ML13210A050

Initial Exam 2013-301 Draft Administrative JPMs

ML13210A050
Person / Time
Site:	Watts Bar
Issue date:	07/26/2013
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
50-390/10-301
Download: ML13210A050 (89)

Text

Watts Bar Nuclear Plant 2013-03 NRC Exam Administrative JPM 1 R

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1R 2013-03 NRC Exam EVALUATION SHEET Task: CALCULATE TARGET BORON (CB) FOR LOAD ESCALATION Alternate Path: n/a Facility JPM #: Modified A.1-2 Safety Function: 2.3

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:

1.) SOI-62.02, Boron Concentration Control, Rev. 55 2.) Nuclear Parameters & Operations Package (NuPOP) WCAP-17401-P, Watts Bar Unit 1 Cycle 11, Rev. 1 Task Number: RO-062-SOI-62-016

Title:

Perform dilution of the Reactor Coolant system.

Task Standard: The applicant completes the calculations required by SOI-62.02, Appendix E REACTIVITY BALANCE CALCULATION, The target RCS Boron Concentration is determined to be 572.5 ppm (acceptable range 563 to 580.5 ppm).

Validation Time: 20 minutes Time Critical: Yes No X

===============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==============================================================

=

COMMENTS PAGE 2 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1R 2013-03 NRC Exam Tools/Equipment/Procedures Needed:

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

1. Copy of XENON CALCULATION WATTS BAR UNIT 1 CYCLE 11 MOL NIX XENON DATA for power change from 80% to 100% at 2%/min.

2. Copy of SOI-62.02, Boron Concentration Control, Appendix E, Reactivity Balance Calculation.

3. NRC REFERENCE DISK.

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

PAGE 3 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1R 2013-03 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 1 is operating at 80% power.

2. Core average burnup is 8000 MWD/MTU, middle-of-life.

3. Control Bank D rods are at 190 steps.

4. RCS boron concentration is 600 ppm

5. Target rod position at 100% power is 220 steps on Control Bank D

6. Power will be raised at 2% per hour.

7. Xenon printout from REACTINW has been performed by an STA and is provided with this cue sheet.

INITIATING CUES:

The Shift Manager has directed you to calculate the target boron concentration for raising power to 100% per SOI-62.02, Appendix E, Reactivity Balance Calculation.

PAGE 4 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1R 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

EXAMINER JPM Steps 1 through 5 evaluate the applicants completion of the first page of Appendix E.

STEP 1: [1] CALCULATE Target CB by performing the following: ___ SAT Obtains: Current RCS Boron CB: __________PPM. ___ UNSAT STANDARD:

Applicant enters 600 ppm from the INITIAL CONDITIONS provided on the APPLICANT CUE SHEET.

COMMENTS:

STEP 2: Enters: Core Burnup: _______MWD/MTU ___ SAT

___ UNSAT STANDARD:

Applicant enters value 8000 from the INITIAL CONDITIONS provided on the APPLICANT CUE SHEET.

COMMENTS:

PAGE 5 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1R 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: Enters: CRITICAL STEP Initial Reactor power = ________ %

Final Reactor power = _________ % ___ SAT Calculates: Total Reactor Power change: _______% ___ UNSAT STANDARD:

Applicant enters target reactor power value from the INITIAL CONDITIONS provided on the APPLICANT CUE SHEET Initial Reactor Power = 80%.

Final Reactor Power = 100%.

Applicant determines total power change to be 20%.

Step is critical since the change in power is the basis for the calculation.

COMMENTS:

PAGE 6 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1R 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: Enters: ___ SAT Rate of Reactor Power change: ________ %/hr ___ UNSAT Number of hours to change power: ________ hr(s)

STANDARD:

Applicant determines rate of reactor power change to be 2% per hour from the INITIAL CONDITIONS provided on the APPLICANT CUE SHEET.

Applicant calculates number of hours projected to reach target power as 10 hrs.

COMMENTS:

STEP 5: Obtains: ___ SAT Current Rod Position: _________ steps ___ UNSAT Final Rod Position: _________ steps STANDARD:

Applicant determines current rod position is 190 steps from the INITIAL CONDITIONS provided on the Applicant Cue Sheet.

Applicant determines final rod position is 220 steps from the INITIAL CONDITIONS provided on the Applicant Cue Sheet.

COMMENTS:

EXAMINER JPM Steps 6 through 11 evaluate the applicants completion of the second page of Appendix E.

PAGE 7 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1R 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: Determines Power Defect. CRITICAL STEP NOTE: Must be entered into equation as a positive value Power Defect From NUPOP, from Table 7-17, 7-18, or 7-19 ___ SAT 1789 pcm PD - 2230 pcm PD = -441 pcm Power Defect ___ UNSAT Initial Final STANDARD:

Applicant determines the following:

The value for initial power level is 1789 pcm from Table 7-18.

The value for the final power level as 2230 pcm from Table 7-18, and enters the values in appropriate table locations.

Applicant then calculates Power Defect by algebraically subtracting the Final Power Defect from Initial Power Defect. The value determined is -441 pcm.

Step is critical since the change in power defect is one of the parameters that are the basis for the calculation.

COMMENTS:

PAGE 8 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1R 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: Determines Xenon. CRITICAL STEP NOTE: Must be entered into equation as a positive value Initial Xenon From REACTW (either current conditions or projection ___ SAT to initial condition).

Final Xenon: From REACTW (projection over time). ___ UNSAT 2739.7 pcm XE - 2621.5 pcm XE = 118.2 pcm Xenon Initial Final STANDARD: Applicant determines the following:

Xenon for the initial power level is -2739.7 pcm from Xenon REACTW printout and enters 2739.7 in appropriate table locations.

Xenon for final power level as -2621.5 pcm from the same printout, and enters 2621.5 in appropriate table locations.

Applicant then calculates Xenon by algebraically subtracting Final Xenon from Initial Xenon. The value determined is 118.2 pcm.

Step is critical since the change in xenon is one of the parameters that are the basis for the calculation.

COMMENTS:

PAGE 9 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1R 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8 Determines rods. CRITICAL STEP NOTE Must be entered into equation as a positive value Rods Integral worth From NUPOP, Figure 6-24, Figure 6-25, or Figure 6-26. ___ SAT 150 pcm Rods - 0 pcm Rods = 150 pcm Rods ___ UNSAT Initial Final STANDARD: Applicant determines Initial Integral Rod Worth for current rod position as 150 pcm (accept 100 to 200 pcm) from NUPOP Figure 6-24.

Applicant determines Final Integral Rod Worth as 0 pcm (accept 0 to 10 pcm) from the same figure, and enters the values in appropriate table locations.

Applicant calculates Rods by algebraically subtracting Final Integral Rod Worth from Initial Integral Rod Worth.

The value determined is 150 pcm (accept 90 to 200 pcm).

Step is critical since the change in rods is one of the parameters that are the basis for the calculation.

COMMENTS:

PAGE 10 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1R 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9: Determines . CRITICAL STEP Add reactivity values to determine pcm adjustment to be made by changing CB. (NOTE: Watch the signs.) ___ SAT

___ UNSAT STANDARD: Applicant adds values entered for:

POWER DEFECT = (-441 pcm)

XENON = (118.2 pcm)

RODS = (150 pcm) (accept 90 to 200 pcm) and enters a value of -172.8 pcm (accept -232.8 to -122.8 pcm) as the SUM.

Step is critical since this is the reactivity change required to accomplish the power change.

COMMENTS:

PAGE 11 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1R 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 10: Converts to PPM . CRITICAL STEP (NUPOP Figure 6-21) -159 ppm/% (Inverse Boron Worth) X -172.8 pcm (needed) X 0.001 %/cm = 27.5 ppm ___ SAT STANDARD: Applicant converts the reactivity change into a boron ___ UNSAT concentration change using the equation provided.

Applicant determines Inverse Boron Worth from NUPOP Figure 6-21 to be -159 pcm/% (accept -158.5 to -159.5 pcm/%) at 8000 MWD/MTU. After performing the indicated calculation, the applicant determines the change in boron concentration to be 27.5 ppm (accept 19.5 to 37 ppm).

Step is critical to determine the boron concentration change required to accomplish the power change.

COMMENTS:

STEP 11: Determines TARGET PPM. CRITICAL STEP 600 Current RCS CB 27.5 Total CB = 572.5 ppm

___ SAT STANDARD: Applicant determines Target Boron Concentration performing the indicated calculation and determines the ___ UNSAT TARGET PPM is 572.5 ppm (accept 563 to 580.5 ppm).

Step is critical since this is the target boron required for the planned power escalation.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 12 0F 16

1R KEY DO NOT HAND TO APPLICANT

1R Handout Package for Applicant

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

INITIAL CONDITIONS:

1. Unit 1 is operating at 80% power.

2. Core average burnup is 8000 MWD/MTU, middle-of-life.

3. Control Bank D rods are at 190 steps.

4. RCS boron concentration is 600 ppm

5. Target rod position at 100% power will be 220 steps on Control Bank D

6. Power will be raised at 2% per hour.

7. Xenon printout from REACTINW has been performed by an STA and is provided with this cue sheet.

INITIATING CUES:

The Shift Manager has directed you to calculate the target boron concentration for raising power to 100% per SOI-62.02, Appendix E, Reactivity Balance Calculation.

1R

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

[REACTW - VERS WB3.4]

XENON CALCULATION WATTS BAR UNIT 1 CYCLE 11 MOL NIX XENON DATA XE DEL XE TIME POWER XE I WORTH WORTH (HRS) (%) (% EQ) (% EQ) (PCM) (PCM)

.0 80.0 93.2 80.0 -2739.7 .0 1.0 82.0 92.9 80.2 -2732.2 7.5 2.0 84.0 92.5 80.6 -2720.0 12.2 3.0 86.0 92.0 81.1 -2705.3 14.7 4.0 88.0 91.5 81.8 -2689.6 15.7 5.0 90.0 91.0 82.6 -2674.2 15.4 6.0 92.0 90.5 83.6 -2659.8 14.4 7.0 94.0 90.0 84.6 -2647.0 12.8 8.0 96.0 89.7 85.7 -2636.3 10.7 9.0 98.0 89.4 87.0 -2627.8 8.5 10.0 100.0 89.2 88.3 -2621.5 6.3 1R

Watts Bar Nuclear Plant 2013-03 NRC Exam Administrative JPM 1 S

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2013-03 NRC Exam EVALUATION SHEET Task: PERFORM FR-I.3, VOIDS IN THE REACTOR VESSEL, APPENDIX D, MAXIMUM VENT TIME CALCULATION.

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

Title:

Conduct of Operations K/A 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Rating(s): 4.3/4.4 CFR: 41.10 / 43.5 / 45.2/45.6 Evaluation Method: Simulator In-Plant Classroom X

References:

FR-I.3, Voids in the Reactor Vessel, Rev.

Task Number: RO-113-FR-I.3-001

Title:

Respond to voids in the reactor vessel.

Task Standard: The applicant performs the calculations contained in FR-I.3, Voids in the Reactor Vessel, and determines the vent time to be 2.38 minutes (acceptable range 2.2 to 2.55 minutes).

Validation Time: 15 minutes Time Critical: Yes No X

===============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==============================================================

=

COMMENTS

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2013-03 NRC Exam Tools/Equipment/Procedures Needed:

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

1. FR-I.3, Voids in Reactor Vessel, Figure 1, Hydrogen Flow Rate vs. RCS Pressure.

2. FR-I.3, Voids in Reactor Vessel, Appendix D, Maximum Vent Time Calculation.

3. 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 1S 2013-03 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

The plant was at 100 percent power when a Small Break LOCA occurred.

• All RCPs have been secured.

• SI has been terminated.

• RVLlS is indicating 85 percent

• Pressurizer level is 94 percent

• 1-PI-68-62 RCS Pressure is 600 psig

• Lower Containment Temperature is 200°F

• Chemistry reports that Containment Hydrogen Concentration is 1.5 percent Based on the present conditions a void has formed in the Reactor Vessel. The US and STA have reviewed FR-0, Status Trees.

It was determined that FR-I.3, Voids In Reactor Vessel, should be implemented.

The crew has completed preparing the Containment for Reactor Vessel venting.

INITIATING CUE:

Based on the information provided, you are to complete FR-I.3, Voids in Reactor Vessel, Appendix D, Maximum Vent Time Calculation.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

EXAMINER: The following actions are taken from FR-I.3, Voids in Reactor Vessel, Appendix D, Maximum Vent Time Calculation.

STEP 1: A. RECORD Lower cntmt temp. ___ SAT STANDARD: ___ UNSAT Applicant records 200 F from the INITIAL CONDITIONS.

COMMENTS:

STEP 2: B. RECORD Cntmt hydrogen concentration (CHECK which ___ SAT instrument used):

___ UNSAT 1-H2I-43-200 ___ 1-H2I-43-210 ___ Chemistry Sample ___

STANDARD:

Applicant enters 1.5% from the Chemistry Sample provided in the INITIAL CONDITIONS in Item 2 blank.

Applicant marks Chemistry Sample as the source of the Cntmt hydrogen concentration.

COMMENTS:

PAGE 5 0F 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: C. CONVERT Item 1 from °F to °R: ___ SAT

___ UNSAT STANDARD:

Applicant adds 200 F to 460 and determines the converted value to be 660 R.

COMMENTS:

STEP 4: D. CALCULATE available lower cntmt air volume based on CRITICAL current cntmt temperature. STEP

___ SAT

___ UNSAT STANDARD:

Applicant performs the mathematical operations and determines available lower containment volume to be 285,509 cu. ft.

Acceptable range for lower containment volume is 283,420 cu. ft.

to 287250 cu. ft.

Step is critical to ensure proper void calculation is performed.

COMMENTS:

PAGE 6 0F 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: E. CALCULATE max hydrogen volume that can be vented CRITICAL and maintain cntmt hydrogen less than 3%. STEP

___ SAT

___ UNSAT STANDARD:

Applicant performs the mathematical operations and determines max hydrogen volume that can be vented and maintain cntmt hydrogen less than 3% to be 4282.6 cu. ft.

Acceptable range for lower containment volume is 4251 cu. ft. to 4309 cu. ft.

Step is critical to ensure proper void calculation is performed.

COMMENTS:

STEP 6: F. RECORD RCS press (CHECK which instrument used): ___ SAT 1-PI-68-66A___ 1-PI-68-62 ___ ___ UNSAT STANDARD:

Applicant determines from the INITIAL CONDITIONS that 1-PI-68-62 is indicating 600 psig COMMENTS:

PAGE 7 0F 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: G. DETERMINE hydrogen flow rate from Figure 1 and Item 6: CRITICAL STEP STANDARD:

___ SAT Applicant determines hydrogen flow rate from Figure 1, Hydrogen Flow Rate vs. RCS Pressure. Based on the RCS pressure of 600 ___ UNSAT psig, the applicant determines the hydrogen flow rate to be 1800 SCFM.

Acceptable range for hydrogen flow rate is 1700 SCFM to 1900 SCFM.

Step is critical to ensure proper void calculation is performed COMMENTS:

PAGE 8 0F 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1S 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8: H. CALCULATE maximum venting time: CRITICAL STEP

1. DETERMINE vent time based on calculation in this Appendix. ___ SAT

___ UNSAT STANDARD:

Applicant performs the mathematical operations and determines vent time to be 2.38 minutes.

Acceptable range for lower containment volume is 2.2 to 2.5 minutes.

Step is critical to ensure that the maximum venting time properly calculated, and that hydrogen concentration will be maintained below 3% during the venting process.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 9 0F 12

1S KEY DO NOT HAND TO APPLICANT 1S

1S Handout Package for Applicant 1S

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

INITIAL CONDITIONS:

The plant was at 100 percent power when a Small Break LOCA occurred.

• All RCPs have been secured.

• SI has been terminated.

• RVLlS is indicating 85 percent

• Pressurizer level is 94 percent

• 1-PI-68-62 RCS Pressure is 600 psig

• Lower Containment Temperature is 200°F

• Chemistry reports that Containment Hydrogen Concentration is 1.5 percent Based on the present conditions a void has formed in the Reactor Vessel. The US and STA have reviewed FR-0, Status Trees.

It was determined that FR-I.3, Voids In Reactor Vessel, should be implemented.

The crew has completed preparing the Containment for Reactor Vessel venting.

INITIATING CUE:

Based on the information provided, you are to complete FR-I.3, Voids in Reactor Vessel, Appendix D, Maximum Vent Time Calculation.

1S

Watts Bar Nuclear Plant 2013-03 NRC Exam Administrative JPM 2

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2

2013-03 NRC Exam EVALUATION SHEET Task: EVALUATE CRITICAL SAFETY FUNCTION STATUS TREES.

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

Title:

Conduct of Operations K/A 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Rating(s): 4.4/4.7 CFR: 41.5 / 43.5 / 45.12 / 45.13 Evaluation Method: Simulator In-Plant Classroom X*

References:

FR-0, Status Trees, Rev.14.

Task Number: STA-113-FR-0-001

Title:

Analyze plant conditions utilizing status trees and/or Integrated Computer System.

Task Standard: The applicant evaluates parameters supplied in Table 1 of the JPM and determines the following:

1. Status Tree Priority:

FR-S - ORANGE FR-C - GREEN FR-H - YELLOW FR-P - ORANGE FR-Z - GREEN FR-I - GREEN

2. 1-FR-S.1, Nuclear Power Generation/ATWS, is the highest priority CSFST.

Validation Time: 15 minutes Time Critical: Yes No X

=

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==============================================================

=

COMMENTS Page 2 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2

2013-03 NRC Exam Tools/Equipment/Procedures Needed:

The following information will be handed out to each applicant:

1. FR-0, Status Trees, Rev.14.

2. NRC REFERENCE DISK.

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

Page 3 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2

2013-03 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 1 tripped from 100% power.

2. A Safety Injection occurred 30 minutes ago.

3. The crew is performing actions in E-1, Loss of Reactor or Secondary Coolant.

4. The SPDS computer is NOT available for monitoring Critical Safety Functions.

5. Containment Phase B has NOT actuated.

INITIATING CUE:

You have been directed perform the initial manual evaluation the Critical Safety Functions using FR-0, Status Trees, based on the values provided in TABLE 1 (attached.).

1. Document each Critical Safety Function evaluation performed in FR-0, Status Trees.

2. Report the highest priority Function Restoration Procedure (FR) required to be implemented, if any.

Page 4 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2

2013-03 NRC Exam TABLE 1 Instrument Parameter Channel I or Channel II or Channel III Channel IV Train A Train B Power Range NI 0 0 0 0 Intermediate Range NI 4 x 10-3% 2.5 x 10-3%

Intermediate Range NI SUR +0.2 +0.3 Source Range NI 0 0 Source Range SUR 0 0 RCS Pressure 1485 psig 1435 psig Highest Core Exit 340 F 338 F Thermocouple RCS Subcooling 256 F 253 F PZR Level 2% 4% 7%

CNTMT Pressure 2.4 psig 2.1 psig 2.2 psig 1.9 psig CNTMT Sump Level 4% 5% 5% 6%

CNTMT Radiation (High 3 R/hr 2 R/hr 1 R/hr 1 R/hr Range, Upper Level)

CNTMT Radiation (High 5 R/hr 8 R/hr 7 R/hr 4 R/hr Range, Lower Level)

Parameter RCS Loop 1 RCS Loop 2 RCS Loop 3 RCS Loop 4 SG Narrow Range Level 28% 32% 0% 22%

(all channels)

SG Pressure 850 psig 870 psig 100 psig 835 psig (all channels)

AFW Flow 110 gpm 90 gpm 0 gpm 180 gpm RCS Wide Range Cold Leg 400 F 410 F 228 F 390 F Temperature RCP Status Off Off Off Off Page 5 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2

2013-03 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: Evaluate SUBCRITICALITY FR-S Status Tree. CRITICAL STEP STANDARD:

___ SAT

___ UNSAT Applicant determines that an ORANGE path exists on FR-S Status Tree, and that FR-S.1, Nuclear Power Generation/ATWS, is required to be entered.

The step is critical to properly evaluate FR-0, Status Trees, to determine that an ORANGE path condition exists. This is the highest priority FR for the conditions given. If this is not evaluated properly, a transition to a lower level procedure could occur, and the highest priority FR would not be implemented.

COMMENTS:

Page 6 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2

2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2: Evaluate CORE COOLING FR-C Status Tree. CRITICAL STEP STANDARD: ___ SAT

___ UNSAT Applicant determines that a GREEN path exists on FR-C Status Tree.

The step is critical to properly evaluate FR-0, Status Trees, to determine each CSF properly to complete task successfully. This CSF evaluation should determine the CSF color and procedure, if any, that apply.

COMMENTS:

Page 7 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2

2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: Evaluate HEAT SINK FR-H Status Tree. CRITICAL STEP STANDARD: ___ SAT

___ UNSAT Applicant determines that a YELLOW path exists on FR-H Status Tree.

The applicant notes that when no RED or ORANGE path exists, the YELLOW path Function Restoration Instruction can be implemented at the Operators discretion.

The step is critical to properly evaluate FR-0, Status Trees, to determine each CSF properly to complete task successfully. This CSF evaluation should determine the CSF color and procedure, if any, that apply.

COMMENTS:

Page 8 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2

2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: Evaluate PRESSURIZED THERMAL SHOCK FR-P Status CRITICAL Tree. STEP STANDARD: ___ SAT

___ UNSAT Applicant determines that an ORANGE path exists on FR-P Status Tree, and that FR-P.1, Pressurized Thermal Shock, is required to be entered.

The step is critical to properly evaluate FR-0, Status Trees, to determine each CSF properly to complete task successfully. This CSF evaluation should determine the CSF color and procedure, if any, that apply.

COMMENTS:

Page 9 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2

2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: Evaluate CONTAINMENT FR-Z Status Tree. CRITICAL STEP STANDARD:

___ SAT

___ UNSAT Applicant determines that a GREEN path exists on FR-Z Status Tree.

The step is critical to properly evaluate FR-0, Status Trees, to determine each CSF properly to complete task successfully. This CSF evaluation should determine the CSF color and procedure, if any, that apply.

COMMENTS:

Page 10 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2

2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: Evaluate INVENTORY FR-I Status Tree. CRITICAL STEP STANDARD:

___ SAT

___ UNSAT Applicant determines that a GREEN path exists on FR-I Status Tree.

The step is critical to properly evaluate FR-0, Status Trees, to determine each CSF properly to complete task successfully. This CSF evaluation should determine the CSF color and procedure, if any, that apply.

COMMENTS:

Page 11 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2

2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: Determination of priority of Critical Safety Functions. CRITICAL STEP STANDARD:

___ SAT Applicant evaluates the results of FR-0, Status Trees, and determines that FR-S, SUBCRITICALITY, is of the highest priority and that FR-S.1, ___ UNSAT Nuclear Power Generation/ATWS, must be implemented.

The step is critical to properly evaluate FR-0, Status Trees, to determine each CSF properly to complete task successfully. This CSF evaluation should determine the CSF color and procedure, if any, that apply.

COMMENTS:

END OF TASK STOP TIME ________

Page 12 of 16

2 KEY DO NOT HAND TO APPLICANT 2

2 Handout Package for Applicant 2

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

INITIAL CONDITIONS:

1. Unit 1 tripped from 100% power.

2. A Safety Injection occurred 30 minutes ago.

3. The crew is performing actions in E-1, Loss of Reactor or Secondary Coolant.

4. The SPDS computer is NOT available for monitoring Critical Safety Functions.

5. Containment Phase B has NOT actuated.

INITIATING CUE:

You have been directed perform the initial manual evaluation the Critical Safety Functions using FR-0, Status Trees, based on the values provided in TABLE 1 (attached.).

1. Document each Critical Safety Function evaluation performed in FR-0, Status Trees.

2. Report the highest priority Function Restoration Procedure (FR) required to be implemented, if any.

2

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

TABLE 1 Instrument Parameter Channel I or Channel II or Channel III Channel IV Train A Train B Power Range NI 0 0 0 0 Intermediate Range NI 4 x 10-3% 2.5 x 10-3%

Intermediate Range NI SUR +0.2 +0.3 Source Range NI 0 0 Source Range SUR 0 0 RCS Pressure 1485 psig 1435 psig Highest Core Exit 340 F 338 F Thermocouple RCS Subcooling 256 F 253 F PZR Level 2% 4% 7%

CNTMT Pressure 2.4 psig 2.1 psig 2.2 psig 1.9 psig CNTMT Sump Level 4% 5% 5% 6%

CNTMT Radiation (High 3 R/hr 2 R/hr 1 R/hr 1 R/hr Range, Upper Level)

CNTMT Radiation (High 5 R/hr 8 R/hr 7 R/hr 4 R/hr Range, Lower Level)

Parameter RCS Loop 1 RCS Loop 2 RCS Loop 3 RCS Loop 4 SG Narrow Range Level 28% 32% 0% 22%

(all channels)

SG Pressure 850 psig 870 psig 100 psig 835 psig (all channels)

AFW Flow 110 gpm 90 gpm 0 gpm 180 gpm RCS Wide Range Cold Leg 400 F 410 F 228 F 390 F Temperature RCP Status Off Off Off Off 2

Watts Bar Nuclear Plant 2013-03 NRC Exam Administrative JPM 3 R

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3R 2013-03 NRC Exam EVALUATION SHEET Task: PERFORM A CLEARANCE WITHOUT USE OF ESOMS COMPUTER.

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

Title:

Equipment Control K/A 2.2.13 Knowledge of tagging and clearance procedures.

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

References:

1.) 1-47W811-1, Mechanical Flow Diagram Safety Injection System, Rev. 50.

2.) NPG-SPP-10.2, Clearance Procedure to Safely Control Energy, Rev. 1 3.) TVA 17984 [11-2005]. CLEARANCE TAG LIST AND OPERATIONAL STEPS.

Task Number: RO-119-NOMS-010

Title:

Enter/edit devices held for active clearances.

Task Standard: The applicant:

1.) Identifies the handswitches, breakers and their required positions to electrically clear the 1B-B SI pump in preparation for relay replacement.

2). Identifies the components and positions required to isolate the correct section of piping in preparation for lubrication and oil sample collection of the 1B SI pump.

3.) Identifies the proper sequence of isolation of components.

Validation Time: 45 minutes Time Critical: Yes No X

=

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

=============================================================

==

COMMENTS Page 2 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3R 2013-03 NRC Exam Tools/Equipment/Procedures Needed:

PRINT HANDOUT containing:

1-45W724-1 through - 4 1-45W760-63-1 through - 9 1-47W811-1 through - 1A BLANK TVA 17984 [11-2005] Clearance Tag List and Operational Steps.

NRC REFERENCE DISK.

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

Page 3 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3R 2013-03 NRC Exam DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 1 is in Mode 1.

2. Electrical Maintenance will be replacing the 30X, 1X and 30RX relays in the 1B SI pump circuit. While relay replacement is in progress, the 1B SI pump will be lubricated and oil samples collected.

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

INITIATING CUES:

Using the references provided, manually prepare a TVA 17984 [11-2005],

Clearance Tag List and Operational Steps, to de-energize and isolate the 1B-B SI pump for relay replacement, cleaning and lubrication.

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

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

Page 4 of 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3R 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

EXAMINER: Control power fuses are REQUIRED to be pulled. Per NPG-SPP-10.2, Clearance Procedure to Safely Control Energy, Requirement O. states, Control power circuits shall be tagged if (1) the work is on the control circuit, (2) the proximity of the work is near the energized control circuit, or (3) there exists a possibility of grounding the control circuit.

Control power fuses are REQUIRED to be addressed to satisfy the CRITICAL STEP.

STEP 1: Applicant identifies components that must be operated to support CRITICAL replacing the 30X, 1X and 30RX relays in the 1B SI pump circuit, STEP lubricating and collecting oil samples from the 1B SI pump.

Applicant enters data in the Equipment ID, Equipment ___ SAT Description, Equipment Location Column.

___ UNSAT STANDARD:

The applicant completes Column 1 of the TVA 17984 [11-2005] form provided:

1-HS-63-15A, SIS PUMP 1B-B 1-M-6 1-HS-63-175A, SIP 1B-B RECIRC TO RWST, 1-M-6 1-BKR-63-15, SIP 1B-B (1-PMP-63-15), 6.9KV SD BD 1B-B, C/15 1-FU-211-B15/1N SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 1-FU-211-B15/1A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 1-FU-211-B15/2N SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 1-FU-211-B15/2A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 1-BKR-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, 480V RX MOV BD 1B1-B, C/13D 1-ISV-63-527, SI PUMP DISCHG ISOL, A7V/700 1-FCV-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, A6U/692 Step is critical to correctly isolate the electrical and mechanical portions of the system prior to work being performed.

COMMENTS:

Page 5 0f 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3R 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2: Applicant identifies components that must be operated to support CRITICAL replacing the 30X, 1X and 30RX relays in the 1B SI pump circuit, STEP lubricating and collecting oil samples from the 1B SI pump.

Applicant enters data in the Tag Type Column. ___ SAT STANDARD: ___ UNSAT The applicant completes Column 3 of the TVA 17984 [11-2005] form provided:

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

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

COMMENTS:

Page 6 0f 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3R 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: Applicant identifies components that must be operated to support CRITICAL replacing the 30X, 1X and 30RX relays in the 1B SI pump circuit, STEP lubricating and collecting oil samples from the 1B SI pump.

Applicant identifies enters data in the Place Seq. Column.

___ SAT STANDARD:

___ UNSAT The applicant completes Column 4 of the TVA 17984 [11-2005]

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

1-HS-63-15A, SIS PUMP 1B-B 1-M-6 (1) 1-HS-63-175A, SIP 1B-B RECIRC TO RWST, 1-M-6 (1) 1-BKR-63-15, SIP 1B-B (1-PMP-63-15), 6.9KV SD BD 1B-B, C/15 (2) 1-FU-211-B15/1N SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 (2) 1-FU-211-B15/1A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 (2) 1-FU-211-B15/2N SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15(2) 1-FU-211-B15/2A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 (2) 1-BKR-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, 480V RX MOV BD 1B1-B, C/13D (3) 1-ISV-63-527, SI PUMP DISCHG ISOL, A7V/700 (4) 1-FCV-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, A6U/692 (4)

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

NOTE: Sequence variations are allowed as long as the sequence does not result in Mechanical Isolations prior to Electrical isolations.

COMMENTS:

Page 7 0f 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3R 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: Applicant identifies components that must be operated to support CRITICAL replacing the 30X, 1X and 30RX relays in the 1B SI pump circuit, STEP lubricating and collecting oil samples from the 1B SI pump SAFELY. Applicant enters the correct position in the Place Config. Column. ___ SAT STANDARD: ___ UNSAT The applicant completes Column 5 of the TVA 17984 [11-2005]

form by listings the following POSITION for each of the following components:

1-HS-63-15A, SIS PUMP 1B-B 1-M-6, - PULL-TO-LOCK 1-HS-63-175A, SIP 1B-B RECIRC TO RWST, 1-M MID POSITION AFTER CLOSE 1-BKR-63-15, SIP 1B-B (1-PMP-63-15), 6.9KV SD BD 1B-B, C/15 -

RACKED DOWN 1-FU-211-B15/1N SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 REMOVED 1-FU-211-B15/1A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 REMOVED 1-FU-211-B15/2NSIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 REMOVED 1-FU-211-B15/2A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 REMOVED 1-BKR-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, 480V RX MOV BD 1B1-B, C/13D - OFF 1-ISV-63-527, SI PUMP DISCHG ISOL, A7V/700 - CLOSED 1-FCV-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, A6U/692 - CLOSED Step is critical to correctly de-energize and isolate the portion of the system prior to work being performed.

COMMENTS:

END OF TASK STOP TIME ________

Page 8 0f 11

3R KEY DO NOT HAND TO APPLICANT 3R

3R Handout Package for Applicant 3R

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

INITIAL CONDITIONS:

1. Unit 1 is in Mode 1.

2. Electrical Maintenance will be replacing the 30X, 1X and 30RX relays in the 1B SI pump circuit. While relay replacement is in progress, the 1B SI pump will be lubricated and oil samples collected.

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

INITIATING CUES:

Using the references provided, manually prepare a TVA 17984 [11-2005],

Clearance Tag List and Operational Steps, to de-energize and isolate the 1B-B SI pump for relay replacement, cleaning and lubrication.

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

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

3R

Watts Bar Nuclear Plant 2013-03 NRC Exam Administrative JPM 3 S

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2013-03 NRC Exam EVALUATION SHEET Task: PERFORM A CLEARANCE WITHOUT USE OF ESOMS COMPUTER.

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

Title:

Equipment Control K/A 2.2.13 Knowledge of tagging and clearance procedures.

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

References:

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

2.) NPG-SPP-10.2, Clearance Procedure to Safely Control Energy, Rev. 1 3.) TVA 17984 [11-2005]. CLEARANCE TAG LIST AND OPERATIONAL STEPS.

Task Number: RO-119-NOMS-010

Title:

Enter/edit devices held for active clearances.

Task Standard: The applicant:

1.) Identifies the handswitches, breakers and their required positions to electrically clear the 1B-B SI pump in preparation for relay replacement.

2). Identifies the components and positions required to isolate the correct section of piping in preparation for cleaning and lubrication of the 1B SI pump.

3.) Identifies the proper sequence of isolation of components.

4.) Determines that the failure of the 1A-A SI pump room cooler requires entry into LCO 3.0.3, and the plant needs to be in Mode 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

Validation Time: 45 minutes Time Critical: Yes No X

=

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

=============================================================

==

COMMENTS PAGE 2 OF 13

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2013-03 NRC Exam Tools/Equipment/Procedures Needed:

PRINT HANDOUT containing:

1-45W724-1 through - 4 1-45W760-63-1 through - 9 1-47W811-1 through - 1A BLANK TVA 17984 [11-2005] Clearance Tag List and Operational Steps.

NRC REFERENCE DISK.

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

PAGE 3 OF 13

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2013-03 NRC Exam DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 1 is in Mode 3 with RCS pressure at 1000 psig and RCS temperature at 380F.

2. Electrical Maintenance will be replacing the 30X, 1X and 30RX relays in the 1B SI pump circuit. While relay replacement is in progress, the 1B SI pump will be lubricated and oil samples collected.

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

INITIATING CUES:

Part 1 - Using the references provided, manually prepare a TVA 17984

[11-2005], Clearance Tag List and Operational Steps, to de-energize and isolate the 1B-B SI pump for relay replacement, cleaning and lubrication.

NOTE: Complete the first, third, fourth, and fifth columns on TVA 17984 [11-2005], Clearance Tag List and Operational Steps.

ASSUME WORK IS NOW IN PROGRESS ON THE 1B-B SI PUMP.

Part 2 - The Auxiliary Building AUO reports the ERCW supply line to the 1A SI Pump room cooler has ruptured. Local actions have been taken to isolate the leak.

What, if any, Technical Specifications/Technical Requirements must be entered due to the failure of the 1A-A SI Pump Room Cooler? What, if any, actions are required to be taken?

PAGE 4 OF 13

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

EXAMINER: Control power fuses are REQUIRED to be pulled. Per NPG-SPP-10.2, Clearance Procedure to Safely Control Energy, Requirement O. states, Control power circuits shall be tagged if (1) the work is on the control circuit, (2) the proximity of the work is near the energized control circuit, or (3) there exists a possibility of grounding the control circuit.

Control power fuses are REQUIRED to be addressed to satisfy the CRITICAL STEP.

STEP 1: Applicant identifies components that must be operated to support CRITICAL replacing the 30X, 1X and 30RX relays in the 1B SI pump circuit STEP and lubricating and collecting oil samples from the 1B SI pump.

Applicant enters data in the Equipment ID, Equipment ___ SAT Description, Equipment Location Column.

___ UNSAT STANDARD:

The applicant completes Column 1 of the TVA 17984 [11-2005] form provided:

1-HS-63-15A, SIS PUMP 1B-B 1-M-6 1-HS-63-175A, SIP 1B-B RECIRC TO RWST, 1-M-6 1-BKR-63-15, SIP 1B-B (1-PMP-63-15), 6.9KV SD BD 1B-B, C/15 1-FU-211-B15/1N SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 1-FU-211-B15/1A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 1-FU-211-B15/2N SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 1-FU-211-B15/2A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 1-BKR-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, 480V RX MOV BD 1B1-B, C/13D 1-ISV-63-527, SI PUMP DISCHG ISOL, A7V/700 1-FCV-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, A6U/692 Step is critical to correctly isolate the electrical and mechanical portions of the system prior to work being performed.

COMMENTS:

PAGE 5 0F 13

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2: Applicant identifies components that must be operated to support CRITICAL replacing the 30X, 1X and 30RX relays in the 1B SI pump circuit STEP and lubricating and collecting oil samples from the 1B SI pump.

Applicant enters data in the Tag Type Column. ___ SAT STANDARD: ___ UNSAT The applicant completes Column 3 of the TVA 17984 [11-2005] form provided:

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

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

COMMENTS:

PAGE 6 0F 13

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: Applicant identifies components that must be operated to support CRITICAL replacing the 30X, 1X and 30RX relays in the 1B SI pump circuit, STEP lubricating and collecting oil samples from the 1B SI pump.

Applicant identifies enters data in the Place Seq. Column.

___ SAT STANDARD:

___ UNSAT The applicant completes Column 4 of the TVA 17984 [11-2005]

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

1-HS-63-15A, SIS PUMP 1B-B 1-M-6 (1) 1-HS-63-175A, SIP 1B-B RECIRC TO RWST, 1-M-6 (1) 1-BKR-63-15, SIP 1B-B (1-PMP-63-15), 6.9KV SD BD 1B-B, C/15 (2) 1-FU-211-B15/1N SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 (2) 1-FU-211-B15/1A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 (2) 1-FU-211-B15/2N SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15(2) 1-FU-211-B15/2A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 (2) 1-BKR-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, 480V RX MOV BD 1B1-B, C/13D (3) 1-ISV-63-527, SI PUMP DISCHG ISOL, A7V/700 (4) 1-FCV-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, A6U/692 (4)

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

NOTE: Sequence variations are allowed as long as the sequence does not result in Mechanical Isolations prior to Electrical isolations.

COMMENTS:

PAGE 7 0F 13

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: Applicant identifies components that must be operated to support CRITICAL replacing the 30X, 1X and 30RX relays in the 1B SI pump circuit, STEP lubricating and collecting oil samples from the 1B SI pump SAFELY. Applicant enters the correct position in the Place Config. Column. ___ SAT STANDARD: ___ UNSAT The applicant completes Column 5 of the TVA 17984 [11-2005]

form by listings the following POSITION for each of the following components:

1-HS-63-15A, SIS PUMP 1B-B 1-M-6, - PULL-TO-LOCK 1-HS-63-175A, SIP 1B-B RECIRC TO RWST, 1-M MID POSITION AFTER CLOSE 1-BKR-63-15, SIP 1B-B (1-PMP-63-15), 6.9KV SD BD 1B-B, C/15 -

RACKED DOWN 1-FU-211-B15/1N SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 REMOVED 1-FU-211-B15/1A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 REMOVED 1-FU-211-B15/2NSIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 REMOVED 1-FU-211-B15/2A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 REMOVED 1-BKR-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, 480V RX MOV BD 1B1-B, C/13D - OFF 1-ISV-63-527, SI PUMP DISCHG ISOL, A7V/700 - CLOSED 1-FCV-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, A6U/692 - CLOSED Step is critical to correctly de-energize and isolate the portion of the system prior to work being performed.

COMMENTS:

PAGE 8 0F 13

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 3S 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: Applicant answers the question in Part 2 of the JPM. CRITICAL STEP The Auxiliary Building AUO reports the ERCW supply line to the 1A SI Pump room cooler has ruptured. Local actions have been taken to isolate the leak. ___ SAT What, if any, Technical Specifications/Technical Requirements ___ UNSAT must be entered due to the failure of the 1A-A SI Pump Room Cooler? What, if any, actions are required to be taken?

STANDARD:

OPERABLE-OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

The applicant determines:

Loss of the 1A-A SI pump room cooler renders the 1A-A SI pump inoperable.

With both of the SI pumps inoperable, entry into LCO 3.0.3 is required.

The plant needs to be in Mode 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

LCO 3.0.3 - When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in:

a. MODE 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />;

b. MODE 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />; and

c. MODE 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.

Exceptions to this Specification are stated in the individual Specifications. Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required. LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 9 0F 13

3S KEY DO NOT HAND TO APPLICANT 3S

3S Handout Package for Applicant 3S

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

INITIAL CONDITIONS:

1. Unit 1 is in Mode 3 with RCS pressure at 1000 psig and RCS temperature at 380F.

2. Electrical Maintenance will be replacing the 30X, 1X and 30RX relays in the 1B SI pump circuit. While relay replacement is in progress, the 1B SI pump will be lubricated and oil samples collected.

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

INITIATING CUES:

Part 1 - Using the references provided, manually prepare a TVA 17984

[11-2005], Clearance Tag List and Operational Steps, to de-energize and isolate the 1B-B SI pump for relay replacement, cleaning and lubrication.

NOTE: Complete the first, third, fourth, and fifth columns on TVA 17984 [11-2005], Clearance Tag List and Operational Steps.

3S

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

ASSUME WORK IS NOW IN PROGRESS ON THE 1B-B SI PUMP.

Part 2 - The Auxiliary Building AUO reports the ERCW supply line to the 1A SI Pump room cooler has ruptured. Local actions have been taken to isolate the leak.

What, if any, Technical Specifications/Technical Requirements must be entered due to the failure of the 1A-A SI Pump Room Cooler? What, if any, actions are required to be taken?

3S

Watts Bar Nuclear Plant 2013-03 NRC Exam Administrative JPM 4

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4

2013-03 NRC Exam EVALUATION SHEET Task: DETERMINE REQUIREMENTS FOR LOCKED HIGH RADIATION AREA (LHRA)

Alternate Path: n/a Facility JPM #: 3-OT-JPMADA.3-2 Safety Function: 2.3

Title:

Radiation Control K/A 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Rating(s): 3.4/3.8 CFR: 41.12 / 43.4 / 45.9 / 45.10 Evaluation Method: Simulator In-Plant Classroom X*

References:

RCI-100, "Control of Radiological Work," Revision 38 RCI-153, "Radiation Work Permits," Revision 3 NPG-SPP-05.1, :"Radiological Controls," Revision 2 Radiation work Permit (RWP) #13105000 Survey Map # M-20120217-1 Task Number: AUO-119-SPP-5.51-001

Title:

Use a Radiation Work Permit AUO-119-SPP-5.01-001 Control Personal Radiation Exposure Task Standard: Applicant determines:

1.) C-zone protective clothing (Dressout), RP coverage, and radiological briefing requirements from the provided Radiation Work Permit.

2.) The maximum inspection time without exceeding the administrative dose level is 35 min (0.58) (OR 30 min (0.5 hrs) based on RCI-100.)

3.) That the LHRA key can only be issued to RP personnel in this situation and that only the RP Shift Supervisor can issue LHRA key.

Validation Time: 15 minutes Time Critical: Yes No X

===============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==============================================================

=

COMMENTS PAGE 2 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4

2013-03 NRC Exam Tools/Equipment/Procedures Needed:

The following information will be handed out to each applicant:

1. Radiation work Permit (RWP) #13105000

2. Survey Map # M-20120217-1

3. Drawing: 47W200-16 EQUIPMENT PLAN-EL 692 & 685.5, Rev. 16 NRC REFERENCE DISK.

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

PAGE 3 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4

2013-03 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. You are the Auxiliary Building AUO, and will be entering the Spent Resin Storage Tank (SRST) valve gallery to inspect instrument sense lines for damage.

2. Your current year dose (CYD) is 650 mrem TEDE.

3. This inspection may require climbing, crawling, or kneeling in the SRST valve gallery, however, entry into the room where the Spent Resin Storage Tank is will not be required.

4. The SRST valve gallery is in a Locked High Radiation Area (LHRA).

5. Unit 1 is at 100% power and no emergency has been declared.

INITIATING CUES:

1. Using the Radiological Work Permit (RWP) and Survey Map provided, determine the following requirements for the task:

a. c-zone protective clothing (Dressout).

b. radiological protection personnel coverage.

c. radiological briefing.

2. Determine the maximum inspection time available without exceeding the TVA annual administrative dose level (ADL) based on the highest general area dose rate in the SRST valve gallery. Show ALL calculations.

3. Determine the following:

a. personnel the LHRA key can be issued to in this situation.

b. personnel authorized to issue the LHRA key.

PAGE 4 OF 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4

2013-03 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: Determine C-zone protective clothing, radiological protection CRITICAL personnel coverage and radiological briefing requirements from STEP the provided Radiological Work Permit (RWP).

___ SAT STANDARD:

___ UNSAT Applicant determines the following requirements from the RWP:

C-zone protective clothing (Dressout) required is: 1 PR coveralls, 1 PR booties, 1 PR shoe covers , 1 PR rubber gloves, cloth inserts, surgeons cap, secure gloves / booties, modesty clothing.

EXAMINER: This protective clothing is required by the RWP due to potential climbing, crawling, or kneeling in SRST valve gallery.

Radiological Protection coverage is: Continuous Radiological Briefing: Brief on current radiological conditions is required prior to RCA entry (Daily Briefing). May also enter Pre-Job Brief Step is critical to ensure compliance with Radiological Work Permit requirements.

COMMENTS:

PAGE 5 0F 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4

2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2: Determine the maximum inspection time available without CRITICAL exceeding the TVA annual administrative dose level based on the STEP highest general area dose rate in the SRST valve gallery.

___ SAT STANDARD:

___ UNSAT Applicant determines the remaining administrative dose is 350 mrem.

1000 mrem - 650 mrem = 350 mrem EXAMINER: The TVA administrative dose level (ADL) is 1000 mrem.

Applicant determines the maximum General area dose to be 600 mrem /

hour from the survey map near the piping in the upper right portion of the SRST valve gallery.

Applicant calculates the maximum inspection time to be 35 minutes (0.58 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br />).

(350 mr) x (1 hr / 600 mr) x (60 min / 1hr) = 35 min (or 0.58 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br />) 350 mr 1 hr 60 min = 35 min 600 mr 1 hr EXAMINER: Applicant may use the calculation formula contained in RCI-100, which subtracts 50 mr to ensure the dose limit is not exceeded.

(350 mr)-(50 mr) x (1 hr / 600 mr) x (60 min / 1hr) = 30 min (or 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />)

Applicant calculates the maximum inspection time to be 30 minutes (0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />).

350 mr-50 mr 1 hr 60 min = 30 min 600 mr 1 hr Step is critical to ensure the TVA annual administrative dose level is not exceeded.

COMMENTS:

PAGE 6 0F 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 4

2013-03 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: Determine the personnel the LHRA key can be issued to in this CRITICAL situation and who is authorized to issue the LHRA key. STEP STANDARD: ___ SAT Applicant determines that LHRA keys for this task can only be issued to ___ UNSAT RP personnel in this non-emergency situation, and that LHRA keys can only be issued by the RP Shift supervisor.

NOTE:

RCI-100 Section 2.6, "Key Control" States:

C. HRA, LHRA and VHRA keys may only be issued to RP personnel, except in declared emergency situations.

I. The on-duty RP Shift Supervisor shall maintain control of the access key to the HRA/LHRA key box. Issue of the key to a HRA or LHRA must be authorized by the on-duty RP Shift Supervisor.

HRA/LHRA keys shall only be issued by a RP Shift Supervisor.

Step is critical to ensure proper RP control and monitoring of this non-emergency work and prevent inadvertent entry into the LHRA.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 7 0F 11

4 Handout Package for Applicant

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

INITIAL CONDITIONS:

1. You are the Auxiliary Building AUO, and will be entering the Spent Resin Storage Tank (SRST) valve gallery to inspect instrument sense lines for damage.

2. Your current year dose (CYD) is 650 mrem TEDE.

3. This inspection may require climbing, crawling, or kneeling in the SRST valve gallery, however, entry into the room where the Spent Resin Storage Tank is will not be required.

4. The SRST valve gallery is in a Locked High Radiation Area (LHRA).

5. Unit 1 is at 100% power and no emergency has been declared.

INITIATING CUES:

1. Using the Radiological Work Permit (RWP) and Survey Map provided, determine the following requirements for the task:

a. c-zone protective clothing (Dressout).

b. radiological protection personnel coverage.

c. radiological briefing.

2. Determine the maximum inspection time available without exceeding the TVA annual administrative dose level (ADL) based on the highest general area dose rate in the SRST valve gallery. Show ALL calculations.

3. Determine the following:

a. personnel the LHRA key can be issued to in this situation.

b. personnel authorized to issue the LHRA key.

4

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

Calculations:

MAXIMUM INSPECTION TIME: MINUTES 4

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

Calculations:

MAXIMUM INSPECTION TIME: MINUTES 4

Watts Bar Nuclear Plant 2013-03 NRC Exam Administrative JPM 5 S

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2013-03 NRC Exam EVALUATION SHEET Task: CLASSIFY THE EVENT PER THE RADIOLOGICAL EMERGENCY PLAN Alternate Path: n/a Facility JPM #: 3-OT-JPMS090 Safety Function: n/a

Title:

K/A 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.

Rating(s): 2.4/4.4 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. 36.

EPIP-4, Site Area Emergency, Rev. 34.

EPIP-5 General Emergency, Rev. 40.

Task Number: SRO-113-EPIP-001

Title:

Classify emergency events requiring Emergency Plan Implementation.

Task Standard: The applicant 1.) Classifies the event as a SITE AREA EMERGENCY, based on EAL 3.1 LOSS OF AC (Power Ops), within 15 minutes.

2.) Completes EPIP-4, Site Area Emergency, Appendix A, TVA Initial Notification Form For Site Area Emergency.

Validation Time: 30 minutes Time Critical: Yes X No

=

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==============================================================

=

COMMENTS

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2013-03 NRC Exam 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 5S 2013-03 NRC Exam DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

TREAT THIS AS A RADIOLOGICAL EMERGENCY DRILL.

1. Unit 1 is in MODE 4, cooling down to MODE 5 for outage work on the secondary plant.

2. RCS temperature is 240° F and RCS pressure is 520 psig.

3. 1A 6.9kV Shutdown Board is de-energized and tagged for inspection of lugs.

4. Twenty minutes ago, an F4 tornado caused a complete loss of both 161kv lines to the plant. The tornado did not impact any plant structures.

5. A fault occurred on 1B Shutdown Board when the diesel generator breaker closed, resulting in the board tripping on differential and considerable damage to the board.

6. All steam generators have normal levels and the TDAFW pump is in service.

7. The electrical maintenance group has estimated that 1A 6.9kV Shutdown Board can be returned to service in approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

8. You are the Shift Manager (SM/SRO).

INITIATING CUES:

1. Using the data provided and the applicable procedure (s) classify the event.

2. Raise your hand when classification is complete.

3. When classification is complete, request from the examiner the correct TVA Initial Classification form, then complete the required form.

4. Determine what, if any, Protective Action Recommendations are required.

5. Raise your hand when you have completed the notification form.

6. The is (are) an element(s) of this task that is (are) time critical.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: Refers to EPIP-1 to determine level of classification required CRITICAL for the events in progress. STEP STANDARD: ___ SAT Applicant refers to EPIP-1, Section 3, Loss of Power. ___ UNSAT Based on Emergency Class Criteria", the applicant determines that a Site Area Emergency, needs to be declared, based on EAL 3.1, Loss of AC (Power Ops), Loss of Offsite and Onsite AC Power >15 minutes.

The applicant may also indicate that EPIP-1, Section 5, Destructive Phenomenon, EAL 5.2, Tornado should be evaluated. EAL 5.2 would result in an Unusual Event.

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

EXAMINER: RECORD time that declaration was made:_________

COMMENTS:

PAGE 5 0F 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 5S 2013-03 NRC Exam STEP/STANDARD SAT/UNSAT EXAMINER: A completed copy of EPIP-4, Site Ares Emergency, Appendix A for this JPM is included and marked NRC EXAM MATERIAL - S5 KEY.

STEP 3: INITIATES EPIP-4, SITE AREA EMERGENCY Appendix A, CRITICAL TVA Initial Notification Form For Site Area Emergency. STEP STANDARD: ___ SAT Applicant completes EPIP-4, Appendix A, TVA Initial Notification Form ___ UNSAT For Site Area Emergency, within 15 minutes of initial event classification.

Critical elements that must appear on Appendix A form:

Item 3 - EAL Designators - EAL 3.1, Item 4. - Brief Description of the Event - Loss of AC (Power Ops),

Loss of Offsite and Onsite AC Power >15 minutes.

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

COMMENTS:

END OF TASK STOP TIME ________

PAGE 6 0F 10

5S KEY DO NOT HAND TO APPLICANT

5S BLANK FORMS HAND REQUESTED FORM TO APPLICANT

5S Handout Package for Applicant

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

INITIAL CONDITIONS:

TREAT THIS AS A RADIOLOGICAL EMERGENCY DRILL.

1. Unit 1 is in MODE 4, cooling down to MODE 5 for outage work on the secondary plant.

2. RCS temperature is 240° F and RCS pressure is 520 psig.

3. 1A 6.9kV Shutdown Board is de-energized and tagged for inspection and cleaning.

4. Twenty minutes ago, an F4 tornado caused a complete loss of both 161kv lines to the plant. The tornado did not impact any of the plant structures.

5. A fault occurred on 1B Shutdown Board when the diesel generator breaker closed, resulting in the board tripping on differential and considerable damage to the board.

6. All steam generators have normal levels and the TDAFW pump is in service.

7. The electrical maintenance group has estimated that 1A 6.9kV Shutdown Board can be returned to service in approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

8. You are the Shift Manager (SM/SRO).

INITIATING CUES:

1. Using the data provided and the applicable procedure (s) classify the event.

2. Raise your hand when classification is complete.

3. When classification is complete, request from the examiner the correct TVA Initial Classification form, then complete the required form.

4. Determine what, if any, Protective Action Recommendations are required.

5. Raise your hand when you have completed the notification form.

6. The is (are) an element(s) of this task that is (are) time critical.

5S