ML090780288
| ML090780288 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 07/21/2008 |
| From: | NRC/RGN-II |
| To: | Florida Power & Light Co |
| References | |
| Download: ML090780288 (35) | |
Text
FACILITY NAME: ---..;S:;..;:t:.;.....;.L=u:;;..;;c:;..;..;ie~_ _ _ _ _ _ __ Section 12 REPORTNUMBER: __~20:;..;:O~8~-3~O~1_________________
FINAL ADMINISTRATIVE JPMS CONTENTS:
D Final ADMIN JPMs o 'As given' with changes made during administration annotated Location of Electronic Files:
Submitted By: _!2-t--=-.t_c_f'_(______ Verified By_ _IC_cTt.._+-_Z-
FLORIDA POWER & LIGHT NRC Admin. Exam
~ST LUCIE NRC LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM A-1 ADM Identify Correct Refueling Machine Positioning During In-Core Fuel Shuffle CANDIDATE EXAMINER ST LUCIE JPM A 1 1
FLORIDA POWER & LIGHT NRC Admin. Exam Determine Fuel Preconditioning Guidelines and Classification of Reactivity Event Examinee:
SAFETY FUNCTION ADMIN. TOPIC TESTING KIA #
ENVIRONMENT NONE Conduct of Classroom / Simulator 2.1.42 (3.4)
Operations POSITION FAULTED VALIDATED TIME TIME CRITICAL (YIN)
(YIN)
SRO Y 15 N STANDARD:
Determine Refueling Machine coordinates for in-core fuel movement.
REFERENCES:
- 3200090 Refueling Operation
- 1-NOP-67.04 Refueling Machine Operation INITIATING CUE:
STEP 1) Unit 1 is in Mode 6 performing an in-core fuel shuffle.
- Using the below data determine if the Refueling Machine positioning (Mast, Bridge and Trolley) is correct PRIOR to grappling on to element T41 from core location D-7.
- THEN determine if the Refueling Machine positioning is correct (Mast, Bridge and Trolley) to lower element T41 into core location V-3 (Refueling Machine Camera is in use).
Step # Mast Fuel Insert From Current Current Current Orientation ID ID Location Bridge Trolley Hoist Digital Digital Digital Readout Readout Readout 1 90 T41 57 D-7 659.14 683.80 Step # Mast Fuel Insert To Current Current Current Orientation ID ID Location Bridge Trolley Hoist Digital Digital Digital Readout Readout Readout 1 90 T41 57 V-3 740.63 651.21 ST LUCIE JPM A 1 2
FLORIDA POWER & LIGHT NRC Admin. Exam STEP 2)
- Using the below data determine if the Refueling Machine positioning (Mast, Bridge and Trolley) is correct PRIOR to grappling on to element S-20 from core location E-3.
- THEN determine if the Refueling Machine positioning (Mast, Bridge and Trolley) is correct to lower element S-20 into core location T -17 (Refueling Machine Camera is in use).
Step # Mast Fuel Insert From Current Current Current Orientation 10 10 Location Bridge Trolley Hoist Digital Digital Digital Readout Readout Readout 2 180 S-20 --------- E-3 667.21 651.19 Step # Mast Fuel Insert TO Current Current Current Orientation 10 10 Location Bridge Trolley Hoist Digital Digital Digital Readout Readout Readout 2 180 S-20 --------- T-17 732.60 732.91 START TIME END TIME DURATION (minutes)
OPERATOR PERFORMANCE AS EVALUATED TO STANDARD (circle one)
SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ __ DATE:
EXAMINER (print):
FLORIDA POWER & LIGHT NRC Admin. Exam
- indicates a "critical" step
- STEP STANDARD S/U
- 1. STEP 1) Refers to Figure 1 of 3200090 Directs Refueling Machine mast Refueling Operation or Figure 1 of 1-NOP- rotated to 270 OR 180 PRIOR to 67.04. Determines mast orientation needs latching on to element T 41.
to be 270 0 OR 180 0 PRIOR to latching on to fuel element T41 to move from 0-7 to V-3
- 2. Refers to Appendix G of 1-NOP-67.04 Determines Appendix G coordinates:
'Refueling Machine Operation' to determine 0-7 Bridge 659.11 Trolley 683.78 correct Bridge and Trolley coordinates.
V-3 Briage 740.69 Trolley 651.19 Coordinates must be within +/-0.05" of Appendix G prior to lowering Refueling Machine hoist.
- 3. Identifies Bridge and Troll~ym4;9t be within ActlJal.b~()~~inates :
+/-0.05" of Appendix G priorlblowering 0-7 Bridge/659.14 Trolley 683.80 Refueling Machine hoist.
V-3 Bridge 740.63 Trolley 651.21 Determines location V-3 Bridge coordinates NOT within +/-0.05".
Directs Refueling Machine operator to align Bridge to within +/-0.05 of 740.69.
I ***, , ' ;
- 4. STEP 2) Ref~rs to Appendix G of 1-NOp- i1Jetermines Appendix G coordinates:
67.04 'RefuelirlgM~Rhine.Operation' to ,/e" E-3 Bridge 667.24 Trolley 651.19 detercrl}i.ne c?:~;~eGt~ridge>*~Q~*.*.*~(811~y T-17 Bridge 732.63 Trolley 732.94 coorCJir1~te~/qpordinates:mu~t~'.~.~Within
+/-0.05" dfAp.R>sndix G prior to lowering Refueling M?chine hoist.
FLORIDA POWER & LIGHT NRC Admin. Exam
- indicates a "critical" step <. . ..
- STEP STANDARD StU
- 5. Identifies Bridge and Trolley must be within Actual coordinates:
+/-0.05" of Appendix G prior to lowering E-3 Bridge 667.21 Trolley 651.19 Refueling Machine hoist.
T-17 Bridge 732.60 Trolley 732.91 Determines Mast location correct.
Determines actual coordinates within
+/-O.'05". Permission to granted to mO'v'e'from core location E-3 to core 10ca'ti0I1\.T-17 .
ENDTIME:
.;,\
FLORIDA POWER & LIGHT NRC Admin. Exam INITIATING CUE:
STEP 1) Unit 1 is in Mode 6 performing an in-core fuel shuffle.
- Using the below data determine if the Refueling Machine positioning (Mast, Bridge and Trolley) is correct PRIOR to grappling on to element T 41 from core location D-7.
- THEN determine if the Refueling Machine positioning is correct (Mast, Bridge and Trolley) to lower element T41 into core location V-3 (Refueling Machine Camera is in use).
Step # Mast Fuel Insert From Current Current Current Orientation ID ID Location Bridge Trolley Hoist Digital Digital Digital Readout Readout Readout 1 90 T41 57 D-7 659.14 683.80 Step # Mast Fuel Insert To Current Current Current Orientation ID ID Location Bridge Trolley Hoist Digital Digital Digital Readout Readout Readout 1 90 T41 57 V-3 740.63 651.21 ST LUCIE JPM A 1 6
FLORIDA POWER & LIGHT NRC Admin. Exam INITIATING CUE (continued):
STEP 2)
- Using the below data determine if the Refueling Machine positioning (Mast, Bridge and Trolley) is correct PRIOR to grappling on to element 8-20 from core location E-3.
- THEN determine if the Refueling Machine positioning (Mast, Bridge and Trolley) is correct to lower element 8-20 into core location T-17 (Refueling Machine Camera is in use).
8tep# Mast Fuel Insert From Current Current Current Orientation ID ID Location Bridge Trolley Hoist Digital Digital Digital Readout Readout Readout 2 180 8-20 --------- E-3 667.21 651.19 8tep# Mast Fuel Insert TO Current Current Current Orientation ID ID Location Bridge Trolley Hoist Digital Digital Digital Readout Readout Readout 2 180 8-20 --------- T-17 732.60 732.91 ST LUCIE JPM A 1 7
FLORIDA POWER & LIGHT NRC Admin. Exam ST LUCIE NRC LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPMA2ADM Determine Shutdown Margin Criteria (SRO)
CANDIDATE EXAMINER ST LUCIE JPM A2 Page 10f4
FLORIDA POWER & LIGHT NRC Admin. Exam Perform Shutdown Margin Verification Surveillance Examinee:
SAFETY FUNCTION ADMIN. TOPIC TESTING KJA#
ENVIRONMENT NONE Equipment Classroom / Simulator 2.1.7 (4.7)
Control POSITION FAULTED VALIDATED TIME TIME CRITICAL (YIN)
(YIN)
SRO N 20 N STANDARD:
Direction to borate due to not meeting SDM requirements
REFERENCES:
- Unit 2 Plant Physics Curves
- 2-NOP-100.04, "Surveillance Requirements for Shutdown Margin; Modes 2,3,4, and 5 (Subcritical)"
INITIATING CUE:
Unit 2 was at 100% power for 100 days, 1143 EFPH. An automatic reactor I turbine trip just occurred. CEA 56 did not drop and is at 132" withdrawn. Current RCS temperature is 532°F, RCS Cb is 1062 ppm, and current time is 1500. You are directed to verify shutdown margin for the current plant conditions.
EXAMINERS NOTE: This SDM calculation was conducted using 1143 EFPH, cycle 17. Plant curves, Figure B.3 dated 3/4/08, Fig. B.4, B.5, B.6, B.8 dated 2/26/08, B.7 1/10108. Ensure the same revisions given to the applicants for performance of this JPM.
START TIME END TIME DURATION (minutes)
OPERATOR PERFORMANCE AS EVALUATED TO STANDARD (circle one)
SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ __ DATE:
EXAMINER (print):
FLORIDA POWER & LIGHT NRC Admin. Exam
- indicates a "cfitical" step
- STEP STANDARD S/U
- Step 50, Total Reactivity 6A
- Step 6B Boron worth
- Step 60 Shutdown Boron Concentration
- Step 6E Required Boron Concentration Step 7A Present Boron Concentration NOT Meeting shutdown ~""rl'1.. n
- Determines SDM not rni:i:t.i'fl'\r>,.
plant conditions ST LUCIE JPM A2 Page 3 of4
FLORIDA POWER & LIGHT NRC Admin. Exam INITIATING CUE:
Unit 2 was at 100% power for 100 days, 1143 EFPH. An automatic reactor / turbine trip just occurred.
CEA 56 did not drop and is at 132" withdrawn. Current RCS temperature is 532°F, RCS C b is 1062 ppm, and current time is 1500. You are directed to verify shutdown margin for the current plant conditions.
REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 28 LPSI Pump and Determine Associated Technical Specifications - UNIT 2 A-3 CANDIDATE _ _ _ _ _ _ _ _ _ _ _ _ __
EXAMINER
REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 28 LPSI pump KA Statement: Ability to obtain and interpret station electrical and mechanical drawings.
KA #: 2.2.41 (3.5 / 3.9)
References:
P&ID 2998-G-078 SH 130B P&ID 2998-G-078 SH 131 P&ID 2998-G-078 SH 105A ADM-09.08 Operations In-Plant Equipment Clearance Orders 2-ADM-03.01A Unit 2 Power Distribution Breaker List 2-ADM-03.01 C Unit 2 Power Distribution Breaker List MCC Operations Policy OPS-406 Clearance Database Conventions Candidate: Time Start ---
Name Time Finish _ __
Performance Rating: Sat Unsat Validation Time 25 minutes Examiner: Signature:
Comments ST. LUCIE TRAINING DEPT.
ADMINISTRATIVE JPM A-3 PAGE 2
REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 28 LPSI pump 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 28 LPSI pump has developed a shaft seal leak. The pump seal requires replacement. No other equipment is out of service Initiating Cue On the attached matrix, develop an ECO for the 28 LPSI Pump that would facilitate replacing the pump shaft seal. Identify any applicable Technical Specifications associated with removing the 28 LPSI pump from service.
ST. LUCIE TRAINING DEPT.
ADMINISTRATIVE JPM A-3 PAGE 3
Info Tag
- V3432 2B LPSI Pump Danger Suction Valve
- Breaker 2-42114 MCC breaker for Danger V3432
- V3205 2B LPSI Pump Recirc Danger Valve
- V3665 SDC Isolation Va Danger
- Breaker 2-42027 ' Danger
- V3539 Danger
- Breaker 2-42131
- V03001 Danger
- V3502 Danger
- Technical Specification:
3.5.2 Action a.1 Restore within 7 Days 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 ADM JPMA-3
(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)
Initial Conditions Unit 2 is at 100% power. The 28 LPSI pump has developed a shaft seal leak. The pump seal requires replacement. No other equipment is out of service Initiating Cue On the attached matrix, develop an ECO for the 28 LPSI Pump that would facilitate replacing the pump shaft seal. Identify any applicable Technical Specifications associated with removing the 28 LPSI pump from service.
ADM JPM A-3
(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)
Component Name Position Tag (type)
ADM JPMA-3
FLORIDA POWER & LIGHT NRC Admin. Exam ST LUCIE NRC LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM A4ADM Use a Survey Map To Determine Radiological Hazards CANDIDATE EXAMINER ST LUCIE JPM A4 Page 1 0'4
FLORIDA POWER & LIGHT NRC Admin. Exam Use a Survey map to determine radiological hazards Examinee:
SAFETY FUNCTION ADMIN. TOPIC TESTING KIA #
ENVIRONMENT NONE Radiation Classroom 1 Simulator KIA 2.3.14 (3.4/3.8)
Control POSITION FAULTED VALIDATED TIME TIME CRITICAL (YIN)
(YIN)
ROISRO N 10 N STANDARD:
Correctly determines radiological hazards in each Charging Pump room.
REFERENCES:
- Completed HPS-207 Charging Pumps Survey Map
- HPP-20 Area Radiation and Contamination Surveys INITIATING CUE:
Using the Survey map determine the radiological hazards in each Charging pump room.
START TIME END TIME DURATION (minutes)
OPERATOR PERFORMANCE AS EVALUATED TO STANDARD (circle one)
SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ _ __ DATE:
EXAMINER (print):
FLORIDA POWER & LIGHT NRC Admin. Exam
- indicates a "critical" step
- STEP STANDARD S/U
- 1. 2A Charging Pump Room
- Contaminated area
- Radiation Area
- 2. 28 Charging Pump Room
- Hot Spot
- 3. 2C Charging Pump Room
FLORIDA POWER & LIGHT NRC Admin. Exam INITIATING CUE: Using the Survey map, determine the radiological postings in each Charging pump room.
FLORIDA POWER & LIGHT NRC Admin. Exam LOCATION; FLORIDA F'O'VER & LIGHT - PSL CHARGING PUMPS - EL. -.5 IT BPS - "'*07
([.;,1 Glt.Il\'E :O.4.:.~GEJ!.
- V-:cl\1- ;-iIGH It..u:l ,Il.;::C,.1l (C) CON!,!!;!..:IJ!'4mD.Jt.BL4.
DAlE: 7/21/08 (t) l.CClG> HIGff RJIDARE..IL (P) HOT' p-.UJXl.E.u:L4.
TI]vlE: 0700 (H} r-aGa ltID .~4. {S) sP!!cm:c itill.'P REQlJIR.ID RPT (pRIrJT): B. Bora (K} R:\DLJLnON Jl.B:EA [J:S) Jill. CO\!UAGE REQUIR.ID 0-1) R.WIO.4.Cm:"E 1\L'l.lERLJU.
RPT SiGNATURE: .l301i.l30'3
(.l\.).lJFliOlt.'f./i! RAD:rO.4..c::m'lTY *.u.a4. I~ MDA= 25.78 dpm R\VP ;::;:u d 2504 j)"\ HlGEn.... r CO:t.."I.lLMJl{.UED *.ILll:E..IL la MDA= 17.32 dpm INSTRUMENT r{PE i # R020/3603 INSTRU1ffiNT TYPE I #: XLB T enn I 2 MilSsl:irm d'pm I HotPiL"'t INSTRU1tENT TI"PE l 1# L-177/21829 INSTRv""MENT nOPE! #: N/A No, probe iLveil YiN' e*.'a SMEARS ThJ ])PM 11~t) eM 1- ..\ < 1000 N 1 <1KL<MDA 6 <1KJ<MDA U <1K L<MDA 16 N/A L N/A 21 N/A/ N/A 26 N/A L N/A B N/A N/A 2 17 L N/A N/AL C N/A N/A
<1K/<MDA "I <1K /<MDA 22 <1K j<MDA N/A 22 N/A ')"'
_/ N/A I N/A D N/A N/A 3 2K L<MDA 8 <1K {.<MDA !J 2K I<MDA u; N/A l N/A 23 NlAL N/A 28 NlA t. N/A E N/A N/A 4 3K/< MDA 9 <1K {.< MDA 14- 3K I<MDA 19 NIA L N/A 2:4 NIA/ NIA 29 NIA t. NIA F N/A N/A 5 <1KL<MDA HI <1KL< MDA 1 <; <1K L< MDA ~() N/A L N/A '";~> N/A l. N/A .30 N/A L N/A G N/A N/A t:EGEND.
- ==General Area Dose Rates Reyiewed By:
'" Contact Dose Rate 0 =Smear Location C. Jones "'G/iar!.... 'Gnss 7/21/08 fJ =Neutron Dose Rate (mremlHr DOE) Pl."mtName Si~atme Date D =Beta Radiation in mRadlHr
--- = Radiation I Contaminated Boundarv_ . ~. . . " '
NlA .f G
N/A-1 Posting Room 3 2C CHARGING PUMP G) §
- 150
~
G) 0 NlA ----IW'III 10
~
CD
. - - - l i - - - - - i i l l - - - N/A
~-----L_ Posting 2B CHARGING PUMP Room 2 1
N/A - - -.....
1 N/A Posting
~-----==~~Ro~o=m~l~ ______~
II1II_ _ _ _ _ _ _ _ _ _ _ _111. 2A CHARGING PUMP ,- s 2 OPS DATE _ _ _ __
E:KpO~Ul'e Received! Completing S'lln;-ey: __2_____m , rem. DOCl ---",H=P..:::.S_ __
DOCN HPS-207 SYS --,,-H=P_ __
COMP _ _ _ __
ITh1 ST LUCIE JPM A4 Page 50f4
ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE PROTECTIVE ACTION RECOMMENDATIONS A-5 CANDIDATE _ _ _ _ _ _ _ _ _ _ _ __
EXAMINER
ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE PROTECTIVE ACTION RECOMMENDATIONS KA Statement: Knowledge of emergency plan protective action recommendations.
KA #: 2.4.44 (2.1 / 4.0)
References:
EPIP-08 Off-Site Notifications and Protective Action Recommendations Candidate: Time Start _ __
Name Time Finish - - -
Performance Rating: Sat Unsat Validation Time 15 minutes Examiner: Signature:
Comments ST. LUCIE TRAINING DEPT.
ADMINISTRATIVE JPM PAGE 2
ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE PROTECTIVE ACTION RECOMMENDATIONS 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 Unit 1 is in a refueling outage. RCS level was at 34' and lowering to mid-loop to install SG Nozzle Dams. Time to boil had been calculated to be 31 minutes. The equipment hatch is open. Subsequently a Station Blackout occurred. All efforts to restore AC power have been unsuccessful. All efforts to get water in the RCS have been unsuccessful. The equipment hatch crew could not get the hatch closed due to a malfunction of the closing device.
At time 0020, the containment has been evacuated and the Emergency Coordinator has declared a General Emergency due to uncovery of the fuel.
At time 0235 Initial manual off-site dose reports have come in and are as follows (only TEDE values are available at this time; CDE values are to be determined later):
1 mile: 4900 mrem 2 miles: 3000 mrem 5 miles: 1100 mrem Wind direction is from 56° Initiating Cue The Shift Manager has directed you to make Protective Action Recommendations for the next State of Florida Notification Form update.
THIS IS A TIME CRITICAL JPM ST. LUCIE TRAINING DEPT.
ADMINISTRATIVE JPM PAGE 3
START TIME: _ _ __ of EPIP-08; "Off-Site Notifications and Protective Action Recommendations" CRITICAL STEP 1: 2. Par Flowchart STEP A. PARs Based on Plant Conditions
- 1. Begin in the upper left hand corner of the chart by answering the General Emergency (GE) question.
- - SAT STANDARD: DETERMINE that a General Emergency exists.
- - UNSAT COMMENTS:
STEP 2: 2. Par Flowchart (cont.) CRITICAL A. PARs Based on Plant Conditions (cont.) STEP
- 2. Correctly answer the questions until you reach one of the boxes that provide PAR information based on plant conditions. - - SAT STANDARD: DETERMINE that Actual or Projected Severe Core Damage does exist. - - UNSAT COMMENTS: Core uncovery has occurred as described in the cue sheet.
STEP 3: 2. Par Flowchart (cont.)
A. PARs Based on Plant Conditions (cont.)
- 3. If there is no release, then go to the PAR Worksheet and fill in the PARs based on plant conditions. The sectors affected can be determined by referring to number 8, Weather Data - - SAT in Attachment 1A, Directions for completing the Florida Nuclear Emergency Notification Form.
- - UNSAT STANDARD: DETERMINE that a release has occurred.
COMMENTS: Offsite dose values from the cue sheet confirm a release.
ST. LUCIE TRAINING DEPT.
ADMINISTRATIVE JPM PAGE 4
STEP 4: 2. Par Flowchart (cont.)
A. PARs Based on Plant Conditions (cont.)
- 4. If a release is involved, then go to Section B, PARs Based on Off-site Dose. - - SAT STANDARD: DETERMINE that Section B needs to be addressed.
- - UNSAT COMMENTS:
STEP 5: 2. Par Flowchart (cont.)
B. PARs Based on Off-Site Dose
- 1. PARs are based on the Total Effective Dose Equivalent (TEDE or total dose) and/or the Committed Dose - - SAT Equivalent (CDE, thyroid dose). Do NOT use dose rate values.
- 2. If using the Class A Model, then in Forecast Mode, print the - - UNSAT State Notification Form Summary for computer generated PARs.
STANDARD: DETERMINE from the cue sheet data that the Class A Model is not to be used.
COMMENTS: Manual PAR determination will be used.
STEP 6: 2. Par Flowchart (cont.)
B. PARs Based on Off-Site Dose (cont.)
- 3. If dose calcs were performed manually using EPIP-09, Off-site Dose Calculations, then calculate TEDE and CDE in - - SAT accordance with the procedure.
- a. Compare the TEDE dose at 1 mile with the values on the Flowchart. Enter the chart at the appropriate - - UNSAT dose level.
STANDARD: DETERMINE that the TEDE dose at 1 mile is 4900 mrem. ENTER the chart at the TEDE 1000-4999 mrem dose level.
COMMENTS:
ST. LUCIE TRAINING DEPT.
ADMINISTRATIVE JPM PAGE 5
STEP 7: 2. Par Flowchart (cont.)
B. PARs Based on Off-Site Dose(cont.)
- 3. If dose calcs were performed manually using EPIP-09, Off-site Dose Calculations, then calculate TEDE and CDE in - - SAT accordance with the procedure. (cont.).
- b. From the selected dose level, move to the right on the chart to the first column, 0-2 miles. The PAR - - UNSAT provided corresponds to the calculated TEDE at 1 mile.
STANDARD: Under the 0-2 Miles column, DETERMINE that 'Evacuate All' is the correct classification.
COMMENTS:
STEP 8: 2. Par Flowchart (cont.)
B. PARs Based on Off-Site Dose(cont.)
- 3. If dose calcs were performed manually using EPIP-09, Off-site Dose Calculations, then calculate TEDE and CDE in - - SAT accordance with the procedure. (cont.).
- c. Enter the PAR in the 0-2 miles block on the TEDE DOSE table below the PAR Flowchart. The sectors - - UNSAT affected can be determined by referring to number 8, Weather Data, in Attachment 1A, Directions for Completing the Florida Nuclear Plant Emergency Notification Form.
STANDARD: ENTER 'ALL' under the Evacuate column, NONE under Shelter and No Action sectors on the 0-2 Miles row in the TEDE DOSE table.
COMMENTS:
ST. LUCIE TRAINING DEPT.
ADMINISTRATIVE JPM PAGE 6
STEP 9: 2. Par Flowchart (cont.) CRITICAL B. PARs Based on Off-Site Dose(cont.) STEP
- 3. If dose calcs were performed manually using EPIP-09, Off-site Dose Calculations, then calculate TEDE and CDE in accordance with the procedure. (cont.). SAT
- d. Continue to determine the corresponding PAR at 2-5 miles using the calculated 2 mile TEDE, at 5-10 miles using the calculated 5 mile TEDE and UNSAT the 10 miles plus (To Be Determined (TBD) distance) using the calculated 10 mile TEDE, as necessary.
STANDARD: DETERMINE from the cue sheet that the 2 mile TEDE dose is 3000 mrem and ENTER the TEDE DOSE column at the TEDE 1000-4999 mrem dose level.
Under the 2-5 Miles column, DETERMINE that 'Evacuate Sectors Affected and Shelter All Remaining' is the correct classification. DETERMINE from Attachment 1A that the affected sectors are 'KLMN' (this is the critical part of this step).
DETERMINE from the cue. sheet that the 5 mile TEDE dose is 1100 mrem and ENTER the TEDE DOSE column at the TEDE 1000-4999 mrem dose level.
Under the 5-10 Miles column, DETERMINE that 'Evacuate Sectors Affected and Shelter All Remaining' is the correct classification. DETERMINE from Attachment 1A that the affected sectors are 'KLMN' (this is the critical part of this step).
COMMENTS:
ST. LUCIE TRAINING DEPT.
ADMINISTRATIVE JPM PAGE 7
STEP 10: 2. Par Flowchart (cont.)
B. PARs Based on Off-Site Dose(cont.)
- 3. If dose calcs were performed manually using EPIP-09, Off-site Dose Calculations, then calculate TEDE and CDE in - - SAT accordance with the procedure. (cont.).
- e. Enter the PAR information in the appropriate blocks of the TEDE DOSE table. - - UNSAT STANDARD: ENTER the PAR information as per the attached Answer Key sheet in the TEDE DOSE table.
COMMENTS:
STEP 11: 2. Par Flowchart (cont.)
B. PARs Based on Off-Site Dose(cont.)
- 3. If dose calcs were performed manually using EPIP-09, Off-site Dose Calculations, then calculate TEDE and CDE in - - SAT accordance with the procedure. (cont.).
- f. Follow the same methodology for determining PARs corresponding to the calculated CDE - - UNSAT values beginning with the calculated value at 1 mile.
STANDARD: DETERMINE from the cue sheet that CDE dose values will be determined later.
COMMENTS:
ST. LUCIE TRAINING DEPT.
ADMINISTRATIVE JPM PAGE 8
STEP 12: 2. Par Flowchart (cont.)
C. Instructions for the PAR Worksheet
- 1. Fill in the time/date and emergency class.
SAT STANDARD: ENTER the present time and date and mark the 'GE' box on the PAR Worksheet. _ _ UNSAT COMMENTS: The PAR Worksheet is page 5 of 5 of Attachment 2.
STEP 13: 2. Par Flowchart (cont.) CRITICAL C. Instructions for the PAR Worksheet (cont.) STEP
- 2. In Part A, determine the most conservative PARs by comparing the PARs based on plant conditions against those based on off-site dose. SAT
- 3. Enter the most conservative PARs in the table in Part B, Protective Actions Recommended by FPL. Use the words, NONE, ALL, ALL REMAINING or list the UNSAT individual affected sectors by letter.
STANDARD: DETERMINE that the PARs based on off-site dose is the most limiting. The Off-Site Dose block is marked in Part A.
ENTER the PAR information in the table in Part B as per the attached Answer Key sheet.
COMMENTS:
ST. LUCIE TRAINING DEPT.
ADMINISTRATIVE JPM PAGE 9
STEP (donel: 2. Par Flowchart (cant.)
C. Instructions for the PAR Worksheet (cant.)
- 4. Obtain review and approval SAT STANDARD:
EXAMINER'S CUE: THIS JPM IS COMPLETE. UNSAT COMMENTS:
END OF TASK
- STOP TIME: _ _ __
- Critical Step: Must be S15 minutes from start time ST. LUCIE TRAINING DEPT.
ADMINISTRATIVE JPM PAGE 10
TEDE Use the following in this table:
NONE, ALL REMAINING or fill in the Letters of the sectors affected MILES EVACUATE SHELTER NO ACTION 0-2 ALL NONE NONE 2-5 K,L,M,N 5-10 K,L,M,N All
>10 Time I Date _ _ _ _ _._---,,~ Emergency Class _
PAR Comparison After comparing the possible most conservative PAR's are based on: one)
Protective Use the following' MAINING or fill in the Letters of the sectors affected SHELTER NO ACTION NONE NONE 0-2 Miles K, L, M, N All Remaining NONE 2-5 Miles K, L, M, N All Remaining NONE 5-10 Miles 10-TBD Miles*
- If necessary, add to State Notification Form ST. LUCIE TRAINING DEPT.
ADMINISTRATIVE JPM PAGE 11
CANDIDATE COpy (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)
Initial Conditions Unit 1 is in a refueling outage. ReS level was at 34' and lowering to mid-loop to install SG Nozzle Dams. Time to boil had been calculated to be 31 minutes. The equipment hatch is open. Subsequently a Station Blackout occurred. All efforts to restore AC power have been unsuccessful. All efforts to get water in the RCS have been unsuccessful. The equipment hatch crew could not get the hatch closed due to a malfunction of the closing device.
At time 0020, the containment has been evacuated and the Emergency Coordinator has declared a General Emergency due to uncovery of the fuel.
At time 0235 Initial manual off-site dose reports have come in and are as follows (only TEDE values are available at this time; CDE values are to be determined later):
1 mile: 4900 mrem 2 miles: 3000 mrem 5 miles: 1100 mrem Wind direction is from 56°.
Initiating Cue The Shift Manager has directed you to make Protective Action Recommendations for the next State of Florida Notification Form update.
THIS IS A TIME CRITICAL JPM