Revision as of 07:53, 13 April 2019

Text

3-2010-03-Draft OP Test, 2010 NRC Walk Through Exam, Job Performance Measure A1, RCS Flow Verification and FC1 Calculation
	ML101870681
Person / Time
Site:	Waterford
Issue date:	03/16/2010
From:	; NRC Region 4
To:	;
References
	50-382/10-03, OP-903-001
	Download: ML101870681 (167)
	v • d • e

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE A1 RCS Flow Verification and FC1 CalculationApplicant: Examiner:

JPM A1 Revision 0 Page 2 of 52010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Perform RCS Flow Factor channel checks and calculate new FC1 value for Channel B. Task Standard: Applicant completes OP-903-001, Technical Specification Surveillance Logs, page 27 for RCS Flow verification in accordance with the key and concludes Channel B does not meet the required value. Applicant then calculates the new value for CPC PID060 in accordance with OP-903-001, attachment 11.9 in accordance with

the key.

References:

OP-903-001, Technical Specification Surveillance Logs Validation Time: 15 minutes Time Critical: NoAlternate Path: NoApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM A1 Revision 0Page 3 of 5 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: OP-903-001, Technical Specification Surveillance Logs

Description:

The setting will be in the simulator for this JPM. The applicant will gather information from the PMC and all 4 Core Protection Calculators to complete page 27 of the Tech Spec Surveillance Logs. Completion of page 27 should conclude that Channel B does not meet the required limits and that Channel B CPC PID 060 must be adjusted. Applicant will complete OP-903-001, Attachment 11.9 for Channel B. At the start of the task, the applicant should only be give page 27 of OP-903-001. He can use the reference books in the simulator for reviewing notes that apply.

Do not give the applicant Attachment 11.9 until he has determined Channel B does not meet the requirements.

READ TO APPLICANTDIRECTION TO APPLICANT: Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk. Provide all answers on the sheets provided.

INITIAL CONDITIONS: The Plant is at 100% power Access to the control panels for additional information is allowed. Access to Control Room procedures is allowed. INITIATING CUES: I&C maintenance was completed on components affecting COLSS RCS flow indication. The CRS directs you to complete OP-903-001, Technical Specification Surveillance Logs, page 27.

JPM A1 Revision 0Page 4 of 5 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Complete page 27 of OP-903-001. Completed in accordance with the key. Channel B MDBAR will be greater than the RCS Flow Factor. Comment: CriticalSAT / UNSAT Evaluator Note When the applicant communicates that Channel B MDBAR is greater than the RCS Flow Factor and that a calculation is required, providethe applicant with Attachment 11.9, Adjustment of FC1. TASK ELEMENT STANDARD Complete Attachment 11.9, Adjustment of FC1 Completed in accordance with the key. Comment: Cue: When page 1 of the attachment is completed, inform the applicant that another operator will verify the calculation and that the task is complete. CriticalSAT / UNSAT END OF TASK JPM A1 Revision 0Page 5 of 5 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: The Plant is at 100% power Access to the control panels for additional information is allowed. Access to Control Room procedures is allowed. INITIATING CUES: I&C maintenance was completed on components affecting COLSS RCS flow indication. The CRS directs you to complete OP-903-001, Technical Specification Surveillance Logs, page 27.

Redacted

OP-903-001 Revision 040Attachment 11.1 (20 of 37) 377.3 The limit for RCS flow reflects the Technical Specification limit plus a value ofuncertainty in the flow calculation for COLSS and CPC's as per the following Operatingcycle schedule:

PlantOperatingCycle TColdUncertainty(%)Uncertainty(LBM/Hr )Minimum Allowed RCSFlow with Uncertainty(LBM/Hr)Cycle 16>549 F4.40%6.512 E

+6154.512 E

+6>549 F, 557 F3.00%4.440 E

+6152.440 E

+6 Cycle 17 549 F2.90%4.292 E

+6152.292 E

+68.0 In Mode 1, >70% PWR, verify total RCS flow as indicated by each CPC channel(MDBAR, PID 265) is less than the value of RCS flow (actual or calculated).8.1 Determine the RCS Flow Factor (% RCS flow) by dividing the value of RCS COLSS orCalculated flow by 148 x 10 6 lbm/hr. NA if not in Mode 1, >70% pwr.8.2 Record MDBAR (% RCS Flow) as indicated by CPC PID-265. NA if not in Mode 1,>70% pwr.8.3 Verify MDBAR < RCS Flow Factor. If MDBAR > RCS flow factor, then performAttachment 11.9, Adjustment of FC1. Re-verify MDBAR < RCS Flow Factor afteradjustment and document in the Remarks section. Attach documentation to thisAttachment. NA if not in Mode 1, >70% pwr.

OP-903-001 Revision 040Attachment 11.9 (1 of 6) 104 11.9 ADJUSTMENT OF FC1CHANNEL UNDER ADJUSTMENT

A B C D11.9.1 SM/CRS Permission: __________________________________________(Signature / Date / Time)11.9.2 Perform New FC1 Calculation:RCS Mass Flow Rate:PMC PID C24564: ________________

ORNE-004-004:________________Core Coolant Mass Flow RateCPC PID-060: ________________Rate Calibration Constant (FC1)Base Core Coolant Mass FlowCPC PID-265:________________

Rate (MDBAR)(RCS Mass Flow Rate) X (FC1)Corrected Value of FC1

=(MDBAR) X (148.0 E+6) X (1.0015)( ) X ( )Corrected Value of FC1

=( ) X (148.222 E+6)( )Corrected Value of FC1

=( )Corrected Value of FC1

=Calculation Performed By:(Signature / Date / Time)Calculation Verified By:(Signature / Date / Time)

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE A2 Manual CEA Subgroup Selection for Reactor Power Cutback Applicant: Examiner:

JPM A2 Revision 0 Page 2 of 52010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Complete a manual CEA Subgroup Selection for Reactor Power CutbackTask Standard: OP-004-015, Reactor Power Cutback System, Attachment 11.1, Manual CEA Subgroup Selection, is completed in accordance with

the key.

References:

OP-004-015, Reactor Power Cutback System Validation Time: 10 minutes Time Critical: NoAlternate Path: NoApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM A2 Revision 0Page 3 of 5 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: OP-004-015, Reactor Power Cutback System, Attachment 11.1 Plant Data Book

Description:

The setting will be in the simulator for this JPM. The applicant will gather information from the PMC and use that data to complete Attachment 11.1. Plant Data Book Figure 1.7.2.1 will be required to complete this task. The Plant Data Book is available in the simulator. The only handout required will be OP-004-015, Attachment

11.1.READ TO APPLICANTDIRECTION TO APPLICANT: Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk. Provide all answers on the sheets provided. INITIAL CONDITIONS: The plant is in Mode 1. No equipment is out of service. The crew has been directed to place Reactor Power Cutback in service. Access to the control panels and Control Room reference material is allowed. INITIATING CUES: The CRS directs you to perform OP-004-015, Reactor Power Cutback System, Attachment 11.1, Manual CEA Subgroup Selection.

JPM A2 Revision 0Page 4 of 5 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Complete OP-004-015, Reactor Power Cutback System, Attachment 11.1, Manual CEA Subgroup Selection. Attachment 11.1 is completed in accordance with the key. Comment: CriticalSAT / UNSAT END OF TASK JPM A2 Revision 0Page 5 of 5 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: The plant is in Mode 1. No equipment is out of service. The crew has been directed to place Reactor Power Cutback in service. Access to the control panels and Control Room reference material is allowed. INITIATING CUES: The CRS directs you to perform OP-004-015, Reactor Power Cutback System, Attachment 11.1, Manual CEA Subgroup Selection.

Redacted OP-004-015 Revision 9 [LAST PAGE] Attachment 11.1 (1 of 1)20 11.1 M ANUAL CEA SUBGROUP SELECTION 11.1.1 Current Reactor Power (PMC Point C24107) % PWR 11.1.2 Current EFPD (PMC Point C24110) EFPD 11.1.3 Number of Operable SBCS Valves 11.1.4 Number of Operable SBCS Valves 9.88 (Maximum Allowed Reactor Power after Reactor Cutback) % PWR 11.1.5 Minimum Allowed Reactor Power Level after Reactor Cutback (Turbine DEH System Program Floor in Automatic Control) 20% PWR 11.1.6 From Plant Data Book Figure 1.7.2.1, select CEA Subgroup 5 (Regulating Group 6) or CEA Subgroups 5 and 11 (Regulating Groups 6 and

5) such that the selections will allow Reactor Power to fall between 20% and the Maximum Allowed Reactor Power determined in Step 11.1.4. Use current Reactor Power and current EFPD with CEA Group Lines. Subgroup 5 Subgroups 5 & 11 (check one)

Performed by: (Signature) (Date) Verified by:

(Signature) (Date) SM/CRS Review: / (Signature) (Date/Time)

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE A3 Tagging Boundary IdentificationApplicant: Examiner:

JPM A3 Revision 0 Page 2 of 62010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Identify the consequences of isolation and the boundaries necessary to replace the limit switches on CC-200 B, CCW Header B to AB Supply Isolation. Task Standard: Applicant identifies the correct breakers to isolate power to the limit switches for CC-200 B and correctly identifies that CC-563, CCW Header AB to B Return Isolation, and CC620, Fuel Pool Heat Exchangers Temperature Control Valve, are affected by operating the listed breakers.

References:

Plant electrical drawing B424, sheet 836 Plant electrical drawing B424, sheet 841 EN-OP-102, Protective and Caution Tagging Validation Time: 20 minutes Time Critical: NoAlternate Path: NoApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM A3 Revision 0Page 3 of 6 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: Plant electrical drawing B424, sheet 836 Plant electrical drawing B424, sheet 841 EN-OP-102, Protective and Caution Tagging

Description:

The applicant will be required to identify the boundaries necessary to replace the limit switches for CC-200 B, CCW Header B to AB Supply Isolation. Additionally, the applicant will be required to identify what other Component Cooling Water valves will be affected by the tagout. The applicant will be allowed access to the Asset Suite software and eB library, as well as the drawings in the Admin area of the Control Room. The applicant will not be allowed access to the ESOMS Tagging program.

READ TO APPLICANTDIRECTION TO APPLICANT: Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk. Provide all answers on the sheets provided.

JPM A3 Revision 0Page 4 of 6 2010 NRC Walk Through ExamEXAMINER COPY ONLY INITIAL CONDITIONS: The plant is in Mode 1 with no equipment out of service. The limit switches for CC-200B, CCW Header B to AB Supply Isolation, are scheduled to be replaced. INITIATING CUES: You have been assigned to develop the tagging boundaries for this limit switch replacement. The Component Cooling Water System and the valve actuator will not be breached during this work. Provide the answers to the following questions on your cue sheet: A.List the applicable breaker(s) that must be opened to support this work.

B.List any other Component Cooling Water valves that will be affected by hanging this tagout. You are allowed access to the Asset Suite software and eB library, as well as the drawings in the Admin area of the Control Room.

You are not allowed access to the ESOMS Tagging program.

JPM A3 Revision 0Page 5 of 6 2010 NRC Walk Through ExamTASK ELEMENT STANDARD List the applicable breaker(s) that must be opened to support this work Correct breakers identified. Comment: 2 breakers must be opened to remove power from the limit switches for CC-200 B: CC EBKR91B - 11 CC EBKR91B - 21 CriticalSAT / UNSAT TASK ELEMENT STANDARD List any other Component Cooling Water valves that will be affected by hanging this tagout. Correct valves identified. Comment: 2 CCW valves will be affected by opening the breakers listed above: CC-563, CCW Header AB to B Return Isolation. CC-620, Fuel Pool Heat Exchangers Temperature Control Valve. CriticalSAT / UNSAT END OF TASK JPM A3 Revision 0Page 6 of 6 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: The plant is in Mode 1 with no equipment out of service. The limit switches for CC-200B, CCW Header B to AB Supply Isolation, are scheduled to be replaced. INITIATING CUES: You have been assigned to develop the tagging boundaries for this limit switch replacement. The Component Cooling Water System and the valve actuator will not be breached during this work. Provide the answers to the following questions on your cue sheet: A.List the applicable breaker(s) that must be opened to support this work.

B.List any other Component Cooling Water valves that will be affected by hanging this tagout. You are allowed access to the Asset Suite software and eB library, as well as the drawings in the Admin area of the Control Room.

You are not allowed access to the ESOMS Tagging program.

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE A4 Gaseous Release EvaluationApplicant: Examiner:

JPM A4 Revision 0 Page 2 of 52010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Meteorological conditions are evaluated for gaseous release from the GWM System. Task Standard: Applicant concludes that a release is permitted. The conclusions must include the restrictions on wind speed, wind direction, and stability class.

References:

OP-007-003, Gaseous Waste Management Validation Time: 10 minutes Time Critical: NoAlternate Path: NoApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM A4 Revision 0Page 3 of 5 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: OP-007-003, Gaseous Waste Management

Description:

The setting will be in the simulator for this JPM. The applicant will gather information from the PMC for the applicable meteorological conditions. The data will be used evaluate the flow chart in OP-007-003, Attachment 11.5.

READ TO APPLICANTDIRECTION TO APPLICANT: Each administrative JPM has a cue sheet with the instructions for that JPM. Each administrative JPM stands alone, and conditions from 1 JPM do not carry over to any other JPM. If you have any questions, raise your hand and I will come to your desk. Provide all answers on the sheets provided. INITIAL CONDITIONS: The plant is in Mode 1. Chemistry has requested a release of all 3 Gas Decay Tanks for planned maintenance. INITIATING CUES: The CRS directs you to complete an evaluation of meteorological conditions for the release in accordance with OP-007-003, Gaseous Waste Management. Document all conclusions on this sheet.

JPM A4 Revision 0Page 4 of 5 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Evaluate 10 meter (33 foot) wind speed. Concludes wind speed is 3.22 m/s and continues down through the flow chart. Comment: 199 foot reading will conclude that there are no restrictions on the release.CriticalSAT / UNSAT TASK ELEMENT STANDARD Evaluate 10 meter (33 foot) wind direction. Concludes wind direction is 72.9 deg and continues right through the flow chart. Comment: 199 foot reading will conclude that there are no restrictions on the release.CriticalSAT / UNSAT TASK ELEMENT STANDARD Evaluate Pasquill Stability Class. Concludis -0.45 °C, stability class D, and that the release is permitted.. Comment: CriticalSAT / UNSAT END OF TASK JPM A4 Revision 0Page 5 of 5 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: The plant is in Mode 1. Chemistry has requested a release of all 3 Gas Decay Tanks for planned maintenance. INITIATING CUES: The CRS directs you to complete an evaluation of meteorological conditions for the release in accordance with OP-007-003, Gaseous Waste Management. Document all conclusions on this sheet.

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S1 Emergency BorationApplicant: Examiner:

JPM S1 Revision 0 Page 2 of 82010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Perform Emergency Boration upon recognition of 2 CEAs failing to insert on a reactor trip. Task Standard: Applicant establishes Emergency Boration in accordance with OP-901-103, Emergency Boration.

References:

OP-901-103, Emergency Boration Validation Time: 5minutes Time Critical: NoAlternate Path: YesApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM S1 Revision 0Page 3 of 8 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: None. Actions are Immediate Operator Actions and procedure reference is not allowed.

Description:

Initiating cue will direct the applicant to trip the reactor due to high Main Turbine vibration. After the reactor is tripped, 2 CEAs will remain withdrawn. The applicant must recognize the condition and initiate Emergency Boration. This is an immediate operator action. There are 2 allowed flow paths for Emergency Boration. There will be faults for both paths. When the applicant attempts the first flow path, the booth operator will remove the malfunction on the path not attempted. The applicant will be required to use the second path to complete the task.

READ TO APPLICANTDIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task. INITIAL CONDITIONS: You are the ATC Operator, only perform actions for the ATC The plant is at 100% power. Alarms have come in for high vibration on the Main Turbine INITIATING CUES: The Control Room Supervisor has directed you to trip the reactor and perform Standard Post Trip Actions in accordance with OP-902-000, Standard Post Trip

Actions.

JPM S1 Revision 0Page 4 of 8 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Trips the reactor when directed by the CRS. Reactor is tripped using the pushbuttons on CP-2 or CP-8. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Check less than TWO CEAs are NOT fully inserted. Applicant recognizes the need to commence Emergency Boration Comment: CriticalSAT / UNSAT Evaluator Note All manipulations associated with Emergency Boration are located on CP-4. TASK ELEMENT STANDARD Place Makeup Mode selector switch to MANUAL. Switch is placed in MANUAL Comment: Switch will already be in Manual CriticalSAT / UNSAT JPM S1 Revision 0Page 5 of 8 2010 NRC Walk Through ExamEvaluator Note Applicant can align a borated water source by 1 of 2 methods. Which ever method is used first will fail, requiring use of the second. The following steps are in the order most likely used by the applicant. Gravity Feed Alignment TASK ELEMENT STANDARD Open the following Boric Acid Makeup Gravity Feed valves: BAM-113 A Boric Acid Makeup Gravity Feed Valve A BAM-113 B Boric Acid Makeup Gravity Feed Valve B Both BAM-113 A and BAM -113 B are open Comment: BAM-113 A will fail to open, requiring the use of the BAM Pumps for Emergency Boration. CriticalSAT / UNSAT Boric Acid Pump Alignment TASK ELEMENT STANDARD Open Emergency Boration Valve, BAM-133. BAM-133 is open. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Start one Boric Acid Pump (A or B). BAM Pump A or B is running. Comment: If the Boric Acid Pumps are used before the Gravity Feed Valves, the applicant will not be able to start either BAM Pump. CriticalSAT / UNSAT JPM S1 Revision 0Page 6 of 8 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Close recirc valve for Boric Acid Pump started: BAM-126 A, Boric Acid Makeup Pump Recirc Valve A BAM-126 B, Boric Acid Makeup Pump Recirc Valve B BAM-126 A or B is closed. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Close VCT Disch Valve, CVC-183. CVC-183 is closed. Comment: This step applies regardless of which flow path is used. CriticalSAT / UNSAT TASK ELEMENT STANDARD Verify at least one Charging Pump operating and Charging Header flow is 40 GPM. Flow is verified at CP-4. Comment: This step applies regardless of which flow path is used. SAT / UNSAT Evaluator Note After Emergency Boration has been established, the applicant will continue with the rest of the Standard Post Trip Actions. End task when applicant moves on to the rest of the Standard Post Trip Actions. END OF TASK JPM S1 Revision 0Page 7 of 8 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: You are the ATC Operator, only perform actions for the ATC The plant is at 100% power. Alarms have come in for high vibration on the Main Turbine INITIATING CUES: The Control Room Supervisor has directed you to trip the reactor and perform Standard Post Trip Actions in accordance with OP-902-000, Standard Post Trip

Actions.

JPM S1 Revision 0Page 8 of 8 2010 NRC Walk Through ExamSIMULATOR OPERATOR INSTRUCTIONS Reset to IC-190 Verify the following Malfunctions:

o Tu01c 7 mils o Tu01g 10 mils o Tu01o 15 mils o Rd11a69 true sticks CEA 69 o Rd11a83 true sticks CEA 83 Verify the following Overrides were used in JPM S1:

o Di-04a4s30-1 BAM-113 A closed o Di-04a4s02-1 BAM Pump A off (trigger 1) o Di-04a4s08-1 BAM Pump B off (trigger 1) o Di-01a08a03s06-1 Moisture Separator Reheater Reset (trigger 2) If applicant attempts to use the Boric Acid Pumps first:

o Initiate Trigger 1 when BAM-133 is opened.

o Delete Override di-04a4s30-1 for BAM-113 A. If applicant attempts to use Boric Acid Gravity Feed first:

o No action required. Do not initiate trigger 1. Initiate Trigger 2 anytime after the reactor is tripped.

Off Normal ProcedureOP-901-103Emergency BorationRevision 2 6D. IMMEDIATE OPERATOR ACTIONS1.Place Makeup Mode selector switch to MANUAL.

2.Align borated water source by performing one of the following (a. or b.):a.Initiate Emergency Boration using Boric Acid Pump as follows:

Open Emergency Boration Valve, BAM-133.

Start one Boric Acid Pump.

Close recirc valve for Boric Acid Pump started:

BAM-126A Boric Acid Makeup Pump Recirc Valve A or* BAM-126B Boric Acid Makeup Pump Recirc Valve B orb.Initiate Emergency Boration using Gravity Feed as follows:

Open the following Boric Acid Makeup Gravity Feed valves:

BAM-113A Boric Acid Makeup Gravity Feed Valve A

BAM-113B Boric Acid Makeup Gravity Feed Valve B3.Close VCT Disch Valve, CVC-183.4.Verify at least one Charging Pump operating and Charging Header flow40 GPM.

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S2Hot and Cold Leg Safety Injection Applicant: Examiner:

JPM S2 Revision 0 Page 2 of 72010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Align Hot and Cold Leg Safety Injection for Trains A and B Task Standard: Applicant aligns Hot and Cold Leg Safety Injection in accordance with OP-902-009, Standard Appendices, Appendix 15.

References:

OP-902-002, Loss of Coolant Accident Recovery OP-902-009, Standard Appendicies Validation Time: 20 minutes Time Critical: NoAlternate Path: NoApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM S2 Revision 0Page 3 of 7 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: OP-902-009, Standard Appendices, Appendix 15, Hot and Cold Leg Injection.

Description:

This JPM occurs during a Loss of Coolant Accident. The applicant will receive direction to align simultaneous Hot and Cold Leg Safety Injection. All manipulations will occur at CP-8. There are no faults during this JPM. Applicant must obtain keys for all of the valves manipulated in this JPM.

READ TO APPLICANTDIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task. INITIAL CONDITIONS: A Loss of Coolant Accident occurred 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago. The crew has entered OP-902-002, Loss of Coolant Accident Recovery All requirements of step 47, Hot and Cold Leg Injection, have been met. You are the BOP operator. INITIATING CUES: The Control Room Supervisor directs you to establish Hot and Cold Leg Injection in accordance with OP-902-009, Standard Appendices, Appendix 15.

JPM S2 Revision 0Page 4 of 7 2010 NRC Walk Through ExamEstablish simultaneous Hot and Cold leg injection for Train A by performing the following: TASK ELEMENT STANDARD Close SI-219A, HPSI HEADER ORIFICE BYPASS valve. SI-219 A is closed. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Open SI-502A, HOT LEG 1 INJECTION ISOLATION valve. SI-502 A is open. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Open SI-506A, HOT LEG 1 INJECTION FLOW CONTROL valve. SI-506 A is open. Comment: CriticalSAT / UNSAT Establish simultaneous Hot and Cold leg injection for Train B by performing the following: TASK ELEMENT STANDARD Close SI-219B, HPSI HEADER ORIFICE BYPASS valve. SI-219 B is closed. Comment: CriticalSAT / UNSAT JPM S2 Revision 0Page 5 of 7 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Open SI-502B, HOT LEG 2 INJECTION ISOLATION valve. SI-502 B is open. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Open SI-506B, HOT LEG 2 INJECTION FLOW CONTROL valve. SI-506 B is open. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD WHEN hot and cold leg injection has been established, THENadjust SI-506 A and SI-506 B to obtain the sum of ALL cold leg flows equal to the sum of the hot leg flows. The sum of all cold leg flows is approximately equal to the sum of the hot leg flows. Comment: Applicant can obtain Hot and Cold Leg flows from either the PMC, the meters on CP-8, or QSPDS. After the initial alignment is complete, Hot Leg flow will be approximately 875 gpm and Cold Leg flow will be approximately 845 gpm. Applicant should throttle SI-506 A and/or B to reduce Hot Leg flow. CriticalSAT / UNSAT END OF TASK JPM S2 Revision 0Page 6 of 7 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: A Loss of Coolant Accident occurred 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago. The crew has entered OP-902-002, Loss of Coolant Accident Recovery All requirements of step 47, Hot and Cold Leg Injection, have been met. You are the BOP operator. INITIATING CUES: The Control Room Supervisor directs you to establish Hot and Cold Leg Injection in accordance with OP-902-009, Standard Appendices, Appendix 15.

JPM S2 Revision 0Page 7 of 7 2010 NRC Walk Through ExamSIMULATOR OPERATOR INSTRUCTIONS Reset to IC-191 Verify the following Malfunctions:

o Rc24a 3%Place the Simulator in Run on the lead examiners cue.

LOSS OF COOLANT ACCIDENT RECOVERY OP-902-002Revision 012Page 35 of 67 WATERFORD 3 SES

Hot and Cold Leg Injection47.IF elapsed time from the start of the event is between 2 and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months AND ANY of the following conditions exist:

RCS subcooling is less than 28°F based on representative CET temperature

Pressurizer level is less than 7%

[23%]*Reactor vessel level indicates at least one of the following:

QSPDS REACTOR VESSEL LEVEL 5 is voided

VESSEL LEVEL PLENUM less than 80%THEN REFER TO Appendix 15, "Hot and Cold Leg Injection" and establish simultaneous hot and cold leg injection.

Reset Safety Systems48.IF any ESFAS actuations have initiated AND are NO longer needed, THEN REFER TO Appendix 5, "ESFAS Reset" and reset ESFAS actuations as required.INSTRUCTIONSCONTINGENCY ACTIONS STANDARD APPENDICESOP-902-009Revision 301Page 120 of 195WATERFORD 3 SESHot and Cold Leg InjectionINSTRUCTIONSCONTINGENCY ACTIONS____ 1.1Establish simultaneous hot andcold leg injection for Train A byperforming the following:a.Close SI 219A, HPSIHEADER ORIFICE BYPASS valve.b.Open SI 502A, HOT LEG 1INJECTION ISOLATION valve.c.Open SI 506A, HOT LEG 1INJECTION FLOW CONTROL valve.____ 1.2Establish simultaneous hot andcold leg injection for Train B byperforming the following:a.Close SI 219B, HPSIHEADER ORIFICE BYPASS valve.b.Open SI 502B, HOT LEG 2INJECTION ISOLATION

valve.c.Open SI 506B, HOT LEG 2INJECTION FLOWCONTROL valve.Appendix 15Page 1 of 2 STANDARD APPENDICESOP-902-009Revision 301Page 121 of 195WATERFORD 3 SES____ 1.3 WHEN hot and cold leg injectionhas been established,THENadjust SI 506A and SI 506B toobtain the sum of ALL cold legflows equal to the sum of the hotleg flows.End of Appendix 15INSTRUCTIONSCONTINGENCY ACTIONSAppendix 15Page 2 of 2 Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S3Pressurizer Spray Valve Testing Applicant: Examiner:

JPM S3 Revision 0 Page 2 of 132010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Cycle Pressurizer Main Spray valves RC-301 A and B and respond to failed Pressurizer pressure transmitter. Task Standard: Cycle RC-301 A and RC-301 B in accordance with OP-903-118, Primary Auxiliaries Quarterly IST Valve Test. Report failure of RC-IPR-0100 X and carry out the actions of OP-901-120, Pressurizer Pressure Control Malfunction, E1, as directed by the CRS.

References:

OP-903-118, Primary Auxiliaries Quarterly IST Valve Test OP-901-120, Pressurizer Pressure Control Malfunction Validation Time: 20 minutes Time Critical: NoAlternate Path: YesApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM S3 Revision 0 Page 3 of 132010 NRC Walk Through Exam JPM S3 Revision 0Page 4 of 13 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: OP-903-118, Primary Auxiliaries Quarterly IST Valve Test, section 7.10. OP-901-120, Pressurizer Pressure Control Malfunction, section E1.

Description:

Applicant will be directed to perform section 7.10 of OP-903-118 to cycle the Pressurizer Main Spray Valves. After the first valve is cycled, Pressurizer pressure instrument RC-IPR-0100 X will fail high. If the applicant places the Pressurizer Spray Valve controller to automatic, action will need to be taken to close the spray valve selected. After the applicant reports the instrument failure to the CRS, direction will be given to carry out the actions of OP-901-120, section E1, and select the non-faulted channel for Pressurizer Pressure Control.

All manipulations are at CP-2.

READ TO APPLICANTDIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task. INITIAL CONDITIONS: Plant is at 100% power. OP-903-118, Primary Auxiliaries Quarterly IST Valve Test, has been started INITIATING CUES: You are directed by the CRS to continue with OP-903-118 with section 7.10, Reactor Coolant, and cycle RC-301 A and RC-301 B.

JPM S3 Revision 0Page 5 of 13 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Obtain SM/CRS permission to perform this Subsection and document on Attachment 10.10, Reactor Coolant. Attachment 10.10 will be provided with the CRS authorization. Comment: SAT / UNSAT TASK ELEMENT STANDARD Procedure Caution This test will initiate Pressurizer spray which may result in a decrease in RCS pressure. RCS pressure should be monitored closely during performance of this test. Acknowledges caution. Comment: Applicant should take time at this point to bring up additional RCS pressure indications on the PMC to aid in monitoring pressure. SAT / UNSAT TASK ELEMENT STANDARD Place Spray Valve Selector Switch to Loop 1A. Spray Valve Selector Switch is in the Loop 1A position. Comment: CriticalSAT / UNSAT JPM S3 Revision 0Page 6 of 13 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Place Spray Valve Indicator Controller, RC-IHIC-0100, in Manual and Raise output until one of the following occurs: Pressurizer Normal Spray Control Valve A, RC-301A, indicates Intermediate or Pressurizer pressure is reduced as indicated on Pressurizer Pressure Indicator, RC-IPI-0102-A3, RC-IPI-0102-B3, or PMC PID

A12205.Controller, RC-IHIC-0100 is in manual and RC-301 A indicates intermediate or Pressurizer pressure is dropping. Comment: RC-301 A should indicate intermediate prior to a change in Pressurizer pressure. CriticalSAT / UNSAT TASK ELEMENT STANDARD Check indication used and document results on Attachment 10.10. Attachment updated. Comment: SAT / UNSAT TASK ELEMENT STANDARD Lower Spray Valve Indicator controller, RC-IHIC-0100, Output to 0%. Controller RC-IHIC-0100 output is 0%. Comment: CriticalSAT / UNSAT JPM S3 Revision 0Page 7 of 13 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Place Spray Valve Selector Switch to Loop 1B. Spray Valve Selector Switch is in the Loop 1B position. Comment: CriticalSAT / UNSAT Evaluator Note Trigger 1 will be initiated during this manipulation, causing RC-IPR0100 X to fail high. TASK ELEMENT STANDARD Place Spray Valve Indicator Controller, RC-IHIC-0100, in Manual and Raise output until one of the following occurs: Pressurizer Normal Spray Control Valve B, RC-301B, indicates Intermediate or Pressurizer pressure is reduced as indicated on Pressurizer Pressure Indicator, RC-IPI-0102-A3, RC-IPI-0102-B3, or PMC PID

A12205.Controller, RC-IHIC-0100 is in manual and RC-301 B indicates intermediate or Pressurizer pressure is dropping. Comment: If applicant places controller RC-IHIC-0100 to automatic at this point, RC-301 B will go full open. The applicant should take action to close RC-301 B if this action is taken. CriticalSAT / UNSAT TASK ELEMENT STANDARD Report indication of the failed RC-IPR-0100 X to the CRS. Report made. Comment: CriticalSAT / UNSAT JPM S3 Revision 0Page 8 of 13 2010 NRC Walk Through ExamEvaluator Cue After applicant reports the failed instrument, provide the following cue: The CRS acknowledges that RC-IPR0100 X has failed and has entered OP-901-120. The CRS directs you to perform the actions of section E1, steps 1 through 4. Provide the applicant a copy of OP-901-120, section E1. TASK ELEMENT STANDARD Verify control channel instrument failure by checking PRESSURIZER PRESSURE CHANNEL X/Y recorder (RC-IPR-0100). Verifies that RC-IPR-0100X has failed high. Comment: SAT / UNSAT TASK ELEMENT STANDARD Transfer Pressurizer pressure control to operable channel using Pressurizer Pressure Channel Selector control switch. Pressurizer Pressure Channel Selector Switch is placed in the Y position. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Transfer Pressurizer Lo Level Heater Cutout selector switch to the Operable Pressurizer Pressure control channel. Pressurizer Lo Level Heater Cutout selector switch is placed in position Y. Comment: CriticalSAT / UNSAT JPM S3 Revision 0Page 9 of 13 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Reset Proportional Heater Banks #1 & #2. Proportional Heater Banks #1 & #2 breakers indicate closed. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Verify proper operation of Pressurizer Pressure controller (RC-IPIC-0100) AND Pressurizer Pressure controlling OR being restored to 2250 PSIA. Verifies RC-IPIC-0100 indication is normal. Comment: SAT / UNSAT Evaluator Cue After applicant has completed OP-901-120, E1, direct him to complete restoration in accordance with OP-903-118, step 7.10.2.5. TASK ELEMENT STANDARD Place Spray Valve Indicator Controller, RC-IHIC-0100, in Manual and Raise output until one of the following occurs: Pressurizer Normal Spray Control Valve B, RC-301B, indicates Intermediate or Pressurizer pressure is reduced as indicated on Pressurizer Pressure Indicator, RC-IPI-0102-A3, RC-IPI-0102-B3, or PMC PID

A12205.Controller, RC-IHIC-0100 is in manual and RC-301 B indicates intermediate or Pressurizer pressure is dropping. Comment: This is the step that was started at the point of the failure. RC-301 B may already indicate intermediate at this point. CriticalSAT / UNSAT JPM S3 Revision 0Page 10 of 13 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Check indication used and document results on Attachment 10.10. Attachment updated. Comment: SAT / UNSAT TASK ELEMENT STANDARD Lower Spray Valve Indicator controller, RC-IHIC-0100, Output to 0%. Controller RC-IHIC-0100 output is 0%. Comment: Applicant may have already taken this action during the malfunction. CriticalSAT / UNSAT TASK ELEMENT STANDARD Place Spray Valve Indicator Controller, RC-IHIC-0100, in Auto Spray Valve Indicator Controller, RC-IHIC-0100, is in Auto. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Document final position on Attachment 10.10 Attachment updated. Comment: SAT / UNSAT JPM S3 Revision 0Page 11 of 13 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Place Spray Valve Selector Switch to Both Spray Valve Selector Switch is in Both. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Document final position on Attachment 10.10. Attachment updated. Comment: SAT / UNSAT END OF TASK JPM S3 Revision 0Page 12 of 13 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: Plant is at 100% power. OP-903-118, Primary Auxiliaries Quarterly IST Valve Test, has been started INITIATING CUES: You are directed by the CRS to continue with OP-903-118 with section 7.10, Reactor Coolant, and cycle RC-301 A and RC-301 B.

JPM S3 Revision 0Page 13 of 13 2010 NRC Walk Through ExamSIMULATOR OPERATOR INSTRUCTIONS Reset to IC - 195 Verify the following Malfunctions:

o Rx14a 100% (Trigger 1) After applicant has placed the Spray Valve Selector Switch in 1B, when manipulating the Spray Valve controller to open RC-301 B, initiate Trigger 1.

Off Normal ProcedureOP-901-120Pressurizer Pressure Control MalfunctionRevision 301 7 E 1 PRESSURIZER PRESSURE CONTROL CHANNEL INSTRUMENT FAILURE PLACEKEEPERSTART DONEN/A1. Verify control channel instrument failure by checkingPRESSURIZER PRESSURE CHANNEL X/Y recorder(RC-IPR-0100).2. Transfer Pressurizer pressure control to operablechannel using Pressurizer Pressure Channel Selectorcontrol switch.

3. IF Pressurizer Pressure control channel is failed high,THEN perform the following:a. Transfer Pressurizer Lo Level Heater Cutoutselector switch to the Operable PressurizerPressure control channel.b. Reset Proportional Heater Banks #1 & #2.4. Verify proper operation of Pressurizer Pressurecontroller (RC-IPIC-0100) AND Pressurizer Pressurecontrolling OR being restored to 2250 PSIA.Continuous5. Refer to Technical Specification 3.2.8.

END Surveillance ProcedureOP-903-118Primary Auxiliaries Quarterly IST Valve TestsRevision 020 96 7.10 R EACTOR COOLANT7.10.1 Obtain SM/CRS permission to perform this Subsection and document onAttachment 10.10, Reactor Coolant.CAUTIONTHIS TEST WILL INITIATE PRESSURIZER SPRAY WHICH MAY RESULT IN ADECREASE IN RCS PRESSURE. RCS PRESSURE SHOULD BE MONITORED CLOSELYDURING PERFORMANCE OF THIS TEST.7.10.2 Testing of RC-301A and RC-301B:7.10.2.1 Place Spray Valve Selector Switch to Loop 1A.7.10.2.2 Place Spray Valve Indicator Controller, RC-IHIC-0100, in Manual and Raiseoutput until one of the following occurs:Pressurizer Normal Spray Control Valve A, RC-301A, indicates Intermediate orPressurizer pressure is reduced as indicated on Pressurizer PressureIndicator, RC-IPI-0102-A3, RC-IPI-0102-B3, or PMC PID A12205.7.10.2.2.1 Check indication used and document results on Attachment 10.10.7.10.2.3 Lower Spray Valve Indicator controller, RC-IHIC-0100, Output to 0%.7.10.2.4 Place Spray Valve Selector Switch to Loop 1B.7.10.2.5 Verify Spray Valve Indicator Controller, RC-IHIC-0100, in Manual and Raiseoutput until one of the following occurs:Pressurizer Normal Spray Control Valve B, RC-301B, indicates Intermediate, orPressurizer pressure is reduced as indicated on Pressurizer PressureIndicator, RC-IPI-0102-A3, or RC-IPI-0102-B3, or PMC PID A12206.7.10.2.5.1 Check indication used and document results on Attachment 10.10.

Surveillance ProcedureOP-903-118Primary Auxiliaries Quarterly IST Valve TestsRevision 020 977.10.2.6 Lower Spray Valve Indicator Controller, RC-IHIC-0100, Output to 0%.7.10.2.7 Place Spray Valve Indicator Controller, RC-IHIC-0100, in Auto.7.10.2.7.1 Document final position on Attachment 10.10.7.10.2.8 Place Spray Valve Selector Switch to Both.7.10.2.8.1 Document final position on Attachment 10.10.

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S4Break Main Condenser Vacuum Applicant: Examiner:

JPM S4 Revision 0 Page 2 of 82010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Break Main Condenser Vacuum Task Standard: Applicant completes step 5 of OP-901-210, Turbine Trip, and commences breaking Main Condenser vacuum.

References:

OP-901-210, Turbine Trip Validation Time: 10 minutes Time Critical: NoAlternate Path: NoApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM S4 Revision 0Page 3 of 8 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: OP-901-210, Turbine Trip, section E0.

Description:

This JPM will be performed after JPM S1. The plant will be tripped and Standard Post Trip Actions complete. The applicant will be directed to carry out the actions of OP-901-210 to break Main Condenser vacuum. The steps require manipulations on panels CP-1 and CP-8.

READ TO APPLICANTDIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task. INITIAL CONDITIONS: The plant has been tripped due to high Main Turbine Vibration. Standard Post Trip Actions have been completed. You are the BOP operator. INITIATING CUES: The CRS directs you to carry out the actions in step 5 of OP-901-210, Turbine Trip, while he and the ATC review Standard Post Trip Actions.

JPM S4 Revision 0Page 4 of 8 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Verify tripped OR Manually trip the Reactor. Verification complete. Comment: SAT / UNSAT TASK ELEMENT STANDARD Go to OP-902-000, STANDARD POST TRIP ACTIONS, AND perform concurrently with this procedure. Provided in the cue. Comment: SAT / UNSAT TASK ELEMENT STANDARD Announce the following twice: ATTENTION STATION PERSONNEL, ATTENTION STATION PERSONNEL, BREAKING CONDENSER VACUUM. Announcement complete. Comment: SAT / UNSAT TASK ELEMENT STANDARD Place STEAM BYPASS MASTER controller (MS-IPIC-1010) in MAN. Controller MS-IPIC-1010 is in Manual. Comment: CriticalSAT / UNSAT JPM S4 Revision 0Page 5 of 8 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Slowly lower output of STEAM BYPASS MASTER controller (MS-IPIC-1010) to zero. Controller MS-IPIC-1010 is at zero. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Verify Steam Generator pressure maintained at approximately 992 psig by Atmospheric Dump valves. Verification complete. Comment: Pressure will initially be lower than 992 psig since they were being controlled by the Steam Bypass System. Applicant may wait at this point to see the Atmospheric Dump valves open. SAT / UNSAT TASK ELEMENT STANDARD Procedure Caution Main Feedwater Pumps will trip when Main Steam is isolated. Caution reviewed. Comment: SAT / UNSAT TASK ELEMENT STANDARD Close BOTH Main Steam Isolation Valves (MS 124A AND MS 124B). MS-124 A and MS-124 B are closed. Comment: CriticalSAT / UNSAT JPM S4 Revision 0Page 6 of 8 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Open Condenser Vacuum Breaker valves by simultaneously depressing THINK push button AND placing CNDSR VAC BKR control switch to OPEN. Condenser Vacuum Breaker valves are open. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD WHEN the following annunciators alarm, THEN secure respective Condenser Vacuum pumps by placing the CONDENSER VACUUM PUMP control switch to STOP for 5 seconds: Condenser Vacuum Pump A AUTO START (Cabinet E, E-1) Condenser Vacuum Pump B AUTO START (Cabinet E, E-2) Condenser Vacuum Pump C AUTO START (cabinet E, E-3) All 3 Condenser Vacuum pumps are secured. Comment: CriticalSAT / UNSAT END OF TASK JPM S4 Revision 0Page 7 of 8 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: The plant has been tripped due to high Main Turbine Vibration. Standard Post Trip Actions have been completed. You are the BOP operator. INITIATING CUES: The CRS directs you to carry out the actions in step 5 of OP-901-210, Turbine Trip, while he and the ATC review Standard Post Trip Actions.

JPM S4 Revision 0Page 8 of 8 2010 NRC Walk Through ExamSIMULATOR OPERATOR INSTRUCTIONSThis JPM will be run following JPM S1. There is no need to reset the Simulator. The Simulator should be in IC - 190 with the reactor tripped. The following Malfunctions were used in JPM S1:

o Tu01c 7 mils o Tu01g 10 mils o Tu01o 15 mils o Rd11a69 true sticks CEA 69 o Rd11a83 true sticks CEA 83 Verify the following Overrides were used in JPM S1:

o Di-04a4s30-1 BAM-113 A closed o Di-04a4s02-1 BAM Pump A off (trigger 1) o Di-04a4s08-1 BAM Pump B off (trigger 1) o Di-01a08a03s06-1 Moisture Separator Reheater Reset (trigger 2) No action is necessary during this JPM.

Off Normal Procedure OP-901-210Turbine Trip Revision 3 6E. SUBSEQUENT OPERATOR ACTIONS E 0 GENERALNOTEHigh vibration is defined for bearings #1 through #10 as a sustained vibration above 10 mils.Due to lower bearing loads, high vibration on Bearing #11 would not require breakingcondenser vacuum unless it affected the adjacent bearing (#10).[ER-W3-2002-0324-001]

1. IF a Reactor trip occurs, THEN perform EITHER of the following:

1.1 IF turbine trip was due to loss of Main Lube Oil OR high vibration, THEN GO TO step 5.1.2 IF turbine trip was due to any reason other than those listed in step 1.1above, THEN GO TO OP-902-000, STANDARD POST TRIP ACTIONS.

2. IF the turbine tripped due to loss of Main Lube Oil OR high vibration, THEN GO TO step 5.3. IF a Reactor Power Cutback occurred, THEN perform OP-901-101, REACTORPOWER CUTBACK, concurrently with this procedure.

4. IF turbine trip was due to any reason other than those listed in step 2, THEN GO TO step 6.5. IF Turbine trip was due to a loss of Main Lube Oil OR high vibration OR normalTurbine coast down may damage the unit, THEN perform the following:5.1 Verify tripped OR Manually trip the Reactor.5.2 Go to OP-902-000, STANDARD POST TRIP ACTIONS, AND performconcurrently with this procedure.5.3 Announce the following twice

ATTENTION STATION PERSONNEL,ATTENTION STATION PERSONNEL,BREAKING CONDENSER VACUUM.5.4 Close ALL Steam Bypass Control valves by performing the following:5.4.1 Place STEAM BYPASS MASTER controller (MS-IPIC-1010) in MAN.5.4.2 Slowly lower output of STEAM BYPASS MASTER controller(MS-IPIC-1010) to zero.

Off Normal Procedure OP-901-210Turbine Trip Revision 3 7 E 0 GENERAL (CONT'D)5.5 Verify Steam Generator pressure maintained at approximately 992 psig byAtmospheric Dump valves.

CAUTIONMAIN FEEDWATER PUMPS WILL TRIP WHEN MAIN STEAM IS ISOLATED.5.6 Close BOTH Main Steam Isolation Valves (MS 124A AND MS 124B).5.7 Open Condenser Vacuum Breaker valves by simultaneously depressingTHINK push button AND placing CNDSR VAC BKR control switch to OPEN.5.8 WHEN the following annunciators alarm, THEN secure respectiveCondenser Vacuum pumps by placing the CONDENSER VACUUM PUMPcontrol switch to STOP for 5 seconds: Condenser Vacuum Pump A AUTO START (Cabinet E, E-1) Condenser Vacuum Pump B AUTO START (Cabinet E, E-2) Condenser Vacuum Pump C AUTO START (cabinet E, E-3) 5.9 GO TO step 9.6. IF a turbine trip has occurred AND a low EH reservoir level exists, THEN placeboth EH pump switches to OFF.7. Verify the following automatic actions have occurred: Turbine tripped The following breakers trip: Generator Breaker A Generator Breaker B EXCITER FIELD BREAKER Automatic transfer from Unit Auxiliary Transformer A to StartupTransformer A Automatic transfer from Unit Auxiliary Transformer B to StartupTransformer B Steam Bypass Control System OR Atmospheric Dump valves responding tomaintain Steam Generator pressure Heater Drain Pumps trip Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S5Start Hydrogen Recombiner AApplicant: Examiner:

JPM S5 Revision 0 Page 2 of 112010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Start Hydrogen Recombiner A Task Standard: Hydrogen Recombiner A is operating in accordance with OP-008-006, Hydrogen Recombiner.

References:

OP-008-006, Hydrogen Recombiner. Validation Time: 25 minutes Time Critical: NoAlternate Path: NoApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM S5 Revision 0Page 3 of 11 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: OP-008-006, Hydrogen Recombiner

Description:

Applicant will be directed to start Hydrogen Recombiner A using OP-008-006. All manipulations will occur at CP-33. One reading will be required to be obtained from CP-8. Step 6.1.10 will direct monitoring for temperature to rise to > 1225 °F. The task will be stopped when this step is reached.

READ TO APPLICANTDIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task. INITIAL CONDITIONS: A Loss of Coolant Accident is in progress. Before the LOCA, Containment Temperature was recorded as 105 °F in OP-903-001, Technical Specification Logs. INITIATING CUES: The CRS directs you to place Hydrogen Recombiner A in service using OP-008-006.

JPM S5 Revision 0Page 4 of 11 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Record present Post-LOCA Containment pressure from Containment Atmosphere Pressure Indicator, ESF-IPI-6750A, on Attachment 11.2, Hydrogen Recombiner Power Control Setting Data Sheet.

Value recorded. Comment: This value can vary based on the time taken to complete JPM S2. Value should be ~19 psia. SAT / UNSAT TASK ELEMENT STANDARD Record Pre-LOCA Containment Average Temperature from OP-903-001, Technical Specification Surveillance Logs, on Attachment 11.2.

Value recorded. Comment: Given in the cue. SAT / UNSAT TASK ELEMENT STANDARD Determine Pressure Factor (Cp) from Attachment 11.4, Dry Containment Recombiner Power Correction Factor Graph. Correction Factor determined. Comment: Will vary based on pressure recorded in step 1. Should determine a value of 1.18 to 1.22. CriticalSAT / UNSAT TASK ELEMENT STANDARD Record Pressure Factor (Cp) on Attachment 11.2. Value recorded. Comment: SAT / UNSAT JPM S5 Revision 0Page 5 of 11 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Determine Hydrogen Recombiner Power Control Setting by multiplying a reference power of 48 KW by Cp. Setting determined. Comment: Equals value determined in step 6.1.1.3

48. Should be 56.6 - 58.6 CriticalSAT / UNSAT TASK ELEMENT STANDARD Record Hydrogen Recombiner Power Control Setting on Attachment 11.2.Value recorded. Comment: SAT / UNSAT TASK ELEMENT STANDARD Continuously monitor the Hydrogen Recombiner A Power Meter, HRA-EM-960, when power level is being changed. Step reviewed. Comment: SAT / UNSAT TASK ELEMENT STANDARD Procedure Note Adjusting the Hydrogen Recombiner Power Control potentiometer slowly compensates for the lag between the meter and the potentiometer adjustments. Note reviewed. Comment: SAT / UNSAT JPM S5 Revision 0Page 6 of 11 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Verify Hydrogen Recombiner A Power Control potentiometer is set at zero (000).Setting verified. Comment: SAT / UNSAT TASK ELEMENT STANDARD Place Hydrogen Recombiner A Power control switch, HRA-001A, to ON. HRA-001A is ON. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Slowly adjust Hydrogen Recombiner Power Control potentiometer for Hydrogen Recombiner A until 5 KW is indicated on Hydrogen Recombiner A Power Meter, HRA-EM-960. 5 KW is indicated on Hydrogen Recombiner A Power Meter. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Hold reading for 10 minutes. Acknowledges hold. Comment: Prompt applicant that 10 minutes has elapsed. SAT / UNSAT JPM S5 Revision 0Page 7 of 11 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Verify Hydrogen Thermocouple Temperatures trend upward when adjusting Power Control Potentiometer, as indicated on Hydrogen Recombiner A Outlet Air Temperature Indicator, HRA-ITI-0001A. Use Temperature Select switch to read thermocouple temperatures. Temperatures monitored. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Adjust Hydrogen Recombiner Power Control potentiometer for Hydrogen Recombiner A until 10 KW indicated on Hydrogen Recombiner A Power Meter, HRA-EM-960. 10 KW is indicated on Hydrogen Recombiner A Power Meter. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Hold reading for 10 minutes. Acknowledges hold. Comment: Prompt applicant that 10 minutes has elapsed. SAT / UNSAT TASK ELEMENT STANDARD Adjust Hydrogen Recombiner Power Control potentiometer for Hydrogen Recombiner A until 20 KW indicated on Hydrogen Recombiner A Power Meter, HRA-EM-960. 20 KW is indicated on Hydrogen Recombiner A Power Meter. Comment: CriticalSAT / UNSAT JPM S5 Revision 0Page 8 of 11 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Hold reading for 10 minutes. Acknowledges hold. Comment: Prompt applicant that 10 minutes has elapsed. SAT / UNSAT TASK ELEMENT STANDARD Procedure Caution DO NOT EXCEED 75 KW. Caution Reviewed. Comment: SAT / UNSAT TASK ELEMENT STANDARD Adjust Hydrogen Recombiner Power Control Potentiometer for Hydrogen Recombiner A to setting calculated on Attachment 11.2. Potentiometer adjusted. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Procedure Caution DO NOT EXCEED 1400 °F. Caution reviewed. Comment: SAT / UNSAT JPM S5 Revision 0Page 9 of 11 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Adjust Hydrogen Recombiner Power Control potentiometer as necessary, within the following guidelines, to maintain heater temperature > 1225 °F to 1400 °F, as read on Hydrogen Recombiner A Outlet Air Temperature Indicator, HRA-ITI-0001A: Use the average of all three thermocouples temperatures to obtain a heater temperature. Example: 1200, 1210, and 1220, use 1210°F. If only two thermocouples are within 50°F of each other, then use average of the closest two temperatures. Examples: 1200, 1210, and 1270, use 1205°F. The following computer points can be used to trend operation of the Hydrogen Recombiner Operation: A42700 - Temp 1 A42701 - Temp 2 A42702 - Temp 3 Step reviewed. Comment: Temperature will be < 300 °F at this time. End task when this step is reached.SAT / UNSAT END OF TASK JPM S5 Revision 0Page 10 of 11 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: A Loss of Coolant Accident is in progress. Before the LOCA, Containment Temperature was recorded as 105 °F in OP-903-001, Technical Specification Logs. INITIATING CUES: The CRS directs you to place Hydrogen Recombiner A in service using OP-008-006.

JPM S5 Revision 0Page 11 of 11 2010 NRC Walk Through ExamSIMULATOR OPERATOR INSTRUCTIONSThis JPM will be performed after JPM S2. No reset is required. Verify the following Malfunctions:

o Rc24a 3%Place the Simulator in Run on the lead examiners cue.

System Operating Procedure OP-008-006Hydrogen Recombiner Revision 8 4 3.0 PRECAUTIONS AND LIMITATIONS 3.1 PRECAUTIONS 3.1.1 At no time should Hydrogen Recombiner temperature be allowed to exceed 1400 F. 3.1.2 At no time should Hydrogen Recombiner power be allowed to exceed 75 KW. 3.2 LIMITATIONS

3.2.1 Hydrogen

Recombination occurs between temperatures of 1150F and 1400 F depending on Hydrogen Concentration. Maintaining Hydrogen Recombiner Temperature > 1225F assures Hydrogen Recombination at lower Hydrogen Concentrations. 3.2.2 Except for testing, Hydrogen Recombiners should only be operated when Containment hydrogen concentration rises to 0.6% Post Accident in Containment.

System Operating Procedure OP-008-006Hydrogen Recombiner Revision 8 7 6.0 NORMAL OPERATION 6.1 RECOMBINER STARTUP 6.1.1 Calculate required Hydrogen Recombiner Power Control potentiometer setting by performing following: 6.1.1.1 Record present Post-LOCA Containment pressure from Containment Atmosphere Pressure Indicator, ESF-IPI-6750A, on Attachment 11.2, Hydrogen Recombiner Power Control Setting Data Sheet. 6.1.1.2 Record Pre-LOCA Containment Average Temperature from OP-903-001, Technical Specification Surveillance Logs, on Attachment 11.2. 6.1.1.3 Determine Pressure Factor (Cp) from Attachment 11.4, Dry Containment Recombiner Power Correction Factor Graph. 6.1.1.3.1 Record Pressure Factor (Cp) on Attachment 11.2. 6.1.1.4 Determine Hydrogen Recombiner Power Control Setting by multiplying a reference power of 48 KW by Cp. 6.1.1.4.1 Record Hydrogen Recombiner Power Control Setting on Attachment 11.2. 6.1.2 Continuously monitor the Hydrogen Recombiner A(B) Power Meter, HRA-EM-960(962), when power level is being changed.

NOTE Adjusting the Hydrogen Recombiner Power Control potentiometer slowly compensates for the lag between the meter and the potentiometer adjustments 6.1.3 Verify Hydrogen Recombiner A(B) Power Control potentiometer is set at zero (000). 6.1.4 Place Hydrogen Recombiner A(B) Power control switch, HRA-001A(B), to ON. 6.1.5 Slowly adjust Hydrogen Recombiner Power Control potentiometer for Hydrogen Recombiner A(B) until 5 KW is indicated on Hydrogen Recombiner A(B) Power Meter, HRA-EM-960(962). 6.1.5.1 Hold reading for 10 minutes. 6.1.6 Verify Hydrogen Thermocouple Temperatures trend upward when adjusting Power Control Potentiometer, as indicated on Hydrogen Recombiner A(B) Outlet Air Temperature Indicator, HRA-ITI-0001A(B). Use Temperature Select switch to read thermocouple temperatures.

System Operating Procedure OP-008-006Hydrogen Recombiner Revision 8 8 6.1.7 Adjust Hydrogen Recombiner Power Control potentiometer for Hydrogen Recombiner A(B) until 10 KW indicated on Hydrogen Recombiner A(B) Power Meter, HRA-EM-960(962). 6.1.7.1 Hold reading for 10 minutes. 6.1.8 Adjust Power Control Potentiometer for Hydrogen Recombiner(s) A(B) until 20 KW is indicated on Hydrogen Recombiner A(B) Power meter, HRA-EM-960(962). 6.1.8.1 Hold reading for 10 minutes.

CAUTIONDO NOT EXCEED 75 KW. 6.1.9 Adjust Hydrogen Recombiner Power Control Potentiometer for Hydrogen Recombiner A(B) to setting calculated on Attachment 11.2.

CAUTION DO NOT EXCEED 1400 F. 6.1.10 Adjust Hydrogen Recombiner Power Control potentiometer as necessary, within the following guidelines, to maintain heater temperature > 1225F to 1400 F, as read on Hydrogen Recombiner A(B) Outlet Air Temperature Indicator, HRA-ITI-0001A(B): Use the average of all three thermocouples temperatures to obtain a heater temperature. Example: 1200, 1210, and 1220, use 1210 F. If only two thermocouples are within 50F of each other, then use average of the closest two temperatures. Examples: 1200, 1210, and 1270, use 1205 F. The following computer points can be used to trend operation of the Hydrogen Recombiner Operation: Hydrogen Recombiner A Hydrogen Recombiner B A42700 - Temp 1 A42703 - Temp 1 A42701 - Temp 2 A42704 - Temp 2 A42702 - Temp 3 A42705 -

Temp 3 System Operating Procedure OP-008-006Hydrogen Recombiner Revision 8 9 6.1.11 Record Containment hydrogen concentration, Date, and Time on Attachment 11.3 when Hydrogen Recombiner Heater temperature reaches > 1225 F. 6.1.12 Verify proper Hydrogen Recombiner operation in accordance with Section 6.2, Verification of Recombiner Operation.

OP-008-006 Revision 8 Attachment 11.2 (1 of 1)18 11.2 HYDROGEN RECOMBINER POWER CONTROL SETTING DATA SHEET SECTION 6.1 (6.2)

STEP # 6.1.1.1 (6.2.4.1) Post-LOCA Containment Pressure, ESF-IPI-6750A (CP-8) 6.1.1.2 (6.2.4.2) Pre-LOCA Containment Temperature (from OP-903-001) 6.1.1.3.1 (6.2.4.3.1) Cp (from Attachment 11.4) 6.1.1.4.1 (6.2.4.4.1) 48 KW X Cp = Recombiner Power Control Setting 48 KW X = Performed by: (Signature) (Date) Verified by:

(Signature) (Date) 1 OP-008-006 Revision 8 Attachment 11.3 (1 of 1)19 11.3 CONTAINMENT HYDROGEN CONCENTRATION DATA SHEET SECTION 6.1 STEP # INITIALS 6.1.11 % Hydrogen concentration at start of recombiners 6.1.11 Start Date and Time SECTION 6.2 STEP # INITIALS 6.2.3 % Hydrogen concentration after 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 6.2.3 Date and Time

OP-008-006 Revision 8 [LAST PAGE] Attachment 11.4 (1 of 1)20 11.4 DRY CONTAINMENT RECOMBINER POWER CORRECTION FACTOR GRAPH Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S6Stabilize RCS Temperature Applicant: Examiner:

JPM S6 Revision 0 Page 2 of 72010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Stabilize RCS Temperature during an Excess Steam Demand Event Task Standard: Actions contained in step 16 of OP-902-004, Excess Steam Demand Recovery, are complete. Emergency Feedwater controller will be failed requiring use of alternate EFW controller to establish flow.

References:

OP-902-004, Excess Steam Demand Recovery Validation Time: 15 minutes Time Critical: NoAlternate Path: YesApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM S6 Revision 0Page 3 of 7 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: OP-902-004, Excess Steam Demand Recovery

Description:

The simulation begins with a Main Steam line break event in progress. The trigger points for taking action in step 16 are CET temperature rising and Pressurizer pressure rising. Pressurizer pressure will begin rising shortly after coming out of freeze. The CET temperature rise will begin a few minutes later. Upon receiving the indication of both critical parameters rising, the applicant will be required to action the actions specified to prevent pressurized thermal shock conditions.

In the JPM, both EFW control stations are failed. The simulator operator will remove the malfunction on the controller the applicant does not use first. The applicant will have to use the alternate controller to establish EFW flow to S/G #1.

READ TO APPLICANTDIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task. INITIAL CONDITIONS: An Excess Steam Demand event is in progress. The crew is implementing OP-902-004, Excess Steam Demand Recovery. Steam Generator #2 is currently blowing down in Containment. INITIATING CUES: The CRS has directed you to monitor for the trigger points in step 16, and carry out the actions of step 16 when appropriate. Carry out the actions of the BOP and the ATC for step 16.

JPM S6 Revision 0Page 4 of 7 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Actions to stabilize RCS temperature following an excess steam demand event should be initiated when BOTHof the following parameters are met: CET temperatures rise Pressurizer pressure rise Both parameters are monitored. Action does not begin until both parameters are rising. Comment: Parameters can be monitored on the control panels, the PMC, or QSPDS. Pressurizer pressure will begin rising shortly after beginning. CET temperature will begin rising a few minutes later. CriticalSAT / UNSAT TASK ELEMENT STANDARD Place the ADV for the least affected steam generator to manual and fully open the ADV. ADV #1 is in manual with 100% output. Comment: CriticalSAT / UNSAT Evaluator Note Proper manual initiation of Emergency Feedwater requires all 4 switches for the correct S/G to be taken to ACT, 2 on CP-7 and 2 on CP-8. TASK ELEMENT STANDARD Manually initiate EFAS for the least affected steam generator. Both EFAS initiation switches for S/G #1 at CP-7 are taken to ACT. Comment: CriticalSAT / UNSAT JPM S6 Revision 0Page 5 of 7 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Manually initiate EFAS for the least affected steam generator. Both EFAS initiation switches for S/G #1 at CP-8 are taken to ACT. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Place the EFW Flow Control Valve to manual and commence feeding the least affected steam generator. EFW is established to S/G #1 at a rate of approximately 400 gpm. Comment: Both the Primary and Backup EFW flow controllers for S/G #1 are faulted. The booth operator will observe which controller the applicant uses first, and then remove the other fault. The applicant will be required to use the alternate controller to establish EFW flow. CriticalSAT / UNSAT TASK ELEMENT STANDARD IF RCS pressure is greater than or equal to 1500 psia, THENstabilize RCS pressure at a value not to exceed 1600 psid between the RCS and the lowest SG pressure. RCS pressure reduced using Auxiliary Spray valves to < 1600 psid of S/G #2. Comment: If applicant asks for a RCS pressure band, request a recommendation. An appropriate RCS pressure band is 1500-1600 psia. The critical element for this task is to lower RCS pressure with Auxiliary Spray. CriticalSAT / UNSAT END OF TASK JPM S6 Revision 0Page 6 of 7 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: An Excess Steam Demand event is in progress. The crew is implementing OP-902-004, Excess Steam Demand Recovery. Steam Generator #2 is currently blowing down in Containment. INITIATING CUES: The CRS has directed you to monitor for the trigger points in step 16, and carry out the actions of step 16 when appropriate. Carry out the actions of the BOP and the ATC for step 16.

JPM S6 Revision 0Page 7 of 7 2010 NRC Walk Through ExamSIMULATOR OPERATOR INSTRUCTIONS Reset to IC - 192 Verify the following Malfunctions:

o Ms11b 25% Verify the following Overrides:

o Di-08a04a01d-1 Push (for S/G #1 Backup Flow Control Valve, Train A) o Di-08a07a01d-1 Push (for S/G #1 Primary Flow Control Valve, Train B) The booth operator must observe which EFW m/a station the applicant attempts to use first. Delete the override of the second m/a station when the applicant is manipulating the first controller.

EXCESS STEAM DEMAND RECOVERYOP-902-004Revision 011Page 16 of 44 WATERFORD 3 SES

NOTE ----------------------------------------------------------

-Actions to stabilize RCS temperature following an excess steam demand eventshould be initiated whenBOTH of the following parameters are met:

CET temperatures rise

-Pressurizer pressure rise

Stabilize RCS Temperature16.Verify RCS temperature is stabilizedby performing the following:a.Place the ADV for the leastaffected steam generator tomanual and fully open the ADV.b.Manually initiate EFAS for theleast affected steam generator.c.Place the EFW Flow Control Valveto manual and commence feedingthe least affected steam generator.

d.IFRCS pressure is greater than orequal to 1500 psia,THEN stabilizeRCS pressure at a value not toexceed 1600 psid between theRCS and the lowest SG pressure.

d.1 IF RCS pressure is less than 1500 psia,THEN stabilize RCSpressure at greater than HPSIshutoff head (1500-1600 psia).INSTRUCTIONSCONTINGENCY ACTIONS Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S7Reset Containment Spray Actuation Applicant: Examiner:

JPM S7 Revision 0 Page 2 of 82010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Reset Containment Spray Actuation Task Standard: CSAS initiation and actuation are reset in accordance with OP-902-009, Standard Appendices, Appendix 5 - E.

References:

OP-902-009, Standard Appendices, Appendix 5 - E OP-902-004, Excess Steam Demand Recovery Validation Time: 15 minutes Time Critical: NoAlternate Path: NoApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM S7 Revision 0Page 3 of 8 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: OP-902-009, Standard Appendices, Appendix 5 - E OP-902-004, Excess Steam Demand Recovery

Description:

The JPM begins in an Excess Steam Demand event, after the applicable Steam Generator has blown dry. Containment Spray termination criteria are met. The applicant will be directed to reset CSAS. Actions for this task take place at CP-8, CP-10 A through D, and CP-33.

READ TO APPLICANTDIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task. INITIAL CONDITIONS: An Excess Steam Demand event has occurred. The crew is implementing OP-902-004, Excess Steam Demand Recovery The conditions of step 44 of OP-902-004 have been verified to be met. Containment Spray is NOT needed for iodine removal. INITIATING CUES: The CRS directs you, the BOP operator, to perform OP-902-009, Standard Appendices, Appendix 5 - E and reset CSAS.

JPM S7 Revision 0Page 4 of 8 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Place control switches for the following valves to CLOSE: CC-641, CCW RCP INLET OUTSIDE ISOL CC-710, CCW RCP OUTLET INSIDE ISOL CC-713, CCW RCP OUTLET OUTSIDE ISOL All 3 valve control switches are in CLOSED. Comment: CriticalSAT / UNSAT Evaluator Note To Reset CSAS Initiation relays, the following 4 steps must be performed on Channels A, B, C, and D. TASK ELEMENT STANDARD Place the Reset Permissive switch to "UNLK" position. (CP-10) The applicable Reset Permissive switch is in UNLK. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Press CSAS Reset pushbutton. CSAS Reset pushbutton is pressed. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Verify the initiation relay indicator lit on the ENGINNERED SAFETY FEATURES SYSTEM mimic. Verification complete. Comment: SAT / UNSAT JPM S7 Revision 0Page 5 of 8 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Place the Reset permissive switch to LK position The applicable Reset Permissive switch is in the LK position. Comment: This sequence must be repeated for Channels A - D. CriticalSAT / UNSAT TASK ELEMENT STANDARD Reset CSAS actuation logic on BOTHtrains as follows: Press the CSAS Reset pushbuttons. (CP-33) CSAS Reset pushbuttons A & B have been de-pressed. Comment: There are 2 buttons on CP-33 that must be pressed, 1 for Train A and 1 for Train B. CriticalSAT / UNSAT TASK ELEMENT STANDARD Verify the actuation relay indicator lit on the ENGINEERED SAFETY FEATURES SYSTEM mimic. (CP-10) CP-10 verification is complete. Comment: SAT / UNSAT TASK ELEMENT STANDARD Stop ONE CS pump at a time. One Containment Spray Pump is secured. Comment: CriticalSAT / UNSAT JPM S7 Revision 0Page 6 of 8 2010 NRC Walk Through ExamTASK ELEMENT STANDARD IF a CS pump is operating, THENstop the remaining CS pump. Second Containment Spray Pump is secured. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Close the following Containment Spray valves: CS-125 A, CNTMT SPRAY HEADER A ISOL CS-125 B, CNTMT SPRAY HEADER B ISOL CS-125 A and CS-125 B are closed. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Place BOTHContainment Spray pump control switches to normal position. Both Containment Spray pump control switches are in the normal position. Comment: CriticalSAT / UNSAT END OF TASK JPM S7 Revision 0Page 7 of 8 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: An Excess Steam Demand event has occurred. The crew is implementing OP-902-004, Excess Steam Demand Recovery The conditions of step 44 of OP-902-004 have been verified to be met. Containment Spray is NOT needed for iodine removal. INITIATING CUES: The CRS directs you, the BOP operator, to perform OP-902-009, Standard Appendices, Appendix 5 - E and reset CSAS.

JPM S7 Revision 0Page 8 of 8 2010 NRC Walk Through ExamSIMULATOR OPERATOR INSTRUCTIONS Reset to IC - 193 Verify the following Malfunctions:

o Ms11b 25%

o Ch09 50%Place the Simulator in Run on the lead examiners cue.

STANDARD APPENDICES OP-902-009Revision 301Page 69 of 195WATERFORD 3 SESESFAS ResetAttachment 5-E: CSAS Reset ProcedureINSTRUCTIONSCONTINGENCY ACTIONS____ 1.1Place control switches for the following valves to "CLOSE:"*CC 641, CCW RCP INLET OUTSIDE ISOL

CC 710, CCW RCP OUTLET INSIDE ISOL

CC 713, CCW RCP OUTLET OUTSIDE ISOL____ 1.2Reset CSAS Initiation relays on ALL four channels as follows:a.Place the Reset Permissive switch to "UNLK" position. (CP-10)b.Press CSAS Reset pushbutton.c.Verify the initiation relay indicator lit on the ENGINNERED SAFETY FEATURES SYSTEM mimic.d.Place the Reset permissive switch to "LK" position.Appendix 5Page 30 of 31 STANDARD APPENDICES OP-902-009Revision 301Page 70 of 195WATERFORD 3 SES____ 1.3Reset CSAS actuation logic on BOTH trains as follows:a.Press the CSAS Reset pushbuttons. (CP-33)b.Verify the actuation relay indicator lit on the ENGINEERED SAFETY FEATURES SYSTEM mimic. (CP-10)____ 1.4Stop ONE CS pump at a time.____ 1.5 IF a CS pump is operating, THEN stop the remaining CS pump.____ 1.6Close the following Containment Spray valves:

CS 125A, CNTMT SPRAY

HEADER A ISOL

CS 125B, CNTMT SPRAY HEADER B ISOL____ 1.7Place BOTH Containment Spray pump control switches to normal position.End of Appendix 5INSTRUCTIONSCONTINGENCY ACTIONSAppendix 5Page 31 of 31 Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S8Start Component Cooling Water Pump ABApplicant: Examiner:

JPM S8 Revision 0 Page 2 of 72010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Start Component Cooling Water Pump AB as the second CCW Pump. Task Standard: Transfer 3AB Bus and start Component Cooling Water Pump AB in accordance with OP-901-311, Loss of Train B Safety Bus.

References:

OP-901-311, Loss of Train B Safety Bus Validation Time: 15 minutes Time Critical: NoAlternate Path: NoApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM S8 Revision 0Page 3 of 7 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: OP-901-311, Loss of Train B Safety Bus

Description:

Plant conditions start after a Loss of Offsite Power. Emergency Diesel Generator B tripped on overspeed; the 3B Safety Bus is not energized. Emergency Diesel Generator A and Component Cooling Water Pump A are running. The applicant will be directed to start CCW Pump AB as the second CCW Pump. The 3AB Bus will be aligned to Train B, requiring an AB Bus transfer prior to starting CCW Pump AB.

Manipulations will occur at CP-1 and CP-8.

READ TO APPLICANTDIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task. INITIAL CONDITIONS: A Loss of Offsite Power has occurred. Emergency Diesel Generator B tripped on Overspeed. Emergency Diesel Generator A is running connected to the 3A Bus INITIATING CUES: The CRS directs you to start Component Cooling Water Pump AB using OP-901-311, Loss of Train B Safety Bus, section E0.

JPM S8 Revision 0Page 4 of 7 2010 NRC Walk Through ExamIf BUS AB3 is not energized, then align BUS AB3 to BUS A3 as follows: TASK ELEMENT STANDARD Place BUS TIE B TO AB keyswitch to TRIP. BUS TIE B TO AB keyswitch is in TRIP. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Place BUS AB STATUS SELECTOR switch to A. BUS AB STATUS SELECTOR switch is in A. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Place BUS TIE A TO AB keyswitch to CLOSE BUS TIE A TO AB keyswitch is in CLOSE. Comment: CriticalSAT / UNSAT Verify two Component Cooling Water Pumps operating and supplying both A and B loops. TASK ELEMENT STANDARD Place CCW Assignment Switch to position B. CCW Assignment Switch is in position B. Comment: CriticalSAT / UNSAT JPM S8 Revision 0Page 5 of 7 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Verify Open the following valves: CC-126B/CC-114B CCW Suct & Disch Header Tie Valves AB to B CC-127B/CC-115B CCW Suct & Disch Header Tie Valves AB to B CC-126B, CC-114B, CC-127B, and CC-115B are verified open. Comment: SAT / UNSAT TASK ELEMENT STANDARD Start CCW Pump AB. CCW Pump AB is running. Comment: CriticalSAT / UNSAT END OF TASK JPM S8 Revision 0Page 6 of 7 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: A Loss of Offsite Power has occurred. Emergency Diesel Generator B tripped on Overspeed. Emergency Diesel Generator A is running connected to the 3A Bus INITIATING CUES: The CRS directs you to start Component Cooling Water Pump AB using OP-901-311, Loss of Train B Safety Bus, section E0.

JPM S8 Revision 0Page 7 of 7 2010 NRC Walk Through ExamSIMULATOR OPERATOR INSTRUCTIONS Reset to IC - 194 Verify the following Malfunctions:

o Eg10b True o Ed01a True o Ed01b True o Ed01c True o Ed01d TruePlace the Simulator in Run on the lead examiners cue.

Off Normal ProcedureOP-901-311Loss of Train B Safety BusRevision 303 6E.SUBSEQUENT OPERATOR ACTIONS E 0 GENERALCAUTIONFAILURE TO ENERGIZE B3 SAFETY BUS OR START COMPONENT COOLING WATERPUMP RAISES THE FOLLOWING CONCERNS: LOSS OF COOLING TO EMERGENCY DIESEL GENERATOR RUNOUT OF OPERATING COMPONENT COOLING WATER PUMP REDUCED COOLING FLOW TO REACTOR COOLANT PUMPS PLACEKEEPERSTART DONEN/A 1. If either BUS B2 TO B3 TIE BKR or BUS B3 TO B2 TIEBKR opens, then verify the following: Emergency Diesel Generator B starts and outputbreaker closes. Emergency Diesel Generator B Sequencer startsloading sequence or has completed loading sequence.2. If BUS AB3 is not energized, then align BUS AB3 toBUS A3 as follows:2.1 BUS TIE B TO AB to TRIP.2.2 BUS AB STATUS SELECTOR to A.2.3 BUS TIE A TO AB to CLOSE.

Off Normal ProcedureOP-901-311Loss of Train B Safety BusRevision 303 7 PLACEKEEPERSTART DONEN/A3. Verify two Component Cooling Water Pumps operating and supplying both A and B loops.3.1 IfCCW Pump AB is the standby pump and it isdesired to align this pump for service, then performthe following:3.1.1 Place CCW Assignment Switch to position B.3.1.2 Verify Open the following valves: CC-126B/CC-114B CCW Suct & DischHeader Tie Valves AB to B CC-127B/CC-115B CCW Suct & DischHeader Tie Valves AB to B3.1.3 Start CCW Pump AB.

3.2 If CCW Pump B is the standby pump and it isdesired to align this pump for service, then performthe following:3.2.1 Start CCW Pump B.3.2.2 Place CCW Assignment Switch to NORM.

Off Normal ProcedureOP-901-311Loss of Train B Safety BusRevision 303 8NOTE(1) Manual Override of RCP Seal Cooler Isolation Valves is accomplished by positioningassociated Control Switch to Close, then to Open.(2) If RCP Seal Cooler(s) re-isolate following being overridden, then OP-901-510,Component Cooling Water Malfunction should be referred to for further guidance.

PLACEKEEPERSTART DONEN/A 3.3 If CCW to Reactor Coolant Pump Seal Cooler (s)Isolate, then within 3 minutes restore ComponentCooling Water flow to applicable Reactor CoolantPump(s) by opening the applicable RCP CCWIsolation Valve(s): CC-679A/CC-6651ARCP 1A CC-679B/CC-6651BRCP 1B CC-680A/CC-666ARCP 2A CC-680B/CC-666BRCP 2B Off Normal ProcedureOP-901-311Loss of Train B Safety BusRevision 303 9CAUTIONCCW PUMP RUNOUT OCCURS AT 8383 GPM. WHEN EVALUATING CCW PUMPOPERATING CONDITIONS, CONSIDER THE NUMBER OF PUMPS RUNNING AND IFCCW TRAINS ARE CROSS CONNECTED.

PLACEKEEPERSTART DONEN/A 4. If two CCW Pumps are not operating, then perform thefollowing:4.1 Secure Emergency Diesel Generator B by pullingthe overspeed trip plunger.NOTEClosing CC-200B/CC-563 will also close CC-620, CCW to the Spent Fuel. CC-620 can be overridden, if necessary to lower Spent Fuel Pool Temperature.4.2 Split CCW trains to prevent runout of operatingpump by closing the following valves: CC 126B/CC 114BCW SUCT & DISCHHEADER TIEVALVES AB TO B CC 200B/CC 563CW SUCT & DISCHHEADER TIE VALVES B TO AB Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE P1Atmospheric Dump Valve Local Operation Applicant: Examiner:

JPM P1 Revision 0 Page 2 of 92010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Locally operate Atmospheric Dump Valve A Task Standard: Open Atmospheric Dump Valve A to 25% open in accordance with OP-005-004, Main Steam. Local pneumatic control will fail during the evolution, requiring local handwheel control.

References:

OP-005-004, Main Steam Validation Time: 20 minutes Time Critical: NoAlternate Path: YesApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM P1 Revision 0Page 3 of 9 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: OP-005-004, Main Steam

Description:

Applicant will be directed to open Atmospheric Dump Valve A to 25% open. During the task, local pneumatic control will not function, requiring local handwheel operation. Task will occur in Main Steam Isolation Valve A room and does require climbing ladders to access the platform. Gloves are required.

READ TO APPLICANTDIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task. INITIAL CONDITIONS: The plant is in Mode 3 RCS temperature is being controlled by Atmospheric Dump Valve A and B. INITIATING CUES: The CRS called and informed you that the CP-8 controller for Atmospheric Dump Valve A is not responding. The CRS directs you to locally open MS-116 A, Atmospheric Dump Valve A to 25% open using OP-005-004, Main Steam. All necessary Tech Spec actions will be performed by the Control Room.

JPM P1 Revision 0Page 4 of 9 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Procedure Note Refer to T.S. 3.7.1.7 prior to performing this section. Note reviewed. Comment: SAT / UNSAT TASK ELEMENT STANDARD Procedure Caution OPENING ADV MAY CAUSE AN RCS COOLDOWN, RESULTING IN A CHANGE IN REACTIVITY AND STEAM GENERATOR LEVELS. Caution reviewed. Comment: SAT / UNSAT TASK ELEMENT STANDARD Establish communications with the Control Room. Control Room contacted. Comment: Cue: Control Room standing by for local operation of MS-116 A, ADV #1. SAT / UNSAT TASK ELEMENT STANDARD Record the pressure at the outlet of the transducer: Pressure recorded. Comment: Pressure reads as it is displayed (~ 3 psig). SAT / UNSAT JPM P1 Revision 0Page 5 of 9 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Adjust the pressure at Air Regulator outlet on the front of the panel to the pressure noted in step 8.7.2.1. Pressure adjusted to pressure from preceding step. Comment: Cue: Turning the regulator operator counter clockwise will lower pressure. When handle is turned in the correct direction, cue that pressure lowers to required pressure. CriticalSAT / UNSAT TASK ELEMENT STANDARD Turn the Pneumatic Permissive Valve above the Transducer to Manual. Pneumatic Permissive Valve is in manual. Comment: Cue: Valve handle is rotated from Auto to Manual. CriticalSAT / UNSAT TASK ELEMENT STANDARD Turn the Pneumatic Permissive Valve above the Air Regulator to Manual. Pneumatic Permissive Valve is in manual. Comment: Cue: Valve handle is rotated from Auto to Manual. CriticalSAT / UNSAT JPM P1 Revision 0Page 6 of 9 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Procedure Note The ADV will be closed when pressure at outlet of Air Regulator is < 4.5 PSIG and full open when pressure at outlet of Air Regulator is > 15 PSIG. Note reviewed. Comment: SAT / UNSAT Evaluator Note The next step introduces the fault. When the air regulator is adjusted, provide the cue that there is no change in pressure and that MS-116 A, ADV #1 is not moving. TASK ELEMENT STANDARD Adjust the Air Regulator pressure to obtain desired valve position by performing any of the following: Open MS-116 A by turning air regulator adjusting screw in the clockwise direction to raise air pressure. Close MS-116 A by turning the air regulator adjusting screw in the counterclockwise direction to lower air pressure. Applicant attempts to adjust pressure. Comment: Cue: pressure and ADV position are not changing. CriticalSAT / UNSAT If desired to operate MS-116A using local handwheel, then perform the following: TASK ELEMENT STANDARD Close Local NG/IA Isolation to the positioner MS-116A SG 1 MS Atm Dump Valve: NG-8271 C, NG/IA Isolation to MS-116A NG-8271 C is closed Comment: Cue: Valve closes when operated. CriticalSAT / UNSAT JPM P1 Revision 0Page 7 of 9 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Open Filter Petcock Drain and bleed off Air/N2 pressure by opening Filter Petcock Drain. Filter Petcock Drain is open. Comment: Cue: Air is heard coming from the drain when opened. Pressure lowers to zero and air flow stops. CriticalSAT / UNSAT TASK ELEMENT STANDARD Open MS-116A SG 1 MS Atm Dump Valve Local Valve Positioner Equalizing Valve. Positioner Equalizing Valve is open. Comment: Cue: Valve open when operated. CriticalSAT / UNSAT Engage local handwheel and Open MS-116A SG 1 MS Atm Dump Valve to desired position by performing the following: TASK ELEMENT STANDARD Unscrew clevis from top of the Manual Override Shaft. Clevis removed. Comment: Cue: Clevis unscrews when operated. CriticalSAT / UNSAT TASK ELEMENT STANDARD Turn handwheel to expose actuator shaft above manual override shaft. Actuator shaft exposed. Comment: Cue: As handwheel is turned clockwise, actuator shaft is exposed. When shaft is fully exposed, notch at the bottom of the shaft is visible. CriticalSAT / UNSAT JPM P1 Revision 0Page 8 of 9 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Slide clevis onto actuator shaft. Clevis installed. Comment: Cue: Clevis fits into notch. CriticalSAT / UNSAT TASK ELEMENT STANDARD Turn handwheel to open MS-116A to desired position. MS-116 A, ADV #1 is 25%

open.Comment: Cue: As handwheel is turned counter clockwise, MS-116 A, ADV #1 opens. Steam issues from ADV #1 exhaust pipe. CriticalSAT / UNSAT END OF TASK JPM P1 Revision 0Page 9 of 9 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: The plant is in Mode 3 RCS temperature is being controlled by Atmospheric Dump Valve A and B. INITIATING CUES: The CRS called and informed you that the CP-8 controller for Atmospheric Dump Valve A is not responding. The CRS directs you to locally open MS-116 A, Atmospheric Dump Valve A to 25% open using OP-005-004, Main Steam. All necessary Tech Spec actions will be performed by the Control Room.

System Operating ProcedureOP-005-004Main SteamRevision 019 268.7 L OCAL OPERATION OF ATMOSPHERIC D UMP VALVENOTERefer to T.S. 3.7.1.7 prior to performing this section.CAUTIONOPENING ADV MAY CAUSE AN RCS COOLDOWN, RESULTING IN A CHANGE INREACTIVITY AND STEAM GENERATOR LEVELS.8.7.1 Establish communications with the control room.

8.7.2 If desired to operate MS-116A(B) locally using pneumatic operation, then performthe following:8.7.2.1Record the pressure at the outlet of the transducer: ________ PSIG.8.7.2.2Adjust the pressure at Air Regulator outlet on the front of the panel to thepressure noted in step 8.7.2.1.8.7.2.3Turn the Pneumatic Permissive Valve above the Transducer to Manual.8.7.2.4Turn the Pneumatic Permissive Valve above the Air Regulator to Manual.NOTEThe ADV will be closed when pressure at outlet of Air Regulator is <4.5 PSIG and full openwhen pressure at outlet of Air Regulator is >15 PSIG.8.7.2.5Adjust the Air Regulator pressure to obtain desired valve position byperforming any of the following: Open MS-116 A(B) by turning air regulator adjusting screw in theclockwise direction to raise air pressure. Close MS-116 A(B) by turning the air regulator adjusting screw in thecounterclockwise direction to lower air pressure.

System Operating ProcedureOP-005-004Main SteamRevision 019 278.7.3 When local pneumatic operation of MS-116A(B) is no longer desired, then performthe following:8.7.3.1Verify the applicable Atmospheric Dump Valve M/A station on CP-8 is inManual with minimum output.8.7.3.2Turn the Pneumatic Permissive Valve above the Air Regulator from Manual to Auto.8.7.3.3Raise the pressure of the Air Regulator on the front of the panel until pressure no longer rises. Check that outlet pressure on the Air Regulator on the frontof the panel is between 20-25 PSIG.8.7.3.4Adjust Air Regulator outlet pressure on the front of the panel until the outletpressure just begins to drop. Check that Air Regulator outlet pressure on thefront of the panel is between 20-25 PSIG.CAUTION IF THE PRESSURE NOTED IN STEP 8.7.3.5.1 IS GREATER THAN 4.5 PSIG, THEN THEADV MAY OPEN WHEN RETURNED TO REMOTE OPERATION.8.7.3.5Verify pressure at outlet of Transducer is 4.5 PSIG.8.7.3.5.1If the pressure is greater than 4.5 PSIG, then verify the applicableAtmospheric Dump Valve M/A station on CP-8 is in Manual withminimum output.8.7.3.5.2If the applicable Atmospheric Dump Valve M/A station is in Manual withminimum output and transducer pressure is 4.5 PSIG, then I&CMaintenance should be contacted for assistance prior to proceeding.

System Operating ProcedureOP-005-004Main SteamRevision 019 28NOTEOperation of the Air Regulator may loosen the lock nut on the Air Regulator on the front of thepanel. The lock nut should be checked for tightness. A 1/2 open end wrench is required totighten the lock nut. Do not over tighten.8.7.3.6Turn the Pneumatic Permissive Valve above the Transducer from Manual to Auto.8.7.4 If desired to operate MS-116A(B) using local handwheel, then perform thefollowing:8.7.4.1Close Local NG/IA Isolation to the positioner for applicable MS-116A(B) SG1(2) MS Atm Dump Vlv: NG MVAAA8271 CNG/IA Isolation to MS-116A or NG MVAAA9281 DNG/IA Isolation to MS-116B8.7.4.2Open Filter Petcock Drain and bleed off Air/N2 pressure by opening FilterPetcock Drain.8.7.4.3Open MS-116A(B) SG 1(2) MS Atm Dump Vlv Local Valve PositionerEqualizing Valve.8.7.4.4Engage local handwheel and Open MS-116A(B) SG 1(2) MS Atm Dump Vlvto desired position by performing the following:8.7.4.4.1Unscrew clevis from top of the Manual Override Shaft.8.7.4.4.2Turn handwheel to expose actuator shaft above manual override shaft.8.7.4.4.3Slide clevis onto actuator shaft.8.7.4.4.4Turn handwheel to open MS-116A(B) to desired position.

System Operating ProcedureOP-005-004Main SteamRevision 019 298.7.5 When local handwheel operation of MS-116A(B) is no longer desired, thenperform the following:8.7.5.1Verify the applicable Atmospheric Dump Valve M/A station on CP-8 is inManual with minimum output.8.7.5.2Using the local handwheel, Close SG 1(2) MS Atm Dump Vlv, MS-116A(B).8.7.5.3Turn local handwheel until pressure is relieved from clevis and remove clevisfrom actuator shaft.8.7.5.4Turn handwheel until clevis can be installed onto manual override shaft andscrew clevis onto manual override shaft.8.7.5.5Close Filter Petcock Drain.8.7.5.6Open Local NG/IA Isolation to the positioner for applicable MS-116A(B) SG1(2) MS Atm Dump Vlv: NG-8271CNG/IA Isolation to MS-116A or NG-9281DNG/IA Isolation to MS-116B8.7.5.7Close MS-116A(B) SG 1(2) MS Atm Dump Vlv Positioner Equalizing Valve.

8.7.5.8Place Atmospheric Dump Valve M/A station in desired position as directed by SM/CRS.

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE P2SUPS MA OperationApplicant: Examiner:

JPM P2 Revision 0 Page 2 of 82010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:Transfer SUPS MA from Alternate to Normal AC Task Standard: SUPS MA is transferred from Alternate to Normal AC alignment in accordance with OP-006-005, Inverters and Distribution.

References:

OP-006-005, Inverters and Distribution Validation Time: 15 minutes Time Critical: NoAlternate Path: NoApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM P2 Revision 0Page 3 of 8 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: OP-006-005, Inverters and Distribution

Description:

SUPS MA will be simulated in the Alternate AC power alignment. Applicant will transfer SUPS MA to the Normal AC alignment. All steps will be simulated in Switchgear Room A. No special PPE will be required for this task.

READ TO APPLICANTDIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task. INITIAL CONDITIONS: SUPS MA is in the Alternate AC alignment with the inverter isolated and the synchronizing circuitry isolated. INITIATING CUES: The CRS directs you to place SUPS MA in the Normal AC alignment in accordance with OP-006-005, Inverters and Distribution.

JPM P2 Revision 0Page 4 of 8 2010 NRC Walk Through ExamTASK ELEMENT STANDARD If Manual Bypass Switch is in SYNC DISCONNECT, then place Manual Bypass Switch to ALTERNATE SOURCE TO LOAD. Manual Bypass Switch is in ALTERNATE SOURCE TO LOAD. Comment: Cue: Demonstrate that the Manual Bypass Switch is in SYNC DISCONNECT. When rotated, the manual Bypass Switch will indicate ALTERNATE SOURCE TO LOAD. CriticalSAT / UNSAT TASK ELEMENT STANDARD Procedure Note At least 60 seconds must be allowed for capacitors to fully discharge prior to re-energizing inverter. Note reviewed. Comment: CriticalSAT / UNSAT TASK ELEMENT STANDARD Procedure caution POTENTIAL SUPS DAMAGE COULD OCCUR IF THE PRE-CHARGE PUSHBUTTON DOES NOT POP BACK OUT AFTER BEING RELEASED.Caution reviewed. Comment: SAT / UNSAT TASK ELEMENT STANDARD If inverter was isolated in accordance with step 6.1.1.3 or section 8.1, then depress and hold Pre-charge pushbutton until the following are met: Pre-charge light Illuminates DC Input voltage 120 VDC Pre-charge button operated properly with correct indications. Comment: Cue: After the Pre-charge button is held, light illuminates and DC voltage rises to as displayed. Button does not stick. CriticalSAT / UNSAT JPM P2 Revision 0Page 5 of 8 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Verify the following applicable SUPS supply breakers ON: ID-EBKR-312A-2B SUPS MA Normal Supply ID-EBKR-1A-22 SUPS MA Emergency Supply (DC)

Breakers ON. Comment: Cue: Breakers will be as displayed, ON. SAT / UNSAT TASK ELEMENT STANDARD Procedure Caution EMERGENCY FEEDER BREAKER SHALL NOT BE PLACED TO "ON" UNLESS PRE-CHARGE LIGHT IS ILLUMINATED AND DC INPUT VOLTAGE IS 120 VDC. Caution reviewed. Comment: SAT / UNSAT TASK ELEMENT STANDARD Verify applicable SUPS Emergency Feeder breaker ON: ID-EBKR-MA-C SUPS MA Emergency Feeder Breaker is ON. Comment: Cue: Breaker will initially OFF. Provide ON indication after operation. CriticalSAT / UNSAT TASK ELEMENT STANDARD Verify Inverter Output frequency is ~60 HZ (59.7 to 60.3 HZ). Verification complete. Comment: Cue: Parameters as displayed. SAT / UNSAT JPM P2 Revision 0Page 6 of 8 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Verify applicable SUPS Normal Feeder breaker ON: ID-EBKR-MA-B SUPS MA Normal Feeder Breaker is ON. Comment: Cue: Breaker will initially OFF. Provide ON indication after operation. CriticalSAT / UNSAT TASK ELEMENT STANDARD Verify DC Output from Rectifier voltage is 136 to 141.5 VDC. Verification complete. Comment: Cue: parameters as displayed. SAT / UNSAT TASK ELEMENT STANDARD Procedure Caution TO PREVENT INVERTER DAMAGE, THE "IN SYNC" LIGHT MUST BE ILLUMINATED PRIOR TO PLACING MANUAL BYPASS SWITCH TO "INVERTER TO LOAD." Caution Reviewed. Comment: SAT / UNSAT TASK ELEMENT STANDARD Verify In Sync light Illuminated. Verification complete. Comment: Cue: As displayed. SAT / UNSAT JPM P2 Revision 0Page 7 of 8 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Place Manual Bypass Switch to INVERTER TO LOAD. Manual Bypass Switch is in INVERTER TO LOAD Comment: Cue: Provide indication that the switch is initially in ALTERNATE SOURCE TO LOAD, then in INVERTER TO LOAD after operation. CriticalSAT / UNSAT TASK ELEMENT STANDARD Verify Transfer To Bypass Source alarm Clears at local SUPS annunciator panel. Alarms verified. Comment: Cue: As displayed. SAT / UNSAT TASK ELEMENT STANDARD Verify DC Output from Rectifier voltage is ~140 VDC (138.5 to 141.5 VDC). Verification complete. Comment: Cue: As displayed. CriticalSAT / UNSAT TASK ELEMENT STANDARD Perform applicable breaker lineup attachment for SUPS being transferred from Alternate to Normal AC Power: Attachment 11.1 SUPS MA Breaker Lineup N/A Comment: Cue: Inform applicant that the attachment will be performed by another operator and that the task is complete. CriticalSAT / UNSAT END OF TASK JPM P2 Revision 0Page 8 of 8 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: SUPS MA is in the Alternate AC alignment with the inverter isolated and the synchronizing circuitry isolated. INITIATING CUES: The CRS directs you to place SUPS MA in the Normal AC alignment in accordance with OP-006-005, Inverters and Distribution.

System Operating ProcedureOP-006-005Inverters and DistributionRevision 303 256.0 NORMAL OPERATIONS6.1 SUPSMA,MB,MC,&MDNORMAL MANIPULATIONS6.1.1 Transfer from Normal to Alternate AC Power as follows:CAUTION(1) SUPS MA, MB, MC, AND MD MAY BE OPERATED ON THE NORMAL AC SUPPLYWITHOUT THE DC INPUT POWER (EMERGENCY DC SUPPLY) SUPPLIED FROMTHE BATTERY. THE DURATION OPERATING IN THIS CONDITION SHOULD BEMINIMIZED.[EC-11831](2) TECHNICAL SPECIFICATIONS 3.8.3.1 AND 3.8.3.2 SHALL BE REVIEWED PRIOR TO TRANSFER OF A SAFETY SUPS TO ALTERNATE AC POWER.(3) TO PREVENT INVERTER DAMAGE, THE IN SYNC LIGHT MUST BE ILLUMINATED PRIOR TO PLACING MANUAL BYPASS SWITCH TO ALTERNATE SOURCE TOLOAD.6.1.1.1Verify SUPS In Sync light Illuminated, then place Manual Bypass Switch toALTERNATE SOURCE TO LOAD.6.1.1.2Verify Transfer To Bypass Source annunciator at local SUPS annunciatorpanel is Illuminated.6.1.1.3If inverter is to be isolated, then place the following applicable SUPS panelbreakers to OFF:MAID-EBKR-MA-B SUPS MA Normal FeederID-EBKR-MA-C SUPS MA Emergency FeederMBID-EBKR-MB-B SUPS MB Normal FeederID-EBKR-MB-C SUPS MB Emergency FeederMCID-EBKR-MC-B SUPS MC Normal FeederID-EBKR-MC-C SUPS MC Emergency FeederMDID-EBKR-MD-B SUPS MD Normal FeederID-EBKR-MD-C SUPS MD Emergency Feeder6.1.1.4If synchronizing circuitry is to be isolated, then place Manual Bypass Switchto SYNC DISCONNECT.

System Operating ProcedureOP-006-005Inverters and DistributionRevision 303 266.1.2 Transfer from Alternate to Normal AC Power as follows:6.1.2.1If Manual Bypass Switch is in SYNC DISCONNECT, then place ManualBypass Switch to ALTERNATE SOURCE TO LOAD.NOTEAt least 60 seconds must be allowed for capacitors to fully discharge prior to re-energizinginverter.CAUTIONPOTENTIAL SUPS DAMAGE COULD OCCUR IF THE PRE-CHARGE PUSHBUTTONDOES NOT POP BACK OUT AFTER BEING RELEASED.[CR-WF3-2005-02224]6.1.2.2If inverter was isolated in accordance with step 6.1.1.3 or section 8.1, thendepress and hold Pre-charge pushbutton until the following are met: Pre-charge light Illuminates DC Input voltage120 VDC6.1.2.3Verify the following applicable SUPS supply breakers ON:MA ID-EBKR-312A-2B SUPS MA Normal Supply ID-EBKR-1A-22 SUPS MA Emergency Supply (DC)MB ID-EBKR-312B-2B SUPS MB Normal Supply ID-EBKR-B-37 SUPS MB Emergency Supply (DC)MC ID-EBKR-311A-14FSUPS MC Normal Supply ID-EBKR-A-38 SUPS MC Emergency Supply (DC)MD ID-EBKR-311B-14FSUPS MD Normal Supply ID-EBKR-1B-22 SUPS MD Emergency Supply (DC)CAUTIONEMERGENCY FEEDER BREAKER SHALL NOT BE PLACED TO "ON" UNLESSPRE-CHARGE LIGHT IS ILLUMINATED AND DC INPUT VOLTAGE IS 120 VDC.6.1.2.4Verify applicable SUPS Emergency Feeder breaker ON: ID-EBKR-MA-C SUPS MA Emergency Feeder ID-EBKR-MB-C SUPS MB Emergency Feeder ID-EBKR-MC-C SUPS MC Emergency Feeder System Operating ProcedureOP-006-005Inverters and DistributionRevision 303 27 ID-EBKR-MD-C SUPS MD Emergency Feeder6.1.2.4.1Verify Inverter Output frequency is ~60 HZ (59.7 to 60.3 HZ).6.1.2.5Verify applicable SUPS Normal Feeder breaker ON: ID-EBKR-MA-B SUPS MA Normal Feeder ID-EBKR-MB-B SUPS MB Normal Feeder ID-EBKR-MC-B SUPS MC Normal Feeder ID-EBKR-MD-B SUPS MD Normal Feeder6.1.2.5.1 Verify DC Output from Rectifier voltage is 136 to 141.5 VDC.CAUTIONTO PREVENT INVERTER DAMAGE, THE "IN SYNC" LIGHT MUST BE ILLUMINATED PRIOR TO PLACING MANUAL BYPASS SWITCH TO "INVERTER TO LOAD."6.1.2.6Verify In Sync light Illuminated.6.1.2.6.1 Place Manual Bypass Switch to INVERTER TO LOAD.6.1.2.7Verify Transfer To Bypass Source alarm Clears at local SUPS annunciatorpanel.6.1.2.8Verify DC Output from Rectifier voltage is ~140 VDC (138.5 to 141.5 VDC).6.1.2.9Perform applicable breaker lineup attachment for SUPS being transferredfrom Alternate to Normal AC Power: Attachment 11.1 SUPS MABreaker Lineup Attachment 11.3 SUPS MBBreaker Lineup Attachment 11.5 SUPS MCBreaker Lineup Attachment 11.7 SUPS MDBreaker Lineup Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE P3BOP Evacuation of the Control Room ActionsApplicant: Examiner:

JPM P3 Revision 0 Page 2 of 72010 NRC Walk Through Exam JOB PERFORMANCE MEASURE DATA PAGE Task:BOP time critical actions during evacuation of the Control Room. Task Standard: Complete OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown, Attachment 4, steps 4 and 5 for BOP Time Critical Actions.

References:

OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown Validation Time: 20 minutes Time Critical: YesAlternate Path: NoApplicant: Time Start: Time Finish: Performance Time: minutes Performance Rating: SAT UNSAT Comments: Examiner: Date:

Signature JPM P3 Revision 0Page 3 of 7 2010 NRC Walk Through ExamEXAMINER COPY ONLY Tools/Equipment/Procedures Needed: OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown

Description:

Task directs the applicant to perform steps 4 and 5 of Attachment 4 of OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown. Task is performed in the RCA. The procedure directs using a specific door to move from step 3 to step 4.

Access through this door is not allowed during normal plant operation and applicant should use normal access routes. Step 4 is performed in EDG Room B. Step 5 is performed in BAM Tank Rooms A and B. No ladder use is required for this task.

READ TO APPLICANTDIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Indicate to me when you understand your assigned task. INITIAL CONDITIONS: The Control Room was evacuated due to a fire in CP-1. OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown, is being implemented. You are the BOP operator. Steps 1 through 3 of OP-901-502, Attachment 4, BOP Time Critical Actions, are complete. INITIATING CUES: Continue performance of Attachment 4, beginning with step 4.

JPM P3 Revision 0Page 4 of 7 2010 NRC Walk Through ExamPerform the following at Emergency Diesel Generator B:TASK ELEMENT STANDARD Select LOCAL control of EDG B by depressing the Control Mode pushbutton. Local control is selected. Comment: Cue: Indications will be as is on arrival. After Local button is depressed, indication and handle shift to Local. CriticalSAT / UNSAT TASK ELEMENT STANDARD At Diesel Generator B RTGB Isolation Panel (EDG B Room north of phone booth on west wall) perform the following: Depress AND Hold Transition pushbutton. Place key-operated switch, FR 2367, to ISOLATE. Release Transition pushbutton. FR 2367 is in isolate, operated with the Transition button held. Comment: Cue: Indications will be as is on arrival. When keyswitch is placed in ISOLATE, provide cue that EDG B started. CriticalSAT / UNSAT TASK ELEMENT STANDARD IF EDG B failed to start, THEN direct NAO to reset Control Power for 3B Swgr Undervoltage Relays AND THEN verify EDG B starts. N/A Comment: Cue: EDG B will start on previous step. SAT / UNSAT TASK ELEMENT STANDARD Inform the following that EDG B is operating: ATC NAOCommunication completed. Comment: Cue: Acknowledge communication. SAT / UNSAT JPM P3 Revision 0Page 5 of 7 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Procedure note (1) The east side stairwell has emergency lighting provided AND is the preferred path for transiting within the CAA.(2) Local BAM Tank indicators must be unisolated PRIOR to reading using BAM-1111A(B), BAMT A(B) Outlet Line BAMILI0240 (0241)

Root, AND re-isolated when done. Note Reviewed. Comment: SAT / UNSAT TASK ELEMENT STANDARD WHEN informed by NAO that breakers for BAM-113A(B) are Open, THEN OPEN the following:BAM-113A Boric Acid Makeup Tank A Gravity Feed Valve BAM-113B Boric Acid Makeup Tank B Gravity Feed Valve BAM-113 A & BAM-113 B are open. Comment: Cue: Provide the cue that the breakers for BAM-113 A & BAM-113 B are open. Applicant will de-clutch and manually operate MOVs BAM-113 A and BAM-113 B. Each valve is in their respective BAM Tank Room. CriticalSAT / UNSAT TASK ELEMENT STANDARD Inform ATC that BAM-113A AND BAM-113B are Open. Communication completed. Comment: Cue: Acknowledge communication. SAT / UNSAT JPM P3 Revision 0Page 6 of 7 2010 NRC Walk Through ExamTASK ELEMENT STANDARD Provide initial BAM Tank A AND BAM Tank B levels to the ATC using the following indicators: BAM-ILI-0240 Boric Acid Make-up Tank A Discharge Header Level Indicator BAM-ILI-0241 Boric Acid Make-up Tank B Discharge Header Level Indicator Level instruments are un-isolated and levels read.

Level instruments isolated after readings are taken. Comment: Cue: Provide manual valve cues when instruments are un-isolated and re-isolated. Provide tank level reading of 88% each. CriticalSAT / UNSAT TASK ELEMENT STANDARD Provide hourly updates of BAM Tank levels to the ATC (or at a frequency as determined by ATC, based on BAMT levels and usage). N/A Comment: Cue: End task at this point. SAT / UNSAT END OF TASK JPM P3 Revision 0Page 7 of 7 2010 NRC Walk Through ExamAPPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER TO UPON COMPLETION OF TASK) INITIAL CONDITIONS: The Control Room was evacuated due to a fire in CP-1. OP-901-502, Evacuation of Control Room and Subsequent Plant Shutdown, is being implemented. You are the BOP operator. Steps 1 through 3 of OP-901-502, Attachment 4, BOP Time Critical Actions, are complete. INITIATING CUES: Continue performance of Attachment 4, beginning with step 4.

Off Normal ProcedureOP-901-502Evacuation of Control Room and Subsequent Plant ShutdownRevision 017 Page 1 of 6 87 ATTACHMENT4BOPTIME CRITICAL ACTIONS PLACEKEEPERSTART DONEN/A1. Transfer controls to LCP-43 as follows:[10 Minutes]1.1 Place ALLTRANSFER SWITCHES in Aux Panels 2 AND 3 to AUX CR. (Rooms B and AB) Aux Panel 2 Door 1 (12 switches) Aux Panel 2 Door 2 (12 switches) Aux Panel 3 Door 3 (5 Switches)1.2 Place ALLISOLATION SWITCHES in Aux Panels2 to ISOLATE. Aux Panel 2 Door 1 (5 switches)1.3 WHEN informed by STA that Room A transfer iscomplete, THEN notify ATC that transfer toLCP-43 is complete.2. Verify MS-EBKR-1B-10, MSIV B Dump Valve B(MS-ISV-0124B-2&4)(DC), ON.[10 Minutes](located in Power Dist Panel B1-DC, near MCC-311B)

Off Normal ProcedureOP-901-502Evacuation of Control Room and Subsequent Plant ShutdownRevision 017 Page 2 of 6 88 ATTACHMENT4BOPTIME CRITICAL ACTIONS (CONTD)PLACEKEEPERSTART DONEN/A3. Perform A Switchgear breaker alignment as follows:3.1 Place the following breakers to OFF:[25 Minutes] EG-EBKR-A-11EG A Engine ControlPanel Feeder #1 (DC) EG-EBKR-A-12EG A Engine ControlPanel Feeder #2 (DC) EFW-EBKR-A-23 Emergency Feedwtrto SG2 B/U Isol(EFW-229B) (DC) EGF-EBKR-312A-3FEG A Fuel OilTransfer Pump MS-EBKR-313A-6MMSIV A UpstreamDrip Pot Bypass Drain (MS-119A)3.1.1 Inform CRS that MS-119A breaker is Open.[30 Minutes]3.2 Locally OPEN 4KV-EBKR-3A-11, Switchgear 3ABus Tie to Switchgear 2A as follows:[30 Minutes]3.2.1 Simultaneously DEPRESS PermissivePushbutton AND place breaker controlswitch to TRIP.3.2.2 OPEN DC knife switch for 4KV-EBKR-3A-11,Switchgear 3A Bus Tie to Switchgear 2A.

3.2.3 IF 4KV-EBKR-3A-11, Switchgear 3A Bus Tieto Switchgear 2A breaker DID NOT Openusing the control switch, THEN TRIP thebreaker by DEPRESSING the Manual TripLever on the breaker.

Off Normal ProcedureOP-901-502Evacuation of Control Room and Subsequent Plant ShutdownRevision 017 Page 3 of 6 89 ATTACHMENT4BOPTIME CRITICAL ACTIONS (CONTD)NOTEEntry into the Controlled Access Area (CAA) is from A Switchgear through Door D018

.[P-25082]PLACEKEEPERSTART DONEN/A4.Perform the following at Emergency Diesel Generator B:[20 Minutes]4.1 Select LOCAL control of EDG B by depressing theControl Mode pushbutton.4.2 At Diesel Generator B RTGB Isolation Panel (EDGB Room north of phone booth on west wall)perform the following:4.2.1 Depress AND Hold Transition pushbutton.4.2.2 Place key-operated switch, FR 2367, toISOLATE.4.2.3 Release Transition pushbutton.

4.3 IF EDG B failed to start, THEN direct NAO to resetControl Power for 3B Swgr Undervoltage Relays AND THEN verify EDG B starts.4.4 Inform the following that EDG B is operating: ATC NAO Off Normal ProcedureOP-901-502Evacuation of Control Room and Subsequent Plant ShutdownRevision 017 Page 4 of 6 90 ATTACHMENT4BOPTIME CRITICAL ACTIONS (CONTD)NOTE(1) The east side stairwell has emergency lighting provided AND is the preferred path fortransiting within the CAA.[P-25082](2) Local BAM Tank indicators must be unisolated PRIOR to reading using BAM-1111A(B),BAMT A(B) Outlet Line BAMILI0240 (0241) Root, AND re-isolated when done.

PLACEKEEPERSTART DONEN/A5. WHEN informed by NAO that breakers forBAM-113A(B) are Open, THEN OPEN the following:[1 Hour] BAM-113ABoric Acid Makeup Tank A GravityFeed Valve BAM-113BBoric Acid Makeup Tank B GravityFeed Valve5.1 Inform ATC that BAM-113A AND BAM-113B are Open.5.2 Provide initial BAM Tank A AND BAM Tank Blevels to the ATC using the following indicators:Continuous BAM-ILI-0240Boric Acid Make-up Tank ADisch Hdr Level Indicator BAM-ILI-0241Boric Acid Make-up Tank BDisch Hdr Level Indicator5.2.1 Provide hourly updates of BAM Tank levelsto the ATC (or at a frequency as determinedby ATC, based on BAMT levels and usage).Continuous Off Normal ProcedureOP-901-502Evacuation of Control Room and Subsequent Plant ShutdownRevision 017 Page 5 of 6 91 ATTACHMENT4BOPTIME CRITICAL ACTIONS (CONTD)PLACEKEEPERSTART DONEN/A6. WHEN informed by the NAO that breaker lineup iscomplete for aligning Essential Chiller B for service, THEN perform the following:[1.5 Hours]

6.1 IF Essential Chiller AB is replacing B, THEN alignEssential Chiller B to replace AB as follows:6.1.1 Verify Essential Chiller AB and EssentialChill Water Pump AB secured.6.1.2 Unlock, THEN CLOSE AND Lock thefollowing: CHW-110AB CHW Expansion Tank ABHeader Isolation CMU-528B Chiller AB Expansion TankMakeup Isolation6.1.3 Unlock, THEN OPEN AND Lock thefollowing: CMU-529B Condensate Makeup toCHW Expansion Tank B

Isolation CC-305B Essential Chiller B CCWInlet Isolation CHW-788B Chill Water Pump B SuctionLine Isolation CHW-110B CHW Expansion Tank BHeader Isolation.6.1.4 Unlock, THEN CLOSE AND Lock thefollowing: CC-304B CCW Header B Supply toEssential Chiller AB CC-318B CCW Header B Return fromEssential Chiller AB CHW-786B Essential Chiller AB ReturnHeader B Isolation CHW-132B Essential Chiller AB to CHWHeader B Supply Isolation6.2 Verify Chill Water Pump B operating.6.3 Verify Essential Chiller B operating.

Off Normal ProcedureOP-901-502Evacuation of Control Room and Subsequent Plant ShutdownRevision 017 Page 6 of 6 92 ATTACHMENT4BOPTIME CRITICAL ACTIONS (CONTD)NOTEDoor blocks for blocking open respective doors are located in the LCP-43 locker.

PLACEKEEPERSTART DONEN/A7. Establish H&V Room (Essential Chiller Area) ventilationas follows: [1.5 Hours]7.1 Start HVR-MFAN-0024B, RAB +46 HVAC RoomExhaust Fan E-41B, from its local control station.7.2 Block open the following doors: Door D087 H&V Room Door at top of stairs Door D043 H&V Room Door at bottomof stairs8. WHEN Attachment 4 has been completed, THEN informthe Shift Manager.

END

@@ Line 2: / Line 2: @@
 | number = ML101870681
 | issue date = 03/16/2010
-| title = Waterford 3-2010-03-Draft OP Test, 2010 NRC Walk Through Exam, Job Performance Measure A1, RCS Flow Verification and FC1 Calculation
+| title = 3-2010-03-Draft OP Test, 2010 NRC Walk Through Exam, Job Performance Measure A1, RCS Flow Verification and FC1 Calculation
 | author name =
 | author affiliation = NRC/RGN-IV

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