Text

Initial Exam 2013-301 Final Administrative JPMs
	ML13210A063
Person / Time
Site:	Watts Bar
Issue date:	07/26/2013
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	50-390/10-301
	Download: ML13210A063 (205)
	v • d • e

Watts Bar Nuclear Plant 201303 NRC Exam Administrative JPM 1

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

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 564.6 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 1

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

The following information will be handed out to each 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, Copy of Nuclear Parameters & Operations Package (NuPOP) WCAP-17401-P, Watts Bar Unit 1 Cycle 11, Rev. 1

4. 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 1

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 1

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 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

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 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

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 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

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 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

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 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

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 6-25.

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 100 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 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

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 100 to 200 pcm) and enters a value of -172.8 pcm (accept -223 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 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

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 ppm/% (accept -158.5 to -159.5 ppm/%) 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 35.4 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 564.6 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 of 16

1 KEY DO NOT HAND TO APPLICANT

NRC EXAM MATERIAL JPM 1 KEY

NRC EXAM MATERIAL Accept 100-200 pcm Accept 0-10 pcm Accept 200-100 pcm Accept -223 to -122.8 pcm Accept 158.5 to 159.5 pcm Accept -223 to -122.8 pcm Accept 19.5 to 35.4 pcm Accept 564.6 to 580.5 ppm JPM 1 KEY

1 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.

1

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 1

WBN Boron Concentration Control SOI-62.02 Unit 1 Rev. 0055 Page 55 of 58 Appendix E (Page 1 of 2)

REACTIVITY BALANCE CALCULATION 1.0 REACTIVITY BALANCE CALCULATION NOTES

1) One calculation is required for each major change. Calculation is an approximation of Final Target CB

2) Appendix E may be used by an SRO to approve and independently verify data provided by Reactor Engineering. In this case, an additional IV by another SRO is NOT required

[1] CALCULATE Target CB by performing the following:

Date: Performer Initials:

DATA REQUIRED DATA Where To Get Initial RCS Boron CB ppm Chem Lab Core Burnup MWD/MTU ICS U7981 Initial Reactor power % NIS Final Reactor power % As required for plant conditions Total Reactor Power change % Initial to Final Reactor power Rate of Reactor power change %/hr As required for plant conditions Number of hours to change power hr(s) As required for plant conditions Current Rod Position steps ICS or MCR Board Final rod position based on estimated number of steps Final Rod Position steps required to control I and insertion limits for power change.

Initial Reactor Power: % Final Reactor Power: %

Parameter Where To Get Calculation Value

WBN Boron Concentration Control SOI-62.02 Unit 1 Rev. 0055 Page 56 of 58 Appendix E (Page 2 of 2)

Date________ Initials 1.0 REACTIVITY BALANCE CALCULATION (continued)

POWER NOTE: Must be entered into equation as a positive value ________pcm Power Defect From NUPOP, Table 7-17, 7-18, or 7-19. ________pcm PD ________pcm PD =

DEFECT POWER Initial Final DEFECT XENON NOTE: Must be entered into equation as a positive value Initial Xenon From REACTW (either current conditions or projection to initial ________pcm condition). _________pcm XE ________pcm XE = XENON Final Xenon:From REACTW (projection over time). Initial Final RODS 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. _______pcm Rods ______pcm Rods = ________pcm RODS Initial Final

________pcm Add reactivity values to determine pcm adjustment to be made by changing CB. (NOTE: Watch the signs.) SUM needed Convert to ________ppm PPM (NUPOP Figure 6-21)________ppm/% (Inverse Boron Worth) X________pcm (needed) X 0.001 %/cm =

Total CB TARGET PPM ________Current RCS CB ________Total CB = ________ppm Target CB PERFORMER:

[2] APPROVE calculation and Target PPM change for planned change in reactor power. ________ SRO

Watts Bar Nuclear Plant 201303 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 X In-Plant Classroom

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 displayed on the STATIC SIMULATOR and determines the following:

1. Status Tree Priority:

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

2. 1-FR-S.1, Nuclear Power Generation/ATWS, ORANGE PATH 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 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2

2013-03 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 347 by performing the following actions:

a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).

b. Locate IC# 347.

c. Right click on IC# 347.

d. Select Reset on the drop down menu.

e. Right click on RESET.

f. Enter the password for IC# 347.

g. Select Yes on the INITIAL CONDITION RESET pop-up window.

h. Perform SWITCH CHECK.

3. ENSURE the following information appears on the Director Summary Screen:

Key Type Event Delay Inserted Ramp Initial Final Value hs-72-10a-1 05010 rwst spray hdr b fcv(green) O 00:00:00 00:00:00 00:00:00 Off Off hs-72-21a-1 06010 cntmt spray pump b mtr sw (green) O 00:00:00 00:00:00 00:00:00 Off Off hs-72-2a-1 05070 cs hdr b isol vlv hand sw (green) O 00:00:00 00:00:00 00:00:00 Off Off hs-72-45a-1 05030 cntmt sump hdr b fcv(green) O 00:00:00 00:00:00 00:00:00 Off Off hs-72-13a-1 05050 cs pump b recirc fcv (green) O 00:00:00 00:00:00 00:00:00 Off Off fi-3-147a 02070 stm gen #3 aux fw in O 00:00:00 00:00:00 00:00:00 130 110 fi-3-147b 02070 stm gen #3 aux fw in O 00:00:00 00:00:00 00:00:00 130 110 csr04 containment spray pump b power R 00:00:00 00:00:00 00:00:00 Off Off fw29c main fw reg vlv fcv-3-90 fail position M 1 00:00:00 00:00:00 00:00:00 0 0 th03b loca - small leak loop2 M 1 00:00:00 00:00:00 00:00:00 37.5 37.5 cs01a containment spray system pump a trip M 13 00:00:00 00:00:00 00:00:00 Active Active

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2

2013-03 NRC Exam Key Type Event Delay Inserted Ramp Initial Final Value ni04a ir channel failure ir chnl 1 M 19 00:00:00 00:00:00 00:00:00 0.05 0.05 ni04b ir channel failure ir chnl 2- M 19 00:00:00 00:00:00 00:00:00 0.055 0.055 nini35d 07030 n35 startup-rate (dpm) ao O 19 00:00:00 00:00:00 00:00:00 0.33 0.33 nini36d 07030 n36 startup-rate (dpm) ao O 18 00:00:00 00:00:00 00:00:00 0.35 0.35

4. ENSURE SIMULATOR REMAINS IN FREEZE FOR THE DURATION OF ALL OF THE JPM PERFORMANCES.

6. PERFORM a board walk-down to verify:

a. Startup Rate on 1-NI-35D, IR STARTUP RATE DPM and 1-NI-36D, IR STARTUP RATE DPM indicate a positive value, approximately 0.3 DPM.

b. TOTAL AFW flow is approximately 430 gpm.

c. WHITE motor trip-out and GREEN light LIT on 1-HS-72-27A, CNTMT SPRAY PUMP A.

d. Containment pressure is approximately 5 psig.

7. ENSURE HOLD ORDER Tags are hung on 1-HS-72-10A, CNTMT SPRAY PUMP B, 1-HS-72-21A, RWST TO CS PMP B SUCTION, 1-HS-72-2A, CNTMT SPRAY HDR B TO CNTMT, 1-HS-72-13, CNTMT SPRAY PMP B MINI FLOW.

8. ENSURE ALL ICS Screens are closed on each ICS terminal. Windows Desktop screen should be visible.

9. RESET/ACKNOWLEDGE annunciators that are flashing.

10. INFORM the Examiner that Copies of FR-0, Status Trees, are available for each applicant as part of this JPM package.

Page 4 of 15

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.

NOTE: THE SIMULATOR WILL REMAIN IN FREEZE FOR THE DURATION OF THE JPM.

INITIAL CONDITIONS:

1. Unit 1 tripped from 100% power.

2. A Safety Injection occurred 15 minutes ago.

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

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

INITIATING CUE:

You have been directed perform a manual evaluation the Critical Safety Functions using FR-0, Status Trees, based on the indications displayed on the simulator.

ENSURE THAT YOU:

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 5 of 15

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 15

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 YELLOW path exists on FR-C 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 7 of 15

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 15

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 a GREEN path exists on FR-P 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 9 of 15

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 an ORANGE path exists on FR-Z Status Tree, and that FR-Z.1 is required to be entered after FR-S.1 actions are complete (assuming the conditions still exist).

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 15

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 15

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, ORANGE PATH is of the highest priority ___ UNSAT and that FR-S.1, 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 15

2 KEY DO NOT HAND TO APPLICANT 2

WBN NRC EXAM MATERIAL Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 1 of 8)

Monitoring Critical Safety Functions SUBCRITICALITY FR-S NOW Orange FR-S.1 Page 4 of 11 A.1-1 JPM SRO 2 KEY KEY

WBN NRC EXAM MATERIAL Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 2 of 8)

Monitoring Critical Safety Functions CORE COOLING FR-C Yellow FR-C.3 Page 5 of 11 A.1-1 JPM SRO 2 KEY KEY

WBN NRC EXAM MATERIAL Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 3 of 8)

Monitoring Critical Safety Functions HEAT SINK FR-H Yellow FR-H.5 Page 6 of 11 A.1-1 JPM SRO 2 KEY KEY

WBN NRC EXAM MATERIAL Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 4 of 8)

Monitoring Critical Safety Functions PRESSURIZED THERMAL SHOCK FR-P Green N/A Page 7 of 11 A.1-1 JPM SRO 2 KEY KEY

WBN NRC EXAM MATERIAL Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 5 of 8)

Monitoring Critical Safety Functions COLD OVERPRESSURE LIMIT CURVE FIGURE 1 Page 8 of 11 A.1-1JPM SRO 2 KEY KEY

WBN NRC EXAM MATERIAL Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 6 of 8)

Monitoring Critical Safety Functions LIMIT A CURVE FIGURE 2 Page 9 of 11 A.1-1 JPM SRO 2 KEY KEY

WBN NRC EXAM MATERIAL Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 7 of 8)

Monitoring Critical Safety Functions CONTAINMENT FR-Z Orange FR-Z.1 Page 10 of 11 A.1-1 JPM SRO 2 KEY KEY

WBN NRC EXAM MATERIAL Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 8 of 8)

Monitoring Critical Safety Functions INVENTORY FR-I Green N/A Page 11 of 11 A.1-1 JPM SRO 2 KEY KEY

2 Handout Package for Applicant 2

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

NOTE: THE SIMULATOR WILL REMAIN IN FREEZE FOR THE DURATION OF THE JPM.

INITIAL CONDITIONS:

1. Unit 1 tripped from 100% power.

2. A Safety Injection occurred 15 minutes ago.

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

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

INITIATING CUE:

You have been directed perform a manual evaluation the Critical Safety Functions using FR-0, Status Trees, based on the indications displayed on the simulator.

ENSURE THAT YOU:

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

Watts Bar Nuclear Plant Unit 1 Emergency Operating Instruction FR-0 Status Trees Revision 0014 Quality Related Level of Use: Continuous Use Effective Date: 12-21-2010 Responsible Organization: OPS, Operations Prepared By: Nicholas Armour Approved By: Brian McIlnay Current Revision Description Minor/editorial revision: Converted to Word 2007 (PCR 4899).

WBN Status Trees FR-0 Unit 1 Rev. 0014 1.0 PURPOSE This instruction provides parameters to be monitored for challenges to Critical Safety Functions and to identify the appropriate Function Restoration Instruction to implement.

2.0 SYMPTOMS AND ENTRY CONDITIONS Status Trees monitoring is initiated when transitioned out of E-0, Reactor Trip or Safety Injection, or as instructed in E-0.

Page 2 of 11

WBN Status Trees FR-0 Unit 1 Rev. 0014 Step Action/Expected Response Response Not Obtained 3.0 OPERATOR ACTIONS NOTE The following rules of usage apply to Status Tree monitoring.

A. While any RED or ORANGE path exists, the Status Trees will be monitored continuously. When no RED or ORANGE path exists, the Status Trees will be monitored every 10 to 20 minutes until the plant operation is controlled by normal operating instructions (GOs) with ESF System ARMED, OR the plant is in COLD SHUTDOWN.

B. Status Trees shall be monitored in the following priority:

1. FR-S, Subcriticality,

2. FR-C, Core Cooling,

3. FR-H, Heat Sink,

4. FR-P, Pressurized Thermal Shock (PTS),

5. FR-Z, Containment,

6. FR-I, Inventory.

C. If a RED path is diagnosed, then the Function Restoration Instruction will be implemented IMMEDIATELY.

D. If an ORANGE path is diagnosed, then the remaining Status Trees will be checked. If NO RED path exists, then the ORANGE path Function Restoration Instruction will be implemented.

E. Once implemented due to any RED or ORANGE path, that Function Restoration Instruction will be performed to completion or to a point of transition UNLESS a higher priority condition develops.

F. When no RED or ORANGE path exists, the YELLOW path Function Restoration Instruction can be implemented at the Operators discretion.

Page 3 of 11

WBN Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 1 of 8)

Monitoring Critical Safety Functions SUBCRITICALITY FR-S Page 4 of 11

WBN Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 2 of 8)

Monitoring Critical Safety Functions CORE COOLING FR-C Page 5 of 11

WBN Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 3 of 8)

Monitoring Critical Safety Functions HEAT SINK FR-H Page 6 of 11

WBN Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 4 of 8)

Monitoring Critical Safety Functions PRESSURIZED THERMAL SHOCK FR-P Page 7 of 11

WBN Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 5 of 8)

Monitoring Critical Safety Functions COLD OVERPRESSURE LIMIT CURVE FIGURE 1 Page 8 of 11

WBN Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 6 of 8)

Monitoring Critical Safety Functions LIMIT A CURVE FIGURE 2 Page 9 of 11

WBN Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 7 of 8)

Monitoring Critical Safety Functions CONTAINMENT FR-Z Page 10 of 11

WBN Status Trees FR-0 Unit 1 Rev. 0014 Attachment 1 (Page 8 of 8)

Monitoring Critical Safety Functions INVENTORY FR-I Page 11 of 11

Watts Bar Nuclear Plant 201303 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 critical breakers and fuses, their required positions to electrically clear the 1B-B SI pump in preparation for relay replacement.

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

3.) Identifies that electrical isolations are required prior to mechanical isolations.

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-B SI pump circuit. While relay replacement is in progress, the 1B-B 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-B SI pump STEP circuit, lubricating and collecting oil samples from the 1B-B 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-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 1B-B MINI FLOW RECIRC TO RWST, A6U/692 Listed components are 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-B SI pump STEP circuit, lubricating and collecting oil samples from the 1B-B 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.

Listed components are critical to correctly isolate the electrical and mechanical portions 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-B SI pump STEP circuit, lubricating and collecting oil samples from the 1B-B 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-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 (3) 1-FU-211-B15/1A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 (3) 1-FU-211-B15/2N SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15(3) 1-FU-211-B15/2A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 (3) 1-BKR-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, 480V RX MOV BD 1B1-B, C/13D (4) 1-ISV-63-527, SI PUMP DISCHG ISOL, A7V/700 (5) 1-FCV-63-175, SI PUMP 1B-B MINI FLOW RECIRC TO RWST, A6U/692 (5)

Listed components are 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-B SI pump STEP circuit, lubricating and collecting oil samples from the 1B-B 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-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 1B-B MINI FLOW RECIRC TO RWST, A6U/692 - CLOSED Positions of listed components are 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

Tennessee Valley Authority Clearance Tag List and Operational Steps Clearance No. Page 1 of 2 Apparatus: Lubricate, sample oil and replace 30X, 1X and 30RX relays on 1B Safety Injection Pump.

Equipment ID Place. Place. Restore Restore Equipment Description Tag Serial Tag Place. Place. 1st 2nd Rest. Restore As left 1st 2nd Tag Notes Equipment Location No. Type Seq. Config. Verifier Verifier Seq. Config. Confg. Verifier Verifier 1-HS-63-15A SIS PUMP B-B Danger 1 PULL-TO-LOCK 1-M-6 1-HS-63-175A SIP 1B-B RECIRC TO RWST Danger 1 MID POSITION 1-M-6 AFTER CLOSE 1-BRK-63-15 SIP 1B-B (1-PMP-63-15) Danger 2 RACKED DOWN 6.9KV SD BD 1B, C/15 1-FU-211-B15/1N SIS PUMP 1B-B FUSES Danger 3 REMOVED 6.9 KV SD BD 1B-B, C/15 1-FU-211-B15/ 1A SIS PUMP 1B-B FUSES Danger 3 REMOVED 6.9 KV SD BD 1B-B, C/15 1-FU-211-B15/ 2N SIS PUMP 1B-B FUSES Danger 3 REMOVED 6.9 KV SD BD 1B-B, C/15 1-FU-211-B15/2A, SIS PUMP 1B-B FUSE Danger 3 REMOVED 6.9 KV SD BD 1B-B, C/15 1-BKR-63-175, SI PUMP 1B-B MINI FLOW RECIRC TO RWST 480V Danger 4 OFF RX MOV BD 1B1-B, C13D 1-ISV-63-527 SI PUMP 1B-B DISCHARGE ISOLATION Danger 5 CLOSED RM 692-A12 SI PUMP !B-B RM EL.

692 A6U/692 1-FCV-63-175 SI PUMP MINI FLOW RECIRC TO RWST Danger 5 CLOSED RM 692-A12 SI PUMP !B-B RM EL.

692 A6U/692 CRITICAL ITEMS ARE IN BOLD PRINT.

TVA 17984 [11-2005]

NPG Standard Clearance Procedure to Safely Control NPG-SPP-10.2 Programs and Energy Rev. 0005 Processes Page 34 of 80 5.0 DEFINITIONS Affected Employee - Employees, contractors, and others who are required to operate or use equipment identified for servicing, maintenance, or modification under a clearance or works in an area where such servicing, maintenance, or modification is being performed.

Affected employees include the general population who works in an area where equipment is under clearance or may observe clearance tags on such equipment. An affected employee becomes an authorized employee when that person performs servicing, maintenance, or modification on equipment under clearance. An affected employee may become an authorized employee, a primary authorized employee, or a responsible employee based on the level of training received and work functions assigned.

Authorized Employees - Employees, contractors, and others who perform servicing, maintenance, or modification on machines or equipment under a clearance and have successfully completed the appropriate level of training required by this procedure. These employees work on equipment under a clearance that has been issued in accordance with this procedure. An authorized employee may become a primary authorized employee or a responsible employee based on the level of training received and work functions assigned.

Capable Of Being Locked Out - An energy-isolating device is capable of being locked out if it has a hasp or other means of attachment to which, or through which, a lock can be affixed, or it has a locking mechanism built into it. Other energy-isolating devices are capable of being locked out, if lockout can be achieved without the need to dismantle, rebuild, or replace the energy-isolating device or permanently alter its energy control capability.

Caution Order Tag - A Caution Order is a yellow tag that is attached to plant equipment, switches, or controls where a hazardous or abnormal condition(s) exists. The Caution Order Tag has its own set of instructions for the condition under caution. See Appendix G.

Clearance - A condition established by an issued clearance meaning that all energy sources of feed and feedback, such as electrical, mechanical and/or hydraulic, have been isolated and tagged. A clearance is established when it is placed in issued status by the Responsible Employee in accordance with this procedure.

Clearance Boundary - Points at energy-isolating devices established in accordance with this procedure that allows authorized employees to safely work on equipment under a clearance.

Clearance Personal Accountability Log (CPAL) - A log that identifies all Authorized Employees who are working on equipment under a specific clearance.

Current SRO - An individual who has obtained and currently holds a valid SRO license for the plant at which they are working and is up to date on all auxiliary requirements such as licensed operator training requirements and medical requirements. This individual may or may not be currently qualified to hold an on-shift SRO position (i.e., be an Active SRO).

Danger Tag - A red tag used to identify energy-isolating devices for a clearance. See Appendix F, Danger Tag.

Electrical Representative PAE - A PAE authorized by the Plant Manager to be qualified to install and remove temporary protective grounds and to receive and return ground discs.

NPG Standard Clearance Procedure to Safely Control NPG-SPP-10.2 Programs and Energy Rev. 0005 Processes Page 35 of 80 5.0 DEFINITIONS (continued)

Electrically De-energized - Free from any electrical connection to a source of potential difference and from electric charge; not having a potential different from that of the earth.

Note: The term is used only with reference to current-carrying parts, which are sometimes electrically energized (live).

Electrically Energized (live) - Electrically connected to a source of potential difference, or electrically charged so as to have a potential significantly different from that of earth in the vicinity.

Emergency - Conditions that threaten the life of an employee or member of the public, or the plant operability.

Energy Isolating Device - A device that physically prevents the transmission or release of energy including, but not limited to, the following: An electrical circuit breaker; a disconnect switch; a manually operated switch by which the conductors of a circuit can be disconnected from all ungrounded supply conductors, and, in addition, no pole can be operated independently; a line valve; a block; and any similar device with a visible indication of the position of the device used to block or isolate energy. Push buttons, selector switches and other control-circuit type devices are not energy-isolating devices.

Energy Source - Any electrical, mechanical, hydraulic, pneumatic, chemical, nuclear, thermal, or other energy source that could cause injury to personnel.

External Energy Source - Any electrical, mechanical (e.g., rotation of a shaft with a come-a-long), hydraulic, pneumatic, chemical, nuclear, thermal, or other energy source that is not provided by the equipments normal designed energy source(s).

Group Tagout - The process by which a PAE holds a clearance for two or more authorized employees who will work on the equipment under a specific clearance. The authorized employees indicate that they are working under the clearance through the Clearance Personal Accountability Log (CPAL).

Issued Clearance - A clearance is issued when all actions required to establish a clearance in accordance with this procedure are completed and the responsible employee places the clearance in issued status. Regardless of the presence of a danger tag, all equipment is considered energized unless it is known to be controlled by a clearance in issued status.

Lines - Refers to transmission system conductors that are installed to distribute electrical power in the power transmission system.

Lockout - The placement of a lockout device on an energy-isolating device, in accordance with an established procedure, ensures that the energy-isolating device and the equipment being controlled cannot be operated until the lockout device is removed.

Lockout Device - A device that utilizes a positive means such as a lock, either key or combination type, to hold an energy-isolating device in the safe position and prevent the energizing of a machine or equipment. Included are blank flanges and bolted slip blinds.

NPG Standard Clearance Procedure to Safely Control NPG-SPP-10.2 Programs and Energy Rev. 0005 Processes Page 36 of 80 5.0 DEFINITIONS (continued)

Normal Energy Source - This is the energy normally available to the machine or equipment for its proper operation. There may be more than one type of normal energy source supplied such as electric, mechanical, hydraulic, pneumatic, etc.

Management Official-In-Charge - This means the plant, facility, production, or site manager.

Operating Permit Tag - An operating permit is a blue tag shown in Figure H-1 that is attached to equipment or controls when the equipment is to be operated by any person other than its operator. The equipment operator may not operate equipment except by instruction of the person holding the operating permit. The operating permit does not authorize persons other than the operator to operate the equipment from a switchboard. It does authorize the operator to operate equipment from a switchboard only under direction of the person holding the Operating Permit. The Operating Permit does not signify that the equipment tagged is de-energized. Where it is necessary for the equipment to be de-energized for work on the equipment, a danger tag clearance shall be issued.

Official Plant Clearance List - A list of names approved by the Plant Manager. The personnel are approved to perform the specific authorized functions designated on the list in accordance with this procedure. A RE, QE, or PAE on this list may be issued clearances.

Primary Authorized Employees - Employees, contractors, and others who request/identify the work to be performed under a clearance, walk down the boundaries of a clearance to determine if energy-isolating devices are set in proper position and tagged in accordance with the applicable clearance instruction; and have successfully completed the appropriate level of training and the associated qualifying examination(s) required by this procedure.

The primary authorized employee is responsible for administering the CPAL.

Qualified Employees - Employees, contractors, and others who prepare equipment for servicing, maintenance, and modification and return equipment to operational status and have successfully completed the training and the associated qualifying examination(s) required by this procedure. They have completed appropriate training for the area of the plant for which they have clearance responsibilities.

Released Clearance- A clearance is released when all actions required to release a clearance in accordance with this procedure are completed and the responsible employee removes the clearance from issued status.

Responsible Employees - Employees, contractors, and others who write and issue clearances in accordance with this procedure and have successfully completed the appropriate level of training and the associated qualifying examination(s) required by this procedure.

Servicing, Maintenance, and Modification - Workplace activities such as constructing, installing, setting up, adjusting, inspecting, modifying, and maintaining and/or servicing machines or equipment. These activities include lubrication, cleaning or un-jamming of machines or equipment and making adjustments or tool changes, where the employee may be exposed to the unexpected energizing or startup of the equipment or release of hazardous energy.

NPG Standard Clearance Procedure to Safely Control NPG-SPP-10.2 Programs and Energy Rev. 0005 Processes Page 37 of 80 5.0 DEFINITIONS (continued)

Sign-on/Sign-off - A personal act an employee, contractor, or other person takes to acknowledge his or her responsibilities for their name being on a log, list, or other documentation associated with a clearance.

Tagout - The placement of a tagout device on an energy-isolating device, in accordance with a clearance instruction, to indicate that the energy-isolating device and the equipment being controlled shall not be operated until the tagout device is removed.

Tagout device - A prominent warning device, such as a tag and a means of attachment, which can be securely fastened to an energy-isolating device in accordance with a clearance instruction, to indicate that the energy-isolating device and the equipment being controlled shall not be operated until the tagout device is removed.

Transmission Operator (Dispatcher) - refers to the TVA power system transmission operator who controls the transmission system lines and equipment.

NPG Standard Clearance Procedure to Safely Control NPG-SPP-10.2 Programs and Energy Rev. 0005 Processes Page 54 of 80 Appendix D (Page 1 of 3)

Special Requirements for Electrical Clearances 1.0 REQUIREMENTS A. Only component handswitches that meet the definition of an energy isolating device may be used as a clearance energy isolation point.

B. Component handswitches not meeting the definition of a clearance isolating device may be tagged as indication/information that associated equipment is under a clearance.

C. If potential or station service transformers are outside of the clearance zone, they may be cleared from the primary side. If they are inside the clearance zone, they shall be cleared from both the primary and secondary side.

D. Coupling capacitors within a clearance zone shall have their secondary circuits shorted if work is to be performed on or within the minimum approach distance to them.

E. Static capacitors within a clearance zone shall be grounded. The PAE holding the clearance is responsible for discharging and grounding the static capacitors.

F. The RE who is responsible for maintaining protection to equipment shall approve any changes in current transformer secondary circuits that are in service.

G. Blocks shall be removed in current transformer secondaries when connected in parallel with current transformers that are energized, before work is performed on them. If blocks are not available, it will be necessary to short circuit the current transformer, ground, and open the secondary circuits.

H. When two or more transformers are connected to ground through a common reactor, the transformers neutral ground switch for the transformer to be cleared shall be opened and tagged with a danger tag.

I. All disconnecting devices or breakers that establish a clearance boundary shall be opened made inoperable, when possible, and tagged to ensure that they will not be closed.

J. Gang or motor-operated disconnects/air-break switches shall be mechanically locked in the open position and visually checked to verify that all blades are open.

K. The QE should verify, by secondary means, the absence of energy on circuits involving circuit breakers whenever a means of verification is available.

L. When opening molded case breakers, positive indication in the form of a snap or click is required to ensure that the breaker is open. If positive indication is not verified, evaluate the situation with the RE.

M. The procedure for clearing a 161 kV or 500 kV air blast power circuit breaker requires the breaker and its disconnects to be opened and then the breaker cycled at the direction of the transmission operator to discharge any capacitors that may be in parallel with the contacts of the breaker.

NPG Standard Clearance Procedure to Safely Control NPG-SPP-10.2 Programs and Energy Rev. 0005 Processes Page 55 of 80 Appendix D (Page 2 of 3)

Special Requirements for Electrical Clearances 1.0 REQUIREMENTS (continued)

N. When placing or removing clearances inside electrical boards, the QE shall ensure that no loose materials remain in the breaker compartment.

O. 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.

P. Clearances on fused circuits other than control circuits (e.g., bus PT, voltage regulator PT, metering PT, etc.) shall have the danger tag attached to the fuse compartment door after the fuses have been removed from the circuit. The fuses shall be placed in an approved storage location.

Q. Clearances involving control fuses located on multi-fused terminal boards required to be tagged shall have the control fuses removed, a danger tag attached to non-conducting fuse blanks, and the blanks inserted into the fuse clips.

R. Clearances on fused control circuits (1) on boards with molded case breakers or (2) for which fuse blanks are not provided, do not require tagging and installation of fuse blanks. The location from which fuses were removed shall have a danger tag attached. Fuses removed should be placed in a secure, easily identifiable location where adverse plant conditions would not occur if they became dislodged from that location. Fuse storage may be in a fuse storage cabinet or in an appropriate bag attached to the compartment from which the fuses were removed (e.g., door handle, lugs attached to the relay covers, etc.). Fuses stored in a fuse storage cabinet should be clearly annotated on the clearance sheet.

S. The following applies for placement of clearances on low voltage circuits (250V or less):

1. When available, appropriate electrical prints for load lists and electrical circuit prints shall be utilized.

2. If plant conditions preclude tagging of main breaker to multiple components in a circuit, fuses shall be removed and tagged where available to isolate only those components affected by the work.

3. If the circuit involves relays or solenoids that are normally energized, the impact of a loss of power as well as a return to power to these components shall be evaluated, e.g. review of applicable logic or control diagrams.

NPG Standard Clearance Procedure to Safely Control NPG-SPP-10.2 Programs and Energy Rev. 0005 Processes Page 56 of 80 Appendix D (Page 3 of 3)

Special Requirements for Electrical Clearances 1.0 REQUIREMENTS (continued)

4. Circuits that supply power to a board or panel often "daisy-chain" and supply additional panels and components. A detailed search of wiring connection prints is required to determine all the components affected.

5. When low-voltage circuits are de-energized, alarms and responses shall be evaluated to ensure expected results are obtained. The MCR shall be contacted immediately prior to opening the circuit. When the affected unit is at power, the MCR shall be contacted after the circuit is opened to verify expected results.

NPG Standard Clearance Procedure to Safely Control NPG-SPP-10.2 Programs and Energy Rev. 0005 Processes Page 57 of 80 Appendix E (Page 1 of 3)

Special Requirements for Mechanical Clearances 1.0 REQUIREMENTS A. An air-operated valve that fails open on a loss of air is not be considered closed for blocking purposes unless it is held closed with an installed jacking device or device used to secure the valve in the required position. A clearance tag will be issued and attached to the jacking or other device.

B. An air-operated valve that fails closed shall have its air supply electrically or mechanically isolated, depressurized, and the valve visually checked-to-be-closed by local or remote indication. The air supply energy-isolating devices shall be tagged.

C. An air-operated valve that fails as is shall be closed and mechanically restrained. Its air supply should be electrically or mechanically isolated, depressurized, and the valve visually checked to be closed by local or remote indication. The air supply energy-isolating devices and mechanical restraint shall be tagged.

D. In cases where it is not possible to physically secure an air operated valve that fails as-is in the closed position, the valve will be tagged closed by applying closing air to the valve diaphragm by the use of the solenoid valve air overrides and tagging both the handswitch in the closed position and the solenoid valve air overrides. Prior to allowing work to begin, the equipment will be drained and de-pressurized to ensure the boundary valves are holding. This condition will be noted in the remarks section of the clearance sheet to inform PAE/Authorized Employee(s) that pressurized air is required to ensure the valve remains closed. This work is considered working on energized equipment and must be approved by the Plant Manager.

E. Pressure controlled valves, relief valves, and check valves will not be used as isolation boundary valves under normal conditions. Where such a valve does not have an external means of physical restraint, the work is considered working on energized equipment and must be approved by the Plant Manager.

F. The following instructions govern the use of freeze plugs

1. The clearance should be in place, but not issued, before establishing the freeze plug.

2. The need for the freeze plug should be identified on the Remarks Section of the clearance sheet. The freeze plug should not be listed as a device held on the clearance sheet. The establishment and maintenance of the freeze plug shall be in accordance with approved procedures or work documents.

3. The freeze plug shall be attended by qualified personnel to ensure that it is maintained intact until all work is complete and the proper Post Maintenance Tests (PMTs) are performed.

4. If the clearance must be released to allow performance of a PMT, the equipment shall be retagged before allowing the freeze plug to thaw. This will prevent migration of a portion of the plug.

NPG Standard Clearance Procedure to Safely Control NPG-SPP-10.2 Programs and Energy Rev. 0005 Processes Page 58 of 80 Appendix E (Page 2 of 3)

Special Requirements for Mechanical Clearances 1.0 REQUIREMENTS (continued)

5. The clearance must be released before allowing the freeze plug to thaw.

However, to prevent migration of the freeze plug, tags on boundary valves shall not be removed until the freeze plug has completely thawed.

6. All vents and drains shall be verified CLOSED before allowing the freeze plug to thaw.

G. If suitable means are not available to depressurize or control hazardous energy, the PAE, RE, and responsible manager(s) will determine actions necessary to protect employees. These actions must be approved by the Plant Manager or designee and documented in the Remarks section. The inability to depressurize shall be clearly documented in the remarks section and communicated to the proposed clearance holder. In cases where the component design does not include a vent or drain path within the clearance boundary, the clearance shall be locked to preclude clearance holder sign-on and initiation of work prior to direct communication with the RE.

Suitable methods to depressurize and prevent repressurization shall be agreed upon by the RE and the PAE before the clearance is held by the PAE.

H. When performing Temporary Lifts that could result in fluid flow (e.g., Motor Operated Valve Actuator Test (MOVAT) testing, valve stroke, etc.) the PAE responsible for the activity shall ensure that a flow blocking clearance is in place to maintain safe isolation and adequate flow blocking.

I. Clearances for work on high energy systems (operate with temperature greater than 200°F or pressure greater than 500 psig), lethal chemical systems, or systems connected to high energy systems shall, when possible isolate the work area by two closed valves in series. If equipped, a tell-tale vent or drain between the isolation valves should be opened. Lack of two valve isolation shall be clearly documented and communicated to the proposed clearance holder before issue.

J. The use of Abandoned Equipment Boundary valves as energy isolating devices requires the application of the same constraints that apply for the use on any other valve used as an energy isolating device. For example: position verification capability, maintenance of isolation from hazardous energy, etc.

K. The establishment of a safe boundary to allow work to be done on an Abandoned Equipment Boundary valve shall utilize equipment NOT abandoned. The boundary shall meet the same criteria as any other boundary.

L. When underground piping systems with slip-joint construction, e.g., a fire protection system, is being cleared, write the clearance to isolate at the second valve back from the work location to prevent release of energy at the first valve by a slip joint during excavation and work. The first valve back from the work location is tagged in the opened position to relieve pressure. If the location of the second valve back is such that the valve may be disturbed by the excavation, then a valve further back shall be closed and tagged to provide a safe clearance.

NPG Standard Clearance Procedure to Safely Control NPG-SPP-10.2 Programs and Energy Rev. 0005 Processes Page 59 of 80 Appendix E (Page 3 of 3)

Special Requirements for Mechanical Clearances 1.0 REQUIREMENTS (continued)

M. Clearances for entry into Permit Required Confined Spaces with piping, lines, or ducts (steam, water, inert gases, chemicals, etc) must be completely protected against the release of energy and material into the space by such means as:, 1) blanking or blinding:, 2) misaligning or removing sections of lines, pipes, or ducts:, 3) a double block and bleed system, such as two closed valves in series with an open vent between the valves. Entry into confined spaces must comply with TSP 801, Confined Space Entry.

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-B SI pump circuit. While relay replacement is in progress, the 1B-B 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

Tennessee Valley Authority Clearance Tag List and Operational Steps Clearance Sheet Clearance No. Page of Apparatus:

Equipment ID Place. Place. Restore Restore st nd st nd Equipment Description Tag Serial Tag Place. Place. 1 2 Rest. Restore As left 1 2 Tag Notes Equipment Location No. Type Seq. Config. Verifier Verifier Seq. Config. Confg. Verifier Verifier TVA 17984 [11-2005]

Tennessee Valley Authority Clearance Tag List and Operational Steps Clearance Sheet Clearance No. Page of Apparatus:

Equipment ID Place. Place. Restore Restore st nd st nd Equipment Description Tag Serial Tag Place. Place. 1 2 Rest. Restore As left 1 2 Tag Notes Equipment Location No. Type Seq. Config. Verifier Verifier Seq. Config. Confg. Verifier Verifier TVA 17984 [11-2005]

Tennessee Valley Authority Clearance Tag List and Operational Steps Clearance Sheet Clearance No. Page of Apparatus:

Equipment ID Place. Place. Restore Restore st nd st nd Equipment Description Tag Serial Tag Place. Place. 1 2 Rest. Restore As left 1 2 Tag Notes Equipment Location No. Type Seq. Config. Verifier Verifier Seq. Config. Confg. Verifier Verifier TVA 17984 [11-2005]

Watts Bar Nuclear Plant 201303 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 lubrication and oil sample collection of the 1B-B SI.

3.) Identifies that electrical isolations are required prior to mechanical isolations.

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 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

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 1.

2. Electrical Maintenance will be replacing the 30X, 1X and 30RX relays in the 1B-B SI pump circuit. While relay replacement is in progress, the 1B-B 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-B SI pump STEP circuit, lubricating and collecting oil samples from the 1B-B 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-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 1B-B MINI FLOW RECIRC TO RWST, A6U/692 Listed components are 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-B SI pump STEP circuit, lubricating and collecting oil samples from the 1B-B 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.

Listed components are critical to correctly isolate the electrical and mechanical portions 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-B SI pump STEP circuit, lubricating and collecting oil samples from the 1B-B 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-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 (3) 1-FU-211-B15/1A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 (3) 1-FU-211-B15/2N SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15(3) 1-FU-211-B15/2A SIS PUMP 1B-B FUSE 6.9 KV SD BD 1B-B, C/15 (3) 1-BKR-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, 480V RX MOV BD 1B1-B, C/13D (4) 1-ISV-63-527, SI PUMP DISCHG ISOL, A7V/700 (5) 1-FCV-63-175, SI PUMP 1-B-B MINI FLOW RECIRC TO RWST, A6U/692 (5)

Listed components are 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-B SI pump STEP circuit, lubricating and collecting oil samples from the 1B-B 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-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 Positions of listed components are 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 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

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

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

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

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