ML111540081

Initial Exam 2011-301 Final Administrative JPMs

ML111540081
Person / Time
Site:	Saint Lucie
Issue date:	04/18/2011
From:	NRC/RGN-II
To:	Florida Power & Light Co
References
50-335/11-301, 50-389/11-301
Download: ML111540081 (76)

Text

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM PERFORM A MANUAL CALORIMETRIC UNIT 2 Al APPLICANT EXAMINER Developed/Revised by: Larry Rich 2/1/11 Date Training Management Approval: Terry Benton 2/1/11 Date

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM PERFORM A MANUAL CALORIMETRIC UNIT 2 KA Statement: 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

KA#: 4.4/4.7

References:

2-3200020, Primary System Manual Calorimetric Rev 31 Steam Tables Calculator Applicant: Time Start Name Time Finish Performance Rating: Sat Unsat Validation Time 20 minutes Examiner: Signature:

Comments NRC JPM Al.

ADMINLSTRATIVE JPM PAGE 2

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM PERFORM A MANUAL CALORIMETRIC UNIT 2 Directions to the applicant for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Critical Tasks Critical task selection based upon 2-3200020, Primary System Manual Calorimetric, components directly contained in the Qcore calculation. See note prior to step 6.2.

Initial Conditions It is Monday, 2-21-1 1. Unit 2 is at approximately 30% (DCS calorimetric power is 30.28%), returning from a Forced Outage. A Chemistry hold is in effect until further notice.

Initiating Cue The Unit Supervisor has instructed you to perform a primary system manual calorimetric lAW 2-3200020. No computers are available to perform this calculation.

NRCJPMA1.

ADMINISTRATIVE JPM PAGE 3

Data Sheet if performed in classroom Steam Pressures Pl-8013A: 885 psia PI-8023A: 886 psia PI-8013B: 887 psia Pl-8023B: 886 psia Pl-8013C: 888 psia Pl-8023C: 887 psia PI-8013D: 889 psia PI-8023D: 886 psia Feedwater temperatures are 330 degrees F Total blowdown = 80 gpm Feed flow 9011-2 (ERDADS) = 1.56 xl 0E6 Ibm/hr Feed flow 9021-2 (ERDADS) = 1.56 xl 0E6 Ibm/hr DCS pt KFA = 29101 DCS pt KFB = 29345 Charging and Letdown are in operation NRC JPM Al.

ADMINISTRATIVE JPM PAGE 4

START TIME:

Data Sheet 1 of OP 2-3200020 Primary System Manual Calorimetric STEP 1: Date and Time STANDARD: ENTER 2/21/11 and current time.

SAT COMMENTS:

UNSAT STEP 2: ENTER MAIN STEAM PRESSURE P 1-801 3A___________

Pl-8023A____________

PI-8013B__________ SAT Pl-8023B____________

P 1-801 3C___________

Pl-8023C___________ UNSAT PI-8013D___________

PI-8023D___________

STANDARD: ENTER correct reads from PIs on RTGB-206 of Simulator Or 886.75 average for all pressures per classroom data Band: (886 887)

COMMENTS:

STEP 3: COMPUTE TOTAL FEEDWATER FLOW A. Loop x ÷ 29178 = xl 0 lb/hr (FT9O1 1-2 (ERDADS), or FR 9011) (DCS PT KFA)

SAT STANDARD: ENTER and CALCULATE UNSAT A. Loop 1.56 x 29101 ÷29178=1.556 x106 lb/hr (FT9O1 1-2 (ERDADS), or FR 9011) (DCS PT KFA)

Band: (1.55 1.56)

COMMENTS:

NRCJPMA1.

ADMINISTRAflVE JPM PAGE 5

STEP 4: COMPUTE TOTAL FEEDWATER FLOW B. Loop x ÷29050= xlO I

6 b/hr (FT9021-2 (ERDADS), or FR 9021) (DCS PT KFB) SAT STANDARD: ENTER and CALCULATE UNSAT B. Loop 1.56 x 29345 ÷ 29050 = 1.576 x 106 lb/hr (FT9021-2 (ERDADS), or FR 9021) (DCS PT KFB)

Band: (1.57 1.58)

COMMENTS:

STEP 5: COMPUTE TOTAL FEEDWATER FLOW MFw= 6 lb/hr x10 SAT (Total A+B Loop)

UNSAT STANDARD: ENTER and CALCULATE MFw= 3.132 xlO l

6 b/hr (Total A+B Loop)

Band: (3.123.14)

COMMENTS:

STEP 6: Average Steam Pressure = divided by 8 TOTAL AVERAGE SAT STANDARD: ENTER and CALCULATE Average Steam Pressure = 7094 divided by 8 886.75 UNSAT TOTAL AVERAGE Band: (886 887)

COMMENTS:

NRCJPMA1.

ADMINISTRATIVE JPM PAGE 6

STEP 7: ENTER FEEDWATER TEMPERATURE TR-09-5B Channel 1 (behind RTGB 202) SAT Channel 2 °F UNSAT STANDARD: ENTER TR-09-5B Channel 1 330 °F (behind RTGB 202)

Channel2 330 °F COMMENTS:

STEP 8: Average Feedwater Temperature = divided by 2 =

TOTAL AVERAGE STANDARD: ENTER and CALCULATE SAT Average Feedwater Temperature = 660 divided by 2 = 330 TOTAL AVERAGE UNSAT COMMENTS:

STEP 9: From the steam tables, enter the enthalpy of the average steam pressure:

hsTEAM=

SAT STANDARD: ENTER UNSAT hsi-EAM= 1196.7 BTU/lbm Band: (1197.30 1196.30)

COMMENTS:

NRC JPM Al.

ADMINISTRATIVE JPM PAGE 7

STEP 10: Calculate the heat output due to steam flow (QsTEAM): CRITICAL 106 106 STEP hsTEAM x [Mw - MBD] = QsTEAM SAT STANDARD: ENTER and CALCULATE UNSAT 1196.7 3.132 106 .039599 106 3700.68 106 BTU/hr hsTEAM x [MFw - MBD] = Q8TEAM Band: (1196.3-1197.3) Band: (3.12-3.14) Band: (3685 3712.11)

COMMENTS:

STEP 11: From the steam tables, enter the enthalpy of the average feedwater temperature:

hFw= SAT Ibm STANDARD: ENTER UNSAT hFw= 300.8 BTU Ibm Band: (298.7 302.93)

COMMENTS:

STEP 12: Calculate the heat feedwater heat input (QFw): CRITICAL STEP x10

)

6 x(_______ x1O B

6 TU MEw hEw QEw hr SAT STANDARD: ENTER and CALCULATE UNSAT (3.132 x 106) x 106]

( 300.8 )= 942.11 x MFw hFw QFw hr Band: (3.12-3.14) Band: (298.7-302.93) Band: (931 951.2)

COMMENTS:

NRCJPMA1.

ADMMSTRATIVE JPM PAGE 8

STEP 13: Circle the total blowdown flow from the S/Gs and the corresponding heat output:

(Interpolation is not required, circle the closest blowdown flow below or the lower flow if between flow rates, to be SAT conservative.)

Total blowdown flow Mass flow Heat output from UNSAT (both steam generators) of blowdown MBD blowdown QBD 40 GPM .019799 x 106 Ibm/hr 9.728 x 106 BTU/hr 80 GPM .039599 x 106 Ibm/hr 19.456 x 106 BTU/hr 120 GPM .059398 x 106 Ibm/hr 29.183 x 106 BTU/hr 160 GPM .079198 x 106 Ibm/hr 38.912 x 106 BTU/hr 200 GPM .098997 x 106 Ibm/hr 48.639 x 106 BTU/hr 240 GPM .118797 x 106 Ibm/hr 58.367 x 106 BTU/hr STANDARD: CIRCLE 80 GPM line Total blowdown flow Mass flow Heat output from (both steam generators) of blowdown MBD blowdown QBD 40 GPM .01 9799 x 106 Ibm/hr 9.728 x 106 BTU/hr

.039599 x 106 Ibm/hr i4561n6RT 120 GPM .059398x 106 Ibm/hr 29.183 x 106 BTU/hr 160 GPM .0791 98 x 106 Ibm/hr 38.912 x 1106 BTU/hr 200 GPM .098997 x 106 Ibm/hr 48.639 x 106 BTU/hr 240 GPM .118797 x 106 Ibm/hr 58.367 x 106 BTU/hr COMMENTS:

NRCJPM Al.

ADMINISTRATIVE JPM PAGE 9

STEP 14: Calculate the heat output from the core: CRITICAL If charging and letdown flow is secured for any reason, use a STEP value of 48.952 for Q0mER.

SAT If charging and letdown flow is operating normally, use a value of 46.905 for Q0mER.

UNSAT

- + - xio B

6 TU QsTEAM QFw QBD Q0THER hr Qc0RE hr STANDARD: ENTER and CALCULATE

[3700.68 942.11 + 19.456 46.9051 X 106 BTU = 2731.12 X 10 BTU QsTEAM QFw QBD Q0THER hr Qc0RE hr Band: (3685-3712.11) Band: (931 951.2)

Band: (2706 2754)

COMMENTS:

NRCJPMA1.

ADMINISTRATIVE JPM PAGE 10

NOTE CRITICAL Calculated Power in percent must be within 2% of DCS Calorimetric STEP power. If not, notify the US / SM. Initiate W/R for 1CM to adjust tT power.

SAT UNSAT STEP 15: Calculate percent core power:

Manual Core Power = x 106 divided by (92.128 x 106) =  % Calorimetric QCORE Power STANDARD: ENTER and CALCULATE Manual Core Power = 2731.12 x 106 divided by (92.128 x QCORE 106)

=1 29.64 % Calorimetric Power Band: (29.3 29.9)

Record DCS Calorimetric Power (QRP% 10 Minute aye). (QRPP (instantaneous) should be used below if the reactor hasjj been in a stable configuration for at least 10 minutes)

DCS Calorimetric Power =

COMMENTS:

NRC JPM Al.

ADMINISTRATIVE JPM PAGE 11

STEP (done): Inform Candidate JPM is complete.

STANDARD:

SAT EXAMINERS CUE: THIS JPM IS COMPLETE.

COMMENTS: UNSAT END OF TASK STOP TIME:

NRCJPMA1.

ADMINISTRATIVE JPM PAGE 12

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Initial Conditions It is Monday, 2-21-11. Unit 2 is at approximately 30% (DCS calorimetric power is 30.28%), returning from a Forced Outage. A Chemistry hold is in effect until further notice.

Initiating Cue The Unit Supervisor has instructed you to perform a primary system manual calorimetric lAW 2-3200020. No computers are available to perform this calculation.

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM NRC Al

SIMULATOR JPM SETUP

1. RESTORE IC-3, 29% power, MOL.

2. UNFREEZE simulator.

FOR INFORMATION ONLY Before use, verify revision and change documentation (if applicable) with a controlled index or document.

/1 DATE VERIFIED /11 INITIAL__*

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REVISION NO.: PROCEDURE TITLE:

4 31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEDURE NO 10 of 1 2-3200020 ST. LUCIE UNIT 2 DATA SHEET I (Page 2 of 3)

TABLE I Circle the total blowdown flow from the S/Gs and the corresponding heat output:

(Interpolation is not required, circle the matching blowdown flow below or the lower flow if between flow rates, to be conservative.)

Total blowdown flow Mass flow Heat output from (both steam generators) of blowdown MBD blowdown QBD 40 G .019799 x 106 Ibm/hr 9.728 x 106 BTU/hr 80 GPM 99 xiim/hr 19.456 x10BTU/hf) 120 GPM .059398 x 10 lbm/hEE13 x iO BTU/hr 160 GPM .079198 x 106 Ibm/hr 38.912 x 106 BTU/hr 200 GPM .098997 x 106 Ibm/hr 48.639 x 106 BTU/hr 240 GPM .118797 x 106 Ibm/hr 58.367 x 106 BTU/hr Calculate the heat output from the core:

If charging and letdown flow is secured for any reason, use a value of 48.952 for QOTHER.

If charging and letdown flow is operating normally, use a value of 46.905 for QOTHER.

(i,c_ 371t.19

, ii + /.,cto 7

q 1 - x 106 BTU =73I. I?x 10 pj QSTM QFW QBD QOTHER hr / QCORE 1r

(;z7o q) 275 NOTE Calculated Power in percent must be within 2% of DCS Calorimetric power.

If not, notify the US I SM. Initiate W/R for 1CM to adjust tT power.

Calculate percent core power:

Manual Core Power =? x 106 divided by (92.128 x 106) = Calorimetric QCORE / Power C .3 Record DCS Calorimetric Fower (QRP % 10 minute aye), (QRPP (instantaneous) should be used below if the reactor has been in a stable power configuration for at least 10 minutes):

DCS Calorimetric Power 30.2-8  %

REVISION NO.: PROCEDURE TITLE: PAG:

v 3

31 PRIMARY SYSTEM MANUAL CALORIMETRIC

.11 of 13 PROCEDURE NO.:

2-3200020 ST LUCIE UNIT 2 DATA SHEET I (Page3of3)

2. On the first Monday of the quarter, complete Data Sheet 2.

Initial

3. On the first Monday of the quarter, complete Data Sheet 3. &c Initial I have reviewed the requirements of this procedure including other surveillances performed during this procedure, if any (I.e., datasheet(s), PMT sheet(s), etc.). Any deviation(s) found during the performance of this procedure has (have) been listed an appropriate actions and notifications made.

RCO US/SM

FPL St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE DETERMINE TIME SDC ENTRY CONDITIONS ARE REQUIRED BASED ON AVAILABLE CST LEVEL -

UNIT1 NRC A2 Developed/Revised by: Larry Rich 2/1/11 Date Training Management Approval: Terry Benton 2/1/11 Date JPM NRC A2 Rev 0 Page 1 of 6

JOB PERFORMANCE MEASURE Task: Given a set of conditions, determine time SDC entry conditions are required based on available CST level Unit 1.

Faulted JPM? No Facility JPM #: New K/A: 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

K/A Rating(s): 3.9/4.2 Duty Area(s): N/A Task Information: 07200105 Task Standard:

Determine time SDC entry conditions are required based on available CST level Evaluation Location: Performance Level:

Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

a 1-EOP-99, Appendices/Figures/Tables/Data Sheets, Revision 41 Validation Time: 10 minutes Time Critical: NO Tools/Egui pmenllProcedures Needed:

a 1 -EOP-99, Appendices/Figures/Tables/Data Sheets, Data Sheet 1, Figures 3, 4, 5, 6, 7 and 8

• Calculator, Straight edge Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.

a None Radiological Protection and RWP Requirements:

• None JPM NRCA2 RevO Page 2 of 6

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

• The task you are to perform is: determine time SDC entry conditions are required based on available CST level Unit 1.

• The performance level to be used for this JPM is Perform.

• During the performance of the task, I will tell you which steps to simulate or discuss.

• I will provide you with the appropriate cues for steps that are simulated or discussed.

• You may use any approved reference materials normally available in the execution of this task, including logs.

• Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

INITIAL CONDITIONS:

• A Unit 1 reactor trip occurred from 100% power two (2) hours ago.

• One (1) RCP in EACH loop is operating.

• Reactor Coolant System Tcold is 530° F.

• Condensate Storage Tank (CST) level is 25 feet.

INITIATING CUES:

The Unit Supervisor has directed you to perform:

1 -EOP-99, Data Sheet 1, Determination Of Condensate Required to remove Decay Heat and RCP Heat to determine the time SDC entry is required.

JPM NRCA2 RevO Page3of6

JOB PERFORMANCE MEASURE START TIME:

DATA SHEET 1 DETERMINATION OF CONDENSATE REQUIRED TO REMOVE DECAY HEAT AND RCP HEAT STEP 1 (1): RECORD the current CST level below.

STANDARD: RECORDS 25 feet on Data Sheet 1 step 3.

SAT EXAMINERS NOTE: PROVIDE Data Sheet 1 and Figures 3, 4, 5, 6, 7, and 8 UNSAT COMMENTS:

STEP 2 (2): DETERMINE the number of CST feet needed to cool down from CRITICAL present RCS temperature to 300° F from Figure 3 RECORD STEP below.

STANDARD: RECORDS 3.7 feet on step 3, Figure 3 Value SAT EXAMINERS NOTE: Acceptable band 3.6 to 3.8 feet UNSAT COMMENTS:

STEP 3 (3): SUBTRACT Figure 3 value from current CST level. The result is CRITICAL CST inventory available for RCS cooldown. STEP STANDARD: RECORD 21.3 on step 3 Available CST level SAT EXAMINERS NOTE: Acceptable band 21.2 to 21.4 CST level UNSAT COMMENTS:

JPM NRC A2 Rev 0 Page 4 of 6

JOB PERFORMANCE MEASURE STEP 4 (4): Utilize the available CST level value from above and DETERMINE CRITICAL the time until SDC entry conditions are required using Figure 4, 5, STEP 6, 7, or 8 depending on the number of RCPs that are operating.

STANDARD: DETERMINES Figure 6 is used based on 2 RCPs running. SAT DETERMINES 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> until SDC entry is required UNSAT EXAMINERS NOTE: Acceptable range 17 to 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> based on 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after shutdown and 21.3 feet available in CST.

EXAMINERS CUE: When Data Sheet 1 is handed back, STATE: This JPM is complete.

COMMENTS:

END OF TASK STOP TIME:

JPM NRCA2 RevO Page5of6

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK)

INITIAL CONDITIONS:

• A Unit 1 reactor trip occurred from 100% power two (2) hours ago.

• One (1) RCP in EACH loop is operating.

• Reactor Coolant System Tcold is 53OF.

• Condensate Storage Tank (CST) level is 25 feet.

INITIATING CUES:

The Unit Supervisor has directed you to perform:

1 -EOP-99, Data Sheet 1, Determination Of Condensate Required to remove Decay Heat and RCP Heat to determine the time SDC entry is required.

JPM NRC A2 Rev 0 Page 6 of 6

REVISION NO.: PROCEDURE TITLE:

1 (J PAGE 41 PPENDICES I FIGURES I TABLES I DATA SHEETS PROCEDURE NO.:

1-EOP-99 ST. LUCIE UNIT I DATA SHEET I DETERMINATION OF CONDENSATE REQUIRED TO REMOVE DECAY HEAT AND RCP HEAT (Page 1 of 1)

This Data sheet yields the required Condensate Inventory in the Unit I CST necessary to maintain RCS temperature constant during post-trip operation with RCPs.

I. RECORD the current CST level below.

2. DETERMINE the number of feet of CST needed to cool down from present RCS temperature to 300°F from Figure 3 RECORD below.

3. SUBTRACT Figure 3 value from current CST level. The result is CST Inventory available for RCS cooldown.

Current CST level Figure3Value - 7 Feet (i-3 Available CST level =.2I3 Feet

( -

4. Utilize the available CST level value from above and DETERMINE the time until SDC entry conditions are required using Figure 4, 5, 6, 7 or 8 depending on the number of RCPs that are operating.

/7 .

Time until SDC entry is required:. (1? - Hours END OF DATA SHEET I

REVISION NO.: PROCEDURE 11TLE:

() PAGE 41 \PPENDICES I FIGURES I TABLES I DATA SHEETS PROCEDURE NO.:

126 1-EOP-99 ST. LUCIE UNITi FIGURE 6 TIME UNTIL SHUTDOWN COOLING REQUIREb VS. CONDENSATE AVAILABIIrIY 2 RCPs RUNNING (Page 1 ofil) ci L3

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REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 2A HPSI Pump and Determine Associated Technical Specifications UNIT 2 -

A3 APPLICANT EXAMINER DevelopedlRevised by: Larry Rich 2/1/11 Date Training Management Approval: Terry Benton 2/1/11 Date JPM NRC A3 Rev. 0

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 2A HPSI pump K/A: 2.2.13 Knowledge of tagging and clearance procedures.

K/A Rating(s): 4.1 I 4.3

References:

P&ID 2998-G-078 SH 130A P&ID 2998-G-083 SH 1 P&ID 2998-G-078 SH 105A CWD 2998-B-327 SH 237 ADM-09.08 Operations In-Plant Equipment Clearance Orders 2-ADM-03.O1A Unit 2 Power Distribution Breaker List Operations Policy OPS-406 Clearance Database Conventions Applicant: Time Start Name Time Finish Performance Rating: Sat Unsat Validation Time 20 minutes Examiner: Signature:

Comments JPM NRC A3 REV. 0 PAGE 2

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 2A HPSI pump Directions to the applicant for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference normally available in the Control Room to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 2 is at 100% power. The 2A HPSI pump has defective shaft seals and they are to be replaced. The 2B HPSI pump shaft seals have been determined to be satisfactory.

No other equipment is out of service.

Initiating Cue On the attached matrix:

1. Develop an Equipment Clearance Order for the 2A HPSI Pump that would facilitate replacing the pump shaft seals.

2. Identify any applicable Technical Specification actions associated with removing the 2A HPSI pump from service.

JPM NRC A3 REV. 0 PAGE3

Component Name Position Tag (type) 2A HPSI Control 2-CS-237 Off Info Tag Room Pump Switch

• Breaker 2-20201 2A HPSI Pump Racked Out Plus Danger Breaker 2-20201 Trip Fuse Removed N/A Breaker 2-20201 Close Fuse Removed N/A

• V3427 2A HPSI Pump Locked Closed Plus Danger Discharge_Valve

• V3470 2A HPSI Pump Locked Closed Plus Danger Suction_Valve

• V3202 2A HPSI Pump Recirc Locked Closed Plus Danger Valve

• V1 4259 2A HPSI Pump Locked Closed Plus Danger Cooling_Inlet_Isol

• V14262 2A HPSI Pump Locked Closed Plus Danger Cooling Outlet to Return_Hdr A_sol NOTE: The following drains and vent may be opened and tagged but only ONE VENT and ONE DRAIN is needed to be opened to meet the critical step. #As per Ops Policy 406, Vents and Drains d not reauire a danoer ta j. It is Dreferred. but not ieauired.

V3679 2AHPSI Pump Open #Danger Casing_Drain

• V3938 2A HPSI Pump Suct. Open #Danger Vent V3678 2A HPSI Pump Open #Danger Casing Drain

• Technical Specification:

3.5.2 Action a.2 Restore within 72 Hours or HSB next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> HSD the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

• Critical Step

1. As per Ops Policy 406, Vents and Drains do not require a danger tag. It is preferred, but not required JPMNRCA3REV.0

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference normally available in the Control Room to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 2 is at 100% power. The 2A HPSI pump has defective shaft seals and they are to be replaced. The 2B HPSI pump shaft seals have been determined to be satisfactory.

No other equipment is out of service.

Initiating Cue On the attached matrix:

1. Develop an Equipment Clearance Order for the 2A HPSI Pump that would facilitate replacing the pump shaft seals.

2. Identify any applicable Technical Specification actions associated with removing the 2A HPSI pump from service.

NRC A3

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Component Name Position Tag (type)

Technical Specification action:

NRC A3

Component Name Position Tag (type) 2A HPSI Control 2-CS-237 Off Info Tag Room Pump Switch

• Breaker 2-20201 2A HPSI Pump Racked Out Plus Danger Breaker 2-20201 Trip Fuse Removed N/A Breaker 2-20201 Close Fuse Removed N/A

• V3427 2A HPSI Pump Locked Closed Plus Danger Discharge_Valve W3470 2A HPSI Pump Locked Cjed Plus Danger Suction Valve

• V3202 2A HPSI Pump Reciru Locked ed Plus Danger Valve

• V1 4259 2A HPSI Pump ocked Clo Plus Danger Cooling_Inlet_Isol WI 4262 2A HPSI Pump d Close lus Danger Cooling Outlet o Return Hdçol NOTE: The following drains and opened and tagg ly ONE VENT and ONE DRAIN is needed to be openeneet th& critical step. #As per licy 406, Vents and Drains do not a danger jaci. It is preferred, but n ujredi V3679 ESl Pump Open #Danger P1_Drain

• V3938 2A , orçn #Danger V3678

• 2A HPSl Op #Danger Casing_Dra F

A w cification:

3.5.2 Action a.2 ReL or HSB next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> HSD the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

• C,jtjcal Step JPM NRC A3 REV. 0

EMERGENCY CORE COOLING SYSTEMS 314.5.2 ECCS SUBSYSTEMS OPERATiNG -

LIMITING CONDITION FOR OPERATION 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERABLE with each subsystem comprised of:

a. One OPERABLE high pressure safety injection pump,

b. One OPERABLE low pressure safety injection pump, and

c. An independent OPERABLE flow path capable of taking suction from the refuehng water tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal, and

d. One OPERABLE charging pump.

APPLICABILITY: MODES 1, 2, and 3**

ACTION:

a. 1. With one ECCS subsystem inoperable only because its associated LPSI train is inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

2. With one ECCS subsystem inoperable for reasons other than condition al., restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

With pressurizer pressure greater than or equal to 1750 psia.

ST. LUCIE UNIT 2

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, s-/ OPERATIONS DEPARTMENT POLICY Rev. 8 Date 03/24/10 CLEARANCE DATABASE CONVENTIONS OPERATIONS Page 7ofll Process Drained Process Drained ECOs will drain an isolated section of pipe for repairs, such as valve replacements, packing replacements, leak repair etc. When creating a Process Drained ECO, all energy sources, including trapped energy need to be accounted for and isolated. Once isolated the drain valve is opened prior to opening a vent. This is a safety issue. If draining hazardous material, remember 0-NOP-24.01. This is a generic Process Drained ECO.

Component Taç Type Placement Restoration 2-CHG PP 2A Non Off Auto 2-HS-CHG-2A Information In Place Tag Removed 2-40217 Danger Racked Out Plus Racked In 2-V2336 Danger Locked Closed Plus Locked Open 2-V2549 Danger Closed Plus Open 2-V2322 Danger Locked Closed Plus Locked Open 2-V2335 Danger Open Closed 2V02110* Non Open Closed Vents and drains do not require a danger tag. It is preferred, but not required. Some drains and vents may be removed during maintenance or need to be cycled during the performance of the scheduled work.

Unisolable ECOs The following is an excerpt from ADM-09.08.

The Nuclear Joint Safety Committee is responsible for reviewing and approving exceptions to the guidance of this procedure on a case-by-case basis, prior to implementation.

§ In cases where isolation boundaries can NOT be established for work affecting the pressure boundary, (e.g., work on the Reactor Vessel head, pressurizer or steam generator primary or secondary sides), an ECO which is controlled by Operations, as well as other departments performing said work, shall be GENERATED.

A. § This ECO shall LIST all such work.

B. § This EGO shall PLACE ECO Caution Tags, on in-service level, pressure, or temperature instruments which would be used to control fill and vent operations.

C. A vent path shall be established as determined by Operations.

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REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE EXPOSURE LIMITS UNDER EMERGENCY CONDITIONS SROA4 APPLICANT EXAMINER Developed/Revised by: Larry Rich 2/2/11 Date Training Management Approval: Terry Benton 2/2/11 Date

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM EVALUATE PERSONNEL EXPOSURE LIMITS KA Statement: 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

KA#: 3.2/3.7

References:

EPIP-02, Duties and Responsibilities of the Emergency Coordinator HP-2, Radiation Protection Manual HPP-30, Personnel Monitoring HPP-201, Emergency Personnel Exposure control NOTE: No references to be handed out for this task, but are available to the applicant.

Applicant: Time Start Name Time Finish Performance Rating: Sat Unsat Validation Time 10 minutes Examiner: Signature:

Comments NRC JPM SRO A4 Administrative JPM PAGE 2

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM EVALUATE PERSONNEL EXPOSURE LIMITS Directions to the applicant for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions A Large Break LOCA occurred on Unit 2 six hours ago.

• 2-EOP-03, LOCA is being implemented

• All safety functions are being met.

• The 2B and 2C charging pumps are operable.

A 10 gpm isolable leak had developed on the 2A Charging header. The reentry team was NOT successful in closing a valve to isolate the leak due to a broken reach rod.

Isolation of the leak is needed to prevent damage to the 2A Charging pump.

Dose rates initially taken three (3) feet from the valve were 2.8 R/hr. HP states the person performing this task will be working within two (2) feet of the valve. The job is estimated to take 45 minutes to perform with ingress and egress dose negligible.

The person performing this task has a year to date dose of 280 mR.

Initiating Cue As the EC (Emergency Coordinator) you have been asked to authorize a second reentry team tasked with disconnecting the reach rod linkage at the valve hand wheel and closing the valve.

Determine the following:

1. Calculate dose that will be received while performing the task.

2. State the procedural limits for this task.

3. State whether this task will be allowable under current procedures NRC JPM SRO A4 Administrative JPM PAGE 3

START TIME:

STEP 1: Calculate dose that will be received while performing the task. CRITICAL STEP STANDARD: Use Inverse square law to calculate dose rate at 2 feet. SAT

= DR 2

DR 1 2 )/(R 1

(R

)

UNSAT 2

DR = (2.8 RIhr) (3 ft) 2 /(2 ft)2 = 6.3 RIhr Apply 45 minutes to work valve:

6.3 Rlhr x 45 minutes x 1 hr/60 minutes = 4.725 R EXAMINERS CUE: NONE COMMENTS:

STEP 2: Procedure limits for this task CRITICAL STEP STANDARD: DETERMINES ACTIONS THAT WOULD NOT DIRECTLY MITIGATE THE SAT EVENT. LIMIT =5 R EXAMINERS CUE: NONE UNSAT COMMENTS:

STEP 3: State whether this task will be allowable under current CRITICAL guidelines. STEP STANDARD: YES 4.725 R <5 R LIMIT SAT EXAMINERS CUE: ACKNOWNLEDGE UNSAT EXAMINERS NOTE: If applicant incorrectly adds his 280 mr. exposure for the year to the 4.725 R for this task he! she will be> 5 R and may incorrectly NOT ALLOW THIS TASK.

COMMENTS:

STOP TIME:

NRCJPMSROA4 Administrative JPM PAGE4

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Initial Conditions A Large Break LOCA occurred on Unit 2 six hours ago.

• 2-EOP-03, LOCA is being implemented

• All safety functions are being met.

• The 2B and 2C charging pumps are operable.

A 10 gpm isolable leak had developed on the 2A Charging header. The reentry team was NOT successful in closing a valve to isolate the leak due to a broken reach rod.

Isolation of the leak is needed to prevent damage to the 2A Charging pump.

Dose rates initially taken three (3) feet from the valve were 2.8 RIhr. HP states the person performing this task will be working within two (2) feet of the valve. The job is estimated to take 45 minutes to perform with ingress and egress dose negligible.

The person performing this task has a year to date dose of 280 mR.

Initiating Cue As the EC (Emergency Coordinator) you have been asked to authorize a second reentry team tasked with disconnecting the reach rod linkage at the valve hand wheel and closing the valve.

Determine the following:

1. Calculate dose that will be received while performing the task.

2. State the procedural limits for this task.

3. State whether this task will be allowable under current procedures NRCJPMSROA4 Administrative JPM PAGE 5

REVISION NO.: PROCEDURE TITLE: PAGE:

47 PERSONNEL MONITORING PROCEDURE NO.:

.;..43of97 HPP-30 ST. LUCIE PLANT APPENDIX 6 AUTHORIZATION TO EXCEED ADMINISTRATIVE GUIDELINES (Page 2 of 4) 7.4 (continued)

4. §2 An individual with a complete Form 4 for the current year may have their site annual dose guideline extended to greater than 2500 mrem by the Radiation Protection Manager, the Plant General Manager and Site Vice President.

5. An individual with a complete Form 4 for the current year may have their annual dose guideline extended to greater than 3000 mrem / year, by the Radiation Protection Manager and Plant General Manager.

6. §2 The Plant General Manager and Radiation Protection Manager shall approve and the Site Vice President shall authorize all dose extensions above the annual guideline of 4500 mrem TEDE.

7. §2 After the TLD has been read and if the site annual TEDE is less than 2500 mrem, the individual may be allowed back into the Radiation Controlled Area until his / her annual TEDE (TLD results and EPD doses) reaches 2500 mrem.

8. Upon reaching an annual TEDE of 2500 mrem, the individual shall not be allowed to enter the Radiation Controlled Area, unless extended > 2500 mrerr

/ yr as required by step 7.4.4 above.

9. §2 FPL permanent employees should have their lifetime dose (TEDE) restricted to I XN where N is the employees age. If an FPL employee has a lifetime dose in excess of IXN, then Plant Manager approval is needed to exceed one rem (TEDE) for the year.

REVISION NO.: PROCEDURE TITLE:

16 EMERGENCY PERSONNEL EXPOSURE CONTROL PROCEDURE NO.:

HP-201 ST. LUCIE PLANT ATTACHMENT I EXPOSURE LIMITS FOR EMERGENCY RESPONSE PERSONNEL (Page 1 of 3)

NOTE

1. Both Total Dose (TEDE) and Thyroid Dose (CDE) should be used for purposes of controlling exposure.

2. Protective clothing, including respirators, should be used where appropriate.

For the following missions, the exposure limit is: Total Dose 2 THYROlD 3

(TEDE) (CDE)

Performance of actions that would not directly mitigate the event, minimize escalation, or minimize effluent releases. 5 REM 50 REM Performance of actions that mitigate the escalation to the event, rescue persons from a non-life threatening situation, minimize exposures or minimize effluent releases. 10 REM 100 REM Performance of actions that decrease the severity of the event or terminate the processes causing the event in an attempt to control effluent releases to avoid extensive exposure of large populations.

Also, rescue of persons from a life-threatening situation. 25 REM 250 REM Rescue of person from a life-threatening situation. (Volunteers 4

should be above the age of 45.) (5) (5)

(1) Exposure limits to the lens of the eye are 3 times the Total Dose (TEDE) values listed.

(2) Total Dose (TEDE) is the whole body exposure from both external and internal (weighted) sources Total Effective Dose Equivalent.

(3) Thyroid Dose (CDE) commitment from internal sources Committed Dose Equivalent.

The same dose limits also apply to other organs (CDE), skin (Shallow Dose Equivalent) and extremities (Extremity Dose Equivalent).

(4) Volunteers with full awareness of risks involved including numerical levels of dose at which acute effects of radiation will be incurred and numerical estimates of the risk of delayed effects.

(5) No upper limit for Total Dose (TEDE) and/or Thyroid Dose (CDE) exposure has been established because it is not possible to prejudge the risks that one person should be allowed to take to save the life of another. Also, no specific limit is given for thyroid exposure since in the extreme case, complete thyroid loss might be an acceptable sacrifice for a life saved. This should not be necessary if respirators and/or thyroid protection for rescue personnel are available as the result of adequate planning.

REVISION NO.: PROCEDURE TITLE:

47 PERSONNEL MONITORING PROCEDURE NO.: V HPP-30 ST. LUCIE PLANT APPENDIX 11 EMERGENCY EXPOSURES (Page 1 of 1)

7.0 Instructions

General This appendix contains the instructions necessary for authorizing emergency exposures and incorporating the emergency exposures into a persons exposure records.

7.1 §io The provisions of this appendix shall apply only to those situations in which exposure is received through the implementation of the St. Lucie Plant Emergency Plan and its implementing procedures.

7.2 § Each Emergency Response Person (ERP) exposure guideline is limited to 5.0 rem TEDE and 50 rem CDE unless exposures in excess of these guidelines is authorized by the Emergency Coordinator.

1. Any existing annual dose shall not be included in the ERP exposure guidelines.

2. The exposure guidelines are in effect for the duration of the emergency response as determined by FPL management.

7.3 ERP that have reached their guideline or extended guideline shall be removed from further exposure and have their dose determined.

7.4 §i, ERP emergency doses shall be evaluated against the regulatory limits in 10 CFR2O.1201.

1 Emergency doses shall be added to the occupational doses for the year in which the emergency doses are incurred.

2. ERP receiving a combination of occupational and emergency doses in excess of the limits in 20.1201 shall be restricted from any further exposure for the remainder of the year.

3. Any combined annual doses in excess of the limits in 20.1201 shall be accounted for as prescribed in 20.1206(e).

7.5 §i, Combined doses in excess of 20.1201 shall be reported to the Nuclear Regulatory Commission in accordance with established plant procedures.

END OF APPENDIX 11

Nuclear Plant Support Services NPSS.HP-WP.ool NUCLEAR DIVISION Rev. 15 Date: 0S127108 Radiation Protection Manual Page 34 of 79 during accidents and emergencies shall be determined and subtracted from the limits for PSEs.

3. Planned Special exposures must be authorized by both the Site Vice President Turkey Point? Site Vice President St. Lucie and the Chief Nuclear Officer. If the individual who will receive the PSE is not an FPL employee, the individuals employer shall also authorize the PSE.

4.1.3 Emergency Doses Under Emergency conditions, efforts should be made to maintain exposures to emergency response personnel as low as reasonably achievable taking into consideration benefits to public health and safety associated with the emergency conditions.

2. The performance of emergency services should be performed on a voluntary basis by non-declared pregnant adults. Persons undertaking any emergency operation, particularly one for which the dose is expected to be high (i.e.>25 rems), should be aware of the risks of radiation exposure.

3. Dose received from exposure under emergency conditions is added to the dose received during the current year, prior to the emergency, to determine compliance with the occupational dose limits in 10 CFR 20. Dose above regulatory limits will require reporting pursuant to 10 CFR 20.2202 and 20.2203.

Any dose in excess of the annual limits specified in 10 CFR 20.1201 (a) will be accounted for in accordance with 10 CFR 20.1206(e). If an individual exceeds any of these limits, then the individual will not be available for additional dose under 20.1201 (a).

4.1.4 Dose Limits for Individual Members of the Public The total effective dose equivalent to individual members of the public shall not exceed 100 mrem in a year; and

2. The dose in any unrestricted area from external sources shall not exceed 2 mrem in any one hour.

Nuclear Plant Support Services NPsS-IIP.wl-ool

. NUCLEAR DIVISION Rev. IS Date: 08/27/08 Radiation Protection Manual Page 33 of 79 and approval from the Plant General Manager, and the Site Vice President.

c. Greater than 3000 mrem/year TEDE from all sites requires review from the Health Physics Supervisor and approval from the Plant General Manager.

(1) Greater than 4500 mrem/year TEDE from all sites requires review from the Health Physics Supervisor and approval from the Plant General Manager, and the Site Vice President.

5. Circumstances requiring extending an annual guideline should be documented. The documentation should include the following:

a. Justification for the guideline extension; and

b. Evaluation of the individuals age and lifetime dose.

6. The administrative guideline for the dose to the embryo/fetus is 450 mrem during the entire pregnancy. Additionally, a monthly administrative guideline not to exceed 50 mrem/month has been established. The FPL guideline for the dose to the embryo/fetus of a declared pregnant woman shall not be exceeded. If the dose to the embryo/fetus is found to have exceeded 450 mrem by the time the woman declares her pregnancy, no additional dose to the embryo/fetus will be permitted during the remainder of the pregnancy. Refer to Section 2.1 .5 and NP-906 for handling work duties.

4.1.2 Planned Special Exposures Planned Special Exposures (PSE) shall be authorized only in exceptional situations when alternatives that might avoid the higher exposure are unavailable or impractical.

2. Prior to authorizing the PSE, all previous PSEs and all doses in excess of the routine occupational limits in effect at the time of the exposure for the individuals lifetime shall be determined from records and documented. Doses received in excess of routine occupational dose limits in effect at the time of the exposures

ST. LUCIE NUCLEAR PLANT ADMINISTRATIVE JPM DETERMINE EXPOSURE LIMITS UNDER NORMAL CONDITIONS ROA5 APPLICANT EXAMINER Developed/Revised by: Larry Rich 2/1/11 Date Training Management Approval: Terry Benton 2/1/11 Date

ST LUCIE NUCLEAR PLANT ADMINISTRATIVE JPM ST. LUCIE RADIATION REQUIREMENTS KA Statement: 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

KA#: 3.2/3.7

References:

HP-2, Radiation Protection Manual HPP-30, Personnel Monitoring NOTE: HP-2 and/or HPP-30 reference to be available to perform this task.

Applicant: Time Start Name Time Finish Performance Rating: Sat Unsat Validation Time 15 minutes Examiner: Signature:

Comments NRCJPM ROA5 ADMINISTRATIVE JPM PAGE 2

ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM ST. LUCIE RADIATION REQUIREMENTS Directions to the applicant for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 2 is in a refueling outage and refueling equipment preparations are under way. The Refueling Machine Hoist Box will need to be rebuilt.

The Hoist Box rebuild will take 45 minutes in a 2700 mR/hr field.

Below are the employees dose records:

Lifetime Current Year Current Year Contract total at all Age Dose FPL at St. Lucie Consult. sites (TEDE) (TEDE)

(TEDE) 1 25 27 R 350 mR 2550 mR 2 38 35 R 550 mR 2000 mR Lifetime Current Year Current Year FPL total at all Age Dose FPL at St. Lucie Employee sites (TEDE) (TEDE)

(TEDE) 1 40 27 R 550 mR 650 mA 2 38 33 A 450 mA 450 mA Initiating Cue What dose would be received for each person and which employee(s) are allowed to rebuild the Hoist Box without the Site Vice Presidents approval?

NRC JPM ROA5 ADMINISTRATIVE JPM PAGE 3

START TIME:

STEP 1: Calculates the dose the employee will receive performing the rebuild.

STANDARD: CALCULATES 2700 mR/hr x 45 mm x 1 hrI6O mm = 2025 mR.

COMMENTS: SAT UNSAT HP-2, FP&L Health Physics Manual CRITICAL STEP 2: Determines Contract employee #1s FPL Site and Total for All Sites doses. STEP STANDARD: DETERMINES that Contract employee #1 will exceed 4500 mR/year for All Sites and will need the St. Vice President approval. Therefore Contract employee #1 can NOT be used.

SAT EXAMINERS NOTE: Contract employee #1 would receive 2375 mR for St.

Lucie site and 4575 mR for all sites. Reference HP-2 step 4.1.1.4.c.(1) page

33. UNSAT If asked cue the exam inee that the provided dose is the total dose received as read from the individuals TLD.

COMMENTS:

STEP 3: Determines Contract employee #2s FPL Site and Total for All Sites doses. CRITICAL STEP STANDARD: DETERMINES that Contract employee #2 will not exceed FPL Site and Total for All Sites dose limits. Therefore Contract employee #2 CAN NOT be used.

EXAMINERS NOTE: Contract employee #2 would receive 2575 mR for St. SAT Lucie site and 4025 mR for all sites. Reference HP-2 step 4.1.1.4.b.(1) page 32.

UNSAT COMMENTS:

NRCJPM ROA5 ADMINISTRATIVE iPM PAGE 4

NRC JPM ROA5 ADMINISTRATIVE JPM PAGE 5

STEP 4: Determines FPL employee #1s FPL Site and Total for All Sites doses. CRITICAL STEP STANDARD: DETERMINES that FPL employee #1 will exceed 2500 mR/year for St.

Lucie Site and will need the St. Vice President approval. Therefore FPL employee #1 can NOT be used.

SAT EXAMINERS NOTE: FPL employee #1 would receive 2575 mR for St. Lucie site and 2675 mR for all sites. Reference HP-2 step 4.1.1.4.b.(1) page 32.

UNSAT COMMENTS:

STEP 5: Determines FPL employee #2s FPL Site and Total for All Sites doses. CRITICAL STEP STANDARD: DETERMINES that FPL employee #2will not exceed FPL Site and Total for All Sites dose limits. Therefore FPL employee #2 CAN be used.

SAT EXAMINERS NOTE: FPL employee #2 would receive 2475 mA for St. Lucie site and 2475 for all sites. Reference HP-2 step 4.1.1 .4.b.(1) page 32.

UNSAT COMMENTS:

STEP (done): Candidate informs the Examiner that the task is complete.

STANDARD: INFORMS the Examiner that the task is complete.

EXAMINERS CUE: TASK IS COMPLETE SAT COMMENTS:

UNSAT END OFTASK STOP TIME:

NRCJPM ROA5 ADMINISTRATIVE JPM PAGE 6

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Initial Conditions Unit 2 is in a refueling outage and refueling equipment preparations are under way. The Refueling Machine Hoist Box will need to be rebuilt.

The Hoist Box rebuild will take 45 minutes in a 2700 mR/hr field.

Below are the employees dose records:

Lifetime Current Year Current Year Contract total at all Age Dose FPL at St. Lucie Consult. sites (TEDE) (TEDE)

(TEDE) 1 25 27 R 350 mR 2550 mR 2 38 35 R 550 mR 2000 mR Lifetime Current Year Current Year FPL total at all Age Dose FPL at St. Lucie Employee sites (TEDE) (TEDE)

(TEDE) 1 40 27 R 550 mR 650 mR 2 38 33 R 450 mR 450 mR Initiating Cue Which employee(s) are allowed to rebuild the Hoist Box without the Site Vice Presidents approval?

NRC JPM ROA5

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM RESPOND TO SECURITY EVENT (SRO)

A6 Portions of this JPM are TIME CRITICAL Developed/Revised by: Larry Rich 2/1/11 Date Training Management Approval: Terry Benton 2/1/11 Date

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM RESPOND TO SECURITY EVENT KA Statement: 2.4.28 Knowledge of procedures relating to security event (non safeguards information)

KA#: 3.2/4.1

References:

O-AOP-72.O1, Response to Security Events EPIP-Ol, Classification of Emergencies EPIP-02, Duties and Responsibilities of the Emergency Coordinator EPIP-08, Off-Site Notifications and Protective Action Recommendations Applicant:

Name Validation Time: 30 minutes Start Time:

Finish Time:

Performance Rating: Sat Unsat Examiner: Signature:

Comments NRC ADM JPM A6 Page 2 of 20

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM RESPOND TO SECURITY EVENT Directions to the applicant for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Both Units are at 100% power.

Today at current time, you as the Shift Manager, receives a report from Security that armed intruders have entered the protected area and are near the cafeteria. No shots have been fired at this time.

Initiating Cue You are located in Unit2.

As the Shift Manager you are to implement 0-AOP-72.01, Response to Security Events NOTE: Portions of this JPM are time critical Portions of this JPM are time critical NRC ADM JPM A6 Page3of2O

START TIME:

TIME CRITICAL O-AOP-72.O1, Response to Security Events START TIME STEP 1 (4.2.2): VERIFY neither of the following have occurred:

SAT

• Security Department reports armed intruders are UNSAT within the Protected Area.

• An aircraft has impacted inside the Protected Area.

STANDARD: DETERMINES from cue armed intruders are within the protected area.

EXAMINERS CUE: NONE EXAMINERS NOTE: This should be the start time to classify the event START TIME_________

COMMENTS:

STEP 2 (4.2.2.2.1): TRIP Unit 1 reactor CRITICAL STEP DIRECTS Unit 1 US to trip the reactor.

SAT STANDARD: DIRECTS Unit 1 US to trip the reactor.

UNSAT EXAMINERS CUE: Unit 1 reactor is tripped COMMENTS:

NRC ADM JPM A6 Page 4of 20

STEP 3 (42.2.2.2): TRIP Unit 2 reactor CRITICAL STEP STANDARD: DIRECTS Unit 2 Us to trip the reactor. SAT EXAMINERS CUE: Unit 2 reactor is tripped UNSAT COMMENTS:

STEP 4 (4.2.2.2.3): DON headset attached to Control Room Security hotline phone.

SAT STANDARD: May DELEGATE to another Licensed Operator to DON headset or UNSAT DON the head set.

EXAMINERS CUE: Licensed Operator has DONNED headset COMMENTS:

STEP 5 (4.2.3): IMPLEMENT Security Checklist per EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

SAT STANDARD: REFERS to EPIP-02, Duties and Responsibilities of the Emergency Coordinator, Security Checklist. UNSAT EXAMINERS CUE: NONE COMMENTS:

NRC ADM JPM A6 Page 5 of 20

EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

STEP 6 (5.2): 5.2 Security Checklist for Land-Based Threat SAT D. Land-Based Threat UNSAT

1. Verify the Control Rooms are implementing 0-AOP-72.01, Response to Security Events.

• Uniti

• Unit2 STANDARD: IMPLEMENTS EPIP-02 section 5.2 Security Checklist.

CONTACTS Unit 1 and Unit 2 Unit Supervisors and directs the continuance of 0-AOP-72.01, Response to Security Events.

EXAMINERS CUE: Unit 1 and Unit 2 Unit Supervisors acknowledge.

EXAMINERS NOTE: A cue may need to be given that the Control Room crews will perform continue performing O-AOP 72.01.

COMMENTS:

NRCADMJPMA6 Page 6of 20

EPIP-02, Duties and Responsibilities of the Emergency Coordinator. CRITICAL STEP STEP 7: 5.2 Security Checklist SAT

2. Off-Site Notifications NOTE UNSAT If a threat has been validated via phone call to the NRC Headquarters, the accelerated notification to the NRC is not required.

A. §2 Make an accelerated notification to the NRC (reference EPIP-08).

This is the St. Lucie Plant. My name is _Applicants Name_. My title is _Shift Manager_. I am providing notification of a Security Event. Brief Description_Armed Intruders in the protected area_. Unit 1 is in Mode_3_, _O  % Power. Unit 2 is in Mode_3_, _O_%Power. Additional information will be provided as soon as practical.

STANDARD: COMMUNICATES to the NRC the above information EXAMINERS CUE: NRC has been notified.

COMMENTS:

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EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

STEP 8 (1): 5.2 Security Checklist SAT

3. ERG Activation UNSAT NOTE The PSL Conference Bridge can be used to communicate with the ERO at an alternate, location. Refer to the PSL Emergency Response Directory (ERD) for the phone number and password.

A. Normal business hours

1. Delay activation of the Emergency Response Facilities or direct ERO personnel to an alternate Location.

2. Request off-site responders to go to EOF I alternate facility per EPIP-03, Attachment 4.

B. Off-normal hours based on site accessibility, consider directing ERG personnel to report to the EOF or alternate location.

STANDARD: DETERMINES delay or activation of the ERO personnel EXAMINERS CUE: If asked it is normal business hours EXAMINERS NOTE: Due to the nature of the event the ERO call out will probably be delayed. Activation of the EOF is permissible due to the EOF location is off site. Call outs should be delegated.

COMMENTS:

NRC ADM JPM A6 Page 8 of 20

EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

STEP 9 (1): 5.2 Security Checklist: SAT

4. For further information, go to the appropriate procedure IJNSAT below:

A. 0-AOP-72.01, Response to Security Events B. §3 EDMG-01, Guidelines for Responding to Large Area Fire or Explosion Involving Multiple Fire Zones.

C. SF1 #6310 Threat Assessment and Notifications.

STANDARD: DETERMINES 0-AOP-72.01 is already being implemented OR call the Unit Supervisors to ensure the AOP is being implemented then continue with EPIP-02.

EXAMINERS CUE: None or respond as US the AOP is being implemented.

EXAMINERS NOTE: The Shift Manager should NOT get involved with the AOP as he I she is the Emergency Coordinator and attention should be focused on the E-PIan.

The Unit Supervisors should be implementing the Security AOP at each Unit.

COMMENTS:

NRC ADM JPM A6 Page 9 of 20

EPIP-02, Duties and Responsibilities of the Emergency Coordinator.

STEP 10 (1): 5.2 Security Checklist: SAT

5. Implement appropriate Emergency Plan Implementing LJNSAT Procedures (EPIPs).

STANDARD: IMPLEMENTS EPIP-Ol Classification of Emergencies EXAMINERS CUE: NONE COMMENTS:

EPIP-Ol Classification of Emergencies TIME CRITICAL STEP 11(1): 5.3 Classifying the Event: STEP STANDARD: IMPLEMENTS EPIP-Ol Classification of Emergencies and SAT DETERMINES classification of SITE AREA EMERGENCY under HS4 HOSTILE ACTION within the PROTECTED AREA UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: Applicant should refer to Attachment 1 and classify the event at this time.

CLASSIFICATION TIME______________

Must be < 15 minutes from time noted in step 1 of this JPM. This is also the 15 minute start time to notify the State.

EXAMINERS CUE: None COMMENTS:

NRC ADM JPM A6 Page lOof 20

EPIP-08 Off-Site Notifications and Protective Action Recommendations APPENDIX A SAT NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM STEP 12 (1): If Security Event, Then go to Step 3.A.1 .a NRC Notification or N/A. UNSAT STANDARD: DETERMINES step is N/A/ as the NRC has been previously notified EXAMINERS CUE: NONE COMMENTS:

EPIP-08 Off-Site Notifications and Protective Action Recommendations APPENDIX A SAT NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM STEP 13 (2): State Watch Office Notification UNSAT A. Prepare the Florida Nuclear Plant Emergency Notification Form (form similar to Attachment 1).

2. All other Security and Non-Security Events Prepare the State Notification Form in accordance with Attachment 1A, Directions for Completing the Florida Nuclear Plant Emergency Notification Form.

STANDARD:

EXAMINERS CUE: NONE EXAMINERS NOTE: Per step 5.1 .2.A.1 of EPIP-08, lines 1-11 of the notification form shall be completed.

COMMENTS:

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e3i ATTACHMENT 1 eRtrlcAL FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM &TEP-STEP 14 (Line 1): SAT

1. A. THISlSADRlLL B. LITHISISANEMERGENCY UNSAT STANDARD: Checks A EXAMINERS CUE: NONE EXAMINERS NOTE: Per EPIP-08, Attachment 1 A step 1, drill, exercises or tests, each message shall be checked this is a drill COMMENTS:

STEP 15 (Line 2): CRITICAL STEP

2. A. Date: I / B.

• Contact Time: Reported by: (Name)

D. Message Number: Reported from: Control Room Q TSC Q EOF F. Q Initial / New Classification OR Q Update Notification SAT STANDARD: A. Todays Date B. Time contact made left blank at this time UNSAT C. Applicants name D. Message # 1 E. Control Room F. Initial I New Classification EXAMINERS CUE: NONE EXAMINERS NOTE: Part B Contact time must be within 15 minutes of the emergency classification time EXAMINERS NOTE: Contact time shall be filled in when contact is made with the state.

EXAMINERS NOTE: Only the

• step is CRITICAL COMMENTS:

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STEP 16 (Line 3):

EP 3* Site: A. El Crystal River Unit 3 B. El St. Lucie Unit 1 C. St. Lucie Unit 2 D. El Turkey Point Unit 3 E. El Turkey Point Unit 4 SAT STANDARD: C, St. Lucie Unit 2 (St. Lucie Unit 2 is expected, Unit 1 is acceptable, but not both marked)

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: EPIP Attachment 1A step 3 requires only one affected unit be selected (either one can be selected but not both).

COMMENTS:

STEP 17 (Line 4): CRITICAL 4*

STEP Emergency Classification:

A. El Notification of Unusual Event B. El Alert C. Site Area Emergency D. El General Emergency SAT STANDARD: C, Site Area Emergency UNSAT EXAMINERS CUE: NONE COMMENTS:

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STEP 18 (Line 5): CRITICAL STEP 5* A. Emergency Declaration: B.LI Emergency Termination:

Date: I / Time:

SAT STANDARD: A, Emergency Declaration time and date. UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: This is the time emergency declaration is made. (Step 11 of this JPM)

COMMENTS:

STEP 19 (Line 6): CRITICAL STEP 6.* Reason for Emergency Declaration:

A. EAL Number HS4 OR B. LI

Description:

SAT STANDARD: A. EAL Number HS4, Hostile Action UNSAT EXAMINERS CUE: NONE COMMENTS:

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STEP 20 (Line 7):

7. Additional Information or Update: A. LI None OR B.

Description:

armed intruders in the protected area Unit 1 and Unit 2 are affected._________ SAT STANDARD: B. ADD additional information armed intruders in the protected area Unit 1 UNSAT and Unit 2 are affected.

EXAMINERS CUE: NONE EXAMINERS NOTE: If both Units affected, should state in the additional information section.

COMMENTS:

STEP 21 (Line 8): CRITICAL STEP 8.* Weather Data:

A. Wind direction from 94° degrees B. Downwind Sectors Affected: MNP SAT STANDARD: DETERMINES sectors affected MNP (step 8G, Page 45 of EPIP-08)

UNSAT EXAMINERS CUE: Wind Direction from 94° EXAMINERS NOTE: Applicant should determine sectors affected MNP (step 8G, PagE 45 of EPIP-08)

EXAMINERS NOTE: If performed in simulator, student correctly uses ERDADS wind direction. Downwind sectors per step 8G of EPIP-08 COMMENTS:

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STEP 22 (Line 9): CRITICAL STEP 9* Release Status: A. None (Go to Item 11) B. LI In progress C. El Has occurred, but stopped (Go to Item 11)

SAT STANDARD: NONE (Go to item 11)

UNSAT EXAMINERS CUE: NONE COMMENTS:

STEP 23 (Line 11): CRITICAL STEP 11.* UTILITY PROTECTIVE ACTION RECOMMENDATIONS FOR THE PUBLIC:

A. No utility recommended actions at this time.

Ifform is completed in the Control Room, go to Item 15 SAT UNSAT STANDARD: A. No utility protective action recommendations for the public. Goes to item 15 EXAMINERS CUE: NONE COMMENTS:

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STEP 24 (Line 1 5): Emergency Coordinator (EC) approval.

15.(Do Not Read) EC or RM Approval Signature: I /

Time: SAT STANDARD: Documents approval including date and time.

UNSAT EXAMINERS CUE: NONE COMMENTS:

STEP 25 (2.C): Using the State HOT RINGDOWN PHONE, dial 100 CRITICAL STEP SAT STANDARD: Dials 100 on the State HOT RINGDOWN PHONE.

EXAMINERS CUE: 100 has been dialed. UNSAT COMMENTS:

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STEP 26 (.2.D): TIME Hold down the button on the handset while talking. This must be CRITICAL done each time you talk. Release the button in order to listen. STEP When the State Duty Officer answers, announce:

This is St. Lucie Nuclear Plant [as applicable (Unit 1, 2)j with an SAT emergency message. Contact Time is I am standing by to transmit the Florida Nuclear Plant Emergency Notification Form when you are ready to copy. UNSAT Allow the Duty Officer to contact St. Lucie County, Martin County and the Bureau of Radiation Control prior to transmitting the information from the notification form. When the parties are on line, provide the information slowly (e.g., in three word intervals) and deliberately, providing time for the information to be written down.

On-line Verification: [1 SWP/DEM Li DOH/BRC

[1 St. Lucie County/Ft. Pierce [1 Martin County STANDARD: VERIFIES the above are on line. Communicates message. States the contact time as the current time.

EXAMINERS CUE: Answer as the State Watch Office. The above agencies are on line.

EXAMINERS NOTE: Contact time above is Stop time for time critical step. This time must be less than 15 minutes from the time listed in step 11.

EXAMINERS NOTE: Applicant should go back to step 2 of this form and fill in Contact Time.

EXAMINERS NOTE: Upon completion of communication, terminate the task.

Time classified event (step 11) Time contact made to state___________

COMMENTS:

END OF TASK STOP TIME__________

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CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference needed to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Both Units are at 100% power.

Today at current time, you as the Shift Manager, receives a report from Security that armed intruders have entered the protected area and are near the cafeteria. No shots have been fired at this time.

Initiating Cue You are located in Unit 2.

As the Shift Manager you are to implement 0-AOP-72.01, Response to Security Events NOTE: Portions of this JPM are time critical NRCADMJPMA6

FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM On-line Verification: U SWP/DEM [] DOHIBRC U St. Lucie County/Ft. Pierce El Martin County

1. A. ThISlSADRILL B. Q This IS AN EMERGENCY

2. A. Date: / / B.

• Contact Time: C. Reported by: (Name) -

D. Message Number: *__

E. Reported from: Control Room El TSC El EOF F. Initial I New Classification OR El Update Notification 3,* jg: A. []Crystal River Unit 3 B. El St. Lucie Unit 1 C. St. Lucie Unit 2 D. El Turkey Point Unit 3 E. El Turkey Point Unit 4 4** Emergency Classification: A. El Notification of Unusual Event B. El Alert C Site Area Emergency D. El General Emergency 5* A. Emergency Declaration: B. El Emergency Termination: Date: / / Time:

6.* Reason for Emergency Declaration: A. EAL Number HS4 OR B. El

Description:

7. Additional Information or Update: A. El None OR B.

Description:

Armed Intruders in the protected area both Units are affected.

8. Weather Data: A. Wind direction from 94 degrees B. Downwind Sectors Affected: MNP 9* Release Status: A. None (Go to Item 11) B. El In progress C. El Has occurred, but stopped (Go to Item 11)

10. Release Significance Category (at the Site Boundary):

A. El Under evaluation.

B. El Release within normal operating limits ( 3.5 E-1 Ci/sec noble gas, 4.6 E-5 Cl/sec iodine)

C. El Non-Significant Fraction of PAG Range (release is > normal limits and < 500 mrem TEDE and 1000 mrem CDE)

D. El PAG Range ( 500 mrem TEDE or 1000 mrem CDE)

E. El Liquid release (no actions required) 11.* UTILITY PROTECTIVE ACTION RECOMMENDATIONS FOR ThE PUBLIC:

A. No utility recommended actions at this time.

B. El The utility recommends the following protective actions:

Evacuate Sectors Shelter Sectors No Action Sectors Evacuate Zones: OR 02 Shelter Zones: 25 510 AND consider issuance of potassium iodide (KI)

Ifform 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? El Yes El No B. Core Adequately Cooled? El Yes El No C. Containment Intact? El Yes El No D. Core Condition: El Stable El Degrading

13. Weather Data: A.

• Wind Speed mph B. Stability Class

14. Additional Release Information: A. El N/A OR Read this statement: I hour projected doses as follows:

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

mrem mrem

15. (Do Not Read) EC or RM Approval Signature: Date: / / Time:

Message Received By: Name:____________________ Date: / / Time:

• Items are evaluated for NRC Performance Indicators (P1s)