Text

301 Final Simulator Scenarios
	ML12356A457
Person / Time
Site:	Catawba
Issue date:	12/17/2012
From:	; Division of Reactor Safety II
To:	; Duke Energy Corp
References
	50-413/12-301, 50-414/12-301
	Download: ML12356A457 (109)
	v • d • e

Catawba Nuclear Station NRC Exam September 2012 HLP NRC EXAM SCENARIO # 1 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 1 of 32

Catawba Nuclear Station NRC Exam September 2012 Facility: Catawba NRC Exam 2012 Scenario No.: 1 Op Test No.: 1 Examiners: Operators: SRO RO BOP Initial Conditions: IC# 176; Unit 1 is at 100% power, EOL. 1D RC pump is tagged out for a motor replacement.

Turnover: Unit 1 is at 100% power, EOL. 1D RC pump is tagged out for a motor replacement. Decrease power per the reactivity management plan and reduce turbine load to ~85% in preparation for Turbine Control Valve movement testing.

Event Malf. No. Event Event No. Type* Description

--- R-RO 1 N-SRO Power reduction to 85% for Turbine Control Valve movement testing.

N-BOP 2 IRX003A C-RO Continuous rod motion (insertion). AP/15 C-SRO 3 RN024 C-BOP Loss of 2A RN pump (Nuclear Service Water). AP/20 TS-SRO 4 NC007F C-BOP Pressurizer PORV 1NC-34A fails open. AP/11 TS-SRO 5 SGL007B C-RO 1CF-37 (1B S/G Feed Reg Vlv) fails closed (ramps in). AP/06 C-SRO 6 CF005D C-ALL Feedline leak on 1D S/G (ramp). AP/28 7 CF005D M-ALL Feedline break inside containment on 1D S/G. (Full severity) 8 NV-047A C-BOP 1NV-253B (NV Pump suction from FWST) fails to auto open.

C-SRO 9 IRX015 C-RO Rod L13 does not fully insert upon reactor trip.

C-SRO

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 2 of 32

Catawba Nuclear Station NRC Exam September 2012 Scenario 1 - Summary Initial Condition Unit 1 is at 100% power. 1D RC Pump (Circulating Water Pump) is tagged out for a motor replacement.

Turnover:

Unit 1 is at 100% power. 1D RC Pump (Circulating Water Pump) is tagged out for a motor replacement. Decrease power per the reactivity management plan and reduce turbine load to

~85% in preparation for Turbine Control Valve movement testing.

Event 1 BOP will initiate a boration; the RO will setup the turbine controls and begin a turbine load reduction to ~85%.

Event 2 Control rods will begin inserting continuously. The RO is required to take rod control to Manual.

This action will successfully terminate the rod insertion. AP/15 (Rod Control Malfunction) will be entered.

Event 3 (Nuclear Service Water) 2A RN Pump trips. AP/20 (Loss of Nuclear Service Water) will be entered. The BOP will manually start another RN pump (there is no auto start feature of the RN pumps for these conditions). TS evaluation by the SRO is required.

Event 4 Pressurizer PORV 1NC-34A fails open. The BOP will manually close the block valve to isolate the leak. TS evaluation by the SRO is required. AP/11 (Pressurizer Pressure Anomalies) will be entered.

Event 5 1CF-37 (1B S/G Feed Reg Vlv) fails closed (ramps closed). This condition requires the RO to take manual control of the feed reg valve to maintain 1B S/G level. AP/06 (Loss of SG Feedwater) will be entered.

Event 6 A feedwater line break inside containment on 1D S/G ramps in to allow the applicants time to discuss containment pressure increasing, and other plant conditions. AP/28 (Secondary Steam Leak) will initially be entered, but the crew will soon recognize the need to manually trip the reactor.

Event 7 The feedwater line break inside containment on 1D S/G increases to full severity.

Event 8 1NV-253B (Charging Pump suction from FWST) fails to auto open on the SI signal. The BOP will manually open this valve due to failed automatic action.

Event 9 Control rod L13 does not fully insert upon the reactor trip. The RO is required to open the reactor trip breakers.

Critical Task 1 - Close the block valve upstream of the stuck open PZR PORV.

Critical Task 2 - Isolate the faulted SG before transition out of E-2.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 3 of 32

Catawba Nuclear Station NRC Exam September 2012 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC 176 START TIME:__________

Trigger Instructor Action Delay Ramp Delete Event Final In MAL-IRX003A (UNCONTROLLED n/a AUTO 2 ROD INSERTION)

MAL-OV0797B (1REDJ5040 RODS 1 TRUE 2 IN DEMAND fail to FALSE/TRUE LOA-RN024 (U2 RN PMP 2A OVER-3 TRIP 3 CURRENT)

VLV-NC007F (NC34A PZR PORV 5 1 4 FAIL TO POSITION)

MAL-SGL005B (S/G B HI PWR LVL 7 100 2 MIN 5 CONTROLLER FAILURE)

MAL-CF005D (CF LINE BRK INSIDE 11 7.5e+5 2 MIN 6 CONTAINMENT S/G D)

MAL-CF005D (CF LINE BRK 12 22e+6 7 INSIDE CONTAINMENT S/G D)

VLV-NV047A (NV253B NV PUMPS n/a SUCT FROM FWST FAIL AUTO 8 ACTIONS)

MAL-IRX015L13 (STUCK ROD L13 n/a 7 9 ON RX TRIP)

RACK n/a LOA-RC068 (RACKOUT RC PMP1D)

OUT Ensure TRIGGER 12 = x01o063g Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 4 of 32

Catawba Nuclear Station NRC Exam September 2012

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, decrease reactor power to 85%

BOOTH INSTRUCTOR ACTION IF the SOC is called to be informed of the power decrease, REPEAT the information.

3.3 Scenario EVENT 2, Continuous rod motion BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 1 to give the control rods a signal to start stepping in.

BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with the control rods, REPEAT back the information.

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

BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with the 2A RN Pump, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Environmental Chemistry is called, REPEAT back the information.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 5 of 32

Catawba Nuclear Station NRC Exam September 2012 3.5 Scenario EVENT 4, 1N-34A (PZR PORV) fails open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to fail open 1NC-34A (PZR PORV).

3.6 Scenario EVENT 5, 1CF-37 (1B S/G Feed Reg Vlv) fails closed BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 7 to fail 1CF-37 (S/G B Feed Reg Vlv) closed.

BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with 1CF-37, REPEAT back the information.

3.7 Scenario EVENT 6, Feed line leak inside containment on 1D S/G.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 11 to initiate a feed line leak on the 1D S/G.

3.8 Scenario EVENTS 7, 8, and 9, Feed line break inside containment on 1D S/G.

BOOTH INSTRUCTOR ACTION IF operator is dispatched to secure all ice condenser air handling units, REPEAT back the information BOOTH INSTRUCTOR ACTION IF operator is dispatched to place containment hydrogen analyzers in service, REPEAT back the information BOOTH INSTRUCTOR ACTION IF Secondary Chemistry is notified to sample all S/Gs for activity, REPEAT the order.

BOOTH INSTRUCTOR ACTION IF RP is contacted to frisk the cation columns for activity, REPEAT back the order.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 6 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 7 of 32 Event

Description:

Power decrease to 85% power.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: Crew will begin with a power decrease. BOP will perform a boration per OP/1/6150/009, Enclosure 4.2. Amount of dilution will be determined by the power decrease plan. The RO will input turbine target data. These two evolutions may be performed concurrently. Initial conditions are complete. A reactivity management brief will be performed during turnover.

Step 3.1 is complete.

BOP Perform a boration.

RO Input target into the main turbine control panel.

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

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) 3.3 Ensure 1NV-238A (B/A Xfer Pmp To Blender Ctrl)

BOP controller in auto.

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

3.5 Record the desired volume of boric acid to be added.

BOP

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

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

NOTE: Boric Acid flow rates > 32 gpm may result in a boric acid flow deviation annunciator.

3.9 Adjust the controller for 1NV-238A (B/A Xfer Pmp To BOP Blender Ctrl) to the desired flow.

NOTE TO EVALUATOR: Step 3.10 will be N/Ad Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 7 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 8 of 32 Event

Description:

Power decrease to 85% power.

Time Position Applicants Actions or Behavior 3.11 IF AT ANY TIME it is desired to divert letdown to the RHT manually operate 1NV-172A (3-Way Divert To VCT-RHT) as follows:

3.11.1 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) to the "RHT" position.

3.11.2 Ensure VCT level is monitored continuously while diverting to the RHT.

NOTE: Procedure may continue while performing the following step.

BOP 3.11.3 WHEN desired VCT level is reached return 1NV-172A (3-Way Divert To VCTRHT) to auto as follows:

3.11.3.1 Place the control switch for 1NV-172A (3-Way Divert To VCTRHT) in the "VCT" position.

3.11.3.2 Place the control switch for 1NV-172A (3-Way Divert To VCTRHT) in the "AUTO" position.

3.12 IF AT ANY TIME during the makeup it becomes necessary to change the makeup flow rate, adjust the BOP setpoint for 1NV-238A (B/A Xfer Pmp To Blender Ctrl) as necessary to achieve the desired flow.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 8 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 9 of 32 Event

Description:

Power decrease to 85% power.

Time Position Applicants Actions or Behavior 3.13 IF AT ANY TIME while boration is in progress it becomes necessary to stop the boration, perform the following:

3.13.1 Place the "NC MAKEUP CONTROL" switch to the "STOP" position.

3.13.2 Ensure the following valves close: (R.M.)

1NV-238A (B/A To Blender Ctrl Vlv)

1NV-186A (B/A Blender Otlt To VCT Otlt) 3.13.3 Record boric acid volume added as indicated on the Boric Acid counter. ____________ gallons 3.13.4 WHEN conditions allow resuming the boration, perform the following:

3.13.4.1 Determine remaining volume to be added by subtracting the amount previously added (Step 3.13.3) from the desired volume to be added (Step 3.5).

BOP __________ - __________ = ___________ gallons (Step 3.5) (Step 3.13.3) 3.13.4.2 Adjust boric acid counter to the volume of boric acid determined in Step 3.13.4.1.

(R.M.)

3.13.4.3 Place the "NC MAKEUP CONTROL" switch in the "START" position. (R.M.)

3.13.4.4 Verify the following:

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

1NV-186A (B/A Blender Otlt To VCT Otlt) opens 3.13.4.5 IF in "AUTO", verify the boric acid pump starts.

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

BOP

Control rod motion

NC System Tavg

Reactor Power 3.15 Place the "NC MAKEUP CONTROL" switch to the BOP "START" position. (R.M.)

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 9 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 10 of 32 Event

Description:

Power decrease to 85% power.

Time Position Applicants Actions or Behavior 3.16 Verify the following:

1NV-238A (B/A To Blender Ctrl Vlv) modulates to BOP 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.

3.18 Verify proper flow by observing the Boric Acid Counter.

BOP

{PIP 96-0137}

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 counter, ensure the following valves close:

BOP (R.M.)

1NV-238A (B/A To Blender Ctrl Vlv)

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

NOTE TO EVALUATOR: Step 3.20 will be N/Ad 3.21 IF automatic makeup is desired, perform one of 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 the system was previously BOP 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 "AUTO".

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

NOTE TO EVALUATOR: Step 3.22 will be N/Ad END OF BORATION Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 10 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 11 of 32 Event

Description:

Power decrease to 85% power.

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) starting at step 3.2.2.

3.2.2 Decrease turbine generator load by performing the following:

3.2.2.1 Select "LOAD RATE" and verify it illuminates.

3.2.2.2 Input the desired load rate.

3.2.2.3 Select "ENTER" and verify "LOAD RATE" goes dark 3.2.2.4 Select "TARGET" and verify it illuminates.

3.2.2.5 Input the desired load target.

RO 3.2.2.6 Select "ENTER" and verify "TARGET" goes dark.

3.2.2.7 Verify new load target appears on Target Display.

3.2.2.8 Select "GO" and verify it illuminates to start load decrease.

3.2.2.9 Coordinate with Secondary Chemistry to adjust S/G blowdown flowrates to obtain maximum blowdown for the appropriate load END OF PREPARATION FOR POWER DECREASE ON THE TURBINE PANEL.

Booth Operator will insert Trigger 1 for EVENT 2 at discretion of lead examiner.

END OF EVENT 1 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 11 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 12 of 32 Event

Description:

Continuous rod motion Time Position Applicants Actions or Behavior EVENT 2 Indications: An audible clicking noise will be heard as the control rods begin to insert without a demand signal present.

Recognize rod motion without demand and place the CRD BANK RO SELECT switch in MAN.

NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/015, Rod Control Malfunctions, Case II (Continuous Rod Movement).

1. Ensure "CRD BANK SELECT" switch - IN RO MANUAL.

RO 2. Verify all rod motion - STOPS.

NOTE For T-Ref failures, T-Ref will need to be determined for current power level.

3. Manually adjust control rods as necessary to maintain T-Avg RO within 1°F of T-Ref

4. Verify the following channels - NORMAL FOR EXISTING PLANT CONDITIONS:

BOP or

NC Loop A T-Avg RO

NC Loop B T-Avg

NC Loop C T-Avg

NC Loop D T-Avg BOP or

5. Determine and correct cause of continuous rod movement.

RO

6. Ensure compliance with appropriate Tech Specs:

3.1.1 (Shutdown Margin (SDM))

3.1.4 (Rod Group Alignment Limits)

3.1.5 (Shutdown Bank Insertion Limits)

SRO

3.1.6 (Control Bank Insertion Limits)

3.3.1 (Reactor Trip Instrumentation)

3.3.2 (ESFAS Instrumentation)

3.4.2 (RCS Minimum Temperature for Criticality).

NOTE TO EVALUATOR: The SRO will determine that no Tech Spec entries are required.

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

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 12 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 13 of 32 Event

Description:

Continuous rod motion Time Position Applicants Actions or Behavior

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).

8. WHEN rod control problem is repaired, THEN perform the following:

a. Ensure T-Avg - WITHIN 1°F OF T-REF.

b. WHEN desired, THEN place control rods in "AUTO".

c. Ensure steam dumps - IN DESIRED MODE FOR EXISTING PLANT CONDITIONS.

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

END OF EVENT 2 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 13 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 14 of 32 Event

Description:

Loss of 2A RN Pump.

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

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

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

BOP or 3. Verify RN System - IN NORMAL DUAL SUPPLY HEADER SRO ALIGNMENT.

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

5. Verify each operating RN pump discharge flow - LESS THAN BOP 23,000 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 BOP THAN 8,600 GPM.

BOP 9. Verify RN - AVAILABLE TO ALL UNIT 1 AND UNIT 2 D/G(S).

10. Determine VC/YC status as follows:

BOP

Verify VC/YC - ALIGNED TO OPERATING RN TRAIN.

Verify YC Chiller - RUNNING.

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

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 14 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 15 of 32 Event

Description:

Loss of 2A RN Pump.

Time Position Applicants Actions or Behavior

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 T.S. 3.7.8 Condition A should be entered.

Booth Operator will insert Trigger 5 for EVENT 4 at discretion of lead examiner.

13. Determine required notifications:

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

SRO

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

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

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

END OF EVENT 3 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 15 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 16 of 32 Event

Description:

1NC-34A (PZR PORV) fails open Time Position Applicants Actions or Behavior EVENT 4 Indications: 1AD-6, E/10 PZR PORV DISCH HI TEMP 1AD-6, F/8 PZR LO PRESS CONTROL OAC pt C1Q0318 VLV NC34A PZR POWER OPERATED RELIEF - OPEN BOP Attempt to close 1NC-34A (PZR PORV)

CRITICAL BOP Close 1NC-33A (PZR PORV ISOL)

STEP 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:

BOP

a. Manually close Pzr PORV(s).

CRITCAL b. IF any Pzr PORV cannot be closed, THEN:

BOP STEP 1) Close the affected PORV(s) isolation valve.

NOTE TO EVALUATOR: Step 2) of RNO does not apply.

NOTE Control rods may withdraw on decreasing NC pressure.

BOP 2. Verify Pzr spray valve(s) - CLOSED.

BOP 3. Verify all Pzr heaters - ENERGIZED.

BOP 4. Ensure 1NV-37A (NV Supply To Pzr Aux Spray) - CLOSED.

NOTE Positive reactivity is inserted during an increase in NC pressure which may cause auto rod insertion.

BOP 5. Verify NC pressure - STABLE OR INCREASING.

6. WHEN NC pressure is stable, THEN:

Stabilize unit at appropriate power level.

Adjust the following as required to maintain T-Avg within 1°F CREW of T-Ref:

Turbine load

Control rods

Boron concentration.

NOTE TO EVALUATOR: Step 7 does not apply.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 16 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 17 of 32 Event

Description:

1NC-34A (PZR PORV) fails open Time Position Applicants Actions or Behavior

8. Ensure compliance with appropriate Tech Specs:

3.3.1 (Reactor Trip System (RTS) Instrumentation)

3.3.2 (Engineered Safety Features Actuation System (ESFAS) 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)

3.4.4 (RCS Loops - MODES 1 and 2)

3.4.5 (RCS Loops - MODE 3)

3.4.6 (RCS Loops - MODE 4)

3.4.9 (Pressurizer)

3.4.10 (Pressurizer Safety Valves)

3.4.11 (Pressurizer Power Operated Relief Valves

3.4.13 (RCS Operational Leakage).

NOTE TO EVALUATOR: The SRO should determine T.S. 3.4.1 (RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB)

Limits) Condition A, and 3.4.11 (Pressurizer Power Operated Relief Valves (PORVs)) Condition B should be entered.

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

END OF EVENT 4 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 17 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 5 Page 18 of 32 Event

Description:

1CF-37 (1B S/G Feed Reg Vlv) fails closed.

Time Position Applicants Actions or Behavior Booth Operator will insert Trigger 7 for EVENT 5 at discretion of lead examiner.

EVENT 5 Indications: 1AD-4, B/2 S/G B LEVEL DEVIATION 1AD-4, C/2 S/G B FLOW MISMATCH LO CF FLOW Place 1CF-37 (S/G B Feed Reg Vlv) in Manual and throttle as RO necessary to control 1B S/G level.

NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/006, Loss of S/G Feedwater, Case III (CF Control Not in Auto).

1. IF AT ANY TIME S/G levels approaching:

83% N/R level (S/G HI-HI Level Turb Trip)

OR

11% N/R level (S/G LO-LO Level Rx Trip).

CREW THEN:

a. Manually trip reactor.

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

2. Verify the following: GO TO Case I (Loss of CF Supply To S/Gs).

RO or

At least one CF pump - IN SERVICE BOP

1AD-3, C/6 "CF ISOL TRN A" - DARK

1AD-3, D/6 "CF ISOL TRN B" - DARK.

RO or 3. IF AT ANY TIME any CF main feed reg valve in manual, THEN BOP ensure associated feed reg bypass valve in manual.

Booth Operator will insert Trigger 11 for EVENT 6 at discretion of lead examiner.

4. Verify CF pump speed controller for in Perform the following:

RO or service CF pump(s):

BOP

IN AUTO

RESPONDING ADEQUATELY

5. Verify all S/G CF control valves:

RO or

IN AUTO BOP

RESPONDING ADEQUATELY Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 18 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 5 Page 19 of 32 Event

Description:

1CF-37 (1B S/G Feed Reg Vlv) fails closed.

Time Position Applicants Actions or Behavior

5. RNO Perform the following for the affected S/G(s):

a. Ensure affected controller(s) - IN MANUAL.

b. IF AT ANY TIME S/G level not on program, THEN RO or adjust CF flow to obtain a slight trend in the appropriate BOP direction.

c. IF AT ANY TIME control valve adjustment is required, THEN attempt to maintain CF/SM D/P constant during CF control valve adjustments

6. Verify the following:

RO or

S/G level(s) - STABLE BOP

S/G level(s) - APPROXIMATELY AT PROGRAM

Malfunction - CORRECTED.

6. RNO Perform the following:

a. Continue to control CF/SM D/P and S/G CF Flow rates to stabilize level in affected S/G(s) approximately at program level.

b. WHEN all the following conditions met:

CREW

S/G level(s) - STABLE

S/G level(s) - APPROXIMATELY AT PROGRAM

Malfunction - CORRECTED.

THEN GO TO Step 7.

c. Do not continue in this procedure until all conditions met.

NOTE TO EVALUATOR: RNO Step 6.b will not be met during this scenario.

END OF EVENT 5 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 19 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 20 of 32 Event

Description:

Feed line leak inside containment on 1D S/G.

Time Position Applicants Actions or Behavior EVENT 6 Indications: 1AD-13, F/5 HVAC PANEL TROUBLE 1AD-19, C/9 VQ CONTAINMENT PRESSURE ALERT 1AD-13, A/7 ICE COND LOWER INLET DOORS OPEN, 1AD-13, A/8 ICE BED RTT LO/HI/HI-HI TEMP NOTE TO EVALUATOR: It is intended that the crew will make the decision to manually trip the reactor and then manually initiate safety injection based on containment pressure. When the reactor is tripped, proceed to EVENT 7 NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/028, Secondary Steam Leak RO and

1. Monitor Enclosure 1 (Foldout Page).

BOP RO 2. Verify turbine - ONLINE.

3. Verify the following:

RO

Reactor power - LESS THAN OR EQUAL TO 100% POWER

T-Avg - WITHIN 1.5°F OF T-Ref.

4. Verify proper reactor response as follows:

RO

Control rods - IN AUTO AND STEPPING IN

P/R neutron flux - DECREASING

4. RNO IF T-Avg is greater than 1.5°F higher than T-Ref, THEN RO insert control rods as required to maintain T-Avg within 1°F of T-Ref.

5. IF AT ANY TIME reactor power is greater than 100%, THEN RO perform Step 3 RNO.

BOP 6. Verify Pzr level - STABLE OR INCREASING.

NOTE TO EVALUATOR: Depending on the speed of the crew, Pzr level may be stable.

6. RNO Perform the following:

BOP

a. Maintain charging flow less than 180 GPM.

6. RNO b. THROTTLE 1NV-294 (NV Pmps A&B Disch Flow Ctrl) to BOP stabilize Pzr level.

6. RNO c. IF Pzr level is stable OR increasing, THEN GO TO Step SRO 7.

7. IF AT ANY TIME while in this procedure Pzr level is SRO decreasing in an uncontrolled manner, THEN RETURN TO Step 6.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 20 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 21 of 32 Event

Description:

Feed line leak inside containment on 1D S/G.

Time Position Applicants Actions or Behavior

8. IF AT ANY TIME VCT level goes below 23%, THEN align NV pump suction to FWST as follows:

a. OPEN the following valves:

1NV-252A (NV Pumps Suct From FWST)

BOP

1NV-253B (NV Pumps Suct From FWST).

b. CLOSE the following valves:

1NV-188A (VCT Otlt Isol)

1NV-189B (VCT Otlt Isol).

9. Attempt to identify and isolate leak as follows:

a. Verify the following conditions - a. Perform the following:

NORMAL:

RO/BOP

Containment temperature

Containment pressure

Containment humidity ventilation units in low speed.

Containment floor & equipment sump

9. RNO 2. a. Perform the following:

RO

1) Evacuate containment.

9. RNO a. 2) Perform the following:

BOP a) Start all lower containment ventilation unit in low speed.

BOP 9. RNO a.2) b) Start all upper containment ventilation units.

9. RNO a.2) c) Place all upper and lower containment ventilation BOP units in "MAX" cooling.

9. RNO a. 3) IF AT ANY TIME containment pressure reaches 1.2 RO PSIG, THEN perform the following:

a) Ensure reactor tripped.

BOP 9. RNO a.3) b) Ensure S/I initiated.

9. RNO a.3) c) CLOSE the following valves:

RO or

All MSIVs BOP

All MSIV bypass valves.

9. RNO a.3) d) GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety CREW Injection).

TRANSITION TO EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection)

END OF EVENT 6 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 21 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8 and 9 Page 22 of 32 Event

Description:

Feed line break inside containment on 1D S/G Time Position Applicants Actions or Behavior EVENTS 7, 8 and 9 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

2. Verify Reactor Trip: Perform the following:

All rod bottom lights - LIT RO

All reactor trip and bypass breakers - OPEN

I/R power - DECREASING.

2. RNO Perform the following:

RO

a. Trip reactor.

END OF EVENT 9 NOTE TO EVALUATOR: RNO 2.b. will not apply

3. Verify Turbine Trip: Perform the following:

RO

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

5. Verify S/I is actuated:

RO 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:

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

9. Verify Phase A Containment Isolation status as follows:

a. Phase A "RESET" lights - DARK.

BOP

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

LIT.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 22 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8 and 9 Page 23 of 32 Event

Description:

Feed line break inside containment on 1D S/G Time Position Applicants Actions or Behavior

10. Verify proper Phase B actuation as follows:

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

10. RNO a. Perform the following:

BOP 1) Verify Phase B Isolation has actuated as follows:

a) Phase B Isolation "RESET" lights - DARK.

NOTE TO EVALUATOR: Step 10 RNO a.1) b) will not apply.

c) Verify following monitor light panel lights - LIT:

Group 1 Sp lights

Group 5 Sp lights

Group 5 St light L/11.

NOTE TO EVALUATOR: Step 10 RNO a.1) d) will not apply.

RO or

10. RNO a. 2) Stop all NC pumps.

BOP BOP 10. RNO a. 3) Maintain seal injection flow.

BOP 10. RNO a. 4) Energize H2 igniters.

10. RNO a. 5) Dispatch operator to perform the following:

a) Secure all ice condenser air handling units.

REFER TO EP/1/A/5000/G-1 (Generic RO or Enclosures), Enclosure 11 (Securing All Ice BOP Condenser Units).

b) Place containment H2 analyzers in service.

REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems).

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

SRO 10. RNO a. 7) GO TO Step 11.

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: Perform the following for affected train(s):

BOP

NV pumps

ND pumps

NI pumps.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 23 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8 and 9 Page 24 of 32 Event

Description:

Feed line break inside containment on 1D S/G Time Position Applicants Actions or Behavior BOP 13. Verify all KC pumps - ON.

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

14. RNO Perform the following:

BOP

a. IF any Unit 2 RN pump is off, THEN start affected pump(s).

NOTE TO EVALUATOR: The BOP will make an attempt to start the 2A RN pump, but it will not start.

NOTE TO EVALUATOR: Step 14 RNO b. will not apply

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: 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.

16. RNO Perform the following:

a. Verify Main Steam Isolation as follows:

RO

All MSIVs - CLOSED

All MSIV bypass valves - CLOSED

All S/G PORVs - CLOSED.

NOTE TO EVALUATOR: Step 16 RNO b. will not apply

17. Verify proper S/I flow as follows:

RO

a. "NV S/I FLOW" - INDICATING FLOW.

RO b. NC pressure - LESS THAN 1620 PSIG.

17.b. RNO b. Perform the following:

RO 1) Ensure ND pump miniflow valve on operating ND pump(s) - OPEN.

NOTE TO EVALUATOR: Step 17 RNO b. 2) will not apply SRO 3) GO TO Step 18.

NOTE Spent Fuel Pool parameters should be monitored within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of event.

18. WHEN time and manpower permit, THEN monitor Spent RO or Fuel Pool level and temperature. REFER TO EP/1/A/5000/G-1 BOP (Generic Enclosures), Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring).

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 24 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8 and 9 Page 25 of 32 Event

Description:

Feed line break inside containment on 1D S/G Time Position Applicants Actions or Behavior

19. Control S/G levels as follows:

RO

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

b. WHEN at least one S/G N/R level is greater than RO 11% (29% ACC), THEN THROTTLE feed flow to maintain all S/G N/R levels between 11% (29% ACC) and 50%.

NOTE TO EVALUATOR: ACC values will be used for the remainder of the scenario.

RO 20. Verify all CA isolation valves - OPEN.

21. Verify S/I equipment status based on monitor light panel -

BOP IN PROPER ALIGNMENT.

NOTE TO EVALUATOR: If the BOP has not identified and corrected 1NV-253B (NV PUMPS SUCT FROM FWST) failure to open until this step, they will transition to the RNO and open 1NV-253B.

END OF EVENT 8 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).

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 BOP the following:

1) CLOSE Pzr PORV(s).

23 RNO a. 2) IF any Pzr PORV cannot be closed, THEN CLOSE BOP its isolation valve.

NOTE TO EVALUATOR: Step 23 RNO.a.3) will not apply BOP 23. b. Normal Pzr spray valves - CLOSED.

BOP 23. c. At least one Pzr PORV isolation valve - OPEN.

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

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 25 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8 and 9 Page 26 of 32 Event

Description:

Feed line break inside containment on 1D S/G Time Position Applicants Actions or Behavior

25. Verify main steamlines intact:

RO or

All S/G pressures - STABLE OR INCREASING BOP

ALL S/Gs - PRESSURIZED.

25. RNO IF pressure in any S/G is decreasing in an uncontrolled manner OR any S/G is depressurized, THEN perform the following:

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

b. GO TO EP/1/A/5000/E-2 (Faulted Steam Generator Isolation).

TRANSITION TO EP/1/A/5000/E-2 (Faulted Steam Generator Isolation)

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 26 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8 and 9 Page 27 of 32 Event

Description:

Feed line break inside containment on 1D S/G Time Position Applicants Actions or Behavior EP/1/A/5000/E-2 (Faulted Steam Generator Isolation)

RO or

1. Monitor Enclosure 1 (Foldout Page).

BOP

2. Maintain any faulted S/G or secondary break isolated during RO or subsequent recovery actions unless needed for NC System BOP cooldown.

3. Verify the following valves - CLOSED:

RO or

All MSIVs BOP

All MSIV bypass valves.

RO or

4. Verify at least one S/G pressure - STABLE OR INCREASING.

BOP

5. Identify faulted S/G(s) as follows:

Verify any S/G pressure - DECREASING IN AN RO or UNCONTROLLED MANNER BOP OR

Verify any S/G - DEPRESSURIZED.

RO or 6. Verify at least one intact S/G - AVAILABLE FOR NC SYSTEM BOP COOLDOWN.

7. Isolate all faulted S/G(s) as follows:

S/G 1D:

a. Verify S/G 1D Feedwater Isolation status light (1SI-5) -

LIT

b. Verify S/G 1D PORV - CLOSED.

c. CLOSE the following valves:

RO or CRITICAL 1) 1SM-74B (S/G 1D Otlt Hdr Bldwn C/V).

BOP STEP 2) 1CA-42B (CA Pmp B Disch To S/G 1D Isol).

3) 1CA-38A (CA Pmp 1 Disch To S/G 1D Isol).

d. Verify the following blowdown isolation valves - CLOSED:

1) 1BB-8A (S/G 1D Bldwn Cont Isol Insd).

2) 1BB-147B (S/G 1D Bldwn Cont Isol Byp).

3) 1BB-10B (S/G 1D Bldwn Cont Isol Otsd).

8. WHEN NC T-Hots start to increase, THEN dump steam from RO intact S/G PORVs to stabilize NC T-Hots.

9. Verify the following annunciators - DARK.

RO or

1AD-5, H/4 "CACST LO LEVEL" BOP

1AD-8, B/1 "UST LO LEVEL".

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 27 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8 and 9 Page 28 of 32 Event

Description:

Feed line break inside containment on 1D S/G Time Position Applicants Actions or Behavior

10. Verify secondary radiation normal as follows:

a. Ensure the following signals - RESET:

BOP 1) Phase A Containment Isolations.

2) CA System valve control

3) KC NC NI NM St signals.

NOTE TO EVALUATOR: CA System valve control will have been previously reset by the RO in order to throttle S/G N/R levels as directed by E-0 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).

BOP e. Verify S/G(s) fault - INSIDE CONTAINMENT.

RO or f. WHEN activity results are reported, THEN verify all S/Gs BOP indicate no activity.

11. Verify S/I termination criteria:

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

b. Verify secondary heat sink as follows:

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

ACC)

RO OR

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

RO c. NC pressure - STABLE OR INCREASING.

BOP d. Pzr level - GREATER THAN 11% (30% ACC).

CREW e. GO TO EP/1/A/5000/ES-1.1 (Safety Injection Termination).

TRANSITION TO EP/1/A/5000/ES-1.1 (Safety Injection Termination)

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 28 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8 and 9 Page 29 of 32 Event

Description:

Feed line break inside containment on 1D S/G Time Position Applicants Actions or Behavior EP/1/A/5000/ES-1.1 (Safety Injection Termination)

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

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.

NOTE TO EVALUATOR: Phase A will have been previously reset by the BOP as directed by E-2

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 BOP 6. Verify VI pressure - GREATER THAN 50 PSIG.

7. Isolate NV S/I flowpath as follows:

a. Verify the following valves - OPEN:

BOP

1NV-252A (NV Pumps Suct From FWST)

1NV-253B (NV Pumps Suct From FWST).

b. Verify the following valves - OPEN:

BOP

1NV-203A (NV Pumps A&B Recirc Isol)

1NV-202B (NV Pumps A&B Recirc Isol)

c. CLOSE the following valves:

BOP

1NI-9A (NV Pmp C/L Inj Isol)

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

END OF EVENT 7 END OF SCENARIO Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 29 of 32

Catawba Nuclear Station NRC Exam December 2010 Attachment List ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - OP/1/A/6150/009 Enclosure 5 (Manual Operation of the Makeup Controls)

ATTACHMENT 4 - AP/1/A/5500/020 Enclosure 1 (Foldout Page)

ATTACHMENT 5 - AP/1/A/5500/028 Enclosure 1 (Foldout Page)

ATTACHMENT 6 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page)

ATTACHMENT 7 - EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification)

ATTACHMENT 8 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control)

ATTACHMENT 9 - EP/1/A/5000/E-0 Enclosure 5 (VX System Operation)

ATTACHMENT 10 - EP/1/A/5000/E-2 Enclosure 1 (Foldout Page)

ATTACHMENT 11 - EP/1/A/5000/ES-1.1 Enclosure 1 (Foldout Page)

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 30 of 32

Catawba Nuclear Station NRC Exam December 2010 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK C-1 Close the block valve upstream of the stuck open PZR PORV C-2 Isolate the faulted SG before transition out of E-2.

Comments:

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 31 of 32

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 100% EOL 80 PPM per OAC Controlling Procedure

OP/1/A/6100/003 (Controlling Procedure for Unit Operation), Enclosure 4.3 (Unit Operation Between 85% and 100% Power). The steps through 3.15 are complete.

Other Information Needed to Assume the Shift

1D RC Pump (Circulating Water Pump) is tagged out for a motor replacement.

Direction for the crew is to decrease power to approx. 85 % for the Control Valve Movement Test NEOs Available Six NEOs 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Catawba Nuclear Station NRC Exam September 2012 HLP NRC EXAM SCENARIO # 3 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 1 of 36

Catawba Nuclear Station NRC Exam September 2012 Facility: Catawba NRC Exam 2012 Scenario No.: 3 Op Test No.: 1 Examiners: Operators: SRO RO BOP Initial Conditions: IC#178; Unit 1 is at 75% power, MOL. 1B LH Pump is tagged out.

Turnover: Unit 1 is at 75% power, MOL. 1B LH Pump is tagged out for a bearing replacement and is expected to be returned to service in approximately one hour. Direction for the crew is to increase power to 100% per the reactivity management plan.

Event Malf. No. Event Event No. Type* Description N-BOP 1 R-RO Begin increasing power to 100%.

N-SRO 2 SM002D C-RO 1D S/G PORV fails open. AP/28 TS-SRO 3 KC027F C-BOP 1KC-C37A (KC pump miniflow) valve fails open.

C-SRO 4 ENB013C TS-SRO N43 fails. AP/16 5 IPE003A C-RO 1NC-27 (PZR spray) fails open. AP/11 TS-SRO 6 SG001A C-ALL 1A S/G tube leak. (15-300 gpm ramp) AP/10 VLV-BB001 7 VLV-BB002 C-BOP S/G blowdown flow control valves fail to auto close on hi rad.

VLV-BB003 VLV-BB004 8 SG001A M-ALL 1A S/G tube rupture.

9 NI004B C-BOP NI-10B (NV Cold Leg Injection Vlv) fails to auto open.

10 CA007C C-RO 1CA-187 (S/G 1C CA NOZZ TEMPERING ISOL) doesnt close on feedwater isolation, but can be manually closed.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 2 of 36

Catawba Nuclear Station NRC Exam September 2012 Scenario 3 - Summary Initial Condition Unit 1 is at 75% power, MOL. 1B LH Pump is tagged out.

Turnover:

Initial Condition IC 178, Unit 1 is at 75% power, MOL. 1B LH Pump is tagged out for a bearing replacement. It is expected to be returned to service in approximately one to two hours.

Direction for the crew is to begin increasing power to 100%.

Event 1 The BOP will setup for and begin a dilution to raise temperature. The RO will setup the turbine controls for the turbine load increase.

Event 2 1D S/G PORV fails open. The RO will manually close the block valve (it takes 60 seconds for this valve to close) to isolate the steam leak. AP/28 (Secondary Steam Leak) will be entered. A TS evaluation by the SRO is required.

Event 3 1KC-C37A (KC pump miniflow) valve fails open (Component Cooling Water system). The BOP will take manual action to close the miniflow to prevent runout damage to the operating KC pump, or start additional KC pumps.

Event 4 Power Range NI N43 fails. This failure requires the BOP to move to an area of the Control Room to investigate the failure. No credit is being taken for a BOP malfunction. The purpose is to ensure that the BOP is removed from the vicinity of the control board for the PZR spray valve failure (Event 6), and ensure that the RO will be required to address the spray valve failure.

AP/16 (Malfunction of Nuclear Instrumentation) will be entered. A TS evaluation by the SRO is required.

Event 5 1NC-27 (PZR Spray Valve) fails open. Manual action by the RO is required to close the spray valve. AP/11 (Pressurizer Pressure Anomalies) will be entered. A TS evaluation by the SRO is required.

Event 6 A tube leak on 1A S/G begins ramping in at 0 gpm. AP/10 (Reactor Coolant Leak) will be entered.

Event 7 Radiation Monitor 1EMF-33 (Condenser Air Ejector Monitor) will fail to auto isolate the S/G blowdown flow control valves. The BOP is required to manually close these valves. The crew will determine that a manual reactor trip is required due to the severity level (increasing) of the tube leak.

Event 8 When the reactor is manually tripped, the severity of the leak will increase to a tube rupture.

Event 9 1NI-10B (NV Cold Leg Injection Valve) fails to auto open on the SI. The BOP will take manual action to open the valve for full injection.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 3 of 36

Catawba Nuclear Station NRC Exam September 2012 Event 10 1CA-187 (S/G 1C CA NOZZ TEMPERING ISOL) doesnt close on feedwater isolation requiring operator action to manually close the valve.

Critical task 1 - Isolate feed/steam from ruptured S/G before a transition to ECA-3.1.

Critical task 2 - Terminate S/I before water release occurs from the ruptured S/G PORV or safety.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 4 of 36

Catawba Nuclear Station NRC Exam September 2012 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC 178 START TIME:__________

Trigger Instructor Action Delay Ramp Delete Event Final In MAL-SM002D (S/G PORV SV1 1 100 2 FAILURE)

VLV-KC027F (1KC-C37A TRAIN A 3 RECIRC LINE ISOL VLV FAIL TO 1 3 POSITION)

VLV-KC027F (1KC-C37A TRAIN A 4 RECIRC LINE ISOL VLV FAIL TO 1 1 SEC 3 POSITION)

MAL-ENB013C (P/R 43 BLOWN 7 INST 4 FUSE)

MAL-IPE003A (PZR SPRAY VLV 9 100 5 NC-27 FAIL, MAN CTRL) 11 MAL-SG001A (S/G A TUBE LEAK) 300 5 MIN 6 VLV-BB001 (BB69 - S/G A n/a BLOWDOWN CTRL VLV FAIL AUTO 7 ACTIONS)

VLV-BB002 (BB73 - S/G B n/a BLOWDOWN CTRL VLV FAIL AUTO 7 ACTIONS)

VLV-BB003 (BB24 - S/G C n/a BLOWDOWN CTRL VLV FAIL AUTO 7 ACTIONS)

VLV-BB004 (BB65 - S/G n/a BLOWDOWN CTRL VLV FAIL AUTO 7 ACTIONS)

MAL-NI004B (ESS HDR ISOL VLV n/a 9 NI10 FAILS TO OPEN)

MAL-CA007C (S/G TEMPERING n/a OPEN 10 VLV CA187 FAILURE)

MAL-CA007C (S/G TEMPERING 14 OPEN 1 SEC 10 VLV CA187 FAILURE)

Ensure TRIGGER 4 = x11i120c Ensure TRIGGER 14 = x02i122c Ensure TRIGGER 9 = xnpo001b Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 5 of 36

Catawba Nuclear Station NRC Exam September 2012

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, increase reactor power to 100%.

BOOTH INSTRUCTOR ACTION IF the SOC is called to be informed of the power increase, REPEAT the information.

3.3 Scenario EVENT 2, 1D S/G PORV fails open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 1 to cause 1SV-1 to fail open.

BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with 1SV-1, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF RP is notified of the leak, REPEAT back the information.

3.4 Scenario EVENT 3, 1KC-C37A opens BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause 1KC-C37A to fail open Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 6 of 36

Catawba Nuclear Station NRC Exam September 2012 BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with 1KC-C37A, REPEAT back the information.

3.5 Scenario EVENT 4, N-43 blown instrument fuse.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 7 to cause the instrument fuse for N-43 to blow.

3.6 Scenario EVENT 5, 1NC-27 fails open BOOTH INSTRUCTOR ACTION IF IAE is contacted to fail bistables per model W/O #00874531, REPEAT back the order.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with 1NC-27, REPEAT the order.

3.7 Scenario EVENT 6, S/G 1A Tube Leak BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 11 to cause a tube leak on the 1A S/G.

BOOTH INSTRUCTOR ACTION IF RP is notified to frisk all cation columns for activity, REPEAT the information and order.

BOOTH INSTRUCTOR ACTION If Chemistry is notified to sample all S/Gs for activity, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Secondary Chemistry is notified to determine affected S/G by sampling REPEAT the order.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 7 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 8 of 36 Event

Description:

Power increase to 100% power.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: Crew will begin with a power increase. BOP will perform a dilution per OP/1/6150/009, Enclosure 4.3. Amount of dilution will be determined by the power increase plan. The RO will input turbine target data. These two evolutions may be performed concurrently. Initial conditions are complete. A reactivity management brief will be performed during turnover. Step 3.1 is complete.

BOP Perform a dilution.

RO Input targets into the main turbine control panel.

NOTE TO EVALUATOR: The CREW may decide to input targets to the main turbine prior to performing a dilution.

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

3.2 IF the blender is set for automatic makeup per Enclosure 4.1 BOP (Automatic 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) 3.4 Ensure 1NV-242A (RMWST To B/A Blender Ctrl) controller in BOP auto.

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

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

3.8 Place the NC MAKEUP MODE SELECT switch to the BOP DILUTE 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 reduce flow rate to 80 gpm to avoid the Rx Make-up Flow Deviation alarm and associated automatic actions.

3.9 Adjust the setpoint for 1NV-242A (RMWST To B/A Blender Ctrl)

BOP to the desired flow.

NOTE TO EVALUATOR: Step 3.10 will not apply.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 8 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 9 of 36 Event

Description:

Power increase to 100% power.

Time Position Applicants Actions or Behavior 3.11 IF AT ANY TIME it is desired to divert letdown to the RHT manually operate 1NV-172A (3-Way Divert To VCT-RHT) as follows:

3.11.1 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) to the RHT position.

3.11.2 Ensure VCT level is monitored continuously while diverting to the RHT.

BOP NOTE: Procedure may continue while performing the following step.

3.11.3 WHEN desired VCT level is reached return 1NV-172A (3-Way Divert To VCTRHT) to auto as follows:

3.11.3.1 Place the control switch for 1NV-172A (3-Way Divert To VCTRHT) in the VCT position.

3.11.3.2 Place the control switch for 1NV-172A (3-Way Divert To VCTRHT) in the AUTO position.

3.12 IF AT ANY TIME during the makeup it becomes necessary to change the makeup flow rate, adjust the setpoint for 1NV-242A BOP (RMWST To B/A Blender Ctrl) as necessary to achieve the desired flow.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 9 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 10 of 36 Event

Description:

Power increase to 100% power.

Time Position Applicants Actions or Behavior 3.13 IF AT ANY TIME while dilution is in progress it becomes necessary to stop the dilution, perform the following:

3.13.1 Place the NC MAKEUP CONTROL switch to the STOP position.

3.13.2 Ensure the following valves close:

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

1NV-181A (B/A Blender Otlt To VCT) 3.13.3 IF in AUTO, verify the reactor makeup water pump stops.

3.13.4 Record reactor makeup water volume added as indicated on the total makeup counter.

____________ gallons 3.13.5 WHEN conditions allow resuming the dilution, perform the following:

3.13.5.1 Determine remaining volume to be added by BOP subtracting the amount previously added (Step 3.13.4) from the desired volume to be added (Step 3.6).

____________ - __________ = ___________ gallons (Step 3.6) (Step 3.13.4) 3.13.5.2 Adjust total makeup counter to the volume of reactor makeup water determined in Step 3.13.5.1. (R.M.)

3.13.5.3 Place the NC MAKEUP CONTROL switch in the START position. (R.M.)

3.13.5.4 Verify the following:

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

1NV-181A (B/A Blender Otlt To VCT) opens 3.13.5.5 IF in AUTO, verify the reactor makeup water pump starts.

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

BOP

Control rod motion

NC System Tavg

Reactor Power 3.15 Place the NC MAKEUP CONTROL switch in the START BOP position. (R.M.)

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 10 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 11 of 36 Event

Description:

Power increase to 100% power.

Time Position Applicants Actions or Behavior 3.16 Verify the following:

1NV-242A (RMWST To B/A Blender Ctrl) modulates to BOP 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 termination.

3.18 WHEN the desired volume of reactor makeup water is reached on the total makeup counter, ensure the following valves close.

BOP (R.M.)

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 BOP 4.1 (Automatic Makeup), perform the following:

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 will be N/Ad END OF DILUTION Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 11 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 12 of 36 Event

Description:

Power increase to 100% power.

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) starting at step 3.1.2.

3.1.2 Increase turbine generator load by performing the following:

3.1.2.1 Select LOAD RATE and verify it illuminates.

3.1.2.2 Input the desired load rate.

3.1.2.3 Select ENTER or OK and verify LOAD RATE goes dark.

3.1.2.4 Select TARGET and verify it illuminates.

3.1.2.5 Input the desired load target.

RO 3.1.2.6 Select ENTER and verify TARGET light goes dark.

3.1.2.7 Verify new load target appears on Target Display.

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

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

END OF PREPARTION FOR POWER INCREASE ON THE TURBINE PANEL.

Booth Operator will insert Trigger 1 for EVENT 2 at discretion of lead examiner.

END OF EVENT 1 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 12 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 13 of 36 Event

Description:

1D S/G PORV fails open Time Position Applicants Actions or Behavior EVENT 2 Indications: OAC PT C1Q1524 VLV SV1 S/G D POWER OPERATED RELIEF - OPEN NOTE TO EVALUATOR: The CREW may choose to address the PORV per the OAC alarm response procedure.

NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/028, Secondary Steam Leak CREW 1. Monitor Enclosure 1 (Foldout Page).

RO 2. Verify turbine - ONLINE.

3. Verify the following:

RO

Reactor power - LESS THAN OR EQUAL TO 100% POWER

T-Avg - WITHIN 1.5°F OF T-Ref.

4. Verify proper reactor response as follows:

RO

Control rods - IN AUTO AND STEPPING IN

P/R neutron flux - DECREASING.

4. RNO IF T-Avg is greater than 1.5°F higher follows: than RO T-Ref, THEN insert control rods as required to maintain T-Avg within 1°F of T-Ref.

5. IF AT ANY TIME reactor power is greater than 100%, THEN CREW perform Step 3 RNO.

BOP 6. Verify Pzr level - STABLE OR INCREASING.

7. IF AT ANY TIME while in this procedure Pzr level is CREW decreasing in an uncontrolled manner, THEN RETURN TO Step 6.

8. IF AT ANY TIME VCT level goes below 23%, THEN align NV pump suction to FWST as follows:

a. OPEN the following valves:

1NV-252A (NV Pumps Suct From FWST)

BOP

1NV-253B (NV Pumps Suct From FWST).

b. CLOSE the following valves:

1NV-188A (VCT Otlt Isol)

1NV-189B (VCT Otlt Isol).

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 13 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 14 of 36 Event

Description:

1D S/G PORV fails open Time Position Applicants Actions or Behavior

9. Attempt to identify and isolate leak as follows:

a. Verify the following conditions - NORMAL:

Containment temperature CREW

Containment pressure

Containment floor & equipment sump level

b. Dispatch operators to locate and identify source of steam leak.

RO c. Verify S/G PORVs - CLOSED.

9.c. RNO c. IF S/G pressure is less than 1090 PSIG, THEN perform the following:

1) CLOSE affected S/G PORV.

RO

2) IF S/G PORV is still open, THEN perform the following:

a) CLOSE affected S/G PORV isolation valve.

Booth Operator will insert Trigger 3 for Event 3 at discretion of lead examiner.

NOTE TO EVALUATOR: Step 9.c RNO c.2)b) will not apply.

d. Verify condenser dump valves - CLOSED.

RO or

e. Verify atmospheric dump valves - CLOSED.

BOP

f. Verify CA PMP #1 - OFF.

NOTE TO EVALUATOR: The CREW should determine that the leak is isolated and that the next step does not apply.

g. IF leak is suspected to be in a doghouse, THEN CLOSE the following valves:

Outside DH:

1SM-77A (S/G 1A Otlt Hdr Bldwn C/V)

RO or

1SM-74B (S/G 1D Otlt Hdr Bldwn C/V).

BOP OR

Inside DH:

1SM-76B (S/G 1B Otlt Hdr Bldwn C/V)

1SM-75A (S/G 1C Otlt Hdr Bldwn C/V).

10. Determine required notifications:

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

SRO

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

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 14 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 15 of 36 Event

Description:

1D S/G PORV fails open Time Position Applicants Actions or Behavior RO or

11. Notify RP of leak.

BOP CREW 12. Verify - LEAK ISOLATED.

13. Determine long term plant status. RETURN TO procedure SRO and step in effect.

END OF EVENT 2 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 15 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 16 of 36 Event

Description:

1KC-C37A fails open Time Position Applicants Actions or Behavior EVENT 3 Indications: 1AD-9, F/5 KC TRAIN SINGLE PUMP RUNOUT 1AD-6, D/1,2,3,4 NCP A,B,C,D MTR LOWER BRG KC OUTLET LO FLOW 1AD-6, E/1,2,3,4 NCPA,B,C,D THERMAL BARRIER KC OUTLET HI/LOW 1AD-7, D/1 SEAL WATER HX KC HI/LO/FLOW BOP Recognize 1KC-C37A is open.

BOP CLOSE 1KC-C37A.

NOTE TO EVALUATOR: The following step is taken from the Immediate Actions of OP/1/A/100/010 J, Annunciator Response for Panel 1AD-9, F/5 (KC TRAIN A SINGLE PUMP RUNOUT).

BOP 1. Close 1KC-C37A (Trn 1A Miniflow Isol).

Booth Operator will insert Trigger 7 for Event 4 at discretion of lead examiner.

END OF EVENT 3 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 16 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 17 of 36 Event

Description:

N1-43 blown instrument fuse.

Time Position Applicants Actions or Behavior EVENT 4 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/1 P/R LOWER DET HI FLUX DEV OR AUTO DEFEAT 1AD-2, B/2 P/R UPPER DET HI FLUX DEV OR AUTO DEFEAT 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 NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/016 Malfunction of Nuclear Instrumentation System, Case IV (Power Range Malfunction)

RO 1. Verify all rod motion - STOPPED.

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

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

3. Identify failed P/R channel:

N-41 OR

N-42 RO OR

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:

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 Sep 2012 NUREG 1021 Revision 9 Page 17 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 18 of 36 Event

Description:

N1-43 blown instrument fuse.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: EVENT 5 will be initiated in the following step.

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

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

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

BOP 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.

9. De-energize the affected channel as follows:

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

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

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

NOTE TO EVALUATOR: It is anticipated that the CREW will proceed to the next event, but may return to this procedure following completion of AP/1/A/5500/011.

10. Ensure affected channel bistables are in the required state.

CREW REFER TO Enclosure 1 (P/R Bistables That Must Be Tripped).

RO

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

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

RO

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

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

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 18 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 19 of 36 Event

Description:

N1-43 blown instrument fuse.

Time Position Applicants Actions or Behavior

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 SRO should determine that the following Tech Spec 3.3.1 conditions for associated functions should be entered:

2. Power Range Neutron Flux

a. High - condition D

3. Power Range Neutron Flux High Positive Rate - condition D

6. Overtemperature T - condition E

7. Overpower T - condition E

16. Reactor Trip System Interlocks

b. Low Power Reactor Trips Block, P-7, - condition S

c. Power Range Neutron Flux, P-8, - condition S

d. Power Range Neutron Flux, P-9, - condition S

e. Power Range Neutron Flux, P-10, - condition R These can be covered during a follow up.

16. 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 17. Notify Reactor Group Engineer of occurrence.

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

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

END OF EVENT 4 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 19 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 20 of 36 Event

Description:

1NC-27 (Pzr Srpray Valve) fails open Time Position Applicants Actions or Behavior EVENT 5 Indications: OAC point C1L4455 NORMAL SPRAY FLOW ACTIVATED 1AD-6, F/8 PZR LO PRESS CONTROL RO Recognizes 1NC-27 (PZR SPRAY CTRL FRM LOOP A) is open RO Verifies Pressurizer pressure is normal RO Places controller for 1NC-27 in Manual and closes 1NC-27.

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.

BOP 2. Verify Pzr spray valve(s) - CLOSED.

2.a. RNO Perform the following:

BOP

a. Manually close affected spray valve(s).

NOTE TO EVALUATOR: Step 2 RNO b. will not apply BOP 3. Verify all Pzr heaters - ENERGIZED.

BOP 4. Ensure 1NV-37A (NV Supply To Pzr Aux Spray) - CLOSED.

BOP 5. Verify NC pressure - STABLE OR INCREASING.

6. WHEN NC pressure is stable, THEN:

Stabilize unit at appropriate power level.

Adjust the following as required to maintain T-Avg within 1°F RO and of T-Ref:

BOP

Turbine load

Control rods

Boron concentration.

7. IF a Pzr pressure channel failed, THEN perform following:

a. Verify P-11 PZR S/I BLOCK PERMISSIVE status light (1SI-

18) in required state for unit conditions.

b. Notify IAE to fail following bistables for affected channel per RO or Model W/O #00874531. Bistables shall be tripped within 72 BOP hours:

Pzr low pressure S/I

OT Delta T

Pzr high pressure Reactor Trip

Pzr low pressure Reactor Trip.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 20 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 3 Event # 5 Page 21 of 36 Event

Description:

1NC-27 (Pzr Srpray Valve) fails open Time Position Applicants Actions or Behavior

8. Ensure compliance with appropriate Tech Specs:

3.3.1 (Reactor Trip System (RTS) Instrumentation)

3.3.2 (Engineered Safety Features Actuation System (ESFAS) Instrumentation)

3.3.3 (Post Accident Monitoring (PAM) Instrumentation)

3.3.4 (Remote Shutdown System)

3.4.1 (RCS Pressure, Temperature, and Flow Departure BOP From Nucleate Boiling (DNB) Limits)

3.4.4 (RCS Loops - MODES 1 and 2)

3.4.5 (RCS Loops - MODE 3)

3.4.6 (RCS Loops - MODE 4)

3.4.9 (Pressurizer)

3.4.10 (Pressurizer Safety Valves)

3.4.11 (Pressurizer Power Operated Relief Valves (PORVs))

3.4.13 (RCS Operational Leakage).

NOTE TO EVALUATOR: The SRO will determine that Tech Spec 3.4.1 Condition A should be entered

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

Booth Operator will insert Trigger 11 for Event 6 at discretion of lead examiner.

END OF EVENT 5 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 21 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7 Page 22 of 36 Event

Description:

A tube leak develops on 1A S/G tube leak (15-300 gpm) Radiation Monitor 1EMF-33 will fail to isolate S/G Blowdown requiring manual action.

Time Position Applicants Actions or Behavior EVENTS 6 AND 7 Indications: 1RAD-1, B/1 1EMF33 CSAE EXHAUST HI RAD 1RAD-1, B/4 1EMF-71 S/G A LEAKAGE HI RAD 1RAD-1, E/7 1EMF-74 S/G D LEAKAGE HI RAD CREW Recognizes symptoms of a S/G tube leak Performs actions of the annunciator response for 1RAD-1, BOP B/1(1EMF CSAE EXHAUST HI RAD) and closes the BB (S/G Blowdown) flow control valves.

Enter AP/1/A/5500/010, Reactor Coolant Leak, Case I (Steam CREW Generator Tube Leak)

NOTE TO EVALUATOR: EVENT 7 will end when the BOP closes the BB (S/G Blowdown Flow Control Valves on 1MC-4 NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/010, Reactor Coolant Leak, Case I (Steam Generator Tube Leak)

RO and 1. Monitor Enclosure 1 (Case I Steam Generator Tube Leak BOP Foldout Page).

BOP 2. Verify Pzr level - STABLE OR INCREASING.

2. RNO: Perform the following:

a. Maintain charging flow less than 180 GPM.

BOP

b. THROTTLE 1NV-294 (NV Pmps A&B Disch Flow Ctrl) to stabilize Pzr level.

NOTE TO EVALUATOR: Crew should determine that step 2 RNO c. does not apply BOP c. IF Pzr level stable OR increasing, THEN GO TO Step 3.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 22 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6 Page 23 of 36 Event

Description:

A tube leak develops on 1A S/G tube leak (15-300 gpm)

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: AT some time the CREW will determine that pressurizer level cannot be maintained and will make the decision to manually trip the reactor and manually initiate safety injection per Enclosure 1, at which point the CREW will transition to EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

d. IF Pzr level continues to decrease, THEN perform the following:

1) Reduce letdown flow to 45 GPM as follows:

a) IF 1NV-10A (Letdn Orif 1B Otlt Cont Isol) open, THEN perform the following:

(1) Control 1NV-148 (Letdn Press Control) to establish letdown pressure between 375 - 400 PSIG.

BOP (2) THROTTLE 1NV-849 (Letdn Flow Var Orif Ctrl) for 45 GPM letdown flow.

(3) WHEN 45 GPM letdown flow established, THEN adjust 1NV-148 (Letdn Press Control) to maintain letdown pressure at 350 PSIG.

(4) WHEN letdown pressure is stable at 350 PSIG, THEN place 1NV-148 (Letdn Press Control) in auto.

2) IF Pzr level continues to decrease, THEN ensure the following valves closed:

BOP

1NV-10A (Letdn Orif 1B Otlt Cont Isol)

1NV-11A (Letdn Orif 1C Otlt Cont Isol)

1NV-13A (Letdn Orif 1A Otlt ContIsol).

NOTE TO EVALUATOR: Crew should determine that step 2 RNO d.3) does not apply

4) IF Pzr level continues to decrease OR Pzr level cannot be maintained greater than 4%, THEN perform the following:

CREW a) Trip reactor.

b) WHEN reactor tripped verified, THEN initiate S/I.

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

END EVENT 6 TRANSITION TO EP/1/A/5000/E-0 (Reator Trip or Safety Injection)

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 23 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 8, 9 and 10 Page 24 of 36 Event

Description:

1A S/G tube rupture, 1NI-10B ( NV Cold Leg Injection Vlv) fails to auto open, 1CA-187 (S/G 1C CA NOZZ TEMPERING ISOL) doesnt close of feedwater isolation.

Time Position Applicants Actions or Behavior EVENTS 8, 9, AND 10 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

2. Verify Reactor Trip: (Immediate action step)

All rod bottom lights - LIT RO

All reactor trip and bypass breakers - OPEN

I/R power - DECREASING.

3. Verify Turbine Trip: (Immediate action step)

RO

All turbine stop valves - CLOSED BOP 4. Verify 1ETA and 1ETB - ENERGIZED. (Immediate action step)

5. Verify S/I is actuated: (Immediate action step)

RO 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:

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 is not obtained, THEN CLOSE valves.

END EVENT 10

9. Verify Phase A Containment Isolation status as follows:

a. Phase A "RESET" lights - DARK.

BOP

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 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 24 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 8 and 9 Page 25 of 36 Event

Description:

1A S/G tube rupture, 1NI-10B (NV Cold Leg Injection Vlv) fails to open Time Position Applicants Actions or Behavior RO or b. IF AT ANY TIME containment pressure exceeds 3 PSIG while BOP 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: Perform the following for affected train(s):

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:

REFER TO Enclosure 2 (Ventilation System Verification).

BOP

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

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:

RO

a. "NV S/I FLOW" - INDICATING FLOW.

RO b. NC pressure - LESS THAN 1620 PSIG.

17.b. RNO b. Perform the following:

RO 1) Ensure ND pump miniflow valve on operating ND pump(s) - OPEN.

NOTE TO EVALUATOR: Step 17 RNO b. 2) will not apply SRO 3) GO TO Step 18.

NOTE Spent Fuel Pool parameters should be monitored within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of event.

18. WHEN time and manpower permit, THEN monitor Spent Fuel RO or Pool level and temperature. REFER TO EP/1/A/5000/G-1 BOP (Generic Enclosures), Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring).

19. Control S/G levels as follows:

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

RO b. WHEN at least one S/G N/R level is greater than 11% (29%

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

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 25 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 8 and 9 Page 26 of 36 Event

Description:

1A S/G tube rupture, 1NI-10B (NV Cold Leg Injection Vlv) fails to open Time Position Applicants Actions or Behavior 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.

END OF EVENT 9 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).

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

BOP

a. All Pzr PORVs - CLOSED.

BOP 23. b. Normal Pzr spray valves - CLOSED.

BOP 23. c. At least one Pzr PORV isolation valve - OPEN.

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

25. Verify main steamlines intact:

RO or

All S/G pressures - STABLE OR INCREASING BOP

ALL S/Gs - PRESSURIZED.

26. Verify S/G tubes are 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 is lit OR any S/G level is increasing in an uncontrolled manner, THEN concurrently:

CREW

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

GO TO EP/1/A/5000/E-3 (Steam Generator Tube Rupture).

TRANSITION TO EP/1/A/5000/E-3 (Steam Generator Tube Rupture)

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 26 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 8 Page 27 of 36 Event

Description:

1A S/G tube rupture Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The following actions are from EP/1/A/5000/E-3 (Steam Generator Tube Rupture).

RO and

1. Monitor Enclosure 1 (Foldout Page).

BOP

2. Identify ruptured S/G(s) as follows:

S/G level - INCREASING IN AN UNCONTROLLED MANNER.

OR

RP determines ruptured S/G by frisking the cation columns in the CT lab.

OR The following EMF trip 1 lights - LIT:

1EMF-26 (Steamline 1A)

1EMF-27 (Steamline 1B)

CREW

1EMF-28 (Steamline 1C)

1EMF-29 (Steamline 1D).

OR

IF S/G Sampling is required to identify ruptured S/G(s),

THEN:

a. Ensure the following signals - RESET:

1) Phase A Containment Isolations.

2) CA System valve control.

3) KC NC NI NM St signals.

b. Align all S/Gs for Chemistry sampling.

c. Notify Chemistry to sample all S/Gs for activity.

3. Verify at least one intact S/G - AVAILABLE FOR NC SYSTEM RO COOLDOWN.

4. Isolate steam 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 TASK RO

1) Close 1SM-77A (S/G 1A Otlt Hdr Bldwn C/V).

2) Verify the following blowdown isolation valves -

CLOSED:

a) 1BB-56A (S/G 1A Bldwn Cont Isol Insd).

b) 1BB-148B (S/G 1A Bldwn Cont Isol Byp).

c) 1BB-57B (S/G 1A Bldwn Cont Isol Otsd).

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 27 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 8 Page 28 of 36 Event

Description:

1A S/G tube rupture Time Position Applicants Actions or Behavior

5. Close the following valves on all ruptured S/G(s):

CRITICAL RO

MSIV TASK

MSIV bypass valve.

6. Control ruptured S/G(s) level as follows:

a. Verify ruptured S/G(s) N/R level - GREATER THAN 11% (29%

ACC).

CRITICAL b. Isolate feed flow to all ruptured S/G(s) as follows:

TASK RO

S/G 1A:

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.

BOP 7. Verify any NC pump - ON.

8. WHEN "P-11 PZR S/I BLOCK PERMISSIVE" status light (1SI-

18) is lit, THEN:

a. Depress ECCS steam pressure "BLOCK" pushbuttons.

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

BOP c. Maintain NC pressure less than 1955 PSIG using one of the following:

Pzr spray OR

Pzr PORV.

NOTE

NC pump trip criteria based on NC subcooling does not apply after starting a controlled cooldown.

After the low steamline pressure main steam isolation signal is blocked Main Steam Isolation will occur if the high steam pressure rate setpoint is exceeded.

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

9. Initiate NC System cooldown as follows:

a. Verify all ruptured S/G(s) pressure - GREATER THAN 320 RO PSIG.

b. Determine required core exit temperature from the table below:

NOTE TO EVALUATOR: The SRO and BOP will use the table in step 9 to determine target core exit temperature Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 28 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 8 Page 29 of 36 Event

Description:

1A S/G tube rupture Time Position Applicants Actions or Behavior

c. Ensure ruptured S/G(s) isolated as follows:

1) Verify the following valves on all ruptured S/G(s) -

CLOSED:

RO

MSIV

MSIV bypass valves.

2) Verify S/G PORV on ruptured S/G(s) - CLOSED OR ISOLATED.

NOTE TO EVALUATOR: Step 9.c.3) will be N/Ad.

d. Verify the condenser is available as follows:

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

MSIV on intact S/G(s) - OPEN.

e. Verify steam dumps - IN PRESSURE MODE.

9.e. RNO e. Place steam dumps in pressure mode as follows:

1) Place "STM DUMP CTRL" M/A station in manual.

2) Adjust "STM DUMP CTRL" M/A station output to match "% STM DUMP DEMAND" (1SMP5211).

RO

3) WHEN output on the "STM DUMP CTRL" M/A station is equal to the "% STM DUMP DEMAND" (1SMP5211), THEN place the steam dumps in pressure mode.

f. WHEN "P-12 LO-LO TAVG" status light (1SI-18) is lit, THEN place the steam dump interlock bypass switches in "BYP RO INTLK."

g. Dump steam to condenser from intact S/G(s) at maximum rate while attempting to avoid a Main Steam Isolation.

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

BOP LIT.

9.h. RNO h. 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) is 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.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 29 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 8 Page 30 of 36 Event

Description:

1A S/G tube rupture Time Position Applicants Actions or Behavior

i. WHEN core exit T/Cs are less than required temperature, RO THEN stabilize core exit T/Cs less than required temperature.

10. Control intact S/G levels as follows:

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

RO (29% ACC).

b. Throttle feed flow to maintain all intact S/G N/R levels between 16% (29% ACC) and 50%.

11. Verify Pzr PORV and isolation valve status as follows:

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

BOP

b. All Pzr PORVs - CLOSED.

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

d. IF AT ANY TIME a Pzr PORV opens due to high pressure while in this procedure, THEN perform the following:

1) WHEN Pzr pressure decreases to less than 2315 PSIG, RO or THEN ensure the valve closes or is isolated.

BOP

2) IF Pzr PORV cannot be closed OR isolated, THEN GO TO EP/1/A/5000/ECA-3.1 (SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired).

12. Reset the following:

BOP a. ECCS.

b. D/G load sequencers.

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

13. Ensure the following containment isolation signals - RESET:

BOP

Phase A

Phase B.

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 stoppedas follows:

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.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 30 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 8 Page 31 of 36 Event

Description:

1A S/G tube rupture Time Position Applicants Actions or Behavior RO 16. Verify ruptured S/G(s) - IDENTIFIED.

17. Verify if NC System cooldown should be stopped:

RO a. Verify core exit T/Cs - LESS THAN REQUIRED TEMPERATURE.

NOTE TO EVALUATOR: At this point the required temperature may not have been reached. The crew will hold per the RNO for step 17.a.

17.a RNO Do not continue in this procedure until core exit T/Cs are SRO less than required temperature.

b. Stabilize core exit T/Cs - LESS THAN REQUIRED RO 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.

RO or 19. Verify NC subcooling based on core exit T/Cs - GREATER BOP THAN 20°F.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 31 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 8 Page 32 of 36 Event

Description:

1A S/G tube rupture Time Position Applicants Actions or Behavior

20. Depressurize NC System using PZR Spray as follows:

a. Verify normal Pzr spray flow - AVAILABLE.

b. Verify Pzr level - LESS THAN 68% (50% ACC)

c. Depressurize NC System with maximum available spray.

d. IF AT ANY TIME during this step one of the following conditions exists:

Spray valves are not effective in reducing NC pressure OR

Ruptured S/G(s) NR level is approaching 83% (75%

ACC).

THEN GO TO Step 21.

e. Do not continue until at least one of the following conditions satisfied:

BOP

NC subcooling based on core exit T/Cs - LESS THAN 0°F OR

Pzr level - GREATER THAN 68% (50% ACC)

OR

Both of the following:

NC pressure - LESS THAN RUPTURED S/G(s)

PRESSURE AND

Pzr level - GREATER THAN 11% (30% ACC).

f. CLOSE the following valve(s):

1) Pzr spray valves.

2) 1NV-37A (NV Supply To Pzr Aux Spray).

SRO g. Observe Caution prior to Step 23 and GO TO Step 23.

CAUTION S/I must be terminated when termination criteria are satisfied to prevent overfilling the 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 RO or 11% (29% ACC)

BOP 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 Sep 2012 NUREG 1021 Revision 9 Page 32 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 8 Page 33 of 36 Event

Description:

1A S/G tube rupture Time Position Applicants Actions or Behavior

24. Stop S/I pumps as follows:

BOP a. Stop NI pumps.

b. Ensure only one NV pump - ON.

25. Isolate NV S/I flowpath as follows:

a. Verify the following valves - OPEN:

1NV-252A (NV Pumps Suct From FWST)

CRITICAL

1NV-253B (NV Pumps Suct From FWST).

b. Ensure the following valves - OPEN:

TASK BOP

1NV-203A (NV Pumps A&B Recirc Isol)

1NV-202B (NV Pmps A&B Recirc Isol).

c. Close the following valves:

1NI-9A (NV Pmp C/L Inj Isol)

1NI-10B (NV Pmp C/L Inj Isol).

END OF EVENT 8 END OF SCENARIO Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 33 of 36

Catawba Nuclear Station NRC Exam December 2010 Attachment List ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - OP/1/A/6150/009 Enclosure 5 (Manual Operation of the Makeup Controls)

ATTACHMENT 4 - AP/1/A/5500/028 Enclosure 1 (Foldout Page)

ATTACHMENT 5 - AP/1/A/5500/010 Enclosure 1 (Foldout Page)

ATTACHMENT 6 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page)

ATTACHMENT 7 - EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification)

ATTACHMENT 8 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control)

ATTACHMENT 9 - EP/1/A/5000/E-3 Enclosure 1 (Foldout Page)

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 34 of 36

Catawba Nuclear Station NRC Exam December 2010 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK C-1 Isolate feed/steam from ruptured S/G before a transition to ECA3.1 C-2 Terminate S/I before water release occurs from the ruptured S/G PORV or safety.

Comments:

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 35 of 36

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 75% MOL Per OAC per OAC Controlling Procedure

OP/1/A/6100/003 (Controlling Procedure for Unit Operation), Enclosure 4.1 (Power Increase). The steps through step 3.54 are complete.

Other Information Needed to Assume the Shift

1B LH pump is tagged out to repair a leak on the motor cooler.

Maintenance estimates that repairs will take 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to complete.

Direction for the crew is to increase reactor power to 100% per the reactivity management plan.

NEOs Available Six NEOs 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Catawba Nuclear Station NRC Exam September 2012 HLP NRC EXAM SCENARIO # 5 Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 1 of 41

Catawba Nuclear Station NRC Exam September 2012 Facility: Catawba NRC Exam 2012 Scenario No.: 5 Op Test No.: 1 Examiners: Operators: SRO RO BOP Initial Conditions: IC#180; Unit 1 is at 100% power, MOL. 1A KF pump is tagged out.

Turnover: Unit 1 is at 100% power, MOL, with 1A KF pump tagged out for breaker refurbishment. The crew direction is to reduce power to less than 50% per the reactivity management plan for removing 1A CF pump from service for maintenance on valve 1CF-6 (Recirc. Valve). York County is under a severe thunderstorm watch for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Event Malf. No. Event Event No. Type* Description 1 --- N-BOP R-RO Begin power reduction to < 50%.

N-SRO 2 LOA-NV067 C-BOP 1B NV pump trips. Requires manual start of 1A NV pump. AP/12 TS-SRO 3 EP003B C-BOP Zone A lockout. Runback initiates. AP/03 TS-SRO 4 IRX009 C-RO Control rods fail to auto insert during runback C-SRO 5 MAL-IDE003H C-RO 1SB-24 (Condenser Dump valve) fails open. AP/28 C-SRO 6 NCP003C C-BOP 1NC Pump C Hi-Hi vibration (30 mils). Requires reactor trip.

C-SRO 7 MAL-SM009 M-ALL Ruptured steam equalization header, with all MSIVs fail to close (auto and MAL-SM006E manual).

8 ISE007A/B C-RO Feedwater auto isolation fails (both trains).

9 VE001A C-BOP 1A VE Fan fails to start. Manual start required.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 2 of 41

Catawba Nuclear Station NRC Exam September 2012 Scenario 5 - Summary Initial Condition Unit 1 is at 100% power, MOL. 1A KF pump is tagged out.

Turnover:

Unit 1 is at 100% power, MOL. 1A KF pump is tagged out for breaker refurbishment. It is expected to be returned to service in approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Crew direction is to reduce power to less than 50% per the reactivity management plan for removing 1A CF pump from service for maintenance on 1CF-6 (Recirc Valve). York County is under a severe thunderstorm watch for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Event 1 The crew begins the power reduction to less than 50%. The BOP will setup for and begin boration. The RO will setup and monitor the turbine during the power reduction.

Event 2 1B NV Pump (Charging) trips. Manual action by the BOP to start the 1A NV pump will restore charging. AP/12 (Loss of Charging or Letdown) will be entered. A TS evaluation by the SRO is required.

Event 3 A Zone A lockout occurs, causing a turbine runback. AP/03 (Load Rejection) will be entered. For offsite power sources, a TS evaluation by the SRO is required.

Event 4 Due to the runback rods should auto insert, but this feature will be failed, requiring the RO to manually insert rods. The control rods should be inserting automatically during the runback. The RO will monitor Tavg/Tref mismatch and recognize that the rods are not inserting, and then take manual control of the rods and insert as necessary to maintain Tavg/Tref within 1°F.

Event 5 1SB-24 (Condenser Dump Valve) fails open. The RO is required to take manual action to close this dump valve by selecting the Steam Dump Interlock Bypass Switch to the "OFF/RESET" position.

Event 6 Following the runback a high-high vibration will begin on the 1C NC pump. The value is 30 mils, requiring that the reactor be tripped, and then the pump be tripped. This will be timed such that the crew will have opportunity to recognize and discuss this condition, and the need to trip the reactor and the pump.

Event 7 When the unit is tripped, a rupture of the steam equalization header occurs, concurrent with the failure of all MSIVs to close. Manual action to close the MSIVs will NOT be successful.

Event 8 Feedwater isolation fails to auto actuate (both trains). Manual actuation of at least one train by the RO is required.

Event 9 1A VE (ANNULUS VENTILATION) Fan fails to start on Safety Injection signal. The BOP will manually start the fan.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 3 of 41

Catawba Nuclear Station NRC Exam September 2012 Critical task 1 - Control AFW flowrate to 75 gpm (lowest readable on indicator) per S/G to minimize cooldown rate before an ORANGE path challenge develops to the integrity Critical Safety Function.

Critical task 2 - Manually initiate Main Feedwater Isolation.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 4 of 41

Catawba Nuclear Station NRC Exam September 2012 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC 180 START TIME:__________

Trigger Instructor Action Delay Ramp Delete Event Final In n/a LOA-KF004 (RACKOUT KF PMP RACK A) OUT LOA-NV067 (RACKOUT NV PMP RACK 1 2 1B) OUT MAL-EP003C (ZONE 1A 3 3 LOCKOUT)

MAL-IRX009 (RODS FAIL TO n/a AUTO 4 MOVE)

MAL-IDE 003H (STEAM DUMP 5 100 5 VLV SB24 FAIL TO POSITION)

MAL-IDE 003H (STEAM DUMP 6 100 1 SEC 5 VLV SB24 FAIL TO POSITION)

MAL-NCP003C (NCP C 7 30 6 VIBRATION)

MAL-SM009 (SM HEADER 8 3.855e+6 7 BREAK)

MAL-SM006E (ALL MSI (MSIV) n/a 7 VLV FAIL)

RACK 11 LOA-NI007 (RACKOUT NI54A) 2 MIN 7 IN RACK 11 LOA-NI008 (RACKOUT NI65B) 2 MIN 7 IN RACK 11 LOA-NI009 (RACKOUT NI76A) 2 MIN 7 IN LOA-NI010 (RACKOUT NI88B) RACK 11 2 MIN 7 IN VLV-SM004F (SM7 MSIV A FAIL 13 0 7 TO POSITION)

VLV-SM003F (SM5 MSIV B FAIL 14 0 7 TO POSITION)

VLV-SM002F (SM3 MSIV C FAIL 15 0 7 TO POSITION)

VLV-SM001F (SM1 MSIV D FAIL 16 0 7 TO POSTION)

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 5 of 41

Catawba Nuclear Station NRC Exam September 2012 MAL-ISE007A (AUTO CF ISOL n/a BLOCK 8 SIGNAL TRN A)

MAL-ISE007B(AUTO CF ISOL n/a BLOCK 8 SIGNAL TRN B)

MAL-VE001A (FAN VE-1A n/a 9 DISABLE AUTOSTART RELAY)

Ensure TRIGGER 4 = x02i184l Ensure TRIGGER 8 = x01o063g Ensure TRIGGER 6 = x02i184l l x02i186l

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, decrease reactor power to 50%.

BOOTH INSTRUCTOR ACTION IF the SOC is called to be informed of the power decrease, REPEAT the information 3.3 Scenario EVENT 2, 1B NV Pump trips.

BOOTH INSTRUCTOR ACTION At the discretion of the lead examiner, Insert Trigger 1 to trip off 1B NV pump.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 6 of 41

Catawba Nuclear Station NRC Exam September 2012 BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance are dispatched to investigate the 1B NV Pump and/or breaker, Repeat back the information.

BOOTH INSTRUCTOR ACTION If NEO 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 NEO dispatched to check the 1A NV Pump, after 5 minutes REPORT: The 1A NV Pump is good for continuous run.

BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with 1B NV Pump, REPEAT back the information.

Scenario EVENTs 3 and 4, Zone A lockout, Control rods fail to auto insert.

BOOTH INSTRUCTOR ACTION At the discretion of the lead examiner, Insert Trigger 3, to initiate a Zone A lockout.

BOOTH INSTRUCTOR ACTION When called as transmission dept, REPEAT back information as required.

BOOTH INSTRUCTOR ACTION When notified as SOC, ASK when the unit will return to 100% power.

BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the Zone a lockout, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with the control rods, REPEAT back the information.

3.4 Scenario EVENT 5, 1SB-24 fails open BOOTH INSTRUCTOR ACTION At the discretion of the lead examiner, Insert Trigger 5 to fail open 1SB-24.

BOOTH INSTRUCTOR ACTION If dispatched as NEO, REPORT back after 5 minutes, nothing seems to be wrong with the valve (1SB-24).

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 7 of 41

Catawba Nuclear Station NRC Exam September 2012 BOOTH INSTRUCTOR ACTION If requested, the Unit supervisor will proceed with creating an R&R to isolate 1SB-24.

BOOTH INSTRUCTOR ACTION IF SWM is called to investigate 1SB-24, REPEAT back the information.

3.5 Scenario EVENTs 6, 7, & 8.

BOOTH INSTRUCTOR ACTION At the discretion of the lead examiner, Insert Trigger 7, this will cause Hi-Hi vibrations on 1A NCP.

BOOTH INSTRUCTOR ACTION IF Maintenance is dispatched to isolate air to S/G A,B,C,D, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF station management is contacted to monitor shutdown margin, REPEAT back the information BOOTH INSTRUCTOR ACTION IF station management is contacted to monitor shutdown margin, REPEAT back the information BOOTH INSTRUCTOR ACTION IF periodic boron samples are requested from Primary Chemistry, REPEAT back the information BOOTH INSTRUCTOR ACTION IF RP is requested to monitor the area of the steam fault for radiation and notify the control room of any abnormal radiation conditions, REPEAT back the information BOOTH INSTRUCTOR ACTION IF chemistry is notified to sample all S/Gs for activity, REPEAT back the information BOOTH INSTRUCTOR ACTION IF RP is contacted to frisk all cation columns for activity, REPEAT back the information BOOTH INSTRUCTOR ACTION IF operator is dispatched to restore power to all CLA discharge isolation valves, Insert Trigger 11.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 8 of 41

Catawba Nuclear Station NRC Exam September 2012 BOOTH INSTRUCTOR ACTION IF operator is dispatched to remove power to all CLA discharge isolation valves, Toggle Trigger 11.

BOOTH INSTRUCTOR ACTION When crew returns to step 5 of ECA 2.,1 Insert Trigger 13,14,15 or 16.

Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 9 of 41

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 1 Page 10 of 41 Event

Description:

The crew will begin to reduce power to 50%. The BOP will begin boration and the RO will begin decreasing Turbine load.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: Crew will begin with a power decrease. BOP will perform a boration per OP/1/6150/009, Enclosure 4.2. Amount of dilution will be determined by the power decrease plan. The RO will input turbine target data. These two evolutions may be performed concurrently. Initial conditions are complete. A reactivity management brief will be performed during turnover.

Step 3.1 is complete.

BOP Perform a boration.

RO Input target into the main turbine control panel.

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

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

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

3.5 Record the desired volume of boric acid to be added.

BOP

_________ gallons 3.6 Adjust the boric acid counter to the desired volume of boric acid BOP to be 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 Xfer Pmp To Blender Ctrl). _______gpm BOP 3.8 Place the "NC MAKEUP MODE SELECT" switch in "BORATE".

NOTE: Boric Acid flow rates > 32 gpm may result in a boric acid flow deviation annunciator.

3.9 Adjust the controller for 1NV-238A (B/A Xfer Pmp To Blender BOP Ctrl) to the desired flow.

NOTE TO EVALUATOR: Step 3.10 will be N/Ad Appendix D Catawba NRC Exam Sep 2012 NUREG 1021 Revision 9 Page 10 of 41

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 1 Page 11 of 41 Event