ML13336A399

2. Verify the following:

At least one KC pump - ON.

AND Flow to KC loads presently in service.

2. RNO Perform the following:

a. Start additional KC pump(s) as necessary.

NOTE TO EVALUATOR: Step 2 RNO b. will not apply SRO

3. IF AT ANY TIME all KC pumps are lost, THEN RETURN TO STEP 2.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

4 Page 15 of 33 Event

Description:

1A2 KC Pump Trips Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 15 of 33 NOTE Uncooled letdown may result in loss of NV pumps within a matter of minutes.

4. Verify the following:

1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK AND At least one KC pump - ON.

5. IF AT ANY TIME 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" LIT, THEN perform Step 4 RNO.

6. Verify both KC surge tank levels - 50% - 90% AND STABLE.

7. Start additional KC pump(s) as necessary to supply any KC loads presently in service.

CAUTION A loss of KC cooling to the NC pumps results in a gradual approach to an overheated condition in approximately 10 minutes which will result in shaft seizure.

8. Verify KC flow to NC pumps as follows:

1AD-20, A/1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK 1AD-21, A/1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK.

9. Verify KC available as follows:

a. Verify the following Train A KC non-essential header isolation valves - OPEN:

1KC-230A (Rx Bldg Non-Ess Hdr Isol) 1KC-3A (Rx Bldg Non-Ess Ret Hdr Isol) 1KC-50A (Aux Bldg Non-Ess Hdr Isol) 1KC-1A (Aux Bldg Non-Ess Ret Hdr Isol).

9. b. Verify the following Train B KC non-essential header isolation valves -OPEN:

1KC-228B (Rx Bldg Non-Ess Hdr Isol) 1KC-18B (Rx Bldg Non-Ess Ret Hdr Isol) 1KC-53B (Aux Bldg Non-Ess Hdr Isol) 1KC-2B (Aux Bldg Non-Ess Ret Hdr Isol).

9. c. Start additional KC pump(s) as necessary to supply any KC loads presently in service.

10. Verify KC surge tank levels normal as follows:

a. Verify both KC surge tank levels - 50% - 90% AND STABLE.

10. b. GO TO Step 14.

14. Ensure KC heat exchanger outlet mode switches -

PROPERLY ALIGNED.

CREW

15. Determine and correct cause of loss of KC.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

4 Page 16 of 33 Event

Description:

1A2 KC Pump Trips Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 16 of 33 SRO

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

SLC 16.9-7 (Boration Systems Flow Path-Shutdown)

SLC 16.9-8 (Boration Systems Flow Path-Operating)

SLC 16.9-9 (Boration Systems Pumps -Shutdown)

SLC 16.9-10 (Boration Systems Charging Pumps -

Operating) 3.5.2 (ECCS - Operating) 3.5.3 (ECCS - Shutdown) 3.6.6 (Containment Spray System) 3.7.5 (Auxiliary Feedwater (AFW) System) 3.7.7 (Component Cooling Water (CCW) System).

NOTE TO EVALUATOR: T.S 3.7.7 (Component Cooling Water (CCW) System) Condition A (Restore CCW train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) should be entered.

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

17. Determine required notifications:

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

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

NOTE TO EVALUATOR: Step 18 will not apply.

19. Verify KC surge tanks level as follows:

Greater than 50%

Stable or increasing BOP

20. WHEN plant conditions permit, THEN perform the following:

Return KC pumps to normal operation. REFER TO OP/1/A/6400/005 (Component Cooling Water System).

Return NV Pump 1A to normal cooling as applicable.

REFER TO Enclosure 2 (Alternate Cooling To NV Pump 1A).

21. Verify the following:

1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK 1AD-7, H/3 "VCT HI TEMP" - DARK Normal letdown - IN SERVICE.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

4 Page 17 of 33 Event

Description:

1A2 KC Pump Trips Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 17 of 33 BOP

22. Ensure VCT and letdown path aligned as follows:

a. IF desired to align NV pump suction to VCT, then perform the following:

1) OPEN the following valves:

1NV-188A (VCT Otlt Isol) 1NV-189B (VCT Otlt Isol).

2) CLOSE the following valves:

1NV-252A (NV Pumps Suct From FWST) 1NV-253B (NV Pumps Suct From FWST).

b. WHEN NV suction aligned to VCT, THEN momentarily place 1NV-172A (3-Way Divert To VCT-RHT) to "VCT" position and return to "AUTO".

c. IF desired to restore letdown flow through NV demineralizers, THEN momentarily place 1NV-153A (Letdn Hx Otlt 3-Way Valve) to "DEMIN" position and return to "AUTO".

23. Determine long term plant status. RETURN TO procedure in affect.

END OF EVENT 4

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

5 Page 18 of 33 Event

Description:

1A CFPT trips and 1A CA Pump fails to start.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 18 of 33 EVENT 5 INDICATIONS: 1AD-1, A/6 TURB TRIP ON LOSS OF BOTH CFPTS 1AD-1, B/1 AMSAC TURB TRIP 1AD-1, C/6 EXT TRAIN A-B/ NON TRAIN TURB TRIP 1AD-1, C/7 LO ETS PRESS 1AD-1, E/7 TURB ETS HDR PRESS LO 1AD-5, A/1 CFPT A TRIPPED 1AD/5, A/4 CFPT A COMMON TROUBLE RO Recognize 1A CFPT Trip and subsequent loss of feedwater.

RO Recognize failure of 1A CA Pump to start and attempts to start it.

RO Determines the need to start CAPT #1 and starts it.

CREW ENTERS AP/1/A/5500/006, CASE I NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/006, Loss of S/G Feedwater, Case I (Loss of CF Supply To S/Gs)

1. Verify reactor power - LESS THAN 5%.

2. Verify all S/G hi-hi level alert alarms (1AD-4) - DARK.

3. Verify 1AD-2, F/9 "DCS ALTERNATE ACTION" - DARK.

4. Verify total CA flow - GREATER THAN Perform the following:

450 GPM.

5. Control S/G levels as follows:

a. Verify all S/G N/R levels - GREATER THAN 11%.

b. WHEN at least one S/G N/R level is greater than 11%, THEN throttle feedflow to maintain all S/G N/R levels between 11% -

50%.

6. REFER TO Case II (Loss of Normal CA Supply).

NOTE TO EVALUATOR: The crew may initiate a makeup to the UST per step 2 of Case II.

No other actions from Case II are necessary.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

5 Page 19 of 33 Event

Description:

1A CFPT trips and 1A CA Pump fails to start.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 19 of 33 SRO

7. Ensure compliance with appropriate Tech Specs and SLCs:

3.3.2 (ESFAS Instrumentation) 3.7.5 (Auxiliary Feedwater System)

SLC 16-7.1 (AMSAC).

SLC 16-7.14 (Trip of All Main Feedwater Pumps Turbine Trip Instrumentation).

NOTE TO EVALUATOR: T.S 3.7.5 Auxiliary Feedwater (AFW) System Condition B (Restore AFW train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) should be entered.

Booth Operator inserts Trigger 7 for EVENT 5 at discretion of lead examiner.

8. Determine required notifications:

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

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

CREW

9. Determine and correct cause of loss of CF supply.

10. Verify at least one CF Pump - ON.

NOTE TO EVALUATOR: It is not intended for the next step to be performed in this scenario.

10. RNO Perform a hot restart of one CF Pump. REFER TO OP/1/A/6250/001 (Condensate and Feedwater System).

END OF EVENT 5

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

6 Page 20 of 33 Event

Description:

1NC-32B (PZR PORV) fails open, 1NC-31B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 20 of 33 EVENTS 6 AND 7 Indications:

1AD-2, D/10 DCS TROUBLE 1AD-6, E/10 PZR PORV DISCH HI TEMP 1AD-6, F/8 PZR LO PRESS CONTROL BOP Recognize 1NC-32B open BOP Attempt to close 1NC-32B BOP Attempt to close 1NC-31B RO Manually Trip the Reactor BOP Manually initiate Safety Injection.

NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/011, Pressurizer Pressure Anomalies, Case I (Pressurizer Pressure Decreasing).

1. Verify all Pzr PORVs - CLOSED.

1. RNO Perform the following:

a. Manually close Pzr PORV(s).

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

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

2) IF the Pzr PORV isolation valve cannot be closed, THEN perform the following:

a) IF in Mode 3 with CLAs isolated OR in Mode 4, THEN GO TO AP/1/A/5500/027 (Shutdown LOCA).

b) Trip reactor.

RO c) WHEN reactor tripped OR S/I setpoint reached, THEN ensure S/I initiated.

EVENT 8 CREW d) GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection).

TRANSITION TO E-0 (Reactor Trip or Safety Injection)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

6, 7, 8 Page 21 of 33 Event

Description:

1NC-32B (PZR PORV) fails open. 1NC-31B (PZR PORV ISOL) will not close. 1B NI pump fails to auto start on SI signal. Control rod K14 sticks at 92 steps on reactor trip.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 21 of 33 NOTE TO EVALUATOR: The following steps are from E-0 Reactor Trip or Safety Injection RO and BOP

1. Monitor Enclosure 1 (Foldout Page).

2. Verify Reactor Trip: Perform the following:

All rod bottom lights - LIT All reactor trip and bypass breakers - OPEN I/R power - DECREASING.

2. RNO Perform the following:

a. Trip reactor.

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

3. Verify Turbine Trip: Perform the following:

All turbine stop valves - CLOSED BOP

4. Verify 1ETA and 1ETB - ENERGIZED.

5. Verify S/I is actuated:

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

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

NOTE TO EVALUATOR:

Upon Loss of Subcooling with S/I flow verified, the RO or BOP will trip the NC (Reactor Coolant) pumps within 5 minutes per Enclosure 1 guidance. This satisfies Critical Task # C-2 RO

6. Announce "Unit 1 Safety Injection".

7. Determine required notifications:

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

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

RO or BOP

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.

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

LIT.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

6, 7, 8 Page 22 of 33 Event

Description:

1NC-32B (PZR PORV) fails open. 1NC-31B (PZR PORV ISOL) will not close. 1B NI pump fails to auto start on SI signal.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 22 of 33 BOP

10. Verify proper Phase B actuation as follows:

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

b. IF AT ANY TIME containment pressure exceeds 3 PSIG while in this procedure, THEN perform Step 10.a.

11. Verify proper CA pump status as follows:

a. Motor driven CA pumps - ON.

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

RO and BOP 11.a. RNO a. Perform the following for affected train(s):

1) Reset ECCS.

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

3) Start affected pump(s).

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

11. 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):

NV pumps ND pumps NI pumps.

CRITICAL TASK BOP

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

a. Reset ECCS.

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

c. Start affected pump(s).

END OF EVENT 8 RO or BOP

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

6 Page 23 of 33 Event

Description:

1NC-32B (PZR PORV) fails open, 1NC-31B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 23 of 33 BOP

13. Verify all KC pumps - ON.

NOTE TO EVALUATOR: The crew may decide not to transition to the RNO based on actions taken in event 3.

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

a. Reset ECCS.

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

c. Start affected pump(s).

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

NOTE TO EVALUATOR: Step 13 RNO e. will not apply.

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

15. Verify proper ventilation systems operation as follows:

REFER TO Enclosure 2 (Ventilation System Verification).

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.

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

17. Verify proper S/I flow as follows:

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

b. NC pressure - LESS THAN 1620 PSIG.

c. NI pumps - INDICATING FLOW.

d. NC pressure - LESS THAN 285 PSIG.

RO 17.d. RNO d. Perform the following:

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

NOTE TO EVALUATOR: Step 17 RNO d. 2) will not apply SRO

3) GO TO Step 18.

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.

RO or BOP

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

6 Page 24 of 33 Event

Description:

1NC-32B (PZR PORV) fails open, 1NC-31B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 24 of 33 RO

19. Control S/G levels as follows:

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

NOTE TO EVALUATOR: Although the crew will transition to the RNO for step 19.a., the steps do not apply.

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%.

20. Verify all CA isolation valves - OPEN.

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

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 Temperature Control).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

6 Page 25 of 33 Event

Description:

1NC-32B (PZR PORV) fails open, 1NC-31B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 25 of 33 BOP

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

a. All Pzr PORVs - CLOSED.

BOP CREW

23. RNO a. IF Pzr pressure is less than 2315 PSIG, THEN perform the following:

1) CLOSE Pzr PORV(s).

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

3) IF 1NC-32B OR 1NC-34A cannot be closed OR isolated, THEN perform the following:

a) Align N2 to PORVs by opening the following valves:

1NI-438A (Emer N2 From CLA A to 1NC-34A) 1NI-439B (Emer N2 From CLA B to 1NC-32B).

b) CLOSE affected PZR PORV.

4) IF any Pzr PORV cannot be closed OR isolated, THEN perform the following:

a) Energize H2 igniters.

b) Dispatch operator to perform the following:

(1) Secure all ice condenser air handling units.

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

(2) Place containment H2 analyzers in service.

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

c) IF both the following conditions exist, Containment pressure - HAS REMAINED LESS THAN 3 PSIG Containment pressure - BETWEEN 1 PSIG AND 3 PSIG THEN start one VX fan and secure normal containment ventilation. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), 8 (VX and Containment Ventilation Control).

d) Concurrently:

Implement F-0 (Critical Safety Function Status Trees GO TO to E-1 (Loss of Reactor or Secondary Coolant.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

6 Page 26 of 33 Event

Description:

1NC-32B (PZR PORV) fails open, 1NC-31B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 26 of 33 TRANSITION TO EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant)

NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant)

RO and BOP

1. Monitor Enclosure 1 (Foldout Page).

RO or BOP

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

NOTE TO EVALUATOR: Depending on the pace of the crew, subcooling may be greater than 0ºF in which case the crew would continue to step 3.

RO or BOP

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

a. Ensure all NC pumps - OFF.

b. Maintain seal injection flow.

3. Verify main steamlines intact:

All S/G pressures - STABLE OR INCREASING All S/Gs - PRESSURIZED RO

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

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

(29% ACC).

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

5. Reset the following:

a. ECCS.

b. D/G load sequencers.

c. Phase A

d. Phase B.

RO or BOP

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

6. Establish VI to Containment as follows:

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

Verify VI pressure - GREATER THAN 85 PSIG.

7. Verify secondary radiation - NORMAL:

a. Ensure the following signals - RESET:

1) CA System valve control BOP

2) KC NC NI NM St signals.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

6 Page 27 of 33 Event

Description:

1NC-32B (PZR PORV) fails open, 1NC-31B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 27 of 33 NOTE TO EVALUATOR: The BOP opens the following valves when aligning the S/Gs for chemistry sample in step b. below:

1NM-191B (S/G 1A SMPL HDR CONT ISOL) 1NM-201A (S/G 1B SMPL HDR CONT ISOL) 1NM-211B (S/G 1C SMPL HDR CONT ISOL) 1NM-221A (S/G 1D SMPL HDR CONT ISOL) 1NM-190A (S/G 1A BLDWN SMPL CONT ISOL) 1NM-200B (S/G 1B BLDWN SMPL CONT ISOL) 1NM-210A (S/G 1C BLDWN SMPL CONT ISOL) 1NM-220B (S/G 1D BLDWN SMPL CONT ISOL)

b. Align all S/Gs for Chemistry sampling.

RO or BOP

c. Perform at least one of the following:

Notify Chemistry to sample all S/Gs for activity.

OR Notify RP to frisk all cation columns for activity.

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

1EMF-33 (Condenser Air Ejector Exhaust) 1EMF-26 (Steamline 1A) 1EMF-27 (Steamline 1B) 1EMF-28 (Steamline 1C) 1EMF-29 (Steamline 1D).

e. Verify all S/Gs - INTACT All S/G pressures - STABLE OR INCREASING All S/Gs - PRESSURIZED RO or BOP

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

8. Verify Pzr PORVs and Isolation Valves:

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

b. All Pzr PORVs - CLOSED.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

6 Page 28 of 33 Event

Description:

1NC-32B (PZR PORV) fails open, 1NC-31B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 28 of 33 BOP 8.b. RNO b. IF Pzr pressure is less than 2315 PSIG, THEN perform the following:

1) CLOSE Pzr PORV(s).

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

3) IF any Pzr PORV cannot be closed OR isolated, THEN perform the following:

a) Align N2 to all Pzr PORVs by opening:

1NI-438A (Emer N2 From CLA A To 1NC-34A) 1NI-439B (Emer N2 From CLA B To 1NC-32B).

b) CLOSE affected Pzr PORV.

c. Any Pzr PORV isolation valve - OPEN.

RO or BOP

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

RO or BOP

9. Verify S/I termination criteria:

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

b. Secondary heat sink:.

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

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

c. NC pressure - STABLE OR INCREASING.

d. Pzr level - GREATER THAN 11% (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 Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

6 Page 29 of 33 Event

Description:

1NC-32B (PZR PORV) fails open, 1NC-31B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 29 of 33 NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/ES-1.1 (Safety Injection Termination)

RO and BOP

1. Monitor Enclosure 1 (Foldout Page).

2. Reset the following:

a. ECCS.

b. D/G load sequencers.

c. Phase A.

d. Phase B.

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

3. Establish VI to Containment as follows:

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

Verify VI pressure - GREATER THAN 85 PSIG.

4. Ensure only one NV pump - ON.

RO or BOP

5. Verify NC pressure - STABLE OR INCREASING.

NOTE TO EVALUATOR: The crew may determine that NC pressure is decreasing and go to the RNO and transition to EP/1/A/5000/ES-1.2 (Post LOCA Cooldown and Depressurization.)

6. Verify VI pressure - GREATER THAN 50 PSIG.

7. Isolate NV S/I flowpath as follows:

a. Verify the following valves - OPEN:

1NV-252A (NV Pumps Suct From FWST) 1NV-253B (NV Pumps Suct From FWST).

b. Verify the following valves - OPEN:

1NV-203A (NV Pumps A&B Recirc Isol) 1NV-202B (NV Pmps A&B Recirc Isol).

BOP 7.b. RNO b. Perform the following:

1) OPEN affected valve(s).

2) IF 1NV-203A AND 1NV-202B are open, THEN GO TO Step 7.c.

c. CLOSE the following valves:

1NI-9A (NV Pmp C/L Inj Isol) 1NI-10B (NV Pmp C/L Inj Isol).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event #

6 Page 30 of 33 Event

Description:

1NC-32B (PZR PORV) fails open, 1NC-31B (PZR PORV ISOL) will not close Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 30 of 33 BOP

8. Establish charging as follows:

a. Verify all of the following valves - OPEN:

1NV-44A (NC Pmp A Seal Supply Cont Isol) 1NV-55A (NC Pmp B Seal Supply Cont Isol) 1NV-66A (NC Pmp C Seal Supply Cont Isol) 1NV-77A (NC Pmp D Seal Supply Cont Isol).

b. THROTTLE 1NV-294 (NV Pmps A&B Disch Flow Ctrl) for 32 GPM charging line flow.

c. CLOSE 1NV-309 (Seal Water Injection Flow).

d. OPEN the following valves:

1NV-312A (Chrg Line Cont Isol) 1NV-314B (Chrg Line Cont Isol).

e. Verify 1NV-309 - ABLE TO BE OPERATED FROM CONTROL ROOM.

f. Place 1NV-309 - IN AUTO.

g. Perform the following:

Maintain charging flow less than 180 GPM.

Maintain 32 GPM seal water flow.

9. Control charging as follows:

a. Control charging flow to maintain Pzr level stable.

b. Verify Pzr level - STABLE OR INCREASING.

10. Determine if NI pumps should be stopped:

a. Verify the following:

NC pressure - STABLE OR INCREASING NC pressure - GREATER THAN 1620 PSIG.

CREW 10.a. RNO a. Perform the following:

1) IF any S/G faulted, THEN do not continue until faulted S/G depressurization stops OR criteria for stopping NI pumps are met.

2) IF no S/G faulted OR conditions for stopping NI pumps cannot be satisfied after faulted S/G depressurization stops, THEN GO TO EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Depressurization TRANSITION TO EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Depressurization)

END OF SCENARIO

Catawba Nuclear Station NRC Exam December 2013 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 31 of 33 Attachment List Scenario 1 ATTACHMENT 1 -

Crew Critical Task Summary ATTACHMENT 2 -

Shift Turnover Information ATTACHMENT 3 - AP/1/A/5500/021 Enclosure 1 (Foldout Page), Rev. 042 ATTACHMENT 4 - AP/1/A/5500/006 Case II (Loss of Normal CA Supply), Rev. 041 ATTACHMENT 5 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page), Rev. 041 ATTACHMENT 6 - EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification), Rev. 041 ATTACHMENT 7 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control), Rev. 041 ATTACHMENT 8 - EP/1/A/5000/E-1 Enclosure 1 (Foldout Page), Rev. 028 ATTACHMENT 9 - EP/1/A/5000/E-1 Enclosure 2 (S/I Termination Criteria), Rev. 028 ATTACHMENT 10 - EP/1/A/5000/ES-1.1 Enclosure 1 (Foldout Page), Rev. 032

Catawba Nuclear Station NRC Exam December 2013 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 32 of 33 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT #

CRITICAL TASK C-1 Establish flow from at least one intermediate head ECCS pump prior to transition from E-0.

C-2 Trip NC pumps on loss of subcooling with S/I flow verified per E-0 within 5 minutes of criteria met.

Comments:

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 1%

BOL 1793 PPM per OAC Controlling Procedure OP/1/A/6100/001 (Controlling Procedure for Unit Startup), Enclosure 4.1 (Unit Startup) is in progress up to step 3.195. All Mode 1 prerequisites have been completed.

Other Information Needed to Assume the Shift 1EMF-72 (S/G B Leakage) is out of service. 1A NI Pump is tagged out for preventive maintenance.

Direction for the crew is to shift the operating charging pumps, and then increase power to 13-15% for placing the turbine on-line per the reactivity management plan. York County is under a severe thunderstorm watch for the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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 Severe Thunderstorm Watch for the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Catawba Nuclear Station NRC Exam September 2013 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 1 of 38 HLP NRC EXAM SCENARIO # 2

Catawba Nuclear Station NRC Exam September 2013 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 2 of 38 Facility:

Catawba NRC Exam 2013 Scenario No.: 2 Op Test No.:

2013301 Examiners:

Operators:

SRO RO BOP Initial Conditions:

IC#178; Unit 1 is at 50% power, MOL. Unit 2 is at 100%. 1A NI Pump is tagged out. 1B CBP is tagged out. 1B LH pump is tagged out.

Turnover:

Unit 1 is at 50% power, MOL. Unit 2 is at 100%. 1A NI Pump and the 1B CBP pump are tagged out for preventive maintenance. 1B LH pump is tagged out and is expected to be returned in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

The crew is to begin increasing power to 100% per the reactivity management plan.

Event No.

Malf. No.

Event Type*

Event Description 1

N-BOP R-RO N-SRO Begin increasing reactor power to 100%.

2 NC013 TS-SRO Pressurizer Level channel 2 fails Hi.

3 NV012F C-BOP C-SRO 1NV-15B (Letdown Isolation Valve) fails closed. AP/12 4

KC045 I-BOP I-SRO TS-SRO KC surge tank level transmitter fails low. AP/21 5

EHC007A C-RO C-SRO Operating LH pump (1A) trips. Requires manual turbine trip. AP/02 6

NCP001D C-RO C-SRO 1D NC Pump trips (electrical).

7 NC013D M-ALL LBLOCA 8

ISE002A/B I-BOP I-SRO Both trains Safety Injection fail to auto actuate.

9 VLV-SM002A C-RO C-SRO 1SM-3 MSIV fails to auto close.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Catawba Nuclear Station NRC Exam September 2013 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 3 of 38 Scenario 2 - Summary Initial Condition Unit 1 is at 50% power, MOL. Unit 2 is at 100%. 1A NI Pump is tagged out. 1B CBP is tagged out. 1B LH pump is tagged out.

Turnover:

Unit 1 is at 50% power, MOL. Unit 2 is at 100%. 1A NI Pump is tagged out. 1B CBP is tagged out for preventive maintenance. 1B LH Pump is tagged out and is expected to be returned to service in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . OP/1/A/6100/003 (Controlling Procedure for Unit Startup), Enclosure 4.1 (Power Increase) has been completed up to step 3.52. The crew is to begin increasing power to 100% per the reactivity management plan.

Event 1 A power increase to 100% is begun. The BOP performs the dilution, the RO sets up and monitors the turbine for the power increase.

Event 2 Pressurizer Level channel 2 fails Hi. TS evaluation required.

Event 3 1NV-15B (Letdown Isolation Valve) fails closed. Requires manual action by the BOP to restore letdown. AP/12 (Loss of Charging or Letdown) entry.

Event 4 The level transmitter for the KC Surge Tank (Component Cooling) fails LOW. Requires BOP manual action to restore KC cooling (system realignment). AP/21 (Loss of Component Cooling) entry. The first KC pump start attempt FAILS. TS evaluation required.

Event 5 The operating LH pump (EHC) trips. The automatic turbine trip setpoint (1100 psig) will be reached, but the turbine will NOT automatically trip. Requires manual action by the RO to trip the turbine. AP/02 (Turbine Trip) entry, since only the turbine is tripped. The reactor remains at power.

Event 6 1D NCP (RCP) trips due to an electrical problem. Crew determines that a reactor trip is required.

Event 7 A LBLOCA initiates on the reactor trip.

Event 8 BOTH trains of SI fail to auto actuate. BOP manually actuates both trains of SI.

Event 9 One MSIV fails to auto close. RO manually closes the MSIV.

Critical task 1 - Manually initiate at least one train of SI before transition out of E-0 to enter any E-1 series, E-2 series, or E-3 series procedure or to any FRG.

Critical task 2 - Trip NC pumps on loss of subcooling with S/I flow verified per E-0 within 5 minutes of criteria met.

Catawba Nuclear Station NRC Exam September 2013 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 4 of 38 EXERCISE GUIDE WORKSHEET

1.

INITIAL CONDITIONS:

1.1 Reset to IC 178 START TIME:__________

Trigger Instructor Action Final Delay Ramp Delete In Event n/a LOA-NI003 (RACKOUT NI PMP 1A)

RACK OUT n/a LOA-CM040 (RACKOUT CBP 1B)

RACK OUT n/a OVR-MT016A (HYDR FLUID PMP 1B OFF LT)

OFF n/a OVR-MT016B (HYDR FLUID PMP 1B ON LT)

OFF n/a MAL-EHC007B (EHC HYDRAULIC FLUID PUMP B TRIP) 1 XMT-NC013 (LNC_5150 PZR LVL CH II TO MTR 1NCP5153 + DCS NCAA5154/NCAA5155) 100 2

3 VLV-NV012F (NV15B L/D ISOL OUTSIDE CNMT VLV FAIL TO POSITION) 0 5 SEC 3

5 XMT-KC046 (LKC_5641 KC SURGE TANK KCLS5640 TO VALVES) 0 4

n/a MAL-KC001B (KC PUMP 1A2 FAILURE)

BOTH 4

16 MAL-KC001B (KC PUMP 1A2 FAILURE)

BOTH 1 SEC 4

n/a MAL-KC001A (KC PUMP 1A1 FAILURE)

BOTH 4

18 MAL-KC001A (KC PUMP 1A1 FAILURE)

BOTH 1SEC 4

7 MAL-EHC007A (EHC HYDRAULIC FLUID PUMP A TRIP) 5 n/a MAL-EHC002 (TURBINE TRIP FAILURE)

AUTO 5

9 MAL-NCP001D (NCP D TRIP) 6 10 MAL-NC013D (NC COLD LEG D LEAK) 27.5 7

n/a MAL-ISE002A (AUTO SI TRN A FAILS TO ACTUATE) 8

Catawba Nuclear Station NRC Exam September 2013 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 5 of 38 n/a MAL-ISE002B (AUTO SI TRN B FAILS TO ACTUATE) 8 n/a VLV-SM002A (SM3 MSIV C FAIL AUTO ACTIONS) 9 Ensure TRIGGER 10 = x01o063g l x01o066g Ensure TRIGGER 16 = x11i119n Ensure TRIGGER 18 = x11i122n

Catawba Nuclear Station NRC Exam September 2013 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 6 of 38

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, Pressurizer Level channel 2 fails Hi BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 1 to cause the Pressurizer Level Channel 2 to fail hi BOOTH INSTRUCTOR ACTION IF SWM is called to write a w/r for Pressurizer level channel 2, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF SWM is called to issue model w/o #00874531 to have IAE trip the bistable, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF IAE is called to trip the bistable, REPEAT back the information.

Catawba Nuclear Station NRC Exam September 2013 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 7 of 38 3.4 Scenario EVENT 3, 1NV-15B closes BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause 1NV-15B to close.

BOOTH INSTRUCTOR ACTION WHEN CREW determines that 1NV-15B is closed, THEN CALL THE CONTROL ROOM AND STATE This is Bobby Raines from OTG. We inadvertently put our test equipment on the wrong jumper in the cabinet that affects the letdown valves. The test equipment has been removed so everything affecting letdown should work correctly.

3.5 Scenario EVENT 4, KC Surge Tank level transmitter failure.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to cause the B train KC Surge Tank level transmitter to fail.

BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with the KC Surge Tank level transmitter REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Operator dispatched to the KC Surge Tanks to look for leaks, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance are dispatched to investigate the KC pump and/or breaker, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Unit 2 Operator is contacted for Unit 2 RN miniflow status, RESPOND Unit 2 RN is in normal miniflow alignment.

3.6 Scenario EVENT 5, 1A LH Pump trips requiring manual Turbine trip.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 7 to trip the 1A LH pump and initiate leak on EHC header.

BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance is dispatched to investigate the 1A LH Pump and/or breaker, REPEAT back the order.

Catawba Nuclear Station NRC Exam September 2013 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 8 of 38 BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with the 1A LH Pump and/or breaker, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an Operator is dispatched close 1SP-3, REPEAT back the order.

3.7 Scenario EVENT 6 1D NC Pump Trip BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 9 to cause the 1D NC Pump to trip 3.8 Scenario EVENT 7, LBLOCA 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 notified to frisk all cation columns for activity, REPEAT the order.

BOOTH INSTRUCTOR ACTION IF Operator dispatched to stop the 1A/1B D/G and place in standby readiness, REPEAT the order.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

1 Page 9

of 38 Event

Description:

Power increase to 100% power.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 9 of 38 NOTE TO EVALUATOR: Crew begins with a power increase. BOP performs 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: Applicant may perform a dilution per OP/1/A/6150/009, Boron Concentration Control, Enclosure 5 (Manual Operation Of The Makeup Controls). Refer to Attachment 3.

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

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

1NV-242A (RMWST To B/A Blender Ctrl) 1NV-181A (B/A Blender Otlt To VCT)

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

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

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

BOP 3.8 Place the "NC MAKEUP MODE SELECT" switch to the "DILUTE" position.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

1 Page 10 of 38 Event

Description:

Power increase to 100% power.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 10 of 38 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.

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

NOTE TO EVALUATOR: Step 3.10 will not apply.

BOP 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.

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

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

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

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

1 Page 11 of 38 Event

Description:

Power increase to 100% power.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 11 of 38 BOP 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 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.

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

Control rod motion

NC System Tavg

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

1 Page 12 of 38 Event

Description:

Power increase to 100% power.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 12 of 38 BOP 3.16 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 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.

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

(R.M.)

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

1NV-181A (B/A Blender Otlt To VCT)

BOP 3.19 IF automatic makeup is desired, perform one of the following:

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

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

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 Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

1 Page 13 of 38 Event

Description:

Power increase to 100% power.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 13 of 38 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.

RO 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.

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 PREPARATION FOR POWER INCREASE ON THE TURBINE PANEL.

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

END OF EVENT 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

2 Page 14 of 38 Event

Description:

Pressurizer Level Channel 2 Fails Hi.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 14 of 38 EVENT 2 Indications: 1AD-6, A/9 PZR HI LEVEL ALERT 1AD-2, F/10 DCS TROUBLE OAC pt. C1A0867 PZR LEVEL CH 2 - HI-HI BOP Recognize Pressurizer Level Channel 2 Fails Hi SRO Enters Tech Spec 3.3.1 NOTE TO EVALUATOR: The following steps are from the annunciator response for 1AD-6, A/9 PZR HI LEVEL ALERT SRO IF a channel malfunction has occurred, perform the following:

1. Refer to TS Table 3.3.1-1 for required number of channels.

NOTE TO EVALUATOR: T.S. 3.3.1 (Reactor Trip System Instrumentation) Condition L (Place channel in trip within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) should be entered.

CREW

2. Issue Model W/O #00874531 to have IAE trip the bistable.

CREW

3. Initiate a work request to have the channel repaired.

END OF EVENT 2 Booth Operator inserts Trigger 3 for EVENT 3 at discretion of lead examiner.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

3 Page 15 of 38 Event

Description:

1NV-15B closes. (Loss of Letdown)

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 15 of 38 EVENT 3 INDICATIONS: OAC pt. C1A0452 NV LETDOWN FLOW - LO-LO BOP BOP recognize closure of 1NV-15B SRO Crew enters AP/1/A/5500/012, CASE II NOTE TO EVALUATOR: The following actions are taken from AP/1/A/5500/012, Loss of Charging or Letdown, Case II (Loss of Letdown)

1. Stop any power changes.

2. Ensure the following letdown isolation valves - CLOSED:

1NV-10A (Letdn Orif 1B Otlt Cont Isol) 1NV-11A (Letdn Orif 1C Otlt Cont Isol) 1NV-13A (Letdn Orif 1A Otlt Cont Isol).

3. Verify Pzr level - GREATER THAN 17%.

4. Control charging to stabilize Pzr level at program level while maintaining seal injection flow.

5. Ensure "PZR HTR GROUP 1C" - ON.

6. Control VCT level as follows:

a. Verify NC system makeup - SET FOR DESIRED BORON CONCENTRATION.

b. Verify "NC MAKEUP MODE SELECT" - IN AUTO.

7. Determine and correct cause of loss of letdown.

NOTE TO EVALUATOR: Based on the call from the field about the cause of 1NV-15B closing, the crew may decide to open 1NV-15B at this point.

CREW

8. IF AT ANY TIME excess letdown required, THEN establish excess letdown. REFER TO OP/1/A/6200/001 (Chemical and Volume Control System).

9. Verify proper VC/YC system operation. REFER TO Enclosure 3 (Control Room Ventilation System Verification).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

3 Page 16 of 38 Event

Description:

1NV-15B closes. (Loss of Letdown)

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 16 of 38 SRO

10. Ensure compliance with appropriate Tech Specs:

3.3.1 (Reactor Trip System (RTS) Instrumentation) 3.3.3 (Post Accident Monitoring (PAM) Instrumentation) 3.3.4 (Remote Shutdown System) 3.4.1 (RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits) 3.4.12 (Low Temperature Overpressure Protection (LTOP)

System) 3.4.13 RCS (Operational Leakage).

3.6.3 (Containment Isolation Valves).

NOTE TO EVALUATOR: NO Tech Specs apply.

11. Verify at least one of the following valves - CLOSED:

1NV-1A (NC Letdn To Regen Hx Isol)

OR 1NV-2A (NC Letdn To Regen Hx Isol).

11. RNO GO TO Step 16.

CREW

16. Establish letdown as follows:

a. Verify ability to establish normal letdown - RESTORED.

16. b. Ensure 1NV-849 (Letdn Flow Var Orif Ctrl) valve demand position - 0%.

16. c. Verify the following valves - OPEN:

1NV-1A (NC Letdn To Regen Hx Isol) 1NV-2A (NC Letdn To Regen Hx Isol).

NOTE If LTOP is in service, then 1NC-34A will be made inoperable when the only letdown path aligned is NV system normal letdown. 1NC-34A LTOP operability is based on the letdown alignment. (PIP C-10-1320)

16. d. OPEN the following valves:

1NV-15B (Letdn Cont Isol) 1NV-10A (Letdn Orif 1B Otlt Cont Isol).

16. e. Adjust 1NV-294 (NV Pmps A&B Disch Flow Ctrl) as necessary to maintain letdown subcooled in following steps.

16. f. THROTTLE 1NV-148 (Letdn Press Control) to 45% demand.

16. g. THROTTLE open 1NV-849 (Letdn Flow Var Orif Ctrl) in 1%

to 5% increments until one of the following conditions met:

Letdown flow and letdown pressure increases OR Valve demand position is 60% open.

CREW

16. h. Do not continue until one of the above conditions met.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

3 Page 17 of 38 Event

Description:

1NV-15B closes. (Loss of Letdown)

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 17 of 38 BOP

16. i. Verify letdown flow and letdown pressure - HAS INCREASED.

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

16. j. Adjust 1NV-148 (Letdn Press Control) to maintain letdown pressure between 150 - 200 PSIG.

NOTE TO EVALUATOR: Time compression may be used in the following step at the discretion of the lead examiner.

16. k. WHEN 5 minutes have elapsed, THEN perform the following:

1) Adjust 1NV-849 (Letdn Flow Var Orif Ctrl) in 1%

increments to desired letdown flow.

2) WHEN letdown at desired flow, THEN perform the following:

a) Adjust 1NV-148 (Letdn Press Control) to maintain letdown pressure at 350 PSIG.

b) Ensure 1NV-148 (Letdn Press Control) - IN AUTO.

3) IF AT ANY TIME additional letdown flow desired, THEN establish letdown with the 45 or 75 GPM orifice. REFER TO OP/1/A/6200/001 (Chemical and Volume Control System).

16. l. WHEN Pzr level restored to programmed level, THEN perform the following:

1) Ensure 1NV-294 (NV Pmps A&B Disch Flow Ctrl) - IN AUTO.

2) Ensure "PZR Level Master" - IN AUTO.

17. Determine required notifications:

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

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

18. Verify excess letdown - ISOLATED.

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

END OF EVENT 3

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

4 Page 18 of 38 Event

Description:

B Train KC Surge Tank level transmitter fails low.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 18 of 38 EVENT 4 Indications:

OAC pt. C1D2214 KC TRAIN B LOW-LOW LEVEL SURGE TANK ISOL -

ACTUATED 1AD-6, C/1-4 NCP A,B,C,D MTR UPPER BRG KC OUTLET HI/LOW FLOW 1AD-6, D/1-4 NCP A,B,C,D MTR LOWER BRG KC OUTLET LO FLOW 1AD-6, E/1-4 NCP A,B,C,D THERMAL BARRIER KC OUTLET HI/LO FLOW 1AD-7, D/1 SEAL WATER HX KC HI/LO FLOW 1AD-7, F/3 LETDN HX OUTLET HI TEMP 1AD-13, F/2 FUEL POOL COOL HX B KC OUTLET HI/LO FLOW 1AD-20, A/1 KC SUPPLY HDR FLOW TO NCP BRGS LOW 1AD-21, A/1 KC SUPPLY HDR FLOW TO NCP BRGS LOW BOP Recognize the following valves close:

1KC-228B (RX BLDG NON-ESS HDR ISOL) 1KC-1B (RX BLDG NON-ESS RET HDR ISOL) 1KC-53B (AUX BLDG NON-ESS HDR ISOL) 1KC-2B (AUX BLDG NON-ESS RET HDR ISOL)

SRO Crew enters AP/1/A/5500/021 NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/021, Loss of Component Cooling.

CAUTION Failure to restore NC pump seal cooling via thermal barrier cooling or NV seal injection within 10 minutes will cause damage to the NC pump seals resulting in NC inventory loss.

RO and BOP

1. Monitor Enclosure 1 (Foldout Page).

2. Verify the following: Perform the following:

At least one KC pump - ON.

AND Flow to KC loads presently in service.

2. RNO Perform the following:

a. Start additional KC pump(s) as necessary.

NOTE TO EVALUATOR: The first pump start attempt will fail.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

4 Page 19 of 38 Event

Description:

B Train KC Surge Tank level transmitter fails low.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 19 of 38 NOTE TO EVALUATOR: Step 2 RNO b. will not apply SRO

3. IF AT ANY TIME all KC pumps are lost, THEN RETURN TO STEP 2.

NOTE Uncooled letdown may result in loss of NV pumps within a matter of minutes.

4. Verify the following:

1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK AND At least one KC pump - ON.

5. IF AT ANY TIME 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" LIT, THEN perform Step 4 RNO.

6. Verify both KC surge tank levels - 50% - 90% AND STABLE.

7. Start additional KC pump(s) as necessary to supply any KC loads presently in service.

CAUTION A loss of KC cooling to the NC pumps results in a gradual approach to an overheated condition in ~ 10 minutes which will result in shaft seizure.

8. Verify KC flow to NC pumps as follows:

1AD-20, A/1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK 1AD-21, A/1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK.

9. Verify KC available as follows:

a. Verify the following Train A KC non-essential header isolation valves - OPEN:

1KC-230A (Rx Bldg Non-Ess Hdr Isol)

1KC-3A (Rx Bldg Non-Ess Ret Hdr Isol)

1KC-50A (Aux Bldg Non-Ess Hdr Isol)

1KC-1A (Aux Bldg Non-Ess Ret Hdr Isol).

9. b. Verify the following Train B KC non-essential header isolation valves -OPEN:

1KC-228B (Rx Bldg Non-Ess Hdr Isol)

1KC-18B (Rx Bldg Non-Ess Ret Hdr Isol)

1KC-53B (Aux Bldg Non-Ess Hdr Isol)

1KC-2B (Aux Bldg Non-Ess Ret Hdr Isol).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

4 Page 20 of 38 Event

Description:

B Train KC Surge Tank level transmitter fails low.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 20 of 38 NOTE The KC non-essential header valves can be reopened when the appropriate train's level switch is reset. This should occur between 40% and 48% KC surge tank level.

BOP 9.b. RNO b. WHEN OAC alarm C1D2214 (KC Train B Low-Low Level Surge Tank Isol) is "NOT ACTUATED" AND cause of valve closure known, THEN ensure the affected valve(s) are open.

9. c. Start additional KC pump(s) as necessary to supply any KC loads presently in service.

10. Verify KC surge tank levels normal as follows:

a. Verify both KC surge tank levels - 50% - 90% AND STABLE.

10. b. GO TO Step 14.

14. Ensure KC heat exchanger outlet mode switches -

PROPERLY ALIGNED.

CREW

15. Determine and correct cause of loss of KC.

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

SLC 16.9-7 (Boration Systems Flow Path-Shutdown)

SLC 16.9-8 (Boration Systems Flow Path-Operating)

SLC 16.9-9 (Boration Systems Pumps -Shutdown)

SLC 16.9-10 (Boration Systems Charging Pumps -

Operating) 3.5.2 (ECCS - Operating) 3.5.3 (ECCS - Shutdown) 3.6.6 (Containment Spray System) 3.7.5 (Auxiliary Feedwater (AFW) System) 3.7.7 (Component Cooling Water (CCW) System).

NOTE TO EVALUATOR: T.S 3.7.7 (Component Cooling Water (CCW) System) Condition A (Restore CCW train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) should be entered.

Booth Operator inserts Trigger 7 for EVENT 5 at discretion of lead examiner.

17. Determine required notifications:

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

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

4 Page 21 of 38 Event

Description:

B Train KC Surge Tank level transmitter fails low.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 21 of 38 NOTE TO EVALUATOR: Step 18 will not apply.

19. Verify KC surge tanks level as follows:

Greater than 50%

Stable or increasing BOP

20. WHEN plant conditions permit, THEN perform the following:

Return KC pumps to normal operation. REFER TO OP/1/A/6400/005 (Component Cooling Water System).

Return NV Pump 1A to normal cooling as applicable.

REFER TO Enclosure 2 (Alternate Cooling To NV Pump 1A).

21. Verify the following:

1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK 1AD-7, H/3 "VCT HI TEMP" - DARK Normal letdown - IN SERVICE.

22. Ensure VCT and letdown path aligned as follows:

a. IF desired to align NV pump suction to VCT, then perform the following:

1) OPEN the following valves:

1NV-188A (VCT Otlt Isol) 1NV-189B (VCT Otlt Isol).

2) CLOSE the following valves:

1NV-252A (NV Pumps Suct From FWST) 1NV-253B (NV Pumps Suct From FWST).

b. WHEN NV suction aligned to VCT, THEN momentarily place 1NV-172A (3-Way Divert To VCT-RHT) to "VCT" position and return to "AUTO".

c. IF desired to restore letdown flow through NV demineralizers, THEN momentarily place 1NV-153A (Letdn Hx Otlt 3-Way Valve) to "DEMIN" position and return to "AUTO".

23. Determine long term plant status. RETURN TO procedure in affect.

END OF EVENT 4

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

5 Page 22 of 38 Event

Description:

1A LH Pump trips, Main Turbine requires a manual trip.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 22 of 38 EVENT 5 Indications:

OAC pt C1A1121 LH PRESS - LO 1AD-1, C/10 HYD FLUID LO PRESS TURB TRIP RO Recognize failure of AUTO Turbine trip.

RO Manually Trip the Turbine NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/002, Turbine Generator Trip RO

1. Verify reactor power - LESS THAN 69%.

2. Verify Turbine Trip:

All turbine stop valves - CLOSED NOTE TO EVALUATOR: The crew may have tripped the turbine by this time and may not proceed to the RNO.

2. RNO Perform the following:

a. Trip turbine.

NOTE TO EVALUATOR: Step 2. RNO b. will not apply RO

3. Verify reactor response:

Control rods - IN "AUTO" AND STEPPING IN P/R neutron flux - DECREASING BOP

4. Ensure C heater drain pumps - OFF.

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

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

a. Place "CRD BANK SELECT" switch - IN MANUAL.

b. Verify reactor power - GREATER THAN 5%.

c. Maintain control rods above insertion limits.

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

10%.

e. IF AT ANY TIME reactor power is less than or equal to 5%,

THEN insert control rods to shutdown reactor to Mode 3.

REFER TO the following procedures:

OP/1/A/6150/008 (Rod Control)

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

5 Page 23 of 38 Event

Description:

1A LH Pump trips, Main Turbine requires a manual trip.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 23 of 38 RO

7. Verify proper steam dump operation as follows:

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

b. Steam dump valves - MODULATING.

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

8. Ensure generator is tripped as follows:

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

b. Ensure the following breakers and MODs - OPEN:

MOD 1BG and 1BT

MOD 1AG and 1AT

Generator Breaker 1A and 1B.

c. Ensure main generator "EXCITATION" - OFF

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

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

a. All Pzr PORVs - CLOSED.

b. Normal Pzr spray valves - CLOSED.

10. Verify Pzr level - TRENDING TO PROGRAM.

NOTE TO EVALUATOR: If the Pressurizer Level Master is still in Manual, the crew may proceed to the RNO and control charging and letdown to maintain program level.

11. Verify S/G N/R levels - TRENDING TO OR STABLE AT 39%.

12. Verify reactor power - GREATER THAN 5%.

NOTE TO EVALUATOR: DNB requirements do not apply during transients.

NOTE TO EVALUATOR: S.R. 3.3.1.2, for a Power Mismatch of > 2%, is only required to be performed when THERMAL POWER is > 15% RTP NOTE TO EVALUATOR: Due to Control Rod M4 in Control Bank D at Half Accuracy, an RPI URGENT FAILURE alarm may occur on Rod Insertion, but will clear when Control Bank D is inserted again.

13. Stabilize reactor power as follows:

a. Maintain control rods above insertion limits.

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

c. Verify all atmospheric steam dump valves - CLOSED.

d. Verify condenser steam dump valves - MODULATING Booth Operator inserts Trigger 9 for EVENT 6 at discretion of lead examiner.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

5 Page 24 of 38 Event

Description:

1A LH Pump trips, Main Turbine requires a manual trip.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 24 of 38 BOP

14. Align AS supply to CF pumps as follows:

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

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

c. Dispatch operator to CLOSE 1SP-3 (SC To CFPT 1A & 1B)

(TB1-640, 1G-24).

15. Verify feed flow - ALIGNED TO CA NOZZLES.

NOTE TO EVALUATOR: It is not intended to perform step 15 RNO in this scenario.

CREW

15. RNO Transfer feed flow to CA nozzles. NOZZLES. REFER TO Enclosure 1 (Transferring Feed Flow From CF to CA Nozzles).

END OF EVENT 5

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

6 Page 25 of 38 Event

Description:

1D NC pump trips (electrical)

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 25 of 38 EVENT 6 INDICATIONS: 1AD-6, D/5 UF NCP BUS ALERT 1AD-6 F/5 UV NCP BUS ALERT 1AD-6, B/4 NCP D TRIP 1AD-6, A/4 LOOP D LO FLOW ALERT RO Recognize trip of the 1D NC pump and perform the Immediate Actions of AP/1/A/5500/004, Loss of Reactor Cooling Pump NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/004, Loss of Reactor Coolant Pump. The actions will be taken, however the procedure will not be read by the CRS, since these are Immediate Actions.

1. Verify all control banks - INSERTED.

1. RNO Perform the following:

a. Ensure reactor - TRIPPED.

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

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

END OF EVENT 6

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

7, 8 and 9 Page 26 of 38 Event

Description:

LBLOCA, both trains of Safety Injection fail to auto actuate, 1SM-3 (S/G 1C SM ISOL) fails to close Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 26 of 38 EVENTS 7, 8 and 9 RO Verifies the 1SM-3 (S/G 1C SM ISOL) fails to close and manually closes it.

BOP Verifies failure of both trains of S/I to actuate and manually initiate S/I on both trains.

NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/E-0, Reactor Trip or Safety Injection RO and BOP

1. Monitor Enclosure 1 (Foldout Page).

2. Verify Reactor Trip:

All rod bottom lights - LIT All reactor trip and bypass breakers - OPEN I/R power - DECREASING.

3. Verify Turbine Trip: Perform the following:

All turbine stop valves - CLOSED BOP

4. Verify 1ETA and 1ETB - ENERGIZED.

5. Verify S/I is actuated:

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

5. RNO a. Perform the following:

1) Verify conditions requiring S/I:

Pzr pressure - LESS THAN 1845 PSIG OR

Containment pressure - GREATER THAN 1.2 PSIG.

CRITICAL TASK BOP

5. RNO a. 2) IF S/I is required, THEN initiate S/I.

NOTE TO EVALUATOR: Step 5 RNO a. 2) may have been done by the BOP as part of the Immediate Actions.

END OF EVENT 8 NOTE TO EVALUATOR: Step 5 RNO a. 3) will not apply.

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

7 and 9 Page 27 of 38 Event

Description:

LBLOCA, 1SM-3 (S/G 1C SM ISOL) fails to close Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 27 of 38 NOTE TO EVALUATOR: After the Immediate Actions are complete, the crew trips the NC (Reactor Coolant) pumps due to a loss of subcooling, completing Critical Task 2.

6. Announce "Unit 1 Safety Injection".

7. Determine required notifications:

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

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

RO or BOP

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.

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

LIT.

10. Verify proper Phase B actuation as follows:

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

10. RNO a. Perform the following:

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.

BOP 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: If the RO noticed 1SM-3 (S/G 1C SM ISOL) was open and manually closed it, then step 10. RNO d) will not apply RO or BOP d) IF monitor light panel not in correct alignment, THEN ensure correct alignment.

END OF EVENT 9 RO or BOP

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

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

10. RNO a. 4) Energize H2 igniters.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

7 Page 28 of 38 Event

Description:

LBLOCA Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 28 of 38 RO or BOP

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 Enclosures), Enclosure 11 (Securing All Ice Condenser Units).

b) Place containment H2 analyzers in service.

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

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

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

11. Verify proper CA pump status as follows:

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:

NV pumps ND pumps NI pumps.

13. Verify all KC pumps - ON.

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).

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:

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

b. NC pressure - LESS THAN 1620 PSIG.

c. NI pumps - INDICATING FLOW.

d. NC pressure - LESS THAN 285 PSIG.

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

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.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

7 Page 29 of 38 Event

Description:

LBLOCA Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 29 of 38 RO or BOP

18. WHEN time and manpower permit, THEN monitor Spent Fuel Pool level and temperature. REFER TO EP/1/A/5000/G-1 (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.

NOTE TO EVALUATOR: Total CA flow may not be > 450 gpm due to being under operator control, in which case, the RNO for 19 a. will not apply.

b. WHEN 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%.

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

20. Verify all CA isolation valves - OPEN.

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

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 Temperature Control).

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

a. All Pzr PORVs - CLOSED.

b. Normal Pzr spray valves - CLOSED.

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

RO or BOP

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

RO or BOP

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

a. Ensure all NC pumps - OFF.

b. Maintain seal injection flow.

RO or BOP

25. Verify main steamlines intact:

All S/G pressures - STABLE OR INCREASING 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) 1EMF-27 (Steamline 1B) 1EMF-28 (Steamline 1C) 1EMF-29 (Steamline 1D).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

7 Page 30 of 38 Event

Description:

LBLOCA Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 30 of 38 RO or BOP All S/G levels - STABLE OR INCREASING IN A CONTROLLED MANNER.

27. Verify NC System is intact as follows:

Containment pressure - LESS THAN 1 PSIG.

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

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

1EMF-53A (Containment Trn A) 1EMF-53B (Containment Trn B).

Containment EMF trip 1 lights - DARK:

1EMF-38 (Containment Particulate) 1EMF-39 (L) (Containment Gas (Lo Range)).

Containment sump level - STABLE.

27. RNO Perform the following:

a. Energize H2 igniters.

RO or BOP

27. RNO b. Dispatch operator to perform the following:

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

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

NOTE TO EVALUATOR: Step 27. RNO c. will not apply CREW

d. Concurrently:

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

GO TO EP/1/A/5000/E-1 (Loss Of Reactor Or Secondary Coolant).

TRANSITION E-1 (Loss Of Reactor Of Secondary Coolant)

NOTE TO EVALUATOR: The crew will address the challenge to the NC (Reactor Coolant) System Integrity per EP/1/A/5000/FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition) if not done previously.

NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition)

RO or BOP

1. Verify NC pressure - GREATER THAN 285 PSIG.

CREW

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

7 Page 31 of 38 Event

Description:

LBLOCA Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 31 of 38 TRANSITION TO EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant)

NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant)

RO and BOP

1. Monitor Enclosure 1 (Foldout Page).

RO or BOP

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

RO or BOP

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

a. Ensure all NC pumps - OFF.

b. Maintain seal injection flow.

3. Verify main steamlines intact:

All S/G pressures - STABLE OR INCREASING All S/Gs - PRESSURIZED RO

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

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

(29% ACC).

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

5. Reset the following:

a. ECCS.

b. D/G load sequencers.

c. Phase A

d. Phase B.

RO or BOP

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

6. Establish VI to Containment as follows:

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

Verify VI pressure - GREATER THAN 85 PSIG.

7. Verify secondary radiation - NORMAL:

a. Ensure the following signals - RESET:

1) CA System valve control BOP

2) KC NC NI NM St signals.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

7 Page 32 of 38 Event

Description:

LBLOCA Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 32 of 38 NOTE TO EVALUATOR: The BOP will open the following valves when aligning the S/Gs for chemistry sample in step b. below:

1NM-191B (S/G 1A SMPL HDR CONT ISOL) 1NM-201A (S/G 1B SMPL HDR CONT ISOL) 1NM-211B (S/G 1C SMPL HDR CONT ISOL) 1NM-221A (S/G 1D SMPL HDR CONT ISOL) 1NM-190A (S/G 1A BLDWN SMPL CONT ISOL) 1NM-200B (S/G 1B BLDWN SMPL CONT ISOL) 1NM-210A (S/G 1C BLDWN SMPL CONT ISOL) 1NM-220B (S/G 1D BLDWN SMPL CONT ISOL)

b. Align all S/Gs for Chemistry sampling.

RO or BOP

c. Perform at least one of the following:

Notify Chemistry to sample all S/Gs for activity.

OR

Notify RP to frisk all cation columns for activity.

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

1EMF-33 (Condenser Air Ejector Exhaust)

1EMF-26 (Steamline 1A)

1EMF-27 (Steamline 1B)

1EMF-28 (Steamline 1C)

1EMF-29 (Steamline 1D).

e. Verify all S/Gs - INTACT

All S/G pressures - STABLE OR INCREASING

All S/Gs - PRESSURIZED RO or BOP

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

8. Verify Pzr PORVs and Isolation Valves:

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

b. All Pzr PORVs - CLOSED

c. Any Pzr PORV isolation valve - OPEN.

RO or BOP

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

7 Page 33 of 38 Event

Description:

LBLOCA Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 33 of 38 RO

9. Verify S/I termination criteria:

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

SRO 9.a. RNO a. GO TO Step 9.f.

RO or BOP

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

CREW

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

RO or BOP

10. Determine if ND pumps should be stopped:

a. NC pressure - GREATER THAN 285 PSIG.

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

12. Verify D/Gs should be stopped:

a. Any D/G - ON.

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

"D/G 1A BKR TO ETA" - OPEN 1ETA - ENERGIZED.

c. Dispatch operator to stop 1A D/G and place in standby readiness. REFER TO OP/1/A/6350/002 (Diesel Generator Operation).

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

"D/G 1B BKR TO ETB" - OPEN 1ETB - ENERGIZED.

e. Dispatch operator to stop 1B D/G and place in standby readiness. REFER TO OP/1/A/6350/002 (Diesel Generator Operation).

13. Obtain containment H2 concentration as follows:

a. Ensure operator dispatched to secure all ice condenser air handling units. REFER TO Enclosure 3 (Securing All Ice Condenser Air Handling Units).

b. Verify containment H2 analyzers - IN SERVICE CREW 13.b. RNO b. Perform the following:

1) Dispatch operator to place containment H2 analyzers in service. REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems).

2) WHEN H2 analyzers are in service, THEN perform Steps 13.c through 13.e.

3) GO TO Step 14.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

7 Page 34 of 38 Event

Description:

LBLOCA Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 34 of 38 BOP

14. Initiate evaluation of plant status as follows:

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

A Train:

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

POWER AVAILABLE OR B Train:

1B ND pump - AVAILABLE 1NI-184B (ND Pump 1B Cont Sump Suct) -

POWER AVAILABLE

b. Determine if leak is in auxiliary building:

1) Verify auxiliary building radiation:

All area monitor EMF trip 1 lights - DARK.

EMF-41 (Aux Bldg Ventilation) trip 1 light - DARK NOTE The following step is checking for a significant NC leak into the ND System.

2) Verify NC to ND pressure boundary intact as follows:

ND Pressure - NORMAL

ND Temperature - NORMAL

ND Flow - NORMAL

c. Determine if NC is leaking into KC system:

1EMF-46A (COMPONENT COOLING TRAIN A) trip 1 light - DARK.

1EMF-46B (COMPONENT COOLING TRAIN B) trip 1 light - DARK.

d. Ensure KC NC NI NM St signals - RESET

e. WHEN TSC is staffed, THEN notify TSC to perform (TSC Actions).

RO or BOP

15. Determine if NC System cooldown and depressurization is required:

a. NC pressure - GREATER THAN 285 PSIG RO

15. RNO a. IF ND flow to C-Legs is greater than 675 GPM, THEN GO TO Step 16.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event #

7 Page 35 of 38 Event

Description:

LBLOCA Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 35 of 38 BOP

16. Verify Containment pressure - GREATER THAN 3 PSIG.

CRS

16. RNO Perform the following:

a. IF starting of any VX fan has previously been attempted, THEN GO TO Step 17.