Text

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 Calculation Applicant:

Examiner:

JPM A1 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: No Alternate Path: No Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 5 2010 NRC Walk Through Exam

JPM A1 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 5 2010 NRC Walk Through Exam

JPM A1 TASK ELEMENT STANDARD Completed in accordance with the key. Channel B Complete page 27 of OP-903-001.

MDBAR will be greater than the RCS Flow Factor.

Comment: Critical SAT / 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 Completed in accordance Complete Attachment 11.9, Adjustment of FC1 with the key.

Comment: Critical Cue: When page 1 of the attachment is completed, inform the applicant that another operator will verify the calculation and that the task is SAT / UNSAT complete.

END OF TASK Revision 0 Page 4 of 5 2010 NRC Walk Through Exam

JPM A1 APPLICANT 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.

Revision 0 Page 5 of 5 2010 NRC Walk Through Exam

Redacted

7.3 The limit for RCS flow reflects the Technical Specification limit plus a value of uncertainty in the flow calculation for COLSS and CPC's as per the following Operating cycle schedule:

Plant Minimum Allowed RCS Uncertainty Uncertainty Operating TCold Flow with Uncertainty

(%) (LBM/Hr )

Cycle (LBM/Hr)

Cycle 16 >549 F 4.40% 6.512 E+6 154.512 E+6

>549 F, 557 F 3.00% 4.440 E+6 152.440 E+6 Cycle 17 549 F 2.90% 4.292 E+6 152.292 E+6 8.0 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 or Calculated flow by 148 x 106 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 perform Attachment 11.9, Adjustment of FC1. Re-verify MDBAR < RCS Flow Factor after adjustment and document in the Remarks section. Attach documentation to this Attachment. NA if not in Mode 1, >70% pwr.

OP-903-001 Revision 040 Attachment 11.1 (20 of 37) 37

11.9 ADJUSTMENT OF FC1 CHANNEL UNDER ADJUSTMENT: A B C D 11.9.1 SM/CRS Permission: __________________________________________

(Signature / Date / Time) 11.9.2 Perform New FC1 Calculation:

RCS Mass Flow Rate: PMC PID C24564: ________________

OR NE-004-004: ________________

Core Coolant Mass Flow Rate CPC PID-060: ________________

Rate Calibration Constant (FC1)

Base Core Coolant Mass Flow CPC 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)

OP-903-001 Revision 040 Attachment 11.9 (1 of 6) 104

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

Examiner:

JPM A2 JOB PERFORMANCE MEASURE DATA PAGE Task: Complete a manual CEA Subgroup Selection for Reactor Power Cutback Task 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: No Alternate Path: No Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 5 2010 NRC Walk Through Exam

JPM A2 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 5 2010 NRC Walk Through Exam

JPM A2 TASK ELEMENT STANDARD Attachment 11.1 is Complete OP-004-015, Reactor Power Cutback System, Attachment completed in accordance 11.1, Manual CEA Subgroup Selection.

with the key.

Comment: Critical SAT / UNSAT END OF TASK Revision 0 Page 4 of 5 2010 NRC Walk Through Exam

JPM A2 APPLICANT 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.

Revision 0 Page 5 of 5 2010 NRC Walk Through Exam

Redacted 11.1 MANUAL 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)

OP-004-015 Revision 9 [LAST PAGE] Attachment 11.1 (1 of 1) 20

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE A3 Tagging Boundary Identification Applicant:

Examiner:

JPM A3 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: No Alternate Path: No Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 6 2010 NRC Walk Through Exam

JPM A3 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 6 2010 NRC Walk Through Exam

JPM A3 EXAMINER 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.

Revision 0 Page 4 of 6 2010 NRC Walk Through Exam

JPM A3 TASK ELEMENT STANDARD List the applicable breaker(s) that must be opened to support this work Correct breakers identified.

Comment: Critical 2 breakers must be opened to remove power from the limit switches for CC-200 B: SAT / UNSAT

CC EBKR91B - 11

CC EBKR91B - 21 TASK ELEMENT STANDARD List any other Component Cooling Water valves that will be affected by Correct valves identified.

hanging this tagout.

Comment: Critical 2 CCW valves will be affected by opening the breakers listed above:

SAT / UNSAT

CC-563, CCW Header AB to B Return Isolation.

CC-620, Fuel Pool Heat Exchangers Temperature Control Valve.

END OF TASK Revision 0 Page 5 of 6 2010 NRC Walk Through Exam

JPM A3 APPLICANT 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.

Revision 0 Page 6 of 6 2010 NRC Walk Through Exam

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE A4 Gaseous Release Evaluation Applicant:

Examiner:

JPM A4 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: No Alternate Path: No Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 5 2010 NRC Walk Through Exam

JPM A4 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 5 2010 NRC Walk Through Exam

JPM A4 TASK ELEMENT STANDARD Concludes wind speed is 3.22 m/s and continues Evaluate 10 meter (33 foot) wind speed.

down through the flow chart.

Comment: Critical 199 foot reading will conclude that there are no restrictions on the release.

SAT / UNSAT TASK ELEMENT STANDARD Concludes wind direction is Evaluate 10 meter (33 foot) wind direction. 72.9 deg and continues right through the flow chart.

Comment: Critical 199 foot reading will conclude that there are no restrictions on the release.

SAT / UNSAT TASK ELEMENT STANDARD Concludes T is -0.45 °C, Evaluate Pasquill Stability Class. stability class D, and that the release is permitted..

Comment: Critical SAT / UNSAT END OF TASK Revision 0 Page 4 of 5 2010 NRC Walk Through Exam

JPM A4 APPLICANT 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.

Revision 0 Page 5 of 5 2010 NRC Walk Through Exam

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S1 Emergency Boration Applicant:

Examiner:

JPM S1 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: 5 minutes Time Critical: No Alternate Path: Yes Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 8 2010 NRC Walk Through Exam

JPM S1 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 8 2010 NRC Walk Through Exam

JPM S1 TASK ELEMENT STANDARD Reactor is tripped using the Trips the reactor when directed by the CRS. pushbuttons on CP-2 or CP-8.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Applicant recognizes the Check less than TWO CEAs are NOT fully inserted. need to commence Emergency Boration Comment: Critical SAT / UNSAT Evaluator Note All manipulations associated with Emergency Boration are located on CP-4.

TASK ELEMENT STANDARD Switch is placed in Place Makeup Mode selector switch to MANUAL.

MANUAL Comment: Critical Switch will already be in Manual SAT / UNSAT Revision 0 Page 4 of 8 2010 NRC Walk Through Exam

JPM S1 Evaluator 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: Both BAM-113 A and

BAM-113 A Boric Acid Makeup Gravity Feed Valve A

BAM-113 B Boric Acid Makeup Gravity Feed Valve B BAM -113 B are open Comment: Critical BAM-113 A will fail to open, requiring the use of the BAM Pumps for Emergency Boration. SAT / UNSAT Boric Acid Pump Alignment TASK ELEMENT STANDARD Open Emergency Boration Valve, BAM-133. BAM-133 is open.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD BAM Pump A or B is Start one Boric Acid Pump (A or B).

running.

Comment: Critical If the Boric Acid Pumps are used before the Gravity Feed Valves, the applicant will not be able to start either BAM Pump. SAT / UNSAT Revision 0 Page 5 of 8 2010 NRC Walk Through Exam

JPM S1 TASK ELEMENT STANDARD Close recirc valve for Boric Acid Pump started:

BAM-126 A, Boric Acid Makeup Pump Recirc Valve A BAM-126 A or B is closed.

BAM-126 B, Boric Acid Makeup Pump Recirc Valve B Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Close VCT Disch Valve, CVC-183. CVC-183 is closed.

Comment: Critical This step applies regardless of which flow path is used.

SAT / UNSAT TASK ELEMENT STANDARD Verify at least one Charging Pump operating and Charging Header flow is Flow is verified at CP-4.

40 GPM.

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 Revision 0 Page 6 of 8 2010 NRC Walk Through Exam

JPM S1 APPLICANT 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.

Revision 0 Page 7 of 8 2010 NRC Walk Through Exam

JPM S1 SIMULATOR 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.

Revision 0 Page 8 of 8 2010 NRC Walk Through Exam

Off Normal Procedure OP-901-103 Emergency Boration Revision 2 D. IMMEDIATE OPERATOR ACTIONS

1. 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 or

b. 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 B

3. Close VCT Disch Valve, CVC-183.

4. Verify at least one Charging Pump operating and Charging Header flow 40 GPM.

6

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S2 Hot and Cold Leg Safety Injection Applicant:

Examiner:

JPM S2 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: No Alternate Path: No Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 7 2010 NRC Walk Through Exam

JPM S2 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 7 2010 NRC Walk Through Exam

JPM S2 Establish 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: Critical SAT / UNSAT TASK ELEMENT STANDARD Open SI-502A, HOT LEG 1 INJECTION ISOLATION valve. SI-502 A is open.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Open SI-506A, HOT LEG 1 INJECTION FLOW CONTROL valve. SI-506 A is open.

Comment: Critical SAT / 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: Critical SAT / UNSAT Revision 0 Page 4 of 7 2010 NRC Walk Through Exam

JPM S2 TASK ELEMENT STANDARD Open SI-502B, HOT LEG 2 INJECTION ISOLATION valve. SI-502 B is open.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Open SI-506B, HOT LEG 2 INJECTION FLOW CONTROL valve. SI-506 B is open.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD The sum of all cold leg WHEN hot and cold leg injection has been established, THEN adjust flows is approximately equal SI-506 A and SI-506 B to obtain the sum of ALL cold leg flows equal to to the sum of the hot leg the sum of the hot leg flows.

flows.

Comment: Critical Applicant can obtain Hot and Cold Leg flows from either the PMC, the meters on CP-8, or QSPDS. SAT / UNSAT 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.

END OF TASK Revision 0 Page 5 of 7 2010 NRC Walk Through Exam

JPM S2 APPLICANT 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.

Revision 0 Page 6 of 7 2010 NRC Walk Through Exam

JPM S2 SIMULATOR OPERATOR INSTRUCTIONS Reset to IC-191 Verify the following Malfunctions:

o Rc24a 3%

Place the Simulator in Run on the lead examiners cue.

Revision 0 Page 7 of 7 2010 NRC Walk Through Exam

WATERFORD 3 SES OP-902-002 Revision 012 Page 35 of 67 LOSS OF COOLANT ACCIDENT RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS Hot and Cold Leg Injection

47. 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 Systems

48. IF any ESFAS actuations have initiated AND are NO longer needed, THEN REFER TO Appendix 5, "ESFAS Reset" and reset ESFAS actuations as required.

WATERFORD 3 SES OP-902-009 Revision 301 Page 120 of 195 STANDARD APPENDICES Appendix 15 Page 1 of 2 Hot and Cold Leg Injection INSTRUCTIONS CONTINGENCY ACTIONS

____ 1.1 Establish simultaneous hot and cold leg injection for Train A by performing the following:

a. Close SI 219A, HPSI HEADER ORIFICE BYPASS valve.

b. Open SI 502A, HOT LEG 1 INJECTION ISOLATION valve.

c. Open SI 506A, HOT LEG 1 INJECTION FLOW CONTROL valve.

____ 1.2 Establish simultaneous hot and cold leg injection for Train B by performing the following:

a. Close SI 219B, HPSI HEADER ORIFICE BYPASS valve.

b. Open SI 502B, HOT LEG 2 INJECTION ISOLATION valve.

c. Open SI 506B, HOT LEG 2 INJECTION FLOW CONTROL valve.

WATERFORD 3 SES OP-902-009 Revision 301 Page 121 of 195 STANDARD APPENDICES Appendix 15 Page 2 of 2 INSTRUCTIONS CONTINGENCY ACTIONS

____ 1.3 WHEN hot and cold leg injection has been established, THEN adjust SI 506A and SI 506B to obtain the sum of ALL cold leg flows equal to the sum of the hot leg flows.

End of Appendix 15

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S3 Pressurizer Spray Valve Testing Applicant:

Examiner:

JPM S3 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: No Alternate Path: Yes Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 13 2010 NRC Walk Through Exam

JPM S3 Revision 0 Page 3 of 13 2010 NRC Walk Through Exam

JPM S3 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 4 of 13 2010 NRC Walk Through Exam

JPM S3 TASK ELEMENT STANDARD Obtain SM/CRS permission to perform this Subsection and document on Attachment 10.10 will be 0.10, Reactor Coolant. 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 Acknowledges caution.

performance of this test.

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 Spray Valve Selector Switch Place Spray Valve Selector Switch to Loop 1A.

is in the Loop 1A position.

Comment: Critical SAT / UNSAT Revision 0 Page 5 of 13 2010 NRC Walk Through Exam

JPM S3 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 A, RC-301A, indicates Controller, RC-IHIC-0100 is Intermediate in manual and RC-301 A or indicates intermediate or

Pressurizer pressure is reduced as indicated on Pressurizer Pressurizer pressure is Pressure Indicator, RC-IPI-0102-A3, RC-IPI-0102-B3, or PMC PID dropping.

A12205.

Comment: Critical RC-301 A should indicate intermediate prior to a change in Pressurizer pressure. SAT / UNSAT TASK ELEMENT STANDARD Check indication used and document results on Attachment 10.10. Attachment updated.

Comment:

SAT / UNSAT TASK ELEMENT STANDARD Controller RC-IHIC-0100 Lower Spray Valve Indicator controller, RC-IHIC-0100, Output to 0%.

output is 0%.

Comment: Critical SAT / UNSAT Revision 0 Page 6 of 13 2010 NRC Walk Through Exam

JPM S3 TASK ELEMENT STANDARD Spray Valve Selector Switch Place Spray Valve Selector Switch to Loop 1B.

is in the Loop 1B position.

Comment: Critical SAT / 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 Controller, RC-IHIC-0100 is Intermediate in manual and RC-301 B or indicates intermediate or

Pressurizer pressure is reduced as indicated on Pressurizer Pressurizer pressure is Pressure Indicator, RC-IPI-0102-A3, RC-IPI-0102-B3, or PMC PID dropping.

A12205.

Comment: Critical 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 SAT / UNSAT B if this action is taken.

TASK ELEMENT STANDARD Report indication of the failed RC-IPR-0100 X to the CRS. Report made.

Comment: Critical SAT / UNSAT Revision 0 Page 7 of 13 2010 NRC Walk Through Exam

JPM S3 Evaluator 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 Verifies that RC-IPR-0100X PRESSURE CHANNEL X/Y recorder (RC-IPR-0100). has failed high.

Comment:

SAT / UNSAT TASK ELEMENT STANDARD Pressurizer Pressure Transfer Pressurizer pressure control to operable channel using Channel Selector Switch is Pressurizer Pressure Channel Selector control switch.

placed in the Y position.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Pressurizer Lo Level Heater Transfer Pressurizer Lo Level Heater Cutout selector switch to the Cutout selector switch is Operable Pressurizer Pressure control channel.

placed in position Y.

Comment: Critical SAT / UNSAT Revision 0 Page 8 of 13 2010 NRC Walk Through Exam

JPM S3 TASK ELEMENT STANDARD Proportional Heater Banks Reset Proportional Heater Banks #1 & #2. #1 & #2 breakers indicate closed.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Verify proper operation of Pressurizer Pressure controller (RC-IPIC-0100) Verifies RC-IPIC-0100 AND Pressurizer Pressure controlling OR being restored to 2250 PSIA. 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 Controller, RC-IHIC-0100 is Intermediate in manual and RC-301 B or indicates intermediate or

Pressurizer pressure is reduced as indicated on Pressurizer Pressurizer pressure is Pressure Indicator, RC-IPI-0102-A3, RC-IPI-0102-B3, or PMC PID dropping.

A12205.

Comment: Critical This is the step that was started at the point of the failure. RC-301 B may already indicate intermediate at this point. SAT / UNSAT Revision 0 Page 9 of 13 2010 NRC Walk Through Exam

JPM S3 TASK ELEMENT STANDARD Check indication used and document results on Attachment 10.10. Attachment updated.

Comment:

SAT / UNSAT TASK ELEMENT STANDARD Controller RC-IHIC-0100 Lower Spray Valve Indicator controller, RC-IHIC-0100, Output to 0%.

output is 0%.

Comment: Critical Applicant may have already taken this action during the malfunction.

SAT / UNSAT TASK ELEMENT STANDARD Spray Valve Indicator Place Spray Valve Indicator Controller, RC-IHIC-0100, in Auto Controller, RC-IHIC-0100, is in Auto.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Document final position on Attachment 10.10 Attachment updated.

Comment:

SAT / UNSAT Revision 0 Page 10 of 13 2010 NRC Walk Through Exam

JPM S3 TASK ELEMENT STANDARD Spray Valve Selector Switch Place Spray Valve Selector Switch to Both is in Both.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Document final position on Attachment 10.10. Attachment updated.

Comment:

SAT / UNSAT END OF TASK Revision 0 Page 11 of 13 2010 NRC Walk Through Exam

JPM S3 APPLICANT 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.

Revision 0 Page 12 of 13 2010 NRC Walk Through Exam

JPM S3 SIMULATOR 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.

Revision 0 Page 13 of 13 2010 NRC Walk Through Exam

Off Normal Procedure OP-901-120 Pressurizer Pressure Control Malfunction Revision 301 E1 PRESSURIZER PRESSURE CONTROL CHANNEL INSTRUMENT FAILURE PLACEKEEPER START DONE N/A

1. Verify control channel instrument failure by checking PRESSURIZER PRESSURE CHANNEL X/Y recorder (RC-IPR-0100).

2. Transfer Pressurizer pressure control to operable channel using Pressurizer Pressure Channel Selector control switch.

3. IF Pressurizer Pressure control channel is failed high, THEN perform the following:

a. Transfer Pressurizer Lo Level Heater Cutout selector switch to the Operable Pressurizer Pressure control channel.

b. Reset Proportional Heater Banks #1 & #2.

Continuous

4. Verify proper operation of Pressurizer Pressure controller (RC-IPIC-0100) AND Pressurizer Pressure controlling OR being restored to 2250 PSIA.

5. Refer to Technical Specification 3.2.8.

END 7

Surveillance Procedure OP-903-118 Primary Auxiliaries Quarterly IST Valve Tests Revision 020 7.10 REACTOR COOLANT 7.10.1 Obtain SM/CRS permission to perform this Subsection and document on Attachment 10.10, Reactor Coolant.

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.

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 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.

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 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, or RC-IPI-0102-B3, or PMC PID A12206.

7.10.2.5.1 Check indication used and document results on Attachment 10.10.

96

Surveillance Procedure OP-903-118 Primary Auxiliaries Quarterly IST Valve Tests Revision 020 7.10.2.6 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.

97

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S4 Break Main Condenser Vacuum Applicant:

Examiner:

JPM S4 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: No Alternate Path: No Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 8 2010 NRC Walk Through Exam

JPM S4 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 8 2010 NRC Walk Through Exam

JPM S4 TASK 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 Provided in the cue.

concurrently with this procedure.

Comment:

SAT / UNSAT TASK ELEMENT STANDARD Announce the following twice:

Announcement complete.

ATTENTION STATION PERSONNEL, ATTENTION STATION PERSONNEL, BREAKING CONDENSER VACUUM.

Comment:

SAT / UNSAT TASK ELEMENT STANDARD Controller MS-IPIC-1010 is Place STEAM BYPASS MASTER controller (MS-IPIC-1010) in MAN.

in Manual.

Comment: Critical SAT / UNSAT Revision 0 Page 4 of 8 2010 NRC Walk Through Exam

JPM S4 TASK ELEMENT STANDARD Slowly lower output of STEAM BYPASS MASTER controller (MS-IPIC- Controller MS-IPIC-1010 is 1010) to zero. at zero.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Verify Steam Generator pressure maintained at approximately 992 psig by Verification complete.

Atmospheric Dump valves.

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 SAT / UNSAT to see the Atmospheric Dump valves open.

TASK ELEMENT STANDARD Procedure Caution Caution reviewed.

Main Feedwater Pumps will trip when Main Steam is isolated.

Comment:

SAT / UNSAT TASK ELEMENT STANDARD MS-124 A and MS-124 B Close BOTH Main Steam Isolation Valves (MS 124A AND MS 124B).

are closed.

Comment: Critical SAT / UNSAT Revision 0 Page 5 of 8 2010 NRC Walk Through Exam

JPM S4 TASK ELEMENT STANDARD Open Condenser Vacuum Breaker valves by simultaneously depressing Condenser Vacuum THINK push button AND placing CNDSR VAC BKR control switch to Breaker valves are open.

OPEN.

Comment: Critical SAT / 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:

All 3 Condenser Vacuum pumps are secured.

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)

Comment: Critical SAT / UNSAT END OF TASK Revision 0 Page 6 of 8 2010 NRC Walk Through Exam

JPM S4 APPLICANT 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.

Revision 0 Page 7 of 8 2010 NRC Walk Through Exam

JPM S4 SIMULATOR OPERATOR INSTRUCTIONS This 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.

Revision 0 Page 8 of 8 2010 NRC Walk Through Exam

Off Normal Procedure OP-901-210 Turbine Trip Revision 3 E. SUBSEQUENT OPERATOR ACTIONS E0 GENERAL NOTE High 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 breaking condenser 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 1.1 above, 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, REACTOR POWER 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 normal Turbine 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 perform concurrently 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.

6

Off Normal Procedure OP-901-210 Turbine Trip Revision 3 E0 GENERAL (CONTD) 5.5 Verify Steam Generator pressure maintained at approximately 992 psig by Atmospheric Dump valves.

CAUTION MAIN 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 depressing THINK push button AND placing CNDSR VAC BKR control switch to OPEN.

5.8 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) 5.9 GO TO step 9.

6. IF a turbine trip has occurred AND a low EH reservoir level exists, THEN place both 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 Startup Transformer A Automatic transfer from Unit Auxiliary Transformer B to Startup Transformer B Steam Bypass Control System OR Atmospheric Dump valves responding to maintain Steam Generator pressure Heater Drain Pumps trip 7

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S5 Start Hydrogen Recombiner A Applicant:

Examiner:

JPM S5 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: No Alternate Path: No Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 11 2010 NRC Walk Through Exam

JPM S5 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 11 2010 NRC Walk Through Exam

JPM S5 TASK ELEMENT STANDARD Record present Post-LOCA Containment pressure from Containment Atmosphere Pressure Indicator, ESF-IPI-6750A, on Attachment 11.2, Value recorded.

Hydrogen Recombiner Power Control Setting Data Sheet.

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, Value recorded.

Technical Specification Surveillance Logs, on Attachment 11.2.

Comment:

Given in the cue.

SAT / UNSAT TASK ELEMENT STANDARD Determine Pressure Factor (Cp) from Attachment 11.4, Dry Containment Correction Factor Recombiner Power Correction Factor Graph. determined.

Comment: Critical Will vary based on pressure recorded in step 1. Should determine a value of 1.18 to 1.22. SAT / UNSAT TASK ELEMENT STANDARD Record Pressure Factor (Cp) on Attachment 11.2. Value recorded.

Comment:

SAT / UNSAT Revision 0 Page 4 of 11 2010 NRC Walk Through Exam

JPM S5 TASK ELEMENT STANDARD Determine Hydrogen Recombiner Power Control Setting by multiplying a Setting determined.

reference power of 48 KW by Cp.

Comment: Critical Equals value determined in step 6.1.1.3

48. Should be 56.6 - 58.6 SAT / 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-Step reviewed.

EM-960, when power level is being changed.

Comment:

SAT / UNSAT TASK ELEMENT STANDARD Procedure Note Adjusting the Hydrogen Recombiner Power Control potentiometer slowly Note reviewed.

compensates for the lag between the meter and the potentiometer adjustments.

Comment:

SAT / UNSAT Revision 0 Page 5 of 11 2010 NRC Walk Through Exam

JPM S5 TASK ELEMENT STANDARD Verify Hydrogen Recombiner A Power Control potentiometer is set at zero Setting verified.

(000).

Comment:

SAT / UNSAT TASK ELEMENT STANDARD Place Hydrogen Recombiner A Power control switch, HRA-001A, to ON. HRA-001A is ON.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Slowly adjust Hydrogen Recombiner Power Control potentiometer for 5 KW is indicated on Hydrogen Recombiner A until 5 KW is indicated on Hydrogen Recombiner Hydrogen Recombiner A A Power Meter, HRA-EM-960. Power Meter.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Hold reading for 10 minutes. Acknowledges hold.

Comment:

Prompt applicant that 10 minutes has elapsed.

SAT / UNSAT Revision 0 Page 6 of 11 2010 NRC Walk Through Exam

JPM S5 TASK ELEMENT STANDARD Verify Hydrogen Thermocouple Temperatures trend upward when adjusting Power Control Potentiometer, as indicated on Hydrogen Temperatures monitored.

Recombiner A Outlet Air Temperature Indicator, HRA-ITI-0001A. Use Temperature Select switch to read thermocouple temperatures.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Adjust Hydrogen Recombiner Power Control potentiometer for Hydrogen 10 KW is indicated on Recombiner A until 10 KW indicated on Hydrogen Recombiner A Power Hydrogen Recombiner A Meter, HRA-EM-960. Power Meter.

Comment: Critical SAT / 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 20 KW is indicated on Recombiner A until 20 KW indicated on Hydrogen Recombiner A Power Hydrogen Recombiner A Meter, HRA-EM-960. Power Meter.

Comment: Critical SAT / UNSAT Revision 0 Page 7 of 11 2010 NRC Walk Through Exam

JPM S5 TASK ELEMENT STANDARD Hold reading for 10 minutes. Acknowledges hold.

Comment:

Prompt applicant that 10 minutes has elapsed.

SAT / UNSAT TASK ELEMENT STANDARD Procedure Caution Caution Reviewed.

DO NOT EXCEED 75 KW.

Comment:

SAT / UNSAT TASK ELEMENT STANDARD Adjust Hydrogen Recombiner Power Control Potentiometer for Hydrogen Potentiometer adjusted.

Recombiner A to setting calculated on Attachment 11.2.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Procedure Caution Caution reviewed.

DO NOT EXCEED 1400 °F.

Comment:

SAT / UNSAT Revision 0 Page 8 of 11 2010 NRC Walk Through Exam

JPM S5 TASK 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 Step reviewed.

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 Comment:

Temperature will be < 300 °F at this time. End task when this step is reached. SAT / UNSAT END OF TASK Revision 0 Page 9 of 11 2010 NRC Walk Through Exam

JPM S5 APPLICANT 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.

Revision 0 Page 10 of 11 2010 NRC Walk Through Exam

JPM S5 SIMULATOR OPERATOR INSTRUCTIONS This 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.

Revision 0 Page 11 of 11 2010 NRC Walk Through Exam

System Operating Procedure OP-008-006 Hydrogen Recombiner Revision 8 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 1150 F and 1400 F depending on Hydrogen Concentration. Maintaining Hydrogen Recombiner Temperature > 1225 F 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.

4

System Operating Procedure OP-008-006 Hydrogen Recombiner Revision 8 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.

7

System Operating Procedure OP-008-006 Hydrogen Recombiner Revision 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.

CAUTION DO 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 > 1225 F 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 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:

Hydrogen Recombiner A Hydrogen Recombiner B A42700 - Temp 1 A42703 - Temp 1 A42701 - Temp 2 A42704 - Temp 2 A42702 - Temp 3 A42705 - Temp 3 8

System Operating Procedure OP-008-006 Hydrogen Recombiner Revision 8 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.

9

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) 1 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)

OP-008-006 Revision 8 Attachment 11.2 (1 of 1) 18

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 Attachment 11.3 (1 of 1) 19

11.4 DRY CONTAINMENT RECOMBINER POWER CORRECTION FACTOR GRAPH OP-008-006 Revision 8 [LAST PAGE] Attachment 11.4 (1 of 1) 20

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S6 Stabilize RCS Temperature Applicant:

Examiner:

JPM S6 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: No Alternate Path: Yes Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 7 2010 NRC Walk Through Exam

JPM S6 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 7 2010 NRC Walk Through Exam

JPM S6 TASK ELEMENT STANDARD Actions to stabilize RCS temperature following an excess steam demand Both parameters are event should be initiated when BOTH of the following parameters are met: monitored. Action does not

CET temperatures rise begin until both parameters

Pressurizer pressure rise are rising.

Comment: Critical Parameters can be monitored on the control panels, the PMC, or QSPDS.

Pressurizer pressure will begin rising shortly after beginning. CET SAT / UNSAT temperature will begin rising a few minutes later.

TASK ELEMENT STANDARD Place the ADV for the least affected steam generator to manual and fully ADV #1 is in manual with open the ADV. 100% output.

Comment: Critical SAT / 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 Both EFAS initiation Manually initiate EFAS for the least affected steam generator. switches for S/G #1 at CP-7 are taken to ACT.

Comment: Critical SAT / UNSAT Revision 0 Page 4 of 7 2010 NRC Walk Through Exam

JPM S6 TASK ELEMENT STANDARD Both EFAS initiation Manually initiate EFAS for the least affected steam generator. switches for S/G #1 at CP-8 are taken to ACT.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD EFW is established to S/G Place the EFW Flow Control Valve to manual and commence feeding the

1 at a rate of least affected steam generator.

approximately 400 gpm.

Comment: Critical 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, SAT / UNSAT and then remove the other fault. The applicant will be required to use the alternate controller to establish EFW flow.

TASK ELEMENT STANDARD IF RCS pressure is greater than or equal to 1500 psia, THEN stabilize RCS pressure reduced RCS pressure at a value not to exceed 1600 psid between the RCS and using Auxiliary Spray valves the lowest SG pressure. to < 1600 psid of S/G #2.

Comment: Critical If applicant asks for a RCS pressure band, request a recommendation.

An appropriate RCS pressure band is 1500-1600 psia. SAT / UNSAT The critical element for this task is to lower RCS pressure with Auxiliary Spray.

END OF TASK Revision 0 Page 5 of 7 2010 NRC Walk Through Exam

JPM S6 APPLICANT 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.

Revision 0 Page 6 of 7 2010 NRC Walk Through Exam

JPM S6 SIMULATOR 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.

Revision 0 Page 7 of 7 2010 NRC Walk Through Exam

WATERFORD 3 SES OP-902-004 Revision 011 Page 16 of 44 EXCESS STEAM DEMAND RECOVERY INSTRUCTIONS CONTINGENCY ACTIONS

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

Actions to stabilize RCS temperature following an excess steam demand event should be initiated when BOTH of the following parameters are met:

CET temperatures rise

Pressurizer pressure rise Stabilize RCS Temperature

16. Verify RCS temperature is stabilized by performing the following:

a. Place the ADV for the least affected steam generator to manual and fully open the ADV.

b. Manually initiate EFAS for the least affected steam generator.

c. Place the EFW Flow Control Valve to manual and commence feeding the least affected steam generator.

d. IF RCS pressure is greater than or d.1 IF RCS pressure is less than 1500 equal to 1500 psia, THEN stabilize psia, THEN stabilize RCS RCS pressure at a value not to pressure at greater than HPSI exceed 1600 psid between the shutoff head (1500-1600 psia).

RCS and the lowest SG pressure.

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S7 Reset Containment Spray Actuation Applicant:

Examiner:

JPM S7 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: No Alternate Path: No Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 8 2010 NRC Walk Through Exam

JPM S7 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 8 2010 NRC Walk Through Exam

JPM S7 TASK ELEMENT STANDARD Place control switches for the following valves to CLOSE:

CC-641, CCW RCP INLET OUTSIDE ISOL All 3 valve control switches

CC-710, CCW RCP OUTLET INSIDE ISOL are in CLOSED.

CC-713, CCW RCP OUTLET OUTSIDE ISOL Comment: Critical SAT / 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 The applicable Reset Place the Reset Permissive switch to "UNLK" position. (CP-10)

Permissive switch is in UNLK.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD CSAS Reset pushbutton is Press CSAS Reset pushbutton.

pressed.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Verify the initiation relay indicator lit on the ENGINNERED SAFETY Verification complete.

FEATURES SYSTEM mimic.

Comment:

SAT / UNSAT Revision 0 Page 4 of 8 2010 NRC Walk Through Exam

JPM S7 TASK ELEMENT STANDARD The applicable Reset Place the Reset permissive switch to LK position Permissive switch is in the LK position.

Comment: Critical This sequence must be repeated for Channels A - D.

SAT / UNSAT TASK ELEMENT STANDARD Reset CSAS actuation logic on BOTH trains as follows: CSAS Reset pushbuttons A

Press the CSAS Reset pushbuttons. (CP-33) & B have been de-pressed.

Comment: Critical There are 2 buttons on CP-33 that must be pressed, 1 for Train A and 1 for Train B. SAT / UNSAT TASK ELEMENT STANDARD Verify the actuation relay indicator lit on the ENGINEERED SAFETY CP-10 verification is FEATURES SYSTEM mimic. (CP-10) complete.

Comment: SAT / UNSAT TASK ELEMENT STANDARD One Containment Spray Stop ONE CS pump at a time.

Pump is secured.

Comment: Critical SAT / UNSAT Revision 0 Page 5 of 8 2010 NRC Walk Through Exam

JPM S7 TASK ELEMENT STANDARD Second Containment Spray IF a CS pump is operating, THEN stop the remaining CS pump.

Pump is secured.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Close the following Containment Spray valves:

CS-125 A, CNTMT SPRAY HEADER A ISOL CS-125 A and CS-125 B

CS-125 B, CNTMT SPRAY HEADER B ISOL are closed.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Both Containment Spray Place BOTH Containment Spray pump control switches to normal pump control switches are position.

in the normal position.

Comment: Critical SAT / UNSAT END OF TASK Revision 0 Page 6 of 8 2010 NRC Walk Through Exam

JPM S7 APPLICANT 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.

Revision 0 Page 7 of 8 2010 NRC Walk Through Exam

JPM S7 SIMULATOR 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.

Revision 0 Page 8 of 8 2010 NRC Walk Through Exam

WATERFORD 3 SES OP-902-009 Revision 301 Page 69 of 195 STANDARD APPENDICES Appendix 5 Page 30 of 31 ESFAS Reset Attachment 5-E: CSAS Reset Procedure INSTRUCTIONS CONTINGENCY ACTIONS

____ 1.1 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

____ 1.2 Reset 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.

WATERFORD 3 SES OP-902-009 Revision 301 Page 70 of 195 STANDARD APPENDICES Appendix 5 Page 31 of 31 INSTRUCTIONS CONTINGENCY ACTIONS

____ 1.3 Reset 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)

____ 1.4 Stop ONE CS pump at a time.

____ 1.5 IF a CS pump is operating, THEN stop the remaining CS pump.

____ 1.6 Close the following Containment Spray valves:

CS 125A, CNTMT SPRAY HEADER A ISOL

CS 125B, CNTMT SPRAY HEADER B ISOL

____ 1.7 Place BOTH Containment Spray pump control switches to normal position.

End of Appendix 5

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE S8 Start Component Cooling Water Pump AB Applicant:

Examiner:

JPM S8 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: No Alternate Path: No Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 7 2010 NRC Walk Through Exam

JPM S8 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 7 2010 NRC Walk Through Exam

JPM S8 If BUS AB3 is not energized, then align BUS AB3 to BUS A3 as follows:

TASK ELEMENT STANDARD BUS TIE B TO AB Place BUS TIE B TO AB keyswitch to TRIP.

keyswitch is in TRIP.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD BUS AB STATUS Place BUS AB STATUS SELECTOR switch to A.

SELECTOR switch is in A.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD BUS TIE A TO AB Place BUS TIE A TO AB keyswitch to CLOSE keyswitch is in CLOSE.

Comment: Critical SAT / UNSAT Verify two Component Cooling Water Pumps operating and supplying both A and B loops.

TASK ELEMENT STANDARD CCW Assignment Switch is Place CCW Assignment Switch to position B.

in position B.

Comment: Critical SAT / UNSAT Revision 0 Page 4 of 7 2010 NRC Walk Through Exam

JPM S8 TASK ELEMENT STANDARD Verify Open the following valves: CC-126B, CC-114B, CC-

CC-126B/CC-114B CCW Suct & Disch Header Tie Valves AB to B 127B, and CC-115B are

CC-127B/CC-115B CCW Suct & Disch Header Tie Valves AB to B verified open.

Comment:

SAT / UNSAT TASK ELEMENT STANDARD Start CCW Pump AB. CCW Pump AB is running.

Comment: Critical SAT / UNSAT END OF TASK Revision 0 Page 5 of 7 2010 NRC Walk Through Exam

JPM S8 APPLICANT 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.

Revision 0 Page 6 of 7 2010 NRC Walk Through Exam

JPM S8 SIMULATOR OPERATOR INSTRUCTIONS Reset to IC - 194 Verify the following Malfunctions:

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

Revision 0 Page 7 of 7 2010 NRC Walk Through Exam

Off Normal Procedure OP-901-311 Loss of Train B Safety Bus Revision 303 E. SUBSEQUENT OPERATOR ACTIONS E0 GENERAL CAUTION FAILURE TO ENERGIZE B3 SAFETY BUS OR START COMPONENT COOLING WATER PUMP 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 PLACEKEEPER START DONE N/A

1. If either BUS B2 TO B3 TIE BKR or BUS B3 TO B2 TIE BKR opens, then verify the following:

Emergency Diesel Generator B starts and output breaker closes.

Emergency Diesel Generator B Sequencer starts loading sequence or has completed loading sequence.

2. If BUS AB3 is not energized, then align BUS AB3 to BUS 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.

6

Off Normal Procedure OP-901-311 Loss of Train B Safety Bus Revision 303 PLACEKEEPER START DONE N/A

3. Verify two Component Cooling Water Pumps operating and supplying both A and B loops.

3.1 If CCW Pump AB is the standby pump and it is desired to align this pump for service, then perform the 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 & Disch Header Tie Valves AB to B CC-127B/CC-115B CCW Suct & Disch Header Tie Valves AB to B 3.1.3 Start CCW Pump AB.

3.2 If CCW Pump B is the standby pump and it is desired to align this pump for service, then perform the following:

3.2.1 Start CCW Pump B.

3.2.2 Place CCW Assignment Switch to NORM.

7

Off Normal Procedure OP-901-311 Loss of Train B Safety Bus Revision 303 NOTE (1) Manual Override of RCP Seal Cooler Isolation Valves is accomplished by positioning associated 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.

PLACEKEEPER START DONE N/A 3.3 If CCW to Reactor Coolant Pump Seal Cooler (s)

Isolate, then within 3 minutes restore Component Cooling Water flow to applicable Reactor Coolant Pump(s) by opening the applicable RCP CCW Isolation Valve(s):

CC-679A/CC-6651A RCP 1A CC-679B/CC-6651B RCP 1B CC-680A/CC-666A RCP 2A CC-680B/CC-666B RCP 2B 8

Off Normal Procedure OP-901-311 Loss of Train B Safety Bus Revision 303 CAUTION CCW PUMP RUNOUT OCCURS AT 8383 GPM. WHEN EVALUATING CCW PUMP OPERATING CONDITIONS, CONSIDER THE NUMBER OF PUMPS RUNNING AND IF CCW TRAINS ARE CROSS CONNECTED.

PLACEKEEPER START DONE N/A

4. If two CCW Pumps are not operating, then perform the following:

4.1 Secure Emergency Diesel Generator B by pulling the overspeed trip plunger.

NOTE Closing 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 operating pump by closing the following valves:

CC 126B/CC 114B CW SUCT & DISCH HEADER TIE VALVES AB TO B CC 200B/CC 563 CW SUCT & DISCH HEADER TIE VALVES B TO AB 9

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE P1 Atmospheric Dump Valve Local Operation Applicant:

Examiner:

JPM P1 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: No Alternate Path: Yes Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 9 2010 NRC Walk Through Exam

JPM P1 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 9 2010 NRC Walk Through Exam

JPM P1 TASK ELEMENT STANDARD Procedure Note Note reviewed.

Refer to T.S. 3.7.1.7 prior to performing this section.

Comment:

SAT / UNSAT TASK ELEMENT STANDARD Procedure Caution OPENING ADV MAY CAUSE AN RCS COOLDOWN, RESULTING IN A Caution reviewed.

CHANGE IN REACTIVITY AND STEAM GENERATOR LEVELS.

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 Revision 0 Page 4 of 9 2010 NRC Walk Through Exam

JPM P1 TASK ELEMENT STANDARD Pressure adjusted to Adjust the pressure at Air Regulator outlet on the front of the panel to the pressure from preceding pressure noted in step 8.7.2.1.

step.

Comment: Critical Cue: Turning the regulator operator counter clockwise will lower pressure.

When handle is turned in the correct direction, cue that pressure lowers SAT / UNSAT to required pressure.

TASK ELEMENT STANDARD Pneumatic Permissive Turn the Pneumatic Permissive Valve above the Transducer to Manual.

Valve is in manual.

Comment: Critical Cue: Valve handle is rotated from Auto to Manual.

SAT / UNSAT TASK ELEMENT STANDARD Pneumatic Permissive Turn the Pneumatic Permissive Valve above the Air Regulator to Manual.

Valve is in manual.

Comment: Critical Cue: Valve handle is rotated from Auto to Manual.

SAT / UNSAT Revision 0 Page 5 of 9 2010 NRC Walk Through Exam

JPM P1 TASK ELEMENT STANDARD Procedure Note The ADV will be closed when pressure at outlet of Air Regulator is < 4.5 Note reviewed.

PSIG and full open when pressure at outlet of Air Regulator is > 15 PSIG.

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 Applicant attempts to adjust clockwise direction to raise air pressure. pressure.

Close MS-116 A by turning the air regulator adjusting screw in the counterclockwise direction to lower air pressure.

Comment: Critical Cue: pressure and ADV position are not changing.

SAT / 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 NG-8271 C is closed Dump Valve: NG-8271 C, NG/IA Isolation to MS-116A Comment: Critical Cue: Valve closes when operated.

SAT / UNSAT Revision 0 Page 6 of 9 2010 NRC Walk Through Exam

JPM P1 TASK ELEMENT STANDARD Open Filter Petcock Drain and bleed off Air/N2 pressure by opening Filter Filter Petcock Drain is open.

Petcock Drain.

Comment: Critical Cue: Air is heard coming from the drain when opened. Pressure lowers to zero and air flow stops. SAT / UNSAT TASK ELEMENT STANDARD Open MS-116A SG 1 MS Atm Dump Valve Local Valve Positioner Positioner Equalizing Valve Equalizing Valve. is open.

Comment: Critical Cue: Valve open when operated.

SAT / 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: Critical Cue: Clevis unscrews when operated.

SAT / UNSAT TASK ELEMENT STANDARD Turn handwheel to expose actuator shaft above manual override shaft. Actuator shaft exposed.

Comment: Critical Cue: As handwheel is turned clockwise, actuator shaft is exposed. When shaft is fully exposed, notch at the bottom of the shaft is visible. SAT / UNSAT Revision 0 Page 7 of 9 2010 NRC Walk Through Exam

JPM P1 TASK ELEMENT STANDARD Slide clevis onto actuator shaft. Clevis installed.

Comment: Critical Cue: Clevis fits into notch.

SAT / UNSAT TASK ELEMENT STANDARD MS-116 A, ADV #1 is 25%

Turn handwheel to open MS-116A to desired position.

open.

Comment: Critical Cue: As handwheel is turned counter clockwise, MS-116 A, ADV #1 opens. Steam issues from ADV #1 exhaust pipe. SAT / UNSAT END OF TASK Revision 0 Page 8 of 9 2010 NRC Walk Through Exam

JPM P1 APPLICANT 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.

Revision 0 Page 9 of 9 2010 NRC Walk Through Exam

System Operating Procedure OP-005-004 Main Steam Revision 019 8.7 LOCAL OPERATION OF ATMOSPHERIC DUMP VALVE NOTE Refer to T.S. 3.7.1.7 prior to performing this section.

CAUTION OPENING ADV MAY CAUSE AN RCS COOLDOWN, RESULTING IN A CHANGE IN REACTIVITY 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 perform the following:

8.7.2.1 Record the pressure at the outlet of the transducer: ________ PSIG.

8.7.2.2 Adjust the pressure at Air Regulator outlet on the front of the panel to the pressure noted in step 8.7.2.1.

8.7.2.3 Turn the Pneumatic Permissive Valve above the Transducer to Manual.

8.7.2.4 Turn the Pneumatic Permissive Valve above the Air Regulator to Manual.

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.

8.7.2.5 Adjust the Air Regulator pressure to obtain desired valve position by performing any of the following:

Open MS-116 A(B) by turning air regulator adjusting screw in the clockwise direction to raise air pressure.

Close MS-116 A(B) by turning the air regulator adjusting screw in the counterclockwise direction to lower air pressure.

26

System Operating Procedure OP-005-004 Main Steam Revision 019 8.7.3 When local pneumatic operation of MS-116A(B) is no longer desired, then perform the following:

8.7.3.1 Verify the applicable Atmospheric Dump Valve M/A station on CP-8 is in Manual with minimum output.

8.7.3.2 Turn the Pneumatic Permissive Valve above the Air Regulator from Manual to Auto.

8.7.3.3 Raise 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 front of the panel is between 20-25 PSIG.

8.7.3.4 Adjust Air Regulator outlet pressure on the front of the panel until the outlet pressure just begins to drop. Check that Air Regulator outlet pressure on the front 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 THE ADV MAY OPEN WHEN RETURNED TO REMOTE OPERATION.

8.7.3.5 Verify pressure at outlet of Transducer is 4.5 PSIG.

8.7.3.5.1 If the pressure is greater than 4.5 PSIG, then verify the applicable Atmospheric Dump Valve M/A station on CP-8 is in Manual with minimum output.

8.7.3.5.2 If the applicable Atmospheric Dump Valve M/A station is in Manual with minimum output and transducer pressure is 4.5 PSIG, then I&C Maintenance should be contacted for assistance prior to proceeding.

27

System Operating Procedure OP-005-004 Main Steam Revision 019 NOTE Operation of the Air Regulator may loosen the lock nut on the Air Regulator on the front of the panel. The lock nut should be checked for tightness. A 1/2 open end wrench is required to tighten the lock nut. Do not over tighten.

8.7.3.6 Turn 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 the following:

8.7.4.1 Close Local NG/IA Isolation to the positioner for applicable MS-116A(B) SG 1(2) MS Atm Dump Vlv:

NG MVAAA8271 C NG/IA Isolation to MS-116A or NG MVAAA9281 D NG/IA Isolation to MS-116B 8.7.4.2 Open Filter Petcock Drain and bleed off Air/N2 pressure by opening Filter Petcock Drain.

8.7.4.3 Open MS-116A(B) SG 1(2) MS Atm Dump Vlv Local Valve Positioner Equalizing Valve.

8.7.4.4 Engage local handwheel and Open MS-116A(B) SG 1(2) MS Atm Dump Vlv to desired position by performing the following:

8.7.4.4.1 Unscrew clevis from top of the Manual Override Shaft.

8.7.4.4.2 Turn handwheel to expose actuator shaft above manual override shaft.

8.7.4.4.3 Slide clevis onto actuator shaft.

8.7.4.4.4 Turn handwheel to open MS-116A(B) to desired position.

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System Operating Procedure OP-005-004 Main Steam Revision 019 8.7.5 When local handwheel operation of MS-116A(B) is no longer desired, then perform the following:

8.7.5.1 Verify the applicable Atmospheric Dump Valve M/A station on CP-8 is in Manual with minimum output.

8.7.5.2 Using the local handwheel, Close SG 1(2) MS Atm Dump Vlv, MS-116A(B).

8.7.5.3 Turn local handwheel until pressure is relieved from clevis and remove clevis from actuator shaft.

8.7.5.4 Turn handwheel until clevis can be installed onto manual override shaft and screw clevis onto manual override shaft.

8.7.5.5 Close Filter Petcock Drain.

8.7.5.6 Open Local NG/IA Isolation to the positioner for applicable MS-116A(B) SG 1(2) MS Atm Dump Vlv:

NG-8271C NG/IA Isolation to MS-116A or NG-9281D NG/IA Isolation to MS-116B 8.7.5.7 Close MS-116A(B) SG 1(2) MS Atm Dump Vlv Positioner Equalizing Valve.

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

29

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE P2 SUPS MA Operation Applicant:

Examiner:

JPM P2 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: No Alternate Path: No Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 8 2010 NRC Walk Through Exam

JPM P2 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 8 2010 NRC Walk Through Exam

JPM P2 TASK ELEMENT STANDARD Manual Bypass Switch is in If Manual Bypass Switch is in SYNC DISCONNECT, then place Manual ALTERNATE SOURCE TO Bypass Switch to ALTERNATE SOURCE TO LOAD.

LOAD.

Comment: Critical Cue: Demonstrate that the Manual Bypass Switch is in SYNC DISCONNECT. When rotated, the manual Bypass Switch will indicate SAT / UNSAT ALTERNATE SOURCE TO LOAD.

TASK ELEMENT STANDARD Procedure Note At least 60 seconds must be allowed for capacitors to fully discharge prior Note reviewed.

to re-energizing inverter.

Comment: Critical SAT / UNSAT TASK ELEMENT STANDARD Procedure caution POTENTIAL SUPS DAMAGE COULD OCCUR IF THE PRE-CHARGE Caution reviewed.

PUSHBUTTON DOES NOT POP BACK OUT AFTER BEING RELEASED.

Comment:

SAT / UNSAT TASK ELEMENT STANDARD If inverter was isolated in accordance with step 6.1.1.3 or section 8.1, then Pre-charge button operated depress and hold Pre-charge pushbutton until the following are met:

properly with correct

Pre-charge light Illuminates indications.

DC Input voltage 120 VDC Comment: Critical Cue: After the Pre-charge button is held, light illuminates and DC voltage rises to as displayed. SAT / UNSAT Button does not stick.

Revision 0 Page 4 of 8 2010 NRC Walk Through Exam

JPM P2 TASK ELEMENT STANDARD Verify the following applicable SUPS supply breakers ON:

ID-EBKR-312A-2B SUPS MA Normal Supply Breakers ON.

ID-EBKR-1A-22 SUPS MA Emergency Supply (DC)

Comment:

Cue: Breakers will be as displayed, ON.

SAT / UNSAT TASK ELEMENT STANDARD Procedure Caution EMERGENCY FEEDER BREAKER SHALL NOT BE PLACED TO "ON" Caution reviewed.

UNLESS PRE-CHARGE LIGHT IS ILLUMINATED AND DC INPUT VOLTAGE IS 120 VDC.

Comment:

SAT / UNSAT TASK ELEMENT STANDARD Verify applicable SUPS Emergency Feeder breaker ON:

Breaker is ON.

ID-EBKR-MA-C SUPS MA Emergency Feeder Comment: Critical Cue: Breaker will initially OFF. Provide ON indication after operation.

SAT / 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 Revision 0 Page 5 of 8 2010 NRC Walk Through Exam

JPM P2 TASK ELEMENT STANDARD Verify applicable SUPS Normal Feeder breaker ON:

Breaker is ON.

ID-EBKR-MA-B SUPS MA Normal Feeder Comment: Critical Cue: Breaker will initially OFF. Provide ON indication after operation.

SAT / 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 Caution Reviewed.

ILLUMINATED PRIOR TO PLACING MANUAL BYPASS SWITCH TO "INVERTER TO LOAD."

Comment:

SAT / UNSAT TASK ELEMENT STANDARD Verify In Sync light Illuminated. Verification complete.

Comment:

Cue: As displayed.

SAT / UNSAT Revision 0 Page 6 of 8 2010 NRC Walk Through Exam

JPM P2 TASK ELEMENT STANDARD Manual Bypass Switch is in Place Manual Bypass Switch to INVERTER TO LOAD.

INVERTER TO LOAD Comment: Critical Cue: Provide indication that the switch is initially in ALTERNATE SOURCE TO LOAD, then in INVERTER TO LOAD after operation. SAT / UNSAT TASK ELEMENT STANDARD Verify Transfer To Bypass Source alarm Clears at local SUPS Alarms verified.

annunciator panel.

Comment:

Cue: As displayed.

SAT / UNSAT TASK ELEMENT STANDARD Verify DC Output from Rectifier voltage is ~140 VDC (138.5 to 141.5 Verification complete.

VDC).

Comment: Critical Cue: As displayed.

SAT / UNSAT TASK ELEMENT STANDARD Perform applicable breaker lineup attachment for SUPS being transferred from Alternate to Normal AC Power: N/A

Attachment 11.1 SUPS MA Breaker Lineup Comment: Critical Cue: Inform applicant that the attachment will be performed by another operator and that the task is complete. SAT / UNSAT END OF TASK Revision 0 Page 7 of 8 2010 NRC Walk Through Exam

JPM P2 APPLICANT 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.

Revision 0 Page 8 of 8 2010 NRC Walk Through Exam

System Operating Procedure OP-006-005 Inverters and Distribution Revision 303 6.0 NORMAL OPERATIONS 6.1 SUPS MA, MB, MC, & MD NORMAL MANIPULATIONS 6.1.1 Transfer from Normal to Alternate AC Power as follows:

CAUTION (1) SUPS MA, MB, MC, AND MD MAY BE OPERATED ON THE NORMAL AC SUPPLY WITHOUT THE DC INPUT POWER (EMERGENCY DC SUPPLY) SUPPLIED FROM THE BATTERY. THE DURATION OPERATING IN THIS CONDITION SHOULD BE MINIMIZED. [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 TO LOAD.

6.1.1.1 Verify SUPS In Sync light Illuminated, then place Manual Bypass Switch to ALTERNATE SOURCE TO LOAD.

6.1.1.2 Verify Transfer To Bypass Source annunciator at local SUPS annunciator panel is Illuminated.

6.1.1.3 If inverter is to be isolated, then place the following applicable SUPS panel breakers to OFF:

MA ID-EBKR-MA-B SUPS MA Normal Feeder ID-EBKR-MA-C SUPS MA Emergency Feeder MB ID-EBKR-MB-B SUPS MB Normal Feeder ID-EBKR-MB-C SUPS MB Emergency Feeder MC ID-EBKR-MC-B SUPS MC Normal Feeder ID-EBKR-MC-C SUPS MC Emergency Feeder MD ID-EBKR-MD-B SUPS MD Normal Feeder ID-EBKR-MD-C SUPS MD Emergency Feeder 6.1.1.4 If synchronizing circuitry is to be isolated, then place Manual Bypass Switch to SYNC DISCONNECT.

25

System Operating Procedure OP-006-005 Inverters and Distribution Revision 303 6.1.2 Transfer from Alternate to Normal AC Power as follows:

6.1.2.1 If Manual Bypass Switch is in SYNC DISCONNECT, then place Manual Bypass Switch to ALTERNATE SOURCE TO LOAD.

NOTE At least 60 seconds must be allowed for capacitors to fully discharge prior to re-energizing inverter.

CAUTION POTENTIAL SUPS DAMAGE COULD OCCUR IF THE PRE-CHARGE PUSHBUTTON DOES NOT POP BACK OUT AFTER BEING RELEASED. [CR-WF3-2005-02224]

6.1.2.2 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 6.1.2.3 Verify 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-14F SUPS MC Normal Supply ID-EBKR-A-38 SUPS MC Emergency Supply (DC)

MD ID-EBKR-311B-14F SUPS MD Normal Supply ID-EBKR-1B-22 SUPS MD Emergency Supply (DC)

CAUTION EMERGENCY FEEDER BREAKER SHALL NOT BE PLACED TO "ON" UNLESS PRE-CHARGE LIGHT IS ILLUMINATED AND DC INPUT VOLTAGE IS 120 VDC.

6.1.2.4 Verify 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 26

System Operating Procedure OP-006-005 Inverters and Distribution Revision 303 ID-EBKR-MD-C SUPS MD Emergency Feeder 6.1.2.4.1 Verify Inverter Output frequency is ~60 HZ (59.7 to 60.3 HZ).

6.1.2.5 Verify 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 Feeder 6.1.2.5.1 Verify DC Output from Rectifier voltage is 136 to 141.5 VDC.

CAUTION TO PREVENT INVERTER DAMAGE, THE "IN SYNC" LIGHT MUST BE ILLUMINATED PRIOR TO PLACING MANUAL BYPASS SWITCH TO "INVERTER TO LOAD."

6.1.2.6 Verify In Sync light Illuminated.

6.1.2.6.1 Place Manual Bypass Switch to INVERTER TO LOAD.

6.1.2.7 Verify Transfer To Bypass Source alarm Clears at local SUPS annunciator panel.

6.1.2.8 Verify DC Output from Rectifier voltage is ~140 VDC (138.5 to 141.5 VDC).

6.1.2.9 Perform applicable breaker lineup attachment for SUPS being transferred from Alternate to Normal AC Power:

Attachment 11.1 SUPS MA Breaker Lineup Attachment 11.3 SUPS MB Breaker Lineup Attachment 11.5 SUPS MC Breaker Lineup Attachment 11.7 SUPS MD Breaker Lineup 27

Waterford 3 2010 NRC Walk Through Exam JOB PERFORMANCE MEASURE P3 BOP Evacuation of the Control Room Actions Applicant:

Examiner:

JPM P3 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: Yes Alternate Path: No Applicant:

Time Start: Time Finish:

Performance Time: minutes Performance Rating: SAT UNSAT Comments:

Examiner: Date:

Signature Revision 0 Page 2 of 7 2010 NRC Walk Through Exam

JPM P3 EXAMINER 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 APPLICANT DIRECTION 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.

Revision 0 Page 3 of 7 2010 NRC Walk Through Exam

JPM P3 Perform the following at Emergency Diesel Generator B:

TASK ELEMENT STANDARD Select LOCAL control of EDG B by depressing the Control Mode Local control is selected.

pushbutton.

Comment: Critical Cue: Indications will be as is on arrival. After Local button is depressed, indication and handle shift to Local. SAT / UNSAT TASK ELEMENT STANDARD At Diesel Generator B RTGB Isolation Panel (EDG B Room north of phone booth on west wall) perform the following:

FR 2367 is in isolate, operated with the Transition

Depress AND Hold Transition pushbutton.

button held.

Place key-operated switch, FR 2367, to ISOLATE.

Release Transition pushbutton.

Comment: Critical Cue: Indications will be as is on arrival. When keyswitch is placed in ISOLATE, provide cue that EDG B started. SAT / UNSAT TASK ELEMENT STANDARD IF EDG B failed to start, THEN direct NAO to reset Control Power for 3B N/A Swgr Undervoltage Relays AND THEN verify EDG B starts.

Comment:

Cue: EDG B will start on previous step.

SAT / UNSAT TASK ELEMENT STANDARD Inform the following that EDG B is operating:

ATC Communication completed.

NAO Comment:

Cue: Acknowledge communication.

SAT / UNSAT Revision 0 Page 4 of 7 2010 NRC Walk Through Exam

JPM P3 TASK ELEMENT STANDARD Procedure note (1) The east side stairwell has emergency lighting provided AND is the preferred path for transiting within the CAA.

Note Reviewed.

(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.

Comment:

SAT / UNSAT TASK ELEMENT STANDARD WHEN informed by NAO that breakers for BAM-113A(B) are Open, THEN OPEN the following: BAM-113 A & BAM-113 B

BAM-113A Boric Acid Makeup Tank A Gravity Feed Valve are open.

BAM-113B Boric Acid Makeup Tank B Gravity Feed Valve Comment: Critical 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 SAT / UNSAT and BAM-113 B.

Each valve is in their respective BAM Tank Room.

TASK ELEMENT STANDARD Inform ATC that BAM-113A AND BAM-113B are Open. Communication completed.

Comment:

Cue: Acknowledge communication.

SAT / UNSAT Revision 0 Page 5 of 7 2010 NRC Walk Through Exam

JPM P3 TASK ELEMENT STANDARD Provide initial BAM Tank A AND BAM Tank B levels to the ATC using the following indicators: Level instruments are un-

BAM-ILI-0240 Boric Acid Make-up Tank A Discharge Header isolated and levels read.

Level Indicator Level instruments isolated

BAM-ILI-0241 Boric Acid Make-up Tank B Discharge Header after readings are taken.

Level Indicator Comment: Critical Cue: Provide manual valve cues when instruments are un-isolated and re-isolated. Provide tank level reading of 88% each. SAT / UNSAT TASK ELEMENT STANDARD Provide hourly updates of BAM Tank levels to the ATC (or at a frequency N/A as determined by ATC, based on BAMT levels and usage).

Comment:

Cue: End task at this point.

SAT / UNSAT END OF TASK Revision 0 Page 6 of 7 2010 NRC Walk Through Exam

JPM P3 APPLICANT 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.

Revision 0 Page 7 of 7 2010 NRC Walk Through Exam

Off Normal Procedure OP-901-502 Evacuation of Control Room and Subsequent Plant Shutdown Revision 017 Page 1 of 6 ATTACHMENT 4 BOP TIME CRITICAL ACTIONS PLACEKEEPER START DONE N/A

1. Transfer controls to LCP-43 as follows: [10 Minutes]

1.1 Place ALL TRANSFER 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 ALL ISOLATION SWITCHES in Aux Panels 2 to ISOLATE.

Aux Panel 2 Door 1 (5 switches) 1.3 WHEN informed by STA that Room A transfer is complete, THEN notify ATC that transfer to LCP-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) 87

Off Normal Procedure OP-901-502 Evacuation of Control Room and Subsequent Plant Shutdown Revision 017 Page 2 of 6 ATTACHMENT 4 BOP TIME CRITICAL ACTIONS (CONTD)

PLACEKEEPER START DONE N/A

3. Perform A Switchgear breaker alignment as follows:

3.1 Place the following breakers to OFF: [25 Minutes]

EG-EBKR-A-11 EG A Engine Control Panel Feeder #1 (DC)

EG-EBKR-A-12 EG A Engine Control Panel Feeder #2 (DC)

EFW-EBKR-A-23 Emergency Feedwtr to SG2 B/U Isol (EFW-229B) (DC)

EGF-EBKR-312A-3F EG A Fuel Oil Transfer Pump MS-EBKR-313A-6M MSIV A Upstream Drip 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 3A Bus Tie to Switchgear 2A as follows: [30 Minutes]

3.2.1 Simultaneously DEPRESS Permissive Pushbutton AND place breaker control switch 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 Tie to Switchgear 2A breaker DID NOT Open using the control switch, THEN TRIP the breaker by DEPRESSING the Manual Trip Lever on the breaker.

88

Off Normal Procedure OP-901-502 Evacuation of Control Room and Subsequent Plant Shutdown Revision 017 Page 3 of 6 ATTACHMENT 4 BOP TIME CRITICAL ACTIONS (CONTD)

NOTE Entry into the Controlled Access Area (CAA) is from A Switchgear through Door D018.

[P-25082]

PLACEKEEPER START DONE N/A

4. Perform the following at Emergency Diesel Generator B:

[20 Minutes]

4.1 Select LOCAL control of EDG B by depressing the Control Mode pushbutton.

4.2 At Diesel Generator B RTGB Isolation Panel (EDG B 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, to ISOLATE.

4.2.3 Release Transition pushbutton.

4.3 IF EDG B failed to start, THEN direct NAO to reset Control Power for 3B Swgr Undervoltage Relays AND THEN verify EDG B starts.

4.4 Inform the following that EDG B is operating:

ATC NAO 89

Off Normal Procedure OP-901-502 Evacuation of Control Room and Subsequent Plant Shutdown Revision 017 Page 4 of 6 ATTACHMENT 4 BOP TIME CRITICAL ACTIONS (CONTD)

NOTE (1) The east side stairwell has emergency lighting provided AND is the preferred path for transiting 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.

PLACEKEEPER START DONE N/A

5. WHEN informed by NAO that breakers for BAM-113A(B) are Open, THEN OPEN the following:

[1 Hour]

BAM-113A Boric Acid Makeup Tank A Gravity Feed Valve BAM-113B Boric Acid Makeup Tank B Gravity Feed Valve 5.1 Inform ATC that BAM-113A AND BAM-113B are Open.

Continuous 5.2 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 Disch Hdr Level Indicator BAM-ILI-0241 Boric Acid Make-up Tank B Disch Hdr Level Indicator Continuous 5.2.1 Provide hourly updates of BAM Tank levels to the ATC (or at a frequency as determined by ATC, based on BAMT levels and usage).

90

Off Normal Procedure OP-901-502 Evacuation of Control Room and Subsequent Plant Shutdown Revision 017 Page 5 of 6 ATTACHMENT 4 BOP TIME CRITICAL ACTIONS (CONTD)

PLACEKEEPER START DONE N/A

6. WHEN informed by the NAO that breaker lineup is complete for aligning Essential Chiller B for service, THEN perform the following: [1.5 Hours]

6.1 IF Essential Chiller AB is replacing B, THEN align Essential Chiller B to replace AB as follows:

6.1.1 Verify Essential Chiller AB and Essential Chill Water Pump AB secured.

6.1.2 Unlock, THEN CLOSE AND Lock the following:

CHW-110AB CHW Expansion Tank AB Header Isolation CMU-528B Chiller AB Expansion Tank Makeup Isolation 6.1.3 Unlock, THEN OPEN AND Lock the following:

CMU-529B Condensate Makeup to CHW Expansion Tank B Isolation CC-305B Essential Chiller B CCW Inlet Isolation CHW-788B Chill Water Pump B Suction Line Isolation CHW-110B CHW Expansion Tank B Header Isolation.

6.1.4 Unlock, THEN CLOSE AND Lock the following:

CC-304B CCW Header B Supply to Essential Chiller AB CC-318B CCW Header B Return from Essential Chiller AB CHW-786B Essential Chiller AB Return Header B Isolation CHW-132B Essential Chiller AB to CHW Header B Supply Isolation 6.2 Verify Chill Water Pump B operating.

6.3 Verify Essential Chiller B operating.

91

Off Normal Procedure OP-901-502 Evacuation of Control Room and Subsequent Plant Shutdown Revision 017 Page 6 of 6 ATTACHMENT 4 BOP TIME CRITICAL ACTIONS (CONTD)

NOTE Door blocks for blocking open respective doors are located in the LCP-43 locker.

PLACEKEEPER START DONE N/A

7. Establish H&V Room (Essential Chiller Area) ventilation as follows: [1.5 Hours]

7.1 Start HVR-MFAN-0024B, RAB +46 HVAC Room Exhaust 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 bottom of stairs

8. WHEN Attachment 4 has been completed, THEN inform the Shift Manager.

END 92

ML101870681

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