Text

301 Final Administrative JPMs
	ML102371238
Person / Time
Site:	Watts Bar
Issue date:	08/25/2010
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	50-390/08-301
	Download: ML102371238 (148)
	v • d • e

RevO PAGE 1 0F21 Watts Bar Nuclear Plant 3-OT-JPMADA 1 -7a Hand Calculation of Boric Acid and Primary Water Integrator Setting for Manual Makeup to the VCT

RevO PAGE 2 0F21 Watts Bar Nuclear Plant 3-OT-JPMADA 1 -7a NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 Initial issue, generated for NRC Initial All D. Hughes License Exam

Rev 0 PAGE 3 0F21 Watts Bar Nuclear Plant 3-OT-JPMADA 1 -7a Task: Hand Calculation of Boric Acid and Primary Water Integrator Setting for Manual Makeup to the VCT Alternate Path: None Facility JPM #: 3-OT-JPMADA 1-7a Rev 0 K/A Rating(s):

2.1.20 Ability to interpret and execute procedure steps. (IIvIPORTANCE RO 4.6 SRO 4.6) 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management. (IMPORTANCE RO 4.3 SRO 4.6) 2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, I such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

(IMPORTANCE RO 4.1 SRO 4.3)

TASK STANDARDS: Correctly perform Hand Calculation of Boric Acid and Primary Water Integrator Setting for Manual Makeup to the VCT Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

1-SOI-62.02 Rev 0047 Tl-59 Rev 0006 Task Number: RO-062-SOl-62-017, APPLICABLE FOR: RO/SRO 10CFR55.45: 1, 5 Time: 15 mm. Time CritiriI No Candidate: Time Start:

NAME SSN/EIN Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: I NAME SIGNATURE DATE COMMENTS

RevO PAGE 4 0F21 Watts Bar Nuclear Plant 3-OT-JPMADA 1 -7a SIMULATOR OPERATOR INSTRUCTIONS:

If JPM conducted in Simulator, reset to any EOL 100% IC Tools/Equipment/Procedures Needed:

copy of latest revision of 1 -SOI-62.02 and TI-59 Calculator Access to controlled copies of plant procedures READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The unit is in Mode 1 at 100% power.

Current RCS CB is 222 ppm.

Current inservice BAT CB is 6350 ppm

Current B-b Depletion value is 12 ppm.

Currently the VCT is at 23%

The Desired VCT Level is 40%

You are an extra operator.

INITIATING CUES:

Due to a suspected problem with REACTINW, the Unit SRO has directed you to perform a hand calculation of the Boric Acid and Primary Water integrator setting for a manual makeup to the VCT, in accordance with SOI-62.02

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

PAGE 5 0F21 3-OT-JPMADA 1-7a START TIME:

STEP 1: Obtain the necessary procedure.

STANDARD: Perlormer obtains copy of latest revision of 1 -SOI-62.02. ___SAT and finds section 6.5 Manual Makeup COMMENTS:

UNSAT EXAMINERS NOTE: Provide copy of SOI 62.02 to candidate.

CUE:

STEP 2: 6.5 Manual Makeup SAT

[1] PERFORM Appendix C, Calculation Of Boric Acid And Primary STANDARD: Performer turns to SOI 62.02 Appendix C UNSAT COMMENTS:

- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 6 0F21 3-OT-JPMADA 1-7a STEP 3:

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

UNSAT STANDARD: Performer refers to iniating cues and realizes that REACTINW is suspect and goes to page 2 of Appendix C COMMENTS:

STEP 4:

2.0 HAND CALCULATION SAT

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

[1.1] Current RCS Boric Acid Concentration. 222 PPM

[1.2] Current BAT Boric Acid Concentration. 6350 PPM UNSAT

[1.3] B-i 0 Depletion Value from Reactivity Management Briefing Sheet 12 PPM

[1.4] Current VCT Level 23 %

[1.5] Desired VCT Level 40 %

STANDARD Correctly obtains information from iniating cues.

COMMENTS:

- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 7 0F21 3-OT-JPMADA l-7a STEP 5 2] CALCULATE BAT Boric Acid Concentration Ratio Critical Step (BACR):

6820 ppm ÷ Step 1 .0[i .2] ppm =_________

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

STANDARD: Performer performs the following calculation:

6820 ppm ÷ 6350 ppm = 1.074 UNSAT COMMENTS:

STEP 6 Critical Step

[3] CALCULATE B-i 0 corrected boron concentration:

PPM STEP i.0[1.i] STEP i.0[i.3j B-b corrected boron SAT STANDARD: Performer performs the following calculation:

222ppm - l2ppm = 2lOppm. UNSAT COMMENTS:

- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 8 0F21 3-OT-JPMADA 1-7a STEP 7* [4] CALCULATE total VCT addition volume needed for Critical Step desired level.

% - %] X 19.3 GalsI% =_______ GALS Step 1 .O[1 .5] Step 1 .0[1 .4]

SAT Total Volume (Round to nearest whole number)

STANDARD: Performer performs the following calculation:

__UNSAT 40 % - 23 %] X 19.3 Gals/% = 328.1 GALS COMMENTS:

2.0 HAND CALCULATION (continued) Critical Step STEP 8 NOTE Corrected Boric Acid Flow Rate in Step 2.0{5] should be obtained from Tl-59, Appendix C for the B-10 corrected boron value calculated in Step 2.0[3].

__SAT

[5]

GPMX_______ GPM Corrected Boric BACR from [X] BA to Blender Acid Flow Rate Step 2.O[2]

UNSAT STANDARD: Performer performs the following calculation:

2.2 GPMX 1.074 = 2.36 GPM Corrected Boric BACR from [XI BA to Blender Acid Flow Rate Step 2.O[2]

COMMENTS:

- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 9 0F21 3-OT-JPMADA 1-7a Critical Step GPM+ 7OGPM GPM Step 2.0[5] [XJ PW to Total Flow Rate SAT Blender Flow STANDARD: Performer performs the following calculation:

2.36 GPM + 70 GPM = 72.36 GPM UNSAT Step 2.O[5] [X] PW to Total Flow Rate Blender Flow COMMENTS:

[7] Critical Step STEP 10:

GPM GPM = GPM Step 2.0[5] [X] Step 2.0[6] [Y] BA Fraction Total Flow Rate STANDARD: Performer performs the following calculation: ..SAT 2.36 GPM ÷ 72.36 GPM = 0.0326 GPM Step 2.0[5] [X] Step 2.0[6] [VI BA Fraction Total Rate UNSAT COMMENTS:

- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

PAGE 10 0F21 3-OT-JPMADA 1-7a STEP 11: Critical Step

[8]

X GALS GALS Step 2.O[7] [Y] Step 2.O[4] Boric Acid Batch Total Volume Counter Setting SAT STANDARD: Performer performs the following calculation:

UNSAT 0.0326 X 328.1 GALS = 10.7 GALS Step 2.0[71 [Y] Step 2.O[4j Boric Acid Batch Total Volume Counter Setting Performer can round BA counter up to 11 GALS COMMENTS:

STEP 12: Critical Step

[9]

70 GPM+ GPM =

Primary H 0

2 Step 2.O[6] [Z] PW Fraction SAT Total Flow Rate UNSAT STANDARD: Performer performs the following calculation:

70 GPM 72.36 GPM = 0.967 Primary H 0

2 Step 2.O[6] [ZI PW Fraction Total Flow Rate COMMENTS:

- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

PAGE 11 0F21 3-OT-JPMADA 1-7a Critical Step X GALS = GALS Step 2.O[9] [Z] Step 2.O[4] Primary Water __SAT Total Volume Batch Counter Setting STANDARD: Performer performs the following calculation:

UNSAT 0.967 X 328.1 GALS = 317.27 GALS Step 2O[9] [Z] Step 2.O[4] Primary Water Batch Total Volume Counter Setting Performer can round PW counter down to 317 GALS COMMENTS:

STEP 14: [11] ENSURE independently verified by SRO.

SAT STANDARD: Performer reports that the task is completed and gives calculation to the SRO COMMENTS:

UNSAT Examiner Acknowledge report, notify performer that the task is cue: complete. End task TIME STOP:

- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The unit is in Mode 1 at 100% power.

Current RCS CB is 222 ppm.

Current inservice BAT CB is 6350 ppm

Current B-10 Depletion value is 12 ppm.

Currently the VCT is at 23%

The Desired VCT Level is 40%

You are an extra operator.

INITIATING CUES:

Due to a suspected problem with REACTINW, the Unit SRO has directed you to perform a hand calculation of the Boric Acid and Primary Water integrator setting for a manual makeup to the VCT, in accordance with SOl-62O2

Report the results of the surveillance to the Unit SRO.

TI-59 Data Candidate Sheet WBN BORON TABLES TI-59 0 Revision 6 Page 15 of 100 APPENDIX C Page 1 of 5 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) 200.0 2.092 400.0 4.314 210.0 2.200 410.0 4.429 220.0 2.308 420.0 4.544 230 .0 2.417 430.0 4 . 659 240.0 2 .525 440.0 4.775 250. 0 2. 635 450.0 4.891 260.0 2.744 460.0 5.008 270.0 2.854 470.0 5.125 280.0 2.964 480.0 5.242 290.0 3.075 490.0 5.360 300.0 3.186 500.0 5.478 310.0 3.297 510.0 5.596 320.0 3.409 520.0 5.715 330.0 3.521 530.0 5.834 340.0 3. 633 540.0 5.954 350.0 3.746 550.0 6.074 360.0 3.858 560.0 6.194 370.0 3 . 972 570.0 6.315 380.0 4.085 580.0 6.436 390.0 4.200 590.0 6.557

TI-59 Data Candidate Sheet WBN BORON TABLES TI-59

) 0 Revision 6

[ Page 16 of 100 APPENDIX C Page 2 of 5 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) 600.0 6.679 850.0 9.858 610.0 6.801 860.0 9.991 620.0 6.924 870.0 10.124 630.0 7.047 880.0 10.258 640.0 7.170 890.0 10.392 650.0 7.294 900.0 10.526 660.0 7.418 910.0 10.661 670.0 7.543 920.0 10.796 680.0 7.668 930.0 10.932 690.0 7.794 940.0 11.069 700.0 7.919 950.0 11.206 710.0 8.046 960.0 11.343 720.0 8.172 970.0 11.481 730.0 8.300 980.0 11.619 740.0 8.427 990.0 11.757 750.0 8.555 1000.0 11.897 760.0 8.683 1010.0 12.036 770.0 8.812 1020.0 12.176 780.0 8.941 1030.0 12.317 790.0 9.071 1040.0 12.458 800.0 9.201 1050.0 12.600 810.0 9.332 1060.0 12.742 820.0 9.463 1070.0 12.884

$30.0 9.594 1080.0 13.027 940.0 9.726 1090.0 13.171

TI-59 Data Candidate Sheet WBN BORON TABLES TI-59 0 Revision 6 Page 17 of 100 APPENDIX C Page 3 of 5 REACTOR COOL2NT 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) 1100 .0 13.315 1350.0 17.088 1110.0 13.460 1360.0 17.246 1120.0 13. 605 1370 .0 17.405 1130.0 13.750 1380.0 17 564 1140.0 13.896 1390.0 17.724 1150.0 14.043 1400.0 17.884 1160.0 14.190 1410.0 18.045 1170.0 14.338 1420.0 18.207 1160.0 14.486 1430.0 18.369 1190.0 14 .635 1440.0 18.532 1200.0 14 .784 1450.0 18.696 1210.0 14 934

. 1460.0 18.860 1220.0 15.084 1470.0 19.024 1230.0 15.235 1480.0 19.190 1240.0 15.386 1490.0 19. 356 1250.0 15.538 1500.0 19. 522 1260.0 15 691

. 1510.0 19.689 1270.0 15.844 1520.0 19.857 1280.0 15. 997 1530.0 20.025 1290.0 16.151 1540.0 20.195 1300.0 16.306 1550.0 20.364 1310.0 16. 461 1560.0 20.535 1320.0 16.617 1570.0 20.706 1330.0 16.774 1580 .0 20.877 1340.0 16. 931 1590.0 21.050

TI-59 Data Candidate Sheet WBN BORON TABLES TI-59 o Revision 6 Page 18 of 100 APPENDIX C Page 4 of 5 REACTOR COOLANT BORON CONCENTRATION VS. AUTOMATIC MAREUP 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) 1600.0 21.222 1850.0 25.773 1610.0 21.396 1860.0 25.964 1620.0 21.570 1870.0 26.157 1630.0 21.745 1880.0 26.350 1640.0 21.921 1890.0 26.544 1650.0 22.097 1900.0 26.738 1660.0 22.274 1910.0 26.934 1670.0 22.452 1920.0 27.130 1680.0 22.630 1930.0 27.327 1690.0 22.810 1940.0 27.525 1700.0 22.989 1950.0 27.724 1710.0 23.170 1960.0 27.923 1720.0 23.351 1970.0 28.124 1730.0 23.533 1980.0 28.325 1740.0 23.716 1990.0 28.527 1750.0 23.899 2000.0 28.730 1760.0 24.083 2010.0 28.933 1770.0 24.268 2020.0 29.138 1780.0 24.453 2030.0 29.343 1790.0 24.640 2040.0 29.549 1800.0 24.827 2050.0 29.757 1810.0 25.014 2060.0 29.965 1820.0 25.203 2070.0 30.173 1830.0 25.392 2080.0 30.383 1840.0 25.582 2090.0 30.594 2100.0 30.805 2110.0 31.018

TI-59 Data Candidate Sheet WBN BORON TABLES TI-59 0 Revision 6 Page 19 of 100 APPENDIX C Page 5 of 5 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) 2120.0 31.231 2390.0 37.354 2130.0 31.445 2400.0 37.596 2140.0 31.660 2410.0 37.838 2150.0 31.876 2420.0 38.081 2160.0 32.093 2430.0 38.326 2170.0 32.311 2440.0 38.571 2180.0 32.530 2450.0 38.818 2190.0 32.750 2460.0 39.066 2200.0 32.971 2470.0 39.315 2210.0 33.192 2480.0 39.565 2220.0 33.415 2490.0 39.816 2230.0 33.639 2500.0 40.069 2240.0 33.863 2250.0 34.089 2260.0 34.316 2270.0 34.543 2280.0 34.772 2290.0 35.001 2300.0 35.232 2310.0 35.464 2320.0 35.696 2330.0 35.930 2340.0 36.165 2350.0 36.400 2360.0 36.637 2370.0 36.875 2380.0 37.114

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN Boron Concentration Control SOl-62.02 Unit 1 Rev. 0047 Page 50 of 62 Appendix C (Page 1 of 4)

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

Date Todays bate 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 & VI + V2 = V3 Where: V is the volume flow rates of water and acid going into and out of the Boric Acid Blender and C is the boric acid concentration of the flow streams.

1.0 REACTINW VCT MAKEUP CALCULATION

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

[1.1] Current RCS Boric Acid Concentration. N/a PPM

[1.2] Current BAT Boric Acid Concentration. N/A PPM

[1.3] B-i 0 Depletion Value from Reactivity Management Briefing Sheet N, A PPM

[1 .4] Current VCT Level N/A

[1.5) Desired VCT Level N/A

[2] RUN REACTINW calculation VCT Makeup Calculation. N/A

[2.1] PRINT the output file:

VCT MAKUP INTEGRATOR SETTINGS CALCUALTION A

[3] SIGN and DATE output sheets. N/A

[4] OBTAIN independent verification by an SRO on output sheets. N/A

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidat&)

r WBN Unit I Boron Concentration Control SOl-62.02 Rev. 0047 Page 51 of 62 Appendix C (Page 2 of 4)

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

Date Todays bate INITIALS 2.0 HAND CALCULATION

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

[1.1) Current RCS Boric Acid Concentration. 222 PPM

[1.2] Current BAT Boric Acid Concentration. 6350 PPM

[1.3] 5-10 Depletion Value from Reactivity Management Briefing Sheet 12 PPM

[1.4] Current VCT Level 23

[1.51 Desired VCT Level 40

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

6820 ppm ÷ Step 1.0[1.2] ppm = 1.074 Candidates (ENTER 1.0 for BACR following a reactor shutdown or for a conservative calculation). Initials

[3] CALCULATE 8-10 corrected boron concentration: Candidates 222

12 = 210 PPM Initials STEP 1.0[1.1] STEP 1.0[1.3] 8-10 corrected boron

[4] CALCULATE total VCT addition volume needed for desired level. Candidates 40 % - 23 % 1 X 19.3 GaIs/% = 328.1 GALS Initials Step 1 .0[1 .5] Step 1 .0[1 .4] Total Volume (Round to nearest whole number)

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN Boron Concentration Control SOI-62.02 Unit I Rev. 0047 Page 52 of 62 Appendix C (Page 3 of 4)

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

Date Todays date INITIALS 2.0 HAND CALCULATION (continued)

NOTE Corrected Boric Acid Flow Rate in Step 2.0[5] should be obtained from Tl-59, Appendix C for the B10 corrected boron value calculated in Step 2.0[3].

[5] Candidates 2.2 GPM x 1.074 2.36 GPM Initials Corrected Boric BACR from [X] BA to Blender Acid Flow Rate Step 2.0[2] Flow

[6] Candidates 2.36 GPM + 70 GPM = 72.36 GPM Initials Step 2.0[5j [X] PW to Total Flow Rate Blender Flow

[7] Candidates 2.36 GPM ÷ 72.36 GPM 0.0326 GPM Initials Step 2.0[5] [X] Step 2.0[6] [Y] BA Fraction Total Flow Rate

[8]

0.0326 x 328.1 GALS 10.7 GALS Step 2.0[7] [Y] Step 2.0[4] Boric Acid Batch Total Volume Counter Setting ae

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN Boron Concentration Control SOl-62.02 Unit I Rev. 0047 Page 53 of 62 Appendix C (Page 4 of 4)

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

Date Todays date INITIALS 2.0 HAND CALCULATION (continued)

NOTE Round answer to nearest whole number.

[9] Candidates 7OGPM ÷ 72.36 GPM = 0.967 Initials Primary H0 2 Step 2.0[6] [Z] PW Fraction Total Flow Rate

[10]

328.1 0.967 x GALS = 317.27 GALS Step 2.0[9] [Z] Step 2.0[4] Primary Water Total Volume Batch Counter Setting 3/7 a11oc 14 a144 a&

NOTE Round answer to nearest whole number.

[11] ENSURE independently verified by SRO.

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

Rev. 0 Page 1 of 23 WATTS BAR NUCLEAR PLANT 3-OT-J P MADA.2-2A Complete Shift Daily Surveillance Log Mode One and Evaluate Surveillance Log

Rev. 0 Page 2 of 23 WATTS BAR NUCLEAR PLANT 3-OT-J PMADA.2-2A NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 INITIAL ISSUE. Used 3-CT- 04/29/08 All A. V. White JPMADA.2-2 and modified to include Data sheet 1 references 2 through 18 and deleted 23. Also modified simulator setup to include several instruments that are not within MCD tolerances.

Rev. 0 Page 3 of 23 WATTS BAR NUCLEAR PLANT 3-OT-J PMADA.2-2A ADMINISTRATIVE JOB PERFORMANCE MEASURE Task: Complete Shift Daily Surveillance Log Mode One and Evaluate Surveillance Log.

Alternate Path: N/A Facility JPM #: New K/A Rating(s): 2.2.12 [3.0/3.4]

Task Standard: Correctly record data on data sheet 1 references 2 throughl3, 15 through 18 and review this data to determine whether or not the surveillance meets acceptance criteria.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

1-Sl-0-2B-01 0700-1900 Shift And Daily Surveillance Log Mode One Rev. 53.

Task Number:: RO-1 13-GEN-004 APLICABLE FOR: RO/SRO 1 OCFR55.45:

Validation Time: 15 mm. Time Critical: No Applicant: Time Start:

NAME SSN/EIN Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner:

NAME SIGNATURE DATE COMMENTS

Rev. 0 Page 4 of 23 WATTS BAR NUCLEAR PLANT 3-OT-J PMADA.2-2A SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize to IC # 273.

2. Acknowledge all alarms.

3. Ensure that the following instrument indicate values that would yield MCD that are not within acceptance criteria. Adjust overrides as necessary (instrument drift, etc).

Loop 3 SG Levels MCD 7% Limit is 6.0%

Loop 2 RCS Flow MCD 5% Limit is 4.0%

RWST Level MCD 8% Limit is 7.0%

4. Freeze simulator until the performance indicates understanding of the task and time is allowed for control board familiarization.

5. NOTE: This JPM has been preshot in IC #273. The following is the setup instructions if needed:

Initialize to IC #40 Acknowledge all alarms.

Insert the following overrides:

IOR ZAOL163183 0.2 CNTMT SUMP LI 63-1 83 IOR ZAOL16353 90 RWST 1-LI 63-53 IOR ZAOL16352 99 RWST 1-LI 63-52 IOR ZAOLI6351 99 RWST 1-LI 63-51 IOR ZA0L16350 98 RWST 1-LI 63-50 IOR ZAOFI6829D 89 RCS FLOW 1 -FI-68-29D IOR ZAOLI6829B 89 RCS FLOW 1 -FI-68-29B IOR ZAOLI6829A 99 RCS FLOW 1 -Fl-68-29A IOR ZAOLI393 58 SG LEVEL 1-Ll-3-93 IOR ZAOLI394 65 SG LEVEL 1-LI-3-94 IOR ZAOLI397 58 SG LEVEL 1-LI-3-97 IOR ZAONI41B 100 REACTOR POWER 1-NI-41B IOR ZAONI42B 102 REACTOR POWER 1-NI-42B IOR ZAONI43B 99.5 REACTOR POWER 1-NI-43B IOR ZAONI44B 99.3 REACTOR POWER 1-NI-44B FREEZE the simulator till the performer indicates an understanding of the task.

6. After performer indicates understanding of task, place simulator in run.

SIMULATOR OPERATOR INSTRUCTIONS:

NONE

Rev. 0 Page 5 of 23 WATTS BAR NUCLEAR PLANT 3-OT-J PMADA.2-2A Tools/Equipment/Procedures Needed:

Copy of 1-SI-0-2B-01 0700-1900 Shift and Daily Surveillance Log Mode One Check on applicants copy of surveillance on page 38 of 56 for 480 Rx MOV Boards the blocks below to represent field data that has already been completed.

3hunt Breaker 1A1-A OFF c/2E1 1-BKR-63-1A At least one ON LI OR Breaker 1 -BKR-63-1 B breaker OFF OPEN LI 1A1-Ac/1OA CLOSED E 3hunt Breaker 1B1-B OPEN E c/2F2 1 -BKR-63-22A At least one CLOSED LI OR Breaker 1 -BKR-63-22B breaker OFF OPEN LI 1B1-Bc/11D CLOSED E Calculator

Rev. 0 Page 6 of 23 WATTS BAR NUCLEAR PLANT 3-OT-J PMADA.2-2A NOTE TO EVALUATOR: Hand out the Applicant Surveillance Instruction along with the Applicants Cue Sheet. The surveillance instruction should be marked per the previous page.

READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The unit is operating at 100% rated thermal power, no LCO entries at this time.

Portions of the field data have been entered by NAUOs.

You are the Unit Operator responsible to perform and review 1-SI-0-2B-01 0700-1900 Shift And Daily Surveillance Log Mode 1 INITIATING CUES:

You are to complete Data Sheet 1 pages 1 through 9 (reference 2 through 13, 15 through 18) and review the data. Another Unit Operator will complete the remainder of Data Sheet 1.

When you have finished performing the assigned pages of Data Sheet 1, and addressed any deviations, notify the Unit Supervisor that you have completed your task.

Rev. 0 3-OT-JPMADA.2-2A Page 7 of 23 START TIME:

STEP 1: Obtain a copy of the instruction.

SAT STANDARD: A copy of 1-Sl-0-2B-01 has been obtained.

EXAMINERS CUE: Provide the applicant with marked up surveillance.

UNSAT COMMENTS:

STEP 2: [Ref 2] Log data for Total Core Thermal Power Average SAT STANDARD: Applicant obtains current reading for total core thermal power average (ICS computer point U2126 using LEFM which is approximately 3445 MWT) record it on the data sheet, determines that the value is 3459 MWT. UNSAT COMMENTS:

STEP 3: [Ref 3] Log data for CST A Level SAT STANDARD: Applicant obtains current reading for CST A Level 1 -Ll-2-230A or 1 -Ll-2-230B (Value 330,000 gallons) record it on the data sheet, determines that the value is 200,000 gallons.

UNSAT COMMENTS:

Rev. 0 3-OT-JPMADA2-2A Page 8 of 23 STEP 4: [Ref 4] Log data in SG Pressure data table, check Operable, Channel Check, and MCD 90 psig.

SAT STANDARD: Applicant obtains current readings for SG Pressure and records them on the data sheet, determines that the channels are operable, channel checked and MCD is within 90 psig:

UNSAT 1-Pl-1-2A Operable, 1000 psig SG 1 Press 1-PI-1-2B Channel Check, 1020 psig 1-P 5 and MCD 90 psig 1000 psig 1-Pl-1-9A Operable, 1015 psig SG 2 Press 1-PI-1-9B Channel Check, 1020 psig 1-Pl-1-12 and MCD 90 psig 1020 psig 1-Pl-1-20A Operable, 1010 psig SG 3 Press 1-Pl-1-20B Channel Check, 1000 psig 1-PI-1-23 and MCD 90 psig 1010 psig 1-Pl-1-27A Operable, 1000 psig SG 4 Press 1-Pl-1-27B Channel Check, 1000 psig 1-pI-1-30 and MCD 90 psig 1010 psig COMMENTS:

Rev. 0 3-OT-JPMADA.2-2A Page 9 of 23 STEP 5: [Ref 5] Log data in SG Level data table, check Operable, CRITICAL Channel Check, and MCD 6.0 % STEP STANDARD: Applicant obtains current readings for SG Level and records SAT them on the data sheet, determines that SG 3 Level channel 1-LI-3-94 is not within MCD is within 6.0%:

UNSAT 1 -Ll-3-42 Operable, 60 %

SG 1 Level 1 -Ll-3-39 Channel Check, 59 %

1 -Ll-3-38 and MCD 6.0% 57 %

1 -Ll-3-55 Operable, 60 %

SG 2 Level 1 -LI 52 Channel Check, 60 %

1-Ll-3-51 and MCD 6.0% 60%

1-Ll-3-97 Operable, 58 %

SG 3 Level 1 -Ll-3-94 Channel Check, 66 %

1 -LI-3-93 and MCD 6.0% 58 %

1-LI-3-1 10 Operable, 60%

SG 4 Level 1 -Ll-3-1 07 Channel Check, 60 %

1 -Ll-3-1 07 and MCD 6.0% 60 %

EXAMINERS CUE: If asked: Respond as Unit Supervisor and acknowledge that 1-LI-3-94 appears to be inoperable as it exceeds MCD. Complete data taking as assigned.

EXAMINERS CUE: If asked to review previous shifts SI-2 Data, Unit Supervisor will retrieve data, if pursued further the Unit Supervisor reviewed data and all instrumentation was within MCD.

COMMENTS:

Rev. 0 3-OT-J PMADA.2-2A Page 10 of 23 STEP 6: [Ref 6] Log data in data table for Shutdown Bank Group Step Counters and RPI Step indications, check Operable, 225 steps withdrawn and +/-12 steps of group step counter.

STANDARD: Applicant obtains current readings for Shutdown Bank Step SAT counters and records the individual rod position which is most deviated from step counter logged. Determines all requirements are met.

UNSAT Shutdown Bank Al Grp 1 Step Operable, 225 Group Step 228 D2, P4, B12, M14 (l-SBAG1) steps, +/-12 steps Grp 1 RPI of group step RPI Step 230 counter Shutdown Bank A2 Grp 2 Step Group Step 228 M2, B4, P12, D14 (l-SBAG2)

Grp2RPl RPI Step 230 Shutdown Bank Bl Grp 1 Step Group Step 228 G3, 09, Jl3, N7 (l-SBBG1)

Grp 1 RPI RPI Step 229 Shutdown Bank B2 Grp 2 Step Group Step 228 J3, N9, G13, 07 (l-SBBG2)

Grp 2 RPI RPI Step 229 Shutdown Bank Cl Grp 1 Step Group Step 228 E3, N5, Cli, L13 (1-SBCG1)

Grp 1 RPI RPI Step 229 Shutdown Bank Dl Grp 1 Step Group Step 228 L3, 05, Nil, E13 (1 -SBDG1)

Grp 1 RPI RPI Step 230 COMMENTS:

Rev. 0 3-OT-JPMADA.2-2A Page ii of 23 STEP 7: [Ref 71 Log data in data table for Control Bank Group Step Counters and RPI Step indications, check Operable, Insertion Limits in COLR, Sequence, and +/-12 steps of group step counter.

SAT STANDARD: Applicant obtains current readings for Control Bank Step counters and records the individual rod position which is most deviated from step counter logged. Determines all UNSAT requirements are met.

Control Bank Al Grp 1 Step Insertion limits in Group Step 228 H6, Hi0, E5, Eli (i-CBAG1) COLR, Gro 1 RPI Sequence, RPI Step 231 Control Bank A2 Grp 2 Step Overlap Group Step 228 F8, K8, L5, Li 1 (1 -CBAG2)

Grp 2 RPI and RPI Step 230 Control Bank Bi Grp 1 Step +/-12 steps of Group Step 228 F2, P6, BlO, K14 (i-CBBG1) group step Grp 1 RPI counter RPI Step 224 Control Bank B2 Grp 2 Step Group Step 228 K2, B6, PlO, Fi4 (1- CBBG2)

Grp 2 RPI RPI Step 229 Control Bank Ci Grp 1 Step Group Step 228 H2, P8, B8, Hi4 (1- CBCG1)

Grp 1 RPI RPI Step 229 Control Bank C2 Grp 2 Step Group Step 228 K6, F6, Kb, FlO (1- CBCG2)

Grp 2 RPI RPI Step 230 Control Bank Di Grp 1 Step Group Step 220 M4, D4, M12, D12 (1- CBDG1)

Grp 1 RPI RPI Step 217 Control Bank D2 Grp 2 Step Group Step 220 H4, H8, M8, D8, (1 -CBDG2)

H12 Grr 2 RPI RPI Step 217 COMMENTS:

Rev. 0 3-OT-JPMADA.2-2A Page 12 of 23 STEP 8: [1] IF Control Rod Bank Dat 118 Steps or further withdrawn, THEN CHECK Control rod banks A, B, and C at their fully SAT withdrawn position.

[2] IF Control Rod Bank D at 117 Steps or further inserted, THEN VERIFY ALL Control Banks fully withdrawn or UNSAT properly overlapped using bank step counters and Data Sheet 7 of 1-SI-0-2-0O.

STANDARD: Applicant determines that step [1] conditions are met and that Control Rod Banks A, B, and C are at their fully withdrawn position. Step [2] should be marked as N/A since stated conditions do not exist.

COMMENTS:

Rev. 0 3-OT-JPMADA.2-2A Page 13 of 23 STEP 9: [Ref 81 Log data Power Range and Intermediate Range Nis into O data table, check Operable, Channel Check, and MCD S7W 2.0%.

SAT STANDARD: Applicant obtains current readings for Power Range, Intermediate Range Nis and records them on the data sheet, determines that the channels are operable, channel checked and MCD is within 2.0%: UNSAT 1-Nl-41B Operable, 100 %full power PR Flux % Power 1 -NI-42B Channel Check, i. 99- full power 1 -NI-43B and MCD 2.0% 9 i-O% full power 1 -NI-44B 98-4 full power IR % Power CH I 1-NI-92-135A Operable when (j2Q% RTP X 2.35)=

below P-10 lowest

% full power IR % Power CH 2 1-Nl-92-136A Operable when NI 136 Highest below P-b channel?

I1YES_D_NO Lowest Channel Channel check, D 1-NI-92-135A and lowest reading F1 1 -N 1-92-1 36A IR X 2.35 is greater than highest reading_IR.

EXAMINERS NOTE: Values may not be recorded for IR channels since only requfred operable below P-1O.

COMMENTS:

6 S itj4cieL s{ JL4 acIe d4Qr4( )42 5

j C

1

( >&% Ac

Rev. 0 3-OT-J PMADA.2-2A Page 14 of 23 STEP 10: [Ref 9] Log data in PZR Level data table, check Operable, less than or equal to 80%, Channel Check, and MCD 6.0 %

SAT STANDARD: Applicant obtains current readings for PZR Level and records them on the data sheet, determines that PZR Level is less than 80%, and MCD is less than 6.0%.

UNSAT 1 -Ll-68-339A Operable, 80% 61 %

PZR Level 1-Ll-68-335A Channel Check, 61 %

1-Ll-68-320 and MCD 6.0% 61 %

COMMENTS:

STEP 11: [Ref 10] Log data in PZR Press data table, check Operable, Channel Check, greater than or equal to 2214 psig, and MCD SAT STANDARD: Applicant obtains current readings for PZR pressure and records them on the data sheet, determines that PZR pressure is greater than or equal to 2214 psig, and MCD is 55 psig UNSAT 1 -Pl-68-340A Operable, 2220 psig PZR Press 1 -P1-68-334 Channel Check, 2220 psig 1-Pl-68-323 2214 psig 2225 psig 1-PI-68-322 and MCD 55 2225 psig psig%

COMMENTS:

Rev. 0 3-OT-JPMADA.2-2A Page 15 of 23 STEP 12: [Refill Log data for RCS Loop zT, RCS Loop OPtT, and RCS Loop OTAT into data table, check Operable, Channel Check, and MCD.

SAT STANDARD: Applicant obtains current readings for RCS Loop Ts and records them on the data sheet, determines that the channels are operable, channel checked and MCD is within 7% for LOOP tiT and OP1T and MCD is within 8%: UNSAT Loop 1 1 -Tl-68-2D Operable, 100 % full power Loop 2 1 -Tl-68-25D Channel Check, 100 % full power Loop 3 1 -TI-68-44D and MCD 7% 100 % full power Loop 4 1 -Tl-68-67D 101 % full power Loop 1 1 -TI-68-2A Operable, 109 % full power Loop 2 1 -Tl-68-25A Channel Check, 110 % full power Loop 3 1 -T1-68-44A and MCD 7% 111 % full power Loop 4 1 -Tl-68-67A 110 % full power Loop 1 1 -Tl-68-2B Operable, 1 18 % full power Loop 2 1 -Tl-68-25B Channel Check, 1 17 % full power Loop 3 1 -Tl-68-44B and MCD 8% 117 % full power Loop 4 1 -Tl-68-67B 120 % full power COMMENTS:

Rev. 0 3-OT-JPMADA.2-2A Page 16 of 23 STEP 13: [Ref 12] Log data for RCS Tavg data table, check Operable, Channel Check, and MCD 5°F. SAT STANDARD: Applicant obtains current readings for RCS Tavg and records them on the data sheet, determines that the channels are operable, channel checked and MCD is within 5°F. UNSAT Operable, Loop 1 1-TI-68-2E 593°F 586°F Loop 2 1-TI-68-25B and 555 ElF 586°F Channel Check, Loop 3 1 -TI-68-44E and MCD 5°F 587 °F Loop 4 1 -TI-68-67E 587 °F COMMENTS:

Rev. 0 3-OT-JPMADA.2-2A Page 17of23 STEP 14: [Ref 131 Log data for RCS Flow into data table, Channel Check, and CRITICAL MCD 4%. STEP STANDARD: Applicant obtains current readings for RCS Flows and records SAT them on the data sheet, determines that total RCS flow rate is greater than or equal to 380,000 gpm (Average 96%), channel checked and determines that 1 -Fl-28-29A is not within MCD is within 4.0%: UNSAT 1-Fl-68-6A Total RCS Flow 100%

Loop 1 Flow 1-Fl-68-6B Rate 380,000 gpm 100%

1-Fl-68-6D for indicators 100%

1 -Fl-68-29A (Average 96%), 105 %

Loop 2 Flow 1 -Fl-68-29B Channel Check, and 99 %

1 -Fl-68-29D and MCD 4% 99 %

1-FI-68-48A 100%

Loop 3 Flow 1-Fl-68-48B 100%

1-Fl-68-48D 100%

1-Fl-68-71A 100%

Loop 4 Flow 1 -Fl-68-71 B 100 %

1-Fl-68-71D 100%

Total all operable indicators and divide by 1098 % tot ÷ number of operable indicators for 11 # md =

average.

98 % Avg Compare average to 98%.

Mark YES if 98%. Mark NO if <98% Yes l1 NO D EXAMINERS CUE: If asked: Respond as Unit Supervisor and acknowledge that 1-Fl-68-29A appears to be inoperable as it exceeds MCD. Complete data taking as assigned.

EXAMINERS CUE: If asked to review previous shifts SI-2 Data, Unit Supervisor will retrieve data, if pursued further the Unit Supervisor reviewed data and all instrumentation was within MCD.

COMMENTS:

Rev. 0 3-OT-JPMADA.2-2A Page 18 of 23 STEP 15: [Ref 15] Log data for Reactor Coolant Pumps into data table.

SAT STANDARD: Applicant enters data into data sheet indicating RCP 1, 2, 3, and 4 are running:

UNSAT RCS Loops RCP Status RCP1 2 34 1,2,3,4 ON OFF DLI RCP 1 1 -HS-68-8AA All RCPs R 1 -HS-68-8BA RCP2 1-HS-68-31AA running R 1 -HS-68-31 BA RCP 3 1 -HS-68-5OAA R 1 -HS-68-5OBA RCP 4 1 -HS-68-73AA R 1 -HS-68-73BA COMMENTS:

Rev. 0 3-OT-JPMADA.2-2A Page 19 of 23 STEP 16: [Ref 16] Log data for 1-FCV 63-1 and 1-FCV-63-22 data table.

SAT STANDARD: Applicant enters data into data sheet indicating Valve 1 -FCV 63-1 and -22 are OPEN and breaker status OPEN for at least one breaker for each valve: UNSAT RWST to RHR 1 -FCV-63-1 OPEN ECCS Suction (1-HS-63-1A) CLOSED SI Pumps to 1-FCV-63-22 OPEN OPEN E CL 1,2,3,4 (1-HS-63-22A) CLOSED 3hunt Breaker 1A1-A OFF El c/2E1 1-BKR-63-1A Atleastone ON OR Breaker 1 -BKR-63-1 B breaker OFF OPEN 1A1-Ac/1OA CLOSED El hunt Breaker 1B1-B OPEN El c/2F2 1 -BKR-63-22A At least one CLOSED LI OR Breaker 1 -BKR-63-22B breaker OFF OPEN LI 1B1-Bc/11D CLOSED El COMMENTS:

Rev. 0 3-OT-JPMADA.2-2A Page 20 of 23 STEP 17: [Ref 17] Log data for CNTMT Sump Level and RWST Level into CRITICAL data table, check Operable, Channel Check, and check STEP MCD.

SAT STANDARD: Applicant obtains current readings for CNTMT Sump Level and RWST Level and records them on the data sheet, determines that CNTMT Sump Level channels are operable, channel checked and MCD is within 6.0%. Determines RWST Level _ UNSAT channel 1 -Ll-63-53 is not within MCD is within 7.0%:

CNTMT Sump_Level Loop 1 1 -Ll-63-1 80 Operable, 0%

Loop 2 1-LI-63-181 Channel Check, 0%

Loop 3 1 -Ll-63-1 82 and MCD 6.0% 0%

Loop 4 1 -Ll-63-1 83 0%

RWST_Level Loop 1 1 -LI 50 Operable, 97 %

Loop 2 1 -LI 51 Channel Check, 98 %

Loop 3 1 -LI 52 and MCD 7.0% 98 %

Loop 4 1 -LI 53 90 %

EXAMINERS CUE: If asked: Respond as Unit Supervisor and acknowledge that 1-LI-63-53 appears to be inoperable as it exceeds MCD. Complete data taking as assigned.

EXAMINERS CUE: If asked to review previous shifts SI-2 Data, Unit Supervisor will retrieve data, if pursued further the Unit Supervisor reviewed data and all instrumentation was within MCD.

COMMENTS:

Rev. 0 3-OT-J PMADA.2-2A Page 21 of 23 STEP 18: [Ref 18] Log data for Cold Leg Accumulator Isolation Valves into data table. SAT STANDARD: Applicant records status of cold leg accumulator valves as open on the data sheet:

UNSAT CL Accum 1 Outlet 1 -FCV-63-1 18 OPEN (1 -HS-63-1 1 8A) CLOSED D CL Accum 1 Outlet 1 -FCV-63-98 Valves OPEN II (1-HS-63-98A) OPEN CLOSED CL Accum 1 Outlet 1 -FCV-63-80 OPEN (1-HS-63-80A) CLOSED CL Accum 1 Outlet 1 -FCV-63-67 OPEN l1 (1-HS-63-67A) CLOSED D COMMENTS:

Rev. 0 3-OT-JPMADA.2-2A Page 22 of 23 STEP 19: Inform the Unit Supervisor that Data Sheet 1 Pages 1-9 have been completed of 1 -Sl-0-2B-O1, and gives package to the Unit Supervisor.

SAT STANDARD: Applicant inform the Unit Supervisor of the completion of Data sheet 1 pages 1 through 9 of 1 -SI-0-2B-O1. Report any Acceptance Criteria not met if not previously communicated.

UNSAT EXAMINERS CUE: Respond as Unit Supervisor and acknowledge that:

SG 3 Narrow Range Level instrument 1-LI-3-94 appears to be inoperable as it exceeds MCD.

Loop 2 RCS Flow Instrument 1-FI-68-29A appears to be inoperable as it exceeds MCD.

RWST Level Transmitter 1-LI-63-53 appears to be inoperable as it exceeds MCD.

EXAMINERS CUE: Acknowledge report as Unit Supervisor, then state We will stop here.

COMMENTS:

END OF TASK TIME STOP:

Rev. 0 3-OT-JPMADA.2-2A Page 23 of 23 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The unit is operating at 100% rated thermal power, no LCO entries at this time.

Portions of the field data have been entered by NAUOs.

You are the Unit Operator responsible to perform and review 1 -Sl-0-2B-01 0700-1900 Shift And Daily Surveillance Log Mode 1.

INITIATING CUES:

You are to complete Data Sheet 1 pages 1 through 9 (reference 2 through 13, 15 through 18) and review the data. Another Unit Operator will complete the remainder of Data Sheet 1.

When you have finished performing the assigned pages of Data Sheet 1, and addressed any deviations, notify the Unit Supervisor that you have completed your task.

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN 0700 1900

- 1-SI-0-2B-01 Unit I Shift And Daily Surveillance Log Rev. 0053 Mode One Page 30 of 56 Data Sheet I (Page 1 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page________ of________

Ref Location Description Instrument # T S Limit Data Acc NOT Met Ref. 2 may be NIAd when Rx Power < 90%

If Rx Power is 3445 greater than Maintain 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months License Limit, the average of 08:00 MWT SRO is to be 3459 MWT notified to reduce Total Core Point U2126 OR while using LEFM power to less than 2 CS Thermal Power Average Ui 126 (8 HrAVG) OR s 3411 MWT or equal to License when complying 12:00 t11 MWT Limit as soon as with TR 3.3.7 possible. If CS Action B. average is INOP or unreliable, perform 16:00 11 MWT Data Sheet 2.

1-M-2 1-Ll-2-230A Perform Data Sheet 3 of 3 Pnl 0-L-209 CST A Level OR 200,000 gallons 330000 1 -S 1-0-2-00 T15M/708 1-Ll-2-230B C gallons CST Level 1-Pl-i-2A 1000 psig SG 1 Press i-Pl-1-2B 1020 psig i-Pl-1-5 1000 psig i-Pl-1-9A 1015 psig SG 2 Press i-Pl-i-9B 1020 psig Operable, 1-Pl-1-12 Channel Check 1020 psig Contact SRO to 4 1-M-4 consult Tech 1-PI-1-20A and ioio psig MCD 90 psig Specs.

SG 3 Press 1-Pl-1-20B 1000 psig i-Pl-1-23 1010 psig 1-Pl-1-27A 1000 psig SG 4 Press 1-Pl-1-27B 1000 psig 1-Pl-1-30 1010 psig Ii) These readings to be taken after SRO initial review of Data Sheet 1.

Initials indicate ace met OR action in Ace not canaates Performers SROs Met column initiated. Initials Initials Initlais Remarks:

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidat&)

WBN 0700 1900

- 1-Sl-0-2B-01 Unit I Shift And Daily Surveillance Log Rev. 0053 Mode One Page 31 of 56 Data Sheet I Today (Page 2 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page________ of________

Ref Location Description Instrument # T S Limit Data Acc NOT Met 1-Ll-3-42 - 60 %

SG 1 Level 1-Ll-3-39 59 %

1-Ll-3-38 57 %

1-Ll-3-55 60 %

SO 2 Level 1-Ll-3-52 60 Operable.

1-LI-3-51 ChanneiCheck 60 % Contact SRO to 5 1 -M-4 consult Tech 1-Ll-3-97 anu %

&__ Specs MCD 6.0%

SO 3 Level 1-Ll-3-94 1-Ll-3-93 58 1-Ll-3-110 60 SO 4 Level 1-LI-3-107 60 1-Ll-3-106 Examiner Note Values may vary by one gradient mark throughout all the readings of this JPM due to parallax error and/or static on gauges.

I Remarks:

I initials indicate acc met OR actio ncnotndidates Performers Met column initiated. Initials Initials SROs Initials Candidates may write the out of spec value on this line.

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN 0700 1900

- 1-Sl-0-2B-01 Unit 1 Shift And Daily Surveillance Log Rev. 0053 Mode One Page 32 of 56 Data Sheet I (Page 3 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page_________ of Descrip Ref Instrument # T S Limit Data Acc NOT Met Description tion Shutdown Bank Al Group Grp 1 Step 228 (l-SBAG1) Step If ONE demand RPI position indicator per D2P4,B12,M14 Grp I RPI (2)

Step 230 bank is inoperable Group for one or more Shutdown Bank A2 Grp 2 Step (l-SBAG2) Step 228 banks, Per RPI LCD 3.1.8 Action C.

M2,B4,P12,D14 Grp 2 RPI (2)

Step 230 then perform Data Sheet 6 of Shutdown Bank Bl Group 1-SI-0-2-00 Grp 1 Step 228 Shut-down Rod Step (l-SBBG1) 225 Steps G3,C9,J13N7 Grp 1 RPI i21 RPI Position once per withdrawn and Step 229 6 1-M-4 +/-l2stepsof 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Shutdown Bank B2 Grp 2 Group Step Group If rod deviation Step (1-SBBG2) Counter Step 228 11 RP1 monitor J3.N9,G13.C7 Grp 2 RPI (2) 229 (computer) is inoperable, individual Group rod positions are to Shutdown Bank Cl Grp Step 228 be recorded on Data Step (l-SBCGI)

E3,N5Cll,L13 2 GrpRPl Sheet6of 229 1 -S 1-0-2-00 Group Shut-down Rod Shutdown Bank Dl Grp Step 228 Position every Step (l-SBDG1) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

L3,C5,N1l,E13 Grp RPI (2i Spi> 230 (1) For each RPI. individual rod position which is most deviated from step counter indication is to be logged.

(2) Rod indications can be from CERPI computer screens on 1-M-4 or ics.

I Remarks:

Initials indicate ace met OR action in Acc not Met column initiated. Candidates Initials Performers Initials SROs Initials

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN 0700 1900

- 1-Sl-0-2B-01 Unit 1 Shift And Daily Surveillance Log Rev. 0053 Mode One Page 33 of 56 Data Sheet I (Page 4 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page of________

Ref Location Description Instrument # T S Limit Data Acc NOT Met Control Bank Al Grp 1 Group Step(1-CBAG1) Step 228 H6,HlO,E5,E11 Grp 1 RPI RPI

? 231 2

Stept If ONE demand Group position indicator per Control Bank A2 Grp 2 Step 228 bank is inoperable for Step (1-CBAG2)

F8,K8,L5,Ll 1 Grp 2 RPI (3 one or more banks, Per 231 LCO 3.1.8 Action C.

then perform Data Control Bank BI Group Sheet 7 of 1-Sl-O-2-OO Grp 1 Insertion Limits Step 228 Control Rod Position Step (1-CBBGI)

RPI once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

F2,P6.B1O,Kl4 Grp 1 RPI in COLR, Sequence, 2 224 Step If rod deviation monitor Overlap and Group (computer) is Control Bank B2 Grp 2 228

+/- 12 steps of Step inoperable, individual Step (1CBBG2) rod positions are to be Group Step RPI K2.B6,P1O,F14 Grp 2 RPI recorded on Data Counter. 21 229 5tep 7 l-M-4 Sheet 7 of 1-SI-O-2-OO (If MTC Group Shut-down Rod Control Bank Cl Grp 1 withdrawal limits Step 228 Position every Step (1-CBCG1)

(3 are in effect, RPI 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

H2,P8,B8,H14 Grp 1 RPI NOB Sheet A-5 2 229 Step If rod insertion monitor IS Group (1-XZ-55-48-87A) is Control Bank C2 Grp 2 to be inoperable, rod Step 228 Step (1-CBCG2) referenced.) insertion limits as listed K6.F6,K1O,F1O Grp 2 RPI (3) 230 in the COLR are to be 2

Sp verified & individual rod Group posistions are to be Control Bank Dl Grp 1 Step 220 recorded on Data Step (1 -CBDG1) Sheet? of 1-81-0-2-00 RPI M4,D4,M12,D12 Grp 1 RPI 3) Control Rod Posistion 1

Step° 217 every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Group Control Bank D2 Grp 2 220 Step (1-CBDG2) Step H4,H8, M8,D8,Hl2 RPI Grp 2 RPI 217 21 Step (I) Sequence & overlap can best be verified during rod withdrawal and insertion. Rod sequence is in accordance with COLR figure 1 and bank overlap is set by Instrument Maintenance, (2) For each RPI. individual rod position which is most deviated from step counter indication is to be logged.

(3) Rod indications can be from CERPI computer screens on 1-M-4 or ICS.

Initials indicate aco met OR action in Acc not Performers Os Met column initiated. Candidates Initiais Initials Initials Remarks:

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN 0700 1900

- 1-Sl-0-2B-01 Unit 1 Shift And Daily Surveillance Log Rev. 0053 Mode One Page 34 of 56 Data Sheet I (Page 5 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Todoy Page________ of

[1] IF Control Rod Bank Dat 118 Steps orfurther withdrawn, THEN CHECK Control rod banks A, B. and C at their fully withdrawn Candidates position. Initials

[2] IF Control Rod Bank D at 117 Steps or further inserted, THEN VERIFY ALL Control Banks fully withdrawn or properly overlapped using bank step counters and Data Sheet 7 of N/A 1 -Sl-O-2-OO.

I Remarks:

I nitials indicate ace met OR action in Ace not Met column initiated.

Candidatesperformers Initials Initials SROs Initials

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN 0700 1900

- 1-SI-0-2B-01 Unit I Shift And Daily Surveillance Log Rev. 0053 Mode One Page 35 of 56 Data Sheet I (Page 6 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page________ of Ref Location Description Instrument # T S Limit Data Acc NOT Met 1-Nl-41B 100 %

PR Flux % 1-NI-42B Operable, Channel Check, L)C)

J 99 %

Power l-Nl-43B and 100 %

MCD If the PRM MCD 1-Nl-44B 98 exceeds 2%,

IR % Power STA shall per CH I 1-Nl-92-135A 140 % RTP Operable when form 1-Sl-92-1 lR % Power below P-b and notify MIG.

1-Nl-92-136A 120 % RTP If the PRM MCD CH II 8 1-M-4 exceeds 4%, the

__120 % RTP x 2.35) = channel should Lowest be evaluated for Channel Check, and Calcd operability.

q lowest channel Lowest reading NI 136 channel Contact SRO to C 1-Nl-92-1 35A IR x 2.35 is greater con-suit Tech 1-Nl-92-136A than highest reading Specs 282 Highest IR.

Calcd channel?

channel YES C NO 1-LI-68-339A Operable, less than 61 or equal to 80%, Contact SRO to 9 1-M-4 PZR Level 1-LI-68-335A 61 % consult Tech Channel Check, and 1-Ll-68-320 Specs.

MCD 6.0% 61 %

1-Pl-68.-340A 2200 psig Operable, channel 1-PI-68-334 check, greater than 2200 psig Contact SRO to 10 1 -M-5 PZR Press consult Tech 1-Pl-68-323 orequal to 2214 psig 2225 psig Specs and MCD 55 psig.

1-PI-68-322 2225 psig Candidates Perfom,ers I Remarks:

I Initials indicate acc met OR action in Acc not Met column initiated. Initials Initials SROs Initials

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN 0700 1900

- 1-Sl-0-2B-01 Unit I Shift And Daily Surveillance Log Rev. 0053 Mode One Page 36 of 56 Data Sheet I (Page 7 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page________ of________

Location Description Instrument # T S Limit Data Acc NOT Met RCS Loop \T Loop I 1-Tl-68-2D Operable, 100 % Full Power Channel Check, Loop 2 l-Tl-68-25D arcl 100 % Full Power Loop 3 1-Tl-68-44D MCD 7% 100 % Full Power Loop 4 1-Tl-68-67D 101 % Full Power RCS Loop OPT Loop 1 1-Tl-68-2A Operable, 109 % Full Power Channel Check, Contact SRO to 11 1-M-5 Loop 2 1-Tl-68-25A 100 % Full Power consult Tech and Loop 3 1-Tl-68-44A MCD 7% % Full Power Specs.

111 Loop 4 1-Tl-68-67A 100 % Full Power RCS Loop OThT Loop 1 1-Tl-68-2B Operable, 118 % Full Power Channel Check, Loop 2 1-Tl-68-25B and 117 % Full Power Loop 3 1-Tl-68-44B MCD 8% 117 % Full Power Loop 4 1 -Tl-68-67B 120 % Full Power ROS Tavg Operable, Loop I 1-Tl-68-2E 593 F 586 F and 555°F, Contact SRO to 12 1-M-5 Loop 2 1-Tl-68-25E 586 F consult Tech Channel Check, Loop 3 1-Tl-68--44E 587 Specs.

and °F Loop 4 1-Tl-68-67E MCD 5F 587 °F SROs IntiaIs Remarks:

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN 0700 1900

- 1-Sl-0-2B-01 Unit I Shift And Daily Surveillance Log Rev. 0053 Mode One Page 37 of 56 Data Sheet I (Page 8 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Tndty Page________ of________

Ref Location Description Instrument # T S Limit Data Acc NOT Met 1-Fl-68-6A 100 %

Loop I Flow 1-Fl-68-68 100 %

1-FI-68-60 100 %

1-Fl-68-29A %

Loop 2 Flow 1-Fl-68-29B 99 %

1-Fl-68-29D 99 %

13 1M-5 If limit is NOT 1F16848A 100 % met using Loop 3 Flow 1-Fl68-48B Total RCS Flow 100 % indicators, Rate 380,000 gpm perform Data 1-Fl-68-48D for indicators 100 Sheet l3of 1-Fl-68-71A (Average 96.0%>, 100 % 1-Sl-0-2-00 and Loop 4 Flow 1-Fl-68-71B Channel Check, and repeat flow MCD 4% 100 readings using 1-Fl-68-71D 100 % Computer Points.

1098 %tot÷ Total all operable indicators and divide by number of operable indicators for average. ii # md =

99.8 %Avg Compare average to 98%.

YES NO D Mark YES if 98%. Mark NO if <98%.

RCP 1 2 3 4 Contact SRO to RCS Loops 1, 2,3,4 RCP Status ON gi consult OFF Q Q Q Q Tech Specs.

1-HS-68-8AA (1)

RCP 1 1 -HS-68-8BA All RCPs 15 1-M-5 1-HS-68-31AA running RCP 2 1-HS-68-31BA 1-HS-68-5OAA (1)

RCP 3 1 -HS-68-5OBA 1-HS-68-73AA (1)

RCP R 1-HS-68-738A (1) Loop status is to be written in data space (Operable (0), Running (R), or INOP).

Initials indicate acc met OR action in Candidates Performers SROs Acc not Met column initiated. Initials Initials Initials Remarks: Candidates may write the out of spec value on this line.

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN 0700 1900

1-Sl-0-2B-01 Unit I Shift And Daily Surveillance Log Rev. 0053 Mode One Page 38 of 56 Data Sheet I (Page 9 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page________ of Ref Location Description Instrument # T S Limit Data Acc NOT Met RWST to RHR 1 -FCV-63-1 OPEN ECCS Suction (1 -HS-63-1 A) CLOSED D 1-M-6 OPEN SI Pumps to I -FCV-63-22 OPEN CL 1, 2, 3, 4 (1 -HS-63-22A) CLOSED D Shunt BKR 1A1-A OFF c/2E1 1 -BKR-63-l A ON D 16 At least one OR breaker OFF Breaker 1 -BKR-63-1 B OFF D 480 Rx 1A1-A cllOA ON MDV Boards Shunt BKR 1B1-B OFF c/2F2 1 -BKR-63-22A ON D At least one OR breaker OFF Breaker 1 -BKR-63-22B OFF D 1B1-B c/liD ON t 1-Ll-63-180 Operable, 0 %

CNTMT 1-Ll-63-181 Channel 0 Contact SRO Sump Level Check, and to consult 1-Ll-63-182 0 % Tech Specs.

MCD 1-Ll-63-183 0 %

17 1-M-6 1-LI-63-50 97 %

Operable, 1-Ll-63-51 Channel 98 %

RWST Level 1-Ll-6352 Check, and 98 %

MCD 7.0%

I -Ll-63-53 1-FCV-63-1 18 OPEN 2 CL Accum 1 Outlet (1-HS-63-1 18A) CLOSED D 1 -FCV-63-98 OPEN 2 CL Accum 2 Outlet (1-HS-63-98A) Valves CLOSED C 18 1-M-6 1 -FCV-63-80 Open OPEN 2 CL Accum 3 Outlet (1-HS-63-80A) CLOSED C CL Accum 4 Outlet 1 -FCV-63-67 OPEN 2 (1 -HS-63-67A) CLOSED C tnitials indicate ace met OR action in Candidates Performers SROs Ace not Met column initiated. Initials Initials Initials Remarks: Candidates may write the out of spec value on this line.

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The unit is operating at 100% rated thermal power, no LCO entries at this time.

Portions of the field data have been entered by NAUOs.

You are the Unit Operator responsible to perform and review 1 -SI-0-2B-01 0700-1900 Shift And Daily Surveillance Log Mode 1.

INITIATING CUES:

You are to complete Data Sheet 1 pages 1 through 9 (reference 2 through 13, 15 through 18) and review the data. Another Unit Operator will complete the remainder of Data Sheet 1.

When you have finished performing the assigned pages of Data Sheet 1, and addressed any deviations, notify the Unit Supervisor that you have completed your task.

Rev. 0 3-OT-JPMADA.2-2B Page 1 of 33 WATTS BAR NUCLEAR PLANT 3-OT-J PMADA.2-2B Review and Evaluate Shift Daily Surveillance Log Mode One WRITTEN BY:

VALIDATED BY:

Rev. 0 3-OT-JPMADA.2-2B Page 2 of 33 WATTS BAR NUCLEAR PLANT 3-OT-J PMADA.2-2B APPROVED BY:

(OPERATIONS TRAINING)

CONCURRENCE:

(OPERATIONS REPRESENTATIVE)

Rev. 0 3-OT-JPMADA.2-2B Page 3 of 33 WATTS BAR NUCLEAR PLANT 3-OT-J P MADA.2-2 B NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 INITIAL ISSUE. Used 3-CT- 04/29/08 All Wm Dimond JPMADA.2-2A and modified to be the SRO review of the data sheets.

Rev. 0 3-OT-J PMADA.2-2B Page 4 of 33 WATTS BAR NUCLEAR PLANT 3-OT-J PMADA.2-2B ADMINISTRATIVE JOB PERFORMANCE MEASURE Task: Review and Evaluate Shift Daily Surveillance Log Mode One.

Alternate Path: N/A Facility JPM #: New K/A Rating(s): 2.2.12 [3.0/3.4]

Task Standard: Correctly review data on data sheet 1 references 2 throughl3, 15 through 18 and to determine whether or not the surveillance meets acceptance criteria.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant Perform X Simulate

References:

1-Sl-0-2B-01 0700-1900 Shift And Daily Surveillance Log Mode One Rev. 53.

Task Number:: RO-113-GEN-004 APLICABLE FOR: RO/SRO 1 OCFR55.45:

Validation Time: 18 mm. Time Critical: No Applicant: Time Start:

NAME SSN/EIN Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner:

NAME SIGNATURE DATE COMMENTS

Rev. 0 3-OT-JPMADA.2-2B Page 5 of 33 WATTS BAR NUCLEAR PLANT 3-OT-J PMADA.2-2B Tools/EguiDmenUProcedures Needed:

Copy of 1-SI-0-2B-0 Instruction sheet.

Attached Completed Copy of 1 -Sl-0-2B-01 0700-1900 Shift and Daily Surveillance Log Mode One partial data sheet.

Calculator

Rev. 0 3-OT-JPMADA.2-2B Page 6 of 33 WATTS BAR NUCLEAR PLANT 3-OT-J PMADA.2-2B NOTE TO EVALUATOR: Hand out the Entire 1-SI-O-2B-O1 and the filled-out data pages along with the Applicants Cue Sheet.

READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The unit is operating at 100% rated thermal power and has been stable for the last 30 days. No LCO entries at this time.

Portions of the field data have been entered by ROs and NAUOs.

Data takers are present.

You are the Unit Supervisor and the Shift Manager has assigned you to review 1-Sl-0-2B-01 0700-1900 Shift And Daily Surveillance Log Mode 1for discrepancies and take appropriate action(s) if any, once the review is complete.

INITIATING CUES:

The Shift Manager directs you to review the data on Data Sheet 1 pages 1 through 9 (reference 2 through 13, 15 through 18). (Another SRO will review the data sheets that are not attached.)

When you have finished reviewing the assigned pages of Data Sheet 1, identify and address any deviations.

Notify the Manager when you have completed your task.

Rev. 0 3-OT-JPMADA.2-2B Page 7 of 33 START TIME:

STEP 1: Obtains a copy of the instruction.

SAT STANDARD: A copy of 1-Sl-0-2B-O1 has been obtained.

EXAMINERS CUE: Provide the applicant with marked up surveillance.

UNSAT COMMENTS:

STEP 2: [Ref 2] Reviews data for Total Core Thermal Power Average SAT STANDARD: Applicant reviews reading for total core thermal power average (ICS computer point U2126 using LEFM which is 3445 MWT) recorded on the data sheet, determines that the value is 3459 MWT. UNSAT COMMENTS:

STEP 3: [Ref 3] Reviews data for CST A Level SAT STANDARD: Applicant reviews readings for CST A Level 1-LI-2-230A or 1-LI-2-230B (Value 330,000 gallons) recorded on the data sheet, determines that the value is 200,000 gallons.

UNSAT COMMENTS:

Rev. 0 3-OT-JPMADA.2-2B Page 8 of 33 STEP 4: [Ref 4] Reviews data in SG Pressure data table, check Operable, Channel Check, and MCD 90 psig.

SAT STANDARD: Applicant reviews readings for SG Pressure on the data sheet, determines that the channels are operable, channel checked and MCD is within 90 psig:

UNSAT 1-Pl-1-2A Operable, 1000 psig SG 1 Press 1-Pl-1-2B Channel Check, 1020 psig 1-P 5 and MCD 90 psig 1000 psig 1-Pl-1-9A Operable, 1015 psig SG 2 Press 1-PI-1-9B Channel Check, 1020 psig 1-Pl-1-12 and MCD 90 psig 1020 psig 1-Pt-i -20A Operable, 1010 psig SG 3 Press i-Pl-i-20B Channel Check, 1000 psig i-Pl-i-23 and MCD 90 psig 1010 psig i-Pt-i -27A Operable, 1000 psig SG 4 Press i-PI-i-27B Channel Check, 1000 psig i-pl-1-30 and MCD 90 psig 1010 psig COMMENTS:

Rev. 0 3-OT-JPMADA.2-2B Page 9 of 33 STEP 5: [Ref 5] Reviews data in SG Level data table, check Operable, Channel Check, and MCD 6.0 % CRITICAL STEP STANDARD: Applicant reviews current readings for SG Level on the data sheet and determines that SG 3 Level channel l-LI-3-94 is not within MCD is within 6.0%. The Candidate should circle 66% SAT for 1 -Ll-3-94, identify the associated Tech Specs and write them on the space provided at the bottom of the data sheet page.

Tech Specs:

3.3.1, Function 13, Condition U - 6 hrs to trip. UNSAT 3.3.2, Function 5. b, Condition I 6 hrs to trip.

3.3.2, Function 6. b, Condition M 6 hrs to trip.

3.3.3, Function 16, Condition A - 30 days EXAMINERS NOTE: Bold items above are critical.

1 -LI 42 Operable, 60 %

SG 1 Level 1 -LI 39 Channel Check, 59 %

1 -LI-3-38 and MCD 6.0% 57 %

1 -LI 55 Operable, 60 %

SG 2 Level 1 -LI 52 Channel Check, 60 %

1 -LI 51 and MCD 6.0% 60 %

1 -LI 97 Operable, 58 %

SG 3 Level 1 -LI-3-94 Channel Check, 66 %

1 -LI 93 and MCD 6.0% 58 %

1-LI-3-110 Operable, 60%

SG 4 Level 1-LI-3-107 Channel Check, 60%

1 -Ll-3-1 07 and MCD 6.0% 60 %

EXAMINERS CUE: If asked: Respond as the RO who took the data that the MCB still indicates as transcribed onto the data sheet.

EXAMINERS CUE: If asked to review previous shifts SI-2 Data, inform the Candidate that all previous data on this instrumentation was within MCD prior to today.

EXAMINERS CUE: If asked the color of the placard for 1-LI-3-94 (to deduce if it is a PAMs instrument), respond that it is a black placard.

COMMENTS:

Rev. 0 3-OT-J PMADA.2-2B Page 10 of 33 STEP 6: [Ref 6] Reviews data in data table for Shutdown Bank Group Step Counters and RPI Step indications, check Operable, 225 steps withdrawn and +/-12 steps of group step counter.

STANDARD: Applicant reviews readings for Shutdown Bank Step counters SAT and individual rod position which is most deviated from step counter logged. Determines that Shutdown Bank B2 Step counter (demand) is not reading as expected.

UNSAT Shutdown Bank Al Grp 1 Step Operable, 225 Group Step 228 D2, P4, B12, Ml4 (1 -SBAG1) steps, +/-12 steps Grp 1 RPI of group step RPI Step 230 counter Shutdown Bank A2 Grp 2 Step Group Step 228 M2, B4, P12, Dl4 (l-SBAG2)

Grp 2 RPI RPI Step 230 Shutdown Bank Bl Grp 1 Step Group Step 228 G3, 09, J13, N7 (l-SBBG1)

Grp 1 RPI RPI Step 229 Shutdown Bank B2 Grp 2 Step Group Step 2i0 J3, N9, G13, C7 (1-SBBG2)

Grp 2 RPI RPI Step 229 Shutdown Bank Cl Grp 1 Step Group Step 228 E3, N5, Cii, L13 (1-SBCG1)

Grp 1 RPI RPI Step 229 Shutdown Bank Di Grp 1 Step Group Step 228 L3, 05, Nil, E13 (1 -SBDG1)

Grp 1 RPI RPI Step 230 EXAMINERS CUE: If asked: Respond as the RO who took the data that the MCB indicates 228 and it was a transcription error. (One line initial date 210 and write 228 next to it.)

EXAMINERS CUE: If asked to review previous shifts SI-2 Data, inform the Candidate that all previous data on this instrumentation was within MCD prior to today.

COMMENTS:

Rev. 0 3-OT-J PMADA.2-2B Page 11 of 33 STEP 7: [Ref 7] Reviews data in data table for Control Bank Group Step Counters and RPI Step indications, check Operable, Insertion Limits in COLR, Sequence, and +/-12 steps of group step counter.

SAT STANDARD: Applicant reviews current readings for Control Bank Step counters and individual rod position which is most deviated from step counter logged. Determines all requirements are met. UNSAT Control Bank Al Grp 1 Step Insertion limits in Group Step 228 H6, Hl0, E5, Ell (1 -CBAG1) COLR, Grp 1 RPI Sequence, RPI Step 231 Control Bank A2 Grp 2 Step Overlap Group Step 228 F8, K8, L5, Ll1 (1-CBAG2)

Grp 2 RPI and RPI Step 230 Control Bank B1 Grp 1 Step +/-12 steps of Group Step 228 F2, P6, BlO, Kl4 (l-CBBG1) group step Grp 1 RPI counter RPI Step 224 Control Bank B2 Grp 2 Step Group Step 228 K2, B6, PlO, F14 (1- CBBG2)

Grp 2 RPI RPI Step 229 Control Bank Cl Grp 1 Step Group Step 228 H2, P8, B8, H14 (1- CBCG1)

Grp 1 RPI RPI Step 229 Control Bank C2 Grp 2 Step Group Step 228 K6, F6, K1O, FlO (1- CBCG2)

Grp 2 RPI RPI Step 230 Control Bank Dl Grp 1 Step Group Step 220 M4, D4, M12, D12 (1- CBDG1)

Grp 1 RPI RPI Step 217 Control Bank D2 Grp 2 Step Group Step 220 H4, H8, M8, D8, (1 -CBDG2)

H12 Grp 2 RPI RPI Step 217 COMMENTS:

Rev. 0 3-OT-JPMADA.2-2B Page 12 of 33 STEP 8: [1] IF Control Rod Bank Dat 118 Steps or further withdrawn, THEN CHECK Control rod banks A, B, and C at their fully SAT withdrawn position.

[2] IF Control Rod Bank D at 117 Steps or further inserted, THEN VERIFY ALL Control Banks fully withdrawn or UNSAT properly overlapped using bank step counters and Data Sheet 7 of 1-SI-0-2-00.

STANDARD: Applicant determines that step [1] conditions are met and that Control Rod Banks A, B, and C are at their fully withdrawn position and that Step [2] is marked N/A correctly since stated conditions do not exist.

COMMENTS:

Rev. 0 3-OT-JPMADA.2-2B Page 13 of 33 STEP 9: [Ref 8] Reviews data for Power Range and Intermediate Range Nis in data table, check Operable, Channel Check, and MCD 2.0%.

SAT STANDARD: Applicant reviews readings for Power Range and Intermediate Range Nis and determines that the channels are operable, channel checked and MCD is within 2.0%:

UNSAT 1-Nl-41B Operable, 100 %full power PR Flux % Power 1 -Nl-42B Channel Check, 99 % full power 1 -Nl-43B and MCD 2.0% 100 % full power 1 -Nl-44B 98 % full power lR % Power CH I 1 -N 1-92-1 35A Operable when (j% RTP X 2.35)=

below P-b lowest

% full power IR % Power OH 2 1-NI-92-136A Operable when NI 136 Highest below P-b channel?

EYES LI NO Lowest Channel Channel check, LI 1-NI-92-135A and lowest reading E 1 -NI-92-1 36A IR X 2.35 is greater than highest reading_IR.

COMMENTS:

Rev. 0 3-OT-JPMADA.2-2B Page 14 of 33 STEP 10: [Ref 9] Reviews data in PZR Level data table, check Operable, ss than or equal to 80%, Channel Check, and MCD 6.0 SAT STANDARD: Applicant reviews readings for PZR Level and determines that PZR Level is less than 80%, and MCD is less than 6.0%.

UNSAT 1 -Ll-68-339A Operable, 80% 61 %

PZR Level 1-Ll-68-335A Channel Check, 61 %

1 -Ll-68-320 and MCD 6.0% 61 %

COMMENTS:

STEP 11: [Ref 10] Reviews data in PZR Press data table and checks Operable, Channel Check, greater than or equal to 2214 psig, and MCD 6.0 %

SAT STANDARD: Applicant reviews readings for PZR pressure and determines that PZR pressure is greater than or equal to 2214 psig, and MCD is 55 psig UNSAT 1 -Pl-68-340A Operable, 2220 psig PZR Press 1 -P1-68-334 Channel Check, 2220 psig 1 -P1-68-323 2214 psig 2225 psig 1 -P1-68-322 and MCD 55 2225 psig psig%

COMMENTS:

Rev. 0 3-OT-JPMADA.2-2B Page 15 of 33 STEP 12: [Refill Reviews data for RCS Loop zT, RCS Loop OPAT, and RCS Loop OTLT in data table, check Operable, Channel Check, and MCD.

SAT STANDARD: Applicant reviews readings for RCS Loop Ts on the data sheet and determines that the channels are operable, channel checked and MCD is within 7% for LOOP T and OPtT and MCD is within 8%: UNSAT Loop 1 1 -Tl-68-2D Operable, 100 % full power Loop 2 1 -Tl-68-25D Channel Check, 100 % full power Loop 3 1 -Tl-68-44D and MCD 7% 100 % full power Loop 4 1-Tl-68-67D 101 % full power Loop 1 1 -TI-68-2A Operable, 109 % full power Loop 2 1-Tl-68-25A Channel Check, 100 Thlfr% full power Loop 3 1 -Tl-68-44A and MCD 7% 111 % full power Loop 4 1 -TI-68-67A /uj -14G4 full power Loop 1 1 -TI-68-2B Operable, 1 18 % full power Loop 2 1 -Tl-68-25B Channel Check, 1 17 % full power Loop 3 1 -Tl-68-44B and MCD 8% 117 % full power Loop 4 1-TI-68-67B 120% full power COMMENTS:

1 fP re r/ed I UduI k2 sfJeJ e9 [P1J q

Oi1(

Rev. 0 3-OT-JPMADA.2-2B Page 16 of 33 STEP 13: [Ref 12] Reviews data for RCS Tavg data table and checks Operable, Channel Check, and MCD 5°F. SAT STANDARD: Applicant reviews readings for RCS Tavg on the data sheet and determines that the channels are operable, channel checked and MCD is within 5°F. UNSAT Operable, Loop 1 1-Tl-68-2E 593 °F 586 °F Loop 2 1-Tl-68-25B and 555 EF 586 °F Channel Check, Loop 3 1 -Tl-68-44E and MCD 5°F 587 °F Loop 4 1 -Tl-68-67E 587 °F COMMENTS:

Rev. 0 3-OT-JPMADA.2-2B Page 17 of 33 STEP 14: [Ref 131 Reviews data for RCS Flow into data table, Channel Check, CRITICAL and MCD4%. STEP STANDARD: Applicant reviews readings for RCS Flows on the data sheet and determines that total RCS flow rate is greater than or equal to SAT 380,000 gpm (Average 96%), channel checked and determines that 1-FI-28-29A is not within MCD is within 4.0%. The Candidate should circle 105% for 1 -Fl-68-29A, identify the associated Tech Specs and write them on the space provided at UNSAT the bottom of the data sheet page.

Tech Specs:

3.3.1, Function 10a, Condition N - 6 hrs to trip.

3.3.1, Function 1 0.b, Condition X - 6 hrs to trip EXAMINERS NOTE: Bold items above are critical.

1 -Fl-68-6A Total RCS Flow 100 %

Loop 1 Flow 1-Fl-68-6B Rate 380,000 gpm 100%

1-FI-68-6D for indicators 100%

1 -Fl-68-29A (Average 96%), 105 %

Loop 2 Flow 1 -Fl-68-29B Channel Check, and 99 %

1 -Fl-68-29D and MCD 4% 99 %

1 -Fl-68-48A 100 %

Loop 3 Flow 1 -Fl-68-48B 100 %

1-Fl-68-48D 100%

1-FI-68-71A 100%

Loop 4 Flow 1 -Fl-68-71 B 100 %

1-FI-68-71D 100%

Total all operable indicators and divide by 1098 % tot ÷ number of operable indicators for 11 # md =

average.

98 % Avg Compare average to 98%.

Mark YES if 98%. Mark NO if <98% Yes li NO LI EXAMINERS CUE: If asked: Respond as the RO who took the data that the MCB still indicates as transcribed onto the data sheet.

EXAMINERS CUE: If asked to review previous shifts SI-2 Data, inform the Candidate that all previous data on this instrumentation was within MCD prior to today.

COMMENTS:

Rev. 0 3-OT-J PMADA.2-2B Page 18 of 33 STEP 15: [Ref 15] Reviews data for Reactor Coolant Pumps into data table.

SAT STANDARD: Applicant reviews data in data sheet indicating RCP 1, 2, 3, and 4 are running and deduces that the individual who took the data must have had a transcription error (otherwise the unit UNSAT wouldnt be running) and contacts the individual to verify the error and have them correct it.

RCS Loops RCP Status RCP1 2 3 4 1,2,3,4 ONE EEE OFF RCP 1 1 -HS-68-8AA A!! RCPs R 1 -HS-68-8BA RCP 2 1-HS-68-31AA running R 1 -HS-68-31 BA RCP 3 1 -HS-68-5OAA R 1 -HS68-5OBA RCP 4 1 -HS-68-73AA R 1 -HS-68-73BA EXAMINERS CUE: If asked: Respond as the RO who took the data that the #1 RCP is indeed running and that it was a transcription error. (One line initial date and check the on box for RCP #1W)

EXAMINERS CUE: If asked to review previous shifts Sl-2 Data, inform the Candidate that all previous data on this instrumentation was within MCD prior to today.

COMMENTS:

Rev. 0 3-OT-JPMADA.2-2B Page 19 of 33 STEP 16: [Ref 16] Reviews data for 1-FCV 63-1 and 1-FCV-63-22 data table. SAT STANDARD: Applicant reviews data sheet indicating Valve 1 -FCV-63-1 and -

22 are OPEN and breaker status OPEN for at least one UNSAT breaker for each valve:

RWST to RHR 1 -FCV-63-1 OPEN E ECCS Suction (1-HS-63-1A) CLOSED SI Pumps to 1 -FCV-63-22 OPEN OPEN CL 1,2,3,4 (1-HS-63-22A) CLOSED 3hunt Breaker 1A1-A OFF c/2E1 1-BKR-63-1A At least one ON LI OR Breaker 1 -BKR-63-1 B breaker OFF OPEN LI 1A1-Ac/1OA CLOSED E 3hunt Breaker 1B1-B OPEN cI2F2 1 -BKR-63-22A At least one CLOSED LI OR Breaker 1 -BKR-63-22B breaker OFF OPEN LI 1B1-Bc/11D CLOSED l1 COMMENTS:

Rev. 0 3-OT-JPMADA.2-2B Page 20 of 33 STEP 17: [Ref 17] Reviews data for CNTMT Sump Level and RWST Level CRITICAL into data table, check Operable, Channel Check, and check STEP MCD.

STANDARD: Applicant reviews readings for CNTMT Sump Level and RWST Level and records them on the data sheet, determines that SAT CNTMT Sump Level channels are operable, channel checked and MCD is within 6.0%. Determines RWST Level channel 1-LI-63-53 is not within MCD is within 7.0%. The Candidate UNSAT should circle 89% for 1 -LI-63-53, identify the associated Tech Specs and write them on the space provided at the bottom of the data sheet page.

Tech Spec:

3.3.2, Function 7.b, Condition K - 6 hrs to bypass.

EXAMINERS NOTE: Bold items above are critical.

CNTMT Sump Level Loop 1 1-Ll-63-180 Operable, 0%

Loop 2 1 -Ll-63-1 81 Channel Check, 0%

Loop 3 1-Ll-63-182 and MCD 6.0% 0%

Loop4 1-Ll-63-183 0%

RWST_Level Loop 1 1 -Ll-63-50 Operable, 97 %

Loop 2 1 -Ll-63-51 Channel Check, 98 %

Loop 3 1 -Ll-63-52 and MCD 7.0% 98 %

Loop 4 1 -Ll-63-53 89 %

EXAMINERS CUE: If asked: Respond as the RO who took the data that the MCB still indicates as transcribed onto the data sheet.

EXAMINERS CUE: If asked to review previous shifts SI-2 Data, inform the Candidate that all previous data on this instrumentation was within MCD prior to today.

EXAMINERS CUE: If asked the color of the placard for 1-LI-63-53 (to deduce if it is a PAMs instrument), respond that it is a white placard.

COMMENTS:

Rev. 0 3-OT-JPMADA.2-2B Page 21 of 33 STEP 18: [Ref 18] Reviews data for Cold Leg Accumulator Isolation Valves in data table. SAT STANDARD: Applicant reviews status of cold leg accumulator valves as open on the data sheet:

UNSAT CL Accum 1 Outlet 1 -FCV-63-1 18 OPEN I1 (1-HS-63-118A) CLOSED CL Accum 1 Outlet 1 -FCV-63-98 Valves OPEN l1 (1-HS-63-98A) OPEN CLOSED CL Accum 1 Outlet 1 -FCV-63-80 OPEN (1-HS-63-80A) CLOSED CL Accum 1 Outlet 1-FCV-63-67 OPEN FZI (1-HS-63-67A) CLOSED COMMENTS:

Rev. 0 3-OT-JPMADA.2-2B Page 22 of 33 STEP 19: Informs the Shift Manager that Data Sheet 1 Pages 1-9 of 1-SI-O-2B-01 have been reviewed and gives the package to the Shift Manager.

SAT STANDARD: Applicant informs the Shift Manager of the completion of Data sheet 1 pages 1 through 9 of 1-SI-0-2B-01 and reports any Acceptance CriterialTech Specs not met if not previously communicated. UNSAT EXAMINERS CUE: Respond as Shift Manager and acknowledge that:

SG 3 Narrow Range Level instrument 1-LI-3-94 appears to be inoperable as it exceeds MCD and the following Tech Specs have been entered.

o 3.3.1, Function 13, Condition U - 6 hrstotrip.

o 3.3.2, Function 5. b, Condition I 6 hrs to trip.

o 3.3.2, Function 6. b, Condition M 6 hrs to trip.

o 3.3.3, Function 16, Condition A - 30 days

Loop 2 RCS Flow Instrument 1 -Fl-68-29A appears to be inoperable as it exceeds MCD and Tech Spec have been entered:

o 3.3.1, Function 10.a, Condition N - 6 hrstotrip.

o 3.3.1, Function 10.b, Condition X - 6 hrs to trip.

RWST Level Transmitter 1-LI 53 appears to be inoperable as it exceeds MCD and the appropriate Tech Spec have been entered:

o 3.3.1, Function 10.a, Condition X - 6 hrs to trip The Applicant may also state that PERs would be written for unexpected LCO entries. That WOs would be initiated for the affected instruments. That the Work Week manager would be contacted.

EXAMINERS CUE: Acknowledge report as Shift Manager, then state We will stop here.

COMMENTS:

END OF TASK TIME STOP:

Rev. 0 3-OT-JPMADA.2-2B Page 23 of 33 CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The unit is operating at 100% rated thermal power and has been stable for the last 30 days. No LCO entries at this time.

Portions of the field data have been entered by ROs and NAUOs.

Data takers are present.

You are the Unit Supervisor and the Shift Manager has assigned you to review 1-SI-0-2B-01 0700-1900 Shift And Daily Surveillance Log Mode 1for discrepancies and take appropriate action(s) if any, once the review is complete.

INITIATING CUES:

The Shift Manager directs you to review the data on Data Sheet 1 pages 1 through 9 (reference 2 through 13, 15 through 18). (Another SRO will review the data sheets that are not attached.)

When you have finished reviewing the assigned pages of Data Sheet 1, identify and address any deviations.

Notify the Manager when you have completed your task.

SRO Candidate Copy of 1 -SI-2B-01 for review WBN 0700 - 1900 1-Sl-0-2B-01 Unit I Shift And Daily Surveillance Log Rev. 0053 Mode One Page 30 of 56 Data Sheet I (Page 1 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page 1 of________

Ref Location Description Instrument # T S Limit Data Acc NOT Met Ref. 2 may be N/Nd when Rx Power < 90%

If Rx Power is 3445 greater than Maintain 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months License Limit, the average of 08:00 MWT SRO is to be 3459 MWT notified to reduce Total Core Point U2126 OR while using LEFM power to less than 2 ICS Thermal Power U1126(8 HrAVG) OR 3411 MWT or equal to License Average when complying 12:00 MWT Limit as soon as with TR 3.3.7 possible. If ICS Action B. average is INOP or unreliable, perform 16:00 MWT DataSheet2.

1-M-2 1-Ll2230A Perform Data 3 CST A Level OR 330,000 Sheet 3 of Pnl 0-L-209 200,000 gallons 1-Ll-2-230B C 1-SlO-2-0o T15M/708 gallons CST Level 1-Pl-1-2A 1000 psig SG 1 Press 1-Pl-1-2B 1020 psig 1-Pl-1-5 1000 psig 1-Pl-1-9A 1015 psig SG 2 Press 1-Pl-1-9B 1020 psig Operable, 1-Pl-1-12 Channel Check 1020 psig Contact SRO to 4 1-M-4 consult Tech 1-Pl-1-20A and MCD 90 psig ioio psig Specs.

SO 3 Press 1-Pl-1-20B 1000 psig 1-Pl-1-23 1010 psig 1-Pl-1-27A 000 psig SG 4 Press 1-Pl-1-27B 000 psig 1-Pl-1-30 010 psig (1) These readings to be taken after SRO initial review of Data Sheet 1.

Initials indicate acc met OR action in Aco not Performers SROs Met column initiated. Initials InitiaIs Remarks:

SRO Candidate Copy of 1-SI-2B-O1 for review WBN 0700 1900

- 1-Sl-0-2B-01 Unit I Shift And Daily Surveillance Log Rev. 0053 Mode One Page 31 of 56 Data Sheet I Today (Page 2 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page__2 of 9 Ref Location Description Instrument # T S Limit Data Acc NOT Met 1-Ll-3-42 60 %

SO 1 Level 1-Ll-3-39 59 %

1-Ll3-38 57 %

1-LI-3-55 60 %

SO 2 Level 1-LI-3-52 60 Operable:

1-Ll-3-51 ChannelCheck, 60 % Contact SRO to 5 1-M-4 consult Tech 1-Ll-3-97 and 58 Specs.

MCD 6.0%

SG 3 Level 1-Ll-3-94 66 1-Ll-3-93 58 1-Ll-3-110 60 804 Level 1-Ll-3-107 60 1-LI-3-106 60 SROs nitias Remarks:

SRO Candidate Copy of 1-Sl-2B-O1 for review WBN 0700 - 1900 1-Sl-0-2B-01 Unit I Shift Arid Daily Surveillance Log Rev. 0053 Mode One Page 32 of 56 Data Sheet I (Page 3 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page________ of Ref Dep Instrument # T S Limit Data Acc NOT Met Description Shutdown Bank Al Grp 1 Step Group Step 228 (1-SBAG1) If ONE demand RPI position indicator per D2,P4,B12.M14 Grp I RPI (2)

Step 230 bank is inoperable Group for one or more Shutdown Bank A2 Grp 2 Step (l-SBAG2) Step 228 banks, Per LCO 3.1.8 Action C.

M2,B4P12,D14 Grp 2 RPI (2) 230 then perform Data Sheet 6 of Shutdown Bank Bl Grp 1 Group l-sI-o-2-oo Step 228 Shut-down Rod Step (l-SBBG1) 225 Steps G3,C9,J13,N7 Grp 1 RPI (2) RPI Position once per withdrawn and Step 229 6 1-M-4 +/-12 steps of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Shutdown Bank B2 Grp 2 Group Step Group Step 210 If rod deviation Step (l-SBBG2) Counter monitor J3,N9,G13,C7 Grp 2 RPI (21 229 (computer) is inoperable, individual Group rod positions are to Shutdown Bank Cl Grp Step (l-SBCG1) Step 228 be recorded on Data E3,N5,C11,L13 Grp RPI (2) Sheet 6 of 229 l-Sl-O-2-O0 Group Shut-down Rod Shutdown Bank Dl Grp Step 228 Position every Step (1-SBDG1) 4hours.

L3,C5,N11,E13 2 GrpRPl 230 5p (1) For each RPI. individual rod position which is most deviated from step counter indication is to be logged.

(2) Rod indications can be from CERPI computer screens on 1-M-4 or CS.

I I

nitials indicate acc met OR action in Acc not Performers SROs Met column initiated. Initials Initials Remarks:

SAC Candidate Copy of 1 -Sl-2B-O1 for review WBN 0700 1900

- 1-Sl-0-2B-0i Unit I Shift And Daily Surveillance Log Rev. 0053 Mode One Page 33 of 56 Data Sheet I (Page 4 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page of 9 Ref Location Description nstrumerit # T S Limit Data Acc NOT Met Control Bank Al Group Grp 1 Step (l-CBAG1) Step 228 RPI H6,H1O,E5,El1 Grp 1 RPI(

r 3

2 231 Step If ONE demand Control Bank A2 Group position indicator per Grp 2 Step 228 bank is inoperable for Step (l-CBAG2)

F8,K8,L5,L1l 13 Grp2RPI one or more banks, Per 231 LCO 3.1.8 Action C.

then perform Data Control Bank Bl Group Sheet 7 of 1-Si-O-2-0O Grp 1 Step (l-CBGl) Insertion Ltmits Step 228 Control Rod Position F2,P6.BlO,Kl4 in COLR, RPI once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Grp 1 RPI Sequence, 2 224 Step If rod deviation monitor Overlap and Group (computer) is Control Bank 82 Grp 2 228

+/- 12 steps of Step inoperable, individual Step (l-CBBG2) rod positions are to be Group Step RPI K2,B6,PlO,F14 Grp 2 RPI 2 229 Stepi recorded on Data 1

Counter.

7 l-M-4 Sheet 7 of 1-SI-O-2-OO (If MTC Group Shut-down Rod Control Bank Cl Grp 1 Step (1-CBCG1) withdrawal limits Step 228 Position every are in effect. RPI 4ho.u H2,P8,B8.H14 Grp 1 RPI NOB Sheet A-5 Step 229 If rod insertion monitor IS Group (1-XZ-55-4B-87A) is Control Bank C2 Grp 2 to be Step 228 inoperable, rod Step (l-CBCG2) referenced.) insertion limits as listed K6.F6,K1O,F1O Grp 2 RPI l3i 230 in the COLR are to be verified & individual rod Group posistions are to be Control Bank Dl Grp 1 Step 220 recorded on Data Step (1-CBDG1) Sheet 7 of 1-Sl-0-2-O0 RPI M4,D4,M12,D12 Grp 1 RPI > Control Rod Posistion 2 217 Step every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .t Group Control Bank D2 Grp 2 220 Step (l-CBDG2) Step RPI H4,H8, M8,D8,Hl2 Grp 2 RPI >>

> 217 2

Step>

(1) Sequence & overlap can best be verified during rod withdrawal and insertion. Rod sequence is in accordance with COLR figure 1 and bank overlap is set by instrument Maintenance.

(2) For each RPI. individual rod position which is most deviated from step counter indication is to be logged.

(3) Rod indications can be from CERPI computer screens on 1-M-4 or CS.

Initials indicate acc met OR action in Acc not Performers SROs Met column initiated. Initials Initials Remarks:

SRO Candidate Copy of 1-SI-2B-01 for review WBN 0700 1900

- 1-Sl-0-2B-01 Unit I Shift And Daily Surveillance Log Rev. 0053 Mode One Page 34 of 56 Data Sheet I (Page 5 of 24)

Mode I Surveillance Log: 0700 - 1900 5

Date Today Page________ of

[1] IF Control Rod Bank D at 118 Steps or further withdrawn, THEN CHECK Control rod banks A, B, and C at their fully withdrawn position. Jro

[2J IF Control Rod Bank Dat 117 Steps or further inserted, THEN VERIFY ALL Control Banks fully withdrawn or properly overlapped using bank step counters and Data Sheet 7 of N/A 1-S 1-0-2-00, Initials indicate ace met OR action in Performers SROs Ace not Met column initiated, Initials Initials Remarks:

SRO Candidate Copy of 1-SI-2B-O1 for review WBN 0700 1900

- 1-Sl-0-2B-01 Unit I Shift And Daily SurveIllance Log Rev. 0053 Mode One Page 35 of 56 Data Sheet I (Page 6 of 24)

Mode I Surveillance Log: 0700 - 1900 6 9 Date Today Page________ of Ref Location Description Instrument # T S Limit Data Acc NOT Met 1-Nl-41B Operable, 100 %

PRFlux% 1-Nl-42B ChannelCheck, 99 %

Power 1-Nl-43B and MCD 2,O %

ioo %

1-Nl-44B 98 % If the PRM MCD exceeds 2%,

IR % Power STA shall per-OH I 1-Nl-92-135A 140 % RTP Operable when form 1-S 1-92-1 lR % Power below P-b and notify MIG, lNl-92136A 120 % RTP If the PRM MCD CH II 8 1-M-4 exceeds 4%, the

__120 % RTP x 2.35) = channel should Lowest be evaluated for Channel Check, and Calcd operability.

J lowest channel Lowest reading NI 136 channel Contact SRO to 0 1 -Nl-92-1 35A IR x 2.35 is greater con-suIt Tech 2 1-Nl-92-136A than highest reading Specs 282 Hghest IR.

Calcd channel?

channel tYES ONO 1-Ll-68-339A Operable, less than 61 Contact SRO to or equal to 80%,

9 1-M-4 PZR Level 1-Ll-68-335A 61 % consult Tech Channel Check, and Specs.

1-Ll-68-320 MCD 6.0% 61 %

1-Pl-68-340A 2220 psig Operable, channel 1-Pl-68-334 check, greater than 2220 psig Contact SRO to 10 1 -M-5 PZR Press orequal to 2214 psig consult Tech 1-PI-68-323 2225 psig 5pe and MCD 55 psig.

1-PI-68-322 2225 psig Remarks:

I Initials indicate acc met OR action in Ace not Met column initiated.

jc Performers Initials SROs Initials

SRO Candidate Copy of 1 -Sl-2B-O1 for review WBN 0700 1900

- 1-Sl-0-2B-01 Unit I Shift And Daily Surveillance Log Rev. 0053 Mode One Page 36 of 56 Data Sheet I (Page 7 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page 7 of 9 Ref Location Description Instrument # T S Limit Data Acc NOT Met RCS Loop AT Loop 1 1-Tl-68-2D Operable, 100 % Full Power Channel Check, Loop 2 1-TI-68-25D and 100 % Full Power Loop 3 1-Tl-68-44D MCD 7% 100 % Full Power Loop 4 1 -Tl-68-67D 101 % Full Power RCS Loop OPAT Loop 1 1-Tl-68-2A Operable, 109 % Full Power Contact SRO to Channel Check, 11 1-M-5 Loop 2 1-Tl-68-25A 100 % Full Power consult Tech Specs, Loop 3 1 -Tl-68-44A MCD 7% 111 % Full Power Loop 4 1-Tl-68-67A 100 % Full Power RCS Loop OTAT Loop 1 1 -Tl-68-2B Operable, 118 % Full Power Channel Check, Loop 2 1-Tl-68-25B and 117 %FullPower Loop 3 1-Tl-68-44B MCD 8% 117 %FullPower Loop 4 1 -Tl-68-678 120 % Full Power RC Tavg Operable, Loop 1 1-Tl-68-2E 593 F 586 °F

. Contact SRO to 12 1-M-5 Loop 2 1-Tl-68-25E 586 F consult Tech Channel Check, Loop 3 1-Tl-68-44E 587 Specs, and °F Loop4 1-Tl-68-67E MCD5F 587 F Initials indicate eec met OR action in JRO Performers SR0s Ace not Met column initiated. Initials Initials Remarks:

r E we ulç i tnot c & C C.

SRO Candidate Copy of 1 -Sl-2B-O1 for review WBN 0700 1900

- 1-Sl-0-2B-01 Unit I Shift And Daily Surveillance Log Rev. 0053 Mode One Page 37 of 56 Data Sheet I (Page 8 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page 8 of________

Ref Location Description Instrument # T S Limit Data Acc NOT Met 1-Fl-68-6A 100 %

Loop 1 Flow 1-Fl-68-6B 100 %

l-F!-68-6D 100 %

1-Fl-68-29A 105 %

Loop 2 Flow 1-Fl-68-29B 99 %

l-Fl-68-29D 99 %

13 1-M-5 If limit is NOT 1-Fl-68-48A 100 % met using Loop 3 Flow 1-FI-68-48B Total RCS Flow 100 % indicators, Rate 380,000 gpm perform Data 1-Fl-68-48D for indicators 100 °° Sheet 13 of 1-FI-68-71A (Average 96.0%), 100 % 1-Sl-0-2-00 and Loop 4 Flow 1-Fl-68-71B Channel Check, and % repeat flow MCD 4%

100 readings using 1-Fl-68-71D 100 % Computer Points.

1098 %tot÷ Total all operable indicators and divide by number of operable indicators for average. md 99.8 %Avg Compare average to 98%.

YES 1 NO D Mark YES if 98%. Mark NO if <98%.

RCP 1 2 3 4 Contact SRO to RCS Loops 1,2, 3,4 RCP Status ON Q consult OFF C C C Tech Specs.

1-HS-68-8AA RCP 1 R 1 -HS-68-8BA All RCPs 15 1-M-5 1-HS-68-31AA RCP 2 running R 1-HS-68-319A 1-HS-68-5OAA (1)

RCP 3 I -HS-68-5OBA 1-HS-68-73AA (1)

RCP 1-HS-68-73BA (1) Loop status is to be written in data space (Operable (0). Running (R). or INOP).

SROs Initials Remarks:

SRO Candidate Copy of 1-Sl-2B-O1 for review WBN 0700 1900- 1-Sl-0-2B-01 Unit I Shift And Daily Surveillance Log Rev. 0053 Mode One Page 38 of 56 Data Sheet I (Page 9 of 24)

Mode I Surveillance Log: 0700 - 1900 Date Today Page 9 of 9 Ref Location Description Instrument # T S Limit Data Acc NOT Met RWSTto RHR 1-FCV63-1 OPEN ECCS Suction (1-HS-63-1A) CLOSED C l-M-6 OPEN SI Pumps to 1 -FCV-63-22 OPEN CL 1, 2, 3, 4 (1-HS-63-22A) CLOSED C Shunt BKR 1A1-A OFF l c/2E1 1-BKR-63-1A ON C 16 At least one OR Breaker 1-BKR-63-1B breaker OFF OFF c 480 Rx IA1-A c/IOA ON MOV Boards ShuntBKRlBl-B OFF cI2F2 1-BKR-63-22A ON C At least one OR breaker OFF Breaker 1-BKR-63-22B OFF c 1B1-Bc/1ID ON t 1-Ll-63-180 Operable, 0 %

CNTMT 1-Ll-63-181 Channel 0 % Contact SRO Sump Level Check, and to consult 1-Ll-63-182 Tech Specs.

MCD 6.0%

1-Ll-63-183 0 17 1-M-6 1-Ll-63-50 97 %

Operable, 1-Ll--63-51 Channel 98 %

RWST Level 1-Ll-63-52 Check, and 98 %

MCD 7.0%

1-Ll-63-53 89 %

1-FCV-63-118 OPEN CL Accum 1 Outlet (1-HS-63-118A) CLOSED C 1-FCV-63-98 OPEN CL Accurn 2 Outlet (1-HS-63-98A) Valves CLOSED C 18 1-M-6 1-FCV-63-80 Open OPEN CL Accum 3 Outlet (1-HS-63-80A) CLOSED C 1-FCV-63-67 OPEN 2 CL Accum 4 Outlet (1-HS-63-67A) CLOSED C I Remarks:

Initials indicate acc met OR action in Acc not Met column initiated.

Performers Initials SROs Initials

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The unit is operating at 100% rated thermal power with no LCO entries at this time.

Portions of the field data have been entered by ROs and NAUOs.

You are the Unit Supervisor and the Shift Manager has assigned you to review 1 -Sl-0-2B-01 0700-1900 Shift And Daily Surveillance Log Mode 1 for discrepancies and take appropriate action(s) if any, once the review is complete.

INITIATING CUES:

The Shift Manager directs you to review the data on Data Sheet 1 pages 1 through 9 (reference 2 through 13, 15 through 18). (Another SRO will review the data sheets that are not attached.)

When you have finished reviewing the assigned pages of Data Sheet 1, identify and address any deviations.

Notify the Manager when you have completed your task.

Rev 0 PAGE 1 OF 35 Watts Bar Nuclear Plant 3-OT-JPMADA 2-3 Hand Calculation of RCS Inventory Balance

RevO PAGE 2 0F35 Watts Bar Nuclear Plant 3-OT-JPMADA 2-3 NUCLEAR TRAINING REVISION/USAGE LOG Rev. # Description of Changes Date Pages Affected Reviewed By 0 Initial issue, generated for NRC Initial All D. Hughes License Exam

Rev 0 PAGE 3 0F35 Watts Bar Nuclear Plant 3-OT-JPMADA 2-3 Task: Hand Calculation of RCS Inventory Balance.

Alternate Path: None Facility JPM #: 3-OT-JPMADA 2-3 Rev 0 K/A Rating(s):

2.2.12 Knowledge of surveillance procedures. I (IMPORTANCE RO 3.7 SRO 4.1)

TASK STANDARDS: Correctly perform Hand Calculation of RCS Inventory Balance Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

1-SI-68-32 Rev 0012 TI-4 Part II Rev 0012 Task Number: RO-068-SI-68-32-001, APPLICABLE FOR: RO/SRO 10CFR55.45: 1 1 Validation Time: 35 mm. Time Critical: No Candidate: Time Start:

NAME SSN/EIN Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner:

NAME SIGNATURE DATE COMMENTS

RevO PAGE 4 0F35 Watts Bar Nuclear Plant 3-OT-JPMADA 2-3 SIMULATOR OPERATOR INSTRUCTIONS:

none Tools/Equipment/Procedures Needed:

Marked up copy of of latest revision of 1 -Sl-68-32 (see next page for data to put in 1 -Sl-68-32)

Copy of Tl-4 Part II.

Steam Tables Calculator Access to controlled copies of plant procedures READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The unit is in Mode 1 at 100% power.

The Plant Computer program RCSWIB is unreliable.

1 -Sl-68-32 Appendix A has been completed through step 4 (2nd Data Set has been taken)

You are an extra operator.

INITIATING CUES:

Due to a suspected problem with RCSWIB, the Unit SRO has directed you to perform a manual calculation of RCS inventory balance.

Report the results of the surveillance to the Unit SRO.

SRO Candidates comply with all applicable Tech Specs.

RevO PAGE 5 0F35 Watts Bar Nuclear Plant 3-OT-JPMADA 2-3 Mark-Up instructions for 1-SI-68-32

1. Starting in section 4.1 initial/N/A steps as required. Fill in the following data at step 6:

[6] RECORD the most recent Steam Generator Leakage obtained from Chemistry in the appropriate column below, and CALCULATE Total SG Leakage (in gpm) as follows: = 0 gpd

2. Continue to initial steps and/or fill in Handswitch/valve postions for all steps in sections 4.2, 4.3, and 6.0 (up to step 6.18). Ensure steps 6.5 thru 6.18 are marked N/A, since Appendix A will be performed.

3. Appendix A initial steps 1 thru 4.

4. Appendix B fill in the following data,( N/A all remaining data points):

Parameter Panel Initial Data Set 2nd Data Set Time N/A 0800 0912 VCT LEVEL LOl 1 2A 31.5% 29.2%

PRESSURIZER P0480A 2235.3 psig 2235.3 psig PRESSURE PRESSURIZER L0482A 60.24% 59.55%

LEVEL RCS T0460A 586.3°F 586.3°F TEMPERATURE REACTOR 1-NI-41 100% 100%

POWER PRT LEVEL L0485A 72.6% 72.6%

RCDT LEVEL 1 LI-77-1 23% 23%

0-PNL-276-L2 DATA SET N/A Initials Initials RECORDED BY

PAGE 6 0F35 3-OT-JPMADA 2-3 START TIME:

EXAMINERS CUE: Provide a marked up copy of 1 -SI-68-32 to candidate.

(The candidates may round their calculations and not exactly match the calculations provided in this JPM. This is allowed)

STEP 1.

CALCULATE RCS leakage per Appendix C. 4 SAT STANDARD: UNSAT Performer turns to 1 -Sl-68-32 Appendix C COMMENTS:

PAGE 7 0F35 3-OT-JPMADA 2-3 STEP 3 Critical Step

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

AT = FINAL TIME INITIAL TIME AT= - .SAT AT = mm UNSAT STANDARD: Performer determines that AT is 72 minutes COMMENTS:

STEP 4:

[2] CONVERT INITIAL and FINAL PZR PRESSURE units of measure to psia as follows:

SAT PARAMETER NITAL FtNAL PZR = psig + 14.7 = psig + 14.7 PRESS

=psia =psia UNSAT STANDARD Performer correctly calculates Initial PZR Pressure and final PZR Pressure to be 2250 psia COMMENTS:

PAGE 8 0F35 3-OT-JPMADA 2-3 3] CALCULATE VCT Leakage as follows: Critical Step STEP 5:

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

AT (Step [1])

VCT Leakage = ( 31.5% 29.2 %) x 19.27 gaII%

- SAT 72 mm STANDARD: Performer performs the following calculation: UNSAT VCT Leakage = O61 557 gpm (Candidate may round the number)

COMMENTS:

PAGE 9 0F35 3-OT-JPMADA 2-3 STEP 6: Critical Step

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

[a] RECORD INITIAL and FINAL PZR PRESSURE in tablebelow using values calculated in Step [2].

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

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

STEP PARAM INITIAL FINAL

[a] PZR PRESS psia psia

[b] PZRLEVEL PZR V /lbm 3

ft flbm 3

ft

[C]

PZR Vg /Ibm 3

ft /lbm 3

ft STANDARD: Performer determines that:

PZR Vf is between 0.026 ft 3 /Ibm and 0.027 ft3 /Ibm (calculated value 0.02698 ft 3 /Ibm)

PZR Vg is between 0.156 ft 3 /Ibm and 0.158 ft3 /lbm (calculated value 0.157025 ft 3 /lbm)

(Candidate may round these numbers)

COMMENTS:

PAGE 10 0F35 3-OT-JPMADA 2-3 STEP 7* Critical Step

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

(Continued)

[d] CALCULATE INITIAL PZR VOLUME as follows:

INITIAL = (PZR LVL + 100- PZR LVL) x 16.73 ft3/% x 7.4805 gal/ft3 x 0.01 605 ft3/lbm ..__SAT PZR Vf Vg VOLUME INITIAL = ( 60.24 + 100-60.24 ) x 2 gal ft3/% Ibm UNSAT PZR Vf Vg VOLUME STANDARD: Performer performs the following calculation and determines that:

Initial Pzr Volume is 4971.946 gal (Candidate may round the number)

COMMENTS:

PAGE 11 0F35 3-OT-JPMADA 2-3 Critical Step STEP 8

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

(Continued)

[e] CALCULATE INITIAL PZR VOLUME as follows:

FINAL = (PZR LVL + 100- PZR LVL) x 16.73 ft3/% x 7.4805 gal/ft3 x 0.01 605 ft3/lbm __SAT Vf Vg VOLUME FINAL = (59.55 + 100-59.55 ) x 2 gal ft31% Ibm __UNSAT PZR Vf Vg VOLUME STANDARD: Performer performs the following calculation and determines that:

Initial Pzr Volume is 4929.5856 gal (Candidate may round the number)

COMMENTS:

PAGE 12 0F35 3-OT-JPMADA 23 STEP 9 Critical Step

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

(Continued)

[F] CALCULATE PZR Leakage as follows:

SAT (Step [dl) (Step [e])

PZR Leakage = INITIAL - FINAL PZR VOLUME PZR VOLUME AT(Step [1])

PZR Leakage aal __UNSAT

= - gal mm PZR Leakage = gpm STANDARD: 4971.946198 gal - 4929.5856 gal /72 mm Performer determines that the PZR Leakage is 0.588 gpm:

(Candidate may have rounded earlier numbers that may have slightly affected this number)

COMMENTS:

STEP 10: [5] IF RCS TEMP FINAL is NOT equal to RCS TEMP INITIAL 4

THEN SAT STANDARD: Performer determines from data that RCS Temperature did not change therefore step 5 is N/A UNSAT COMMENTS:

PAGE 13 0F35 3-OT-JPMADA 2-3 STEP 11: Critical Step

[6] CALCULATE Total RCS Leakage as follows:

(Step [3]) (Step [4]) (Step [5] or 0)

Total RCS Leakage = VCT Leakage + PZR Leakage + Temp Corr Total RCS Leakage = gpm + gpm + gpm __SAT Total RCS Leakage = gpm UNSAT STANDARD: Performer performs the following calculation:

0.6155 gpm + 0.588 gpm + 0 gpm = 1.2035 gpm (Candidate may have rounded earlier numbers that may have slightly affected this number)

COMMENTS:

PAGE 14 0F35 3-OT-JPMADA 2-3 STEP 12: [7] CALCULATE Leakage to Pressurizer Relief Tank (PRT) as follows:

[a] CONVERT INITIAL and FINAL PRT LEVEL from percent (%) to gallons using TI-4,Part II, and SAT RECORD the converted PRT LEVELS in Step [b].

[b] CALCULATE Leakage to PRT using the following equation:

UNSAT Leakage = FINAL PRT LVL INITIAL PRT LVL To PRT AT (Step [1])

Leakage=( al- aFl ToPRT _min Leakage = gpm To PRT STANDARD: Performer determines that since the PRT level did not change the Leakage to the PRT is 0 gpm.

COMMENTS:

PAGE 15 0F35 3-OT-JPMADA 2-3 STEP 13:

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

[a] CONVERT INITIAL and FINAL RCDT LEVEL from percent (%) to gallons using TI-4, Part II, and SAT RECORD the converted RCDT LEVELS in Step [b].

[b] CALCULATE Leakage to RCDT using the following equation:

Leakage = FINAL RCDT LVL INITIAL RCDT LVL UNSAT To RCDT AT (Step [11)

Leakage = ( gal - gal)

To RCDT mm Leakage = gpm To RCDT STANDARD: Performer determines that since the RCDT Ieve did not change the Leakage to the RCDT is 0 gpm.

COMMENTS:

PAGE 16 0F35 3-OT-JPMADA 2-3 STEP 14: Critical Step

[9] CALCULATE Identified Leakage as follows:

(Section 4.1 (Step [7)) (Step [81) Step [6))

Identified = Leakage + Leakage + Total SG SAT Leakage To PRT to RCDT Leakage Identified = gpm + gpm + gpm Leakage UNSAT Identified = gpm (Acc Crit: 10 gpm)

STANDARD: Performer determines that Identified Leakage is 0 gpm.

COMMENTS:

PAGE 17 0F35 3-OT-JPMADA 2-3 STEP 15: Critical Step

[10] CALCULATE Unidentified Leakage as follows:

(Step [6]) (Step [9])

Unidentified = Total RCS Leakage Identified Leakage Leakage

__SAT Unidentified = gpm - gpm Leakage Unidentified = gpm (Acc Crit: I gpm) __UNSAT STANDARD: Performer performs the following calculation:

1.2035 gpm + 0 gpm = 01.2035 gpm SROs identify that this leakage does not meet Tech Spec requirement of less than 1 gpm unidentified and should direct entry into Tech Spec 3.4.13, Condition A, reduce RCS Leakage to within limits in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

COMMENTS:

PAGE 18 0F35 3-OT-JPMADA 2-3 STEP 16:

ENSURE independently verified.

SAT STANDARD: Performer reports that the task is completed and that the unidentified leakage exceeds the acceptance criteria (Tech Spec limit) and gives the calculation to the SRO for independent verification. UNSAT COMMENTS:

Examiner Acknowledge report and cue: notify the performer that the task is complete.

End task TIME STOP:

Candidate Handout Sheet WBN I PLANT CURVE BOOK, TANK I TI-4, PART II 0 I CURVES, TURBINE CURVES I Revision 12 I Page 32 of 45 APPENDIX 26 Pace I of 1 PRESSURIZER RELIEF TANK 13,107 gailon capacity at 100%

1:

ffl I

+/-EHHHH 80

- I zJf::

:::::: ::::: 4::: ::: :::

)cwlva4 aiarm,

-J LU wo

-Jo 50 -H I C

z 30 ::.::.: :H:

20 :: H 10 z:.::::i::: ::::::.:::::: 4::::::i:*:::

0 3i5g*ns 1I1[1illHHLHW 0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 VOLUME- GALLONS x 1000 NOTE: Hi/Lo levels alarm at 1-XA-55-5A-888. Any revisions to this curve will require a software change request per PAt-I .05 to incorporate the changes into ERFDS computer program RCSWIB.

C:FLWPRtPF VsUngtxuse Oraing 1098E08 Contract 54114 1106U

Candidate Handout Sheet WBN I PLANT CURVE BOOK, TANK I TI -4, PART II 0 I CURVES, TURBINE CURVES I Revision 12 I I Page 34 cf 45 APPENDIX 28 Page 1 cf 1 REACTOR COOLANT DRAIN TANK 341 gaflon capacity at 100%

100

.1 hi-hi I azm, 8%

80 pmpuorI.64%

-J 60 Lu I

pu,pA ut,,atar, O%

j 40 C) z 20 i IUtQpUrTp1UI-ff

/4___.bIw.4a,m.11%

18%

{

0 0 100 200 300 400 VOLUME IN GALLONS NOTE: HI-Hi and Lo-Lo levels alarm at panel O-L-2. Any revisions to this curve will require a software change request per PAl-I .05 to incorporate the changes into ERFDS computer program RCSWIB.

C:FLRCDT.PRE WesUnghouse Orawhig 11 02E08 Contract 54114 1 iC 6tJ

Candidate Handout Sheet WBN REACTOR COOLANT SYSTEM 1.-SI-68-32 1 WATER INVENTORY BALANCE Revision 12 Page 20 of 33 Data Package: Page of Date Today APPENDIX A Page 1 of 2 MANUAL PERFORMANCE OF RCS WATER INVENTORY BALANCE

[1] OBTAIN controlled copy of TI-4, Part II pages that show graphs of volume vs. indicated level for Pressurizer Relief Tank (PRT) and Reactor Coolant Drain Tank (RCDT).

[2] RECORD initial RCS data per Appendix 8. TRO

[3] WAIT at least one hour (optimum is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ). TRO

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

[5] CALCULATE RCS leakage per Appendix C. 4 NOTE Additional copies of Appendix C may be used to perform independent verification.

[6] PERFORM independent verification of Appendix C.

Independent

[7] IF unidentified leakage is less than 0 gpm (negative leakage) THEN 3

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

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

[c] CALCULATE RCS leakage per Appendix C. 4

[d] PERFORM independent verification of Appendix C.

Candidate Handout Sheet WBN REACTOR COOLANT SYSTEM 1-SI-68-32 1 WATER INVENTORY BALANCE Revision 12 Page 21 of33 Data Package: Page of Date Today APPENDIX A Page 2 of 2 MANUAL PERFORMANCE OF RCS WATER INVENTORY BALANCE

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

. THEN (Continued) 3

[e] REPEAT Steps [a] through [e] UNTIL one of the follong conditions exist:

A. Unidentified leakage rate is more positive than -0.10 gpm.

B. Total RCS leakage is less than or equal to 1.Ogpm.

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

[f] IF SI is aborted per Step [e] C, THEN NOTIFY SM/Unit SRO and /or cognizant System Engineer that an investigation to determine the source of inleakage to the RCS must be 3

initiated.

[8] GO TO Section 6.0, Step [19].

Candidate Handout Sheet WBN REACTOR COOLANT SYSTEM 1-SI-68-32 1 WATER INVENTORY BALANCE Revision 12 Page 22 of 33 Data Package: Page of Date Today APPENDIX B Page 1 of 3 RCS WATER INVENTORY BALANCE DATA SHEET NOTE I Time for each data set is the time of day when the first instrument is read. Recording each data set as quickly as possible will ensure an accurate relationship between parameters. Additional copies of Appendix A may be used as required.

NOTE 2 Only one instrument should be used for each parameter and the same instrument must be used for each data set. Instruments not used should be marked N/A for each data set.

PARAMETER INSTRUMENT [PANEL] INITIAL 2nd 3rd 4th 5th DATA SET DATA SET DATA SET DATA SET DATA SET TIME N/A 0800 0912 LOI12A 31.5%

VCT LEVEL 29.2%

1-LI-62-129A

[1-M-6]

N/A N/A 1-PI-68-342A psig PRESSURIZER

< 1700 psi N/A N/A PRESSURE 1-PI-68-340A

[1 -M-5J N/A psig N/A P0480A psig 3

2235 2235.3 1-PR-68-340 psig

[1 -M-5]

N/A N/A P0481A N/A psig N/A 1-PI-68-322 psig

[1-M-5] N/A N/A P0483A N/A psig N/A

Candidate Handout Sheet WBN REACTOR COOLANT SYSTEM 1-SI-68-32 1 WATER INVENTORY BALANCE Revision 12 Page 23 of 33 Data Package: Page of Date Todpy APPENDIX B Page 2 of 3 RCS WATER INVENTORY BALANCE DATA SHEET PARAMETER NSTRUMENT [PANEL] NITIAL 2nd 3rd 4th 5th DATA SET DATASET DATA SET DATA SET DATA SET TME N/A 0800 0912 PRESS URIZER 1 -LI-68-321 LEVEL <35OF N/A °° N/A 1-LI-68-320 °°

[1-M-4] N/A N/A L0482A 60.24 % 59.55 1-L-68-335A

[1 -M-4]

N/A ° N/A L0481A N/A % N/A 1-LI-68-339A

[1M-4]

N/A °° N/A L0480A N/A % N/A

Candidate Handout Sheet WBN REACTOR COOLANT SYSTEM 1-SI-68-32 1 WATER INVENTORY BALANCE Revision 12 Page 24 of 33 Data Package: Page of Date Today APPENDIX B Page 3of3 RCS WATER INVENTORY BALANCE DATA SHEET PARAMETER INSTRUMENT [PANEL] INITIAL 2nd 3rd 4th 5th DATA SET DATA SET DATA SET DATA SET DATA SET N/A F RCS TEMPERATURE 1-TI-68-2E

[1-M-5]

N/A T0438A N/A 0F N/A T < 5300F OL O 0 TO4BOA ..OV..) OF JOO.3 T0440A N/A OF N/A T0420A N/A r N/A TO400A N/A OF N/A REACTOR 1-NI-41 100.0 % 100.0 %

POWER [1-M-4]

1-NI-42 N/A N/A 1-M-43 N/A N/A 1-NI-44 N/A N/A PRT LEVEL 1-U-68-300 N/A °° N/A

[1-M-4]

L0485A 72.6 72.6 %

RCDT LEVEL 1-U-77-I 23 °° 23 %

D-PNL-276-L2 DATA SET RECORDED BY Jftc, TOTAL RCS LEAKAGE N/A (Appendix C Step [6])

IDENTIFIED LEAKAGE N/A (Acc Cut: 10 gpm)

(Appendix C Step f9fl UNIDENTIFIED LEAKAGE N/A (Aec Crit: I çjpm)

(Appendix C Step [10]

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN REACTOR COOLANT SYSTEM 1-SI-68-32 1 WATER INVENTORY BALANCE Revision 12 Page 25 ofS3 Data Package: Page of Date Today APPENDIX C Page 1 of 8 RCS WATER INVENTORY BALANCE CALCULATIONS NOTE Throughout this Appendix, INITIAL indicates the data is to be taken from first data set recorded in Appendix B and FINAL indicates data is to be taken from the last data set recorded in Appendix B. A copy of this Appendix is required to be completed each time RCS leakage is calculated.

[1] CALCULATE elapsed time (ST) as follows:

= FINAL TIME INITIAL TIME T=O912- 0800 Candidates AT = 72 mm Initials 2nd Party

[2] CONVERT INITIAL and FINAL PZR PRESSURE units of measure to psia as follows:

PARAMETER INITIAL FINAL PZR =22353psig ÷ 14.7 3psig 2

= + 14.7 PRESS

=2250ps1a =225Opsia Candidates Initials 2nd Party

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN REACTOR COOLANT SYSTEM 1-SI-68-32 1 WATER INVENTORY BALANCE Revision 12 Page 26 of 33 Data Package: Page of Date Today APPENDIX C Page 2 of 8

[3] CALCULATE VCT Leakage as follows:

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

\T (Step [1])

VCT Leakage = (31.5% .29.2%) x 19.27 çaI/%

72 mm Candidates VCT Leakage = 0.6155 gpm Initials 2nd Party

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

[a] RECORD INITIAL and FINAL PZR PRESSURE in table Candidates Initials below using values calculated in Step [2].

[b] RECORD INITIAL and FINAL PZR LEVEL in table Candidates Initials below using values recorded in Appendix B.

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

STEP PARAM INITIAL FINAL

[a] PZR PRESS 22Qpsia 225sia

[b] PZR LEVEL 64% 595)/

PZR Vf °/lbm /lbrn 8

°

[c]

PZR V 1 °tlbm ?tRbm 0 Candidates Initials 5- @ 2200 psia Vf = 0.02669 0

4- 2300 psia Vf = 0.02727 I

0>

Caic value @ 2250 = (0.02727 - 0.02669)/2 + 0.02669 = 0.02698 c

00 r .4-

@ 2200 psia V 2300 psia V 9 = 0.16272 9 0.15133 CaIc value @ 2250 = (0.16272 - 0.15133)/a + 0.15133 = 0.157025

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN REACTOR COOLANT SYSTEM 1-51-68-32 1 WATER INVENTORY BALANCE Revision 12 Page 27 of 33 Data Package: Page of Date Today APPENDIX C Page 3 of 8

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

[d] CALCULATE INITIAL PZR VOLUME as follows: 5 INITIAL = (PZR LVL + 100- PZR LVL) x 16.73 3 ft

/ % x 7.4805 3 gal/ft x 0.01605 ft Jlbm 3

PZR V Vg VOLUME INITIAL ( 60.24% + 100 -6O.24/) x 2 gal ft 3 1% Ibm PZR 0.157O5 002698 VOLUME ft-/Ibm ft /ibm Candidates INITIAL al 4971

=

9

4 PZR VOLUME 2nd Party

[e] CALCULATE FINAL PZR VOLUME as follows: 5 FINAL (PZR LVL ÷ 100 PZR LVL) x 16.73 ft

- /% x 7.4805 gal/ft 3 3 x 0.01605 ft /Ibm 3

PZR Vf V 9

VOLUME FINAL = ( 59.55% ÷ 100 -59.55%)x2 gal ft

/% ibm 3

PZR o.o269 0.157025 VOLUME ft/Ibm ft/ibm 4929.5856 Candidates FINAL = gal Initials PZR VOLUME 2nd Party If the Candidate uses 16.75 ft3/% x 7.4805 gal/ft x 0.01605 ft3/Ibm then the calculation will be times 2.08637678 versus x 2 (as it is rounded to in the second calculation line). This will change their numbers to:

Initial Volume 4993.419 Final Volume: 4950.877 Pzr leakage (next page): 0.5908 These numbers will then carry forward in their calculations.

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN REACTOR COOLANT SYSTEM 1-SI-68-32 1 WATER iNVENTORY BALANCE Revision 12 Pace 28 of 33 Data Package: Page of Date Today APPENDIX C Page 4 of 8

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

[f] CALCULATE PZR Leakage as follows:

(Step [d]) (Step [e])

PZR Leakage = INITIAL - FINAL PZR VOLUME PZR VOLUME T(Step [1])

4971.946 4929.5856 PZR Leakage = al - çjal 72 mm Candidates PZR Leakage = 0.588 gpm Initials 2nd Party

[5] IF RCS TEMP FINAL is NOT equal to RCS TEMP INITIAL ,

4 THEN Candidates

[a] RECORD INITIAL and FINAL PZR PRESSURE in table Initials below using values calculated in Step [2j.

Candid:tes

[b] RECORD INITIAL and FINAL RCS TEMPERATURE in table below using values recorded in Appendix B.

[c] DETERMINE and RECORD INITIAL and FINAL RCS SPECIFIC VOLUME in table below using PZR PRESSURE, RCS TEMPERATURE and ASME Steam Tables Ccidtes (Table 3, Properties of Superheated Steam and Compressed Water).

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN REACTOR COOLANT SYSTEM 1-SI-68--32 1 WATER INVENTORY BALANCE Revision 12 Page 29 of 33 Data Package: Page of Date Today APPENDIX C Page 5 of 8

[5] IF RCS TEMP FINAL is NOT equal to RCS TEMP INITIAL ,

4 THEN (Continued)

[d] CALCULATE INIT1AL and FINAL RCS DENSITY as follows, and RECORD in table below:

RCSDENSITY= 1 RCS SPECIFIC VOLUME STEP PARAM INITIAL FINAL

[a] PZR psia psia PRESS

[b] RCS °F TEMP

[c] RCS SPECIFIC /lbm 3

ft VOLUME

[d] RCS DENSITY = 3 Ibm/ft = 3 Ibm/ft N/A 2nd Party

[e] CALCULATE RCS Temperature Correction as follows:

Temp Corr = INITIAL FINAL RCS DENSITY RCS DENSITY x 10902 3 ft x 7.4805 gal/ft 3 x 0.01605 ft

/Ibm 3

T (Step [1])

Temp Corr = ( 3 Ibm/ft - 3 x 1308.92 gal ft lbm/ft /Ibm 3

miii Candidates Initials Temp Corr = gpm 2nd Party Q

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN REACTOR COOLANT SYSTEM 1-SI--68-32 1 WATER INVENTORY BALANCE Revision 12 Page 30 of 33 Data Package: Page of Date Today APPENDIX C Page 6 of 8

[6] CALCULATE Total RCS Leakage as follows:

(Step [3]) (Step [4]) (Step [5] or 0)

Total RCS Leakage = VCT Leakage + PZR Leakage + Temp Corr 0.6155 0.588 Total RCS Leakage = gpm + gpm + 0 gpm Candidates Total RCS Leakage = 1.2035 gpm Initials 2nd Party

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

[a] CONVERT INITIAL and FINAL PRT LEVEL from percent (%) to gallons using TI-4,Part II, and Candidates Initials RECORD the converted PRT LEVELS in Step [b].

[b] CALCULATE Leakage to PRT using the following equation:

Leakage = FINAL PRT LVL INITIAL PRT LVL To PRT T (Step [1])

72.6 72.6 Leakage = ( al - aI)

T0PRT 72mm Candidates Leakage =

gprn Initials To PRT 2nd Party

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN REACTOR COOLANT SYSTEM 1-SI-68-32 1 WATER LNVENTORY BALANCE Revision 12 Page 31 of33 Data Package: Page of Date Today APPENDIX C Page 7 of 8

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

[a] CONVERT INITIAL and FINAL RCDT LEVEL from percent (%) to gallons using TI-4. Part II, and iithd:es 1

ca RECORD the converted RCDT LEVELS in Step [b].

[b] CALCULATE Leakage to RCDT using the following equation:

Leakage = FINAL RCDT LVL INITIAL RCDT LVL -

To RCDT xT (Step [1])

Leakage = ( 23 cial 23 gal) -

To RCDT 72 mm Leakage = 0 gpm Candidates To RCDT Initials 2nd Party

[9] CALCULATE Identified Leakage as follows:

(Section 4.1 (Step [71) (Step [8]) Step [6])

Identified = Leakage + Leakage + Total SO Leakage To PRT to RCDT Leakage Identified = 0 gpm + 0 gpm + 0 gpm Leakage Candidates Identified = 0 gpm (Acc Crit: jo gprn) Initials 2nd Party

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN REACTOR COOLANT SYSTEM 1-SI-68-32 1 WATER DTVENTORY BALANCE Revision 12 Page 32 of33 Data Package: Page of Date Today APPENDIX C Page 8 of 8

[10] CALCULATE Unidentified Leakage as follows:

(Step [6]) (Step [9])

Unidentified = Total ROS Leakage Identified Leakage Leakage Unidentified =_

gpm 3

° 2 5 - 0 gpm Leakage Candidates 1 2035 Unidentified = gpm (Acc Crit: I gpm) Initials 2nd Party

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

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN REACTOR COOLANT SYSTEM 1-SI-68-32 1 WATER iNVENTORY BALANCE Revision 12 Page 24 of 33 Data Package Page of Date APPENDIX B Page 3 of 3 RCS WATER INVENTORY BALANCE DATA SHEET PARAMETER INSTRUMENT [PANEL] INITIAL 2nd 3rd 4th 5th DATA SET DATA SET DATA SET DATA SET DATA SET RCS 1-TI-68-2E j A F TEMPERATURE [1-M-5 INI T0439A N/A F

< 530F T0460A 586.3 F T0440A N/A F T0420A N/A F TO400A F N/A REACTOR 1-NI-41 POWER [1-M-4] if 1-NI-42 N/A %

1-NI-43 N/A %

1-NI-44 N/A %

PRT LEVEL 1-LI-68-300 °°

[I-M-4] N/A L0485A 72.6 %

RCDT LEVEL 1-LI-77-1 0-PNL-276-L2 23 DATA SET RECORDED BY IRO TOTAL RCS LEAKAGE N/A (Appendix C Step [6])

1 2035 IDENTIFIED LEAKAGE N/A (Ace Crit: 10 gpm)

(Appendix C Step [9]) 0 UNIDENTIFIED LEAKAGE N/A (Ace Crit: I gpm) 1 .2035 (Appendix C Step [10)

CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The unit is in Mode 1 at 100% power.

The Plant Computer program RCSWIB is unreliable.

1 -SI-68-32 Appendix A has been completed through step 4 (2nd Data Set has been taken)

You are an extra operator.

INITIATING CUES:

Due to a suspected problem with RCSWIB, the Unit SRO has directed you to perform a manual calculation of RCS inventory balance.

Report the results of the surveillance to the Unit SRO.

SRO Candidates comply with all applicable Tech Specs.

Rev.1 PageloflO WATTS BAR NUCLEAR PLANT 3-OT-J PMADA.3-1 TASK TITLE: DETERMINE IF PERSONNEL WILL EXCEED ADMINISTRATIVE DOSE LIMITS WHILE PERFORMING TASK

Rev.1 Page2oflO WATTS BAR NUCLEAR PLANT 3-OT-J PMADA.3-1 NUCLEAR TRAINING REVISION/USAGE LOG Rev # Date Description of changes Pages Affected Reviewed By 0 Initial Issue, NRC JPM exam question. All H.J. Voiles Does not need to be word processed.

1 03/04/08 Added the option for another route to the All D.L.Hughes task area. Corrected K/A references to comply with revision 2 supplement 1 of NUREG 1122

Rev. 1 3-OT-JPMADA.3-1 Page3of 10 REGION II INITIAL LICENSE EXAMINATION ADMINISTRATIVE JOB PERFORMANCE MEASURE Task: DETERMINE IF PERSONNEL WILL EXCEED ADMINISTRATIVE DOSE LIMITS WHILE PERFORMING TASK Alternate Path: N/A Facility JPM #: 3-OT-JPMADA3-1 K/A Rating(s): 2.3.7 [3.5/3.6]

Task Standard: Ability to comply with radiation work permit requirements during normal or abnormal conditions.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant Perform X Simulate

References:

SPP 5.1 Rev 0006 Radiological Controls Task Number:: AUO-119-SSP-5.01-001 APLICABLE FOR: AUO/RO/SRO 10CFR55.45: 1 0 IIr4tiiri Time: 15 min Time Critical: No Applicant: Time Start:

NAME SSN Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS

- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Rev. 1 3-OT-JPMADA.3-1 Page4of 10 Tools/Equipment/Procedures Needed:

Calculator NOTE TO EVALUATOR: Hand out the Applicants Data Sheet along with the Applicants Cue Sheet.

READ TO OPERATOR DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the administrative task to be performed. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The unit has experienced a valid safety injection signal.

The unit has also experienced a loss of both Unit 1 shutdown boards.

RCP Seal Injection and thermal barrier cooling have been isolated per ECA-0.0 Appendix A.

Shutdown Board lA-A has been re-energized and the US directs you to dispatch AUO5 locally to start the 1A TBBP and throttle open the discharge valve.

A survey map is available for elevation 737 of the auxiliary building, showing dose rates and travel times to reach the TBBP Discharge valve that they will throttle open.

Three NAUOs are available for assignment to perform this task. All 3 NAUOs have a current NRC FORM-4 documenting current year and previous years exposures.

RADPROT personnel are currently unavailable to provide assistance.

NAUC #1 has TEDE of 631 mRem

NAUO #2 has TEDE of 603 mRem

NAUQ #3 has TEDE of 613 mRem INITIATING CUES:

1. Calculate the Total Dose for the job.

2. Calculate the amount of dose for each AUO.

3. Indicate which AUOs can perform the task without exceeding NORMAL administrative limits.

(EPIP-15, Emergency Exposure Guidelines are not to be considered.)

- Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Rev. 1 3-OT-JPMADA.3-1 Page5of 10 START TIME:

NOTE TO EVALUATOR: The following steps may be performed out of order.

STEP 1: Calculate Exposure during pump start and throttle valve Critical Task operation.

SAT STANDARD: (1.2 R/hr).(l000mR/R).(1HR/6OMin).(10 Mm) = 200 MR EVALUATOR QUE: If the operator locates the current revision of SPP 5.1 UNSAT Radiological Controls, a copy may be given to him/her.

COMMENTS:

STEP 2: Calculate the exposure getting to task area and return.

STANDARD: Dose received for 2 way travel for survey area B: SAT (2.7 R/hr).(l000mR/R).(1HR/6OMin).(4 Mm) = 180 mRem Dose received for 2 way travel for survey area C: UNSAT (4.0 R/hr)(l000mR/R).(1HR/6OMin).(3 Mm) = 200 mRem Determines that Route B is the route to take.

COMMENTS:

- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

Rev. 1 3-OT-JPMADA.3-1 Page6of 10 STEP 3: Calculate total dose for job.

Critical Task STANDARD: Dose received for 2 way travel (in and out of area) for survey area B is added to dose received in Survey Area A: SAT

1) Two way Survey Area B = 180 mRem

2) Dose in Survey Area A = 200 mRem

3) Total Dose = 200 MR + 180 MR = 380 mRem UNSAT COMMENTS:

STEP 5: Determine total dose that would be received for all NAUO.s involved.

SAT STANDARD: Performer Determines dose that would be received by NAUOs.

1) NAUO#1: 631 mrem+380mrem= 1011 mRem

2) NAUO #2: 603 mrem + 380 mrem = 983 mRem UNSAT

3) NAUO #3: 613 mrem + 380 mrem = 993 mRem COMMENTS:

STEP 5: Determines which NAUO can perform tasks without exceeding Critical Task Administrative limits.

STANDARD: Performer determines NAUOs #2 and #3 are the only NAUOs SAT that could perform task.

COMMENTS:

UNSAT END OF TASK TIME STOP:

- ltalicized Cues Are To Be Used Only If JPM Performance Is Being Simulated.

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The unit has experienced a valid safety injection signal.

The unit has also experienced a loss of both Unit 1 shutdown boards.

RCP Seal Injection and thermal barrier cooling have been isolated per ECA-O.0 Appendix A.

Shutdown Board lA-A has been re-energized and the US directs you to dispatch AUOs locally to start the 1A TBBP and throttle open the discharge valve.

A survey map is available for elevation 737 of the auxiliary building, showing dose rates and travel times to reach the TBBP Discharge valve that they will throttle open.

Three NAUOs are available for assignment to perform this task. All 3 NAUOs have a current NRC FORM-4 documenting current year and previous years exposures.

RADPRQT personnel. are currently unavailable to provide assistance.

NAUC #1 has TEDE of 631 mRem

NAUO #2 has TEDE of 603 mRem

NAUO #3 has TEDE of 613 mRem INITIATING CUES:

1. Calculate the Total Dose for the job.

2. Calculate the amount of dose for each AUO.

3. Indicate which AUOs can perform the task without exceeding NORMAL administrative limits.

(EPIP-15, Emergency Exposure Guidelines are not to be considered.)

APPLICANT DATA SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

SURVEY DATA:

TBBP control switches and pump discharge FCV are located in Survey area A.

> Estimated time at control switch and discharge valve is 10 minutes.

> ONE-way travel time to Valve & control switches via route B is 2 minutes.

> ONE-way travel time to Valve & control switches via route C is 1 minute 30 seconds.

> General Area Dose rate for Survey Area A is 1 .2 RIhr.

> General Area Dose rate for Survey Area B is 2.7 RIhr.

General Area Dose rate for Survey Area C is 4.0 R!hr.

NAUO #1 has TEDE of 631 mRem

NAUO #2 has TEDE of 603 mRem

NAUO #3 has TEDE of 613 mRem RESULTS:

1. Total dose for the job:

2. Accumulative TEDE for each AUC, if job is performed:

NAUO1

NAUO2

NAUO3

3. Indicate below by checking yes or no if the respective NAUO can be allowed to perform task without exceeding administrative dose limits.

YES NO NAUO #1 NAUO #2 NAUO #3

APPLICANT DATA SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

AUXILIARY BLDG ELEV. 737 G/A

1. U/2 Heating & Ventilation Room

2. U12 Vent & Purge Air Room

3. U12 Gross Failed Fuel Detector Room

4. Spent Fuel Pool Equipment Area

5. U/l Letdown Heat Exchanger Room

6. U12 Letdown Heat Exchanger Room

7. U/I Gross Failed Fuel Detector Room

8. U/l Vent & Purge Air Room

9. U/l Heating & Ventilation Room

10. Hot Instrument Shop

11. Component Cooling Heat Exchangers

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

RESULTS:

1. Total dose for the job: 380 mR

2. Dose for each AUO:

AUO1 lOllmR

AUO2 983mR

AUO3 993mR

3. Indicate below by checking yes or no if the respective NAUO can be allowed to perform task without exceeding administrative dose limits.

YES NO NAUO#1 x NAUO#2 x NAUO#3 x

REV. 0 PAGE 1 0F16 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO81 b TASK TITLE: CLASSIFY THE EVENT PER THE REP (LOCA WITH SIGNIFICANT FUEL FAILURE AND POTENTIAL LOSS OF CONTAINMENT)

REV. 0 PAGE 2 0F16 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO81 b NUCLEAR TRAINING REVISION/USAGE LOG REV # Date Description of Changes Pages Affected Reviewed By 0 03/05/08 Initial issue, generated for NRC Initial License ALL D.LHughes Exam

REV. 0 PAGE 3 0F16 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO81 b EVALUATION SHEET Task: Classify The Event Per The REP (LOCA WITH SIGNIFICANT FUEL FAILURE AND POTENTIAL LOSS OF CONTAINMENT)

Alternate Path: N/A Facility JPM #: 3-OT-JPMSOB1b K/A Rating(s): 2.4.29 Knowledge of the emergency plan. IMPORTANCE RO 3.1 SRO 4.4 Task Standard: The event is classified as an GENERAL EMERGENCY based on Loss Of Any Two Barriers And A Potential Loss Of Third Barrier Notifications are made per EPIP-5.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate This JPM will be simulated.

References:

EPIP-1 Emergency Plan Classification Flowpath, Rev. 27; EPIP-5 GENERAL EMERGENCY, Rev. 34 Task Number: SRO-113-EPIP-OO1 APPLICABLE FOR: SRO 10CFR55.45: 10, 11, 12 Validation Time: 20 mm. Time Critical: Yes Applicant: Time Start:

NAME SSN/EIN Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner:

NAME SIGNATURE DATE COMMENTS

REV. 0 PAGE 4 0F16 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO81 b EVALUATOR INFORMATION SHEET TASK TITLE: CLASSIFY THE EVENT PER THE REP (LOCA WITH SIGNIFICANT FUEL FAILURE AND POTENTIAL LOSS OF CONTAINMENT)

SIMULATOR SETUP INSTRUCTIONS:

NONE: THIS JPM IS SIMULATED and the simulator will not be used to reflect the conditions.

REQUIRED MATERIALS:

EPIP-1 and EPIP-5 SAFETY CONSIDERATIONS:

None ToolslEguipmentlProcedures Needed:

Ensure clean copy of EPIP-1, EPIP-5, Emergency Instructions, and Status Trees are available for the Candidate.

Print out Met Tower Cue Sheets on following 3 pages. The Met Tower cue sheets are to be given to the performer when they are obtaining information from the Integrated Computer System (lOS).

4 N

Lus MtIUAIA IAVG 350 360/0 10 340 20 WIND DIR & SPEED 330 30 320 40 MET46A1S 310 50 MI/HR 60 MET46D1S 290 70 DEGREES (FROM) 280 80 W27o goE 260 100 250 110 240 120 230 130 220 140 210 10

A

REV. 0 PAGE 8 0F16 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO81 b Ensure clean copy of EPIP-1 and EPIP-5 in all copies of Emergency Instructions on the Simulator Floor and in the file drawer of Unit Supervisors desk.

READ TO OPERATOR DIRECTION TO TRAINEE:

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

THE CURRENT SIMULATOR CONDITIONS ARE NOT REPRESENTATIVE OF THIS JPM.

INITIAL CONDITIONS:

- Unit 1 was at 100% RTP when a LOCA occurred.

- An SI occurred due to high containment pressure.

- RCS pressure stabilized at 350 psig saturated conditions.

- The CLAs are injecting.

- The ONLY ECCS pump in service is the 1 B-B RHR pump, all other ECCS pumps tripped shortly after the SI and cannot be restarted.

- Containment pressure is 1 .8 psig and stable.

- 1 -RM-90-273 & 1 -RM-90-274 have risen to 35 rem/hr.

- 1 -RM-90-271 & 1 -RM-90-272 have risen to 60 rem/hr.

- Containment Hydrogen concentration is 6% as indicated on the H2 analyzers.

- RCS Subcooling reads 0 °F.

- Incore Thermal Couples read 750 °F.

- RVLIS indicates 20%.

- The Ring Down Phone is inoperable.

- You are the SM/SRO INITIATING CUES:

The Unit Supervisor has informed you of the above conditions.

You are to make the initial classification of the event per the REP EPIPs and make required notifications.

Portions of this JPM are time critical.

REV. 0 PAGE 9 0F16 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO81 b START TIME:

STEP 1: Refers to EPIP-1 to determine level of event. CRITICAL STEP STANDARD: Performer refers to EPIP-1 and declares a GENERAL EMERGENCY based on Loss Of Any Two Barriers And A Potential Loss Of Third Barrier (1 .1.1 Loss, 1.22 Loss, & SAT 1.3.2 Potential Loss) This must be completed within 15 minutes of task assignment.

This step is critical to ensure proper activation of TVA UNSAT resources for event in progress.

COMMENTS: RECORD time that declaration was made:________

STEP 2: Implements EPIP-5, GENERAL EMERGENCY SAT STANDARD: EPIP-5, GENERAL EMERGENCY, is implemented.

COMMENTS: UNSAT

REV. 0 PAGE 10 0F16 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO81 b STEP 3: [1] IF the onsite emergency centers are not staffed, THEN DIRECT Shift Personnel to activate the Emergency Paging System (EPS) to staff the Technical Support Center (TSC) SAT and Operations Support Center (050). Shift Personnel should confirm activation and provide the 20 minute printed report to the SM for review.

A IF the EPS system fails, call the ODS, ringdown or (5- UNSAT 751-1700) and DIRECT him to activate the EPS.

B IF the above methods of activating the EPS fail, THEN DIRECT Shift Personnel to use the Watts Bar Nuclear Plant Emergency Response Call-List to staff the TSC and OSC. (This list is located in the EPS Manual near the terminal.)

STANDARD: The SRO activates the emergency paging system (EPS) to staff the TSC and Operations Support Center (OSC) or EPS is activated in the control room.

This step is critical if performed on the simulator to ensure proper activation of TVA resources for event in progress.

If the JPM is NOT performed on the simulator then:

- CUE: Another SRO has just activated the Emergency Paging System.

COMMENTS:

REV. 0 PAGE 11 0F16 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO81 b STEP 4: [2] IF the TSC has not been activated, THEN

a. INITIATE Appendix A and B, Initial Notification FORM CRITICAL for GENERAL EMERGENCY and Protective Action STEP Recommendations.

STANDARD: Appendix A is accurately completed with SAT

1. This isa Drill

2. Their name, Shift Manager (SED) at WBN Plant.

General Emergency declared on UNIT 1

3. EAL Designators: [lii Loss and 1.2.2 Loss, and UNSAT 1.3.2 Potential LOSS]

4. Brief description of incident: [Core Cooling Red, RCS LOCA with a Loss of Subcooled Margin, and High Hydrogen concentration in Containment] (or something similar)

5. Radiological Conditions [Either Release information not known or Minor releases within federally approval limits]

6. Event Declared: [Time and Date]

7. Wind direction at 46 meters, coming from [73] degrees AND wind speed at 46 meters [4.8] mph.

Evaluator Cue (1): The Met Tower cue sheets are to be given to the performer when they are obtaining information from the Integrated Computer System (ICS).

Evaluator Cue (2): If Asked if there are any short term releases are in progress then respond Short Term Release data is unknown.

NOTE TO EVALUATOR: Items 2, 3, 6, and 7 above are the critical parts.

Items 2 & 3 are critical due to correct EALs must be used for General Emergency declaration.

Item 6 is critical and it must be within 15 minutes of the performer stating that they understand their task and the JPM is started.

Item 71s critical to ensure proper protective actions are recommended (PARs).

COMMENTS:

REV. 0 PAGE 12 0F16 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO81 b STEP 5: Critical Step Appendix B:

SAT STANDARD: Operator determines from page 15, logic chart in EPIP-5, that appropriate protective action recommendation is RECOMMENDATION 2. This should be identified on the notification form in the next JPM step.

UNSAT COMMENTS STEP 6: Critical Step Appendix A completion:

SAT STANDARD: Appendix A is accurately completed with:

Item 8:

UNSAT Recommendation 2 is checked 69-110 A-i, B-i, C-i, D-i, X A-3, D-2, -4, -5 is checked (Both blocks should be checked)

COMMENTS

REV. 0 PAGE 13 0F16 WATTS BAR NUCLEAR PLANT 3-OT-JPMSO81 b STEP 7: [2.b] NOTIFY the ODS direct by ODS Ring-down or by CRITICAL USING 5-751-1 700 or 5-751-2495 and STEP

1) PROVIDE the information from Appendix A.

2) FAX Appendix A to the ODS. (# pre-programmed or 5- SAT 751-8620).

STANDARD: The ODS is notified and Drovided the information on Arpendix A. This notification must be made within 10 UNSAT minutes of event declaration. Appendix A is placed in the fax machine and transmission simulated.

EVALUATOR NOTE: DO NOT allow actual call to actual ODS.

If this JPM is performed on the simulator, then ensure the call is made to simulator operator.

The ring down phone is not functioning per the task conditions so the Candidate should simulate using any phone and calling 5-751 -1 700 (or 2495).

- CUE: Role play as the ODS and repeat back the report.

- CUE: Do NOT allow fax to be actually transmitted.

COMMENTS: RECORD time that ODS was notified:________

EVALUATOR CUE: Once the performer informs the ODS, then inform them that another SRO will continue on from here and inform the performer that the task is complete.

End of task TIME STOP:

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN GENERAL EMERGENCY EPIP-i APPENDIX A (Page 1 of 1)

WA INITIAL NOTIFCATION FORM FOR GENERAL EMERGENCY

1. This is a Drill fl This is an Actual Event - Repeat This is an Actual Event

2. This is Candidates name Watts Bar has declared a GENERAL EMERGENCY affecting Unit 1

3. EALDesignator(s):l.l.l.L, 1.2.2.L & 1.3.2.P

[All Applicable EAL(s)]

4. Brief Description of the Event:COre Cooling Red, RCS LOCA with a Loss of Subcooled Margin, and High Hydrogen concentration in Containment.

(Or something similar in effect to relate the above conditions.)

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

Airborne Releases Offsite Liguid Releases Offsite XMinor releases within federally approved limits,, Minor releases within federally approved limits 1

or Releases above federally approved limitsor Releases above federally approved limits Release information not known Release information not known Tech Specs) ( Tech Specs)

6. Event Declared: Time: Time of declaration Date: Todays bate

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

Wind Direction is FROM: 73 degrees Wind Speed: 4.8 m.p.h

8. Provide Protective Action Recommendation: (Check either 1. 2 or 3, and mark wind direction.)

Recommendation I R WIND FROM

° F Recommendation 2 EVACUATE LISTED SECTORS (Mark) EVACUATE LISTED SECTORS (2 mile Radius and 10 miles downwind)

E E (2 mile radius and 5 mile downwind)

E.SHELTER all other non-listed sectors.

C C SHELTER all other non-listed sectors.

CONSlDER issuance of Potassium Iodide in CONSlDER issuance of Potassium accordance with the State Plan. Iodide in accordance with the State Plan.

A-I. B-i, C-i, D-i, 26-68 A-i, B-i, C-i, D-i, C-7,-9,D-2,-4,-5,-6,-7,-8,-9 C-7,D-2,-4,-5 A-i, B-i, C-i, D-i,69-110 A-i, B-i. C-i, D-i, A-3,-4,D-2,-3,-4,-5,-6,-7,-8,-9 A-3,D-2.-4.-5 A-i.B-i,C-i,D-i. 111-170 A-i,B-i,C-i,D-i, A-2, -3, -4, -5, -6, -7, D-2, -3, -5, -6 A-2, -3, D-2, -5 A-i, B-i, C-i, D-i, 171-230 A-i,B-i,C-i,D-i.

A-2, -3, -5, -6, .7, B-2, -3, -4, -5. C-2 A-2, -3, 8-2. -4, C-2 A-i, B-i, C-i, D-i, 231-270 A-i, B-i, C-i, D-i.

B-2. -3. -4. -5. C-2, -3. B-2, -4, C-2 A-i,B-i,C-i,D-i, 271-325 A-1,B-i,C-i,D-i, B-2, -3, C-2, -3. -4. -5. -6, -ii B-2, C-2. -4, -5, A-i, B-i, C-i, D-i, 326-25 A-i, B-i, C-i, D-i, C-2, -4, -5, -6, -7. -8, -9, -10, -ii, D-4, -9 C-2, -4. -5, -7. -8, D-4 Recommendation 3

=SHELTER all sectors. =CONSlDER issuance of Potassium Iodide in accordance with the State Plan.

9. Please repeat the information you have received to ensure accuracy.

10. Time and Date this information was provided. Time: Date_______________

Action: When notification complete, FAX form as prescribed in this instruction. *Revision PAGE 14 of 18 REVISION 35

Comparison Sheet for NRC Evaluator (Do NOT give this sheet to the Candidate!)

WBN GENERALEMERGENCY EPIP-5 APPENDIX B (Page 1 of 1)

PROTECTIVE ACTION RECOMMENDATIONS Note 1: If conditions are unknown utilizing the flowchart, then answer is NO.

Note 2: A short term release is defined as a release that does not exceed a 15 minute duration.

GENERAL EMERGENCY DECLARED CONTINUE ASSESSMENT

Modify protective actions based on available plant and field monitoring information.

Locate and evaluate localized hot spots.

Is there a short term controlled N

,/ release whereas near K plant areas cannot be N evacuated before N plume arrival?

Note 2)

RECOMMENDATION 3 SHELTER 10 mile EPZ N 1 N RECOMMENDATION I RECOMMENDATION 2 EVACUATE 2 miles radius EVACUATE 2 miles radius and 10 miles downwind and 5 miles downwind AND AND SHELTER remainder of SHELTER remainder of 10 mile EPZ 10 mile EPZ

.1 TABLE I Protective Action Guides (PAG)

TYPE LIMIT Note: Measured 3.9 E-6 micro Cl/cc of Iodine 131 or The candidate may 1 REM per hour External Dose or may not have Projected 1 REM TEDE or written on this 5 REM Thyroid CDE appendix, but they should still PAGE 15 of 18 REVISION 35 ascertain recommendation 2 is applicable.

REV. 0 PAGE 16 0F16 PERFORMER HANDOUT SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

THE CURRENT SIMULATOR CONDITIONS ARE NOT REPRESENTATIVE OF THIS JPM.

INITIAL CONDITIONS:

- Unit 1 was at 100% RTP when a LOCA occurred.

- An SI occurred due to high containment pressure.

- RCS pressure stabilized at 350 psig saturated conditions.

- The CLAs are injecting.

- The ONLY ECCS pump in service is the 1 B-B RHR pump, all other ECCS pumps tripped shortly after the SI and cannot be restarted.

- Containment pressure is 1.8 psig and stable.

- 1-RM-90-273 & 1-RM-90-274 have risen to 35 rem/hr.

- 1-RM-90-271 & 1-RM-90-272 have risen to 60 rem/hr.

- Containment Hydrogen concentration is 6% as indicated on the H2 analyzers.

- RCS Subcooling reads 0 °F.

- Incore Thermal Couples read 750 °F.

- RVLIS indicates 20%.

- The Ring Down Phone is inoperable.

- YouaretheSM/SRO INITIATING CUES:

The Unit Supervisor has informed you of the above conditions.

You are to make the initial classification of the event per the REP EPIPs and make required notifications.

Portions of this JPM are time critical.

ML102371238

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