ML13336A399

2. Verify the following:

At least one KC pump - ON.

BOP 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

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 14 of 33

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 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 BOP AND

At least one KC pump - ON.

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

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

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

10. Verify KC surge tank levels normal as follows:

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

SRO 10. b. GO TO Step 14.

14. Ensure KC heat exchanger outlet mode switches -

BOP PROPERLY ALIGNED.

CREW 15. Determine and correct cause of loss of KC.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 15 of 33

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

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 -

SRO 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

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 BOP

1AD-7, H/3 "VCT HI TEMP" - DARK

Normal letdown - IN SERVICE.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 16 of 33

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

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 SRO affect.

END OF EVENT 4 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 17 of 33

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 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)

RO 1. Verify reactor power - LESS THAN 5%.

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

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

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

RO 450 GPM.

5. Control S/G levels as follows:

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

RO 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%.

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

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

No other actions from Case II are necessary.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 18 of 33

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

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.

RO 10. Verify at least one CF Pump - ON.

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

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

END OF EVENT 5 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 19 of 33

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 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).

RO 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, RO 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.

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

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

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 20 of 33

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 NOTE TO EVALUATOR: The following steps are from E-0 Reactor Trip or Safety Injection RO and

1. Monitor Enclosure 1 (Foldout Page).

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:

a. Trip reactor.

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

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:

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

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

NOTE TO EVALUATOR: Upon Loss of Subcooling with S/I flow verified, the RO or BOP 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

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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 21 of 33

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

10. Verify proper Phase B actuation as follows:

BOP a. Verify Containment pressure - HAS REMAINED LESS THAN 3 PSIG RO or b. IF AT ANY TIME containment pressure exceeds 3 PSIG BOP while in this procedure, THEN perform Step 10.a.

11. Verify proper CA pump status as follows:

RO a. Motor driven CA pumps - ON.

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

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

1) Reset ECCS.

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

BOP 3) Start affected pump(s).

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

RO 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.

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

CRITICAL a. Reset ECCS.

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

c. Start affected pump(s).

END OF EVENT 8 RO or d. IF AT ANY TIME B/O occurs, THEN restart S/I BOP equipment previously on.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 22 of 33

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 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.

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

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.

RO b. NC pressure - LESS THAN 1620 PSIG.

c. NI pumps - INDICATING FLOW.

d. NC pressure - LESS THAN 285 PSIG.

17.d. RNO d. Perform the following:

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

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

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).

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 23 of 33

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

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%

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

RO 20. Verify all CA isolation valves - OPEN.

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

NOTE 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).

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 24 of 33

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

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

a. All Pzr PORVs - CLOSED.

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:

BOP (1) Secure all ice condenser air handling units.

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

Enclosure 18 (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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 25 of 33

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 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

1. Monitor Enclosure 1 (Foldout Page).

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

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

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

BOP a. Ensure all NC pumps - OFF.

b. Maintain seal injection flow.

3. Verify main steamlines intact:

All S/G pressures - STABLE OR INCREASING

All S/Gs - PRESSURIZED

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

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

RO (29% ACC).

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

5. Reset the following:

a. ECCS.

BOP b. D/G load sequencers.

c. Phase A

d. Phase B.

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

6. Establish VI to Containment as follows:

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

Verify VI pressure - GREATER THAN 85 PSIG.

7. Verify secondary radiation - NORMAL:

RO a. Ensure the following signals - RESET:

1) CA System valve control BOP 2) KC NC NI NM St signals.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 26 of 33

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 NOTE TO EVALUATOR: The BOP opens the following valves when aligning the S/Gs for chemistry sample in step b. below:

1NM-191B (S/G 1A SMPL HDR CONT ISOL)

1NM-201A (S/G 1B SMPL HDR CONT ISOL)

1NM-211B (S/G 1C SMPL HDR CONT ISOL)

1NM-221A (S/G 1D SMPL HDR CONT ISOL)

1NM-190A (S/G 1A BLDWN SMPL CONT ISOL)

1NM-200B (S/G 1B BLDWN SMPL CONT ISOL)

1NM-210A (S/G 1C BLDWN SMPL CONT ISOL)

1NM-220B (S/G 1D BLDWN SMPL CONT ISOL)

BOP b. Align all S/Gs for Chemistry sampling.

c. Perform at least one of the following:

RO or

Notify Chemistry to sample all S/Gs for activity.

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 RO

All S/G pressures - STABLE OR INCREASING

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

8. Verify Pzr PORVs and Isolation Valves:

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

b. All Pzr PORVs - CLOSED.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 27 of 33

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 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.

BOP 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.

BOP c. Any Pzr PORV isolation valve - OPEN.

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

9. Verify S/I termination criteria:

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

b. Secondary heat sink:.

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

RO or BOP OR

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

c. NC pressure - STABLE OR INCREASING.

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

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

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 28 of 33

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 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).

2. Reset the following:

a. ECCS.

b. D/G load sequencers.

BOP c. Phase A.

d. Phase B.

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

3. Establish VI to Containment as follows:

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

Verify VI pressure - GREATER THAN 85 PSIG.

BOP 4. Ensure only one NV pump - ON.

RO or

5. Verify NC pressure - STABLE OR INCREASING.

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

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

7. Isolate NV S/I flowpath as follows:

a. Verify the following valves - OPEN:

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

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

b. Verify the following valves - OPEN:

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

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

7.b. RNO b. Perform the following:

1) OPEN affected valve(s).

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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 29 of 33

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

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:

BOP a. Control charging flow to maintain Pzr level stable.

b. Verify Pzr level - STABLE OR INCREASING.

10. Determine if NI pumps should be stopped:

a. Verify the following:

NC pressure - STABLE OR INCREASING

NC pressure - GREATER THAN 1620 PSIG.

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.

CREW 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 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 30 of 33

Catawba Nuclear Station NRC Exam December 2013 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 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 31 of 33

Catawba Nuclear Station NRC Exam December 2013 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

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

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

Comments:

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 32 of 33

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

Catawba Nuclear Station NRC Exam September 2013 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 Malf. No. Event Event No. Type* Description N-BOP 1 --- R-RO Begin increasing reactor power to 100%.

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

3 NV012F C-BOP 1NV-15B (Letdown Isolation Valve) fails closed. AP/12 C-SRO 4 KC045 I-BOP KC surge tank level transmitter fails low. AP/21 I-SRO TS-SRO 5 EHC007A C-RO Operating LH pump (1A) trips. Requires manual turbine trip. AP/02 C-SRO 6 NCP001D C-RO 1D NC Pump trips (electrical).

C-SRO 7 NC013D M-ALL LBLOCA 8 ISE002A/B I-BOP Both trains Safety Injection fail to auto actuate.

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

C-SRO

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 2 of 38

Catawba Nuclear Station NRC Exam September 2013 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.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 3 of 38

Catawba Nuclear Station NRC Exam September 2013 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC 178 START TIME:__________

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

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

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

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

MAL-EHC007B (EHC HYDRAULIC n/a FLUID PUMP B TRIP)

XMT-NC013 (LNC_5150 PZR LVL 1

CH II TO MTR 1NCP5153 + DCS 100 2 NCAA5154/NCAA5155)

VLV-NV012F (NV15B L/D ISOL 3

OUTSIDE CNMT VLV FAIL TO 0 5 SEC 3 POSITION)

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

MAL-KC001B (KC PUMP 1A2 n/a BOTH 4 FAILURE)

MAL-KC001B (KC PUMP 1A2 16 BOTH 1 SEC 4 FAILURE)

MAL-KC001A (KC PUMP 1A1 n/a BOTH 4 FAILURE)

MAL-KC001A (KC PUMP 1A1 18 BOTH 1SEC 4 FAILURE)

MAL-EHC007A (EHC HYDRAULIC 7 5 FLUID PUMP A TRIP)

MAL-EHC002 (TURBINE TRIP n/a AUTO 5 FAILURE) 9 MAL-NCP001D (NCP D TRIP) 6 MAL-NC013D (NC COLD LEG D 10 27.5 7 LEAK)

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 4 of 38

Catawba Nuclear Station NRC Exam September 2013 MAL-ISE002B (AUTO SI TRN B n/a 8 FAILS TO ACTUATE)

VLV-SM002A (SM3 MSIV C FAIL n/a 9 AUTO ACTIONS)

Ensure TRIGGER 10 = x01o063g l x01o066g Ensure TRIGGER 16 = x11i119n Ensure TRIGGER 18 = x11i122n Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 5 of 38

Catawba Nuclear Station NRC Exam September 2013

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.

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

Catawba Nuclear Station NRC Exam September 2013 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.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 7 of 38

Catawba Nuclear Station NRC Exam September 2013 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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 8 of 38

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 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).

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":

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.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 9 of 38

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 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.

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 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.

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 2013 NUREG 1021 Revision 9 Page 10 of 38

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 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:

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 2013 NUREG 1021 Revision 9 Page 11 of 38

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 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 2013 NUREG 1021 Revision 9 Page 12 of 38

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 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 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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 13 of 38

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 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 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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 14 of 38

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 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)

RO 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).

BOP 3. Verify Pzr level - GREATER THAN 17%.

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

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

6. Control VCT level as follows:

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

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

BOP 7. Determine and correct cause of loss of letdown.

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.

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

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 15 of 38

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

10. Ensure compliance with appropriate Tech Specs:

3.3.1 (Reactor Trip System (RTS) Instrumentation)

3.3.3 (Post Accident Monitoring (PAM) Instrumentation)

3.3.4 (Remote Shutdown System)

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

3.4.12 (Low Temperature Overpressure Protection (LTOP)

System)

3.4.13 RCS (Operational Leakage).

3.6.3 (Containment Isolation Valves).

NOTE TO EVALUATOR: NO Tech Specs apply.

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

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

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

SRO 11. RNO GO TO Step 16.

16. Establish letdown as follows:

CREW

a. Verify ability to establish normal letdown - RESTORED.

16. b. Ensure 1NV-849 (Letdn Flow Var Orif Ctrl) valve demand BOP 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 BOP necessary to maintain letdown subcooled in following steps.

BOP 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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 16 of 38

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

16. i. Verify letdown flow and letdown pressure - HAS BOP 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 BOP pressure between 150 - 200 PSIG.

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

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 BOP 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:

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

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

17. Determine required notifications:

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

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

BOP 18. Verify excess letdown - ISOLATED.

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

END OF EVENT 3 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 17 of 38

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 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 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

1. Monitor Enclosure 1 (Foldout Page).

2. Verify the following: Perform the following:

At least one KC pump - ON.

BOP 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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 18 of 38

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

3. IF AT ANY TIME all KC pumps are lost, THEN RETURN TO SRO 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 BOP AND

At least one KC pump - ON.

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

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

7. Start additional KC pump(s) as necessary to supply any KC BOP 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 BOP 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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 19 of 38

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 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.

9.b. RNO b. WHEN OAC alarm C1D2214 (KC Train B Low-Low Level Surge Tank Isol) is "NOT ACTUATED" AND BOP 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 BOP loads presently in service.

10. Verify KC surge tank levels normal as follows:

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

SRO 10. b. GO TO Step 14.

14. Ensure KC heat exchanger outlet mode switches -

BOP 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 -

SRO 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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 20 of 38

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 NOTE TO EVALUATOR: Step 18 will not apply.

19. Verify KC surge tanks level as follows:

Greater than 50%

Stable or increasing

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 BOP

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 SRO affect.

END OF EVENT 4 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 21 of 38

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 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

3. Verify reactor response:

Control rods - IN "AUTO" AND STEPPING IN

P/R neutron flux - DECREASING BOP 4. Ensure C heater drain pumps - OFF.

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

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

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

b. Verify reactor power - GREATER THAN 5%.

c. Maintain control rods above insertion limits.

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

10%.

RO 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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 22 of 38

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

7. Verify proper steam dump operation as follows:

a. "C-9 COND AVAILABLE FOR STM DUMP" status light RO (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:

BOP a. All Pzr PORVs - CLOSED.

b. Normal Pzr spray valves - CLOSED.

BOP 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.

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

RO 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 RO 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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 23 of 38

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

14. Align AS supply to CF pumps as follows:

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

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

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

(TB1-640, 1G-24).

RO 15. Verify feed flow - ALIGNED TO CA NOZZLES.

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

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

END OF EVENT 5 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 24 of 38

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 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 Recognize trip of the 1D NC pump and perform the Immediate RO 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.

RO 1. Verify all control banks - INSERTED.

1. RNO Perform the following:

RO a. Ensure reactor - TRIPPED.

1 RNO b. 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 2013 NUREG 1021 Revision 9 Page 25 of 38

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 EVENTS 7, 8 and 9 Verifies the 1SM-3 (S/G 1C SM ISOL) fails to close and manually RO closes it.

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

1. Monitor Enclosure 1 (Foldout Page).

2. Verify Reactor Trip:

All rod bottom lights - LIT RO

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 BOP OR

Containment pressure - GREATER THAN 1.2 PSIG.

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

TASK 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.

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 26 of 38

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 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.

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

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:

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 BOP

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

END OF EVENT 9 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.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 27 of 38

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

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:

NV pumps BOP

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).

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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 28 of 38

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

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.

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%

RO 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.

RO 20. Verify all CA isolation valves - OPEN.

21. Verify S/I equipment status based on monitor light panel - IN BOP 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 RO 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 24. Verify NC subcooling based on core exit T/Cs - GREATER BOP THAN 0°F.

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

BOP a. Ensure all NC pumps - OFF.

b. Maintain seal injection flow.

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)

1EMF-27 (Steamline 1B)

1EMF-28 (Steamline 1C)

1EMF-29 (Steamline 1D).

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 29 of 38

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 RO or

All S/G levels - STABLE OR INCREASING IN A BOP 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.

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),

RO or 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).

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

d. Concurrently:

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

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

TRANSITION 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

1. Verify NC pressure - GREATER THAN 285 PSIG.

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 30 of 38

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 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

1. Monitor Enclosure 1 (Foldout Page).

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

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

BOP a. Ensure all NC pumps - OFF.

b. Maintain seal injection flow.

3. Verify main steamlines intact:

All S/G pressures - STABLE OR INCREASING

All S/Gs - PRESSURIZED

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

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

RO (29% ACC).

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

5. Reset the following:

a. ECCS.

BOP b. D/G load sequencers.

c. Phase A

d. Phase B.

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

6. Establish VI to Containment as follows:

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

Verify VI pressure - GREATER THAN 85 PSIG.

7. Verify secondary radiation - NORMAL:

RO a. Ensure the following signals - RESET:

1) CA System valve control BOP 2) KC NC NI NM St signals.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 31 of 38

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 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)

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.

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 RO

All S/G pressures - STABLE OR INCREASING

All S/Gs - PRESSURIZED RO or f. WHEN activity results are reported, THEN verify all S/Gs BOP 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.

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 32 of 38

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

9. Verify S/I termination criteria:

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

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

RO or 10. Determine if ND pumps should be stopped:

BOP 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 BOP 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 BOP handling units. REFER TO Enclosure 3 (Securing All Ice Condenser Air Handling Units).

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

1) Dispatch operator to place containment H2 analyzers in service. REFER TO OP/1/A/6450/010 CREW (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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 33 of 38

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

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 Enclosure 7 (TSC Actions).

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

a. NC pressure - GREATER THAN 285 PSIG

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 34 of 38

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 BOP 16. Verify Containment pressure - GREATER THAN 3 PSIG.

16. RNO Perform the following:

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

17. Determine if transfer to Cold Leg Recirc is required:

BOP a. FWST level - LESS THAN 20% (1AD-9, D/8 "FWST 2/4 LO LEVEL").

CREW 17. RNO a. RETURN TO Step 14.

END OF EVENT 7 END OF SCENARIO Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 35 of 38

Catawba Nuclear Station NRC Exam September 2013 Attachment List Scenario 2 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),

Rev. 077 ATTACHMENT 4 - AP/1/A/5500/012 Enclosure 3 (Control Room Ventilation System Verification), Rev. 033 ATTACHMENT 5 - AP/1/A/5500/021 Enclosure 1 (Foldout Page), Rev. 042 ATTACHMENT 6 - AP/1/A/5500/002 Enclosure 4 (Rod Insertion Limit Boration), Rev. 032 ATTACHMENT 7 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page), Rev. 041 ATTACHMENT 8 - EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification), Rev, 041 ATTACHMENT 9 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control), Rev. 041 ATTACHMENT 10 - EP/1/A/5000/E-0 Enclosure 5 (VX System Operation), Rev. 041 ATTACHMENT 11 - EP/1/A/5000/E-1 Enclosure 1 (Foldout Page), Rev. 028 ATTACHMENT 12 - EP/1/A/5000/E-1 Enclosure 2 (S/I Termination Criteria), Rev. 028 ATTACHMENT 13 - EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 18 (VX and Containment Ventilation Control), Rev. 006 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 36 of 38

Catawba Nuclear Station NRC Exam September 2013 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK C-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.

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

Comments:

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 37 of 38

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 50% MOL 1027 PPM per OAC Controlling Procedure

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

Other Information Needed to Assume the Shift

Unit 1 is at 50% power, 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 . Direction to crew is to begin increasing 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 2013 HLP NRC EXAM SCENARIO # 3 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 1 of 34

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1 Facility: Catawba NRC Exam 2013 Scenario No.: 3 Op Test No.: 2013301 Examiners: Operators: SRO RO BOP Initial Conditions: IC#179; Unit 1 is at 85% power, MOL. 1B CBP pump is tagged out of service. 1B LH pump is tagged out.

Turnover: Unit 1 is at 85% power, MOL. 1B CBP pump is tagged out for preventive maintenance and is expected to be returned to service in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . 1B LH Pump is tagged out and is expected to return to service in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Increase power to 100% 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 .

Event Malf. No. Event Event No. Type* Description N-BOP 1 --- R-RO Power increase to 100%

N-SRO 2 IPE-003C C-BOP 1NC-29 (PZR spray) fails open. AP/11 C-SRO TS-SRO 3 NC005 TS-SRO NC Loop B Flow channel 2 fails low.

4 FWP015C C-RO 1B CFPT Trips with failed auto runback. AP/03 C-SRO 5 RN003 C-BOP 1B RN pump trips. AP/20 C-SRO TS-SRO 6 CF006F C-RO 1CF-33 (1A CF CONT ISOL) closes requiring reactor trip. AP/06 C-SRO 7 SM008C M-ALL 1A S/G Steamline break outside containment.

8 ISE006A I-RO Main Steam Isolation fails to auto initiate.

ISE006B I-SRO 9 VLV-NI001A C-BOP 1NI-9A fails to open in AUTO.

C-SRO

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 2 of 34

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1 Scenario 3 - Summary Initial Condition IC 179 Unit 1 is at 85% power, MOL. 1B CBP is out of service. 1B LH Pump is tagged out.

Turnover:

Unit 1 is at 85% power, MOL. 1B CBP is tagged out for preventive maintenance and is expected to be returned to service in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . 1B LH Pump is tagged out and expected to return to service in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Increase power per the reactivity management plan and increase turbine load to 100%. 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 .

Event 1 Increase power to 100%.

Event 2 1NC-29 (PZR Spray Valve) fails open. BOP manually closes the spray valve (will be successful).

AP/11 (Pressurizer Pressure Anomalies) entry. TS evaluation required.

Event 3 NC Loop B Flow channel 2 fails LOW. TS evaluation required.

Event 4 1B Main Feedwater Pump trips and the Main Turbine will NOT run back in auto. RO recognizes that the Main Turbine needs to be run back to ~ 65% turbine load manually. AP/03 (Load Rejection) Case I entry.

Event 5 (Nuclear Service Water) 1B RN Pump trips. AP/20 (Loss of Nuclear Service Water) entry. BOP manually starts another RN pump (there is no auto start feature of the RN pumps for these conditions). TS evaluation required.

Event 6 1CF-33 (S/G 1A CF CONT ISOL) fails closed causing a loss of all feed flow to the 1A S/G requiring the RO to trip the reactor per AP/06 (Loss of S/G Feedwater).

Event 7 A steamline break outside containment occurs on the 1A S/G when the reactor trips.

Event 8 Main Steam Isolation fails to auto actuate. RO manually actuates Main Steam Isolation.

Event 9 1NI-9A (NV Cold Leg Injection Valve) fails to auto open on the SI. BOP takes manual action to open the valve for full injection.

Critical Task 1 - Isolate the faulted S/G before transition out of E-2.

Critical Task 2 - Manually actuate main steamline isolation before a severe (orange-path) challenge develops to either the subcriticality or the integrity CSF or before transition to ECA 2.1, whichever happens first.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 3 of 34

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC 179 START TIME:__________

Trigger Instructor Action Delay Ramp Delete Event Final In n/a LOA-CM040 (RACKOUT CBP 1B)

MAL-RN003B (RN PMP 1B n/a AUTO FAILURE TO STRT)

MAL-RN003D (PMP 2B FAILURE n/a AUTO TO STRT)

MAL-IPE003C (PZR SPRAY VLV 1 100 2 NC-29 FAIL, MAN CTRL)

XMT-NC005 (FNC_5040 NC LOOP 3 0 3 B FLOW MTR (FI-425))

MAL-EHC003F (ALL TURBINE n/a BLOCK 4 AUTO RUNBACK FAILURE)

OVR-FWP015C (CFPT 1B 5 ON 4 TRIP_RESET TRIP PB)

LOA-RN003 (RACKOUT RN PUMP RACK 7 5 1B) OUT LOA-VC039 (MNL RST OF LATCH 20 8 FOR CHILLER B HI COND PRESS RESET 5 SEC TRIP DUE TO LOSS OF RN)

VLV-CF006F (CF CONT ISOL VLV 11 0 4 SEC 6 CF033 FAIL TO POSITION)

MAL-SM008A (STM LINE BRK 12 OUTSIDE CONTAINMENT LOOP 1.52e+6 7 A)

MAL-ISE006A (AUTO SM ISOL n/a BLOCK 8 SIGNAL TRN A)

MAL-ISE006B (AUTO SM ISOL n/a BLOCK 8 SIGNAL TRN B)

VLV-NI001A (NI9A B.I.T.

n/a DISCHARGE ISOL VLV FAIL 9 AUTO ACTIONS)

Ensure TRIGGER 8 = x14o013r l x14o014r l x11o038r Ensure TRIGGER 12 = x01o063g l x01o066g Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 4 of 34

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1

2. SIMULATOR BRIEFING 2.1 Control Room Assignments:

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

3. EXERCISE PRESENTATION 3.1 Familiarization Period A. Allow examinees time to familiarize themselves with 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, 1NC-29 fails open.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 1 to cause 1NC-29 to fail open.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with 1NC-29, REPEAT the information.

3.4 Scenario EVENT 3, NC Loop B Flow Channel 2 fails low.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause NC Loop B Channel 2 to fail low BOOTH INSTRUCTOR ACTION IF SWM is contacted to issue model w/o #00874531, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF SWM is contacted to write a w/r on NC Loop B Channel 2, REPEAT back the information.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 5 of 34

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1 3.5 Scenario EVENT 4, 1B CFPT Trips with a failed auto Main Turbine runback.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to trip the 1B CFPT.

BOOTH INSTRUCTOR ACTION IF SWM is contacted to write a w/r on the 1B CFPT, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance is dispatched to investigate the 1B CFPT, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF the SOC is notified of current unit status, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF RP is notified to sample and analyze gaseous effluents, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Primary Chemistry is notified to sample for isotopic analysis of iodine, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF the Reactor Group Engineer is notified of the occurrence, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Operator dispatched to complete the shutdown of the C Heater Drain Pumps, REPEAT back the information.

3.6 Scenario EVENT 5, 1B RN Pump trips.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 7 to cause the 1B RN Pump to trip.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with 1B RN Pump and/or breaker, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an Operator and/or Maintenance are dispatched to investigate the 1B RN Pump and/or breaker, REPEAT back the information.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 6 of 34

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1 BOOTH INSTRUCTOR ACTION IF Environmental Chemistry is contacted, REPEAT back the information..

3.7 Scenario EVENT 6, 1CF-51 goes closed.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 11 to cause the 1CF-51 to close.

3.8 Scenario EVENTS 7, 8 and 9 Steamline break inside containment on the 1C 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 notified to frisk all cation columns for activity, REPEAT the order.

BOOTH INSTRUCTOR ACTION IF RP is requested to monitor the area of the steam fault for radiation, REPEAT the order.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 7 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 8 of 34 Event

Description:

Power increase to 100% power.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: Crew begins with a power increase. BOP performs a dilution per OP/1/6150/009, Enclosure 4.3. Amount of dilution is 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 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":

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.)

BOP 3.8 Place the "NC MAKEUP MODE SELECT" switch to the "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 2013 NUREG 1021 Revision 9 Page 8 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 9 of 34 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 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.

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 2013 NUREG 1021 Revision 9 Page 9 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 10 of 34 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 subtracting the amount previously added (Step BOP 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:

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 2013 NUREG 1021 Revision 9 Page 10 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 11 of 34 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 2013 NUREG 1021 Revision 9 Page 11 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 12 of 34 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 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 Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 12 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 2 Page 13 of 34 Event

Description:

1NC-29 (Pzr Spray Valve) fails open Time Position Applicants Actions or Behavior EVENT 2 Indications: OAC point C1L4455 NORMAL SPRAY FLOW ACTIVATED 1AD-6, F/8 PZR LO PRESS CONTROL RO Recognizes 1NC-29 (PZR SPRAY CTRL FRM LOOP A) is open RO Verifies Pressurizer pressure is normal RO Places controller for 1NC-29 in Manual and closes 1NC-29.

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:

a. Manually close affected spray valve(s).

NOTE TO EVALUATOR: Step 2 RNO b. may apply.

b. IF affected spray valve(s) will not close, THEN perform the following:

1) IF AT ANY TIME the Control Room Supervisor determines that a reactor trip is required, THEN:

a) Trip reactor.

b) WHEN reactor power less than 5%, THEN stop NC Pumps 1A and 1B.

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

2) Select "FAIL CLOSED" for affected spray valve(s) mode select switch:

"1 NC-27 PZR SPRAY VLV MODE SELECT"

"1 NC-29 PZR SPRAY VLV MODE SELECT".

3) IF NC pressure is stable OR increasing, THEN GO TO Step 3.

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.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 13 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 2 Page 14 of 34 Event

Description:

1NC-29 (Pzr Spray Valve) fails open Time Position Applicants Actions or Behavior

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:

Turbine load

Control rods

Boron concentration.

NOTE TO EVALUATOR: Step 7 does not apply.

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: Tech Spec 3.4.1 Condition A (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) should be entered. This condition is likely to be cleared by the time Tech Specs are reviewed per the AP.

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

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

END OF EVENT 2 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 14 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 15 of 34 Event

Description:

NC Loop B Flow Channel 2 fails low.

Time Position Applicants Actions or Behavior EVENT 3 Indications: 1AD-6, A/2 LOOP B LO FLOW ALERT 1AD-2, F/10 DCS TROUBLE BOP Recognize NC Loop B Flow Channel 2 Fails low SRO Enters Tech Spec 3.3.1 NOTE TO EVALUATOR: The following steps are from the annunciator response for 1AD-6, A/2 LOOP B LO FLOW ALERT 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 M (Place channel in trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 3 Booth Operator inserts Trigger 5 for EVENT 4 at discretion of lead examiner.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 15 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 16 of 34 Event

Description:

1B CFPT trips and the Main Turbine fails to runback in automatic requiring the RO to runback the Main Turbine in manual.

Time Position Applicants Actions or Behavior EVENT 4 Indications: 1AD-5, C/1 CFPT B TRIPPED 1AD-5, C/4 CFPT COMMON TROUBLE 1AD-4, C/1,2,3,4 S/G A,B,C,D FLOW MISMATCH LO CF FLOW RO Recognize 1B CFPT tripped RO Recognize auto Main Turbine Runback failure RO Manually runback the Main Turbine as required.

CREW Enter AP/1/A/5500/003, Load Rejection NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/003, Load Rejection, Case 1 (Switchyard Available)

RO 1. Verify turbine load - DECREASING IN AUTOMATIC.

1. RNO Perform the following:

a. Select "MANUAL" on turbine control panel.

b. Depress "CONTROL VALVES LOWER" pushbutton and reduce turbine load as required.

2. Verify proper reactor response:

Control rods - IN "AUTO" AND STEPPING IN

P/R neutron flux - DECREASING.

3. Verify proper steam dump operation as follows:

a. Verify T-Ref instrumentation - AVAILABLE.

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

RO c. Verify the following:

"C-7A LOSS OF LOAD INTLK COND DUMP" status light (1SI 18) - LIT.

Steam dump valves - MODULATING.

d. T-Avg - DECREASING TO T-REF.

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

BOP a. All Pzr PORVs - CLOSED.

b. Normal Pzr spray valves - CLOSED.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 16 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 17 of 34 Event

Description:

1B CFPT trips and the Main Turbine fails to runback in automatic requiring the RO to runback the Main Turbine in manual.

Time Position Applicants Actions or Behavior

5. Verify proper CM System operation as follows:

a. WHEN reactor power is less than 75%, THEN ensure both C-htr drain pumps - OFF.

b. Verify reactor power - GREATER THAN 56% PRIOR TO THE EVENT.

c. Verify standby hotwell pump(s) - ON.

BOP d. Verify standby condensate booster pump(s) - ON NOTE TO EVALUATOR: The crew will determine that the RNO for step 5.d. will not be necessary

6. Verify the following generator alarms - DARK:

1AD-11, C/1 "GEN BKR A OVER CURRENT"

1AD-11, F/1 "GEN BKR B OVERCURRENT".

7. Verify S/G levels are adequate as follows:

All S/G low level alert alarms (1AD-4) - DARK

All S/G low CF flow alarms (1AD-4) - DARK.

RO 8. Verify reactor power - GREATER THAN 20%.

9. IF AT ANY TIME reactor power is less than or equal to 20%,

RO THEN perform Step 8 RNO.

10. Verify AS header pressure - GREATER THAN OR EQUAL TO BOP 140 PSIG.

11. Adjust 1TL-4 (Stm Seal Reg Byp) as necessary to maintain RO steam seal pressure between 4 PSIG - 6 PSIG.

BOP 12. Monitor Enclosure 3 (Rod Insertion Limit Boration).

RO 13. Verify reactor power - LESS THAN 30%.

NOTE TO EVALUATOR: The crew will determine that the RNO step 13.a. does not apply.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 17 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 18 of 34 Event

Description:

1B CFPT trips and the Main Turbine fails to runback in automatic requiring the RO to runback the Main Turbine in manual.

Time Position Applicants Actions or Behavior

13. RNO Perform the following:

b. WHEN the appropriate runback target load is reached, THEN:

1) Stabilize unit at appropriate power level.

2) Maintain control rods above insertion limits.

RO and 3) Adjust the following as required to maintain T-Avg BOP within 1°F of T-Ref:

Turbine load

Control rods

Boron concentration.

c. GO TO Step 15.

15. Verify the following PCBs - CLOSED:

Generator breaker 1A

Generator breaker 1B BOP

PCB 14

PCB 15

PCB 17

PCB 18.

16. Adjust power factor as necessary. REFER TO Unit 1 RO Revised Data Book Figure 43.

17. WHEN the appropriate runback target load is reached, THEN:

Stabilize unit at appropriate power level.

Maintain control rods above insertion limits.

RO and

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

Turbine load

Control rods

Boron concentration.

RO or 18. Notify System Operating Center (SOC) using the red BOP dispatcher telephone of current unit status.

CREW 19. Determine and correct cause of load rejection.

20. Shut down unnecessary plant equipment as follows:

BOP a. Restore CM and CF as follows:

1) Verify C-htr drain pumps - ON.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 18 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 19 of 34 Event

Description:

1B CFPT trips and the Main Turbine fails to runback in automatic requiring the RO to runback the Main Turbine in manual.

Time Position Applicants Actions or Behavior 20.a.1) RNO 1) WHEN time and manpower permit, THEN complete the shutdown of the C-htr drain pumps. REFER TO BOP OP/1/B/6250/004 (Feedwater Heater Vents, Drains and Bleed System).

BOP 20.a. 2) Verify both CF Pumps - IN SERVICE.

SRO 20.a.2) RNO 2) GO TO Step 20.b.

20. b. RC pump(s) and cooling tower fans. REFER TO BOP OP/1/B/6400/001A (Condenser Circulating Water System).

21. Reset steam dump valves as follows:

a. Verify reactor power - STABLE.

b. Verify steam dump valves - IN "T-AVG" MODE.

c. Verify steam dump valves - CLOSED.

d. Reset steam dump valves.

RO e. Verify the following status lights (1SI-18) - DARK:

"C-7A LOSS OF LOAD INTLK COND DUMP"

"C-7B LOSS OF LOAD INTLK ATMOS DUMP".

f. IF "T-AVG" mode of operation is available, THEN ensure steam dump valves in "T-AVG" mode.

g. Verify "STM DUMP CTRL" - IN AUTO.

RO 22. Verify reactor power - GREATER THAN 15%.

RO 23. Verify CA pumps - OFF.

24. Verify reactor power change - GREATER THAN OR EQUAL RO TO 15% IN A 1 HOUR PERIOD.

25. Notify the following sections to take appropriate samples:

Radiation Protection to sample and analyze gaseous effluents. REFER TO Selected Licensee Commitments Manual, Section 16.11-6.

RO or

Primary Chemistry to sample for isotopic analysis of iodine.

BOP REFER TO Tech Specs 3.4.16 (Sample must be taken between 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following last power change greater than or equal to 15% rated thermal power within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period).

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 19 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 20 of 34 Event

Description:

1B CFPT trips and the Main Turbine fails to runback in automatic requiring the RO to runback the Main Turbine in manual.

Time Position Applicants Actions or Behavior

26. Ensure compliance with appropriate Tech Specs:

3.1.1 (Shutdown Margin (SDM))

3.1.6 (Control Bank Insertion Limits)

3.8.1 (AC Sources - Operating)

SLC 16.8-2 (230 KV Switchyard Systems).

NOTE TO EVALUATOR: No Tech Specs need to be entered.

BOP 27. Notify Reactor Group Engineer of occurrence.

28. Determine long term plant status. RETURN TO SRO OP/1/A/6100/003 (Controlling Procedure For Unit Operation).

END OF EVENT 4 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 20 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 21 of 34 Event

Description:

Loss of 1B RN Pump.

Time Position Applicants Actions or Behavior EVENT 5 Indications: 1AD-11, D/1 4KV ESS PWR TRAIN B TROUBLE 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 Enclosure 1 SRO (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.

NOTE TO EVALUATOR: No switches in the following step need to be manipulated. The KC (Component Cooling) Hx Otlt Mode switch should be in the KC Temp position if the corresponding train of KC is in service.

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).

NOTE TO EVALUATOR: The BOP determines that no changes have occurred to the VC/YC (Control Room Ventilation and Chilled Water System) via the OAC or on rear of 1MC-3 in the following step.

10. Determine VC/YC status as follows:

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 2013 NUREG 1021 Revision 9 Page 21 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 22 of 34 Event

Description:

Loss of 1B 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))

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: T.S. 3.7.8 Condition A (Restore 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 11 for EVENT 6 at discretion of lead examiner.

13. Determine required notifications:

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

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

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

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

END OF EVENT 5 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 22 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6 Page 23 of 34 Event

Description:

1CF-33 (S/G 1A CF CONT ISOL) closes.

Time Position Applicants Actions or Behavior EVENT 6 Indications: 1AD-4, A-1 S/G A FLOW MISMATCH LO CF FLOW 1AD-4, A/1,2,4 S/G A,B,D FLOW MISMATCH CF>STM 1AD-4, B/1 S/G A LEVEL DEVIATION Recognizes loss of all feed flow to the 1A S/G at greater than 5%

RO reactor power.

Manually trips the reactor per the immediate actions of RO AP/1/A/5500/006 (Loss of S/G Feedwater), Case l (Loss of CF Supply To S/Gs).

CREW Enter EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/0006, (Loss of S/G Feedwater), Case l (loss of CF Supply To S/Gs).

RO 1. Verify reactor power - LESS THAN 5%.

1. RNO IF AT ANY TIME all CF supply to S/G(s) lost, THEN RO perform the following:

a. Manually trip reactor.

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

END OF EVENT 6 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 23 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7, 8 and 9 Page 24 of 34 Event

Description:

Steamline break outside containment on the 1A S/G. Main Steam Isolation (both trains) fails to actuate requiring manual initiation. 1NI-9A (NV PUMP C/L INJ ISOL) fails to open on the Safety Injection.

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).

2. Verify Reactor Trip:

All rod bottom lights - LIT RO

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:

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)

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.

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

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 24 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7, 8 and 9 Page 25 of 34 Event

Description:

Steamline break outside containment on the 1A S/G. Main Steam Isolation (both trains) fails to actuate requiring manual initiation. 1NI-9A (NV PUMP C/L INJ ISOL) fails to open on the Safety Injection.

Time Position Applicants Actions or Behavior

11. Verify proper CA pump status as follows:

RO a. Motor driven CA pumps - ON.

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

NOTE TO EVALUATOR: If the RO takes longer to recognize the failed Main Steam Isolation, S/G N/R levels may be below 11% and the crew would transition to the RNO and may start CA PMP #1.

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

NV pumps BOP

ND pumps

NI pumps.

BOP 13. Verify all KC pumps - ON.

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

NOTE TO EVALUATOR: The crew may determine that the 1B RN Pump will not start due to the failure and proceed to step 15.

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

14. RNO b. IF any Unit 1 RN pump is off, THEN perform the following for affected train(s):

BOP 1) Reset ECCS.

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

3) Start affected pump(s).

RO and 14. RNO b. 4) IF AT ANY TIME B/O occurs, THEN restart S/I BOP equipment previously 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 hands Enclosure 3 to a Unit 2 operator and sets 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:

All MSIVs - CLOSED

All MSIV bypass valves - CLOSED

All S/G PORVs - CLOSED.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 25 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7, 8 and 9 Page 26 of 34 Event

Description:

Steamline break outside containment on the 1A S/G. Main Steam Isolation (both trains) fails to actuate requiring manual initiation. 1NI-9A (NV PUMP C/L INJ ISOL) fails to open on the Safety Injection.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The actions of step 16 RNO b.1) may have already been performed by the RO due to the failed automatic Main Steam Isolation.

b. IF any valve open, THEN perform the following:

CRITICAL RO 1) Initiate Main Steam Isolation.

TASK

2) IF any valve is still open, THEN CLOSE valve.

END OF EVENT 8

17. Verify proper S/I flow as follows:

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

RO b. NC pressure - LESS THAN 1620 PSIG.

RO c. NI pumps - INDICATING FLOW.

RO d. NC pressure - LESS THAN 285 PSIG.

17.d.RNO Perform the following:

RO or

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

NOTE TO EVALUATOR: Step 17 RNO d. 2) will not apply SRO 3) Observe note prior to Step 18 and 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).

19. Control S/G levels as follows:

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%.

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 1NI-9A (NV PUMP C/L INJ ISOL) failure to open until this step, they will transition to the RNO and open 1NI-9A.

END OF EVENT 9 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 26 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7 Page 27 of 34 Event

Description:

Steamline break outside containment on the 1A S/G.

Time Position Applicants Actions or Behavior 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:

a. All Pzr PORVs - CLOSED.

b. Normal Pzr spray valves - CLOSED.

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.

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 2013 NUREG 1021 Revision 9 Page 27 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7 Page 28 of 34 Event

Description:

Steamline break outside containment on the 1A 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).

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 any S/G pressure - STABLE OR INCREASING.

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. Maintain at least one intact S/G available for NC System BOP cooldown in subsequent steps.

RO or

7. Verify faulted S/G(s) PORV - CLOSED.

BOP RO or

8. Ensure CA System valve control - RESET.

BOP NOTE TO EVALUATOR: The actions of step 9.c.1) may have been performed by the RO during performance of Enclosure 4 (NC Temperature Control) of EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection)

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

S/G 1A:

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

b. CLOSE the following valves:

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

RO or CRITICAL 2) 1CA-62A (CA Pmp A Disch To S/G 1A Isol).

BOP TASK 3) 1CA-66B (CA Pmp 1 Disch To S/G 1A Isol).

c. Verify the following blowdown isolation valves - CLOSED:

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

2) 1BB-148B (S/G 1A Bldwn Cont Isol Byp).

3) 1BB-57B (S/G 1A Bldwn Cont Isol Otsd).

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 28 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7 Page 29 of 34 Event

Description:

Steamline break outside containment on the 1A S/G.

Time Position Applicants Actions or Behavior

11. 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 was previously reset by the RO in order to throttle S/G N/R levels as directed by E-0.

NOTE TO EVALUATOR: The BOP opens the following valves when aligning the S/Gs for chemistry sample in step b. below:

1NM-191B (S/G 1A SMPL HDR CONT ISOL)

1NM-201A (S/G 1B SMPL HDR CONT ISOL)

1NM-211B (S/G 1C SMPL HDR CONT ISOL)

1NM-221A (S/G 1D SMPL HDR CONT ISOL)

1NM-190A (S/G 1A BLDWN SMPL CONT ISOL)

1NM-200B (S/G 1B BLDWN SMPL CONT ISOL)

1NM-210A (S/G 1C BLDWN SMPL CONT ISOL)

1NM-220B (S/G 1D BLDWN SMPL CONT ISOL)

BOP b. Align all S/Gs for Chemistry sampling.

c. Perform at least one of the following:

RO or

Notify Chemistry to sample all S/Gs for activity.

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).

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 29 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7 Page 30 of 34 Event

Description:

Steamline break outside containment on the 1A S/G.

Time Position Applicants Actions or Behavior 11.e.RNO e. Request RP to perform the following:

RO or 1) Monitor the area of the steam fault for radiation.

BOP 2) Notify Control Room of any abnormal radiation conditions RO or f. WHEN activity results are reported, THEN verify all S/Gs BOP indicate no activity.

12. 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 2013 NUREG 1021 Revision 9 Page 30 of 34

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7 Page 31 of 34 Event

Description:

Steamline break outside containment on the 1A 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 ES-1.1 (Safety Injection Termination)

RO and

1. Monitor Enclosure 1 (Foldout Page).

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 was previously reset by the BOP as directed by E-2.

3. Establish VI to Containment as follows:

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

Verify VI pressure - GREATER THAN 85 PSIG.

BOP 4. Ensure only one NV pump - ON.

NOTE TO EVALUATOR: BOP will secure one NV pump.

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:

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 Pumps 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 7 END OF SCENARIO Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 31 of 34

Catawba Nuclear Station NRC Exam December 2013 Attachment List Scenario 3 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),

Rev. 077 ATTACHMENT 4 - AP/1/A/5500/003 Enclosure 3 (Rod Insertion Limit Boration), Rev. 041 ATTACHMENT 5 - AP/0/A/5500/020 Enclosure 1 (Foldout Page), Rev. 042 ATTACHMENT 6 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page), Rev. 041 ATTACHMENT 7 - EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification), Rev. 041 ATTACHMENT 8 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control), Rev. 041 ATTACHMENT 9 - EP/1/A/5000/E-2 Enclosure 1 (Foldout Page), Rev. 014 ATTACHMENT 10 - EP/1/A/5000/ES-1.1 Enclosure 1 (Foldout Page), Rev. 032 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 32 of 34

Catawba Nuclear Station NRC Exam December 2013 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK C-1 Isolate the faulted S/G before transition out of E-2.

Manually actuate main steamline isolation before a C-2 severe (orange-path) challenge develops to either the subcriticality or the integrity CSF or before transition to ECA 2.1, whichever happens first.

Comments:

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 33 of 34

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 85% MOL 874 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) is in progress up to step 3.2.

Other Information Needed to Assume the Shift

1B CBP pump is tagged out for preventative maintenance and is expected to be returned to service in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . 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 .

1B LH Pump is tagged out and expected to return to service in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Direction for the crew is to increase reactor power to 100%.

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 HLP NRC EXAM SCENARIO # 4 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 1 of 42

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1 Facility: Catawba NRC Exam 2013 Scenario No.: 4 Op Test No.: 2013301 Examiners: Operators: SRO RO BOP Initial Conditions: IC# 180; Unit 1 is at 100% power, EOL. 1B LH Pump is out of service.

Turnover: Unit 1 is at 100% power, EOL. 1B LH Pump is out of service. Letdown flow has been increased to 100 gpm for NC System cleanup in preparation for the upcoming outage. Direction for the crew is to decrease power per the reactivity management plan to ~95% in preparation for Main Steam Safety Valve testing.

Event Malf. No. Event Event No. Type* Description N-BOP 1 --- R-RO Decrease power to 95%.

N-SRO 2 KF004 C-BOP 1A KF (Spent Fuel Pool Cooling) pump trips. AP/41 C-SRO 3 ENB013B TS-SRO N42 fails low. AP/16 4 SGL005D C-RO 1CF-55 (1D S/G Feed Reg Vlv) fails closed (ramps in). AP/06 C-SRO 5 NV001 I-BOP 1NV-172A (divert valve) diverts to Recycle Holdup Tank.

I-SRO 6 NC009F C-RO C-SRO 1NC-36B (PZR PORV) fails open, manual closure successful. AP/11.

TS-SRO 7 SG001D C-ALL 1D S/G tube leak. (25-350 gpm ramp) AP/10 8 SG001D M-ALL 1D S/G tube rupture.

9 EHC002 C-RO Turbine trip failure on reactor trip.

C-SRO 10 ISE003B I-BOP Train B Phase A Isolation Signal failure.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 2 of 42

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1 Scenario 4 - Summary Initial Condition IC 180 Unit 1 is at 100% power, EOL. 1B LH pump is out of service.

Turnover:

Unit 1 is at 100% power, EOL. 1B LH Pump is out of service. Letdown flow has been increased to 100 gpm for NC System cleanup in preparation for the upcoming outage. Direction for the crew is to decrease power per the reactivity management plan to ~95% in preparation for Main Steam Safety Valve testing.

Event 1 Decrease power to 95%.

Event 2 1A KF (Spent Fuel Pool Cooling) pump trips. AP/41 (Loss of Spent Fuel Cooling or Level) entry.

BOP manually starts the 1B KF pump.

Event 3 Power Range NI N42 fails LOW. AP/16 (Malfunction of Nuclear Instrumentation) entry. TS evaluation required.

Event 4 1CF-55 (1D S/G Feed Reg Vlv) fails closed (ramps closed). RO takes manual control of the feed reg valve to maintain 1D S/G level. AP/06 (Loss of SG Feedwater) will be entered.

Event 5 1NV-172A (VCT LEVL CTRL) controller fails HI, causing 1NV-172A to divert to the RHT (Recycle Holdup Tank). BOP places the control switch for 1NV-172A to the VCT (Volume Control Tank) position.

Event 6 1NC-36B (PZR PORV) fails open. Manual closure will be successful. AP/11 (Pressurizer Pressure Anomalies) entry. TS evaluation required.

Event 7 A tube leak on 1D S/G ramps from 25 - 350 gpm. AP/10 (Reactor Coolant Leak) entry. Tube leak increases to a tube rupture and requires a reactor trip.

Event 8 Tube leak increases to a tube rupture and requires a reactor trip.

Event 9 Main Turbine fails to trip on the reactor trip. RO manually trips the turbine.

Event 10 Train B Phase A Isolation fails to actuate on the safety injection. BOP manually initiates.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 3 of 42

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1 Critical Task 1 - Isolate feed/steam to/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.

Critical Task 3 - Manually trip the main turbine before a severe (orange-path) challenge develops to either subcriticality or the integrity CSF or before transition to ECA-2.1, whichever happens first.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 4 of 42

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC #180 START TIME:__________

Trigger Instructor Action Delay Ramp Delete Event Final In OVR-MT016A (HYDR FLUID PMP n/a OFF 1B OFF LT)

LOA-KF004 (RACKOUT KF PMP RACKO 1 2 A) UT MAL-ENB013B (P/R 42 BLOWN 3 INST 3 FUSE)

MAL-SGL005D (S/G/D/HI PWR 5 200 2 MIN 4 LVL CONTROLLER FAILURE)

MAL-NV001 (VCT LVL CTRL 7 100 5 FAILURE)

XMT-VQ001 (PVQ_5040 CNT 9 .125 6 PRESS MTR)

VLV-NC009F (NC36B PZR PORV 10 1 6 FAIL TO POSITION)

VLV-NC009F (NC36B PZR PORV 12 1 1 SEC 6 FAIL TO POSITION)

MAL - SG001D (S/G D TUBE 15 350 2 MIN 7,8 LEAK)

MAL-EHC002 (TURBINE TRIP n/a AUTO 9 FAILURE)

MAL-ISE003B (AUTO PHASE A n/a BLOCK 10 ISOL SIGNAL TRN B)

Ensure TRIGGER 10 = x5ri017a Ensure TRIGGER 12 = x10i277c Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 5 of 42

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1

2. SIMULATOR BRIEFING 2.1 Control Room Assignments:

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

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

3.2 Scenario EVENT 1, decrease reactor power to 95%.

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

3.3 Scenario EVENT 2, 1A KF Pump trips.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 1 to trip the 1A KF Pump.

BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance is dispatched to investigate the 1A KF Pump and/or Breaker, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with 1A KF Pump and or Breaker, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF SWM is called to write a w/r for the 1A KF Pump and/or Breaker, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF RP is notified of the loss of Spent Fuel Pool cooling, REPEAT back the information.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 6 of 42

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1 BOOTH INSTRUCTOR ACTION IF Operator is dispatched to check out 1B KF Pump, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Operator is dispatched to ensure 1KC-155 OPEN, REPEAT back the information. After 3 minutes contact the Control Room and state that 1KC-155 is open. Give a call back number!

BOOTH INSTRUCTOR ACTION IF Operator is dispatched to throttle 1KF-22, REPEAT back the information. After 3 minutes had elapsed, contact the Control Room and state that 1KF-22 has been throttled 3 turns open.

BOOTH INSTRUCTOR ACTION IF Operator is dispatched to adjust 1KF-22, REPEAT back the information. After 1 minute has elapsed, contact the Control Room and state that 1KF-22 has been adjusted as required.

3.4 Scenario EVENT 3, N-42 blown instrument fuse.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause the instrument fuse for N-42 to blow.

BOOTH INSTRUCTOR ACTION IF IAE is contacted to fail bistables per model W/O #00874531, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF SWM is contacted to write a w/r for N42, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF the Reactor Group is notified of N42 failure, REPEAT back the information.

3.5 Scenario EVENT 4, 1CF-55 (S/G D Feed Reg Vlv) fails closed.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to fail 1CF-55 (S/G D Feed Reg Vlv) closed.

BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with 1CF-55, REPEAT back the information.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 7 of 42

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1 BOOTH INSTRUCTOR ACTION IF Operator is dispatched to locally investigate 1CF-55, REPEAT back the information.

3.6 Scenario EVENT 5, 1NV-172A Controller Fails Hi BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 7 to cause the controller for 1NV-172A to fail Hi BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with 1NV-172A controller, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to write a w/r for the 1NV-172A controller, REPEAT back the information.

3.7 Scenario EVENT 6, 1NC-36B (PZR PORV) fails open.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 9 to cause 1AD-13, F/5 (HVAC PANEL TROUBLE) to alarm.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to write a w/r for the 1NC-36B, REPEAT back the information.

3.8 Scenario EVENT 7, S/G 1D Tube Leak BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 15 to cause a tube leak on the 1D S/G.

BOOTH INSTRUCTOR ACTION IF Chemistry is contacted to verify chemistry valves per 1EMF-33 alarm response, REPEAT back the order 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.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 8 of 42

Catawba Nuclear Station NRC Exam September 2013 Appendix D Scenario Outline Form ES-D-1 BOOTH INSTRUCTOR ACTION IF Secondary Chemistry is notified to determine affected S/G by sampling REPEAT the order Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 9 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 10 of 42 Event

Description:

Power decrease to 95% power.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: Crew begins with a power decrease. BOP performs a boration per OP/1/6150/009, Enclosure 4.2. Amount of boration is determined by the power decrease plan. The RO inputs turbine target data. These two evolutions may be performed concurrently. Initial conditions are complete. A reactivity management brief was performed during turnover. Step 3.1 is complete.

BOP Perform a boration.

RO Input target into the main turbine control panel.

NOTE TO EVALUATOR: Applicant may perform a boration 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 from OP/1/6150/009, Boron Concentration Control, Enclosure 4.2 (Boration).

3.2 Ensure the following valve control switches in "AUTO":

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.

_________ 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 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 IF required, adjust the controller for 1NV-238A (B/A Xfer BOP Pmp To Blender Ctrl) to the desired flow.

NOTE TO EVALUATOR: Step 3.10 will be N/Ad Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 10 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 11 of 42 Event

Description:

Power decrease to 95% 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 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.

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 2013 NUREG 1021 Revision 9 Page 11 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 12 of 42 Event

Description:

Power decrease to 95% 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:

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 2013 NUREG 1021 Revision 9 Page 12 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 13 of 42 Event

Description:

Power decrease to 95% 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.

{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 2013 NUREG 1021 Revision 9 Page 13 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 14 of 42 Event

Description:

Power decrease to 95% 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 inserts Trigger 1 for EVENT 2 at discretion of lead examiner.

END OF EVENT 1 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 14 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 2 Page 15 of 42 Event

Description:

1A KF Pump trips.

Time Position Applicants Actions or Behavior EVENT 2 Indications: 1AD-11, A/1 4KV ESS PWR TRAIN A TROUBLE OAC pt C1X1060 NEW TRAIN A 1.47 ALARM BOP Recognize 1A KF (Spent Fuel Pool Cooling) Pump tripped CREW Enter AP/1A/5500/041 (Loss of Spent Fuel Cooling or Level)

BOP Start the 1B KF Pump.

NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/041 (Loss of Spent Fuel Cooling or Level), Case l (Loss of Spent Fuel Pool Cooling).

NOTE

Spent Fuel Pool temperature can be verified locally with an infrared thermometer.

Spent Fuel Pool level can be determined locally when instrument indications are unavailable. The bottom of spent fuel pool skimmer trough elevation is 38 feet 10 inches.

1. Verify Spent Fuel Pool conditions as follows:

a. Verify the following:

Spent Fuel Pool level - GREATER THAN 39 FT.

Spent Fuel Pool level - STABLE.

b. IF AT ANY TIME Spent Fuel Pool level decreases to less than 39 Ft, THEN perform the following:

CREW

1) Stop KF pump(s).

2) GO TO Case II (Loss of Spent Fuel Pool Level).

BOP 2. Verify fuel movement - IN PROGRESS.

SRO 2. RNO GO TO Step 4.

4. IF AT ANY TIME conditions in the Spent Fuel Bldg. warrant, RO THEN evacuate non-essential personnel from Spent Fuel Bldg.

RO or

5. Notify RP of loss of spent fuel cooling.

BOP BOP 6. Ensure KC pumps - IN SERVICE AS REQUIRED.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 15 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 2 Page 16 of 42 Event

Description:

1A KF Pump trips.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The CRS should determine that Unit 1 S/I has not actuated.

7. Verify LOCA occurred as follows:

Unit 1 S/I - ACTUATED CREW OR

Unit 2 S/I - ACTUATED

7. RNO Perform the following:

a. IF AT ANY TIME either unit S/I actuates, THEN CREW RETURN TO Step 7.

b. GO TO Step 10.

10. Verify at least one train of KC - ALIGNED TO AUX BLDG NON ESSENTIAL HEADER.

A Train:

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

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

B Train:

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

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

BOP 11. Verify KF pumps - OFF.

NOTE TO EVALUATOR: The crew determines that step 12 does not apply.

BOP 13. Place KF in service as follows:

NOTE TO EVALUATOR: The crew determines that steps 13.a. and 13.b do not apply.

c. Determine the allowable KF pump flowrate. REFER TO CREW Enclosure 2 (Allowable KF Flowrates).

NOTE TO EVALUATOR: The crew determines that the allowable flowrate is 2,840 gpm.

d. Verify Spent Fuel Pool level sufficient to allow starting KF pump as follows:

Spent Fuel Pool Level - GREATER THAN OR EQUAL BOP TO 39 FT.

Allowable KF pump flowrate - GREATER THAN OR EQUAL TO 750 GPM.

e. Record the allowable KF pump flowrate on Enclosure 3 SRO Placing KF In Service).

f. Verify Spent Fuel Pool temperature - LESS THAN OR EQUAL TO 200°F.

BOP Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 16 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 2 Page 17 of 42 Event

Description:

1A KF Pump trips.

Time Position Applicants Actions or Behavior NOTE If available the previously running pump is preferable to start.

g. Place available KF pump in service using the allowable KF CREW pump flowrate. REFER TO Enclosure 3 (Placing KF In Service).

NOTE TO EVALUATOR: The CRS may decide to read Enclosure 3 or hand it off to the BOP.

NOTE TO EVALUATOR: The following steps are from Enclosure 3 (Placing KF In Service).

1. Record allowable KF flowrate ____________. REFER TO SRO Enclosure 2 (Allowable KF Flowrates).

NOTE TO EVALUATOR: Step 2 will not apply.

3. Ensure sufficient KC pumps in service to allow an increase of BOP 2000 GPM KC flow.

NOTE TO EVALUATOR: The crew may decide to start an additional KC (Component Cooling) Pump.

NOTE TO EVALUATOR: Step 4 will not apply.

NOTE TO EVALUATOR: The BOP will dispatch an operator to perform steps 5.a, 5.d, and 5.f.

5. IF placing KF Cooling Loop 1B in operation, THEN perform the following:

a. Ensure 1KC-155 (1B KF Hx Inlet) (AB-585, PP-52/53, Rm 418)

- OPEN.

BOP b. Close 1KC-149 (KF Hx 1A Cool Wtr Otlt).

BOP c. Adjust 1KC-156 (KF Hx 1B Cool Wtr Otlt) to 2000 gpm.

d. Throttle 1KF-22 (1B KF Loop Flow Control) (AB-587, PP-52, BOP Rm 418) three turns open.

BOP e. Start KF Pump 1B.

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

f. Adjust 1KF-22 (1B KF Loop Flow Control) (AB-587, PP-52, Rm BOP 418) to achieve to the allowable flowrate recorded in Step 1.

g. Adjust 1KC-156 (KF Hx 1B Cool Wtr Otlt) as required to BOP achieve desired Spent Fuel Pool temperature.

6. WHEN time and personnel permit, THEN perform applicable BOP steps of OP/1/A/6200/005 (Spent Fuel Cooling System).

NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/041 (Loss of Spent Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 17 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 2 Page 18 of 42 Event

Description:

1A KF Pump trips.

Time Position Applicants Actions or Behavior Fuel Cooling or Level), Case l (Loss of Spent Fuel Pool Cooling).

NOTE It may take several hours for Spent Fuel Pool temperature to stabilize after cooling is reestablished.

14. Verify Spent Fuel Pool temperature - STABLE OR BOP DECREASING.

BOP 15. Verify Spent Fuel Pool temperature less than 125°F.

16. Ensure VF in filter mode. REFER TO Enclosure 4 (VF Filter BOP Mode Verification).

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 proper VC/YC system operation. REFER TO BOP Enclosure 5 (Control Room Ventilation System Verification).

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

3.7.14 (Spent Fuel Pool Water Level)

3.7.15 (Spent Fuel Pool Boron Concentration)

3.7.16 (Spent Fuel Assembly Storage)

3.9.6 (Refueling Cavity Water Level)

4.3 (Fuel Storage)

SLC 16.7-9 (Standby Shutdown System)

SLC 16.9-21 (Refueling Operations - Storage Pool Water Level).

NOTE TO EVALUATOR: No Tech Specs apply.

20. Verify the following:

Spent Fuel Pool temperature - LESS THAN 125°F.

KF pump(s) - ON.

21. IF purification of the Spent Fuel Pool is desired, THEN BOP REFER TO OP/1/A/6200/005 (Spent Fuel Cooling System).

22. Determine long term plant status. RETURN TO procedure CREW in affect.

END OF EVENT 2 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 18 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 19 of 42 Event

Description:

N-42 blown instrument fuse.

Time Position Applicants Actions or Behavior EVENT 3 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 1AD-2, F/10 DCS TROUBLE 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 (failed low)

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:

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.

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 2013 NUREG 1021 Revision 9 Page 19 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 20 of 42 Event

Description:

N-42 blown instrument fuse.

Time Position Applicants Actions or Behavior

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

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

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.

NOTE The following annunciators will actuate in the following step:

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/5, "P/R HI VOLTAGE FAILURE"

9. De-energize the affected channel as follows:

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

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

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

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

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

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

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

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

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

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 20 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 21 of 42 Event

Description:

N-42 blown instrument fuse.

Time Position Applicants Actions or Behavior

15. Ensure compliance with appropriate Tech Specs:

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 (Perform SR 3.2.4.2 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when > 75 % RTP and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to place the channel in trip)

3. Power Range Neutron Flux High Positive Rate Condition D (Perform SR 3.2.4.2 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when > 75 % RTP and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to place the channel in trip)

6. Overtemperature T Condition E (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to place the channel in trip)

7. Overpower T Condition E (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to place the channel in trip)

16. Reactor Trip System Interlocks

b. Low Power Reactor Trips Block, P-7, - Condition S (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to verify interlock is in required state for existing conditions)

c. Power Range Neutron Flux, P-8, - Condition S (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to verify interlock is in required state for existing conditions)

d. Power Range Neutron Flux, P-9, - Condition S (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to verify interlock is in required state for existing conditions)

e. Power Range Neutron Flux, P-10, - Condition R (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to verify interlock is in required state for existing conditions)

16. Determine required notifications:

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

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.

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

END OF EVENT 3 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 21 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4 Page 22 of 42 Event

Description:

1CF-55 (1D S/G Feed Reg Vlv) fails closed.

Time Position Applicants Actions or Behavior EVENT 4 Indications: 1AD-4, B/4 S/G D LEVEL DEVIATION 1AD-4, C/4 S/G D FLOW MISMATCH LO CF FLOW Place 1CF-55 (S/G D Feed Reg Vlv) in Manual and throttle as RO necessary to control 1D 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)

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:

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

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

RO or service CF pump(s):

IN AUTO

RESPONDING ADEQUATELY

5. Verify all S/G CF control valves:

RO or

IN AUTO BOP

RESPONDING ADEQUATELY

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 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 22 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4 Page 23 of 42 Event

Description:

1CF-55 (1D S/G Feed Reg Vlv) fails closed.

Time Position Applicants Actions or Behavior

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 4 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 23 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 5 Page 24 of 42 Event

Description:

Controller for 1NV-172A (VCT LEVEL CTRL) fails Hi.

Time Position Applicants Actions or Behavior EVENT 5 Indications: OAC pt C1Q0348 VLV NV172A NC FILTER OTLT 3-WAY CTRL -

INTERMEDIATE Recognizes that 1NV-172A (3-WAY DIVERT TO VCT-RHT) has BOP diverted to the RHT Places the control switch for 1NV-172A (3-WAY DIVERT TO VCT-BOP RHT) to the VCT position.

NOTE TO EVALUATOR: The following steps are from the OAC alarm response for pt.

C1Q0348 VLV NV172A NC FILTER OTLT 3-WAY CTRL BOP 1. Check VCT Level BOP 2. IF VCT Level is high, THEN monitor NV-172A position.

3. WHEN VCT Level returns to normal, THEN ensure NV-172A BOP returns to the VCT position.

4. Verify NV-172A control switch is in AUTO or position required by BOP plant operation.

Booth Operator inserts Trigger 9 for EVENT 6 at discretion of lead examiner.

END OF EVENT 5 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 24 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 Page 25 of 42 Event

Description:

1NC-36B (PZR PORV) fails open Time Position Applicants Actions or Behavior EVENT 6 NOTE TO EVALUATOR: 1AD-13, F/5 HVAC PANEL TROUBLE alarms. BOP goes to the rear of the control boards to acknowledge the alarm. When the BOP depresses the acknowledge button, 1NC-36B (PZR PORV) will fail open.

Indications: 1AD-6, E/10 PZR PORV DISCH HI TEMP 1AD-6, F/8 PZR LO PRESS CONTROL OAC pt C1Q0756 VLV NC36B PZR POWER OPERATED RELIEF - OPEN RO Close 1NC-36B (PZR PORV)

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

RO 1. Verify all Pzr PORVs - CLOSED.

1. RNO Perform the following:

a. Manually close Pzr PORV(s).

NOTE TO EVALUATOR: Step 1.b. 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.

NOTE TO EVALUATOR: Depending on how fast the RO responded to the PORV failure, the Pzr heaters may not be energized, however, the crew will determine that the step 3 RNO will not apply.

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 2013 NUREG 1021 Revision 9 Page 25 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 Page 26 of 42 Event

Description:

1NC-36B (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:

T.S. 3.4.1 (RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits) Condition A (restore to within limits in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months )

T.S. 3.4.11 (Pressurizer Power Operated Relief Valves (PORVs)) Condition A (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to close and maintain power to associated block valve).

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

END OF EVENT 6 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 26 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7 Page 27 of 42 Event

Description:

A tube leak develops on 1D S/G tube leak (25-350 gpm)

Time Position Applicants Actions or Behavior EVENT 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 Selects AUTO on Unit 1 CSAE EXH switch on panel 1MC-13 per BOP the annunciator response for 1RAD-1, B/1 (1EMF CSAE EXHAUST HI RAD).

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

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.

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

NOTE TO EVALUATOR: Crew determines that step 2 RNO c. does not apply

c. IF Pzr level stable OR increasing, THEN GO TO Step BOP 3.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 27 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7 Page 28 of 42 Event

Description:

A tube leak develops on 1D S/G tube leak (25-350 gpm)

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The crew will eventually recognize that pressurizer level cannot be maintained and manually trip the reactor and manually initiate safety injection per Enclosure 1, and then transition to 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:

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

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

1NV-13A (Letdn Orif 1A Otlt Cont Isol).

NOTE TO EVALUATOR: Crew determines 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 7 TRANSITION TO EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 28 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 8, 9 and 10 Page 29 of 42 Event

Description:

1D S/G tube rupture, Main Turbine fails to trip on reactor trip, Train B of Phase A Isolation Signal fails to actuate.

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).

2. Verify Reactor Trip:

All rod bottom lights - LIT RO

All reactor trip and bypass breakers - OPEN

I/R power - DECREASING.

3. Verify Turbine Trip:

All turbine stop valves - CLOSED CRITICAL 3. RNO Perform the following:

RO TASK a. Trip turbine.

NOTE TO EVALUATOR: Step 3. RNO b. will not apply.

END OF EVENT 9 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)

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 9. a. RNO a. Initiate Phase A Isolation.

END OF EVENT 10 Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 29 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 8 Page 30 of 42 Event

Description:

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

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

BOP LIT.

10. Verify proper Phase B actuation as follows:

BOP a. Verify Containment pressure - HAS REMAINED LESS THAN 3 PSIG RO or b. IF AT ANY TIME containment pressure exceeds 3 PSIG 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:

NV pumps BOP

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).

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

NOTE TO EVALUATOR: SRO hands Enclosure 3 to a Unit 2 operator and sets Enclosure 3 off to the side.

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

17. Verify proper S/I flow as follows:

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

RO b. NC pressure - LESS THAN 1620 PSIG.

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.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 30 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 8 Page 31 of 42 Event

Description:

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

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%.

RO 20. Verify all CA isolation valves - OPEN.

21. Verify S/I equipment status based on monitor light panel - IN BOP 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 RO Temperature Control).

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

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)

1EMF-27 (Steamline 1B)

1EMF-28 (Steamline 1C)

1EMF-29 (Steamline 1D).

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 31 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 8 Page 32 of 42 Event

Description:

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

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 2013 NUREG 1021 Revision 9 Page 32 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 8 Page 33 of 42 Event

Description:

1D 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).

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

S/G level - INCREASING IN AN UNCONTROLLED MANNER.

OR Chemistry or RP has determined ruptured S/G CREW OR Any of the following EMF trip 1 lights - LIT:

1EMF-26 (Steamline 1A)

1EMF-27 (Steamline 1B)

1EMF-28 (Steamline 1C)

1EMF-29 (Steamline 1D).

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 CRITICAL follows:

TASK

S/G 1D RO

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

2) Verify the following blowdown isolation valves -

CLOSED:

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

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

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

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

CRITICAL RO

MSIV TASK

MSIV bypass valve.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 33 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 8 Page 34 of 42 Event

Description:

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

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 1D:

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

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

c. IF AT ANY TIME ruptured S/G(s) N/R level is less than 11%

(29% ACC), THEN perform Step 6.

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

BOP 8. Verify any NC pump - ON.

BOP 9. Verify Pzr pressure - GREATER THAN 1955 PSIG.

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, maintaining steam pressure negative rate less than 2 psig per second will prevent a Main Steam Isolation.

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

10. Initiate NC System cooldown as follows:

RO a. Determine required core exit temperature based on lowest ruptured S/G pressure from table below:

NOTE TO EVALUATOR: SRO and BOP use the table in step 10 to determine target core exit temperature.

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

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

CLOSED:

MSIV

MSIV bypass valves.

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

NOTE TO EVALUATOR: Step 10.b.3) will be N/Ad.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 34 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 8 Page 35 of 42 Event

Description:

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

c. 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.

d. Verify steam dumps - IN PRESSURE MODE.

10.d. RNO 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).

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.

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

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

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

BOP LIT.

10.g. RNO Perform the following:

1) Depressurize NC System to less than 1955 PSIG using one of the following:

Pzr spray OR

Pzr PORV.

BOP 2) WHEN "P-11 PZR S/I BLOCK PERMISSIVE" status light (1SI-18) 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.

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

11. Control intact S/G levels as follows:

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

RO (29% ACC).

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 35 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 8 Page 36 of 42 Event

Description:

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

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

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

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

13. Reset the following:

a. ECCS.

BOP b. D/G load sequencers.

c. Phase A

d. Phase B.

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

14. Establish VI to containment as follows:

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

Verify VI pressure - GREATER THAN 85 PSIG.

15. Determine if ND pumps should be stopped:

a. Any ND pump - ON.

b. Any running ND pump suction - ALIGNED TO FWST.

BOP c. NC pressure - GREATER THAN 285 PSIG.

d. Stop all ND pump(s) with suction aligned to FWST.

e. IF AT ANY TIME NC pressure decreases to less than 285 PSIG in an uncontrolled manner, THEN restart ND pumps.

RO 16. Verify ruptured S/G(s) - IDENTIFIED. (1D)

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. Stop NC System cooldown.

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

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 36 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 8 Page 37 of 42 Event

Description:

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

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.

20. Depressurize NC System using PZR Spray as follows:

a. Verify normal Pzr spray flow - AVAILABLE.

b. Initiate NC depressurization using maximum available spray.

c. IF AT ANY TIME during this step one of the following conditions exists, THEN GO TO Step 21:

Spray valves not effective in reducing NC pressure OR

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

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

Both of the following:

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

PRESSURE BOP

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

Both of the following:

NC pressure - WITHIN 300 PSIG OF RUPTURED S/G(s) PRESSURE

Pzr level - GREATER THAN 41% (50% ACC)

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

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

e. CLOSE normal Pzr spray valves.

f. Verify 1NV-37A (NV Supply To Pzr Aux Spray) - CLOSED SRO g. Observe Caution prior to Step 23 and GO TO Step 23.

Appendix D Catawba NRC Exam Sep 2013 NUREG 1021 Revision 9 Page 37 of 42

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 8 Page 38 of 42 Event

Description:

1D S/G tube rupture Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The crew may decide that spray valves are not effective and transition to step 21.

21. Depressurize NC System using Pzr PORV as follows:

a. Verify at least one Pzr PORV - AVAILABLE.

b. OPEN one Pzr PORV.

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

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

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

Both of the following:

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

PRESSURE

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

d. CLOSE Pzr PORV.

e. CLOSE Pzr spray valves.

BOP 22. Verify NC pressure - INCREASING.

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)