Text

Initial Exam 2013-301 Final Administrative JPMs
	ML13156A104
Person / Time
Site:	Turkey Point
Issue date:	06/05/2013
From:	; NRC/RGN-II
To:	; Florida Power & Light Co
References
	Download: ML13156A104 (112)
	v • d • e

Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Ala RO 2013 Admin - JPM Ala RO (REV_021 813) NUREG 1021, Revision 9

Appendix C Page 2 of 10 Form ES-C-i Job Performance Measure Worksheet Facility: Turkey Point Task No.:

Task

Title:

Calculate QPTR JPM No.: 2013 Admin JPM Al a RD K/A

Reference:

GKIA 2.1.7 (4.4)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), the Data Sheet (2 to last Page of this JPM).

Initial Conditions:

Unit 3 is operating at 100% power.

Excore detector currents for all in service power range nuclear instrumentation channels are as shown on the Data Sheet.

Initiating Cue:

The US has directed you to perform Section 4.2 of 3-OSP-059.10, Determination of Quadrant Power Tilt Ratio.

The SM has given approval to perform this procedure.

List all Technical Specifications that are required to be entered and all procedure sections required to be performed.

Task Standard: The operator will calculate QPTR to be greater than 1.02 per 3-DSP-059.10. The operator will identify that Technical Specification LCD 3.2.4 is NDT being complied with, and that Section 4.3 of 3-OSP-059.i0 must be performed.

Required Materials: Calculator General

References:

3-OSP-059. 10, Quadrant Power Tilt Ratio, (Rev OB) 2013 Admin JPM Al a RD NUREG 1021, Revision 9

Appendix C Page 3 of 10 Form ES-C-i Job Performance Measure Worksheet U3 Plant Curve Book Section 5 Fig 5 Turkey Point Plant Unit 3 and 4 Technical Specifications Handouts: None (Ensure all General References are available)

Time Critical Task: NO Validation Time: 20 minutes 2013 Admin JPM Ala RO

- NUREG 1021, Revision 9

Appendix C Page 4 of 10 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with a checkmark fVJ)

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), the Data Sheet (2 to last Page of this JPM).

START TIME:

RECORD on Attachment 1, Determination of NIS QPTR Using Excore STEP I : Detector Currents, the top and bottom detector current for all in service SAT Power Range Nuclear Instrumentation channels (meter face).

U N SAT The operator records the following information from the Data Sheet onto Attachment 1 Step 2:

N41 Top Current = 214.6 microamps N42 Top Current = 178.5 microamps N43 Top Current = 202.2 microamps Standard: N44 Top Current = 215.7 microamps N41 Bottom Current = 193.2 microamps N42 Bottom Current = 193.0 microamps N43 Bottom Current = 177.3 microamps N44 Bottom Current = 199.7 microamps EXAMINER NOTE 2013 Admin JPM Ala RO

- NUREG 1021, Revision 9

Appendix C Page 5 of 10 Form ES-C-i PERFORMANCE INFORMATION NOTE Plant Curve Book Section 5 Figure 5, contains the Power Range currents for 100% power values.

RECORD the 100% power current values on Attachment 1 for each in STEP 2 : service Power Range Nuclear Instrumentation detector. SAT V

UNSAT The operator obtains Plant Curve Book Section 5 Figure 5.

The operator records the following information from the Data Sheet onto Attachment 1 Step 2:

N4i 100% Top Current = 218.5 microamps N42 100% Top Current = 175.9 microamps Standard: N43 100% Top Current = 200.0 microamps N44 100% Top Current = 216.3 microamps N41 100% Bottom Current = 194.1 microamps N42 100% Bottom Current = 186.1 microamps N43 100% Bottom Current = 175.2 microamps N44 100% Bottom Current = 198.9 microamps EXAMINER NOTE COMPLETE calculations on Attachment 1.

STEP 3 SAT V

UNSAT Standard The operator completes the calculations on Attachment 1 in accordance with the Attached Key.

EXAMINER NOTE 2013 Admin JPM Al a RO NUREG 1021, Revision 9

Appendix C Page 6 of 10 Form ES-C-i PERFORMANCE INFORMATION COMPARE results of Attachment 1 to Acceptance Criteria below.

STEP 4 SAT NIS QPTR is less than or equal to 1.02 (2.0%)

UNSAT The operator compares the highest NIS QPTR determined on Attachment 1 (1 .025) with the Acceptance Criteria of 1.02 and Standard: determines that the Acceptance Criteria has NOT been met.

EXAMINER NOTE IF QPTR is greater than 1 .02 (2.0%) OR Attachment 1 yields suspect STEP 5 : QPTR results, THEN PERFORM Section 4.3. SAT 7

UNSAT The operator identifies evaluates Technical Specification LCO 3.2.4 Quadrant Power Tilt Ratio, and identifies that this LCO is NOT met, Standard: and that Section 4.3 of 3-OSP-059.iO must be performed.

EXAMINER NOTE Stop Time 20i3Admin-JPM Ala RO NUREG 1021, Revision 9

Appendix C Page 7 of 10 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No: 2013 Admin JPM Ala RO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2013 Admin JPM Ala RO

- NUREG 1021, Revision 9

Appendix C Page 8 of 10 Form ES-C-i VERIFICATION OF COMPLETION KEY:

Upper Section Normalized Detector Currents N41 Top Current = 214.6 micro amps = 0.982 100% Top Current 218.5 micro amps N42 Top Current = 178.5 micro amps = 1.015 100% Top Current 175.9 micro amps N43 Top Current = 202.2 micro amps = 1.011 100% Top Current 200.0 micro amps N44 Top Current = 215.7 micro amps = 0.997 100% Top Current 216.3 micro amps Upper Section Normalized Current Total = 4.005 Lower 3ection Normalized Detector Currents N41 Bottom Current = 193.2 micro amps 0.995 100% Bottom Current 194.1 micro amps N42 Bottom Current = 193.0 micro mn 1.037 100% Bottom Current 186.1 micro amps N43 Bottom Current = 177.3 micro amns = 1 .012 100% Bottom Current 175.2 micro amps N44 Bottom Current = 199.7 micro amps 1.004 100% Bottom Current 198.9 micro amps Lower Section Normalized Current Total = 4.048 Average Uer Section Normalized Power Upper Section Normalized Current Total = 4.005 = 1.001 Upper Detectors Used (3 or 4) 4 Average Lower Section Normalized Power Lower Section Normalized Current Total = 4.048 = 1.012 Lower Detectors Used (3 or 4) 4 Upper Section Tilt Ratio Largest Upper Section Normalized Detector Current = 1.015 1.014 Average Upper Section Normalized Power 1.001 Lower Section Tilt Ratio Largest Lower Section Normalized Detector Current = 1.037 = 1.025 Average Lower Section Normalized Power 1.012 NIS QPTR = highest Section QPTR = 1.025 (UNSAT) 2013 Admin JPM Ala RO

- NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM CUE SHEET Data Sheet:

Excore detector currents for all in service power range nuclear instrumentation channels are as follows:

N-41 Top: 214.6 micro-amps N-41 Bottom: 193.2 micro-amps N-42 Top: 178.5 micro-amps N-42 Bottom: 193.0 micro-amps N-43 Top: 202.2 micro-amps N-43 Bottom: 177.3 micro-amps N-44 Top: 215.7 micro-amps N-44 Bottom: 199.7 micro-amps RO NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:

Unit 3 is operating at 100% power.

Excore detector currents for all in service power range nuclear instrumentation channels are as shown on the Data Sheet.

INITIATING CUE:

The US has directed you to perform Section 4.2 of 3-OSP-059.10, Determination of Quadrant Power Tilt Ratio.

The SM has given approval to perform this procedure.

List all Technical Specifications that are required to be entered and all procedure sections required to be performed.

Acknowledge to the examiner when you are ready to begin.

RO NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Ala SRO 2013 Admin - JPM Ala SRO (REV_021813) NUREG 1021, Revision 9

Appendix C Page 2 of 1 1 Form ES-C-i Job Performance Measure Worksheet Facility: Turkey Point Task No.:

Task

Title:

Calculate QPTR JPM No.: 2013 Admin JPM Ala SRO K/A

Reference:

GKIA 2.1.7 (4.7)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial ConditionsiCue (Last Page of this JPM), the Data Sheet (2 to last Page of this JPM).

Initial Conditions:

Unit 3 is operating at 100% power.

Excore detector currents for all in service power range nuclear instrumentation channels are as shown on the Data Sheet.

Initiating Cue:

The US has directed you to perform Section 4.2 of 3-OSP-059.10, Determination of Quadrant Power Tilt Ratio.

The SM has given approval to perform this procedure.

List all Technical Specifications that are required to be entered, any ACTION that is required and all procedure sections required to be performed.

Task Standard: The operator will calculate QPTR to be greater than 1.02 per 3-DSP-059.10. The operator will identify that Technical Specification LCO 3.2.4 is NOT being complied with, that ACTION statements a.i-4 are applicable, and that Section 4.3 of 3-OSP-059.i0 must be performed.

Required Materials: Calculator 2013 Admin JPM Ala SRO

- NUREG 1021, Revision 9

Appendix C Page 3 of I 1 Form ES-C-i Job Performance Measure Worksheet General

References:

3-OSP-059.1O, Quadrant Power Tilt Ratio, (Rev OB)

U3 Plant Curve Book Section 5 Fig 5 Turkey Point Plant Unit 3 and 4 Technical Specifications Handouts: None (Ensure all General References are available)

Time Critical Task: NO Validation Time: 25 minutes 2013 Admin JPM Ala SRO

- NUREG 1021, Revision 9

Appendix C Page 4 of 1 1 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with a checkmark fVJ)

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), the Data Sheet (2 to last Page of this JPM).

START TIME:

RECORD on Attachment 1, Determination of NIS QPTR Using Excore STEP I : Detector Currents, the top and bottom detector current for all in service SAT

,,, Power Range Nuclear Instrumentation channels (meter face).

UNSAT The operator records the following information from the Data Sheet onto Attachment 1 Step 2:

N41 Top Current = 214.6 microamps N42 Top Current = 178.5 microamps N43 Top Current 202.2 microamps Standard: N44 Top Current = 215.7 microamps N41 Bottom Current = 193.2 microamps N42 Bottom Current = 193.0 microamps N43 Bottom Current = 177.3 microamps N44 Bottom Current 199.7 microamps EXAMINER NOTE 2013 Admin - JPM Al a SRO NUREG 1021, Revision 9

Appendix C Page 5 of 1 1 Form ES-C-i PERFORMANCE INFORMATION NOTE* Plant Curve Book Section 5 Figure 5, contains the Power Range currents for 100% power values.

RECORD the 100% power current values on Attachment 1 for each in STEP 2 : service Power Range Nuclear Instrumentation detector. SAT v/

UNSAT The operator obtains Plant Curve Book Section 5 Figure 5.

The operator records the following information from the Data Sheet onto Attachment 1 Step 2:

N41 100% Top Current 218.5 microamps N42 100% Top Current = 175.9 microamps Standard: N43 100% Top Current 200.0 microamps N44 100% Top Current = 216.3 microamps N41 100% Bottom Current = 194.1 microamps N42 100% Bottom Current = 186.1 microamps N43 100% Bottom Current = 175.2 microamps N44 100% Bottom Current = 198.9 microamps EXAMINER NOTE COMPLETE calculations on Attachment 1.

STEP 3 : SAT V

UNSAT Standard The operator completes the calculations on Attachment 1 in accordance with the Attached Key.

EXAMINER NOTE 2Ol3Admin-JPMA1aSRO NUREG 1021, Revision 9

Appendix C Page 6 of 1 1 Form ES-C-i PERFORMANCE INFORMATION COMPARE results of Attachment 1 to Acceptance Criteria below.

STEP 4 : SAT

,- NIS QPTR is less than or equal to 1.02 (2.0%)

UNSAT The operator compares the highest NIS QPTR determined on Attachment 1 (1.025) with the Acceptance Criteria of 1.02 and Standard: determines that the Acceptance Criteria has NOT been met.

EXAMINER NOTE 2013 Admin JPM Ala SRO NUREG 1021, Revision 9

Appendix C Page 7 of 1 1 Form ES-C-i PERFORMANCE INFORMATION IF QPTR is greater than 1.02 (2.0%) OR Attachment I yields suspect STEP 5 : QPTR results, THEN PERFORM Section 4.3. SAT v/

UNSAT The operator identifies evaluates Technical Specification LCO 3.2.4 Quadrant Power Tilt Ratio, and identifies that this LCO is NOT met, and that Section 4.3 of 3-OSP-059.10 must be performed.

The operator determines that Technical Specification ACTION statement a.1, a.2, a.3 and a.4 are applicable:

ACTION a: With the QUADRANT POWER TILT RATIO determined to exceed 1 .02 but less than or equal to 1 .09:

1. Calculate the QUADRANT POWER TILT RATIO at least once per hour until either: a) The QUADRANT POWER TILT RATIO is reduced to within its limit, or b) THERMAL POWER is reduced to less than 50%

of RATED THERMAL POWER.

2. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either: a) Reduce the QUADRANT POWER TILT RATIO to within its limit, or b) Reduce THERMAL POWER at least 3%

from RATED THERMAL POWER for each 1% of indicated Standard: QUADRANT POWER TILT RATIO in excess of I (i.e. 94% power) and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3. Verify that the QUADRANT POWER TILT RATIO is within its limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and

4. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified acceptable at 95% or greater RATED THERMAL POWER.

EXAMINER NOTE Terminating Cue: STOP Stop Time 2013 Admin JPM Ala SRO NUREG 1021, Revision 9

Appendix C Page 8 of 1 1 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 Admin - JPM Ala SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

20i 3 Admin - JPM Al a SRO NUREG 1021, Revision 9

Appendix C Page 9 of 1 1 Form ES-C-i VERIFICATION OF COMPLETION KEY:

Upper Section Normalized Detector Currents N41 Top Current = 214.6 micro amps = 0.982 100% Top Current 218.5 micro amps N42 Top Current = 178.5 micro amps = 1.015 100% Top Current 175.9 micro amps N43TopCurrent 202.2microamps = 1.011 100% Top Current 200.0 micro amps N44 Top Current = 215.7 micro amps = 0.997 100% Top Current 216.3 micro amps Upper Section Normalized Current Total = 4.005 Lower 3ection Normalized Detector C irrents N41 Bottom Current = 193.2 micro amps 0.995 100% Bottom Current 194.1 micro amps N42 Bottom Current = 193.0 micro amos 1.037 100% Bottom Current 186.1 micro amps N43 Bottom Current = 177.3 micro amns = 1.012 100% Bottom Current 175.2 micro amps N44 Bottom Current = 199.7 micro amps 1.004 100% Bottom Current 198.9 micro amps Lower Section Normalized Current Total = 4.048 Average Uooer Section Normalized Power Unoer Section Normalized Current Total = 4.005 = 1.001 Upper Detectors Used (3 or 4) 4 Average Lower Section Normalized Power Lower Section Normalized Current Total = 4.048 = 1.012 Lower Detectors Used (3 or 4) 4 Upper Section Tilt Ratio Largest Upper Section Normalized Detector Current = 1.015 = 1.014 Average Upper Section Normalized Power 1.001 Lower Section Tilt Ratio Largest Lower Section Normalized Detector Current = 1.037 = 1.025 Average Lower Section Normalized Power 1.012 NIS QPTR = highest Section QPTR = 1.025 (UNSAT) 2013 Admin JPM Ala SRO

- NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM CUE SHEET Data Sheet:

Excore detector currents for all in service power range nuclear instrumentation channels are as follows:

N-41 Top: 214.6 micro-amps N-41 Bottom: 193.2 micro-amps N-42 Top: 178.5 micro-amps N-42 Bottom: 193.0 micro-amps N-43 Top: 202.2 micro-amps N-43 Bottom: 177.3 micro-amps N-44 Top: 215.7 micro-amps N-44 Bottom: 199.7 micro-amps SRO NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:

Unit 3 is operating at 100% power.

Excore detector currents for all in service power range nuclear instrumentation channels are as shown on the Data Sheet.

INITIATING CUE:

The US has directed you to perform Section 4.2 of 3-OSP-059.10, Determination of Quadrant Power Tilt Ratio.

The SM has given approval to perform this procedure.

List all Technical Specifications that are required to be entered, any ACTION that is required and all procedure sections required to be performed.

Acknowledge to the examiner when you are ready to begin.

SRO NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Aib RO 2013 Admin JPM Aib RO (REV_021813)

NUREG 1021, Revision 9

Appendix C Page 2 of 18 Form ES-C-i Job Performance Measure Worksheet Facility: Turkey Point Task No.: 0i02800410i/040C Task

Title:

Verify AdeQuate Shutdown Margin JPM No.: 2013 Admin JPM Al b RO KJA

Reference:

GKIA2.l.37 (4.3)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and the two handouts listed.

Initial Conditions:

The current time is 0800

At 0700 today, Unit 3 reactor tripped from 100% power.

Two rods fail to insert on the trip and remain fully withdrawn.

RCS Tave is being maintained at 547 °F by the atmospheric steam dumps, and it is expected to be maintained at this temperature until 0400 tomorrow.

Current Unit 3 burnup is 1000 MWD/MTU

Unit 3 Boron Concentration was 1208 ppm at 0500.

No boron additions or dilutions occurred between the sample and the trip.

Initiating Cue:

The SM has directed you to verify adequate SHUTDOWN MARGIN exists per 0-OSP-028.8, Shutdown Margin Calculation, for maintaining Unit 3 at Hot Standby 547°F until 0400 tomorrow, assuming a Xenon-Free condition.

IF it is determined that adequate SHUTDOWN MARGIN does NOT exist, determine the amount of boric acid that must be added to ensure adequate shutdown margin exists.

2013 Admin JPM Aib RO NUREG 1021, Revision 9

Appendix C Page 3 of 18 Form ES-C-i Job Performance Measure Worksheet Task Standard: The operator will determine the RCS boron concentration for the projected plant conditions, and compare this to the existing RCS boron concentration, and conclude that adequate SHUTDOWN MARGIN does NOT exist, and then calculate that 3325-3394 gallons of boric acid must be added to the RCS.

Required Materials: Calculator General

References:

Unit 3 Plant Curve Book,Section III 0-OSP-028.8, Shutdown Margin Calculation, (Rev 1)

Handouts: 0-OSP-028.8, Shutdown Margin Calculation (Blank Copy)

Unit 3 Plant Curve Book Time Critical Task: NO Validation Time: 40 minutes 2013 Admin JPM Al b RO NUREG 1021, Revision 9

Appendix C Page 4 of 18 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with a checkmark f/J)

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and the two handouts listed.

START TIME:

Obtain the procedural guidance.

STEP I : SAT U N SAT The operator recognizes that the plant is in Mode 3.

Standard: The operator reviews the Purpose, the Scope, the Precautions and Limitation, the Prerequisites, and the instructions and determines that Attachment 2 should be used.

EXAMINER NOTE (Attachment 2, Steps 1-3)

STEP 2 : SAT RECORD unit number:

RECORD cycle number: UNSAT RECORD shutdown date and time:

The operator records 3 in the Unit Number Block.

Standard: The operator records 26 in the Cycle Number Block.

The operator records Todays Date and 0700 in the Date and Time Block.

EXAMINER NOTE 2013 Admin JPM Al b RO NUREG 1021, Revision 9

Appendix C Page 5 of 18 Form ES-C-i PERFORMANCE INFORMATION The Cycle Burnup value in the PCB, Section 5, Figure 4 is periodically updated by Reactor Engineering. Although the actual burnup can be approximately determined to account for core burnup since the last update, recording the most recent value from PCB Section 5, Figure 4 Note in Attachment 2 Step 4 will produce conservative results. To approximately determine the actual burnup, increase the burnup by adding 32 MWD/MTU for each day of full power operation (or fraction thereof, e.g., add 8 MWD/MTU for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months at full power or 16 MWD/MTU for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at 50% power, etc., ) since the date and time of the last update.

(Attachment 2, Step 4)

STEP 3 SAT Cycle burnup (Plant Curve Book (P08), Section 5, Figure 4):

UNSAT The operator records 1000 in the MWD/MTU Block.

Standard:

EXAMINER NOTE The information was provided on turnover sheet.

NoteS The CALCULATION POINT is the point in time at which the Shutdown Margin is to be calculated. It is NOT necessarily the present time.

(Attachment 2, Step 5.A)

STEP 4 : SAT RECORD the following calculation point conditions:

UNSAT Calculation point:

Standard The operator records Tomorrows Date and 0400 in the Date and Time Block.

EXAMINER NOTE 2013 Admin - JPM Aib RO NUREG 1021, Revision 9

Appendix C Page 6 of 18 Form ES-C-i PERFORMANCE INFORMATION (Attachment 2, Step 5.B)

STEP 5 : SAT Time since shutdown:

UNSAT Standard: The operator records 21 in the Time Since Shutdown Block.

EXAMINER NOTE The measured RCS boron concentration entered below should be from the most recent sample. Primary Nuclear Chemistry can be Note contacted or the Chemistry Department (P1) database can be accessed to obtain the latest RCS boron concentration, and the date and time of the sample (Attachment 2, Step 5.C)

STEP 6 : SAT Most recent RCS boron concentration:

UNSAT The operator records 1208 in the PPM Block.

Standard: The operator records Todays Date in the Sample Date Block.

The operator records 0500 in the Sample Time Block.

EXAMINER NOTE 2013 Admin JPM Aib RO

- NUREG 1021, Revision 9

Appendix C Page 7 of 18 Form ES-C-i PERFORMANCE INFORMATION (Attachment 2, Step 5.D)

STEP 7 SAT Average RCS Temperature at Date/Time in Attachment 2 Step 5.A:

UNSAT Standard: The operator records 547 in the °F Block.

EXAMINER NOTE (Attachment 2, Step 5.E)

STEP 8 SAT MODE:

UNSAT Standard: The operator places a V in the Mode 3 Hot Standby Block.

EXAMINER NOTE (Attachment 2, Step 5.F)

STEP 9 : SAT RECORD number of Control Rods that are NOT fully inserted:

UNSAT Standard: The operator records 2 in the Block provided.

EXAMINER NOTE 2013 Admin JPM Al b RO

- NUREG 1021, Revision 9

Appendix C Page 8 of 18 Form ES-C-i PERFORMANCE INFORMATION The Minimum Shutdown Boron Concentration (MSBC) calculated in Attachment 2 Step 6 is a function of RCS Temperature and Burnup.

There are three methods available to determine MSBC as follows:

A very conservative reactivity determination of MSBC may be made without interpolation by using the applicable PCB Section 3, Figure 5A and choosing the burnup statepoint/curve and the RCS temperature statepoint/curve that are less than or equal to the burnup in Attachment 2 Step 4 and temperature in Attachment 2 Step 5.D, respectively. However, using this method, the result may be a higher value than what is desired for the actual plant condition.

Note:

A conservative reactivity determination of MSBC may be made by a single interpolation of burnup using the applicable PCB Section 3, Figure 5A and choosing the temperature statepoint/curve that is less than or equal to the temperature in Attachment 2 Step 5.D.

This is the preferred and recommended method.

Accepting the built-in conservatism in unit/cycle specific data, an accurate reactivity determination of MSBC may be made by a double interpolation of burnup and average RCS temperature using the applicable PCB Section 3, Figure 5A. Using this method, the result is the lowest acceptable value achievable, which may be desired for the actual plant condition.

(Attachment 2, Steps 6 and 6.A)

STEP 10 : SAT DETERMINE the Minimum Shutdown Boron Concentration:

UNSAT A. RECORD minimum average RCS temperature that will be assumed in the calculation and will bound the actual temperature in Attachment 2 Step 5.D and expected changes in plant conditions, based on Operations input, over the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Assumed Minimum Average RCS Temperature:

Standard: The operator records 547 in the °F Block.

EXAMINER NOTE 2013 Admin JPM Al b RO

- NUREG 1021, Revision 9

Appendix C Page 9 of 18 Form ES-C-i PERFORMANCE INFORMATION To preclude a non-conservative reactivity determination of Minimum Shutdown Boron Concentration, the temperature statepoint/curve used in Attachment 2 Step 6.B must be less than or equal to the actual Caution: average RCS Temperature recorded in Attachment 2 Step 5.D or the lowest average RCS temperature expected by Operations due to potential changes in plant conditions during the ensuing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , as applicable.

(Attachment 2, Step 6.B)

STEP 11 : SAT RECORD the RCS temperature and burnup value that will be used to calculate the Minimum Shutdown Boron Concentration: UNSAT RCS Temperature Bu mu p The operator records 547 in the °F Block.

Standard:

The operator records 1000 in the MWD/MTU Block.

EXAMINER NOTE In Attachment 2 Step 6.C below, Plant Curve Book Section 3, Figure 5A already includes the reactivity effects of the minimum, Hot Full Note: Power, steady state Samarium concentration. Figure 5A conservatively does NOT take credit for the additional build-up of Samarium_that_occurs_after_Unit_shutdown.

(Attachment 2, Step 6.0)

STEP 12 : SAT Using the burnup and temperature from Attachment 2 Step 6.B, AND the applicable P08 Section 3, Figure 5A (Minimum Shutdown Boron UNSAT vs. RCS Temperature as a function of Burnup), RECORD the Minimum Shutdown Boron Concentration:

The operator uses Figure 5A (15 Mar 2012) and determines the Standard: intersection of 1000 MWD/MTU and 547°F to be 1316 PPM.

The_operator_records_1316_in_the_PPM_Block.

EXAMINER NOTE 2013 Admin - JPM Aib RO NUREG 1021, Revision 9

Appendix C Page 10 of 18 Form ES-C-i PERFORMANCE INFORMATION (Attachment 2, Step 6.D)

STEP 13 : SAT IF the following are NOT true:

UNSAT

Temperature in Attachment 2 Step 6.B is less than or equal to the temperature selected in Attachment 2 Step 6.A.

The burnup in Attachment 2 Step 6.B is less than or equal to burnup from Attachment 2 Step 4.

IF used, THEN interpolation calculation results are correct.

THEN RETURN to Attachment 2 Step 6.A.

The operator recognizes that all are TRUE.

Standard:

The operator initials the Performed BY Block.

EXAMINER NOTE 2013 Admin - JPM Al b RO NUREG 1021, Revision 9

Appendix C Page 11 of 18 Form ES-C-i PERFORMANCE INFORMATION The amount of negative reactivity in the core post trip due to Xenon varies with core burnup, the initial power level, power changes pre-trip, and time since trip. The Xenon concentration in the core peaks at 6 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months post trip, decays to approximately the value prior to the downpower/trip condition at 13 to 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months post trip, and fully decays to essentially zero pcm at 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months post trip.

There are two methods available to determine the Boron Equivalent of the Xenon Worth as follows:

If the time since shutdown is > 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months , then Xenon Worth may Note be set equal to zero. Using a zero value assumes NO credit is taken in the SDM calculation for the negative reactivity associated with the actual Xenon present in the reactor core. This is the preferred method when the Unit is borated to the Xenon-free condition.

If the time since shutdown is 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months , a conservative determination of the Boron Equivalent of the Xenon Worth can be made by interpolating between the burnup tables in the PCB Section 2, Figure 2A. Interpolate using the Xenon Worth that will bound the MINIMUM Xenon Worth that will exist in the core for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months past the calculation point.

An assumption is made in Attachment 2 Step 7 to set Xenon Worth equal to zero pcm (e.g., Xenon free Condition) or to use the MINIMUM Xenon Worth that will exist in the core for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months past the calculation point. This will assure that at NO time between this shutdown margin (SDM) calculation and the next SDM calculation (i.e.,

the Tech Spec 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months time interval) will the transient Xenon Worth Caution challenge satisfying the Tech Spec Minimum SDM requirement. This approach is also consistent with 3/4-GOP-103 that allows Operations flexibility to delay boration of the RCS to the Xenon-free condition for up to 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months post trip. IF zero pcm is assumed and Operations has NOT borated to the Xenon-free condition, THEN the calculation may show the minimum SDM requirement is NOT met in Attachment 2 Step 10.

(Attachment 2, Step 7)

STEP 14 : SAT Using the Time Since Shutdown from Attachment 2 Step 5.B, AND the PCB, Section 2, Figure 2A (Xenon Worth vs Time After Shutdown), or UNSAT the ERDADS Poison Program, RECORD the Boron Equivalent of the Xenon Worth as follows:

Assuming a Xenon-Free condition (Initial Conditions), the operator Standard: records 0 in the PCM Block.

The operator records 0 in the PPM Block.

EXAMINER NOTE 2013 Admin JPM Aib RO

- NUREG 1021, Revision 9

Appendix C Page 12 of 18 Form ES-C-i PERFORMANCE INFORMATION In Attachment 2 Step 8, a linear interpolation for Most Reactive Stuck Note: Rod Worth between BOC and EOC using the Burnup in Attachment 2 Step 4 is appropriate.

(Attachment 2, Steps 8.A and B)

STEP 15 : SAT CALCULATE the RCCA correction as follows:

UNSAT IF Attachment 2 Step 5.F equals zero or one...

IF Attachment 2 Step 5.F is greater than one, THEN using the PCB, Section 3, Figure 7, Summary of Reactivity Requirements and Shutdown Margin, RECORD the Boron equivalent of those rods NOT fully inserted as follows:

The operator recognizes that Step 8.A is NA.

The operator records 2 in the Attachment 2 Step 5.F Block.

The operator uses Section 3, Figure 7 (5/29/1 2), interpolates linearly between BOC and EOC and determines the worth of the most reactive Standard: Rod and BOC is 1052.85 pcm.

The operator records 1052.85 in the PCM Block. (If the operator does not interpolate, may use 1049)

The operator performs the math and records -150.4 in the PPM Block.

(-149.9 if no interpolation used in procedure step 8)

EXAMINER N OTE 2013 Admin JPM Aib RO

- NUREG 1021, Revision 9

Appendix C Page 13 of 18 Form ES-C-i PERFORMANCE INFORMATION (Attachment 2, Step 9)

STEP 16 SAT V RECORD Corrected Minimum Shutdown Boron Concentration as follows: UNSAT The operator records 1316 in the Attachment 2 Step 6.C Block.

The operator records 0 in the Attachment 2 Step 7 Block.

Standard The operator records -150.4 in the Attachment 2 Step 8.A or B Block.

(-149.9 if no interpolation)

The operator performs the math and records 1466.4 in the PPM Block.

(1465.9 if no interpolation)

EXAMINER NOTE A YES answer in Attachment 2 Step 10 confirms the minimum N: required SHUTDOWN MARGIN per Technical Specifications is being met.

(Attachment 2, Step 10)

STEP 17 : SAT DOCUMENT if Attachment 2 Step 9 is less than or equal to Attachment 2 Step 5.C: UNSAT The operator compares the RCS boron concentration recorded in Step Standard 9 (1466.4) to the RCS boron concentration recorded in Step 5.C (1208), and places a V in the NO Block.

EXAMINER NOTE 2013 Admin - JPM Aib RO NUREG 1021, Revision 9

Appendix C Page 14 of 18 Form ES-C-i PERFORMANCE INFORMATION (Attachment 2, Step ii)

STEP 18 : SAT IF Attachment 2 Step 10 is YES,.....

U N SAT Standard: The operator recognizes that Step 1 1 is NA.

EXAMINER NOTE (Attachment 2, Step 12 Al)

STEP 19 : SAT CALCULATE the gallons of acid required to increase the RCS Boron Concentration to greater than or equal to that of Attachment 2 Step 9 UNSAT as follows:

50,790 x Ln [5245PPM - X]I[5245 PPM-Y]

where:

X Most recent RCS boron concentration from Attachment 2 Step 5.C Y = Corrected minimum shutdown boron concentration from Attachment 2 Step 9 (1) SUBTRACT the following:

The operator records 1208 in the Attachment 2 Step 5.C Block.

Standard: The operator performs the math and records 4037 in the PPM Block.

EXAMINER NOTE 2013 Admin JPM Aib RD

- NUREG 1021, Revision 9

Appendix C Page 15 of 18 Form ES-C-i PERFORMANCE INFORMATION (Attachment 2, Step 12 A.2)

STEP 20 : SAT (2) SUBTRACT the following:

U N SAT The operator records 1466.4 in the Attachment 2 Step 9 Block.

Standard: The operator performs the math and records 3778.6 in the PPM Block.

(3779.1 if no interpolation used in step 8)

EXAMINER NOTE (Attachment 2, Step 12 A.3)

STEP 21 : SAT (3) DIVIDE the following:

UNSAT The operator records 4037 in the Attachment 2 Step 1 2.A. I Block.

The operator records 3778.6 in the Attachment 2 Step 12.A.2 Block.

(3779.1 if no interpolation used in step 8)

Standard:

The operator performs the math and records 1.0684 in the Block provided.

(1 .0682 if no interpolation)

EXAMINER NOTE 2013 Admin JPM Aib RO NUREG 1021, Revision 9

Appendix C Page 16 of 18 Form ES-C-i PERFORMANCE INFORMATION (Attachment 2, Step 12 A.4)

STEP 22 : SAT (4) TAKE natural log of Attachment 2 Step 12.A(3):

UNSAT The operator records 1.0684 in the Attachment 2 Step 12.A.3 Block.

(1 .0682 if no interpolation)

Standard The operator performs the math and records .0661 in the Block provided.

(0.0660 if no interpolation)

EXAMINER NOTE (Attachment 2, Step 12A.5)

STEP 23 : SAT (5) MULTIPLY the following:

UNSAT The operator records .0661 in the Attachment 2 Step 1 2.A.4 Block.

(0.0660 if no interpolation)

Standard: The operator performs the math and records 3359.7+/-1% (3325-3394) in the Block provided.

(3353.0 if no interpolation)

EXAMINER NOTE Stop Time 2013 Admin - JPM Aib RO NUREG 1021, Revision 9

Appendix C Page 17 of 18 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 Admin JPM Aib RO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2013 Admin - JPM Aib RO NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:

The current time is 0800

At 0700 today, Unit 3 reactor tripped from 100% power.

Two rods fail to insert on the trip and remain fully withdrawn.

RCS Tave is being maintained at 547 °F by the atmospheric steam dumps, and it is expected to be maintained at this temperature until 0400 tomorrow.

Current Unit 3 burnup is 1000 MWD/MTU

Unit 3 Boron Concentration was 1208 ppm at 0500.

No boron additions or dilutions occurred between the sample and the trip.

INITIATING CUE:

The SM has directed you to verify adequate SHUTDOWN MARGIN exists per 0-OSP-028.8, Shutdown Margin Calculation, for maintaining Unit 3 at Hot Standby 547°F until 0400 tomorrow, assuming a Xenon-Free condition.

IF it is determined that adequate SHUTDOWN MARGIN does NOT exist, determine the amount of boric acid that must be added to ensure adequate shutdown margin exists.

Acknowledge to the examiner when you are ready to begin.

RO NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-i Worksheet JPM Aib SRO 2013 Admin - JPM Al b SRO (REV_021 81 3) NUREG 1021, Revision 9

Appendix C Page 2 of 9 Form ES-C-i Job Performance Measure Worksheet Facility: Turkey Point Task No.: 02023013300 Task

Title:

Determine Contingency Actions for JPM No.: 2013 Admin JPM Al b a Loss of RHR in Mode 5 and the SRO Loops are Not Available K/A

Reference:

GKIA 2.1.23 (4.4)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions!Cue (Last Page of this JPM), and O-ADM-051.

Initial Conditions:

Unit 3 is in Mode 5 for a mid-cycle, short-duration, non-refueling outage.

Unit 3 was shutdown 216 hours0.0025 days 0.06 hours 3.571429e-4 weeks 8.2188e-5 months ago.

The RCS has been drained to Mid-Loop conditions in accordance with 3-NOP-041 .09, Reduced Inventory Operations.

The 3A RHR Pump is operating.

RCS temperature is 140°F.

The RCS is depressurized.

Subsequently:

The 3A RHR Pump tripped.

The crew entered 3-ONOP-050, Loss of RHR.

When the crew attempted to start the 3B RHR Pump it failed to start.

2013 Admin JPM Al b SRO NUREG 1021, Revision 9

Appendix C Page 3 of 9 Form ES-C-i Job Performance Measure Worksheet Initiating Cue: The US has directed you to evaluate the present plant conditions in accordance with Section 5.4 of O-ADM-051 Outage Risk Assessment and Control, and identify the following:

The approximate time to 200°F

The approximate RCS Heat-Up Rate

The required Contingency Actions (By Enclosure and Page #)

The Safe Shutdown Function Color Code

The approximate time to core uncovery Task Standard: The operator will assess current plant conditions and determine that the approximate time to saturated conditions is 10.9- 12 minutes, the approximate RCS Heat-Up Rate is 5°F/Minute (5.0 5.5°F/Minute), the required Contingency Actions (By Enclosure and Page #) are Actions 1-10 listed for the Decay Heat Removal Safe Shutdown Function/Two RHR Pumps on Enclosure 2 (Page 1 of 9), the Safe Shutdown Function Color Code is RED, and that the approximate time to core uncover is 180 +/-4 Minutes.

Required Materials: Calculator General

References:

0-ADM-051, Outage Risk Assessment and Control, (Rev 10) 3-ONOP-050, Loss of RHR, (Rev 2) 3-NOP-041 .09, Reduced Inventory Operations, (Rev 3)

Handouts: 0-ADM-051, Outage Risk Assessment and Control, (Blank Copy)

Time Critical Task: NO Validation Time: 25 minutes 2013 Admin JPM Aib SRO NUREG 1021, Revision 9

Appendix C Page 4 of 9 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with a checkmark F))

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and O-ADM-051.

START TIME:

(Step 5.4.1) Typical post shutdown unit heat up rates following a loss STEP I : of cooling are shown in Figures 1, 2 and 3. The time frames for SAT operator action prior to heating above 200° F at the core outlet can be derived from these curves. UNSAT The operator will refer to Figure 1 and determine that this figure is applied only when the Vessel is FULL, and sets this aside.

The operator will refer to Figure 2 and determine that this figure is applied only when the water level is 2 feet below the Rx Vessel Flange, and sets this aside.

Standard: The operator will refer to Figure 3 and identify the intersection between Time After Shutdown (216 Hours) and the curve to be an approximate RCS Heat-Up Rate of 5-5.5 degrees per minute.

The operator will conclude that the plant will heat to 200°F in 10.9 - 12 minutes.

EXAMINER NOTE 2013 Admin - JPM Al b SRO NUREG 1021, Revision 9

Appendix C Page 5 of 9 Form ES-C-i PERFORMANCE INFORMATION

Enclosures i through 7 contain suggested preplanned contingency actions which the Shift Manager can evaluate for implementation when minimum equipment requirements are not met. The Shift Manager shall determine which contingencies are to be implemented for any given situation.

Steps 5.4.2 through 5.4.4 only apply when fuel is in the Containment Building. When the reactor is defueled spent fuel pool status and required support systems should be as specified in the NOTEs: RO logs and Enclosure 7 and monitored by the System Engineers.

If a loss of Spent Fuel Pit Cooling occurs when the reactor is defueled, take actions to restore the required systems as specified in 3/4-ONOP-033.i, Spent Fuel Pit Cooling System Malfunction, 3/4-ONOP-030, Component Cooling Water System Malfunction, 3/4-ONOP-0i9, Intake Cooling Water System Malfunction, and/or applicable TCNs. Typical reactor defueled Spent Fuel Pit heat up rates are provided in Figure 4, and can be utilized to estimate available repair/action time.

(Step 5.4.2) During Phase I of an outage, the equipment listed in STEP 2 : Enclosures i through 3 should be maintained Available. When the SAT minimum equipment recommendations are not met, the Shift Manager shall determine the appropriate contingencies to be implemented. UNSAT The operator will evaluate the definitions of Phase I and Phase II, and conclude that Phase I of the Outage is applicable.

Standard: The operator addresses Enclosures 1, 2 and 3; and determines that Enclosure 2 is applicable.

Phase I The initial portion of an outage in which the decay heat load is high and additional equipment is maintained Functional. This provides for a better Defense In Depth. It is defined as the first 240 hours0.00278 days 0.0667 hours 3.968254e-4 weeks 9.132e-5 months following unit shutdown or completion of fuel offload to the Spent Fuel Pit, whichever occurs first.

EXAMINER NOTE Phase II The later stages of an outage in which the decay heat load is reduced and relaxations of Functional equipment requirements are allowed. It is defined as greater than 240 hours0.00278 days 0.0667 hours 3.968254e-4 weeks 9.132e-5 months following unit shutdown, or start of fuel reload to the reactor vessel as part of a full core offload, whichever occurs first.

2013 Admin - JPM Aib SRO NUREG 1021, Revision 9

Appendix C Page 6 of 9 Form ES-C-i PERFORMANCE INFORMATION (Step 5.4.2) When the minimum equipment recommendations are not STEP 3 : met, the Shift Manager shall determine the appropriate contingencies SAT to be implemented.

UNSAT The operator will evaluate Enclosure 2 and identify that both RHR Pumps are required equipment, that there are ten Contingency Standard Actions (Actions 1-10) required (Those Listed on Page 1 of 9 of Enclosure 2 [Page 58]), AND that with both RHR Pumps inoperable, the Color Code is RED.

EXAMINER NOTE (Contingency Action 10) If RCS Inventory is at Mid-Loop, then refer to STEP 4 : Figure 5, Time to Core Uncovery From Mid-Loop. SAT V

UNSAT The operator will refer to Figure 5 and identify the intersection between Standard: Time After Shutdown (216 Hours) and the 140°F Initial RCS Temperature Curve to be 180 minutes until core uncovery.

EXAMINER NOTE Terminating Cue: STOP Stop Time 2013 Admin - JPM Aib SRO NUREG 1021, Revision 9

Appendix C Page 7 of 9 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 Admin JPM Al b SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2013 Admin - JPM Al b SRO NUREG 1021, Revision 9

Appendix C Page 8 of 9 Form ES-C-i VERIFICATION OF COMPLETION KEY:

The approximate time to saturated conditions (JPM Step 1) = 10.9 12 minutes Based on 5-5.5 minutes using Figure 3 60°F x minute!5°F 12 minutes 60°F x minutel5.5°F 10.9 minutes The approximate RCS Heat-Up Rate (JPM Step 1) = 5°FlMinute (5.0 - 5.5°F/Minute).

The required Contingency Actions (By Enclosure and Page #) (JPM Step 3) Actions 1-10 listed for the Decay Heat Removal Safe Shutdown FunctionlTwo RHR Pumps on (Page 1 of 9) [Page 58].

The Safe Shutdown Function Color Code (JPM Step 3) = RED The approximate time to core uncover (JPM Step 4) = 180 +/-4 Minutes 2013 Admin JPM Aib SRO NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM BRIEFING SHEET INITIAL CONDITIONS:

Unit 3 is in Mode 5 for a mid-cycle, short-duration, non-refueling outage.

Unit 3 was shutdown 216 hours0.0025 days 0.06 hours 3.571429e-4 weeks 8.2188e-5 months ago.

The RCS has been drained to Mid-Loop conditions in accordance with 3-NOP-041 .09, Reduced Inventory Operations.

The 3A RHR Pump is operating.

RCS temperature is 140°F.

The RCS is depressurized.

Subsequently:

The 3A RHR Pump tripped.

The crew entered 3-ONOP-050, Loss of RHR.

When the crew attempted to start the 3B RHR Pump it failed to start.

INITIATING CUE:

The US has directed you to evaluate the present plant conditions in accordance with Section 5.4 of 0-ADM-051, Outage Risk Assessment and Control, and identify the following:

The approximate time to 200°F

The approximate RCS Heat-Up Rate

The required Contingency Actions (By Enclosure and Page #)

The Safe Shutdown Function Color Code

The approximate time to core uncovery Acknowledge to the examiner when you are ready to begin.

SRO NUREG 1021, Revision 9

C REVISION NO.: PROCEDURE TITLE: PAGE:

1 SHUTDOWN MARGIN CALCULATION 22 of 31 PROCEDURE NO; O-OSP-028.8 TURKEY POINT PLANT ATTACHMENT 2 INITIAL Shutdown Margin C&culation For MODES 3, 4 And 5 (Page 1 of 10)

1. RECORD unit number:

2. RECORD cycle number:

LZ

3. RECORD shutdown date and time:

Date: Time:

NOTE The Cycle Burnup value in the PCB, Section 5, Figure 4 is periodically updated by Reactor Enineering. Although the actual burnup can be approximately determined to account for core burnup since the last update, recording the most recent value from PCB Section 5, Figure 4 in Attachment 2 Step 4 will produce conservative results. To approximately determine the actual burnup, increase the burnup by adding 32 MWD/MTU for each day of full power operation (or fraction thereof, e.g., add 8 MWD/MTU for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months at full power or 16 MWD/MTU for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at 50% power, etc., ) since the date and time of the last update.

4. Cycle burnup (Plant Curve Book (PCB), Section 5, Figure 4):

MWD/MTU NOTE The CALCULATION POINT is the point in time at which the Shutdown Margin is to be calculated. It is NOT necessarily the present time.

5. RECORD the following calculation point conditions:

A. Calculation point:

Date . LTime 1X/

REVISION NO.: PROCEDURE TITLE: PAGE:

SHUTDOWN MARGIN CALCULATION 23 Of 31 PROCEDURE NO.:

O-OSPO28.8 TURKEY POINT PLANT ATTACHMENT 2 INITIAL Shutdown Margin Calculation For MODES 3, 4 And 5 (Page 2 of 10)

5. (continued)

B. Time since shutdown:

2 Hrs NOTE The measured RCS boron concentration entered below should be from the most recent sample. Primary Nuclear Chemistry can be contacted or the Chemistry Department (P1) database can be accessed to obtain the latest RCS boron concentration, and the date and time of the sample.

C. Most recent RCS boron concentration:

Sample Date Sample TIme J D. Average RCS Temperature at Date/Time in Attachment 2 Step 5.A:

I :LL7 E. MODE:

MODE 3: RCS temperature greater than Hot Standby or equal to 350F MODE 4: RCS temperature greater than Hot Shutdown 200°F and less than 350°F MODE 5: RCS temperature less than or Cold Shutdown equal to 200°F

REVISION NO.: PROCEDURE TITLE: PAGE SHUTDOWN MARGIN CALCULATION 24 of 31 PROCEDURE NO..

O-OSP-028.8 TURKEY POINT PLANT ATTACHMENT 2 NITIAL Shutdown Margin Calculation For MODES 3, 4 And 5 (Page 3 of 10)

5. (continued)

F. RECORD number of Control Rods that are NOT fully inserted:

NOTE The Minimum Shutdown Boron Concentration (MSBC) calculated in Attachment 2 Step 6 is a function of RCS Temperature and Burnup. There are three methods available to determine MSBC as follows:

A very conservative reactivity determination of MSBC may be made without interpolation by using the applicable PCB Section 3, Figure 5A and choosing the burnup statepoint/curve and the RCS temperature statepointlcurve that are less than or equal to the burnup in Attachment 2 Step 4 and temperature in Attachment 2 Step 5.D, respectively. However, using this method, the result may be a higher value than what is desired for the actual plant condition.

A conservative reactivity determination of MSBC may be made by a single interpolation of burnup using the applicable PCB Section 3, Figure 5A and choosing the temperature statepoint/curve that is less than or equal to the temperature in Attachment 2 Step 5.D. This is the preferred and recommended method.

Accepting the built-in conservatism in unit/cycle specific data, an accurate reactivity determination of MSBC may be made by a double interpolation of burnup and average RCS temperature using the applicable PCB Section 3, Figure 5A. Using this method, the result is the lowest acceptable value achievable, which may be desired for the actual plant condition.

6. DETERMINE the Minimum Shutdown Boron Concentration:

A. RECORD minimum average RCS temperature that will be assumed in the calculation and will bound the actual temperature in Attachment 2 Step 5.D and expected changes in plant conditions, based on Operations input, over the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Assumed MInimum Average RCS Temperature ( 1 F

REVISION NO,. PROCEDURE TITLE:

PAGE:

1 SHUTDOWN MARGIN CALCULATION 25 of 31 PROCEDURE NO.,

O-OSP-028.8 TURKEY POINT PLANT ATTACHMENT 2 INITIAL Shutdown Margin Calculation For MODES 3, 4 And 5 (Page 4 of 10)

6. (continued)

CAUTION To preclude a non-conservative reactivity determination of Minimum Shutdown Boron Concentration, the temperature statepoint/curve used in Attachment 2 Step 6.B must be less than or equal to the actual average RCS Temperature recorded in Attachment 2 Step 5.D or the lowest average RCS temperature expected by Operations due to potential changes in plant conditions during the ensuing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , as applicable.

B. RECORD the RCS temperature and burnUp value that wif be used to calculate the Minimum Shutdown Boron Concentration:

RCS Temperature: cc 7 F Burnup: tçt9: MWD/MTU NOTE In Attachment 2 Step 6.C below, Plant Curve Book Section 3, Figure 5A already includes the reactivity effects of the minimum, Hot Full Power, steady state Samarium concentration. FigLire 5A conservatively does NOT take credit for the additional build-up of Samarium that occurs after Unit shutdown.

C. Using the burnup and temperature from Attachment 2 Step 6.B, AND the applicable PCB Section 3, Figure 5A (Minimum Shutdown Boron vs RCS Temperature as a function of Burnup), RECORD the Minimum Shutdown Boron Concentration:

PPM

REVISION NO.. PROCEDURE TITLE: PAGE 1

SHUTDOWN MARGIN CALCULATION 26 of 31 PROCEDURE NO:

O-OSP-028.8 TURKEY POINT PLANT ATTACHMENT 2 INITIAL Shutdown Margin Calculation For MODES 3, 4 And 5 (Page 5 of 10)

6. (continued)

D. IF the following are NOT true:

Temperature fl Attachment 2 Step 6.B is less than or equal to the temperature selected in Attachment 2 Step 6.A,

The burnup in Attachment 2 Step 6.B is less than or equal to burnup from Attachment 2 Step 4.

IF used, THEN interpolation calculation results are correct.

THEN RETURN to Attachment 2 Step 6.A.

Performed By: Verified By:

Initial Initial

REVISION NO.: PROCEDURE TITLE: PAGE:

1 SHUTDOWN MARGIN CALCULATION 27 of 31 PROCEDURE NO.:

O-OSP-028.8 TURKEY POINT PLANT ATTACHMENT 2 INITIAL Shutdown Margin Calculation For MODES 3, 4 And 5 (Page 6 of 10)

NOTE The amount of negative reactivity in the core post trip due to Xenon varies with core burnup, the initial power level, power changes pre-trip, and time since trip.

The Xenon concentration in the core peaks at 6 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months post trip, decays to approximately the value prior to the downpower/trip condition at 13 to 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months post trip, and fully decays to essentially zero pcm at 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months post trip.

There are two methods available to determine the Boron Equivalent of the Xenon Worth as follows:

If the time since shutdown is > 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months , then Xenon Worth may be set equal to zero. Using a zero value assumes NO credit is taken in the SDM calculation for the negative reactivity associated with the actual Xenon present in the reactor core. This is the preferred method when the Unit is borated to the Xenon-free condition.

If the time since shutdown is 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months , a conservative determination of the Boron Equivalent of the Xenon Worth can be made by interpolating between the burnup tables in the PCB Section 2, Figure 2A. Interpolate using the Xenon Worth that will bound the MINIMUM Xenon Worth that will exist in the core for LIP to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months past lhe calculation point.

CAUTION An assumption is made in Attachment 2 Step 7 to set Xenon Worth equal to zero pcm (e.g., Xenon free Condition) or to use the MINIMUM Xenon Worth that will exist in the core for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months past the calculation point. This will assure that at NO time between this shutdown margin (SDM) calculation and the next SDM calculation (i.e.,

the Tech Spec 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months time interval) will the transient Xenon Worth challenge satisfying the Tech Spec Minimum SDM requirement. This approach is also consistent with 3/4-GOP-103 that allows Operations flexibility to delay boration of the RCS to the Xenon-free condition for LIP to 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months post trip, IF zero pcrn is assumed and Operations has NOT borated to the Xenon-free condition, THEN the calculation may show the minimum SDM requirement is NOT met in Attachment 2 Step 10.

7. Using the Time Since Shutdown from Attachment 2 Step 5B. AND the PCB, Section 2, Figure 2A (Xenon Worth vs Time After Shutdown), or the ERDADS Poison Program, RECORD the Boron EqLlivalent of the Xenon Worth as follows:

PCM 15 5 PCM/PPM = I PPM Xenon Worth

REVISION NO: PROCEDURE TITLE: PAGE:

1 SHUTDOWN MARGIN CALCULATION 28 of 31 PROCEDURE NO.:

0-OSP028.8 TURKEY POINT PLANT ATTACHMENT 2 INITIAL Shutdown Margin Cafculation For MODES 3, 4 And 5 (Page 7 of 10)

NOTE In Attachment 2 Step 8, a linear interpolation for Most Reactive Stuck Rod Worth between BOG and EOC using the Burnup in Attachment 2 Step 4 is appropriate.

8. CALCULATE the RCCA correction as follows:

A. IF Attachment 2 Step 5.F equals zero or one, THEN the RCCA correction equals zero ppm.

OPPM B. IF Attachment 2 Step 5.F IS greater than one, THEN using the PCB, Section 3, Figure 7, Summary of Reactivity Requirements and Shutdown Margin, RECORD the Boron equivalent of those rods NOT fully inserted as follows:

( 1 ) X c PCM 70 PCM/PPM = t! \ PPM Attachment 2 Most Reactive Step 5.F Stuck Rod Worth

r

9. RECORD Corrected Minimum Shutdown Boron Concentration as follows:

i ( PPM PPM / ( PPM tt PPM Attachment 2 Attachment 2 Attachment 2 Step 6.C Step 7 Step 8.A or Attachment 2 Step 8.13 NOTE A YES answer in Attachment 2 Step 10 confirms the minimum required SHUTDOWN MARGIN per Technical Specifications is being met.

10. DOCUMENT if Attachment 2 Step 9 is less than or equal to Attachment 2 Step 5.0:

Yes: 0 No: 0

REVISION NO.: PROCEDURE TITLE: PAGE:

SHUTDOWN MARGIN CALCULATION 29 of 31 PROCEDURE NO.:

OOSP-028.8 TURKEY POINT PLANT ATTACHMENT 2 INITIAL Shutdown Margin Calculation For MODES 3, 4 And 5 (Page 8 of 10)

11. IF Attachment 2 Step 10 is YES, THEN CALCULATE the Excess SHUTDOWN MARGIN as follows:

PPM PPM ) X 7 0 PCM/PPM

= PCM Attachment 2 Attachment 2 Step 5.C Step 9

12. IF Attachment 2 Step 10 is NO, THEN immediately PERFORM the following:

A. CALCULATE the gallons of acid reqLlired to increase the RCS Boron Concentration to greater than or eqUal to that of Attachment 2 Step 9 as follows:

PPM Xl 50,790 gal x Lnr-

[5245 PPM Yj where: X = Most recent RCS boron concentration from Attachment 2 Step 5.C Y = Corrected minimum shutdown boron concentration from Attachment 2 Step 9 (1) SUBTRACT the following:

I 5245 PPM PPM = PPM I Attachment 2 Step S.C (2) SUBTRACT the following:

5245 PPM PPM = <7 / PPM Attachment 2 Step 9 (3) DIVIDE the following:

Attachment 2 Step 12.A(1): PPM =

Attachment 2 Step 1 2.A(2): : PPM

ç,

REVISION NO.: PROCEDURE TITLE: PAGE 1

SHUTDOVVN MARGIN CALCULATION 30 of 31 PROCEDURE NO.:

O-OSP-028.8 TURKLY POINT PLANT ATTACHMENT 2 INITIAL Shutdown Margin Calculation For MODES 3, 4 And 5 (Page 9 of 10)

12. A. (continued)

(4) TAKE natural log of Attachment 2 Step 1 2.A(3):

Ln of Attachment 2 Step 12.A(3)

(5) MULTIPLY the following:

50 790 gal X c gaI Attachment 2 Step 12.A(4) Ic: /

L fiLl)

B. ADD the volume of acid from Attachment 2 Step 12A(5), at a rate 16 gpn using 3/4-ONOP-046.1, Emergency Boration.

C. After sufficient time for mixing, OBTAIN a new RCS chemistry sample.

D. PERFORM Attachment 2 Step 5 through Attachment 2 Step 12 to confirm SHUTDOWN MARGIN per Technical Specifications is being met.

N OTE

The second attachment shall be performed by a different person than the person who performed the first calculation.

Verification copy of Attachment 2 is NOT required to be attached as a record.

13. PERFORM a verification of the shutdown margin calculation by independently calculating the shutdown margin by using a separate Attachment 2 without referencing the original calculations.

REVISION NO: PROCEDURE TITLE. PAGE.

1 SHUTDOWN MARGIN CALCULATION 31 of 31 PROCEDURE NO..

O-OSP-028.8 TURKEY POINT PLANT ATTACHMENT 2 Shutdown Margin Calculation For MODES 3, 4 And 5 (Page 10 of 10)

13. (continued>

Remarks:

Performed By: Date:

The verification performed was independent of the first calculation on a separate Attachment 2 with the same results as the first calculation.

Verified By: Date.

Appendix C Job Performance Measure Form ES-C-i Worksheet JPM A2 RO 2013 Admin JPM A2 RO (REV_021813)

- NUREG 1021, Revision 9

Appendix C Page 2 of 14 Form ES-C-i Job Performance Measure Worksheet Facility: Turkey Point Task No.: 01094010200 Task

Title:

Perform Accident Monitoring JPM No.: 2013 Admin JPM A2 Instrument Channel Checks RO KJA

Reference:

GKIA 2.2.40 (3.4)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), the Data Sheet (21(

to last Page of this JPM), and a blank copy of 3-OSP-204.

Initial Conditions:

Unit 3 and 4 are both Mode 1 100% power.

No equipment is DOS.

All prerequisites of 3..OSP-204, Accident Monitoring Instrumentation Channel Checks, have been met.

Initiating Cue:

The US has directed you to perform the monthly check of the Core Exit Thermocouples by completing Section 4.10 of 3-OSP-204, Accident Monitoring Instrumentation Channel Checks.

Another operator will perform Attachment 1, QSPDS CET/RVLIS Sensors Out of Service, if needed.

Identify any Technical Specification LCOs that are NOT met, and why.

Task Standard: The operator will determine that the Functional Criteria is NOT met for all Quadrant 2 and 3 CETs, and that the Acceptance Criteria is NOT met for Quadrant 2 CETs. The operator will identify that LCD 3.3.3.3 Functional Unit 14, Total Number of Channels is NOT met, because the Total Number of Channels is NOT met for Quadrant 2.

2013 Admin JPM A2 RD

- NUREG 1021, Revision 9

Appendix C Page 3 of 14 Form ES-C-i Job Performance Measure Worksheet Required Materials: Calculator General

References:

3-OSP-204, Accident Monitoring Instrumentation Channel Checks, (Rev 6)

Handouts: 3-OSP-204, Accident Monitoring Instrumentation Channel Checks (Blank Copy)

Technical Specifications Time Critical Task: NO Validation Time: 20 minutes 2013 Admin - JPM A2 RO NUREG 1021, Revision 9

Appendix C Page 4 of 14 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with a checkmark fVJ)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), the Data Sheet (2 to last Page of this JPM), and a blank copy of 3-OSP-204.

START TIME:

Obtain the procedural guidance.

STEP I : SAT UNSAT The operator reviews the Purpose, the Scope, the Precautions and Standard: Limitation, the Prerequisites, of 3-OSP-204, and proceeds to Section 4.10.

EXAMINER NOTE (Step 4.10.1) IF reactor power is less than or equal to 2%...

STEP 2 : SAT UNSAT Standard: The operator recognizes that this step is NA, and continues.

EXAMINER NOTE 2013 Admin - JPM A2 RO NUREG 1021, Revision 9

Appendix C Page 5 of 14 Form ES-C-i PERFORMANCE INFORMATION Those CETs that have )000( entered into their data field below have been bypassed by the QSPDS software in accordance with procedure, NOTE: 3-OP-042.1, QSPDS - Inadequate Core Cooling Monitor Infrequent Operations, Subsection 7.1.

(Step 4.10.2) RECORD Quadrant One CET Temperatures in Table 3:

STEP 3 SAT

/ Functional Criteria:

UNSAT

If Reactor Power is 2%

If Reactor Power is >2%, then the CET readings are 545°F to 650°F.

Acceptance Criteria:

At least 4 CETs in Quadrant 1 were determined to be functional.

The operator records the data from the Data Sheet as follows:

Channel A Channel B P7 563 R7 621 N10 XXXX P8 XXXX N8 618 N6 600 L6 616 N4 573 K8 615 Mu XXXX M9 xxxx I L8 604 Standard:

The operator recognizes reactor power is > 2%.

The operator evaluates the data an determines that all readings are between 545°F and 650°F; and places a CHECK in the Functional Criteria Results SAT Checkbox.

The operator evaluates the data and determines that EIGHT (8) CETs in Quadrant 1 are determined to be Functional; and places a CHECK in the Acceptance Criteria Results SAT Checkbox.

EXAMINER NOTE 2013 Admin - JPM A2 RO NUREG 1021, Revision 9

Appendix C Page 6 of 14 Form ES-C-i PERFORMANCE INFORMATION Those CETs that have )(XXX entered into their data field below have been bypassed by the QSPDS software in accordance with procedure, NOTE: 3-OP-042.i, QSPDS - Inadequate Core Cooling Monitor Infrequent Operations, Subsection 7.1.

(Step 4.10.3) RECORD Quadrant Two CET Temperatures in Table 4:

STEP 4 SAT Functional Criteria:

UNSAT

If Reactor Power is 2%

If Reactor Power is >2%, then the CET readings are 545°F to 650°F.

Acceptance Criteria:

At least 4 CETs in Quadrant 2 were determined to be functional.

The operator records the data from the Data Sheet as follows:

Channel A Channel B M3 542 K5 541 H5 604 K3 XXXX H3 655 J2 608 G2 544 G6 651 E4 652 Gi 615 D3 536 F5 538 F3 652 Standard:

The operator recognizes reactor power is > 2%.

The operator evaluates the data an determines that NINE (9) readings are outside the 545°F and 650°F band; and places a CHECK in the Functional Criteria Results U NSAT Checkbox.

The operator evaluates the data and determines that THREE (3) CETs in Quadrant 2 are determined to be Functional; and places a CHECK in the Acceptance Criteria Results UNSAT Checkbox.

EXAMINER NOTE 2013 Admin - JPM A2 RO NUREG 1021, Revision 9

Appendix C Page 7 of 14 Form ES-C-i PERFORMANCE INFORMATION Those CETs that have X)O(.X entered into their data field below have been bypassed by the QSPDS software in accordance with procedure, NOTE: 3-OP-042.i, QSPDS - Inadequate Core Cooling Monitor Infrequent Operations, Subsection 7.1.

(Step 4.10.4) RECORD Quadrant Three CET Temperatures in Table STEP 5 : 5: SAT V

Functional Criteria: UNSAT

. If Reactor Power is 2%

. If Reactor Power is >2%, then the CET readings are 545°F to 650°F.

Acceptance Criteria:

. At least 4 CETs in Quadrant 3 were determined to be functional.

The operator records the data from the Data Sheet as follows:

Charnel A Channel B G8 612 H8 666 ElO 558 F9 XXXX E7 625 E8 603 D5 XXXX C12 568 C8 621 A8 XXXX Standard:

The operator recognizes reactor power is > 2%.

The operator evaluates the data an determines that TWO (2) readings are outside the 545°F and 650°F band; and places a CHECK in the Functional Criteria Results UNSAT Checkbox.

The operator evaluates the data and determines that SEVEN (7) CETs in Quadrant 3 are determined to be Functional; and places a CHECK in the Acceptance Criteria Results SAT Checkbox.

EXAMINER NOTE 2013 Admin - JPM A2 RO NUREG 1021, Revision 9

Appendix C Page 8 of 14 Form ES-C-i PERFORMANCE INFORMATION (Step 4.10.5) RECORD Quadrant Four CET Temperatures in Table 6:

STEP 6 SAT

/ Functional Criteria:

UNSAT

If Reactor Power is 2%......

If Reactor Power is >2%, then the CET readings are 545°F to 650°F.

Acceptance Criteria:

At least 4 CETs in Quadrant 4 were determined to be functional.

The operator records the data from the Data Sheet as follows:

Channel A Channel B L14 577 Ku 615 Ll2 619 HiS 564 Jl2 621 Hi3 623 Jl0 621 H9 602 HIl 604 Ei4 S67 G15 561 Fl 3 621 Standard: Fll 609 The operator recognizes reactor power is > 2%.

The operator evaluates the data an determines that NO readings are outside the 545°F and 650°F band; and places a CHECK in the Functional Criteria Results SAT Checkbox.

The operator evaluates the data and determines that FOURTEEN (14)

CETs in Quadrant 4 are determined to be Functional; and places a CHECK in the Acceptance Criteria Results SAT Checkbox.

EXAMINER NOTE 2013 Admin JPM A2 RO NUREG 1021, Revision 9

Appendix C Page 9 of 14 Form ES-C-i PERFORMANCE INFORMATION Attachment 2, Temperature Element Descriptions and Locations A Train QSPDS and Attachment 3, Temperature Element Descriptions and Locations B Train QSPDS provide a cross reference from NOTE: temperature element core location to the specific temperature element designation. The temperature element designation is required to properly identify the component on any PWOs generated to address their failure.

(Step 4.10.6) ENSURE all out of service CETs are documented per STEP 7 : Attachment 1, QSPDS CET/RVLIS Sensors Out of Service. SAT UNSAT The operator recognizes that another operator will perform Attachment Standard: 1 and continues.

EXAMINER NOTE (Step 4.10.7) IF Reactor Power is greater than 2%, THEN RECORD STEP 8 : the following representative CET temperatures: SAT

ChannelA

Channel B UNSAT Acceptance Criteria:

IF Reactor Power is greater than 2%, representative CET temperatures are between 545°F and 650°F.

The operator recognizes reactor power is> 2%.

The operator records the data from the Data Sheet as follows:

Channel A Channel B Standard: Representative CET Temp 642 644 The operator evaluates the data and determines that BOTH channels are between 545°F and 650°F; and places a CHECK in the Acceptance Criteria Results Channel A and Channel B SAT Checkbox.

EXAMINER NOTE 2013 Admin JPM A2 RO NUREG 1021, Revision 9

Appendix C Page 10 of 14 Form ES-C-i PERFORMANCE INFORMATION (Step 4.10.8) RECORD the following CET Subcooling temperatures:

STEP 9 : . Channel A SAT v

Channel B

Reactor Power UNSAT Acceptance Criteria:

CET Subcooling Temperatures are within the temperature range below for the current reactor power:

100% steady-state: 5°F-30°F The operator records the data from the Data Sheet as follows:

Channel A Channel B CET Subcooling temperatures: 12 10 The operator reactor power is 100%.

Standard:

The operator evaluates the data an determines that CET Subcooling Temperatures are within the temperature range below for 100%

power; and places a CHECK in the Acceptance Criteria Results Channel A and Channel B SAT Checkbox.

EXAMINER NOTE 2013 Admin - JPM A2 RD NUREG 1021, Revision 9

Appendix C Page 11 of 14 Form ES-C-I PERFORMANCE INFORMATION Identify any Technical Specification LCOs that are NOT met.

STEP 10 : SAT V

U N SAT The operator evaluates Technical Specifications and determines that LCD 3.3.3.3, Accident Monitoring Instrumentation, Functional Unit 14, Standard: Total Number of Channels is NOT met for Quadrant 2.

EXAMINER NOTE Terminating Cue: STOP Stop Time 2013 Admin - JPM A2 RD NUREG 1021, Revision 9

Appendix C Page 12 of 14 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 Admin - JPM A2 RO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2013 Admin - JPM A2 RO NUREG 1021, Revision 9

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Appendix C Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:

Unit 3 and 4 are both Mode 1 100% power.

No equipment is OOS.

All prerequisites of 3-OSP-204, Accident Monitoring Instrumentation Channel Checks, have been met.

INITIATING CUE:

The US has directed you to perform the monthly check of the Core Exit Thermocouples by completing Section 4.10 of 3-OSP-204, Accident Monitoring Instrumentation Channel Checks.

Another operator will perform Attachment 1, QSPDS CET/RVLIS Sensors Out of Service, if needed.

Identify any Technical Specification LCOs that are NOT met, and why.

Acknowledge to the examiner when you are ready to begin.

RO NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-i Worksheet JPM A2 SRO 2013 Admin - JPM A2 SRO (REV_021813) NUREG 1021 Revision 9

Appendix C Page 2 of 14 Form ES-C-i Job Performance Measure Worksheet Facility: Turkey Point Task No.: 01094010200 Task

Title:

Perform Accident Monitoring JPM No.: 2013 Admin JPM A2 Instrument Channel Checks SRO KJA

Reference:

GKIA 2.2.40 (4.7)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom X Simulator Plant READ TO THE EXANIINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions!Cue (Last Page of this JPM), the Data Sheet (

n 2 d to last Page of this JPM), and a blank copy of 3-OSP-204.

Initial Conditions:

Unit 3 and 4 are both Mode 1 100% power.

No equipment is OOS.

All prerequisites of 3-OSP-204, Accident Monitoring Instrumentation Channel Checks, have been met.

Initiating Cue:

The US has directed you to perform the monthly check of the Core Exit Thermocouples by completing Section 4.10 of 3-OSP-204, Accident Monitoring Instrumentation Channel Checks.

Another operator will perform Attachment 1, QSPDS CET/RVLIS Sensors Out of Service, if needed.

Identify any Technical Specification LCOs that are NOT met, and why.

Identify any Technical Specification ACTION that must be taken.

2013 Admin JPM A2 SRO

- NUREG 1021, Revision 9

Appendix C Page 3 of 14 Form ES-C-i Job Performance Measure Worksheet Task Standard: The operator will determine that the Functional Criteria is NOT met for all Quadrant 2 and 3 CETs, and that the Acceptance Criteria is NOT met for Quadrant 2 CETs. The operator will identify that LCO 3.3.3.3 Functional Unit 14, Total Number of Channels is NOT met, because the Total Number of Channels is NOT met for Quadrant 2; and that ACTION 31 must betaken.

Required Materials: Calculator General

References:

3-OSP-204, Accident Monitoring Instrumentation Channel Checks, (Rev 6)

Handouts: 3-OSP-204, Accident Monitoring Instrumentation Channel Checks (Blank Copy)

Technical Specifications Time Critical Task: NO Validation Time: 25 minutes 2013 Admin JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 4 of 14 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with a checkmark f.7)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), the Data Sheet (2 to last Page of this JPM), and a blank copy of 3-OSP-204.

START TIME:

Obtain the procedural guidance.

STEP I : SAT UNSAT The operator reviews the Purpose, the Scope, the Precautions and Standard: Limitation, the Prerequisites, of 3-OSP-204, and proceeds to Section 4.10.

EXAMINER NOTE (Step 4.10.1) IF reactor power is less than or equal to 2%...

STEP 2 : SAT UNSAT Standard: The operator recognizes that this step is NA, and continues.

EXAMINER NOTE 2013 Admin JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 5 of 14 Form ES-C-i PERFORMANCE INFORMATION Those CETs that have XXXX entered into their data field below have been bypassed by the QSPDS software in accordance with procedure, NOTE: 3-OP-042.1, QSPDS Inadequate Core Cooling Monitor Infrequent Operations, Subsection 7.1.

(Step 4.10.2) RECORD Quadrant One CET Temperatures in Table 3:

STEP 3 SAT

/ Functional Criteria:

UNSAT

If Reactor Power is 2%

If Reactor Power is >2%, then the CET readings are 545°F to 650°F.

Acceptance Criteria:

At least 4 CETs in Quadrant 1 were determined to be functional.

The operator records the data from the Data Sheet as follows:

Charnel A Channel B P7 563 R7 621 N10 XXXX P8 XXXX N8 618 N6 600 L6 616 N4 573 Mu xxxx M9 xxxx L8 604 Standard:

The operator recognizes reactor power is > 2%.

The operator evaluates the data an determines that all readings are between 545°F and 650°F; and places a CHECK in the Functional Criteria Results SAT Checkbox.

The operator evaluates the data and determines that EIGHT (8) CETs in Quadrant 1 are determined to be Functional; and places a CHECK in the Acceptance Criteria Results SAT Checkbox.

EXAMINER NOTE 2013 Admin JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 6 of 14 Form ES-C-i PERFORMANCE INFORMATION Those CETs that have XXXX entered into their data field below have been bypassed by the QSPDS software in accordance with procedure, NOTE: 3-OP-042.1, QSPDS Inadequate Core Cooling Monitor Infrequent Operations, Subsection 7.1.

(Step 4.10.3) RECORD Quadrant Two CET Temperatures in Table 4:

STEP 4 SAT V Functional Criteria:

UNSAT

If Reactor Power is 2%

If Reactor Power is >2%, then the CET readings are 545°F to 650°F.

Acceptance Criteria:

At least 4 CETs in Quadrant 2 were determined to be functional.

The operator records the data from the Data Sheet as follows:

Channel A Channel B M3 542 K5 541 H5 604 K3 XXXX H3 655 J2 608 G2 544 G6 651 E4 652 G1 615 D3 536 F5 538 F3 652 Standard:

The operator recognizes reactor power is> 2%.

The operator evaluates the data an determines that NINE (9) readings are outside the 545°F and 650°F band; and places a CHECK in the Functional Criteria Results UNSAT Checkbox.

The operator evaluates the data and determines that THREE (3) CETs in Quadrant 2 are determined to be Functional; and places a CHECK in the Acceptance Criteria Results UNSAT Checkbox.

EXAMINER NOTE 2013 Admin JPM A2 SRO

- NUREG 1021, Revision 9

Appendix C Page 7 of 14 Form ES-C-I PERFORMANCE INFORMATION Those CETs that have )(XXX entered into their data field below have been bypassed by the QSPDS software in accordance with procedure, NOTE: 3-OP-042.1, QSPDS - Inadequate Core Cooling Monitor Infrequent Operations, Subsection 7.1.

(Step 4.10.4) RECORD Quadrant Three CET Temperatures in Table STEP 5 : 5: SAT V

Functional Criteria: UNSAT

. If Reactor Power is 2%

. If Reactor Power is >2%, then the CET readings are 545°F to 650°F.

Acceptance Criteria:

. At least 4 CETs in Quadrant 3 were determined to be functional.

The operator records the data from the Data Sheet as follows:

Charnel A Channel B G8 612 H8 666 ElO 558 F9 XXXX E7 625 E8 603 D5 XXXX 600 C12 568 F C8 621 A8 XXXX Standard:

The operator recognizes reactor power is > 2%.

The operator evaluates the data an determines that TWO (2) readings are outside the 545°F and 650°F band; and places a CHECK in the Functional Criteria Results UNSAT Checkbox.

The operator evaluates the data and determines that SEVEN (7) CETs in Quadrant 3 are determined to be Functional; and places a CHECK in the Acceptance Criteria Results SAT Checkbox.

EXAMINER NOTE 2013 Admin - JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 8 of 14 Form ES-C-i PERFORMANCE INFORMATION (Step 4.10.5) RECORD Quadrant Four CET Temperatures in Table 6:

STEP 6 SAT V Functional Criteria:

UNSAT

If Reactor Power is 2%

If Reactor Power is >2%, then the CET readings are 545°F to 650°F.

Acceptance Criteria:

At least 4 CETs in Quadrant 4 were determined to be functional.

The operator records the data from the Data Sheet as follows:

Channel A Channel B L14 577 Ku 615 L12 619 HiS 564 J12 621 H13 623 J10 621 H9 602 Hil 604 E14 567 G15 561 E12 614 F13 621 Standard: FlI 609 The operator recognizes reactor power is > 2%.

The operator evaluates the data an determines that NO readings are outside the 545°F and 650°F band; and places a CHECK in the Functional Criteria Results SAT Checkbox.

The operator evaluates the data and determines that FOURTEEN (14)

CETs in Quadrant 4 are determined to be Functional; and places a CHECK in the Acceptance Criteria Results SAT Checkbox.

EXAMINER NOTE 2013 Admin JPM A2 SRO

- NUREG 1021, Revision 9

Appendix C Page 9 of 14 Form ES-C-i PERFORMANCE INFORMATION Attachment 2, Temperature Element Descriptions and Locations A Train QSPDS and Attachment 3, Temperature Element Descriptions and Locations B Train QSPDS provide a cross reference from NOTE: temperature element core location to the specific temperature element designation. The temperature element designation is required to properly identify the component on any PWOs generated to address their failure.

(Step 4.10.6) ENSURE all out of service CETs are documented per STEP 7 : Attachment 1, QSPDS CET/RVLIS Sensors Out of Service. SAT UNSAT The operator recognizes that another operator will perform Attachment Standard: 1 and continues.

EXAMINER NOTE (Step 4.10.7) IF Reactor Power is greater than 2%, THEN RECORD STEP 8 : the following representative CET temperatures: SAT

ChannelA

Channel B UNSAT Acceptance Criteria:

IF Reactor Power is greater than 2%, representative CET temperatures are between 545°F and 650°F.

The operator recognizes reactor power is> 2%.

The operator records the data from the Data Sheet as follows:

Channel A Channel B Standard: Representative CET Temp 642 644 The operator evaluates the data and determines that BOTH channels are between 545°F and 650°F; and places a CHECK in the Acceptance Criteria Results Channel A and Channel B SAT Checkbox.

EXAMINER NOTE 2013 Admin JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 10 of 14 Form ES-C-i PERFORMANCE INFORMATION (Step 4.10.8) RECORD the following CET Subcooling temperatures:

STEP 9

Channel A SAT

Channel B

Reactor Power UNSAT Acceptance Criteria:

CET Subcooling Temperatures are within the temperature range below for the current reactor power:

100% steady-state: 5°F-30°F The operator records the data from the Data Sheet as follows:

Channel A Channel B CET Subcooling temperatures: 12 10 The operator reactor power is 100%.

Standard:

The operator evaluates the data an determines that CET Subcooling Temperatures are within the temperature range below for 100%

power; and places a CHECK in the Acceptance Criteria Results Channel A and Channel B SAT Checkbox.

EXAMINER NOTE 2013 Admin - JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page ii of 14 Form ES-C-i PERFORMANCE INFORMATION Identify any Technical Specification LCOs that are NOT met, and any STEP 10 : ACTION required. SAT V

UNSAT The operator evaluates Technical Specifications and determines that LCO 3.3.3.3, Accident Monitoring Instrumentation, Functional Unit 14, Total Number of Channels is NOT met for Quadrant 2.

The operator determines that ACTION 31 is applicable: With the number of OPERABLE accident monitoring instrumentation channel(s)

Standard less than the Total Number of Channels either restore the inoperable channel(s) to OPERABLE status within 30 days, or submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 14 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.

EXAMINER NOTE Terminating STOP Stop Time 2013 Admin - JPM A2 SRO NUREG 1021, Revision 9

Appendix C Page 12 of 14 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 Admin - JPM A2 SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2013 Admin - JPM A2 SRO NUREG 1021, Revision 9

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Appendix C Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:

Unit 3 and 4 are both Mode 1 100% power.

No equipment is OOS.

All prerequisites of 3-OSP-204, Accident Monitoring Instrumentation Channel Checks, have been met.

INITIATING CUE:

The US has directed you to perform the monthly check of the Core Exit Thermocouples by completing Section 4.10 of 3-OSP-204, Accident Monitoring Instrumentation Channel Checks.

Another operator will perform Attachment 1, QSPDS CET/RVLIS Sensors Out of Service, if needed.

Identify any Technical Specification LCOs that are NOT met, and why.

Identify any Technical Specification ACTION that must be taken.

Acknowledge to the examiner when you are ready to begin.

SRO NUREG 1021, Revision 9

Appendix C Job Performance Measure Form ES-C-i Worksheet JPMA3RO&SRO 2013 Admin - JPM A3 RO & SRO (REV_021 81 3)

NUREG 1021, Revision 9

Appendix C Page 2 of 14 Form ES-C-i Job Performance Measure Worksheet Facility: Turkey Point Task No.: 01038034100 Task

Title:

Evaluate Conditions for Restart of JPM No.: 2013 Admin JPM A3 Refueling Pre-shuffle in the Spent RO & SRO Fuel Pit K/A

Reference:

GKIA 2.3.12 (3.2/3.7)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and 3-NOP-040.03.

Initial Conditions:

Refueling Pre-shuffle activities were interrupted in the Unit 3 Spent Fuel Pit.

Subsequently, the SM desires to resume Pre-shuffle activities.

The following plant conditions now exist:

Spent Fuel pool Level is 56 feet 8 inches.

Spent fuel boron concentration is 2330 ppm as determined by the last sample taken 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ago.

The Tube Gate is CLOSED.

Control Room Temperatures are 75°F.

ONLY one communications system is functional.

RP coverage is available.

FME Monitor is NOT available.

2013 Admin JPM A3 RO & SRO

- NUREG 1021, Revision 9

Appendix C Page 3 of 14 Form ES-C-i Job Performance Measure Worksheet

The following plant components are now inoperable:

Spent Fuel Pit skimmer pump is OOS.

Rl-3-1419B, Unit 3 SPENT FUEL PIT EXHAUST DUCT, is inoperable. A portable monitor without an alarming device has been substituted.

Unit 3 SEP SPING LOW Range Noble Gas Monitor is QOS.

C Control Room AC Air Handler is OOS.

Initiating Cue:

The SM has directed you to evaluate conditions for recommencement of Pre-shuffle in accordance with Attachment 2 of 3-NOP-040.03, Fuel Handling and insert Shuffle in the Spent Fuel Pit.

Identify all the items, if any that will prevent the recommencement of Pre-shuffle.

Task Standard: The operator will use Attachment 2 of 3-NOP-040.03 and identify that there are four issues preventing the restart of the Pre-Shuffle activities:

(1) Spent Fuel Pit Level is too low, (2) Rl-3-1419B is now inoperable and is without a suitable replacement (i.e. no alarm), (3) the Control Room Emergency Ventilation System is now inoperable and (4) that FME Controls are no longer in effect.

Required Materials: Calculator General

References:

3-NOP-040.03, Fuel Handling And Insert Shuffle In The Spent Fuel Pit, (Rev 9)

Turkey Point Technical Specifications Handouts: 3-NOP-040.03, Fuel Handling And Insert Shuffle In The Spent Fuel Pit, (Blank Copy)

Time Critical Task: NO Validation Time: 20 minutes 2013 Admin JPM A3 RO & SRO

- NUREG 1021, Revision 9

Appendix C Page 4 of 14 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with a checkmark (<1)

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and 3-NOP-040.03.

START TIME:

(Step 4.2.1.20) IF fuel movement is stopped, THEN PERFORM STEP I : Attachment 2, Restart Minimum Equipment Checklist, prior to restart. SAT Equipmentl Minimum Checked Applicable REMARKS UNSAT Conditions Requirement Initials Tech.

for Spec.

Shuffle Spent Fuel OPERABLE N/A Pit Ventilation System The operator evaluates the given conditions and determines that no change has taken place with the Spent Fuel Pit Ventilation System Standard: which was previously OPERABLE.

EXAMINER NOTE 2013 Admin - JPM A3 RO & SRO NUREG 1021, Revision 9

Appendix C Page 5 of 14 Form ES-C-i PERFORMANCE INFORMATION (Step 4.2.1.20) IF fuel movement is stopped, THEN PERFORM STEP 2 Attachment 2, Restart Minimum Equipment Checklist, prior to restart. SAT 7

Equipment! Minimum Checked Applicable REMARKS UNSAT Conditions Requirement Initials Tech.

for Spec.

Shuffle Spent Fuel 57 0 3.9.11 IF level Pit Level drops below minimum, THEN INSERT fuel assembly in a storage location.

The operator evaluates the given conditions and determines that Spent Fuel Pit Level is too low to initiate a Pre-shuffle Restart.

Standard: The operator records Spent Fuel Pit Level < 57 0 as a reason for stopping fuel shuffle.

EXAMINER NOTE 2013 Admin - JPM A3 RO & SRO NUREG 1021, Revision 9

Appendix C Page 6 of 14 Form ES-C-i PERFORMANCE INFORMATION (Step 4.2.1.20) IF fuel movement is stopped, THEN PERFORM STEP 3 Attachment 2, Restart Minimum Equipment Checklist, prior to restart. SAT Equipmentl Minimum Checked Applicable REMARKS UN SAT Conditions Requirement Initials Tech.

for Spec.

Shuffle Spent Fuel CLEAR N/A CHECK Pit Water DailyIF surface and NOT clear, subsurface THEN is clear REQUEST enough to RP place allow good Tn-Nuclear visibility in service, during change refueling filters, or operations skim pool surface as needed.

The operator evaluates the given conditions and determines that no change has taken place with the Spent Fuel Pit water clarity which Standard: was previously CLEAR.

EXAMINER NOTE 2013 Admin - JPM A3 RO & SRO NUREG 1021, Revision 9

Appendix C Page 7 of 14 Form ES-C-i PERFORMANCE INFORMATION (Step 4.21.20) IF fuel movement is stopped, THEN PERFORM STEP 4 Attachment 2, Restart Minimum Equipment Checklist, prior to restart. SAT Equipmentl Minimum Checked Applicable REMARKS UN SAT Conditions Requirement Initials Tech.

for Spec.

Shuffle Spent Fuel In service N/A May be Pool Demin waived by aligned to Radiation SEP Protection Supervision if clarity and dose rates permit.

The operator evaluates the given conditions and determines that no change has taken place with the Spent Fuel Pit Demineralizer Standard: alignment which was previously aligned to SFP and in-service.

EXAMINER NOTE 2013 Admin - JPM A3 RO & SRO NUREG 1021, Revision 9

Appendix C Page 8 of 14 Form ES-C-i PERFORMANCE INFORMATION (Step 4.2.1.20) IF fuel movement is stopped, THEN PERFORM STEP 5 Attachment 2, Restart Minimum Equipment Checklist, prior to restart. SAT V

Equipmentl Minimum Checked Applicable REMARKS UNSAT Conditions Requirement Initials Tech.

for Spec.

Shuffle Rl-3-1 407 B, OPERABLE N/A IF area Rl-3-141 9B, monitor is and Rl NOT 1421 operable, Remote! THEN Local INSTALL a Indications portable and Alarms monitor with an alarm.

The operator evaluates the given conditions and determines that RI 1419B is now inoperable and is without a suitable replacement (i.e. no alarm).

Standard.

The operator records Rl-3-1419B inoperability without an alarming replacement monitor as a reason for stopping fuel shuffle.

EXAMINER NOTE 2013 Admin - JPM A3 RO & SRO NUREG 1021, Revision 9

Appendix C Page 9 of 14 Form ES-C-i PERFORMANCE INFORMATION (Step 4.2.1.20) IF fuel movement is stopped, THEN PERFORM STEP 6 Attachment 2, Restart Minimum Equipment Checklist, prior to restart. SAT Equipment/C Minimum Checked Applicable REMARKS UNSAT onditions Requirement Initials Tech.

for Spec.

Shuffle Spent Fuel Pit Greater than 3.9.14.b IF tube gate Boron or equal to is OPEN, Concentration 2300 ppm THEN CHECK daily.

IF tube gate is CLOSED, THEN CHECK by the most recent SFP boron sample and an additional sample is NOT required.

The operator evaluates the given conditions and determines that the Spent Fuel Pit Boron Concentration is sufficient to permit Pre-Shuffle Standard: Re-Start.

EXAMINER NOTE 2013 Admin - JPM A3 RO & SRO NUREG 1021, Revision 9

Appendix C Page 10 of 14 Form ES-C-i PERFORMANCE INFORMATION (Step 4.2.1.20) IF fuel movement is stopped, THEN PERFORM STEP 7 Attachment 2, Restart Minimum Equipment Checklist, prior to restart. SAT Equipment! Minimum Checked Applicable REMARKS UNSAT Conditions Requirement Initials Tech.

for Spec.

Shuffle Spent Fuel OPERABLE Table 3.3-4 Storage Pool Item 2a Area High Action 28 Gaseous Radioactivity Monitor The operator evaluates the given conditions and determines that no change has taken place with the Spent Fuel Storage Pool Area High Standard: Gaseous Radioactivity Monitor which was previously OPERABLE.

EXAMINER NOTE (Step 4.2.1.20) IF fuel movement is stopped, THEN PERFORM STEP 8 : Attachment 2, Restart Minimum Equipment Checklist, prior to restart. SAT Equipment! Minimum Checked Applicable I REMARKS I UNSAT Conditions Requirement Initials Tech.

for Spec.

Shuffle Comm. CONTINUOUS N/A PERFORM Headsets! Attachment other reliable 4, Refueling comm. Comm.

system -

Verification Control Checklist. At Room to least SEP one comm.

system is functional.

The operator evaluates the given conditions and determines that the available Communication System is sufficient to permit Pre-Shuffle Standard: Re-Start.

EXAMINER NOTE 2013 Admin - JPM A3 RO & SRO NUREG 1021, Revision 9

Appendix C Page 11 of 14 Form ES-C-i PERFORMANCE INFORMATION (Step 4.2.1.20) IF fuel movement is stopped, THEN PERFORM STEP 9 : Attachment 2, Restart Minimum Equipment Checklist, prior to restart. SAT Equipmentl Minimum Checked Applicable REMARKS UNSAT Conditions Requirement Initials Tech.

for Spec.

Shuffle RP CONTINUOUS N/A Coverage The operator evaluates the given conditions and determines that the Standard: RP Coverage is sufficient to permit Pre-Shuffle Re-Start.

EXAMINER NOTE (Step 4.2.1.20) IF fuel movement is stopped, THEN PERFORM STEP 10 Attachment 2, Restart Minimum Equipment Checklist, prior to restart. SAT 7

Equipmentl Minimum Checked Applicable REMARKS UNSAT Conditions Requirement Initials Tech.

for Spec.

Shuffle Control OPERABLE 3.7.5 Requires 3

Room air handlers Emergency and 2 Ventilation compressors System and Control Room air temperature 120°F The operator evaluates the given conditions and determines that the Control Room Emergency Ventilation System is now inoperable.

Standard: The operator records Control Room Emergency Ventilation System inoperability as a reason for stopping fuel shuffle.

EXAMINER NOTE 2013 Admin - JPM A3 RO & SRO NUREG 1021, Revision 9

Appendix C Page 12 of 14 Form ES-C-i PERFORMANCE INFORMATION (Step 4.2.1.20) IF fuel movement is stopped, THEN PERFORM STEP 11 : Attachment 2, Restart Minimum Equipment Checklist, prior to restart. SAT V

Equipment! Minimum Checked Applicable REMARKS UNSAT Conditions Requirement Initials Tech.

for Spec.

Shuffle

_ FME Monitor CONTINUOUS N/A The operator evaluates the given conditions and determines that FME Controls are no longer in effect.

Standard:

The operator records the lack of FME Controls in the SFP Area as a reason for stopping fuel shuffle.

EXAMINER NOTE Stop Time 2013 Admin JPM A3 RO & SRO NUREG 1021, Revision 9

Appendix C Page 13 of 14 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 Admin - JPM A3 RO & SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Timeto Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2013 Admin - JPM A3 RO & SRO NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM BRIEFING SHEET INITIAL CONDITIONS:

Refueling Pre-shuffle activities were interrupted in the Unit 3 Spent Fuel Pit.

Subsequently, the SM desires to resume Pre-shuffle activities.

The following plant conditions now exist:

Spent Fuel pool Level is 56 feet 8 inches.

Spent fuel boron concentration is 2330 ppm as determined by the last sample taken 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ago.

The Tube Gate is CLOSED.

Control Room Temperatures are 75°F.

ONLY one communications system is functional.

RP coverage is available.

FME Monitor is NOT available.

The following plant components are now inoperable:

Spent Fuel Pit skimmer pump is OOS.

RI-3-1419B, Unit 3 SPENT FUEL PIT EXHAUST DUCT, is inoperable. A portable monitor without an alarming device has been substituted.

Unit 3 SFP SPING LOW Range Noble Gas Monitor is OOS.

C Control Room AC Air Handler is DOS.

INITIATING CUE:

The SM has directed you to evaluate conditions for recommencement of Pre-shuffle in accordance with Attachment 2 of 3-NOP-040.03, Fuel Handling and insert Shuffle in the Spent Fuel Pit.

Identify all the items, if any that will prevent the recommencement of Pre-shuffle.

Acknowledge to the examiner when you are ready to begin.

ROISRO NUREG 1021, Revision 9

REVISION NO.: PROCEDURE TITLE: PAGE FUEL HANDLING AND INSERT SHUFFLE IN THE SPENT FUEL PIT 26 of 35 PROCEDURE NO.:

3-NOP-040.03 TURKEY POINT UNIT 3 ATTACHMENT 2 Restart Minimum Equipment Checklist (Page 1 of 2)

Minimum Checked Equipmentl Conditions Requirement for Initials Applicable Tech. REMARKS Spec.

Shuffle Spent Fuel Pit Ventilation System OPERABLE N/A Spent Fuel Pit Level 57 0 IF level drops below minimum, THEN INSERT 3.9.11 fuel assembly in a storage location.

Spent Fuel Pit Water surface and subsurface CHECK Daily IF NOT clear, THEN is clear enough to allow good visibility during CLEAR N/A REQUEST RP place Tn-Nuclear in service, refueling operations change filters, or skim pool surface as needed.

Spent Fuel Pool Demin aligned to SFP In service May be waived by Radiation Protection N/A supervision if clarity and dose rates permit.

Rl-3-1407B, RI-3-1419B, and Rl-3-1421 IF area monitor is NOT operable, THEN OPERABLE ti)4- N/A Remote/Local Indications and Alarms INSTALL a portable monitor with an alarm.

IF tube gate is OPEN, THEN CHECK daily.

Greater than or Spent Fuel Pit Boron Concentration equal to 3.9.14.b IF tube gate is CLOSED, THEN CHECK by the 2300 ppm most recent SFP boron sample and an additional sample is NOT required.

Spent Fuel Storage Pool Area High Gaseous Table 3.3-4 Item 2a Radioactivity Monitor OPERABLE flAJ4( Action 28 Communications Headsets/other reliable PERFORM Attachment 4, Refueling communication system Control Room to SFP CONTINUOUS N/A Communication Verification Checklist. At least one communication system is functional.

RP Coverage CONTINUOUS N/A

REVISION NO.: PROCEDURE TITLE:

rzji PAGE:

FUEL HANDLING AND INSERT SHUFFLE IN THE SPENT FUEL PIT 27 of 35 PROCEDURE NO.:

3-NOP-040.03 TURKEY POINT UNIT 3 ATTACHMENT 2 Restart Minimum Equipment Checklist (Page 2 of 2)

Minimum Checked Applicable Tech.

Equipment! Conditions Requirement for Initials REMARKS Spec.

Shuffle Control Room Emergency Ventilation System Requires 3 air handlers and 2 compressors OPERABLE 3.75 Control Room air temperature 12QF.

FME Monitor CONTINUOUS N/A Reason for stopping fuel shuffle. ccEt-W 1el E+ ttvL .c-io

-V3 1-1)9 Vf-IaW.. t&o Qrt Qe vif Va4&

re- i&orn4(

Name Date Time Signature Performed By (RO or SRO) 144 g

4 fz: .

.1 Unit Supervisor confirms conditions are met to restart Shift Manager gives permission to restart Reviewed By:

Shift Manager or SRO Designee Date

Appendix C Job Performance Measure Form ES-C-I Worksheet JPMA4SRO 2013 Admin - JPM A4 SRO (REV 021 813) NUREG 1021, Revision 9

Appendix C Page 2 of 8 Form ES-C-i Job Performance Measure Worksheet Facility: Turkey Point Task No.: 01001013400 Task

Title:

Classify the Event and Issue PARs JPM No.: 2013 Admin - JPM A4 SRO K/A

Reference:

GKJA 2.4.41 (4.6)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), the Unit 3 Current Conditions (2 to Last Page of this JPM), and a blank copy of 0-EPIP-201 01.

Initial Conditions:

Unit 3 has tripped from 100% power, and has implemented the Emergency Operating Procedures.

You are the Emergency Coordinator in the Control Room.

Two previous Emergency Plan messages have been sent to the State and county authorities with the last being an ALERT.

The EOF is NOT operational.

Initiating Cue: Re-assess plant conditions using 0-EPIP-2010i, Duties of Emergency Coordinator, complete the Florida Nuclear Plant Emergency Notification Form using 0-EPIP- 20134, Offsite Notifications and Protective Action Recommendations.

Task Standard: The operator will assess the current conditions and determine that a General Emergency Exists based on FG1. The operator will then complete the Florida Nuclear Plant Emergency Notification Form in accordance with the provided KEY.

Required Materials: None 2013 Admin - JPM A4 SRO NUREG 1021, Revision 9

Appendix C Page 3 of 8 Form ES-C-i Job Performance Measure Worksheet General

References:

0-EPIP-20i01, Duties of Emergency Coordinator, (Rev 8) 0-EPIP- 20134, Offsite Notifications and Protective Action Recommendations, (Rev 2) 3-EOP-FR-C.2, Response to Degraded Core Cooling, (Rev 2)

Handouts: 0-EPIP-201 01, Duties of Emergency Coordinator, (Blank Copy) 0-EPIP- 20134, Offsite Notifications and Protective Action Recommendations, (Blank Copy)

Time Critical Task: NO Validation Time: 25 minutes 2013 Admin - JPM A4 SRO NUREG 1021, Revision 9

Appendix C Page 4 of 8 Form ES-C-i PERFORMANCE INFORMATION (Denote Critical Steps with a checkmark fVJ)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), the Unit 3 Current Conditions (2 to Last Page of this JPM), and a blank copy of O-EPIP-20101.

START TIME:

(EPIP-20101, Step 5.6.1.11) Reassess plant conditions using STEP I : Attachment 1 and/or 2 periodically. SAT

.7 UNSAT The operator proceeds to Attachment 1, to re-assess plant conditions.

The operator evaluates plant conditions and determines that a General Emergency Exists based on Loss of the Fuel Cladding and RCS Barriers, and the Potential Loss of the Primary Containment Barrier.

Fuel Cladding -6. Containment Radiation Monitoring 1. CHRRM reading > 5.4E3 R/hr. (LOSS)

Standard RCS 2. RCS Leak Rate 1. RCS leak rate greater than available makeup capacity as indicated by a loss of RCS subcooling based on core exit TCs LESS THAN 30°F [210°F]. (LOSS)

Primary Containment 2. Containment Pressure 3.a Containment pressure > 20 psig AND 3.b less than one full train of depressurization equipment operating; OR 3. Core Exit Thermocouple Reading 2.a Core exit thermocouples in excess of 700°F AND RVLMS head voids and FR-C.2 not effective within 15 minutes. (Potential LOSS)

EXAMINER NOTE 2013 Admin JPM A4 SRO NUREG 1021, Revision 9

Appendix C Page 5 of 8 Form ES-C-i PERFORMANCE INFORMATION If the EOF is operational and the emergency has been upgraded, it is imperative that the Recovery Manager be notified concurrently with the CAUTION: declaration. This will ensure that the fifteen minute notification time limit is met.

(Step 5.6.1.12) IF upgrading emergency classification level, THEN STEP 2 : proceed to applicable section of this procedure using Attachment 1 or SAT 2 AND IF the EOF is operational UNSAT The operator PROCEEDS TO Section 5.8, General Emergency Standard:

EXAMINER NOTE Notification steps may be performed out of sequence in order to meet NOTE: State of Florida and/or NRC Notification time requirements.

(Step 5.8.1.12) IF off-site (State and County) notification STEP 3 responsibilities are with the Emergency Coordinator on site, SAT V THEN complete the following steps:

UNSAT (Step 5.8.i.12.a) Complete a form similar to F439 (Florida Nuclear Plant Emergency Notification Form.

The operator obtains a Blank Copy of F-439.

Standard The operator refers to 0-EPIP-201 34, Attachment 1 B and Attachment 3, to complete the F-439 in accordance with the attached Key.

EXAMINER NOTE Terminating Cue: STOP Stop Time 2013 Admin JPM A4 SRO NUREG 1021, Revision 9

Appendix C Page 6 of 8 Form ES-C-i VERIFICATION OF COMPLETION Job Performance Measure No.: 2013 Admin JPM A4 SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2013 Admin JPM A4 SRO NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM BRIEFING SHEET Current Unit 3 Conditions:

Unit 3 is in Mode 3.

The Reactor tripped due to a LOCA in the Containment.

The crew has been in 3-EOP-FR-C.2, Response to Degraded Core Cooling, for 20 minutes.

All RCPs are OFF.

Sump Levels are responding as anticipated.

RCS Pressure is 42 psig.

One Train of Safety Injection has actuated.

HHSI flow is 100 gpm.

CETs are 800° F and rising.

RVLMS Head and Plenum levels indicates zero.

Containment High Range Radiation Monitors are reading 1.5 E5 RIHr.

Containment Operating Floor Radiation Monitor Rl-3-14028 is Off-Scale LOW.

Containment Pressure is 42 psig and rising slowly.

One ECC is operating.

Neither Train of Containment Spray has actuated.

Containment Temperature is 230°F.

No radioactive release is in progress.

Wind speed is 10mph.

Wind direction is from 172°.

SRO NUREG 1021, Revision 9

Appendix C Form ES-C-i JPM BRIEFING SHEET INITIAL CONDITIONS:

Unit 3 has tripped from 100% power, and has implemented the Emergency Operating Procedures.

You are the Emergency Coordinator in the Control Room.

Two previous Emergency Plan messages have been sent to the State and county authorities with the last being an ALERT.

The EOF is NOT operational.

INITIATING CUE:

Re-assess plant conditions using 0-EPIP-2010i, Duties of Emergency Coordinator, complete the Florida Nuclear Plant Emergency Notification Form using 0-EPIP- 20134, Offsite Notifications and Protective Action Recommendations.

Acknowledge to the examiner when you are ready to begin.

SRO NUREG 1021, Revision 9

FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATI ON FORM 4 Online Verification: STATE MIAMI-DADE COUNTY MONROE COUNTY

1. A. This Is A Drill B. D This Is An Actual Event

2. A. Date I / *8. Contact Time:_______ C. Reported by: Name_________________________

D. Message Number:3 E. Reported From: Control Room D TSC D EOF F. Initial/New Classification OR D Update Notification

3 SITE A. fl GeystalcUNfl:3 B. D St-hucie-l4NI-4 C. Q St4.uGieUNl1:2 D. I Turkey Point UNIT 3 E. C Turkey Point UNIT 4

4 EMERGENCY CLASSIFICATION:

A. C Notification Of Unusual Event C I

B. Alert C. Site Area Emergency D. General Emergency

5 A. EMERGENCY DECLARATION: B. Q EMERGENCY TERMINATION Date: / / Time:

6. REASON FOR EMERGENCY DECLARATION:

A. EAL Number:FG1 OR B. Q Description_____________

7. ADDITIONAL INFORMATION OR UPDATE: A.

Q None OR B. D Description______________________________

may add

8. WEATHER DATA: A. Wind direction from 172

9 RELEASE STATUS: degrees. B. Downwind Sectors Affected R,A,B A. None (Go to Item 11) 8. Q In Progress C.

Q Has occurred, but stopped (go to Item 11)

10. RELEASE SIGNIFICANCE CATEGORY (at the Site Boundary)

A. Q Under evaluation B. Q Release within Normal Operating Limits (Tech Specs)

C. Q Non-Significant (Fraction of PAG Range)D. Q PAG Range (Protective Actions required)

E. Q Liquid release (no actions required)

11. UTILITY RECOMMENDED PROTECTIVE ACTIONS FOR THE PUBLIC:

A. C No recommended actions at this time. B. The utility recommends the following protective actions:

EVACUATE ZONES:__________________ OR Miles Evacuate Sectors Shelter Sectors No Action Sectors SHELTER ZONES:_________________ 0-2 All None None 2-5 R,A,B All Remaining None 5- 10 None All None AND consider issuance of potassium iodide (1(1)

If form is completed in the Control Room, go to item 15. If completed in the TSC or EOF, continue with item 12.

12. PLANT CONDITIONS:

A. Reactor Shutdown? Q YES 1 NO B. Core Adequately Cooled? DYES Q NO C. Containment Intact? Q YES Q NO D. Core Condition: Q Stable Q Degrading

13. WEATHER DATA: A. Wind Speed mph B. StabilityClass______

14. ADDITIONAL RELEASE INFORMATION: A. Q Not applicable (Go to Item 15)

Distance Proiected Thyroid Dose (CDE) for 1 Hour Projected Total Dose (TEDE) for 1 Hour 1 Mile (Site Boundary) B. mrem C. mrem 2 Miles D. E. mrem 5 Miles F. mrem G. mrem 10 Miles H. mrem I. mrem

15. (Do not read to State) EC or RM Approval Signature Date / / Time_______

MESSAGE RECEIVED BY: Name Date / I Time______

IF EMERGENCY CLASS ESCALATION IS KNOWN TO BE NECESSARY AND A NEW NOTIFICAT ION FORM WILL BE TRANSMITTED WITHIN 15 MINUTES, THEN YOU MAY GO TO EC/RM APPROVAL SIGNATURE LINE.

ITEMS ARE EVALUATED FOR NRC PERFORMANCE INDICATORS (PIs)

F-4391 I :2 Rev 9 (11/09/09) cvcV

FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM METEOROLOGICAL WORKSHEET SECTOR

REFERENCE:

The chart below can be used to determine sectors affected by a radiological release, wind direction from the meteorological recorders in the Control Room. through comparison with If the wind direction is directly on the edge of two sectors (e.g., 110, 33°, 56°,

should be added to the protective action recommendations. For example, if the etc.), an additional sector then the affected sectors for PARs should be L, M, N and P. wind direction is from 78°.

SECTOR INFORMATION:

WIND SECTOR WIND FROM DEGREES WIND TOWARD SECTORS AFFECTED

[Al N 348-il S I-IJK

[BI NNE 11-33 SSW JKL

[C[ NE 33-56 SW KLM

[D] ENE 56-78 WSW LMN

[El E 78-101 W MNP

[F] ESE 101-123 WNW NPO

[0] SE 123-146 NW PQR

[I-Il SSE 146-168 NNW QRA

[J] S 168-191 N RAB

[K] SSW 191-213 NNE ABC

[L] SW 213-236 NE BCD

[Mj WSW 236-258 ONE CDE

[NI W 258-281 E DEF

[P1 WNW 281-303 ESE EFG

[0] NW 303-326 SE FGH

[RI NNW 326-348 SSE GHJ STABILITY CLASSIFICATION

REFERENCE:

Either ERDADS or the below chart can be used to determine atmospheric stability classification notification to the State of Florida. Primary method is from AT via the South Dade (60 meter) tower. for method is from Sigma Theta via the Ten Meter Tower. If neither meteorological tower is available, Backup Classification shall be determined using data from National Weather Service (See 0-EPIP-2012 Stability Dose Calculations). 6, Off-site CLASSIFICATION OF ATMOSPHERIC STABILITY:

Primary Backup Stability Pasquill Delta T Sigma Theta Classification iggorigy Range (Deetma Extremely unstable A AT -1.7 ST 22.5 Moderately unstable B -1.7 <AT-l.5 22.5> ST 17.5 Slightly unstable C -1.5 <AT-l.4 t7.5 > ST 12.5 Neutral D -1.4 <AT -0.5 12.5 > ST 7.5 Slightly stable E -0.5 <AT+i.4 7.5>ST3.8 Moderately stable F +1.4 <AT +3.6 3.8>ST2.1 Extremely stable 0 +3.6 <AT 2.1 > ST Meteorological information needed to fill out the Florida Nuclear Plant Emergency Notification Form available from the Dose Calculation Worksheet (0-EPIP-20126). The Worksheet shall be filled out is Chemistry and given to the Emergency Coordinator. by F.439/22 Rev 9(11/09/09)

ML13156A104

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