ML15201A561

301 Final Administrative JPMs

ML15201A561
Person / Time
Site:	Saint Lucie
Issue date:	07/16/2015
From:	NRC/RGN-II
To:	Florida Power & Light Co
References
Download: ML15201A561 (163)

Text

St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE 2B EDG INOPERABLE EVALUATE OPPOSITE TRAIN COMPONENTS HLC 22 NRC RO Admin JPM A1 1 of 27 HLC-22 NRC JPM A1 RO Rev.2

Task: Given an Emergency Diesel Generator inoperable, verify opposite train equipment OPERABLE.

Faulted JPM? No Facility JPM #: No K/A: G2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

K/A 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-OSP-59.01B, 2B Emergency Diesel Generator Monthly Surveillance, Attachment 1, Operability Checklist Prior to Removing 2B EDG from Service, Rev 29 Validation Time: 15 minutes Time Critical: NO Tools/Equipment/Procedures Needed:

2-OSP-59.01B, 2B Emergency Diesel Generator Monthly Surveillance, Attachment 1, Operability Checklist Prior to Removing 2B EDG from Service Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.

None Radiological Protection and RWP Requirements:

None 2 of 27 HLC-22 NRC JPM A1 RO Rev.2

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 2B EDG operability. 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. All other equipment status is as indicated by control room indications.

INITIATING CUES:

The Unit Supervisor has directed you, the Desk RCO, to perform 2-OSP-59.01B, 2B Emergency Diesel Generator Monthly Surveillance, Attachment 1, Operability Checklist Prior to Removing 2B EDG from Service. Report the results of Attachment 1 to the Unit Supervisor. The Unit Supervisor will be reviewing the Action Tracker - Equipment Out of Service log while you perform Attachment 1.

3 of 27 HLC-22 NRC JPM A1 RO Rev.2

START TIME: __________

2-OSP-59.01B, Attachment 1, Operability Checklist Prior to Removing 2B EDG from Service (These steps are bulleted and may be performed in any order.)

STEP 1: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG 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 EXAMINERS CUE: None.

COMMENTS:

STEP 2: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG from service:

Charging pump powered from the A side _____ SAT STANDARD: DETERMINES that 2A Charging Pump is OPERABLE.

_____ UNSAT EXAMINERS CUE: None.

EXAMINERS NOTE: The C Charging Pump is aligned to the B Train (Cue Sheet).

COMMENTS:

4 of 27 HLC-22 NRC JPM A1 RO Rev.2

STEP 3: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG from service:

PORV Block Valve V1476, BLOCK VALVE _____ SAT STANDARD: DETERMINES that PORV Block Valve V1476 is OPERABLE.

_____ UNSAT EXAMINERS CUE: None.

COMMENTS:

STEP 4: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG from service:

2A HPSI Pump and flowpath _____ SAT STANDARD: DETERMINES that 2A HPSI Pump and flowpath are OPERABLE.

_____ UNSAT EXAMINERS CUE: None.

COMMENTS:

5 of 27 HLC-22 NRC JPM A1 RO Rev.2

STEP 5: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG 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-OSP-59.01B, Attachment 1, Operability Checklist as _____ UNSAT a discrepancy EXAMINERS CUE: If asked, report there is no scheduled work on V-3615.

COMMENTS:

STEP 6: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG from service:

2A Containment Spray Pump and flowpath _____ SAT STANDARD: DETERMINES that 2A Containment Spray Pump and flowpath are OPERABLE. _____ UNSAT EXAMINERS CUE: None.

COMMENTS:

6 of 27 HLC-22 NRC JPM A1 RO Rev.2

STEP 7: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG from service:

2A Hydrazine Pump _____ SAT STANDARD: DETERMINES that 2A Hydrazine Pump is OPERABLE.

_____ UNSAT EXAMINERS CUE: None.

COMMENTS:

STEP 8: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG 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 and T-23 is lit) so it is inoperable. Notes the status on 2-OSP-59.01B, Attachment 1, Operability Checklist as _____ UNSAT a discrepancy EXAMINERS CUE: None.

COMMENTS:

7 of 27 HLC-22 NRC JPM A1 RO Rev.2

STEP 9: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG from service:

HVE-6A, SBVS EXHAUST FAN and flowpath _____ SAT STANDARD: DETERMINES that HVE-6A, SBVS EXHAUST FAN and flowpath are OPERABLE. _____ UNSAT EXAMINERS CUE: None.

COMMENTS:

STEP 10: VERIFY the following A train equipment and flowpaths are NOT out CRITICAL of service prior to removing the 2B EDG 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-OSP-59.01B, Attachment 1, Operability Checklist as _____ UNSAT a discrepancy.

EXAMINERS CUE: None COMMENTS:

8 of 27 HLC-22 NRC JPM A1 RO Rev.2

STEP 11: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG 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.

EXAMINERS CUE: None.

EXAMINERS 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 2B EDG 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 EXAMINERS CUE: None.

EXAMINERS NOTE: The C ICW Pump is aligned to the B Train (Cue Sheet).

COMMENTS:

9 of 27 HLC-22 NRC JPM A1 RO Rev.2

STEP 13: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG 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.

EXAMINERS CUE: None.

COMMENTS:

STEP 14: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG 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 EXAMINERS CUE: None.

COMMENTS:

10 of 27 HLC-22 NRC JPM A1 RO Rev.2

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.

_____ UNSAT EXAMINERS 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.

EXAMINERS CUE: None.

COMMENTS:

11 of 27 HLC-22 NRC JPM A1 RO Rev.2

STEP 17: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG from service:

2A Emergency Diesel Generator _____ SAT STANDARD: DETERMINES that 2A Emergency Diesel Generator is OPERABLE.

_____ UNSAT EXAMINERS CUE: None.

COMMENTS:

STEP 18: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG 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 EXAMINERS CUE: The Board RCO reports 205 KW of Pressurizer heaters available.

COMMENTS:

12 of 27 HLC-22 NRC JPM A1 RO Rev.2

STEP 19: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG 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.

EXAMINERS 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 2B EDG from service:

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

PT-07-4A1, CNTMT PRESS

_____ UNSAT STANDARD: DETERMINES that PT-07-4A1, CNTMT PRESS is OPERABLE.

EXAMINERS CUE: None.

EXAMINERS NOTE: PT-07-4A1 is located on PACB #2.

COMMENTS:

13 of 27 HLC-22 NRC JPM A1 RO Rev.2

STEP 21: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG from service:

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

LI-1110X, LEVEL (Pressurizer), OR UR-01-1, Pzr Level /

Press(LY-1110X, pressurizer Level) _____ UNSAT STANDARD: DETERMINES that:

LI-1110X, LEVEL (Pressurizer)

OR UR-01-1, Pzr Level / Press(LY-1110X, pressurizer Level) is OPERABLE.

EXAMINERS CUE: None.

COMMENTS:

14 of 27 HLC-22 NRC JPM A1 RO Rev.2

STEP 22: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG 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 LI-9014, 2A S/G WIDE RANGE LEVEL (PACB 2) _____ UNSAT STANDARD: DETERMINES that:

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

EXAMINERS CUE: None.

EXAMINERS NOTE: LI-9014 is located on PACB #2.

COMMENTS:

15 of 27 HLC-22 NRC JPM A1 RO Rev.2

STEP 23: VERIFY the following A train equipment and flowpaths are NOT out of service prior to removing the 2B EDG 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.

EXAMINERS CUE: None.

EXAMINERS NOTE: LT-07-13A is located on PACB #2.

COMMENTS:

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-1B Containment Fan Cooler.

_____ UNSAT EXAMINERS CUE: This JPM is complete.

COMMENTS:

END OF TASK STOP TIME: __________

16 of 27 HLC-22 NRC JPM A1 RO Rev.2

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-1B is 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 and T-23.

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 17 of 27 HLC-22 NRC JPM A1 RO Rev.2

(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 2B EDG operability. 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. All other equipment status is as indicated by control room indications.

INITIATING CUES:

The Unit Supervisor has directed you, the Desk RCO, to perform 2-OSP-59.01B, 2B Emergency Diesel Generator Monthly Surveillance, Attachment 1, Operability Checklist Prior to Removing 2B EDG from Service. Report the results of Attachment 1 to the Unit Supervisor. The Unit Supervisor will be reviewing the Action Tracker - Equipment Out of Service log while you perform Attachment 1.

18 of 27 HLC-22 NRC JPM A1 RO Rev.2

19 of 27 HLC-22 NRC JPM A1 RO Rev.2 20 of 27 HLC-22 NRC JPM A1 RO Rev.2 21 of 27 HLC-22 NRC JPM A1 RO Rev.2 22 of 27 HLC-22 NRC JPM A1 RO Rev.2 ST. LUCIE PLANT OPS-503 OPERATIONS DEPARTMENT POLICY REVISION 64 TECHNICAL SPECIFICATION GUIDANCE Page 37 of 42 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 equipment verification, within four (4) hours, restore the inoperable component, or declare the redundant component supported by the inoperable diesel inoperable, and enter that features TS LCO requirements.

B. 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-OSP-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.

23 of 27 HLC-22 NRC JPM A1 RO Rev.2

24 of 27 HLC-22 NRC JPM A1 RO Rev.2 25 of 27 HLC-22 NRC JPM A1 RO Rev.2 26 of 27 HLC-22 NRC JPM A1 RO Rev.2 27 of 27 HLC-22 NRC JPM A1 RO Rev.2 St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE 2B EDG INOPERABLE EVALUATE OPPOSITE TRAIN COMPONENTS AND EVALUATE TECHNICAL SPECIFICATIONS HLC 22 NRC SRO Admin JPM A1 1 of 15 HLC-22 NRC JPM A1 SRO Rev.1

Task: Given an Emergency Diesel Generator inoperable, verify opposite train equipment OPERABLE and evaluate Technical Specifications.

Faulted JPM? No Facility JPM #: No K/A: G2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrumentation interpretations.

K/A Rating(s): 4.4 / 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-OSP-59.01B, 2B Emergency Diesel Generator Monthly Surveillance, Attachment 1, Operability Checklist Prior to Removing 2B EDG 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-OSP-59.01B, 2B Emergency Diesel Generator Monthly Surveillance, Attachment 1, Operability Checklist Prior to Removing 2B EDG 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 2 of 15 HLC-22 NRC JPM A1 SRO Rev.1

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 2B EDG operability. Engineering has also identified that this only affects the 2B EDG, 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-OSP-59.01B, Attachment 1, Operability Checklist Prior to Removing 2B EDG from Service.

INITIATING CUES:

The Shift Manager has declared the 2B EDG INOPERABLE. Engineering reports replacement of the relay will take 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Review the completed 2-OSP-59.01B, Attachment 1, and determine the Tech Spec implications and required actions.

3 of 15 HLC-22 NRC JPM A1 SRO Rev.1

START TIME: __________

2-OSP-59.01B, Attachment 1, Operability Checklist Prior to Removing 2B EDG from Service STEP 1: Review 2-OSP-59.01B, Attachment 1, Operability Checklist Prior to CRITICAL Removing 2B EDG from Service. STEP STANDARD: DETERMINES that 2C Auxiliary Feedwater Pump is removed from _____ SAT service for maintenance and is INOPERABLE.

EXAMINERS 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 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, restore the 2C AFW Pump to OPERABLE status. Otherwise, declare 2B AFW Pump INOPERABLE and enter LCO 3.7.1.2, Auxiliary Feedwater System and apply the _____ UNSAT Tech Spec Action Statement for 2 inoperable AFW pumps EXAMINERS CUE: None.

EXAMINERS NOTE: The applicant may identify the one hour action to perform Surveillance Requirement 4.8.1.1.a. This is required but the cue has applicant determine the Tech Spec implication as a result of the cross train checks per 2-OSP-59.01B Attachment 1.

EXAMINERS NOTE: Ops Policy 503 for LCO 3/4.8.1 (page 35 of 40) also has supporting guidance for this condition.

COMMENTS:

4 of 15 HLC-22 NRC JPM A1 SRO Rev.1

STEP 4: Inform the Shift Manager.

STANDARD: INFORMS the Shift Manager of applicable Tech Specs and required actions. _____ SAT EXAMINERS CUE: This JPM is complete. _____ UNSAT COMMENTS:

END OF TASK STOP TIME: __________

5 of 15 HLC-22 NRC JPM A1 SRO Rev.1

(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 2B EDG operability. Engineering has also identified that this only affects the 2B EDG, 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-OSP-59.01B, Attachment 1, Operability Checklist Prior to Removing 2B EDG from Service.

INITIATING CUES:

The Shift Manager has declared the 2B EDG INOPERABLE. Engineering reports replacement of the relay will take 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Review the completed 2-OSP-59.01B, Attachment 1, and determine the Tech Spec implications and required actions.

6 of 15 HLC-22 NRC JPM A1 SRO Rev.1

(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 2B EDG operability. Engineering has also identified that this only affects the 2B EDG, 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-OSP-59.01B, Attachment 1, Operability Checklist Prior to Removing 2B EDG from Service.

INITIATING CUES:

The Shift Manager has declared the 2B EDG INOPERABLE. Engineering reports replacement of the relay will take 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Review the completed 2-OSP-59.01B, Attachment 1, and determine the Tech Spec implications and required actions.

TS 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, restore the 2C AFW Pump.

Otherwise, declare the 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 ( which is to be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />).

7 of 15 HLC-22 NRC JPM A1 SRO Rev.1

8 of 15 HLC-22 NRC JPM A1 SRO Rev.1 9 of 15 HLC-22 NRC JPM A1 SRO Rev.1 ST. LUCIE PLANT OPS-503 OPERATIONS DEPARTMENT POLICY REVISION 64 TECHNICAL SPECIFICATION GUIDANCE Page 37 of 42 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 equipment verification, within four (4) hours, restore the inoperable component, or declare the redundant component supported by the inoperable diesel inoperable, and enter that features TS LCO requirements.

B. 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-OSP-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.

10 of 15 HLC-22 NRC JPM A1 SRO Rev.1

11 of 15 HLC-22 NRC JPM A1 SRO Rev.1 12 of 15 HLC-22 NRC JPM A1 SRO Rev.1 13 of 15 HLC-22 NRC JPM A1 SRO Rev.1 14 of 15 HLC-22 NRC JPM A1 SRO Rev.1 15 of 15 HLC-22 NRC JPM A1 SRO Rev.1 St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE PERFORM RCS INVENTORY BALANCE - UNIT 2 HLC 22 NRC RO Admin JPM A2 1 of 16 HLC-22 NRC JPM A2 RO Rev.1

Task: Given a set of conditions, perform a Reactor Coolant System Inventory Balance for Unit 2.

Faulted JPM? No Facility JPM #: N/A K/A: G2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

K/A 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-OSP-01.03, Reactor Coolant System Inventory Balance, Revision 25 Validation Time: 10 minutes Time Critical: NO Tools/Equipment/Procedures Needed:

2-OSP-01.03, Reactor Coolant System Inventory Balance Calculator Specific Safety Rules, Personal Protective Equipment and Hazards associated with the task.

None Radiological Protection and RWP Requirements:

None 2 of 16 HLC-22 NRC JPM A2 RO Rev.1

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 PI-VIEW and the RCS Leak Rate Calculator are unavailable INITIATING CUES:

To satisfy the requirements of 2-AOP-01.08, RCS Leakage Abnormal Operation, the Unit Supervisor has directed you to perform a one hour manual RCS leak rate determination per 2-OSP-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 gallons 0.0 gallons 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 63.0% 63.2%

Quench Tank Level 65.0% 65.1%

Charging Pump Seal Tank Level 2A: 1 inch 2B: 2 inches 2C: 1 inch 3 of 16 HLC-22 NRC JPM A2 RO Rev.1

START TIME: __________

2-OSP-01.03, Reactor Coolant System Inventory Balance Attachment 4, Manual Leak Rate Calculation STEP 1 (1&2): CALCULATE the RCS Leak rate using PI-VIEW as follows:

_____ SAT STANDARD: DETERMINES that PI-VIEW is unavailable.

EXAMINERS CUE: Provided in Initial Conditions. This _____ UNSAT eliminates use of Step 2 in Att. 4.

COMMENTS:

STEP 2 (3): If PI-VIEW is un-available, THEN RECORD data using DCS.

A. RECORD results in Hand Calc Section. _____ SAT STANDARD: DETERMINES that PI-VIEW is unavailable, and that data is to be recorded in the Hand Calc Section. _____ UNSAT EXAMINERS CUE: Provided in Initial Conditions.

COMMENTS:

STEP 3 (4): RECORD results in Hand Calc Section.

_____ SAT STANDARD: RECORDS all data provided in Initiating Cue.

EXAMINERS CUE: None _____ UNSAT COMMENTS:

4 of 16 HLC-22 NRC JPM A2 RO Rev.1

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 ( + 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.

EXAMINERS CUE: None EXAMINERS NOTE: Tolerance allowed for rounding calculated values.

COMMENTS:

5 of 16 HLC-22 NRC JPM A2 RO Rev.1

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.

EXAMINERS CUE: None EXAMINERS NOTE: Tolerance allowed for rounding calculated values.

EXAMINERS 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 EXAMINERS CUE: None EXAMINERS NOTE: Tolerance allowed for rounding calculated values.

COMMENTS:

6 of 16 HLC-22 NRC JPM A2 RO Rev.1

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 ( + 0.02 ) gpm _____ SAT STANDARD: CALCULATES Unidentified Leakage Rate. _____ UNSAT EXAMINERS CUE: None EXAMINERS NOTE: Either +/- leak rate is acceptable for leak rate. The absolute value is critical. 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 EXAMINERS CUE: None EXAMINERS NOTE: Either +/- leak rate is acceptable for leak rate. The absolute value is critical. Tolerance allowed for rounding calculated values.

COMMENTS:

END OF TASK STOP TIME: __________

7 of 16 HLC-22 NRC JPM A2 RO Rev.1

(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 PI-VIEW and the RCS Leak Rate Calculator are unavailable INITIATING CUES:

To satisfy the requirements of 2-AOP-01,08, RCS Leakage Abnormal Operation, the Unit Supervisor has directed you to perform a one hour manual RCS leak rate determination per 2-OSP-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 gallons 0.0 gallons 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 63.0% 63.2%

Quench Tank Level 65.0% 65.1%

Charging Pump Seal Tank Level 2A: 1 inch 2B: 2 inches 2C: 1 inch 8 of 16 HLC-22 NRC JPM A2 RO Rev.1

9 of 16 HLC-22 NRC JPM A2 RO Rev.1 10 of 16 HLC-22 NRC JPM A2 RO Rev.1 11 of 16 HLC-22 NRC JPM A2 RO Rev.1 12 of 16 HLC-22 NRC JPM A2 RO Rev.1 13 of 16 HLC-22 NRC JPM A2 RO Rev.1 14 of 16 HLC-22 NRC JPM A2 RO Rev.1 15 of 16 HLC-22 NRC JPM A2 RO Rev.1 16 of 16 HLC-22 NRC JPM A2 RO Rev.1 St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE PERFORM RCS INVENTORY BALANCE - UNIT 2 AND EVALUATE TECHNICAL SPECIFICATIONS HLC 22 NRC SRO Admin JPM A2 1 of 31 HLC-22 NRC JPM A2 SRO Rev 1

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 K/A: G2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

K/A 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-OSP-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-OSP-01.03, Reactor Coolant System Inventory Balance Calculator 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 2 of 31 HLC-22 NRC JPM A2 SRO Rev 1

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 PI-VIEW and the RCS Leak Rate Calculator are unavailable INITIATING CUES:

To satisfy the requirements of 2-AOP-01,08, RCS Leakage Abnormal Operation, you are to perform a one hour manual RCS leak rate determination per 2-OSP-01.03, Reactor Coolant System Inventory Balance, starting at section 4.1.6. Also, determine the required Technical Specification actions based on the results of the leak rate calculation, if any.

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 Integrator 0.0 gallons 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: 2 inches 2C: 1 inch 3 of 31 HLC-22 NRC JPM A2 SRO Rev 1

START TIME: __________

2-OSP-01.03, Reactor Coolant System Inventory Balance Attachment 4, Manual Leak Rate Calculation STEP 1 (1&2): CALCULATE the RCS Leak rate using PI-VIEW as follows:

_____ SAT STANDARD: DETERMINES that PI-VIEW is unavailable.

EXAMINERS NOTE: Provided in Initial Conditions. This _____ UNSAT eliminates use of Step 2 in Att. 4.

COMMENTS:

STEP 2 (3): If PI-VIEW is un-available, THEN RECORD data using DCS.

A. RECORD results in Hand Calc Section. _____ SAT STANDARD: DETERMINES that PI-VIEW is unavailable, and that data is to be recorded in the Hand Calc Section. _____ UNSAT EXAMINERS CUE: Provided in Initial Conditions.

COMMENTS:

STEP 3 (4): RECORD results in Hand Calc Section.

_____ SAT STANDARD: RECORDS all data provided in Initiating Cue.

EXAMINERS CUE: None _____ UNSAT COMMENTS:

4 of 31 HLC-22 NRC JPM A2 SRO Rev 1

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 ( + 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.

EXAMINERS CUE: None EXAMINERS 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.

EXAMINERS CUE: None EXAMINERS NOTE: Tolerance allowed for rounding calculated values.

EXAMINERS NOTE: Charging Pump Seal Tank levels are reported by the SNPO as inches change over an hour.

COMMENTS:

5 of 31 HLC-22 NRC JPM A2 SRO Rev 1

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 EXAMINERS CUE: None EXAMINERS 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 ( + 0.2 ) gallons

• Elapsed Time = 60 minutes

• Unidentified Leakage Rate = 1.118 ( + 0.02 ) gpm _____ SAT STANDARD: CALCULATES Unidentified Leakage Rate. _____ UNSAT EXAMINERS CUE: None EXAMINERS NOTE: Either +/- leak rate is acceptable for leak rate. The absolute value is required. Tolerance allowed for rounding calculated values.

COMMENTS:

6 of 31 HLC-22 NRC JPM A2 SRO Rev 1

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 EXAMINERS CUE: None EXAMINERS NOTE: Either +/- leak rate is acceptable for leak rate. The absolute value is required. Tolerance allowed for rounding calculated values.

COMMENTS:

2-OSP-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 ( + 0.01 ) gpm

• Unidentified Leakage Rate = 1.118 ( + 0.02 ) gpm _____ UNSAT STANDARD: RECORDS Identified and Unidentified Leakage Rates calculated in Attachment 4.

EXAMINERS CUE: None EXAMINERS NOTE: Either +/- leak rate is acceptable for leak rate. The absolute value is required. Tolerance allowed for rounding calculated values.

COMMENTS:

7 of 31 HLC-22 NRC JPM A2 SRO Rev 1

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 EXAMINERS 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 EXAMINERS CUE: None.

COMMENTS:

8 of 31 HLC-22 NRC JPM A2 SRO Rev 1

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 EXAMINERS CUE: None.

COMMENTS:

STEP 13 (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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD _____ SAT SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

EXAMINERS CUE: None. _____ UNSAT EXAMINERS CUE: This JPM is complete.

COMMENTS:

END OF TASK STOP TIME: __________

9 of 31 HLC-22 NRC JPM A2 SRO Rev 1

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 PI-VIEW and the RCS Leak Rate Calculator are unavailable INITIATING CUES:

To satisfy the requirements of 2-AOP-01,08, RCS Leakage Abnormal Operation, you are to perform a one hour manual RCS leak rate determination per 2-OSP-01.03, Reactor Coolant System Inventory Balance, starting at section 4.1.6. Also, determine the required Technical Specification actions based on the results of the leak rate calculation, if any.

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 Integrator 0.0 gallons 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: 2 inches 2C: 1 inch 10 0f 31 HLC-22 NRC JPM A2 SRO Rev 1

11 of 31 HLC-22 NRC JPM A2 SRO Rev 1 12 of 31 HLC-22 NRC JPM A2 SRO Rev 1 13 of 31 HLC-22 NRC JPM A2 SRO Rev 1 14 of 31 HLC-22 NRC JPM A2 SRO Rev 1 15 of 31 HLC-22 NRC JPM A2 SRO Rev 1 16 of 31 HLC-22 NRC JPM A2 SRO Rev 1 17 of 31 HLC-22 NRC JPM A2 SRO Rev 1 18 of 31 HLC-22 NRC JPM A2 SRO Rev 1 19 of 31 HLC-22 NRC JPM A2 SRO Rev 1 20 of 31 HLC-22 NRC JPM A2 SRO Rev 1 21 of 31 HLC-22 NRC JPM A2 SRO Rev 1 22 of 31 HLC-22 NRC JPM A2 SRO Rev 1 23 of 31 HLC-22 NRC JPM A2 SRO Rev 1 24 of 31 HLC-22 NRC JPM A2 SRO Rev 1 25 of 31 HLC-22 NRC JPM A2 SRO Rev 1 26 of 31 HLC-22 NRC JPM A2 SRO Rev 1 27 of 31 HLC-22 NRC JPM A2 SRO Rev 1 28 of 31 HLC-22 NRC JPM A2 SRO Rev 1 29 of 31 HLC-22 NRC JPM A2 SRO Rev 1 30 of 31 HLC-22 NRC JPM A2 SRO Rev 1 31 of 31 HLC-22 NRC JPM A2 SRO Rev 1 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 1 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1

Task: Perform the Borated Water Sources surveillance for Mode 1 - Unit 2.

Faulted JPM? No Facility JPM #: No K/A: G2.2.12 Knowledge of surveillance procedures.

K/A Rating(s): 3.7 / 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-OSP-02.07, Boration Flowpath and Sources, Revision 12 Validation Time: 15 minutes Time Critical: NO Tools/Equipment/Procedures Needed:

2-OSP-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 2 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1

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 operating at full power. You are the Desk RCO, and 2-OSP-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 and inform the US of your results.

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-07-2B = 34.1 feet Cb = 5967 ppm Cb = 5856 ppm LIS-07-2C = 33.8 feet Temp = 109°F Temp = 105°F LIS-07-2D = 34.0 feet RWT Cb = 2094 ppm RWT Temp = 78°F 3 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1

START TIME: __________

2-OSP-02.07, Boration Flowpath 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 EXAMINERS CUE: None.

_____ UNSAT EXAMINERS NOTE: Procedure NOTE following step 1 explains that satisfactory compliance with Tech Spec LCO 3.1.2.8 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 EXAMINERS CUE: None.

COMMENTS:

4 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1

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.

EXAMINERS CUE: None.

COMMENTS:

STEP 4 (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 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.

EXAMINERS CUE: None.

COMMENTS:

5 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1

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 EXAMINERS 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 EXAMINERS CUE: None. _____ UNSAT COMMENTS:

END OF TASK STOP TIME: __________

6 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1

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

INITIAL CONDITIONS:

Unit 2 is operating at full power. You are the Desk RCO, and 2-OSP-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 and inform the US of your results.

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-07-2B = 34.1 feet Cb = 5967 ppm Cb = 5856 ppm LIS-07-2C = 33.8 feet Temp = 109°F Temp = 105°F LIS-07-2D = 34.0 feet RWT Cb = 2094 ppm RWT Temp = 78°F 7 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1

8 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 9 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 10 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 11 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 12 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 13 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 14 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 15 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 16 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 17 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 18 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 19 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 20 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 21 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 22 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 23 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 24 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 25 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 26 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 27 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 28 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 29 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 30 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 31 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 32 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 33 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 34 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 35 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 36 of 36 HLC-22 NRC JPM A3 RO-SRO Rev 1 St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE DETERMINE EXPOSURE LIMITS UNDER NORMAL CONDITIONS HLC 22 NRC RO Admin JPM A4 1 of 16 HLC-22 NRC JPM A4 RO Rev 1

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

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

None Radiological Protection and RWP Requirements:

None 2 of 16 HLC-22 NRC JPM A4 RO Rev 1

SPECIFIC DIRECTIONS:

The task you are to perform is: Determine Exposure Limits Under Normal 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 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 years exposures are documented and up to date.

Below are the employees 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 650 mR 2 450 mR 450 mR Initiating Cue What dose would be received for the worker and which employee(s) are allowed to rebuild the Hoist Box without the Site Vice Presidents approval?

3 of 16 HLC-22 NRC JPM A4 RO Rev 1

START TIME: __________

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

_____ SAT STANDARD: CALCULATES 2700 mR/hr x 45 min x 1 hr/60 min = 2025 mR.

_____ UNSAT COMMENTS:

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

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

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 individuals TLD.

COMMENTS:

STEP 3: Determines Contract employee #2s FPL Site and Total for All Sites doses. CRITICAL STEP STANDARD: DETERMINES that Contract employee #2 will 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. _____ UNSAT Lucie site and 4025 mR for all sites.

COMMENTS:

4 of 16 HLC-22 NRC JPM A4 RO Rev 1

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 #2s FPL Site and Total for All Sites doses. CRITICAL STEP STANDARD: DETERMINES that FPL employee #2 will 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. _____ UNSAT COMMENTS:

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

STANDARD: INFORMS the Examiner that the task is complete.

EXAMINERS CUE: TASK IS COMPLETE

_____ SAT COMMENTS:

_____ UNSAT END OF TASK STOP TIME: __________

5 of 16 HLC-22 NRC JPM A4 RO Rev 1

(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 years exposures are documented and up to date.

Below are the employees 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 650 mR 2 450 mR 450 mR Initiating Cue What dose would be received for the worker and which employee(s) are allowed to rebuild the Hoist Box without the Site Vice Presidents approval?

6 of 16 HLC-22 NRC JPM A4 RO Rev 1

7 of 16 HLC-22 NRC JPM A4 RO Rev 1 8 of 16 HLC-22 NRC JPM A4 RO Rev 1 9 of 16 HLC-22 NRC JPM A4 RO Rev 1 10 of 16 HLC-22 NRC JPM A4 RO Rev 1 11 of 16 HLC-22 NRC JPM A4 RO Rev 1 12 of 16 HLC-22 NRC JPM A4 RO Rev 1 13 of 16 HLC-22 NRC JPM A4 RO Rev 1 14 of 16 HLC-22 NRC JPM A4 RO Rev 1 15 of 16 HLC-22 NRC JPM A4 RO Rev 1 16 of 16 HLC-22 NRC JPM A4 RO Rev 1 St. Lucie Nuclear Plant Operations Training JOB PERFORMANCE MEASURE DETERMINE RADIATION EXPOSURE LIMITS UNDER EMERGENCY CONDITIONS HLC 22 NRC SRO Admin JPM A4 1 of 11 HLC-22 NRC JPM A4 SRO Rev 1

Task: Given a set of conditions, determine radiation exposure limits under emergency conditions.

Faulted JPM? No Facility JPM #: No K/A: G2.3.4 Knowledge of radiation exposure limit under normal and emergency conditions.

K/A Rating(s): 3.2 / 3.7 Duty Area(s): N/A 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.

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

None Radiological Protection and RWP Requirements:

None 2 of 11 HLC-22 NRC JPM A4 SRO Rev 1

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 are 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.

2B 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 CDE 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.

3 of 11 HLC-22 NRC JPM A4 SRO Rev 1

START 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 EXAMINERS CUE: None

_____ UNSAT COMMENTS:

EPIP-02, Attachment 5 STEP 2: IDENTIFY the TEDE and CDE 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 CDE.

EXAMINERS CUE: None _____ UNSAT COMMENTS:

4 of 11 HLC-22 NRC JPM A4 SRO Rev 1

STEP 3: DETERMINE whether or not the worker will be able to accomplish CRITICAL the task without exceeding the identified TEDE and CDE 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 CDE).

_____ UNSAT EXAMINERS CUE: This JPM is complete.

COMMENTS:

END OF TASK STOP TIME: __________

5 of 11 HLC-22 NRC JPM A4 SRO Rev 1

(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 are 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.

2B 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 CDE 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.

6 of 11 HLC-22 NRC JPM A4 SRO Rev 1

7 of 11 HLC-22 NRC JPM A4 SRO Rev 1 8 of 11 HLC-22 NRC JPM A4 SRO Rev 1 9 of 11 HLC-22 NRC JPM A4 SRO Rev 1 10 of 11 HLC-22 NRC JPM A4 SRO Rev 1 11 of 11 HLC-22 NRC JPM A4 SRO Rev 1 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 1 of 11 HLC-22 NRC JPM A5 SRO Rev.1

Task: 09200180, Classify Plant Events (EPIP).

Faulted JPM? No Facility JPM #: 0821138T K/A: 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.

K/A Rating(s): SRO 4.1 Duty Area(s): N/A Task Information:

Task Standard: This JPM is complete when the event is classified, the Florida Nuclear Plant Emergency Notification Form is complete and the associated State Watch Office notification time has been documented.

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:

• Dry erase pen if laminated classification tool provided EPIP-08, Off-Site Notifications and Protective Action Recommendations (Florida Nuclear Plant Emergency Notification Form)

St. Lucie Plant Classification Tool - EAL HOT AND COLD 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 2 of 11 HLC-22 NRC JPM A5 SRO Rev.1

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: classify the event, Fill out the Florida Nuclear Plant Emergency Notification Form and notify the State and County agencies.

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

• Fill out the Florida Nuclear Plant Emergency Notification Form

• 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.

3 of 11 HLC-22 NRC JPM A5 SRO Rev.1

START TIME: __________

EPIP-01 Classification of Emergencies, Attachment 1: St. Lucie Plant Classification Tool -

EAL HOT BASIS Emergency 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 FA1, Loss of the RCS _____ SAT barrier.

EXAMINERS CUE: ACKNOWLEDGE EVENT _____ UNSAT CLASSIFICATION EVALUATORS NOTE: Record the time initial event classification is made for determining the time critical NOTIFICATION OF AGENCIES:

This time must be < 15 minutes of the time when the applicant STARTED the JPM The event must be classified within 15 minutes of when indications became available that an initiating condition has been met or exceeded)

COMMENTS:

4 of 11 HLC-22 NRC JPM A5 SRO Rev.1

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 EPIP-08.

EXAMINERS 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:

5 of 11 HLC-22 NRC JPM A5 SRO Rev.1

Appendix A EPIP-08, Off-Site Notifications and Protective Action Recommendations STEP 3 (2B): 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 EXAMINERS CUE: Transmission is at the examiners discretion. This JPM is complete.

EVALUATORS 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: __________

6 of 11 HLC-22 NRC JPM A5 SRO Rev.1

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 7 of 11 HLC-22 NRC JPM A5 SRO Rev.1

(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

• Fill out the Florida Nuclear Plant Emergency Notification Form

• 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.

8 of 11 HLC-22 NRC JPM A5 SRO Rev.1

9 of 11 HLC-22 NRC JPM A5 SRO Rev.1 10 of 11 HLC-22 NRC JPM A5 SRO Rev.1 11 of 11 HLC-22 NRC JPM A5 SRO Rev.1