jpm ala ro - nrc: home page · 2013. 6. 11. · n41 100% bottom current = 194.1 microamps n42 100%...

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-iJob Performance Measure Worksheet

Facility: Turkey Point Task No.:

Task Title: Calculate QPTR JPM No.: 2013 Admin - JPM Al aRD

K/A Reference: GKIA 2.1.7 (4.4)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: XClassroom X Simulator Plant

READ TO THE EXAMINEE

I will explain the initial conditions, which steps to simulate or discuss, and provide initiatingcues. When you complete the task successfully, the objective for this Job PerformanceMeasure will be satisfied.

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), the Data Sheet (2to 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 3.2.4is NDT being complied with, and that Section 4.3 of 3-OSP-059.i0 mustbe 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


U3 Plant Curve Book Section 5 Fig 5Turkey 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-iPERFORMANCE INFORMATION

(Denote Critical Steps with a checkmark fVJ)

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

START TIME:

RECORD on Attachment 1, Determination of NIS QPTR Using ExcoreSTEP 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 Sheetonto Attachment 1 Step 2:N41 Top Current = 214.6 microampsN42 Top Current = 178.5 microampsN43 Top Current = 202.2 microamps

Standard: N44 Top Current = 215.7 microampsN41 Bottom Current = 193.2 microampsN42 Bottom Current = 193.0 microampsN43 Bottom Current = 177.3 microampsN44 Bottom Current = 199.7 microamps

EXAMINERNOTE



NOTE Plant Curve Book Section 5 Figure 5, contains the Power Rangecurrents for 100% power values.

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

VUNSAT

The operator obtains Plant Curve Book Section 5 Figure 5.

The operator records the following information from the Data Sheetonto Attachment 1 Step 2:N4i 100% Top Current = 218.5 microampsN42 100% Top Current = 175.9 microamps

Standard: N43 100% Top Current = 200.0 microampsN44 100% Top Current = 216.3 microampsN41 100% Bottom Current = 194.1 microampsN42 100% Bottom Current = 186.1 microampsN43 100% Bottom Current = 175.2 microampsN44 100% Bottom Current = 198.9 microamps

EXAMINERNOTE

COMPLETE calculations on Attachment 1.STEP 3 SAT

VUNSAT

Standard The operator completes the calculations on Attachment 1 inaccordance with the Attached Key.

EXAMINERNOTE

2013 Admin - JPM Al a RO NUREG 1021, Revision 9


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 onAttachment 1 (1 .025) with the Acceptance Criteria of 1.02 and

Standard: determines that the Acceptance Criteria has NOT been met.

EXAMINERNOTE

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

‘7UNSAT

The operator identifies evaluates Technical Specification LCO 3.2.4Quadrant 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.

EXAMINERNOTE

Stop Time

20i3Admin-JPM Ala RO NUREG 1021, Revision 9

Appendix C Page 7 of 10 Form ES-C-iVERIFICATION OF COMPLETION

Job Performance Measure No: 2013 Admin - JPM Ala RO

Examinee’s Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT

Examiner’s Signature: Date:


Appendix C Page 8 of 10 Form ES-C-i

VERIFICATION OF COMPLETION

KEY:

Upper Section Normalized Detector CurrentsN41 Top Current = 214.6 micro amps = 0.982100% Top Current 218.5 micro ampsN42 Top Current = 178.5 micro amps = 1.015100% Top Current 175.9 micro ampsN43 Top Current = 202.2 micro amps = 1.011100% Top Current 200.0 micro ampsN44 Top Current = 215.7 micro amps = 0.997100% Top Current 216.3 micro amps

Upper Section Normalized Current Total = 4.005

Lower 3ection Normalized Detector Currents193.2 micro amps194.1 micro amps193.0 micro mn186.1 micro amps177.3 micro amns =175.2 micro amps199.7 micro amps198.9 micro amps

Lower Section Normalized Current Total =

0.995

1.037

1 .012

1.004

4.048

Average Uer Section Normalized PowerUpper Section Normalized Current Total = 4.005 = 1.001Upper Detectors Used (3 or 4) 4

Average Lower Section Normalized PowerLower Section Normalized Current Total = 4.048 = 1.012Lower Detectors Used (3 or 4) 4

Upper Section Tilt RatioLargest Upper Section Normalized Detector Current = 1.015 1.014

1.001Average Upper Section Normalized Power

Lower Section Tilt RatioLargest Lower Section Normalized Detector Current = 1.037 = 1.025Average Lower Section Normalized Power 1.012

NIS QPTR = highest Section QPTR = 1.025 (UNSAT)

N41 Bottom Current =100% Bottom CurrentN42 Bottom Current =100% Bottom CurrentN43 Bottom Current =100% Bottom CurrentN44 Bottom Current =100% Bottom Current


N-41 Top: 214.6 micro-amps




N-41 Bottom: 193.2 micro-amps




Appendix C Form ES-C-i

JPM CUE SHEET

Data Sheet:

• Excore detector currents for all in service power range nuclear instrumentation channels areas follows:

RO NUREG 1021, Revision 9

Appendix C Form ES-C-iJPM CUE SHEET

INITIAL CONDITIONS:

• Unit 3 is operating at 100% power.

• Excore detector currents for all in service power range nuclearinstrumentation 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 enteredand all procedure sections required to be performed.

Acknowledge to the examiner when you are ready to begin.



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-iJob Performance Measure Worksheet

Facility: Turkey Point Task No.:

Task Title: Calculate QPTR JPM No.: 2013 Admin - JPM AlaSRO




Method of testing:




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

Initial Conditions: • Unit 3 is operating at 100% power.


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


• List all Technical Specifications that are required to be entered, anyACTION that is required and all procedure sections required to beperformed.

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 3.2.4is NOT being complied with, that ACTION statements a.i-4 areapplicable, and that Section 4.3 of 3-OSP-059.i0 must be performed.


2013 Admin - JPM Ala SRO NUREG 1021, Revision 9

of I

Job Performance Measure Worksheet

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

None (Ensure all General References are available)

NO

25 minutes

Appendix C 1 Form ES-C-i

General References:

Handouts:

Time Critical Task:

Validation Time:


Appendix C Page 4 of 1 1 Form ES-C-i

PERFORMANCE INFORMATION


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 ExcoreSTEP 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 Sheetonto Attachment 1 Step 2:N41 Top Current = 214.6 microampsN42 Top Current = 178.5 microampsN43 Top Current 202.2 microamps

Standard: N44 Top Current = 215.7 microampsN41 Bottom Current = 193.2 microampsN42 Bottom Current = 193.0 microampsN43 Bottom Current = 177.3 microampsN44 Bottom Current 199.7 microamps

EXAMINERNOTE

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



NOTE• Plant Curve Book Section 5 Figure 5, contains the Power Rangecurrents for 100% power values.

RECORD the 100% power current values on Attachment 1 for each inSTEP 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 Sheetonto Attachment 1 Step 2:N41 100% Top Current 218.5 microampsN42 100% Top Current = 175.9 microamps

Standard: N43 100% Top Current 200.0 microampsN44 100% Top Current = 216.3 microampsN41 100% Bottom Current = 194.1 microampsN42 100% Bottom Current = 186.1 microampsN43 100% Bottom Current = 175.2 microampsN44 100% Bottom Current = 198.9 microamps

EXAMINERNOTE

COMPLETE calculations on Attachment 1.STEP 3 : SAT

VUNSAT

Standard The operator completes the calculations on Attachment 1 inaccordance with the Attached Key.

EXAMINERNOTE

2Ol3Admin-JPMA1aSRO NUREG 1021, Revision 9



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 onAttachment 1 (1.025) with the Acceptance Criteria of 1.02 and

Standard: determines that the Acceptance Criteria has NOT been met.

EXAMINERNOTE


Appendix C Page 7 of 1 1 Form ES-C-iPERFORMANCE INFORMATION

IF QPTR is greater than 1.02 (2.0%) OR Attachment I yields suspectSTEP 5 : QPTR results, THEN PERFORM Section 4.3. SAT

v/

UNSAT

The operator identifies evaluates Technical Specification LCO 3.2.4Quadrant 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 ACTIONstatement a.1, a.2, a.3 and a.4 are applicable:

ACTION a: With the QUADRANT POWER TILT RATIO determined toexceed 1 .02 but less than or equal to 1 .09:1. Calculate the QUADRANT POWER TILT RATIO at least once perhour until either: a) The QUADRANT POWER TILT RATIO is reducedto within its limit, or b) THERMAL POWER is reduced to less than 50%of RATED THERMAL POWER.

2. Within 2 hours either: a) Reduce the QUADRANT POWER TILTRATIO 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) andsimilarly reduce the Power Range Neutron Flux-High Trip Setpointswithin the next 4 hours.

3. Verify that the QUADRANT POWER TILT RATIO is within its limitwithin 24 hours after exceeding the limit or reduce THERMAL POWERto less than 50% of RATED THERMAL POWER within the next 2hours and reduce the Power Range Neutron Flux-High Trip Setpointsto less than or equal to 55% of RATED THERMAL POWER within thenext 4 hours; and

4. Identify and correct the cause of the out-of-limit condition prior toincreasing THERMAL POWER; subsequent POWER OPERATIONabove 50% of RATED THERMAL POWER may proceed provided thatthe QUADRANT POWER TILT RATIO is verified within its limit at leastonce per hour for 12 hours or until verified acceptable at 95% orgreater RATED THERMAL POWER.

EXAMINERNOTE

TerminatingCue: STOP

Stop Time2013 Admin - JPM Ala SRO NUREG 1021, Revision 9



Job Performance Measure No.: 2013 Admin - JPM Ala SRO

Examinee’s Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:


Result: SAT UNSAT


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

Appendix C Page 9 of 1 1 Form ES-C-iVERIFICATION OF COMPLETION

KEY:

Upper Section Normalized Detector CurrentsN41 Top Current = 214.6 micro amps = 0.982100% Top Current 218.5 micro ampsN42 Top Current = 178.5 micro amps = 1.015100% Top Current 175.9 micro ampsN43TopCurrent 202.2microamps = 1.011100% Top Current 200.0 micro ampsN44 Top Current = 215.7 micro amps = 0.997100% Top Current 216.3 micro amps

Upper Section Normalized Current Total = 4.005

LowerN41 Bottom Current =100% Bottom CurrentN42 Bottom Current =100% Bottom CurrentN43 Bottom Current =100% Bottom Current

3ection Normalized Detector C irrents193.2 micro amps194.1 micro amps193.0 micro amos186.1 micro amps177.3 micro amns =175.2 micro amps199.7 micro amps198.9 micro amps

Lower Section Normalized Current Total =

N44 Bottom Current =100% Bottom Current

0.995

1.037

1.012

1.004

4.048

Average Uooer Section Normalized Power

-

Unoer Section Normalized Current Total = 4.005 = 1.001Upper Detectors Used (3 or 4) 4

Average Lower Section Normalized PowerLower Section Normalized Current Total = 4.048 = 1.012Lower Detectors Used (3 or 4) 4

Upper Section Tilt RatioLargest Upper Section Normalized Detector Current = 1.015 = 1.014

1.001Average Upper Section Normalized Power

Lower Section Tilt RatioLargest Lower Section Normalized Detector Current = 1.037 = 1.025Average Lower Section Normalized Power 1.012

NIS QPTR = highest Section QPTR = 1.025 (UNSAT)



JPM CUE SHEET









Data Sheet:

• Excore detector currents for all in service power range nuclear instrumentation channels areas follows:

SRO NUREG 1021, Revision 9


JPM CUE SHEET

INITIAL CONDITIONS:

• Unit 3 is operating at 100% power.


INITIATING CUE:

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


• List all Technical Specifications that are required to beentered, any ACTION that is required and all proceduresections required to be performed.



Appendix C Job Performance Measure Form ES-C-iWorksheet

JPM Aib RO

2013 Admin - JPM Aib RO (REV_021813) NUREG 1021, Revision 9


Facility: Turkey Point Task No.: 0i02800410i/040C

Task Title: Verify AdeQuate Shutdown Margin JPM No.: 2013 Admin - JPM Al bRO

KJA Reference: GKIA2.l.37 (4.3)



Method of testing:




Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and the twohandouts 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 until0400 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 MARGINexists per 0-OSP-028.8, Shutdown Margin Calculation, formaintaining Unit 3 at Hot Standby 547°F until 0400 tomorrow,assuming a Xenon-Free condition.

• IF it is determined that adequate SHUTDOWN MARGIN does NOTexist, determine the amount of boric acid that must be added toensure adequate shutdown margin exists.

2013 Admin - JPM Aib RO NUREG 1021, Revision 9


Task Standard: The operator will determine the RCS boron concentration for theprojected plant conditions, and compare this to the existing RCS boronconcentration, and conclude that adequate SHUTDOWN MARGIN doesNOT exist, and then calculate that 3325-3394 gallons of boric acid mustbe added to the RCS.


General References: Unit 3 Plant Curve Book, Section III0-OSP-028.8, Shutdown Margin Calculation, (Rev 1)

Handouts: 0-OSP-028.8, Shutdown Margin Calculation (Blank Copy)Unit 3 Plant Curve Book



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


(Denote Critical Steps with a checkmark f/J)

Provide Candidate with Initial ConditionslCue (Last Page of this JPM), and the twohandouts 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 andLimitation, the Prerequisites, and the instructions and determines thatAttachment 2 should be used.

EXAMINERNOTE

(Attachment 2, Steps 1-3)STEP 2 : SAT

RECORD unit number:RECORD cycle number: UNSATRECORD 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 Today’s Date and 0700 in the Date and TimeBlock.

EXAMINERNOTE




The Cycle Burnup value in the PCB, Section 5, Figure 4 is periodicallyupdated by Reactor Engineering. Although the actual burnup can beapproximately determined to account for core burnup since the lastupdate, recording the most recent value from PCB Section 5, Figure 4

Note in Attachment 2 Step 4 will produce conservative results. Toapproximately determine the actual burnup, increase the burnup byadding 32 MWD/MTU for each day of full power operation (or fractionthereof, e.g., add 8 MWD/MTU for 6 hours at full power or 16MWD/MTU for 24 hours at 50% power, etc., ) since the date and timeof the last update.(Attachment 2, Step 4)

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

UNSAT

The operator records 1000 in the MWD/MTU Block.Standard:

EXAMINERNOTE The information was provided on turnover sheet.

NoteS The CALCULATION POINT is the point in time at which the ShutdownMargin 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 Tomorrow’s Date and 0400 in the Date andTime Block.

EXAMINERNOTE




(Attachment 2, Step 5.B)STEP 5 : SAT

Time since shutdown:UNSAT

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

EXAMINERNOTE

The measured RCS boron concentration entered below should befrom the most recent sample. Primary Nuclear Chemistry can be

Note contacted or the Chemistry Department (P1) database can beaccessed to obtain the latest RCS boron concentration, and the dateand 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 Today’s Date in the Sample Date Block.

The operator records 0500 in the Sample Time Block.

EXAMINERNOTE




(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.

EXAMINERNOTE

(Attachment 2, Step 5.E)STEP 8 SAT

MODE:UNSAT

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

EXAMINERNOTE

(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.

EXAMINERNOTE




The Minimum Shutdown Boron Concentration (MSBC) calculated inAttachment 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 bemade without interpolation by using the applicable PCB Section 3,Figure 5A and choosing the burnup statepoint/curve and the RCStemperature statepoint/curve that are less than or equal to theburnup in Attachment 2 Step 4 and temperature in Attachment 2Step 5.D, respectively. However, using this method, the result maybe a higher value than what is desired for the actual plantcondition.

Note:• A conservative reactivity determination of MSBC may be made by

a single interpolation of burnup using the applicable PCB Section3, Figure 5A and choosing the temperature statepoint/curve that isless 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, anaccurate reactivity determination of MSBC may be made by adouble interpolation of burnup and average RCS temperatureusing the applicable PCB Section 3, Figure 5A. Using this method,the result is the lowest acceptable value achievable, which may bedesired 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 assumedin the calculation and will bound the actual temperature in Attachment2 Step 5.D and expected changesin plant conditions, based on Operations input, over the next 24 hours.

Assumed Minimum Average RCS Temperature:

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

EXAMINERNOTE




To preclude a non-conservative reactivity determination of MinimumShutdown Boron Concentration, the temperature statepoint/curve usedin Attachment 2 Step 6.B must be less than or equal to the actualaverage RCS Temperature recorded in Attachment 2 Step 5.D or thelowest average RCS temperature expected by Operations due topotential changes in plant conditions during the ensuing 24 hours, asapplicable.

Caution:

(Attachment 2, Step 6.B)STEP 11 : SAT

RECORD the RCS temperature and burnup value that will be used tocalculate the Minimum Shutdown Boron Concentration: UNSAT

RCS TemperatureBu mu p

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

The operator records 1000 in the MWD/MTU Block.

EXAMINERNOTE

In Attachment 2 Step 6.C below, Plant Curve Book Section 3, Figure5A already includes the reactivity effects of the minimum, Hot Full

Note: Power, steady state Samarium concentration. Figure 5Aconservatively does NOT take credit for the additional build-up ofSamarium_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 UNSATvs. RCS Temperature as a function of Burnup), RECORD theMinimum 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.

EXAMINERNOTE




(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 thetemperature selected in Attachment 2 Step 6.A.

• The burnup in Attachment 2 Step 6.B is less than or equal toburnup 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.

EXAMINERNOTE



The amount of negative reactivity in the core post trip due to Xenonvaries with core burnup, the initial power level, power changes pre-trip,and time since trip. The Xenon concentration in the core peaks at 6 to8 hours post trip, decays to approximately the value prior to thedownpower/trip condition at 13 to 20 hours post trip, and fully decaysto essentially zero pcm at 100 hours post trip.

There are two methods available to determine the Boron Equivalent ofthe Xenon Worth as follows:• If the time since shutdown is > 20 hours, then Xenon Worth may

Note be set equal to zero. Using a zero value assumes NO credit istaken in the SDM calculation for the negative reactivity associatedwith the actual Xenon present in the reactor core. This is thepreferred method when the Unit is borated to the Xenon-freecondition.

• If the time since shutdown is 20 hours, a conservativedetermination of the Boron Equivalent of the Xenon Worth can bemade by interpolating between the burnup tables in the PCBSection 2, Figure 2A. Interpolate using the Xenon Worth that willbound the MINIMUM Xenon Worth that will exist in the core for upto 24 hours past the calculation point.

An assumption is made in Attachment 2 Step 7 to set Xenon Worthequal to zero pcm (e.g., Xenon free Condition) or to use the MINIMUMXenon Worth that will exist in the core for up to 24 hours past thecalculation point. This will assure that at NO time between thisshutdown margin (SDM) calculation and the next SDM calculation (i.e.,the Tech Spec 24 hour time interval) will the transient Xenon Worth

Caution challenge satisfying the Tech Spec Minimum SDM requirement. Thisapproach is also consistent with 3/4-GOP-103 that allows Operationsflexibility to delay boration of the RCS to the Xenon-free condition forup to 20 hours post trip. IF zero pcm is assumed and Operations hasNOT borated to the Xenon-free condition, THEN the calculation mayshow the minimum SDM requirement is NOT met in Attachment 2Step 10.

(Attachment 2, Step 7)STEP 14 : SAT

Using the Time Since Shutdown from Attachment 2 Step 5.B, AND thePCB, Section 2, Figure 2A (Xenon Worth vs Time After Shutdown), or UNSATthe ERDADS Poison Program, RECORD the Boron Equivalent of theXenon 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.

EXAMINERNOTE



In Attachment 2 Step 8, a linear interpolation for Most Reactive StuckNote: 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:

UNSATIF 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 andShutdown Margin, RECORD the Boron equivalent of those rods NOTfully 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 linearlybetween 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 doesnot 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)

EXAMINERN OTE




(Attachment 2, Step 9)STEP 16 SAT

V RECORD Corrected Minimum Shutdown Boron Concentration asfollows: 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)

EXAMINERNOTE

A YES answer in Attachment 2 Step 10 confirms the minimumN: 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 toAttachment 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.

EXAMINERNOTE




(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.

EXAMINERNOTE

(Attachment 2, Step 12 Al)STEP 19 : SAT

,-CALCULATE the gallons of acid required to increase the RCS BoronConcentration to greater than or equal to that of Attachment 2 Step 9 UNSATas follows:

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

where:X Most recent RCS boron concentration from Attachment 2 Step 5.CY = Corrected minimum shutdown boron concentration fromAttachment 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.

EXAMINERNOTE

2013 Admin - JPM Aib RD NUREG 1021, Revision 9



(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)

EXAMINERNOTE


,-(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 Blockprovided.(1 .0682 if no interpolation)

EXAMINERNOTE





,-(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 Blockprovided.(0.0660 if no interpolation)

EXAMINERNOTE

(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)

EXAMINERNOTE

Stop Time




Job Performance Measure No.: 2013 Admin - JPM Aib RO

Examinee’s Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:


Result: SAT UNSAT




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 atmosphericsteam dumps, and it is expected to be maintained at thistemperature 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 sampleand the trip.

INITIATING CUE:

• The SM has directed you to verify adequate SHUTDOWNMARGIN exists per 0-OSP-028.8, Shutdown MarginCalculation, for maintaining Unit 3 at Hot Standby 547°F until0400 tomorrow, assuming a Xenon-Free condition.

• IF it is determined that adequate SHUTDOWN MARGIN doesNOT exist, determine the amount of boric acid that must beadded to ensure adequate shutdown margin exists.




Worksheet

JPM Aib SRO

2013 Admin - JPM Al b SRO (REV_021 81 3) NUREG 1021, Revision 9


Facility: Turkey Point Task No.: 02023013300

Task Title: Determine Contingency Actions for JPM No.: 2013 Admin - JPM Al ba Loss of RHR in Mode 5 and the SROLoops are Not Available




Method of testing:




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-refuelingoutage.

• Unit 3 was shutdown 216 hours 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


Initiating Cue: The US has directed you to evaluate the present plant conditions inaccordance with Section 5.4 of O-ADM-051 Outage Risk Assessment andControl, 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 theapproximate time to saturated conditions is 10.9- 12 minutes, theapproximate RCS Heat-Up Rate is 5°F/Minute (5.0 - 5.5°F/Minute), therequired Contingency Actions (By Enclosure and Page #) are Actions 1-10listed for the Decay Heat Removal Safe Shutdown Function/Two RHRPumps on Enclosure 2 (Page 1 of 9), the Safe Shutdown Function ColorCode is RED, and that the approximate time to core uncover is 180 ±4Minutes.


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)



2013 Admin - JPM Aib SRO NUREG 1021, Revision 9



(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 lossSTEP 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 bederived from these curves. UNSAT

The operator will refer to Figure 1 and determine that this figure isapplied only when the Vessel is FULL, and sets this aside.

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

Standard: The operator will refer to Figure 3 and identify the intersection betweenTime After Shutdown (216 Hours) and the curve to be an approximateRCS 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 - 12minutes.

EXAMINERNOTE




• Enclosures i through 7 contain suggested preplanned contingencyactions which the Shift Manager can evaluate for implementationwhen minimum equipment requirements are not met. The ShiftManager shall determine which contingencies are to beimplemented for any given situation.

• Steps 5.4.2 through 5.4.4 only apply when fuel is in theContainment Building. When the reactor is defueled spent fuel poolstatus 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 isdefueled, take actions to restore the required systems as specifiedin 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/orapplicable TCNs. Typical reactor defueled Spent Fuel Pit heat uprates are provided in Figure 4, and can be utilized to estimateavailable repair/action time.

(Step 5.4.2) During Phase I of an outage, the equipment listed inSTEP 2 : Enclosures i through 3 should be maintained Available. When the SAT

,-minimum equipment recommendations are not met, the Shift Managershall determine the appropriate contingencies to be implemented. UNSAT

The operator will evaluate the definitions of Phase I and Phase II, andconclude that Phase I of the Outage is applicable.

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

Phase I — The initial portion of an outage in which the decay heat loadis high and additional equipment is maintained Functional. Thisprovides for a better Defense In Depth. It is defined as the first 240hours following unit shutdown or completion of fuel offload to theSpent Fuel Pit, whichever occurs first.

EXAMINERNOTE Phase II - The later stages of an outage in which the decay heat load

is reduced and relaxations of Functional equipment requirements areallowed. It is defined as greater than 240 hours following unitshutdown, or start of fuel reload to the reactor vessel as part of a fullcore offload, whichever occurs first.



(Step 5.4.2) When the minimum equipment recommendations are notSTEP 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 RHRPumps are required equipment, that there are ten Contingency

Standard Actions (Actions 1-10) required (Those Listed on Page 1 of 9 ofEnclosure 2 [Page 58]), AND that with both RHR Pumps inoperable,the Color Code is RED.

EXAMINERNOTE

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

VUNSAT

The operator will refer to Figure 5 and identify the intersection betweenStandard: Time After Shutdown (216 Hours) and the 140°F Initial RCS

Temperature Curve to be 180 minutes until core uncovery.

EXAMINERNOTE


Stop Time



Job Performance Measure No.: 2013 Admin - JPM Al b SRO

Examinee’s Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:


Result: SAT UNSAT




KEY:

The approximate time to saturated conditions (JPM Step 1) = 10.9 - 12 minutesBased on 5-5.5 minutes using Figure 360°F x minute!5°F 12 minutes60°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 1-10listed for the Decay Heat Removal Safe Shutdown FunctionlTwo RHR Pumps onEnclosure 2 (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


Appendix C Form ES-C-iJPM BRIEFING SHEET

INITIAL CONDITIONS:

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

• Unit 3 was shutdown 216 hours ago.• The RCS has been drained to Mid-Loop conditions in

accordance with 3-NOP-041 .09, Reduced InventoryOperations.

• 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 inaccordance with Section 5.4 of 0-ADM-051, Outage RiskAssessment 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



C

REVISION NO.: PROCEDURE TITLE: PAGE:

1SHUTDOWN MARGIN CALCULATION 22 of 31PROCEDURE NO;

O-OSP-028.8 TURKEY POINT PLANT

ATTACHMENT 2 INITIALShutdown Margin C&culation For MODES 3, 4 And 5

(Page 1 of 10)

1. RECORD unit number:

2. RECORD cycle number:

LZ3. RECORD shutdown date and time:

Date: Time:

NOTE

The Cycle Burnup value in the PCB, Section 5, Figure 4 is periodically updatedby Reactor Enineering. Although the actual burnup can be approximatelydetermined to account for core burnup since the last update, recording themost recent value from PCB Section 5, Figure 4 in Attachment 2 Step 4 willproduce conservative results. To approximately determine the actual burnup,increase the burnup by adding 32 MWD/MTU for each day of full poweroperation (or fraction thereof, e.g., add 8 MWD/MTU for 6 hours at full power or16 MWD/MTU for 24 hours at 50% power, etc., ) since the date and time of thelast 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 Marginis to be calculated. It is NOT necessarily the present time.

5. RECORD the following calculation point conditions:

A. Calculation point:

Date . LTime 1X/


__________________

SHUTDOWN MARGIN CALCULATION 23 Of 31PROCEDURE NO.:

O-OSPO28.8 TURKEY POINT PLANT

ATTACHMENT 2 INITIALShutdown Margin Calculation For MODES 3, 4 And 5

(Page 2 of 10)

5. (continued)

B. Time since shutdown:

2 Hrs

C. Most recent RCS boron concentration:

Sample Date Sample TIme J

D. Average RCS Temperature at Date/Time inAttachment 2 Step 5.A:

I :LL7E. MODE:

MODE 3: Hot StandbyRCS temperature greater thanor equal to 350F

MODE 4: Hot ShutdownRCS temperature greater than200°F and less than 350°F

MODE 5: Cold ShutdownRCS temperature less than orequal to 200°F

NOTE

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

REVISION NO.: PROCEDURE TITLE: PAGE

SHUTDOWNMARGIN CALCULATION 24 of 31PROCEDURE NO..


ATTACHMENT 2 NITIALShutdown 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 inAttachment 2 Step 6 is a function of RCS Temperature and Burnup. Thereare three methods available to determine MSBC as follows:

A very conservative reactivity determination of MSBC may be madewithout interpolation by using the applicable PCB Section 3, Figure 5Aand choosing the burnup statepoint/curve and the RCS temperaturestatepointlcurve that are less than or equal to the burnup inAttachment 2 Step 4 and temperature in Attachment 2 Step 5.D,respectively. However, using this method, the result may be a highervalue than what is desired for the actual plant condition.

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

Accepting the built-in conservatism in unit/cycle specific data, anaccurate reactivity determination of MSBC may be made by a doubleinterpolation of burnup and average RCS temperature using theapplicable PCB Section 3, Figure 5A. Using this method, the result isthe lowest acceptable value achievable, which may be desired for theactual plant condition.

6. DETERMINE the Minimum Shutdown Boron Concentration:

A. RECORD minimum average RCS temperature that will beassumed in the calculation and will bound the actualtemperature in Attachment 2 Step 5.D and expected changesin plant conditions, based on Operations input, over the next24 hours.

Assumed MInimum Average RCS Temperature ( 1 F

REVISION NO,. PROCEDURE TITLE: PAGE:

1SHUTDOWN MARGIN CALCULATION 25 of 31PROCEDURE NO.,


ATTACHMENT 2Shutdown Margin Calculation For MODES 3, 4 And 5

(Page 4 of 10)

6. (continued)

INITIAL

B. RECORD the RCS temperature and burnUp value that wif beused to calculate the Minimum Shutdown BoronConcentration:

RCS Temperature: cc 7 “F

Burnup: tçt9’: MWD/MTU

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

PPM

CAUTION

To preclude a non-conservative reactivity determination of Minimum ShutdownBoron Concentration, the temperature statepoint/curve used inAttachment 2 Step 6.B must be less than or equal to the actual average RCSTemperature recorded in Attachment 2 Step 5.D or the lowest average RCStemperature expected by Operations due to potential changes in plantconditions during the ensuing 24 hours, as applicable.

NOTE

In Attachment 2 Step 6.C below, Plant Curve Book Section 3, Figure 5Aalready includes the reactivity effects of the minimum, Hot Full Power, steadystate Samarium concentration. FigLire 5A conservatively does NOT take creditfor the additional build-up of Samarium that occurs after Unit shutdown.

REVISION NO.. PROCEDURE TITLE: PAGE

1SHUTDOWN MARGIN CALCULATION 26 of 31PROCEDURE NO:



(Page 5 of 10)

6. (continued)

D. IF the following are NOT true:

• Temperature fl Attachment 2 Step 6.B is less than orequal to the temperature selected inAttachment 2 Step 6.A,

• The burnup in Attachment 2 Step 6.B is less than orequal to burnup from Attachment 2 Step 4.

• IF used, THEN interpolation calculation results arecorrect.

THEN RETURN to Attachment 2 Step 6.A.

Performed By: Verified By:

Initial Initial


1SHUTDOWN MARGIN CALCULATION 27 of 31PROCEDURE NO.:



(Page 6 of 10)

NOTE

The amount of negative reactivity in the core post trip due to Xenon varies withcore burnup, the initial power level, power changes pre-trip, and time since trip.The Xenon concentration in the core peaks at 6 to 8 hours post trip, decays toapproximately the value prior to the downpower/trip condition at 13 to 20 hourspost trip, and fully decays to essentially zero pcm at 100 hours post trip.There are two methods available to determine the Boron Equivalent of the XenonWorth as follows:

If the time since shutdown is > 20 hours, then Xenon Worth may be set equalto zero. Using a zero value assumes NO credit is taken in the SDM calculationfor the negative reactivity associated with the actual Xenon present in thereactor core. This is the preferred method when the Unit is borated to theXenon-free condition.If the time since shutdown is 20 hours, a conservative determination of theBoron Equivalent of the Xenon Worth can be made by interpolating betweenthe burnup tables in the PCB Section 2, Figure 2A. Interpolate using theXenon Worth that will bound the MINIMUM Xenon Worth that will exist in thecore for LIP to 24 hours past lhe calculation point.

CAUTIONAn 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 thecore for up to 24 hours past the calculation point. This will assure that at NO timebetween this shutdown margin (SDM) calculation and the next SDM calculation (i.e.,the Tech Spec 24 hour time interval) will the transient Xenon Worth challengesatisfying the Tech Spec Minimum SDM requirement. This approach is also consistentwith 3/4-GOP-103 that allows Operations flexibility to delay boration of the RCS to theXenon-free condition for LIP to 20 hours post trip, IF zero pcrn is assumed andOperations has NOT borated to the Xenon-free condition, THEN the calculation mayshow the minimum SDM requirement is NOT met in Attachment 2 Step 10.

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

PCM — 15 5 PCM/PPM = I PPM

Xenon Worth

REVISION NO: PROCEDURE TITLE: PAGE:

1SHUTDOWN MARGIN CALCULATION 28 of 31PROCEDURE NO.:

0-OSP028.8 TURKEY POINT PLANT

ATTACHMENT 2 INITIALShutdown 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 RodWorth between BOG and EOC using the Burnup in Attachment 2 Step 4 isappropriate.

8. CALCULATE the RCCA correction as follows:

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

OPPM

B. IF Attachment 2 Step 5.F IS greater than one, THEN using thePCB, Section 3, Figure 7, Summary of ReactivityRequirements and Shutdown Margin, RECORD the Boronequivalent of those rods NOT fully inserted as follows:

( 1 ) X c PCM — 70 PCM/PPM = t! \ PPMAttachment 2 Most Reactive

Step 5.F Stuck Rod Worth- :r

9. RECORD Corrected Minimum Shutdown Boron Concentration asfollows:

i ( PPM PPM / ‘( PPM tt PPMAttachment 2 Attachment 2 Attachment 2

Step 6.C Step 7 Step 8.A orAttachment 2

Step 8.13

NOTE

A YES answer in Attachment 2 Step 10 confirms the minimum requiredSHUTDOWN MARGIN per Technical Specifications is being met.

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

Yes: 0 No: 0


SHUTDOWNMARGIN CALCULATION 29 of 31PROCEDURE NO.:

O—OSP-028.8 TURKEY POINT PLANT


(Page 8 of 10)

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

PPM PPM ) X 7 0 PCM/PPM = PCM

Attachment 2 Attachment 2Step 5.C Step 9

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

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

50,790 gal x Lnr-PPM — Xl

[5245 PPM — Yj

where: X = Most recent RCS boron concentrationfrom Attachment 2 Step 5.C

Y = Corrected minimum shutdown boronconcentration from Attachment 2 Step 9


I 5245 PPM PPM = PPM IAttachment 2 Step S.C


5245 PPM PPM =

REVISION NO.: PROCEDURE TITLE: PAGE

1SHUTDOVVN MARGIN CALCULATION 30 of 31PROCEDURE NO.:

O-OSP-028.8 TURKLY POINT PLANT


(Page 9 of 10)

12. A. (continued)

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

Ln of

Attachment 2Step 12.A(3)

(5) MULTIPLY the following:

50 790 gal X c gaIAttachment 2 / fiLl)Step 12.A(4) Ic: L —

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

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

D. PERFORM Attachment 2 Step 5 throughAttachment 2 Step 12 to confirm SHUTDOWN MARGIN perTechnical Specifications is being met.

N OTE

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

• Verification copy of Attachment 2 is NOT required to be attached as arecord.

13. PERFORM a verification of the shutdown margin calculation byindependently calculating the shutdown margin by using a separateAttachment 2 without referencing the original calculations.

REVISION NO: PROCEDURE TITLE. PAGE.

1SHUTDOWN MARGIN CALCULATION 31 of 31PROCEDURE NO..


ATTACHMENT 2Shutdown Margin Calculation For MODES 3, 4 And 5

(Page 10 of 10)

13. (continued>

Remarks:

Performed By: Date:

Performed By: Date:

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

Verified By: Date.


Worksheet

JPM A2 RO

2013 Admin - JPM A2 RO (REV_021813) NUREG 1021, Revision 9


Facility:

Task Title:

Turkey Point

Perform Accident MonitoringInstrument Channel Checks

Task No.: 01094010200

JPM No.: 2013 Admin - JPM A2RO

KJA Reference:

Examinee:

GKIA 2.2.40 (3.4)

NRC Examiner:

Facility Evaluator:

Method of testing:

Date:

Simulated Performance:

Classroom X Simulator

Actual Performance:

Plant

x



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:

Task Standard:

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

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

• Identify any Technical Specification LCOs that are NOT met, andwhy.

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

2013 Admin - JPM A2 RD NUREG 1021, Revision 9



General References: 3-OSP-204, Accident Monitoring Instrumentation Channel Checks, (Rev6)

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

Technical Specifications



2013 Admin - JPM A2 RO NUREG 1021, Revision 9



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

START TIME:


UNSAT

The operator reviews the Purpose, the Scope, the Precautions andStandard: Limitation, the Prerequisites, of 3-OSP-204, and proceeds to Section

4.10.

EXAMINERNOTE

(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.

EXAMINERNOTE




NOTE:

STEP 3

/

Those CETs that have )000( entered into their data field below havebeen bypassed by the QSPDS software in accordance with procedure,3-OP-042.1, QSPDS - Inadequate Core Cooling Monitor InfrequentOperations, Subsection 7.1.

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

Functional Criteria:

• 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:

SAT

UNSAT

Standard:

Channel A Channel BP7 563 R7 621

N10 XXXX P8 XXXXN8 618 N6 600L6 616 N4 573K8 615 Mu XXXX

M9 xxxxI L8 604

The operator recognizes reactor power is > 2%.

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

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

EXAMINERNOTE




Those CETs that have )(XXX entered into their data field below havebeen bypassed by the QSPDS software in accordance with procedure,

NOTE: 3-OP-042.i, QSPDS - Inadequate Core Cooling Monitor InfrequentOperations, Subsection 7.1.

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

Functional Criteria:UNSAT


650°F.




Channel A Channel BM3 542 K5 541H5 604 K3 XXXXH3 655 J2 608G2 544 G6 651E4 652 Gi 615D3 536 F5 538

F3 652Standard:


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

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

EXAMINERNOTE




Those CETs that have X)O(.X entered into their data field below havebeen bypassed by the QSPDS software in accordance with procedure,

NOTE: 3-OP-042.i, QSPDS - Inadequate Core Cooling Monitor InfrequentOperations, Subsection 7.1.

(Step 4.10.4) RECORD Quadrant Three CET Temperatures in TableSTEP 5 : 5: SAT

VFunctional Criteria: UNSAT

. If Reactor Power is 2%

. If Reactor Power is >2%, then the CET readings are 545°F to650°F.


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


Charnel A Channel BG8 612 H8 666ElO 558 F9 XXXXE7 625 E8 603D5 XXXX

C12 568C8 621A8 XXXX

Standard:


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

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

EXAMINERNOTE



STEP 6

/

Standard:

(Step 4.10.5) RECORD Quadrant Four CET Temperatures in Table 6:


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

650°F.




G15Fl 3

561621

SAT

UNSAT

EXAMINERNOTE


The operator evaluates the data an determines that NO readings areoutside the 545°F and 650°F band; and places a CHECK in theFunctional 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 aCHECK in the Acceptance Criteria Results SAT Checkbox.

Channel A Channel BL14 577 Ku 615Ll2 619 HiS 564Jl2 621 Hi3 623Jl0 621 H9 602HIl 604 Ei4 S67

Fll 609



Attachment 2, Temperature Element Descriptions and Locations ATrain QSPDS and Attachment 3, Temperature Element Descriptionsand Locations B Train QSPDS provide a cross reference from

NOTE: temperature element core location to the specific temperature elementdesignation. The temperature element designation is required toproperly identify the component on any PWOs generated to addresstheir 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 AttachmentStandard: 1 and continues.

EXAMINERNOTE

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

—• ChannelA• Channel B UNSAT


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

The operator recognizes reactor power is> 2%.


Channel A Channel BStandard: Representative CET Temp 642 644

The operator evaluates the data and determines that BOTH channelsare between 545°F and 650°F; and places a CHECK in theAcceptance Criteria Results Channel A and Channel B SATCheckbox.

EXAMINERNOTE



(Step 4.10.8) RECORD the following CET Subcooling temperatures:STEP 9 : . Channel A SAT

v • Channel B• Reactor Power UNSAT


CET Subcooling Temperatures are within the temperature rangebelow for the current reactor power:• 100% steady-state: 5°F-30°F


Channel A Channel BCET Subcooling temperatures: 12 10

The operator reactor power is 100%.Standard:

The operator evaluates the data an determines that CET SubcoolingTemperatures are within the temperature range below for 100%power; and places a CHECK in the Acceptance Criteria ResultsChannel A and Channel B SAT Checkbox.

EXAMINERNOTE


Appendix C Page 11 of 14 Form ES-C-IPERFORMANCE INFORMATION

Identify any Technical Specification LCOs that are NOT met.STEP 10 : SAT

VU N SAT

The operator evaluates Technical Specifications and determines thatLCD 3.3.3.3, Accident Monitoring Instrumentation, Functional Unit 14,

Standard: Total Number of Channels is NOT met for Quadrant 2.

EXAMINERNOTE


Stop Time



Job Performance Measure No.: 2013 Admin - JPM A2 RO

Examinee’s Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:


Result: SAT UNSAT



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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 MonitoringInstrumentation Channel Checks, have been met.

INITIATING CUE:

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

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

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



Appendix C Job Performance Measure Form ES-C-iWorksheet

JPM A2 SRO

2013 Admin - JPM A2 SRO (REV_021813) NUREG 1021 Revision 9




Task Title: Perform Accident MonitoringInstrument Channel Checks

JPM No.: 2013 Admin - JPM A2SRO

KJA Reference: GKIA 2.2.40 (4.7)

Examinee:

Facility Evaluator:

Method of testing:

NRC Examiner:

Date:

Simulated Performance:

Classroom X Simulator

Actual Performance:

Plant

x

READ TO THE EXANIINEE


Provide Candidate with Initial Conditions!Cue (Last Page of this JPM), the Data Sheet (2nd

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

Unit 3 and 4 are both Mode 1 100% power.No equipment is OOS.All prerequisites of 3-OSP-204, Accident Monitoring InstrumentationChannel Checks, have been met.

Initiating Cue: • The US has directed you to perform the monthly check of the CoreExit Thermocouples by completing Section 4.10 of 3-OSP-204,Accident Monitoring Instrumentation Channel Checks.

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

• Identify any Technical Specification LCOs that are NOT met, andwhy.

• Identify any Technical Specification ACTION that must be taken.

Initial Conditions: ••

•

2013 Admin - JPM A2 SRO NUREG 1021, Revision 9


Task Standard: The operator will determine that the Functional Criteria is NOT met forall Quadrant 2 and 3 CETs, and that the Acceptance Criteria is NOT metfor Quadrant 2 CETs. The operator will identify that LCO 3.3.3.3Functional Unit 14, Total Number of Channels is NOT met, because theTotal Number of Channels is NOT met for Quadrant 2; and that ACTION31 must betaken.


General References: 3-OSP-204, Accident Monitoring Instrumentation Channel Checks, (Rev6)

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

Technical Specifications





(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:


UNSAT

The operator reviews the Purpose, the Scope, the Precautions andStandard: Limitation, the Prerequisites, of 3-OSP-204, and proceeds to Section

4.10.

EXAMINERNOTE

(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.

EXAMINERNOTE



NOTE:

STEP 3

/

Those CETs that have XXXX entered into their data field below havebeen bypassed by the QSPDS software in accordance with procedure,3-OP-042.1, QSPDS - Inadequate Core Cooling Monitor InfrequentOperations, Subsection 7.1.

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



650°F.




SAT

UNSAT

Standard:

Charnel A Channel BP7 563 R7 621

N10 XXXX P8 XXXXN8 618 N6 600L6 616 N4 573

MuM9

xxxxxxxx

L8 604

EXAMINERNOTE


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

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



NOTE:

STEP 4

V

Those CETs that have XXXX entered into their data field below havebeen bypassed by the QSPDS software in accordance with procedure,3-OP-042.1, QSPDS - Inadequate Core Cooling Monitor InfrequentOperations, Subsection 7.1.

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



650°F.




SAT

UNSAT

Standard:

Channel A Channel BM3 542 K5 541H5 604 K3 XXXXH3 655 J2 608G2 544 G6 651E4 652 G1 615D3 536 F5 538

F3 652

EXAMINERNOTE


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

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


Appendix C Page 7 of 14 Form ES-C-I


Those CETs that have )(XXX entered into their data field below havebeen bypassed by the QSPDS software in accordance with procedure,

NOTE: 3-OP-042.1, QSPDS - Inadequate Core Cooling Monitor InfrequentOperations, Subsection 7.1.

(Step 4.10.4) RECORD Quadrant Three CET Temperatures in TableSTEP 5 : 5: SAT

VFunctional Criteria: UNSAT

. If Reactor Power is 2%

. If Reactor Power is >2%, then the CET readings are 545°F to650°F.


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


Charnel A Channel BG8 612 H8 666ElO 558 F9 XXXXE7 625 E8 603D5 XXXX 600

C12 568 FC8 621A8 XXXX

Standard:


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

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

EXAMINERNOTE



STEP 6

V

Standard:

(Step 4.10.5) RECORD Quadrant Four CET Temperatures in Table 6:



650°F.





The operator evaluates the data an determines that NO readings areoutside the 545°F and 650°F band; and places a CHECK in theFunctional 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 aCHECK in the Acceptance Criteria Results SAT Checkbox.

SAT

UNSAT

EXAMINERNOTE

Channel A Channel BL14 577 Ku 615L12 619 HiS 564J12 621 H13 623J10 621 H9 602Hil 604 E14 567G15 561 E12 614F13 621FlI 609



Attachment 2, Temperature Element Descriptions and Locations ATrain QSPDS and Attachment 3, Temperature Element Descriptionsand Locations B Train QSPDS provide a cross reference from

NOTE: temperature element core location to the specific temperature elementdesignation. The temperature element designation is required toproperly identify the component on any PWOs generated to addresstheir 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 AttachmentStandard: 1 and continues.

EXAMINERNOTE

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

• ChannelA• Channel B UNSAT


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



Channel A Channel BRepresentative CET Temp 642 644

The operator evaluates the data and determines that BOTH channelsare between 545°F and 650°F; and places a CHECK in theAcceptance Criteria Results Channel A and Channel B SATCheckbox.

EXAMINERNOTE

Standard:



(Step 4.10.8) RECORD the following CET Subcooling temperatures:STEP 9 • Channel A SAT

— • Channel B• Reactor Power UNSAT


CET Subcooling Temperatures are within the temperature rangebelow for the current reactor power:• 100% steady-state: 5°F-30°F


Channel A Channel BCET Subcooling temperatures: 12 10

The operator reactor power is 100%.Standard:

The operator evaluates the data an determines that CET SubcoolingTemperatures are within the temperature range below for 100%power; and places a CHECK in the Acceptance Criteria ResultsChannel A and Channel B SAT Checkbox.

EXAMINERNOTE


Appendix C Page ii of 14 Form ES-C-iPERFORMANCE INFORMATION

Identify any Technical Specification LCOs that are NOT met, and anySTEP 10 : ACTION required. SAT

VUNSAT

The operator evaluates Technical Specifications and determines thatLCO 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 thenumber of OPERABLE accident monitoring instrumentation channel(s)

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

EXAMINERNOTE

TerminatingSTOP

Stop Time




Job Performance Measure No.: 2013 Admin - JPM A2 SRO

Examinee’s Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:


Result: SAT UNSAT



I-LULU(0LUDC)

0

C’)LUE0U-

C)>

Appendix C Form ES-C-iJPM 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 theCore Exit Thermocouples by completing Section 4.10 of 3-OSP-204, Accident Monitoring Instrumentation ChannelChecks.

• Another operator will perform Attachment 1, QSPDSCET/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 betaken.




Worksheet

JPMA3RO&SRO

2013 Admin - JPM A3 RO & SRO (REV_021 81 3)NUREG 1021, Revision 9




Task Title: Evaluate Conditions for Restart of JPM No.: 2013 Admin - JPM A3Refueling Pre-shuffle in the Spent RO & SROFuel Pit

K/A Reference: GKIA 2.3.12 (3.2/3.7)



Method of testing:




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 SpentFuel 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 hours 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


• The following plant components are now inoperable:• Spent Fuel Pit skimmer pump is OOS.• Rl-3-1419B, Unit 3 SPENT FUEL PIT EXHAUST DUCT,

jpm ala ro - nrc: home page · 2013. 6. 11. · n41 100% bottom current = 194.1 microamps n42 100%...

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