ML15201A553

301 Draft Administrative JPMs

ML15201A553
Person / Time
Site:	Saint Lucie
Issue date:	07/16/2015
From:	NRC/RGN-II
To:	Florida Power & Light Co
References
Download: ML15201A553 (168)

Text

{{#Wiki_filter:* FPL St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE 2B EOG INOPERABLE EVALUATE OPPOSITE TRAIN COMPONENTS HLC 22 NRC RO Admin JPM A1 NRG RO Adm in JPM A 1 Rev 1 Page 1 of 18 JPM A-1 RO Page 1

JOB PERFORMANCE MEASURE Task: Given an Emergency Diesel Generator inoperable, verify opposite train equipment OPERABLE. Faulted JPM? No Facility JPM #: No KIA: G2.1 .31 Ability to locate control room switches, controls , and indications, and to determine that they correctly reflect the desired plant lineup. KIA Rating(s): 4.6 / 4.3 Duty Area(s): N/A Task Information: 07059005 Task Standard: The JPM is complete when the student informs the US of the results of the Operability Checklist for Train A equipment. Evaluation Location: Performance Level: Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

• 2-0SP-59.01 B, 28 Emergency Diesel Generator Monthly Surveillance, Attachment 1, Operability Checklist Prior to Removing 28 EOG from Service, Rev 29 Validation Time: 15 minutes Time Critical: NO Tools/Equipment/Procedures Needed:
• 2-0SP-59.018, 28 Emergency Diesel Generator Monthly Surveillance, Attachment 1, Operability Checklist Prior to Removing 28 EOG from Service Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
• None Radiological Protection and RWP Requirements:
• None NRC RO Adm in JPM A 1 Rev 1 Page 2 of 18 JPM A-1 RO Page 2

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS ._ SPECIFIC DIRECTIONS:

• The task you are to perform is: verify Unit 2 Train A equipment OPERABLE.
• The performance level to be used for this JPM is Perform.
• During the performance of the task, I will tell you which steps to simulate or discuss.
• I will provide you with the appropriate cues for steps that are simulated or discussed.
• You may use any approved reference materials normally available in the execution of this task, including logs.
• Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you .

INITIAL CONDITIONS: Unit 2 is operating at 100% power. Engineering has identified a relay issue potentially impacting 28 EOG operability. The Shift Manager is performing an immediate operability determination. The time is now 0830. The C Charging Pump, C Intake Cooling Water Pump and C Component Cooling Water Pump are currently mechanically and electrically aligned to the 8 Train. INITIATING CUES: The Unit Supervisor has directed you , the Desk RCO, to perform 2-0SP-59.01 B, 28 Emergency Diesel Generator Monthly Surveillance, Attachment 1, Operability Checklist Prior to Removing 28 EOG from Service. Report the results of Attachment 1 to the Unit Supervisor. The Unit Supervisor will be reviewing the Action Tracker while you perform Attachment 1. NRC RO Admin JPM A 1 Rev 1 Page 3 of 18 JPM A-1 RO Page 3

JOB PERFORMANCE MEASURE START TIME: _ _ __ 2-0SP-59.018, Attachment 1, Operability Checklist Prior to Removing 28 EOG from Service These ste s are bulleted and ma be erformed in an order. STEP 1: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 28 EOG from service: Boration flowpath powered from the A side SAT STANDARD: DETERMINES that 2A Boric Acid Pump, 2B Boric Acid Pump, and V-2514 are OPERABLE. UNSAT EXAMINER'S CUE: None. COMMENTS: STEP 2: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EOG from service: Charging pump powered from the A side SAT STANDARD: DETERMINES that 2A Charging Pump is OPERABLE. UNSAT EXAMINER'S CUE: None. EXAMINER'S NOTE: The C Charging Pump is aligned to the B Train (Cue Sheet). COMMENTS: NRC RO Ad min JPM A1 Rev 1 Page 4of1 8 JPM A-1 RO Page 4

JOB PERFORMANCE MEASURE STEP 3: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EOG from service: PORV Block Valve V1476, BLOCK VALVE SAT STANDARD: DETERMINES that PORV Block Valve V1476 is OPERABLE. UNSAT EXAMINER'S CUE: None. COMMENTS: STEP 4: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EOG from service: 2A HPSI Pump and flowpath SAT STANDARD: DETERMINES that 2A HPSI Pump and flowpath are OPERABLE. UNSAT EXAMINER'S CUE: None. COMMENTS: NRC RO Adm in JPM A 1 Rev 1 Page 5of1 8 JPM A-1 RO Page 5

JOB PERFORMANCE MEASURE STEP 5: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 28 EOG from service: CRITICAL STEP 2A LPSI Pump and flowpath STANDARD: DETERMINES that the 2A LPSI Pump is operable BUT the 2A LPSI SAT Pump flowpath has an inoperable valve (V-3615). A Thermal Overload Annunciator (R-58) is in alarm for the valve. Notes the status on 2-0SP-59.018, Attachment 1, Operability Checklist as UNSAT a discrepancy EXAMINER'S CUE: None. COMMENTS: STEP 6: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 28 EOG from service: 2A Containment Spray Pump and flowpath SAT STANDARD: DETERMINES that 2A Containment Spray Pump and flowpath are OPERABLE. UNSAT EXAMINER'S CUE: None. COMMENTS: NRC RO Admin JPM A1 Rev 1 Page 6 of 18 JPM A-1 RO Page 6

JOB PERFORMANCE MEASURE STEP 7: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EOG from service: 2A Hydrazine Pump SAT STANDARD: DETERMINES that 2A Hydrazine Pump is OPERABLE. UNSAT EXAMINER'S CUE: None. COMMENTS: STEP 8: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EOG from service: CRITICAL STEP 2A and 2B Containment Coolers STANDARD: DETERMINES that the 2A Containment Fan Cooler is operable SAT BUT the 2B Containment Fan Cooler breaker is racked out (Annunciator T-11 is lit) so it is inoperable. Notes the status on 2-0SP-59.01 B, Attachment 1, Operability Checklist as a UNSAT discrepancy EXAMINER'S CUE: None. COMMENTS: NRC RO Adm in JPM A 1 Rev 1 Page 7 of 18 JPM A-1 RO Page 7

JOB PERFORMANCE MEASURE - STEP 9: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 28 EOG from service: HVE-6A, SBVS EXHAUST FAN and flowpath SAT STANDARD: DETERMINES that HVE-6A, SBVS EXHAUST FAN and flowpath are OPERABLE. UNSAT EXAMINER'S CUE: None. COMMENTS: STEP 10: VERIFY the following A train equipment and flowpaths are NOT out CRITICAL of service prior to removing the 28 EOG from service: STEP 2A and 2C Auxiliary Feedwater Pumps SAT STANDARD: DETERMINES that 2A Auxiliary Feedwater Pump is OPERABLE, and that that 2C Auxiliary Feedwater Pump is inoperable. Notes the status on 2-0SP-59.018, Attachment 1, Operability Checklist as UNSAT a discrepancy. EXAMINER'S NOTE: At the examiner's discretion, the JPM can be terminated any time after 2C AFW Pump has been reported inoperable. EXAMINER'S CUE: Another RO will complete the remainder of Attachment 1. COMMENTS: NRC RO Adm in JPM A 1 Rev 1 Page 8of18 JPM A-1 RO Page 8

JOB PERFORMANCE MEASURE STEP 11: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 28 EOG from service: A powered and aligned Component Cooling Water Pump and A SAT header STANDARD: DETERMINES that A Component Cooling Water Pump and A CCW UNSAT header are OPERABLE. EXAMINER'S CUE: None. EXAMINER'S NOTE: The C CCW Pump is aligned to the B Train (Cue Sheet). COMMENTS: STEP 12: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 28 EOG from service: A powered and aligned Intake Cooling Water Pump and A header SAT STANDARD: DETERMINES that A Intake Cooling Water Pump and A ICW header are OPERABLE. UNSAT EXAMINER'S CUE: None. EXAMINER'S NOTE: The C ICW Pump is aligned to the B Train (Cue Sheet). COMMENTS: NRC RO Adm in JPM A 1 Rev 1 Page 9 of 18 JPM A-1 RO Page 9

JOB PERFORMANCE MEASURE - STEP 13: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EOG from service: HVE-13A, CONTROL ROOM EMERG FLTR FAN and A train SAT Control Room Emergency Ventilation System components STANDARD: DETERMINES that HVE-13A, CONTROL ROOM EMERG FLTR UNSAT FAN and A train Control Room Emergency Ventilation System components are all OPERABLE. EXAMINER'S CUE: None. COMMENTS: STEP 14: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EOG from service: HVE-9A, ECCS EMERG EXHAUST FAN and flowpath _ _ SAT STANDARD: DETERMINES that HVE-9A, ECCS EMERG EXHAUST FAN and flowpath are OPERABLE. UNSAT EXAMINER'S CUE: None. COMMENTS: NRC RO Ad m in JPM A 1 Rev 1 Page 10of1 8 JPM A-1 RO Page 10

JOB PERFORMANCE MEASURE STEP 15: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG from service: 2A Startup Transformer SAT STANDARD: DETERMINES that 2A Startup Transformer is OPERABLE. UN SAT EXAMINER'S CUE: None. COMMENTS: STEP 16: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG from service: A side A. C. Electrical Distribution required by Tech Specs 3.8.3.1 for SAT MODES 1, 2, 3 and 4, OR Tech Specs 3.8.3.2 for MODES 5 and 6 STANDARD: DETERMINES that A side A.C . Electrical Distribution required by UNSAT Tech Spec 3.8.3.1 for MODE 1 is OPERABLE. EXAMINER'S CUE: None. COMMENTS: NRC RO Adm in JPM A 1 Rev 1 Page 11 of 18 JPM A-1 RO Page 11

JOB PERFORMANCE MEASURE STEP 17: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 28 EOG from service: 2A Emergency Diesel Generator SAT STANDARD: DETERMINES that 2A Emergency Diesel Generator is OPERABLE. UNSAT EXAMINER'S CUE: None. COMMENTS: STEP 18: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 28 EOG from service: Pressurizer Heaters at least 155 KW in MODES 1, 2, and 3 ... SAT STANDARD: DETERMINES that at least 155 KW of Pressurizer Heaters (Backup Heater #1) are OPERABLE, using DCS point W943A. UNSAT EXAMINER'S CUE: The Board RCO reports 205 KW of Pressurizer heaters available. COMMENTS: NRC RO Adm in JPM A 1 Rev 1 Page 12of18 JPM A-1 RO Page 12

JOB PERFORMANCE MEASURE - STEP 19: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 28 EOG from service: A powered Tech Spec Remote Shutdown Instrumentation per Tech SAT Spec 3.3.3.5 for MODES 1, 2 and 3. STANDARD: DETERMINES that A powered Tech Spec Remote Shutdown UNSAT Instrumentation is OPERABLE, per Tech Spec 3.3.3.5. EXAMINER'S CUE: The Unit Supervisor informs you that all Remote Shutdown Instrumentation is in compliance with Tech Spec LCO 3.3.3.5. COMMENTS: STEP 20: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 28 EOG from service: Accident Monitoring Instrumentation per Tech Spec 3.3.3.6 for SAT MODES 1, 2 and 3 as follows : PT-07-4A 1, CNTMT PRESS UNSAT STANDARD: DETERMINES that PT-07-4A1 , CNTMT PRESS is OPERABLE. EXAMINER'S CUE: None. EXAMINER'S NOTE: PT-07-4A1 is located on PACB #2. COMMENTS: NRC RO Admin JPM A1 Rev 1 Page 13of18 JPM A-1 RO Page 13

JOB PERFORMANCE MEASURE STEP 21: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 28 EOG from service: Accident Monitoring Instrumentation per Tech Spec 3.3.3.6 for SAT MODES 1, 2 and 3 as follows: Ll-111 OX, LEVEL (Pressurizer), OR UR-01-1, Pzr Level I Press(L Y-111 OX, pressurizer Level) UNSAT STANDARD: DETERMINES that:

• Ll-111 OX, LEVEL (Pressurizer)
• UR-01-1 , Pzr Level I Press(L Y-111 OX, pressurizer Level) is OPERABLE.

EXAMINER'S CUE: None. COMMENTS: NRG RO Adm in JPM A 1 Rev 1 Page 14of18 JPM A-1 RO Page 14

JOB PERFORMANCE MEASURE STEP 22: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EOG from service: Accident Monitoring Instrumentation per Tech Spec 3.3.3.6 for SAT MODES 1, 2 and 3 as follows : L9012, DCS Point S/G 2A LEVEL WR, OR Ll-9014, 2A S/G WIDE RANGE LEVEL (PACB 2) UNSAT STANDARD: DETERMINES that:

• L9012 , DCS Point S/G 2A LEVEL WR OR
• Ll-9014, 2A S/G WIDE RANGE LEVEL (PACB 2) is OPERABLE.

EXAMINER'S CUE: None. EXAMINER'S NOTE: Ll-9014 is located on PACB #2. COMMENTS: STEP 23: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EOG from service: Accident Monitoring Instrumentation per Tech Spec 3.3.3.6 for SAT MODES 1, 2 and 3 as follows: LT-07-13A, A CNTMT SUMP LEVEL WIDE RANGE _ _ UNSAT STANDARD: DETERMINES that LT-07-13A, A CNTMT SUMP LEVEL WIDE RANGE is OPERABLE. EXAMINER'S CUE: None. EXAMINER'S NOTE: LT-07-13A is located on PACB #2. COMMENTS: NRC RO Ad min JPM A1 Rev 1 Page 15of18 JPM A-1 RO Page 15

JOB PERFORMANCE MEASURE STEP 24: Sign Attachment 1 and inform the Unit Supervisor. STANDARD: SIGNS Attachment 1 and INFORMS the Unit Supervisor that all equipment is OPERABLE, with the exception of the 2C Auxiliary _ _ SAT Feedwater Pump, the 2A LPSI Pump flowpath and 2-HVS-18 Containment Fan Cooler. _ _ UNSAT EXAMINER'S CUE: "This JPM is complete." COMMENTS: END OF TASK STOP TIME: _ _ __ NRC RO Adm in JPM A 1 Rev 1 Page 16of18 JPM A-1 RO Page 16

JOB PERFORMANCE MEASURE SIMULATOR JPM SETUP

1. RESTORE IC-80

2. This IC Set requires ALL AB busses to be aligned to the "B" Train during switch check. Swap the Breaker lens covers to match this alignment. Also swap the lens covers for the 2C CCW pump cross-tie valves to match this alignment.

3. The 2C Auxiliary Feedwater Pump is out of service for pump seal replacement. Place the control switches for MV-08-13 and 14 in Close and hang ECO info tags on them. Take MV-08-3 to stop using key #78 and hang an ECO info tag on it. Place green mylar on annunciators G-14 and G-46.

4. Containment Fan Cooler 2-HVS-1 Bis out of service for breaker change out. Hang an ECO info tag on its control switch and place the switch in STOP. Place green mylar on annunciator T-11.

5. Annunciator R-58 should be in alarm due to a thermal overload condition on MV-3615, LPSI Header Injection valve.

6. Ensure PORVs are aligned such that PORV Block Valve V1476 is OPEN (PORV V-1474 in service).

7. Place a "B" Protected Train Placard on RTGB 203

8. Place a Green OLRM Risk Placard on RTGB 203 NRC RO Adm in JPM A 1 Rev 1 Page 17of18 JPM A-1 RO Page 17

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK) INITIAL CONDITIONS: Unit 2 is operating at 100% power. Engineering has identified a relay issue potentially impacting 28 EOG operability. The Shift Manager is performing an immediate operability determination. The time is now 0830. The C Charging Pump, C Intake Cooling Water Pump and C Component Cooling Water Pump are currently mechanically and electrically aligned to the 8 Train . INITIATING CUES: The Unit Supervisor has directed you, the Desk RCO, to perform 2-0SP-59.018, 28 Emergency Diesel Generator Monthly Surveillance, Attachment 1, Operability Checklist Prior to Removing 28 EOG from Service. Report the results of Attachment 1 to the Unit Supervisor. The Unit Supervisor will be reviewing the Action Tracker while you perform Attachment 1. JPM A-1 RO Page 18

REVISION NO.: PROCEDURE TITLE : PAGE: 29 28 EMERGENCY DIESEL GENERATOR MONTHLY SURVEILLANCE 62 of 89 PROCEDURE NO.: 2-0SP-59.01 B ST. LUCIE UNIT 2 INITIAL ATTACHMENT 1 Operability Checklist Prior to Removing 28 EOG from Service (Page 1 of 2) VERIFY following A train equipment and flowpaths are NOT out of seNice prior to removing the 28 EOG from seNice: NOTE

• 2A and 28 Boric Acid Pumps, and V-2514, EMERG~NCY BORATE, are powered from the A Side.
• V-2508 and V-2509, BA Gravity Feed Valves , and V-2504, REFUEL WATER TO CHARGING PUMPS, are powered from the B Side.
• Boration flowpath powered from A side
• Charging pump powered from the A side
• PORV Block Valve V1476 , BLOCK VALVE , (may be de-energized and closed in MODES 1, 2 and 3)
• 2A HPSI Pump and flowpath
• 2A LPSI Pump and flowpath
• 2A Containment Spray Pump and flowpath
• 2A Hydrazine Pump
• 2A and 28 Containment Coolers
• HVE-6A, SBVS EXHAUST FAN , and flowpath
• 2A and 2C Auxiliary Feedwater Pumps (2C AFW NOT required MODE 4 and below)
• A powered and aligned Component Cooling Water Pump and A header
• A powered and aligned Intake Cooling Water Pump and A header
• HVE-13A, CONTROL ROOM EMERG FLTR FAN, and A train Control Room Emergency Ventilation System components
• HVE-9A, ECCS EMERG EXHAUST FAN , and flowpath JPM A-1 RO Page 19

REVISI ON NO.: PROCEDURE TITLE: PAGE: 29 28 EMERGENCY DIESEL GENERATOR MONTHLY SURVEILLANCE 63 of 89 PROCEDURE NO.: 2-0SP-59.01 B ST. LUCIE UNIT 2 INITIAL ATTACHMENT 1 Operability Checklist Prior to Removing 28 EOG from Service (Page 2 of 2)

• 2A Startup Transformer
• A side AC . Electrical Distribution required by Tech Specs 3.8.3.1 for MODES 1, 2, 3 and 4, OR Tech Specs 3.8.3.2 for MODES 5 and 6
• 2A Emergency Diesel Generator
• Pressurizer Heaters at least 155 KW in MODES 1, 2 and 3 (Tech Spec Section 3.4.3, Pressurizer, requirement for 150 KW. plus 5 KW transformer losses) from emergency power (Backup Heater #1) using Distributed Control System point W943A PRESSZER HEATER PWER 2A, Steam Generator 2A and 28 Heat Rate page 1
• A powered Tech Spec Remote Shutdown Instrumentation per Tech Spec 3.3.3.5 for MODES 1, 2 and 3 NOTE The removal of the 28 EOG from service with Accident Monitoring Instrumentation inoperable is permitted if the actions of Tech Spec 3.3.3.6 and Table 3.3.10 are entered.
• Accident Monitoring Instrumentation per Tech Spec 3.3.3.6 for MODES 1, 2 and 3 as follows :
• PT-07-4A1 , CNTMT PRESS Ll-111 OX, LEVEL (Pressurizer), or UR-01-1 , Pzr Level I Press, (L Y-111 OX, Pressurizer Level)

L9012, DCS Point S/G 2A LEVEL WR, or Ll-9014, 2A SIG WIDE RANGE LEVEL (PACB 2)

• LT-07-13A, A CNTMT SUMP LEVEL WIDE RANGE Performed By: ~~~~~~~~~~~~~~~~~~

PrinUSign Initials Date Reviewed By: ~~~~~~~~~~~~~~~~~~~~~~ Unit Super-Visor (PrinUSign) Date JPM A-1 RO Page 20

REVIS ION NO.: PROCEDURE TITL E: PAGE: 29 28 EMERGENCY DIESEL GENERATOR MONTHLY ' SURVEILLANCE 62 of 89, PROCEDURE NO .: 2-0SP-59.01 B ST. LUCIE UNIT 2 INITIAL ATTACHMENT 1 " - Operability Checklist Prior to Removing 28 EOG from Service (Page 1 of 2) VERIFY following A train equipment and flowpaths are NOT out of service prior to removing the 2B EOG from service:

                                                         ;.//\

_ b16t~ ) 2A and 28 Boric Acid Pumps, a~~514, EMERG~NCY BORATE , are ewered from the A Side. V-2508 and V-2509, BA Gravity Feed Valves , and V-2504, REFUEL WATER TO CHARGING PUMPS, are powered from the 8 Side.

• Boration flowpath powered from A side
• Charging pump powered from the A side
• PORV Block Valve V1476 , BLOCK VALVE , (may be de-energized and closed in MODES 1, 2 and 3)

-

• 2A HPSI Pump and flowpath 2A LPSI Pump and flowpath 2A Containment Spray Pump and flowpath

                                                                                         *_-r,rz_

• 2A Hydrazine Pump -TR
• 2A and 28 Containment Coolers {x'~
• HVE-6A, SBVS EXHAUST FAN, and flowpath

                                                                                             --1z_
                                                                                            , _J 2A and 2C Auxiliary Feedwater Pumps (2C AFW NOT required MODE 4 and below)

A powered and aligned Component Cooling Water Pump and A header

• A powered and aligned Intake Cooling Water Pump and A header
• HVE-13A. CONTROL ROOM EMERG FLTR FAN , and A train Control Room Emergency Ventil ation System components
• HVE-9A, ECCS EMERG EXHAUST FAN, and flowpath

REVISION NO.: PROCEDURE TITLE: 29 **r. 28 EMERGENCY DIESEL GENERATOR MONTHLY SURVEILLANCE 63 of 89 , I PROCEDURE NO.: 2-0SP-59.01 B ST. LUCIE UNIT 2 INITIAL _ ATTACHMENT 1 Operability Checklist Prior to Removing 28 EOG from Service (Page 2 of 2)

• 2A Startup Transformer
• A side AC . Electrical Distribution required by Tech Specs 3.8.3.1 for MODES 1, 2, 3 and 4, OR Tech Specs 3.8.3.2 for MODES 5 and 6 qiR__
• 2A Emergency Diesel Generator :1l'L-
• Pressurizer Heaters at least 155 KW in MODES 1, 2 and 3 (Tech Spec Section 3.4.3, Pressurizer, requirement for 150 KW plus 5 KW transformer losses) from emergency power (Backup Heater #1) using Distributed Control System point W943A PRESSZER HEATER -::::fu_

PWER 2A, Steam Generator 2A and 28 Heat Rate page 1 ~

• A powered Tech Spec Remote Shutdown Instrumentation per Tech Spec 3.3.3.5 for MODES 1, 2 and 3 cjjL.

{]<?XE) The removal of the 28 EOG from serv(ce with Accident Monitoring Instrumentation inoperable is permitted if the actions of Tech Spec 3.3.3.6 and Table 3.3.1 0 are entered.

• Accident Monitoring Instrumentation per Tech Spec 3.3.3.6 for MODES 1, 2 and 3 as follows :
• PT-07-4A1 , CNTMT PRESS Ll-1110X, LEVEL (Pressurizer), or UR-01-1, Pzr Level I Press, ~

(L Y-1110X, Pressurizer Level) --.J'-- L9012, DCS Point SIG 2A LEVEL WR , or Ll-9014, 2A S/G WIDE RANGE LEVEL (PACB 2)

• LT-07-13A, A CNTMT SUMP LEVEL WIDE RANGE Performed By: ---->'~'--+----(ba~=...,,..'if)~-------

U-- Print/Sign Initials Reviewed By:

                   --------------------~

Unit Supervisor (Print/Sign) Date JP M A-1 RO Page 22

ST. LUCIE PLANT OPS-503 OPERATIONS DEPARTMENT POLICY REVISION 63 TECHNICAL SPECIFICATION GUIDANCE Page 35 of 40 Operational Guidance for Section 3/4.8 3/4.8.1 , 3/4 .8.2 , and 3/4.8.3 AC Sources, DC Sources, and Onsite Power Distribution Systems

1. Station Blackout Cross Tie While not specifically addressed in the Technical Specifications, the Station Blackout Cross tie is a component of the Risk Assessment Matrix. As such it is considered a risk significant component. The guidance of ADM-17 .16, Implementation of the Configuration Risk Management Program, Section 6.1.20 should be used whenever a Station Blackout Cross tie breaker is removed from service.

2. Redundant Equipment Operability (Action 3.8.1.1.b)

A. When a Diesel Generator is declared inoperable, Then one of the required activities is to verify that all required systems , subsystems, trains, components, and devices that depend on the remaining OPERABLE Diesel Generator as a source of emergency power are also OPERABLE . Redundant equipment is defined in the applicable Diesel Generator surveillance procedure. If a redundant feature is found inoperable, during the cross train equ~ent verification , within four (4) hours, restore the inoperable component(,£0 declare the redundant component supported by the inoperable diesel inoperable, and enter that feature's TS LCO requirements.

a. If a LCO for a system, subsystem, train, component, or device does NOT explicitly require the associated Diesel Generator to be operable to satisfy that LCO , Then :

1. Equipment is not inoperable solely due to Diesel Generator inoperability, when powered from the preferred off-site power source. As long as its required redundant counterpart is operable.

2. Therefore, when only a Diesel Generator is inoperable, it suffices to enter only the action 3.8.1.1.b.

3. Off-Site Power Availability Determination (Surveillance 4.8.1.1.1.a)

Determining the availability of off-site power to satisfy Technical Specification Surveillance Requirement 4.8.1.1.1 .a is accomplished via use of the sync plug on RTGB-101 /201 AND by verifying 4160V breaker alignment by referencing , as needed , 1/2-0SP-100.xx (Tuesday Dayshift). Initial Documentation for successful completion of the surveillance will be in the narrative logs. Subsequent documentation, at a minimum, will be in the data logger. JPM A-1 RO Page 23

SECTION NO.: PAGE: TITLE: TECHNICAL SPECIFICATIONS 3/4.8 BASES ATTACHMENT 10 OF ADM-25 .04 3 of 9 - REVISION NO.: 5 ELECTRICAL POWER SYSTEMS ST. LUCIE UNIT 2 BASES FOR SECTION 3/4.8 3/4.8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES and ONSITE POWER DISTRIBUTION SYSTEMS The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety related equipment required for 1) the safe shutdown of the facility and 2) the mitigation and control of accident conditions within the facility. The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criteria 17 of Appendix "A" to 10 CFR 50. The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation. The OPERABILITY of the power sources are consistent with the initial condition assumptions of the safety analyses and are based upon maintaining at least one redundant set of onsite A.C . and D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss of offsite power and single failure of the other onsite AC . source. The A.C . and D.C. source allowable out-of-service times are based on Regulatory Guide 1.93, "Availability of Electrical Power Sources, " December 1974. When one diesel generator is inoperable, there is an additional requirement to check that all required systems, subsystems, trains, components and devices (i.e., redundant features), that depend on the remaining OPERABLE diesel generator as a source of emergency power, are also OPERABLE, and that the steam-driven auxiliary feedwater pump is OPERABLE. These redundant required features are those that are assumed to function to mitigate an accident, coincident with a loss of offsite power, in the safety analysis, such as the emergency core cooling system and auxiliary feedwater system. Upon discovery of a concurrent inoperability of required redundant features the feature supported by the inoperable EOG is declared inoperable. Thus plant operators will be directed to supported feature TS action requirements for appropriate remedial actions for the inoperable required features . JPM A-1 RO Page 24

SECTION NO.: PAGE: -- TITLE: TECHNICAL SPECIFICATIONS

                                                                                                 '1 3/4.8                 BASES ATTACHMENT 10 OF AOM-25.04                        4 of9      I REVISION NO.:                      ELECTRICAL POWER SYSTEMS                                     '

5 ST. LUCIE UNIT 2 3/4.8 ELECTRICAL POWER SYSTEMS (continued) I BASES (continued) 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES and ONSITE POWER DISTRIBUTION SYSTEMS (continued) The four hour completion time upon discovery that an opposite train required feature is inoperable is to provide assurance that a loss of offsite power, during the period that a EOG is inoperable, does not result in a complete loss of safety function of critical redundant required features . The four hour completion time allows the operator time to evaluate and repair any discovered inoperabilities. This completion time also allows for an exception to the normal "time zero" for beginning the allowed outage time "clock." The four hour completion time only begins on discovery that both an inoperable EOG exists and a required feature on the other train is inoperable. TS 3.8.1.1, ACTION "b" provides an allowed outage/action completion time (AOT) of up to 14 days to restore a single inoperable diesel generator *to operable status. This AOT is based on the findings of a deterministic and probabilistic safety analysis and is referred to as a "risk-informed" AOT. Entry into this action requires that a risk assessment be performed in accordance with the Configuration Risk Management Program (CRMP) , which is described in the Administrative Procedure that implements the Maintenance Rule pursuant to 10 CFR 50.65. All EOG inoperabilities must be investigated for common-cause failures regardless of how long the EOG inoperability persists. When one diesel generator is inoperable, required ACTIONS 3.8.1.1.b and 3.8.1.1.c provide an allowance to avoid unnecessary testing of EOGs. If it can be determined that the cause of the inoperable EOG does not exist on the remaining OPERABLE EOG, then SR 4.8.1.1 .2.a.4 does not have to be performed. Eight (8) hours is reasonable to confirm that the OPERABLE EOG is not affected by the same problem as the inoperable EOG . If it cannot otherwise be determined that the cause of the initial inoperable EOG does not exist on the remaining EOG, then satisfactory performance of SR 4.8.1.1 .2.a.4 suffices to provide assurance of continued OPERABILITY of that EOG. If the cause of the initial inoperability exists on the remaining OPERABLE EOG, that EOG would also be declared inoperable upon discovery, and ACTION 3.8.1 .1.e would be entered. Once the failure is repaired (on either EOG) , the common-cause failure no longer exists. JPM A-1 RO Page 25

REVISION NO.: PROCEDURE TITLE: PAGE: 15 61 CONTROL ROOM PANEL R RTGB-206 PROCEDURE NO.: WINDOW: R-58 2-ARP-01-ROO ST. LUCIE UNIT 2 (Page 1 of 1) CAUSES: For either valve, any of the following :

• Associated 480V MCC breaker is in TRIP position LPSI
• Thermal overload has actuated V3615N3625
• Control power fuse is blown
• Circuit failure occurred OVRLD/
• Valve was throttle or closed after a SIAS SIAS OVRD R-58 DEVICE: SETPOINT: LOCATION:

74/257 Energized 480V MCC-2A5 Compt EF3, 2-41220 49/257 Thermal overload actuated 480V MCC-2A5 Compt EF3, 2-41220 3/257 Energized 480V MCC-2A5 Campi EF3, 2-41220 74/260 Energized 480V MCC 2A6 Compt CF3, 2-41312 49/260 Thermal overload actuated 480V MCC 2A6 Campi CF3, 2-41312 3/260 Energized 480V MCC 2A6 Compt CF3, 2-41312 ALARM CONFIRMATION

1. Both indicating lights for either of the following are OFF:

• HCV-3615, HEADER A TO LOOP 2A2 VALVE
• HCV-3625, HEADER A TO LOOP 2A1 VALVE

2. SIAS is present and either of the above valves were OPEN and manually throttled or closed .

3 . Either V3615 or V3625 do NOT change position when in MaintenancefTest and the hand switch or push buttons are operated. OPERATOR ACTIONS

1. IF V3615, HEADER A TO LOOP 2A2 VALVE, OR V3625, HEADER A TO LOOP 2A1 VALVE, are NOT required to be CLOSED, THEN ENSURE both are OPEN .

2 . IF the associated indicating lights are OFF , THEN locally CHECK the status of the following breakers:

• 2-41220, LPSI FLOW CONTROL VLV HCV-3615
• 2-41312, LPSI FLOW CONTROL VA HCV-3625

3. IF the associated breaker is NOT TRIPPED, THEN PERFORM the following:

A. PRESS the Thermal Overload RESET button or NOTIFY EM to reset the Thermal Overload . B. ENSURE the associated breaker is ON . C . IF the associated breaker is ON AND indicating lights are OFF, THEN ENSURE the associated control power fuse is checked and replaced as necessary. 4 . IF the associated breaker is TRIPPED OR the thermal overload repeatedly actuates, THEN NOTIFY EM to troubleshoot and repair.

REFERENCES:

1. CWD 2998-8-327, sheet 257, 260, 32 JPM A-1 RO Page 26

REVISION NO.; PROCEDURE TITLE: PAGE: 7 14 CONTROLROOMPANELTHVCB PROCEDURE NO.: WINDOW: T-11 2-ARP-01-TOO ST. LUCIE UNIT 2 (Page 1 of 1) CAUSES: Any of the following :

• Trip of the 480V 8wgr breaker CNTMT FAN CLR
• Thermal overload condition on the MCC breaker HVS-18
• Control power loss due to a blown fuse or open MCC breaker OVRLD/

TRIP T-11 DEVICE: SETPOINT: LOCATION: 8DE1/308 TRIP 480VAC SWGR 2A5 Comp! 30, 2-40359 8DE2/308 TRIP 480VAC 8WGR 2A5 Compt 30 , 2-40359 74F/286 De-energized 480VAC MCC-2A9 Compt 801 , 2-42602 49F/286 Thermal Overload 480VAC MCC-2A9 Compt 801 , 2-42602 748/286 De-energized 480VAC MCC-2A9 Comp! 801 , 2-42602 498/286 Thermal Overload 480VAC MCC-2A9 Comp! 801 , 2-42602 ALARM CONFIRMATION

1. IF HVS-1 B, CONTAINMENT COOLER B, was running, green indicating light ON indicates thermal overload condition.

2. HVS-1B indicating lights OFF indicates either the control power fuse is blown or either of the following breakers are open:

• 2-42602, CONTAINMENT COOLING FAN 2HVS-1B
• 2-40359, FDR. BKR FOR MCC 2A9-2HVS-1 B

'-- OPERATOR ACTIONS

1. GO TO 2-AOP-25.01 , Loss of RCS Cooling Fans.

REFERENCES:

1. CWD 2998-8-327 sheets 286 , 308 JPM A-1 RO Page 27

eFPL St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASBRE 28 EOG INOPERABbE EVALUATE OPPOSITE TRAIN COMPONENTS AND EVALUATE TECHNICAL SPECIFICATIONS HLC 22 NRC SRO Admin JPM A1 NRC SRO Admin JPM A 1 Page 1 of 6 JPM A-1 SRO Page 1

JOB PERFORMANCE MEASURE Task: Given an Emergency Diesel Generator inoperable, verify opposite train equipment OPERABLE and evaluate Technical Specifications. Faulted JPM? No Facility JPM #: No KIA: G2.1 .7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrumentation interpretations. KIA Rating(s): 4.4 I 4.7 Duty Area(s): N/A Task Information: 07059005 Task Standard: The JPM is complete when the US evaluates the results of the Operability Checklist for Train A equipment and Technical Specifications are evaluated. Evaluation Location: Performance Level: Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

• 2-0SP-59.01 B, 28 Emergency Diesel Generator Monthly Surveillance, Attachment 1, Operability Checklist Prior to Removing 28 EOG from Service, Rev 29
• Tech Spec LCO 3.7.1.2, Auxiliary Feedwater System
• Tech Spec LCO 3.8.1.1 .b, A.C. Sources (Operating)

Validation Time: 20 minutes Time Critical: NO Tools/Equipment/Procedures Needed:

• Completed 2-0SP-59.01 B, 28 Emergency Diesel Generator Monthly Surveillance, Attachment 1, Operability Checklist Prior to Removing 28 EOG from Service
• PSL Unit 2 Technical Specifications
• OPS-503, Technical Specification Guidance Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
• None Radiological Protection and RWP Requirements:
• None NRC SRO Adm in JPM A 1 Page 2 of 6 JPM A-1 SRO Page 2

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS - SPECIFIC DIRECTIONS:

• The task you are to perform is: verify Unit 2 Train A equipment OPERABLE and evaluate Technical Specifications.
• The performance level to be used for this JPM is Perform.
• During the performance of the task, I will tell you which steps to simulate or discuss.
• I will provide you with the appropriate cues for steps that are simulated or discussed.
• You may use any approved reference materials normally available in the execution of this task, including logs.
• Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you .

INITIAL CONDITIONS: Unit 2 is operating at 100% power. Engineering has identified a relay issue potentially impacting 28 EOG operability. Engineering has also identified that this only affects the 28 EOG, and does not constitute a common mode failure concern. The Shift Manager is performing an immediate operability determination. The C Charging Pump, C Intake Cooling Water Pump and C Component Cooling Water Pump are currently mechanically and electrically aligned to the B Train . The Desk RCO has completed 2-0SP-59.01 B, Attachment 1, Operability Checklist Prior to Removing 28 EOG from Service. INITIATING CUES: The Shift Manager has declared the 28 EOG INOPERABLE. Review the completed 2-0SP-59.01 B, Attachment 1, and determine the Tech Spec implications and required actions. NRC SRO Admin JPM A1 Page 3 of 6 JPM A-1 SRO Page 3

JOB PERFORMANCE MEASURE ST ART TIME: _ _ __ 2-0SP-59.018, Attachment 1, Operability Checklist Prior to Removing 28 EOG from Service STEP 1: Review 2-0SP-59.01 B, Attachment 1, Operability Checklist Prior to CRITICAL Removing 2B EOG from Service. STEP STANDARD: DETERMINES that 2C Auxiliary Feedwater Pump is removed from SAT service for maintenance and is INOPERABLE. EXAMINER'S CUE: None. UNSAT COMMENTS: STEP 3: Review Unit 2 Technical Specifications for applicable LCOs. CRITICAL STEP STANDARD: IDENTIFIES LCO 3.8.1 .1.b, A.C. Sources (Operating), and determines the following required actions: SAT

• Within 1 hour, perform Surveillance Requirement 4.8.1.1 .a.
• Within 4 hours, restore the 2C AFW Pump OR 2B EOG to OPERABLE status. Otherwise, declare 2B AFW Pump UNSAT INOPERABLE and enter LCO 3.7.1.2, Auxiliary Feedwater System and apply the Tech Spec Action Statement for 2 inoperable AFW pumps EXAMINER'S CUE: None.

EXAMINER'S NOTE: The applicant will find the 2C Auxiliary Feedwater Pump cleared for maintenance. This pump is required because the unit is not in Mode 4 or lower. EXAMINER'S NOTE: Ops Policy 503 for LCO 3/4.8.1 (page 35 of 40) also has supporting guidance for this condition. COMMENTS: NRC SRO Adm in JPM A 1 Page 4 of 6 JPM A-1 SRO Page 4

JOB PERFORMANCE MEASURE STEP 4: Inform the Shift Manager. STANDARD: INFORMS the Shift Manager of applicable Tech Specs and required actions. SAT EXAMINER'S CUE: "This JPM is complete." UNSAT COMMENTS : END OF TASK STOP TIME: _ _ __ NRC SRO Adm in JPM A 1 Page 5 of 6 JPM A-1 SRO Page 5

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK) INITIAL CONDITIONS: Unit 2 is operating at 100% power. Engineering has identified a relay issue potentially impacting 28 EOG operability. Engineering has also identified that this only affects the 28 EOG, and does not constitute a common mode failure concern. The Shift Manager is performing an immediate operability determination . The C Charging Pump, C Intake Cooling Water Pump and C Component Cooling Water Pump are currently mechanically and electrically aligned to the B Train . The Desk RCO has completed 2-0SP-59.01 B, Attachment 1, Operability Checklist Prior to Removing 28 EOG from Service. INITIATING CUES: The Shift Manager has declared the 28 EOG INOPERABLE. Review the completed 2-0SP-59.018 , Attachment 1, and determine the Tech Spec implications and required actions. JPM A-1 SRO Page 6

REVISION NO.: PROCEDURE TITLE:

                                                                                   ~J~F-~~:::-':,:.-../:,;,~:
                                                                                                        . ***f.**.

29 28 EMERGENCY DIESEL GENERATOR MONTHLY ..,. .. t' SURVEILLANCE

                                                                                  ;;,-62 of 89.0 PROCEDURE NO.:                                                                    '~ -*~**                 ~-.~ \.,'
                                                                                                      '*~'.?',_ ,;

2-0SP-59.01 B ST. LUCIE UNIT 2 INITIAL ATTA CHMENT 1 Operability Checklist Prior to Removing 28 EOG from Service (Page 1 of 2) VERIFY following A train equipment and flowpaths are NOT out of service prior to removing the 2B EOG from service: 2A and 2B Boric Acid Pumps, an V-2514 , EMERGENCY BORATE, are powered from the A Side. V-2508 and V-2509, BA Gravity Feed Valves , and V-2504, REFUEL WATER TO CHARGING PUMPS, are powered from the B Side.

• Boration flowpath powered from A side ...::::rh
• Charging pump powered from the 'A side -.:::::!'7--
• PORV Block Valve V1476 , BLOCK VALVE, (may be de-energized

                                                                                           -::f CL and closed in MODES 1, 2 and 3)

• 2A HPSI Pump and flowpath ...:::r lL
• 2A LPSI Pump and flowpath S<L
• 2A Containment Spray Pump and flowpath .::rdL

                                                                                           ,...........lQ_

• 2A Hydrazine Pump
• 2A and 2B Containment Coolers 56L HVE-6A, SBVS EXHAUST FAN, and flowpath ..::SQ_

2A and 2C Auxiliary Feedwater Pumps (2C AFW NO"!" required MODE 4 and below)

• A powered and aligned Component Cooling Water Pump and A header q1L
• A powered and aligned Intake Cooling Water Pump and A header GIL-
• HVE-13A, CONTROL ROOM EMERG FL TR FAN, and A train Control Room Emergency Ventilation System components '"JOZ._
• HVE-9A, ECCS EMERG EXHAUST FAN, and flowpath c:[L,

REVISION NO.: PROCEDURE TITLE : 29 28 EMERGENCY DIESEL GENERATOR MONTHLY PROCEDURE NO.: SURVEILLANCE 2-0SP-59 .01 B ST. LUCIE UNIT 2 ATTACHMENT 1 Operability Checklist Prior to Removing 28 EOG from Service (Page 2 of 2)

• 2A Startup Transformer
• A side A.C. Electrical Distribution required by Tech Specs 3.8.3.1 for MODES 1, 2, 3 and 4, OR Tech Specs 3.8.3.2 for MODES 5 and 6 ~n._
• 2A Emergency Diesel Generator :TYL
• Pressurizer Heaters at least 155 KW in MODES 1, 2 and 3 (Tech Spec Section 3.4.3, Pressurizer, requirement for 150 KW plus 5 KW transformer losses) from emergency power (Backup Heater #1) using Distributed Control System point W943A PRESSZER HEATER ~

PWER 2A, Steam Generator 2A and 28 Heat Rate page 1 - l4L

• A powered Tech Spec Remote Shutdown Instrumentation per Tech Spec 3.3.3.5 for MODES 1, 2 and 3 .(j{L

{]~;(E) The removal of the 28 EOG from serv(ce with Accident Monitoring Instrumentation inoperable is permitted if the actions of Tech Spec 3.3.3.6 and Table 3.3.10 are entered.

• Accident Monitoring Instrumentation per Tech Spec 3.3.3.6 for MODES 1, 2 and 3 as follows:

PT-07-4A1, CNTMT PRESS Ll-1110X, LEVEL (Pressurizer), or UR-01-1 , Pzr Level I Press, r-n (L Y-111 OX, Pressurizer Level) _, ..__

• L9012, DCS Point SIG 2A LEVEL WR, or Ll-9014, 2A SIG WIDE RANGE LEVEL (PACB 2) ~
• LT-07-13A, A CNTMT SUMP LEVEL WIDE RANGE .cm--

Performed By: Reviewed By: tr {kv_ PrinUSign Unit Supervisor (PrinUSign)

                                                                          -::nz_

Initials

                                                                                       -hj~

Da Date JPM A-1 SRO Pa e

1(,Z Y REVISION NO.: PROCEDURE TITLE: PA9E:* 29 28 EMERGENCY DIESEL GENERATOR MONTHLY ... SURVEILLANCE 62 of 89. PROCEDURE NO.: 2-0SP-59 .018 ST. LUCIE UNIT 2 INITIAL ATTACHMENT 1  ; i - ~ .* Operability Checklist Prior to Removing 28 EDG from Service (Page 1 of 2) VERIFY following A train equipment and flowpaths are NOT out of service prior to removing the 2B EOG from service:

                                                       ~
            -                                    Nm$ )
          -  .J2A and 28 Boric Acid Pumps, a~~ EMERGENCY BORATE, are
      < -    ~ewered     from the A Side.
       ,4      V-2508 and V-2509, BA Gravity Feed Valves, and V-2504, REFUEL WATER TO CHARGING PUMPS , are powered from the B Side.

• Boration flowpath powered from A side
• Charging pump powered from the A side
• PORV Block Valve V1476, BLOCK VALVE , (may be de-energized and closed in MODES 1, 2 and 3)
• 2A HPSI Pump and flowpath
• 2A LPSI Pump and flowpath
• 2A Containment Spray Pump and flowpath
• 2A Hydrazine Pump
• 2A and 2B Containment Coolers
• HVE-6A, SBVS EXHAUST FAN , and flowpath 2A and 2C Auxiliary Feedwater Pumps (2C AFW NOT required MODE 4 and below)
• A powered and aligned Component Cooling Water Pump and A header
• A powered and aligned Intake Cooling Water Pump and A header
• HVE-13A, CONTROL ROOM EMERG FLTR FAN, and A train Control Room Emergency Ventilation System components
• HVE-9A, ECCS EMERG EXHAUST FAN , and flowpath

REVISION NO.: PROCEDURE TITLE: P~G~:\?*~,, 29 28 EMERGENCY DIESEL GENERATOR MONTHLY PROCEDURE NO.: SURVEILLANCE 63 of 89 *.' *

                                                                                              -i ~;

2-0SP-59.01 B ST. LUCIE UNIT 2 JNITiAL _ 1 ATTACHMENT 1 Operability Checklist Prior to Removing 28 EOG from Service (Page 2 of 2)

• 2A Startup Transformer
• A side A.C. Electrical Distribution required by Tech Specs 3.8.3.1 for MODES 1, 2, 3 and 4, OR Tech Specs 3.8.3.2 for MODES 5 and 6 ~ifL
• 2A Emergency Diesel Generator
• Pressurizer Heaters at least 155 KW in MODES 1, 2 and 3 (Tech Spec Section 3.4.3, Pressurizer, requirement for 150 KW plus 5 KW transformer losses) from emergency power (Backup Heater #1) using Distributed Control System point W943A PRESSZER HEATER PWER 2A, Steam Generator 2A and 28 Heat Rate page 1
• A powered Tech Spec Remote Shutdown Instrumentation per Tech Spec 3.3 .3.5 for MODES 1, 2 and 3

{]OXE) The removal of the 28 EOG from serv(ce with Accident Monitoring Instrumentation inoperable is permitted if the actions of Tech Spec 3.3.3.6 and Table 3.3.10 are entered.

• Accident Monitoring Instrumentation per Tech Spec 3.3.3.6 for '

MODES 1, 2 and 3 as follows:

• PT-07-4A1 I CNTMT PRESS Ll-1110X, LEVEL (Pressurizer), or UR-01-1 , Pzr Level I Press,  :::JL_

(L Y-111 OX , Pressurizer Level) L9012 , DCS Point S/G 2A LEVEL WR, or Ll-9014, 2A SIG WIDE RANGE LEVEL (PACB 2)

• LT-07-13A, A CNTMT SUMP LEVEL WIDE RANGE Performed By: _ _ _ _.,.~'- ---{?o ......._,=---~""""--------

U- Print/Sign Initials Reviewed By:

                  --------------------~

Unit Supervisor (Print/Sign) Date JPM A-1 SRO Page 10

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK) INITIAL CONDITIONS: Unit 2 is operating at 100% power. Engineering has identified a relay issue potentially impacting 28 EOG operability. Engineering has also identified that this only affects the 28 EOG, and does not constitute a common mode failure concern. The Shift Manager is performing an immediate operability determination. The C Charging Pump, C Intake Cooling Water Pump and C Component Cooling Water Pump are currently mechanically and electrically aligned to the B Train . The Desk RCO has completed 2-0SP-59.01 B, Attachment 1, Operability Checklist Prior to Removing 2B EOG from Service. INITIATING CUES: The Shift Manager has declared the 2B EOG INOPERABLE. Review the completed 2-0SP-59.01 B, Attachment 1, and determine the Tech Spec implications and required actions. T.S. 3.8.1.1 Action b: A required redundant feature , 2C AFW pump, is out of service during the cross train equipment verification. Within 4 hours , restore the 2C AFW Pump QB 28 EOG to OPERABLE status. Otherwise, declare 2B AFW Pump INOPERABLE and enter LCO 3.7.1.2, Auxiliary Feedwater System and apply the Tech Spec Action Statement for 2 inoperable AFW pumps (be in HOT STANDBY within 6 hours and HOT SHUTDOWN within the following 6 hours). JPM A-1 SRO Page 11

ST. LUC IE PLANT OPS-503 OPERATIONS DEPARTMENT POLICY REVISION 61 TECHNICAL SPECIFICATION GUIDANCE Page 34 of 39 Operational Gu idance for Section 3/4.8 3/4.8.1, 3/4 .8.2 , and 3/4 .8.3 AC Sources , DC Sources , and Onsite Power Distribution Systems

1. Station Blackout Cross Tie While not specifically addressed in the Technical Specifications, the Station Blackout Cross tie is a component of the Risk Assessment Matrix. As such it is considered a risk significant component. The guidance of ADM-17.16 , Implementation of the Configuration Risk Management Program, Section 6.1.20 should be used whenever a Station Blackout Cross tie breaker is removed from service.

2. Redundant Equipment Operability (Action 3.8.1 .1.b}

A. When a Diesel Generator is declared inoperable, Then one of the required activities is to verify that all required systems , subsystems , trains , components, and devices thaf depend on the remaining OPERABLE Diesel Generator as a source of emergency power are also OPERABLE. Redundant equipment is defined in the applicable Diesel Generator surveillance procedure. If a redundant feature is found inoperable, during the cross train equipment verification, within four (4) hours, restore the inoperable component, or declare the redundant component supported by the inoperable diesel inoperable , and enter that feature 's TS LCO requirements .

8. If a LCO for a system, subsystem, train, component, or device does NOT explicitly require the ass.ociated Diesel Generator to be operable to satisfy 1hat LCO, Then:

1. Equipment is not inoperable solely due to Diesel Generator inoperability, when powered from the preferred off-site power source . As long as its required redundant counterpart is operable .

2. Therefore, when only a Diesel Generator is inoperable, it suffices to enter only the action 3.8.1 .1. b.

3. Off-Site Power Availability Determination (Surveillance 4.8.1 .1.1.a)

Determining the availability of off-site power to satisfy Technical Specification Surveillance Requirement 4.8 .1.1.1.a is accomplished via use of the sync plug on RTGB-101/201 AND by verifying 4160V breaker alignment by referencing , as needed, 1/2-0SP-100.xx (Tuesday Dayshift). Initial Documentation for successful completion of the surveillance will be in the narrative logs. Subsequent documentation, at a minimum , will be in the data logger. JPM A-1 SRO Page 12

PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7 .1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with :

a. Two feedwater pumps, each capable of being powered from separate OPERABLE emergency busses, and

b. One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY: MODES 1, 2, and 3. ACTION:

a. With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours.

b. With two auxiliary feedwater pumps inoperable be in at least HOT STANDBY within 6 hours and in HOT SHUTDOWN within the following 6 hours.

c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a. At least once per 31 days by:

1. Verifying that each valve (manual , power-operated , or automatic) in the flow path that is not locked , sealed , or otherwise secured in position, is in its correct position.

ST. LUCIE - UNIT 2 314 7-4 Amendment No . ~. 146 JPM A-1 SRO Page 13

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS <Continued)

b. At least once per 18 months during shutdown by:

1. Verifying that each automatic valve in the flowpath path actuates to its correct position upon receipt of an auxiliary feedwater actuation test signal.

2. Verifying that each pump starts automatically upon receipt of an auxiliary feedwater actuation test signal.

c. Following an extended cold shutdown (30 days or longer) and prior to entering MODE 2, a flow test shall be performed to verify the normal flow path from the condensate storage tank (CST) to the steam generators.

d. By verifying the developed head of each AFW pump at the flow test point is greater than or equal to the required developed head when tested in accordance with the lnservice Testing Program. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 when testing the steam turbine-driven AFW pump and this Surveillance must be performed within 24 hours after entering MODE 3 and prior to entering MODE 2.

ST. LUCIE - UNIT 2 3/4 7-5 Amendment No. 146 JPM A-1 SRO Page 14

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.G. SOURCES OPERATING LIMITING CONDITION FOR OPERATIO N 3.8.1.1 As a minimum, the following AC . electrical power sources shalt be OPERABLE:

a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system , and

b. Two separate and independent diesel generators, each with :

1. Two separate engine-mounted fuel tanks containing a minimum volume of 200 gallons of fuel each ,

2. A separate fuel storage system containing a minimum volume of 42,500 gallons of fuel, and

3. A separate fuel transfer pump.

APPLICABILITY: MODES 1, 2, 3, and 4. ACTION:

a. With one offsite circuit of 3.8.1.1.a inoperable, except as provided in Action f.

below, demonstrate the OPERABILITY of the remaining AC . sources by performing Surveillance Requirement 4.8.1 .1.1.a within 1 hour and at least once per 8 hours thereafter. Restore the offsite circuit to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and COLD SHUTDOWN within the following 30 hours.

b. With one diesel generator of 3.8.1.1.b inoperable, demonstrate the OPERABILITY of the AC. sources by performing Surveillance Requirement 4.8.1.1.1 .a within 1 hour and at least once per 8 hours thereafter; and if the EOG became inoperable due to any cause other than an inoperable support system , an independently testable component, or preplanned preventative maintenance or testing, demonstrate the OPERABILITY of the remaining OPERABLE EOG by performing Surveillance Requirement 4.8.1 .1.2a.4 within 8 hours, unless it can be confirmed that the cause of the inoperable EOG does not exist on the remaining EOG*; restore the diesel generator to OPERABLE status within 14 days or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. Additionally , within 4 hours from the discovery of concurrent inoperability of required redundant feature(s) (including the steam driven auxiliary feed pump in MODE 1, 2, and 3) ,

declare required feature(s) supported by the inoperable EOG inoperable if its redundant required feature(s) is inoperable.

• '--'rthe absence of any common-cause failure cannot be confirmed , this test shall be
• completed regardless of when the inoperable EOG is restored to OPERABILITY.

ST. LUCIE - UNIT 2 3/4 8-1 Amendment No. aa, ~. +s, .++a,

                                                                        ~. 163 JPM A-1 SRO Page 15

SECTION NO.: PAGE: TITLE: TECHNICAL SPECIFICATIONS 3/4.8 BASES ATTACHMENT 10 OF ADM-25.04 3 of 9 REVISION NO.: ELECTRICAL POWER SYSTEMS 5 ST. LUCIE UNIT 2 BASES FOR SECTION 3/4.8 3/4.8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES and ONSITE POWER DISTRIBUTION SYSTEMS The OPERABILITY of the A.C . and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety related equipment required for 1) the safe shutdown of the facility and 2) the mitigation and control of accident conditions within the facility. The minimum specified independent and redundant A.C . and D.C. power sources and distribution systems satisfy the requirements of General Design Criteria 17 of Appendix "A" to 10 CFR 50. The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation. The OPERABILITY of the power sources are consistent with the initial condition assumptions of the safety analyses and are based upon maintaining at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss of offsite power and single failure of the other onsite A.C . source. The A.C . and D.C. source allowable out-of-service times are based on Regulatory Guide 1.93, "Availability of Electrical Power Sources," December 1974. When one diesel generator is inoperable , there is an additional requirement to check that all required systems , subsystems, trains , components and devices (i.e ., redundant features) , that depend on the remaining OPERABLE diesel generator as a source of emergency power, are also OPERABLE, and that the steam-driven auxiliary feedwater pump is OPERABLE. These redundant required features are those that are assumed to function to mitigate an accident, coincident with a loss of offsite power, in the safety analysis, such as the emergency core cooling system and auxiliary feedwater system . Upon discovery of a concurrent inoperability of required redundant features the feature supported by the inoperable EOG is declared inoperable. Thus plant operators will be directed to supported feature TS action requirements for appropriate remedial actions for the inoperable required features . JPM A-1 SRO Page 16

SECTION NO.: PAGE: TITLE: TECHNICAL SPECIFICATIONS 3/4.8 BASES ATTACHMENT 10 OF *AOM-25 .04 4 of 9 REVISION NO.: ELECTRICAL POWER SYSTEMS 5 ST. LUCIE UNIT 2 3/4.8 ELECTRICAL POWER SYSTEMS (continued) I BASES (continued) 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES and ONSITE POWER DISTRIBUTION SYSTEMS (continued) The four hour completion time upon discovery that an opposite train required feature is inoperable is to provide assurance that a loss of offsite power, during the period that a EOG is inoperable , does not result in a complete loss of safety function of critical redundant required features. The four hour completion time allows the operator time to evaluate and repair any discovered inoperabilities. This completion time also allows for an exception to the normal "time zeron for beginning the allowed outage time. "clock." The four hour completion time only begins on discovery that both an inoperable EOG exists and a required feature on the other train is inoperable. TS 3.8.1 .1, ACTION "b" provides an allowed outage/action completion time (AOT) of up to 14 days to restore a single inoperable diesel generator to operable status. This AOT is based on the findings of a deterministic and probabilistic safety analysis and is referred to as a "risk-informed" AOT. Entry into this action requires that a risk assessment be performed in accordance with the Configuration Risk Management Program (CRMP), which is described in the Administrative Procedure that implements the Maintenance Rule pursuant to 10 CFR 50.65. All EOG inoperabilities must be investigated for common-cause failures regardless of how long the EOG inoperability persists. When one diesel generator is inoperable, required ACTIONS 3.8.1.1.b and 3.8.1 .1.c provide an allowance to avoid unnecessary testing of EOGs. If it can be determined that the cause of the inoperable EOG does not exist on the remaining OPERABLE EOG, then SR 4.8.1 .1.2.a.4 does not have to be performed . Eight (8) hours is reasonable to confirm that the OPERABLE EOG is not affected by the same problem as the inoperable EOG. If it cannot otherwise be determined that the cause of the initial inoperable EOG does not exist on the remaining EOG, then satisfactory performance of SR 4.8.1.1.2.a.4 suffices to provide assurance of continued OPERABILITY of that EOG . If the cause of the initial inoperability exists on the remaining OPERABLE EOG , that EOG would also be declared inoperable upon discovery, and ACTION 3.8.1.1.e would be entered . Once the failure is repaired (on either EOG) , the common-cause failure no longer exists. JPM A-1 SRO Page 17

• FPL St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE PERFORM RCS INVENTORY BALANCE - UNIT 2 HLC 22 NRC RO Admin JPM A2 NRC RO Admin JPM A2 Page 1of10 JPM A-2 RO Page 1

JOB PERFORMANCE MEASURE Task: Given a set of conditions, perform a Reactor Coolant System Inventory Balance for Unit 2. Faulted JPM? No Facility JPM #: NIA KIA: G2.1 .7 Ability to evaluate plant performance and make operational judgments based on operating characteristics ; reactor behavior, and instrument interpretation. KIA Rating(s): 4.4/4.7 Duty Area(s): N/A Task Information: 07200105 Task Standard: Perform a Reactor Coolant System Inventory Balance for Unit 2. Evaluation Location: Performance Level: Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

• 2-0SP-01 .03, Reactor Coolant System Inventory Balance, Revision 25 Validation Time: 10 minutes Time Critical: NO Tools/Equipment/Procedures Needed:
• 2-0SP-01 .03, Reactor Coolant System Inventory Balance Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
• None Radiological Protection and RWP Requirements:
• None NRC RO Admin JPM A2 Page 2of10 JPM A-2 RO Page 2

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

• The task you are to perform is: perform a Reactor Coolant System Inventory Balance for Unit 2.
• The performance level to be used for this JPM is Perform.
• During the performance of the task, I will tell you which steps to simulate or discuss.
• I will provide you with the appropriate cues for steps that are simulated or discussed.
• You may use any approved reference materials normally available in the execution of this task, including logs.
• Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you .

INITIAL CONDITIONS:

• Unit 2 is operating at 100% power
• The Unit Supervisor has entered 2-AOP-01 .08 , RCS Leakage Abnormal Operation, due to suspected RCS leakage
• RS-26-25 , Containment Particulate , EAP-541, is in ALERT
• RS-26-26, Containment Particulate, PAP-551, is in ALERT
• The zinc injection system is shutdown
• Stable plant conditions have been maintained throughout the duration of the measurement period
• Pl-VIEW and the RCS Leak Rate Calculator are unavailable INITIATING CUES:

To satisfy the requirements of 2-AOP-01 .08 , RCS Leakage Abnormal Operation, Step 4.2.1.3, the Unit Supervisor has directed you to perform a one hour manual RCS leak rate determination per 2-0SP-01 .03 , Reactor Coolant System Inventory Balance, Attachment 4, Manual Leak Rate Calculation. The following readings are observed at the beginning and end of the measurement period : Parameter (@ 0100 (@.0200 RCS Tcold 550.4°F 550.4°F Boric Acid Integrator 0.0 Qallons 0.0 gallons Primarv Makeup Water lnteQrator 0.0 gallons 0.0 gallons Zinc lniection Tank Level n/a n/a VCT Level 54.2% 51 .7% Pressurizer Level 63.0% 63.2% Quench Tank Level 65.0% 65.1% Charging Pump Seal Tank Level 2A: 1 inch 2B:2inches 2C: 1 inch NRC RO Admin JPM A2 Page 3 of 10 JPM A-2 RO Page 3

JOB PERFORMANCE MEASURE START TIME: _ _ __ 2-0SP-01.03, Reactor Coolant System Inventory Balance Attachment 4, Manual Leak Rate Calculation STEP 1 (1&2): CALCULATE the RCS Leak rate using Pl-VIEW as follows: SAT STANDARD: DETERMINES that Pl-VIEW is unavailable. EXAMINER'S CUE: Provided in Initial Conditions. This UNSAT eliminates use of Step 2 in Att. 4. COMMENTS: STEP 2 (3): lf Pl-VIEW is un-available, THEN RECORD data using DCS . A RECORD results in Hand Cale Section. SAT STANDARD: DETERMINES that Pl-VIEW is unavailable, and that data is to be recorded in the Hand Cale Section. UNSAT EXAMINER'S CUE: Provided in Initial Conditions. COMMENTS: STEP 3 (4): RECORD results in Hand Cale Section. SAT STANDARD: RECORDS all data provided in Initiating Cue. EXAMINER'S CUE: None UNSAT COMMENTS: NRC RO Admin JPM A2 Page 4 of 10 JPM A-2 RO Page 4

JOB PERFORMANCE MEASURE STEP 4 (5): DETERMINE Total Leakage of RCS by COMBINING differences of CRITICAL the following : STEP

• BA Integrator = 0.0 gallons
• PMW Integrator = 0.0 gallons
• Zinc Injection = 0.0 (or N/A, system not in service) gallons SAT
• VCT level = -84.5 (2: 0.1) gallons
• Pzr Level = +13.408 (2: 0.1) gallons Total Leakage =-71 .092 (~ 0.2} gallons UNSAT STANDARD: RECORDS applicable data from Step 4 table and calculates Total Leakage .

EXAMINER'S CUE: None EXAMINER'S NOTE: Tolerance allowed for rounding calculated values. COMMENTS: NRC RO Admin JPM A2 Page 5of10 JPM A-2 RO Page 5

JOB PERFORMANCE MEASURE STEP 5 (6) : DETERMINE Identified Leakage by COMBINING differences of the CRITICAL following components: STEP

• QT Level =- 1.65 ~ 0.1) gallons
• Chg Pp Seal Tanks =-2.36 gallons
• Attachment 2 (if used) = 0.0 (or N/A) gallons _ _ SAT Identified Leakage = -4.01 ~ 0.1) gallons STANDARD: RECORDS applicable data from Step 4 table and calculates _ _ UNSAT Identified Leakage.

EXAMINER'S CUE: None EXAMINER'S NOTE: Tolerance allowed for rounding calculated values. EXAMINER'S NOTE: Charging Pump Seal Tank levels are reported by the SNPO as inches change over an hour. COMMENTS: STEP 6 (7) : DETERMINE Unidentified Leakage by SUBTRACTING Identified CRITICAL Leakage from Total Leakage. STEP

• Total Leakage =-71 .092 ~ 0.1) gallons
• Identified Leakage = -4.01 ~ 0.1) gallons
• Unidentified Leakage =-67 .082 ~ 0.2) gallons SAT STANDARD: CALCULATES Unidentified Leakage.

_ _ UNSAT EXAMINER'S CUE: None EXAMINER'S NOTE: Tolerance allowed for rounding calculated values. COMMENTS: NRC RO Adm in JPM A2 Page 6of 10 JPM A-2 RO Page 6

JOB PERFORMANCE MEASURE STEP 7 (8) : DETERMINE Unidentified Leakage rate by DIVIDING Unidentified CRITICAL Leakage value in Attachment 4 , Step 7 by elapsed time in minutes. STEP

• Unidentified Leakage = -67.082 (:!: 0.2) gallons
• Elapsed Time = 60 minutes
• Unidentified Leakage Rate = -1 .118 et 0.02) gpm _ _ SAT STANDARD: CALCULATES Unidentified leakage Rate. _ _ UNSAT EXAMINER'S CUE: None EXAMINER'S NOTE: Tolerance allowed for rounding calculated values.

COMMENTS: STEP 8 (9) : DETERMINE Identified Leakage rate by DIVIDING Identified CRITICAL Leakage value in Attachment 4, Step 6 by elapsed time in minutes. STEP

• Identified Leakage = -4.01 (:!: 0.1) gallons
• Elapsed Time = 60 minutes
• Identified Leakage Rate = -0.067 (:!: 0.01) gpm _ _ SAT STANDARD: CALCULATES Identified Leakage Rate. UNSAT EXAMINER'S CUE: None EXAMINER'S NOTE: Tolerance allowed for rounding calculated values.

COMMENTS: NRC RO Admin JPM A2 Page 7 of1 0 JPM A-2 RO Page 7

JOB PERFORMANCE MEASURE 2-0SP-01.03, Main Body, Section 4.1, Steps 7 and 8 STEP 9 (4.1.7):RECORD Identified and Unidentified Leakage Rate.

• Calculation Start: Date: Today Time: 0100 SAT
• Calculation Stop: Date: Today Time: 0200
• Identified Leakage Rate = -0.067 (+ 0.001) gpm
• Unidentified Leakage Rate = -1.118 (+ 0.02) gpm UNSAT STANDARD: RECORDS Identified and Unidentified Leakage Rates calculated in Attachment 4.

EXAMINER'S CUE: None EXAMINER'S NOTE: Tolerance allowed for rounding calculated values. COMMENTS: STEP 10 (4.1 .8) : VERIFY RCS leakage rates are within Technical CRITICAL Specification 3.4.6.2 requirements as follows: STEP STANDARD: RECORDS surveillance results, indicating Identified Leakage Rate is SAT and Unidentified Leakage Rate is UNSAT. SAT EXAMINER'S CUE: None. UNSAT COMMENTS: NRC RO Admin JPM A2 Page 8of10 JPM A-2 RO Page 8

JOB PERFORMANCE MEASURE STEP 11 (4.1.8.A): IF RCS Leakage exceeds 1 GPM, THEN REFER TO 2-AOP-01.08, RCS Leakage Abnormal Operations. SAT STANDARD: INFORMS Unit Supervisor:

• Identified Leakage Rate is 0.067 gpm, and is SAT UNSAT
• Unidentified Leakage Rate is 1.118 gpm, and is UNSAT
• REFER TO 2-AOP-01.08, RCS Leakage Abnormal Operations EXAMINER'S CUE: None.

COMMENTS: STOP TIME: _ _ __ NRG RO Admin JPM A2 Page 9 of 10 JPM A-2 RO Page 9

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

• Unit 2 is operating at 100% power
• The Unit Supervisor has entered 2-AOP-01 .08, RCS Leakage Abnormal Operation, due to suspected RCS leakage
• RS-26-25, Containment Particulate, EAP-541, is in ALERT
• RS-26-26, Containment Particulate, PAP-551, is in ALERT
• The zinc injection system is shutdown
• Stable plant conditions have been maintained throughout the duration of the measurement period
• Pl-VIEW and the RCS Leak Rate Calculator are unavailable INITIATING CUES:

To satisfy the requirements of 2-AOP-01 ,08, RCS Leakage Abnormal Operation, Step 4.2.1.3, the Unit Supervisor has directed you to perform a one hour manual RCS leak rate determination per 2-0SP-01.03, Reactor Coolant System Inventory Balance, Attachment 4, Manual Leak Rate Calculation. The following readings are observed at the beginning and end of the measurement period: Parameter (@ 0100 (@0200 RCS Tcold 550.4°F 550.4°F Boric Acid lnteqrator 0.0 gallons 0.0 qallons Primary Makeup Water Integrator 0.0 gallons 0.0 gallons Zinc lniection Tank Level n/a n/a VCT Level 54.2% 51.7% Pressurizer Level 63.0% 63.2% Quench Tank Level 65.0% 65.1% Charging Pump Seal Tank Level 2A: 1 inch 28:2inches

            , /   -                                         2C: 1 inch
             \~

JPM A-2 RO Page 10

REVISION NO. : PROCEDUR E TIT LE: PAGE: 12 RCS LEAKAGE ABNORMAL OPERATIONS 1Oof61 PROCEDURE NO.: 2-AOP-01 .08 ST. LUCIE UNIT 2 I1NSTRUCTIONS I ICONTINGENCY ACTIO NS I 4.2.1 General Actions (continued) NOTE Thumb rule for estimating leak rate is that 1" level rise on Ll-07-6, RX CAVITY LEVEL, on RTGB-205 is about 46 gallons. DETERMINE RCS leak rate by any of the following methods:

• ESTIMATE leak rate based on gross charg ing-letdown mismatch .
• ESTIMATE leak rate based on abnormal tank or sump level rise rates .

CALCULATE leak rate per 2-0SP-01 .03, Reactor Coolant System Inventory Balance. JPM A-2 RO Page 11

REVISION NO .: PROCEDURE TITLE : PAGE: 25 REACTOR COOLANT SYSTEM INVENTORY BALANCE 28 of 31 PROCEDURE NO.: 2-0SP-01 .03 ST. LUCIE UNIT 2 INITIAL ATTACHMENT 4 Manual Leak Rate Calculation (Page 1 of 4)

1. CALCULATE the RCS Leak Rate using Pl-VIEW as follows.

2. IF Pl-View is available, THEN PERFORM the following:

A. SELECT START at RO LAN workstation. B. SELECT ALL PROGRAMS C. SELECT Pl-View. D. CLICK Pl-View (1) ENSURE Pl Server PSL-ERDADS is selected. (2) SET START/END as desired (3) SELECT desired sample increment using slide bar. (4) SELECT Get Data. E. RECORD end and start time data for desired leak rate duration. F. CALCULATE and RECORD differences. G. ENTER the data in the Hand Calculated Section . H. CLICK on the Hand Calculated Section Results , Save Data button. I. VERIFY that no action levels are displayed .

3. IF Pl-View is un-available, THEN RECORD data using DCS A. RECORD results in Hand Cale Section .

4. IF Pl-View and DCS are unavailable OR at US/SM discretion, THEN RECORD data using RTGB indications.

• RECORD results in Hand Cale Section .

JPM A-2 RO Page 12

REVISION NO.: PROCEDURE T ITLE: PAGE: 25 REACTOR COOLANT SYSTEM INVENTORY BALANCE 29 of 31 PROCEDURE NO.: 2-0SP-01 .03 ST. LUCIE UNIT 2 ATTACHMENT 4 Manual Leak Rate Calculation (Page 2 of 4)

4. (continued)

Initial Conditions Final Conditions Notes Difference Date :- -I- -I- - Date: __/__/__ 2 hour minimum desired unless not at steady state .

                                                                                                           ' ;./      Min Time:                     Time:                                  (Chg . Pump data excluded)

(Attachment 2 data excluded) T COLD: OF TcoLD: OF Held constant (< .1°F) ** OF B.A. B.A. Integrator: Integrator: Always Negative - gal.

                                                                                        ...... \.

PMW PMW Integrator: Integ rat or: Always Negative - gal. Notify SNPO to mark Notify SNPO to mark Zinc Injection Tank Zinc Injection Tank 60 minute minimum required .

                                                                                                         -             gal.

gauge glass (LG-02-2) gauge glass (LG-02-2) Always negative (gal) (gal)

                                                                 + if final > initial VCT Level:            %   VCT Level:                       %     - if final < initial                   ( )            gal.
                                            \                    (%change x 33.8 Qal. per%)
                                          ~
                                                                 + if final > initial Pzr Level:            %   Pzr Level :                      %     - if final < initial                   ( )            gal.
                                          ..............         (% chanqe x 67.04 gal. per%)

Always Negative Q.T. Level :  % Q.T. Level:  % NIA if final < initial - gal. (%change x 16.5 qaf. per%) 30 minute minimum required . Notify SNPO to mark Notify SNPO to mark Always Negative. Seal Tank level for ALL Seal Tank level for ALL N/A if final < initial - gal. available Chg . Pps .

• available Chg. Pps . *

                                                                           =

(1 inch 0.59 gal.)

• Data should be recorded for any pump hydraulically connected to the system .

** If Tcold is NOT held constant, consideration should be given to repeating calculation when conditions permit.

JPM A-2 RO Page 13

REVISION NO.: PROCEDURE TITLE: PAGE: 25 REACTOR COOLANT SYSTEM INVENTORY BALANCE 30 of 31 PROCEDURE NO.: 2-0SP-01 .03 ST. LUCIE UNIT 2 ATTACHMENT 4 Manual Leak Rate Calculation (Page 3 of 4)

5. DETERMINE Total Leakage of RCS by COMBINING differences of the following :

• B.A. Integrator gal.
• PMW Integrator gal.
• Zinc Injection gal.
• VCT Level ( ) gal.
• Pzr Level ( ) gal.

Total Leakage gal.

6. DETERMINE Identified Leakage by COMBINING differences of the following components:

• Q.T. Level _ _ _ gal.
• Chg . Pp . Seal Tanks _ _ _gal.
• Attachment 2 (if used) _ _ _gal.

Identified Leakage = _ _ _gal.

7. DETERMINE Unidentified Leakage by SUBTRACTING Identified Leakage from Total Leakage .

• Total Leakage () _ _ _ gal.
• Identified Leakage -( ) gal.
• Unidentified Leakage = ( )_ _ _ gpm JPM A-2 RO Page 14

REVISION NO.: PROCEDURE TITLE: PAGE: 25 REACTOR COOLANT SYSTEM INVENTORY BALANCE 31 of 31 PROCEDURE NO .: 2-0SP-01 .03 ST. LUCIE UNIT 2 INITIAL ATTACHMENT 4 Manual Leak Rate Calculation (Page 4 of 4)

8. DETERMINE Unidentified Leakage rate by DIVIDING Unidentified Leakage value in Attachment 4, Step 7 by elapsed time in minutes.

• Unidentified Leakage ._ _ _ gal.
• Elapsed time _ _ _ min .

Unidentified Leakage rate =___gpm

9. DETERMINE Identified Leakage rate by DIVIDING Identified Leakage value in Attachment 4, Step 6 by elapsed time in minutes .

• Identified Leakage _ _ _g,al.
• Elapsed time _ _ _ min .

Identified Leakage rate =___gpm JPM A-2 RO Page 15

REVISION NO.: PROCEDURE TITLE: PAGE: 25 REACTOR COOLANT SYSTEM INVENTORY BALANCE 29 of 31 PROCEDURE NO.: 2-0SP-01 .03 ST. LUCIE UNIT 2 ~ - ATTACHMENT 4 Manual Leak Rate Calculation (Page 2 of 4)

4. (continued)

Initial Conditions Final Conditions Notes Difference 2 hour minimum desired Date:- -I- -I- - Date:_ _, __! __ unless not at steady state. bO Min Time: Olbl) Time: 6L-o 12) (Chg. Pump data excluded) (Attachment 2 data excluded) TcoLO: 5$1>. '1 OF TcoLO: SS'l>. &-/ OF Held constant (< .1°F) ** Q OF B.A. B.A. Integrator: D Integrator: 0 Always Negative

                                                                                        -       0       gal.
                                                                                   ~

PMW PMW Integrator: 0 Integrator: 0 Always Negative - (") gal. Notify SNPO to mark Notify SNPO to mark Zinc Injection Tank Zinc Injection Tank 60 minute minimum required. gauge glass (LG-02-2) gauge glass (LG-02-2) Always negative

                                                                                        -     0         gal.

(gal) (gal)

                                                           + if final > initial VCT Level:    9-1. 2-    %    VCT Level: SJ. i       %     - if final < initial         (- ) 8'1-~ gal.

(%change x 33.8 gal. per%)

                                                           + if final > initial Pzr Level: l:. 3        %    Pzr Level: l. S. l.     %    - if final < initial         (+-)  Is . '+l?Bgal.

1 (%change x 67.04 gal. per%) Q.T. Level : (pS'  % Q.T. Level: ,5. I  % Always Negative N/A if final < initial (%change x 16.5 gal. per%) (

                                                                                         - \.(,c.;      gal.

30 minute minimum required. Notify SNPO to mark Notify SNPO to mark Always Negative. - 2 . 3~ N/A if final < initial ~** Seal Tank level for ALL Seal Tank level for ALL gal. available Chg . Pps.

• available Chg . Pps. *

(1 inch = 0.59 gal.)

• Data should be recorded for any pump hydraulically connected to the system.

** If Tcold is NOT held constant, consideration should be given to repeating calculation when conditions permit.

JPM A-2 RO Page 16

REVISION NO.: PROCEDURE TITLE: PAGE: 25 REACTOR COOLANT SYSTEM INVENTORY BALANCE 30 of 31 PROCEDURE NO.: 2-0SP-01 .03 ST. LUCIE UNIT 2 ATTACHMENT 4 Manual Leak Rate Calculation (Page 3 of 4)

5. DETERMINE Total Leakage of RCS by COMBINING differences of the following :

• B.A Integrator 0 gal.
• PMW Integrator D gal.
• Zinc Injection 0 gal.
• VCT Level (- ) 84./. -r gal.
• Pzr Level (* ) n. '-I CBgal.

Total Leakage - "7 I .0'11-gal.

6. DETERMINE Identified Leakage by COMBINING differences of the following components :

• Q.T. Level - i.r..r gal.
• Chg . Pp. Seal Tanks - 2. 3l. gal.

                                                                        ~) (l,.

• Attachment 2 (if used) - gal.

Identified Leakage =-i* ~' gal.

7. DETERMINE Unidentified Leakage by SUBTRACTING Identified Leakage from Total Leakage.

• Total Leakage (- ) 7 /. l>Ci~ al.
• Identified Leakage _ ( - ) '1.D I gal.
• Unidentified Leakage = (- ) ~/.tf>bgpm JPM A-2 RO Page 17

REVISION NO.: PROC EDURE TITLE: PAGE : 25 REACTOR COOLANT SYSTEM INVENTORY BALANCE 31 of 31 PROCEDURE NO. : 2-0SP-01 .03 ST. LUCIE UNIT 2 INITIAL ATTACHMENT 4 Manual Leak Rate Calculation (Page 4 of 4)

8. DETERMINE Unidentified Leakage rate by DIVIDING Unidentified Leakage value in Attachment 4, Step 7 by elapsed time in minutes.

• Unidentified Leakage
• Elapsed time bO min .

Unidentified Leakage rate = /. 11& gpm

9. DETERMINE Identified Leakage rate by DIVIDING Identified Leakage value in Attachment 4 , Step 6 by elapsed time in minutes.

• Identified Leakage - l/. \:)I gal.
• Elapsed time bo min.

Identified Leakage rate =.Ob 1 gpm JPM A-2 RO Page 18

GFPL St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE PERFORM RCS INVENTORY BAbANCE - UNIT 2 AND EVALUATE TECHNICAL SPECIFICATIONS HLC 22 NRC SRO Admin JPM A2 NRC SRO Admin JPM A2 Page 1 of 11 JPM A-2 SRO Page 1

JOB PERFORMANCE MEASURE Task: Given a set of conditions , perform a Reactor Coolant System Inventory Balance for Unit 2, and evaluate Technical Specifications. Faulted JPM? No Facility JPM #: N/A KIA: G2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. KIA Rating(s): 4.4/4.7 Duty Area(s): N/A Task Information: 07200105 Task Standard: Perform a Reactor Coolant System Inventory Balance for Unit 2, and evaluate Technical Specifications. Evaluation Location: Performance Level: Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

• 2-0SP-01.03, Reactor Coolant System Inventory Balance, Revision 25
• 2-AOP-01 .08, RCS Leakage Abnormal Operation, Revision 12
• Technical Specifications LCO 3.4.6.2, RCS Leakage Validation Time: 15 minutes Time Critical: NO Tools/Equipment/Procedures Needed:
• 2-0SP-01.03, Reactor Coolant System Inventory Balance
• 2-AOP-01 .08, RCS Leakage Abnormal Operation
• Technical Specifications LCO 3.4.6.2, RCS Leakage Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
• None Radiological Protection and RWP Requirements:
• None NRC SRO Admin JPM A2 Page 2 of 11 JPM A-2 SRO Page 2

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

• The task you are to perform is: perform a Reactor Coolant System Inventory Balance for Unit 2.
• The performance level to be used for this JPM is Perform .
• During the performance of the task, I will tell you which steps to simulate or discuss .
• I will provide you with the appropriate cues for steps that are simulated or discussed .
• You may use any approved reference materials normally available in the execution of this task, including logs.
• Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you .

INITIAL CONDITIONS:

• Unit 2 is operating at 100% power
• The Unit Supervisor has entered 2-AOP-01 .08, RCS Leakage Abnormal Operation , due to suspected RCS leakage
• RS-26-25, Containment Particulate, EAP-541 , is in ALERT
• RS-26-26, Containment Particulate, PAP-551 , is in ALERT
• The zinc injection system is shutdown
• Stable plant conditions have been maintained throughout the duration of the measurement period
• Pl-VIEW and the RCS Leak Rate Calculator are unavailable INITIATING CUES:

To satisfy the requirements of 2-AOP-01 ,08, RCS Leakage Abnormal Operation, Step 4.2.1.3, the Unit Supervisor has directed you to perform a one hour manual RCS leak rate determination per 2-0SP-01 .03, Reactor Coolant System Inventory Balance, Attachment 4, Manual Leak Rate Calculation. Also, determine any required actions based on the results of the leak rate calculation , including any related time constraints. The following readings are observed at the beginning and end of the measurement period : Parameter ~/ (@ 0100 @0200 RCS Tcold 550.4°F 550.4°F Boric Acid Integrator 0.0 gallons 0.0 gallons Primary Makeup Water lnteQrator 0.0 Qallons 0.0 gallons Zinc Injection Tank Level n/a n/a VCT Level 54.2% 51.7% Pressurizer Level 63.0% 63.2% Quench Tank Level 65.0% 65.1% Charging Pump Seal Tank Level 2A: 1 inch 2B: 2inches 2C: 1 inch - NRC SRO Admin JPM A2 Pa ge 3 of 11 JPM A-2 SRO Page 3

JOB PERFORMANCE MEASURE START TIME: _ _ __ -- 2-0SP-01.03, Reactor Coolant System Inventory Balance Attachment 4, Manual Leak Rate Calculation STEP 1 (1&2): CALCULATE the RCS Leak rate using Pl-VIEW as follows : SAT STANDARD: DETERMINES that Pl-VIEW is unavailable. EXAMINER'S NOTE: Provided in Initial Conditions. This UN SAT eliminates use of Step 2 in Att. 4. COMMENTS: STEP 2 (3): If Pl-VIEW is un-available, THEN RECORD data using DCS. A. RECORD results in Hand Cale Section. _ _ SAT STANDARD: DETERMINES that Pl-VIEW is unavailable, and that data is to be recorded in the Hand Cale Section. _ _ UNSAT EXAMINER'S CUE: Provided in Initial Conditions. COMMENTS: STEP 3 (4): RECORD results in Hand Cale Section. SAT STANDARD: RECORDS all data provided in Initiating Cue. EXAMINER'S CUE: None UNSAT COMMENTS: NRC SRO Admin JPM A2 Page 4 of 11 JPM A-2 SRO Page 4

JOB PERFORMANCE MEASURE STEP 4 (5) : DETERMINE Total Leakage of RCS by COMBINING differences of CRITICAL the following : STEP

• BA Integrator = 0.0 gallons
• PMW Integrator = 0.0 gallons
• Zinc Injection = 0.0 (or NIA, system not in service) gallons SAT
• VCT level = -84.5 (.+/- 0.1) gallons
• Pzr Level = + 13.408 (.+/- 0.1) gallons Total Leakage =-71 .092 (.+/- 0.2) gallons UNSAT STANDARD: RECORDS applicable data from Step 4 table and calculates Total Leakage.

EXAMINER'S CUE: None EXAMINER'S NOTE: Tolerance allowed for rounding calculated values. COMMENTS: STEP 5 (6) : DETERMINE Identified Leakage by COMBINING differences of the CRITICAL following components : STEP

• QT Level = -1 .65 (+/-. 0.1) gallons
• Chg Pp Seal Tanks =-2.36 gallons
• Attachment 2 (if used) = 0.0 (or N/A) gallons SAT Identified Leakage = -4.01(.+/-0.1) gallons STANDARD: RECORDS applicable data from Step 4 table and calculates _ _ UNSAT Identified Leakage.

EXAMINER'S CUE: None EXAMINER'S NOTE: Tolerance allowed for rounding calculated values. EXAMINER'S NOTE: Charging Pump Seal Tank levels are reported by the SNPO as inches change over an hour. COMMENTS: NRC SRO Admin JPM A2 Page 5of 11 JPM A-2 SRO Page 5

JOB PERFORMANCE MEASURE STEP 6 (7): DETERMINE Unidentified Leakage by SUBTRACTING Identified CRITICAL Leakage from Total Leakage. STEP

• Total Leakage =-71 .092 (2: 0.1) gallons
• Identified Leakage =-4.01 (2: 0.1) gallons
• Unidentified Leakage = -67 .082 (2: 0.2) gallons SAT STANDARD: CALCULATES Unidentified Leakage.

UNSAT EXAMINER'S CUE: None EXAMINER'S NOTE: Tolerance allowed for rounding calculated values. COMMENTS: STEP 7 (8): DETERMINE Unidentified Leakage rate by DIVIDING Unidentified CRITICAL Leakage value in Attachment 4, Step 7 by elapsed time in minutes. STEP

• Unidentified Leakage =-67.082 (2: 0.2) gallons
• Elapsed Time = 60 minutes
• Unidentified Leakage Rate = -1.118 (2: 0. 02) gpm SAT STANDARD: CALCULATES Unidentified Leakage Rate . UNSAT EXAMINER'S CUE: None EXAMINER'S NOTE: Tolerance allowed for rounding calculated values.

COMMENTS: NRC SRO Admin JPM A2 Page 6of11 JPM A-2 SRO Page 6

JOB PERFORMANCE MEASURE STEP 8 (9): DETERMINE Identified Leakage rate by DIVIDING Identified CRITICAL Leakage value in Attachment 4, Step 6 by elapsed time in minutes. STEP

• Identified Leakage = -4.01 (.+/- 0.1) gallons
• Elapsed Time = 60 minutes
• Identified Leakage Rate = -0.067 (.+/- 0.01) gpm _ _ SAT STANDARD: CALCULATES Identified Leakage Rate. _ _ UNSAT EXAMINER'S CUE: None EXAMINER'S NOTE: Tolerance allowed for rounding calculated values.

COMMENTS: 2-0SP-01.03, Main Bod , Section 4.1, Ste s 1 and 8 STEP 9 (4.1.7):RECORD Identified and Unidentified Leakage Rate.

• Calculation Start: Date: Today Time: 0100 _ _ SAT
• Calculation Stop: Date: Today Time: 0200
• Identified Leakage Rate = -0.067 (+ 0.001) gpm
• Unidentified Leakage Rate = -1.118 (+ 0.02) gpm _ _ UNSAT STANDARD: RECORDS Identified and Unidentified Leakage Rates calculated in Attachment 4.

EXAMINER'S CUE: None EXAMINER'S NOTE: Tolerance allowed for rounding calculated values. COMMENTS: NRC SRO Admin JPM A2 Page 7of11 JPM A-2 SRO Page 7

JOB PERFORMANCE MEASURE STEP 10 (4.1.8): VERIFY RCS leakage rates are within Technical CRITICAL Specification 3.4.6.2 requirements as follows: STEP STANDARD: RECORDS surveillance results , indicating Identified Leakage Rate is SAT and Unidentified Leakage Rate is UNSAT. SAT EXAMINER'S CUE: None. UNSAT COMMENTS: STEP 11 (4.1.8.A) : IF RCS Leakage exceeds 1 GPM, THEN REFER TO 2-AOP-01 .08, RCS Leakage Abnormal Operations. SAT STANDARD: INFORMS Unit Supervisor:

• Identified Leakage Rate is 0.067 gpm, and is SAT UNSAT
• Unidentified Leakage Rate is 1.118 gpm , and is UNSAT
• REFER TO 2-AOP-01.08, RCS Leakage Abnormal Operations EXAMINER'S CUE: None.

COMMENTS: NRC SRO Admin JPM A2 Page 8of 11 JPM A-2 SRO Page 8

JOB PERFORMANCE MEASURE STEP 12 (4.1.8.A) : IF RCS Leakage exceeds 1 GPM, THEN REFER TO 2-AOP-01 .08, RCS Leakage Abnormal Operations. SAT STANDARD: INFORMS Unit Supervisor:

• Unidentified Leakage Rate is 1.12 gpm, and is UNSAT _ _ UNSAT
• Identified Leakage Rate is 0.067 gpm , and is SAT
• REFER TO 2-AOP-01 .08, RCS Leakage Abnormal Operations EXAMINER'S CUE: None.

COMMENTS: 2-AOP-01.08, RCS Leaka e Abnormal 0 erations, Step 4.2.1.4 STEP 13 (4.2.1.4): VERIFY all of the following conditions are met:

• UNIDENTIFIED LEAKAGE less than or equal to 1 gpm SAT STANDARD: RECOGNIZES that Unidentified Leakage is greater than 1 gpm (1 .12 gpm). UNSAT EXAMINER'S CUE: None.

COMMENTS : NRC SRO Admin JPM A2 Page 9of11 JPM A-2 SRO Page 9

JOB PERFORMANCE MEASURE STEP 14 (CA 4.1 ): REFER to TS LCO 3.4.6.2, Reactor Coolant System Leakage. CRITICAL STEP STANDARD: IDENTIFIES that TS LCO 3.4.6.2, Action b applies and that the crew must reduce the leakage rate to within limits within 4 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SAT SHUTDOWN within the following 30 hours. EXAMINER'S CUE: None. UNSAT EXAMINER'S CUE: This JPM is complete. COMMENTS: END OF TASK STOP TIME: _ _ __ NRC SRO Adm in JPM A2 Page 10of11 JPM A-2 SRO Page 10

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

• Unit 2 is operating at 100% power
• The Unit Supervisor has entered 2-AOP-01 .08, RCS Leakage Abnormal Operation, due to suspected RCS leakage
• RS-26-25, Containment Particulate, EAP-541 , is in ALERT
• RS-26-26, Containment Particulate, PAP-551 , is in ALERT
• The zinc injection system is shutdown
• Stable plant conditions have been maintained throughout the duration of the measurement period
• Pl-VIEW and the RCS Leak Rate Calculator are unavailable INITIATING CUES:

To satisfy the requirements of 2-AOP-01 ,08, RCS Leakage Abnormal Operation, Step 4.2.1 .3, the Unit Supervisor has directed you to perform a one hour manual RCS leak rate determination per 2-0SP-01 .03, Reactor Coolant System Inventory Balance, Attachment 4, Manual Leak Rate Calculation. Also , determine any required actions based on the results of the leak rate calculation , including any related time constraints. The following readings are observed at the beginning and end of the measurement period: Parameter (@ 0100 (@0200 RCS Tcold 550.4°F 550.4°F Boric Acid Integrator 0.0 oallons 0.0 oallons Primary Makeup Water Integrator 0.0 gallons 0.0 gallons Zinc Injection Tank Level n/a n/a VCT Level \ '- 54.2% 51.7% Pressurizer Level } I 63.0% 63.2% Quench Tank Level 65.0% 65.1% Charging Pump Seal Tank Level 2A: 1 inch 28: 2 inches {"' *..  ! 2C : 1 inch 1 (._ JPM A-2 SRO Page 11

Procedure Nci. ST. LUCIE UNIT 2 2-AOP -01 .08 ABNORMA L OP ERATING PROCEDURE Revision. No. FPL SAFETY RELATED 12 CONTINUOUS USE

Title:

RCS LEAKAGE ABNORMAL OPERATIONS Responsible Departme nt: OPERATION S Special Considerations: Performance of this procedure may affect core reactivity. FOR INFORMATION ONLY Before use, verify revision and change documentation (if applicable) with a controlled index or document. DATE VERIF IED INITIAL_ __ _ Revision Approved By Approval Date UNIT# UN IT2 DATE DOCT PROCEDURE 0 John Owens 12/11/09 DOCN 2-AOP-01.08 SYS STATUS COMPLETED 12 T. Spillman 05/28/14 REV 12

                                                                          #OF PGS JPM A-2 SRO Page 12

REVISION NO.: PROCEDURE TITLE: PAGE: , 12 RCS LEAKAGE ABNORMAL OPERATIONS 2 of 61 PROCEDURE NO. : 2-AOP-01 .08 ST. LUCIE UNIT 2 REVISION

SUMMARY

Rev. No. Description 12 Incorporated PCR 1967072 for TCC 281726. Reversed alarm logic for Annunciator R-57 , due to leakage past V3247 , check valve for 282 SIT Outlet. (Author: J Fiori) i 11 Incorporated PCR 1950595. EC 277899 restored the normal logic for annunciator Q-17 to high pressure. EC 276581 restored the normal logic for annunciator R-57 to high pressure. (Author: J. Fiori) 10 Incorporated PCR 1874184 (EC 249985) to replace Att. 6 markup for boil-off curve and correct JPN-PSL-SENP-94-029 rev#. (Author: H. Martin) 9 Incorporated PCR 1827818. Installed Temporary Modification EC 277899 to reverse the logic for annunciator Q-17 from high pressure to low pressure alarm . (Author: J. Fiori) 8 Incorporated PCR 1688464 for TSA 2-11-004 (EC 273882) to restore the logic for annunciator Q-17 from low pressure alarm to high pressure alarm. ...... (Author: J Fiori) 7 Incorporated PCR 1773820 to support TSA 2-12-002 (EC276581) to reverse alarm logic for Annunciator R-57 . (Author: D. Melody) 6 Incorporated PCR 564265 to add that evacuation of containment should be considered . (Author: D. Coggeshall) 5 Incorporated PCR 1688350 for TSA 2-11-004 (EC 273882) to reverse the logic for annunciator Q-17 from high pressure alarm to low pressure alarm. (Author: J . Fiori) 4 Incorporated PCR 1635733 to change Attachment 7, Section 3.3, Makeup using LPSI Gravity Feed . This change is for RWT 589853, uncontrolled gravity feed of RCS. (Author: J. Fiori) 3 Incorporated PCR 592340 to revise step order to minimize the chance of inadvertent gravity drain. (Author: J . Fiori) 2 Incorporated PCR 562343 to add options derived from EC 0000236024, PSL Unit 2 - Emergency Response Data Acquisition and Display System (ERDADS) Replacement. (Author: Dave deFerrari) 18 Incorporated PCR 10-1893 to update procedure number reference . (Author: Clair Heitzenrater) JPM A-2 SRO Page 13

REVISION NO.: PROCEDURE TITLE: PAGE: 12 RCS LEAKAGE ABNORMAL OPERATIONS 3 of 61 PROCEDURE NO.: 2-AOP -01.08 ST. LUCIE UNIT 2 TABLE OF CONTENTS SECTION

1. 0 PURPOSE ......................... .. ........................................................................................ 4 2.0 ENTRY CONDITIONS .. ............................... .... ............................................................ 5 3.0 EXIT CONDITIONS ........ ... .................. ..... ............................. .. .............. .. .................... 7 4 .0 OPERATOR ACTIONS ................. ....................................................... ....................... 8 4.1 Immediate Operator Actions ................................................. .. ....... ...... .. .............. ... ..... 8 4.2 Subsequent Ope rator Actions .............. ........................................................... ... ........ .. 8 4.2.1 General Actions ............................................ ......... .. ....................... ..................... .. .. .... 8 4.2.2 Actions for Modes 1 Through 3 With SIAS Ava ilable .................................... ...... ....... 13 4.2.3 Actions for Modes 3 Through 6 With SIAS Blocked .................... .. .. .. ......................... 22 5.0 RECORDS ................................................................................................................. 41

6.0 REFERENCES

AND COMMITMENTS ... ..... .......... ....... ....... .. ... ........... ... .... ... .... ....... 41 - ATTACHMENTS ATTAC HMENT 1 General Information ..................... ...................................... .. ........ 43 ATTACHMENT 2 Charg ing Pump Seal Leak Rate Determination .......... .... ............. 44 ATTACHMENT 3 Loca l Sample Valve Isolation ....................................................... 48 ATTACHMENT 4 RV Head Seal Leak Rate Determin ation ............... ... .. .................. 49 ATTACHMENT 5 RCS Level Indications vs . Elevation ......... .. .. ................................ 51 ATTACHMENT 6 Min imum Flow to Make Up for Boil-Off... .. ... .. ............. .. ................ 52 A TT ACHM ENT 7 Adding Emergency Makeup to RCS ........... .... .......................... ... . 53 JPM A-2 SRO Page 14

REVISION NO .: PROCEDURE TITLE: PAGE: 12 RCS LEAKAGE ABNORMAL OPERATIONS 4 of 61 PROCEDURE NO .: 2-AOP-01 .08 ST. LUCIE UN IT 2 1.0 PURP OSE This procedure provides guidance for quantifying and respond ing to an RCS leak of any size while attempting to identify the leak location and isolate the leak if possible. It also deals with loss of inventory due to boil-off following a total loss of SOC. The overall strategy of this AOP is as follows: Unit in MODE 1, 2. or 3 with SIAS available : Attempt to maintain pressurizer level using charg ing and letdown while determining the leak rate and attempting to locate and isolate the leak. If makeup is inadequate, then exit to 2-EOP-01 (SPTAs) if in MODE 1 or 2 or exit to 2-EOP-03 (LOCA) if in MODE 3; SIAS will likely be required . If leak is found and isolated, then power operation may continue at discretion of plant management depending upon final plant condition. If leak cannot be isolated but makeup is adequate, then plant shutdown and cooldown will be directed . Unit in MODE 3, 4. 5, or 6 with SIAS blocked : If entered due to a leak, then attempt to maintain pressurizer level using charging and letdown while determining the leak rate and attempting to locate and isolate the leak. Commence monitoring applicable low mode AOP SFSCs. If makeup is inadequate, then use HPSI and LPSI as needed to maintain RCS inventory. If makeup is still inadequate, depressurize RCS while cooling down to allow more injection flow. If leak is found and *isolated, then effect repairs while remaining shutdown . If leak cannot be isolated but makeup is adequate, then plant shutdown and coo ldown will be directed if required. If SFSCs cannot be maintained , then exit to applicable low mode AOP . If entered due to loss of inventory caused by boil-off following a total loss of SOC, then add makeup at a rate greater than the minimum flow required to makeup for boil-off. JPM A-2 SRO Page 15

REVISION NO. : PROCEDURE TITLE: PAGE: 12 RCS LEAKAGE ABNORMAL OPERATIONS 5 of 61 PROCEDURE NO.: 2-AOP-01 .08 ST. LUCIE UNIT 2 2.0 ENTRY CO NDITIONS 2.1 Indications

• RCS inventory balance indicates RCS UNIDENTIFIED LEAKAGE greater than

               *or equal to 1 gpm

• Flow mismatch between charging and sum of letdown and RCP CBO
• Lowering pressurizer level with constant RCS temperature
• Elevated temperatures on pressurizer safety/PORV discharge lines
• Flow indication on pressurizer safety/PORV acoustic monitors
• Quench tank level , temperature , and pressure rising
• Lowering VCT level
• High or rising safety injection header loop pressure
• High or rising flow into reactor cavity sump with attendant level rise
• Refueling cavity seal ring or SIG nozzle dam leakage
• Reactor vessel head inner 0-ring leakage
• Ris ing CCW surge tank levels and rising CCW activity levels
• Rising radiation leve ls on process radiation monitors Containment air particulate and gas monitor CCW radiation monitor Conta inment area radiation monitors
• Loss of inventory due to boil-off following a total loss of SOC
• JPM A-2 SRO Page 16

REVISION NO. : PROCED URE T ITLE: PAGE: 12 RCS LEAKAGE ABNORMAL OPERATIONS 6 of 61 PROCEDURE NO.: 2-AOP-0 1.08 ST. LUCIE UNIT 2 2.2 A nnunciators

• LC-7 , RCGVS PRESS LOW
• M-3, VCT LEVEL HIGH/LOW
• M-5 , LETDOWN PRESS HIGH/LOW
• M-11 , VCT LEVEL LOW-LOW
• N-21 , RX CAVITY SUMP LEVEL HIGH-HIGH
• N-46 , RX CAVITY LEAKAGE HIGH
• Q-16 , HOT LEG INJ LOOP 2A PRESS HIGH
• Q-17 , HOT LEG !NJ LOOP 28 PRESS HIGH
• R-31 , 2A 1 SIT LEVEL HIGH/LOW
• R-32, *2A2 SIT LEVEL HIGH/LOW
• R-33, 281 SIT LEVEL HIGH/LOW
• R-34 , 282 SIT LEVEL HIGH/LOW
• R-41 , 2A 1 SIT LEVEL HIGH-HIGH
• R-42 , 2A2 SIT LEVEL HIGH-H IGH
• R-43 , 281 SIT LEVEL HIGH-HIGH R-44 , 282 SIT LEVEL HIGH-HIGH R-46 , SI HEADER 2A 1 LOOP PRESS HIGH R-47 , SI HEADER 281 LOOP PRESS HIGH
• R-56 , SI HEADER 2A2 LOOP PRESS HIGH
• R-57 , SI HEADER 282 LOOP PRESS LOW JPM A-2 SRO Page 17

REVISION NO.: PROCEDURE TITLE: PAGE: 12 RCS LEAKAGE ABNORMAL OPERATIONS 7 of 61 PROCEDURE NO .: 2-AOP-01 .08 ST. LUCIE UNIT 2 3.0 EXIT CONDITIONS Any of the following conditions are met:

• RCS leakage source has been identified and isolated .
• Leak cannot be isolated AND leak is within makeup capacity AND SFSCs are being monitored AND, if applicable, plant cooldown and depressurization are in progress.
• If entered due to inventory loss due to boil-off, then makeup flow greater than the minimum flow required to makeup for boil-off has been established AND RCS level is rising OR has been restored.
• Exit to an EOP or low mode AOP has been directed per this procedure.

JPM A-2 SRO Page 18

REVISION NO .: PROCEDURE TITLE : PAGE: 12 RCS LEAKAGE ABNORMAL OPERATIONS 8 of 61 PROCEDURE NO.: 2-AOP-01 .08 ST. LUCIE UNIT 2 IINSTRUCTIONS I ICONTINGENCY ACTIONS I 4.0 OPERATOR ACTIONS 4.1 Immediate Operator Actions None 4.2 Subsequent Operator Actions 4.2.1 General Actions

1. ADD RCS makeup per appl icable section (s) of Table 1 as directed by us while CONTINU ING with this AOP :

Table 1 Ma keup Method Se Iect1on Base d on Plant C on dl 11ons MODE SIAS Status Makeup Methods Attachment Section Available Charging Attachment 7, Section 1.0

                                        *'    \'-~.   '

1, 2, or 3 ........ Charging Attachment 7, Section 1.0 Blocked HPS! Attachment 7, Section 2.0

              *~

Charg ing Attachment 7, Section 1.0 c.,-> HPSI Attachment 7, Section 2.0 4, 5, or6 Blocked

      ~

LPSI Attachment 7, Section 3.0 JPM A-2 SRO Page 19

REVISION NO .: PROCEDURE TITLE: PAGE: 12 RCS LEAKAGE ABNORMAL OPERATIONS 9 of 61 PROCEDURE NO.: 2-AOP-01 .08 ST. LUCIE UNIT 2 IINSTRUCTIONS I ICONTINGENCY ACTIONS I 4.2.1 General Actions (continued)

2. MAINTAIN RCS level 2.1 IF leak rate is greater than stable OR rising. available charging pump capacity AND unit is in MODE 1 or 2, THEN PERFORM the following:

A. TRIP reactor. B. GO TO 2-EOP-01, Standard Post Trip Actions . 2.2 IF the following conditions are met:

• Leak rate is greater than available charging pump capacity .
• Unit is in MODE 3.
• SIAS is NOT blocked.

THEN GO TO 2-EOP-03, Loss of Coolant Accident. JPM A-2 SRO Page 20

REVISION NO.: PROCEDURE TITLE: PAGE: 12 RCS LEAKAGE ABNORMAL OPERATIONS 10 of 61 PROCEDURE NO.: 2-AOP-O 1.08 ST. LUCIE UNIT 2 IINSTRUCTIONS I ICONTINGENCY ACTIONS I 4.2.1 General Actions (continued) NOTE Thumb rule for estimating leak rate is that 1" level rise on Ll-07-6, RX CAVITY LEVEL, on RTGB-205 is about 46 gallons. DETERMINE RCS leak rate by any of the following methods:

• ESTIMATE leak rate based on gross charging-letdown mismatch.
• ESTIMATE leak rate based on abnormal tank or sump level rise rates .

CALCULATE leak rate per 2-0SP-01 .03, Reactor Coolant System Inventory Balance . JPM A-2 SRO Page 21

REVISION NO.: PROCEDURE TITLE: PAGE: 12 RCS LEAKAGE ABNORMAL OPERATIONS 11 of 61 PROCEDURE NO.: 2-AOP-01.08 ST. LUCIE UNIT 2 IINSTRUCTIONS I ICONTINGENCY ACTIONS I 4.2.1 General Actions (continued) NOTE To aid in classifying RCS leaks for E-Plan purposes, Attachment 1 (4 .2.1

4) , General Information, defines certain terms to ensure classifications are made consistently within this context.

4. VERIFY fill of the following 4.1 REFER TO Tech Specs 3.4.6.2, conditions are met: Reactor Coolant System Leakage. *

• UNIDENTIFIED LEAKAGE 4.2 IF leak rate is known to be less than or equal to 1 gpm unisolable AND greater than Tech Spec limits ,
• IDENTIFIED LEAKAGE THEN IMPLEMENT E-Plan.

less than or equal to 10 gpm 4.3 IF personnel are inside Containment, THEN CONSIDER

• NO secondary plant evacuating Containment.

radiation alarms or rising trends on any of the fo llowing:

• Condenser air ejector monitor
• SIG blowdown monitors
• Main steamline monitors JP M A-2 SRO Page 22

REVISION NO .: PROCEDURE TITLE: PAGE: 25 REACTOR COOLANT SYSTEM INVENTORY BALANCE 28 of 31 PROCEDURE NO.: 2-0SP-01 .03 ST. LUCIE UNIT 2 INITIAL ATTACHMENT 4 Manual Leak Rate Calculation (Page 1 of 4)

1. CALCULATE the RCS Leak Rate using Pl-VIEW as follows .

2. IF Pl-View is available, THEN PERFORM the following:

A. SELECT START at RO LAN workstation . B. SELECT ALL PROGRAMS C. SELECT Pl-View. D. CLICK Pl-View (1) ENSURE Pl Server PSL-ERDADS is selected. (2) SET START/END as desired (3) SELECT desired sample increment using slide bar. (4) SELECT Get Data . E. RECORD end and start time data for desired leak rate duration . F. CALCULATE and RECORD differences. G. ENTER the data in the Hand Calculated Section . H. CLICK on the Hand Calculated Section Results , Save Data button. I. VERIFY that no action levels are displayed.

3. IF Pl-View is un-available , THEN RECORD data using DCS A. RECORD results in Hand Cale Section.

4. IF PINiew and DCS are unavailable OR at US/SM discretion , THEN RECORD data using RTGB indications.

• RECORD results in Hand Cale Section.

JP M A-2 SRO Page 23

REVISION NO.: PROCEDURE TITLE : PAGE: 25 REACTOR COOLANT SYSTEM INVENTORY BALANCE 29 of 31 PROCEDURE NO. : 2-0SP-01 .03 ST. LUCIE UNIT 2 ATTACHMENT 4 Manual Leak Rate Calculation (Page 2 of 4)

4. (continued)

Initial Conditions Final Conditions Notes Difference 2 hour minimum desired Date:_ _!_ _!_ _ Date: __/__/__ unless not at steady state .

                                                                                                '    1~-f'      Min Time:                      Time:                            (Chg. Pump data excluded)

(At1achment 2 data excluded) T COLD: OF TcoLD: OF Held constant (<.1°F) ** -~ OF B.A. B .A. Integrator: Integrator: Always Negative - gal. v PMW PMW Integrator: Integrator: Always Negative - gal. Notify SNPO to mark Notify SNPO to mark Zinc Injection Tank Zinc Injection Tank 60 minute minimum required . gauge glass (LG-02-2) gauge glass (LG-02-2) Always negative

                                                                                                  -              gal.

(gal) (gal) -- VCT Level:  % VCT Level :

                                              \
                                                               + if final > initial
                                                               - if final < initial

(%change x 33.8 gal. per%) ( ) gal. Pzr Level:  % Pzr Level :  :\*

                                                               + if final > initial
                                                               - if final < initial

(% chanqe x 67 .04 qal. per%) ( ) gal. Always Negative Q.T. Level:  % Q.T. Level :  % NIA if final < initial - gal. (%change x 16.5 gal. per%) 30 minute minimum required . Notify SNPO to mark Notify SNPO to mark Always Negative. Seal Tank level for ALL Seal Tank level for ALL NIA if final < initial

                                                                                                  -              gal.

available Chg . Pps .

• available Chg . Pps . *

(1 inch = 0.59 gal.)

• Data should be recorded for any pump hydraulically connected to the system .

   ** If Tcold is NOT held constant, consideration should be given to repeating calculation when conditions permit.

JP M A-2 SRO Page 24

REVISION NO .: PROCEDUR E TITLE: PAGE: 25 REACTOR COOLANT SYSTEM INVENTORY BALANCE 30 of 31 PROCEDURE NO.: 2-0SP-01 .03 ST. LUCIE UNIT 2 ATTACHMENT 4 Manual Leak Rate Calculation (Page 3 of 4)

5. DETERMINE Total Leakage of RCS by COMBINING differences of the following :

• B.A. Integrator gal.
• PMW Integrator gal.
• Zinc Injection gal.
• VCT Level gal.
• Pzr Level gal.

Total Leakage gal.

6. DETERMINE Identified Leakage by COMBINING differences of the following components :

• Q.T. Level _ _ _gal.
• Chg . Pp. Seal Tanks _ _ _gal.

Attachment 2 (if used) _ _ _ gal. Identified Leakage = _ __ gal.

7. DETERMINE Unidentified Leakage by SUBTRACTING Identifi ed Leakage from Total Leakage.

• Total Leakage (). _ __ gal.
• Identified Leakage -( ) gal.
• Unidentified Leakage =( )_ _ gpm JPM A-2 SRO Page 25

REVISION NO.: PROCEDURE TITLE: PAGE: 25 REACTOR COOLANT SYSTEM INVENTORY BALANCE 31 of 31 PROCEDURE NO. : 2-0SP-01 .03 ST. LUCIE UNIT 2 INITIAL ATTACHMENT 4 Manual Leak Rate Calculation (Page 4 of 4)

8. DETERMINE Unidentified Leakage rate by DIVIDING Unidentified Leakage value in Attachment 4, Step 7 by elapsed time in minutes.

• Unidentified Leakage
• Elapsed time - - -min .

Unidentified Leakage rate =___g, pm

9. DETERMINE Identified Leakage rate by DIVIDING Identified Leakage value in Attachment 4 , Step 6 by elapsed time in minutes.

• Identified Leakage _ _ _gal.
• Elapsed time _ __ min .

Identified Leakage rate =___ gpm JPM A-2 SRO Page 26

REVISION NO.: PROC EDURE T ITLE: PAGE: 25 - PROC EDURE NO.: 2-0SP-01. 03 REACTOR COOLANT SYSTEM INVENTORY BALANCE ST. LUCIE UNIT 2 29 of 31 ATTACHMENT 4 Manual Leak Rate Calculation (Page 2 of 4)

4. (continued)

Initial Conditions Final Conditions Notes Difference 2 hour minimum desired Date :- -I- -I- - Date: __/_ _/_ _ unless not at steady state . £0 Min Time: C) t ()I,) Time: ~l--o u (Chg . Pump data excluded) (Attachment 2 data excluded) Tcow: S"S-o . '-I OF TcoLo: 5 b1'. i..f OF Held constant (<.1 °F) 0 Q OF D B.A. B.A . Integrator: 0 Always Negative - 0 gal. Integrator: 0 0 PMW PMW Integrator: Integrator: 0 Always Negative - 0 gal. Notify SNPO to mark Notify SNPO to mark Zinc Injection Tank Zinc Injection Tank 60 minute minimum required .

                                                                                                  -     0 gauge glass (LG-02-2)

(gal) gauge glass (LG-02-2) (gal ) Always negative .gal.

                                                                  + if final > initial VCT Level :       5"1. Z-   %   VCT Level : S I* 7         %     - if final < initial           (-)     8 ~. :;- gal.

(%change x 33 .8 qal. per %)

                                                                  + if final > initial Pzr Leve l: b 3            %   Pzr Level : ~ S. ?..       %     - if final < initial           (~-) . I '3 . L!*C>Qga 1.

I (%change x 67 .04 gal. per%) Always Negative Q.T. Level: ~5" <:,5". \\ ,....

                             %   Q.T . Level :         I    %     NIA if final < initial         - '6~               gal.

(%change x 16.5 gal. per %) 30 minute minimum required. Notify SNPO to mark Notify SNPO to mark Seal Tank level for ALL Seal Tank level for ALL Always Negative. i./ - 2 . "§l:, gal. NIA if final < initial available Chg . Pps .

• available Chg . Pps . *

(1 inch= 0.59 gal.)

• Data should be recorded for any pump hydraulically connected to the system.

 ** If Tcold is NOT held constant, consideration should be given to repeating calculation when conditions permit.

JPM A-2 SRO Page 27

REVISION NO.: PROCEDURE TITLE: PAGE: 25 REACTOR COOLANT SYSTEM INVENTORY BALANCE 30 of 31 PROCEDURE NO.: 2-0SP-01 .03 ST. LUCIE UNIT 2 ATTACHMENT 4 Manual Leak Rate Calculation (Page 3 of 4)

5. DETERMINE Total Leakage of RCS by COMBINING differences of the following :

• B.A. Integrator * () gal.
• PMW Integrator 0 gal.
• Zinc Injection 0 gal.
• VCT Level (-) 8'1 . r gal.
• Pzr Level (f ) n. '-/ o8gal.

Total Leakage - I I . o~* i....gal.

6. DETERMINE Identified Leakage by COMBINING differences of the following components:

• Q.T. Level - \. br°- gal.
• Chg . Pp. Seal Tanks 3 ~ gal.

                                                                    -  /~)~

• Attachment 2 (if used) gal.

Identified Leakage =-"{.~I gal.

7. DETERMINE Unidentified Leakage by SUBTRACTING Identified Leakage from Total Leakage.

• Total Leakage (-) 7 /. lYilgal.
• Identified Leakage _(-) '1 .0 I gal.
• Unidentified Leakage = (-) ~/ ,u5]..gpm JPM A-2 SRO Page 28

REVISION NO.: PROCEDURE TITLE: PAGE: 25 REACTOR COOLANT SYSTEM INVENTORY BALANCE 31 of 31 PROCEDURE NO.: 2-0SP-01.03 ST. LUCI E UNIT 2 INITIAL ATTAC HMENT 4 Manual Leak Rate Calculation (Page 4 of 4)

8. DETERMINE Unidentified Leakage rate by DIVIDING Unidentified Leakage va lue in Attachment 4, Step 7 by elapsed time in minutes.

• Uniden tified Leakage - fo 7 .DlZgal.
• Elapsed time 60 min.

Unidentified Leakage rate = /. I I $ gpm

9. DETERMINE Identifi ed Leakage rate by DIVIDING Identified Leakage va lue in Attachment 4 , Step 6 by elapsed time in minutes.

• Identified Leakage - Lf. 0 1 gal.
• Elapsed time b () min .

Identified Leakage rate = .0(:;. / gpm JPM A-2 SRO Page 29

REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4 .6.2 Reactor Coolant System operational leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE,

b. 1 gpm UNIDENTIFIED LEAKAGE,

c. 150 gallons per day primary-to-secondary leakage through any one steam generator (SG) ,

d. 10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System, and

e. 1 gpm leakage (except as noted in Table 3.4-1) at a Reactor Coolant System pressure of 2235 :t 20 psig from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 .

APPLICABILITY: MODES 1, 2, 3, and 4. ACTION:

a. With any PRESSURE BOUNDARY LEAKAGE or with primary-to-secondary leakage not within limit, be in at least HOT ST AND BY within 6 hours and in COLD SHUTDOWN within the following 30 hours.

b. With any Reactor Coolant System operational leakage greater than any one of the limits, excluding primary-to-secondary leakage, PRESSURE BOUNDARY LEAKAGE , and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.

c. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.

d. With RCS leakage alarmed and confirmed in a flow path with no flow indication, commence an RCS water inventory balance within 1 hour to determine the leak rate .

SURVEILLANCE REQUIREMENTS 4.4.6 .2.1 Reactor Coolant System operational leakages shall be demonstrated to be within each of the above limits by :

a. Monitoring the containment atmosphere gaseous and particulate radioactivity monitor at least once per 12 hours.

b. Monitoring the containment sump inventory and discharge at least once per 12 hours.

ST . LUCIE - UNIT 2 3/4 4-19 Amendment No . ~. 147 JPM A-2 SRO Page 30

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

c. *Performance of a Reactor Coolant System water inventory balance at least once per 72 hours.

d. Monitoring the reactor head flange leakoff system at least once per 24 hours.

e. Verifying primary-to-secondary leakage is ~ 150 gallons per day through any one steam generator at least once per 72 hours.**

4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve check valve specified in Table 3.4-1 shall be demonstrated OPERAB LE by verifying leakage to be within its limit:

a. At least once per 18 months,

b. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been petiormed in the previous 9 months ,

c. Prior to returning the valve to service following maintenance, repair or replacement work on the valve ,

d. Following valve actuation due to automatic or manual action or flow through the valve:

1. Within 24 hours by verifying valve closure, and

2. Within 31 days by verifying leakage rate.

4.4 .6.2.3 Each Reactor Coolant System Pressure Isolation Valve motor-operated valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit;

a. At least once per 18 months, and

b. Prior to returning the valve to service following maintenance ,

repair, or replacement work on the valve. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

• Not required to be performed until 12 hours after establishment of steady state operation .

Not applicable to primary-to-secondary leakage.

• • Not required to be performed until 12 hours after establishment of steady state operation .

ST. LUCIE - UN IT 2 3/4 4-20 Amendment No . ~ . 147 JPM A-2 SRO Page 31

TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES Check Valve No. Motor Operated Valve No. V3217 V3525 V3480 V3227 V3524 V3481 V3237 V3527 V3652 V3247 V3526 V3651 V3259 V3258 V3260 V3261 V3215 V3225 V3235 V3245 NOTES (a) Maximum Allowable Leakage (each valve):

1. Except as noted below leakage rates greater than 1.0 gpm are unacceptable.

2. For motor-operated valves (MOVs) only, leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount the reduces the margin between previous measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.

3. For motor-operated valves (MOVs) only, leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are unacceptable if the latest measured rate exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.

4. Leakage rates greater than 5.0 gpm are unacceptable.

(b) To satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in accord-ance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the leakage

     -criteria.

(c) Minimum test differential pressure shall not be less than 200 psid. ST _LUC IE - UNIT 2 3/4 4-21 JPM A-2 SRO Page 32

eFPL St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE PERFORM BORATED WATER SOURCES SURVEILLANCE FOR MODE 1 - UNIT 2 HLC 22 NRC RO/SRO Admin JPM A3 NRC RO/SRO Admin JPM A3 Page 1 of 7 JPM A-3 Page 1

JOB PERFORMANCE MEASURE Task: Perform the Borated Water Sources surveillance for Mode 1 - Unit 2. Faulted JPM? No Facility JPM #: No KIA: G2.2.12 Knowledge of surveillance procedures . KIA Rating(s): 3.7 I 4.1 Duty Area(s): N/A Task Information: 07002610 Task Standard: The JPM is complete when the student informs the US of the results of the Borated Water Sources surveillance. Evaluation Location: Performance Level: Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

• 2-0SP-02.07, Boration Flowpath and Sources, Revision 12 Validation Time: 10 minutes Time Critical: NO Tools/Eq ui pment/P roced u res Needed:
• 2-0SP-02.07 , Boration Flowpath and Sources
• Unit 2 Technical Specifications
• Calculator, Straight edge Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
• None Radiological Protection and RWP Requirements:
• None NRC RO/SRO Adm in JPM A3 Page 2 of 7 JPM A-3 Page 2

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

• The task you are to perform is: Perform the Borated Water Sources surveillance - Unit 2.
• The performance level to be used for this JPM is Perform.
• During the performance of the task, I will tell you which steps to simulate or discuss.
• I will provide you with the appropriate cues for steps that are simulated or discussed.
• You may use any approved reference materials normally available in the execution of this task , including logs.
• Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you.

INITIAL CONDITIONS: A Unit 2 is operating at full power. You are the Desk RCO, and 2-0SP-02.07, Boration Flowpath and Sources is due on your shift. INITIATING CUES: Perform the Borated Water Source portion (step 4.1.1) of the surveillance for the given conditions . Relevant parameter values are as follows: RWT 2A BAM Tank 2B BAM Tank LIS-07-2A = 34.3 feet .' l LIA-2206 = 87.0% LIA-2208 = 84.0% LIS-07-28 = 34.1 feet ~~ .Cb =5967 ppm Cb= 5856 ppm LIS-07-2C = 33.8 feet Temp= 109°F Temp= 105°F LIS-07-20 = 34.0 feet RWT Cb = 2094 ppm RWT Temp= 78°F NRC RO/SRO Admin JPM A3 Page 3 of 7 JPM A-3 Page 3

JOB PERFORMANCE MEASURE START TIME: _ _ __ 2-0SP-02.07, Boration Flow ath and Sources, Section 4.1.1 STEP 1 (4.1.1.1): DOCUMENT the present MODE. Present MODE: 1 2 3 4 (circle one) STANDARD: CIRCLES Mode 1. _ _ SAT EXAMINER'S CUE: None. UNSAT EXAMINER'S NOTE: Procedure NOTE following step 1 explains that satisfactory compliance with Tech Spec LCO 3.1.2.7 requires two borated water sources. COMMENTS: STEP 2 {4.1.1.2): VERIFY the following borated water source parameters: CRITICAL

• RWT parameters STEP
• 2A BAM Tank parameters
• 2B BAM Tank parameters SAT STANDARD: TRANSFERS RWT data from the cue sheet to the RWT parameters table in step 2. DETERMINES that all RWT parameters are SAT

(~33 feet). _ _ UNSAT EXAMINER'S CUE: None. COMMENTS: NRC RO/SRO Admin JPM A3 Pag e 4 of 7 JPM A-3 Page 4

JOB PERFORMANCE MEASURE STEP 3 (4.1.1.2): VERIFY the following borated water source parameters: CRITICAL

• RWT parameters STEP
• 2A BAM Tank parameters
• 2B BAM Tank parameters SAT STANDARD: TRANSFERS 2A BAM Tank data from the cue sheet to the 2A BAM Tank table in step 2. CALCULATES 2A BAM Tank level [8004 (+/-. 0) gallons]. Using Attachment 2, DETERMINES that 2A BAM Tank is UNSAT SAT.

EXAMINER'S CUE: None. COMMENTS: STEP 4 (4.1.1.2): VERIFY the following borated water source parameters: CRITICAL

• RWT parameters STEP
• 2A BAM Tank parameters
• 28 BAM Tank parameters SAT STANDARD: TRANSFERS 2B BAM Tank data from the cue sheet to the 2B BAM Tank table in step 2. CALCULATES 2B BAM Tank level [7728 (+/-. 0) gallons]. Using Attachment 2, DETERMINES that 2B BAM Tank is UNSAT UNSAT.

EXAMINER'S CUE: None. COMMENTS: NRC RO/SRO Adm in JPM A3 Page 5 of 7 JPM A-3 Page 5

JOB PERFORMANCE MEASURE STEP 4 (4.1.1.3): VERIFY the following Acceptance Criteria are met: CRITICAL STEP STANDARD: DETERMINES that two borated water sources are OPERABLE, the RWT and 2A BAM Tank. RECORDS the result as SAT. SAT EXAMINER'S CUE: None. UNSAT COMMENTS: STEP 5 (n/a): INFORM the US. STANDARD: INFORMS the US that the RWT and 2A BAM Tank are the OPERABLE Borated Water Sources. _ _ SAT EXAMINER'S CUE: None. UNSAT COMMENTS: END OF TASK NRC RO/SRO Admin JPM A3 Page 6 of 7 JPM A-3 Page 6

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK) INITIAL CONDITIONS: A Unit 2 is operating at full power. You are the Desk RCO, and 2-0SP-02.07, Boration Flowpath and Sources is due on your shift. INITIATING CUES: Perform the Borated Water Source portion (step 4.1.1) of the surveillance for the given conditions . Relevant parameter values are as follows: RWT 2A BAM Tank 2B BAM Tank LIS-07-2A = 34.3 feet LIA-2206 =87.0% -- ~ LIA-2208 = 84.0% LIS-07-28 = 34.1 feet Cb= 5967 ppm \ Cb= 5856 ppm LIS-07-2C = 33.8 feet Temp= 109°F '. Temp= 105°F LIS-07-20 = 34.0 feet ~v RWT Cb = 2094 ppm RWT Temp= 78°F JPM A-3 Page 7

Procedure No. ST. LUCIE UNIT 2 2-0SP-02.07 OPERATIONS SURVEILLANCE PROCEDURE Revision No. FPL SAFETY RE LATED 12 REFERENCE USE

Title:

BORATION FLOWPATH AND SOURCES Responsible Department: OPERATIONS Special Considerations: IThis is an Upgraded Procedure. FOR INFORMATION ONLY Before use, verify revision and change documentation (if applicable) with a controlled index or document. DATE VERIF IED INITIAL_ __ _ Revision Approved By Approval Date UNIT# UNIT2 DATE DOCT PROCEDURE 0 C. Costanzo 07/25/06 DOCN 2-0SP-02.07 SYS STATUS COM PLETED 12 R. Webber 12/11/13 REV 12

                                                                           #OF PGS JPM A-3 Page 8

REVISION NO.: PR OCEDURE T ITLE: PAG E: 12 BORATION FLOWPATH AND SOURCES 2 of 24 PROCED URE NO.: 2-0SP-02 .07 ST. LUCIE UNIT 2 REVISION

SUMMARY

Rev. No. Description 12 Incorporated PCR 1926085. In Section 4.1.2 Step 3 added note 1 to gravity Feed valves that was left out in Revision 9. (Author: J.R. Guist) 11 Incorporated PCR 1947014. In Section 2.1 added guidance for crediting charging pumps for Boration Flowpaths. Incorporated PCR to correct typos and clarify valve positions for V2509 and V2508 . (Author: J. R. Guist) 10 Incorporated PCR 1921461 to correct position of V2504 in Section 4 .1.2 as well as OPERABLE sources in the .Notes. (Author: R. Ross) 9 Incorporated PCR 1617808 to upgrade 2-0SP-02 .07 Rev 8 to AD-AA-100-1003, FPL Procedure Writer's Guide, as part of the Procedure Upgrade Project. Since this procedure was significantly reformatted , revision bars are NOT used .

• Moved Data Sheet 1 from old revision into main body of procedure .
• Deleted Note in Section "References" regarding use of symbols in th is procedure . All symbols have been removed. Reference tags have replaced items that need to be tracked .
• Spilt Instructions 1A and 1 B into MODE specific sections .
• Added flowpaths for MODE 5 & 6 from BAMT via Gravity, BAMPs or Charging Pumps .
• Deleted ECCS Subsystems as a boration flowpath as the referenced Tech Spec is NO longer valid for this item .
• Moved combined BAMT calculation to an attachment.

(Author: Robert Ross) JPM A-3 Page 9

REVISION NO.: PROCEDURE TITLE : PAGE: 12 BORATION FLOWPATH AND SOURCES 3of24 PROCEDURE NO.: 2-0SP-02 .07 ST. LUCIE UNIT 2 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE .............................................................. ....................... ................ .............. 4 2.0 PRECAUTIONS AND LIMITATIONS ... ...... ... ........................................ .. ....... ..... ......... 5 3.0 PREREQUISITES AND INITIAL CONDITIONS ......... .................. ...... ......................... 5 4.0 INSTRUCTIONS ...... .. .................................................................... ......................... ..... 6 4.1 MODES 1, 2, 3, or 4 ... .... ............. ..... .... ... ............................ .... ................. .... ... ... .. ....... 6 4.1.1 Borated Water Source ........................ ......................................................................... 6 4.1.2 Bo ration Flow paths .. .. .............. ........ ...... ... .................. .. ...... ..... ...... ............................. 8 4.2 MODES 5 or 6 .......................................... ............... ...... ............................................ 11 4.2.1 Borated Water Source ................. ... ...... .. ..................... ................ .............................. 11 4.2.2 Boration Flow Paths ........... ...... .. .... ........... .......................... ..... ................................. 13 5.0 RESTORATION AND DOCUMENTATION .. .. .............. ............................................. 18 6.0 ACCEPTANCE CRITERIA ..................................... .. .. .... .. ..... .... ........ .. ...... ..... .... ....... 19

7. 0 RECORDS ... .............................................................................................................. 20

8.0 REFERENCES

AND COMMITMENTS ............ ....................... .. ................................ 20 ATTACHMENTS ATTACHMENT 1 Combined BAMT Calculations ... .. ................ ...... .......................... 22 ATTACHMENT 2 Volume Vs Stored BAMT Concentration Curve .......................... . 24 JPM A-3 Page 10

REVISION NO.: PROCEDURE TITLE : PAGE: 12 BORATION FLOWPATH AND SOURCES 4 of 24 PROCEDURE NO .: 2-0SP-02 07 ST. LUCIE UNIT 2 1.0 PURPOSE 1.1 Purpose The purpose of this Surveillance is to ensure boration flowpaths and sources are lined up and in service per Technical Specifications. 1.2 Scope 1.2.1 Requirement This procedure satisfies the following Technical Specifications for Boration Systems:

• 3/4.1.2.1 , Flowpaths - Shutdown
• 3/4.1.2.2, Flowpaths - Operating
• 3/4. 1.2. 7, Borated Water Sources - Shutdown
• 3/4.1.2.8, Borated Water Sources - Operating 1.2.2 Frequency
• At least once per seven days for Borated Water Sources
• At least once per 31 days for Boration Flowpaths 1.2.3 Applicability
• MODES 1, 2, 3, and 4 - Operating
• MODES 5 and 6 - Shutdown 1.2.4 MODE Restrictions None JPtvi A-3 Page 11

REVISION NO. : PROCEDURE TIT LE: PAGE: 12 BORATION FLOWPATH AND SOURCES 5 of 24 PROCEDURE NO . 2-0SP-02 .07 ST. LUCIE UNIT 2 2.0 PRECAUTIONS AND LIMITATIONS 2.1 Precautions

1. One ECCS subsystem charging pump shall satisfy the flow path requirements of Specification 3.1.2.2.a or 3.1.2.2.d. The second ECCS substation charging pump shall satisfy the flow requirements of Specification 3.1 .2.2.b or 3.1.2.2.e.

2.2 Limitations

1. When in MODES 1, 2, 3, and 4, minimum RWT level is administratively limited to greater than or equal to 33 feet.

(Section 8.2, Commitment 1) 3.0 PREREQUISITES AND INITIAL CONDITIONS 3.1 Prerequisites None 3.2 Initial Conditions None JPM A-3 Page 12

REVISION NO.: PROCEDURE TITL E: PAGE: 12 BORATION FLOWPATH AND SOURCES 6 of 24 PROCEDURE NO.: 2-0SP-02.07 ST. LUCIE UNIT 2 4.0 INSTRUCTIONS 4.1 MODES 1, 2, 3, or 4 4.1.1 Borated Water Source

1. DOCUMENT the present MODE:

Present MODE: 1 2 3 4 (circle one) NOTE Satisfactory compliance of either the RWT and the combined BAM Tanks OR two of the following three :

• RWT
• 2A BAM Tank
• 2B BAM Tank assures compliance to the applicable Technical Specifications 3.1. 2.8.

2. VERIFY the following borated water source parameter:

• RWT parameters :

                                               *~

VARIABLE INDICATION REQUIRED SPEC OPERABLE (-../) LI S-07-2A Ft. ~ ~33 Ft. D SAT 0 UNSAT LIS-07-28 ...... Ft. ~33 Ft. D SAT 0 UNSAT LIS-07-2C ) Ft. ~33 Ft. OSAT 0 UNSAT LIS-07-20 " Ft. ~33 Ft. 0 SAT 0 UNSAT

                           'V RWf Cb                      ppm      >1900 ppm and <2200 ppm       D SAT    0 UNSAT RWf Temp                        OF            >55°F and <100°F       DSAT     D UNSAT

• 2A BAM Tank parameters :

VARIABLE INDICATION REQUIRED SPEC OPERABLE (../) LIA-2206 _ _ % X 92 gal/% =__ gal Variable D SAT 0 UNSAT Cb ppm 5420 to 6119 ppm (Attachment 2) TEMP OF >55°F OSAT D UNSAT JPM A-3 Page 13

REV ISION NO_ : PROCEDURE TITLE: PAGE: 12 BORATION FLOWPATH AND SOURCES 7 of 24 PROCEDURE NO.: 2-0SP-02 .07 ST. LUCIE UNIT 2 4.1.1 Borated Water Source (continued)

2. (continued)

• 2B BAM Tank parameters:

VARIABLE INDICATION REQUIRED SPEC OPERABLE (.../) LIA-2208 _ _ % X 92 gal/% =__gal Variable D SAT D UNSAT Cb ppm 5420 to 6119 ppm (Attachment 2) TEMP OF >55°F D SAT D UNSAT

3. IF crediting for combined BAM Tanks, THEN PERFORM Attachment 1, Combined BAMT Calculations.

4. VERIFY the following Acceptance Criteria are met:

                                                       -~

Acceptance Criteria Results (-../) Borated Water Sources meet D SAT D UNSAT requirements of T .S. 3.1.2 .8 Performed By:

                    ~----------------------

PrinUSign Date JPM A-3 Page 14

REVISION NO.: PROCEDURE TITLE: PAGE: 12 BORATION FLOWPATH AND SOURCES 8 of 24 PROCEDURE NO .: 2-0SP-02 .07 ST. LUCIE UNIT 2 4.1.2 Boration Flow paths

1. DOCUMENT the present MODE .

Present MODE: 1 2 3 4 (circle one) NOTE To be used as a source at least one of the following must be OPERABLE:

• 2A BAMT
• 28 8AMT
• Combined volume of 2A and 28 BAMT

2. IF crediting the BAMT flow path,

• BAMT
• Gravity flow path
• Charging Pump(s)

THEN VERIFY the following : (all located on RTGB-205 except V2598) Component Description Required Position OPERABLE (-1') CHARGING LINE VALVE OPEN V2598 no1e1 D SAT D UNSAT (RTGB-203) SE-02-2 LOOP 2A2 CHARGING ISOL OPEN no1e1 D SAT D UNSAT SE-02-1 LOOP 2B1 CHARGING ISOL OPEN note 1 0 SAT D UNSAT V2509 BA Gravity Feed 2A CLOSED Note 2 D SAT 0 UNSAT V2508 BA Gravity Feed 2B CLOSED Note 2 D SAT 0 UNSAT V2523 CHARGING LINE (Key 42) LOCKED OPEN 0 SAT D UNSAT Note 1 These valves may be in different positions during PZR cooldown, when the Charging System is shutdown , and other plant evolutions at the discretion of the US/SM . Note 2 Valve is capable of being operated. JPM A-3 Page 15

REVISION NO .: PROCEDURE TITLE: PAGE: 12 BORATION FLOWPATH AND SOURCES 9 of 24 PROCE DURE NO.: 2-0SP-02 .07 ST. LUCIE UNIT 2 4.1.2 Bo ration Flow paths (continued) NOTE To be used as a source , at least one of the following must be OPERABLE:

• 2A BAMT
• 28 BAMT
• Combined volume of 2A and 28 BAMT

3. IF crediting the following flow path:

• BAMT
• BAMP(s)
• Charging Pump(s)

THEN VERIFY the following on RTGB-205: Component Description {- ,/ Required Position OPERABLE(./') V2509 BA Gravity Feed 2A I CLOSED Note 1 D SAT D UNSAT V2508 BA Gravity Feed 2B CLOSED Note 1 DSAT D UNSAT V2650 TANK 2A RECIRC VALVE OPEN D SAT D UNSAT V2651 TANK 2B RECIRC VALVE OPEN D SAT D UNSAT REFUEL WATER TO CHARGING V2504 CLOSED D SAT D UNSAT PUMPS V2598 CHARGING LINE VALVE (RTGB-203) OPEN Note2 D SAT D UNSAT SE-02-1 LOOP 281 CHARGING ISOL OPEN Note2 D SAT D UNSAT SE-02-2 LOOP 2A2 CHARGING !SOL OPEN Note2 D SAT D UNSAT V2523 CHARGING LINE (Key 42) LOCKED OPEN D SAT D UNSAT V2514 .EMERGENCY BORATE CLOSED Note 3 D SAT D UNSAT Nole 1 If NO suction flow path is available to the Charging Pumps, consideration should be given to maintaining one or both Gravity Feed Valves OPEN. Note 2 These valves may be in different positions during PZR cooldown, when the Charging System is shutdown, and other plant evolutions at the discretion of the US/SM. Note 3 Valve is capable of being operated. JPM A-3 Page 16

REVISION NO .: PROCEDURE TITLE: PAGE: 12 BORATION FLOWPATH AND SOURCES 10 of 24 PROCEDURE NO.: 2-0SP-02.07 ST. LUCIE UNIT 2 4.1.2 Boration Flow paths (continued)

4. IF crediting the following flow path:

• RWT
• Charging Pumps(s)

THEN VERIFY the following on RTGB-205: Component Description Required Position OPERABLE(./) REFUELING WATER TO CHARGING CLOS ED Note 1 Note 2 V2504 0 SAT D UNSAT PUMPS SE-02-1 LOOP 281 CHARGING ISOL OPEN note 1 D SAT 0 UNSAT SE-02-2 LOOP 2A2 CHARGING ISOL OPEN note 1 0 SAT 0 UNSAT CHARGING LINE VALVE V2598 OPEN D SAT 0 UNSAT (RTGB-203) V2523 CHARGING LINE (Key 42) LOCKED OPEN 0 SAT 0 UNSAT Note 1 These valves may be in different positions during PZR cooldown, when the Charging System is shutdown , and other plant evolutions at the discretion of the US/SM. Note 2 Valve is capable of being operated . ,

5. VERIFY the following Acceptance Criteria are met:

Acceptance Criteria Results (--./) Two Boration Flow Paths meet the D SAT D UNSAT requirements of T.S. 3.1.2.2 Performed By:

                    ~~~,.----~~~~~~~~~~~~~~~~~~~

PrinUSign Date JPM A-3 Page 17

REVISION NO.: PROCEDURE TIT LE : PAGE: 12 BORATION FLOWPATH AND SOURCES 11 of 24 PR OCEDURE NO .: 2-0SP-02 .07 ST. LUCIE UNIT 2 4.2 MODES 5 or 6 4.2.1 Borated Water Source

1. DOCUMENT the present MODE.

Present MODE : 5 6 (circle one) NOTE Satisfactory compl iance of one of the following three :

• RWT
• 2A BAM Tank
• 2B BAM Tank assures compliance to the applicable Technical Specifications 3.1.2.7.

2. VERIFY the following borated water source parameters :

• RWT parameters :

VARIABLE INDICATION REQUIRED SPEC OPERABLE (.t') LIS-07-2A Ft. ~8.6 Ft. D SAT D UNSAT LIS-07-28 1..-:* Ft. ~8 . 6 Ft. D SAT D UNSAT LIS-07-2C Ft. ~8 . 6 Ft. D SAT D UNSAT LIS-07-20 / )

                                  ~

Ft. ~8 . 6 Ft. D SAT D UNSAT RWTCb ppm ~1900 ppm D SAT D UNSAT RWT Temp OF >40°F and <120°F DSAT D UNSAT

• 2A BAM Tank parameters :

VARIABLE INDICATION REQUIRED SPEC OPERABLE (.t') LIS -2206 _ _ % X 92 gal/% =__gal  ;::3550 gallons D SAT D UNSAT Cb ppm 5420 to 6119 ppm D SAT D UNSAT TEMP OF >55°F D SAT D UNSAT JPM A-3 Page 18

REVI SION NO.: PROCEDURE T ITLE: PAGE: 12 BORATION FLOWPATH AND SOURCES 12 of 24 - PROCEDURE NO.: 2-0SP-02 .07 ST. LUCIE UNIT 2 4.2.1 Borated Water Source (continued)

2. (continued)

• 28 BAM Tank parameters:

VARIABLE INDICATION REQUIRED SPEC OPERABLE(./) LIS-2208 _ _% X 92 gal/% =_ _ gal ~3550 gallons 0 SAT 0 UNSAT Cb ppm 5420 to 6119 ppm OSAT 0 UNSAT TEMP OF >55°F 0 SAT 0 UNSAT

3. VERIFY the following Acceptance Criteria are met:

Acceptance Criteria Results(~) Borated Water Source meets OSAT 0 UNSAT requirement of T .S. 3.1.2.7 . Performed By: ~~~~~~~~~~~~~~~~~~~~~~~ PrinUSign Date JPM A-3 Page 19

REVISION NO.: PROCEDURE T ITL E: PAGE: 12 BORATION FLOWPATH AND SOURCES

• 13of24 PROCEDUR E NO.:

2-0SP-02 .07 ST. LUCIE UNIT 2 4.2.2 Boration Flow Paths

1. DOCUMENT the present MODE:

Present MODE: 5 6 (circle one) NOTE At least one BAMT shall be OPERABLE.

2. IF cred iting the following flow path :

• BAMT
• Gravity flow path
• Charging Pump(s)

THEN VERIFY the following on RTGB-205: Component Description ~ Required Position OPERABLE (v") (Circle One) SE-02-2 OPEN/CLOSED Note 1 D SAT D UNSAT LOOP 2A2 CHARGING ISOL (Circle One) SE-02-1 OPEN/CLOSED Note 1 D SAT D UNSAT LOOP 281 CHARGING ISOL V2509 BA Gravity Feed 2A CLOSED Note 2 D SAT D UNSAT V2508 BA Gravity Feed 28 CLOSED Note 2 D SAT D UNSAT CHARGING LINE VALVE V2598 OPEN D SAT D UNSAT (RTGB-203) V2523 CHARGING LINE (Key 42) LOCKED OPEN D SAT D UNSAT Note 1 These valves may be in different positions during PZR cooldown , when the Charging System is shutdown , and other plant evolutions at the discretion of the US/SM . Note 2 Va lve is capable of being operated . JPM A-3 Page 20

REVISION NO.: PROCEDURE TITLE: PAGE: 12 BORATION FLOWPATH AND SOURCES 14 of 24 PROCE DURE NO.: 2-0SP-02.07 ST. LUCIE UNIT 2 4.2.2 Boration Flow Paths (continued) NOTE At least one BAMT SHALL be OPERABLE.

3. IF cred iting the following flow path:

• BAMT
• BAMP(s)
• Charging Pump(s)

THEN VERIFY the following on RTGB-205 : Component Description Required Position OPERABLE (v") V2509 BA Gravity Feed 2A CLOSED D SAT D UNSAT V2508 BA Gravity Feed 28 CLOSED 0 SAT D UNSAT V2523 CHARGING LINE (key 42) ,.. LOCKED OPEN D SAT 0 UNSAT CHARGING LINE VALVE pr V2598 OPEN D SAT 0 UNSAT (RTGB-203) - (Circle One) SE-02-2 OPEN/CLOSED Note 1 0 SAT D UNSAT LOOP 2A2 CHARGING ISOL (Circle One) SE-02-1 OPEN/CLOSED Note 1 DSAT 0 UNSAT LOOP 281 CHARGING ISOL V2514 EMERGENCY BORATE CLOSED Nol e 2 0 SAT D UNSAT Nole 1 These valves may be in different positions during PZR cooldown , when the Charging System is shutdown , and other plant evolutions at the discretion of the US/SM . Note 2 Valve is capable of being operated . JPM A-3 Page 21

REVIS ION NO.: PROCEDURE TITLE: PAGE: 12 BORATION FLOWPATH AND SOURCES 15 of 24 PROCEDURE NO.: 2-0SP-02 .07 ST. LUCIE UNIT 2 4.2.2 Boration Flow Paths (continued)

4. IF cred iting the following flow path :

• RWT
• Charging Pumps(s)

THEN VERIFY the following : (all located on RTGB-205 except V2598) Component Description Required Position OPERABLE (v) REFUEL WATER TO CHARGING V2504 OPEN 0 SAT 0 UNSAT PUMPS ,"..

                                                                               ~

V2523 CHARGING LI NE (key 42) OPEN D SAT D UNSAT CHARGING LINE VALVE OPEN Note1orNo1e2 V2598 D SAT D UNSAT (RTGB-203) LOOP 2A2 CHARG ING ISOL (C ircle One) SE-02-2 OPEN/CLOSED Nole 1 DSAT D UNSAT LOOP 281 CHARGING !SOL (Circle One) SE-02-1 OPEN/CLOSED Note 1 0 SAT 0 UNSAT ( V2501 VCT OUTLET VALVE CLOSED 0 SAT 0 UNSAT Note 1 These valves may be in different positions during PZR cooldown , when the Charging System is shutdown , and other plant evolutions at the discretion of the US/SM . Note 2 Valve is capable of being operated . JPM A-3 Page 22

REVISIO N NO.: PROCEDUR E TITLE: PAGE: 12 BORATION FLOWPATH AND SOURCES 16 of 24 PROCEDURE NO.: 2-0SP-02 .07 ST. LUCIE UN IT 2 4.2.2 Boration Flow Paths (continued)

5. IF crediting the following flow path :

• RWT
• 2A HPSI Pump THEN VERIFY the following on RTGB-206:

Required Component Description OPERABLE (*I') Position MV-07-1 A SUCTION FROM RWT A TRAIN OPEN 0 SAT D UNSAT PUMP 2A DISCHARGE VALVE OPEN V3656 Note 1 0 SAT D UNSAT (Key 67) HCV-3617 HEADER A TO LOOP 2A2 VALVE CLOSED Note 2 0 SAT 0 UNSAT HCV-3627 HEADER A TO LOOP 2A1 VALVE CLOSED Note 2 0 SAT D UNSAT HCV-3637 HEADER A TO LOOP 281 VALVE CLOSED Note 2 0 SAT D UNSAT HCV-3647 HEADER A TO LOOP 282 VALVE CLOSED Note 2 0 SAT D UNSAT Note 1 These valves may be in different positions during PZR cooldown , when the Charging System is shutdown , and other plant evolutions at the discretion of the US/SM . Note2 Valve is capable of being operated .

6. IF cred iting the following flow path:

• RWT
• 28 HPSI Pump THEN VERIFY the following on RTG~-206 :

Required Component Description OPERABLE (-1') Position MV-07-18 SUCTION FROM RWT 8 TRAIN OPEN 0 SAT D UNSAT V3654 PUMP 28 DISCHARGE VALVE (Key 65) OP EN Note 1 DSAT 0 UNSAT HCV-3616 HEADER 8 TO LOOP 2A2 VALVE CLOSED Note 2 0 SAT D UNSAT HCV-3626 HEADER B TO LOOP 2A1 VALVE CLOSED Note2 0 SAT 0 UNSAT HCV-3636 HEADER B TO LOOP 281 VALVE CLOSED Note 2 0 SAT D UNSAT HCV-3646 HEADER B TO LOOP 282 VALVE CLOSED Note 2 0 SAT D UNSAT Note 1 These valves may be in different positions during PZR cooldown , when the Charging System is shutdown , and other plant evolutions at the discretion of the US/SM. Note 2 Valve is capable of being operated . JPM A-3 Page 23

REVISION NO.: PROCEDURE T ITLE : PAGE: 12 BORATION FLOWPATH AND SOURCES 17 of 24 PROCEDURE NO .: 2-0SP-02.07 ST. LUCIE UNIT 2 4.2.2 Boration Flow Paths (continued)

7. VERIFY the following Acceptance Criteria are met:

Acceptance Criteria Results (-../) One Boration Flow Path meets 0 SAT 0 UNSAT requirement of T.S. 3.1.2.1. Performed By:

                 ~~~~~~~~~~~~~~~~~~~~---=-,-----~~

PrinUSign Date JPM A-3 Page 24

REVISION NO.: PROCEDURE TITLE : PAGE: 12 BORATION FLOWPATH AND SOURCES 18 of 24 PROCEDURE NO.: 2-0SP-02.07 ST. LUCIE UNIT 2 5.0 RESTORATION AND DOCUMENTATION 5.1 Restoration None 5.2 Documentation I have reviewed the requirements of this procedure including other surveillances performed during this procedure, if any (i .e., data sheet(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:

                  --------------------~

SM/US (Print/Sign) Date Remarks: JPM A-3 Page 25

REVIS ION NO. : PROCEDURE TITLE: PAGE: 12 BORATION FLOWPATH AND SOURCES 19 of 24 PROCEDURE NO.: 2-0SP-02 .07 ST. LUCIE UNIT 2 6.0 ACCEPTANCE CRITERIA

1. All Acceptance Criteria in the following steps are satisfactory:

Acceptance Criteria Steps Section 4.1.1 , Step 4 Section 4 .1.2, Step 5 Section 4.2.1, Step 3 Section 4.2.2, Step 7

                                                                /
                                                               *r '

Reviewed By : ~~~~~~~~~~~~~~~~~~~~~ SM/US (PrinUSign) Date JPM A-3 Page 26

REVISION NO .: PROCEDURE TITLE: PAGE: 12 BORATION FLOWPATH AND SOURCES 20 of 24 PROCE DURE NO .: 2-0SP-02.07 ST. LUCIE UNIT 2 7.0 RECORDS The completed copy of this procedure shall be maintained in the plant files in accordance with RM-AA-100-1000 , Processing Quality Assurance Records .

8.0 REFERENCES

AND COMMITMENTS 8.1 References 8.1 .1 Implementing References

1. T.S. 3.1.2.1 Boration Flowpaths - Shutdown

2. T.S. 3.1.2.2 Boration Flowpaths - Operating

3. T.S . 3.1.2.7 Borated Water Sources - Shutdown

4. T.S. 3.1.2.8, Borated Water Sources - Operating 8.1.2 Developmental Reverences

1. Drawings

• P&ID 2998-G-078, Sht 1058, Auxiliary Pumps
• P&ID 2998-G-078, Sht 120, Chemical and Volume Control System
• P&ID 2998-G-078 Sht 121A, Chemical and Volume Control System P&ID 2998-G-078 Sht 1218, Chemical and Volume Control System P&ID 2998-G-078 Sht 122, Chemical and Volume Control System
• 2998-G -078, Sheet 130A, Flow Diagram Safety Injection System
• 2998-G-078 , Sheet 131A, Flow Diagram Safety Injection System JPM A-3 Page 27

REVI SION NO.: PROCEDURE T ITLE : PAGE : 12 BORATION FLOWPATH AND SOURCES 21 of 24 PROCE DURE NO.: 2-0SP-02 .07 ST. LUCIE UNIT 2 8.1.2 Developmental Reverences (continued)

2. Updated Final Safety Analysis Report (UFSAR)

• Section 7. 7 .1.1, Control Systems
• Section 9.3.4, Chemical and Volume Control System

3. EC 246506, Flexible Hose Installation 8.1.3 Management Directives None 8.2 Commitments

1. Response to request for additional information regarding Bulletin 2003-01 , "Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized Water Reactors," dated May 20, 2005, L-2005-124. (Section 2.2, Step 1)

JPM A-3 Page 28

REVISION NO.: PROCEDURE TITLE: PAGE: 12 BORATION FLOWPATH AND SOURCES 22 of 24 PROCEDURE NO.: 2-0SP-02.07 ST. LUCIE UNIT 2 ATTACHMENT 1 Combined BAMT Calculations (Page 1 of 2)

1. RECORD the following parameters:

VARIABLE INDICATION CA LC ULA TION SPEC LIA-2206  %  % X 92 gal/%= gal N/A 2A BAM Cb ppm N/A NIA 2A BAM TEMP OF NIA ,/

                                                                                     >55°F LIA-2208                   %           % X 92 gal/%=       ,.

r gal NIA 2B BAM Cb ppm NIA '- N/A 2B BAM TEMP OF N/A ~* >55°F ( "'-.,'\

2. PERFORM the following calculations for combined BAMT volume and concentration :

A. CALCULATE the volumetric concentration of 2A BAMT as follows : 2A BAMT Vol Cone = (A) x (B) where : A = 2A BAMT Volume (gal) B = 2A BAMT Boron Concentration (ppm) 2A BAMTYol Conc= _ _ _ x _ _ _ = _ _ _ _ _ gal ppm CALCULATE the volumetric concentration of 2B BAMT as follows : 28 BAMT Vol Cone= (C) x (0) where: C = 28 BAMT Volume (ga l) D = 28 BAMT Boron Concentration (ppm) 2BBAMT Yo1Conc = _ _ _ x _ _ _ = _ _ _ _ _ galppm JPM A-3 Page 29

REVISION NO.: PROCED URE TITLE: PAGE: 12 80RATION FLOWPATH AND SOURCES 23 of 24 PROCEDURE NO.: 2-0SP-02 .07 ST. LUCIE UNIT 2 ATTACHMENT 1 Combined BAMT Calculations (Page 2 of 2)

2. (continued)

C. CALCULATE the combined BAMT volume as follows : where : A = 2A BAMT Volume (gal) 8 = 28 8AMT Volume (gal) CombinedBAMTYol =- - - + - - -- =- -- - - - gal D. CALCULATE the combined BAMT concentration as follows : Combined BAMT Cone = ( (A) + (B) ] (C) where: A = 2A 8AMT Vol Cone (Attachment 1, Step 2.A) 8 = 28 8AMT Vol Cone (Attachment 1, Step 2.8) C = Combined BAMT Volume (Attachment 1, Step 2.C) ( )+ ( ) Combined BAMTConc =~-(-~)-~-----ppm

3. VERIFY the combined BAM Tanks meet the requirements of Attachment 2, Volume Vs Stored BAMT Concentration Curve, AND both tank temperatures are greater than 55°F.

Performed By:

                   - - - - - - - - - - PrinUSign - -- - -- - - - - - --                      Date JPM A-3 Page 30

REVISION NO.: PROCEDURE TITLE : PAGE : 12 BORATION FLOWPATH AND SOURCES 24 of 24 PROCEDURE NO. : 2-0SP-02 .07 ST LUCIE UNIT 2 ATTACHMENT 2 Volume Vs Stored BAMT Concentration Curve (Page 1 of 1) 10000 9000 -cI ll 0 - tO C'l 8000 w UNACCEPTABLE

E OPERATION

...J 0 > 7000 ~ 2 c:( co 2 2 6000 z 2 3.00 3.10 3.20 3.30 3.40 3.50 (5245 PPM) (5420 PPM) (5594 PPM) (5769 PPM) (5944 PPM) (6119 PPM)1 STORED BAMT CONCENTRATION (wt% Boric Acid and PPM Boron) JPM A-3 Page 31

REVISION NO.: PROCEDURE TITLE: PAGE : 12 BORATION FLOWPATH AND SOURCES 6 of 24 PROCEDURE NO.: 2-0SP-02 .07 ST. LUCIE UNIT 2 4.0 INSTRUCTIONS 4.1 MODES 1, 2, 3, or 4 4.1 .1 Borated Water Source

1. DOCUMENT the present MODE:

Present MODE: {5J 2 3 4 (circle one) NOTE Satisfactory compliance of either the RWT and the combined BAM Tanks OR two of the following three:

• RWT
• 2A BAM Tank
• 2B BAM Tank assures compliance to the applicable Techn ical Specifications 3.1.2.8.

2. VERIFY the following borated water source parameter:

• RWT parameters :

VARIABLE INDICATION .\ REQUIRED SPEC OPERABLE (") LIS-07-2A >'/. 3 Ft.

                                                             ~33   Ft.         EfsAT      0 UNSAT LIS-07-28         1,1.f,/   Ft.                     ~ 33  Ft.         ITTAT      0 UNSAT LIS-07-2 C         >).<6    Ft.                     ~33   Ft.         13"'SAT    0 UNSAT LIS-07-20          'f'f.D   Ft.                     ~33   Ft.         ~AT        O UNSAT RWTCb           (.o'1'f ppm       > 1900 ppm and <2200 ppm           B"'SAT     0 UNSAT RWT Temp            1 '&      OF               >55°F and <100°F        GYSAT      0 UNSAT

• 2A BAM Tank parameters:

VARIABLE INDICATION REQUIRED SPEC OPERABLE (-.J) LIA-2206 <t,7 .o % X 92 gal/% =~gal Variable B"§AT D UNSAT Cb 51b 7 ppm 5420 to 6119 ppm (Attachment 2) TEMP /09 OF >55°F G"SAT D UNSAT JPM A-3 Page 32

REVISION NO .: PROCEDURE TITLE : PAGE: 12 BORATION FLOWPATH AND SOURCES 7 of 24 PROCEDURE NO .: 2-0SP-02 .07 ST. LUCIE UNIT 2 4.1.1 Borated Water Source (continued)

2. (continued)

• 2B BAM Tank parameters:

8~.o 772,$;? VARIABLE ~o INDICATION J.$:2.-o REQUIRED SPEC OPERABLE (--l) LIA-2208 ~% X 92 gal/%= ~ gal Variable 0 SAT GYUNSAT Cb 5"<3:>"6 ppm 5420 to 6119 ppm (Attachment 2) TEMP 105" OF >55°F urSAT 0 UNSAT

3. IF crediting for combined BAM Tanks, THEN PERFORM Attachment 1, Combined BAMT Calculations .

4. VERIFY the following Acceptance Criteria are met:

Acceptance Criteria R_e sults (.../) Borated Water Sources meet rni'AT 0 UNSAT requirements of T.S. 3.1.2.8 Performed By: ~~~~~~~~~~~~~~~~~~~~~~ PrinUSign Date JPM A-3 Page 33

REVISION NO.: PROC EDURE T ITLE: PAGE : 12 BORATION FLOWPATH AND SOURCES 24 of 24 PROCEDU RE NO.: 2-0SP-02.07 ST. LUCIE UNIT 2 ATTACHMENT 2 Volume Vs Stored BAMT Concentration Curve (Page1of1) 10000 9000 -"'c: 0 8000 ta UJ C'I UNACCEPTABLE ~

> OPERATION

...J 0 > 7000 I- ~ c:z: co ~ ~ 6000 z

E 4000 3.00 3.10 3.20 3.30 3.40 3.50 (5245 PPM) (5420 PPM) (5594 PPM) (5769 PPM) (5944 PPM) (6119 PPM)1 STORED BAMT CONCENTRATION (wt% Boric Acid and PPM Boron)

JPM A-3 Page 34

REACTIVITY CONTROL SYSTEMS FLOW PATHS -OPERATING LIMITING CONDITION FOR OPERATION 3.1 .2.2 At least two of the following three boron injection flow paths shall be OPERABLE :

a. One flow path from the boric acid makeup tank(s) with the tank meeting Specification 3.1.2.8 part a} orb), via a boric acid makeup pump through a charging pump to the Reactor Coolant System .

b. One flow path from the boric acid makeup tank(s) with the tank meeting Specification 3.1.2.8 part a) orb) , via a gravity feed valve through a charging pump to the Reactor Coolant System .

c. The flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System .

OR At least two of the following three boron injection flow paths shall be OPERABLE:

d. One flow path from each boric acid makeup tank with the combined tank contents meeting Specification 3.1.2.8 c), via both boric acid makeup pumps through a charging pump to the Reactor Coolant System .

e. One flow path from each boric acid makeup tank with the combined tank contents meeting Specification 3.1.2.8 c), via both gravity feed valves through a charging pump to the Reactor Coolant System .

f. The flow path from the refueling water storage tank, via a charging pump to the Reactor Coolant System .

APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE , restore at least two boron injection flow paths to the Reactor Coolant System to OPERABLE status within 72 hours or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to its COLR limit at 200 °F within the next 6 hours; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours. - ST . LUCIE - UNIT 2 3/4 1-8 Amendment No. 3, ~ . .W, .wa, 163 JPM A-3 Page 35

REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING SURVEILLANCE REQUIREMENTS 4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:

a. At least once per 24 hours, when the Reactor Auxiliary Building air temperature is below 55°F, by verifying that the solution temperature of the Boric Acid Makeup Tanks is above 55°F.

b. At least once per 31 days by verifying that each valve (manual, power-operated or automatic) in the flow path that is not locked, sealed , or otherwise secured in position, is in its correct position .

c. At least once per 18 months during shutdown by verifying that each automatic valve in the flow path actuates to its correct position on an SIAS test signal.

d. At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2a and 3.1 .2.2b delivers at least 40 gpm to the Reactor Coolant System.

ST. LUC IE - UNIT 2 3/4 1-Ba Amendment No. 40 JPM A-3 Page 36

• FPL St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE DETERMINE EXPOSURE LIMITS UNDER NORMAL CONDITIONS HLC 22 NRC RO Admin JPM A4 NRC RO Admin JPM A4 Page 1 of 7 JPM A-4 RO Page 1

JOB PERFORMANCE MEASURE Task: Determine Exposure Limits Under Normal Conditions Faulted JPM? No Facility JPM #: N/A KA #: 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. KA Rating: 3.2 / 3.7 Duty Area(s): N/A Task Information: N/A Task Standard: The JPM is complete when the student informs the examiner which workers can be used to perform the task without Site Vice President approval/authorization. Evaluation Location: Performance Level: Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

HPP-30, "Personnel Monitoring" RP-AA-101 , "Personnel Monitoring Program" Validation Time: 10 minutes Time Critical: NO Tools/Equipment/Procedures Needed:

• HPP-30,"Personnel Monitoring"
• RP-AA-101 ,"Personnel Monitoring Program" Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.
• None Radiological Protection and RWP Requirements:
• None NRC RO Admin JPM A4 Page 2 of 7 JPM A-4 RO Page 2

JOB PERFORMANCE MEASURE SPECIFIC DIRECTIONS:

• The task you are to perform is: Perform the Borated Water Sources surveillance - Unit 2.
• The performance level to be used for this JPM is Perform.
• During the performance of the task, I will tell you which steps to simulate or discuss.
• I will provide you with the appropriate cues for steps that are simulated or discussed.
• You may use any approved reference materials normally available in the execution of this task, including logs.

Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you. Initial Conditions Unit 2 is in a refueling outage and refueling equipment preparations are under way. The Refueling Machine Hoist Box will need to be rebuilt. The Hoist Box rebuild will take 45 minutes in a 2700 mR/hr field . It has been decided that this does NOT constitute a Planned Special Exposure nor is this task an Emergency. All four workers' current year's exposures are documented and up to date. Below are the employee's dose records: Current Year Current Year Contract FPL at St. total at all Consult. Lucie sites (TEDE} (TEDE) 1 350mR 2550 mR 2 550mR 2000 mR Current Year Current Year FPL FPL at St. total at all Employee Lucie sites (TEDE} (TEDE) 1 550mR 650 mR 2 450mR 450 mR Initiating Cue What dose would be received for each person and which employee(s) are allowed to rebuild the Hoist Box without the Site Vice President's approval? NRC RO Admin JPM A4 Page 3 of 7 JPM A-4 RO Page 3

JOB PERFORMANCE MEASURE START TIME: _ _ __ STEP 1: Calculates the dose the employee will receive performing the rebuild .

                                                                                               - - SAT STANDARD:     CALCULATES 2700 mR/hr x 45 minx 1 hr/60 min= 2025 mR.
                                                                                               - - UNSAT COMMENTS:

1 *~

                                                                                          /

I~ HP-2, FP&L Health Physics Manual \v( CRITICAL STEP 2: Determines Contract employee #1 "s FPL Site and Total for All Sites doses . STEP STANDARD: DETERMINES that Contract employee #1 will exceed 4500 mR/year for All Sites and will need the St. Vice President approval. Therefore Contract

                                                                                               - - SAT employee #1 can NOT be used.

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

                                                                                               - - UNSAT Lucie site and 4575 mR for all sites.

If asked - cue the examinee that the provided dose is the total dose received as read from the individual's TLD. COMMENTS:

                                       ~
                                            \,,

STEP 3: Determines Contract employee #2"s FPL Site and Total for All Sites doses. CRITICAL STEP STANDARD: DETERMINES that Contract employee #2 will exceed FPL Site but not the Total for All Sites dose limits. Therefore Contract employee #2 CAN NOT - - SAT be used. EXAMINERS NOTE: Contract employee #2 would receive 2575 mR for St. Lucie site and 4025 mR for all sites.

                                                                                               - - UN SAT COMMENTS:

NRC RO Admin JPM A4 Page 4 of7 JPM A-4 RO Page 4

JOB PERFORMANCE MEASURE STEP 4: Determines FPL employee #1s FPL Site and Total for All Sites doses. CRITICAL STEP STANDARD: DETERMINES that FPL employee #1 will exceed 2500 mR/year for St. Lucie Site and will need the St. Vice President approval. Therefore FPL SAT employee #1 can NOT be used. EXAMINERS NOTE: FPL employee #1 would receive 2575 mR for St. Lucie UNSAT site and 2675 mR for all sites . . COMMENTS: STEP 5: Determines FPL employee #2"s FPL Site and Total for All Sites doses. CRITICAL STEP STANDARD : DETERMINES that FPL employee #2will not exceed FPL Site and Total for All Sites dose limits. Therefore FPL employee #2 CAN be used. SAT EXAMINERS NOTE: FPL employee #2 would receive 2475 mR for St. Lucie site and 2475 for all sites. UN SAT COMMENTS: STEP (done): Candidate informs the Examiner that the task is complete. STANDARD: INFORMS the Examiner that the task is complete. EXAMINER'S CUE: TASK IS COMPLETE SAT COMMENTS: UNSAT END OF TASK STOP TIME: - - - - NRC RO Adm in JPM A4 Page 5 of 7 JPM A-4 RO Page 5

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK) Initial Conditions Unit 2 is in a refueling outage and refueling equipment preparations are under way. The Refueling Machine Hoist Box will need to be rebuilt. The Hoist Box rebuild will take 45 minutes in a 2700 mR/hr field . It has been decided that this does NOT constitute a Planned Special Exposure nor is this task an Emergency. All four workers' current year's exposures are documented and up to date. Below are the employee's dose records: Current Year Current Year Contract FPL at St. total at all Consult. Lucie sites (TEDE) (TEDE) 1 350 mR 2550 mR 2 550 mR 2000 mR Current Year Current Year FPL FPL at St. total at all Employee Lucie sites *- (TEDE) (TEDE) 1 550 mR 650mR 2 450mR 450mR Initiating Cue Which employee(s) are allowed to rebuild the Hoist Box without the Site Vice President's approval? JPM A-4 RO Page 6

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET ANSWER KEY HEALTH PHYSICS FORM HPP-30.12 RADIATION EXPOSURE EXTENSION REQUEST (Page 1 of 1) NOTE JOB DESCRIPTION - - - - -- - - -- - - - - - -- It is tho ro5ponsiblllty of each i n d ividual to be awure o f and k eep h is supervisor inf o n ned or hia curren t radia t io n ex s u re.

• All e x a u r* i n mnitm
• Recor-d Worl<e r'&

ln1t1a1s I ~I . ROqli.)05tcd Limit A nnui31 Expcauro DAtft 1 tra.t Accum St~tu* PID# _ _ _ _ _ _La _ e_._F_1_,.._1_______-+-__(_1~)--+-__s_ 11_ _ s_1_N_a_m e _ __,__A _n _ n_ ua_1 _..,__~ PSL Cu r Y_' -~-- g~&_ A~ _...__u_l_e_t*_m _ e -i RequesUng Supervisor Dale/Dept sit;; Annuel Do&e > 1 000 mrem Annual Dose >- 3000 mrem RP Mgr RP Mgr 1-R-coo-

      - rd
         - s_ C_he

_ o_k_e_d_ by _ Dos __l_m_ c_ try

                                           - : - -- - - - -- - - -D- o         _ tc

_ m= mo

                                                                                      - - - - -- - - - - - - i Plenl Oen Mg1                              Plant Gen Mgr Sile A n nual DotMt > 2500 rnrem Annunl f')Ot11;ft !Io 4500    m~m Enter in HP Computer t>y :                                                   Oerefrime                             RP Mgr                                RP Mgr Ptant Gen Mgr                         Plant Oen Mgr Site VP                               Site VP Record Status - Current Year I - lncc m lute        c

• Com le re Coniph~ t o f or F~ ~ni ployecs onty

                                                                                                                                                     <>_ _OPS OAT..__ _ _ _ _ __

(1) WOfker Compfetew

                                                                                                                                              ~--H-,rx~~~:R*u;;'---

svs_ ___,""-----

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HPP ::\0 Fl"l:A JPM A-4 RO Page 7

REVISION NO.: PROCEDURE TITLE: PAGE: 55 PERSONNEL MONITORING 39 of 88 PROCEDURE NO.: HPP-30 ST. LUCIE PLANT APPENDIX 6 AUTHORIZATION TO EXCEED ADMINISTRATIVE GUIDELINES (Page 1 of 4) 7 .0 Instructions: General This appendix contains the instructions necessary to authorize persons to exceed administrative exposure guidelines. 7.1 When an individual is expected to exceed his exposure guidelines, a Radiation Exposure Extension Request (HPP-30.12) shall be completed . NOTE A request for this extension should be made at least 8 hours prior to ex ectin the individual to exceed the administrative ex osure uidelines. 7.2 Before an extension is authorized , an investigation into the individual's radiation exposure history shall be conducted. 7 .3 §2 Authorization may be granted as long as the exposure limits in 10 CFR 20 are not exceeded. 7.4 §2 Administrative Exposure Guidelines

1. Any individual with non-documented current year exposure shall have their annual exposure guidelines set to the following doses:

A. TEDE 0.25 rem

8. Lens of eye 1.35 rem

c. Skin 4.5 rem D. Extremity 4.5 rem E. COE 4.5 rem

2. §2 An individual with a complete Form 4 for the current year may have their site annual dose guideline extended to 2500 mrem I yr by the Radiation Protection Manager Head and the Plant General Manager.

JPM A-4 RO Page 8

REVISION NO.: PROCEDURE TITLE: PAGE: 55 PERSONNEL MONITORING 40 of 88 PROCEDURE NO.: HPP-30 ST. LUCIE PLANT APPENDIX 6 AUTHORIZATION TO EXCEED ADMINISTRATIVE GUIDELINES (Page 2 of 4) 7.4 (continued)

3. §2 An individual with a complete Form 4 for the current year may have their site annual dose guideline extended to greater than 2500 mrem by the Radiation Protection Manager, the Plant General Manager and Site Vice President.

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

5. §2 The Plant General Manager and Radiation Protection Manager shall approve and the Site Vice President shall authorize all dose extensions above the annual guideline of 4500 mrem TEDE.

6. §2 After the TLD has been read and if the site annual TEDE is less than 2500 mrem, the individual may be allowed back into the Radiation Controlled Area until his I her annual TEDE (TLD results and EPD doses) reaches 2500 mrem.

7. Upon reaching an annual TEDE of 2500 mrem, the individual shall not be allowed to enter the Radiation ~ontrolled Area, unless extended > 2500 mrem I yr as required by step 7.4.4 above.

JPM A-4 RO Page 9

REVISION NO.: PROCEDURE TITLE: PAGE: 55 PERSONNEL MONITORING 41 of 88 PROCEDURE NO.: HPP-30 ST. LUCIE PLANT APPENDIX 6 AUTHORIZATION TO EXCEED ADMINISTRATIVE GUIDELINES (Page 3 of 4) NOTE Circumstances requiring extending an annual guideline should be documented . The documentation should include justification for the guideline extension and an evaluation of the individual's lifetime dose with res ect to the individual's a e. 7.5 HPP-30.12 Request for Exposure Extension Form

1. When an exposure extension is needed , the requesting supervisor completes the following items on the HPP-30.12:

A. RWP# B. Job description C. PIO# D. Name E. Signature F. Date G. Requested limit H. Obtains worker's initials to ensure the worker is aware a request for extension is being submitted. Then, I. Submits the completed form to the dosimetry office.

2. Dosimetry office personnel :

A. Review the current annual exposure. Note the date and time this exposure information is obtained from Health Physics computer system. B. Review the personnel exposure history files to verify the status of the records . Enter a "C" for complete or "I" for incomplete in the status box on the form HPP-30.12. - c. D. Sign and enter the date/time in the "Records Checked By" box. Advise the requesting supervisor that Form H PP-30 .12 is ready for the approval process. JPM A-4 RO Page 10

REVISION NO.: PROCEDURE TITLE: PAGE : 55 PERSONNEL MONITORING 42 of 88 PROCEDURE NO.: HPP-30 ST. LUCIE PLANT APPENDIX 6 AUTHORIZATION TO EXCEED ADMINISTRATIVE GUIDELINES (Page 4 of 4) 7.5 (continued)

3. The requesting supervisor retrieves the HPP-30.12 from the dosimetry office and routes it for the required approval signatures.

A. Requests approval signatures

1. RP Manager

2. Plant General Manager

3. Site VP (when applicable)

B. Form HPP-30.12 must be returned to the Dosimetry Office. NOTE The requesting supervisor should review a copy of the HPP-30.12 form to ensure there are sufficient qualified workers available since some workers ma not have received an extension.

4. Upon receipt of the approved HPP-30.12, Dosimetry personnel:

A. Enter the extensions into the RP computer system for those individuals with a "C" status (not to exceed the limits specified in HPP-30, Personnel Monitoring). B. Line through the individuals with an "I" status. Do not extend these individuals. C. Retain the original copy of the HPP-30.12 form . 7 .6 The administrative guidelines below should be followed when monitoring shallow (skin and extremity) dose:

1. When a person's annual shallow dose (skin or extremity) reaches 20 rem, the person's TLD should be read to update shallow dose results.

2. §2 When a person's annual shallow dose (skin or extremity) reaches 25 rem site dose or 45 rem all sites, the person shall be restricted from

- further entry into the RCA for the remainder of the year. END OF APPENDIX 6 JPM A-4 RO Page 11

REVISION NO.: PROGRAM TITLE: PAGE: 0 PERSONNEL MONITORING PROGRAM 16 of 16 PROGRAM NO.: RP-AA-101 NUCLEAR FLEET ATTACHMENT 1 FEDERAL AND ADMINISTRATIVE EXPOSURE LIMITS (Page 1 of 1) Radiation Workers 1 Exposure Category Administrative Limit Federal Limit

1. Deep Dose Equivalent. (DOE) See Item 7 See Item 7 2

2. Eye Dose Equivalent to Lens of the Eye. (LOE) Per Site Guidance 15,000 mrem/year 2

3. Shallow Dose Equivalent, Whole Body. (SOE, WB) Per Site Guidance 50,000 mrem/year 2

4. Shallow Dose Equivalent, Max Extremity. (SOE, ME) Per Site Guidance 50,000 mrem/year

5. Committed Effective Dose Equivalent. (CEDE) See Item 7 See Item 7 2

6. Committed Dose Equivalent, Maximally (COE) Per Site Guidance See Item 8 Exposed Organ.

7. Total Effective Dose Equivalent (TEDE) 3,000 mrem/year 5,000 mrem/year (DOE+ CEDE) (All Licensees) or 1,000 mrem/year (EDE+ CEDE) (At Site)

8. Total Organ Dose Equivalent (TODE) Per Site Guidance2 50,000 mrem/year (ODE+ COE)

9. Embryo/Fetus Dose of a Declared Per Site Guidance2 500 mrem/gestation Pregnant Radiation Worker. - 50 mrem/month 3

10. Planned Special Exposures *' ) " (TEDE, LOE Per Site Guidance 2

Per 10CFR20.1206 SOE and 4

                                      ..... '\'   .*     TODE)

1. Radiation Workers include Temporary RCA Workers/Escorted Radiation Workers . These limits are based on occupational dose received at all licensed facilities for the current year, except where noted.

2. See individual site guidance for Administrative Limit equal to or below Federal Limit

3. A lower federal limit of 50 mrem/gestation may apply based on dose to an embryo/fetus prior to declaration, per 10CFR20.1208.

4. Planned Special Exposures have exposure limits applicable to all dose categories.

JPM A-4 RO Page 12

REVISION NO.: PROCEDURE TITLE: PAGE: 55 PERSONNEL MON ITORING PROCEDURE NO.: 76 of 88 HPP-30 ST. LUCIE PLANT HEAL TH PHYSICS FORM HPP-30.12 RADIATION EXPOSURE EXTENSION REQUEST (Page 1 of 1) ):> JOB DESCRIPTION - - - - - - - - - - - - NOTE

                                                                                                                                                                                                                    -z_

It is the respo nsibility o f each ind ividual to be aware of and kee p his superviso r informed of his c urre nt radiation ex posure . *All e xoosure in mrem * (J\ I (" ..;', 1 \

                                                                     ...... J .
                                                                 \. )/J               Worker's Requested Limit            Annual Exposure Date

• I ~

I Record Initials Time :

                                                                                                                                                       *--                                   Accum Status     PIO#                  Last Name, First           I.         (1)            Site                 Annua l        PSL                  Cur Yr             Age      Lifetime I

1'l Jr.*

                                                                    .... -~
                                                                                           )    \ '*\       ~

I I ... I f.

                                                                                                      .\ (......

I ( /

                                                                                                                                //

I

                                                                                                                                                                                                            ')

Requesting Supervisor* Date/Dept ......... APPROVALS

                                                                                                          /             Site Annual Dose > 1000 mrem Annual Dose > 3000 mrem RP Mgr RP Mgr                                                -(

Records Checked by Dosimetry: Date/Time 7 Plant Gen Mgr

                                                                                                                                          ~
                                                                                                                                                   \

Plant Gen Mgr Site Annual Dose > 2500 mrem AnnuaTDose > 4500 mrem Enter in HP Computer by: Date!Time RP Mgr RP Mgr Plant Gen Mgr (,* Plant Gen Mgr Record Status - Current Year

                                                                                                        \........... ........._

Site VP I Site VP I - Incomplete C - Comolete *-;*,

                                                                                                                                                                              . '                            ~

Complete for FPL employees only I,

                         !r Completes OAlE DOCT S_ _OPS J:'JW"'A
                                                                                                                                                                        ),./{/

DOCN !jPN~l2 ,  ; SYS HP ' ' COMP ITM HPP-30-F09 Form Rev.si on

• 1

REVISION NO.: PROCEDURE TITLE: PAGE: 55 PERSONNEL MONITORING 39 of 88 PROCEDURE NO.: HPP-30 ST. LUCIE PLANT APPENDIX 6 AUTHORIZATION TO EXCEED ADMINISTRATIVE GUIDELINES (Page 1 of 4)

7.0 Instructions

General This appendix contains the instructions necessary to authorize persons to exceed administrative exposure guidelines. 7.1 When an individual is expected to exceed his exposure guidelines, a Radiation Exposure Extension Request (HPP-30.12) shall be completed. NOTE A request for this extension should be made at least 8 hours prior to ex ectin the individual to exceed the administrative ex osure uidelines. 7.2 Before an extension is authorized, an investigation into the individual's radiation exposure history shall be conducted. 7.3 §2 Authorization may be granted as long as the exposure limits in 10 CFR 20 are not exceeded. 7.4 §2 Administrative Exposure Guidelines

1. Any individual with non-documented current year exposure shall have their annual exposure guidelines set to the following doses:

A. TEDE 0.25 rem B. Lens of eye 1.35 rem

c. Skin 4.5 rem D. Extremity 4.5 rem E. COE 4.5 rem~-----------

An individual with a complete Forni 4 for the current year may have their site annual dose guideline extended to 2500 mrem I yr by the Radiation Protection Manager Head and the Plant General Manager. No JPM A-4 RO Page 14

REVISION NO.: PROCEDURE TITLE: PAGE: 55 PERSONNEL MONITORING 40 of 88 PROCEDURE NO.: HPP-30 ST. LUCIE PLANT APPENDIX 6 AUTHORIZATION TO EXCEED ADMINISTRATIVE GUIDELINES (Page 2 of 4) 7.4 (continued) --=------ S (IC: ...,.. f<_ .

 '7       '2SO               3. ,         An individual with a complete Form 4 for the current year may have the1
        -.. .{ p     ')?e.Ul-             site annual dose guideline extended to greater than 2500 mrem by the
 ~v~             .,                       Radiation Protection Manager, the Plant General Manager and Site Vice
 .,....                                   P 'dent.

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

5. §2 The Plant General Manager and Radiation Protection Manager shall approve and the Site Vice President shall authorize all dose extensions above the annual guideline of 4500 mrem TEDE.

6. §2 After the TLD has been read and if the site annual TEDE is less than

- 2500 mrem, the individual may be allowed back into the Radiation Controlled Area until his I her annual TEDE (TLD results and EPD doses) reaches 2500 mrem. Upon reaching an annual TEDE of 2500 mrem , the individual shall not be allowed to enter the Radiation Controlled Area , unless extended > 2500 mrem I yr as required by step 7.4.4 above. JPM A-4 RO Page 15

REVISION NO.: PROGRAM TITLE: PAGE: 0 PERSONNEL MONITORING PROGRAM 16 of 16 PROGRAM NO.: RP-AA-101 NUCLEAR FLEET ATTACHMENT 1 FEDERAL AND ADM INISTRATIVE EXPOSURE LIMITS (Page 1 of 1) Radiation Workers 1 "'> .,,, Exposure Category Administrative Limit Federal Limit

1. Deep Dose Equivalent. (ODE) See Item 7 See Item 7 2

2. Eye Dose Equivalent to Lens of the Eye. (LOE) Per Site Guidance 15,000 mrem/year

3. Shallow Dose Equivalent, Whole Body. (SOE, WB) Per Site Guidance 2 50,000 mrem/year

4. Shallow Dose Equivalent, Max Extremity. (SOE, ME) Per Site Guidance2 50,000 mrem/year

5. Committed Effective Dose Equivalent. (CEDE) See Item 7 See Item 7 2

6. Committed Dose Equivalent, Maximally (COE) Per Site Guidance See Item 8

_"'\. Exposed Organ . ~ ~

7. Total Effective Dose Equivalent  %,600 mrem/year " ]5,000 mrem/year (TEDE) (

(ODE+ CEDE) (All Licensees) or 1,000 mrem/year (EDE+ CEDE) (AtSite) ~

8. Total Organ Dose Equivalent (TODE) Per Site Guidance 2 50,000 mrem/year (ODE+ COE)

9. Embryo/Fetus Dose of a Declared Per Site Guidance 2 500 mrem/gestation 3

Pregnant Radiation Worker. 50 mrem/month 1o. Planned Special Exposures (TEDE, LOE Per Site Guidance 2 Per 10CFR20.1206 SOE and

                        ~/.      '\.. (l/    TODE) 4

1. Radiation Workers include Temporary RCA Workers/Escorted Radiation Workers. These limits are based on occupational dose received at all licensed facilities for the current year, except where noted.

2. See individual site guidance for Administrative Limit equal to or below Federal Limit

3. A lower federal limit of 50 mrem/gestation may apply based on dose to an embryo/fetus prior to declaration , per 10CFR20.1208.

4. Planned Special Exposures have exposure limits applicable to all dose categories .

JP M A-4 RO Page 16

• FPL St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE DETERMINE RADIATION EXPOSURE LIMITS UNDER EMERGENCY CONDITIONS HLC 22 NRC SRO Admin JPM A4 NRC SRO Admin JPM A4 Page 1 of6 JPM A-4 SRO Page 1

JOB PERFORMANCE MEASURE Task: Given a set of conditions, determine radiation exposure limits under emergency conditions . Faulted JPM? No Facility JPM #: No KIA: G2.3.4 Knowledge of radiation exposure limit under normal and emergency conditions. KIA Rating(s): 3.2 / 3.7 Duty Area(s) : NIA Task Information: 07200105 Task Standard: Determine radiation exposure limits under emergency conditions. Evaluation Location: Performance Level: Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

• EPIP-02, Duties and Responsibilities of the Emergency Coordinator Validation Time: 10 minutes Time Critical: NO Tools/Equipment/Procedures Needed:
• EPIP-02, Duties and Responsibilities of the Emergency Coordinator, Attachment 5.

Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.

• None Radiological Protection and RWP Requirements:
• None NRC SRO Admin JPM A4 Page 2 of 6 JPM A-4 SRO Page 2

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS SPECIFIC DIRECTIONS:

• The task you are to perform is: determine radiation exposure limits under emergency conditions.
• The performance level to be used for this JPM is Perform.
• During the performance of the task, I will tell you which steps to simulate or discuss.
• I will provide you with the appropriate cues for steps that are simulated or discussed.
• You may use any approved reference materials normally available in the execution of this task, including logs.
• Indicate to me that you have finished the assigned task by returning the Candidate Cue Sheet that I provided to you .

INITIAL CONDITIONS:

• A large break LOCA has occurred on Unit 2, six hours ago.
• The crew is implementing 2-EOP-03, LOCA
• All EOP-03 safety functions being met.
• There is a 10 gpm leak in the A Charging header.
• The leak is isolable, but the re-entry team could not close the valve due to a broken reach rod.
• Isolation of the leak is necessary to prevent equipment damage to 2A Charging Pump.
• 28 and 2C Charging Pumps are OPERABLE.
• Dose rates initially taken at the valve were 7.8 Rem/hour.
• A second re-entry team is prepared to attempt to repair and close the valve to isolate the leak. Time to complete the task is estimated to be 45 minutes.

INITIATING CUES: As the Emergency Coordinator (EC) you are responsible for authorizing the second re-entry team. In support of that decision, in accordance EPIP-02, Attachment 5, perform the following :

1. Determine the estimated dose the worker will be expected to receive .

2. Identify the TEDE and COE limits applicable for the task.

3. Determine whether or not the worker will be able to accomplish the task without exceeding the identified TEDE and CDE limits.

NRC SRO Admin JPM A4 Page 3 of 6 JPM A-4 SRO Page 3

JOB PERFORMANCE MEASURE ST ART TIME: - - - - STEP 1: CALCULATE estimated dose for the selected worker .. CRITICAL STANDARD: CALCULATES an estimated dose of 5.85 Rem , as follows : STEP (7.8 mR/hr) x (45 min) x (1 hr/60 min)= 5.85 Rem _ _ SAT EXAMINER'S CUE: None _ _ UNSAT COMMENTS: EPIP-02, Attachment 5 . STEP 2: IDENTIFY the TEDE and COE limits applicable for the task. CRITICAL STEP STANDARD: REFERS to EPIP-02, Duties and Responsibilities of the Emergency Coordinator, Attachment 5, Exposure Limits for Emergency Response Personnel , and DETERMINES that the applicable SAT exposure limits are 5 Rem TEDE and 50 Rem COE. EXAMINER'S CUE: None UNSAT COMMENTS: NRC SRO Admin JPM A4 Page 4 of 6 JPM A-4 SRO Page 4

JOB PERFORMANCE MEASURE STEP 3: DETERMINE whether or not the worker will be able to accomplish CRITICAL the task without exceeding the identified TEDE and COE limits. STEP STANDARD: DETERMINES that the work CANNOT perform the task. (5.85 Rem estimated dose is greater than the procedural limits of 5 SAT Rem TEDE and 50 Rem COE). UNSAT EXAMINER'S CUE: "This JPM is complete." COMMENTS: END OF TASK STOP TIME: _ _ __ NRC SRO Admin JPM A4 Page 5 of 6 JPM A-4 SRO Page 5

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

• A large break LOCA has occurred on Unit 2, six hours ago.
• The crew is implementing 2-EOP-03, LOCA
• All EOP-03 safety functions being met.
• There is a 10 gpm leak in the A Charging header.
• The leak is isolable, but the re-entry team could not close the valve due to a broken reach rod .
• Isolation of the leak is necessary to prevent equipment damage to 2A Charging Pump.
• 28 and 2C Charging Pumps are OPERABLE.
• Dose rates initially taken at the valve were 7.8 Rem/hour.
• A second re-entry team is prepared to attempt to repair and close the valve to isolate the leak. Time to complete the task is estimated to be 45 minutes INITIATING CUES:

As the Emergency Coordinator (EC) you are responsible for authorizing the second re-entry team. In support of that decision, In accordance EPIP-02, Attachment 5, perform the following :

1. Determine the estimated dose the worker will be expected to receive.

2. Identify the TEDE and COE limits applicable for the task.

3. Determine whether or not the worker will be able to accomplish the task without exceeding the identified TEDE and COE limits.

JPM A-4 SRO Page 6

REVISION NO.: PROCEDURE TITLE : PAGE : 39 DUTIES AND RESPONSIBILITIES OF THE 47 of 50 PROCEDURE NO .: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT ATTACHMENT 5

 §1             EXPOSURE LIMITS FOR EMERGENCY RESPONSE PERSONNEL (Page 1 of 4)

NOTE

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

2. Protective clothinQ, including respirators , should be used where aQpropriate.

For the following missions, the exposure limit is(1>: Total Dose<2> THYROID(3l (TEDE) (COE} Performance of actions that would not directly mitigate the event , minimize escalation , or minimize effluent releases . 5 REM 50 REM Performance of actions that mitigate the escalation to the event, rescue persons from a non-life threatening situation, minimize exposures or minimize effluent releases . 10 REM 100 REM Performance of actions that decrease the severity of the event or term inate the processes causing the event in an attempt to control effluent releases to avoid extensive exposure of large populations . Also, rescue of persons from a life-threatening situation . 25 REM 250 REM Rescue of person from a life-threatening situation. (Volunteers(4 ) should be above the age of 45 .) (5) (5) (1) Exposure limits to the lens of the eye are 3 times the Total Dose (TEDE) values listed . (2) Total Dose (TEDE} is the total whole body exposure from both external and internal (weighted} sources - Total Effective Dose Equivalent. (3) Thyroid Dose (COE) commitment from internal sources - Committed Dose Equivalent. The same dose limits also apply to other organs (COE), skin (Shallow Dose Equivalent} and t extremities (Extremity Dose Equivalent). (4) Volunteers with full awareness of risks involved including numerical levels of dose at which acute effects of radiation will be incurred and numerical estimates of the risk of delayed effects. (5) No upper limit for Total Dose (TEDE) and/or Thyroid Dose (CDE) exposure has been established because it is not possible to prejudge the risks that one person should be allowed to take to save the life of another. Also, no specific limit is given for thyroid exposure since in the extreme case, complete thyroid loss might be an acceptable sacrifice for a life saved . This should not be necessary if respirators and/or thyroid protection for rescue personnel are available as the result of adequate planning . JPM A-4 SRO Page 7

REVISION NO.: PROCEDURE TITLE: PAGE: - 39 PROCEDURE NO.: EPIP-02 DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR ST. LUCIE PLANT 48 of 50 ATTACHMENT 5 EXPOSURE LIMITS FOR EMERGENCY RESPONSE PERSONNEL (Page 2 of 4) Guidance for use of Potassium Iodide - A Thyroid Blocking Agent NOTE The distribution of Potassium Iodide (Kl) is based on actual or projected dose to the thyroid . In emergency conditions, the dose to the individual may be difficult to estimate. The determination will need to assess the potential for exposure to radioiodine, including consideration of air sample results , activity reported on whole body counts , fuel and reactor coolant system integrity, and the release status. Conservative threshold values are iven to facilitate uick determination of the need to distribute Kl.

1. The TSC HP Supervisor (consulting with the EOF HP Manager, if needed) will determine the need to dispense Potassium Iodide (Kl) based upon a projected or actual thyroid Committed Dose Equivalent (COE)~ 5 rem. (The thyroid COE~ 5 rem threshold is based on the FDA recommended threshold for ingestion of Kl by pregnant and lactating women) .

2. Consider Kl issuance if the following is encountered:

A. Entry into areas (without an SCBA) when iodine air sample results indicate

                 ~2 . 6 E-6 uCi/ml of 1-131 (based on a one-hour exposure) .

B. Whole .body counts indicating ~1 . 8 uCi of 1-131 . C. An entry into areas suspected of having significant levels of radioiodine is required . Factors to evaluate include:

1. Fuel integrity (loss of fuel integrity increases the radioiodine risk) .

2. Use of an SCBA or other respiratory protection with a high protection factor.

3. Radiation monitor readings .

4. Duration of the entry.

3. Kl distribution will be coordinated by the TSC HP Supervisor, the Field Monitoring Team Communicator I Coordinator, and the HPOSC once a decision for use has been determined .

JPM A-4 SRO Page 8

REVISION NO.: PROCEDURE T ITLE : PAGE; 39 DUTIES AND RESPONSIBILITIES OF THE 49 of 50 PROCEDURE NO .: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT ATTACHMENT 5 EXPOSURE LIMITS FOR EMERGENCY RESPONSE PERSONNEL (Page 3 of 4)

4. The TSC HP Supervisor is responsible for Kl distribution in the Unit 1 and Unit 2 Control Rooms , the Technical Support Center, and for Security personnel not assigned to the OSC.

A. The Field Monitoring Team Communicator I Coordinator, in consultation with the TSC HP Supervisor, is responsible for Kl distribution for Field Monitoring Team personnel after dispatch from the OSC.

5. The HPOSC is responsible for Kl distribution in the OSC.

NOTE For optimal protection against inhaled radioiodine , Kl should be administered before or immediately coincident with the intake, through Kl may have a protective effect if taken after the exposure. The FDA has determined that Kl has a protective effect for up to 24 hours. CAUTION Kl is a safe and effective means to prevent radioiodine uptake by the thyroid . However, there are risks associated with Kl. Some personnel may have side affects with the administration of Kl , including allergic reactions , minor rashes, and I or gastrointestinal disturbances. Personnel should be aware of these risks before taking Kl.

6. Kl should be administered and ingested within 2 hours after the projected or actual thyroid COE ~5 rem intakes occurred.

7. Prior to issuance of Kl , caution the emergency response personnel of potential Kl side effects if they are allergic to shellfish or iodine.

A. Emergency response personnel who know they have such allergies should be replaced in lieu of directing them to ingest Kl.

8. When Kl is issued, perform the following :

A. Document that the names of the personnel issued Kl on RP-SL-101-2000 , Emergency Personnel Exposure Control, Attachment 4, Potassium Iodide (Kl) Distribution Log and Briefing Information (or in the position logs). B. Indicate on RP-SL-101-2000 , Emergency Personnel Exposure Control , Attachment 4, Potassium Iodide (Kl) Distribution Log and Briefing Information (or the in position logs) that the personnel were advised of potential Kl side effects . C. Utilize whole body counts to estimate the actual thyroid intake. JPM A-4 SRO Page 9

REVISION NO.: PROCEDURE TITLE: PAGE: 39 DUTIES AND RESPONSIBILITIES OF THE 50 of 50 PROCEDURE NO.: EMERGENCY COORDINATOR EPIP-02 ST. LUCIE PLANT ATTACHMENT 5 EXPOSURE LIMITS FOR EMERGENCY RESPONSE PERSONNEL (Page 4 of 4)

9. All Kl is stored in the HP Ekits, Unit 1 Control Room I Technical Support Center, Unit 2 Control Room, Operation Support Center and Field Monitoring Team Kits .

END OF ATTACHMENT 5 JPM A-4 SRO Page 10

JOB PERFORMANCE MEASURE Ausw~e:E $~~ v (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF THE TASK) INITIAL CONDITIONS:

• A large break LOCA has occurred on Unit 2, six hours ago.
• The crew is implementing 2-EOP-03, LOCA
• All EOP-03 safety functions being met.
• There is a 10 gpm leak in the A Charging header.
• The leak is isolable, but the re-entry team could not close the valve due to a broken reach rod .
• Isolation of the leak is necessary to prevent equipment damage to 2A Charging Pump.
• 28 and 2C Charging Pumps are OPERABLE .
• Dose rates initially taken at the valve were 7.8 Rem/hour.
• A second re-entry team is prepared to attempt to repair and close the valve to isolate the leak. Time to complete the task is estimated to be 45 minutes INITIATING CUES:

As the Emergency Coordinator (EC) you are responsible for authorizing the second re-entry team . In support of that decision, In accordance EPIP-02, Attachment 5, perform the following :

1. Determine the estimated dose the worker will be expected to receive .

(7.8 mR/hr) x (45 min) x (1 hr/60 min)= 5.85 Rem

2. Identify the TEDE and COE limits applicable for the task.

Attachment 5, Exposure Limits for Emergency Response Personnel, are 5 Rem TEDE and 50 Rem COE.

3. Determine whether or not the worker will be able to accomplish the task without exceeding the identified TEDE and COE limits.

DETERMINES that the work CANNOT perform the task. (5.85 Rem estimated dose is greater than the procedural limits of 5 Rem TEDE and 50 Rem COE). JPM A-4 SRO Page 11

• FPL St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE IMPLEMENT EPIP FOR SGTR/LOOP HLC 22 NRC SRO Admin JPM A5 This is a Time Critical JPM NRC SRO Adm in JPM A5 Page 1 of 8 JPM A-5 SRO Page 1

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS Task: 09200180, Classify Plant Events (EPIP). Faulted JPM? No Facility JPM #: 0821138T KIA: G2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. KIA Rating(s): SRO 4.1 Duty Area(s): N/A Task Information: Task Standard: This JPM is complete when applicable protective action recommendations have been determined. Evaluation Location: Performance Level: Simulator In Plant Lab Other Perform Simulate Discuss x x

References:

• EPIP-01 , Classification of Emergencies
• EPIP-08, Off-Site Notifications and Protective Action Recommendations (Florida Nuclear Plant Emergency Notification Form)
• St. Lucie Plant Classification Tool - EAL HOT BASIS Emergency Action Levels. Fission Product Barrier Table (Specifically)

Validation Time: 15 minutes Time Critical: YES Tools/Equipment/Procedures Needed:

• EPIP-08, Off-Site Notifications and Protective Action Recommendations (Florida Nuclear Plant Emergency Notification Form)
• St. Lucie Plant Classification Tool - EAL HOT BASIS Emergency Action Levels (including Fission Product Barrier Table)

Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.

• None Radiological Protection and RWP Requirements:
• None NRC SRO Admin JPM A5 Page 2 of 8 JPM A-5 SRO Page 2

JOB PERFORMANCE MEASURE INITIAL CONDITIONS AND SPECIFIC DIRECTIONS Examiner Note:

• The preferred method of administering this JPM is either in the Simulator or Control Room .

The student is expected to obtain Met Data from ERDADS. The attached Met Data is only to be provided to the student if this JPM is administered in a classroom environment. SPECIFIC DIRECTIONS:

• The task you are to perform is: determine applicable protective action recommendations.
• The performance level to be used for this JPM is Perform.
• This IS 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 has just been manually tripped from 100% power due to a steam generator tube rupture in the 2A SG.
• A Loss of Offsite Power occurred.
• Letdown has been isolated and all three charging pumps are running .
• Pressurizer level is dropping and secondary radiation is rising.
• The US has just completed 2-EOP-01, "Standard Post Trip Actions".
• SIAS has actuated.

INITIATING CUES: You are the Shift Manager and you are tasked with:

• Classifying the event per EPIP-01, "Classification of Emergencies" and then, if required.
• Fill out the Florida Nuclear Plant Emergency Notification Form and notify the State and County agencies per EPIP-08, "Off-Site Notifications and Protective Action Recommendations. n The Shift Communicator is unavailable.

These actions are TIME CRITICAL. NRC SRO Admin JPM AS Page 3 of 8 JPM A-5 SRO Page 3

JOB PERFORMANCE MEASURE START TIME: _ _ __ EPIP-01 Classification of Emergencies, Attachment 1: St. Lucie Plant Classification Tool - EAL HOT BASIS Erner enc Action Levels -- Fission Product Barrier Table STEP 1 (5.3): The SM shall classify the abnormal condition in accordance CRITICAL with the Fission Product Barrier Table of the St. Lucie Plant STEP Classification Tool- EAL HOT BASIS Emergency Action Level STANDARD: CLASSIFY the event as an "Alert" under FA 1, Loss of the RCS SAT barrier. EXAMINER'S CUE: ACKNOWLEDGE EVENT UNSAT CLASSIFICATION EVALUATOR'S NOTE: Record the time initial event classification is made for determining the time critical notification of agencies: This must be ~_15 minutes of START TIME. COMMENTS: NRC SRO Admin JPM A5 Page 4 of 8 JPM A-5 SRO Page 4

JOB PERFORMANCE MEASURE Appendix A EPIP-08, Off-Site Notifications and Protective Action Recommendations STEP 2 (2.A.2) : State Watch Office Notification CRITICAL STEP STANDARD: COMPLETE 'Florida Nuclear Plant Emergency Notification Form ' (form similar to Attachment 1) per EPI P-08. EXAMINER'S CUE: None. SAT EXAMINER NOTE: All

• steps are critical with the exception of step #1. A or UNSAT B is acceptable.

Step 3.C Step 4.B Step 5 Step 6. A. FA1 Step 8. A. 92 B. MNP Step 9. B Step 9 on the Notification Form should have "in progress" checked AND Step 10 on the Notification Form, should have "under evaluation" checked (this is not an asterisked step). Step 11. B Answer Key provided COMMENTS: NRC SRO Admin JPM A5 Page 5 of 8 JPM A-5 SRO Page 5

JOB PERFORMANCE MEASURE Appendix A EPIP-08, Off-Site Notifications and Protective Action Recommendations STEP 3 (28): Using the State HOT RING DOWN (HRD) Phone, dial 100. Transmit the information FROM ATTACHMENT 1 from EPIP-08, Per Appendix A Step C. SAT STANDARD: TRANSMIT information within 15 minutes of classifying event UNSAT EXAMINER'S CUE: Transmission is at the examiner's discretion. This JPM is complete." EVALUATOR'S NOTE:

                    *Record the time that the State acknowledges contact
                    *Must be  ~15   minutes from step 1 time EVALUATOR NOTE: Review the State Notification Form for accuracy after the student has completed Step 3. All asterisked items must be correct. The asterisk is used identify steps that are evaluated for NRC performance indicator points.

COMMENTS : END OF TASK STOP TIME: _ _ __ NRC SRO Admin JPM A5 Page 6 of 8 JPM A-5 SRO Page 6

JOB PERFORMANCE MEASURE CANDIDATE CUE SHEET Met Tower Data 10 METER 59.7 METER 15-MINUTE AVG. WIND SPEED 12 MPH 17 MPH 15-MINUTE AVG . WIND DIRECTION 92 DEG 111 DEG 15-MINUTE AVG. TEMPERATURE 76 DEG F 79 DEG F JPM A-5 SRO Page 7

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

• Unit 2 has just been manually tripped from 100% power due to a steam generator tube rupture in the 2A SG.
• A Loss of Offsite Power occurred.
• Letdown has been isolated and all three charging pumps are running .
• Pressurizer level is dropping and secondary radiation is rising.
• The US has just completed 2-EOP-01, "Standard Post Trip Actions".
• SIAS has actuated.

INITIATING CUES: You are the Shift Manager and you are tasked with :

• Classifying the event per EPIP-01 , "Classification of Emergencies" and then, if required .
• Fill out the Florida Nuclear Plant Emergency Notification Form and notify the State and County agencies per EPIP-08, "Off-Site Notifications and Protective Action Recommendations ."

The Shift Communicator is unavailable. These actions are TIME CRITICAL. JPM A-5 SRO Page 8

ATTACHMENT 1 FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 1 of 1) ""'-line Verification : 0 SWPIDEM 0 DOH/BRC D St. Lucie County/Ft. Pierce 0 Martin County A. 0 THIS IS A DRILL B. 0 THIS IS AN EMERGENCY

2. A. Date: - - - - ' - - B.

• Contact Time: C. Reported by: (Name) _ _ _ _ _ _ _ _ _ _ __

D. Message Number: _ __ E. Reported from : D Control Room 0 TSC 0 EOF F. 0 Initial I New Classification OR 0 Update Notification 3.* Site: A. D Crystal River Unit 3 B. 0 St. Lucie Unit 1 C. 0 St. Lucie Unit 2 D. D Turkey Point Unit 3 E. 0 Turkey Point Unit 4 4.* Emergency Classification: A. 0 Notification of Unusual Event B. 0 Alert C. 0 Site Area Emergency D. D General Emergency 5.* A. O Emergency Declaration: B. 0 Emergency Termination: Date: _.......__,__ Time: _ _ __ 6.* Reason for Emergency Declaration : A. 0 EAL Number I I OR B. D

Description:

Alpha I Alpha I Numeric

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

Description:

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

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

A. 0 Under evaluation. B. D Release within normal operating limits (:s> 3.5 E-1 Ci./sec noble gas, s 4 .6 E-5 Ci/sec iodine) C. D Non-Significant Fraction of PAG Range (release is> normal limits and< 500 mrem TEDE and 1000 mrem COE) D. O PAG Range (e> 500 mrem TEDE or c- 1000 mrem COE) E. O Liquid release (no actions required) 11.* UTILITY PROTECTIVE ACTION RECOMMENDATIONS FOR THE PUBLIC: A. D No utility recommended actions at this lime. B. O The utility recommends the following protective actions: Evacuate Sectors Shelter Sectors Monitor & Prepare Sectors Evacuate Zones: OR 0-2 Shelter Zones: 2-5 5-10 AND consider issuance of otassium iodide (Kl)" If form is completed in the Control Room, go to Item 15. If completed in the TSC or EOF, continue with item 12.

12. Plant Conditions: A. Reactor Shutdown? D Yes 0 No B. Core Adequately Cooled? D Yes D No C. Containment Intact? 0 Yes 0 No D. Core Condition: 0 Stable O Degrading

13. Weather Data: A. *Wind Speed _ _ _ mph B. Stability Class _ __

14. Additional Release Information: A. O NIA OR Read this statement: "1 hour projected doses as follows :

Distance Projected Thyroid Dose (COE) for 1 Hour Projected Total Dose CTEDEl for 1 Hour 1 Mile (Site Boundary) B. mrem C. mrem 2 Miles D. - - - - - - - - - mrem E. mrem 5 Miies ~ mrem G. mrem 10 Miles H. mrem I. mrem

'15.   (Do Not Read) EC or RM Approval Signature: - - - - - - - - -                               Date:_ _.__-'--              Time: _ __

Message Received By: Name:. _ _ _ _ _ _ _ _ _ _ _ _ __ Date:_ _,__.....:..._ Time: _ __

• Items are evaluated for NRC Performance Indicators (Pl's)

EPIP-08-F01 JPM A-5 SRO Page 9 Form Revision: 3

REVISION NO.: PROCEDURE TITLE: PAGE: 35 OFF-SITE NOTIFICATIONS AND PROTECTIVE 40 of 56 PROCEDURE NO.: ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 1A DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 3 of 6)

8. (continued)

C. If the wind is located on the edge of a sector (i.e., 11°, 33°, etc.) an additional (fourth) sector should be added. D. Enter the wind direction (wind from) in degrees in item "A." ./ E. Enter the downwind sectors in item "B" using the following chart Wind Sectors Wind Sectors Wind Sectors From Affected From Affected From Affected 348-11 HJK 123-146 PQR 236-258 COE 11-33 JKL 146-168 QRA "-v 258-281 DEF 33-56 KLM 168-191 RAB 281-303 EFG 5f\_ 7Q I "'\[\J 191-213 ABC 303-326 FGH

  \18-101           MNP '.)          213-236           BCD          326-348         GHJ 101-123          NPQ              There is no "O" sector         There is no "I" sector

9. Release Status A. If there are no indications of a release of radioactive material, check box "A" and go to item 11.

B. If a release is in progress, check box "B" and go to item 10. C. If a release has occurred, but stopped, check box "C" and go to item 11 .

10. Release Significance Category Check the appropriate box as given by Dose Assessment or EC JPM A-5 SRO Page 10

                                                          <    L'-- -.:J l    ) L C't/

r 1'-- _,,, ATTACHMENT 1 FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 1 of 1) n-line Verification: 0 SWP/DEM 0 DOH/BRC D St. Lucie County/Fl. Pierce D Martin County 1.* A. 181 THIS IS A DRILL B. 0 THIS IS AN EMERGENCY

2. A. Date: to I da I y B. ~ Contact Time: C. Reported by: (Name) ~c=a~n=d'""id=a=te"----------

D. Message Number: _1_ E. Reported from: 181 Control Room 0 TSC D EOF F. 181 Initial I New Classification OR 0 Update Notification 3.* Site: A. D Crystal River Unit 3 B. D St. Lucie Unit 1 C. 181 St. Lucie Unit 2 D. D Turkey Point Unit 3 E. 0 Turkey Point Unit 4 4.* Emergency Classification: A. 0 Notification of Unusual Event B. 181 Alert C. D Site Area Emergency D. D General Emergency 5.* A. 181 Emergency Declaration: B. D Emergency Termination: Date: to I da I y Time: classification time 6.* Reason for Emergency Declaration: A. 181 EAL Number F I A I 1 OR B. D

Description:

Alpha I Alpha I Numeric

7. Additional Information or Update: A. 181 None OR B. 0

Description:

B.* Weather Data: A. Wind direction from~ degrees B. Downwind Sectors Affected : ~M~N~P_ _ __ 9.* Release Status: A. 0 None (Go to Item 11) 8. 181 In progress C. D Has occurred, but stopped (Go to Item 11)

10. Release Significance Category lat the Site Boundary):

A. 181 Under evaluation. B. D Release within normal operating limits(:> 3.5 E-1 CVsec noble gas,::; 4.6 E-5 CVsec iodine) C. D Non-Significant Fraction of PAG Range (release is> normal limits and< 500 mrem TEDE and 1000 mrem COE) D. 0 PAG Range(~ 500 mrem TEDE or ~ 1000 mrem COE) E. 0 Liquid release {no actions required) 11.* UTILITY PROTECTIVE ACTION RECOMMENDATIONS FOR THE PUBLIC: A. 181 No utility recommended actions at this time.

8. D The utility recommends the following protective actions:

Evacuate Sectors Sheller Sectors No Action Sectors Evacuate Zones: OR 0-2 Shelter Zones: 2-5 5-10 AND consider issuance of potassium iodide {Kl)" lfform is completed in the Control Room, go to Item 15. If completed in the TSC or EOF, continue with item 12.

12. Plant Conditions: A. Reactor Shutdown? 0 Yes 0 No B. Core Adequately Cooled? 0 Yes D No C. Containment Intact? 0 Yes 0 No D. Core Condition: 0 Stable D Degrading

13. Weather Data : A. *Wind Speed _ _ _ mph 8. Stability Class _ __

14. Additional Release Information: A. D N/A OR Read th is statement: "1 hour projected doses as follows:

Distance Projected Thyroid Dose ICDEl for 1 Hour Projected Total Dose ITEDE) for 1 Hour 1 Mile (Site Boundary) 8. mrem C. mrem 2 Miles D. _ _ _ _ __ _ _ __ mrem E. mrem 5 Miles F. mrem G. mrem 10 Miles H. mrem I. _ _ _ _ _ _ _ _ _ _ mrem

15. (Do Not Read) EC or RM Approval Signature: - -- - - - -- - Date:_-'---'-- Time: _ __

Message Received By: Name:_ _ _ _ _ _ _ _ _ _ __ __ Date : _~-'-- Time: _ __

• Items are evaluated for NRC Performance Indicators {Pl's)

JPM A-5 SRO Page 11 EPIP-08-FOl Form Revision: 2}}