Text

302 Draft Administrative JPMs
	ML17165A487
Person / Time
Site:	Watts Bar
Issue date:	06/14/2017
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	50-390/13-302, 50-391/13-302 50-390/OL-13, 50-391/OL-13
	Download: ML17165A487 (150)
	v • d • e

Watts Bar Nuclear Plant NRC EXAM 2013302 Administrative JPM 1

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

NRC EXAM 2013-302 EVALUATION SHEET Task: PERFORM SOI-62.01, BORON CONCENTRATION CONTROL, APPENDIX C, CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS).

Alternate Path: n/a Facility JPM #:

Safety Function: 2.1

Title:

Conduct of Operations K/A 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

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

References:

SOI-62.02, Boron Concentration Control, Rev. 56.

TI-59, Boron Tables, Rev. 7.

Task Number: RO-062-SOI-62-017

Title:

Perform manual makeup to the Volume Control Tank.

Task Standard: The applicant performs SOI-62.02, Boron Concentration Control, Appendix C, CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS), and calculates:

1.) The total VCT addition to be 367 +/- 1 gallon.

2.) The BA flow rate to be 10.60 gpm. (10.729 gpm is acceptable, if applicant elects to perform conservative calculation.)

3.) The amount of BA to be entered into the BA integrator to be 48 gallons +/- 1 gallon.

4.) The amount of PW to be entered into the PW integrator to be 318 gallons +/-

1 gallon.

Validation Time: 25 minutes Time Critical: Yes No X

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

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

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

COMMENTS Page 2 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

NRC EXAM 2013-302 Tools/Equipment/Procedures Needed:

A copy of the NRC REFERENCE DISK.

A copy of SOI-62.02, Boron Concentration Control, Appendix C, CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS), for each applicant.

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

Page 3 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

NRC EXAM 2013-302 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 at 100% power, MOL conditions.

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

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

4. RCS Boric Acid Concentration is 915 ppm.

5. BAT Boric Acid Concentration is 6900 ppm.

6. REACTINW computer program is NOT AVAILABLE.

INITIATING CUES:

Using the appropriate plant procedure, you are to determine the following:

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

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

3. Amount of boric acid to be added.

4. Amount of primary water to be added.

Notify the Examiner when you have completed the calculation.

UNLESS DIRECTED OTHERWISE BY THE PROCEDURE, ROUND ALL CALCULATIONS TO 3 DECIMAL PLACES Page 4 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: Obtain a copy of the procedure.

___ SAT STANDARD:

The applicant locates copy of SOI-62.02, Boron Concentration ___ UNSAT Control, Appendix C, CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS).

COMMENTS:

STEP 2: [1] OBTAIN the following data for use in the HAND

___ SAT CALCULATION:

[1.1] Current RCS Boric Acid Concentration. ___ UNSAT

[1.2] Current BAT Boric Acid Concentration.

[1.3] B-10 Depletion Value from Reactivity Management Briefing Sheet

[1.4] Current VCT Level

[1.5] Desired VCT Level STANDARD:

Applicant correctly transposes the data from the INITIAL CONDITIONS and INITIATING CUES portion to the APPLICANT HANDOUT SHEET.

Applicant refers to the Reactivity Management Briefing Sheet and determines the B-10 depletion to be 0 PPM

[1.1] Current RCS Boric Acid Concentration: 915 ppm

[1.2] Current BAT Boric Acid Concentration: 6900 ppm

[1.3] B-10 Depletion Value from Reactivity Management Briefing Sheet: 0 from Cycle 12 MOL Reactivity Briefing Book.

[1.4] Current VCT Level: 22%

[1.5] Desired VCT Level: 41%

COMMENTS:

Page 5 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT EXAMINER: Step 2 allows for the entry of 1.0 for a conservative calculation. This value is also acceptable. Remaining steps which are affected by this difference are calculated each of the values.

STEP 3: [2] CALCULATE BAT Boric Acid Concentration Ratio (BACR): ___ SAT 6820 ppm ÷ Step 2.0[1.2]ppm =_________ ___ UNSAT (ENTER 1.0 for BACR following a reactor shutdown or for a conservative calculation).

STANDARD:

Applicant determines that the BACR is 0.988. (Rounded from 0.988405) 6820PPM / 6900 PPM = 0.988405 OR Applicant elects to perform the conservative calculation and enters a value of 1.0.

Step is critical since the BACR affects a later calculation of the BA Blender Flow Rate setting.

COMMENTS:

STEP 4: [3] CALCULATE B-10 corrected boron concentration: ___ SAT

__________-______________=____________ PPM ___ UNSAT STEP 2.0[1.1] STEP 2.0[1.3] B-10 corrected boron STANDARD:

Applicant adds 915 PPM and 0 PPM and calculates the B-10 corrected boron concentration to be 915 PPM.

COMMENTS:

Page 6 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 5: [4] CALCULATE total VCT addition volume needed for desired CRITICAL level. STEP

___ SAT

___ UNSAT STANDARD:

Applicant calculates the total VCT additional volume to be 367 GAL.

41%-22% x 19.3 GAL/% = 366.7 GAL, rounded to 367 GAL.

Step is critical since the change in level is the basis for the remainder of the calculation.

COMMENTS:

Page 7 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT NOTE Corrected Boric Acid Flow Rate in Step 2.0[5] should be obtained from TI-59, Appendix C for the B-10 corrected boron value calculated in Step 2.0[3].

STEP 6: [5] CALCULATE 1-FC-62-139, BA TO BLENDER FCV-62-140 CRITICAL CONTROL, flow setpoint. STEP

___ SAT

___ UNSAT STANDARD:

Applicant refers to TI-59, Boron Tables, Appendix C, Reactor Coolant Boron Concentration Vs. Automatic Makeup Flow Rate Primary Water Flow of 70 GPM With 4% Boric Acid, Page 20.

10.796 - 10.661 = 0.135 / 2 = 0.068 + 10.661 = 10.729 Applicant performs an interpolation and determines that the corrected boric acid flow rate for 915 PPM is 10.729 GPM.

Applicant multiplies 10.729 times 0.988 and determines that the BA to Blender Flow is 10.60 GPM (Rounded from 10.600252).

OR Applicant multiplies 10.729 times 1.0 and determines that the BA to Blender Flow is 10.729 GPM Step is critical since the flow rate determination affects the total amount of boric acid which will be added.

COMMENTS:

Page 8 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 7: [6] CALCULATE TOTAL flow rate. CRITICAL STEP

___ SAT

___ UNSAT STANDARD:

Applicant adds 10.60 GPM to 70 GPM to determine the TOTAL FLOW RATE to be 80.60 GPM.

OR Applicant adds 10.729 GPM to 70 GPM to determine the TOTAL FLOW RATE to be 80.729 GPM.

Step is critical since the flow rate determination affects the total amount of boric acid which will be added.

COMMENTS:

STEP 8: [7] CALCULATE [Y] BA Fraction.

CRITICAL STEP

___ SAT

___ UNSAT STANDARD:

Applicant divides 10.60 GPM by 80.60 GPM and determines the BA Fraction to be 0.132 (Rounded from 0.131513648.)

OR Applicant divides 10.729 GPM by 80.729 GPM and determines the BA Fraction to be 0.133 (Rounded from 0.132901436.)

Step is critical since the flow rate determination affects the total amount of boric acid which will be added.

COMMENTS:

Page 9 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 9: [8] CALCULATE 1-FQ-62-139, BA BATCH COUNTER Setting. CRITICAL STEP

___ SAT

___ UNSAT STANDARD:

Applicant multiplies 0.132 times 367 GALs and determines the Boric Acid Batch Counter Setting to be 48 GAL (Rounded from 48.44 GAL.).

OR Applicant multiplies 0.133 times 367 GALs and determines the Boric Acid Batch Counter Setting to be 49 GAL (Rounded from 48.811 GAL.).

Step is critical since the flow rate determination affects the total amount of boric acid which will be added.

COMMENTS:

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

Page 10 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 10: [9] CALCULATE [Z] PW Fraction. CRITICAL STEP

___ SAT

___ UNSAT STANDARD:

Applicant divides 70 GPM by 80.60 GPM and determines the PW Fraction to be 0.868.

OR Applicant divides 70 GPM by 80.729 GPM and determines the PW Fraction to be 0.867.

Step is critical since the flow rate determination affects the total amount of primary water which will be added.

COMMENTS:

STEP 11: [10] CALCULATE 1-FQ-62-142, PW BATCH COUNTER CRITICAL Setting. STEP

___ SAT

___ UNSAT STANDARD:

Applicant multiplies 0.868 times 367 GAL and determines the Primary Water Batch Counter Setting to be 319 GAL (Rounded from 318.556 GAL.).

OR Applicant multiplies 0.867 times 367 GAL and determines the Primary Water Batch Counter Setting to be 318 GAL (Rounded from 318.189 GAL.).

Step is critical since the flow rate determination affects the total amount of primary water which will be added.

COMMENTS:

Page 11 of 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 1

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 12: Notify the Unit Supervisor that SOI-62.02, Boric Concentration ___ SAT Control, Appendix C, CALCULATION OF BORIC ACID AND ___ UNSAT PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS).

STANDARD:

Applicant notifies the Unit Supervisor that the calculation is complete and ready for review.

COMMENTS:

END OF TASK STOP TIME ________

Page 12 of 15

1 KEY DO NOT HAND TO APPLICANT Page 13 of 15

WBN Boron Tables TI-59 Unit 1 Rev. 0007 Page 20 of 105 2013-302 NRC EXAM JPM 1 KEY Appendix C (Page 3 of 7)

Reactor Coolant Boron Concentration Vs. Automatic Makeup Flow Rate Primary Water Flow of 70 GPM With 4% Boric Acid BORON BORIC ACID BORON BORIC ACID CONCENTRATION FLOW RATE (gpm) CONCENTRATION FLOW RATE (gpm) 810 9.332 1010 12.036 820 9.463 1020 12.176 830 9.594 1030 12.317 840 9.726 1040 12.458 850 9.858 1050 12.600 860 9.991 1060 12.742 870 10.124 1070 12.884 880 10.258 1080 13.027 890 10.392 1090 13.171 900 10.526 1100 13.315 910 10.661 1110 13.460 845 PPM BORIC ACID FLOW RATE IS 10.729 920 10.796 1120 13.605 930 10.932 1130 13.750 940 11.069 1140 13.896 950 11.206 1150 14.043 960 11.343 1160 14.190 970 11.481 1170 14.338 980 11.619 1180 14.486 990 11.757 1190 14.635 1000 11.897 1200 14.784

2013-302 NRC EXAM JPM 1 KEY 2013-302 NRC EXAM JPM 1 KEY 2013-302 NRC EXAM JPM 1 KEY 2013-302 NRC EXAM JPM 1 KEY 1

Handout Package for Applicant Page 14 of 15

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

INITIAL CONDITIONS:

1. Unit 1 is at 100% power, MOL conditions.

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

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

4. RCS Boric Acid Concentration is 915 ppm.

5. BAT Boric Acid Concentration is 6900 ppm.

6. The REACTW computer program is NOT AVAILABLE.

INITIATING CUES:

Using the appropriate plant procedure, you are to determine the following:

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

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

3. Amount of boric acid to be added.

4. Amount of primary water to be added.

Notify the Examiner when you have completed the calculation.

UNLESS DIRECTED OTHERWISE BY THE PROCEDURE, ROUND ALL CALCULATIONS TO 3 DECIMAL PLACES 1

Watts Bar Nuclear Plant Unit 1 System Operating Instruction SOI-62.02 Boron Concentration Control Revision 0056 Quality Related Level of Use: Continuous Use Effective Date: 06-27-2013 Responsible Organization: OPS, Operations Prepared By: P.R. Neu Approved By: R.B. Nessell

WBN Boron Concentration Control SOI-62.02 Unit 1 Rev. 0056 Page 2 of 58 Revision Log Rev or Change Effective Affected Page Number Date Numbers Description of Revision/Change 51 10/01/10 2, 4, 7, 9-12, 14- Minor/editorial revision:

17, 19, 21, 23- Added signoffs to Steps 8.1[22] through 8.1[25]

29, 31-33, 35, (PCR 4637).

38, 40-44, 57 Added () notation for direct reactivity steps.

Reformatted source notes, added section end identification and created external attachments for all checklists.

UC-1 12/31/10 2, 33, 35-39 Added steps to section 8.2 to prevent invalid data being sent to the BEACON core monitoring software

[SR 303078] [DCN 52277].

Minor/ Editorial and administrative changes to correct step number in NOTE in section 8.1, change branching steps to IF/THEN logic and reformatted a step for ease of use.

52 01/11/11 2, 33, 35, 36, 38, Incorporate UC-1 39 53 07/14/11 2, 7 Minor Editorial change. PER 367518: Revise Section 3.0.B to state pressurizer boron concentration should be within 50 ppm of RCS boron concentration.

54 07/16/12 2, 7, 35, 50, 51 Added P&L to show overflow volume of the RWST

[PER 522766]

Corrected formulas to use subscripts for better formula formatting [PCR 5826]

Corrected Cross References in Appendix C section 2.0 [PCR 5964]

UC-1 08/29/12 2, 26, 27 Removed notes defining minor boration and dilution from section 6.6 and 6.7.

55 09/04/12 2, 26, 27 Incorporated UC-1.

56 06/27/13 2, 18, 40 Updated procedure steps for Boron Concentration Control [PER708518-001]

WBN Boron Concentration Control SOI-62.02 Unit 1 Rev. 0056 Page 3 of 58 Table of Contents

1.0 INTRODUCTION

.......................................................................................................... 5 1.1 Purpose ........................................................................................................................ 5 1.2 Scope............................................................................................................................ 5

2.0 REFERENCES

............................................................................................................. 6 2.1 Performance References .............................................................................................. 6 2.2 Developmental References........................................................................................... 6 3.0 PRECAUTIONS AND LIMITATIONS ........................................................................... 7 4.0 PREREQUISITE ACTIONS .......................................................................................... 8 4.1 Preliminary Actions ....................................................................................................... 8 4.2 Field Preparations ......................................................................................................... 8 4.3 Approvals and Notifications .......................................................................................... 8 5.0 STARTUP (OR STANDBY READINESS) .................................................................... 9 6.0 NORMAL OPERATION .............................................................................................. 10 6.1 Auto Makeup ............................................................................................................... 10 6.2 Dilution ........................................................................................................................ 11 6.3 Alternate Dilution or Flush........................................................................................... 15 6.4 Boration ...................................................................................................................... 18 6.5 Manual Makeup .......................................................................................................... 22 6.6 Minor Dilution .............................................................................................................. 26 6.7 Minor Boration ............................................................................................................ 27 7.0 SHUTDOWN ............................................................................................................... 29 8.0 INFREQUENT OPERATIONS .................................................................................... 30 8.1 RWST Makeup Using Blender .................................................................................... 30 8.2 Batching to Holdup Tank A Prior to Pumping Transfer Canal ..................................... 34 8.3 Boration with the Boric Acid Integrator Out of Service ................................................ 40 8.4 Minor Boration with the Boric Acid Integrator Out of Service ...................................... 43 8.5 VCT Level Reduction .................................................................................................. 45 9.0 RECORDS .................................................................................................................. 46 9.1 QA Records ................................................................................................................ 46

WBN Boron Concentration Control SOI-62.02 Unit 1 Rev. 0056 Page 4 of 58 Table of Contents (continued) 9.2 Non-QA Records ........................................................................................................ 46 Appendix A: VCT Level Program ................................................................................... 47 Appendix B: Blending Greater Than 2500 ppm ............................................................ 48 Appendix C: CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS) .......................................................................................................... 50 Appendix D: Calculation For Amount Of Boric Acid Or Primary Water (TI 59) ......................................................................................................... 54 Appendix E: REACTIVITY BALANCE CALCULATION ................................................. 55 Appendix F: CALCULATION OF TIME FOR A BORIC ACID ADDITION WHILE THE BORIC ACID INTEGRATOR IS OUT OF SERVICE .................................................................................................... 57 Source Notes............................................................................................. 58 ATTACHMENTS P: Boron Concentration Control Power Checklist 62.02-1P V: Boron Concentration Control Valve Checklist 62.02-1V

WBN Boron Concentration Control SOI-62.02 Unit 1 Rev. 0056 Page 5 of 58

1.0 INTRODUCTION

1.1 Purpose To provide instructions for operation of the CVCS Boron Concentration Control System.

1.2 Scope This Instruction includes the following operations:

A. Startup (Standby Readiness)

B. Automatic Makeup C. Dilution D. Alternate Dilution E. Boration F. Manual Makeup G. Minor Dilution H. Minor Boration I. RWST Makeup Using Blender J. Batching to Holdup Tank A Prior to Pumping Transfer Canal K. Major and Minor Boration with Boric Acid Integrator out of service L. VCT Level Reduction

WBN Boron Concentration Control SOI-62.02 Unit 1 Rev. 0056 Page 6 of 58

2.0 REFERENCES

2.1 Performance References A. 1-TRI-62-3, Boric Acid Flow Paths: Valve Position Verification B. NUPOP, Nuclear Parameters and Operations Package C. SOI-62.01, CVCS-Charging and Letdown D. SOI-62.05, Boric Acid Batching, Transfer and Storage E. SOI-62.06, Boron Disposal System F. SOI-78.01, Spent Fuel Pit Cooling and Cleaning System G. SOI-81.01, Primary Makeup Water Systems H. SOI-236.01, 125V DC Vital Battery Board I I. TI-4 PART II, Pant Curve Book, Tank Curves, Turbine Curves J. Tech Requirements Fig 3.1.6, Boric Acid Tank Limits K. Computer Program REACTW and REACTW Computer Program User's Guide.

L. Computer Program REACTINW and REACTINW Computer Program User's Guide M. TI-59, Boration Tables 2.2 Developmental References A. Tech Spec Section 3.1, Reactivity Control Systems B. System Description N3 62 4001, Chemical and Volume Control System C. TVA Drawings:

1. 47W610-62-3

2. 47W611-62-2

3. 47W809-2

4. 47W812-1

5. 47W855-1

WBN Boron Concentration Control SOI-62.02 Unit 1 Rev. 0056 Page 7 of 58 3.0 PRECAUTIONS AND LIMITATIONS A. At least one Reactor Coolant Pump (RCP) or one Residual Heat Removal (RHR) Pump will be in operation during boron concentration (CB) changes.

[C.1][C.2][C.3]

B. Pressurizer (Pzr) CB should be within 50 ppm of RCS CB.

C. Axial Offset should be maintained in Target Band during CB changes.

D. Normally the reactor will NOT be made critical by boron dilution.

E. Boric Acid Tank (BAT) level should be monitored during makeup or boration to avoid violating Tech Requirement (TR) 3.1.6 level limits, and consideration of the other requirements of TR 3.1.5 and 3.1.6 should be evaluated, particularly in sections which use the in-service BAT.

F. TI-59 Boration Tables were calculated using 70 gpm Primary Water flow up to 2500 ppm. For blending at concentrations greater than 2500 ppm, primary water flow will need to be adjusted downward per Appendix B while Boric Acid flow is maintained at 40 gpm (e.g. 100% on 1-FC-62-142)

G. Expect a delay between time boration/dilution is started until effect is seen in RCS.

H. When subcritical, Boration/Dilution effects are monitored by Source Range counts. Unexplained change in count rate requires the operation to be stopped.

I. At power, Boration/Dilution effects are monitored by Rod movement and Tavg.

Operation must be stopped if Rods move in the wrong direction or Tavg change is unexplained.

J. The following should be evaluated as potential Reactivity Management issues:

unanticipated

1. power change >0.5%,

2. rod motion > 5 steps,

3. Tavg change >1°F.

K. During refueling operations, boron concentration changes can affect Mansell readings. If Mansell is in service for RCS level indication, and RCS boron concentration is changed, the Boron Concentration Input value to Mansell should be adjusted.

L. The overflow volume for the RWST is 380,000 gallons. Overflow is through an 8" line which drains back into the pipe tunnel that connects with the auxiliary building.

WBN Boron Concentration Control SOI-62.02 Unit 1 Rev. 0056 Page 8 of 58 Date________ Initials 4.0 PREREQUISITE ACTIONS 4.1 Preliminary Actions NOTES

1) Throughout the Instruction where an IF/THEN statement occurs, the step should be N/A if stated condition does NOT exist.

2) Signoffs/information in unused Sections may be left blank.

[1] INDICATE Section to be performed, and reason for use:

5.0 Startup 7.0 Shutdown 6.0 Normal 8.0 Infrequent Operation Operations Section/ Reason/ Remarks:

4.2 Field Preparations

[1] ENSURE Section 3.0, Precautions, and Limitations, REVIEWED. ________

[2] CHECK Primary Water System IN SERVICE (ref SOI-81.01). ________

[3] ENSURE Refuel Water Storage Tank (RWST) and Boric Acid Tank(s) AVAILABLE. ________

[4] CHECK Boric Acid Pump(s) IN OPERATION (ref SOI-62.05). ________

4.3 Approvals and Notifications

[1] COORDINATE performance with US and UO. ________

WBN Boron Concentration Control SOI-62.02 Unit 1 Rev. 0056 Page 50 of 58 Appendix C (Page 1 of 4)

CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS)

Date________ Initials NOTES

1) Use page 1 of this appendix when using VCT MAKEUP CALCULATION program in REACTINW, otherwise use pages 2 and 3 when performing Hand Calculations.

2) The computer code named REACTINW (VCT MAKEUP CALCULATION) when used from the Y: server is a verified and validated program. The methodology used is based on the equations:

V1C1 + V2C2 = V3C3 & V1 + V2 = V3 1.0 REACTINW VCT MAKEUP CALCULATION

[1] OBTAIN the following data for input to the REACTINW program: ________

[1.1] Current RCS Boric Acid Concentration. ________ PPM

[1.2] Current BAT Boric Acid Concentration. ________ PPM

[1.3] B-10 Depletion Value from Reactivity Management Briefing Sheet ________ PPM

[1.4] Current VCT Level ________ %

[1.5] Desired VCT Level ________ %

[2] RUN REACTINW calculation VCT Makeup Calculation. ________

[3] PRINT the output file: VCT MAKEUP INTEGRATOR SETTINGS CALCULATION ________

[4] SIGN and DATE output sheets. ________

[5] OBTAIN independent verification and approval by an SRO on output sheets. ________

WBN Boron Concentration Control SOI-62.02 Unit 1 Rev. 0056 Page 51 of 58 Appendix C (Page 2 of 4)

CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS)

Date________ Initials 2.0 HAND CALCULATION

[1] OBTAIN the following data for use in the HAND CALCULATION: ________

[1.1] Current RCS Boric Acid Concentration. ________PPM

[1.2] Current BAT Boric Acid Concentration. ________PPM

[1.3] B-10 Depletion Value from Reactivity Management Briefing Sheet ________PPM

[1.4] Current VCT Level ________%

[1.5] Desired VCT Level ________%

[2] CALCULATE BAT Boric Acid Concentration Ratio (BACR):

6820 ppm ÷ Step 2.0[1.2]ppm =_________

(ENTER 1.0 for BACR following a reactor shutdown or for a conservative calculation). ________

[3] CALCULATE B-10 corrected boron concentration:

__________-______________=____________ PPM ________

STEP 2.0[1.1] STEP 2.0[1.3] B-10 corrected boron

[4] CALCULATE total VCT addition volume needed for desired level.

[ % - % ] X 19.3 Gals/% = GALS Step 1.0[1.5] Step 1.0[1.4] Total Volume (Round to nearest whole number)

WBN Boron Concentration Control SOI-62.02 Unit 1 Rev. 0056 Page 52 of 58 Appendix C (Page 3 of 4)

CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS)

Date________ Initials 2.0 HAND CALCULATION (continued)

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

[5]

GPM x = GPM Corrected Boric BACR from [X] BA to Blender Acid Flow Rate Step 2.0[2] Flow

[6]

GPM + 70 GPM = GPM Step 2.0[5] [X] PW to Total Flow Rate Blender Flow

[7]

GPM ÷ GPM = GPM Step 2.0[5] [X] Step 2.0[6] [Y] BA Fraction Total Flow Rate

[8]

x GALS = GALS Step 2.0[7] [Y] Step 2.0[4] Boric Acid Batch Total Volume Counter Setting

WBN Boron Concentration Control SOI-62.02 Unit 1 Rev. 0056 Page 53 of 58 Appendix C (Page 4 of 4)

CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS)

Date________ Initials 2.0 HAND CALCULATION (continued)

NOTE Round answer to nearest whole number.

[9]

70 GPM ÷ GPM =

Primary H2O Step 2.0[6] [Z] PW Fraction Total Flow Rate

[10]

x GALS = GALS Step 2.0[9] [Z] Step 2.0[4] Primary Water Total Volume Batch Counter Setting

[11] APPROVE calculation results. ________

IV/SRO Calculation check: Step 2.0[8] results + Step 2.0[10] results should = Step 2.0[4] results

Watts Bar Nuclear Plant NRC EXAM 2013302 Administrative JPM 2 R

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2R NRC EXAM 2013-302 EVALUATION SHEET Task: DETERMINE AFW PUMP REQUIREMENTS.

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

Title:

Conduct of Operations.

K/A 2.1.32 Ability to explain and apply system limits and precautions.

Rating(s): 2.7/3.5 CFR: 41.10/43.2/45.12 Evaluation Method: Simulator In-Plant Classroom X

References:

GOI-7, Generic Equipment Operating Guidelines, Rev. 50.

Task Number: RO-003-SOI-3.02-006

Title:

Manually startup the motor driven Auxiliary Feedwater pumps.

Task Standard: The applicant determines:

1.) No starting limitations have been violated based on GOI-7, Generic Equipment Operating Guidelines.

2.) 1B-B MD AFW Pump may be started immediately, or at any time after 2125. The 1A-A MD AFW pump cannot be restarted on October 15, 2013.

3.) Electrical Maintenance (EM) must be notified to perform 2500-volt megger, bridge, and dc high-potential tests after the 1B-B AFW pump tripped by instantaneous overcurrent relay operation.

Validation Time: 10 minutes Time Critical: Yes No X

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

=

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

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

==

COMMENTS

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2R NRC EXAM 2013-302 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 following is the run history for 1A-A MD AFW pump and 1B-B MD AFW pump on October 15, 2013:

Pump Start Shutdown Run Time Time Time (minutes) 1A-A 0115 0137 0205 0220 0310 0335 0818 0845 1130 1215 1400 1445 1B-B 0230 0255 0305 0315 0535 0615 1545 1620 1950 2105 Each of the listed pump starts resulted in a normal start.

Current time is 2125.

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

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

1. If any starting limitations have been violated.

2. The pump(s) allowed to be started an additional time on October 15, 2013.

Part 2 If an instantaneous overcurrent relay operation occurs on the next Auxiliary Feedwater Pump start, what motor testing is required to be performed?

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2R NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

Part 1 STEP 1: Applicant determines that no starting limitations have been ___ SAT violated based on GOI-7, Generic Equipment Operating Guidelines.

___ UNSAT STANDARD:

From GOI-7, Generic Equipment Operating Guidelines, Section 5.2.5, Motor Operating and Starting Limitations.

[3] IF NO Nameplate data exists, THEN USE the following generic guidelines for starting motors:

A. Two starts in succession, coasting to rest between starts with the motor initially at ambient temperature; or B. One start with the motor initially at normal operating temperature.

[4] APPLY the following limitations to motors greater than/equal to 200 hp following any start under either condition in Step 5.2.5[3]

above:

A. Allow the motor to cool for 20 minutes while running at normal or no load; OR B. Allow the motor to cool for 45 minutes while standing idle before each additional restart is attempted.

Applicant locates GOI-7, Generic Equipment Operating Guidelines, Page 28 NOTE, which states that The Auxiliary Feedwater Pump motor is limited to six starts per day and the Condenser Circulating Water Pump motor is limited to eight starts per day.

The applicant determines that 1A-A MD AFW Pump has been started 6 times today, and 1B-B MD AFW Pump has been started 5 times today.

COMMENTS:

PAGE 5 0F 9

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2R NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 2: Applicant determines that the 1B-B MD AFW Pump may be CRITICAL started immediately, or at 2125. STEP Applicant determines the 1A-A MD AFW pump cannot be ___ SAT restarted on October 15, 2013.

STANDARD: ___ UNSAT Applicant determines that the 1B-B MD AFW Pump may be started at 2125 or any time thereafter.

Step is critical to ensure the correct AFW Pump started without violating starting duty limits.

COMMENTS:

Part 2 STEP 3: Applicant addresses the question ___ SAT If an instantaneous overcurrent relay operation occurs on the next Auxiliary Feedwater Pump start, what motor ___ UNSAT testing is required to be performed?

STANDARD:

Applicant determines that Electrical Maintenance (EM) must be notified to perform 2500-volt megger, bridge, and dc high-potential tests after a 6,900-volt motor has been tripped by relay operation.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 6 0F 9

2R KEY DO NOT HAND TO APPLICANT PAGE 7 0F 9

2-R KEY Part 1 Evaluate the Auxiliary Feedwater pump start history provided and determine:

1. If any starting limitations have been violated.

The applicant evaluates the data provided and determines that there were NO starting limitations violated.

2. The pump(s) allowed to be started an additional time on October 15, 2013.

The applicant determines that the 1B-B AFW pump may be started at 2125 or any time thereafter on October 15, 2013.

Part 2 If an instantaneous overcurrent relay operation occurs on the next Auxiliary Feedwater Pump start, what motor testing is required to be performed?

From GOI-7, Generic Equipment Operating Guidelines, Section 5.2,5, Motor Operating and Starting Limitations, Item [6]

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

WBN Generic Equipment GOI-7 Unit 0, 1, & 2 Operating Guidelines Rev. 0050 Page 28 of 75 5.2.5 Motor Operating and Starting Limitations (continued)

CAUTION The Auxiliary Feed Pump motor is limited to six starts per day and the Condenser Circulating Water Pump motor is limited to eight starts per day.

NOTE The life of a motor is affected by the number of start attempts made on an individual motor.

Most squirrel-cage motors are rotor critical, and the stator temperature rise will NOT reflect excessive temperature rise in the rotor squirrel cage caused by excessive starting duty.

[2] START motors greater than/equal to 200 hp once when at ambient or once when at operating temperature, THEN START motors per Nameplate data for any additional starts.

[3] IF NO Nameplate data exists, THEN USE the following generic guidelines for starting motors:

A. Two starts in succession, coasting to rest between starts with the motor initially at ambient temperature; or B. One start with the motor initially at normal operating temperature.

[4] APPLY the following limitations to motors greater than/equal to 200 hp following any start under either condition in Step 5.2.5[3] above:

A. Allow the motor to cool for 20 minutes while running at normal or no load; OR B. Allow the motor to cool for 45 minutes while standing idle before each additional restart is attempted.

[5] IF a motor stalls during a starting attempt, THEN CORRECT the conditions which caused the motor to stall, AND EXAMINE the motor thoroughly for damage caused by overheating before an additional restart is attempted. The rotor squirrel cage should be examined visually and tested electrically.

WBN Generic Equipment GOI-7 Unit 0, 1, & 2 Operating Guidelines Rev. 0050 Page 29 of 75 5.2.5 Motor Operating and Starting Limitations (continued)

NOTES

1) Severe damage to the motor and the auxiliary electrical system can be sustained by attempting to start a motor that already has a faulted stator winding.

2) If it is determined by an SRO that plant safety requires the restart of the motor, an exception to the limitations below may be made.

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

[7] NOTIFY EM to perform megger and bridge tests after a 480V motor (greater than/equal to 100 horsepower) has been tripped by protective relays or devices. This is done to determine whether the motor is suitable for service unless it can be determined that the motor was tripped because of overloading. When the trip out is apparently the result of overloading, the motor and the driven equipment should be inspected visually before attempting to restart the motor.

5.2.6 Auxiliary Power System Transformer Loading NOTE Yellow lines are placed on transformer primary and secondary ammeters to indicate nameplate loading (primary feeds to multiple transformers are NOT marked). Red lines are placed on the ammeters to indicate maximum transformer loading.

[1] MAINTAIN loadings at or below the yellow line on all transformers having associated ammeters, AND NOTIFY the Shift Manager (SM) of any transformer loaded above the yellow line.

2R Handout Package for Applicant PAGE 8 0F 9

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

INITIAL CONDITIONS:

The following is the run history for 1A-A MD AFW pump and 1B-B MD AFW pump on October 15, 2013:

Pump Start Shutdown Run Time Time Time (minutes) 1A-A 0115 0137 0205 0220 0310 0335 0818 0845 1130 1215 1400 1445 1B-B 0230 0255 0305 0315 0535 0615 1545 1620 1950 2105 Each of the listed pump starts resulted in a normal start.

Current time is 2125.

INITIATING CUE:

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

1. If any starting limitations have been violated.

2. The pump(s) allowed to be started an additional time on October 15, 2013.

Part 2 If an instantaneous overcurrent relay operation occurs on the next Auxiliary Feedwater Pump start, what motor testing is required to be performed?

2R

Watts Bar Nuclear Plant NRC EXAM 2013302 Administrative JPM 2 S

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S NRC EXAM 2013-302 EVALUATION SHEET Task: DETERMINE AFW PUMP START REQUIREMENTS.

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

Title:

Conduct of Operations.

K/A 2.1.32 Ability to explain and apply system limits and precautions.

Rating(s): 2.7/3.5 CFR: 41.10/43.2/45.12 Evaluation Method: Simulator In-Plant Classroom X

References:

GOI-7, Generic Equipment Operating Guidelines, Rev. 50.

LCO 3.7.5, Auxiliary Feedwater (AFW) System, Amendment 91.

Task Number: RO-003-SOI-3.02-006

Title:

Manually startup the motor driven Auxiliary Feedwater pumps.

Task Standard: The applicant determines:

1. NO motor start limitations have been violated based on the history provided

2. 1B-B AFW pump can be started at 2125 on October 15, 2013. The 1A-A AFW pump cannot be restarted on October 15, 2013.

3. Electrical Maintenance (EM) must be notified to perform 2500-volt megger, bridge, and dc high-potential tests after the 1B-B AFW pump tripped by instantaneous overcurrent relay operation.

4. LCO 3.7.5, Auxiliary Feedwater (AFW) System, Action B is applicable, and the 1B-B AFW pump must be declared INOPERABLE, and restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Validation Time: 10 minutes Time Critical: Yes No X

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

=

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

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

==

COMMENTS

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S NRC EXAM 2013-302 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 following is the run history for 1A-A MD AFW pump and 1B-B MD AFW pump on October 15, 2013:

Pump Start Shutdown Run Time Time Time (minutes) 1A-A 0115 0137 0205 0220 0310 0335 0818 0845 1130 1215 1400 1445 1B-B 0230 0255 0305 0315 0535 0615 1545 1620 1950 2105 Each of the listed pump starts resulted in a normal start.

Current time is 2125.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S NRC EXAM 2013-302 INITIATING CUES:

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

1. If any starting limitations have been violated.

2. The pump(s) allowed to be started an additional time on October 15, 2013.

Part 2 Unit 1 is in Mode 2 when the 1A-A MD AFW Pump trips on instantaneous overcurrent relay operation when started.

1.) What testing must be performed on the 1A-A MD AFW Pump motor as a result of the trip?

2.) What actions are required to be taken to comply with Tech Specs?

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

Part 1 STEP 1: Applicant determines that no starting limitations have been ___ SAT violated based on GOI-7, Generic Equipment Operating Guidelines.

___ UNSAT STANDARD:

From GOI-7, Generic Equipment Operating Guidelines, Section 5.2.5, Motor Operating and Starting Limitations.

[3] IF NO Nameplate data exists, THEN USE the following generic guidelines for starting motors:

A. Two starts in succession, coasting to rest between starts with the motor initially at ambient temperature; or B. One start with the motor initially at normal operating temperature.

[4] APPLY the following limitations to motors greater than/equal to 200 hp following any start under either condition in Step 5.2.5[3]

above:

A. Allow the motor to cool for 20 minutes while running at normal or no load; OR B. Allow the motor to cool for 45 minutes while standing idle before each additional restart is attempted.

Applicant locates GOI-7, Generic Equipment Operating Guidelines, Page 28 NOTE, which states that The Auxiliary Feedwater Pump motor is limited to six starts per day and the Condenser Circulating Water Pump motor is limited to eight starts per day.

The applicant determines that 1A-A MD AFW Pump has been started 6 times today, and 1B-B MD AFW Pump has been started 5 times today.

COMMENTS:

PAGE 5 0F 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 2: Applicant determines that the 1B-B MD AFW Pump may be CRITICAL started immediately, or at 2125. STEP Applicant determines the 1A-A MD AFW pump cannot be ___ SAT restarted on October 15, 2013.

STANDARD: ___ UNSAT Applicant determines that the 1B-B MD AFW Pump may be started at 2125 or any time thereafter.

Step is critical to ensure the correct AFW Pump started without violating starting duty limits.

COMMENTS:

PAGE 6 0F 11

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE 2S NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Part 2 STEP 3: Applicant addresses the question ___ SAT Unit 1 is in Mode 2 when the 1A-A MD AFW Pump trips on ___ UNSAT instantaneous overcurrent relay operation when started.

1.) What testing must be performed on the 1A-A MD AFW Pump motor as a result of the trip?

STANDARD:

Applicant determines that Electrical Maintenance (EM)must be notified to perform 2500-volt megger, bridge, and dc high-potential tests after a 6,900-volt motor has been tripped by relay operation.

COMMENTS:

STEP 4: Applicant addresses the question. CRITICAL STEP

___ SAT 2.) What actions are required to be taken to comply with Tech Specs?

STANDARD: ___ UNSAT Applicant refers to LCO 3.7.5, and determines that CONDITION B applies.

B. One AFW train inoperable in MODE 1, 2 or 3 for reasons other than Condition A. Restore AFW train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND 10 days from the discovery of failure to meet the LCO.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 7 0F 11

2S KEY DO NOT HAND TO APPLICANT PAGE 8 0F 11

2-S KEY Part 1 Evaluate the Auxiliary Feedwater pump start history provided and determine: