ML15245A305

Initial Exam 2015-301 Final Simulator Scenarios

ML15245A305
Person / Time
Site:	Catawba
Issue date:	08/31/2015
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
50-413/15-301, 50-414/15-301
Download: ML15245A305 (218)

Text

Catawba Nuclear Station NRC Exam May 2015 NRC INITIAL LICENSE EXAM SCENARIO # 1 Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 1 of 78

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1 Facility: Catawba NRC Exam 2015 Scenario No.: 1 Op Test No.: 2015301 Examiners: Operators: SRO RO BOP Initial Conditions: IC#160; Unit 1 is at 50% power at the BOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 50% power at the BOL. 1A CA pump has been tagged out for annual PMs. 1A CA pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 1A ND pump is tagged out for performance of electrical testing. 1A ND pump has been inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and is expected to be returned to service in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Direction for the crew is to begin power increase to 100% power.

Event Malf. No. Event Event No. Type* Description N-BOP 1 N-SRO Power increase to 100% power R-RO I-BOP 2 ENB013A I-SRO N41 loss of control power - AP/16 TS-SRO C-BOP 3 RN059D C-SRO 2A RN pump trip - AP/20 TS-SRO C-RO 4 MT005B Turbine bearing high vibration - AP/02 C-SRO C-RO 5 IRX009 Control rods fail to move in auto on turbine trip C-SRO 6 NC013D M-ALL Large break LOCA KC028 KC001A C-BOP 7 Running KC pump trips, other KC pumps fail to auto start on SI KC001C C-SRO KC001D 8 SM003A C-RO 1SM-5 fails to close on Main Steam Isolation signal 9 ND015 C-ALL 1B ND pump trip - Loss of Emergency Coolant Recirc

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 2 of 78

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1 Scenario 1 - Summary Initial Condition Unit 1 is at 50% power at the BOL. Unit 2 is at 100% power.

Turnover:

Unit 1 is at 50% power at the BOL. 1A CA pump has been tagged out for annual PMs. 1A CA pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 1A ND pump is tagged out for performance of electrical testing. 1A ND pump has been inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and is expected to be returned to service in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Direction for the crew is to begin power increase to 100% power.

Event 1 Crew will use the provided reactivity plan to begin a power increase to 100%. RO will input desired target and load rate into the turbine control panel. BOP will perform a dilution per the reactivity plan. RO may withdraw rods to increase temperature. RO will place the turbine in GO to initiate load increase.

Event 2 N41 control power will be lost. Crew will enter AP/1/A/5500/016 (Malfunction of Nuclear Instrumentation System)

Case IV (Power Range Malfunction) to remove the failed NI from service.

Verifiable Action - BOP will remove N41 from service from the NI racks in the back of the control room.

Event 3 2A RN pump will trip. Crew will enter AP/0/A/5500/020 (Loss of Nuclear Service Water) Case I (Loss of RN train) to start another RN pump.

Verifiable Action - BOP will be required to start an RN pump to supply flow to loads presently in service.

Event 4 Turbine bearing high vibration alarm is received. Per the annunciator response procedure, a turbine trip will be required. Crew will enter AP/1/A/5500/002 (Turbine Trip) to address the turbine trip.

Verifiable Action - OATC will have to manually trip the main turbine to prevent further damage.

Event 5 Following the turbine trip, the control rods fail to move in auto. This will require manual rod insertion by the RO per the immediate actions of AP/1/A/5500/002. The crew may further address rod control issue using AP/1/A/5000/015 (Rod Control Malfunction).

Verifiable Action - OATC will manually insert control rods to maintain Tavg within 1°F of Tref.

Event 6 A large break LOCA occurs. Crew will enter EP/1/A/5000/E-0 (Reactor Trip) to diagnose and address the LOCA.

Verifiable Action - The crew members will be required to trip the NC pumps on loss of subcooling. The OATC will have to control feed flows to maintain S/G levels.

Event 7 Following the reactor trip, the running KC pump will trip and the remaining KC pumps will fail to auto start on the Safety Injection signal. This will require the BOP to start the 3 remaining KC pumps to supply KC loads that are in service.

Verifiable Action - The BOP will be required to reset S/I and the D/G load sequencers and start the 3 available KC pumps.

Event 8 Following the Main Steam Isolation signal generated by Hi/Hi containment pressure, 1SM-5 (1B Main Steam Isolation Valve) will fail to auto close, requiring the RO to manually close it.

Verifiable Action - The OATC will manually close 1SM-5.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 3 of 78

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1 Scenario 1 - Summary (cont.)

Event 9 Following entry into EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant), 1B ND pump will trip. Crew will transition to EP/1/A/5000/ECA-1.1 (Loss of Emergency Coolant Recirculation) to address.

Verifiable Action - Crew will be required to minimize RWST outflow and take actions to either begin an RWST makeup or assign a Unit 2 operator to perform the makeup.

Critical Task 1 - Manually start at least the minimum number of CCW pumps required to provide adequate component cooling for the operating safeguards train(s) before loss of any ECCS component occurs.

Critical Task 2 - Makeup to the RWST and minimize RWST outflow.

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 8

2. Malfunctions after EOP entry (1-2) 3

3. Abnormal events (2-4) 3

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 2

6. EOP contingencies requiring substantive actions (0-2) 1

7. Critical tasks (2-3) 2 Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 4 of 78

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC # 160 START TIME:__________

Trigger Instructor Action Delete Final Delay Ramp Event In MAL-ENB013A (P/R 41 BLOWN INSTRU 2 2 FUSE) MENT OVR-RN059D (RN PMP 2A PB 3 ON 3 (UNIT 2) OFF PB)

MAL-MT005B (TURBINE 4 13 1:00 4 VIBRATION 6)

MAL-IRX009 (RODS FAIL TO N/A AUTO 5 MOVE)

MAL-NC013D (NC COLD LEG D 6 27.5 :30 6 LEAK)

MAL-KC001A (KC PUMP 1A1 7 AUTO 7 FAILURE)

MAL-KC001C (KC PUMP 1B1 7 AUTO 7 FAILURE)

MAL-KC001D (KC PUMP 1B2 7 AUTO 7 FAILURE)

LOA-KC028 (RACKOUT KC PMP RACK-7 7 1A2) OUT VLV-SM003A (SM5 MSIV B FAIL N/A ACTIVE 8 AUTO ACTIONS)

LOA-ND015 (RACKOUT ND PMP RACK-9 4:00 9 1B) OUT LOA-VC038 (MNL RST OF LATCH 11 FOR CHILLER A HI COND PRESS RESET 10:00 TRP DUE TO LOSS RN) 12 LOA-CNT002 (H2 ANALYZERS) BOTH 10:00 LOA-CA017 (RACKOUT CA PUMP RACK-N/A 1A) OUT LOA-ND014 (RACKOUT ND PMP RACK-N/A 1A) OUT ENSURE EVENT 7 = jpplp4 (1) l jpplp4 (2)

ENSURE EVENT 9 = xeai167r Place red tag collars on 1A CA pump and 1A ND pump.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 5 of 78

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1

2. SIMULATOR BRIEFING 2.1 Control Room Assignments:

Position Name CRS RO BOP 2.2 Give a copy of Attachment 2 (Shift Turnover Information) to the CRS.

3. EXERCISE PRESENTATION 3.1 Familiarization Period A. Allow examinees time to familiarize themselves with the Control Board alignments.

3.2 Scenario EVENT 1, Increase reactor power to 100%

BOOTH INSTRUCTOR ACTION IF contacted as SOC that power increase to 100% is commencing, REPEAT the information.

3.3 Scenario EVENT 2, PR N41 loss of instrument power BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 2 to cause N41 to fail low.

BOOTH INSTRUCTOR ACTION WHEN contacted as IAE to place bistables in the tripped condition per Model W/O

1. 00874531, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as the SWM to write a W/R or PIP for N41 failure, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF notified as the reactor group engineer that N41 has failed, REPEAT the information.

3.4 Scenario EVENT 3, 2A RN pump trip BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause 2A RN pump to trip.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 6 of 78

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1 BOOTH INSTRUCTOR ACTION IF contacted as the Unit Supervisor or an AO to restore VC/YC to service, THEN INSERT SIMULATOR Trigger 11.

After 10 minutes has elapsed and YC chiller A has restarted, NOTIFY the control room that A train VC/YC is returned to service.

BOOTH INSTRUCTOR ACTION IF contacted as AO or Unit supervisor to investigate reason for 2A RN pump trip, REPEAT the information. No call back will be required.

BOOTH INSTRUCTOR ACTION IF contacted as SWM or WCC SRO to initiate a W/R or PIP for 2A RN pump trip, REPEAT the information.

BOOTH INSTRUCTOR ACTION WHEN contacted as AO to check out the RN pump started, REPEAT the information.

After 5 minutes, REPORT RN pump ___ looks good for continued operation.

BOOTH INSTRUCTOR ACTION IF contacted as the Unit 2 control room to ensure RN aligned to in service KC heat exchangers and to ensure KC Hx Otlt Mode switches properly aligned, REPORT Yes to both.

BOOTH INSTRUCTOR ACTION WHEN notified as environmental chemistry of the RN pump shift, REPEAT the information.

3.5 Scenario EVENTS 4 & 5, Turbine bearing high vibration and failure of rods to automatically insert following the turbine trip BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 4 to cause a turbine bearing 5, 6, & 7 high vibration.

BOOTH INSTRUCTOR ACTION IF contacted as the SWM to write a W/R or PIP for the turbine bearing high vibration or for failure of rods to move in automatic, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as the SWM to write a W/R or PIP for the failure of rods to move, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as an AO to close 1SP-3, REPEAT the information.

After 10 minutes, contact the control room and REPORT 1SP-3 is closed.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 7 of 78

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1 3.6 Scenario EVENTS 6, Large break LOCA, 7, Running KC pump trips & all other KC pumps fail to auto start, 8, 1SM-5 fails to close on Main Steam Isolation Signal, 9, 1B ND pump trip causing a Loss of Emergency Coolant Recirculation capability BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 6 to cause a large break LOCA.

BOOTH INSTRUCTOR ACTION WHEN dispatched as an AO to secure all ice condenser air handling units per EP/1/A/5000/G-1 Enclosure 11, REPEAT the information.

BOOTH INSTRUCTOR ACTION WHEN dispatched as an AO to place the Hydrogen Analyzers in service per OP/1/A/6450/010, REPEAT the information and INSERT SIMULATOR Trigger 12.

After 10 minutes has elapsed, NOTIFY control room that all ice condenser air handling units have been secured per EP/1/A/5000/G-1 Enclosure 11 & the hydrogen analyzers have been placed in service per OP/1/A/6450/010.

BOOTH INSTRUCTOR ACTION IF contacted as secondary chemistry to sample all S/Gs for activity, REPEAT the information.

After 20 minutes, contact the control room and REPORT that S/Gs have no abnormal activity.

BOOTH INSTRUCTOR ACTION IF contacted as RP to frisk all cation columns for activity, REPEAT the information.

After 10 minutes, contact the control room and REPORT that S/Gs have no abnormal activity.

BOOTH INSTRUCTOR ACTION IF dispatched as an AO to secure 1A & 1B D/Gs and place them in standby readiness per OP/1/A/6350/002, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as the SWM to write a W/R or PIP for the 1B ND pump trip, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as the SWM to expedite restoration of 1A ND pump or 1A CA pump, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as maintenance to assist in restoring cold leg recirculation capability per EM/1/A/5200/006, REPEAT the information.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 8 of 78

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1 BOOTH INSTRUCTOR ACTION IF contacted as station management to monitor Shutdown Margin during NC system cooldown, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as primary chemistry to periodically perform NC boron samples, REPEAT the information.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 9 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 10 of 78 Event

Description:

Increase reactor power to 100%.

Time Position Applicants Actions or Behavior EVENT 1 NOTE TO EVALUATOR: Crew will begin by performing a dilution per the reactivity plan provided by reactor engineering. They will also set up the turbine controls for proper load rate and target load. Crew may also decide to withdraw rods a couple of steps to provide a temperature error prior to placing the turbine in GO. These steps may be performed in any order that the crew chooses.

NOTE TO EVALUATOR: All needed materials have been provided to the crew to perform any needed pre job briefs prior to being brought into the simulator for their control board walk down prior to assuming the watch.

NOTE TO EVALUATOR: The following steps are taken from OP/1/A/6150/009 (Boron Concentration Control) Enclosure 4.3 (Dilution).

NOTE: This enclosure will affect reactivity of the core and is therefore ALL designated important to Reactivity Management per the guidelines of AD-OP-ALL-0203 (Reactivity Management). (R.M.)

BOP 3.1 Ensure valves are aligned per Enclosure 4.8 (Valve Checklist).

3.2 IF the blender is set for automatic makeup per Enclosure 4.1 (Automatic BOP Makeup), record the setpoint on 1NV-242A (RMWST To B/A Blender Ctrl): _______________ gpm 3.3 Ensure the following valve control switches in AUTO:

BOP

• 1NV-242A (RMWST To B/A Blender Ctrl)

• 1NV-181A (B/A Blender Otlt To VCT)

BOP 3.4 Ensure 1NV-242A (RMWST To B/A Blender Ctrl) controller in auto.

BOP 3.5 Ensure at least one reactor makeup water pump is in AUTO or ON.

3.6 Record the desired volume of reactor makeup water to be added. _____

BOP gallons 3.7 Adjust the total makeup counter to the desired volume of reactor BOP makeup water to be added. (R.M.)

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 10 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 11 of 78 Event

Description:

Increase reactor power to 100%.

Time Position Applicants Actions or Behavior 3.8 Place the NC MAKEUP MODE SELECT switch to the DILUTE BOP position.

NOTE: High letdown flow rates result in increased backpressure on the letdown line. If letdown flow is > 90 gpm, it may be desirable to BOP reduce the dilution flow rate to 80 gpm to avoid the Rx Make-up Flow Deviation alarm and associated automatic actions.

3.9 IF required, adjust the setpoint for 1NV-242A (RMWST To B/A Blender BOP Ctrl) to the desired flow.

NOTE TO EVALUATOR: Step 3.10 is N/A. Steps 3.11, 3.12, and 3.13 are conditional steps that should not be required during this scenario. Step 3.11 may be used by the crew to divert letdown to the RHT to maintain VCT level.

3.14 WHILE makeup is in progress, monitor the following for expected results:

ALL

• Control rod motion

• NC System Tavg

• Reactor Power NOTE: If a small makeup is being performed, place keeping for Steps 3.15 BOP through 3.17 may be performed after Step 3.18 is performed.

3.15 Place the NC MAKEUP CONTROL switch in the START position.

BOP (R.M.)

3.16 Verify the following:

BOP

• 1NV-242A (RMWST To B/A Blender Ctrl) modulates to establish desired flow

• 1NV-181A (B/A Blender Otlt To VCT) opens BOP 3.17 IF in AUTO, verify the reactor makeup water pump starts.

NOTE: The total makeup counter may count up 1 - 5 gallons after BOP termination.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 11 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 12 of 78 Event

Description:

Increase reactor power to 100%.

Time Position Applicants Actions or Behavior 3.18 WHEN the desired volume of reactor makeup water is reached on the total makeup counter, ensure the following valves close. (R.M.)

BOP

• 1NV-242A (RMWST To B/A Blender Ctrl)

• 1NV-181A (B/A Blender Otlt To VCT) 3.19 IF automatic makeup is desired, perform one of the following:

3.19.1 IF it is desired to change the blender outlet boron concentration, refer to Enclosure 4.1 (Automatic Makeup).

OR 3.19.2 IF makeup at the previous concentration is acceptable AND the system was previously aligned per Enclosure 4.1 (Automatic Makeup), perform the following:

BOP 3.19.2.1 Ensure the controller for 1NV-242A (RMWST To B/A Blender Ctrl) is set to the value recorded in Step 3.2.

(R.M.)

3.19.2.2 Place the NC MAKEUP MODE SELECT switch in AUTO.

3.19.2.3 Place the NC MAKEUP CONTROL switch to the START position. (R.M.)

NOTE TO EVALUATOR: Step 3.20 is N/A. This concludes the dilution portion of EVENT 1.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 12 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 13 of 78 Event

Description:

Increase reactor power to 100%.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The following steps are from OP/1/B/6300/001 (Turbine Generator)

Enclosure 4.2 (Load Changing).

3.1.1 Ensure the proper reactivity management controls established per RO AD-OP-ALL-0203 (Reactivity Management). (R.M.)

NOTE TO EVALUATOR: Step 3.1.2 is a continuous action step that may be verified by the crew, but will not need to be performed as part of this scenario.

CAUTION: 1. Until it is recognized that the first stage shell metal temperature change rate stays below the allowable limit (150°F/hr), the following load rate shall NOT be exceeded:

• 1/2%/min - First Stage Inner Shell Temperature (1MC3 or OAC point C1A1140 (Turbine Lower Inner Shell Temp))

< 350°F

• 1%/min - First Stage Inner Shell Temperature (1MC3 or OAC point C1A1140 (Turbine Lower Inner Shell Temp))

RO

> 350°F

2. Normal steady-state load changes shall be made without exceeding the limits shown on Enclosure 4.7 (Generator Operating Limits) and in the Unit One OAC Databook Recommended Startup and Loading Curves.

3. Unit One Reactor Operating Data, Section 2.4 shall be referred to for allowable ramp rates. A LOAD RATE > 6.2 MW/MIN shall NOT be used during normal load changes.

3.1.3 Increase turbine generator load by performing the following:

3.1.3.1 Select LOAD RATE and verify it illuminates.

3.1.3.2 Input the desired load rate.

3.1.3.3 Select ENTER and verify LOAD RATE goes dark.

3.1.3.4 Select TARGET and verify it illuminates.

RO 3.1.3.5 Input the desired load target.

3.1.3.6 Select ENTER and verify TARGET light goes dark.

3.1.3.7 Verify new load target appears on Target Display.

3.1.3.8 Select GO and verify it illuminates to start load increase.

3.1.3.9 Coordinate with Secondary Chemistry to adjust S/G blowdown flowrates to obtain maximum blowdown for the appropriate load.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 13 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 14 of 78 Event

Description:

Increase reactor power to 100%.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The following steps are from OP/1/A/6150/008 (Rod Control) Enclosure 4.16 (Control Bank Manual Operation At Power). This procedure was given to the crew as part of the turnover package with initial conditions and step 3.1 signed off. Crew may decide not to perform these steps at this time.

NOTE: Steps 3.2 through 3.6 may be signed off as time allows ensuring RO operator maintains proper focus on reactivity management.

3.2 Monitor the following:

• Tavg/Tref

• Demand Counter positions

• DRPI rod positions ALL

• ROD MOTION RODS-IN/RODS-OUT Light

• ROD MOTION DEMAND SIGNALS - TEMP ERROR/POWER MISMATCH

• Power Range instruments

• IR SUR (Startup Rate) 3.3 IF plant conditions require, place the CRD BANK SELECT switch in RO MAN.

3.4 IF withdrawing Control Banks, pull and hold the ROD MOTION lever RO OUT as required until control rods are in the desired position. (R.M.)

3.5 IF inserting Control Banks, push and hold the ROD MOTION lever IN RO as required until control rods are in the desired position. (R.M.)

3.6 IF automatic rod control is desired, perform the following:

3.6.1 Verify Unit 1 Reactor Power is > 15% RTP.

RO 3.6.2 WHEN Tavg is within 1°F of Tref, place CRD BANK SELECT in AUTO.

Booth Operator will insert Trigger 2 for EVENT 2 at the discretion of the lead evaluator.

END OF EVENT 1 Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 14 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 15 of 78 Event

Description:

N41 Loss of instrument power.

Time Position Applicants Actions or Behavior EVENT 2 Indications: 1AD-2, A/1 P/R HI NEUTRON FLUX RATE ALERT 1AD-2, A/3 P/R HI NEUTRON FLUX HI SET POINT ALERT 1AD-2, B/3 COMPARATOR P/R CHANNEL DEVIATION 1AD-2, B/5 P/R HI VOLTAGE FAILURE 1AD-2, E/8 OVER POWER ROD STOP 1AD-2, F/10 DCS TROUBLE N41 indication fails to bottom of the scale NOTE TO EVALUATOR: The crew may make a plant page announcing the entry into AP/1/A/5500/016 (Malfunction of Nuclear Instrumentation System)

NOTE TO EVALUATOR: The following steps are taken from AP/1/A/5500/016, Case IV (Power Range Malfunction).

RO 1. Verify all rod motion - STOPPED.

RO 2. Verify 1AD-2, E/8 OVER POWER ROD STOP - DARK.

RO 2.RNO. Adjust Turbine load to maintain T-Avg at T-Ref.

RO 3. Identify failed P/R channel: N-41, N-42, N-43, OR N-44.

RO 4. Ensure unaffected channels - OPERABLE.

5. Request IAE to place the following bistables in the tripped condition.

REFER TO Model W/O #00874531:

RO/BOP

• OT DELTA T

• OP DELTA T

6. Perform the following actions at the Miscellaneous Control And Indication Panel:

a. Place the appropriate ROD STOP BYPASS switch to the affected channel position.

BOP

b. Verify the affected nuclear overpower rod stop channel bypassed status light (1SI-19) - LIT.

c. Place POWER MISMATCH BYPASS switch to the affected channel position.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 15 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 16 of 78 Event

Description:

N41 Loss of instrument power.

Time Position Applicants Actions or Behavior

7. Perform the following actions at the Detector Current Comparator panel:

a. Place UPPER SECTION channel defeat switch to the affected channel.

BOP

b. Verify the CHANNEL DEFEAT light for the upper section - LIT.

c. Place LOWER SECTION channel defeat switch to the affected channel.

d. Verify the CHANNEL DEFEAT light for the lower section - LIT.

8. At the Comparator And Rate panel, place the COMPARATOR BOP CHANNEL DEFEAT switch to the affected channel position.

NOTE The following annunciators will actuate in the following step:

1AD-2, A/1 P/R HI NEUTRON FLUX RATE ALERT ALL 1AD-2, A/3 P/R HI NEUTRON FLUX HI SET POINT ALERT 1AD-2, B/5 P/R HI VOLTAGE FAILURE NOTE TO EVALUATOR: In the following step, after removing control power fuses, the crew may hand the fuses to the evaluator to keep as the SM.

9. De-energize the affected channel as follows:

a. Remove the control power fuses at Power Range A drawer.

NOTE Replacement of the affected P/R control power fuses shall not occur without authorization of the Superintendent of Operations BOP or his designee.

b. Request the OSM to maintain the control power fuses under his control.

c. Verify the affected Power Range cabinet shows no physical signs of damage.

10. Ensure affected channel bistables are in the required state. REFER RO TO Enclosure 1 (P/R Bistables That Must Be Tripped).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 3 in the back of this guide.

11. Ensure operable P/R channel selected to record on NIS RO RECORDER.

RO 12. Adjust control rods to maintain T-Ave at T-Ref.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 16 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 17 of 78 Event

Description:

N41 Loss of instrument power.

Time Position Applicants Actions or Behavior

13. WHEN T-Avg within 1°F of T-Ref, AND auto rod control desired, RO THEN return control rods to auto.

SRO 14. Determine and correct cause of P/R malfunction.

15. Ensure compliance with appropriate Tech Specs:

SRO

• 3.2.4 (Quadrant Power Tilt Ratio (QPTR))

• 3.3.1 (Reactor Trip System (RTS) Instrumentation).

NOTE TO EVALUATOR: The following Tech Specs apply:

• T.S. 3.3.1 Condition D to place Channel 1 of Power Range Neutron Flux High and Power Range Neutron Flux High Positive Rate in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

• T.S. 3.3.1 Condition E to place Channel 1 Overtemperature T and Overpower T in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

• T.S. 3.3.1 Condition R to verify P-10 is in required state for existing unit conditions within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

• T.S. 3.3.1 Condition S to verify P-7, P-8, and P-9 are in required state for existing unit conditions within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

• T.S. 3.2.4 SR 3.2.4.1 has a NOTE which allows the crew to use the remaining 3 operable channels to calculate QPTR as long as THERMAL POWER is < 75%. This calculation is not required until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after exceeding 50% power. The crew could also perform an incore flux map per SR 3.2.4.2 in lieu of performing SR 3.2.4.1.

16. Determine required notifications:

SRO

• REFER TO RP/0/A/5000/001 (Classification of Emergency)

• REFER TO RP/0/B/5000/013 (NRC Notification Requirements).

RO/BOP 17. Notify Reactor Group Engineer of occurrence.

18. WHEN the affected P/R channel is repaired, THEN ensure IAE ALL returns the channel to service.

SRO 19. Determine long term plant status. RETURN TO procedure in effect.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 17 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 18 of 78 Event

Description:

N41 Loss of instrument power.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The SRO may perform a crew brief or focus brief as time allows to summarize the event and to inform the crew of applicable Tech Specs.

It is not required to wait for the crew to perform the brief prior to continuing with the next event.

Booth Operator will insert Trigger 3 for EVENT 3 at the discretion of the lead evaluator.

END OF EVENT 2 Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 18 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 19 of 78 Event

Description:

2A RN Pump Trip.

Time Position Applicants Actions or Behavior EVENT 3 Indications: 1AD-12, A/2 RN ESSENTIAL HDR A PRESSURE - LO 1AD-12, A/5 RN ESSENTIAL HDR B PRESSURE - LO 1AD-13, F/5 HVAC PANEL TROUBLE OAC alarm for KC HX A Outlet Temperature - High RN Pump 2A control switch ON & OFF lights - DARK NOTE TO EVALUATOR: The crew may make a plant page announcing the entry into AP/0/A/5500/020 (Loss of Nuclear Service Water).

NOTE TO EVALUATOR: The following steps are taken from AP/0/A/5500/020 Case I (Loss of RN Train).

BOP 1. Start idle RN pump(s) as required.

2. Ensure Unit 1 and Unit 2 OATC monitors Enclosure 1 (Foldout SRO Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 4 in the back of this guide.

3. Verify RN System in normal alignment as follows:

BOP

• Both RN Supply headers - ALIGNED AND

• Both RN Discharge headers - ALIGNED

4. Verify each operating RN pump discharge flow - GREATER THAN BOP 8,600 GPM.

5. Verify each operating RN pump discharge flow - LESS THAN 23,000 BOP GPM.

BOP 6. Ensure RN pumps - IN OPERATION AS NEEDED.

7. Ensure proper alignment of RN to KC Hxs as follows:

BOP a. Verify RN - ALIGNED TO IN SERVICE KC HX(s).

b. Ensure KC Hx Otlt Mode switches - PROPERLY ALIGNED.

8. Verify each operating RN pump discharge flow - GREATER THAN BOP 8,600 GPM.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 19 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 20 of 78 Event

Description:

2A RN Pump Trip.

Time Position Applicants Actions or Behavior BOP 9. Verify RN - AVAILABLE TO ALL UNIT 1 AND 2 D/G(s).

10. Determine VC/YC status as follows:

BOP

• Verify VC/YC - ALIGNED TO OPERATING RN TRAIN.

• Verify YC Chiller - RUNNING 10.RNO. Align VC/YC to operating RN train. REFER TO BOP OP/0/A/6450/011 (Control Room Area Ventilation/Chilled Water System).

NOTE TO EVALUATOR: The A YC chiller will have tripped due to high condenser pressure when the loss of RN occurred. It is not meant for the BOP to restore VC/YC in this scenario. If an AO is dispatched out to manually reset the high condenser pressure manual latch locally, the A YC chiller will restart.

SRO 11. Determine and correct cause of loss of RN train.

12. Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual:

• SLC 16.7-6 (RN Discharge Instrumentation)

• 3.6.5 (Containment Air Temperature)

• 3.6.6 (Containment Spray System)

• 3.6.17 (Containment Valve Injection Water System (CVIWS))

SRO

• 3.7.5 (Auxiliary Feedwater (AFW) System)

• 3.7.7 (Component Cooling Water (CCW) System)

• 3.7.8 (Nuclear Service Water System (NSWS))

• 3.7.10 (Control Room Area Ventilation System (CRAVS))

• 3.7.11 (Control Room Area Chilled Water System (CRACWS))

• 3.8.1 (A.C. Sources - Operating)

• 3.8.2 (A.C. Sources - Shutdown)

NOTE TO EVALUATOR: The SRO should determine that both Unit 1 & 2 are in T.S. 3.7.8 Condition A to restore NSWS train to OPERABLE status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

The SRO will direct the BOP to perform OP/0/A/6400/006 C (Nuclear Service Water System) Enclosure 4.11 (Operability Actions With One RN Pump and/or Its Associated D/G Inoperable With Both Units Entering An Action Statement). This procedure will be a system lineup verification only, therefore at the discretion of the lead evaluator, once the T.S.

determination is made, the scenario may continue to the next failure.

The SRO may decide to hold a focus brief or crew brief to summarize the event and inform the crew of applicable Tech Specs. Also LCO 3.0.6 applies to prevent having to cascade to all supported system LCOs.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 20 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 21 of 78 Event

Description:

2A RN Pump Trip.

Time Position Applicants Actions or Behavior

13. Determine required notifications:

SRO REFER TO RP/0/A/5000/001 (Classification Of Emergency)

REFER TO RP/0/B/5000/013 (NRC Notification Requirements)

14. Notify Environmental Chemistry of any RN pump shifts that have RO/BOP occurred.

ALL 15. Determine long term plant status. RETURN TO procedure in effect.

Booth Operator will insert Trigger 4 for EVENT 4 at the discretion of the lead evaluator.

END OF EVENT 3 Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 21 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4&5 Page 22 of 78 Event

Description:

Turbine Bearing High Vibration and failure of rods to move in auto on turbine trip.

Time Position Applicants Actions or Behavior EVENTS 4 & 5 Indications: 1AD-1, E/8 TURBINE GEN HI VIBRATION OAC alarms for Turbine Bearing Vibration High on bearings 5, 6, and 7.

NOTE TO EVALUATOR: Per the annunciator response procedure for 1AD-1, E/8, the crew should decide to trip the Unit 1 Main Turbine following validation of vibration levels exceeding 12 Mils. This annunciator response is Attachment 5 in the back of this guide.

RO Trip Unit 1 Main Turbine due to high vibration.

NOTE TO EVALUATOR: The following steps are taken from AP/1/A/5500/002 (Turbine Generator Trip). The crew may make a plant page announcing entry into AP/1/A/5500/002.

RO 1. Verify reactor power - LESS THAN 69%.

2. Verify Turbine Trip:

RO

• All turbine stop valves - CLOSED.

3. Verify reactor response:

RO

• Control rods - IN AUTO AND STEPPING IN

• P/R neutron flux - DECREASING.

NOTE TO EVALUATOR: Control rods will not insert in auto. Crew may still have control rods in manual following the power change at the beginning of the scenario.

RO may decide to put rods back to auto prior to or following the turbine trip. Whether the crew decides to place rods back in auto or not, the RO will have to manually insert rods to maintain T-Avg. The RO will insert rods as necessary to maintain the total combined temperature/power mismatch error approximately at 1°F.

NOTE TO EVALUATOR: The crew may eventually address the failure of the control rods to move in auto by referring to AP/1/A/5500/015 (Rod Control Malfunction) Case I (Failure of Rods to Move). The crew should stabilize the plant using AP/1/A/5500/002 prior to referring to AP/15. The steps for AP/15 are included in Attachment 14 at the back of this document.

3.RNO. IF T-Avg is greater than 1.5°F higher than T-Ref, THEN:

a. Ensure CRD BANK SELECT switch - IN MANUAL.

RO b. Operate control rods until one of the following is met:

• Reactor power is less than 10%

OR

• T-Avg is less than 560°F.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 22 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4&5 Page 23 of 78 Event

Description:

Turbine Bearing High Vibration and failure of rods to move in auto on turbine trip.

Time Position Applicants Actions or Behavior BOP 4. Ensure C heater drain pumps - OFF.

BOP 5. Monitor Enclosure 4 (Rod Insertion Limit Boration).

6. WHEN reactor power is less than 20%, THEN:

a. Place CRD BANK SELECT switch - IN MANUAL.

b. Verify reactor power - GREATER THAN 5%.

c. Maintain control rods above insertion limits.

RO d. Operate control rods to stabilize reactor power between 6%-10%.

e. IF AT ANY TIME reactor power is less than or equal to 5%, THEN insert control rods to shutdown to Mode 3. REFER TO the following procedures:

• OP/1/A/6150/008 (Rod Control)

• OP/1/A/6100/002 (Controlling Procedure For Unit Shutdown).

7. Verify proper steam dump operation as follows:

a. C-9 COND AVAILABLE FOR STM DUMP status light (1SI-18) - LIT.

RO

b. Steam dump valves - MODULATING.

c. T-Avg - DECREASING TO T-REF.

8. Ensure generator is tripped as follows:

a. Verify turbine generator megawatt output - LESS THAN OR EQUAL TO ZERO MW.

b. Ensure the following breakers and MODs - OPEN:

RO

• MOD 1BG and 1BT

• MOD 1AG and 1AT

• Generator Breaker 1A and 1B.

c. Ensure main generator EXCITATION - OFF

d. Verify MAN/AUTO REG select switch MAN mode light - LIT.

9. Verify Pzr PORV and Pzr spray valve status as follows:

BOP a. All Pzr PORVs - CLOSED.

b. Normal Pzr spray valves - CLOSED.

BOP 10. Verify Pzr level - TRENDING TO PROGRAM.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 23 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4&5 Page 24 of 78 Event

Description:

Turbine Bearing High Vibration and failure of rods to move in auto on turbine trip.

Time Position Applicants Actions or Behavior RO 11. Verify S/G N/R levels - TRENDING TO OR STABLE AT 39%.

RO 12. Verify reactor power - GREATER THAN 5%.

13. Stabilize reactor power as follows:

a. Maintain control rods above insertion limits.

b. Operate control rods in manual to stabilize reactor power between RO 6%-10%.

c. Verify all atmospheric steam dump valves - CLOSED.

d. Verify condenser steam dump valves - MODULATING.

14. Align AS supply to CF pumps as follows:

a. Adjust 1AS-2 (Main Stm To Aux Steam) to maintain 165 psig.

BOP b. Ensure 1AS-12 (AS To CFPT Isol) - OPEN.

c. Dispatch operator to CLOSE 1SP-3 (SC To CFPT 1A & 1B) (TB1-640, 1G-24).

NOTE TO EVALUATOR: At this point the plant should be fairly stabilized. The crew will be borating and operating control rods as necessary to maintain the control rods above the insertion limits and to stabilize reactor power between 6%-10%. At the discretion of the lead evaluator, Trigger 6 for EVENT 6 may be inserted to begin the Major Event.

NOTE TO EVALUATOR: The remaining steps in AP/1/A/5500/002 are for aligning systems for the current plant power and setting the plant up to either restart the turbine or to commence with Unit shutdown.

Booth Operator will insert Trigger 6 for EVENT 6 at the discretion of the lead evaluator.

END OF EVENTS 4 & 5 Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 24 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 25 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior EVENTS 6, 7, 8, & 9 Indications: 1AD-13, F/5 HVAC PANEL TROUBLE 1AD-13, A/7 ICE COND LOWER INLET DOORS OPEN 1FO-1, D/5 HI CONT PRESS S/I RX TRIP SAFETY INJECTION ACTUATED status light (1SI-13) - LIT E/S Load Sequencer Actuated status lights (1SI-14) - LIT NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/E-0 (Reactor Trip or Safety Injection).

RO/BOP 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 6 in the back of this guide.

2. Verify Reactor Trip:

RO

• All rod bottom lights - LIT

• All reactor trip and bypass breakers - OPEN

• I/R power - DECREASING.

3. Verify Turbine Trip:

RO

• All turbine stop valves - CLOSED BOP 4. Verify 1ETA and 1ETB - ENERGIZED.

5. Verify S/I actuated:

BOP a. SAFETY INJECTION ACTUATED status light (1SI-13) - LIT.

b. Both E/S load sequencer actuated status lights (1SI-14) - LIT.

RO 6. Announce Unit 1 Safety Injection.

7. Determine required notifications:

SRO

• REFER TO RP/0/A/5000/001 (Classification of Emergency)

• REFER TO RP/0/B/5000/013 (NRC Notification Requirements).

RO 8. Verify all Feedwater Isolation status lights (1SI-5) - LIT.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 25 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 26 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior

9. Verify Phase A Containment Isolation status as follows:

BOP a. Phase A RESET lights - DARK.

b. Monitor Light Panel Group 5 St lights on energized train(s) - LIT.

10. Verify proper Phase B actuation as follows:

BOP a. Verify Containment pressure - HAS REMAINED LESS THAN 3 PSIG.

10.a.RNO. Perform the following:

1) Verify Phase B Isolation actuated as follows:

a) Phase B Isolation RESET lights - DARK.

b) IF Phase B Isolation RESET lights lit, THEN initiate Phase B Isolation.

c) Verify following monitor light panel lights - LIT:

• Group 1 Sp lights

• Group 5 Sp lights

• Group 5 St light L/11.

d) IF monitor light panel not in correct alignment, THEN ensure correct alignment.

BOP 2) Stop all NC pumps.

3) Maintain seal injection flow.

4) Energize H2 igniters.

5) Dispatch operator to perform the following:

a) Secure all ice condenser air handling units. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 11 (Securing All Ice Condenser Units).

b) Place containment H2 analyzers in service. REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems).

6) WHEN 9 minutes elapsed, THEN verify proper VX system operation. REFER TO Enclosure 5 (VX System Operation).

7) GO TO Step 11.

NOTE TO EVALUATOR: Monitor light panel Group 5 Sp light M/3 will be dark if 1SM-5 has not been closed by this point. Closing this valve will be the end of EVENT 8.

NOTE TO EVALUATOR: Enclosure 5 can be found as Attachment 10 in the back of this guide.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 26 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 27 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior

11. Verify proper CA pump status as follows:

RO a. Motor driven CA pumps - ON.

b. 3 S/G N/R levels - GREATER THAN 11%.

12. Verify all of the following S/I pumps - ON:

BOP

• NV pumps

• ND pumps

• NI pumps BOP 13. Verify all KC pumps - ON.

13.RNO. Perform the following for affected train(s):

a. Reset ECCS.

b. Reset D/G load sequencer(s).

Critical c. Start affected pump(s).

BOP Task #1 d. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on.

e. IF KC flow cannot be established to NC pumps, THEN stop all NC pumps.

NOTE TO EVALUATOR: The applicant will reset both trains of ECCS and D/G load sequencers and start the 1A1, 1B1, and 1B2 KC pumps. This will be the end of EVENT 7.

BOP 14. Verify all Unit 1 and Unit 2 RN pumps - ON.

NOTE TO EVALUATOR: 2A RN will not be running due to previously tripping and cannot be manually started. Step 14 RNO b will have the operator attempt to manually start 2A RN pump.

15. Verify proper ventilation systems operation as follows:

BOP

• REFER TO Enclosure 2 (Ventilation System Verification).

• Notify Unit 2 operator to perform Enclosure 3 (Opposite Unit Ventilation Verification).

NOTE TO EVALUATOR: Enclosure 2 can be found as Attachment 7 in the back of this guide.

RO 16. Verify all S/G pressures - GREATER THAN 775 PSIG.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 27 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 28 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior

17. Verify proper S/I flow as follows:

a. NV S/I FLOW - INDICATING FLOW.

b. NC pressure - LESS THAN 1620 PSIG.

BOP

c. NI pumps - INDICATING FLOW.

d. NC pressure - LESS THAN 285 PSIG.

e. ND pumps - INDICATING FLOW TO C-LEGS.

18. WHEN time and manpower permit (within two hours of event),

THEN monitor Spent Fuel Pool level and temperature. REFER TO BOP EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring).

NOTE TO EVALUATOR: G-1 Enclosure 1 can be found as Attachment 9 in the back of this guide.

19. Control S/G levels as follows:

a. Verify total CA flow - GREATER THAN 450 GPM.

RO b. WHEN each S/G N/R level greater than 11% (29% ACC), THEN control feed flow to maintain that S/G N/R level between 11% (29%

ACC) and 50%.

RO 20. Verify all CA isolation valves - OPEN.

21. Verify S/I equipment status based on monitor light panel - IN BOP PROPER ALIGNMENT.

BOP 21.RNO. Align equipment.

NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until RO subsequent procedures provide alternative NC temperature control guidance.

22. Control NC Temperature. REFER TO Enclosure 4 (NC Temperature RO Control).

NOTE TO EVALUATOR: Enclosure 4 can be found as Attachment 8 in the back of this guide.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 28 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 29 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior

23. Verify Pzr PORV and Pzr Spray Valve status as follows:

a. All Pzr PORVs - CLOSED.

BOP

b. Normal Pzr spray valves - CLOSED.

c. At least one Pzr PORV isolation valve - OPEN.

24. Verify NC subcooling based on core exit T/Cs - GREATER THAN RO 0°F.

24.RNO IF any NV or NI pump on, THEN perform the following:

BOP a. Ensure all NC pumps - OFF.

b. Maintain seal injection flow.

25. Verify main steamlines intact:

RO

• All S/G pressures - STABLE OR INCREASING

• ALL S/Gs - PRESSURIZED.

26. Verify S/G tubes intact as follows:

• Verify the following EMF trip 1 lights - DARK:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-26 (Steamline 1A)

RO/BOP

• 1EMF-27 (Steamline 1B)

• 1EMF-28 (Steamline 1C)

• 1EMF-29 (Steamline 1D)

• All S/G levels - STABLE OR INCREASING IN A CONTROLLED MANNER.

27. Verify NC System intact as follows:

• Containment pressure - LESS THAN 1 PSIG.

• IF normal off-site power available, THEN verify containment pressure less than 0.3 PSIG.

• Containment high range EMFs - LESS THAN 3 R/HR:

BOP

• 1EMF-53A (Containment Trn A)

• 1EMF-53B (Containment Trn B).

• Containment EMF trip 1 lights - DARK:

• 1EMF-38 (Containment Particulate)

• 1EMF-39 (L) (Containment Gas (Lo Range)).

• Containment sump level - STABLE.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 29 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 30 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior 27.RNO Perform the following:

a. Energize H2 igniters.

b. Dispatch operator to perform the following:

1) Secure all ice condenser air handling units. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 11 (Securing All Ice Condenser Units).

2) Place containment H2 analyzers in service. REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems).

c. IF both the following conditions exist, BOP

• Containment pressure - HAS REMAINED LESS THAN 3 PSIG

• Containment pressure - BETWEEN 1 PSIG AND 3 PSIG THEN start one VX fan and secure normal containment ventilation. REFER TO EP/1/A/5000/G-1 (Generic Enclosures),

Enclosure 18 (VX and Containment Ventilation Control).

d. Concurrently:

• Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees).

• GO TO EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant).

NOTE TO EVALUATOR: The NC Integrity status tree will in an Orange condition, requiring entry into EP/1/A/5000/FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition).

TRANSITION TO EP/1/A/5000/FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition).

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 30 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 31 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition).

RO/BOP 1. Verify NC pressure - GREATER THAN 285 PSIG.

1.RNO. IF ND flow to C-Legs is greater than 675 GPM, THEN RETURN BOP TO procedure and step in effect.

TRANSITION TO EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant)

NOTE TO EVALUATOR: The SRO may elect to perform a focus brief or a crew brief to summarize the event and solicit for any crew input.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 31 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 32 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant).

ALL 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 11 in the back of this guide.

2. Verify NC subcooling based on core exit T/Cs - GREATER THAN RO 0°F.

2.RNO. IF any NV or NI pump on, THEN perform the following:

BOP a. Ensure all NC pumps - OFF.

b. Maintain seal injection flow.

3. Verify main steamlines intact:

RO

• All S/G pressures - STABLE OR INCREASING

• All S/Gs - PRESSURIZED.

4. Control intact S/G N/R levels as follows:

a. Verify N/R level in any intact S/Gs - GREATER THAN 11% (29%

RO ACC).

b. THROTTLE feed flow to maintain all intact S/G N/R levels between 11% (29% ACC) and 50%.

5. Reset the following:

a. ECCS.

b. D/G load sequencers.

BOP c. Phase A

d. Phase B.

e. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on.

NOTE TO EVALUATOR: Once the BOP resets the Phase B signal, a 4 minute timer starts. At the end of the 4 minutes, the 1B ND pump will trip initiating EVENT 9.

6. Establish VI to Containment as follows:

BOP

• Ensure 1VI-77B (VI Cont Isol) - OPEN.

• Verify VI pressure - GREATER THAN 85 PSIG.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 32 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 33 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior

7. Verify secondary radiation - NORMAL:

a. Ensure the following signals - RESET:

1) CA System valve control

2) KC NC NI NM St signals.

b. Align all S/Gs for Chemistry sampling.

c. Perform at least one of the following:

• Notify Chemistry to sample all S/Gs for activity OR

• Notify RP to frisk all cation columns for activity.

BOP d. Verify the following EMF trip 1 lights - DARK:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-26 (Steamline 1A)

• 1EMF-27 (Steamline 1B)

• 1EMF-28 (Steamline 1C)

• 1EMF-29 (Steamline 1D)

e. Verify all S/Gs - INTACT:

• All S/G pressures - STABLE OR INCREASING

• All S/Gs - PRESSURIZED.

f. WHEN activity results reported, THEN verify all S/Gs indicate no activity.

8. Verify Pzr PORV and Isolation Valves:

a. Power to all Pzr PORV isolation valves - AVAILABLE.

b. All Pzr PORVs - CLOSED.

BOP c. Any Pzr PORV isolation valve - OPEN.

d. IF AT ANY TIME any Pzr PORV opens due to high pressure, THEN after Pzr pressure decreases to less than 2315 PSIG, ensure PORV closes or is isolated.

9. Verify S/I termination criteria:

a. NC subcooling based on core exit T/Cs - GREATER THAN 0°F.

b. Secondary heat sink:

RO/BOP

• Any intact S/G N/R level - GREATER THAN 11% (29% ACC)

OR

• Total feed flow to intact S/Gs - GREATER THAN 450 GPM.

c. NC pressure - STABLE OR INCREASING.

d. Pzr level - GREATER THAN 11%

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 33 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 34 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior SRO 9.a.RNO. GO TO Step 9.f.

9.f. Monitor S/I termination criteria. REFER TO Enclosure 2 (S/I Termination Criteria).

RO/BOP

g. IF AT ANY TIME S/I termination criteria met while in this procedure, THEN RETURN TO Step 9.

NOTE TO EVALUATOR: Enclosure 2 can be found as Attachment 12 in the back of this guide.

10. Determine if ND pumps should be stopped:

BOP

a. NC pressure - GREATER THAN 285 PSIG.

BOP 10.a.RNO. GO TO Step 12.

12. Verify D/Gs should be stopped:

a. Any D/G - ON.

b. Verify 1ETA energized by offsite power as follows:

• D/G 1A BKR TO ETA - OPEN

• 1ETA - ENERGIZED.

BOP c. Dispatch operator to stop 1A D/G and place in standby readiness.

REFER TO OP/1/A/6350/002 (Diesel Generator Operation).

d. Verify 1ETB energized by offsite power as follows:

• D/G 1B BKR TO ETB - OPEN

• 1ETB - ENERGIZED.

e. Dispatch operator to stop 1B D/G and place in standby readiness.

REFER TO OP/1/A/6350/002 (Diesel Generator Operation).

13. Obtain containment H2 concentration as follows:

a. Ensure operator dispatched to secure all ice condenser air handling units. REFER TO EP/1/A/5000/G-1 (Generic Enclosures),

Enclosure 11 (Securing All Ice Condenser Units).

BOP b. Verify containment H2 analyzers - IN SERVICE.

c. Verify containment H2 concentration - LESS THAN 6%.

d. Verify H2 igniters - ON.

e. Verify containment H2 concentration - LESS THAN 0.5%.

NOTE TO EVALUATOR: At this point, 1B ND pump should have tripped and Cold Leg Recirc capability will not be able to be verified in the following step. A transition to EP/1/A/5000/ECA-1.1 (Loss Of Emergency Coolant Recirculation) will be made.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 34 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 35 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior

14. Initiate evaluation of plant status as follows:

a. Verify Cold Leg Recirc capability from at least one train:

• A Train

• 1A ND pump - AVAILABLE

• 1NI-185A (ND Pump 1A Cont Sump Suct) - POWER BOP AVAILABLE.

OR

• B Train

• 1B ND pump - AVAILABLE

• 1NI-184B (ND Pump 1B Cont Sump Suct) - POWER AVAILABLE.

14.a.RNO. IF cold leg recirc capability not available from either train, THEN ALL GO TO EP/1/A/5000/ECA-1.1 (Loss Of Emergency Coolant Recirculation).

TRANSITION TO EP/1/A/5000/ECA-1.1 (Loss Of Emergency Coolant Recirculation)

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 35 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 36 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/ECA-1.1 (Loss Of Emergency Coolant Recirculation).

1. IF loss of Emergency Coolant Recirculation is due to sump ALL blockage, THEN GO TO EP/1/A/5000/ECA-1.3 (Containment Sump Blockage).

RO/BOP 2. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 13 in the back of this guide.

3. Restore recirc capability as follows:

a. Verify all of the following pumps - AVAILABLE TO BE OPERATED FROM CONTROL ROOM:

BOP

• ND pumps

• NV pumps

• NI pumps.

3.a.RNO. IF power is available to affected essential bus(s), THEN dispatch operator and maintenance to determine and correct cause of BOP pump failure. REFER TO EM/1/A/5200/005 (Troubleshooting Cause For ND, NI, or NV Pump(s) Failing to Start).

3.b. Verify the following valves - AVAILABLE TO BE OPERATED FROM CONTROL ROOM:

BOP

• 1NI-185A (ND Pump 1A Cont Sump Suct)

• 1NI-184B (ND Pump 1B Cont Sump Suct).

3.c. Verify containment sump level adequate as follows:

BOP

• 1AD-20, B/2 CONT SUMP LEVEL > 2.5 ft - LIT OR

• 1AD-21, B/2 CONT SUMP LEVEL > 2.5 ft - LIT BOP 3.d. Verify Cold Leg Recirc capability - RESTORED.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 36 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 37 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior 3.d.RNO. Perform the following:

1) Continue attempts to restore recirc capability as follows:

• Power restoration

• Local valve operation

• Obtain maintenance assistance as required. REFER TO EM/1/A/5200/006 (Troubleshooting Cause For FW, ND, NI, or NV Valves(s) Failing to Operate).

BOP

• Other actions as specified by station management.

2) WHEN emergency coolant recirc capability is restored, THEN perform the following:

• IF transfer to Cold Leg Recirc is required, THEN GO TO EP/1/A/5000/ES-1.3 (Transfer To Cold Leg Recirculation).

• RETURN TO procedure and step in effect.

3) GO TO Step 4.

4. Ensure S/I - RESET:

a. ECCS.

BOP b. D/G load sequencers.

c. IF AT ANY TIME a B/O occurs, THEN restart S/I equipment previously on.

5. Depress DEFEAT pushbuttons on the following switches:

BOP

• C-LEG RECIR FWST TO CONT SUMP SWAP TRN A

• C-LEG RECIR FWST TO CONT SUMP SWAP TRN B

6. Verify adequate FWST level as follows:

a. FWST level - GREATER THAN 5% (1AD-9, E/8 FWST LO-LO BOP LEVEL alarm setpoint).

b. IF AT ANY TIME FWST level is less than 5% (1AD-9, E/8 FWST LO-LO LEVEL alarm setpoint), THEN GO TO Step 32.

7. Verify criteria to align NS for recirc as follows:

BOP a. Verify both NS pumps - OFF.

b. Verify containment pressure - GREATER THAN 3 PSIG.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 37 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 38 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior 7.b.RNO. Perform the following:

1) IF AT ANY TIME containment pressure goes above 3 PSIG, BOP THEN perform Step 7.

2) GO TO Step 8.

8. Align NS spray valves as follows:

BOP

a. Verify NS Pump 1A - ON.

8.a.RNO. Ensure the following valves - CLOSED:

BOP

• 1NS-29A (NS Spray Hdr 1A Cont Isol)

• 1NS-32A (NS Spray Hdr 1A Cont Isol)

BOP 8.b. Verify NS Pump 1B - ON.

8.b.RNO. Ensure the following valves - CLOSED:

BOP

• 1NS-15B (NS Spray Hdr 1B Cont Isol)

• 1NS-12B (NS Spray Hdr 1B Cont Isol) 8.c. IF AT ANY TIME NS pumps are stopped or started, THEN perform the following:

BOP

• CLOSE associated spray valve after securing pump.

• OPEN associated spray valves prior to starting NS pump(s).

Critical 9. Initiate makeup to FWST. REFER TO OP/1/A/6200/014 (Refueling SRO Task #2 Water System).

NOTE TO EVALUATOR: The critical part of this step is just for the crew to address starting the FWST makeup. This can be accomplished by the SRO stating that he would get a Unit 2 operator to perform the makeup. It is not intended to allow the crew to perform this makeup due to there being several options of sources of makeup, long calculations to perform, and system manipulations that are required to be made by AOs outside the control room. At lead evaluator discretion, if the crew begins to perform this makeup themselves, the following cue may be given - The Unit 2 BOP will perform the FWST makeup per OP/1/A/6200/014.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 38 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 39 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior

10. Control intact S/G levels as follows:

a. Verify N/R level in all intact S/Gs - GREATER THAN 11% (29%

RO ACC).

b. THROTTLE feed flow to maintain all intact S/G N/R levels between 11% (29% ACC) and 50%.

11. Monitor shutdown margin during cooldown as follows:

a. Notify station management to monitor shutdown margin during NC system cooldown.

BOP b. Request periodic NC boron samples from Primary Chemistry.

NOTE Boron sample results are not required prior to initiating cooldown in subsequent steps.

c. WHEN each NC boron sample obtained, THEN perform the following:

12. WHEN P-11 PZR S/I BLOCK PERMISSIVE status light (1SI-18) is lit, THEN perform the following:

BOP

a. Depress ECCS steam pressure BLOCK pushbuttons

b. Verify main steam isolation blocked status lights (1SI-13) - LIT.

NOTE After low steamline pressure main steam isolation signal is blocked, maintaining steam pressure negative rate less than 2 PSIG per ALL second will prevent a Main Steam Isolation.

OAC graphic SMRATES to monitor S/G pressure rates can be accessed via a hot button in the center of the SM graphic.

13. Initiate NC System cooldown to Cold Shutdown as follows:

a. Verify C-9 COND AVAILABLE FOR STM DUMP status light (1SI-RO

18) - LIT.

b. Verify MSIVs on all intact S/Gs - OPEN NOTE TO EVALUATOR: It is possible if CAPT #1 is running that another Main Steam Isolation could occur when opening the MSIV bypass valves in the following steps. If this happens, the crew will have to reset the MSI signal again or use the S/G PORVs when performing the cooldown. The crew will not be able to begin the actual cooldown during this scenario due to reactor coolant temperatures having decreased to approximately 265°F.

The cooldown limit is < 100°F/hour and includes any cooldown up to that point.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 39 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 40 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior 13.b.RNO. Perform the following:

1) IF MSIVs are closed to isolate break downstream of MSIVs, THEN perform the following:

2) Reset Main Steam Isolation signal as follows:

a) Ensure manual loaders for all MSIV bypass valves -

ADJUSTED TO 0%.

b) Reset SM Isolation.

c) Reset S/G PORVs.

3) Place steam dumps in pressure mode as follows:

a) Place STM DUMP CTRL in manual.

b) Adjust STM DUMP CTRL to 0% demand.

RO c) Place steam dumps in pressure mode.

4) Perform the following to equalize pressure across MSIVs on intact S/Gs:

a) OPEN MSIV bypass valve on intact S/Gs.

b) IF AT ANY TIME pressure does not equalize as required, THEN isolate steam loads off main steam header. REFER TO Enclosure 5 (Equalizing Across MSIVs).

5) WHEN all intact S/Gs pressure is within 50 psig of steam header pressure, THEN perform the following:

a) OPEN all MSIVs on intact S/Gs.

b) CLOSE all MSIV bypass valves.

c) Perform Steps 13.c through 13.e.

6) GO TO Step 14.

14. Verify S/I in service:

• Any NI pump - ON OR

• 1NI-9A (NV Pmp C/L Inj Isol) - OPEN OR BOP

• 1NI-10B (NV Pmp C/L Inj Isol) - OPEN OR

• At least one ND pump on with suction aligned to either of the following:

• FWST OR

• Containment Sump.

15. Establish one train of S/I flow as follows:

BOP

a. Verify only one NV pump - ON.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 40 of 78

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8, & 9 Page 41 of 78 Event

Description:

Large Break LOCA, running KC pump trips & other KC pumps fail to auto start, 1SM-5 fails to close on MSI signal, 1B ND pump trips causing loss of containment sump recirc capability.

Time Position Applicants Actions or Behavior Critical 15.a.RNO. Perform the following:

BOP Task #2 1) IF both NV pumps are on, THEN stop one NV pump.

BOP 15.b. Verify only one NI pump - ON.

Critical 15.b.RNO. Perform the following:

BOP Task #2 1) IF both NI pumps are on, THEN stop one NI pump.

15.c. Verify NC pressure - LESS THAN 285 PSIG.

BOP

d. Verify only one ND pump - ON.

15.d.RNO. perform the following:

1) IF both ND pumps are on, THEN stop one ND pump.

BOP

2) IF both ND pumps are off, AND available suction source is aligned, THEN start one ND pump.

NOTE TO EVALUATOR: At this point all steps have been taken to minimize FWST outflow, therefore at the discretion of the lead evaluator the scenario may be terminated by putting the simulator in FREEZE.

END OF EVENT 9 END OF SCENARIO 1 Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 41 of 78

Catawba Nuclear Station NRC Exam May 2015 Attachment List Scenario 1 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - AP/1/A/5500/016 Enclosure 1 (PR Bistables That Must Be Tripped) rev 27 ATTACHMENT 4 - AP/0/A/5500/020 Enclosure 1 (Foldout Page) rev 43 ATTACHMENT 5 - 1AD-1, E/8 TURBINE GEN HI VIBRATION Annunciator Response rev 57 ATTACHMENT 6 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page) rev 42 ATTACHMENT 7 - EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification) rev 42 ATTACHMENT 8 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control) rev 42 ATTACHMENT 9 - EP/1/A/5000/G-1 Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring) rev 9 ATTACHMENT 10 - EP/1/A/5000/E-0 Enclosure 5 (VX System Operation) rev 42 ATTACHMENT 11 - EP/1/A/5000/E-1 Enclosure 1 (Foldout Page) rev 28 ATTACHMENT 12 - EP/1/A/5000/E-1 Enclosure 2 (S/I Termination Criteria) rev 28 ATTACHMENT 13 - EP/1/A/5000/ECA-1.1 Enclosure 1 (Foldout Page) rev 40 ATTACHMENT 14 - AP/1/A/5500/015 Case I (Failure of Rods To Move) rev 14 Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 42 of 78

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK Manually start at least the minimum number of CCW pumps required to provide adequate component cooling for the 1

operating safeguards train(s) before loss of any ECCS component occurs.

2 Makeup to the RWST and minimize RWST outflow.

Comments:

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 43 of 78

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 50 % BOL 1551 PPM per OAC Controlling Procedure

• OP/1/A/6100/003 (Controlling Procedure for Unit Operation), Enclosure 4.1 (Power Increase). The steps up to step 3.52 are complete.

Other Information Needed to Assume the Shift

• Unit 1 is at 50% power. 1A CA pump has been tagged out for annual PMs. 1A CA pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 1A ND pump is tagged out for performance of electrical testing. 1A ND pump has been inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and is expected to be returned to service in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Direction for the crew is to begin a power increase to 100%.

AOs Available Seven AOs are available as listed on the status board METEOROLOGICAL CONDITIONS

• Upper wind direction = 315 degrees, speed = 3 mph

• Lower wind direction = 315 degrees, speed = 4.5 mph

• Forecast calls for clear skies over the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 44 of 78

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 3 Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 45 of 78

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Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 10 Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 67 of 78

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 11 Appendix D Catawba NRC Exam May 2015 Scenario 1 NUREG 1021 Revision 9 Page 68 of 78

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Catawba Nuclear Station NRC Exam May 2015 NRC INITIAL LICENSE EXAM SCENARIO # 2 Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 1 of 70

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1 Facility: Catawba NRC Exam 2015 Scenario No.: 2 Op Test No.: 2015301 Examiners: Operators: SRO RO BOP Initial Conditions: IC#161; Unit 1 is at 17% power at the EOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 17% power at the EOL with a Unit shutdown in progress for a refueling outage. 1A CA pump has been tagged out for annual PMs. 1A CA pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 1A ND pump is tagged out for performance of electrical testing. 1A ND pump has been inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and is expected to be returned to service in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Direction for the crew is to begin power decrease to

~15% power at 10%/hour and to swap Main Feedwater to the CA nozzles per OP/1/A/6100/002 (Controlling Procedure for Unit Shutdown) Enclosure 4.1 (Unit Shutdown to Mode 3) step 3.6.

Event Malf. No. Event Event No. Type* Description N-BOP Power decrease to 15% power & transfer of Main Feedwater to the CA 1 N-SRO Nozzles R-RO C-RO 2 MT010 1TL-3 fails closed - AP/23 C-SRO ENB010A I-BOP N35 loss of power - AP/16 3

I-SRO 4 EHC007B TS-SRO FWST Channel 1 fails low C-BOP 5 NCP008C NCP 1C #1 Seal Leakoff high flow - AP/08 C-SRO M-ALL 6 SG001A 1A Steam Generator Tube Rupture TS-SRO ISE003A C-BOP 7 Both trains Phase A Isolation fail to actuate on SI signal ISE003B C-SRO ISE007A C-RO 8 Both trains CF isolation fail to actuate ISE007B C-SRO

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 2 of 70

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1 Scenario 2 - Summary Initial Condition Unit 1 is at 17% power at the EOL. Unit 2 is at 100% power.

Turnover:

Unit 1 is at 17% power at the EOL with a Unit shutdown in progress for a refueling outage. 1A CA pump has been tagged out for annual PMs. 1A CA pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 1A ND pump is tagged out for performance of electrical testing. 1A ND pump has been inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and is expected to be returned to service in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Direction for the crew is to begin power decrease to ~15%

power at 10%/hour and to swap Main Feedwater to the CA nozzles per OP/1/A/6100/002 (Controlling Procedure for Unit Shutdown) Enclosure 4.1 (Unit Shutdown to Mode 3) step 3.6.

Event 1 Crew will use the provided reactivity plan to begin a power decrease to ~15% power in preparation for swapping main Feedwater to the CA nozzles. BOP will perform a boration per the reactivity plan. RO will input a target and load rate into the turbine control panel and place the turbine in GO to commence power decrease. BOP will swap Feedwater to the CA nozzles per OP/1/A/6100/002 Enclosure 4.1.

Event 2 1TL-3 (Steam Seal Reg Valve) will fail closed. This will cause Steam seal header pressure to decrease to a point that main condenser vacuum will begin to decrease. Crew can adjust 1TL-4 (Stm Seal Reg Byp) to increase steam seal pressure and recover main condenser vacuum. Crew may refer to AP/1/A/5500/023 (Loss of Condenser Vacuum) for guidance on restoring main condenser vacuum.

Verifiable Action - OATC will be required to throttle open 1TL-4 to increase steam seal pressure and recover condenser vacuum.

Event 3 N35 will lose power. Crew will enter AP/1/A/5500/016 (Malfunction of Nuclear Instrumentation System) Case III (Intermediate Range Malfunction) to remove the failed NI from service. If this is not done, and reactor power decreases to < 10%, the reactor will trip on Intermediate Range Hi Flux.

Verifiable Action - BOP will be required to remove N35 and N31 from service from the NI racks in the rear of the control room.

Event 4 FWST level channel 1 will fail low. This will require a Tech Spec call from the CRS.

Event 5 NCP 1C #1 seal will fail. Crew will enter AP/1/A/5500/008 (Malfunction of Reactor Coolant Pump) to address the seal failure. A reactor trip will be required, followed by trip of the 1C NCP.

Verifiable Action - The OATC will have to trip the reactor. When reactor power is < 5%, the BOP will trip the 1C NCP and close 1C NCP seal return isolation valve.

Event 6 Following the reactor trip and transition to ES-0.1, a Steam Generator Tube rupture will occur on 1A S/G.

Verifiable Action - The BOP will be required to manually initiate S/I due to not being able to maintain Pressurizer Level > 4%.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 3 of 70

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1 Scenario 2 - Summary (cont.)

Event 7 Both trains of Phase A containment isolation will fail to actuate on the Safety Injection, requiring the BOP to manually initiate.

Verifiable Action - The BOP will be required to initiate both trains of Phase A (St) Containment Isolation.

Event 8 Both trains of CF Isolation fail to actuate on the reactor trip and Safety Injection, requiring the RO to manually initiate.

Verifiable Action - The OATC will be required to initiate both trains of CF Isolation.

Critical Task 1 - Isolate Feedwater into and steam flow from ruptured S/G before a transition to ECA-3.1 occurs.

Critical Task 2 - Establish/maintain an RCS temperature so that transition from E-3 does not occur because the RCS temperature is in either of the following conditions:

• Too high to maintain the minimum required subcooling

• Below the RCS temperature that causes an extreme (red-path) or a severe (orange-path) challenge to the subcriticality and/or integrity status tree.

Critical Task 3 - Depressurize RCS to meet SI termination criteria before water release occurs from the ruptured S/G PORV or safety.

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 7

2. Malfunctions after EOP entry (1-2) 3

3. Abnormal events (2-4) 4

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 2

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 3 Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 4 of 70

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC #161 START TIME: _________

Trigger Instructor Action Delete Final Delay Ramp Event In MAL-MT010 (GLAND STEAM 2 0 :05 2 REGULATOR FAILURE (TL3))

MAL-ENB010A (I/R N35 LOSS OF INSTRU-3 INSTRUMENT OR CONTROL 3 MENT POWER)

XMT-FW001 (LFW_5000 WR FWST 4 0 4 LVL CH 1 TO DCS (FWAA5000))

MAL-NCP008C (NCP C NO. 1 SEAL 5 10 :10 5 FAILURE) 6 MAL-SG001A (S/G A TUBE LEAK) 300 3:00 6 MAL-ISE003A (AUTO PHASE A N/A BLOCK 7 ISOL SIGNAL TRN A)

MAL-ISE003B (AUTO PHASE A N/A BLOCK 7 ISOL SIGNAL TRN B)

MAL-ISE007A (AUTO CF ISOL N/A BLOCK 8 SIGNAL TRN A)

MAL-ISE007B (AUTO CF ISOL N/A BLOCK 8 SIGNAL TRN B)

LOA-CA017 (RACKOUT CA PUMP RACK-N/A 1A) OUT LOA-ND014 (RACKOUT ND PMP RACK-N/A 1A) OUT ANN-AD11-B03 (TRANSFORMER N/A ON A TROUBLE)

ANN-AD11-E03 (TRANSFORMER B N/A ON TROUBLE)

Ensure EVENT 6 = x10i154f Place red tag collar on 1A CA pump Place red tag collar on 1A ND pump Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 5 of 70

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1

2. SIMULATOR BRIEFING 2.1 Control Room Assignments:

Position Name CRS RO BOP 2.2 Give a copy of Attachment 2 (Shift Turnover Information) to the CRS.

3. EXERCISE PRESENTATION 3.1 Familiarization Period A. Allow examinees time to familiarize themselves with the Control Board alignments.

3.2 Scenario EVENT 1, Decrease reactor power to ~ 15% and swap feed flow to the CA nozzles per OP/1/A/6100/002 BOOTH INSTRUCTOR ACTION IF contacted as SOC that power decrease to 15% is commencing on Unit 1, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as Secondary Chemistry for required blowdown flow rates, REPORT Current flow rates are acceptable.

BOOTH INSTRUCTOR ACTION IF contacted as Security to CAD Secure doors AX661 & AX657B, REPORT that the doors are CAD secured.

BOOTH INSTRUCTOR ACTION IF contacted as Security to Un-CAD Secure doors AX661 & AX657B, REPORT the doors are no longer CAD secured.

3.3 Scenario EVENT 2, 1TL-3 fails closed BOOTH INSTRUCTOR ACTION WHEN directed by lead examiner, THEN INSERT SIMULATOR Trigger 2 to cause 1TL-3 to fail closed.

BOOTH INSTRUCTOR ACTION IF contacted as AO to check for problems with 1TL-3 or to check for steam seal relief valve issues, REPEAT the information.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 6 of 70

Catawba Nuclear Station NRC Exam May 2015 Appendix D Scenario Outline Form ES-D-1 After 10 minutes, contact the control room and REPORT no issues noted.

3.4 Scenario EVENT 3, N-31 & N-35 loss of power BOOTH INSTRUCTOR ACTION WHEN directed by lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause N-31 &

N-35 to lose power.

BOOTH INSTRUCTOR ACTION IF contacted as WCC or SWM to initiate a W/R or PIP for N-31 & N-35 failure, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as the Reactor Group Engineer for notification of N-31 & N-35 failures, REPEAT the information.

3.5 Scenario EVENT 4, FWST Channel 1 fails low BOOTH INSTRUCTOR ACTION WHEN directed by lead examiner, THEN INSERT SIMULATOR Trigger 4 to cause FWST Channel 1 to fail low.

BOOTH INSTRUCTOR ACTION IF contacted as WCC or SWM to initiate a W/R or PIP for Channel 1 FWST level, REPEAT the information.

3.6 Scenario EVENT 5, NCP 1C #1 Seal Leakoff High Flow BOOTH INSTRUCTOR ACTION WHEN directed by lead examiner, THEN INSERT SIMULATOR Trigger 5 to cause an NCP 1C #1 seal failure.

3.7 Scenario EVENTS 6, 7, & 8, 1A S/G Tube Rupture, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to actuate.

BOOTH INSTRUCTOR ACTION IF contacted as Secondary Chemistry to sample all S/Gs for activity, REPEAT the information.

After 20 minutes, contact the control room and REPORT that 1A S/G shows signs of increased activity.

BOOTH INSTRUCTOR ACTION IF contacted as RP to frisk all Unit 1 cation columns, REPEAT the information.

After 10 minutes, contact the control room and REPORT that 1A S/G shows signs of increased activity.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 7 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 8 of 70 Event

Description:

Decrease reactor power to 15% and swap feed flow to the CA nozzles Time Position Applicants Actions or Behavior EVENT 1 NOTE TO EVALUATOR: Crew will begin by performing a boration per OP/1/A/6150/009 Enclosure 4.2. Then the crew will set up the turbine controls for the reactor power decrease. Crew may also decide to insert control rods a couple of steps to provide a temperature error prior to placing the turbine in GO.

These steps may be performed in any order that the crew decides.

NOTE TO EVALUATOR: All needed materials have been provided to the crew to perform any needed pre job briefs prior to being brought into the simulator for their control board walk down prior to assuming the watch.

NOTE TO EVALUATOR: The following steps are taken from OP/1/A/6150/009 (Boron Concentration Control) Enclosure 4.2 (Boration).

NOTE: This enclosure will affect reactivity of the core and is therefore ALL designated important to Reactivity Management per the guidelines of AD-OP-ALL-0203 (Reactivity Management). (R.M.)

BOP 3.1 Ensure valves are aligned per Enclosure 4.8 (Valve Checklist).

3.2 Ensure the following valve control switches in AUTO:

BOP

• 1NV-238A (B/A To Blender Ctrl Vlv)

• 1NV-186A (B/A Blender Otlt To VCT Otlt)

BOP 3.3 Ensure 1NV-238A (B/A To Blender Ctrl Vlv) controller in auto.

BOP 3.4 Ensure at least one boric acid transfer pump is in AUTO or ON.

BOP 3.5 Record the desired volume of boric acid to be added. ______ gallons 3.6 Adjust the boric acid counter to the desired volume of boric acid to be BOP added. (R.M.)

3.7 IF the blender is set up for automatic makeup per Enclosure 4.1 BOP (Automatic Makeup), record the setpoint of the controller for 1NV-238A (B/A To Blender Ctrl Vlv). __________ gpm BOP 3.8 Place the NC MAKEUP MODE SELECT switch in BORATE.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 8 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 9 of 70 Event

Description:

Decrease reactor power to 15% and swap feed flow to the CA nozzles Time Position Applicants Actions or Behavior NOTE: Boric Acid flow rates > 32 gpm may result in a boric acid flow BOP deviation annunciator.

3.9 IF required, adjust the controller for 1NV-238A (B/A To Blender Ctrl Vlv)

BOP to the desired flow.

3.10 IF NC System boron concentration will be changed by > 50 ppm, initiate PZR spray to equalize the boron concentration throughout the BOP system by operating backup heaters per OP/0/A/6200/005 (Miscellaneous Component Operation).

NOTE TO EVALUATOR: Step 3.11, 3.12, and 3.13 are conditional steps and should not need to be performed during this scenario.

3.14 WHILE makeup is in progress, monitor the following for expected results:

RO

• Control rod motion

• NC System Tavg

• Reactor Power NOTE: If a small makeup is being performed, placekeeping for Steps 3.15 BOP through 3.18 may be performed after Step 3.19 is performed.

3.15 Place the NC MAKEUP CONTROL switch to the START position.

BOP (R.M.)

3.16 Verify the following:

BOP

• 1NV-238A (B/A To Blender Ctrl Vlv) modulates to establish desired flow

• 1NV-186A (B/A Blender Otlt To VCT Otlt) opens BOP 3.17 IF in AUTO, verify the boric acid transfer pump starts.

BOP 3.18 Verify proper flow by observing the Boric Acid Counter. {PIP 96-0137}

BOP NOTE: The boric acid counter may count up 1 - 5 gallons after termination.

3.19 WHEN the desired volume of boric acid is reached on the boric acid BOP counter, ensure the following valves close: (R.M.)

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 9 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 10 of 70 Event

Description:

Decrease reactor power to 15% and swap feed flow to the CA nozzles Time Position Applicants Actions or Behavior

• 1NV-238A (B/A To Blender Ctrl Vlv)

• 1NV-186A (B/A Blender Otlt To VCT Otlt)

NOTE: If additional borations will be performed over the course of the shift, BOP flushing the makeup line is NOT recommended.

3.20 IF desired, flush the makeup line as follows:

3.20.1 Record the setpoint on 1NV-242A (RMWST To B/A Blender Ctrl): ________ gpm 3.20.2 Place controller for 1NV-242A (RMWST To B/A Blender Ctrl) in manual.

3.20.3 Increase demand on controller for 1NV-242A (RMWST To B/A Blender Ctrl) to full open.

3.20.4 Open the following valves:

• 1NV-242A (RMWST To B/A Blender Ctrl)

• 1NV-186A (B/A Blender Otlt To VCT Otlt) 3.20.5 Ensure one reactor makeup water pump is in ON.

BOP 3.20.6 WHEN ~ 20 gallons of makeup water have been flushed through the makeup line, close the following valves:

• 1NV-242A (RMWST To B/A Blender Ctrl)

• 1NV-186A (B/A Blender Otlt To VCT Otlt) 3.20.7 Place the following valve control switches in AUTO:

• 1NV-242A (RMWST To B/A Blender Ctrl)

• 1NV-186A (B/A Blender Otlt To VCT Otlt) 3.20.8 Ensure controller for 1NV-242A (RMWST To B/A Blender Ctrl) is set to the value recorded in Step 3.20.1. (R.M.)

3.20.9 Place controller for 1NV-242A (RMWST To B/A Blender Ctrl) in auto.

3.20.10 IF NOT required for current plant operation, place the reactor makeup water pump started in Step 3.20.5 in AUTO.

3.21 IF automatic makeup is desired, perform the following:

3.21.1 IF it is desired to change the blender outlet boron concentration, refer to Enclosure 4.1 (Automatic Makeup).

OR 3.21.2 IF makeup at the previous concentration is acceptable AND BOP the system was previously aligned per Enclosure 4.1 (Automatic Makeup), perform the following:

3.21.2.1 Ensure the controller for 1NV-238A (B/A Xfer Pmp To Blender Ctrl) is set to the value recorded in Step 3.7.

(R.M.)

3.21.2.2 Place the NC MAKEUP MODE SELECT switch in Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 10 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 11 of 70 Event

Description:

Decrease reactor power to 15% and swap feed flow to the CA nozzles Time Position Applicants Actions or Behavior AUTO.

3.21.2.3 Place the NC MAKEUP CONTROL switch to the START position. (R.M.)

3.22 IF initiated in Step 3.10, terminate PZR spray by securing backup BOP heaters per OP/0/A/6200/055 (Miscellaneous Component Operation).

END OF OP/1/A/6150/009 NOTE TO EVALUATOR: The following steps are taken from OP/1/B/6300/001 (Turbine Generator)

Enclosure 4.2 (Load Changing).

3.2 IF decreasing turbine generator load, perform the following:

3.2.1 Ensure the proper reactivity management controls established per AD-OP-ALL-0203 (Reactivity Management). (R.M.)

3.2.2 WHILE decreasing turbine generator load, perform the following:

RO 3.2.2.1 IF CV4 fully closes (92% of full load, 1109 MWe), verify 1SM-33 (Ctrl Vlv #4 Stm Lead Drn) opens.

3.2.2.2 IF CV3 fully closes (65% of full load, 783 MWe), verify 1SM-25 (Ctrl Vlv #3 Stm Lead Drn) opens.

CAUTION: 1. Normal steady-state load change shall be made without exceeding limits shown on Enclosure 4.7 (Generator Operating Limits) and in the Unit One OAC Databook RO Recommended Starting and Loading Curves.

2. Unit One Reactor Operating Data, Section 2.4 shall be referred to for allowable ramp rates.

3.2.3 Decrease turbine generator load by performing the following:

3.2.3.1 Select LOAD RATE and verify it illuminates.

3.2.3.2 Input the desired load rate.

3.2.3.3 Select ENTER and verify LOAD RATE goes dark.

3.2.3.4 Select TARGET and verify it illuminates.

RO 3.2.3.5 Input the desired load target.

3.2.3.6 Select ENTER and verify TARGET goes dark.

3.2.3.7 Verify new load target appears on Target Display.

3.2.3.8 Select GO and verify it illuminates to start load decrease.

3.2.3.9 Coordinate with Secondary Chemistry to adjust S/G blowdown flowrates to obtain maximum blowdown for the appropriate load.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 11 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 12 of 70 Event

Description:

Decrease reactor power to 15% and swap feed flow to the CA nozzles Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The following steps are taken from OP/1/A/6100/002 (Controlling Procedure for Unit Shutdown) Enclosure 4.1 (Unit Shutdown to Mode 3).

These steps will be performed when the CA NOZZLE permissive lights are lit for all the S/Gs. This will occur at approximately 17-18% reactor power.

3.6 WHEN at 15% CF flow (0.56 MPPH) for all S/Gs, transfer feedwater BOP from CF to CA nozzles as follows: (R.M.)

NOTE: Refer to CNSD 3.1.2 (Access to Containment or Annulus and Areas BOP Having High Pressure Steam Relief Devices).

3.6.1 Coordinate with Security to restrict access to the doghouses by CAD Securing the below plant doors while transferring feedwater nozzles as follows:

• CAD Secure AX661 (CAD#512) (Unit 1 Exterior Doghouse BOP Door)

• CAD Secure AX657B (CAD#SO1) (Access to Unit 1 Interior Doghouse Door)

Security notified ____________________________

NOTE: 1. The CA nozzle swap permissive light for each S/G is lit by:

• Median selected CF flow less than 15%.

• Feedwater isolation valve for the S/G being open.

BOP

• CA bypass valve for the S/G being closed.

2. The S/G automatic transfer for CF to CA per Step 3.6.2 be performed in any order.

3.6.2 IF automatic transfer to the CA nozzle(s) is desired, perform the following:

3.6.2.1 For S/G 1A A. IF CA NOZZLE light on S/G 1A NOZZLE SWAP PERMISSIVE is lit, N/A the next substep and continue.

C. Press the CA NOZZLE on S/G 1A NOZZLE SEL.

BOP D. Verify the following:

• 1) 1CA-149 (S/G 1A CF Byp To CA Nozzle) opens.

• 2) 1CF-33 (S/G 1A CF Cont Isol) closes.

• 3) 1CF-90 (S/G 1A CF Cont Isol Byp) opens.

3.6.2.2 For S/G 1B A. IF CA NOZZLE light on S/G 1B NOZZLE SWAP Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 12 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 13 of 70 Event

Description:

Decrease reactor power to 15% and swap feed flow to the CA nozzles Time Position Applicants Actions or Behavior PERMISSIVE is lit, N/A the next substep and continue.

C. Press the CA NOZZLE on S/G 1B NOZZLE SEL.

D. Verify the following:

• 1) 1CA-150 (S/G 1B CF Byp To CA Nozzle) opens.

• 2) 1CF-42 (S/G 1B CF Cont Isol) closes.

• 3) 1CF-89 (S/G 1B CF Cont Isol Byp) opens.

3.6.2.3 For S/G 1C A. IF CA NOZZLE light on S/G 1C NOZZLE SWAP PERMISSIVE is lit, N/A the next substep and continue.

C. Press the CA NOZZLE on S/G 1C NOZZLE SEL.

D. Verify the following:

• 1) 1CA-151 (S/G 1C CF Byp To CA Nozzle) opens.

• 2) 1CF-51 (S/G 1C CF Cont Isol) closes.

• 3) 1CF-88 (S/G 1C CF Cont Isol Byp) opens.

3.6.2.4 For S/G 1D A. IF CA NOZZLE light on S/G 1D NOZZLE SWAP PERMISSIVE is lit, N/A the next substep and continue.

C. Press the CA NOZZLE on S/G 1D NOZZLE SEL.

D. Verify the following:

• 1) 1CA-152 (S/G 1D CF Byp To CA Nozzle) opens.

• 2) 1CF-60 (S/G 1D CF Cont Isol) closes.

• 3) 1CF-87 (S/G 1D CF Cont Isol Byp) opens.

NOTE TO EVALUATOR: Step 3.6.3 is N/A. This ends the required steps for EVENT 1.

Booth Operator will insert Trigger 2 for EVENT 2 at the discretion of the lead evaluator.

END OF EVENT 1 Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 13 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 14 of 70 Event

Description:

1TL-3 Fails closed Time Position Applicants Actions or Behavior EVENT 2 Indications: OAC alarm for Turbine Steam Seal Header Pressure Low 1TLP5000 decreases to 0 PSIG Main Condenser Vacuum begins to decrease NOTE TO EVALUATOR: The crew may make a plant page announcing the entry into AP/1/A/5500/023 (Loss of Condenser Vacuum).

NOTE TO EVALUATOR: The crew may elect to throttle open 1TL-4 (Stm Seal Reg Byp) to restore steam seal header pressure per the OAC alarm response. The following steps are taken from AP/1/A/5500/023.

ALL 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 is Attachment 3 in the back of this guide.

ALL NOTE REFER TO OAC Graphic CMCOND.

2. Verify all of the following conditions exist:

• OAC point C1A1134 (Exhaust Hood A Metal Temp) - LESS THAN 136°F RO/BOP

• OAC point C1A1135 (Exhaust Hood B Metal Temp) - LESS THAN 129°F

• OAC point C1A1129 (Exhaust Hood C Metal Temp) - LESS THAN 124.5°F

• OAC point C1A0484 (Hotwell Temperature) - LESS THAN 134°F.

3. Monitor actual vacuum conditions as follows:

a. Continue to monitor exhaust hood metal and hotwell temperatures.

b. Consult with Station Management as required to determine if actual low condenser vacuum conditions exist.

RO/BOP c. Do not continue in this procedure until at least one of the following exist:

• Exhaust hood metal temperature indicates low vacuum.

• Hotwell temperature indicates low vacuum.

• As directed by Station Management.

NOTE Reducing turbine generator load to stabilize vacuum is only effective when low vacuum is due to reduced RC cooling.

ALL CA system is inoperable when available Condensate Storage System water temperature is greater than 136°F.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 14 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 15 of 70 Event

Description:

1TL-3 Fails closed Time Position Applicants Actions or Behavior

4. Decrease turbine load as required to stabilize vacuum as follows:

RO

a. Verify vacuum loss due to reduced RC cooling.

4.a.RNO. 1) IF AT ANY TIME vacuum loss due to reduced RC cooling, RO THEN RETURN TO Step 4.

2) GO TO Step 5.

5. Verify proper RC System operation as follows:

a. Verify average condenser inlet temperature OAC point C1P1493 (Unit BOP 1 C1 & C2 Average RC Inlet Temp) - LESS THAN 90°F.

b. Verify 1AD-8, B/4 COOLING TOWER BASIN HI/LO LEVEL - DARK.

6. IF AT ANY TIME cause of vacuum loss suspected to be air in-leakage, THEN dispatch operator to start main vacuum pump(s) in ALL preparation for aligning to condensers. REFER TO Enclosure 4 (Placing Main Vacuum Pumps in Service).

7. Verify 1SAP5010 STM PRESS TO CSAE - GREATER THAN 140 BOP PSIG.

8. Verify steam seal header conditions as follows:

a. Ensure at least one of the following valves - OPEN:

• 1TL-2 (Main Stm To Stm Seal Reg)

RO

• 1TL-8 (Aux Stm To Stm Seal Reg).

b. Adjust 1TL-4 (Stm Seal Reg Byp) as required to obtain steam seal header pressure between 4 psig and 6 psig.

c. Verify OAC - AVAILABLE.

NOTE TO EVALUATOR: Once 1TL-4 is throttled, steam seal pressure will increase and main condenser vacuum will increase. The remaining steps in AP/1/A/5500/023 do not need to be completed prior to continuing to the next event.

Booth Operator will insert Trigger 3 for EVENT 3 at the discretion of the lead evaluator.

END OF EVENT 2 Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 15 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 16 of 70 Event

Description:

I/R N35 Loss of Power (Also affects N31)

Time Position Applicants Actions or Behavior EVENT 3 Indications: 1AD-2, C/1 IR/SR NON-OPERATE 1AD-2, C/2 IR/SR AMPLIFIER NON-OPERATE 1AD-2, D/1 SR NON-OPERATE N31 & N35 fail to bottom of scale NOTE TO EVALUATOR: The crew may make a plant page announcing entry into AP/1/A/5500/016 (Malfunction of Nuclear Instrumentation).

NOTE TO EVALUATOR: Both Case I and Case III are applicable and will be entered. Whichever case is entered first will direct transition eventually to the other case.

The following steps are taken from Case I.

1. Verify at least one of the following S/R Channels - OPERABLE:

BOP

• N-31 OR

• N-32 RO 2. Verify unit - IN MODE 2 BELOW P-6.

RO 2.RNO. GO TO Step 5.

BOP 5. Verify unit - IN MODE 6.

BOP 5.RNO. GO TO Step 7.

7. Identify the affected S/R channel(s):

BOP

• N-31 OR

• N-32

8. Verify the following alarms - DARK:

RO

• 1AD-2, D/3 S/R HI FLUX LEVEL AT SHUTDOWN

• 1AD-2, D/4 S/R HI FLUX LEVEL AT SHUTDOWN NOTE 1AD-2, C/4 N/I SYS S/R & I/R TRIP BYPASS will actuate in the ALL following step.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 16 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 17 of 70 Event

Description:

I/R N35 Loss of Power (Also affects N31)

Time Position Applicants Actions or Behavior

9. At the affected S/R drawer, place the LEVEL TRIP switch for the BOP affected channel in BYPASS.

10. Verify the affected S/R channel trip bypass status light (1SI-19) -

RO LIT.

RO 11. Verify 1AD-2, C/4 N/I SYS S/R & I/R TRIP BYPASS - LIT.

NOTE Annunciator 1AD-2 D/2 S/R HI SHUTDOWN FLUX ALM BLOCKED ALL is disabled above P-10 (10% reactor power).

12. Block the high flux at shutdown function as follows:

a. At the affected S/R drawer, ensure the HIGH FLUX AT BOP SHUTDOWN switch for the affected channel in BLOCK.

b. Verify 1AD-2, D/2 S/R HI SHUTDOWN FLUX ALM BLOCKED -

LIT.

13. Align components to operable S/R channel as follows:

• IF Audio Count Rate required to be in service, THEN align Audio BOP Count Rate Channel CHANNEL SELECTOR switch to operable S/R channel.

• Ensure NIS RECORDER aligned to operable S/R channel.

ALL CAUTION Loss of S/R control power below P-6 will result in a reactor trip.

ALL 14. Determine and correct cause of S/R malfunction.

15. Ensure compliance with appropriate Tech Specs:

SRO

• 3.3.1 (Reactor Trip System (RTS) Instrumentation)

• 3.9.2 (Nuclear Instrumentation)

• 3.3.9 (Boron Dilution Mitigation System (BDMS)).

NOTE TO EVALUATOR: Tracking entries would be made at this time for this failure for T.S. 3.3.1 Condition I & K and 3.9.2 Condition A.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 17 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 18 of 70 Event

Description:

I/R N35 Loss of Power (Also affects N31)

Time Position Applicants Actions or Behavior

16. Determine required notifications:

SRO

• REFER TO RP/0/A/5000/001 (Classification of Emergency)

• REFER TO RP/0/B/5000/013 (NRC Notification Requirements).

RO/BOP 17. Notify Reactor Group Engineer of occurrence.

18. WHEN the affected S/R channel is repaired, THEN ensure IAE ALL returns the channel to service.

NOTE IR Channel instrument power failure may cause a SR and IR channel ALL to malfunction.

19. IF IR channel malfunction exists and not previously addressed by SRO this procedure, THEN GO TO Case III (Intermediate Range Malfunction).

NOTE TO EVALUATOR: The following steps are taken from AP/1/A/5500/016 Case III.

RO 1. Verify reactor power - GREATER THAN 10%.

RO 2. Verify 1AD-2, C/3 I/R HI FLUX LEVEL ROD STOP - DARK.

3. Identify affected I/R channel:

RO

• N-35 OR

• N-36.

NOTE 1AD-2, C/4 N/I SYS S/R & I/R TRIP BYPASS will actuate in the ALL following step.

4. At the affected I/R drawer, place the LEVEL TRIP switch for BOP affected channel in BYPASS.

RO 5. Verify the affected I/R channel trip bypass status light (1SI-19) - LIT.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 18 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 19 of 70 Event

Description:

I/R N35 Loss of Power (Also affects N31)

Time Position Applicants Actions or Behavior RO 6. Verify 1AD-2, C/4 N/I SYS S/R & I/R TRIP BYPASS - LIT.

RO 7. Ensure operable I/R channel selected to record on NIS RECORDER.

CAUTION Loss of I/R control power below P-10 will result in reactor trip.

ALL Loss of I/R instrument power below P-10 will result in reactor trip unless affected channel LEVEL TRIP switch in BYPASS.

RO/BOP 8. Determine and correct cause of I/R malfunction.

9. Ensure compliance with Tech Spec 3.3.1 (Reactor Trip System (RTS)

SRO Instrumentation).

NOTE TO EVALUATOR: T.S. 3.3.1 conditions F, G, & H are for reactor powers that are < 10% and will be tracking entries at this time.

10. Determine required notifications:

SRO

• REFER TO RP/0/A/5000/001 (Classification of Emergency)

• REFER TO RP/0/B/5000/013 (NRC Notification Requirements).

RO/BOP 11. Notify Reactor Group Engineer of occurrence.

CAUTION Closing either I/R control power breaker or instrument power ALL breaker with any P/R channel inoperable or in tripped condition may result in a reactor trip on P/R rate trip due to voltage spikes.

12. WHEN the affected I/R channel is repaired, THEN ensure IAE ALL returns the channel to service.

NOTE IR Channel instrument power failure may cause a SR and IR channel ALL to malfunction.

13. IF SR channel malfunction exists and not previously addressed by SRO this procedure, THEN GO TO Case I (Source Range Malfunction).

SRO 14. Determine long term plant status. RETURN TO procedure and step Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 19 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 20 of 70 Event

Description:

I/R N35 Loss of Power (Also affects N31)

Time Position Applicants Actions or Behavior in effect.

Booth Operator will insert Trigger 4 for EVENT 4 at the discretion of the lead evaluator.

END OF EVENT 3 Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 20 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 21 of 70 Event

Description:

FWST Channel 1 fails low Time Position Applicants Actions or Behavior EVENT 4 Indications: 1AD-9, B/4 FWST LO LEVEL 1AD-9, C/8 FWST PRE-LO LEVEL 1AD-9, E/8 FWST LO-LO LEVEL NOTE TO EVALUATOR: This will just be a Tech Spec call by the CRS. The Annunciator responses for the above alarms will direct the CRS to refer to T.S. 3.3.2.

Applicable Tech Specs are 3.3.2 Condition N to place the channel in bypass in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Also a tracking entry would be made for Tech Spec 3.3.3 Condition B.

Booth Operator will insert Trigger 5 for EVENT 5 at the discretion of the lead evaluator.

END OF EVENT 4 Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 21 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 22 of 70 Event

Description:

NCP 1C #1 Seal Leakoff High Flow Time Position Applicants Actions or Behavior EVENT 5 Indications: 1AD-7, C/1 NCP #1 SEAL LEAKOFF HI FLOW OAC Alarm for NC Pump C No.1 seal leakoff flow high (7.5 GPM)

NOTE TO EVALUATOR: The crew may make a plant page announcing entry into AP/1/A/5500/008 Malfunction of Reactor Coolant Pump NOTE TO EVALUATOR: The following steps are taken from AP/1/A/5500/008 Case I (NC Pump Seal Malfunction)

RO/BOP 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 is Attachment 4 in the back of this guide.

2. Verify the following parameters for all NC Pumps:

BOP * #1 seal outlet temperature - LESS THAN 235°F

• Lower bearing temperature - LESS THAN 225°F

• #1 seal delta P - GREATER THAN 200 PSID.

NOTE If seal maintenance has been performed, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of NC pump ALL operation may be required before seals seat and operate properly.

BOP 3. Verify any NC pump #1 seal leakoff flow - GREATER THAN 6 GPM.

4. WHEN NC loop flow indicates the affected NC pump(s) is stopped, BOP THEN close the affected NC pump(s) seal return isolation valve.

REFER TO Enclosure 1 (Foldout Page).

5. Ensure the KC thermal barrier isolation valve for the affected NC pump(s) - OPEN:

BOP

• 1KC-394A (NC Pump 1A Therm Bar Otlt)

• 1KC-364B (NC Pump 1B Therm Bar Otlt)

• 1KC-345A (NC Pump 1C Therm Bar Otlt)

• 1KC-413B (NC Pump 1D Therm Bar Otlt)

BOP 6. Verify #1 seal leakoff flow - LESS THAN 7.5 GPM.

BOP 6.RNO. GO TO Step 12.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 22 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 23 of 70 Event

Description:

NCP 1C #1 Seal Leakoff High Flow Time Position Applicants Actions or Behavior

12. Shutdown the affected NC pump(s) within 5 minutes as follows:

a. Verify Unit - IN MODE 1 OR 2.

b. IF all NC pumps affected, THEN place steam dumps in pressure mode.

c. Trip reactor.

BOP

d. WHEN reactor power less than 5%, THEN perform the following:

1) Trip the affected NC pump(s).

2) Ensure the normal spray valve associated with the tripped NC pump(s) - IN MANUAL AND CLOSED.

e. GO TO EP/1/A/5000/E-0 (Reactor Trip or Safety Injection).

NOTE TO EVALUATOR: Once the candidate depresses the 1C NC pump OFF pushbutton, a 3 minute timer is started. At the end of the 3 minute timer, a S/G tube rupture will occur on 1A S/G (EVENT 6). The crew will have to decide to take EP/1/A/5000/ES-0.1 (Reactor Trip Response) Enclosure 1 (Foldout Page) guidance to initiate safety injection if Pressurizer level cannot be maintained > 4%.

END OF EVENT 5 Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 23 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, & 8 Page 24 of 70 Event

Description:

1A SGTR, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to acuate Time Position Applicants Actions or Behavior EVENTS 6, 7, & 8 Indications: 1RAD-1, B/1 1EMF-33 CSAE EXHAUST HI RAD 1RAD-1, B/4 1EMF-71 S/G A LEAKAGE HI RAD 1RAD-1, E/5 1EMF-74 S/G D LEAKAGE HI RAD Pressurizer level decreasing 1A S/G level increasing in an uncontrolled manner NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

RO/BOP 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 is Attachment 5 in the back of this guide.

2. Verify Reactor Trip:

RO

• All rod bottom lights - LIT

• All reactor trip and bypass breakers - OPEN

• I/R power - DECREASING.

3. Verify Turbine Trip:

RO

• All turbine stop valves - CLOSED.

BOP 4. Verify 1ETA and 1ETB - ENERGIZED.

5. Verify S/I actuated:

BOP

a. SAFETY INJECTION ACTUATED status light (1SI-13) - LIT.

5.a.RNO. Perform the following:

1) Verify conditions requiring S/I:

• Pzr pressure - LESS THAN 1845 PSIG OR

• Containment pressure - GREATER THAN 1.2 PSIG.

BOP

2) IF S/I required, THEN initiate S/I.

3) IF S/I not required, THEN concurrently:

• Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees).

• GO TO EP/1/A/5000/ES-0.1 (Reactor Trip Response).

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 24 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, & 8 Page 25 of 70 Event

Description:

1A SGTR, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to acuate Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/ES-0.1 (Reactor Trip Response). Crew should notice indications of 1A S/G tube rupture after the first few steps of ES-0.1, and should decide to initiate Safety Injection and return to E-0.

NOTE TO EVALUATOR: 1RAD-1, B/1 1EMF-33 CSAE EXHAUST HI RAD will come into alarm 3 minutes following the trip of 1C NCP.

NOTE TO EVALUATOR: Following this alarm, Steam Generator Tube Leakage will be > than Tech Spec allowable, and Tech Spec 3.4.13 condition B is applicable.

This Tech Spec call will be determined through a follow up question following scenario completion.

RO/BOP 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 is Attachment 6 in the back of this guide.

2. Verify the following:

BOP

• All 6.9 KV busses - ENERGIZED.

• VI pressure - GREATER THAN 85 PSIG.

3. Announce Unit 1 Reactor Trip, non-essential personnel stay out of RO Unit 1 Turbine bldg.

NOTE Enclosure 2 (NC Temperature Control) shall remain in effect until RO subsequent steps provide alternative NC temperature control guidance.

4. Control NC temperature. REFER TO Enclosure 2 (NC Temperature RO Control).

NOTE TO EVALUATOR: Enclosure 2 is Attachment 7 in the back of this guide.

5. Determine required notifications:

SRO

• REFER TO RP/0/A/5000/001 (Classification of Emergency)

• REFER TO RP/0/B/5000/013 (NRC Notification Requirements)

6. Verify Main Generator as follows:

a. Verify turbine generator megawatt output - LESS THAN OR EQUAL TO ZERO MW.

RO

b. Ensure the following breakers and MODs - OPEN:

• MOD 1BG and 1BT

• MOD 1AG and 1AT Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 25 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, & 8 Page 26 of 70 Event

Description:

1A SGTR, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to acuate Time Position Applicants Actions or Behavior

• Generator Breakers 1A and 1B.

c. Ensure main generator EXCITATION - OFF.

d. Verify MAN/AUTO REG select switch MAN mode light - LIT.

7. Verify feedwater status as follows:

RO a. T-Avg - LESS THAN 564°F.

b. All Feedwater Isolation status lights (1SI-5) - LIT.

7.b.RNO. Perform the following:

1) Initiate Feedwater Isolation.

RO

2) IF any status light remains dark, THEN perform Enclosure 3 (Closure of Feedwater Isolation Valves).

NOTE TO EVALUATOR: If the crew makes it to this step prior to initiating safety injection, then this will satisfy mitigating EVENT 8. Otherwise it will be done per EP/1/A/5000/E-0.

END OF EVENT 8 Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 26 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, & 8 Page 27 of 70 Event

Description:

1A SGTR, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to acuate Time Position Applicants Actions or Behavior EVENT 6, 7, & 8 NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/E-0 following the crews decision to initiate safety injection.

RO/BOP 1. Monitor Enclosure 1 (Foldout Page).

2. Verify Reactor Trip:

RO

• All rod bottom lights - LIT

• All reactor trip and bypass breakers - OPEN

• I/R power - DECREASING.

3. Verify Turbine Trip:

RO

• All turbine stop valves - CLOSED.

BOP 4. Verify 1ETA and 1ETB - ENERGIZED.

5. Verify S/I actuated:

BOP a. SAFETY INJECTION ACTUATED status light (1SI-13) - LIT.

b. Both E/S load sequencer actuated status lights (1SI-14) - LIT.

RO 6. Announce Unit 1 Safety Injection.

7. Determine required notifications:

SRO

• REFER TO RP/0/A/5000/001 (Classification of Emergency)

• REFER TO RP/0/B/5000/013 (NRC Notification Requirements)

RO 8. Verify all Feedwater Isolation status lights (1SI-5) - LIT.

8.RNO. Perform the following:

a. Initiate Feedwater Isolation.

RO

b. IF proper status light indication not obtained, THEN CLOSE valves.

END OF EVENT 8 Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 27 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, & 8 Page 28 of 70 Event

Description:

1A SGTR, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to acuate Time Position Applicants Actions or Behavior

9. Verify Phase A Containment Isolation status as follows:

BOP

a. Phase A RESET lights - DARK BOP 9.a.RNO. Initiate Phase A Isolation.

END OF EVENT 7 BOP 9.b. Monitor Light Panel Group 5 St lights on energized train(s) - LIT

10. Verify proper Phase B actuation as follows:

a. Verify Containment pressure - HAS REMAINED LESS THAN 3 BOP PSIG.

b. IF AT ANY TIME containment pressure exceeds 3 PSIG while in this procedure, THEN perform Step 10.a.

11. Verify proper CA pump status as follows:

RO a. Motor driven CA pumps - ON.

b. 3 S/G N/R levels - GREATER THAN 11%.

12. Verify all of the following S/I pumps - ON:

BOP

• NV pumps

• ND pumps

• NI pumps.

BOP 13. Verify all KC pumps - ON.

BOP 14. Verify all Unit 1 and Unit 2 RN pumps - ON.

15. Verify proper ventilation systems operation as follows:

BOP

• REFER TO Enclosure 2 (Ventilation System Verification).

• Notify Unit 2 operator to perform Enclosure 3 (Opposite Unit Ventilation Verification).

NOTE TO EVALUATOR: Enclosure 2 is Attachment 8 in the back of this guide.

RO 16. Verify all S/G pressures - GREATER THAN 775 PSIG.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 28 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, & 8 Page 29 of 70 Event

Description:

1A SGTR, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to acuate Time Position Applicants Actions or Behavior

17. Verify proper S/I flow as follows:

BOP a. NV S/I FLOW - INDICATING FLOW.

b. NC pressure - LESS THAN 1620 PSIG.

17.b.RNO. Perform the following:

1) Ensure ND pump miniflow valve on operating ND pump(s) -

OPEN.

BOP

2) IF ND pump miniflow valve(s) cannot be opened, THEN perform the following for affected train(s):

3) GO TO Step 18.

18. WHEN time and manpower permit (within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of even), THEN monitor Spent Fuel Pool level and temperature. REFER TO BOP EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring).

NOTE TO EVALUATOR: G-1 Enclosure 1 is Attachment 10 in the back of this guide.

19. Control S/G levels as follows:

a. Verify total CA flow - GREATER THAN 450 GPM.

RO b. WHEN each S/G N/R level greater than 11% (29% ACC), THEN control feed flow to maintain that S/G N/R level between 11% (29%

ACC) and 50%.

RO 20. Verify all CA isolation valves - OPEN.

21. Verify S/I equipment status based on monitor light panel - IN BOP PROPER ALIGNMENT.

NOTE TO EVALUATOR: 1A CA pump and 1A ND pump will not be aligned due to being tagged out.

NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until RO subsequent procedures provide alternative NC temperature control guidance.

22. Control NC temperature. REFER TO Enclosure 4 (NC Temperature RO Control).

NOTE TO EVALUATOR: Enclosure 4 is Attachment 9 in the back of this guide.

23. Verify Pzr PORV and Pzr Spray Valve status as follows:

BOP

a. All Pzr PORVs - CLOSED.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 29 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, & 8 Page 30 of 70 Event

Description:

1A SGTR, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to acuate Time Position Applicants Actions or Behavior

b. Normal Pzr spray valves - CLOSED.

c. At least one Pzr PORV isolation valve - OPEN.

24. Verify NC subcooling based on core exit T/Cs - GREATER THAN RO 0°F.

25. Verify main steamlines intact:

RO

• All S/G pressures - STABLE OR INCREASING

• ALL S/Gs - PRESSURIZED.

26. Verify S/G tubes intact as follows:

• Verify the following EMF trip 1 lights - DARK:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-26 (Steamline 1A)

BOP

• 1EMF-27 (Steamline 1B)

• 1EMF-28 (Steamline 1C)

• 1EMF-29 (Steamline 1D)

• All S/G levels - STABLE OR INCREASING IN A CONTROLLED MANNER.

26.RNO. IF any EMF trip 1 light lit OR any S/G level increasing in an uncontrolled manner, THEN concurrently:

ALL

• Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees).

• GO TO EP/1/A/5000/E-3 (Steam Generator Tube Rupture).

NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/E-3 (Steam Generator Tube Rupture).

ALL 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 is Attachment 11 in the back of this guide.

2. Identify ruptured S/G(s) as follows:

• S/G level - INCREASING IN AN UNCONTROLLED MANNER.

OR

• Chemistry or RP has determined ruptured S/G\

RO/BOP OR

• Any of the following EMF trip 1 lights - LIT:

• 1EMF-26 (Steamline 1A)

• 1EMF-27 (Steamline 1B)

• 1EMF-28 (Steamline 1C)

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 30 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, & 8 Page 31 of 70 Event

Description:

1A SGTR, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to acuate Time Position Applicants Actions or Behavior

• 1EMF-29 (Steamline 1D)

3. Verify at least one intact S/G - AVAILABLE FOR NC SYSTEM BOP COOLDOWN.

4. Isolate flow from ruptured S/G(s) as follows:

a. Verify all ruptured S/G(s) PORV - CLOSED.

b. Verify S/G(s) 1B and 1C - INTACT.

c. Isolate blowdown and steam drain on all ruptured S/G(s) as follows:

Critical

• S/G 1A:

RO task #1 1) CLOSE 1SM-77A (S/G 1A Otlt Hdr Blwdn C/V).

2) Verify the following blowdown isolation valves - CLOSED:

a) 1BB-56A (S/G 1A Blwdn Cont Isol Insd).

b) 1BB-148B (S/G 1A Blwdn Cont Isol Byp).

c) 1BB-57B (S/G 1A Bldwn Cont Isol Otsd).

5. CLOSE the following valves on all ruptured S/G(s):

Critical RO

• MSIV task #1

• MSIV bypass valve.

6. Control ruptured S/G(s) N/R level as follows:

a. Verify ruptured S/G(s) N/R level - GREATER THAN 11% (29% ACC).

b. Isolate feed flow to all ruptured S/G(s) as follows:

Critical

• S/G 1A:

RO task #1 1) CLOSE 1CA-62A (CA Pmp A Disch To S/G 1A Isol).

2) CLOSE 1CA-66B (CA Pmp 1 Disch To S/G 1A Isol).

c. IF AT ANY TIME ruptured S/G(s) N/R level is less than 11% (29%

ACC), THEN perform Step 6.

RO 7. Verify all ruptured S/G(s) pressure - GREATER THAN 320 PSIG.

BOP 8. Verify any NC pump - ON.

BOP 9. Verify Pzr pressure - GREATER THAN 1955 PSIG.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 31 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, & 8 Page 32 of 70 Event

Description:

1A SGTR, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to acuate Time Position Applicants Actions or Behavior NOTE NC pump trip criteria based on NC subcooling does not apply after starting a controlled cooldown.

After low steamline pressure main steam isolation signal is blocked, ALL maintaining steam pressure negative rate less than 2 PSIG per second will prevent a Main Steam Isolation.

OAC graphic SMRATES to monitor S/G pressure rates can be accessed via a hot button in the center of the SM graphic.

10. Initiate NC System cooldown as follows:

a. Determine required core exit temperature based on lowest ruptured S/G pressure from table below:

LOWEST RUPTURED S/G REQUIRED PRESSURE (PSIG) CORE EXIT T/Cs (°F)

EQUAL TO OR GREATER 532 (512 ACC)

THAN 1200 1100 - 1199 520 (501 ACC) 1000 - 1099 507 (489 ACC)

RO b. Ensure ruptured S/G(s) isolated as follows:

1) Verify the following valves on all ruptured S/G(s) - CLOSED:

• MSIV

• MSIV bypass valves.

2) Verify S/G PORV on ruptured S/G(s) - CLOSED OR ISOLATED.

3) IF S/G 1B OR 1C ruptured, THEN verify one of the following CAPT steam supply valves - CLOSED:

c. Verify condenser is available as follows:

• C-9 COND AVAILABLE FOR STM DUMP status light (1SI-18)

- LIT

• MSIV on intact S/G(s) - OPEN

d. Verify steam dumps - IN PRESSURE MODE.

10.d.RNO. Place steam dumps in pressure mode as follows:

1) Place STM DUMP CTRL slim station in manual.

RO 2) Adjust STM DUMP CTRL slim station output to match %

STM DUMP DEMAND (1SMP5211).

3) WHEN output on STM DUMP CTRL slim station equal to

% STM DUMP DEMAND (1SMP5211), THEN place steam Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 32 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, & 8 Page 33 of 70 Event

Description:

1A SGTR, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to acuate Time Position Applicants Actions or Behavior dumps in pressure mode.

e. WHEN P-12 LO-LO TAVG status light (1SI-18) lit, THEN place steam dump interlock bypass switches in BYP INTLK.

Critical RO f. Dump steam to condenser from intact S/G(s) at maximum rate while task #2 attempting to avoid a Main Steam Isolation.

g. Verify main steam isolation blocked status lights (1SI-13) - LIT.

10.g.RNO. Perform the following:

1) Depressurize NC System to less than 1955 PSIG using one of the following:

• Pzr spray OR

• Pzr PORV BOP

2) WHEN P-11 PZR S/I BLOCK PERMISSIVE status light (1SI-18) lit, THEN perform the following:

a) Depress ECCS steam pressure BLOCK pushbuttons.

b) Verify main steam isolation blocked status lights (1SI-13)

- LIT.

3) Maintain NC pressure less than 1955 PSIG.

Critical 10.h. WHEN core exit T/Cs less than required temperature, THEN stabilize RO task #2 core exit T/Cs less than required temperature.

11. Control intact S/G levels as follows:

a. Verify N/R level in all intact S/Gs - GREATER THAN 11% (29%

BOP ACC).

b. THROTTLE feed flow to maintain all intact S/G N/R levels between 16% (29% ACC) and 50%.

12. Verify Pzr PORV and isolation valve status as follows:

a. Power to all Pzr PORV isolation valves - AVAILABLE.

b. All Pzr PORVs - CLOSED.

BOP c. At least one Pzr PORV isolation valve - OPEN.

d. IF AT ANY TIME a Pzr PORV opens due to high pressure, WHEN Pzr pressure decreases to less than 2315 PSIG, ensure valve closes or is isolated.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 33 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, & 8 Page 34 of 70 Event

Description:

1A SGTR, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to acuate Time Position Applicants Actions or Behavior

13. Reset the following:

a. ECCS

b. D/G load sequencers BOP c. Phase A

d. Phase B.

e. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on.

14. Establish VI to Containment as follows:

BOP

• Ensure 1VI-77B (VI Cont Isol) - OPEN.

• Verify VI pressure - GREATER THAN 85 PSIG.

15. Determine if ND pumps should be stopped:

a. Any ND pump - ON.

b. Any running ND pump suction - ALIGNED TO FWST.

BOP c. NC pressure - GREATER THAN 285 PSIG.

d. Stop all ND pump(s) with suction aligned to FWST.

e. IF AT ANY TIME NC pressure decreases to less than 285 PSIG in an uncontrolled manner, THEN restart ND pumps.

ALL 16. Verify ruptured S/G(s) - IDENTIFIED.

17. Verify if NC System cooldown should be stopped:

Critical a. Verify core exit T/Cs - LESS THAN REQUIRED TEMPERATURE.

RO task #2 b. Stop NC System cooldown.

c. Stabilize core exit T/Cs - LESS THAN REQUIRED TEMPERATURE.

18. Verify ruptured S/G(s) pressure is under operator control as follows:

RO a. All ruptured S/G(s) pressure - STABLE OR INCREASING.

b. IF AT ANY TIME ruptured S/G(s) pressure is decreasing while in this procedure, THEN perform Step 18.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 34 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, & 8 Page 35 of 70 Event

Description:

1A SGTR, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to acuate Time Position Applicants Actions or Behavior

19. Verify NC subcooling based on core exit T/Cs - GREATER THAN RO 20°F.

20. Depressurize NC System using PZR Spray as follows:

a. Verify normal Pzr spray flow - AVAILABLE.

b. Initiate NC depressurization using maximum available spray.

c. IF AT ANY TIME during this step one of the following conditions exists, THEN GO TO Step 21:

• Spray valves not effective in reducing NC pressure OR

• Ruptured S/G(s) NR level approaching 83% (75% ACC).

d. Do not continue until at least one of the following conditions satisfied:

• Both of the following:

• NC pressure - LESS THAN RUPTURED S/G(s) PRESSURE Critical

• Pzr level - GREATER THAN 11% (30% ACC)

BOP task #3 OR

• Both of the following:

• NC pressure - WITHIN 300 PSIG OF RUPTURED S/G(s)

PRESSURE

• Pzr level - GREATER THAN 41% (50% ACC)

OR

• Pzr level - GREATER THAN 68% (50% ACC)

OR

• NC subcooling based on core exit T/Cs - LESS THAN 0°F

e. CLOSE normal Pzr spray valves.

f. Verify 1NV-37A (NV Supply To Pzr Aux Spray) - CLOSED

g. Observe Caution prior to Step 23 and GO TO Step 23.

CAUTION S/I must be terminated when termination criteria are satisfied to ALL prevent overfilling ruptured S/G(s).

23. Verify S/I termination criteria as follows:

a. NC subcooling based on core exit T/Cs - GREATER THAN 0°F.

b. Verify secondary heat sink as follows:

• N/R level in at least one intact S/G - GREATER THAN 11%

RO/BOP (29% ACC)

OR

• Total feed flow available to S/G(s) - GREATER THAN 450 GPM.

c. NC pressure - STABLE OR INCREASING.

d. Pzr level - GREATER THAN 11% (30% ACC).

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 35 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, & 8 Page 36 of 70 Event

Description:

1A SGTR, both trains of Phase A containment isolation fail to actuate, both trains of CF Isolation fail to acuate Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: At this point all critical tasks for the scenario have been satisfied. It is not required to have the crew complete the S/I termination. At the discretion of the lead evaluator, the scenario can be terminated by having the booth operator take the simulator to FREEZE.

END OF EVENTS 6, 7, & 8 END OF SCENARIO 2 Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 36 of 70

Catawba Nuclear Station NRC Exam May 2015 Attachment List Scenario 2 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - AP/1/A/5500/023 Enclosure 1 (Foldout Page) rev 22 ATTACHMENT 4 - AP/1/A/5500/008 Enclosure 1 (Foldout Page) rev 18 ATTACHMENT 5 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page) rev 42 ATTACHMENT 6 - EP/1/A/5000/ES-0.1 Enclosure 1 (Foldout Page) rev 40 ATTACHMENT 7 - EP/1/A/5000/ES-0.1 Enclosure 2 (NC Temperature Control) rev 40 ATTACHMENT 8 - EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification) rev 42 ATTACHMENT 9 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control) rev 42 ATTACHMENT 10 - EP/1/A/5000/G-1 Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring) rev 9 ATTACHMENT 11 - EP/1/A/5000/E-3 Enclosure 1 (Foldout Page) rev 43 Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 37 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK Isolate Feedwater into and steam flow from ruptured S/G 1

before a transition to ECA-3.1 occurs.

Establish/maintain an RCS temperature so that transition from E-3 does not occur because the RCS temperature is in either of the following conditions:

2

• Too high to maintain the minimum required subcooling

• Below the RCS temperature that causes an extreme (red-path) or a severe (orange path) challenge to the subcriticality and/or integrity status tree.

Depressurize RCS to meet SI termination criteria before water 3

release occurs from the ruptured S/G PORV or safety.

Comments:

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 38 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 17% EOL 385 PPM per OAC Controlling Procedure

• OP/1/A/6100/002 (Controlling Procedure for Unit Shutdown), Enclosure 4.1 (Unit Shutdown to Mode 3). The steps up to step 3.5 are complete.

Other Information Needed to Assume the Shift

• Unit 1 is at 17% power. 1A CA pump has been tagged out for annual PMs. 1A CA pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 1A ND pump is tagged out for performance of electrical testing. 1A ND pump has been inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and is expected to be returned to service in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Direction for the crew is for the RO to decrease reactor power to ~ 15% power at a rate of 10%/hour and for the BOP to swap feedwater flow to the CA nozzles per OP/1/A/6100/002(Controlling Procedure For Unit Shutdown) Enclosure 4.1 (Unit Shutdown To Mode 3) Step 3.6.

AOs Available Seven AOs are available as listed on the status board METEOROLOGICAL CONDITIONS

• Upper wind direction = 315 degrees, speed = 3 mph

• Lower wind direction = 315 degrees, speed = 4.5 mph

• Forecast calls for clear skies over the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 39 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 3 Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 40 of 70

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Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 4 Appendix D Catawba NRC Exam May 2015 Scenario 2 NUREG 1021 Revision 9 Page 42 of 70

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Catawba Nuclear Station NRC Exam May 2015 NRC INITIAL LICENSE EXAM SCENARIO # 3 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 1 of 70

Catawba Nuclear Station NRC Exam May 2015 Facility: Catawba NRC Exam 2015 Scenario No.: 3 Op Test No.: 2015301 Examiners: Operators: SRO RO BOP Initial Conditions: IC#162; Unit 1 is just below POAH, MOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance.

Turnover: Unit 1 is at 7eº² % power, MOL. Unit 2 is at 100%. 1D RC pump is tagged out for preventative maintenance. 1B NI (Safety Injection) Pump is tagged out for preventative maintenance. Power increase to 15% is in progress in preparation for placing the main turbine on line. The crew is to shift operating KC (Component Cooling) pumps by starting the 1B2 KC pump and securing the 1B1 KC pump and then increase power to 1% by withdrawing control rods. LCO 3.0.4.(b) has been assessed for the 1B NI Pump inoperability and Mode change has been authorized.

Event Malf. No. Event Event No. Type* Description 1 --- N-BOP Shift operating Component Cooling pumps.

N-SRO 2 --- R-RO Withdraw control rods to increase reactor power to 1%

N-SRO 3 RN001A C-BOP RN (Nuclear Service Water) Pit A Screen Hi D/P. AP/20 C-SRO FWP015C C-RO 4 CA004B C-SRO 1B CF (Main Feed) Pump trips, 1B CA (AFW Pump fails to start) AP/06 TS-SRO C-BOP 5 NV066 C-SRO 1A NV pump trips. Requires manual start of 1B NV pump. AP/12 TS-SRO 6 NC008F M-ALL PZR PORV fails open. Manual closure attempt is unsuccessful. Manual NC009F block valve will not close.

7 NI001A C-BOP 1A NI (Safety Injection) Pump fails to start in AUTO.

C-SRO 8 CA022A C-RO 1CA-152 fails to close on Feedwater Isolation

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 2 of 70

Catawba Nuclear Station NRC Exam May 2015 Scenario 3 - Summary Initial Condition Unit 1 is just below POAH, MOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance.

Turnover:

Unit 1 just below POAH, MOL. Unit 2 at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump tagged out. The crew is to shift operating KC (Component Cooling) pumps by starting the 1B2 KC pump and securing the 1B1 KC pump and then increase power to 1% by withdrawing control rods. LCO 3.0.4.(b) has been assessed for the 1B NI Pump inoperability and Mode change has been authorized.

Event 1 Shift operating Component Cooling pumps per OP/1/A/6400/005 (Component Cooling System), Enclosure 4.17 (Shifting KC Pumps).

Event 2 Raise reactor power to 1%. Crew will use rods since unit is below POAH.

Event 3 A train RN intake screen will clog. AP/0/A/5500/020 (Loss of Nuclear Service Water) Case 2 for loss of pit level will be entered. No Tech Specs will be applicable for this failure.

Verifiable Action - BOP will manually align A intake to the Standby Nuclear Service Water Pond and start RN pumps as required.

Event 4 1B Main Feedwater Pump trips, along with the failure of the 1B AFW pump to auto start. AP/06 Case I entry. A TS evaluation required due to failure of the 1B AFW pump to start.

Verifiable Action - OATC will be required to manually start CAPT#1 to maintain S/G levels.

Event 5 1A NV Pump (Charging) trips. BOP manually starts the 1B NV pump to restore charging and letdown.

AP/12 (Loss of Charging or Letdown) will be entered. TS evaluation required.

Verifiable Action - BOP will be required to start 1B NV pump and restore letdown per AP/12.

Event 6 1NC-36B (PZR PORV) fails open. RO attempts manual closure of the PORV. This will not be successful.

AP/11 (Pressurizer Pressure Anomalies) entry. This is the major event because the PZR PORV cannot be closed, nor will the manual block isolation close. Recognizing a LOCA, the crew will determine that the reactor must be tripped.

Verifiable Action - OATC will trip Unit 1 reactor and the BOP will initiate S/I on both trains.

Event 7 1A NI (Safety Injection) Pump fails to auto start on the SI signal. BOP manually starts to establish intermediate head injection flow.

Verifiable Action - BOP will be required to reset B train ECCS and D/G load sequencer and start 1B NI pump manually.

Event 8 1CA-152 (S/G 1D CF BYP TO CA NOZZLE) fails to close on the feedwater isolation. RO manually closes the valve.

Verifiable Action - OATC will be required to manually close 1CA-152.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 3 of 70

Catawba Nuclear Station NRC Exam May 2015 Scenario 3 - Summary (cont.)

Critical Task 1 - Establish flow from at least one intermediate head ECCS pump prior to transition from E-0.

Critical Task 2 - Trip NC pumps on loss of subcooling with S/I flow verified per E-0 within 5 minutes of criteria met.

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5-8) 6

2. Malfunctions after EOP entry (1-2) 2

3. Abnormal events (2-4) 4

4. Major transients (1-2) 1

5. EOPs entered/requiring substantive actions (1-2) 1

6. EOP contingencies requiring substantive actions (0-2) 0

7. Critical tasks (2-3) 2 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 4 of 70

Catawba Nuclear Station NRC Exam May 2015 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC # 162 START TIME:__________

Instructor Action Delete Trigger Final Delay Ramp Event In MAL-RN001A (RN PIT SCREEN A HI 3 97 :10 3 D/P)

OVR-FWP015C (CFPT 1B 4 ON 4 TRIP_RESET TRIP PB)

MAL-CA004B FAILURE OF CA N/A BOTH 4 PUMP B TO START)

LOA-NV066 (RACKOUT NV PMP RACK-5 5 1A) OUT VLV-NC009F (NC36B PZR PORV 6 1 6 FAIL TO POSITION)

VLV-NC008F (NC35B PORV ISOL N/A 1 6 VLV FAIL TO POSITION)

N/A MAL-NI001A (NI PUMP A FAILURE) AUTO 7 VLV-CA022A (CA152 S/G MAIN CF N/A BYP TO CA NOZ FAIL AUTO ACTIVE 8 ACTIONS)

RACK-N/A LOA-NI004 (RACKOUT NI PMP 1B)

OUT N/A LOA-RC068 (RACKOUT RC PMP RACK-1D) OUT ANN-AD11-B03 (TRANSFORMER A N/A ON TROUBLE)

N/A ANN-AD11-E03 (TRANSFORMER B ON TROUBLE)

Place red collar on the 1B NI Pump.

Place red collar on the 1D RC Pump.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 5 of 70

Catawba Nuclear Station NRC Exam May 2015

2. SIMULATOR BRIEFING 2.1 Control Room Assignments:

Position Name CRS RO BOP 2.2 Give a copy of Attachment 2 (Shift Turnover Information) to the CRS.

3. EXERCISE PRESENTATION 3.1 Familiarization Period A. Allow examinees time to familiarize themselves with Control Board alignments.

3.2 Scenario EVENT 1, Shift KC Pumps BOOTH INSTRUCTOR ACTION IF Operator dispatched to perform a pre-operational pump checkout, REPORT that the pump looks good for start.

BOOTH INSTRUCTOR ACTION WHEN one minute has elapsed from the start of the 1B2 KC Pump, CALL the control room and inform them that the 1B2 KC Pump looks good for a continuous run.

3.3 Scenario EVENT 2, Increase reactor power to 1%

3.4 Scenario EVENT 3, RN Pit A Screen Hi D/P BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause the RN Pit A Screen Hi D/P.

BOOTH INSTRUCTOR ACTION IF contacted as Unit 2 to determine whether 2AD-12 B/1 & B/4 are dark, REPORT that both annunciators are dark.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with RN Pit A, REPEAT back the information.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 6 of 70

Catawba Nuclear Station NRC Exam May 2015 BOOTH INSTRUCTOR ACTION IF an Operator and/or Maintenance are dispatched to investigate RN Pit A, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Operator dispatched to check out the RN pump that was started, REPEAT the information.

After 10 minutes, contact the control room and REPORT that the pump started looks good for a continuous run.

BOOTH INSTRUCTOR ACTION IF Environmental Chemistry is contacted about the pump swap, REPEAT back the information.

3.6 Scenario EVENT 4, 1B CFPT trips, 1B CA Pump fails to start BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 4 to cause the 1B CFPT to trip.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with 1B CFPT, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an Operator and/or Maintenance are dispatched to investigate the 1B CA pump and/or breaker, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with 1B CA Pump, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an Operator is dispatched to perform the alarm response for the 1B CFPT, REPEAT back the information.

3.7 Scenario EVENT 5, 1A NV Charging Pump trips BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to cause the 1A NV Charging Pump to trip.

BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance are dispatched to investigate the 1A NV Pump and/or breaker, Repeat back the information.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 7 of 70

Catawba Nuclear Station NRC Exam May 2015 BOOTH INSTRUCTOR ACTION IF an Operator dispatched to breaker and/or pump, after 10 minutes REPORT: No relays are present on the breaker and no abnormal conditions are noted at the pump.

BOOTH INSTRUCTOR ACTION IF AO dispatched to check the 1B NV Pump, after 5 minutes REPORT: The 1B NV Pump looks good for continuous run.

BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with 1A NV Pump, REPEAT back the information.

3.8 Scenario EVENTS 6, 7, AND 8 1NC-36B fails open, 1NC-35B will not close, 1A NI Pump will not start on Safety Injection, 1CA-152 (S/G 1D CF BYB TO CA NOZZLE) fails to close on feedwater isolation.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 6 to cause the 1NC-36B to fail open.

BOOTH INSTRUCTOR ACTION IF SWM is contacted to investigate 1NC-36B and/or 1NC-35B, REPEAT back the order.

BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance are dispatched to investigate the 1A NI Pump and/or breaker, REPEAT the order.

BOOTH INSTRUCTOR ACTION IF Operator is dispatched to secure all ice condenser air handling units and place Hydrogen Analyzers in service, REPEAT the order.

After 10 minutes, REPORT that ice condenser air handling units are secured and the hydrogen analyzers are in service.

BOOTH INSTRUCTOR ACTION IF Secondary Chemistry is notified to sample all S/Gs for activity, REPEAT the order.

After 20 minutes, contact the control room and REPORT that S/Gs show no signs of abnormal activity.

BOOTH INSTRUCTOR ACTION IF RP is notified to frisk all cation columns for activity, REPEAT the order.

After 10 minutes, contact the control room and REPORT that S/Gs show no signs of abnormal activity.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 8 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 9 of 70 Event

Description:

Shift operating KC (Component Cooling) Pumps.

Time Position Applicants Actions or Behavior EVENT 1 NOTE TO EVALUATOR: Crew begins by shifting the operating Component Cooling pumps per OP/1/A/6400/005 (Component Cooling System),

Enclosure 4.17 (Shifting KC Pumps).

NOTE TO EVALUATOR: The crew may have a Focus Brief and then make a plant page announcing the start of the 1B2 KC Pump.

BOP Start 1B2 KC Pump BOP Secure 1B1 KC Pump NOTE TO EVALUATOR: The following actions are from OP/1/A/6400/005 (Component Cooling System), Enclosure 4.17 (Shifting KC Pumps).

3.2 IF shifting KC Train 1B pumps, perform the following:

3.2.1 Start the idle KC Train 1B pump:

BOP

• "KC PUMP B1" OR

• "KC PUMP B2" NOTE: 1KC-C40B (Train B Miniflow Isol) may open during performance of the next step.

3.2.2 Adjust the following flow controllers on 1MC11 to zero gpm flow:

BOP

• 1KC-149 (KF Hx 1A Cool Wtr Otlt)

• 1KC-156 (KF Hx 1B Cool Wtr Otlt) 3.2.3 Stop the desired KC Train 1B pump:

• "KC PUMP B1" BOP OR

• "KC PUMP B2" 3.2.4 IF KC Train 1B flow approaches 5700 gpm while BOP performing the next step, ensure 1KC-C40B (Train B Miniflow Isol) is closed.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 9 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 10 of 70 Event

Description:

Shift operating KC (Component Cooling) Pumps.

Time Position Applicants Actions or Behavior 3.2.5 Perform the following for the KF cooling loops that are in service:

• IF 1A KF Cooling Loop is in service, adjust 1KC-149 (KF Hx 1A Cool Wtr Otlt) flow controller on 1MC11 to 3000 gpm or as necessary to maintain Spent Fuel BOP Pool temperature < 125°F.

• IF 1B KF Cooling Loop is in service, adjust 1KC-156 (KF Hx 1B Cool Wtr Otlt) flow controller on 1MC11 to 3000 gpm or as necessary to maintain Spent Fuel Pool temperature < 125°F.

END OF EVENT 1 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 10 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 2 Page 11 of 70 Event

Description:

Increase reactor power to 1%

Time Position Applicants Actions or Behavior EVENT 2 RO Withdraw control rods to increase reactor power.

NOTE TO EVALUATOR: The following actions are from OP/1/A/6100/001 (Controlling Procedure for Unit Startup), Enclosure 4.1 (Unit Startup).

NOTE: 1. Control rod withdrawal shall NOT exceed the temporary rod withdrawal limits specified in Unit One R.O.D. Section 2.3.

2. Refer to Unit One R.O.D. Section 2.4 for the rate at which reactor power can be changed.

3. The throttling of a S/G bypass reg valve affects the other S/G bypass reg valves. Therefore, SM/CF P needs to be monitored as the unit approaches POAH.

4. If NC boron concentration is greater than 1000 ppmB, T-AVG control may be very sensitive above the POAH due to a positive MTC. Unit One R.O.D. Section 5.10 provides MTC at the current conditions.

5. When approaching the beginning of the Power Range NI indication (.1% on the PR), a startup rate of < 0.2 dpm is required. The < .2 dpm rate shall NOT be exceeded, except when performing PT/0/A/4150/001 J (Zero Power Physics Testing), until the turbine is placed on line. (AD-OP-ALL-0203 (Reactivity Management)). (R.M.)

6. Per SOER 07-01 (Reactivity Management) it is recommended that Plant Operators monitor multiple indications such as Thermal Power Best Estimate, Nuclear Instrumentation, Steam Pressure, T's, CF Flowrate, and Turbine Load when making at power reactivity changes. (R.M.)

RO 3.181 Increase reactor power to 1%. (R.M.)

END OF EVENT 2 Booth operator can insert Trigger 3 for EVENT 3 at the discretion of the lead examiner.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 11 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 12 of 70 Event

Description:

RN Pit Screen A Hi D/P Time Position Applicants Actions or Behavior EVENT 3 Indications: 1AD-12, B/2 RN PIT A SCREEN HI D/P OAC PT. C1A1006 RN PIT A SCREEN DIFF LEVEL NOTE TO EVALUATOR: Annunciator response for 1AD-12, B/2 is Attachment 4 in the back of this guide.

BOP Recognize A Pit level decreasing CREW Enter AP/0/A/5500/020 (Loss of Nuclear Service Water)

BOP Swap suctions and discharges to the SNSWP NOTE TO EVALUATOR: The crew may choose to use the annunciator response to address this event. REFER to Attachment 4.

NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/0/A/5500/020, Loss of Nuclear Service Water.

NOTE TO EVALUATOR: The following steps are from AP/0/A/5500/020, Loss of Nuclear Service Water, Case II (Loss of RN Pit Level)

1. Verify the following alarms - DARK:

BOP

• 1AD-12, B/2 "RN PIT A SCREEN HI D/P"

• 1AD-12, B/5 "RN PIT B SCREEN HI D/P

1. RNO IF the operating RN pump is on the affected pit with high BOP D/P, THEN align RN to SNSWP. REFER TO Enclosure 2 (RN Valve Alignment for RN Swap to SNSWP).

NOTE TO EVALUATOR: The SRO may choose to read Enclosure 2 or hand Enclosure 2 to the BOP to perform.

NOTE TO EVALUATOR: The following steps are from AP/0/A/5500/020, Loss of Nuclear Service Water, Enclosure 2 (RN Valve Alignment for RN Swap to the SNSWP).

1. Ensure the following valves - OPEN:

• 1RN-3A (RN P/H Pit A Isol From SNSWP)

• 1RN-4B (RN P/H Pit B Isol From SNSWP)

BOP

• 1RN-58B (RN Hdr B Ret To SNSWP)

• 1RN-63A (RN Hdr A Ret To SNSWP)

• 1RN-846A (D/G 1A Hx Ret To SNSWP)

• 1RN-848B (D/G 1B Hx Ret To SNSWP)

• 2RN-846A (D/G 2A Hx Ret To SNSWP)

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 12 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 13 of 70 Event

Description:

RN Pit Screen A Hi D/P Time Position Applicants Actions or Behavior

• 2RN-848B (D/G 2B Hx Ret To SNSWP).

2. Ensure the following valves - CLOSED:

• 1RN-1A (RN P/H Pit A Isol From Lake)

• 1RN-2B (RN P/H Pit A Isol From Lake)

• 1RN-5A (RN P/H Pit B Isol From Lake)

• 1RN-6B (RN P/H Pit B Isol From Lake)

• 1RN-53B (Station RN Disch Hdr X-Over)

• 1RN-54A (Station RN Disch Hdr X-Over)

• 1RN-57A (Station RN Disch To RL Sys)

BOP

• 1RN-843B (Station RN Disch To RL Sys)

• 1RN-49A (Non-Ess Supply Hdr Isol)

• 1RN-50B (Non-Ess Supply Hdr Isol)

• 2RN-49A (Non-Ess Supply Hdr Isol)

• 2RN-50B (Non-Ess Supply Hdr Isol)

• 1RN-847A (D/G 1A Hx Ret To Lake)

• 1RN-849B (D/G 1B Hx Ret To Lake)

• 2RN-847A (D/G 2A Hx Ret To Lake)

• 2RN-849B (D/G 2B Hx Ret To Lake).

NOTE TO EVALUATOR: Step 3 will not apply.

4. IF RN Pit A initiated the auto or manual swap to the SNSWP, THEN ensure the following valves are closed:

BOP

• 1RN-48B (RN Supply X-Over Isol)

• 2RN-48B (RN Supply X-Over Isol).

NOTE TO EVALUATOR: Step 5 will not apply.

NOTE TO EVALUATOR: End of Enclosure 2 BOP 2. Start idle RN pump(s) on the unaffected train.

3. Verify affected pit level adequate as follows:

• 1AD-12, B/1 "RN PUMP INTAKE PIT A LEVEL-LO" - DARK

• 1AD-12, B/4 "RN PUMP INTAKE PIT B LEVEL-LO" - DARK BOP

• 2AD-12, B/1 "RN PUMP INTAKE PIT A LEVEL-LO" - DARK

• 2AD-12, B/4 "RN PUMP INTAKE PIT B LEVEL-LO" - DARK

• Affected pit level indication - STABLE OR INCREASING.

BOP 4. Verify each operating RN pump discharge flow - LESS THAN Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 13 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 14 of 70 Event

Description:

RN Pit Screen A Hi D/P Time Position Applicants Actions or Behavior 23,000 GPM.

NOTE After automatic swapover to SNSWP on emergency-low RN pit level, RN swap to SNSWP annunciators will only be lit for 2 minutes following swapover.

5. IF any of the following alarms are lit OR were previously lit:

• 1AD-12, E/2 "RN PIT A SWAP TO SNSWP" OR

• 2AD-12, E/2 "RN PIT A SWAP TO SNSWP" OR

• 1AD-12, E/5 "RN PIT B SWAP TO SNSWP" OR

• 2AD-12, E/5 "RN PIT B SWAP TO SNSWP".

BOP THEN perform the following:

a. Ensure all RN pumps - ON.

b. Ensure correct RN valve alignment. REFER TO Enclosure 2 (RN Valve Alignment for RN Swap to SNSWP).

c. IF AT ANY TIME RN pump(s) running on RN pit with LO-LO level, THEN secure affected pump(s).

d. IF WL discharge in progress, THEN coordinate with Radwaste Chemistry to secure all controlled WL discharges.

e. IF any RN chemical addition is in progress, THEN have Chemistry secure it.

6. Verify SNSWP level adequate and stable as follows:

BOP

• 1AD-12, A/3 "SNSWP LEVEL LO" - DARK

• SNSWP level indication - STABLE.

NOTE TO EVALUATOR: The KC heat exchanger outlet mode switches will be in the KC Temp position if the corresponding train of KC is in service.

Otherwise, it will be in the Miniflow position.

7. Ensure proper alignment of RN to KC Hxs as follows:

BOP a. Verify RN - ALIGNED TO KC HX(S) IN SERVICE.

b. Ensure KC Hx Otlt Mode switches - PROPERLY ALIGNED.

8. Verify each operating RN pump discharge flow - GREATER BOP THAN 8,600 GPM.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 14 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 15 of 70 Event

Description:

RN Pit Screen A Hi D/P Time Position Applicants Actions or Behavior CREW 9. Determine and correct cause of loss of RN pit level.

10. Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual:

• SLC 16.7-6 (RN Discharge Instrumentation)

• 3.3.2 (Engineered Safety Features Actuation System BOP (ESFAS) Instrumentation).

• 3.6.5 (Containment Air Temperature)

• 3.7.8 (Nuclear Service Water System (NSWS))

• 3.7.9 (Standby Nuclear Service Water Pond (SNSWP)).

NOTE TO EVALUATOR: No Tech Spec Actions need to be entered.

Booth Operator will insert Trigger 4 for EVENT 4 at the discretion of the lead examiner.

11. Determine required notifications:

• REFER TO RP/0/A/5000/001 (Classification Of Emergency)

SRO

• REFER TO RP/0/B/5000/013 (NRC Notification Requirements).

12. WHEN corrective action for loss of pit level taken, THEN restore RN to normal alignment. REFER TO Enclosure 3 CREW (Returning RN alignment To Normal After Transfer To SNSWP).

BOP 13. Ensure RN pumps - IN OPERATION AS NEEDED.

14. Verify each operating RN pump discharge flow - GREATER BOP THAN 8,600 GPM.

15. Notify Environmental Chemistry of any RN pump shifts that BOP have occurred.

16. Determine long term plant status. RETURN TO procedure in SRO effect.

NOTE TO EVALUATOR: The SRO will conduct a Crew Brief or a Focus Brief to summarize the event.

END OF EVENT 3 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 15 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 16 of 70 Event

Description:

1B CF (Main Feedwater) Pump Trips, 1B CA (Auxiliary Feedwater) Pump fails to start Time Position Applicants Actions or Behavior EVENT 4 INDICATIONS: 1AD-1, A/6 TURB TRIP ON LOSS OF BOTH CFPTS 1AD-1, B/1 AMSAC TURB TRIP 1AD-1, C/6 EXT TRAIN A-B/ NON TRAIN TURB TRIP 1AD-1, C/7 LO ETS PRESS 1AD-1, E/7 TURB ETS HDR PRESS LO 1AD-5, C/1 CFPT B TRIPPED 1AD/5, C/4 CFPT B COMMON TROUBLE RO Recognize 1B CFPT Trip and subsequent loss of feedwater.

RO Recognize failure of 1B CA Pump to start and attempts to start it.

CREW ENTERS AP/1/A/5500/006, CASE I NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/006, Loss of S/G Feedwater.

NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/006, Loss of S/G Feedwater, Case I (Loss of CF Supply To S/Gs)

RO 1. Verify reactor power - LESS THAN 5%.

RO 2. Verify all S/G hi-hi level alert alarms (1AD-4) - DARK.

RO 3. Verify 1AD-2, F/9 "DCS ALTERNATE ACTION" - DARK.

4. Verify total CA flow - GREATER THAN RO 450 GPM.

5. Control S/G levels as follows:

RO

a. Verify all S/G N/R levels - GREATER THAN 11%.

NOTE TO EVALUATOR: The crew will start CAPT #1 to be able to feed 1C and 1D steam generators due to the failure of 1B CA pump to start.

5.a. RNO a. Maintain total feed flow greater than 450 GPM to intact RO S/Gs until at least one S/G N/R level greater than 11%.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 16 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 17 of 70 Event

Description:

1B CF (Main Feedwater) Pump Trips, 1B CA (Auxiliary Feedwater) Pump fails to start Time Position Applicants Actions or Behavior

b. WHEN at least one S/G N/R level is greater than 11%, THEN RO throttle feedflow to maintain all S/G N/R levels between 11% -

50%.

SRO 6. REFER TO Case II (Loss of Normal CA Supply).

NOTE TO EVALUATOR: The crew may initiate a makeup to the UST per step 2 of Case II.

No other actions from Case II are necessary.

7. Ensure compliance with appropriate Tech Specs and SLCs:

• 3.3.2 (ESFAS Instrumentation)

• 3.7.5 (Auxiliary Feedwater System)

SRO

• SLC 16-7.1 (AMSAC).

• SLC 16-7.14 (Trip of All Main Feedwater Pumps Turbine Trip Instrumentation).

NOTE TO EVALUATOR: T.S 3.7.5 Auxiliary Feedwater (AFW) System Condition B (Restore AFW train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) should be entered. Per T.S. 3.7.5, LCO 3.0.4.(b) does not apply and Mode change is not allowed now.

NOTE TO EVALUATOR: The SRO will conduct a Crew Update to inform the crew of any Tech Spec conditions that have been entered.

Booth Operator will insert Trigger 5 for EVENT 5 at the discretion of the lead examiner.

8. Determine required notifications:

• REFER TO RP/0/A/5000/001 (Classification Of Emergency)

SRO

• REFER TO RP/0/B/5000/013 (NRC Notification Requirements).

CREW 9. Determine and correct cause of loss of CF supply.

RO 10. Verify at least one CF Pump - ON.

NOTE TO EVALUATOR: It is not intended for the next step to be performed in this scenario.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 17 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 18 of 70 Event

Description:

1B CF (Main Feedwater) Pump Trips, 1B CA (Auxiliary Feedwater) Pump fails to start Time Position Applicants Actions or Behavior

10. RNO Perform a hot restart of one CF Pump. REFER TO BOP OP/1/A/6250/001 (Condensate and Feedwater System).

NOTE TO EVALUATOR: Due to the likelihood that the scenario will progress to the next event prior to completing all of the steps of the AP, the SRO may not do a Crew Brief or Focus Brief to summarize the event.

END OF EVENT 4 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 18 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 19 of 70 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Applicants Actions or Behavior EVENT 5 Indications: 1AD-11, A/1 4KV ESS PWR TRAIN A TROUBLE 1AD-7, C/4 NCP SEAL WATER LO FLOW 1AD-7, E/1 CHARGING LINE HI/LO FLOW BOP Recognizes 1A NV pump tripped CREW Enters AP/1/A/5500/012, Loss of Charging or Letdown NOTE TO EVALUATOR: The following steps are taken from AP/1/A/5500/012, Loss of Charging or Letdown, Case I (Loss of Charging).

RO 1. Stop any power changes.

2. Ensure the following letdown isolation valves - CLOSED:

• 1NV-10A (Letdn Orif 1B Otlt Cont Isol)

BOP

• 1NV-11A (Letdn Orif 1C Otlt Cont Isol)

• 1NV-13A (Letdn Orif 1A Otlt Cont Isol).

BOP 3. Ensure any malfunctioning NV pump - SECURED.

4. Monitor conditions for continued NC pump operation as BOP or follows:

RO NC pump #1 seal outlet temperature - LESS THAN 235°F NC pump lower bearing temperature - LESS THAN 225°F.

NOTE TO EVALUATOR: Step 5 will not apply.

NOTE: Gas entrainment in the NV pump suction can produce pump failure or degradation. Gas entrainment can result in a complete loss of charging, or in a reduction of charging capacity, without indication of cavitation.

6. Verify NV pump status as follows:

BOP

• At least one NV pump - ON.

6. RNO Perform the following:

a. Ensure any malfunctioning NV pump - SECURED.

BOP b. Ensure the following valves - OPEN:

• 1NV-203A (NV Pumps A&B Recirc Isol)

• 1NV-202B (NV Pmps A&B Recirc Isol).

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 19 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 20 of 70 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Applicants Actions or Behavior

c. Ensure only one suction source as follows:

• VCT

• 1NV-188A (VCT Otlt Isol) - OPEN

• 1NV-189B (VCT Otlt Isol) - OPEN BOP

• VCT level - GREATER THAN 23%

• 1NV-252A (NV Pumps Suct From FWST) -

CLOSED

• 1NV-253B (NV Pumps Suct From FWST) -

CLOSED.

NOTE TO EVALUATOR: The crew will determine that step 6 RNO d. does not apply

e. Start the available NV pump as follows:

1) OPEN 1NV-309 (Seal Water Injection Flow) to full open.

BOP 2) CLOSE 1NV-294 (NV Pmps A&B Disch Flow Ctrl).

3) Start NV pump aux oil pump.

4) Start available NV pump.

5) Stop NV pump aux oil pump.

NOTE TO EVALUATOR: The crew will determine that step 6 RNO e.6) does not apply NOTE TO EVALUATOR: The crew will determine that step 6 RNO f. does not apply

7. Verify charging header aligned to NC loop as follows:

a. 1NV-312A (Chrg Line Cont Isol) - OPEN.

b. 1NV-314B (Chrg Line Cont Isol) - OPEN.

c. Verify one of the following valves - OPEN:

• 1NV-32B (NV Supply To Loop A Isol)

BOP OR

• 1NV-39A (NV Supply To Loop D Isol).

d. Verify the following NC pump conditions:

• #1 seal outlet temperatures less than or equal to 180°F

• Lower bearing temperatures less than or equal to 180°F.

e. Verify 1NV-294 (NV Pmps A&B Disch Flow Ctrl) - OPEN.

7.e. RNO e. Perform the following:

1) OPEN 1NV-309 (Seal Water Injection Flow).

BOP 2) THROTTLE 1NV-294 (NV Pmps A&B Disch Flow Ctrl) to establish greater than 32 GPM "N/R CHRG LN FLOW" Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 20 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 21 of 70 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Applicants Actions or Behavior

8. Verify the following:

BOP * "TOTAL SEAL WTR FLOW" - GREATER THAN 32 GPM

• 1NV-309 (Seal Water Injection Flow) - IN AUTO.

8. RNO Perform the following:

a. IF any NC pump #1 seal outlet temperature OR lower bearing temperature greater than 180°F, THEN maintain BOP cooldown rate less than or equal to 1°F per minute.

b. Slowly THROTTLE 1NV-309 (Seal Injection Flow) to establish 32 GPM "TOTAL SEAL WTR FLOW"

c. Place 1NV-309 in auto.

BOP 9. Verify Pzr level - GREATER THAN 17%.

BOP 10. Control charging to stabilize Pzr level greater than 17%.

BOP 11. Ensure "PZR HTR GROUP 1C" - ON.

12. Control VCT level as follows:

a. Verify NC system makeup - SET FOR DESIRED BORON BOP CONCENTRATION.

b. Verify "NC MAKEUP MODE SELECT" - IN AUTO.

BOP 13. Verify normal letdown - IN SERVICE.

NOTE TO EVALUATOR: Step 13 RNO a. will not be performed and step b. will be applicable. The SRO may wait to evaluate Tech Specs until after the restoration of letdown.

NOTE TO EVALUATOR: To shorten the scenario, the Booth Operator can insert Trigger 7 to start the Major event at the discretion of the lead examiner and the Tech Specs can be covered by follow up questioning.

13. RNO Perform the following:

SRO b. Restore normal letdown. REFER TO Case II (Loss of Letdown).

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 21 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 22 of 70 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Applicants Actions or Behavior

14. Ensure compliance with appropriate Tech Specs:

• 3.4.13 (RCS Operational Leakage)

• 3.4.14 (RCS Pressure Isolation Valve (PIV) Leakage)

• 3.5.2 (ECCS - Operating)

• 3.5.3 (ECCS - Shutdown)

SRO

• 3.5.5 (Seal Injection Flow)

• 3.6.3 (Containment Isolation Valves)

• SLC 16.9-9 (Boration Systems Charging Pump - Shutdown)

• SLC 16.9-10 (Boration Systems Charging Pump -

Operating).

NOTE TO EVALUATOR: SRO should determine that Tech Spec 3.5.2 (ECCS-Operating)

Condition A (Restore train to OPERABLE status 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) continues to apply and SLC 16.9-10 (Boration Systems Charging Pump - Operating) Condition A (Restore non-functional pump to FUNCTIONAL status 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) should be entered.

15. Determine required notifications:

• REFER TO RP/0/A/5000/001 (Classification Of Emergency)

SRO

• REFER TO RP/0/B/5000/013 (NRC Notification Requirements).

BOP 16. Verify at least one NV pump - ON.

NOTE TO EVALUATOR: Step 17 will not apply

18. Determine long term plant status. RETURN TO procedure in SRO effect.

NOTE TO EVALUATOR: The following steps are taken from AP/1/A/5500/012, Loss of Charging or Letdown, Case II (Loss of Letdown).

RO 1. Stop any power changes.

2. Ensure the following letdown isolation valves - CLOSED:

• 1NV-10A (Letdn Orif 1B Otlt Cont Isol)

BOP

• 1NV-11A (Letdn Orif 1C Otlt Cont Isol)

• 1NV-13A (Letdn Orif 1A Otlt Cont Isol).

BOP 3. Verify Pzr level - GREATER THAN 17%.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 22 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 23 of 70 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Applicants Actions or Behavior

4. Control charging to stabilize Pzr level at program level while BOP maintaining seal injection flow.

BOP 5. Ensure "PZR HTR GROUP 1C" - ON.

6. Control VCT level as follows:

a. Verify NC system makeup - SET FOR DESIRED BORON BOP CONCENTRATION.

b. Verify "NC MAKEUP MODE SELECT" - IN AUTO.

BOP 7. Determine and correct cause of loss of letdown.

8. IF AT ANY TIME excess letdown required, THEN establish BOP excess letdown. REFER TO OP/1/A/6200/001 (Chemical and Volume Control System).

9. Verify proper VC/YC system operation. REFER TO Enclosure BOP 3 (Control Room Ventilation System Verification).

NOTE TO EVALUATOR: Enclosure 3 is Attachment 5 in the back of this guide.

NOTE TO EVALUATOR: The SRO may wait to evaluate Tech Specs until after the restoration of letdown.

10. Ensure compliance with appropriate Tech Specs:

• 3.3.1 (Reactor Trip System (RTS) Instrumentation)

• 3.3.3 (Post Accident Monitoring (PAM) Instrumentation)

• 3.3.4 (Remote Shutdown System)

• 3.4.1 (RCS Pressure, Temperature, and Flow Departure SRO From Nucleate Boiling (DNB) Limits)

• 3.4.12 (Low Temperature Overpressure Protection (LTOP)

System)

• 3.4.13 RCS (Operational Leakage).

• 3.6.3 (Containment Isolation Valves).

NOTE TO EVALUATOR: The SRO should determine that no Tech Specs apply for the loss of letdown.

11. Verify at least one of the following valves - CLOSED:

• 1NV-1A (NC Letdn To Regen Hx Isol)

BOP OR

• 1NV-2A (NC Letdn To Regen Hx Isol).

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 23 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 24 of 70 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Applicants Actions or Behavior SRO 11. RNO GO TO Step 16.

16. Establish letdown as follows:

a. Verify ability to establish normal letdown - RESTORED.

b. Ensure 1NV-849 (Letdn Flow Var Orif Ctrl) valve demand BOP position - 0%.

c. Verify the following valves - OPEN:

• 1NV-1A (NC Letdn To Regen Hx Isol)

• 1NV-2A (NC Letdn To Regen Hx Isol).

NOTE If LTOP is in service, then 1NC-34A will be made inoperable when the only letdown path aligned is NV system normal letdown. 1NC-34A LTOP operability is based on the letdown alignment. (PIP C-10-1320)

d. OPEN the following valves:

• 1NV-15B (Letdn Cont Isol)

• 1NV-10A (Letdn Orif 1B Otlt Cont Isol).

e. Adjust 1NV-294 (NV Pmps A&B Disch Flow Ctrl) as necessary to maintain letdown subcooled in following steps.

BOP f. THROTTLE 1NV-148 (Letdn Press Control) to 45% demand.

g. THROTTLE open 1NV-849 (Letdn Flow Var Orif Ctrl) in 1% to 5% increments until one of the following conditions met:

• Letdown flow and letdown pressure increases OR

• Valve demand position is 60% open.

SRO h. Do not continue until one of the above conditions met.

BOP i. Verify letdown flow and letdown pressure - HAS INCREASED.

j. Adjust 1NV-148 (Letdn Press Control) to maintain letdown BOP pressure between 150 - 200 PSIG.

NOTE TO EVALUATOR: Time compression may be used in the following step at the discretion of the lead examiner.

k. WHEN 5 minutes have elapsed, THEN perform the following:

1) Adjust 1NV-849 (Letdn Flow Var Orif Ctrl) in 1% to 5%

BOP increments to desired letdown flow.

2) WHEN letdown at desired flow, THEN perform the following:

a) Adjust 1NV-148 (Letdn Press Control) to maintain Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 24 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 25 of 70 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Applicants Actions or Behavior letdown pressure at 350 PSIG.

b) Ensure 1NV-148 (Letdn Press Control) - IN AUTO.

Booth Operator will insert Trigger 6 for EVENT 6 at discretion of lead examiner.

3) IF AT ANY TIME additional letdown flow desired, THEN BOP establish letdown with the 45 or 75 GPM orifice. REFER TO OP/1/A/6200/001 (Chemical and Volume Control System).

l. WHEN Pzr level restored to programmed level, THEN perform the following:

BOP 1) Ensure 1NV-294 (NV Pmps A&B Disch Flow Ctrl) - IN AUTO.

2) Ensure "PZR Level Master" - IN AUTO.

17. Determine required notifications:

• REFER TO RP/0/A/5000/001 (Classification Of Emergency)

SRO

• REFER TO RP/0/B/5000/013 (NRC Notification Requirements).

BOP 18. Verify excess letdown - ISOLATED.

19. Determine long term plant status. RETURN TO procedure in SRO effect.

END OF EVENT 5 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 25 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6 Page 26 of 70 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior EVENT 6 Indications: 1AD-2, D/10 DCS TROUBLE 1AD-6, E/10 PZR PORV DISCH HI TEMP 1AD-6, F/8 PZR LO PRESS CONTROL BOP Recognize 1NC-36B open BOP Attempt to close 1NC-36B BOP Attempt to close 1NC-35B RO Manually Trip the Reactor BOP Manually initiate Safety Injection.

NOTE TO EVALUATOR: Due to the immediate action nature of the event, it is not anticipated the crew will have time to make a plant page announcing the entry into AP/1/A/5500/0011, Pressurizer Pressure Anomalies.

NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/011, Pressurizer Pressure Anomalies, Case I (Pressurizer Pressure Decreasing).

BOP 1. Verify all Pzr PORVs - CLOSED.

1. RNO Perform the following:

a. Close Pzr PORV(s).

b. IF any Pzr PORV cannot be closed, THEN:

1) Close the affected PORV(s) isolation valve.

BOP 2) IF the Pzr PORV isolation valve cannot be closed, THEN perform the following:

a) IF in Mode 3 with CLAs isolated OR in Mode 4, THEN GO TO AP/1/A/5500/027 (Shutdown LOCA).

RO b) Trip Unit 1 reactor.

c) WHEN reactor tripped OR S/I setpoint reached, BOP THEN ensure S/I initiated.

d) GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety CREW Injection).

TRANSITION TO E-0 (Reactor Trip or Safety Injection)

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 26 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, & 8 Page 27 of 70 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

RO and

1. Monitor Enclosure 1 (Foldout Page).

BOP NOTE TO EVALUATOR: Enclosure 1 is Attachment 6 in the back of this guide.

2. Verify Reactor Trip: Perform the following:

• All rod bottom lights - LIT RO

• All reactor trip and bypass breakers - OPEN

• I/R power - DECREASING.

3. Verify Turbine Trip: Perform the following:

RO

• All turbine stop valves - CLOSED BOP 4. Verify 1ETA and 1ETB - ENERGIZED.

5. Verify S/I actuated:

RO a. "SAFETY INJECTION ACTUATED" status light (1SI-13) - LIT.

b. Both E/S load sequencer actuated status lights (1SI-14) - LIT.

NOTE TO EVALUATOR: Upon Loss of Subcooling with S/I flow verified, the RO or BOP should trip the NC (Reactor Coolant) pumps within 5 minutes per Enclosure 1 guidance. This satisfies Critical Task # 2.

RO 6. Announce "Unit 1 Safety Injection".

7. Determine required notifications:

• REFER TO RP/0/A/5000/001(Classification Of Emergency)

SRO

• REFER TO RP/0/B/5000/013 (NRC Notification Requirements).

RO or

8. Verify all Feedwater Isolation status lights (1SI-5) - LIT BOP

8. RNO Perform the following:

a. Initiate Feedwater Isolation.

RO

b. IF proper status light indication not obtained, THEN CLOSE valves NOTE TO EVALUATOR: 1CA-152 will be manually closed by the RO.

END OF EVENT 8 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 27 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, & 8 Page 28 of 70 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior

9. Verify Phase A Containment Isolation status as follows:

BOP

a. Phase A "RESET" lights - DARK.

b. Monitor Light Panel Group 5 St lights on energized train(s) -

BOP LIT.

10. Verify proper Phase B actuation as follows:

BOP a. Verify Containment pressure - HAS REMAINED LESS THAN 3 PSIG RO or b. IF AT ANY TIME containment pressure exceeds 3 PSIG BOP while in this procedure, THEN perform Step 10.a.

11. Verify proper CA pump status as follows:

RO a. Motor driven CA pumps - ON.

b. 3 S/G N/R levels - GREATER THAN 11%.

11.a. RNO a. Perform the following for affected train(s):

1) Reset ECCS.

RO

2) Reset D/G load sequencer(s),

3) Start affected pump(s).

RO and 4) IF AT ANY TIME B/O occurs, THEN restart S/I BOP equipment previously on.

12. Verify all of the following S/I pumps - ON: Perform the following for affected train(s):

BOP

• NV pumps

• ND pumps

• NI pumps.

12. RNO Perform the following for affected train(s):

CRITICAL a. Reset ECCS.

BOP TASK #1 b. Reset D/G load sequencer(s)

c. Start affected pump(s).

RO and d. IF AT ANY TIME B/O occurs, THEN restart S/I BOP equipment previously on.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 28 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, & 8 Page 29 of 70 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior END OF EVENT 7 BOP 13. Verify all KC pumps - ON.

BOP 14. Verify all Unit 1 and Unit 2 RN pumps - ON.

15. Verify proper ventilation systems operation as follows:

• REFER TO Enclosure 2 (Ventilation System Verification).

BOP

• Notify Unit 2 operator to perform Enclosure 3 (Opposite Unit Ventilation Verification).

NOTE TO EVALUATOR: Enclosure 2 is Attachment 7 in the back of this guide.

NOTE TO EVALUATOR: SRO will state that they will hand Enclosure 3 to a Unit 2 operator and set Enclosure 3 off to the side.

RO 16. Verify all S/G pressures - GREATER THAN 775 PSIG.

17. Verify proper S/I flow as follows:

a. "NV S/I FLOW" - INDICATING FLOW.

RO b. NC pressure - LESS THAN 1620 PSIG.

c. NI pumps - INDICATING FLOW.

d. NC pressure - LESS THAN 285 PSIG.

17.d. RNO d. Perform the following:

RO 1) Ensure ND pump miniflow valve on operating ND pump(s) - OPEN.

NOTE TO EVALUATOR: Step 17 RNO d. 2) will not apply SRO 3) GO TO Step 18.

18. WHEN time and manpower permit (within two hours of RO or event), THEN monitor Spent Fuel Pool level and temperature.

BOP REFER TO EP/1/A/5000/G-1(Generic Enclosures), Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring).

NOTE TO EVALUATOR: G-1 Enclosure 1 is Attachment 8 in the back of this guide.

19. Control S/G levels as follows:

RO

a. Verify total CA flow - GREATER THAN 450 GPM.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 29 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, & 8 Page 30 of 70 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: Total CA flow may not be > 450 gpm due to being under operator control, in which case, the RNO for 19 a. will not apply.

b. WHEN each S/G N/R level greater than 11% (29% ACC),

RO THEN control feed flow to maintain that S/G N/R level between 11% (29% ACC) and 50%.

RO 20. Verify all CA isolation valves - OPEN.

21. Verify S/I equipment status based on monitor light panel - IN BOP PROPER ALIGNMENT.

BOP 21. RNO Align equipment.

NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance.

22. Control NC temperature. REFER TO Enclosure 4 (NC RO Temperature Control).

NOTE TO EVALUATOR: Enclosure 4 is Attachment 9 in the back of this guide.

23. Verify Pzr PORV and Pzr Spray Valve status as follows:

BOP

a. All Pzr PORVs - CLOSED.

23. RNO a. IF Pzr pressure is less than 2315 PSIG, THEN perform the following:

BOP 1) CLOSE Pzr PORV(s).

2) IF any Pzr PORV cannot be closed, THEN CLOSE its isolation valve.

NOTE TO EVALUATOR: RNO step 23.a.3) will not apply

4) IF any Pzr PORV cannot be closed OR isolated, THEN perform the following:

a) Energize H2 igniters.

b) Dispatch operator to perform the following:

(1) Secure all ice condenser air handling units.

RO or REFER TO EP/1/A/5000/G-1 (Generic BOP Enclosures), Enclosure 11(Securing All Ice Condenser Units).

(2) Place containment H2 analyzers in service.

REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems).

c) IF both the following conditions exist, Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 30 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, & 8 Page 31 of 70 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior

• Containment pressure - HAS REMAINED LESS THAN 3 PSIG

• Containment pressure - BETWEEN 1 PSIG AND 3 PSIG THEN start one VX fan and secure normal containment ventilation. REFER TO EP/1/A/5000/G-1 (Generic Enclosures),

Enclosure 18 (VX and Containment Ventilation Control).

d) Concurrently:

• Implement EP/1/A/5000/F-0 (Critical Safety CREW Function Status Trees).

• GO TO EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant).

TRANSITION TO EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant)

NOTE TO EVALUATOR: The SRO may conduct a Crew Brief or a Focus Brief to summarize the event.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 31 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, & 8 Page 32 of 70 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant)

RO and

1. Monitor Enclosure 1 (Foldout Page).

BOP NOTE TO EVALUATOR: Enclosure 1 is Attachment 10 in the back of this guide.

RO or 2. Verify NC subcooling based on core exit T/Cs - GREATER BOP THAN 0°F.

NOTE TO EVALUATOR: Depending on the pace of the crew, subcooling may be greater than 0ºF in which case the crew would continue to step 3.

2. RNO IF any NV OR NI pump is on, THEN perform the RO or following:

BOP a. Ensure all NC pumps - OFF.

b. Maintain seal injection flow.

3. Verify main steamlines intact:

BOP

• All S/G pressures - STABLE OR INCREASING

• All S/Gs - PRESSURIZED.

4. Control intact S/G N/R levels as follows:

a. Verify N/R level in any intact S/Gs - GREATER THAN 11%

RO (29% ACC).

b. THROTTLE feed flow to maintain all intact S/G N/R levels between 11% (29% ACC) and 50%.

5. Reset the following:

a. ECCS.

BOP b. D/G load sequencers.

c. Phase A

d. Phase B.

RO or e. IF AT ANY TIME B/O occurs, THEN restart S/I equipment BOP previously on.

6. Establish VI to Containment as follows:

BOP

• Ensure 1VI-77B (VI Cont Isol) - OPEN.

• Verify VI pressure - GREATER THAN 85 PSIG.

RO 7. Verify secondary radiation - NORMAL:

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 32 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, & 8 Page 33 of 70 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior

a. Ensure the following signals - RESET:

1) CA System valve control BOP 2) KC NC NI NM St signals.

NOTE TO EVALUATOR: The BOP opens the following valves when aligning the S/Gs for chemistry sample in step b. below:

• 1NM-191B (S/G 1A SMPL HDR CONT ISOL)

• 1NM-201A (S/G 1B SMPL HDR CONT ISOL)

• 1NM-211B (S/G 1C SMPL HDR CONT ISOL)

• 1NM-221A (S/G 1D SMPL HDR CONT ISOL)

• 1NM-190A (S/G 1A BLDWN SMPL CONT ISOL)

• 1NM-200B (S/G 1B BLDWN SMPL CONT ISOL)

• 1NM-210A (S/G 1C BLDWN SMPL CONT ISOL)

• 1NM-220B (S/G 1D BLDWN SMPL CONT ISOL)

BOP b. Align all S/Gs for Chemistry sampling.

c. Perform at least one of the following:

RO or

• Notify Chemistry to sample all S/Gs for activity.

BOP OR

• Notify RP to frisk all cation columns for activity.

d. Verify the following EMF trip 1 lights - DARK:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-26 (Steamline 1A)

BOP

• 1EMF-27 (Steamline 1B)

• 1EMF-28 (Steamline 1C)

• 1EMF-29 (Steamline 1D).

e. Verify all S/Gs - INTACT RO

• All S/G pressures - STABLE OR INCREASING

• All S/Gs - PRESSURIZED.

RO or f. WHEN activity results reported, THEN verify all S/Gs indicate BOP no activity.

8. Verify Pzr PORVs and Isolation Valves:

BOP a. Power to all Pzr PORV isolation valves - AVAILABLE.

b. All Pzr PORVs - CLOSED.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 33 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, & 8 Page 34 of 70 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior 8.b. RNO b. IF Pzr pressure is less than 2315 PSIG, THEN perform the following:

BOP 1) CLOSE Pzr PORV(s).

2) IF any Pzr PORV cannot be closed, THEN CLOSE its isolation valve.

NOTE TO EVALUATOR: RNO step 8.B.3) will not apply BOP c. Any Pzr PORV isolation valve - OPEN.

d. IF AT ANY TIME any Pzr PORV opens due to high pressure, RO or THEN after Pzr pressure decreases to less than 2315 PSIG, BOP ensure PORV closes or is isolated.

9. Verify S/I termination criteria:

a. NC subcooling based on core exit T/Cs - GREATER THAN 0°F.

b. Secondary heat sink:.

RO or

• Any intact S/G N/R level - GREATER THAN 11% (29% ACC)

BOP OR

• Total feed flow to intact S/Gs - GREATER THAN 450 GPM.

c. NC pressure - STABLE OR INCREASING.

d. Pzr level - GREATER THAN 11% (30% ACC).

CREW e. GO TO EP/1/A/5000/ES-1.1 (Safety Injection Termination).

NOTE TO EVALUATOR: Depending on timing of the crew in getting to this point, NC pressure may be determined to be decreasing. If this is the case, the crew will continue in E-1 and eventually will determine the need to transition to EP/1/A/5000/ES-1.2 (Post LOCA Cooldown and Depressurization). Once the crew makes this determination and makes the transition to ES-1.2 from either E-1 or ES-1.1, the scenario may be terminated by having the booth operator place the simulator in FREEZE.

TRANSITION TO EP/1/A/5000/ES-1.1 (Safety Injection Termination)

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 34 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, & 8 Page 35 of 70 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/ES-1.1 (Safety Injection Termination)

RO and

1. Monitor Enclosure 1 (Foldout Page).

BOP NOTE TO EVALUATOR: Enclosure 1 is Attachment 11 in the back of this guide.

2. Reset the following:

a. ECCS.

b. D/G load sequencers.

BOP c. Phase A.

d. Phase B.

e. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on.

3. Establish VI to Containment as follows:

BOP

• Ensure 1VI-77B (VI Cont Isol) - OPEN.

• Verify VI pressure - GREATER THAN 85 PSIG.

BOP 4. Ensure only one NV pump - ON.

RO or

5. Verify NC pressure - STABLE OR INCREASING.

BOP NOTE TO EVALUATOR: The crew may determine that NC pressure is decreasing and go to the RNO, ensure Pzr spray valves - CLOSED and transition to EP/1/A/5000/ES-1.2 (Post LOCA Cooldown and Depressurization.)

BOP 6. Verify VI pressure - GREATER THAN 50 PSIG.

7. Isolate NV S/I flowpath as follows:

a. Verify the following valves - OPEN:

• 1NV-252A (NV Pumps Suct From FWST)

BOP

• 1NV-253B (NV Pumps Suct From FWST).

b. Verify the following valves - OPEN:

• 1NV-203A (NV Pumps A&B Recirc Isol)

• 1NV-202B (NV Pmps A&B Recirc Isol).

7.b. RNO b. Perform the following:

1) OPEN affected valve(s).

BOP

2) IF 1NV-203A AND 1NV-202B are open, THEN GO TO Step 7.c.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 35 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, & 8 Page 36 of 70 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior

c. CLOSE the following valves:

BOP

• 1NI-9A (NV Pmp C/L Inj Isol)

• 1NI-10B (NV Pmp C/L Inj Isol).

NOTE TO EVALUATOR: The crew may determine that subcooling is < 0ºF and use Enclosure 1 guidance to realign the NV S/I flow path per EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 14 (NV Alignment to S/I Mode). See Attachment 12 in the back of this guide.

8. Establish charging as follows:

a. Verify all of the following valves - OPEN:

• 1NV-44A (NC Pmp A Seal Supply Cont Isol)

• 1NV-55A (NC Pmp B Seal Supply Cont Isol)

• 1NV-66A (NC Pmp C Seal Supply Cont Isol)

• 1NV-77A (NC Pmp D Seal Supply Cont Isol).

b. THROTTLE 1NV-294 (NV Pmps A&B Disch Flow Ctrl) for 32 GPM charging line flow.

c. CLOSE 1NV-309 (Seal Water Injection Flow).

d. Ensure one of the following valves - OPEN:

• 1NV-32B (NV Supply To Loop A Isol)

BOP OR

• 1NV-39A (NV Supply To Loop D Isol)

e. Ensure 1NV-37A (NV Supply To Pzr Aux Spray) - CLOSED

f. OPEN the following valves:

• 1NV-312A (Chrg Line Cont Isol)

• 1NV-314B (Chrg Line Cont Isol).

g. Verify 1NV-309 - ABLE TO BE OPERATED FROM CONTROL ROOM.

h. Place 1NV-309 - IN AUTO.

i. Perform the following:

• Maintain charging flow less than 180 GPM.

• Maintain 32 GPM seal water flow.

9. Control charging as follows:

BOP a. Control charging flow to maintain Pzr level stable.

b. Verify Pzr level - STABLE OR INCREASING.

10. Determine if NI pumps should be stopped:

BOP or a. Verify the following:

RO

• NC pressure - STABLE OR INCREASING

• NC pressure - GREATER THAN 1620 PSIG.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 36 of 70

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, & 8 Page 37 of 70 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior 10.a. RNO a. Perform the following:

BOP 1) IF Pzr level decreasing, THEN increase charging flow to stabilize Pzr level while maintaining less than 180 GPM.

NOTE TO EVALUATOR: RNO Step 10.a.2) will not apply.

SRO 3) GO TO Step 10.d BOP d. Verify Pzr spray valves - CLOSED

e. Verify main steamlines intact as follows:

RO

• ALL S/G pressures - STABLE OR INCREASING

• ALL S/Gs - PRESSURIZED NOTE If Pzr heaters are off, NC pressure may decrease slowly due to Pzr spray bypass flow. This may be considered stable pressure.

BOP f. Verify NC pressure - STABLE OR INCREASING BOP or

g. Verify NC pressure - GREATER THAN 1620 PSIG RO 10.g. RNO g. Perform the following:

1) Do not continue until one of the following met:

• NC pressure - GREATER THAN 1620 PSIG SRO OR

• NC pressure - STABILIZES LESS THAN 1620 PSIG OR

• NC pressure - DECREASING NOTE TO EVALUATOR: RNO Step 10.g.2) will not apply.

3) IF NC pressure remains less than 1620 PSIG, SRO THEN GO TO EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Depressurization).

TRANSITION TO EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Depressurization)

END OF SCENARIO Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 37 of 70

Catawba Nuclear Station NRC Exam May 2015 Attachment List Scenario 3 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - OP/1/A/6400/005 Enclosure 4.17 (Shifting KC Pumps)

ATTACHMENT 4 - OP/1/A/6100/010M (Annunciator Response For Panel 1AD-12), B/2 (RN PIT A SCREEN HI D/P)

ATTACHMENT 5 - AP/1/A/5500/012 Enclosure 3 (Control Room Ventilation System Verification), Rev. 33 ATTACHMENT 6 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page), Rev. 42 ATTACHMENT 7 - EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification), Rev. 42 ATTACHMENT 8 - EP/1/A/5000/G-1 Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring), Rev.9 ATTACHMENT 9 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control), Rev. 42 ATTACHMENT 10 - EP/1/A/5000/E-1 Enclosure 1 (Foldout Page), Rev. 28 ATTACHMENT 11 - EP/1/A/5000/ES-1.1 Enclosure 1 (Foldout Page), Rev. 33 ATTACHMENT 12 - EP/1/A/5000/G-1 Enclosure 14 (NV Alignment To S/I Mode), Rev. 9 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 38 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK Establish flow from at least one intermediate head ECCS 1

pump prior to transition from E-0.

Trip NC pumps on loss of subcooling with S/I flow verified 2

per E-0 within 5 minutes of criteria met.

Comments:

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 39 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 7eº² % MOL 1584 PPM per OAC Controlling Procedure

• OP/1/A/6100/001 (Controlling Procedure for Unit Startup), Enclosure 4.1 (Unit Startup). The steps up to step 3.180 are complete.

Other Information Needed to Assume the Shift

• Unit 1 is at 7eº² % power, MOL. Unit 2 is at 100%. 1D RC pump is tagged out for preventative maintenance. 1B NI (Safety Injection) Pump is tagged out for preventative maintenance.

Power increase to 15% is in progress in preparation for placing the main turbine on line. The crew is to shift operating KC (Component Cooling) pumps by starting the 1B2 KC pump and securing the 1B1 KC pump and then increase power to 1% by withdrawing control rods. LCO 3.0.4.(b) has been assessed for the 1B NI Pump inoperability and Mode change has been authorized.

AOs Available Seven AOs are available as listed on the status board METEOROLOGICAL CONDITIONS

• Upper wind direction = 315 degrees, speed = 10 mph

• Lower wind direction = 315 degrees, speed = 10.5 mph

• Forecast calls for clear skies over the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 40 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 3 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 41 of 70

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Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 4 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 43 of 70

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Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 9 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 61 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 9 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 62 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 9 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 63 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 9 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 64 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 10 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 65 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 10 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 66 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 10 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 67 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 11 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 68 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 12 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 69 of 70

Catawba Nuclear Station NRC Exam May 2015 ATTACHMENT 12 Appendix D Catawba NRC Exam May 2015 Scenario 3 NUREG 1021 Revision 9 Page 70 of 70