appendix B, "State of Tennessee Notification." EPIP-5, "General Emergency," Appendix A, "General Emergency Initial Notification Form," Appendix B, "State of Tennessee Notification," and Appendix H, "Initial - Protective Action Recommendations."

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5 NRC EXAM 2013-302 Page 5 of 11 READ TO THE APPLICANT:

DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. 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 1 was shut down due to increasing RCS activity. 2. Indications of a primary system leak developed during the shutdown. 3. A safety injection was manually initiated during the performance of AOI-6, "Small Reactor Coolant System Leak" due to a imminent loss of pressurizer level with charging flow at 150 gpm and letdown isolated. 4. The operators are performing actions of E-0, "Reactor Trip or Safety Injection." 5. The following conditions currently exist: a. Containment pressure is +0.11 psid and steady.

b. Containment Sump level is not increasing.

c. Several RHR/CVCS Pipe Break Status lights are now LIT. d. 0-RM-90-101B, AUX BLDG VENT is increasing rapidly. e. Several Area Rad Monitors on elevation 692 and 713 are in Hi Rad. f. Chemistry reports a step rise in the RCS activity to 311 µCi/gm dose equivalent Iodine 131. g. Wind is from 125 degrees, and speed is 15 mph. 6. You are the Site Emergency Director. INITIATING CUES: DO NOT USE SED JUDGEMENT AS A BASIS FOR CLASSIFICATION. 1. Based on the information provided to you, classify the event. Record your EAL(s) in the space below. RAISE YOUR HAND when your classification is complete. 2. Complete the associated TVA Initial Classification form. 3. Determine what, if any, Protective Action Recommendations are required. 4. RAISE YOUR HAND when you have completed the notification form. Element(s) of this task is/are time critical.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5 NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 6 of 11 START TIME: _______ STEP 1: Determines that a GENERAL EMERGENCY must be classified per EALs 1.1.2 Loss, 1.2.2, Potential Loss and 1.3.2 Loss. STANDARD: Applicant refers to EPIP-1, "Emergency Plan Classification Logic," and determines that conditions require the declaration of a GENERAL EMERGENCY. 1.1.2 LOSS, "RCS sample activity is greater than 300 µCi/gm dose equivalent I-131." 1.2.2 POTENTIAL LOSS, "Non Isolatable RCS leak exceeding the capacity of one charging pump in the normal charging alignment." 1.3.2 LOSS, "Containment pressure or sump level not increasing with a LOCA in progress." Based on "Emergency Class Criteria", the applicant determines the need to declare a General Emergency, based on Loss of two barriers and potential loss of the third barrier. Step is critical for the EALs to be correctly identified and the declaration made within 15 minutes. RECORD time that declaration was made:_________ COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5 NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 11 STEP 2: INITIATES EPIP-5, "GENERAL EMERGENCY" Appendix A, "General Emergency Initial Notification Form." STANDARD: Applicant completes EPIP-5, Appendix A, ""General Emergency Initial Notification Form," within 15 minutes of initial event classification. Critical elements that must appear on Appendix A form: Item 3. - EAL Designators - 1.1.2 Loss, 1.2.2, Potential Loss and 1.3.2 Loss. Item 4. - Brief Description of the Event - Fuel Clad barrier breach, with a concurrent loss of coolant greater than the capacity of the CCP and indications of a LOCA Outside Containment. (Applicant description will vary) Item 5. - Radiological Conditions - EITHER "Minor releases within federally approved limits" OR "Release Information not known" checked or otherwise indicated on form. Item 6. - Time that applicant declared the event and the date. Item 7. - Meteorological Conditions. Wind Speed and direction correctly entered. (15 mph and 125 degrees). Item 8. - Recommendation 2 selected, and the proper area to be evacuated indicated on the form (110-170 degrees indicated). COMMENTS:

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

Page 8 of 11 5 S KEY DO NOT HAND TO APPLICANT

Page 9 of 11 5 S BLANK FORMS

WBN Unit 0 Notification of Unusual Event EPIP-2 Rev. 0031 Page 12 of 22 Appendix A (Page 1 of 1) Notification of Unusual Event Initial Notification Form 1. This is a Drill This is an Actual Event - Repeat - This is an Actual Event 2. _______________________ the SED at Watts Bar has declared a NOTIFICATION OF UNUSUAL EVENT. 3. EAL Designator: _____________________________(USE ONLY ONE EAL DESIGNATOR) 4. Brief Description of the Event: ______________________________________________________________________________________

__________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________ 5. Radiological Conditions: (Check one under both Airborne and Liquid column.) Airborne Releases Offsite Liquid Releases Offsite Minor releases within federally approved limits1 Minor releases within federally approved limits1 Releases above federally approved limits1 Releases above federally approved limits1 Release information not known (1Tech Specs/ODCM) Release information not known (1Tech Specs/ODCM) 6. Event Declared: Time:________________ Eastern Time Date:__________________ 7. Protective Action Recommendation: None Completed By : ________________________________________ Approved By: ________________________________________

WBN Unit 0 Alert EPIP-3 Rev. 0037 Page 13 of 28 Appendix A (Page 1 of 1) Alert Initial Notification Form 1. This is a Drill This is an Actual Event - Repeat - This is an Actual Event 2. __________________, the SED at Watts Bar has declared an ALERT 3. EAL Designator: ________________________________ 4. Brief Description of the Event: ________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________ 5. Radiological Conditions: (Check one under both Airborne and Liquid column.) Airborne Releases Offsite Liquid Releases Offsite Minor releases within federally approved limits1 Minor releases within federally approved limits1 Releases above federally approved limits1 Releases above federally approved limits1 Release information not known (1Tech Specs/ODCM) Release information not known (1Tech Specs/ODCM) 6. Event Declared: Time:________________ Eastern Time Date:__________________ 7. Protective Action Recommendation: None Completed by: ____________________________________________ Approved by: ____________________________________________

WBN Unit 0 Site Area Emergency EPIP-4 Rev. 0035 Page 13 of 26 Appendix A (Page 1 of 1) Site Area Emergency Initial Notification Form 1. This is a Drill This is an Actual Event - Repeat - This is an Actual Event 2. ____________________ the SED at Watts Bar has declared a Site Area Emergency 3. EAL Designator: ________________________________ 4. Brief Description of the Event: ________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________ 5. Radiological Conditions: (Check one under both Airborne and Liquid column.) Airborne Releases Offsite Liquid Releases Offsite Minor releases within federally approved limits1 Minor releases within federally approved limits1 Releases above federally approved limits1 Releases above federally approved limits1 Release information not known (1Tech Specs/ODCM) Release information not known (1Tech Specs/ODCM) 6. Event Declared: Time:________________ Eastern Time Date:__________________ 7. Provide Protective Action Recommendation: None Completed By: _______________________________________ Approved By: _______________________________________

WBN Unit 0 General Emergency EPIP-5 Rev. 0041 Page 14 of 31 Appendix A (Page 1 of 1) General Emergency Initial Notification Form 1. This is a Drill This is an Actual Event - Repeat - This is an Actual Event 2. ___________________,the SED at Watts Bar has declared a GENERAL EMERGENCY 3. EAL Designator(s):_______________________(Use three EAL designators when using the Fission Product Barrier Matrix.) 4. Brief Description of the Event:_____________________________________________________________

________________________________________________________________________________________

5. Radiological Conditions: (Check one under both Airborne and Liquid column.) Airborne Releases Offsite Liquid Releases Offsite Minor releases within federally approved limits1 Releases above federally approved limits1 Release information not known (1Tech Specs/ODCM) Minor releases within federally approved limits1 Releases above federally approved limits1 Release information not known (1Tech Specs/ODCM) 6. Event Declared: Time:__________________ Date:_____________________ 7. The Meteorological Conditions are: (Use 46 meter data from the Met Tower. IF data is NOT available from the MET tower, contact the National Weather Service by dialing 9-1-423-586-8400. The National Weather Service will provide wind direction and wind speed.) Wind Direction is FROM:_____________degrees (15 minute average) Wind Speed: ______________m.p.h (15 minute average)

8. Provide Protective Action Recommendation utilizing Appendix H: (Check either 1 or 2 or 3) Recommendation 1 RECOMENDATION 1 WIND FROM DEGREES (Mark wind direction from step 7) RECOMENDATION 2 Recommendation 2 EVACUATE LISTED SECTORS (2 mile Radius and 10 miles downwind) EVACUATE LISTED SECTORS(2 mile Radius and 5 miles downwind) SHELTER remainder of 10 mile EPZ SHELTER remainder of 10 mile EPZ CONSIDER issuance of POTASSIUM IODIDE in accordance with the State Plan CONSIDER issuance of POTASSIUM IODIDE in accordance with the State Plan A1, B1, C1, D1, C7, C9, D2, D4, D5, D6, D7, D8, D9 From 26-68 A1, B1, C1, D1, C7, D2, D4, D5 A1, B1, C1, D1, A3, A4, D2, D3, D4, D5, D6, D7, D8, D9 From 69-110 A1, B1, C1, D1, A3, D2, D4, D5 A1, B1, C1, D1, A2, A3, A4, A5, A6, A7, D2, D3, D5, D6 From 111-170 A1, B1, C1, D1, A2, A3, D2, D5 A1, B1, C1, D1, A2, A3, A5, A6, A7, B2, B3, B4, B5, C2 From 171-230 A1, B1, C1, D1, A2, A3, B2, B4, C2 A1, B1, C1, D1, B2, B3, B4, B5, C2, C3, From 231-270 A1, B1, C1, D1, B2, B4, C2 A1, B1, C1, D1, B2, B3, C2, C3, C4, C5, C6, C11 From 271-325 A1, B1, C1, D1, B2, C2, C4, C5, A1, B1, C1, D1, C2, C4, C5, C6, C7, C8, C9, C10, C11, D4, D9 From 326-25 A1, B1, C1, D1, C2, C4, C5, C7, C8, D4 Recommendation 3 SHELTER all sectors CONSIDER issuance of POTASSIUM IODIDE in accordance with the State Plan Completed by ______________ Approved by (SED)________________

WBN Unit 0 General Emergency EPIP-5 Rev. 0041 Page 27 of 31 Appendix H (Page 1 of 2) Initial - Protective Action Recommendations WBN Unit 0 General Emergency EPIP-5 Rev. 0041 Page 28 of 31 Appendix H (Page 2 of 2) Initial - Protective Action Recommendations 5 S Handout Package for Applicant APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) 5 INITIAL CONDITIONS: 1. Unit 1 was shut down due to increasing RCS activity. 2. Indications of a primary system leak developed during the shutdown. 3. A safety injection was manually initiated during the performance of AOI-6, "Small Reactor Coolant System Leak" due to a imminent loss of pressurizer level with charging flow at 150 gpm and letdown isolated. 4. The operators are performing actions of E-0, "Reactor Trip or Safety Injection." 5. The following conditions currently exist: a. Containment pressure is +0.11 psid and steady.

b. Containment Sump level is not increasing.

c. Several RHR/CVCS Pipe Break Status lights are now LIT. d. 0-RM-90-101B, AUX BLDG VENT is increasing rapidly. e. Several Area Rad Monitors on elevation 692 and 713 are in Hi Rad. f. Chemistry reports a step rise in the RCS activity to 311 µCi/gm dose equivalent Iodine 131. g. Wind is from 125 degrees, and speed is 15 mph. 6. You are the Site Emergency Director. INITIATING CUES: DO NOT USE SED JUDGEMENT AS A BASIS FOR CLASSIFICATION. 1. Based on the information provided to you, classify the event. Record your EAL(s) in the space below. RAISE YOUR HAND when your classification is complete. 2. Complete the associated TVA Initial Classification form. 3. Determine what, if any, Protective Action Recommendations are required. 4. RAISE YOUR HAND when you have completed the notification form. Element(s) of this task is/are time critical. CLASSIFICATION (EAL(s) _________________________EXAMINERS INITIALS _______ TIME ______ APPENDIX A COMPLETION TIME _________ EXAMINERS INITIALS _______