ML100620150

Initial Exam 2009-301 Draft Administrative JPMs

ML100620150
Person / Time
Site:	Saint Lucie
Issue date:	02/09/2010
From:	NRC/RGN-II
To:
References
50-335/09-301, 50-389/09-301
Download: ML100620150 (100)

Text

{{#Wiki_filter:FACILITY NAME: __ S.;:;.t;;.;... -=L~uc;:;.;;.ie~ ___ _ Section 6 REPORTNUMBER:_~20~O~9~-3~O~1 ________________________ _ DRAFT ADMINISTRATIVE JPMS CONTENTS: o Draft ADMIN JPMs Location of Electronic Files: h A' ~::=-:::, Submitted By: /~~ Verified By: _______ F ACI LlTY NAM E: __ .;:;.St;::., *.=L.=..uc=.:,i.=..e ___ Section 6 REPORTNUMBER: __ ~2~OO~9~-3~O~1~ _______ ____ DRAFT ADMINISTRATIVE JPMS CONTENTS: D Draft ADMIN JPMs ( Location of Electronic Files: h A" '~ Submitted By: /~d',6 Verified By: ________

ES-301 Administrative Topics Outline Form ES-301-1 Facility: St. Lucie Plant Date of Examination: 10/19/09 Examination Level: RO ~ SRO ~ Operating Test Number: HLC-19 NRC Administrative Topic Type Describe activity to be performed (see Note) Code* M Perform an Estimated Critical Condition Calculation - Unit 2 Conduct of Operations M Perform a Manual Calorimetric at 45% power. Conduct of Operations N Develop ECO for Unit 1 Containment Spray Pump. Equipment Control N Perform Immediate Operator Actions For a Dropped New Fuel Element (SRO) Radiation Control D Operate Portable Radiation Monitoring Equipment (RO) M,P Determine PARs During Core Melt Scenario (SRO) Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:::; 3 for ROs; :::; 4 for SROs & RO retakes) (N)ew or (M)odified from bank (?: 1) (P)revious 2 exams (:::; 1; randomly selected) ES-301 Administrative Topics Outline Form ES-301-1 Facility: St. Lucie Plant Date of Examination: 10/19/09 Examination Level: RO [gJ SRO lM Operating Test Number: HLC-19 NRC Administrative Topic Type Describe activity to be performed (see Note) Code* M Perform an Estimated Critical Condition Calculation - Unit 2 Conduct of Operations M Perform a Manual Calorimetric at 45% power. Conduct of Operations N Develop ECO for Unit 1 Containment Spray Pump. Equipment Control ( N Perform Immediate Operator Actions For a Dropped New Fuel Element (SRO) Radiation Control D Operate Portable Radiation Monitoring Equipment (RO) M,P Determine PARs During Core Melt Scenario (SRO) Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~ 3 for ROs; :s 4 for SROs & RO retakes) (N)ew or (M)odified from bank (~ 1) (P)revious 2 exams (:s 1; randomly selected) (

( ES-301 Administrative Topics Outline ADMINISTRATIVE JPM

SUMMARY

DESCRIPTION CONDUCT OF OPERATION Perform a Unit 2 Estimated Critical Condition Calculation 2-GOP-302, 'Reactor Plant Startup - Mode 3 to Mode 2' Appendix C 'Estimated Critical Conditions'. This may be performed on the Simulator or in the classroom. CONDUCT OF OPERATION Perform a Unit 2 Manual Calorimetric at 45% power. Form ES-301-1 2-3200020, 'Primary System Manual Calorimetric' will be used. This may be performed on the simulator or in the classroom. EQUIPMENT CONTROL Develop a clearance for the 1 B Containment Spray Pump. The pump cooler is to be removed from service due to a leak. RADIATION CONTROL (SRO) Perform Operator Actions for a Dropped New Fuel Element. During offloading of new fuel in the new fuel area a dropped fuel element occurs. Without reference to procedures, state the Immediate Operator actions that must be carried out. (RO) USing 2-NOP-26.01 'Radiation Monitors', obtain Main Steam Line radiation readings using the portable RM-23 in the field from the RM-80 enclosure. EMERGENCY PROCEDURES/PLAN Determine PAR's During Core Melt Scenario (Modified from 2008 NRC exam) ES-301 Administrative Topics Outline ADMINISTRATIVE JPM

SUMMARY

DESCRIPTION CONDUCT OF OPERATION Perform a Unit 2 Estimated Critical Condition Calculation 2-GOP-302, 'Reactor Plant Startup - Mode 3 to Mode 2' Appendix C 'Estimated Critical Conditions'. This may be performed on the Simulator or in the classroom. CONDUCT OF OPERATION Perform a Unit 2 Manual Calorimetric at 45% power. Form ES-301-1 2-3200020, 'Primary System Manual Calorimetric' will be used. This may be performed on the simulator or in the classroom. EQUIPMENT CONTROL Develop a clearance for the 1 B Containment Spray Pump. The pump cooler is to be removed from service due to a leak. RADIATION CONTROL (SRO) Perform Operator Actions for a Dropped New Fuel Element. During offloading of new fuel in the new fuel area a dropped fuel element occurs. Without reference to procedures, state the Immediate Operator actions that must be carried out. (RO) Using 2-NOP-26.01 'Radiation Monitors', obtain Main Steam Line radiation readings using the portable RM-23 in the field from the RM-80 enclosure. EMERGENCY PROCEDURES/PLAN Determine PAR's During Core Melt Scenario (Modified from 2008 NRC exam)

CANDIDATE EXAMINER ST LUCIE INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE NRC JPM A-1 ADM Calculate Estimated Critical Conditions Unit 2 NRC ADM JPM COO ECC REV, 0 Page 1 of 11 ( CANDIDATE EXAMINER ST LUCIE INITIAL LICENSE EXAMINATION JOB PERFORMANCE MEASURE NRC JPM A-1 ADM Calculate Estimated Critical Conditions Unit 2 NRC ADM JPM COO ECC REV. a Page 1 of 11

( TASK: Perform an Estimated Critical Conditions Calculation K/A 2.1.25 (3.9 I 4.2) Ability to interpret reference materials, such as graphs, curves, tables, etc. POSITION: RO I SRO Location: Simulator I Classroom Method: Perform Estimated JPM Completion Time: 25 Minutes Actual JPM Completion Time: Minutes The JPM Operator's performance was evaluated against the standards of this JPM and is determined to be: SATISFACTORY/UNSATISFACTORY (circle one) Evaluator's Signature ____________ _ Date / /

References:

2-GOP-302 Reactor Plant Startup - Mode 3 to Mode 2, Appendix C. Unit 2 Plant Physics Curves Cycle 18 NRC ADM JPM COO ECC REV. 0 Page 2 of 11 ( TASK: Perform an Estimated Critical Conditions Calculation K/A 2.1.25 (3.9 I 4.2) Ability to interpret reference materials, such as graphs, curves, tables, etc. POSITION: RO I SRO Location: Simulator I Classroom Method: Perform Estimated JPM Completion Time: 25 Minutes Actual JPM Completion Time: Minutes The JPM Operator's performance was evaluated against the standards of this JPM and is determined to be: SATISFACTORY/UNSATISFACTORY (circle one) Evaluator's Signature ____________ _ Date / /

References:

2-GOP-302 Reactor Plant Startup - Mode 3 to Mode 2, Appendix C. Unit 2 Plant Physics Curves Cycle 18 NRC ADM JPM COO ECC REV. 0 Page 2 of 11

INITIAL CONDITIONS Unit 2 has been operating for 118 days at 100% power. The unit was shut down at 1800 on Sept. 29, 2009, due to Main Feedwater problems. We anticipate reactor startup #09-2 to reach criticality at 1500 on Sept. 30, 2009. The following conditions exist: Reactor core exposure is 2800 EFPH. RCS Boron concentration is 1200 ppm. A JPN Engineering Evaluation is unavailable for this startup. The Shift Manager instructs you to perform a manual determination of Estimated Critical Conditions by completing Appendix C (Estimated Critical Conditions) of 2-GOP-302 (Reactor Plant Startup - Mode 3 to Mode 2) in preparation for the unit startup. JPM OVERALL STANDARD: Calculate required Estimated Critical Conditions using Appendix C (Estimated Critical Conditions) of 2-GOP-302 (Reactor Plant Startup - Mode 3 to Mode 2). NOTES: This JPM may be performed in the Simulator or the classroom. Physics Curves for Unit 2 cycle 18 are required as references. last Stable RCS Boron and Criticality Data LJ RC System Boron was 948 ppm at 1300 on Sept 29, 2009. o Reactor Criticality Data from RCO Log dated 1300 Sept 29, 2009. CEA Group/Position (inches) 5 / 136 T-avg (OF) 574 Reactor Power (%) o Reactivity Deviation (PCM) 100 o NRC ADM JPM COO ECC REV, 0 Page 3 of 11 INITIAL CONDITIONS Unit 2 has been operating for 118 days at 100% power. The unit was shut down at 1800 on Sept. 29, 2009, due to Main Feedwater problems. We anticipate reactor startup #09-2 to reach criticality at 1500 on Sept. 30, 2009. The following conditions exist: Reactor core exposure is 2800 EFPH. RCS Boron concentration is 1200 ppm. A JPN Engineering Evaluation is unavailable for this startup. The Shift Manager instructs you to perform a manual determination of Estimated Critical Conditions by completing Appendix C (Estimated Critical Conditions) of 2-GOP-302 (Reactor Plant Startup - Mode 3 to Mode 2) in preparation for the unit startup_ JPM OVERALL STANDARD: Calculate required Estimated Critical Conditions using Appendix C (Estimated Critical Conditions) of 2-GOP-302 (Reactor Plant Startup - Mode 3 to Mode 2). NOTES: This JPM may be performed in the Simulator or the classroom. Physics Curves for Unit 2 cycle 18 are required as references. Last Stable RCS Boron and Criticality Data LJ RC System Boron was 948 ppm at 1300 on Sept 29, 2009. o Reactor Criticality Data from RCO Log dated 1300 Sept 29, 2009. CEA Group/Position (inches) 5 / 136 T -avg (OF) 574 Reactor Power (%) o Reactivity Deviation (PCM) 100 o NRC ADM JPM COO ECC REV. 0 Page 3 of 11

START TIME ___ Appendix C Estimated Critical Conditions and Inverse Count Rate Ratio STEPS ELEMENTS Record required data 1.A Unit - 1.B S/U - 1.C Date of ECC 1.0 Record the Burnup: EFPH 2.A.1.a Record shutdown and startup times: Date/time of shutdown / 2.A.2.a Anticipated date/time of criticality Obtain last stable Boron sample critical conditions before shutdown. STANDARD Operator records Unit 2 Operator records Startup 09-2. Operator records: Sept. 30,2009 Operator determines this based on initial conditions and records 2800 EFPH Operator records date: 9/29/09 at 1800 Operator records date: 9/30/09 at 1500. Operator notes that NC System Boron sample was within 24 hours of the shutdown. S/U COMMENTS REQUIRED FOR UNSAT NRC ADM JPM COO ECC REV. 0 Page 4 of 11 ( START TIME ___ Appendix C Estimated Critical Conditions and Inverse Count Rate Ratio STEPS ELEMENTS Record required data 1.A Unit - 1.B StU - 1.C Date of ECC 1.0 Record the Burnup: EFPH Record shutdown and 2.A.1.a startup times: Date/time of shutdown / 2.A.2.a Anticipated date/time of criticality / Obtain last stable Boron sample critical conditions before shutdown. STANDARD Operator records Unit 2 Operator records Startup 09-2. Operator records: Sept. 30,2009 Operator determines this based on initial conditions and records 2800 EFPH Operator records date: 9/29/09 at 1800 Operator records date: 9/30/09 at 1500. Operator notes that NC System Boron sample was within 24 hours of the shutdown. StU COMMENTS REQUIRED FOR UNSAT NRC ADM JPM COO ECC REV. 0 Page 4 of 11

STEPS ELEMENTS STANDARD Stu COMMENTS REQUIRED FOR UNSAT COLUMN 1 CONTINUED Record the power defect Operator determines this from PPCS Figure A.1 based on initial conditions and PPCS: + 1335 pcm pem (1300 to 1370) Record the xenon worth Operator determines this from PPCS Figure A.4 based on initial conditions and PPCS: + 2550 pcm pem (2525 to 2600) Record the samarium and neptunium worth from Operator determines this PPCS Figure A.5 based on initial conditions pcm and PPCS: + 806 pem (805 to 808) Record the diff. boron Operator determines this worth from PPCS, Figure based on data provided A.8 and PPCS: pcm/ppm + 8.18 pem/ppm (7.95 to 8.2) Record prior to shutdown Operator determines this RCS Soron concentration based on initial conditions ppm + 948 ppm Calculate the boron worth: Operator calculates boron __ ppm Soron x __ worth: pcm/ppm Soron = 948 ppm Soron x 8.18 pcm pcm/ppm = + 7755 pem. (7749 to 7773)

• DENOTES CRITICAL NRC ADM JPM COO ECC REV. o Page 5 of 11 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT COLUMN 1 CONTINUED Record the power defect Operator determines this from PPCB Figure A1 based on initial conditions and PPCB:

+ 1335 pcm pem (1300 to 1370) Record the xenon worth Operator determines this from PPCB Figure AA based on initial conditions and PPCB: + 2550 pcm pem (2525 to 2600) Record the samarium and neptunium worth from Operator determines this PPCB Figure A5 based on initial conditions ( and PPCB: + 806 pcm pem (805 to 808) Record the diff. boron Operator determines this worth from PPCB, Figure based on data provided A8 and PPCB: pcm/ppm + 8.18 pem/ppm (7.95 to 8.2) Record prior to shutdown Operator determines this RCS Boron concentration based on initial conditions ppm + 948 ppm Calculate the boron worth: Operator calculates boron __ ppm Boron x __ worth: pcm/ppm Boron = 948 ppm Boron x 8.18 pcm pcm/ppm = + 7755 pem. (7749 to 7773)

• DENOTES CRITICAL NRC ADM JPM COO ECC REV. o Page 5 of 11

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Record the CEA reactivity Operator determines this worth, Figure A.6 or A. 7 based on data, Figure A.6: + 8580 pcm pcm (NO band since pcm given on curve) 2a2 FILL IN COLUMN 2: Record the xenon worth Operator determines this from PPCB Figure AA based on initial conditions and PPCB: + 2460 pcm pcm (2500 to 2550) Record the samarium and Operator determines this neptunium worth from based on initial conditions and PPCB: + 826 PPCB Figure A.5 pcm pcm (825 to 827) Record the diff. boron worth from Column 1. Operator records: pcm/ppm + 8.18 pcm/ppm (8.1 to 8.2) Record current RCS Boron Concentration Operator determines this based on initial ppm conditions: + 1200 ppm Calculate the boron worth: __ ppm Boron x __ Operator calculates boron pcm/ppm Boron = worth: pcm 1200 ppm Boron x 8.18 pcm/ppm = + 9816 pcm.

• DENOTES CRITICAL NRC ADM JPM COO ECC REV. 0 Page 6 of 11 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Record the CEA reactivity Operator determines this worth, Figure A.6 or A. 7 based on data, Figure A.6:

pcm + 8580 pcm (NO band since pcm given on curve) 2a2 FILL IN COLUMN 2: Record the xenon worth Operator determines this from PPCB Figure AA based on initial conditions and PPCB: + 2460 pcm pcm (2500 to 2550) ( Record the samarium and Operator determines this neptunium worth from based on initial conditions and PPCB: + 826 PPCB Figure A.5 pcm pcm (825 to 827) Record the diff. boron worth from Column 1. Operator records: pcm/ppm + 8.18 pcm/ppm (8.1 to 8.2) Record current RCS Boron Concentration Operator determines this based on initial ppm conditions: + 1200 ppm Calculate the boron worth: ( __ ppm Boron x __ Operator calculates boron pcm/ppm Boron = worth: pcm 1200 ppm Boron x 8.18 pcm/ppm = + 9816 pcm.

• DENOTES CRITICAL NRC ADM JPM COO ECC REV. 0 Page 6 of 11

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (9720 to 9840) Determine whether to go critical at normal point of Operator determines that 60 inches on group 5. the normal critical rod position is desired. Record the CEA reactivity Operator determines this worth from PPCB, Figure A.60rA.7 based on data provided and PPCB, Figure A.6: pcm Group 5 @ 60" + 8289 pcm Enters Reactivity (8275 to 8300) Deviation Enters 0 given in cue sheet. 2a2b Verify that the critical rod Operator verifies that 60 position is above the inches on Group 5 is insertion limits and initial above 55 inches on group Note 2 of the worksheet. 3 and initials Note 2 on the work sheet. 2a2c Calculate the CEA Operator calculates CEA position at +500 pcm and positions at +500, -500 & - -500 pcm from the 1000 pcm from the esti-estimated critical position: mated critical position. +500 pcm _ in on Grp 8789pcm = ARO 7789pcm = 111 in on Group 3 -500 pcm _ in on Grp (104to 118) -1000pcm _ in on Grp 7289 pcm = 45 in on Group 3 ( 37 to 52 ) 2a2d Calculate line-by-line differences and Net Reactivity:

• DENOTES CRITICAL NRC ADM JPM COO ECC REV. a Page 7 of 11 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT (9720 to 9840)

Determine whether to go critical at normal point of Operator determines that 60 inches on group 5. the normal critical rod position is desired. Record the CEA reactivity worth from PPCS, Figure Operator determines this A.6 or A.7 based on data provided and PPCS, Figure A.6: pcm Group 5 @ 60" + 8289 pcm Enters Reactivity (8275 to 8300) Deviation Enters 0 given in cue sheet. 2a2b Verify that the critical rod Operator verifies that 60 position is above the inches on Group 5 is insertion limits and initial above 55 inches on group Note 2 of the worksheet. 3 and initials Note 2 on the work sheet. 2a2c Calculate the CEA Operator calculates CEA position at +500 pcm and positions at +500, -500 & - -500 pcm from the 1000 pcm from the esti-estimated critical position: mated critical position. +500 pcm _ in on Grp 8789pcm = ARO 7789pcm = 111 in on Group 3 -500 pcm _ in on Grp (104 to 118) -1 OOOpcm _ in on Grp 7289 pcm = 45 in on Group 3 ( 37 to 52 ) 2a2d Calculate line-by-line differences and Net Reactivity:

• DENOTES CRITICAL NRC ADM JPM COO ECC REV. 0 Page 7 of 11

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Operator subtracts Column 1 from Column 2 Calculate the power line-by-line. defect difference: Column 1 - Column 2 = 1335 - 0 = +1335 pcm pcm (1300 to 1370) Calculate the xenon worth difference: Column 1 - Column 2 = 2550 - 2460 = + 90 pcm pcm (25 to 100) Calculate the samarium ( and neptunium worth difference: Column 1 - Column 2 = 806 - 826 = -20 pcm pcm (-17 to -22) Calculate the boron worth: difference: 7755 - 9816 = - 2061 Column 1 - Column 2 = pcm pcm (-1947 to -2091) Calculate the CEA reactivity worth difference. Column 1 - Column 2 = 8580 - 8289 = -291 pcm pcm (-280 to -305) Reactivity Deviation o pcm 2a2e Net Reactivity:

• DENOTES CRITICAL NRC ADM JPM COO ECC REV. 0 Page 8 of 11 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Operator subtracts Column 1 from Column 2 Calculate the power line-by-line.

defect difference: Column 1 - Column 2 = 1335 - 0 = +1335 pcm pcm (1300 to 1370) Calculate the xenon worth difference: Column 1 - Column 2 = 2550 - 2460 = + 90 pcm pcm (25 to 100) Calculate the samarium ( and neptunium worth difference: Column 1 - Column 2 = 806 - 826 = -20 pcm pcm (-17 to -22) Calculate the boron worth: difference: 7755 - 9816 = - 2061 Column 1 - Column 2 = pcm pcm (-1947 to -2091) Calculate the CEA reactivity worth difference. Column 1 - Column 2 = 8580 - 8289 = -291 pcm pcm (-280 to -305) ( Reactivity Deviation o pcm 2a2e Net Reactivity:

• DENOTES CRITICAL NRC ADM JPM COO ECC REV. 0 Page 8 of 11

( STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Total up all the -947 pcm differences. (- 749 to - 1068) 2a2f Total change in Boron: Net Reactivity) diff. boron -947/8.18 = -116 ppm worth. (-91 to -114.2) pcm ) _ pcm/ppm = __ ppm. Dilute 2a2f Estimated Critical Boron Concentration. Present RCS Boron + Total Change in Boron _ppm+_ppm = 1200 ppm - 116 = 1084 _ppm (91 to 144.2) (1055 to 1109) 3.0 Per Note 3 the operator Cue: Tell the operator must compare the ECC that the Desk RCO with the shutdown margin completed Data Sheet 2 requirements of 2-NOP-for 2-NOP-1 00.04 and 100-04. determined that the The operator locates 2-Required Boron NOP-1 00.04 to determine Concentration is 841 shutdown margin for these ppm. conditions.

• DENOTES CRITICAL NRC ADM JPM COO ECC REV. 0 Page 9 of 11 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Total up all the

-947 pcm differences. (- 749 to - 1068) 2a2f Total change in Boron: Net Reactivity) diff. boron -947 I 8.18 = -116 ppm worth. (-91 to -114.2) ~ pcm ) ~ pcm/ppm = __ ppm. Dilute 2a2f Estimated Critical Boron Concentration. Present RCS Boron + ( Total Change in Boron _ppm +~ppm = 1200 ppm - 116 = 1084 _ppm (91 to 144.2) (1055 to 1109) 3.0 Per Note 3 the operator Cue: Tell the operator must compare the ECC that the Desk RCO with the shutdown margin completed Data Sheet 2 requirements of 2-NOP-for 2-NOP-1 00.04 and 100-04. determined that the The operator locates 2-Required Boron NOP-1 00.04 to determine Concentration is 841 shutdown margin for these ppm. conditions.

• DENOTES CRITICAL NRC ADM JPM COO ECC REV. 0 Page 9 of 11

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 4.0 Per Note 2 the operator INITIALS Note 2 of ECC ensures that the critical Calculation Worksheet CEA position is above the insertion limits of Technical Specification 3.1.3.6 and initial Note 2 of ECC Calculation Worksheet. 5.0 Calculates CEA position at ENTERS the CEA -1000 PCM, +500 PCM, positions on the and -500 peM from the estimated critical condition appropriate line. This was and enter on the calculated on step 2a2c. appropriate line. ( 6.0 The licensed operator SIGNS the Prepared by preparing the worksheet line. shall sign the Prepared by line 7.0 Reactor Engineering shall Cue: Tell the operator independently verify the that this verification will ECC and sign the be completed by RE LfJdegendently: Verified by: later. END of JPM. line. STOP TIME ____ _

• DENOTES CRITICAL NRC ADM JPM COO ECC REV. 0 Page 10 of 11 STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 4.0 Per Note 2 the operator INITIALS Note 2 of ECC ensures that the critical Calculation Worksheet CEA position is above the insertion limits of Technical Specification 3.1.3.6 and initial Note 2 of ECC Calculation Worksheet.

5.0 Calculates CEA position at ENTERS the CEA -1000 PCM, +500 PCM, positions on the and -500 PCM from the estimated critical condition appropriate line. This was and enter on the calculated on step 2a2c. appropriate line. ( 6.0 The licensed operator SIGNS the Prepared by preparing the worksheet line. shall sign the Prepared by line 7.0 Reactor Engineering shall Cue: Tell the operator independently verify the that this verification will ECC and sign the be completed by RE Ll}degendently: Verified by: later. END of JPM. line. STOP TIME ____ _

• DENOTES CRITICAL NRC ADM JPM COO ECC REV. 0 Page 10 of 11

( CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS Unit 2 has been operating for 118 days at 100% power with all rods out. The unit was shut down at 1800 on Sept. 29, 2009, due to Main Feedwater problems. We anticipate reactor startup #09-2 to reach criticality at 1500 on Sept. 30, 2009. The following conditions exist: Reactor core exposure is 2800 EFPH. RCS Boron concentration is 1200 ppm. A JPN Engineering Evaluation is unavailable for this startup. The Shift Manager instructs you to perform a manual Estimated Critical Condition Calculation by completing Appendix C (Estimated Critical Conditions) of 2-GOP-302 (Reactor Plant Startup - Mode 3 to Mode 2) in preparation for the unit startup. Last Stable RCS Boron and Criticality Data o RC System Boron was 948 ppm at 1300 on Sept 29, 2009. o Reactor Criticality Data from RCO Log dated 1300 Sept 29, 2009. CEA Group/Position (inches) 5 / 136 T-avg (OF) 574 Reactor Power (%) 100 o Reactivity Deviation (PCM) 0 Page 11 of 11 ( CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK) INITIAL CONDITIONS Unit 2 has been operating for 118 days at 100% power with all rods out. The unit was shut down at 1800 on Sept. 29, 2009, due to Main Feedwater problems. We anticipate reactor startup #09-2 to reach criticality at 1500 on Sept. 30, 2009. The following conditions exist: Reactor core exposure is 2800 EFPH. RCS Boron concentration is 1200 ppm. A JPN Engineering Evaluation is unavailable for this startup. The Shift Manager instructs you to perform a manual Estimated Critical Condition Calculation by completing Appendix C (Estimated Critical Conditions) of 2-GOP-302 (Reactor Plant Startup - Mode 3 to Mode 2) in preparation for the unit startup. Last Stable RCS Boron and Criticality Data [j RC System Boron was 948 ppm at 1300 on Sept 29, 2009. o Reactor Criticality Data from RCO Log dated 1300 Sept 29, 2009. CEA Group/Position (inches) 5 / 136 T-avg(OF) 574 Reactor Power (%) 100 [] Reactivity Deviation (PCM) 0 Page 11 of 11

~+ EVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 52 of 61 ROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIXC ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 6 of8) ECC CALCULATION WORKSHEET (Page 1 of 2) Unit No.: 2 Startup No.: 07' - ::2 Date of ECC: 9;3b/ Or;. Exposure: :2tfOO EFPH COLUMN 1 COLUMN 2 PARAMETER Conditions Prior to Shutdown Estimated Critical Conditions Difference Sign Time 1: Date~/$!1.!l.- Time: ItO!) Time 2: Date i 1_3...12.-, ()9 Time:1.5 () i) (PCM) Determination At LOO f 3()1J... 1370 11300-1370 Power Defect % Power FigUr~A.)3s) NA NA (+) PCM (+)Always 13>,./ PCM 113~:n

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"~~ -.<,00 From Figure AA or as provided by R.E. ZS DO.. 25'""{PtM

I:.S":.-I() D Xenon Worth From DCS or Figure AA Lf( '10)

PCM (2%D ~ ( '2..~(., 0) (+) If Column 1 is Samarium and ?O~ -gor From Figure A.S. or as provided by R.E. f~ 5-"';.~7pCM 17-Z""l/ greater than From Figure A.S. ..... ) PCM Column 2 Neptunium Worth ('80' \\ PCM ( PZc.) (- 2.0) (-) If Column 1 is PI.L z qs-:- tf::GO '7"1 V7'-777 Present Boron conlntration e ~720-9jlJo /t;t/l-ZOCJt less than Column 2 Boron Worth ~ lZ D £1-,2-PPM X Boron Worth ~ PCM ""') PC (Note 1) From Figure A('lr*I'r) ( 77~ o PPM X Boron~)orth (-2.06 l) From Figure A'¥?I/ fi-

• Cfi'/b}

/' -0/ . Group £ withdraw to.b..12-Inche:;l., 7??Jo6 2!O-30£' (-) If Column 1 is Group4e:v-withdraw to ~ inches P5fO greater than CEA Reactivity PCM (-) PCM Column 2 Worth Use Figure A.6. or A.7. ~ Use Figure A.6. or A.7. (Note 2) ( ?2r9) / -2 q,) (+) If Column 1 is less than Column 2 Reagivity N/A N/A From Figure 8.3 or as provided by R.E. ~PCM ()~PCM Deviation NeYReactivity Total up the reactivities in the Difference column and enter the value here. Observe signs. ( ) peM _J FEVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 52 of 61 ~ROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 6 of 8) ECC CALCULATION WORKSHEET (Page 1 of 2) Unit No.: 2 Startup No.: 01 ~ L Date of ECC: q /.Jo/ oQ Exposure: :z tfOO EFPH COLUMN 1 COLUMN Z PARAMETER Conditions Prior to Shutdown Estimated Critical Conditions Difference Sign !L~Q£ IjO/) Time 2: Date L..1!L, (}9 Time:L5 () () (PCM) Determinatio n Time 1: Date' I I. Time: LOO ! 3()()- J370 1300-1370 Power Defect At % Power FigUr~A.1 ) NA NA (+) PCM (+) Always 1 3>3:; PCM ( 13o§J ,;)..5.:l,'t" ~..<'OO From Figure AA or as provided by R.E. 2-5 ( )0 - '25'5fl'CM t<. S':)[) 0 Xenon Worth From DCS or Figure AA i-f( q 0) PCM (2560 ) PCM ( '2.~("O) (+) If Column 1 is Samarium and foS -gor From Figure A.5. or as provided by R.E. ft? $--:'f).. 7PCM 17-2.v greater than From Figure A.5. ..... ) PCM Column 2 Neptunium Worth (DoC. 'I PCM ( ?2.c.) (- 2.0) (-) If Column 1 is ~ Zt{C;-- tf:::GO -'77 '17 -777 Present Boron conz.ntration (1720 - 9[1/0 /'117-209/ less than Column 2 Boron Worth ~ IZD f;f-,2. PPM X Boron Worth I' PCM -'-') PCM (Note 1) From Figure A.("6.1't) ( PCM o PPM X Boron Worth 1(-2.oG n 77 S:;-") From Figure A.f.!?, If)" .q?/~ } / / fo<. 75- ?306 2jO-30~ (-) If Column 1 is GrouP4~ withdraw 10 ~ inches ?5f'O Group __ withdraw to ft inches greater than CEA Reactivity PCM (-) PCM Column 2 Worth Use Figure A.S. or A.7. ~ Use Figure A.S. or A.7. (Note 2) ( ?zrCj) if -2 q I) (+) If Column 1 is less than Column 2 Reactivity N/A N/A From Figure B.3 or as provided by R.E. ~PCM ( )~PCM Deviation Net Reactivity Total up the reactivities in the Difference column and enter the value here. Observe signs. ( ) PCM

(~ EVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 53 of 61 ROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIXC ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 7 of 8) ECC CALCULATION WORKSHEET (Page 2 of 2) Sign PARAMETER Difference Determination ( 1tf9-I06Y .,. q /.;. It/4t Z, If sign is +, Total Change in ( Net Reactivity ) _ ( (-) (Cj '+ 7) PCM) ~) II (; PPM Borate Boron Column 2 Boron Worth £/ _ l(, Z, PCMIPPM If sign is -, (<;.1 Y) Dilute Estimated Critical (I ;{ O!) ) ( (-) C~ I ( -, fZ {' ~ r-- 1P 55 -1°9) Boron + ~ ( )! 03' PPM (Note 3) Concentration Present RCS Boron Concentration Total Change in Boron Concentration GEA Position at -1000 PGM from EGG = 31; 5 'Y Inches withdrawn on Group:1 S1artup (Mode 2) entry pOln( 7.;:( ! f f c", ) CEA Position at +500 PCM from ECC loti -/ I ( Inches withdrawn on Group 3 ( 77 J-9 pc. ~ ) CEA Position at -500 PCM from ECC = /If( D Inches withdrawn on Group ( j>J ;-7 jJc)y, ) ..~...................... -........ "....,....,."..............l.. P.EVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 53 of 61 PROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 7 of 8) ECC CALCULATION WORKSHEET (Page 2 of 2) PARAMETER Difference Sign Determination { 1L/9-l q6Y ,. q /.;. 14!f/z,.. If sign is +, Total Change in ( Net Reactivity ) = ( (-) (<=j '17) PCM) ~) II (g Borate PPM Boron Column 2 Boron Worth f;/ -' f, z,. PCM/PPM If sign is -, \\¥.IY) Dilute Estimated Critical ( J ;Z 00 ) ( (ell - /<f,(.?/) r-..I() 55 - /109) Boron (-). (L£G2' ( ) IOJ"f PPM (Note 3) Present RCS Boron Concentration + Total Change i~ Boron Concentration Concentration CEA Position at -1000 PCM from ECC = 3.j - <j Y Inches withdrawn on Group 3 Startup (Mode 2) ent", pOin,( 7.:? f f j7 c"" ) IOtj -/I (' 3 ( 77J-y pCJn) CEA Position at +500 PCM from ECC = Inches withdrawn on Group CEA Position at -500 PCM from ECC = /lIZ 0 Inches withdrawn on Group (t-J r7 le)y, ) I " _..... -". --~." .--l

REVISION NO.: PROCEDURE TITLE: PAGE: 54 of 61 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 1---------------; PROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 8 of 8) ECC CALCULATION WORKSHEET ( continued) NOTES:

1.

If the difference in time between when the boron sample was drawn and the time of shutdown exceeds 24 hours, contact Reactor Engineering.

2.

The critical CEA PJ(J\\~ has been verified to be above PDIL (Technical Specification COLR Fig. 3.1-2) (initials).

3. The ECC Boron Concentration must meet or exceed the boron concentration requirements for shutdown margin with CEAs at Column 2 position in accordance with 2-NOP-100.04, surveill"N;e Requirements for Shutdown Margin, Modes 2, 3, 4 and 5, Subcritical.

'1/\\ ~ l----' Prepared By: t \\./ RCO ACTUAL CRITICAL CONDITIONS Date of Criticality __, __ /_ Independently Time (24 hour clock) Verified By: ____

=--_--::=--:-----:--_____ CEA Group/Position (inches) ____....:' __

Reactor Engineering RCS Boron Concentration (PPM) ___ Xenon Worth (DCS or Fig A.4) I have reviewed the requirements of this procedure including other surveillances T-avg (OF) Reactor Power (%) ____ _ performed during this procedure, if any (i.e., datasheet(s), PMT sheet(s), etc.). Any deviations, abnormal results, equipment problems, failures, or human performance issues must be documented via a Condition Report for each individual item. C.R.# ________ _ Reviewed By: ___________________________ _ Reactivity Manager ApprovedBy: _____________ ~------------ SM or US ( REVISION NO.: PROCEDURE TITLE: PAGE: 54 of 61 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 I------~------~ PROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 8 of 8) ECC CALCULATION WORKSHEET ( continued) NOTES:

1.

If the difference in time between when the boron sample was drawn and the time of shutdown exceeds 24 hours, contact Reactor Engineering.

2.

The critical CEA pXO\\~ has been verified to be above POlL (Technical Specification COLR Fig. 3.1-2) (initials).

3.

The ECC Boron Concentration must meet or exceed the boron concentration requirements for shutdown margin with CEAs at Column 2 position in accordance with 2-NOP-1 00.04, Surveill~;e Requirements for Shutdown Margin, Modes 2, 3, 4 and 5, Subcritical. Prepared By, lAv ~ L--. ACTUAL CRITICAL CONDITIONS Date of Criticality __ / __ /_ Independently Time (24 hour clock) Verified By: _______________ CEA Group/Position (inches) __ -.0/ __ Reactor Engineering RCS Boron Concentration (PPM) ___ _ Xenon Worth (DCS or Fig A.4) I have reviewed the requirements of this procedure including other surveillances T-avg (OF) Reactor Power (%) ____ _ performed during this procedure, if any (i.e., datasheet(s), PMT sheet(s), etc.). Any deviations, abnormal results, equipment problems, failures, or human performance issues must be documented via a Condition Report for each individual item. C.R.# ________ _ Reviewed By: ___________________________ _ Reactivity Manager ApprovedBy: ___________ ~ __ -~------------- SM or US

REVISION NO.: PROCEDURE TITLE: PAGE: 54 of 61 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 I--------------~ 38 PROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 8 of 8) ECC CALCULATION WORKSHEET (continued) NOTES:

1.

If the difference in time between when the boron sample was drawn and the time of shutdown exceeds 24 hours, contact Reactor Engineering.

2.

The critical CEA position has been verified to be above PDIL (Technical Specification COLR Fig. 3.1-2) (initials).

3.

The ECC Boron Concentration must meet or exceed the boron concentration requirements for shutdown margin with CEAs at Column 2 position in accordance with 2-NOP-100.04, Surveillance Requirements for Shutdown Margin, Modes 2, 3, 4 and 5, Subcritical. Prepared By: ______________ _ ACTUAL CRITICAL CONDITIONS RCO Date of Criticality __ 1 __ 1_ Independently Time (24 hour clock) Verified By: _______________ CEA GrouplPosition (inches) 1 Reactor Engineering RCS Boron Concentration (PP=-M-:-) =~::::::::==_ Xenon Worth (DCS or Fig A.4) I have reviewed the requirements of this procedure including other surveillances T-avg (OF) Reactor Power (%) ____ _ performed during this procedure, if any (i.e., datasheet(s), PMT sheet(s}, etc.}. Any deviations, abnormal results, equipment problems, failures, or human performance issues must be documented via a Condition Report for each individual item. C.R.# _________ _ Reviewed By: ___________________________ _ Reactivity Manager Approved By: _________________________ __ SM or US ( ( ( REVISION NO.: PROCEDURE TITLE: PAGE: 54 of 61 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 I--------------~ 38 PROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 8 of 8) ECC CALCULATION WORKSHEET ( continued) NOTES:

1.

If the difference in time between when the boron sample was drawn and the time of shutdown exceeds 24 hours, contact Reactor Engineering.

2.

The critical CEA position has been verified to be above PDIL (Technical Specification COLR Fig. 3.1-2) (initials).

3.

The ECC Boron Concentration must meet or exceed the boron concentration requirements for shutdown margin with CEAs at Column 2 position in accordance with 2-NOP-100.04, Surveillance Requirements for Shutdown Margin, Modes 2, 3, 4 and 5, Subcritical. Prepared By: ______________ _ ACTUAL CRITICAL CONDITIONS RCO Date of Criticality __ / __ /_ Independently Time (24 hour clock) Verified By: ________________ CEA Group/Position (inches)::---c----'/ Reactor Engineering RCS Boron Concentration (PPM) _____ _ Xenon Worth (DCS or Fig AA) I have reviewed the requirements of this procedure including other surveillances T-avg (OF) Reactor Power (%) _______ _ performed during this procedure, if any (i.e., datasheet(s), PMT sheet(s), etc.). Any deviations, abnormal results, equipment problems, failures, or human performance issues must be documented via a Condition Report for each individual item. C.R.# _________ _ Reviewed By: ____________________________ _ Reactivity Manager Approved By: ____________________________________________________ _ SM or US

REVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 1---.....:....::...----1 PROCEDURE NO.: 47 of 61 2-GOP~302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 1 of 8) NOTE The ECC worksheet should be considered valid for a period not to exceed 1/2 hour before or 1/2 hour after the time entered in Column 2 of the ECC Calculation Worksheet. The decision to change ECCs during the approach to criticality shall be made by the Reactivity Manager with concurrence of the US or SM. !f the intended time of criticality exceeds 4 days from the time of shutdown, Then Xenon and Samarium effects will be negligible and the 1/2 hour guideline is NOT applicable. Data being used is required to be consistent with current core burnup.

1.

Enter the following data on the ECC Calculation Worksheet: A. B. Unit No: Startup No: Enter the unit number for which the ECC applies. Enter the Startup number as determined from the Unit 2 Control Room working copy of OP-0030129, Reactor Trip Records. C. Date of ECC: Enter the date that the ECC calculation is prepared. D. Exposure: Enter the current Exposure of the core from DCS. NOTE At the discretion of the Reactor Engineering Supervisor, Estimated Critical Conditions provided by the Nuclear Fuel Department, BEACON modeling, or equivalent, may be used instead of the ECC Worksheet Manual calculation. !f one of these alternate methods is used, Then skip Step 2A and perform Step 2B.

2.

Determine Estimated Critical Conditions as follows: NOTE The values entered in column 1 are for the last known equilibrium conditions which the reactor operated at a stable power level for a minimum of 40 hours. The values entered in column 2 correspond to the reactor conditions in column 1. A. Manual determination of Estimated Critical Conditions: ( REV[S[ON NO.: PROCEDURE T[TLE: PAGE: 47 of 61 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 [---------1 38 PROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 1 of 8) NOTE The ECC worksheet should be considered valid for a period not to exceed 112 hour before or 112 hour after the time entered in Column 2 of the ECC Calculation Worksheet. The decision to change ECCs during the approach to criticality shall be made by the Reactivity Manager with concurrence of the US or SM. If the intended time of criticality exceeds 4 days from the time of shutdown, Then Xenon and Samarium effects will be negligible and the 112 hour guideline is NOT applicable. Data being used is required to be consistent with current core burnup.

1.

Enter the following data on the ECC Calculation Worksheet: A. Unit No: Enter the unit number for which the ECC applies. B. Startup No: Enter the Startup number as determined from the Unit 2 Control Room working copy of OP-0030129, Reactor Trip Records. C. Date of ECC: Enter the date that the ECC calculation is prepared. D. Exposure: Enter the current Exposure of the core from DCS. NOTE At the discretion of the Reactor Engineering Supervisor, Estimated Critical Conditions provided by the Nuclear Fuel Department, BEACON modeling, or equivalent, may be used instead of the ECC Worksheet Manual calculation. If one of these alternate methods is used, Then skip Step 2A and perform Step 2B.

2.

Determine Estimated Critical Conditions as follows: NOTE The values entered in column 1 are for the last known equilibrium conditions which the reactor operated at a stable power level for a minimum of 40 hours. The values entered in column 2 correspond to the reactor conditions in column 1. A. Manual determination of Estimated Critical Conditions:

REVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 I--------i 48 of 61 PROCEDURE NO.:

2.

2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 2 of 8) A. (continued)

1.

Complete Conditions Prior to Shutdown (Column 1) as follows:

a.

Time 1: Enter the date and time (24 hour clock) of Reactor shutdown.

b.

Conditions Prior to Shutdown: Using the last stable boron sample (chemical analysis) and recorded critical conditions from the RCO log, calculate the reactivity for each parameter. (Note that if the time difference between the last stable boron sample and the time of the Reactor shutdown is greater than 24 hours, Reactor Engineering should be contacted for a more precise value of the reactivity to be used for Column 1 boron worth.)

c.

11 at the time of shutdown equilibrium conditions were not present, Then ensure the data in column 1 reflects the last known equilibrium operating conditions at the operating power level prior to the time of shutdown.

2.

Complete Estimated Critical Conditions (Column 2) as follows:

a.

Time 2: Enter estimated date and time (24 hour clock) that criticality is expected to be achieved. NOTE Reactivity defect associated with temperature changes are accounted for in power defect values which assume criticality is attained at 532°F.

b.

Estimated critical conditions: Using the plant physics curves or data provided by RE, calculate the reactivity for each parameter at Time 2. When estimating CEA withdrawal height (if possible, apprOXimately 60 inches on Group 5), verify that the critical position is above the insertion limits and initial Note 2 of ECC Calculation Worksheet that this has been checked.

c.

Calculate CEA position at +500 PCM and -500 PCM from the estimated critical condition and enter on the appropriate line. { \\ ( REVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 1--------; 48 of 61 PROCEDURE NO.:

2.

2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 2 of 8) A. (continued)

1.

Complete Conditions Prior to Shutdown (Column 1) as follows:

a.

Time 1: Enter the date and time (24 hour clock) of Reactor shutdown.

b.

Conditions Prior to Shutdown: Using the last stable boron sample (chemical analysis) and recorded critical conditions from the RCO log, calculate the reactivity for each parameter. (Note that if the time difference between the last stable boron sample and the time of the Reactor shutdown is greater than 24 hours, Reactor Engineering should be contacted for a more precise value of the reactivity to be used for Column 1 boron worth.)

c.

11 at the time of shutdown equilibrium conditions were not present, Then ensure the data in column 1 reflects the last known equilibrium operating conditions at the operating power level prior to the time of shutdown.

2.

Complete Estimated Critical Conditions (Column 2) as follows:

a.

Time 2: Enter estimated date and time (24 hour clock) that criticality is expected to be achieved. NOTE Reactivity defect associated with temperature changes are accounted for in power defect values which assume criticality is attained at 532°F.

b.

Estimated critical conditions: Using the plant physics curves or data provided by RE, calculate the reactivity for each parameter at Time 2. When estimating CEA withdrawal height (if possible, apprOXimately 60 inches on Group 5), verify that the critical position is above the insertion limits and initial Note 2 of ECC Calculation Worksheet that this has been checked.

c.

Calculate CEA position at +500 PCM and -500 PCM from the estimated critical condition and enter on the appropriate line.

( REVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 I--------t 49 of 61 PROCEDURE NO.:

2.

2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 3 of 8) A.

2.

(continued)

d.

Subtract the absolute value of the parameter in Column 2 from the absolute value of the parameter in Column 1 and enter the difference in the difference column. Refer to the determination of sign column for each parameter and assign the sign accordingly.

e.

Add all values in the difference column, applying signs as appropriate and enter the total. Divide this Net Reactivity by Boron Worth. The sign of the total change in boron determines if boron concentration needs to be increased or decreased.

f.

Enter the total change in Boron required from the present concentration and calculate the Estimated Critical Boron Concentration.

g.

If equilibrium conditions were not present at the time of shutdown, Then ensure that the data used in column 2 corresponds to the reaction conditions in column 1. B. Determine the Estimated Critical Conditions using an Alternate Method as follows:

1.

The Reactor Engineer shall obtain an estimate of critical conditions. This may be provided by the Nuclear Fuel department, completion of a BEACON model, or an equivalent output document, which determines critical boron concentration for a specific Lead Group position (normally 60 inches withdrawn on Group 5).

2.

The estimated critical conditions, determined by one of the preceding methods, shall include a minimum of 24 critical boron concentrations spaced at one hour intervals to allow for possible delays.

3.

Complete the ECC Worksheet by marking all Column 1 and Column 2 variables as "N/A", with the exception of Column 2 CEA position. Attach the document used to determine the boron concentrations to the back of the ECC Worksheet. Engineering Document Type and Number: ______ Date __ 1 __ 1 __ Reactor Engineer Providing the Estimate: _______ Date __ 1 __ 1 __ ( REVISION NO.. PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 I----:....----f 49 of 61 PROCEDURE NO.:

2.

2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 3 of 8) A.

2.

(continued)

d.

Subtract the absolute value of the parameter in Column 2 from the absolute value of the parameter in Column 1 and enter the difference in the difference column. Refer to the determination of sign column for each parameter and assign the sign accordingly.

e.

Add all values in the difference column, applying signs as appropriate and enter the total. Divide this Net Reactivity by Boron Worth. The sign of the total change in boron determines if boron concentration needs to be increased or decreased.

f.

Enter the total change in Boron required from the present concentration and calculate the Estimated Critical Boron Concentration.

g.

If equilibrium conditions were not present at the time of shutdown, Then ensure that the data used in column 2 corresponds to the reaction conditions in column 1. B. Determine the Estimated Critical Conditions using an Alternate Method as follows:

1.

The Reactor Engineer shall obtain an estimate of critical conditions. This may be provided by the Nuclear Fuel department, completion of a BEACON model, or an equivalent output document, which determines critical boron concentration for a specific Lead Group position (normally 60 inches withdrawn on Group 5).

2.

The estimated critical conditions, determined by one of the preceding methods, shall include a minimum of 24 critical boron concentrations spaced at one hour intervals to allow for possible delays.

3.

Complete the ECC Worksheet by marking all Column 1 and Column 2 variables as "N/A", with the exception of Column 2 CEA position. Attach the document used to determine the boron concentrations to the back of the ECC Worksheet. Engineering Document Type and Number: ______ Date __ 1 __ 1 __ Reactor Engineer Providing the Estimate: _______ Date __ 1 __ 1 __

( ( REVISION NO. PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 1--------/ 50 of 61 PROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 4 of 8)

3.

§1 Ensure the Estimated Critical Boron Concentration is greater than or equal to the boron concentration required for shutdown margin needed prior to Startup (Mode 2), in accordance with 2-NOP-100.04, Surveillance Requirements for Shutdown Margin, Modes 2, 3, 4, and 5 (Subcritical).

4.

§1 Ensure that the critical CEA position is above the insertion limits of Technical Specification 3.1.3.6 and initial Note 2 of ECC Calculation Worksheet.

5.

6.

7.

8.

9.

10.

Calculate CEA position at -1000 PCM, +500 PCM, and -500 PCM from the estimated critical condition and enter on the appropriate line. The licensed operator preparing the worksheet shall sign the Prepared by line. Reactor Engineering shall Independently Verify the ECC and sign the Independently Verified by line. The Reactivity Manager shall review ECC in accordance with Appendix E and sign the Reviewed by line. The SM or US shall review the worksheet and sign the ~pproved by line. Following the boration / dilution to achieve the Estimated Critical Boron Concentration, the present boron concentration should be determined by chemical analysis. There should be approximately a 20 minute wait between the boron concentration change and RCS sampling. NOTE An ICRR shall be plotted for all approaches to criticality. The initial approach to criticality following refueling shall be performed in accordance with Preop 2-3200088, Initial Criticality Following Refueling. After a Reactor trip from low power or during start-up testing, the critical conditions at the time of trip may be used for recovery or restart.

11.

Complete the ICRR Data Sheet and Plot Sheet as follows: A. Verify that the ECC Calculation Worksheet has been completed and enter the estimated critical CEA position on a copy of the ICRR Data Sheet (Figure A.9 Data Sheet in the Physics Curve Book). B. Select two Startup or Wide Range Log Safety channels and record the stable CPS or percent power with CEAs at the initial position and record initial CEA position. REVISION NO. PROCEDURE TITLE: PAGE: 50 of 61 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 1---------1 38 PROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 4 of 8)

3.

§1 Ensure the Estimated Critical Boron Concentration is greater than or equal to the boron concentration required for shutdown margin needed prior to Startup (Mode 2), in accordance with 2-NOP-1 00.04, Surveillance Requirements for Shutdown Margin, Modes 2, 3, 4, and 5 (Subcritical).

4.

§1 Ensure that the critical CEA position is above the insertion limits of Technical Specification 3.1.3.6 and initial Note 2 of ECC Calculation Worksheet.

5.

Calculate CEA position at -1000 PCM, +500 PCM, and -500 PCM from the estimated critical condition and enter on the appropriate line.

6.

The licensed operator preparing the worksheet shall sign the Prepared by line.

7.

Reactor Engineering shall Independently Verify the ECC and sign the Independently Verified by line.

8.

The Reactivity Manager shall review ECC in accordance with Appendix E and sign the Reviewed by line.

9.

The SM or US shall review the worksheet and sign the Approved by line.

10.

Following the boration / dilution to achieve the Estimated Critical Boron Concentration, the present boron concentration should be determined by chemical analysis. There should be approximately a 20 minute wait between the boron concentration change and RCS sampling. NOTE An ICRR shall be plotted for all approaches to criticality. The initial approach to criticality following refueling shall be performed in accordance with Preop 2-3200088, Initial Criticality Following Refueling. After a Reactor trip from low power or during start-up testing, the critical conditions at the time of trip may be used for recovery or restart.

11.

Complete the ICRR Data Sheet and Plot Sheet as follows: A. Verify that the ECC Calculation Worksheet has been completed and enter the estimated critical CEA position on a copy of the ICRR Data Sheet (Figure A.9 Data Sheet in the Physics Curve Book). B. Select two Startup or Wide Range Log Safety channels and record the stable CPS or percent power with CEAs at the initial position and record initial CEA position.

REVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 I-------~ PROCEDURE NO.: 51 of 61 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 5 of 8)

11.

(continued) C. Commence a Reactor Startup in accordance with this procedure and at approximate positions indicated on the ICRR Data Sheet In Plant Physics Curves, stop CEA withdrawal and allow the count rate to stabilize. D. Record the CPS or percent power indication on the ICRR Data Sheet and compute the ICRR for both selected channels using the formula: % P cps* ICRRn= 0 owen or=~i % Powern cpsn Where: % Power j = Initial % Power CPS i = Initial counts per second % Power n = % Power at present CPS n = Counts per second at present ICRR n = Present Inverse Count Rate Ratio E. Plot the ICRR on the Figure A.9 Inverse Count Rate Ratio Plot Sheet. F. If the ICRR plot indicates that criticality will occur at a CEA height which is less than the POlL limits of Technical Specification 3.1.3.6, Then:

1.

Stop CEA withdrawal.

2.

Recompute the ECC using the current verified RCS boron concentration by chemistry analysis, if necessary.

3.

Determine a boron concentration that will establish criticality above the POlL.

4.

Borate to the calculated concentration.

5.

Start the ICRR plot over again (re-normalize) by substituting the count rate after the boron change for CPS j.

6.

Continue CEA withdrawal as before.

12.

Between 3 x 10-4 % and 7 x 10-4 % of rated power, following criticality, stabilize conditions then record actual critical data on the ECC Calculation Worksheet. ( ( REVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 1--------1 51 of 61 PROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 5 of 8)

11.

(continued) C. Commence a Reactor Startup in accordance with this procedure and at approximate positions indicated on the ICRR Data Sheet In Plant Physics Curves, stop CEA withdrawal and allow the count rate to stabilize. D. Record the CPS or percent power indication on the ICRR Data Sheet and compute the ICRR for both selected channels using the formula: % P cps' ICRRn= 0 owen or=~i % Powern cpsn Where: % Power i = Initial % Power CPS i = Initial counts per second % Power n = % Power at present CPS n = Counts per second at present ICRR n = Present Inverse Count Rate Ratio E. Plot the ICRR on the Figure A.9 Inverse Count Rate Ratio Plot Sheet. F. If the ICRR plot indicates that criticality will occur at a CEA height which is less than the POI L limits of Technical Specification 3.1.3.6, Then:

1.

Stop CEA withdrawal.

2.

Recompute the ECC using the current verified RCS boron concentration by chemistry analysis, if necessary.

3.

Determine a boron concentration that will establish criticality above the POlL.

4.

Borate to the calculated concentration.

5.

Start the ICRR plot over again (re-normalize) by substituting the count rate after the boron change for CPS i.

6.

Continue CEA withdrawal as before.

12.

Between 3 x 10-4 % and 7 x 10-4 % of rated power, following criticality, stabilize conditions then record actual critical data on the ECC Calculation Worksheet.

EVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 52 of 61 ROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 6 of 8) ECC CALCULATION WORKSHEET (Page 1 of 2) Unit No.: 2 Startup No.: Date of ECC: / / Exposure: EFPH COLUMN 1 COLUMN 2 PARAMETER Conditions Prior to Shutdown Estimated Critical Conditions Difference Sign (PCM) Determination Time 1: Date --'--'-- Time: Time 2: Date --'--'-- Time: Power Defect At % Power Figure A.1 NA NA (+) PCM (+) Always PCM Xenon Worth From DCS or Figure A.4 From Figure AA or as provided by R.E. PCiV1 PCM ( ) PCM (+) If Column 1 is Samarium and From Figure A.S. or as provided by R.E. greater than From Figure A.S. PCM ( ) PCM Column 2 Neptunium Worth PCiV1 (-) If Column 1 is Present Boron Concentration less than Column 2 Boron Worth PPM X Boron Worth PPM X Boron Worth PCM ( ) PCM (Note 1) From Figure A.B. PCM From Figure A.B. (-) If Column 1 is Group ___ withdraw to inches ' Group __ withdraw to inches greater than CEA Reactivity PCM ( ) PCM Column 2 Worth Use Figure A.6. or A.7.' PCM Use Figure A,6. or A.7. (Note 2) I (+) If Column 1 is less than Column 2 Reactivity N'A N'A From Figure B.,3 oras provided by R.E. PCM ( ) PCM Deviation Net Reactivity Total up the reactivities in the Difference column and enter the value here. Observe signs. ( ) PCM '~--~-.-.....,---~--, ~ PEVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 52 of 61 PROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 6 of 8) ECC CALCULATION WORKSHEET (Page 1 of 2) Unit No.: 2 Startup No.: Date of ECC: I I Exposure: EFPH COLUMN 1 COLUMN 2 PARAMETER Conditions Prior to Shutdown Estimated Critical Conditions Difference Sign (PCM) Determination Time 1: Date I I Time: Time 2: Date I I Time: Power Defect At % Power Figure A.1 NA NA (+) PCM (+) Always PCM Xenon Worth From DCS or Figure AA From Figure AA or as provided by RE. PCrV1 PCM ( ) PCM (+) If Column 1 is Samarium and From Figure A.S. or as provided by R.E. greater than From Figure A.S. PCM ( ) PCM Column 2 Neptunium Worth peM (-) If Column 1 is Present Boron Concentration less than Column 2 Boron Worth PPM X Boron Worth PPM X Boron Worth ( ) peM PCM (Note 1) From Figure A.B. peM From Figure A.B. (-) If Column 1 is Group ___ withdraw to inches . Group __ withdraw to inches greater than CEA Reactivity PCM ( ) peM Column 2 Worth Use Figure A.S. or A.7. peM Use Figure A.S. or A.7. (Note 2) (+) If Column 1 is less than Column 2 Reactivity N/A N/A From Figure B.3, Of,as provided by R.E. PCM ( ) peM Deviation Net Reactivity Total up the reactivities in the Difference column and enter the value here. Observe signs. ( ) PCM . - ---~--.,---~~-- -

REVISION NO.: PROCEDURE TITLE: PAGE: 38 PROCEDURE NO.: REACTOR PLANT STARTUP - MODE 3 TO MODE 2 53 of 61 2-GOP-302 ST. LUCIE UNIT 2 APPENDIXC ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 7 of 8) ECC CALCULATION WORKSHEET (Page 2 of 2) PARAMETER Difference Sign Determination If sign is +, ( Net Reactivity ) _ ( ( ) PCM ) Borate Total Change in ( ) PPM Boron Column 2 Boron Worth PCM/PPM If sign is -, Dilute Estimated Critical (present RCS Boron concentration) + [ T~tai Change in Boron concentration) Boron ( ) PPM (Note 3) Concentration CEA Position at -1000 PCM from ECC = Inches withdrawn on Group Startup (Mode 2) entry point CEA Position at +500 PCM from ECC = Inches withdrawn on Group CEA Position at -500 PCM from ECC = Inches withdrawn on Group REVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 53 of 61 PROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 7 of 8) ECC CALCULATION WORKSHEET (Page 2 of 2) PARAMETER Difference Sign Determination If sign is +, ( Net Reactivity ) _ ( ( ) PCM ) Borate Total Change in ( ) PPM Boron Column 2 Boron Worth PCM/PPM If sign is *, Dilute Estimated Critical ( Present RCS Boron concentration) + ( T~tai Change in Boron concentration) Boron ( ) PPM (Note 3) Co ncentratio n CEA Position at *1000 PCM from ECC = Inches withdrawn on Group Startup (Mode 2) entry point CEA Position at +500 PCM from ECC = Inches withdrawn on Group CEA Position at *500 PCM from ECC = Inches withdrawn on Group

REVISION NO.: PROCEDURE TITLE: PAGE: 38 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 ~------------~ 54 of 61 PROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2

• t

~ ______________ L-________________________________________ ~ ~' APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 8 of 8) ECC CALCULATION WORKSHEET (continued) NOTES:

1. If the difference in time between when the. boron sample was drawn and the time of shutdown exceeds 24 hours, contact Reactor Engineering.

2. The critical CEA position has been verified to be above POlL (Technical Specification COLR Fig. 3.1-2)

(initials).

3.

The ECC Boron Concentration must meet or exceed the boron concentration requirements for shutdown margin with CEAs at Column 2 position in accordance with 2-NOP-100.04, Surveillance Requirements for Shutdown Margin, Modes 2, 3, 4 and 5, Subcritical. Prepared By: ________ :::--:-___ ------- RCO ACTUAL CRITICAL CONDITIONS Date of Criticality __, __ /_ Independently Time (24 hour clock) Verified By: _________ ---,-_____ CEA Group/Position (inches) __ ~, __ Reactor Engineering RCS Boron Concentration (PPM) ___ Xenon Worth (DCS or Fig A.4) I have reviewed the requirements of this procedure including other surveillances T-avg (OF) Reactor Power (%) ____ _ performed during this procedure, if any (Le., datasheet(s), PMT sheet(s), etc.). Any deviations, abnormal results, equipment problems, failures, or human performance issues must be documented via a Condition Report for each individual item. C.R.# ________ _ Reviewed By: ___________________________ _ Reactivity Manager Approved By: ____________________________ _ SM or US ( REVISION NO.: PROCEDURE TITLE: PAGE: 54 of 61 REACTOR PLANT STARTUP - MODE 3 TO MODE 2 r--------------; 38 PROCEDURE NO.: 2-GOP-302 ST. LUCIE UNIT 2 APPENDIX C ESTIMATED CRITICAL CONDITIONS AND INVERSE COUNT RATE RATIO (Page 8 of 8) ECC CALCULATION WORKSHEET (continued) NOTES:

1.

If the difference in time between when the boron sample was drawn and the time of shutdown exceeds 24 hours, contact Reactor Engineering.

2.

The critical CEA position has been verified to be above PDIL (Technical Specification COLR Fig. 3.1-2) (initials).

3.

The ECC Boron Concentration must meet or exceed the boron concentration requirements for shutdown margin with CEAs at Column 2 position in accordance with 2-NOP-100.04, Surveillance Requirements for Shutdown Margin, Modes 2, 3, 4 and 5, Subcritical. Prepared By: -------=-=c-=-------- RCO ACTUAL CRITICAL CONDITIONS Date of Criticality __, __,_ Independently Time (24 hour clock) Verified By: ______ :--:::-__,--_____ CEA Group'Position (inches) ___ ---...:' Reactor Engineering RCS Boron Concentration (PPM) ___ Xenon Worth (DCS or Fig A.4) I have reviewed the requirements of this procedure including other surveillances T-avg (OF) Reactor Power (%) ________ _ performed during this procedure, if any (i.e., datasheet(s), PMT sheet(s), etc.). Any deviations, abnormal results, equipment problems, failures, or human performance issues must be documented via a Condition Report for each individual item. C.R.# _________ _ Reviewed 8y: ______________________________________________ _ Reactivity Manager Approved 8y: __________________________ __ SM or US

CANDIDATE EXAMINER REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Perform a Manual Calorimetric NRC A-2 NRC ADM JPM A-2 fRey 0 Classroom PAGE 1 CANDIDATE EXAMINER ( REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Perform a Manual Calorimetric NRC A-2 NRC ADM JPM A-2 fRey 0 Classroom PAGE 1

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Perform Manual Calorimetric KA Statement: Ability to evaluate plant performance and make operational judgments based on I operating characteristics, reactor behavior, and instrument interpretation. KA#: 2.1.7(4.4/4.7)

References:

2-3200020, Primary System Manual Calorimetric, Steam Tables Candidate: Time Start Name Performance Rating: Sat Unsat Validation Time 30 minutes Examiner: Signature: Comments Time Finish NRC ADM JPM A-2 IRev 0 PAGE 2 REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Perform Manual Calorimetric KA Statement: Ability to evaluate plant performance and make operational judgments based on I operating characteristics, reactor behavior, and instrument interpretation. KA#: 2.1.7(4.414.7)

References:

2-3200020, Primary System Manual Calorimetric, Steam Tables Candidate: Name Performance Rating: Sat Unsat Validation Time 30 minutes Examiner: Signature: Comments Time Start --- Time Finish --- NRC ADM JPM A-2 fRey 0 PAGE 2

( { REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Perform Manual Calorimetric Directions to the candidate for Administrative JPMS: I wi" 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 Today is Thursday 10-01-09, 11 :30am. Unit 2 is at approximately 45% power steady state. Initiating Cue The Unit Supervisor has instructed you to perform a primary system manual calorimetric lAW 2-3200020', Primary System Manual Calorimetric' Data Sheet 1 and determine core power. NO computers are available to perform this calculation. Classroom Data Sheet Steam Generator Pressures are as follows: PI-8013A: 885 psia PI-8023A: 886 psia PI-8013B: 887 psia PI-8023B: 886 psia PI-8013C: 888 psia PI-8023C: 887 psia PI-8013D: 889 psia PI-8023D: 886 psia Feedwater Temperatures are 362.rF. Total blowdown = 80 gpm Feed flow 9011-2 (ERDADS) = 2.50 x1 06 Ibm/hr Feed flow 9021-2 (ERDADS) = 2.50 x1 06 Ibm/hr DCS pt KFA = 29101 DCS pt KFB = 29345 Charging and Letdown are in operation. DCS 10 min avg: 46.1% NRC ADM JPM A-2 (Rev 0 PAGE 3 ( REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Perform Manual Calorimetric 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 Today is Thursday 10-01-09, 11 :30am. Unit 2 is at approximately 45% power steady state. Initiating Cue The Unit Supervisor has instructed you to perform a primary system manual calorimetric lAW 2-3200020', Primary System Manual Calorimetric' Data Sheet 1 and determine core power. NO computers are available to perform this calculation. Classroom Data Sheet Steam Generator Pressures are as follows: PI-8013A: 885 psia PI-8023A: 886 psia PI-8013B: 887 psia PI-8023B: 886 psia PI-8013C: 888 psia PI-8023C: 887 psia PI-8013D: 889 psi a PI-8023D: 886 psi a Feedwater Temperatures are 362.rF. Total blowdown = 80 gpm Feed flow 9011-2 (ERDADS) = 2.50 x1 06 Ibm/hr Feed flow 9021-2 (ERDADS) = 2.50 x1 06 Ibm/hr DCS pt KFA = 29101 DCS pt KFB = 29345 Charging and Letdown are in operation. DCS 10 min avg: 46.1% NRC ADM JPM A-2 (Rev 0 PAGE 3

JOB PERFORMANCE MEASURE 2-3200020, Primary System Manual Calorimetric Section 6.0 Data Sheet 1 STEP 1 (6.2): Date and current time. STANDARD: ENTERS date and current time on Data Sheet 1 per classroom data. EXAMINER'S CUE: None COMMENTS: __ SAT UNSAT r--.-----------------------------------------------r--------~ STEP 2 (6.2): MAIN STEAM PRESSURE PI-8013A: 885 psia PI-8023A: 886 psia PI-8013B: 887 psia PI-8023B: 886 psia PI-8013C: 888 psia PI-8023C: 887 psia PI-8013D: 889 psia PI-8023D: 886 psia STANDARD: ENTER MAIN STEAM PRESSURE for all pressures per classroom data. EXAMINER'S CUE: None COMMENTS: CRITICAL STEP __ SAT UNSAT

---

l NRC JPMI Rev 0 Classroom Page 4 of 14

( ( JOB PERFORMANCE MEASURE 2-3200020, Primary System Manual Calorimetric Section 6.0 Data Sheet 1 STEP 1 (6.2): Date and current time. STANDARD: ENTERS date and current time on Data Sheet 1 per classroom data. EXAMINER'S CUE: None COMMENTS: __ SAT UNSAT .--------------------------------------+--------1 STEP 2 (6.2): MAIN STEAM PRESSURE PI-8013A: 885 psia PI-8023A: 886 psia PI-8013B: 887 psia PI-8023B: 886 pSia PI-8013C: 888 psia PI-8023C: 887 psia PI-8013D: 889 psi a PI-8023D: 886 psi a STANDARD: ENTER MAIN STEAM PRESSURE for all pressures per classroom data. EXAMINER'S CUE: None COMMENTS: CRITICAL STEP __ SAT UNSAT L _____________________________________ --1 _____ 1 NRC JPMI Rev 0 Classroom Page 4 of 14

JOB PERFORMANCE MEASURE STEP 3 (6.3): COMPUTE TOTAL FEEDWATER FLOW A A Loop x -;- 29178 = ~~_x 106 1b/hr (FT 9011-2 (ERDADS), or F-9011) (DCS PT KFA) STANDARD: ENTERS and CALCULATES FEEDWATER FLOW A Loop. A A Loop 2.50 x 29101 -;- 29178 = 2.493 x 106 Ib/hr FEEDWATER FLOW A Loop = (2.490 - 2.493 X 106 Ib/hr) EXAMINER'S CUE: None COMMENTS: CRITICAL STEP __ SAT UNSAT ~-.--~.-.~~-~~~~~~~~~~~~~~~~~~~~~+-~----------.-- STEP 4 (6.3) COMPUTE TOTAL FEEDWATER FLOW B. B Loop x -;- 29050 = ~~_x 106 1b/hr (FT 9021-2 (ERDADS), or F-9021) (DCS PT KFB) STANDARD: ENTERS and CALCULATES FEEDWATER FLOW BLoop. B. BLoop 2.50 x 29345 -;- 29050 = 2.525 x 106 Ib/hr FEEDWATER FLOW BLoop = (2.52 - 2.53 X10 6 Ib/hr) EXAMINER'S CUE: None COMMENTS: CRITICAL STEP __ SAT UNSAT I .......... ______._... _________ ~ _________L ___ . _____. __.J NRC JPMI Rev 0 Classroom Page 5 or 14 ( I JOB PERFORMANCE MEASURE r*-----*- IS-TEP 3 (6.3): COMPUTE TOTAL FEEDWATER FLOW A. A Loop x .;- 29178 = x 106 Ib/hr (FT 9011-2 (ERDADS), or F-9011) (DCS PT KFA) STANDARD: ENTERS and CALCULATES FEEDWATER FLOW A Loop. A. A Loop 2.50 x 29101.;- 29178 = 2.493 x 106 Ib/hr FEEDWATER FLOW A Loop = (2.490 - 2.493 X 106 1b/hr) EXAMINER'S CUE: None COMMENTS: CRITICAL STEP __ SAT UNSAT

---

.-~.-.--:-__=_----__:_c_:::______c---------------__+_---.. --....

STEP 4 (6.3) COMPUTE TOTAL FEEDWATER FLOW B. B Loop x .;- 29050 = ___ x 106 Ib/hr (FT 9021-2 (ERDADS), or F-9021) (DCS PT KFB) STANDARD: ENTERS and CALCULATES FEEDWATER FLOW BLoop. B. BLoop 2.50 x 29345.;- 29050 = 2.525 x 106 Ib/hr FEEDWATER FLOW BLoop := (2.52 - 2.53 X10 6 Ib/hr) EXAMINER'S CUE: None COMMENTS: CRITICAL STEP SAT UNSAT L........ _____.... _.. __________________________ -"-_________... _.. _.1 NRC JPMI Rev 0 Classroom Page 5 or 14

JOB PERFORMANCE MEASURE STEP 5 (6.3) COMPUTE TOTAL FEEDWATER FLOW MFW = x 106 1b/hr (Total A+B Loop) STANDARD: ENTERS and CALCULATES TOTAL FEEDWATER FLOW. MFW = (2.493 + 2.525 = 5.018 X 106 1b/hr (Total A+B Loop) ( 2.49 + 2.52 = 5.01) ( 2.493 + 2.53 = 5.023) MFW Flow total = ( 5.01 - 5.023 X106 Ib/hr) EXAMINER'S CUE: None COMMENTS: STEP 6 (6.3) COMPUTE Average Steam Pressure. Average Steam Pressure = ____ divided by 8 = _____ TOTAL AVERAGE STANDARD: ENTERS and CALCULATES Average Steam Pressure per classroom data. 885 +886 +887 +886 +888 +887 +889 +886 = 7094/8 = 886.75 Average Steam Pressure = 886.8 psia. EXAMINER'S CUE: None COMMENTS: CRITICAL STEP __ SAT UNSAT CRITICAL STEP __ SAT UNSAT NRC JPMI Rev 0 Classroom Page 6 of 14 ( I JOB PERFORMANCE MEASURE STEP 5 (6.3) COMPUTE TOTAL FEEDWATER FLOW MFW = x 106 Jb/hr (Total A+8 Loop) STANDARD: ENTERS and CALCULATES TOTAL FEEDWATER FLOW. MFW = (2.493 + 2.525 = 5.018 X 106 1b/hr (Total A+8 Loop) ( 2.49 + 2.52 = 5.01) ( 2.493 + 2.53 = 5.023) MFW Flow total = ( 5.01 - 5.023 X1 0 6 Ih/hr) EXAMINER'S CUE: None COMMENTS: CRITICAL STEP __ SAT UNSAT I--------------------------------+-----~-- I STEP 6 (6.3) COMPUTE Average Steam Pressure. I Average Steam Pressure = ____ divided by 8 = _____ TOTAL AVERAGE STANDARD: ENTERS and CALCULATES Average Steam Pressure per classroom data. 885 +886 +887 +886 +888 +887 +889 +886 = 7094/8 = 886.75 Average Steam Pressure = 886.8 psia. EXAMINER'S CUE: None COMMENTS: CRITICAL STEP __ SAT UNSAT NRC JPMI Rev 0 Classroom Page 6 of 14

JOB PERFORMANCE MEASURE STEP 7 (6.3): ENTER FEEDWATER TEMPERATURE TR-09-5B Channel 1 ___ oF Channel 2 ___ oF (behind RTGB 202) Average Feedwater Temperature ____ divided by 2 = ______ TOTALAVERAGE STANDARD: ENTERS FEEDWATER TEMPERATURE and CALCULATES Average Feedwater Temperature. Both channels were given as 362. rF per classroom data so total Average Feedwater Temperature is 362.7°F. No calculation is required. EXAMINER'S CUE: None COMMENTS: STEP 8 (6.4.1): Determine the enthalpy for the average main steam pressure (hsTEAM). STANDARD: DETERMINES and ENTERS the enthalpy for the average main steam pressure (hsTEAM). 886.8 psia average main steam pressure 860 psi a : hSTEAM= 1197.5 BTU/Ibm 900 psia : hSTEAM= 1196.2 BTU/Ibm hSTEAM= 1196.6 BTU/Ibm hSTEAM: = (1196.4 - 1197.3 BTUllbm) EXAMINER'S CUE: None __ SAT UNSAT CRITICAL STEP __ SAT UNSAT --.. ~------------------------------------------'---------- NRC JPMI Rev 0 Classroom Page 7 of 14 ( ( I I JOB PERFORMANCE MEASURE STEP 7 (6.3): ENTER FEEDWATER TEMPERATURE TR-09-5B ChanneI1 ___ oF ChanneI2 ___ oF (behind RTGB 202) Average Feedwater Temperature ____ divided by 2 = _____ TOTALAVERAGE STANDARD: ENTERS FEEDWATER TEMPERATURE and CALCULATES Average Feedwater Temperature. Both channels were given as 362. rF per classroom data so total Average Feedwater Temperature is 362.7°F. No calculation is required. EXAMINER'S CUE: None SAT UNSAT I COMMENTS: I I 1------------------------------------1-------1 STEP 8 (6.4.1): Determine the enthalpy for the average main steam CRITICAL pressure (hsTEAM). STEP STANDARD: DETERMINES and ENTERS the enthalpy for the average main steam pressure (hsTEAM). 886.8 psia average main steam pressure 860 psia : hSTEAM= 1197.5 BTU/Ibm 900 psia : hSTEAM= 1196.2 BTU/Ibm hSTEAM= 1196.6 BTU/Ibm hSTEAM: = (1196.4 - 1197.3 BTUllbm) EXAMINER'S CUE: None __ SAT UNSAT ~ _____.. J NRC JPMI Rev 0 Classroom Page 7 of 14

JOB PERFORMANCE MEASURE COMMENTS: STEP 9 (6.4.2): Determine the mass flow of blowdown by using Table 1, Data Sheet 1, to convert GPM to Ibm/hr. STANDARD: DETERMINES And ENTERS and the mass flow of blowdown. .039599 x 106 1bm/hr EXAMINER'S CUE: None COMMENTS: STEP 9 (6.4.3): Subtract blowdown mass flow (MBD) from feedwater mass flow (MFw) to obtain steam flow. STANDARD: DETERMINES And ENTERS steam flow. (5.01 - 5.023.. 039599 X 106) = (4.97-4.983 X 106 Ibm/hr) [ MFW MBO] = Steam flow Steam Flow: 4.97-4.983 X 106 Ibm/hr EXAMINER'S CUE: None COMMENTS: CRITICAL STEP __ SAT UNSAT CRITICAL STEP __ SAT UNSAT STEP 9 (6.4.4): Multiply the quantity from step 6.4.3 times the enthalpy from CRITICAL step 6.4.1. This resultant is QSTEAM. STEP 106 106 106 BTU/hr hSTEAM X [MFW - MBO] = QSTEAM __ SAT NRC JPM! Rev 0 Classroom Page 8 of 14 ( ( JOB PERFORMANCE MEASURE rOMMENTS I STEP 9 (6.4.2): Determine the mass flow of blowdown by using Table 1, Data Sheet 1, to convert GPM to Ibm/hr. STANDARD: DETERMINES And ENTERS and the mass flow of blowdown. .039599 x 106 Ibm/hr EXAMINER'S CUE: None COMMENTS: I STEP 9 (6.4.3): Subtract blowdown mass flow (MBD) from feedwater mass flow (MFw) to obtain steam flow. I i STANDARD: DETERMINES And ENTERS steam flow. I I j (5.01 - 5.023 -.039599 X 10 6 ) = (4.97-4.983 X 10 6 Ibm/hr) [ MFW MBO] = Steam flow Steam Flow: 4.97-4.983 X 106 Ibm/hr EXAMINER'S CUE: None I COMMENTS: CRITICAL STEP __ SAT UNSAT CRITICAL STEP __ SAT UNSAT I~-~~-----------------~---------------+--------~-~ I STEP 9 (6.4.4): Multiply the quantity from step 6.4.3 times the enthalpy from step 6.4.1. This resultant is QSTEAM. 106 106 106 BTU/hr hSTEAM X [MFW - MBO] = QSTEAM CRITICAL STEP __ SAT NRC JPM! Rev 0 Classroom Page 8 of 14

JOB PERFORMANCE MEASURE STANDARD: DETERMINES QSTEAM. (1196.4 - 1197.3) X (5.01 - 5.023 -.039599 X 106) = (5946.1 - 5962.6 X 106 BTU/hr) hSTEAM X [ MFW MBD] = QSTEAM (4.97 - 4.983) QSTEAM = ( 5946.1 - 5966.1 X 106 Ib/hr ) EXAMINER'S CUE: None COMMENTS: STEP 10 (6.5.1) : From the steam tables, enter the enthalpy of the average feedwater temperature: hFw = ____ BTU/Ibm STANDARD: ENTER the enthalpy of the average feedwater temperature using steam tables: TFW 362.rF 360°F = 332.34 BTU/Ibm 364°F = 336.57 BTUllbm hFW = 334.45 BTU Ibm hFw = (334.0- 335.0 BTU/Ibm) EXAMINER'S CUE: None COMMENTS: UNSAT CRITICAL STEP __ SAT UNSAT NRC JPMI Rev 0 Classroom Page 9 of 14 ( ( JOB PERFORMANCE MEASURE STANDARD: DETERMINES QSTEAM. (1196.4-1197.3) X(5.01-5.023.. 039599X106) =(5946.1-5962.6 X106 BTU/hr) hSTEAM X [ MFW MBD] = QSTEAM (4.97 - 4.983) QSTEAM = ( 5946.1 - 5966.1 X 10 6 Ib/hr ) EXAMINER'S CUE: None COMMENTS: STEP 10 (6.5.1) : From the steam tables, enter the enthalpy of the average feedwater temperature: hFw = _____ BTU/Ibm STANDARD: ENTER the enthalpy of the average feedwater temperature using steam tables: TFW 362.rF 360°F = 332.34 BTU/Ibm 364°F = 336.57 BTU/Ibm hFW = 334.45 BTU Ibm hFw = (334.0- 335.0 BTUllbm) EXAMINER'S CUE: None COMMENTS: UNSAT CRITICAL STEP SAT UNSAT NRC JPMI Rev 0 Classroom Page 9 of 14

JOB PERFORMANCE MEASURE STEP 11 (6.5.2) : Calculate the heat feedwater heat input (QFW): STANDARD: ENTER and CALCULATE the heat feedwater heat input. (QFW). (5.01 - 5.023 x 106 ) x (334.0 - 335.0) = 1673.34 - 1691.75 x 106 BTU MFW hFW QFW hr QFW = (1673.0 - 1683.0 X 106 BTU/hr) EXAMINER'S CUE: None COMMENTS: CRITICAL STEP __ SAT UNSAT NRC JPMI Rev 0 Classroom Page 10 of 14 JOB PERFORMANCE MEASURE I STEP 11 (6.5.2) : Calculate the heat feedwater heat input (QFW): I (x 10 6 ) X ( ) = x 10 6 BTU I MFW hFW OFW hr I I \\ STANDARD: ENTER and CALCULATE the heat feedwater heat input. (OFW). (5.01 - 5.023 x 106 ) x (334.0 - 335.0) = 1673.34 - 1691.75 x 106 BTU MFW hFW OFW hr OFW = (1673.0 - 1683.0 X 106 BTu/hr) EXAMINER'S CUE: None COMMENTS: ( ( CRITICAL STEP __ SAT UNSAT NRC JPMI Rev 0 Classroom Page 10 or 14

JOB PERFORMANCE MEASURE STEP 12 (6.6): Circle the total blowdown flow from the S/Gs and the CRITICAL corresponding heat output: (Interpolation is not required, STEP circle the matching blowdown flow below or the lower flow if between flow rates, to be conservative.) SAT Total blowdown flow (both steam generators) 40 GPM 80 GPM 120 GPM 160 GPM 200 GPM 240 GPM Mass flow of blowdown Mso .019799 x 10e lbm/hr .039599 x 10e lbm/hr .059398 x 10e lbm/hr .079198 x 10e lbm/hr .098997 x 10e lbm/hr .118797 x 10e lbm/hr Heat output from blowdown Qso 9.728 x 1 Oe BTU/hr 19.456 x 106 BTU/hr 29.183 x 1 Oe BTU/hr 38.912 x 106 BTU/hr 48.639 x 1 Oe BTU/hr 58.367 x 106 BTU/hr STANDARD: CIRCLES the total blowdown flow from the S/Gs and the corresponding heat output per classroom data. Determines QBO to be 19.456 X 106 BTU/hr and enters on Data Sheet 1 EXAMINER'S CUE: None COMMENTS: STEP 13 (6.7) If charging and letdown flow is secured for any reason, use a value of 48.952 for QOTHER. This was provided by step 6.7 If charging and letdown flow is operating normally, use a value of 46.905 for QOTHER. STANDARD: CHOOSES 46.905 for QOTHER. Based on classroom data sheet that Charging and Letdown are in operation an enters UNSAT CRITICAL STEP ~ o_n_D_a_t_a_S_h_e_e_t_1 ______________________________ ~~ ________ ~ NRC JPMI Rev 0 Classroom Page II of 14 JOB PERFORMANCE MEASURE STEP 12 (6.6): 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 GPM .019799 x 106 1bm/hr 9.728 x 106 BTU/hr 80 GPM .039599 x 106 1bm/hr 19.456 x 106 BTU/hr 120 GPM .059398 x 106 1bm/hr 29.183 x 1 OB BTU/hr 160 GPM .079198 x 106 1bm/hr 38.912 x 106 BTU/hr 200 GPM .098997 x 106 1bm/hr 48.639 x 106 BTU/hr 240 GPM .118797 x 10"lbm/hr 58.367 x 106 BTU/hr STANDARD: CIRCLES the total blowdown flow from the S/Gs and the corresponding heat output per classroom data. Determines QBD to be 19.456 X 106 BTU/hr and enters on Data Sheet 1 EXAMINER'S CUE: None COMMENTS: CRITICAL STEP __ SAT UNSAT ---~-------.-------------------------t---------~ STEP 13 (6.7) If charging and letdown flow is secured for any reason, use a value of 48.952 for QOTHER. This was provided by step 6.7 If charging and letdown flow is operating normally, use a value of 46.905 for QOTHER. STANDARD: CHOOSES 46.905 for QOTHER. Based on classroom data sheet that Charging and Letdown are in operation an enters on Data Sheet 1 CRITICAL STEP NRC JPMI Rev 0 Classroom Page II of 14

( JOB PERFORMANCE MEASURE I STEP 13 (6.8) Calculate the heat output from the core: I i + ~_--,l x 106 BTU = ___ .x 106 BTU QOTHER hr Q CORE hr QSTEAM QBO I STANDARD: ENTER and CALCULATE the heat output from the core. I I i [(5946.1 5966.1) - (1673.0-1683.0)]+ [19.456 - 46.905]x10" BTU = 4245.6-4279.7x 10"BTU hr QCORE = ( 4235.0 - 4265.65 BTU/hr) EXAMINER'S CUE: None i COMMENTS: i I CRITICAL STEP __ SAT UNSAT 1- __________________ NRC JPMI Rev 0 Classroom Page 12 of 14 ( JOB PERFORMANCE MEASURE I STEP 13 (6.8) Calculate the heat output from the core: I i + ~~~~ ~---,l x 106 BTU = ___ x 106 BTU QOTHER hr Q CORE hr QSTEAM QBD i I STANDARD: ENTER and CALCULATE the heat output from the core. I I I [(5946.1 - 5966.1) - (1673.0-1683.0)]+ [19.456 - 46.905]x1 06 BTU = 4245.6-4279.7x 106BTU hr OCORE = ( 4235.0 - 4265.65 BTU/hr) EXAMINER'S CUE: None i COMMENTS: i I CRITICAL STEP ~~SAT UNSAT I ____. ______.. ~~~~~~--~~--'---------... - __ NRC JPMI Rev 0 Classroom Page 12 of 14

JOB PERFORMANCE MEASURE NOTE Calculated Power in percent must be within 2% of DCS Calorimetric power. If not, notify the US I SM. Initiate W/R for ICM to adjust !J. T power. STEP 14 (6.9): Calculate percent core power. Core Power = __ x 106 divided by (92.128 x 106) = __ % Manual QCORE Calorimetric Power STANDARD: ENTER and CALCULATE percent core power. Core Power = 4235.0 - 4265.65 x 106 I (92.128 x 106 ) = 45.9 - 46.3% Manual QCORE Calorimetric Power Core Power = ( 45.9 - 46.3%) EXAMINER'S CUE: Upon completion of Step 14 after manual calorimetric power is entered on Data Sheet 1 JPM is complete. COMMENTS: END OF TASK STOP TIME: CRITICAL STEP __ SAT UNSAT NRC JPMI Rev 0 Classroom Page 13 of 14 ( JOB PERFORMANCE MEASURE NOTE Calculated Power in percent must be within 2% of DCS Calorimetric power. If not, notify the US I SM. Initiate W/R for ICM to adjust l\\ T power. STEP 14 (6.9): Calculate percent core power. Core Power = __ x 106 divided by (92.128 x 106 ) = __ % Manual QCORE Calorimetric Power STANDARD: ENTER and CALCULATE percent core power. Core Power = 4235.0 - 426565 x 10 6

(92.128 X 10 6

) = 459 - 463% Manual QCORE Calorimetric Power Core Power = ( 45.9 - 46.3%) EXAMINER'S CUE: Upon completion of Step 14 after manual calorimetric power is entered on Data Sheet 1 JPM is complete. COMMENTS: END OF TASK STOP TIME: CRITICALl STEP I __ SAT UNSAT NRC.rPM/ Rev 0 Classroom Page 13 of 11

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) Initial Conditions It is Thursday 10-01-09, 11 :30am. Unit 2 is at approximately 45% power steady state. Initiating Cue The Unit Supervisor has instructed you to perform a primary system manual calorimetric lAW 2-3200020', Primary System Manual Calorimetric' Data Sheet 1 and determine core power. NO computers are available to perform this calculation. Classroom Data Sheet Steam Generator Pressures are as follows: PI-8013A: 887 psia PI-8023A: 886 psia PI-8013B: 887 psia PI-8023B: 886 psia PI-8013C: 888 psia PI-8023C: 887 psia PI-8013D: 887 psia PI-8023D: 886 psia Feedwater Temperatures are 362. rF. Total blowdown = 80 gpm Feed flow 9011-2 (ERDADS) = 2.50 x1 OE6 1bm/hr Feed flow 9021-2 (ERDADS) = 2.50 x1 OE6 Ibm/hr DCS pt KFA = 29101 DCS pt KFB = 29345 Charging and Letdown are in operation. DCS 10 min avg: 46.1% NRC JPMI Rev 0 Classroom Page 14 of 14 ( (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) Initial Conditions It is Thursday 10-01-09, 11 :30am. Unit 2 is at approximately 45% power steady state. Initiating Cue The Unit Supervisor has instructed you to perform a primary system manual calorimetric lAW 2-3200020', Primary System Manual Calorimetric' Data Sheet 1 and determine core power. NO computers are available to perform this calculation. Classroom Data Sheet Steam Generator Pressures are as follows: PI-8013A: 887 psia PI-8023A: 886 psia PI-8013B: 887 psia PI-8023B: 886 psia PI-8013C: 888 psia PI-8023C: 887 psia PI-8013D: 887 psia PI-8023D: 886 psia Feedwater Temperatures are 362.TF. Total blowdown = 80 gpm Feed flow 9011-2 (ERDADS) = 2.50 x1 OE6 1bm/hr Feed flow 9021-2 (ERDADS) = 2.50 x1 OE6 Ibm/hr DCS pt KFA = 29101 DCS pt KFB = 29345 Charging and Letdown are in operation. DCS 10 min avg: 46.1 % NRC JPM! Rev () Classroom Page 14 or J 4

c: o Eai c: E Q) :J E 0

J 0

...J g ~ Z"'OO...J O Q)x~ C> Q) I-Z C:"'O-ca c: Z o..c:'- 0"'0 1-"'02 << c: (5 -== ca.b .:::; c: c: 0:::.Q 8 o.~ ca LL Q)..c: z.... ::: 0 -~~W 0:::.;::,...... - O~2!+/-: LL -{ij 0::: Q) 0 W ~ '5.. > Q)a. W o ca !;;: Ci>:=" 0 co . &.6! TITLE: PRIMARY SYSTEM MANUAL CALORIMETRIC IPRIDCEDUF~E NO.:

1.

2-3200020 ST. LUCIE UNIT 2 DATA SHEET 1 (Page 1 of 3) Time: ENTER MAIN STEAM PRESSURE PI-8013A . 9f~ fj/C. P,-8023A'_--I:YL-I-ft-:-",0"'---f-F-.)L..!!'-=C.:!<-o-__ P'-8013B_""",=?~r~7---'fpr.....::...)~C(.:---_ PI-8023B ?f'(; 4x{ PI-8013C f'ff' 1/iJJ)c.* PI-8023C_.J.£.......I./--~----,'fl£-LL.::>,.. __ PI-8013D_.v.,..~-L;-_.p:t!.....:..!o<:'--__ PI-8023D_...lL--w--=----,f4J-='---__ COMPUTE TOTAL FEEDWATER FLOW .2~t/l!f - 2.1/93 A Loop

2" S D x ~~~~_

+ 29178 =.;J. 493 x 106 Ib/hr B L(OFTop901~ ;El3QAQ.S), or F-9011) x.....,'.i:::::DD~~'!=f-.~_ 5 A. B. ~"LV ~ + 29050 =2.. Zr; 106 Ib/hr (FT 9W1-2 (ERDADS), or F-9021) (DCS PT FB) S /J MFw=~OI - 5.0,?,,] x 106 1b/hr p... 2-tX-~S0 (Total A+B Loop) e Steam Pressure = 709'1 divided by 8 = tK L 75-' (,;,C i'V TOTAL AVERAGE ENTER FEEDWATER TEMPERATURE TR-09-5B Channel 1 Jt,2...?oF (behindRTGB 202) Feedwater Temperature 7 U </ (;r,1, 181~}) Channel 21b2-.loF divided by 2 = '3 C b. 7 AVERAGE the steam tables, entEir Jh~ enthalpy of th~ average steam pressure: hSTEAM=/Jn.~ BTU/Ibm VI "-f,. IllJ"b)) the heat o~ut due to steam flow (QSTEAM): I-:--'c....::....:.=-- fo/-f.olfiJ06,D),592106 106 BTu/hr J) hSTEAM X [MFW 7 - !V1BO] = QSTEAM( s-'1 ~'.I-~'itG. I; SLOPS DATE. ____ DOCT Procedure DOCN 2-3200020

c. tJ. 'j - f.'} rJ From the steam fables, enter the enthalpy of the average feedwater temperature:

SYS OPS hFw = BTU COMP COMPLETED Ibm ITM. ____ the heat feedW!ter.,~ input (QFW): '-->/--_ x 106 ) x <71'L -'b;) = x 106 BTU hFw I QFW hr ~~~~---------7~-=~--~~r---------------------------~ ( ( c .2......; REVISION NO.: 31 PROCEDURE NO.: 2-3200020 PROCEDURE TITLE: PRIMARY SYSTEM MANUAL CALORIMETRIC ST. LUCIE UNIT 2 DATA SHEET 1 (Page 1 of 3) Nffi ~ § oate:L 0 ILl OC; Eu ~ Time:

l 0

.....J g ~ Z-oO-l o ~ ~ <{ Z C -0 E co c Z O..c.- u-o 1---02 oCt C (5 0:::: co.):; ,::;cc 0:::.Q 8 o.~ co U. al..c Z ..... :=:o -~3:w 0::: *c ~ - o ~2 ~

u. --g a:

al u W ~ '5.. > alc.. W ..... co I-0.... <{ Qi=-o OJ

1.

ENTER MAIN STEAM PRESSURE PI-8013A 9£5' PYLe: 9t~ I PI-8023A rJIC~ PI-8013B ? 7 'vr)C{. rfr~ I PI-8023B aoq PI-8013C r-f f' / fl)J)C. PI-8023C 6ft ffi~ PI-8013D df (:)G, PI-8023D f1 ~ f/tA f[1 COMPUTE TOTAL FEEDWATER FLOW .2,t/q - 2. t/93 A Loop

)/5D x~~~

"",-_729178=.:l4~3 x10 6 Ib/hr (FT 9011-2 (E I}OA..QS), or F-9011) 1D; PT K,:(:;A A.

B. BLoop e2~LO xc>L. 3. 729050 = 2.. 5Zr; 106 Ib/hr (FT 9W1-2 (ERDADS), or F-9021) (DCS PT FB) MFw =c5... 01 - 5".023 x 106 1b/hr tZ.5<Z - ,2~S.,] (Total A+B Loop) Average Steam Pressure = 7 () 9 f divided by 8 = tJ-(; I ? 5...;../ TOTAL AVERAGE (J;Cj,V ENTER FEEDWATER TEMPERATURE TR-09-5B Channel 1 J~2.fF (behind.RTGB 202) Average Feedwater Temperature 7 U ! (p;" IBZ~}) Channel Jb{/.I°F divided by 2 = J C h 7 AVERAGE From the steam tables, entfir the enthalpy of th~ average steam pressure: hSTEAM= 1/7'. ( BTUllbm lJl r'. f,. 1/ rz.)) C~culate the heat 0y!put due to steam flow (QSTEAM): 11 i7. 3 ~()I-f.{)lii106, 03'75'97 106 10 6 BTU/hr J) hSTEAM X [MFW 7 ~BDl = QSTEAM( f1,/c,.I-1)CJtG.!; eLI. 'j - tl5rJ From the steam t~bles, enter the enthalpy of the average feedwater temperature: hFw = BTU Ibm Calculate the heat feedwater ~ input (QFW): SLOPS DATE, ____ DOCT Procedure DOCN 2-3200020 SYS OPS COMP COMPLETED ITM ____ (I X 10 6 ) x (]1</-J~ = x 10 6 BTU . V;tl _ }:~2.-iJ hFw / QFW hr ~~~-----rJ-'~1~J~-)-~~r7Jr-----------------~

TITLE: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC NO.: 2-3200020 ST. LUCIE UNIT 2 DATA SHEET 1 (Page 2 of 3) TABLE 1 ircle the total blowdown flow from the S/Gs and the correspond output: nterpolation is not required, circle the matching blowdown flow below or the lower flow if IngnA/<"gn flow rates, to be conservative.) Total blowdown flow (both steam generators) ~OGeM... ~ 120 GPM 160 GPM 200 GPM 240 GPM Mass flow of blowdown MBO Calculate the heat output from the core: Heat output from blowdown QBO f charging and letdown flow is secured for any reason, use a value If char,ging and letdown flow is operating normally, use a valu of 46.905 or QOTHER. 1Qfl(,..l-1~7]- [~"./ - //:;J'J + Ii. tjS( -~'.~x 106 BTU = x 106 ~ "2iS-QSTEAM QFW QBO QOTHER hr QCORE hr,/Z6r;'J NOTE Calculated Power in percent must be within 2% of DCS Calorimetric power. If not, noti the US I SM. Initiate W/R for ICM to ad'ust 11 Tower. Calc~te percent core power: 'It: 5 -1),.1 1/]; Jr-lj?4I':c.?1 I* 0 I Manual Core Power = x 1ov-divided by (92.128 x 106) = Yo Calorimetric QCORE Power Record DCS Calorimetric Power (QRP % 10 minute ave), (QRPP (instantaneous) should be used below if the reactor has not been in a stable power configuration for at least 10 minutes): DCS Calorimetric Power = (j C,. ) ( REVISION NO.: PROCEDURE TITLE: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEDURE NO.: 2-3200020 ST. LUCIE UNIT 2 DATA SHEET 1 (Page 2 of 3) TABLE 1 Circle the total blowdown flow from the S/Gs and the correspondin 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 (both steam generators) Mass flow of blowdown MBO Heat output from blowdown QBO ~OG~ ~ 120 GPM .019799 x 1061bmL~ a~9 x ~g: :~~~~ ~~~;:...:..:~~~~ .059398 x. r 160 GPM 200 GPM 240 GPM .079198 x 106 Ibm/hr .098997 x 106 Ibm/hr .118797 x 106 Ibm/hr Calculate the heat output from the core: If charging and letdown flow is secured for any reason, use a value If cha~ging and letdown flow is. operating normally, use a valu of 46.905 or QOTHER. 51f/~.*1- /073- [~"./ - I/:',!' J + 11. 'If( - ~C. 7D.JJ x 106 BTU = x 106 IDi 'I2J:S - QSTEAM QFW QBO QOTHER hr QCORE hr - '/2(;~ ('5"""" NOTE Calculated Power in percent must be within 2% of DCS Calorimetric power. If not, noti the US I SM. Initiate W/R for ICM to ad'ust ~ Tower. Calc~te per£§nt core powe.s-) LJ.t: 5 --!)C.J -,

• '12:-Jf -,,'l*tf:tS/

I 0 I Manual Core Power = x 106 divided by (92.128 x 106) = Yo Calorimetric QCORE Power Record DCS Calorimetric Power (QRP % 10 minute ave), (QRPP (instantaneous) should be used below if the reactor has not been in a stable power configuration for at least 10 minutes): DCS Calorimetric Power = 5/ L" I }

NO.: PROCEDURE TITLE: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC NO.: 2-3200020 ST. LUCIE UNIT 2 DATA SHEET 1 (Page 3 of 3) On the first Monday of the quarter, complete Data Sheet 2. On the first Monday of the quarter, complete Data Sheet 3. have reviewed the requirements of this procedure including other surveillances

lit}

Initial ~ during this procedure, if any (i.e., datasheet(s), PMT sheet(s), etc.). Any n(s) found during the performance of this procedure has (have) been listed an ppropriate actions and notifications made. A~~ 'kco US/SM

0

,W .~

.0 w

~ ( REVISION NO.: 31 PROCEDURE NO.: 2-3200020 PROCEDURE TITLE: PRIMARY SYSTEM MANUAL CALORIMETRIC ST. LUCIE UNIT 2 DATA SHEET 1 (Page 3 of 3)

2.

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

3.

On the first Monday of the quarter, complete Data Sheet 3. PAGE:,> jl/tJ 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. A ~,-.~' RCO US/SM

FPL

Title:

ST. LUCIE UNIT 2 OPERATING PROCEDURE SAFETY RELATED CONTINUOUS USE Effective Date 08/26/08 PRIMARY SYSTEM MANUAL CALORIMETRIC Responsible Department: REACTOR ENGINEERING REVISION

SUMMARY

Revision 31 - Incorporated PCR 08-3524 to change the periodicity of the performance of data sheet 2 and 3. (Carlos Diaz, 08/18/08) Revision 30 - Incorporated PCR 08-3603 for PCM 08096 to change device number. (Brad Bishop, 07/24/08) Revision 29B - Incorporated MC 08-0040 to change verbiage to clarify when determining blowdown flow values. (Clyde Price, 01/14/08) Revision 29A - Incorporated PCR 07-4414 to label Table 1 and added verbage for clarification in determining values when in between flow rates. (Clyde Price, 12/17/07) Revision 29 - Incorporated PCR 07-1166 for PCM 05137 to reflect new blowdown mass flow rate and heat output values in Data Sheet 1. (Tim Bolander, 09/10/07) Revision 28C - Incorporated MC 07-2322 to add FlO stamp and SOPS stamp on Data Sheet 1. (Clyde Price, 07/10/07) Revision 28B - Incorporated PCR 07-0228 to replace FR-9011 with F-9011. (Dave Pottorff, 01/17/07) Revision 28A - Incorporated PCR 06-3831 to add comment to note box. (R. Poppell, 10/26/06) Revision FRG Review Date Approved By Approval Date S...LOPS 0 03/08/83 C. M. Wethy 03/08/83 DATE Plant General Man DOCT Revision FRG Review Date Approved By Approval Date DOCN 31 N/A SYS Plant General Manager COM John Harmon 08/25/08 ITM Authorized Approver N/A Authorized Approver (Minor Correction) ( FPL

Title:

ST. LUCIE UNIT 2 OPERATING PROCEDURE SAFETY RELATED CONTINUOUS USE Procedure No.

• J;;;n~*;\\

2-320002'0 Current t-'UUISlnn No. Effective Date 08/26/08 PRIMARY SYSTEM MANUAL CALORIMETRIC Responsible Department: REACTOR ENGINEERING REVISION

SUMMARY

Revision 31 - Incorporated PCR 08-3524 to change the periodicity of the performance of data sheet 2 and 3. (Carlos Diaz, 08/18/08) Revision 30 - Incorporated PCR 08-3603 for PCM 08096 to change device number. (Brad Bishop, 07/24/08) Revision 298 - Incorporated MC 08-0040 to change verbiage to clarify when determining blowdown flow values. (Clyde Price, 01/14/08) Revision 29A - Incorporated PCR 07-4414 to label Table 1 and added verbage for clarification in determining values when in between flow rates. (Clyde Price, 12/17/07) Revision 29 - Incorporated PCR 07-1166 for PCM 05137 to reflect new blowdown mass flow rate and heat output values in Data Sheet 1. (Tim Bolander, 09/10/07) Revision 28C - Incorporated MC 07-2322 to add FlO stamp and SOPS stamp on Data Sheet 1. (Clyde Price, 07/10/07) Revision 288 - Incorporated PCR 07-0228 to replace FR-9011 with F-9011. (Dave Pottorff, 01/17/07) Revision 28A - Incorporated PCR 06-3831 to add comment to note box. (R. Poppell, 10/26/06) Revision FRG Review Date Approved By Approval Date S....LOPS 0 03/08/83 C. M. Wethy 03/08/83 DATE Plant General Man DOCT Revision FRG Review Date Approved By Approval Date DOCN 31 N/A SYS Plant General Manager COM John Harmon 08/25/08 ITM Authorized Approver N/A Authorized Approver (Minor Correction)

NO.: PROCEDURE TITLE: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEDURE NO.: 2-3200020 ST. LUCIE UNIT 2 TABLE OF CONTENTS SECTION 1.0 PURPOSE...................................................................................................... 3 .0 REFERENCES............................................................................................... 3 .0 PREREQUISITES.......................................................................................... 4 .0 PRECAUTIONS I LIMITATIONS.................................................................... 4 5.0 RECORDS REQUIRED................................................................................. 4 6.0 INSTRUCTIONS............................................................................................ 5 7.0 INFREQUENT OPERATIONS....................................................................... 8 DATA SHEETS DATA SHEET 1........................................................................................................ 9 DATA SHEET 2...................................................................................................... 12 DATA SHEET 3...................................................................................................... 13 ( REVISION NO.: PROCEDURE TITLE: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEDURE NO.: 2-3200020 ST. LUCIE UNIT 2 TABLE OF CONTENTS SECTION PAGE,,: "f!;{~.. " 2 of 13 ~. 1.0 PURPOSE...................................................................................................... 3

2.0 REFERENCES

............................................................................................... 3 3.0 PREREQUISITES.......................................................................................... 4 4.0 PRECAUTIONS / LIMITATIONS.................................................................... 4 5.0 RECORDS REQUIRED................................................................................. 4 6.0 INSTRUCTIONS............................................................................................ 5 7.0 INFREQUENT OPERATIONS....................................................................... 8 DATA SHEETS DATA SHEET 1........................................................................................................ 9 DATA SHEET 2...................................................................................................... 12 DATA SHEET 3...................................................................................................... 13

c 31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEDURE NO.: 2-3200020 ST. LUCIE UNIT 2 1.0 PURPOSE 1.1 To provide a method to accurately calculate the reactor thermal power manually under steady state conditions. REFERENCES NOTE One or more of the following symbols may be used in this procedure: § Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without the required Focus review and appropriate approval. ~ Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff. n off on an attachment. 2.1 Miscellaneous Documents Unit 2 Drawing 2998-G-056-Sh. 2, Heat Balance at Rated Power Steam Tables PCM 028-295 Installation of an Acoustic Flow Meter for Measuring Feedwater Flow ~1 CR 01-0344 ( REVISION NO.: PROCEDURE TITLE: PAGE:';':1t 31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEDURE NO.: 3 of 13 2-3200020 ST. LUCIE UNIT 2 1.0 PURPOSE 1.1 To provide a method to accurately calculate the reactor thermal power manually under steady state conditions.

2.0 REFERENCES

2.1 NOTE One or more of the following symbols may be used in this procedure: § Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without the required Focus review and appropriate approval. 11 Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff. '+/-' Indicates a step that requires a sign off on an attachment. Miscellaneous Documents Unit 2 Drawing 2998-G-056-Sh. 2, Heat Balance at Rated Power Steam Tables PCM 028-295 Installation of an Acoustic Flow Meter for Measuring Feedwater Flow 111 CR 01-0344

( PROCEDURE TITLE: PRIMARY SYSTEM MANUAL CALORIMETRIC rl"'.uvcu'U,",C NO.: 2-3200020 ST. LUCIE UNIT 2 3.0 PREREQUISITES 3.1 The reactor and related equipment should be in a steady state condition with plant power greater than or equal to 20% of Rated Thermal Power. PRECAUTIONS I LIMITATIONS Reactor power, RCS temperature, steam generator level, blowdown, charging and letdown rates should be maintained as constant as possible during data taking. If core power is determined to be above licensed or administrative limits, steps should be taken to reduce it to an acceptable level. Any parameters that are determined by redundant inputs should be compared with each other to establish each as a believable or non-believable value. Te should be between 548°F and 548.8°F for operation at rated thermal power. RECORDS REQUIRED The data sheets from this procedure shall be maintained in the plant files in accordance with QI-17 -PSL-1, Quality Assurance Records. 5.2 Forms similar to those contained in this procedure may be used provided they contain all of the essential information as the forms attached. ( REVISION NO.: PROCEDURE TITLE: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEDURE NO.: 2-3200020 ST. LUCIE UNIT 2 3.0 PREREQUISITES 3.1 The reactor and related equipment should be in a steady state condition with plant power greater than or equal to 20% of Rated Thermal Power. 4.0 PRECAUTIONS I LIMITATIONS 4.1 Reactor power, RCS temperature, steam generator level, blowdown, charging and letdown rates should be maintained as constant as possible during data taking. 4.2 If core power is determined to be above licensed or administrative limits, steps should be taken to reduce it to an acceptable level. 4.3 Any parameters that are determined by redundant inputs should be compared with each other to establish each as a believable or non-believable value. 4.4 Tc should be between 548°F and 548.8°F for operation at rated thermal power. 5.0 RECORDS REQUIRED 5.1 The data sheets from this procedure shall be maintained in the plant files in accordance with QI-17 -PSL-1, Quality Assurance Records. 5.2 Forms similar to those contained in this procedure may be used provided they contain all of the essential information as the forms attached.

31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEDURE NO.: 2-3200020 ST. LUCIE UNIT 2 INSTRUCTIONS Establish plant conditions per section 3.0 NOTE Use Data Sheet 1, Manual Calorimetric Calculation, in conjunction with the ste s below. NOTE Reactor core thermal power shall be determined using the following equation: QCORE + QFW+ QRCP + QCH + QpZR-Qccw-QSTEAM-QBD-QLD-L = 0 M is mass flow rate in Ibm/hr, h is enthal in BTU/Ibm NOTE The DCS feedwater data points are on the SG 2A (2B) FW BLOWDOWN CALCS screens accessible throu h the POWER MENU. Collect all data as required by Data Sheet 1, Manual Calorimetric Calculation. Record the time the data was taken. Compute total feedwater flow, average feedwater temperature and average main steam pressure. Compute the net heat output due to steam flow (QSTEAM). NOTE QSTEAM = (MFw-MBD) X hSTEAM

1.

Determine the enthalpy for the average main steam pressure (hsTEAM)'

2.

Determine the mass flow of blowdown by using Table 1, Data Sheet 1, to convert GPM to Ibm/hr.

3.

Subtract blowdown mass flow (MBD) from feedwater mass flow (MFw) to obtain steam flow.

4.

Multiply the quantity from step 6.4.3 times the enthalpy from step 6.4.1. This resultant is QSTEAM. ( ( REVISION NO.: PROCEOURE TITLE: PAGE: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEOURE NO.: 2-3200020 ST. LUCIE UNIT 2 6.0 INSTRUCTIONS 6.1 Establish plant conditions per section 3.0 NOTE Use Data Sheet 1, Manual Calorimetric Calculation, in conjunction with the steps below. NOTE of 13'" Reactor core thermal power shall be determined using the following equation: QCORE + QFW + QRCP + QCH + QpZR - Qccw - QSTEAM - QBO - QLD - L = 0 M is mass flow rate in Ibm/hr, h is enthalpy in BTU/Ibm NOTE The DCS feedwater data points are on the SG 2A (2B) FW BLOWDOWN CALCS screens accessible through the POWER MENU. 6.2 Collect all data as required by Data Sheet 1, Manual Calorimetric Calculation. Record the time the data was taken. 6.3 Compute total feedwater flow, average feedwater temperature and average main steam pressure. 6.4 Compute the net heat output due to steam flow (QSTEAM). NOTE QSTEAM = (MFw-Mso) X hSTEAM

1.

Determine the enthalpy for the average main steam pressure (hSTEAM).

2.

Determine the mass flow of blowdown by using Table 1, Data Sheet 1, to convert GPM to Ibm/hr.

3.

Subtract blowdown mass flow (MBO) from feedwater mass flow (MFw) to obtain steam flow.

4.

Multiply the quantity from step 6.4.3 times the enthalpy from step 6.4.1. This resultant is QSTEAM.

NO.: PROCEDURE TITLE: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEDURE NO.: 2-3200020 ST. LUCIE UNIT 2 NOTE The effect of moisture carryover has been neglected because it is difficult to measure and accounts for less than 0.2%

r.

Compute the feedwater heat input (QFW). NOTE QFW= MFwx hFw

1.

Determine the enthalpy for the average feedwater temperature (hFw).

2.

Multiply the total feedwater flow (MFw) times hFw (from above). This result is QFW. 6.6 . Determine the Blowdown Heat Output (QBO). NOTE QBO = MBO X hBO hBO blowdown enthal is assumed to be constant.

1.

Determine total (both S/Gs) blowdown flow rate (MBD), from Table 1 of Data Sheet 1.

2.

Enter Table 1 of Data Sheet 1 and determine blowdown heat output (QBD). (Interpolation is not required.) 7 The following is the determination for the constant used to represent other net heat losses and gains (QOTHER). QOTHER- = 46.905 x 106STU/hr-(48.952 x 106 BTU/hr if charging and letdown flow is secured for maintenance) NOTE QOTHER = QRCP + QCH + QpZR - Qccw - QLD - L

1.

The following constant is supplied for the Reactor Coolant Pump heat flow (QRCP). QRCP = 55.951 x 106 BTU/hr ( REVISION NO.: 31 PROCEOURE NO.: PROCEOURE TITLE: PRIMARY SYSTEM MANUAL CALORIMETRIC PAGE: f, 6 of 1 2-3200020 ST. LUCIE UNIT 2 NOTE The effect of moisture carryover has been neglected because it is difficult to measure and accounts for less than 0.2% power. 6.5 Compute the feedwater heat input (OFW). NOTE OFW= MFwx hFw

1.

Determine the enthalpy for the average feedwater temperature (hFw).

2.

Multiply the total feedwater flow (MFw) times hFw(from above). This result is OFW. 6.6 . Determine the Blowdown Heat Output (OBO).

1.

2.

NOTE OBO = MBo X hBo hBo (blowdown enthalpy) is assumed to be constant. Determine total (both S/Gs) blowdown flow rate (MBo), from Table 1 of Data Sheet 1. Enter Table 1 of Data Sheet 1and determine blowdown heat output (OBO). (Interpolation is not required.) 6.7 The following is the determination for the constant used to represent other net heat losses and gains (OOTHER). OOTHER = 46.905 x 106 BTU/hr (48.952 x 106 BTU/hr if charging and letdown flow is secured for maintenance) NOTE OOTHER = ORCP + OCH + OPZR - Occw-OLD-L

1.

The following constant is supplied for the Reactor Coolant Pump heat flow (ORCP). ORCP = 55.951 X 106 BTU/hr

31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEDURE NO.: 2-3200020 ST. LUCIE UNIT 2 6.7 (continued)

2.

Charging heat input (QCH) is defined by the equation QCH = MCH X hCH, where MCH is the mass flow rate and hCH is the enthalpy. The following constant is based on o.ne charging pump operating at a VCT temperature of 105°F. QCH = 1.174 X 106 BTU/hr

3.

The constant for the net Pressurizer heat input (QpZR) was determined as a result of Hot Ops II. QpZR = 0.592 x 106 BTU/hr

4.

The constant for the Component Cooling Water heat output (Qccw) was determined as a result of Hot Ops II. Qccw = 0.458 X 106 BTu/hr

5.

Letdown heat flow (QLD) is defined by the equation QLD = MLD X hLD, where . MLD is the letdown mass flow rate and hLD is the letdown enthalpy. The following constant is based on one charging pump operating with a letdown temperature of 250°F out of the Regenerative Heat Exchanger and 100°F out of the Letdown Heat Exchanger. QLD = 3.221 X 106 BTU/hr

6.

The following constant is supplied to account for all piping, radiation and other losses (L). L = 7.133 X 106 BTu/hr Calculate the heat output from the core (QCORE). NOTE QCORE = QSTEAM - QFW + QBD - QOTHER Calculate percent core power NOTE Core Power (%) = QCORE 192.128 X 106 (a conversion factor) 10 Complete the attached data sheets, as required. END OF SECTION 6.0 ( REVISION NO.: PROCEDURE TITLE: 31 PROCEDURE NO.: PRIMARY SYSTEM MANUAL CALORIMETRIC

• • ,7 of 13 2-3200020 ST. LUCIE UNIT 2 6.7 (continued)

2.

Charging heat input (OCH) is defined by the equation OCH = MCH X hcH, where MCH is the mass flow rate and hCH is the enthalpy. The following constant is based on one charging pump operating at a VCT temperature of 105°F. OCH = 1.174 X 106 BTu/hr

3.

The constant for the net Pressurizer heat input (OPZR) was determined as a result of Hot Ops II. OPZR = 0.592 x 106 BTU/hr

4.

The constant for the Component Cooling Water heat output (Occw) was determined as a result of Hot Ops II.

5.

Occw = 0.458 x 106 BTu/hr Letdown heat flow (OLD) is defined by the equation OLD = MLD X hLD, where MLD is the letdown mass flow rate and hLD is the letdown enthalpy. The following constant is based on one charging pump operating with a letdown temperature of 250°F out of the Regenerative Heat Exchanger and 100°F out of the Letdown Heat Exchanger. OLD = 3.221 X 106 BTu/hr

6.

The following constant is supplied to account for all piping, radiation and other losses (L). L = 7.133 X 106 BTu/hr 6.8 Calculate the heat output from the core (OCORE). NOTE OCORE = QSTEAM - OFW + OBD - OOTHER 6.9 Calculate percent core power NOTE Core Power (%) = OCORE / 92.128 x 1 06 (a conversion factor) 6.10 Complete the attached data sheets, as required. END OF SECTION 6.0

ON NO.: PROCEDURE TITLE: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC NO.: 2-3200020 ST. LUCIE UNIT 2 .0 INFREQUENT OPERATIONS .1 None END OF SECTION 7.0 ( REVISION NO.: PROCEDURE TITLE: PAGE:,

):~'~ :

31 PRIMARY SYSTEM MANUAL CALORIMETRIC .. 8 of 1

-\\, l' PROCEDURE NO.

2-3200020 ST. LUCIE UNIT 2 7.0 INFREQUENT OPERATIONS ,~>:c . i*t~ '~> 7.1 None END OF SECTION 7.0 (

C .Q~ 1955 C E Q) :::l E u

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..J g ~ Z"OO....J o:g,~ ~ Z c"o !:: C\\'l C Z O..c::*- U"O I-"O~ <<CO -=C\\'l~ -=cc 0:::.Q 8 o*~ C\\'l LL. Q)..c:: z.... ;::: 0 -~$:UJ 0::: *c,....... - o ~~ !:!: LL. -.g c::: Q) u UJ ~ '5. > Q)o..UJ C\\'l I-0..... <C 1D::::- 0 co 31 IPRI:>CEDUF~E NO.: 2-3200020 PRIMARY SYSTEM MANUAL CALORIMETRIC ST. LUCIE UNIT 2 DATA SHEET 1 (Page 1 of 3) Date: __ 1 __ 1 __ Time: ___

1.

ENTER MAIN STEAM PRESSURE PI-8013A. __________ PI-8023A. __________ PI-8013B __________ PI-8023B __________ PI-8013C. ___________ _ PI-8023C. ___________ _ PI-8013D ___________ _ PI-8023D ___________ _ COMPUTE TOTAL FEEDWATER FLOW A. B. A Loop x .;. 29178 = x 106 Ib/hr (FT 9011-2 (ERDADS). or F-9011) --==(D:"::C-=-S-='PT=-K=-=F:-:A-:-) - B Loop X .;. 29050 = X 106 Ib/hr (FT 9021-2 (ERDADS). or F-9021) (DCS PT KFB) MFw = X 1061b/hr (Total A+B Loop) Steam Pressure = _............ ___ divided by 8 = _______ =-- TOTAL AVERAGE ENTER FEEDWATER TEMPERATURE TR-09-5B (bebindR'-GB202) ChanneI1 ___ 0F Channel 2 of 1LJ.\\""'~"'r'Q Feedwater Temperature divided by 2 = _-:-:-:==-:-=-::=- TOTAL AVERAGE the steam tables, enter the enthalpy of the average steam pressure: hSTEAM= BTU/lbm luClIll..UIICnC the heat output due to steam flow (QSTEAM): 106 106 106 BTUlhr X [MFW MSDl = QSTEAM the steam tables, enter the enthalpy of the average feedwater temperature: hFw = BTU Ibm the heat feedwater heat input (QFW): 1'-__ -- X 106 ) X ( ) = X 106 BTU MFw hFw QFW hr S...LOPS DATE. ____ DOCT Procedure DOCN 2-3200020 SYS OPS COMP COMPLETED ITM, _____ _ REVISION NO.: PROCEDURE TITLE: PAGE:.. 70

• 31 PRIMARY SYSTEM MANUAL CALORIMETRIC

"'*;;v 9 of 13 PROCEDURE NO.: 2-3200020 ST. LUCIE UNIT 2 IF DATA SHEET 1 ,fL (Page 1 of 3) Date: I I Time:

1.

ENTER MAIN STEAM PRESSURE PI-8013A PI-8023A PI-8013B PI-8023B PI-8013C PI-8023C PI-8013D PI-8023D 111 COMPUTE TOTAL FEEDWATER FLOW ( A. A Loop x .;- 29178 = x 106 Ib/hr (FT 9011-2 (ERDADS), or F-9011) (DCS PT KFA) B. BLoop X .;- 29050 = x 106 Ib/hr (FT 9021-2 (ERDADS), or F-9021) MFw = X 10 6 1b/hr (DCS PT KFB) (Total A+B Loop) Average Steam Pressure = divided by 8 = TOTAL AVERAGE ENTER FEEDWATER TEMPERATURE TR-09-5B Channel 1 of (behindRTGB 202) Channel 2 of Average Feedwater Temperature divided by 2 = TOTAL AVERAGE From the steam tables, enter the enthalpy of the average steam pressure: hSTEAM= BTUllbm Calculate the heat output due to steam flow (QSTEAM): S-LOPS 106 106 106 BTU/hr DATE hSTEAM X [MFw Msol = QSTEAM DOCT Procedure DOCN 2-3200020 From the steam tables, enter the enthalpy of the average feedwater temperature: SYS OPS hFw = BTU COMP COMPLETED Ibm ITM Calculate the heat feedwater heat input (QFW): ( x 1 06 ) X ( ) = x 1 06 BTU MFw hFw QFW hr

SION NO.: PROCEOURE TITLE: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEOURE NO.: 2-3200020 ST. LUCIE UNIT 2 DATA SHEET 1 (Page 2 of 3) TABLE 1 ircle 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 ,n",nM"n flow rates, to be conservative.) Total blowdown flow (both steam generators) 40GPM 80GPM 120 GPM 160 GPM 200 GPM 240 GPM Mass flow of blowdown MBo .019799 x 106 Ibm/hr .039599 x 106 Ibm/hr .059398 x 1061bm/hr .079198 x 106 1bm/hr .098997 x 106 Ibm/hr .118797 x 106 Ibm/hr Calculate the heat output from the core: Heat output from blowdown QBO 9.728 X 106 BTU/hr 19.456 x 106 BTUlhr 29.183 x 106 BTUlhr 38.912 x 106 BTU/hr 48.639 x 106 BTU/hr 58.367 x 106 BTUlhr f 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. -oil x 106 BTU = __ -<.X,-1,...,,0,-6 BTU + QSTEAM QBO QOTHER hr QCORE hr NOTE Calculated Power in percent must be within 2% of DCS Calorimetric power. If not, noti the US I SM. Initiate W/Rfor ICM to adjust LlT power. Calculate percent core power: Core Power = xi 06 divided by (92.128 x 106) = QCORE Manual Calorimetric Power Record DCS Calorimetric Power (QRP % 10 minute ave), (QRPP (instantaneous) should be used below if the reactor has not been in a stable power configuration for at least 10 minutes): DCS Calorimetric Power = ______ % ( REVISION NO.: 31 PROCEDURE NO.: 2-3200020 PROCEDURE TITLE: PRIMARY SYSTEM MANUAL CALORIMETRIC ST. LUCIE UNIT 2 DATA SHEET 1 (Page 2 of 3) TABLE 1 PAGE: '\\ o of 13 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 (both steam generators) 40GPM 80 GPM 120 GPM 160 GPM 200 GPM 240 GPM Mass flow of blowdown MBD .019799 x 106 Ibm/hr .039599 x 106 Ibm/hr .059398 x 106 Ibm/hr .079198 x 106 Ibm/hr .098997 x 106 Ibm/hr .118797 x 106 Ibm/hr Calculate the heat output from the core: Heat output from blowdown QBD 9.728 X 106 BTu/hr 19.456 x 106 BTu/hr 29.183 x 106 BTu/hr 38.912 x 106 BTu/hr 48.639 x 106 BTu/hr 58.367 x 106 BTu/hr 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. [ ___ - ___ + --::-__ - --::-_-,1 x 106 BTU = __ ~X~1~0~6 BTU QSTEAM QFW QBD QOTHER hr QCORE hr NOTE Calculated Power in percent must be within 2% of DCS Calorimetric power. If not, notify the US I SM. Initiate W/Rfor ICM to adjust Ll T power. Calculate percent core power: I % I Core Power = __

---

'x~1 0=-6 divided by (92.128 x 106) =

L====':"'=---.l. QCORE Manual Calorimetric Power Record DCS Calorimetric Power (QRP % 10 minute ave), (QRPP (instantaneous) should be used below if the reactor has not been in a stable power configuration for at least 10 minutes): DCS Calorimetric Power =

NO.: PROCEDURE TITLE: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEDURE NO.: 2-3200020 ST. LUCIE UNIT 2 DATA SHEET 1 (Page 3 of 3) On the first Monday of the quarter, complete Data Sheet 2. On the first Monday of the quarter, complete Data Sheet 3. I have reviewed the requirements of this procedure including other surveillances Initial Initial ed during this procedure, if any (i.e., datasheet(s), PMT sheet(s), etc.). Any eviation(s) found during the performance of this procedure has (have) been listed an nnrnnr*'*!:1 actions and notifications made. RCO US/SM

0 w

( REVISION NO.: 31 PROCEDURE NO.: 2-3200020 PROCEDURE TITLE: PRIMARY SYSTEM MANUAL CALORIMETRIC ST. LUCIE UNIT 2 DATA SHEET 1 (Page 3 of 3)

2.

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

3.

On the first Monday of the quarter, complete Data Sheet 3. PAGE:. 11 of 1 Initial 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

NO.: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEDURE NO.: 2-3200020 ST. LUCIE UNIT 2 DATA SHEET 2 (Page 1 of 1) NOTE This data sheet will compare feedwater temperature inputs into DCS calorimetric with feedwater temperature indications used in manual calorimetric.

1.

Record feedwater temperature inputs from DCS. PT T0910A1 __ PT T0910A2 __ PT T0910A3 __ Compare PTs T0910A1 through T0910A3 to be within 2°F, if greater than 2°F notify I&C. PT T091081 __ _ PT T091082 __ _ PT T091 083 __ _ Compare PTs T091081 through T091083 to be within 2°F, if greater than 2°F notify I&C. Record feedwater temperatures from DCS and from TR-09-58 (behind RTG8 202). DCS PT TFA TR-09-58 Channel 1 Ensure feedwater temperatures to be within 5°F or notify I&C and US. DCS PT TF8 ____ TR-09-58 Channel 2 __ __ Ensure feedwater temperatures to be within 5°F or notify I&C and US. 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 ( REVISION NO.: PROCEDURE TITLE: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC PROCEDURE NO.: 2-3200020 ST. LUCIE UNIT 2 DATA SHEET 2 (Page 1 of 1) NOTE This data sheet will compare feedwater temperature inputs into DCS calorimetric with feedwater temperature indications used in manual calorimetric.

1.

Record feedwater temperature inputs from DCS. PT T0910A1 __ _ PT T0910A2 __ _ PT T0910A3 __ _ Compare PTs T0910A1 through T0910A3 to be within 2°F, if greater than 2°F notify I&C. PT T091 081 __ _ PT T091 082 __ _ PT T091083 __ Compare PTs T091081 through T091083 to be within 2°F, if greater than 2°F notify I&C.

2.

Record feedwater temperatures from DCS and from TR-09-S8 (behind RTG8 202). DCS PT TFA __ TR-09-S8 Channel 1 __ Ensure feedwater temperatures to be within SOF or notify I&C and US. DCS PT TF8 __ TR-09-S8 Channel 2 __ Ensure feedwater temperatures to be within SOF or notify I&C and US. 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

( 31 PROCEDURE NO.: 2-3200020 PRIMARY SYSTEM MANUAL CALORIMETRIC ST. LUCIE UNIT 2 DATA SHEET 3 (Page 1 of 1) NOTE This data sheet will compare calorimetric and Delta T power as computed by the DCS for consistency. Delta T power is used as the input into the DCS Xenon calculation and as a backup reactor power signal supplied to BEACON. CAUTION Calorimetric power should have been stable (i.e., no power maneuvers were in progress) over the hour time period selected for the Delta T power com arison.

1.

RECORD the following data from the DCS Hourly Reactor Poison and Power Log. Delta Power Avg Pwr Last Hour%

2.

COMPARE Delta T power to AVG PWR Last Hour %.

3.

1f Delta T Power and AVG PWR Last Hour % DO NOT agree within 2 percent, or 1f Delta T Power adjustment is desired, Then NOTIFY I&C and SCE. (N/A if notification not required) 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 ( PROCEDURE TITLE: 31 PRIMARY SYSTEM MANUAL CALORIMETRIC 3 of 1 PROCEDURE NO.: 2-3200020 ST. LUCIE UNIT 2 DATA SHEET 3 (Page 1 of 1) NOTE This data sheet will compare calorimetric and Delta T power as computed by the DCS for consistency. Delta T power is used as the input into the DCS Xenon calculation and as a backup reactor power signal supplied to BEACON. CAUTION Calorimetric power should have been stable (i.e., no power maneuvers were in progress) over the hour time period selected for the Delta T power comparison.

1.

RECORD the following data from the DCS Hourly Reactor Poison and Power Log. Delta Power Avg Pwr Last Hour%

2.

COMPARE Delta T power to AVG PWR Last Hour %.

3.

if Delta T Power and AVG PWR Last Hour % DO NOT agree within 2 percent, or if Delta T Power adjustment is desired, Then NOTIFY I&C and SCE. (N/A if notification not required) 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 +'

'<;~'

'0'1 ~.;

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 1 B Containment Spray Pump CANDIDATE EXAMINER NRC A-3 NRC ADM JPM A-3 fRev 0 PAGE 1 ( REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 1 B Containment Spray Pump CANDIDATE EXAMINER NRC A-3 NRC ADM JPM A-3 tRev 0 PAGE 1

( KA Statement: KA#:

References:

Candidate: REGION" ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 1 B Containment Spray Pump. Ability to obtain and interpret station electrical and mechanical drawings. 2.2.41 (3.5/3.9) P&ID 8770-G-088 SH 1 P&ID 8770-G-083 SH 2 CWO 8770-B-326 SH 290 ADM-09.08 Operations In-Plant Equipment Clearance Orders 1-ADM-03.01 A Unit 1 Power Distribution Breaker List Operations Policy OPS-406 Clearance Database Conventions Time Start __ _ Name Time Finish --- Performance Rating: Sat Unsat Validation Time Examiner: Comments 25 minutes Signature: NRC ADM JPM A-3 fRey 0 PAGE 2 ( KA Statement: KA#:

References:

Candidate: REGION" ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 1 B Containment Spray Pump. Ability to obtain and interpret station electrical and mechanical drawings. 2.2.41 (3.5/3.9) P&ID 8770-G-088 SH 1 P&ID 8770-G-083 SH 2 CWD 8770-B-326 SH 290 ADM-09.08 Operations In-Plant Equipment Clearance Orders 1-ADM-03.01 A Unit 1 Power Distribution Breaker List Operations Policy OPS-406 Clearance Database Conventions Time Start --- Name Time Finish __ _ Performance Rating: Sat Unsat Validation Time Examiner: Comments 25 minutes Signature: NRC ADM JPM A-3 IRev 0 PAGE 2

REGION" ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 1 B CS 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 1 is at 100% power. The 1 B Containment Spray Pump has developed a pump cooler leak. The pump cooler is to be removed from service to repair the leak. No other equipment is out of service. NOMS is unavailable. Initiating Cue On the attached matrix, develop an ECO lAW ADM-09.08, 'Operations In-Plant Equipment Clearance Orders', for the 1 B Containment Spray Pump that would facilitate repairing the pump cooler leak. Ensure tagged components are placed in the proper sequence. NRC ADM JPM A-3 fRey 0 PAGE 3 ( REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM Develop ECO for 1 B CS 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 1 is at 100% power. The 1 B Containment Spray Pump has developed a pump cooler leak. The pump cooler is to be removed from service to repair the leak. No other equipment is out of service. NOMS is unavailable. Initiating Cue On the attached matrix, develop an ECO lAW ADM-09.08, 'Operations In-Plant Equipment Clearance Orders', for the 1 B Containment Spray Pump that would facilitate repairing the pump cooler leak. Ensure tagged components are placed in the proper sequence. NRC ADM JPM A-3 IRev 0 PAGE 3

Com~onent Name Position Tag (type) NOTE: Plus is NOT required for position to meet Critical Steps Control Room Control 1-CS-290 In Place Info Tag Switch for 1 B Containment Spray Pump

• Breaker 1-20407 1 B Containment Spray Racked Out Plus Danger Pump
• 1-V407124 1 B Containment Spray Locked Closed Plus Danger Pump Suction Valve
• 1-V07130 1 B Containment Spray Locked Closed Plus Danger Pump Discharge Valve
• 1-V07118 Equalizer Valve for Closed Plus Danger V07124
• 1-V07135 Equalizer Valve for Closed Plus Danger V07130
• 1-V07262 Isolation Valve for Sodium Locked Closed Plus Danger Hydroxide Feed to Containment Spray Pump 1 B Suction
• 1-V07226 Primary Isolation Valve for Locked Closed Plus Danger Containment Spray Pump 1B Recic.
• 1-V14292 Isolation for Containment Locked Closed Plus Danger Spray Pump 1 B CCW inlet
• 1-V14295 Isolation for Containment Locked Closed Plus Danger Spray Pump 1 B CCW outlet 120/208 VAC PP-102 4160V SWGR 1 B2 Motor Open Plus Danger CKT -31 and Space Heaters 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 do not require a danger tag. It is preferred, but not required'.

1-V07123 1-V07128 1-V07125 V07128 V14294 V14293

• Cntlcal Step Drain Valve on Containment Spray Pump 1 B Suction Drain Valve on Containment Spray Pump 1 B Discha~ge Root Valve for PX 2B Upstream of SS-07-1 B (Vent)

Drain Valve on Containment Spray Pump 1 B Discharge Root Valve for PX 19B CSP 1B CCW Outlet (Vent) Root Valve for PX 19B CSP 1B CCW Inlet(Vent) Open Open Open Open Open Open

1. Danger
2. Danger
3. Danger
4. Danger
5. Danger
6. Danger NRC ADM JPM A-3 fRey 0 PAGE 4 I

( ( Component Name Position Tag (type) NOTE: Plus is NOT required for position to meet Critical Steps Control Room Control 1-CS-290 In Place Info Tag Switch for 1 B Containment Spray Pump

• Breaker 1-20407 1 B Containment Spray Racked Out Plus Danger Pump
• 1-V407124 1 B Containment Spray Locked Closed Plus Danger Pump Suction Valve
• 1-V07130 1 B Containment Spray Locked Closed Plus Danger Pump Discharge Valve
• 1-V07118 Equalizer Valve for Closed Plus Danger V07124
• 1-V07135 Equalizer Valve for Closed Plus Danger V07130
• 1-V07262 Isolation Valve for Sodium Locked Closed Plus Danger Hydroxide Feed to Containment Spray Pump 1 B Suction
• 1-V07226 Primary Isolation Valve for Locked Closed Plus Danger Containment Spray Pump 1 B Recic.
• 1-V14292 Isolation for Containment Locked Closed Plus Danger Spray Pump 1 B CCW inlet
• 1-V14295 Isolation for Containment Locked Closed Plus Danger Spray Pump 1 B CCW outlet 120/208 VAC PP-102 4160V SWGR 1 B2 Motor Open Plus Danger CKT -31 and Space Heaters 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 do not require a danger tag. It is preferred, but not required'.

1-V07123 Drain Valve on Containment Spray Pump 1 B Suction 1-V07128 Drain Valve on Containment Spray Pump 1 B Discharge 1-V07125 Root Valve for PX 2B Upstream of SS-07-1 B (Vent) V07128 Drain Valve on Containment Spray Pump 1 B Discharge V14294 Root Valve for PX 19B CSP 1B CCW Outlet (Vent) V14293 Root Valve for PX 19B CSP 1B CCW Inlet (Vent)

• Cntlcal Step Open Open Open Open Open Open

1. Danger
2. Danger
3. Danger
4. Danger
5. Danger
6. Danger NRC ADM JPM A-3 IRev 0 PAGE 4 I

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) Initial Conditions Unit 1 is at 100% power. The 1 B Containment Spray Pump has developed a pump cooler leak. The pump cooler is to be removed from service to repair the leak. No other equipment is out of service. NOMS is unavailable. Initiating Cue On the attached matrix, develop an ECO lAW ADM-09.08, 'Operations In-Plant Equipment Clearance Orders', for the 1 B Containment Spray Pump that would facilitate repairing the pump cooler leak. Ensure tagged components are placed in the proper sequence. NRC ADM JPM A-3 IRev 0 ( (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) Initial Conditions Unit 1 is at 100% power. The 1 B Containment Spray Pump has developed a pump cooler leak. The pump cooler is to be removed from service to repair the leak. No other equipment is out of service. NOMS is unavailable. Initiating Cue On the attached matrix, develop an ECO lAW ADM-09.08, 'Operations In-Plant Equipment Clearance Orders', for the 1 B Containment Spray Pump that would facilitate repairing the pump cooler leak. Ensure tagged components are placed in the proper sequence. NRC ADM JPM A-3 fRev 0

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) Component Name Position Tag (type) NRC ADM JPM A-3 fRey 0 (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) Component Name Position Tag (type) ~ ( I ( NRC ADM JPM A-3 fRey 0

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) Component Name Position Tag (type) I I f I ( I~--* f------ I r l-I I NRC ADM JPM A-3 IRev 0 (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) Component Name Position Tag (type) I I ( I-~- ~- I r ( I I NRC ADM JPM A-3 IRev 0

( FPL St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE Operate Portable Radiation Monitoring Equipment RM-23P UNIT 2 NRC JPM (RO) A-4 IN-PLANT Revised By _____ La_rrL-y _Ri_ch ____ Approval _______________ Date NRC ADM JPM Rad. Control REV. 0 Page 1 of 12 ( e FPL St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE Operate Portable Radiation Monitoring Equipment RM-23P UNIT 2 NRC JPM (RO) A-4 IN-PLANT Revised By _____ La_rr"--y R_i_ch ____ Approval ------------ Date NRC ADM JPM Rad. Control REV. 0 Page 1 of 12

Job Performance Measure A-4 (RO) Task Number: 03203020, Operate Portable Radiation Monitoring Equipment, RM-23P Task

Title:

Faulted JPM: Facility JPM # K/A Ratings: Operate Portable Radiation Monitoring Equipment DYes I:8J No 0321307 2.9 K/A Statement: 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. Duty Areas: Radiation Control Task Information: N/A Task Standard: Applicant tests a RM-80 using the RM-23P per procedure. Evaluation Location Performance Level D Simulator I:8J In Plant I:8J Perform I:8J Simulate D Discuss D Lab D Other

References:

2-NOP-26.01, Radiation Monitors Validation Time: 30 Minutes Time Critical DYes Tools/Equipment/Procedures Needed: Standard Personal Protective Equipment Flashlight Radio 2-NOP-26.01, Radiation Monitors RM-23P pre-staged in TB Switchgear Specific Safety Concerns, PPE and Hazards associated with the task: None Radiological Protection and RWP Requirements: None I:8J No NRC ADM JPM Rad. Control REV. 0 Page 2 of 12 ( Job Performance Measure A-4 (RO) Task Number: 03203020, Operate Portable Radiation Monitoring Equipment, RM-23P Task

Title:

Operate Portable Radiation Monitoring Equipment Faulted JPM: 0 Yes [gJ No Facility JPM # 0321307 K/A Ratings: 2.9 K/A Statement: 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. Duty Areas: Radiation Control Task Information: N/A Task Standard: Applicant tests a RM-80 using the RM-23P per procedure. Evaluation Location Performance Level o Simulator [gJ In Plant [gJ Perform [gJ Simulate 0 Discuss o Lab o Other

References:

2-NOP-26.01, Radiation Monitors Validation Time: 30 Minutes Time Critical 0 Yes Tools/Equipment/Procedures Needed: Standard Personal Protective Equipment Flashlight Radio 2-NOP-26.01, Radiation Monitors RM-23P pre-staged in TB Switchgear Specific Safety Concerns, PPE and Hazards associated with the task: None Radiological Protection and RWP Requirements: None [gJ No NRC ADM JPM Rad. Control REV. 0 Page 2 of 12

Specific Directions: Job Performance Measure A-4 (RO) The Task you are to perform Operate Portable Rad Monitoring Equipment is: The performance level to be used for this JPM is PERFORM/SIMULATE. (Circle the performance level being used for this implementation of the task.) This Is Not a time critical JPM. 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: Unit 2 is operating at 100% power. The PC-11 Group 15, Loop 3 is out of service. Initiating Cues: The US has directed you to obtain the local reading from the Main Steam Line Monitor 1 for the A Main steam Line, RIM-26-71, using the RM-23P in accordance with 2-NOP-26.01, Radiation Monitors. NRC ADM JPM Rad. Control REV. 0 Page 3 of 12 Specific Directions: Job Performance Measure A-4 (RO) The Task you are to perform Operate Portable Rad Monitoring Equipment is: The performance level to be used for this JPM is PERFORM/SIMULATE. (Circle the performance level being used for this implementation of the task.) This Is Not a time critical JPM. 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: Unit 2 is operating at 100% power. The PC-11 Group 15, Loop 3 is out of service. Initiating Cues: ( The US has directed you to obtain the local reading from the Main Steam Line Monitor 1 for the A Main steam Line, RIM-26-71, using the RM-23P in accordance with 2-NOP-26.01, Radiation Monitors. NRC ADM JPM Rad. Control REV. a Page 3 of 12

( Start Time: Job Performance Measure A-4 (RO) PERFORMANCE CHECKLIST 2-NOP-26.01, Radiation Monitors, Step 6.3, Portable RM-23 Operation STEP 1 (6.3.1) ENSURE Section 3.0, Prerequisites, completed. Standard: Examiner's Cue: Comments: STEP 2 (6.3.2) Standard: Examiner's Cue: Comments: Operator CHECKS Section 3.0, Prerequisites. Section 3.0, Prerequisites is checked. REVIEW Section 4.0, Precautions / Limitations. Operator REVIEWS Section 4.0, Precautions / Limitations. Section 4.0, Precautions I Limitations is reviewed. __ Sat Unsat Sat Unsat Step 6.3.3, Perform a functional test of the monitor as follows: STEP 3 (6.3.3) Standard: Examiner's Cue: Comments: PERFORM a functional test of the monitor as follows: Critical Step A. ENERGIZE the monitor by plugging into a 120V AC power outlet. Sat Operator ENERGIZES the RM-23P. __ Unsat RM-23P is ENERGIZED. Page 4 of 12 NRC ADM JPM Rad. Control REV. 0 ( ( Start Time: Job Performance Measure A-4 (RO) PERFORMANCE CHECKLIST 2-NOP-26.01, Radiation Monitors, Step 6.3, Portable RM-23 Operation STEP 1 (6.3.1) ENSURE Section 3.0, Prerequisites, completed. Standard: Examiner's Cue: Comments: STEP 2 (6.3.~ Standard: Examiner's Cue: Comments: Operator CHECKS Section 3.0, Prerequisites. Section 3.0, Prerequisites is checked. REVIEW Section 4.0, Precautions / Limitations. Operator REVIEWS Section 4.0, Precautions / Limitations. Section 4.0, Precautions I Limitations is reviewed. Sat __ Unsat Sat __ Unsat Step 6.3.3, Perform a functional test of the monitor as follows: STEP 3 (6.3.3) Standard: Examiner's Cue: Comments: PERFORM a functional test of the monitor as follows: A. ENERGIZE the monitor by plugging into a 120V AC power outlet. Operator ENERGIZES the RM-23P. RM-23P is ENERGIZED. Page 4 of 12 Critical Step Sat Unsat NRC ADM JPM Rad. Control REV. 0

STEP 4 (6.3.3.8) Standard: Examiner's Cue: Comments: STEP 5 {6.3.3.C} Standard: ( Examiner's Cue: Examiner's Cue: Comments: STEP 6 {6.3.3.D} Standard: Examiner's Cue: I Comments: Job Performance Measure A-4 (RO) TURN monitor power switch ON. TURN monitor power switch ON. Monitor power switch is ON. VERIFY the following indications:

• The display window reads 0.00
• Top left button (mR/hr display I contrallight) is LIT.

VERIFY the display window reads 0.00. VERIFY the top left button (mR/hr display I contral light) is LIT. Window reads 0.00. Top left button (mR/hr display I control light) is LIT. ENTER the following command: 997 [ITEM]. ENTER command: 997 [ITEM]. Command: 997 [ITEM] entered correctly. Page 5 of 12 Critical Step Sat Unsat Sat Unsat Critical Step Sat Unsat NRC ADM JPM Rad. Control REV. 0 STEP 4 (6.3.3.8) Standard: Examiner's Cue: Comments: STEP 5 (6.3.3.C} Standard: ( Examiner's Cue: Examiner's Cue: Comments: STEP 6 (6.3.3.D} Standard: Examiner's Cue: I Comments: ( Job Performance Measure A-4 (RO) TURN monitor power switch ON. TURN monitor power switch ON. Monitor power switch is ON. VERIFY the following indications:

• The display window reads 0.00
• Top left button (mR/hr display I control light) is LIT.

VERIFY the display window reads 0.00. VERIFY the top left button (mR/hr display I control light) is LIT. Window reads 0.00. Top left button (mR/hr display I control light) is LIT. ENTER the following command: 997 [ITEM]. ENTER command: 997 [ITEM]. Command: 997 [ITEM] entered correctly. Page 5 of 12 Critical Step Sat Unsat Sat Unsat Critical Step Sat Unsat NRC ADM JPM Rad. Control REV. 0

STEP 7 (6.3.3.E) Standard: Examiner's Cue: Comments: STEP 8 (6.3.3.E) Standard: Examiner's Cue: Comments: STEP 9 (6,3.3.E) Standard: Examiner's Cue: Comments: Job Performance Measure A-4 (RO) VERIFY the following indications:

• The display window reads 8.888 + 18.

VERIFY the display window reads 8.888 + 18. The display window reads 8.888 + 18. VERIFY the following indications:

• All (12) red, yellow and green indication lights are LIT.

VERIFY all (12) red, yellow and green indication lights are LIT. All (12) red, yellow and green indication lights are LIT. VERIFY the following indications:

• All (8) white channel buttons on the upper keyboard are LIT.

VERIFY all (8) white channel buttons on the upper keyboard are LIT. All (8) white channel buttons on the upper keyboard are LIT. Page 6 of 12 Sat Unsat Sat Unsat Sat Unsat NRC ADM JPM Rad. Control REV. 0 STEP 7 (6.3.3.E) Standard: Examiner's Cue: Comments: STEP 8 (6.3.3.E) Standard: ( Examiner's Cue: Comments: STEP 9 (6.3.3.E) Standard: Examiner's Cue: Comments: ( Job Performance Measure A-4 (RO) VERIFY the following indications:

• The display window reads 8.888 + 18.

VERIFY the display window reads 8.888 + 18. The display window reads 8.888 + 18. VERIFY the following indications:

• All (12) red, yellow and green indication lights are LIT.

VERIFY all (12) red, yellow and green indication lights are LIT. All (12) red, yellow and green indication lights are LIT. VERIFY the following indications:

• All (8) white channel buttons on the upper keyboard are LIT.

VERIFY all (8) white channel buttons on the upper keyboard are LIT. All (8) white channel buttons on the upper keyboard are LIT. Page 6 of 12 Sat Unsat Sat Unsat Sat Unsat NRC ADM JPM Rad. Control REV. 0

STEP 10 (6.3.3.El Standard: Examiner's Cue: Comments: STEP 11 (6.3.3.F} Standard: Examiner's Cue: Comments: STEP 12 (6.3.3.G} Standard: Examiner's Cue: Comments: Job Performance Measure A-4 (RO) VERIFY the following indications:

• ITEM and MON pushbuttons on the lower keypad are LIT VERIFY ITEM and MON push buttons on the lower keypad are LIT.

ITEM and MON push buttons on the lower keypad are LIT. If any of the lights fail to illuminate during the functional test, Then PERFORM the following:

1. Notify M& TE to investigate and repair the defective unit.

DETERMINES all lights illuminate properly.. All lights illuminate properly during functional test. TURN monitor power switch OFF. TURN monitor power switch OFF. Monitor power switch is OFF. Page 7 of 12 Sat Unsat Sat Unsat Critical Step Sat Unsat NRC ADM JPM Rad. Control REV. 0 STEP 10 (6.3.3.El Standard: Examiner's Cue: Comments: STEP 11 (6.3.3.F} Standard: ( Examiner's Cue: Comments: STEP 12 (6.3.3.G} Standard: Examiner's Cue: Comments: ( Job Performance Measure A-4 (RO) VERIFY the following indications:

• ITEM and MON push buttons on the lower keypad are LIT VERIFY ITEM and MON push buttons on the lower keypad are LIT.

ITEM and MON push buttons on the lower keypad are LIT. If any of the lights fail to illuminate during the functional test, Then PERFORM the following:

1. Notify M& TE to investigate and repair the defective unit.

DETERMINES all lights illuminate properly.. All lights illuminate properly during functional test. TURN monitor power switch OFF. TURN monitor power switch OFF. Monitor power switch is OFF. Page 7 of 12 Sat Unsat Sat Unsat Critical Step Sat Unsat NRC ADM JPM Rad. Control REV. 0

c STEP 13 (6.3.3.Hl Standard: Examiner's Cue: Comments: STEP 14 {6.3.4.A} Standard: Examiner's Cue: Comments: STEP 15 {6.3.4.B} Standard: Examiner's Cue: Comments: Job Performance Measure A-4 (RO) UNPLUG monitor. UNPLUG monitor. Monitor is UNPLUGGED. PERFORM the following to obtain RM-80 readings: ENSURE the RM-23P power switch is OFF. The RM*23P power switch is OFF. CAUTION The RM-80 enclosure contains energized equipment. CAUTION The RM-80 enclosure contains energized equipment. CONNECT the RM-23P power cord to the 120V AC outlet located at the lower right corner inside the RM-80 enclosure. CONNECT the RM-23P power cord to the 120V AC outlet located inside the RM-80 enclosure. The RM*23P power cord is connected to the 120V AC outlet. Page 8 of 12 Critical Step Sat Unsat Sat Unsat Critical Step Sat Unsat NRC ADM JPM Rad. Control REV. 0 STEP 13 (6.3.3.Hl Standard: Examiner's Cue: Comments: STEP 14 (6.3.4.A} Standard: Examiner's Cue: Comments: ( STEP 15 (6.3.4.B} Standard: Examiner's Cue: Comments: ( Job Performance Measure A-4 (RO) UNPLUG monitor. UNPLUG monitor. Monitor is UNPLUGGED. PERFORM the following to obtain RM-80 readings: ENSURE the RM-23P power switch is OFF. The RM-23P power switch is OFF. CAUTION The RM-80 enclosure contains energized equipment. CAUTION The RM-80 enclosure contains energized equipment. CONNECT the RM-23P power cord to the 120V AC outlet located at the lower right corner inside the RM-80 enclosure. CONNECT the RM-23P power cord to the 120V AC outlet located inside the RM-80 enclosure. The RM-23P power cord is connected to the 120V AC outlet. Page 8 of 12 Critical Step Sat Unsat Sat Unsat Critical Step Sat Unsat NRC ADM JPM Rad. Control REV. 0

( Job Performance Measure A-4 (RO) STEP 16 (6.3.4.C) CONNECT the RM-23P signal cable to the RM-80 communications port. Standard: CONNECT the RM-23P signal cable to the RM-80 communications port. Examiner's Cue: The RM-23P signal cable is connected to the RM-80 communications port. Comments: STEP 17 (6.3.4.D) PLACE the RM-23P power switch in ON. Standard: PLACE the RM-23P power switch in ON. Examiner's Cue: The RM-23P power switch is ON. Comments: NOTE Critical Step __ Sat __ Unsat Critical Step __ Sat __ Unsat The top four white buttons are the channel select pushbuttons. The buttons are used to select the appropriate channel dependent upon what type monitor the RM-23P is reading. Buttons represented from left to right. MONITOR SSG/SSL PIG WRGM Main Steam Line STEP 18 (6.3.4.E) Standard: Examiner's Cue: Comments: BUTTON 1 BUTTON 2 BUTTON 3 Gas I Liquid Gas Particulate Iodine Low Range Mid RanQe HiQh Range SLM PRESS the appropriate channel select pushbutton to obtain the desired reading. PRESS the appropriate channel select pushbutton to obtain the desired reading. Determines 0.3 mr/hr. is normal background reading. Button #1 for 2A SLM is depressed and the reading indicates 0.3 mr/hr. Page 9 of 12 BUTTON 4 Effluent Critical Step __ Sat __ Unsat NRC ADM JPM Rad. Control REV. 0 ( ( Job Performance Measure A-4 (RO) STEP 16 (6.3.4.C) CONNECT the RM-23P signal cable to the RM-80 communications port. Standard: CONNECT the RM-23P signal cable to the RM-80 communications port. Examiner's Cue: The RM-23P signal cable is connected to the RM-80 communications port. Comments: STEP 17 (6.3.4.D) PLACE the RM-23P power switch in ON. Standard: PLACE the RM-23P power switch in ON. Examiner's Cue: The RM-23P power switch is ON. Comments: NOTE Critical Step __ Sat __ Unsat Critical Step __ Sat __ Unsat The top four white buttons are the channel select pushbuttons. The buttons are used to select the appropriate channel dependent upon what type monitor the RM-23P is reading. Buttons represented from left to right. MONITOR SSG/SSL PIG WRGM Main Steam Line STEP 18 (6.3.4.E) Standard: Examiner's Cue: I ~ments: BUTTON 1 BUTTON 2 BUTTON 3 Gas I Liquid Gas Particulate Iodine Low Range Mid Range His:Jh Range SLM PRESS the appropriate channel select pushbutton to obtain the desired reading. PRESS the appropriate channel select pushbutton to obtain the desired reading. Determines 0.3 mr/hr. is normal background reading. Button #1 for 2A SLM is depressed and the reading indicates 0.3 mr/hr. Page 9 of 12 BUTTON 4 Effluent Critical Step __ Sat __ Unsat NRC ADM JPM Rad. Control REV. 0

STEP 19 (6.3.4.F) Standard: Examiner's Cue: Comments: Stop Time: __ Job Performance Measure A-4 (RO) When the desired readings have been obtained, Then PERFORM the following to remove the RM-23P from service:

1. PLACE the RM-23P power switch in OFF.

PLACE the RM-23P power switch in OFF. The RM-23P power switch is OFF. TELL candidate that another operator will complete the remaining steps of the procedure. END OF TASK Page 10 of 12 Critical Step __ Sat Unsat NRC ADM JPM Rad. Control REV. 0 STEP 19 (6.3.4.F) Standard: Examiner's Cue: Comments: ( Stop Time: __ Job Performance Measure A-4 (RO) When the desired readings have been obtained, Then PERFORM the following to remove the RM-23P from service:

1. PLACE the RM-23P power switch in OFF.

PLACE the RM-23P power switch in OFF. The RM-23P power switch is OFF. TELL candidate that another operator will complete the remaining steps of the procedure. END OF TASK Page10of12 Critical Step __ Sat Unsat NRC ADM JPM Rad. Control REV. 0

( ( Initial Conditions: Job Performance Measure A-4 (RO) CANDIDATE CUE SHEET Unit 2 is operating at 100% power. The PC-11 Group 15, Loop 3 is out of service. Initiating Cues: The US has directed you to obtain the local reading from the Main Steam Line Monitor 1 for the A Main steam Line, RIM-26-71, using the RM-23P in accordance with 2-NOP-26.01, Radiation Monitors. Page 11 of 12 NRC ADM JPM Rad. Control REV. 0 ( ( Initial Conditions: Job Performance Measure A-4 (RO) CANDIDATE CUE SHEET Unit 2 is operating at 100% power. The PC-11 Group 15, Loop 3 is out of service. Initiating Cues: The US has directed you to obtain the local reading from the Main Steam Line Monitor 1 for the A Main steam Line, RIM-26-71, using the RM-23P in accordance with 2-NOP-26.01, Radiation Monitors. Page 11 of 12 NRC ADM JPM Rad. Control REV. 0

RM-23P; "PORTABLE RM-23" 05@ 05 Gt::NEr-jAL A,TOfoAIC 01 L_ ._-] \\!J 0 GENERAL ATOMIC MODEL RM-23P >~ HIGHO 0 0 0 1.C" ALERTO 0 0 0 ,-.,""d OPERO 0 0 0 ~~ \\J o~ OJ '-l co MEl (j) ~ CABLE ASSEMBLY ~ ~ s, ~

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( ( FPL St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE Perform Immediate Operator Actions For a Dropped New Fuel Element in the New Fuel Area UNIT 1 NRC JPM (SRO) A-4 Revised By _____ L_a--->'rrY'--R_ic_h ___ Approval __________ Date NRC SRO ADM JPM Rad, Control REV, 0 Page 1 of 8 e FPL St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE Perform Immediate Operator Actions For a Dropped New Fuel Element in the New Fuel Area UNIT 1 NRC JPM (SRO) A-4 Revised By ____

---

'L=a--"-rry'----'-R~ic_'__'___h ___

Approval __________ Date NRC SRO ADM JPM Rad. Control REV. 0 Page 1 of 8

Job Performance Measure Task Number: Task

Title:

Perform immediate operator actions for a dropped new fuel element. Faulted JPM: DYes I:8J No Facility JPM # K/A Ratings: 3.8 K/A Statement: 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. Duty Areas: Radiation Control Task Information: N/A Task Standard: Perform immediate operator actions for a dropped new fuel element. Evaluation Location Performance Level D Simulator D In Plant D Perform I:8J Simulate D Discuss D Lab I:8J Other Classroom

References:

1-1600030 Accidents Involving New or Spent Fuel. Validation Time: 5 Minutes Time Critical DYes Tools/Equipment/Procedures Needed: 1-1600030 Accidents Involving New or Spent Fuel. Specific Safety Concerns, PPE and Hazards associated with the task: None Radiological Protection and RWP Requirements: None I:8J No NRC SRO ADM JPM Rad. Control REV. 0 Page 2 of 8 ( Job Performance Measure Task Number: Task

Title:

Perform immediate operator actions for a dropped new fuel element. Faulted JPM: DYes [g] No Facility JPM # K/A Ratings: 3.8 K/A Statement: 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. Duty Areas: Radiation Control Task Information: N/A Task Standard: Perform immediate operator actions for a dropped new fuel element. Evaluation Location Performance Level D Simulator D In Plant D Perform [g] Simulate D Discuss D Lab LX] Other Classroom

References:

1-1600030 Accidents Involving New or Spent Fuel. Validation Time: 5 Minutes Time Critical DYes Tools/Equipment/Procedures Needed: 1-1600030 Accidents Involving New or Spent Fuel. Specific Safety Concerns. PPE and Hazards associated with the task: None Radiological Protection and RWP Requirements: None [g] No NRC SRO ADM JPM Rad. Control REV. 0 Page 2 of 8

Job Performance Measure Specific Directions: The Task you are to perform Perform Immediate Operator Actions For a Dropped is: New Fuel Element in the New Fuel Room The performance level to be used for this JPM is PERFORM/SIMULATE. (Circle the performance level being used for this implementation of the task.) This Is Not a time critical JPM. 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. As these are IMMEDIATE OPERATOR ACTIONS REFERENCES ARE NOT ALLOWED. Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you. Initial Conditions: Unit 1 is operating at 100% power. New fuel is being off loaded in the new fuel area. Initiating Cues: New fuel is being off loaded in the new fuel area and EM is performing work in the spent fuel area. You are the SRO in charge of the new fuel off load on to the ground floor next to the container. As a new fuel bundle is being raised, the grapple separates and the new fuel element falls from an elevation of 20 feet and lands in a horizontal position. You are to carry out the IMMEDIATE OPERATOR ACTIONS pertaining to this event. NRC SRO ADM JPM Rad. Control REV. 0 Page 3 of 8 Job Performance Measure Specific Directions: The Task you are to perform Perform Immediate Operator Actions For a Dropped is: New Fuel Element in the New Fuel Room The performance level to be used for this JPM is PERFORM/SIMULATE. (Circle the performance level being used for this implementation of the task.) This Is Not a time critical JPM. 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. As these are IMMEDIATE OPERATOR ACTIONS REFERENCES ARE NOT ALLOWED. Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you. Initial Conditions: Unit 1 is operating at 100% power. New fuel is being off loaded in the new fuel area. Initiating Cues: ( New fuel is being off loaded in the new fuel area and EM is performing work in the spent fuel area. You are the SRO in charge of the new fuel off load on to the ground floor next to the container. As a new fuel bundle is being raised, the grapple separates and the new fuel element falls from an elevation of 20 feet and lands in a horizontal position. You are to carry out the IMMEDIATE OPERATOR ACTIONS pertaining to this event. ( NRC SRO ADM JPM Rad. Control REV. 0 Page 3 of 8

Start Time: STEP 1 {7.4.} Standard: Examiner's Cue: Examiner's Note: Comments: STEP 2 {7.4.} Standard: Examiner's Cue: Comments: Job Performance Measure A-4 PERFORMANCE CHECKLIST 1-1600030 Accidents Involving New or Spent Fuel. If the accident occurred in the New Fuel Area, Then perform the following: A. Ensure all material is left in a safe condition. Ensures all material is left in a safe condition. All material is in a safe condition. After step 'C' immediate operator actions DO NOT have to be in the specific order of the procedure. If the accident occurred in the New Fuel Area, Then perform the following: B. Evacuate the New Fuel Area. Announce evacuation of the New Fuel Area. Evacuation of the New Fuel area has been announced. Page 4 of 8 Sat Unsat Critical Step Sat Unsat NRC SRO ADM JPM Rad. Control REV. 0 Start Time: STEP 1 {7.4.} Standard: Examiner's Cue: Examiner's Note: Comments: ( STEP 2 {7.4.} Standard: Examiner's Cue: Comments: Job Performance Measure A-4 PERFORMANCE CHECKLIST 1-1600030 Accidents Involving New or Spent Fuel. 11 the accident occurred in the New Fuel Area, Then perform the following: A. Ensure all material is left in a safe condition. Ensures all material is left in a safe condition. All material is in a safe condition. After step 'C' immediate operator actions DO NOT have to be in the specific order of the procedure. 11 the accident occurred in the New Fuel Area, Then perform the following: B. Evacuate the New Fuel Area. Announce evacuation of the New Fuel Area. Evacuation of the New Fuel area has been announced. Page 4 of 8 Sat Unsat Critical Step Sat Unsat NRC SRO ADM JPM Rad. Control REV. 0

STEP 3 {7 A.} Standard: Examiner's Cue: Comments: STEP 4 {7.4.} Standard: Examiner's Cue: Comments: Job Performance Measure A-4 If the accident occurred in the New Fuel Area, Then perform the following: C. Ensure the Spent Fuel Area is evacuated Ensures all personnel have left the Spent Fuel Pool Area. All personnel have left the Spent Fuel Pool area. If the accident occurred in the New Fuel Area, Then perform the following: D. Ensure all FHB doors are closed and evacuate the area. Ensures all FHB doors are closed and evacuates the area. FHB doors are closed and the area is evacuated. Page 5 of 8 Critical Step Sat Unsat Critical Step Sat Unsat NRC SRO ADM JPM Rad. Control REV. 0 STEP 3 (7.4.} Standard: Examiner's Cue: Comments: STEP 4 (7.4.} Standard: Examiner's Cue: Comments: Job Performance Measure A-4 if the accident occurred in the New Fuel Area, Then perform the following: C. Ensure the Spent Fuel Area is evacuated Ensures all personnel have left the Spent Fuel Pool Area. All personnel have left the Spent Fuel Pool area. if the accident occurred in the New Fuel Area, Then perform the following: D. Ensure all FHB doors are closed and evacuate the area. Ensures all FHB doors are closed and evacuates the area. FHB doors are closed and the area is evacuated. Page 5 of 8 Critical Step Sat Unsat Critical Step I Sat Unsat NRC SRO ADM JPM Rad. Control REV. 0

STEP 5 {7.4.} Standard: Examiner's Cue: Comments: STEP 6 {7.4.} ( I Standard: Examiner's Cue: Comments: STEP 7 (7.4.} Standard: Examiner's Cue: Comments: Job Performance Measure A-4 if the accident occurred in the New Fuel Area, Then perform the following: E. Notify HP to perform a radiological assessment. Notifies HP to perform a radiological assessment. HP acknowledges to perform a radiological assessment. if the accident occurred in the New Fuel Area, Then perform the following: F. Notify Reactor Engineering Notifies Reactor Engineering Reactor Engineering has been notified. if the accident occurred in the New Fuel Area, Then perform the following: G. Notify Security Notifies Security Security has been notified. Page 6 of 8 Critical Step Sat Unsat Critical Step Sat Unsat Critical Step Sat Unsat NRC SRO ADM JPM Rad. Control REV. 0 STEP 5 (7A.} Standard: Examiner's Cue: Comments: STEP 6 {7A.} ( Standard: Examiner's Cue: Comments: STEP 7 (7A.} Standard: Examiner's Cue: Comments: ( Job Performance Measure A-4 11 the accident occurred in the New Fuel Area, Then perform the following: E. Notify HP to perform a radiological assessment. Notifies HP to perform a radiological assessment. HP acknowledges to perform a radiological assessment. 11 the accident occurred in the New Fuel Area, Then perform the following: F. Notify Reactor Engineering Notifies Reactor Engineering Reactor Engineering has been notified. 11 the accident occurred in the New Fuel Area, Then perform the following: G. Notify Security Notifies Security Security has been notified. Page 6 of 8 Critical Step Sat Unsat Critical Step Sat Unsat Critical Step Sat Unsat NRC SRO ADM JPM Rad. Control REV. 0

STEP 8 {7.4.} Standard: Examiner's Cue: Comments: Stop Time: __ ( Job Performance Measure A-4 If the accident occurred in the New Fuel Area, Then perform the following: H. Notify the SM to determine reportability requirements. Notifies SM SM has been notified. END OF TASK Page 7 of 8 Critical Step Sat Unsat NRC SRO ADM JPM Rad. Control REV. 0 ( STEP 8 (7.4.) Standard: Examiner's Cue: Comments: Stop Time: __ Job Performance Measure A-4 If the accident occurred in the New Fuel Area, Then perform the following: H. Notify the SM to determine reportability requirements. Notifies SM SM has been notified. END OF TASK Page 7 of 8 Critical Step Sat __ Unsat NRC SRO ADM JPM Rad. Control REV. 0

Initial Conditions: Job Performance Measure A-4 CANDIDATE CUE SHEET Unit 1 is operating at 100% power. New fuel is being off loaded in the new fuel area. Initiating Cues: New fuel is being off loaded in the new fuel area and EM is performing work in the spent fuel area. You are the SRO in charge of the new fuel off load on to the ground floor next to the container. As a new fuel bundle is being raised, the grapple separates and the new fuel element falls from an elevation of 20 feet and lands in a horizontal position. You are to carry out the IMMEDIATE OPERATOR ACTIONS pertaining to this event. Page 8 of 8 NRC SRO ADM JPM Rad. Control REV. 0 ( ( Initial Conditions: Job Performance Measure A-4 CANDIDATE CUE SHEET Unit 1 is operating at 100% power. New fuel is being off loaded in the new fuel area. Initiating Cues: New fuel is being off loaded in the new fuel area and EM is performing work in the spent fuel area. You are the SRO in charge of the new fuel off load on to the ground floor next to the container. As a new fuel bundle is being raised, the grapple separates and the new fuel element falls from an elevation of 20 feet and lands in a horizontal position. You are to carry out the IMMEDIATE OPERATOR ACTIONS pertaining to this event. Page 8 of 8 NRC SRO ADM JPM Rad. Control REV. 0

ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE PROTECTIVE ACTION RECOMMENDATIONS A-6 CANDIDATE ____________ EXAMINER CANDIDATE { EXAMINER ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM DETERMINE PROTECTIVE ACTION RECOMMENDATIONS A-6

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 (4.4) Knowledge of emergency plan protective action recom mendations.

References:

EPIP-08 Off-Site Notifications and Protective Action Recommendations Candidate: Time Start Name Performance Rating: Sat Validation Time 15 minutes Examiner: Comments Unsat Signature: Time Finish --- ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 2 ( ( 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 (4.4) Knowledge of emergency plan protective action recommendations.

References:

EPIP-08 Off-Site Notifications and Protective Action Recommendations Candidate: Time Start Name Performance Rating: Sat Validation Time 15 minutes Examiner: Comments Unsat Signature: Time Finish 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 experiencing a total loss of feedwater and a loss of offsite power. The 1 A HPSI pump was out of service prior to the event. The crew just initiated once through cooling and the 1 B HPSI pump tripped and is unable to be started. RCS pressure is rising and currently is 1620 psia. At time 0230, Containment High Range Monitor indicates 1.67 x 105 R/hr. A containment vacuum breaker has failed resulting in a release path from the containment. At time 0445 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: 1800 mrem 2 miles: 950 mrem 5 miles: 400 mrem Wind direction is from 78° Initiating Cue The Shift Manager has directed you to determine 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 ( ( 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 experiencing a total loss of feedwater and a loss of offsite power. The 1 A HPSI pump was out of service prior to the event. The crew just initiated once through cooling and the 1 B HPSI pump tripped and is unable to be started. RCS pressure is rising and currently is 1620 psia. At time 0230, Containment High Range Monitor indicates 1.67 x 105 R/hr. A containment vacuum breaker has failed resulting in a release path from the containment. At time 0445 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: 1800 mrem 2 miles: 950 mrem 5 miles: 400 mrem Wind direction is from 78° Initiating Cue The Shift Manager has directed you to determine 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" STEP 1: STANDARD: COMMENTS: STEP 2: STANDARD: COMMENTS: STEP 3: STANDARD: COMMENTS:

2. Determination of PARs A. Instructions for selecting PARs Based on Plant Conditions

1. Refer to the PARs Based on Plant Conditions.

SAT REFER to page 5 of 7 on Attachment 2 -- UNSAT

2. Determination of PARs (cont.)

CRITICAL A. Instructions for selecting PARs Based on Plant Conditions (cont.) STEP

2. Begin in the upper left hand corner of the chart by answering the General Emergency (GE) question.

SAT DETERMINE that a General Emergency Exists. UNSAT

2. Determination of PARs (cont.)

CRITICAL A. Instructions for selecting PARs Based on Plant Conditions (cont.) STEP

3. Correctly answer the questions until you reach one of the boxes that provide PAR information based on plant conditions.

SAT DETERMINE that PARs based on severe core damage. UNSAT ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 4 ( ( START TIME: ___ _ of EPIP-08; "Off-Site Notifications and Protective Action Recommendations" STEP 1:

2. Determination of PARs A. Instructions for selecting PARs Based on Plant Conditions

1. Refer to the PARs Based on Plant Conditions.

STANDARD: REFER to page 5 of 7 on Attachment 2 COMMENTS: STEP 2:

2. Determination of PARs (cont.)

A. Instructions for selecting PARs Based on Plant Conditions (cont.)

2. Begin in the upper left hand corner of the chart by answering the General Emergency (GE) question.

STANDARD: DETERMINE that a General Emergency Exists. COMMENTS: STEP 3:

2. Determination of PARs (cont.)

A. Instructions for selecting PARs Based on Plant Conditions (cont.)

3. Correctly answer the questions until you reach one of the boxes that provide PAR information based on plant conditions.

STANDARD: DETERMINE that PARs based on severe core damage. COMMENTS: SAT UNSAT CRITICAL STEP SAT UNSAT CRITICAL STEP SAT UNSAT ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 4

STEP 4: STANDARD: COMMENTS: STEP 5: STANDARD: COMMENTS: STEP 6: STANDARD: COMMENTS:

2. Determination of PARs (cont.)

A. Instructions for selecting PARs Based on Plant Conditions (cont.)

4. Circle the box with the appropriate PARs.

SAT CIRCLES the PARs based on severe Core Damage. UNSAT

2. Determination of PARs (cont.)

A. Instructions for selecting PARs Based on Plant Conditions (cont.)

5. J£ there is no release, Then transfer the PARs to the State Notification Form. Section 11. The sectors affected can be SAT determined by referring to number 8, weather data in A. Directions for completing the Florida Nuclear Plant Emergency Notification Form.

-- UNSAT DETERMINE that a release is occurring, step is N/A.

2. Determination of PARs (cont.)

A. Instructions for selecting PARs Based on Plant Conditions (cont.)

6. J£ a release is involved, Then go to Section B, Instructions for PARs based on Off-site Dose, below.

SAT DETERMINE that a release is occurring. UNSAT ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 5 STEP 4: STANDARD: COMMENTS: STEP 5: STANDARD: COMMENTS: ( STEP 6: STANDARD: COMMENTS: (

2. Determination of PARs (cont.)

A. Instructions for selecting PARs Based on Plant Conditions (cont.)

4. Circle the box with the appropriate PARs.

SAT CIRCLES the PARs based on severe Core Damage. UNSAT

2. Determination of PARs (cont.)

A. Instructions for selecting PARs Based on Plant Conditions (cont.)

5. J£ there is no release, Then transfer the PARs to the State Notification Form. Section 11. The sectors affected can be SAT determined by referring to number 8, weather data in A. Directions for completing the Florida Nuclear Plant Emergency Notification Form.

-- UNSAT DETERMINE that a release is occurring, step is N/A.

2. Determination of PARs (cont.)

A. Instructions for selecting PARs Based on Plant Conditions (cont.)

6. J£ a release is involved, Then go to Section B, Instructions for PARs based on Off-site Dose, below.

SAT DETERMINE that a release is occurring. UNSAT ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 5

STEP 7: STANDARD: COMMENTS: STEP 8: ( STANDARD: COMMENTS:

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose.

1. PARs are based on Total Effective Dose Equivalent (TEDE or total dose) and I or the Committed Dose Equivalent -- SAT (CDE, throid dose). Do NOT use dose rate values.

UNSAT DETERMINE TEDE to be used for selection of PARs.

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose (cont.)

2. See below:

a. If performing dose calculations using the Class A Model, -- SAT Then in Forecast Mode, print the State Notification Form Summary for computer generated PARs.

UNSAT DETERMINES Dose calculations were performed manually as per initiating cue. ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 6 STEP 7: STANDARD: COMMENTS: STEP 8: ( STANDARD: COMMENTS: (

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose.

1. PARs are based on Total Effective Dose Equivalent (TEDE or total dose) and / or the Committed Dose Equivalent -- SAT (CDE, throid dose). Do NOT use dose rate values.

UNSAT DETERMINE TEDE to be used for selection of PARs.

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose (cont.)

2. See below:

a. If performing dose calculations using the Class A Model, -- SAT Then in Forecast Mode, print the State Notification Form Summary for computer generated PARs.

UNSAT DETERMINES Dose calculations were performed manually as per initiating cue. 8T. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 6

STEP 9: STANDARD: ( COMMENTS:

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose (cont.)

2. See below:

b. If dose calculations were performed manually using EPIP-09, Off-site Dose Calculations, Then calculate TEDE and CDE in accordance with the procedure.

1. Refer to the PARs Based on Manual Dose Calculation flowchart.

(a) Compare the TEDE dose at 1 mile with the values on the flowchart. Enter the chart at the appropriate dose level by determining if the dose is between 500 and 999 mrem or between 1000 and 4999 mrem or 5000 mrem or greater. (b) From the selected dose level, move to the right on the chart to the first column, 0-2 miles. The PAR provided corresponds to the calculated TEDE at 1 mile. DETERMINE from the cue sheet that the 1 mile TEDE dose is 1800 mrem and ENTER the TEDE DOSE column at the TEDE 1000-4999 mrem dose level. Under the 0-2 Miles column, DETERMINE that 'EVACUATE ALL" is the correct classification. DETERMINE from Attachment 1 A that the affected sectors are 'LMNP' (this is the critical part of this step). DETERMINE from the cue sheet that the 2 mile TEDE dose is 950 mrem and ENTER the TEDE DOSE column at the TEDE 500-999 mrem dose level. Under the 2-5 Miles column, DETERMINE that 'SHELTER Sectors Affected" is the correct classification. SAT UNSAT ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 7 ( STEP 9:

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose (cont.)

2. See below:

b. If dose calculations were performed manually using EPIP-09, Off-site Dose Calculations, Then calculate TEDE and CDE in accordance with the procedure.

1. Refer to the PARs Based on Manual Dose Calculation flowchart.

(a) Compare the TEDE dose at 1 mile with the values on the flowchart. Enter the chart at the appropriate dose level by determining if the dose is between 500 and 999 mrem or between 1000 and 4999 mrem or 5000 mrem or greater. (b) From the selected dose level, move to the right on the chart to the first column, 0-2 miles. The PAR provided corresponds to the calculated TEDE at 1 mile. STANDARD: DETERMINE from the cue sheet that the 1 mile TEDE dose is 1800 mrem and ENTER the TEDE DOSE column at the TEDE 1000-4999 mrem dose level. Under the 0-2 Miles column, DETERMINE that 'EVACUATE ALL" is the correct classification. DETERMINE from Attachment 1A that the affected sectors are 'LMNP' (this is the critical part of this step). COMMENTS: DETERMINE from the cue sheet that the 2 mile TEDE dose is 950 mrem and ENTER the TEDE DOSE column at the TEDE 500-999 mrem dose level. Under the 2-5 Miles column, DETERMINE that 'SHELTER Sectors Affected" is the correct classification. SAT UNSAT ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 7

STEP 10: STANDARD: COMMENTS: STEP 11: STANDARD: COMMENTS:

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose (cont.)

2. See below:

SAT

c. Enter the PAR in the 0-2 mile block on the TEDE DOSE table below the flowchart. The sectors affected can be determined by referring to number 8, Weather -- UNSAT Data, in Attachment 1 A. Directions for completing the Florida Nuclear Plant Emergency Notification Form.

ENTER the PAR information as per the attached Answer Key sheet in the TEDE DOSE table. DETERMINE from Attachment 1A that the affected sectors are 'LMNP' (this is the critical part of this step).

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose (cont.)

2. See below:

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 the 10

-- UNSAT mile plus (To Be Determined (TBD) distance) using the calculated 10 mile TEDE, as necessary. DETERMINE from the cue sheet that the 2 mile TEDE dose is 950 mrem and ENTER the TEDE DOSE column at the TEDE 500-999 mrem dose level. Under the 2-5 Miles column, DETERMINE that SHELTER SECTORS AFFECTED is the correct classification DETERMINE 400 mrem at 5 miles is NONE for the 5-10 Miles PAR. ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 8 STEP 10: STANDARD: COMMENTS: STEP 11: ( STANDARD: COMMENTS:

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose (cont.)

2. See below:

SAT

c. Enter the PAR in the 0-2 mile block on the TEDE DOSE table below the flowchart. The sectors affected can be determined by referring to number 8, Weather -- UNSAT Data, in Attachment 1 A. Directions for completing the Florida Nuclear Plant Emergency Notification Form.

ENTER the PAR information as per the attached Answer Key sheet in the TEDE DOSE table. DETERMINE from Attachment 1 A that the affected sectors are 'LMNP' (this is the critical part of this step).

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose (cont.)

2. See below:

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 the 10

-- UNSAT mile plus (To Be Determined (TBD) distance) using the calculated 10 mile TEDE, as necessary. DETERMINE from the cue sheet that the 2 mile TEDE dose is 950 mrem and ENTER the TEDE DOSE column at the TEDE 500-999 mrem dose level. Under the 2-5 Miles column, DETERMINE that SHELTER SECTORS AFFECTED is the correct classification DETERMINE 400 mrem at 5 miles is NONE for the 5-10 Miles PAR. ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 8

STEP 12:

2. Determination of PARs (cant.)

CRITICAL B. Instructions for selecting PARs Based on Off-Site Dose (cant.) STEP

2. See below:

e. Enter the PAR information in the appropriate blocks of the TEDE DOSE table.

SAT STANDARD: ENTER the following on bottom of page 6 of 7 of ATTACHMENT 2: -- UNSAT TEDE DOSE Miles 0-2 2-5 5-10 >10 COMMENTS: STEP 13: STANDARD: COMMENTS: EVACUATE SHELTER NO ACTION ALL NONE NONE NONE LMNP NONE NONE NONE NONE

2. Determination of PARs (cant.)

B. Instructions for selecting PARs Based on Off-Site Dose (cant.)

2. See below:

SAT

f. Follow the same methodology for determining the PARs corresponding to the calculated CDE values beginning at 1 mile

-- UNSAT DETERMINE CDE values will be later as per initiating cue. ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 9 ( STEP 12:

2. Determination of PARs (cont.)

CRITICAL B. Instructions for selecting PARs Based on Off-Site Dose (cont.) STEP

2. See below:

e. Enter the PAR information in the appropriate blocks of the TEDE DOSE table.

SAT STANDARD: ENTER the following on bottom of page 6 of 7 of ATTACHMENT 2: UNSAT TEDE DOSE Miles 0-2 2-5 5-10 >10 COMMENTS: STEP 13: EVACUATE SHELTER NO ACTION ALL NONE NONE NONE LMNP NONE NONE NONE NONE

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose (cont.)

2. See below:

f. Follow the same methodology for determining the PARs corresponding to the calculated CDE values beginning at 1 mile SAT UNSAT STANDARD:

DETERMINE CDE values will be later as per initiating cue. COMMENTS: ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 9

STEP 14: STANDARD: COMMENTS: STEP 15: STANDARD: COMMENTS: STEP 16: STANDARD: COMMENTS:

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose (cont.)

2. See below:

g. Enter each of the determined PARs in the CDE

-- SAT (Thyroid) DOSE table below the flowchart. DETERMINE CDE values will be later as per initiating cue. -- UNSAT

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose (cont.)

2. See below:

h. Go to Section C, Instructions for the PAR

-- SAT worksheet, below. REFERS to Section C UNSAT

2. Determination of PARs (cont.)

C. Instructions for the PAR Worksheet

1. Fill in the time, date and emergency class:

FILLS in the current time, date and General Emergency SAT UNSAT ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 10 STEP 14: STANDARD: COMMENTS: STEP 15: STANDARD: COMMENTS: STEP 16: STANDARD: COMMENTS:

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose (cont.)

2. See below:

g. Enter each of the determined PARs in the CDE

-- SAT (Thyroid) DOSE table below the flowchart. DETERMINE CDE values will be later as per initiating cue. -- UNSAT

2. Determination of PARs (cont.)

B. Instructions for selecting PARs Based on Off-Site Dose (cont.)

2. See below:

h. Go to Section C, Instructions for the PAR

-- SAT worksheet, below. REFERS to Section C UNSAT

2. Determination of PARs (cont.)

C. Instructions for the PAR Worksheet

1. Fill in the time, date and emergency class:

FILLS in the current time, date and General Emergency SAT UNSAT ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 10

STEP 17:

2. Determination of PARs (cont.)

C. Instructions for the PAR Worksheet (cont.)

2. In Part a, PAR Comparison determine the basis for the most conservative PAR by comparing the PARs

-- SAT based on plant conditions against those based on off-site dose. It is important to compare PARs at each distance (0-2, 2-5, 5-10) because the basis of the most -- UNSAT conservative PAR could be different at different distances. STANDARD: REFERS to PARs for General Emergency 'Severe Core Damage' page 5 of 7 on Attachment 2. Compares to PARs based on TEDE dose. COMMENTS: STEP 18:

2. Determination of PARs (cont.)

CRITICAL C. Instructions for the PAR Worksheet (cont.) STEP

3. Enter the most conservative PARs into the table in Part B, Protective Actions to be Recommended by FPL.

Use the word(s) NONE, ALL, ALL REMAINING or list -- SAT the individual affected sectors by letter. UNSAT STANDARD: DETERMINES PARs for General Emergency (plant conditions) are more conservative than PARs based on TEDE Dose. Enter PAR's as per answer key. COMMENTS: END OF TASK

• STOP TIME: ____ _
• Critical Step: Must be S15 minutes from start time ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 11 ( ( STEP 17:

2. Determination of PARs (cont.)

C. Instructions for the PAR Worksheet (cont.)

2. In Part a, PAR Comparison determine the basis for the most conservative PAR by comparing the PARs

-- SAT based on plant conditions against those based on off-site dose. It is important to compare PARs at each distance (0-2,2-5,5-10) because the basis of the most -- UNSAT conservative PAR could be different at different distances. STANDARD: REFERS to PARs for General Emergency 'Severe Core Damage' page 5 of 7 on Attachment 2. Compares to PARs based on TEDE dose. COMMENTS: STEP 18:

2. Determination of PARs (cont.)

CRITICAL C. Instructions for the PAR Worksheet (cont.) STEP

3. Enter the most conservative PARs into the table in Part B, Protective Actions to be Recommended by FPL.

Use the word(s) NONE, ALL, ALL REMAINING or list -- SAT the individual affected sectors by letter. UNSAT STANDARD: DETERMINES PARs for General Emergency (plant conditions) are more conservative than PARs based on TEDE Dose. Enter PAR's as per answer key. COMMENTS: END OF TASK

• STOP TIME:
• Critical Step: Must be S15 minutes from start time ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 11

A. PAR Comparison Compare protective actions based on plant conditions versus dose, determine the more conservative and check the applicable box in the table below. If no PAR is necessary, Then check 'none' ~ Downwind Distance Plant Conditions Dose None 0-2 miles

• .J
• .J 2-5 miles

/ 5-10 miles / >10 TBD miles

• Both Plant and Dose are the same for 0-2 miles. Either I or are acceptable.

B. Protective Actions to be Recommended by FPL Complete the table below with the protective actions to be recommended. Use these items: NONE, ALL REMAINING or fill in the Letters of the sectors affected Downwind Distance EVACUATE SECTORS 1---- ALL 0-2 Miles L,M,N,P 2-5 Miles NONE 5-10 Miles 10-TBD Miles*

• If necessary, add to State Notification Form SHELTER SECTORS NONE ALL REMAINING ALL NO ACTION SECTORS NONE NONE NONE ST, LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 12 ( A. PAR Comparison Compare protective actions based on plant conditions versus dose, determine the more conservative and check the applicable box in the table below. If no PAR is necessary, Then check 'none' Downwind Distance Plant Conditions Dose None 0-2 miles

• {

V 2-5 miles -J 5-10 miles I I >10 TBD miles L _____

• Both Plant and Dose are the same for 0-2 miles. Either I or are acceptable.

B. Protective Actions to be Recommended by FPL Complete the table below with the protective actions to be recommended. Use these items: NONE, ALL REMAINING or fill in the Letters of the sectors affected Downwind Distance EVACUATE SECTORS ALL 0-2 Miles L, M, N, P 2-5 Miles NONE 5-10 Miles 10-TBD Miles*

• If necessary, add to State Notification Form SHELTER SECTORS NONE ALL REMAINING ALL NO ACTION SECTORS NONE NONE NONE ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 12

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) Initial Conditions Unit 1 is experiencing a total loss of feedwater and a loss of offsite power. The 1A HPSI pump was out of service prior to the event. The crew just initiated once through cooling and the 1 B HPSI pump tripped and is unable to be started. RCS pressure is rising and currently is 1620 psia. At time 0230, Containment High Range Monitor indicates 1.67 x 105 R/hr. A containment vacuum breaker has failed resulting in a release path from the containment. At time 0445 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: 1800 mrem 2 miles: 950 mrem 5 miles: 400 mrem Wind direction is from 78° Initiating Cue The Shift Manager has directed you to determine Protective Action Recommendations for the next State of Florida Notification Form update. THIS IS A TIME CRITICAL JPM ( ( CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) Initial Conditions Unit 1 is experiencing a total loss of feedwater and a loss of offsite power. The 1 A HPSI pump was out of service prior to the event. The crew just initiated once through cooling and the 1 B HPSI pump tripped and is unable to be started. RCS pressure is rising and currently is 1620 psia. At time 0230, Containment High Range Monitor indicates 1.67 x 105 R/hr. A containment vacuum breaker has failed resulting in a release path from the containment. At time 0445 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: 1800 mrem 2 miles: 950 mrem 5 miles: 400 mrem Wind direction is from 78° Initiating Cue The Shift Manager has directed you to determine Protective Action Recommendations for the next State of Florida Notification Form update. THIS IS A TIME CRITICAL JPM

E: PROCEDURE NO.: PLANT ATTACHMENT 2 D:ETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS (PARs) (Page 5 of7) to i\\ssess Cont!ihons ()~2 2-5 5-10 EV,ACUAfE SHELTER NOt':tt ,451 None None None NO liON Nonl;! ,A,II A;I NOilB None None N:mB ( 20 OFF-SITE NOTIF!CATIONS AND PROTECTIVE ACTION RECOlv1rv1ENDA TIONS ST LUC!E PLANT ATTACHMENT 2 50 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS (PARs) (Pnge 5 of 7)

t ".

C;Y11i:,UF t.:; l;,r;S8SS Comlrh:YIS 5-10 None Nor,e SH::Ll1::K ?.!1 None 2-5 5-;(: E'vACUA~E Aji rione no ic,.CIION

>Jon&

,A,II NO ;\\CTJON None NJf1B N)f1B A; N)f1B

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) Initial Conditions Unit 1 is experiencing a total loss of feedwater and a loss of offsite power. The 1 A HPSI pump was out of service prior to the event. The crew just initiated once through cooling and the 1 B HPSI pump tripped and is unable to be started. RCS pressure is rising and currently is 1620 psia. At time 0230, Containment High Range Monitor indicates 1.67 x 105 R/hr. A containment vacuum breaker has failed resulting in a release path from the containment. Wind direction is from 78° At time 0445 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: 1800 mrem 2 miles: 950 mrem 5 miles: 400 mrem Wind direction is from 78° Initiating Cue The Shift Manager has directed you to determine Protective Action Recommendations for the next State of Florida Notification Form update. THIS IS A TIME CRITICAL JPM CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER) Initial Conditions Unit 1 is experiencing a total loss of feedwater and a loss of offsite power. The 1 A HPSI pump was out of service prior to the event. The crew just initiated once through cooling and the 1 B HPSI pump tripped and is unable to be started. RCS pressure is rising and currently is 1620 psia. At time 0230, Containment High Range Monitor indicates 1.67 x 105 R/hr. A containment vacuum breaker has failed resulting in a release path from the containment. Wind direction is from 78° At time 0445 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: 1800 mrem 2 miles: 950 mrem ( 5 miles: 400 mrem Wind direction is from 78° Initiating Cue The Shift Manager has directed you to determine Protective Action Recommendations for the next State of Florida Notification Form update. THIS IS A TIME CRITICAL JPM

FROCSD).;RE 7]"1...E: PLANT ATTACHMENT 1 A DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 4 of 8) F. If are no !I,til,.*~tjf'\\r*,<:: of ;) to item 11,

a.

1.

OR 20 DLF-E NO.: PRClCEJ)J.:RE TFLE: OFF-SITE NOTIFICATiONS.AND PROTECTIVE ACTION RECO~",'MENDATIONS S1. LUCIE PLANT ATTACHMENT 1A 41 of 56 DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 4 of 8) B. (continued) F. Entertlle v'Iind cHrecticm (vifind from) in degrees in item 'A': G. Enter tile downwind sectors in item '8. Sectors Affected HJK Sectors Affected PC1R 326-348 Tllere is no "1" sector A. If there are no indications of a release of nldioactive rnaterl£ll, clled, box "A" and go to itern11. I. 1I1~' Re!ease

a.

Evaluation guidance dwing the early stages of a declared ernergency, one of the following is true:

1.

An Increase of (approxirnately) 10 times or one decade above pre-transIent values on of the followinG! rnonitors: (a) AlB Stearniine (b) AlB ECCS (c) Plant Vent (d) Fuel Building OR

A. PAR Comparison Compare protective actions based on plant conditions versus dose, determine the more conservative and check the applicable box in the table below. If no PAR is necessary, Then check 'none' Downwind Distance Plant Conditions Dose None 0-2 miles

• ,[
• ,[

2-5 miles ,[ 5-10 miles ,[ .. <,.;4 >10 TBD miles <~i:j.*..

• Both Plant and Dose are thesarne for 0-2 miles. Either lor are acceptable.

B. Protective Actions to be Recoml'l1ended by FPL Complete the table below with theprQtective actions to be recommended. Use these items: NONE, ALL REMAININ~;Q(Ji" in tbeiLetters of the sectors affected Downwind Distance '~::f;~~b~~': <"'; ';3 EVACUATE

C!~\\;

;

!~~~~L TER SECTORS

.i**yi SECTORS 0-2 Miles L, M, N, 'f' ALL REMAINING 2-5 Miles NONE ALL 5-10 Miles 10-TBD Miles*

• If necessary, add to State Notification Form NO ACTION SECTORS NONE NONE NONE ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 12 ( A. PAR Comparison Compare protective actions based on plant conditions versus dose, determine the more conservative and check the applicable box in the table below. If no PAR is necessary, Then check 'none' Downwind Distance Plant Conditions Dose None -2 miles

• /"
• /"

2 -5 miles /" 5 -10 miles /" > 10 TSD miles

---

~-~-

• Both Plant and Dose are the same for 0-2 miles. Either lor are acceptable.

B. Protective Actions to be Recommended by FPL Complete the table below with the protective actions to be recommended. Use these items: NONE, ALL REMAINING or fill in the Letters of the sectors affected

---

~---

Downwind Distance EVACUATE SECTORS ALL 0-2 Miles L, M, N, P 2-5 Miles NONE 5-10 Miles 10-TBD Miles*

• If necessary, add to State Notification Form SHELTER SECTORS NONE ALL REMAINING ALL NO ACTION SECTORS NONE NONE NONE

~ ST. LUCIE TRAINING DEPT. ADMINISTRATIVE JPM PAGE 12}}