ML111540509

° HTWL PUMP IC 2.5 Within 30 seconds after pump start, verify that the hotwell pump vent valve closes automatically. (On I HWCP, TB-568, I J-22, or OAC BOP CMHWP graphic)

° I CM-28 (HWP-C Vent Vlv) 2.6 Place the control switch for the hotwell pump to be stopped in the OFF BOP position:

HTWL PUMP lB 2.7 Place the hotwell pump stopped in Step 2.6 in standby alignment, place BOP the control switch in AUTO:

HTWL PUMP I B Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Pacle 8 of 32

Appendix D Reqiiirri QprntntActions Form ES-D-2 Op Test No.:

NRC Scenario #

1 Event #

1 Page 9

of 32 Event

Description:

Start 1 C Hotwell pump and shutdown 1 B HotweN pump.

Time Position Applicants Actions or Behavior 2.8 Record the Hotwell pumps now in service:

D HTWL PUMP 1A BOP

° HTWL PUMP 1 B HTWL PUMP 1C NOTE TO EVALUATOR: Step 2.9should be NIAd.

BOP 2.10 File this enclosure in the Control Copy folder of this procedure.

END OF EVENTI

=

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Pacie 9of32

Appendix D Required Operator Actions Form ES-D-2 Op Test NoL NRG Scenaria 1-Event #..

a Page 10

-of 32 Event

Description:

1 SB-9 fails to intermediate position.

Time Position Applicants Actions or Behavior

Booth Operator can insert Event 2át the disretion of leadexaminer.

Indications: cOAC alarm for 1SB-9 in intermediate position.

Tavg decreasing.

ciReactor power increasing.

Attempts to manually close the condenser dump valve by going to

J OFF/RESET position on STEAM DUMP INTLK BYP TRN NB.

RD Manually decreases turbine load to maintain reactor power less than 100%.

SRO Enters AP/1IA55001028 (Secondary Steam Leak).

NOTE TO EVALUATOR: The following actions are taken from AP111A155001028 (Secondary Steam Leak).

1. Monitor Enclosure I (Foldout Page).

RD

2. Verify turbine - ONLINE.

3. Verify the following:

RD LI Reactor power - LESS THAN OR EQUAL TO 100% POWER LI T-Avg

- WITHIN 1.5°F OF T-Ref.

4. Verify proper reactor response as follows:

RD L Control rods - IN AUTO AND STPPING IN LI P/R neutron flux

- DECREASING.

CREW

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

BDP

6. Verify Pzr level - STABLE OR INCREASING.

CREW

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

CREW

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

9. Attempt to identify and isolate leak as follows:

a. Verify the following conditions - NORMAL:

LI Containment temperature BDP LI Containment pressure LI Containment humidity LI Containment floor & equipment sump level.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 10 of 32

Appendix D Required Operator Actions Form ES-D-2 Op TesU1o NRC Scenario #

i Event#

2.

Page.

ii f

32 Event

Description:

1SB-9 fails to intermediate position.

Time Position Applicants Actions or Behavior I

BOP 9b. Dispatch operators to locate and identify source of steam leak.

RD 9c. Verify SIC PORVs

- CLOSED.

RD 9d. Verify condenser dump valves -CLOSED.

9d. RNO Perform the following:

1)

Select OFF RESET on the following switches:

RO L STEAM DUMP INTLK BYP TRN A D STEAM DUMP INTLK BYP TRN B.

2) IF valve will not close, THEN dispatch operator to close affected condenser dump valve isolation valve.

RO 9e. Verify atmospheric dump valves

- CLOSED.

BOP 9f. Verify CA PMP #1

- OFF.

BOP 9g. IF leak is suspected to be in a doghouse, THEN close the following valves:

10. Determine required notifications:

SRO L REFER TO RP/0/N5000/001 Classification Of Emergercy)

REFER TO RPIO/B/50001013 (NRC Notification Requirements).

11. Notify RP of leak.

RD

12. Verify - LEAK ISOLATED.

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

ENDOFEVENT2 Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 11 of 32

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

NR Seena4& #

I-Event#

3 Pag 12

-of Event

Description:

1 RN-2B fails closed causing A RN pit low/low level.

Time L Position Applicants Actions or Behavior Booth Operator can insert Event 3 at the discretion of the lead examiner.

Indications: 1AD-12 B/i RN PUMP INTAKE PIT A LEVEL-tO.

IAD-12 E/2 RN PIT-A SWAP TO SNSWP.

BOP Recognizes RN pit A level is low and decreasing to low/low.

SRO Recognizes entry conditions for AP/OIA5500/020 (Loss of Nuclear Service Water) Case II (Loss of RN Pit Level).

BOP Verifies RN system swapped properly to SNSWP.

BOP Stops excess RN pump running on A train.

NOTE TO EVALUATOR: The following actions are taken from AP101A155001020 (Loss ofNuclear Service Water) Case II.

i.

Verify the following alarms - DARK:

BOP LI iAD-i2, B12 RN PIT A SCREEN HI DIP LI 1AD-12, B/5 RN PIT B SCREEN HI DIP.

2. Start idle RN pump(s) on the unaffected train.

3.

Verify affected pit level adequate as follows:

Li IAD-12, BI1 RN PUMP INTAKE PIT A LEVEL-LO - DARK LI IAD-12, B14 RN PUMP INTAKE PIT B LEVEL-LO DARK BOP LI 2AD-12, BI1 RN PUMP INTAKE PIT A LEVEL-LO DARK LI 2AD-12, B14 RN PUMP INTAKE PIT B LEVEL-LO DARK LI Affected pit level indication - STABLE OR INCREASING.

BOP 3.

RNO Align RN to the SNSWP. REFER TO Enclosure 2 (RN Valve Alignment for RN Swap to SNSWP).

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

NOTE: After automatic swapover to the SNSWP on emergency-low RN pit level, the RN swap to the SNSWP annunciators will only be lit for 2 minutes following swapover Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 12 of 32

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

NRC Scenario #-

1-Event #-

3 Page of 32E Event

Description:

1 RN-2B fails closed causing A RN pit low/low level.

Time Position Applicants Actions or Behavior

5. IF any of the following alarms are lit OR were previously lit:

LI 1AD-12, E/2 RN PIT A SWAP TO SNSWP THEN perform the following:

a.

Ensure all RN pumps - ON.

b.

Ensure correct RN valve alignment. REFER TO Enclosure 2 (RN BOP Valve Alignment for RN Swap to SNSWP).

c.

IF AT ANY TIME RN pump(s) running on RN pit with O-LO level, THEN secure affected pump(s).

d.

IF WL discharge in progress, THEN coordinate with Radwaste Chemistry to secure all controlled WL discharges.

e.

IF any RN chemical addition is in progress, THEN have Chemistry secure it.

6. Verify SNSWP level adequate and stable as follows:

BOP LI 1AD-12, N3 SNSWP LEVEL LO DARK LI SNSWP level indication

- STABLE.

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

a. Verify RN - ALFGNED TO KC HX(S) IN SERVICE.

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

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

8. RNO NOTE: IF RN supply headers are in normal two header operation, and the RN supply crossover isolations are -closed, THEN one RN pump on each train must be in service if desired to supply both trains of RN.

8. RNO Stop any RN pump(s) not required to support system operation.

NOTE TO EVALUATOR: tthis time, flow on both A train RN pumps is less than8,600 GPM. One of the A train RN 7

pumps should be securedo alléviátethis low flow condition.

9. Determine and correct cause of loss of RN pit level.

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

LI SLC 16.7-6 (RN Discharge Instrumentation)

SRO LI 3.3.2 (Engineered Safety Features Actuation System ESFAS)

Instrumentation).

LI 3.6.5 (Containment Air Temperature)

LI 3.7.8 (Nuclear Service Water System (NSWS))

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 13 of 32

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

-NRC-Seenai4o #- Event #

-3 Page 14 of 32 Event

Description:

I RN-2B fails closed causing A RN pit low/low level.

Time Position 1

Applicants Actions or Behavior E 3.7.9 (Standby Nuclear Service Water Pond (SNSWP)).

NOTE TO EVALUATOR: No Tech Specs or Sélectéd Licensee Commitments apply at this time.

11. Determine required notifications:

SRO L REFER TO RPIOIA50001001 Classification Of Emergency)

L REFER TO RP/O/B/5000101 3 (NRC Notification Requirements).

12. WHEN corrective action for loss of pit level taken, THEN restore RN to normal alignment.

13. Ensure RN pumps - IN OPERATION AS NEEDED.

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

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

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

NDOFEVENT Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 14 of 32

Appendix D Required Operator Actions Form ES-D-2 Op TestNo.:

NRC Scenario #

t Event#

P.ag 15 of 32 Event

Description:

Blackout of 1 ETB switchgear Time Position Applicants Actions or Behavior Booth Operator can insert Event 4 at the discretion of the lead examiner.

INDICATIONS: lAD-il DI1 4KVESS PWR TRAIN B TROUBLE.

lAD-Il E/7 DIG B PANEL TROUBLE.

SWGR ETB UV status lights on ISI-14.

BOP Verify I B D/G starts and loads 1ETB.

SRO Recognizes entry conditions for AP/1/N5500/007 (Loss of Normal Power) Case I (Loss of Normal Power to and Essential Train).

RO Decreases turbine load as required to maintain reactor power < 100%

due to CA system autostart.

BOP Secure excess NV and CA pumps.

NPTE TO EVALUATOR: The following actions are taken from AP/IIA/5500!007, Case I (Loss of Normal Power).

CREW I. Monitor Enclosure I (Foldout Page).

2. Verify affected bus - ENERGIZED.

3. Verify proper diesel generator operation as follows:

a. Dispatch operator to affected D/G roon(s) to monitor DIG operation.

REFER TO OP/i /N6350/002 (Diesel Generator Operation).

b. Verify RN cooling flow to the affected D/G.

4. Stop any dilutions in progress.

5. Verify CA Pump #1

- ON.

6. Maintain reactor power less than or equal to 100%.

7. Verify S!I status as follows:

a. S/I

- HAS ACTUATED.

SRO 7a. Observe Caution prior to Step 8 and GO TO Step 8.

CAUTION Resetting sequencer will prevent further automatic loading of B/O loads.

8. Verify ND System status as follows:

a. Verify ND on affected train(s) - PREVIOUSLY OPERATING IN RESIDUAL HEAT REMOVAL MODE.

SRO 8a. RNO GO TO Step 9.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 15 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test Nn NRC Scenario I

Event#

4 Page 1&

of 32 Event

Description:

Blackout of I ETB switchgear Time Position Applicants Actions or Behavior

9. Verify BlO busses are energized as follows:

a. lAD-Il, K/3 4KV BlO BUS FTA VOLTAGE LO

- DARK.

b. lAD-li, K/4 4KV BID BUS FTB VOLTAGE LO

- DARK.

10. Verify BIO loads in service as follows:

a. Maintain DIG load less than 5750 KW.

b. Ensure proper BIO sequencer(s) loading as follows:

BOP El REFER TO Enclosure 2 (Blackout Loads)

El Dispatch operator to ensure all required in plant loads are energized or on. REFER TO Enclosure 3 (Local Blackout Loads).

c. Restore spent fuel pool cooling. REFER TO OP/1/A/6200I005 {Spent Fuel Cooling System).

11. Verify VI pressure - GREATER THAN 85 PSIG AND STABLE.

12. Verify 6.9KV busses

- ENERGIZED.

NOTE: There is a five minute time delay for the automatic swapover from YVtoRN.

13. Verify W OPERABLE light - LIT.

RD

14. Verify C-9 COND AVAILABLE FOR STM DUMP status light (151-18)-LIT.

NOTE: Maintaining DIG load greater than 500 KW will facilitate paralleling with offsite power.

15. Stop unnecessary loads placed on affected bus by the sequencer as follows:

a. Reset affected DIG load sequencer(s).

b. Establish normal control room ventilation. REFER TO 0PI01N6450101 I (Control Room Area Ventilation/Chilled Water System).

c. Stop unnecessary loads.

NOTE TO EVALUATOR: Operators should recognize the need to shutdown lB GA pump, CAPT #

1, and possibly lB NV pump. This should still-keep DIG load greater than 5OOKW.

-S SRO

16. Determine and correct cause of blackout.

17. IF spent fuel pool instrumentation is failed low... NIA Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 16 of 32

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

NRC Scenario#

I Event 4

Page i7 of 32 Event

Description:

Blackout of 1 ETB switchgear Time Position Applicants Actions or Behavior

18. Ensure compliance with appropriate Tech Specs:

Li 3.8.1 (A.C. Sources - Operating)

Li 3.8.2 {A.C. Sources - Shutdown)

SRO Li 3.8.7 (Inverters - Operating)

Li 3.8.8 (Inverters

- Shutdown)

Li 3.8.9 (Distribution Systems

- Operating)

Li 3.8.10 (Distribution Systems

- Shutdown).

NOTE TO EVALUATOR:, Tech Spec 3.8.1 ConditionA (Perform an available power source PT within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and RestoreOffsite Circuit to OPERABLE status in 7,2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) for Unit I and Tech Spec 3,7.8 ConditiGn A (Restore NSWS train to OPERABLE status in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) for both Units apply at this time. Also SRO should mention performing an RN system enclosure 4.11 to verify operability of the B train DIGs.

19. Determine required notifications:

SRO Li REFER TO RP/01A15000/001 (Classification Of Emergency)

Li REFER TO RPIOIBI5000/013 (NRC Notification Requirements).

ENDOFEVENT4 Appendix D Catawba NRC Exam Dec 2010 Page 17 of 32 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 QpiesiNo.:

NC Soario#

1 E3LenL#

5-P-age 18 ot 32 Event

Description:

Control rod K6 drops partially into the core.

Time Position Applicants Actions or Behavior Booth Operator can insert Event 5 at the discretion of the lead examiner:

Indications: 1AD-2 B12 P/R UPPER DET HI FLUX DEV OR AUTO DEFEAT.

IAD-2 B13 COMPARATOR P/R CHANNEL DEVIATION.

DRPI display shows rod K6 inserted partially into the core with an orange background showing it is deviated from its bank by> 12 steps.

RO Verifies only I rod misaligned.

Recognizes entry conditions for API1/A155001014 {Control Rod

Misalignment) Case I.

NOTE TO EVALUATOR: The following actions are taken from AP!11A15500!014 (Control Rod Misalignment).

1. Verify only one rod

- MISALIGNED. (Immediate action step)

2. Ensure CRD BANK SELECT switch IN MANUAL.

3. Verify affected rod bottom light(s) - DARK.

4. Stop any turbine load changes in progress.

5. Adjust turbine load to maintain T-Avg within 1°F of T-Ref.

6. Verify any of the following DRPI indications

- IN ALARM:

LI Data A Failure RO OR LI Data B Failure.

6. RNO GO TO Step 11.

11. Ensure compliance with appropriate Tech Specs:

LI 3.1.1 (Shutdown Margin (SDM))

LI 3.1.4 (Rod Group Alignment Limits)

LI 3.1.5 (Shutdown Bank Insertion Limit)

SRO LI 3.1.6 (Control Bank Insertion Limits)

LI 3.1.7 (Rod Position Indication)

LI 3.2.3 (Axial Flux Difference (AFD))

LI 3.2.4 (Quadrant Power Tilt Ratio <QPTR))

LI SLC 16.7-11 (Position Indication System

- Shutdown).

NOTE TO EVALUATO: TechSpec 3.1.4 Condition B applies athis time.

End Event 5 after Tech Spec call has been made.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 18 of 32

Appendix D Required Operator Actions Form ES-D-2 OpJestN NRC Scenario #

1

£vent#

6, 7,and Paga i

of 32.-

Event

Description:

Control rod K6 ejects from the core, causing an intermediate sized LOCA. Failure of A train of SI (auto and manual) requiring manual alignment of A train equipment. Failure of automatic feedwater isolation requiring manual initiation.

Time Position Applicants Actions or Behavior Booth operator can insert-Event 6at the iead examiners discretion.

Indications: Pressurizer pressure decreasing, containment pressure and humidity increasing.

SRO Recognize that a reactor trip and safety injection are needed.

RO Trip the reactor.

BOP Manually Safety Inject.

RO Manually initiate feedwater isolation after Tavg decreases to 564°F.

BOP Manually align A train SI equipment NOTE TO EVALUATOR: The following step is from AP!11N550010lO (Reactor Coolant Leak) End 2.

CRITICAL

a. IF Pzr level cannot be maintained greater than 4% ORPzr/NC STEP pressure is decreasing in an uncontrolled manner, THEN:

1) IF in Mode 1, 2 or 3 with CLAs in service, THEN:

SRO a) Manually trip reactor.

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

c) GO TO EPIIIAJ5000IE-0 (Reactor Trip Or Safety Injection).

NOTE TO EVALUATOR: The following actions are from EP!1!AJ5000JE-O (Reactor Trip or Safety Injection).:

CREW

1. Monitor Enclosure I (Foldout Page).

2. Verify Reactor Trip: (Immediate action step)

L All rod bottom lights LIT RO u All reactor trip and bypass breakers OPEN hR amps - DECREASING.

3. Verify Turbine Trip: (Immediate action step)

E All turbine stop valves - CLOSED SOP

4. Verify IETA and IETB - ENERGIZED. (Immediate action step)

Appendix D Catawba NRC Exam Dec 2010 Page 19 of 32 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 OpTestNo J1R Scenario#

£vent#

,7-,and8-.

Page 20

- -of 32 Event

Description:

Control rod K6 ejects from the core, causing an intermediate sized LOCA. Failure of A train of SI (auto and manual) requiring manual alignment of A train equipment. Failure of automatic feedwater isolation requiring manual initiation.

Time I

Position Applicants Actions or Behavior

5. Verify SIl is actuated: (Immediate action step)

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

BOP LIT.

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

LIT.

6. Announce Unit I Safety Injection.

7. Determine required notifications:

El REFER TO RPIOIN5000IOOI (Classification Of SRO Emergency)

L REFER TO RP/0/B/5000/01 3 (NRC Notification Requirements).

8. Verify all Feedwater Isolation status lights (ISI-5) - LIT.

8 RNO a. Manually initiate Feedwater Isolation.

b. IF proper status light indication is not obtained, THEN manually close valves.

9. Verify Phase A Containment Isolation status as follows:

a. Phase A RESET lights

- DARK.

b. Monitor Light Panel Group 55t lights - LIT.

10. Verify proper Phase B actuation as follows:

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

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

11. Verify proper CA pump status as follows:

a. Motor driven CA pumps

- ON.

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

12. Verify all of the following SIl pumps - ON:

El NV pumps BOP El ND pumps El NI pumps.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 20 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test Ni NR Scenario I

- Event #

6,7, and8 Page 21 of 32 Event

Description:

Control rod K6 ejects from the core, causing an intermediate sized LOCA. Failure of A train of SI (auto and manual) requiring manual alignment of A train equipment. Failure of automatic feedwater isolation requiring manual initiation.

Time j

Position Applicants Actions or Behavior CRITICAL 12 RNO Perform the following for affected train(s):

STEP

a. Reset EOCS.

b. Reset DIG load sequencer.

c. Manually start affected pump.

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

13. Verify all KC pumps - ON.

14. Verify all Unit I and Unit 2 RN pumps - ON.

15. Verify proper ventilation systems operation as follows:

L REFER TO Enclosure 2 <Ventilation System BOP Verification).

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

16. Verify all SIG pressures GREATER THAN 775 PSIG.

17. Verify proper Sf1 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.

I 7d RNO 1) Ensure ND pump miniflow valve on operating ND pump(s) - OPEN.

2) IF the ND pump miniflow valve(s) cannot be opened, THEN perform the following for affected train(s):

3) GO TO Step 18.

18. Control SIG 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 11%

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

19. Verify all CA isolation valves - OPEN.

20. Verify S!I equipment status based on monitor light panel

- IN PROPER ALIGNMENT.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 21 of 32

Appendix D Required Operator Actions Form ES-D-2 Op TesLNo.:

NRC Scenarios 1

Event#

6,7,ani8 Rage 22-o 32 Event

Description:

Control rod K6 ejects from the core, causing an intermediate sized LOCA. Failure of A train of SI (auto and manual) requiring manual alignment of A train equipment. Failure of automatic feedwater isolation requiring manual initiation.

Time Position Applicants Actions or Behavior RD

21. Control NC temperature. REFER TO Enclosure 4 (NC Temperature Control).

22. 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.

RD

23. Verify NC subcooling based on core exit TICs -

GREATER THAN 0°F.

24. Verify main steamlines are intact as follows:

RD LI All SIG pressures -STABLE OR INCREASING LI ALL S/Gs

- PRESSURIZED.

25. Verify SIG tubes are intact as follows:

LI Verify the following EMF trip 1 lights

- DARK:

LI 1 EMF-33 Concienser Air Ejector Exhaust)

LI 1EMF-26tSteamline IA)

BOP LI 1 EMF-27 (Steamline 1 B)

LI IEMF-28 (Steamline 1C)

LI I EMF-29 (Steamline 1 D).

LI All SIG levels -STABLE OR INCREASING IN A CONTROLLED MANNER.

26. Verify NC System is intact as follows:

a. Verify the following NC pump thermal barrier alarms -

DARK:

LI 1AD-6, Eli, NCP A THERMAL BARRIER KC OUTLET HI/LO FLOW LI 1AD-6, El2, NCP B THERMAL BARRIER KC OUTLET BOP HI/LO FLOW LI 1AD-6, E13, NCPC THERMAL BARRIER FCC OUTLET HI/LO FLOW LI IAD-6, El4, NCP D THERMAL BARRIER FCC OUTLET HIILO FLOW.

b. Verify NC System is intact as follows:

LI Containment pressure - LESS THAN 1 PSIG.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 22 of 32

Appendix D Required Operator Actions Form ES-D-2 Op ThsLN:

NRC

.Scenariu #

1 Event#

,. 7ani&

Page 23-

- of 32 Event

Description:

Control rod K6 ejects from the core, causing an intermediate sized LOCA. Failure of A train of SI (auto and manual) requiring manual alignment of A train equipment. Failure of automatic feedwater isolation requiring manual initiation.

Time Position Applicants Actions or Behavior 26b RNO 1) Energize H2 igniters.

2) Dispatch operator to perform the following:

a) Secure all ice condenser air handling units.

REFER TO Enclosure 13 (Securing All Ice Condenser Air Handling Units).

b) Place containment H2 analyzers in service.

REFER TO OPI1IA/6450101 0 Hydrogen Control Systems).

3) IF both the following conditions exist, BOP LI Containment pressure - GREATER THAN 1 PSIG LI Containment pressure HAS REMAINED LESS THAN 3 PSIG THEN manually start one VX fan. REFER TO (VXFan Manual Start).

4) Concurrently:

LI Implement EP/1/N5000IF-0.(Critical Safety Function Status Trees).

LI GO TO EPI1 IN5000IE-1 (toss Of Reactor Or Secondary Coolant).

NOTE TO EVALUATOR: The following actions are from EPII!AI5000IE-1 (Loss of Reactor or Secondary Coolant).

CREW

1. Monitor Enclosure I (Foldout Page).

2. Verify main steamlines are intact as follows:

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

3. Control intact SIG 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%.

4. Verify secondary radiation is normal as follows:

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 23 of 32

Appendix D Required Operator Actions Form ES-D-2 Op TestN NRf Scenario #

I Event a, 7and S.

Page 24 of 32 Event

Description:

Control rod K6 ejects from the core, causing an intermediate sized LOCA. Failure of A train of SI (auto and manual) requiring manual alignment of A train equipment. Failure of automatic feedwater isolation requiring manual initiation.

Time Position Applicants Actions or Behavior

a. Ensure the following signals

- RESET:

1) Phase A Containment Isolations

2) CA System valve control

3) KC NC NI NM St signals.

b. Align all SIGs for Chemistry sampling.

c. Perform at least one of the following:

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

OR LI Notify RP to frisk all cation columns for activity.

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

LI 1EMF-33 (Condenser Air Ejector Exhaust)

Li 1EMF-26SteamIine IA)

LI 1 EMF-27 (Steamline 1 B)

LI 1EMF-28 (Steamline 1C)

LI 1EMF-29 (Steamline 1D).

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

5. 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, THEN, after Pzr pressure decreases to less than 2315 PSIG, ensure the valve closes or is isolated.

6. Verify SIl termination criteria as follows:

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

b. Verify secondary heat sink as follows:

CREW LI N/R level in at least one intact SIG - GREATER THAN 11% (29% ACC)

OR LI Total feed flow to all intact S/Gs

- GREATER THAN 450 GPM.

c. NC pressure

- STABLE OR INCREASING.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 24 of 32

Appendix D Required Operator Actions Form ES-D-2 Q TestNo NRC Scenaria#

1 Event#.

6 7,-and &

Pag.

2 f

32-Event

Description:

Control rod K6 ejects from the core, causing an intermediate sized LOCA. Failure of A train of SI (auto and manual) requiring manual alignment of A train equipment. Failure of automatic feedwater isolation requiring manual initiation.

Time Position Applicants Actions or Behavior

d. Pzr level

- GREATER THAN 11% (20% ACC).

6d RNO Perform the following:

1) IF NC pressure is increasing AND normal Pzr spray

-CREW is available, THEN attempt to stabilize NC pressure using normal Pzr spray.

2) GO TO Step 6.f.

CREW 6f. Monitor S/I termination criteria. REFER TO Enclosure 2 (S/I Termination Criteria).

CRW 6g. IF AT ANY TIME S/I termination criteria is met while in this t

procedure, THEN RETURN TO Step 6.

NOTE TO EVALUATOR: Depending on how rapid the crew gets to this point, NC system pressure may be stable or increasing at this point. If crew reads this step and initiates pressurizer spray then pressurizer level could increase to 11%

and SI termination criteria would be met. However Si termination procedure will not allow a full termination and will require an eventual transitioi to EPI1AI5OOOIES-12 (Post LOCACooldown and Depressurization). EPIIJAI5000!ES-1.1 (Safety injection Termination) steps will be at the end of this form.

7. Verify proper NS pump operation as follows:

a. At least one NS pump

- ON.

7a. RNO Perform the following:

1) IF AT ANY TIME an NS pump(s) starts while in this procedure, THEN perform Step 7.

2) GO TO Step 8.

8. Verify criteria to stop operating ND pumps as follows:

a. NC pressure - GREATER THAN 285 PSIG.

b. NC pressure

- STABLE OR INCREASING.

c. At least one ND pump - ON.

d. ND pumps suction

- ALIGNED TO FWST.

e. Verify FWST level

- GREATER THAN 45%.

f. Ensure S/I

- RESET:

1) ECCS.

2) D/G load sequencers.

3) IF AT ANY TIME a BIO occurs, THEN restart S/I equipment previously on.

Appendix D Catawba NRC Exam Dec 2010 NURG 1021 Revision 9 Page 25 of 32

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

NRC Sce.nath #

Eient #

.7, and &

Page 2&

of 32 Event

Description:

Control rod K6 ejects from the core, causing an intermediate sized LOCA. Failure of A train of SI (auto and manual) requiring manual alignment of A train equipment. Failure of automatic feedwater isolation requiring manual initiation.

Time Position Applicants Actions or Behavior

g. Stop ND pumps.

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

9. Verify NC and SIG pressures as follows:

a. All S/G pressures

- STABLE OR INCREASING.

b. NC pressure

- STABLE OR DECREASING.

tiOTE TO EVALUATOR: If thecrew says that NC pressure is increasing at this point then a loop back to step I of EPIIIN5000IE-1 will occur.

10. Verify conditions to stop operating DIGs as follows:

a. At leastone DIG-ON.

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

ii DIG 1ABKRTOETAOPEN 1ETA-ENERGIZED.

c. WHEN S/I is reset, THEN dispatch operator to stop 1A D/G and place in standby readiness. REFER TO OP/i /N6350/002 (DieselGenerator Operation).

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

E D/G I B BKR TO ETB OPEN

[1 IETB-ENERGIZED.

10 d. RNO 1) Attempt to restore offsite power to affected switchgear. REFER TO API1IN5500/007 (Loss of Normal Power).

2) IF I ETA is energized from offsite power, THEN GO TO Step 10.f.

3)GO TO Step 11.

. NTETO EVALUATOR: The crew will not perform step IO.e due to I ETA being energized from offsite power (step IO.d.2) RNO).

10.

f. Ensure S/I - RESET:

1) ECCS.

Appendix D Catawba NRC Exam Dec 2010 Page 26 of 32 NUREG 1021 Revision 9 BOP

Appendix D Required Operator Actions Form ES-D-2

]

Op test Nn NRC Scenaria I

Event S 7, and 2

- Page 27-E 32 Event

Description:

Control rod K6 ejects from the core, causing an intermediate sized LOCA. Failure of A train of SI (auto and manual) requiring manual alignment of A train equipment. Failure of automatic feedwater isolation requiring manual initiation.

Time Position Applicants Actions or Behavior

2) DIG load sequencers.

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

11. Obtain containment H2 concentration as follows:

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

b. Verify containment H2 analyzers IN SERVICE.

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

d. Verify containment H2 concentration

- d. Dispatch operator to place H2 LESS THAN 0.5%.

e. WHEN the ice condenser air handling units are off AND H2 concentration is less than 6%, THEN energize the H2 igniters_(IMC-7).

12. Initiate evaluation of plant status as follows:

a. Verify S/I systems - ALIGNED FOR INJECTION MODE.

b. Verify Cold Leg Recirc capability as follows:

1) At least one ND pump - AVAILABLE.

2) Verify power to all of the following valves AVAI LABLE:

E IFW-27A (ND Pump IA Suct From FWST)

Li lNl-185A (ND Pump lACont Sump Suct)

El 1ND-28AND Supply To NV & IA NI Pmps) n I FW-55B (ND Pump 1 B Suct From FWST)

GOP El INI-184B (ND Pump lB Cont Sump Suct)

El 1 Nl-332A (NI Pump Suct X-Over From ND)

El 1 Nl-333B (NI Pump Suct From ND)

Li INI-334B (NI Pump Suct X-Over From ND)

El INI-136B (ND Supply To NI Pump 1G).

3) Verify power to all of the following valves AVAILABLE:

El I NI-i 15A (NI Pump IA Miniflow Isol)

El INI-144A (NI Pump lB Miniflow lsol)

El INI-147B (NI Pump Miniflow HdrTo FWST Isol).

4) Verity_the_ENABLE_lights_for the_following_switches_-

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 27 of 32

Appendix D Required Operator Actions Form ES-D-2 OpTestNri 11RC Scenath#

£vent#

- 6,7, anii8 Page 2g f

32 Event

Description:

Control rod K6 ejects from the core, causing an intermediate sized LOCA. Failure of A train of SI (auto and manual) requiring manual alignment of A train equipment. Failure of automatic feedwater isolation requiring manual initiation.

Time 1

Position Applicants Actions or Behavior LIT:

LI C-LEG RECIR FWST TO CONT SUMP SWAP TRN A LI C-LEG RECIRFWST TO CONT SUMP SWAP TRN B.

c. Verify auxiliary building radiation is normal as follows:

LI EMF-41 (Aux Bldg Ventilation) trip ilight DARK LI All area monitor EMF trip I lights

- DARK.

d. WHEN the TSC is activated AND staffed, THEN:

1) Notify the Reactor Engineer to assess-core damage.

REFER TO RPIOIAI5000/015 (Core Damage Assessment).

2) Notify Chemistry to obtain current NC boron concentration.

3) WHEN ND is aligned for Cold Leg Recirc, THEN notify BOP/SRO Chemistry to obtain currentcontainment sump boron concentration.

4) Notify Operating Engineer of the following:

a) VA is required to be aligned to normal AND filter mode within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the event.

b) Evaluate aligning VA to normal AND filter mode.

REFER TO OPIO/N64501003 (Auxiliary Building Ventilation System).

e. Notify station management to evaluate starting additional plant equipment to assist in recovery.

BOPISRO

13. Verify NC System cooldown and depressurization is required as follows:

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 28 of 32

Appendix D Required Operator Actions Form ES-D-2 Op Test No NRC Scenadci#

1 E.vent 6,7, and 8 Page 29 f

32 Event

Description:

Control rod K6 ejects from the core, causing an intermediate sized LOCA. Failure of A train of SI (auto and manual) requiring manual alignment of A train equipment. Failure of automatic feedwater isolation requiring manual initiation.

Time Position Applicants Actions or Behavior

a. NC pressure

- GREATER THAN 285 PSIG.

b. GO TO EPI1IN5000!ES-1.2 (Post LOCACooldown And Depressurization).

END OF SCENARIO NOTE TO EVALUATOR: If the crew enters ES-I.1 to terminate SI, begin here.

CREW

1. Monitor Enclosure I (Foldout Page).

2. Ensure SIl

- RESET:

a. EOCS.

b. D/G load sequencers.

c. IF AT ANY TIME a BID occurs, THEN restart S/I equipment_previously on.

3. Ensure the following containment isolation signals -

RESET:

BOP LI Phase A LI Phase B.

4. Establish VI to containment as follows:

BOP LI Ensure lVl-77B {Vl Cont Isol)

- OPEN.

LI Verify VI pressure

- GREATER THAN 85 P51G.

5. Verify proper NS pump operation as follows:

a. Containment pressure HAS EXCEEDED 3 P51G.

b. Verify the following valves - OPEN:

LI 1 FW-27A (ND Pump 1A Suct From FWST)

BOP LI 1FW-55B (ND Pump lB Suct From FWST).

c. Containment pressure

- LESS THAN 2.4 PSIG.

d. Reset NS.

e. Stop NS pumps.

Appendix D Catawba NRC Exam Dec 2010 Page 29 Of 32 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Time Position Applicants Actions or Behavior

f. Close the following valves:

D 1NS-29A (NS Spray Hdr lACont Isol)

El I NS-32A (NS Spray Hdr 1A Cont Isol)

El 1NS-15B (NSSpray Hdr 1B-Cont Isol)

El 1NS-12B (NS Spray Hdr lB Cont Isol).

BOP/RO

6. Ensure only one NV pump - ON.

BOPIRO

7. Verify NC pressure - STABLE OR INCREASING.

7. RNO Perform the following:

BOP/RO

a. Ensure Pzr spray valves -CLOSED.

b. IF NC pressure continues to decrease, THEN GO TO EPIIIN5000IES-1.2 -(Post LOCA Cooldown And Depressurization).

END OF SCENARIO Appendix D Catawba NRC Exam Dec 2010 Page 30 of 32 NUREG 1021 Revision 9 Op Test No NRC Scenario#

t Event #

6-, 7, and &

P-age 30-o 32

Event

Description:

Control rod K6 ejects from the core, causing an intermediate sized LOCA. Failure of A train of SI (auto and manual) requiring manual alignment of A train equipment. Failure of automatic feedwater isolation requiring manual initiation.

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

SUMMARY

SAT UNSAT CT#

CRITICAL TASK C-I Manually trip the reactor from the control room before an automatic reactor trip occurs on CT delta T.

C-2 Establish flow from at least one intermediate-head ECCS pump before transition out of E-O.

Comments:

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 31 of32

ATTACHMENT 2 SHIFT TURNOVER iNFGRMATION Unit I Status Power Level Power History NCS 8oron Xenon 100%

Per IC 1224 PPM perOAC Controlling Procedure OP/11N6100/003 (Controlling Procedure for Unit Operation), Enclosure 4.3 (Unit Operation Between 85% and 100% Power). The steps required for 100% power operation are complete.

Other Information Needed to Assume the Shaft I B NI pump is tagged out due to its breaker failing to close during an IWP on the previous shift.

TS 3.5.2 (ECCS-Operating) was entered 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ago and I B NI pump is expected to be returned to service in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Crew direction is to swap hotwell pumps, placing 1 C in service and shutting down 1 B.

NLOs Available Six NLOs are available as listed on the status board METEOROLOGICAL CONDITIONS Upper wind direction 315 degrees, speed = 10mph 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 December 2010 HLP NRC EXAM SCENARIO #2 Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 1 of 35

Catawba Nuclear Station NRC Exam December 2010 FacThty Catawba NRC Exam 2U1 Scenaric No.:2 0pTefNOJ Examiners:

Operators:

SRO RO BOP Initial Conditions:

IC#142; Unit 1 is at 100% power EOL. 1A LH pump is tagged out.

Turnover:

IA LH pump is tagged out to repair a leak on the motor-cooler. Maintenance estimates that repairs will take 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to complete. Direction for the crew is to swap NV pumps, placing 1 B in service and shutting down 1A.

Event Maif. No.

Event Event No.

Type*

Description 1

N-BOP Swap NV pumps placing 1 B in service and securing 1A.

N-SRO 2

C-BOP NVO56D NV pump I B trip.

TS-SRO 3

C-SRO FWPO12C 1A CFPT trip with failure of automatic turbine runback.

R-RO 4

l-BOP ENBO1 3B PR N-42 blown control power fuse.

TS-SRO 5

FWPO1 5C C-RO 18 CFPT trip <Loss of all CF flow to S!Gs) requiring reactor trip.

6 EHCOO2 C-RO Automatic and manual failure of turbine trip on reactor trip.

7 CAOO5

-C-R0 CAPT # 1 overspeed trip, motor driven CA pumps fail to start.

CAOO4NB

-C-SRO 8

M-ALL Loss of secondary heat sink.

[9 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 2 of 35

Catawba Nuclear Station NRC Exam December 2010 Scenario 2

- Summary Initial Condition Unit I is at 100% powerEOL. 1A LH pump is tagged out.

Turnover:

1A LH pump is tagged out to repair a leak on the motor cooler. Maintenance estimates that repairs will take 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . Direction for the crew is to swap NV pumps, placing 1 B in service and shuffing down 1A.

Event 1 Crew swaps NV pumps, placing 1 B in service and securing IA.

Event 2 lB NV pump trips, causing a loss of charging and letdown. AP/1/A/5500/012 (Loss of Charging or Letdown) Cases I & 2 will be entered to restore charging and letdown. TS evaluation by SRO is required.

Event 3 IA CFPT trips. An automatic turbine runback to 65% does not occur and requires-RO to manually decrease turbine load. AP111N55001003 (Load Rejection) will beentered.

Event 4 Power range N-42 control power fuse blows. Crew will enter AP/1/A/5500/016 (Malfunction of Nuclear Instrumentation) Case 4 will be entered to remove this channel from service. TS evaluation by SRO is required.

Event 5 lB CFPTtrips, causing a loss of all feed flowto the SIGs. Immediate actionsofAP/l/N5500/006 (Loss of SIG Feedwater) will have the RO trip the reactor with reactor power greater than 5%.

Event 6 Upon reactor trip, the turbine will fail to trip automatically and manually, requiring the RO to manually close the turbine control valves. Crew enters E-0 (Reactor Trip or Safety Injection).

Event 7 IA and lB motor driven CA pumps fail to start automatically and cannot be started manually. CAPT

1 will trip on a mechanical overspeed.

Event 8 Once all S/G levels decrease to less than 11% NR level, a transition will be made to FR-H.1 (Response to Loss of Secondary Heat Sink). Crew will establish feed flow to at least one SIG from the main condensate system by depressurizing a SIG to less than 505 psig and aligning CF flow to the CA nozzles on the SIG to be fed.

Critical task 1 Manually trip the main turbine before a severe (orange-path) challenge develops to either the subcritIcallty or the integrity CSF or before transition to ECA-2. I (Uncontrolled Depressurization ofAll SIGs), whichever happens first Critical task 2 Establish feedwater flow To at least one SIG before reactor coolant system feed and bleed is required.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 3 of 35

Catawba Nuclear Station NRC Exam December 2010 EXERCISE GUIDE WORKSHEET 1.

INITIAL CONDITIONS:

1.1 Resetto IC 142 START TIME:

Instructor Action Delay Ramp Delete Eve Final In nt MAL-EHCOO3F (ALL TURBINE AUTO BLOCK RUNBACK FAILURE)

MAL-EHCOO2 (TURBINE TRIP BOTH FAILURE)

MAL-CAOO4A (FAILURE OF CA PUMP BOTH A TO START)

MAL-CAOO4B (FAILURE OF CA PUMP BOTH B TO START)

OVR-NVO56D (NV PMP lB OFF PB)

ON I

OVR-FWPOI2C (CFPT IA TRIP_

ON RESETTRIPPB)

MAL-ENBOI3B (PIR 42 BLOWN FUSE CONTROL 5

OVR-FWPOI5C (CFPT lB TRIP_RESET ON 7

TRIP PB)

MAL-CAOO5 (CA PUMP OVERSPEED MECHANIC TRIP)

AL

LOA-EHCOI4 (RACKOUT EHC PMP IA)

RACKOUT j Place a red tag collar on IA LH pump.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 4 of 35

Catawba Nuclear Station NRC Exam December 2010 2.

SIMULATOR BRIEFING 2.1 Control Room Assignments:

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

3.

EXERCISE PRESENTATION 3.1 Familiarization Period A.

Allow examinees time to familiarize themselves with Control Board alignments.

3.2 Scenario EVENT 1, Swap of NV pumps.

I v

j BOOTH INSTRUCTOR ACTION IF called to check out the 1 B NV pump, THEN wait 3 minutes report that the pump is running normally.

3.3 Scenario EVENT 2, 1 B NV pump trips.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR EVENT I to trip the lB NV pump.

BOOTH INSTRUCTOR ACTION IF an NLO is dispatched to investigate the 1 B NV pump and/or 1 ETB breaker, repeat back the order. No reason will be given.

Appendix D Catawba NRC Exam Dec 2010 Page 5 of 35 NUREG 1021 Revision 9

Catawba Nuclear Station NRC Exam December 2010 BOOTH INSTRUCTOR ACTION IF an NEC is dispatched to check out the IA NV pump, repeat back the order. After 3 minutes report that the 1A NV pump is running normally.

3.4 Scenario EVENT 3, 1ACFPT trips.

v_j BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR EVENT 3 to trip 1A CFPT.

VI BOOTH INSTRUCTOR ACTION WHEN the SOC is contacted repeat back the information.

IF and NEC is dispatched to investigate the cause of the 1A CFPT tripping, repeat back the order. No reason will be given for the trip.

ff BOOTH INSTRUCTOR ACTION BOOTH INSTRUCTOR ACTION WHEN RP is notified to sample and analyze gaseous effluents repeat back the information.

WHEN PC is notified to sample for isotopic analysis of iodine repeat back the information.

BOOTH INSTRUCTOR ACTION WHEN the Reactor Group Engineer is notified of the occurrence repeat back the information.

3.5 Scenario EVENT 4, Power Range N42 blown control power fuse.

VI BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR EVENT 5 to give a loss of N-42.

Appendix D Catawba NRC Exam Dec 2010 Page 6 of 35 NUREG 1021 Revision 9 V

Catawba Nuclear Station NRC Exam December 2010 if BOOTH INSTRUCTOR ACTION WHEN IAE is directed to place bistables in the tripped condition repeat back the order.

BOOTH INSTRUCTOR ACTION WHEN the Reactor Group Engineer is notified of the occurrence repeat back the information.

3.6 Scenario EVENT 5, 1 B CFPT trips.

if BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR EVENT 7 tocause the lB CFPT to trip.

if BOOTH INSTRUCTOR ACTION IF an NEC is dispatched to investigate why the 1 B CFPT tripped repeat back the order. No reason will be given.

BOOTH INSTRUCTOR ACTION IF and NEC is dispatched to investigate why the MD CA pumps did not start repeat back the order. No reason will be given.

v, BOOTH INSTRUCTOR ACTION IF an NEC is dispatched to investigate why the CAPT #1 tripped repeat back the order. No reason will be given.

if BOOTH INSTRUCTOR ACTION IF the NEC is ordered to reset the mechanical overspeed trip wait 3 minutes THEN report that the trip lever is mechanically bound and cannot be reset.

Appendix D Catawba NRC Exam Dec 2010 Page 7 of 35 NUREG 1021 Revision 9

Appendix D RequWed Operator Aotkns Form ES-D-2 Op Test No.:

NRC Scenario #

2 Event #

I Page 8

of 35 Event

Description:

Crew will swap to the 1 B NV pump and secure 1A NV pump.

Time 1

Position Applicants Actions or Behavior CREW ASSUMES THE WATCH:

NOTE TO EVALUATOR: The following actions are taken from OPII!A162001001, Chemicél and VolUme Control System, Enclosure 4.13. All initial conditions are complete and a pre-job brief has been completed. A NEO is in the field standing by for the start of I B NV pump.

2.1 Shift the operating centrifugal charging pump by completing the following steps:

2.1.1 Ensure VCT pressure is between 18-40 psig as read on 1NVP5500 (VOT Vent Press) (1 MC5).

2.1.2 30 seconds prior to starting the idle NV pump, place its associated aux oil pump in the ON position:

NV PUMP 1AAUXOILPUMP

NV PUMP lB AUX OIL PUMP BOP 2.1.3 Start the idle NV pump. (R.M.)

NV PUMP lA

NV PUMP 18 2.1.4 Place the NV pump aux oil pump started in Step 2.1.2 in AUTO.

2.1.5 Stop the previously running NV pump:

NV PUMP 1A

NV PUMP 18 2.1.6 Verify propercharging flow rate.

END OF EVENTI Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 8 of 35

Aendix D Reauired Ooerator Actions Form ES-D-2 2

Pags 9

of35 Event

Description:

NV pump trip.

Applicants Actions or Behavior Op Test-No.

NRC* Scertaricr#

2 Event Time Position Booth Operator can inseit Event 2 at the discretion of lead examiner.

Indications:

LI 1AD-7, C14 NCP SEAL WATER LO FLOW alarm - LIT El 1AD-7, Eli CHARGING LINE HI/LO FLOW alarm LIT LI Pzr level DECREASING ii Letdown Isolates No operator actions are required outside of the AP.

NOTE TO EVALUATOR: The following actions aretaken from 1!A15501012, Case 1, Loss of Charging.

1. Stop any power changes.

2. Ensure the following letdown isolation valves - CLOSED:

El I NV-i OA (Letdn Orif i B Otlt Cont Isol)

BOP El I NV-i IA (Letdn Orif IC Otlt Cont Isol)

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

3. Ensure any malfunctioning NV pump - SECURED.

4. Monitor conditions for continued NC pump operation as follows:

BOP El NC pump #1 seal outlet temperature - LESS THAN 235°F El NC pump lower bearing temperature

- LESS THAN 225°F.

5. IF excess letdown in service, THEN ensure manual loader for INV 124B (Excess Letdn Press CtrI)

ADJUSTED TO 0%.

NOTE Gas entrainment in the NV pump suction can produce pump failure or degradation. Gas entrainmentcan result in a complete loss of charging, or in a reduction of charging-capacity, without indication of cavitation.

6. Verify NV pump status as follows:

BOP El At least one NV pump - ON.

El Charging flow - ADEQUATE FOR PLANT CONDITIONS.

Appendix D Catawba NRC Exam Dec 2010 Page 9 of 35 NUREG 1021 Revision 9

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

NRC Scenaiio#

2 vent#

2 Page 10 of 35 Event

Description:

NV pump trip.

Time Position Applicants Actions or Behavior

6. RNO a. Ensure any malfunctioning NV pump - SECURED.

b. Ensure the following valves

- OPEN:

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

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

c. Ensure only one suction source as follows:

LIVCT LI 1 NV-I 88A (VCT OtIt isol) -OPEN LI 1 NV-i 89B (VCT OtIt Isol)

- OPEN LI VOT level -<3REATER THAN 23%

BOP LI 1NV-252A(NV PumpssuctFromfWST)--CLOSED LI 1 NV-253B (NV Pumps Suct From FWST) -CLOSED.

OR LI FWST LI Either of the following valves

- OPEN:

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

LI 1NV-253B (NV PumpsSuctfrom FWST).

LI Either of the following valves - CLOSED:

LI I NV-i 88A (VCT OtIt fsol)

LI I NV-i 89B (VCT OtIt Isol).

NOTE TO EVALUATOR: Step 6.dshould be N!Ad

6. e. Start the available NV pump as follows:

I) Open 1 NV-309 (Seal Water Injection Flow) to full open.

2) Close I NV-294 (NV Pmps A&B Disch Flow Ctrl).

3) Start NV pump aux oil pump.

4) Start available NV pump.

5) Stop NV pump aux oil pump.

6) IF suction is from the FWST, THEN adjust Control Rods and Turbine load, as required, to maintain T-Avg within 1°F of T-Ref.

REFER TO the following:

LI APIIIN5500IOO9 (Rapid Downpower)

OR LI OP/I /N61 00/003 (Controlling Procedure For Unit Operation).

NOTE TO EVALUATOR: Step 6.f should be N1Ad The SRO will continue with step 7, Appendix D Catawba NRC Exam Dec 2010 Page 10 of 35 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 I

Op Test Nü NRC

- Scenartü#

2 Event #

Page 11 of 35 Event

Description:

NV pump trip.

Time Position Applicants Actions or Behavior

7. Verify charging header is aligned to NC loop as follows:

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

- OPEN.

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

OPEN

c. Verify one of the following valves OPEN BOP i I NV-32B (NV Supply To Loop A [sol)

OR I NV-39A (NV Supply To Loop D [sol).

d. Verify 1 NV-294 (NV Pmps A&B Disch Flow Ctrl) - OPEN.

8. Verify the following:

Li TOTAL SEAL WTR FLOW

- GREATER THAN 32-GPM BOP ii I NV-309 (Seal Water Injection Flow)

IN AUTO.

8. RNO Perform the following:

a. Slowly throttle 1 NV-309 (Seal Water Injection Flow) to establish 32 GPM TOTAL SEAL WTR FLOW.

b. Place 1 NV-309 in auto.

9. Verify Pzr level - GREATER THAN 17%.

10. Control charging to stabilize Pzr level BOP greater than 17%.

11. Ensure PZR HTR GROUP I C - ON.

12. Control VCT level as follows:

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

b. Verify NC MAKEUP MODE SELECT

- IN AUTO.

13. Verify normal letdown - IN SERVICE.

13. RNO Perform the following:

a. IF excess letdown was previously in service, THEN perform the following:

1) Establish excess letdown. REFER TO OP/1/A/62001001 (Chemical and Volume Control System)

2) GO TO Step 14.

b. Restore normal letdown. REFER TO Case II (Loss of Letdown).

NOTE TO EVALUATOR: Restoration of LJDJs performed in Case 2 of APII!A15500!O12 following Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 11 of 35

Appendix D Required Operator Actions Form ES-D-2 Op Test No-NRC Scenario #

2 Event #

2 Pagu 12 of

- 5 Event

Description:

NV pump trip.

Time Position I

Applicants Actions or Behavior the end of this case.

14. Ensure compliance with appropriate Tech Specs:

E 3.4.13 (RCS Operational Leakage)

Li 3.4.14 (RCS Pressure Isolation Valve {PIV) Leakage)

Li 3.5.2 (ECCS

- Operating)

SRO Li 3.5.3 (ECCS

- Shutdown)

Li 3.5.5{Seal Injection Flow)

Li 3.6.3 (Containment Isolation Valves)

Li SLC 16.9-9 {Boration SystemsCharging Pump

- Shutdown)

Li SLC 16.9-10 (Boration Systems Charging Pump -Operating).

NOTE TOEVALUATOR: T.S. 3.5.2 and SLC 169-1O apply.

15. Determine required notifications:

SRO Li REFER TO RPIO/N50001001 (Classification Of Emergency)

Li REFER TO RPIOIBI5000IOI3 (NRC Notification Requirements).

16. Verify at least one NV pump - ON.

17. IF Standby Makeup Pump is in service and is no longer required, BOP THEN secure the pump. REFER TO OPIOIB!61001013 (Standby Shutdown Facility Operations).

CREW

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

ENDOFCASEI.

NOTE TO EVALUATGR: APII!A!5500!012, Case 2, begins here.

1. Stop any power changes.

2. Ensure the following letdown isolation valves - CLOSED:

BOP Li 1 NV-I OA (Letdn Orif I B Otit Cont Isol)

Li 1 NV-I 1A (Letdn Orif IC Otlt Cont Isol)

Li INV-13A (Letdn Crlf 1A Ctlt Cont lsol).

3. Verify Pzr level - GREATER THAN 17%.

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

5. Ensure PZR HTR GROUP IC - ON.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 12 of 35

Appendix D Required Operator Actions Form ES-D-2 OpTetNo.-

NRC Scenario #

Q Event#

2 Page-13 of 35 Event

Description:

NV pump trip.

Time Position Applicants Actions or Behavior

6. Control VCT level as follows:

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

b. Verify NC MAKEUP MODE SELECT - IN AUTO.

CREW

7. Determine and correct cause of loss of letdown.

8. IF AT ANY TIME excess letdown is required, THEN establish excess BOP letdown. REFER TO 0P111A16200!OO1 (Chemical and Volume-Control System).

9. Verify proper VCIYC system operation. REFER TO Enclosure 5 (Control Room Ventilation System Verification).

10. Ensure compliance with appropriate Tech Specs:

El 3.3.1 (Reactor Trip System (RTS) Instrumentation)

El 3.3.3 (Post Accident Monitoring (PAM) Instrumentation)

El 3.3.4 (Remote Shutdown System)

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

El 3.4.12 (Low Temperature Overpressure Protection (LTOP) System)

El 3.4.13 RCS (Operational Leakage).

El 3.6.3 (Containment Isolation Valves).

NOTE TO EVALUATOR: No T.S.ppIy for this case.

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

BOP El 1 NV-lA (NC Letdn To Regen Hx lsol)

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

SRO 11.RNO GOTOStepl6.

16. Establish letdown as follows:

a. Verify ability to establish normal letdown

- RESTORED.

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

BOP 0%.

c. Verify the following valves - OPEN:

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 13 of 35

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

NRC Scenario#

2 Event#

2 Pane 14 of 35 Event

Description:

NV pump trip.

Time Position Applicants Actions or Behavior El INV-1A (NC Letdn To Regen Hx Isol)

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

NOTE If LTOP is in service, then I NC-34A will be made inoperable when the only letdown path aligned is NV system normal letdown. I NC 34A LTOP operability is based on the letdown alignment. (PIP C-l0-1320)

d. Open the following valves:

El 1NV-15B (LetdnCont Isol)

El I NV-i OA (Letdn Orif I B OtIt Cont [sol)

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

f. Throttle 1 NV-i48 (Letdn Press Control) to 45% demand.

g. Throttle open 1NV-849 (LetdnFlowVarOrifCtrl) in 1%o 5%

increments until one of the following conditions is met:

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

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

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

j. Adjust 1 NV-148 (Letdn Press Control) to maintain letdown pressure between 150 - 200 PS[G.

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

1) IF AT ANY TIME letdown flow is increased to greater than 80 GPM, THEN perform the following:

a) Determine current NC Dose Equivalent Iodine concentration (DEl). (OAC Point Ci P0097) b) Verify DEl specific activity

- LESS THAN 0.18 pCi/GM.

c) Notify Primary Chemistry that lower DEl limits are in effect due to NV letdown flows greater than 80 GPM.

16.

2) Adjust I NV-849 (Letdn Flow Var Crlf Ctrl) in 1% increments to BOP desired letdown flow.

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

a) Adjust_1NV-I48_(Letdn_Press_Control)_to_maintain_letdown Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 14 of 35

Appendix D Required Operator Actions Form ES-D-2 Op Test Nri-RC Scenario 2

Everrt#

2 Page 15 0f 35 Event

Description:

NV pump trip.

Time Position Applicants Actions or Behavior pressure at 350 PSIG.

b) Ensure 1NV-148 (Letdn Press Control)

- IN AUTO.

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

I. WHEN Pzr level is restored to programmed level, THEN perform the following:

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

2) Ensure PZR Level Master IN AUTO.

17. Determine required notifications:

LI REFER TO RP/0/N5000/001 (Classification Of Emergency)

LI REFER TO RP/0/B/5000/01 3 (NRC Notification Requirements).

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

ENDOFEvENT2 Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 15 of 35

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

NRC SceTiarlo 2

Event #

3 Pace 6

35 Event

Description:

1 RN-2B fails closed causing A RN pit low/low level.

Time Position Applicants Actions or Behavior Booth Operator can insert Event 3 at the discretion of the lead examiher.

Indications:

AD5, Al CFPT A TRIPPED AD5, A4 CFPT A COMMON TROUBLE 1AD1, F4 TURB RUNBACK INITIATED IAD2, A4 T-REF/T-AV-G HI/LO Generator MW will NOT be decreasing Main Turbine Control Valves will NOT be closing RD Manually decreases turbine load RO Ensures control rods are operating properly SRO Enter AP/l/A155001003 (Load Rejection)

NOTE TO EVALUATOR The following actions are taken from 1!A155001003, Case 1, Load Rejection.

RD j

1. Verify turbine load - DECREASlIG IN AUTOMATIC.

1. RNO Perform the following:

RD

a. Select MANUAL on turbine-control panel.

b. Depress CONTROL VALVEStOWER pushbutton and reduce turbine load as required.

2. Verify proper reactor response:

RD LI Control rods - IN AUTO AND STEPPING IN LI 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 (ISI-1-8) - UT.

c. Verify the following:

LI C-7A LOSS OF LOAD INTLK COND DUMP status light-(ISI-18) -

LIT.

LI Steam dump valves - MODUIATING.

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

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 16 of 35

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

NR Sceriro# 2 Everit#

3 P

¶7 Of 35 Event

Description:

1 RN-2B fails closed causing A RN pit low/low level.

Time Position Applicants Actions or Behavior

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

a. All Pzr PORVs

- CLOSED.

b. Normal Pzr spray valves

- CLOSED.

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.

d. Verify standby condensate booster d. Manually start standby condensate pump(s)

- ON.

BOP 5.c. RNO Manually start standby hotwell pump(s) as necessary.

BOP 5.d. RNO Manually start standby condensate booster pump(s) as necessary.

6. Verify the following generator alarms - DARK:

BOP ii lAD-il, C/I GEN BKRAOVER CURRENT E lAD-Il, Ff1 GEN BKR B OVER CURRENT.

7. Verify SIG levels are adequate as follows:

BOP L All S/G low level alert alarms (IAD-4)

DARK E All S/G low CF flow alarms (IAD-4)

- DARK.

8. Verify reactor power - GREATER THAN 20%.

9. IF AT ANY TIME reactor power is less than or equal to 20%, THEN perform Step 8 RNO.

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

BOP II. Adjust ITL-4 (Stm Seal Reg Byp) as necessary to maintain steam seal pressure between 4 PSIG -6 PSIG.

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

13. Verify reactor power - LESS THAN 30%.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 17 of 35

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

NRC Sceriarlo#

2 Evht#

3 Page 18 of 35 Event

Description:

1 RN-2B fails closed causing A RN pit low/low level.

Time Position Applicants Actions or Behavior

13. RNO

a. IF the runback target load is less than 30%, THEN:

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

1) Stabilize unit atcurrent power level.

2) Maintain control rods above insertion limits.

RD

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

Li Turbine load Li Control rods Li Boron concentration.

c. GO TO Step 15.

15. Verify the following PCBs - CLOSED:

Li Generator breaker IA Li Generator breaker 1 B BOP EPCB14 Li PCB 15 Li PCB 17 Li PCB 18.

RD

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

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

Li Stabilize unit at appropriate power level.

Li Maintain control rods above insertion limits.

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

Li Turbine load Li Control rods Li Boron concentration.

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

CREW

19. Determine and correct cause of load rejection.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 18 of 35

Appendix D Required Operator Actions Form ES-D-2 OpTestNo.

NRC ScenarI#

2 EVerIt#

a Page 9

of 35 Event

Description:

1 RN-2B fails closed causing A RN pit low/low level.

Time Position Applicants Actions or Behavior

20. Shut down unnecessary plant equipment as follows:

a. RestoreCM and -CF as follows:

1) Verify-htr drain pumps

- ON.

2) Verify both -CF Pumps IN SERVICE.

3) Shutdown one CF pump as necessary. REFER TO OPI1/A162501001 (Condensate and Feedwater System).

4) Shutdown excess Condensate Booster Pumps. REFER TO 0P111N62501001 (Condensate and Feedwater System).

5) Shutdown excess Hotwell Pumps. REFER TO 0P111AJ62501001 (Condensate and FeedwaterSystem).

b. RC pump(s) and cooling tower fans. REFER TO OP/1/B16400/OOIA (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

- C1..OSED.

Note to. Evaluator: Depending on the speed of the crew the steamdumps may not be closed at this time. If the steam dumps are open the crew will go to the RNO, then step 22 and then back to 2td when the steam dumps are closed.

21.c. RNO Perform the following:

1) WHEN steam dump valves are closed, THEN perform Steps 21.d through 21.g.

2) GO TO Step 22.

d. Reset steam dump valves.

e. Verify the following status lights -(1SI-1 8)

- 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.

22. Verify reactor power - GREATER THAN 15%.

Appendix D Catawba NRC Exam Dec 2010 Page 19 of 35 NUREG 1021 Revision 9 RO RO RO

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

NRC Senaflo #

2-Event #

3 Page 20 Of 35 Event

Description:

I RN-2B fails closed causing A RN pit low/low level.

Time Position Applicants Actions or Behavior RO

23. Verify CA pumps - OFF.

24. Verify reactor power change GREATER THAN OREQUAL TO 15% IN A 1 HOUR PERIOD.

25. Notify the following sections to take appropriate samples:

E Radiation Protection to sample and analyze gaseous effluents. REFER TO Selected Licensee Commitments Manual, Section 16.1 1-6.

SOP i Primary Chemistry to sample for isotopic analysis of iodine. 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).

26. Ensure compliance with appropriate Tech Specs:

E 3.1.1 (Shutdown Margin (5DM))

[1 3.1.6 (Control Bank Insertion Limits) i 3.8.1 (AC Sources - Operating).

Note to Evaluator: The crewshould enter TS. 3.1.6 (control Bank Insertion Limits).

27. Notify Reactor Group Engineer of occurrence.

28. Determine long term plant status. RETURN TO 0P111A161001003 (Controlling Procedure For Unit Operation).

END OF EVENT3 Appendix D Catawba NRC Exam Dec 2010 Page 20 of 35 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Test Ne.:

RC Scenario #

-2 Event 4

Page 21 of 35 -

Event

Description:

PR N-42 blown control power fuse.

Time Position Applicants Actions or Behavior Booth Operator can insert Event 4 at the discretion f the lead examiner.

Indications:

AD2, Al P/R NEUTRON FLUX RATE ALERT AD2, A3 PIR HI NEUTRON FLUX HI SET POINT ALERT AD2, B5 P/R HI VOLTAGE FAILURE AD2, E8 OVER POWER ROD STOP AD2, FlO DCS TROUBLE INDICATING LIGHTS ON N-42 PANEL GO DARK RO Verifies all rod motion is stopped SRO Enters AP111N55001016, Malfunction of Nuclear Instrumentation System, Case IV Power Range Malfunction EVALUATOR NOTE: The following actions are fromAP!1IN550OI016, Malfunction of Nuclear Instrumentation System, Case IV Power Range Malfunction.

RO I. Verify all rod motion - STOPPED.

2. Verify IAD-2, E18 OVER POWER ROD STOP - DARK.

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

3. Identify failed PIR channel:

LI N-41 OR LI N-42 RO OR LI N-43 OR LI N-44.

4. Ensure unaffected channels - OPERABLE.

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

REFER TO Model WIO #00874531:

BOP LIOTDELTAT LI OP DELTAT.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 21 of 35

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

NRC-- Scenario1 2-Event#

4 Page 22 of 35 Event

Description:

PR N-42 blown control power fuse.

Time Position Applicants Actions or Behavior

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<tSl-19)

- LIT.

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

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

a. Place UPPER SECTION channel defeatswitch to the affected channel.

b. Verify the CHANNEL DEFEAT light for the upper section

- LIT.

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

d. Verify the CHANNEL DEFEAT light for the lower section

- LIT.

sop

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

NOTE The following annunciators will actuate in the following step:

1AD-2 A/l PIR HI NEUTRON FLUX RATE ALERT SRO 1AD-2, N3 PIR HI NEUTRON FLUX HI SET POINT ALERT IAD-2, B15 PIR HI VOLTAGE IAILURE.

9. De-energize the affected channel as follows:

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

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

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

10. Ensure affected channel bistables are in the required state. REFER TO (P1R Bistables That Must Be Tripped).

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

RD

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 desired, THEN return control rods to auto.

CREW

14. Determine and correct cause of PIR malfunction.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 22 of 35

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

NRC Scenariod

-2 Event #

4 Page 23 f

35 Event

Description:

PR N-42 blown control power fuse.

Time PositionJ Applicants Actions or Behavior

15. Ensure compliance with appropriate Tech Specs:

SRO E 3.2.4 -(Quadrant Power Tilt Ratio.(QPTR))

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

Note to Evaluator: The crew will enter tS.3.3.1

16. Determine required notifications:

SRO El REFER TO RPIOIAI5000IOOI-.(Classification Of Emergency)

Li REFER TO RPIOIBI5000/013 (NRC Notification Requirements).

17. Notify Reactor Group Engineer of occurrence.

18. WHEN the affected PIR channel is repaired, THEN ensure IAE returns the channel to service.

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

- END OFEVENT4 Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 23 of 35

Appendix D Required Operator Actions Form ES-D-2 Op Test Ne.:

NRC Scenario #

2-Event #

-- 5,6, -and 7 Page

- 24 of Event

Description:

1 B CFPT trip (loss of all CF flow to S!Gs) requiring reactor trip. Auto and Manual Turbine trip failure on reactor trip. CAPT #1 overspeed trip, MD CA failure to start.

Time Position Applicants Actions or Behavior j

Booth Operator can insert Ever 5 at the discretion of the lead examiner.

Indications:

AD5, Cl CFPT B TRIPPED AD1, A6 TURB TRIP ON LOSS OF BOTH CFPTS NUMEROUS AD1 ALARMS AD4, Cl -C4 SIG A - D FLOW MISMATCH LOCF FLOW AD4, BI 84 SIG A D LEVEL DEVIATION ENTER AP111N55001006 J_OSS OF S/G FEEDWATER)

RO SRO RO Manually trip the reactor Go to EPII/a/50001E-O (Reactor Trip or Safety Injection)

Manually reduce Turbine Load EViALUATOR NOTE: The following actions are taken from APIIIAI5SOO!006 (LOSS OF SIG FEEDWATER) Case I.

1. Verify reactor power - LESS THAN 5%.

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

a. Manually trip reactor.

b. GO TO EP/1IAI5000IE-O (Reactor Trip Or Safety Injection).

EVALUATOR NOTE: The following actions are taken from EP!IIAI5000IE-O (Reactor Trip Or Safety Injection). The RO and BOP will perform the immediate actins:

RO/

1. Monitor Enclosure I (Foldout Page).

2. Verify Reactor Trip:

E All rod bottom lights LIT RO 11 All reactor trip and bypass breakers OPEN u hR amps - DECREASING.

3. Verify Turbine Trip:

RO E All turbine stop valves - CLOSED Appendix D Catawba NRC Exam Dec 2010 Page 24 of 35 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op Te+ Ne.:

NRC Scenario #

2-Event#

5,8, and 7 Page 25-of

- 35 Event

Description:

1 B CFPT trip (loss of all CF flow to SIGs) requiring reactor trip. Auto and Manual Turbine trip failure on reactor trip. CAPT #1 overspeed trip, MD CA failure to start.

Time 1

Position Applicants Actions or Behavior

3. RNO Perform the following:

a. Manually trip the turbine.

b. IF turbine will not trip, THEN:

1) Depress the MANUAL pushbutton on the turbine-control panel.

CRITICAL TASK RO

2) Rapidly unload turbine by simultaneously depressing the CONTROL VALVE LOWER and FAST RATE pushbuttons.

3) IF turbine will not runback, THEN close:

All MSIVs All MSIV bypass valves.

4. Verify IETA and IETB - ENERGIZED.

5. Verify SIl is actuated:

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

5.a RNO a. Perform the following:

1) Verify conditions requiring S/I:

Pzr pressure - LESS THAN 1845 PSIG OR u Containment pressure - GREATER THAN 1.2 PSIG.

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

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

El Implement EPIIIAI5000IF-O (Critical Safety Function Status Trees).

El GO TO EPII/N5000IES-O.1 (Reactor Trip Response).

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 25 of 35

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

-NRC Scenario #

2 Everit#-

- -5, -8, and 7 Page 26 of

-35 Event

Description:

1 B CFPT trip (loss of all CF flow to SIGs) requiring reactor trip. Auto and Manual Turbine trip failure on reactor trip. CAPT #1 overspeed trip, MD CA failure to start.

Time 1

Position Applicants Actions or Behavior EVALUATOR NOTE: The following actions are taken from EPII!A15000!ES-O.1 (Reactor Trip Response).

ROl

1. Monitor Enclosure I (Foldout Page).

2. Verify the following:

L All 6.9 KV busses

- ENERGIZED.

-BOP D VI pressure

- GREATER THAN 85 PSI-G.

3. Announce Unit I Reactor Trip.

4. Determine required notifications:

- SRO L REFER TO RPIO/A/5000/O01 (Classification Of Emergency)

L REFER TO RP/01B150001013 (NRC Notification Requirements).

NOTE Enclosure 2 (NC Temperature Control) shall remain in effect until subsequentsteps provide alternative NC temperature-control guidance.

5. Control NC temperature. REFER TO Enclosure 2 (NC Temperature Control).

6. Verify feedwater status as follows:

a. T-Avg - LESS THAN 564°F.

b. All Feedwater Isolation status lights (1 SI-5)

- LIT.

c. Total feed flow to S/G(s)

GREATER THAN 450 GPM.

6.c. RNO

c. Establish feed flow to maintain at least one S/G NIR level greater than 11% OR total feed flow greater than 450-GPM using one of the following:

BOP!

LICA pumps RO OR LI Main Feedwater System. REFER TO OP/I /N6250/0O1 (Condensate and Feedwater System).

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 26 of 35

Appendix D Required Operator Actions Form ES-D-2 Op TetNo.:

- NRC

-Scenario#

2

-Event#

5,6, and?

Page 27 of Event

Description:

1 B CFPT trip (loss of all CF flow to SIGs) requiring reactor trip. Auto and Manual Turbine trip failure on reactor trip. CAPT #1 overspeed trip, MD CA failure to start.

Time Position Applicants Actions or Behavior

7. Verify adequate shutdown margin as follows:

a. DRPI indication

- AVAILABLE.

b. All control and shutdown rods -FULLY INSERTED.

c. All NC T-Colds -GREATER THAN 545°F.

d. IF AT ANY TIME NC T-Colds decrease to less than or equal to 545°F, THEN perform Step 7.c.

e. Stop any boron dilutions in progress.

8. Verify proper Pzr level control as follows:

a. Pzr level -GREATER THAN 17%.

b. Charging and letdown

- IN SERVIcE

c. Pzr level - TRENDING TO PZR REF LEVEL.

9. Verify proper Pzr pressure control as follows:

a. Pzr pressure -GREATER THAN 1845 PSIG.

b. Pzr pressure - STABLE AT OR TRENDING TO 2235 PSIG.

10. Control SIG levels as follows:

a. Verify NIR level in any S/G GREATER THAN 11%.

b. Throttle feed flow to maintain SIG N/R levels between 11% and 50%.

CREW

11. Initiate concurrent actions in Abnormal Procedures as needed while continuing with this procedure.

EVALUATOR NOTE: Depending on the speed of the crew in closing the main turbine stop valves. The restof ES-O.1 is verification of proper plant response, shutting down équipmént and shifting steam dumps to pressure mode.

FR-H.1 will be entered when S!G NR levelsare <11% and total CA flow is<45OGPM.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 27 of 35

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

NRC

- Scenario #-

2-Event#

8 Page 35 Event

Description:

Loss of secondary heat sink.

Time Position J Applicants Actions or Behavior EVALUATOR NOTE: The following steps are from EPII!N5000!FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.

1. IF total feed flow is less than 450 GPM due to operator action, THEN RETURN TO procedure and step in effect.

2. Verify secondary heat sink is required as follows:

a. NC pressure - GREATER THAN ANY NON-FAULTED SIG PRESSURE.

b. Any NC T-Hot - GREATER THAN 350°F.

ROIBOP

3. Monitor Enclosure I (Foldout Page).

4. Verify at least one NV pump - AVAILABLE.

5. Verify bleed and feed is required as follows:

a. W/R level in at least 3 SIGs LESS THAN 24%(36% ACC).

5.a RNO Perform the following:

1) Monitor bleed and feed initiation criteria. REFER TO Enclosure 1 RO/BOP (Foldout Page).

2) WHEN criteria is satisfied, THEN GO TO Step 19.

3) GO TO_Step 6.

6. Ensure SIG BB and NM valves closed. REFER TO Enclosure 16 (SIG BB and NM Valve Checklist).

7. Attempt to establish CA flow to at least one SIG as follows:

a. Verify 1AD-8, B/I UST LO LEVEL

- DARK.

b. Verify ICA-4 (CA Pmps Suct From UST) - OPEN.

c. Verify proper CA pump status as follows:

1) Power to both motor driven CA pumps

- AVAILABLE.

2) IAD-5, F/3 CAPT MECH OS TRIP - DARK.

7.c.2 RNO Perform the following:

a) Dispatch operator to reset the CAPT trip and throttle valve.

BOP b) IF AT ANY TIME the CAPT trip and throttle valve is reset prior to reaching bleed and feed criteria, THEN perform Step 7.

c)_GO TO_Step_7.d.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 28 of 35

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

NRC Scenaria#

2 Everrt#

8-Page 29 of 35 Event

Description:

Loss of secondary heat sink.

Time Position I

Applicants Actions or Behavior

7. d. Ensure all CA isolation valves

- OPEN.

e. Verify all CA flow control valves -OPEN.

f. Start all available CA pumps.

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

7.g RNO Perform the following:

1) IF any CA pump is on, AND Step 34 has been implemented, THEN GO TO Enclosure 8 (S/G CA Flow Restoration).

2) IF any feed flow to at least one S/G verified, THEN perform the following:

3) IF no CA flow indicated, THEN perform the following:

a) IF no CA pump can be started, THEN dispatch operator and BOP maintenance to CA pumps to attempt to restore one CA pump to service. REFER TO EM/1/A5200/007 (Troubleshooting Cause For CA Pump(s) Failing to Start).

b) Dispatch operator to verify proper CA valve alignment. REFER TO (Local -CA Flowpath Restoration).

c) IF AT ANY TIME CA flow is restored prior to meeting bleed and feed initiation criteria, THEN perform Step 7.

4) GO TO_Step_8.

8. Transfer condenser steam dump to pressure control mode as follows:

a. Verify condenser - AVAILABLE:

LI C-9 COND AVAILABLE FOR STM DUMP status light (151-i 8) - LIT.

Li Any MSIV - OPEN.

b. Verify Steam Dumps in - T-AVG MODE.

c. Place steam dumps in pressure mode as follows:

1) Ensure STM DUMP CTRLSETAT 1090 PSIG STEAM HEADER PRESSURE.

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

3) Adjust STM DUMP CTRL M/A station output to match %

STM DUMP DEMAND (1SMP5211).

4) WHEN output on STM DUMP CTRL M/A station is equal to

% STM DUMP DEMAND (1 SMP52I 1), THEN place steam dumps in

- PRESSURE MODE.

d. Place STM DUMP CTRL M/A station in auto.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 29 of 35

Appendix D Required Operator Actions Form ES-D-2 Op-Test Nv.:

NRC Sceriarft t 2

vent#

Page 30 ot 3S Event

Description:

Loss of secondary heat sink.

Time Position Applicants Actions or Behavior BOP

9. Stop all NC pumps.

10. Verify CM System is in service as follows:

BOP El Hotwell pump(s)

ON El Condensate Booster pump(s) - ON.

11. Reset Feedwater Isolation as follows:

a. Verify the following annunciators

- DARK:

El 1AD-8, D/7 INNER DOGHOUSE TRAIN A LEVEL HI BOP El IAD-8, E17 INNER DOGHOUSE TRAIN B LEVEL HI El 1AD-8, D18 OUTER DOGHOUSE TRAIN A LEVEL HI El IAD-8, E18 OUTER DOGHOUSE TRAIN B LEVEL HI.

b. Verify S/I

- HAS PREVIOUSLY ACTUATED.

11.b RNO Perform the following:

1) ResetFeedwater Isolation.

2) IF Feedwater Isolation will not reset, THEN notify IAE to bypass Feedwater Isolation. REFER TO EM/I /A/5200/009 (Bypassing Feedwater Isolation).

3) GO TO_Step_11.e.

SRO 11.e IF AT ANY TIME a subsequent Feedwater Isolation occurs, THEN RETURN TO Step 11.

12. Attempt to establish CF flow to at least one SIG as follows:

a. Verify CM System

- IN SERVICE.

b. Place the following valves in manual and closed:

El All CF control valves RO El All CF bypass control valves.

c. Ensure at least one of the following valves

- OPEN:

El 1OF-lO (1A CF Pump Disch Isol) (TB-579, IE-21)

El ICF-17 (lB CF Pump Disch Isol) (TB-579, IE-20).

d. Verify at least one CF pump - AVAILABLE TO BE STARTED.

RO 12.d RNO IF both CF pumps are known to be incapable of starting, THEN GO TO Step 14.

14. Depressurize NC System as follows:

a. Verify letdown - IN SERVICE.

b. Verify power to 1 NV-37A (NV Supply To Pzr Aux Spray) -

AVAILABLE.

c._Depressurize_NC_System_to_less than_1905_PSIG_using_NV aux Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 30 of 35

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

NRC Scenario vent 8

Page Si of 35 Event

Description:

Loss of secondary heat sink.

Time Position Applicants Actions or Behavior spray as follows:

1) OPEN the following valves:

LI 1 NV-31 2A (Chrg LineCont Isol)

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

2) Ensure the following valves - CLOSED:

LI 1 NC-27 (Pzr Spray Ctrl Frm Loop A)

LI 1 NC-29 (Pzr Spray Ctrl Frm Loop B)

LI 1 NV-39A (NV Supply To Loop D Isol)

LI 1 NV-32B (NV Supply To Loop A Isol).

3) Maintain charging flow less than 180 GPM.

4) Throttle 1 NV-37A (NV Supply To Pzr Aux Spray) and charging flow as required.

d. Maintain NC pressure less than 1905 PSIG.

e. IF AT ANY TIME letdown is lost AND a Pzr PORV is available, THEN:

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

2) OPEN one of the following valves:

LI 1NV-39A(NV Supply To Loop D Isol)

OR LI 1 NV-32B (NV Supply To Loop A Isol).

3) Depressurize NC System to less than 1905 PSIG using one Pzr PORV.

15. Block S/I as follows:

a. Verify P-Il PZR S/I BLOCK PERMISSIVE status light (1 SI-i 8) -

LIT.

b. Depress the BLOCK pushbuttons for the following signals:

LI ECCS steam pressure BOP LI ECCS Pzr pressure.

c. Verify the following status lights (1SI-13)

- LIT:

LI Main Steam lsol LI Pzr low pressure S/I.

d. IF AT ANY TIME conditions degrade while in this procedure, THEN initiate S/I.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 31 of35

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

NRC Scenario #

2 Event #

8 1a.e 32 Of 35 Event

Description:

Loss of secondary heat sink.

Time Position Applicants Actions or Behavior

16. Attempt to establish feed flow from CM as follows:

a. Verify condenser - AVAILABLE Li C-9COND AVAILABLE FOR STM DUMP status light (151-18)- LIT.

Li MSIV on SIGs to be depressurized

- OPEN.

b. Place STM DUMP CTRL M/A-station in manual.

c. Verifysteam dumps in PRESSURE MODE.

d. WHEN P-12 LO-LO TAVG status light (lSl-18) is lit, THEN place steam dump interlock bypass switches in BYP INTLK.

e. Verify Bleed and Feed PREVIOUSLY ESTABLISHED Steps 20 through 33 Completed) 16.e RNO Perform the following:

1)CLOSE MSIV on two S/Gs not to be depressurized.

2) Ensure SIG PORV closed or in AUTO on two S/Gs not to be depressurized.

3) GO TO Step 16.h.

NOTE Li After 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.

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

h. Depressurize at least one SIG to less than 505 PSIG as follows:

1) Dump steam to condenser at maximum rate while attempting to avoid a Main Steam Isolation.

CRITICAL STEP RO

i. WHEN SIG pressure is less than 505 PSIG, THEN stabilize SIG pressure less than 505 PSIG.

j. Verify Bleed and Feed

- PREVIOUSLY ESTABLISHED Steps 20 through 33 Completed)

SRO 16.j RNO GO TO Step 16.1.

16. I. Verify CF Isolation signal - RESET OR BYPASSED.

m. OPEN CF to CA valve on SIG(s) to be fed:

Li ICA-149 (SIG IA CF Byp To CA Nozzle)

Li 1 CA-ISO (SIG I B CF Byp To CA Nozzle)

CRITICAL STEP RO Li 1CA-151 (SIG IC CF Byp To CA Nozzle)

Li 1CA-152 (SIG IDCF Byp ToGA Nozzle).

n. Throttle open CF control valve or CF bypass control valve for SIG(s) to be fed.

o. Verify feedwater flow to depressurized SIG(s)

- INDICATING FLOW.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 32 of 35

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

- NC Scenorlo #

2 Evurit

- 8 Page 33 of 35 Event

Description:

Loss of secondary heat sink.

Time Position Applicants Actions or Behavior SRO Appendix D Catawba NRC Exam Dec 2010 Page 33 of 35 NUREG 1021 Revision 9 16.o RNO Perform the following:

1) IF depressurizeds/G pressure is less than 505 PS[G, THEN GO TO Step 18.

2) RETURN TO Step 16.h.

NOTE TO EVALUATOR: At this point feed flow should be established to at least oneSIG.

ENDOFSCENARIO

Catawba Nuclear Station NRC Exam December 2010 ATTACHMENT I CREW CRfl1CAL TASK SUV MARY SAT UNSAT CT#

CRITICAL TASK C-I Manually trip the main turbine before a severe (orange-path) challenge develops to either the subcriticality or the integrity SF or before transition to ECA-2.1 (Uncontrolled Depressurization of All SIGs), whichever happens first.

C-2 Establish feedwater flow to at least one SIG before reactor coolant system feed and bleed is required.

Comments:

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 34 of 35

ATTACHMENT 2 INFORMATION Unit I Status Power Level Power History NCS Boron Xenon 100%

EOL 90 PPM per OAC Controlling Procedure OP/l/A/61001003 (Controlling Procedure for Unit Operation), Enclosure 4.3 (Unit Operation Between 85% and 100% Power). The steps required for 100% power operation are complete.

Other Information Needed to Assume the Shaft IA LH pump is tagged out to repair a leak on the motor cooler.

Maintenance estimates that repairs will take 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to complete.

Direction for the crew is to swap NV pumps, placing 1 B in service and shutting down IA.

NLOs Available Six NLOs 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 December 2010 HLP NRC EXAM SCENARIO #3 Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 1 of 37

Catawba Nuclear Station NRC Exam December 2010 Facility:

Catawba NRC Exam 2010 Scenario No.: 3 Op Test No.:

Examiners:

Operators:

SRO RO BOP Initial Conditions:

IC#143; Unit 1 is at 50% power BOL. 1A LH pump is tagged out.

Turnover:

IA LH pump is tagged out to repair a leak on the motor cooler. Maintenance estimates that repairs will take 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to complete. Direction for the crew is to increase power to 100%.

Event Malt. No.

Event Event No.

Type*

Description 1

N-BOP Increase reactor power to 100%.

N-SRO R-RO 2

C-RO

[C046D TSSRO Pressurizer PORV 1 NC-34A fails open.

3 KC046 I-SOP KC surge tank B level failure causing non essential header isolations to TSSRO close. One B train KC pump fails to start.

4 C-BOP S000I D TS-SRO SIG 1 D develops a tube leak.

5 IRXOO9 C-RO Failure of control rods to move in automatic on TS required shutdown.

C-SRO 6

S0001 D M-ALL SIG 1 D tube rupture.

7 C-RO SMOO2D SRO SIG ID PORV fails open requiring manual isolation.

8 ISEOO3AIB C-RO Failure of automatic Phase A containment isolation signal.

9 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D Catawba NRC Exam Dec 2010 Page2of37 NUREG 1021 Revision 9

Catawba Nuclear Station NRC Exam December 2010 Scenario 3 - Summary Initial Condition Unit 1 is at 50% power BOL. 1A LH pump is tagged out.

Turnover:

IA LH pump is tagged out to repair a leak on the motor cooler. Maintenance estimates that repairs will take 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . Direction for the crew is to increase reactor power to 100%.

Event I BOP will perform an NC system dilution and RO will set turbine control setpoints to begin power increase to 100% power.

Event 2 An HVAC panel alarm will require the BOP to step out of the horseshoe area. Subsequently pressurizer PORV 1 NC-34A will fail open. RO will attempt to manually close the PORV unsuccessfully, and will have to close the PORV isolation valve per the immediate actions of AP/1/A/5500/Q11 (Pressurizer Pressure Anomalies) Case 1. Crewenters AP/il to address this issue. TS evaluation by SRO is required.

Event 3 KCsurge tank B level switch that feeds automatic isolation of both non essential headers fails low. With an A train KC pump running, this causes a loss ofcooling flow to the running 1 B NV pump. Crew will enter AP/1/A15500/021 (Loss of Component Cooling Water) to address this issue. The first B train KC pump that the crew tries to start fails. The second pump starts. TS evaluation by SRO is required.

Event 4 A 15 GPM tube leak develops on the ID SIG. Crew will enter AP/1/N5500/01 0 (Reactor Coolant Leak) Case I to address. TS evaluation by SRO is required. A shutdown will be required due to the leak si.ze. AP111A155001009 (Rapid Downpower) will be entered to direct the shutdown.

Event 5 When a TavglTref mismatch of> 1.5 degrees F exists, RO will recognize thatcontrol rods failed to insert as required. Crew will enter AP/1/N5500/015 (Rod Control Malfunction).

Event 6 Tube leak size on 1 D SIG increases to the point that the crew will not be able to maintain pressurizer level. AP/1/A15500/010 End. 1 guidance states for the crew to manually trip the reactor and safety inject and to go to E-0 (Reactor Trip or Safety Injection).

Event 7 SIG 1 D PORV fails open, providing a release path to the environment. RO will attempt to manually close the PORV and eventually close the PORV isolation valve Event 8 Automatic actuation of Phase A containment isolation fails, requiring BOP to manually initiate or to ensure that at least one valve in each major penetration from containrrient is closed.

Critical task I Close containment isolation valves such that at least one valve is closed on each critical phase-A penetration before the end of the scenario.

Critical task 2 Depressurize the RCS to meet SI termination criteria before SIG ID reaches 92% narrow range level.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 3 of 37

Catawba Nuclear Station NRC Exam December 2010 EXERCISE GUIDE WORKSHEET 1.

INITIAL CONDITIONS:

1.1 ResettoICl43 START TIME:

v Instructor Action Final Delay Ramp Delete Event In MAL-IRXOO9 (RODS FAIL TO AUTO MOVE)

MAL-KCOOIC (KC PUMP IBI MANUAL FAILURE)

MAL-KC0OID (KC PUMP 1B2 FAILURE)

MANUAL

MAL-ISEOO3B (AUTO PHASE A BLOCK ISOLATION TRN B)

MAL-ISEOO3B (AUTO PHASE A BLOCK ISOLATION TRN A)

ANN-ADI3-F05 (HVAC PANEL ON I

TROUBLE)

ANN-ADI9-F04 (YN CRITICAL ON I

TROUBLE)

MAL-SG0OID (SIG D TUBE LEAK) 300 11 MAL-SMOO2D (SIG PORV SVI 100 13 FAILURE)

ANN-ADI3-F05 (HVAC PANEL ON 2

TROUBLE)

MAL-KCOOIC (KC PUMP IBI MANUAL 29 FAILURE)

MAL-KCOOID (KC PUMP 1B2 MANUAL 30 FAILURE)

OVR-NCO46D (1NC34 PZR PORV ON 3

SEL SW OPEN POS)

XMT-KC046 (LKC_5641 KC SURGE 0

5 TANK KCLS564O TO VALVES)

MAL-SGOOID (SIG D TUBE LEAK) 15 9

Set EVENT 2 = x5riOl7a Set EVENT 3 = psm_5170> 1065 Set EVENT 29 = xli i289n Set EVENT 30 = x11i286n Place a red tag collar on IA LH pump.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page4of37

Catawba Nuclear Station NRC Exam December 2010 2.

SIMULATOR BRIEFING 2.1 Control Room Assignments:

Pósition f

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

3.

EXERCISE PRESENTATION 3.1 Familiarization Period A.

AlIow-examinees time to familiarize themselves with Control Board alignments.

3.2 Scenario EVENT 1, increase reactor powerto 100%.

j*;

BOOTHINSTRUCTORACTION j IF the SOC is called to be informed of the power increase repeat the information.

3.3 Scenario EVENT 2, Pzr PORV fails open.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR EVENT I to give an1 HVAC panel trouble alarm and ADI9 alarm.

j I V BOOTH 1NSTRUCI OR ACTION IF SWM is called to investigate the problem with I NC34A repeat back the information.

3.4 Scenario EVENT 3, IA CFPT trips.

l

- BOOTH INS UCTORACTION-:

-=

WHEN directed by the lead examiner, THEN INSERT SIMULATOR EVENT 5 to give a failure of KC surge tank level indication.

Appendix D Catawba NRC Exam Dec2010 NUREG 1021 Revision 9 Page5of37

Catawba Nuclear Station NRC Exam December 2010 j

BOOTHINSTRUCTORACTION IF the SWM is contacted to investigate the problem with KC level instrumentation repeat back the information.

BOOTH iNSTRUCTOR ACTION IF and NEC is dispatched to investigate the cause of the B train KC pump failure to start repeat back the order.

3.5 Scenario EVENT 4, Power Range N42 blown control power fuse.

B00THINSTRVTGRAQT10N WHEN directed by the lead examiner, THEN INSERT EVENT SIMULATOR 9 to give a leak in SIG 1D.

yr BOOTH INSTRTORATION IF RP is contacted to frisk the cation ccumns repeat back the order.

I

,j

y BOOTH INSTRUCTOR ACTION IF Secondary Chemistry is notified to determine affected SIG by sampling repeat the order.

BOOTH INSTRUCTOR ACTION WHEN a NEC is contacted to align auxiliary systems referring to enclosure 5 repeat back the order.

yr-BOOTHINSTRUCTOR ACTION WHEN RP is notified of the value of the leakage and to perform HPIO/B/10091003 repeat the information and order.

Y f

BOOTH INSTRUCTOR ACTION WHEN Reactor Engineering is notified of the occurrence repeat back the information.

3.6 Scenario EVENT 5, rods fail to move in AUTC.

s BOOTHINSTRUCIORACTION IF the SWM is contacted to investigate the failure of the rods to move repeat back the information.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page6of37

Catawba Nuclear Station NRC Exam December 2010 3.7 Scenario EVENT 6, SIG D tube leak increases to 300 gpm.

BoOTHNsTRuCToATIoN

/

WHEN directed by the lead examiner, THEN INSERT SIMULATOR EVENT 11 to cause the I D SIG leak to increase.

I BOOTH INSTRUCTOR ACTION IF RP is contacted to frisk the cation columns repeat back the order.

I V

J BOOTHINSTRUCTORACTION 1 IF Secondary Chemistry is notified to determine affected S/G by sampling repeat the order.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 7 of 37

Appendix D Required Operator Actions Form ES-D-2 I

Op Test No.:

NRC Scenario #

3 Event #

1 Page 8

of 37 Event

Description:

Power increase to 100% power.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: Crew will begin with apower increase. BOP will perform a Dilution per 0P1116150!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 arecomplete. A reactivity management brief will be performed during turnover. Step 3.1 is complete.

3.2 IF the blender is set for automatic makeup per Enclosure 4.1, BOP Automatic Makeup, record the setpoint on 1 NV-242A (RMWST To_B/A_Blender Ctrl):

orm 3.3 Ensure the following valve control switches in AUTO:

BOP I NV-242A (RMWST To B/A Blender Ctrl) 1 NV-I 81A (B/A Blender OtIt To VCT)

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

BOP 3.5 Ensure at least one reactor makeup water pump is in AUTO or BOP 3.6 Adjust the total makeup counter to the desired volume of reactor makeup water tobe_added._(R.M.)

BOP 3.7 Place the NC MAKEUP MODE SELECT-switch to the DILUTE position.

BOP 3.8 Adjust the setpoint for 1 NV-242A (RMWST To B/A Blender Ctrl) to the desired flow.

3.9 IF NC System boron concentration will be changed by 50 ppm, BOP initiate PZR spray to equalize the boron -concentration throughout the_system.

BOP RO Perform a dilution.

Input targets into the main turbine control panel.

NOTE TO EVALUATOR: The following actions are taken from OPII!61501009,Boron Concentration Control.

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 the dilution flow rate to 80 gpm to avoid the Rx Make-up Flow Deviation alarm and associated automatic actions.

Appendix D Catawba NRC Exam Dec 2010 Page 8of37 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 I

Op Test No.:

NRC Scenario #

3 Event #

1 Page 9

of 37 Event

Description:

Power increase to 100% power.

Time Position Applicants Actions or Behavior 3.10 IF AT ANY TIME it is desired to divert letdown to the RHT manually operate I NV-I 72A (3-Way Divert To VCT-RHT) as follows:

3.10.1 Place the control switch for 1 NV-I 72A(3-Way Divert To VCT-RHT) to the RHT position.

3.10.2 Ensure VCT level is monitoredcontinuously while BOP diverting to the RHT.

3.10.3 WHEN desired VCT level is reached return INV-172A(3-Way Divert To VCTRHT) to auto as folows:

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

3.10.3.2 Place thecontrol switch for 1 NV-I 72A.(3-Way Divert To VCTRHT) in the AUTO position.

NOTE TO EVALUATOR: Step 3.11 will be NIAd.

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

BOP iControl rod motion EINC System Tavg IlReactor Power BOP 3.13 Place the NC MAKEUP CONTROL switch in the START position._(R.M.)

3.14 Verify the following valves open:

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

I NV-I 81A (B/A Blender Otlt To VCT)

BOP 3.15 IF in AUTO, verify the reactor makeup water pump starts.

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

BOP (R.M.)

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

Appendix D Catawba NRC Exam Dec2010 NUREG 1021 Revision 9 Page 9of37

Appendix D Required Operator Actions Form ES-D-2 3.17 IF automatic makeup is desired, perform one of the following:

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

OR 3.17.2 IF makeup at the previousconcentration is acceptable BOP AND the system was previously aligned per Enclosure 4.1 (Automatic Makeup), perform the following:

3.17.2.1 Ensure the controller for 1NV-242A (RMWST To B/A BlenderCtrl) is set to the value recorded in Step 3.2. (R.M.)

3.17.2.2 Place the NC MAKEUP MODE SELECT switch in AUTO.

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

ENDOF DILUTION NOTE TO EVALUATOR: The following steps are from 0P111B163001001, Turbine Generator, starting at step 2.1.2.

2.1.2 Increase turbine generator load by performing the following:

2.1.2.1 Select LOAD RATE and verify it illuminates.

2.1.2.2 Input the desired load rate.

2.1.2.3 SelectENTER orOK and verify LOAD RATE goes dark.

2.1.2.4 Select TARGET and verify it illuminates.

RO 2.1.2.5 Input the desired load target.

2.1.2.6 Select ENTER and verify TARGET goes dark.

2.1.2.7 Verify new load target appears on Target Display.

2.1.2.8 SelectGO and verify it illuminates to start load increase.

2.1.2.9 S/G blowdown changes shall be coordinated with Secondary_Chemistry.

END OF PREPARATION FOR POWER INCREASE ON THE TURBINE PANEL.

Appendix D Catawba NRC Exam Dec 2010 Page 10 of 37 NUREG 1021 Revision 9 Op Test No.:

NRC Scenario#

3 Event#

1 Page 10 of 37 Event

Description:

Power increase to 100% power.

Time Position Applicants Actions or Behavior

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

NRC Scenario #

3 Event #

2 Page 11 of 37 Event

Description:

Pzr PORV 1 NC34A fails open.

Time I

Position Applicants Actions or Behavior Booth Operator can insert Event 2at the discretion of lead examiner.

Indications: IAD6, E-1O VZR PDRV DISCH HI TEMP IAD6, F-8 PZR LO PRESSCONTROL NC PRESSURE DECREASING 1AD6, D-1O PZR LO PRESS PORV NC32 AND 36 BLOCKED 1AD6, Dli PZR LO PRESS PORV NC34 BLOCKED BOP

[ Proceed to back of MCB to investigate HVAC trouble alarm.

RD Recognize 1 NC34A is open and attempt to close or isolate.

NOTE TO EVALUA3OR: An HVAC Trouble alarm wiI come in requiring the BOP to leave the horseshoe area.

NOTE TO EVALUATOR: The following steps are from API1!A155001011, Pressurizer Pressure Anomalies.

RD

1. Verify all Pzr PORVs -CLOSED.

1. RNO Perform the following:

a. Manually close Pzr PDRV(s).

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

1) Close_the_affected_PORV.(s)_isolation_valve.

NOTE Control rods may withdraw on decreasing NC pressure.

RD

2. Verify Pzr spray valve(s)

- CLOSED.

RD

3. Verify all Pzr heaters - ENERGIZED.

RD

4. Ensure INV-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.

RD

5. Verify NC pressure - STABLE OR INCREASING.

6. WHEN NC pressure is stable, THEN:

El Stabilize unit at appropriate power level.

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

LI Turbine load El Control rods El Boron concentration.

NOTE TO EVALUATOR: Step 7will be N!Ad.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 11 of 37

Appendix D Required Operator Actions Form ES-D-2 1 Op Test No.:

NRC Scenario #

3 Event #

2 Page 12 of 37 Event

Description:

Pzr PORV I NC34A fails open.

Time Position 1

Applicants Actions or Behavior

8. Ensure compliance with appropriate Tech Specs:

LI 3.3.1 (Reactor Trip System (RTS)

Instrumentation)

LI 3.3.2 (Engineered Safety Features Actuation System(ESFAS)

Instrumentation)

LI 3.3.3 (Post Accident Monitoring (PAM) Instrumentation)

LI 3.3.4 (Remote Shutdown System)

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

LI 3.4.4 (RCS Loops - MODES 1 and 2)

LI 3.4.5 (RCS Loops - MODE 3)

LI 3.4.6 fGS Loops

- MODE 4)

LI 3.4.9 (Pressurizer)

LI 3.4.10 (Pressurizer Safety Valves)

LI 3.4.11 (Pressurizer Power Operated Relief Valves (PORVs))

LI 3.4.13 (RCS Operational Leakage).

9. Determine long term plant status.

SRO RETURN TO procedure in effect.

NOTE TO EVALUATOR: The SRO should determineentrylntoT.S. 3.4.11 is required

[

1 ENDOFEVENT2.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 12 of 37

Appendix D Required Operator Actions Form ES-D-2 OpTestNo.:

NRC Scenario#

3 Event#

3 Page 13 of 37 Event

Description:

KC surge tank B level failure causes non-essential header isolations to close. One B train K-C pump fails to start.

Time Position Applicants Actions or Behavior Booth Operator can insert Event 3 at the discretion of lead examiner.

Indications: KG B header crossconnect valves go closed.

1AD7, D-3 NV PMP B OIL COOLER LOFLOW Crew enters AP/1/A/5500/021, Loss of Component Cooling REW Recognize a failure of the KC level transmitter going to the KC

header cross-connect valves.

NOTE TO EVALUATOR: The following steps are from AP!11A155001021, 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 CREW damage to the NC pump seals resulting in NC inventory loss.

RO/BOP

1. Monitor Enclosure I (Foldout Page).

2. Verify at least one KG pump - ON.

3. IF AT ANY TIME all KC pumps are lost, THEN RETURN TO STEP_2.

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

4. Verify the following:

BOP El IAD-7, Ff3 LETDN HX OUTLET HI TEMP

- DARK.

AND El_At_least one_KC_pump_-_ON.

5. IF AT ANY TIME IAD-7, F13 LETDN HX OUTLET HI TEMP LIT, THEN_perform_Step 4_RNO.

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

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

NOTE TO EVALUATOR: The first KC pump started will not start. The LOP will start the second KC pump on B train.

CAUTION A loss of KCcooling to the NC pumps results in a gradual approach to an overheated condition in approximately 10 minutes_which_will_result_in_shaft_seizure.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 13 of 37

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

NRC Scenario It 3

Event #

3 Page 14 of 37 Event

Description:

KC surge tank B level failure causes non-essential header isolations to close. One B train KC pump fails to start.

Time Position Applicants Actions or Behavior

8. Verify KC flow to NC pumps as follows:

1AD-20, All KG SUPPLY HDRFLOWTO NCP BRGS LOW BOP

-DARK LI 1AD-21, NI KC SUPPLY HDR FLOW TO NCP BRGS LOW

- DARK.

9. Verify KG available as follows:

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

LI 1 KC-230A (Rx Bldg NonEss Hdr Isol)

LI IKC-3A (Rx Bldg Non-Ess Ret Hdr Isol)

LI I KC-5OA (Aux Bldg Non-Ess Hdr Isol)

BOP LI 1 KC-IA (Aux Bldg NonEss Ret Hdr Isol).

b. Verify the following Train B KG non-essential header isolation valves

- OPEN:

LI I KC-228B (Rx Bldg Non-Ess Hdr Iso!)

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

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

LI IKC-2B.(Aux Bldg Non-Ess Ret Hdr Isol).

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

9.b RNO NOTE The KG non-essential header valves can be reopened when the appropriate trains level switch is reset.

This should occur between 40% and 48% KC surge tank BOP level.

b. WHEN OAG alarm G1D2214 (KG Train B Low-Low Level Surge Tank Isol) is NOT ACTUATED, THEN ensure the affected valve(s) are open.

10. Verify KG surge tank levels normal as follows:

a. Verify both KG surge tank levels

- 50%

- 90% AND STABLE.

b. GO TO Step 14.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 14 of 37

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

NRC Scenario #

3 Event #

3 Page 15 of 37 Event

Description:

KC surge tank B level failure causes non-essential header isolations to close. One B train KC pump fails to start.

Time Position II Applicants Actions or Behavior

14. Ensure KG heat exchanger outlet mode switches -

PROPERLY ALIGNED.

BOP CREW SRO SRO

15. Determine and correct cause of loss of KC.

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

LISLC 16.9-7 (Boration Systems Flow Path

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

LI SLC 16.9-9(BorationSystems Pumps-Shutdown)

El SLC 16.9-10 (Boration Systems Charging Pumps Operating)

El 3.5.2 (ECCS

- Operating)

Li 3.5.3 (ECCS

- Shutdown) ii 3.6.6 (ContainmentSpray System)

Li 3.7.5 (Auxiliary Feedwater (AFW) System)

[1 3.7.7 (Component Coolina Water CCW) System).

NOTE TO EVALUATOR: TheSRO should determine T.S. 3.7.7 should be entered.

SRO NOTE TO EVALUATOR: Step 18 will be N/Ad.

19. Verify KG surge tanks level as follows:

BOP Li Greater than 50%

Li Stable or increasing.

20. WHEN plant conditions permit, THEN:

Li Return KC pumps to normal operation. REFER TO BOP OP/1/A16400/005 (Component Cooling Water System).

LI Return NV Pump lAto normal cooling as applicable. REFER TO_Enclosure_4_(Alternate_Cooling_To_NV_Pump_1A).

17. Determine required notifications:

Li REFER TO RP/0/A!5000/001 (Classification OfEmergency)

Li REFER TO RPIOIB/50001013 (NRC Notification ReQuirements).

18. IF KC Hx leak to RN is suspected, THEN perform the following:

Appendix D Catawba NRC Exam Dec 2010 Page 15 of 37 NUREG 1021 Revision 9

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

NRC Scenario #

3 Event #

3 Page 16 of 37 Event

Description:

KC surge tank B level failure causes non-essential header isolations to close. One B train KC pump fails to start.

Time Position Applicants Actions or Behavior

21. Verify the following:

LI 1AD-7, F13 LETDN HX OUTLET HI TEMP

- DARK BOP LI 1AD-7, H13 VCT HI TEMP

- DARK LI Normal letdown

- IN SERVFCE.

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:

LI 1NV-188A (VCT OtIt Isol)

[I 1NV-189B (VCT OtIt [sol).

2) Close the following valves:

BOP LI INV-252A (NV PumpsSuct From FWST)

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

b. WHEN NV suction aligned to VCT, THEN momentarily place 1 NV-I 72A (3-Way Divert To VCT-RHT) to the VCT position and return to AUTO.

c. IF desired to restore [etdown flow through the NV demineralizers, THEN momentarily place 1NV-153ALetdn Hx OtIt 3-Way Vlv) to the DEMIN position and return to AUTO.

CREW

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

END OF EVENT 3.

Appendix D Catawba NRC Exam Dec2010 NUREG 1021 Revision 9 Page 16 of 37

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

Event

Description:

SIG 1 D develops a tube leak. Auto rod control is failed.

Applicants Actions or Behavior NRC Scenario #

3 Event #

4 and 5 Page 17 of 37 Booth Operator can insert Event 4 at the discretion oflead examiner.

Indications: 1 RAD-i, B-i 1 EMf 33 CSAE EXHAUST HI RAD 1RAD-i, B-4 IEMF 71 SIG A LEAKAGE HI RAD I RAD-i, E-5 1EMF 74 SIG D LEAKAGE HI RAD J

CREW j Recognize a S/G tube leak.

NbTE TO EVALUATOR: The following steps are from AP/115500I010, Reator Coolant Leak Case I.

RO/BOP

1. Monitor Enclosure I (Case I Steam Generator Tube Leak Foldout_Page).

2. Verify Pzr level

- STABLE OR INCREASING.

3. IF AT ANY TIME Pzr level decreases in an uncontrolled CREW manner or cannot be maintained greater than 4%, THEN perform_Step 2.

NOTE In subsequent steps the term affected S/G is a SIG with primary_to_secondary_leakage.

4. Identify the affected S/G(s) as follows:

El Notify RP to frisk all cation columns.

OR El Any SIG N/R Level - INCREASING IN AN UNCONTROLLED MANNER.

OR NOTE The SIG Leakage EMFs are highly sensitive which may cause the EMFs located on the adjacent steamline to be increasing or in alarm.

El Verify any of the following S/G leakage EMF indication(s)

RO/BOP INCREASING OR IN ALARM:

El 1EMF-71 (SIG A Leakage)

El 1 EMF-72 (S/G B Leakage)

El 1EMF-73 (SIG C Leakage)

El I EMF-74 (S/G D Leakage).

OR El Verify any of the following SIG steamline EMF indication(s)

INCREASING OR IN ALARM:

El 1EMF-26 (Steamline IA)

El 1EMF-27 (Steamline 1B)

El 1EMF-28 (Steamline IC)

El 1 EMF-29 (Steamline I D).

(Continued)

Time II Position Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 17 of 37

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

NRC Scenario 3

Event #

4 and 5 Page 18 of 37 Event

Description:

S!G 1 D develops a tube leak. Auto rod control is failed.

Time Position Applicants Actions or Behavior OR El Verify CF flow - LOWER TO ANY SIG AS COMPARED TO OTHERS.

OR LI Notify Secondary Chemistry to4etermine affected SIG by sampling.

5. Verify VCT level able to be maintained by normal makeup as follows:

a. One of the following conditions exists:

El SIG tube leak is less than 90 gpm.

OR El Automatic makeup stabilizes or increases VCT level.

OR BOP El Manual makeup stabilizes or increases VCT level.

b. IF AT ANY TIME the following conditions exist:

El 1AD-7, Ill VCT LO LVL alarm LIT AND LI Reactor trip breakers are closed.

THEN perform Step 5.a RNO.

6. Minimize Secondary contamination as follows:

a. Remove CM polishing demineralizers from service as follows:

1) Ensure POLSH DEMIN BYP CTRL

- PLACED IN MANUAL.

2) Ensure POLSH DEMIN BYP CTRL

- OPEN.

3) Notify Secondary Chemistry CM polishing demineralizers have been bypassed.

RO/BOP

b. Align auxiliary systems to minimize secondary side

contamination as follows:

1) Transfer turbine steam supply to AS as follows:

a) Open 1TL-8 (AuxStm To Stm Seal Reg).

b) Close 1TL-2 (Main Stm To Stm Seal Reg).

2) Dispatch operator(s) to align auxiliary systems. REFER TO Enclosure 5 (Auxiliary System Alignment).

c._Stop_any_transfer_of water_between_both_Units_CSTs.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 18 of 37

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

NRC Scenario #

3 Event#

4 and 5 Page 19 of 37 Event

Description:

SIG 1 D develops a tube leak. Auto rod control is failed.

Time Position Applicants Actions or Behavior NOTE El Tritium sampling may be the most effective method for determining leak fate for small tube leaks when in Mode 2 or3.

El The OAC calculated leak rate may be invalid during mode changes and/or transient conditions unless there is current, coordinated sampling_data_avaifable.

7. Determine S!G leak rate by any of the following methods:

El Monitor the following computer points:

El Cl P0187 (Estimated Total Pri To Sec Leakrate)

El Cl P01 89 (Pri To Sec Leakrate 15 Mm Running Avg)

El.EROSLEAK(Primary To Secondary Leakage).

OR NOTE The SIG Leakage EMFs are highly sensitive which may cause the EMFs located on the adjacent steamline to be increasing or in alarm.

El SIG leakage EMF indication(s):

BOP El 1 EMF-71 (SIG A Leakage)

El 1EMF-72 (S/G B Leakage)

El IEMF-73 (SIG C t.eakage)

El 1 EMF-74 (S/G D Leakage).

OR El Compare charging flow and letdown flow OR El Monitor OAC NVGraphic OR El Initiate OAC Program NSNCLEAK OR El Monitor OAC point C1P0976(Gross FC System Leak Rate, Ten Mm Run Avg).

OR El Secondary Chemistry performance of PT/1/B/4600/028 (Determination_of_Steam_Generator Tube_Leak_For_Unit_1).

Appendix D Catawba NRC Exam Dec2010 Page 19 of 37 NUREG 1021 Revision 9

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

NRC Scenario #

3 Event #

4 and 5 Page 20 of 37 Event

Description:

S/G 1 D develops a tube leak. Auto rod control is failed.

Time T Position Applicants Actions or Behavior

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

1 3.4.13 (RCS Operational Leakage)

D 3.4.14 (RCS Pressure Isolation Valve SRO (PIV) Leakage)

L 3.5.5 (Seal Injection flow) 3.7.17(Secondary Specific Activity)

LrSLC 16.7-9{Standby Shutdown System).

NOTE TO EVALUATOR: The SRO should determine entry into T.S. 3.4.13 is necessary due to SIG tube leakage exceeding limits..

9. Verify Unit in Mode 1.

NOTE 0 The following leak rates are based on leakage in one SIG.

0 In the event of an oscillating leak, the leak rate shall be determined_based_on_the_peak_value_of the_spike.

RO/BOP

10. Verify leak rate - GREATtR THAN OR EQUAL TO 5 GPD.

RO/BOP

11. Verify leak rate - GREATER THAN OR EQUAL TO 30 GPD.

12. Verify at least one of the following:

0 Leak rate is greater than or equal to 100 gpd.

OR 0 Leak rate greater than or equal to 75 gpd has been sustained for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

BOP OR 0 All of the following:

0 Leak Rate is greater than orequal to 75 gpd 0 Cl P0187 (Estimated Total Pri To Sec Leakrate) - INVALID ii Any main steam line N-16 radiation monitor - INOPERABLE.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 20 of 37

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

NRC Scenario #

3 Event #

4 and 5 Page 21 of 37 Event

Description:

SIG 1 D develops a tube leak. Auto rod control is failed.

Time j

Position Applicants Actions or Behavior

13. Perform the following:

NOTE Leakage indications are validated by an EMF trending in the same direction. Precise duplication of leakage values is not required.

a. Verify at least one of the following EMFs validate leakage md ication:

Li 1EMF-71 (S/GALeakage)

Li 1EMF-72 (S/G B Leakage)

Li 1 EMF-73 (S/G C Leakage)

Li 1EMF-74S/G DLeakage).

NOTE Unit shutdown should not be postponed while waiting for chemistry calculation results.

b. IF AT ANY TIME Chemistry calculations contradict leakage indications, THEN perform the following:

BOP Li Unit shutdown may be suspended Li RETURN TO Step 8.

NOTE EMFs should be monitored every 15 minutes.

c. Monitor the following EMFs:

Li I EMF-33 (Condenser Air Ejector Exhaust)

[1 IEMF-71 (S/G A Leakage)

LI 1 EMF-72 (S/G B Leakage)

Li 1 EMF-73 (S/G C Leakage)

LI 1 EMF.-74 (SIG D Leakage).

d. Notify RP of the following:

1) The current value of leakage.

2) Perform H PlO/B/I 009/003 (Radiation Protection Response Following A Primary To Secondary Leak).

e. Evaluate secondary contamination potential. Review PT/I /B14 150/001 G (Turbine Building Sump Isolation).

14. Determine unit shutdown requirements as follows:

a. IF AT ANY TIME leak rate is greater than or equal to 100 SRO gpd, THEN perform the following:

1) Ensure reactor power less than 50% within 1 hr.

2) Ensure unit in Mode 3 within the following 2 hrs.

3) Observe Note prior to Step 15 and GO TO Step 15.

Catawba NRC Exam Dec 2010 Page 21 of 37 NUREG 1021 Revision 9 NOTE TO EVALUATOR: The rest of step 14 will be N/A.,

Appendix D

Appendix D Required Operator Actions Form ES-D-2 Applicants Actions or Behavior Appendix D Catawba NRC Exam Dec 2010 Page 22 of 37 NUREG 1021 Revision 9 Op Test No.:

Time Position Event

Description:

S/G 1 D develops a tube leak. Auto rod control is failed.

NRC Scenario #

3 Event #

4 and 5 Page 22 of 37 NOTE EMF indications may decrease during unit shutdown. Unit shutdown should not be suspended based solely on decreasing radiation monitor indications.

15. Shutdown the Unit as follows:

a. Notify -Reactor Group Engineer of occurrence.

b. Verify reactor power -GREATER THAN 1-5%.

c. Initiate unit shutdown. REFER TO:

Li OP/I /N61 00/003 (Controlling ProcedureFor Unit RO/BOP Operation)

OR Li AP/11A15500/009 (Rapid Downpower).

d. Ensure adequate shutdown margin is maintained. REFER TO ROD Book, Section 5.11.

NOTE TO EVALUATOR: At this step the crew will refer to APIIIPJ5500IOO9 (Rapid Downpower) and begin a rapid shutdown.

NOTE TO EVALUATOR: The following steps are from AP111A155001009 (Rapid Downpower).

RO/BOP

1. Monitor Enclosure I (Foldout Page).

2. Determine required notifications:

Li REFER TO RPIOIAI5000/001 {Classification Of SRO Emergency)

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

CREW

3. IF AT ANY TIME prompt separation from the grid is required, THEN GO TO Step 26.

4. IF load reduction is due to grid instability, THEN perform the following:

NOTE TO EVALUATOR: Step 4 will be N1A.

5. Verify Turbine Control - IN AUTO.

6. Verify the following load reduction criteria - KNOWN:

CREW Li Time required to reduce load Li Target load power level.

7. Verify time required to reduce load

- GREATER THAN OR EQUAL TO_15_MINUTES.

Op Test No.:

L Appendix D Required Operator Actions Form ES-D-2 Event

Description:

S/G 1 D develops a tube leak. Auto rod control is failed.

I Applicants Actions or Behavior NRC Scenario #

3 Event #

4 and 5 Page 23 of 37 Time II Position NOTE The following tables are estimates only and can be used for rapid entry into the turbine control panel.

SRO/BOP

8. Determine the required power reduction rate (MWIMin) from the table below:

NQTE TO EVALUATOR: The SROand BOP will refer to the táblé inthis step and determine the appropriate load reduction rate.

]

SROIBOP j 9. Determine the target load from the table below:

NOTE TO EVALUATOR:The SRO and BOP will refer to the table in this step and determine the appropriate target load.

10. Initiate turbine load reduction as follows:

NOTE Any load reduction rate of greater than 25 MW/Mm must be performed in the manual mode.

0 Unloading rates greater than 60 MW/Min(5%/minute) will meet C-7A interlock and may result in steam dump actuation.

RD

a. Verify automatic turbine load reduction

- DESIRED.

b. Enter the desired LOAD RATE on the turbine control panel.

c. Enter the desired TARGET on the turbine control panel.

d. Depress the GO pushbutton on the turbine control panel.

e. Verify turbine load

- DECREASING AS REQUIRED.

f. IF AT ANY TIME the turbine controls fail to respond properly, THEN perform Step 10.e.

RORO

11. IF AT ANY TIME the turbine load reduction rate OR the target load must be changed, THEN RETURN TO Step 5.

RD

12. Adjust power factor as necessary. REFER TO Unit I Revised Data Book Figure 43.

13. Attempt to control T-Avg as follows:

RD

a. Verify T-Ref instrumentation - AVAILABLE.

b. Verify control rods - IN AUTO AND STEPPING IN.

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

Appendix D Catawba NRC Exam Dec 2010 Page 23 of 37 NUREG 1021 Revision 9

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

NRC Scenario #

3 Event #

4 and 5 Page 24 of 37 Event

Description:

S/G 1 D develops a tube leak. Auto rod control is failed.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: At this step Event 5 is in progress. The RO should recognize a failure of rods to move and take manual control of the rods to retore Tavg.

13.c. Maintain T-Avg greater than or equal to 551°F.

d. Verify Reactor Engineering Power Maneuvering-Guidance has been provided by Duty Reactor Engineer.

13.d RNO Perform the following:

1) Borate NC System as required. REFER TO R.O.D. book (section 4.8).

2) GO TO Step 13.f.

13. f. Ensure operator monitors Enclosure 2 (Rod Insertion Limit Boration).

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

a. All Pzr PORVs - CLOSED.

b. Normal Pzr spray valves - CLOSED.

NOTE TO EVALUATOR: The following steps are from APII5, Rod Control Malfunctions.

The crew may refer to this AP dUe tothe failure. of rods to move in automatic.

1. Verify plant conditions - STABLE.

1. RNO Perform the following:

a. IF load rejection in progress, THEN do not continue in this procedure until plant conditions are stable.

b. IF power decrease in progress, THEN perform the following:

1) Determine if power decrease can be stopped.

2) IF power decrease can be stopped, THEN perform the following:

a) Stop power decrease.

b) Observe Caution prior to Step 2 and GO TO Step 2.

3) IF power decrease must continue, THEN perform the following:

u IF auto and manual rod control not available, THEN perform one of the following:

L Borate to maintain T-Avg at T-Ref and RETURN TO procedure in effect.

OR Appendix D Catawba NRC Exam Dec2010 NUREG 1021 Revision 9 Page 24 of 37

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

NRC Scenario #

3 Event #

4 and 5 Page 25 of 37 Event

Description:

SIG ID develops a tube leak. Auto rod control is failed.

Time Position J

Applicants Actions or Behavior LI Trip reactor and GO TO EP/1/N5000/.E-O (Reactor Trip Or Safety Injection).

LI IF auto or manual rod control available, THEN perform the following:

a) IF AT ANY TIME two or more rods are misaligned by greater than 24 steps, THEN:

(1) Trip Reactor.

(2) GO TO EPI1IA/50001E-O (Reactor Trip Or Safety Injection).

b) WHEN plant conditions are stable, THEN observe Caution prior to Step 2 and GO TO Step 2.

C) RETURN TO procedure in effect.

END OF EVENT 4 and 5.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 25 of 37

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

NRC Scenario #

3 Event #

6, 7 and 8 Page 26 of 37 Event

Description:

SIG 1 D Tube Rupture with a stuck open S/G 1 D PORV. Phase A fails to actuate Automatically.

Time Position I

Applicants Actions or Behavior NOTE TO EVALUATOR: After step 14 of AP-09, the booth instructor can insert Event 6 at thelead instructor% discretion.

Indications: Pzr Level begins to decrease in an uncontrolled rate.

CREW Recognize the need for a reactor trip and safety injection RO Manually trip the reactor BOP Manually actuate safety injection RO Recognize the failed SIG PORV RO Manually isolate the failed SIG PORV BOP Manually actuate Phase A containment isolation.

NOTE TO EVALUATOR: The following step is from APIIIAI5500IOIO (Reactor Coolant Leak) End 1.

a. IF Pzr level cannot be maintained greater than 4% OR Pzr pressure is decreasing in an uncontrolled manner, THEN:

CREW

1) Manually trip reactor.

2) WHEN reactor trip verified, THEN manually initiate S/I.

3) GO TO EPI1IN5000/E-0 (Reactor Trip Or Safety_Injection).

NOTE TO EVALUATOR: The following actions are from EPIIIA15000IE-o (Reactor Trip or Safety Injection).

CREW

1. Monitor Enclosure I (Foldout Page).

2. Verify Reactor Trip: (Immediate action step)

LI All rod bottom lights LIT RO LI All reactor trip and bypass breakers OPEN LI hR amps

- DECREASING.

3. Verify Turbine Trip: (Immediate action step)

LI All turbine stop valves CLOSED BOP

4. Verify IETA and IETB

- ENERGIZED. (Immediate action step)

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 26 of 37

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

NRC Scenario #

3 Event #

6, 7 and 8 Page 27 of 37 Event

Description:

SIG ID Tube Rupture with a stuck open SIG 1 D PORV. Phase A fails to actuate Automatically.

Time Position Applicants Actions or Behavior

5. Verify SII is actuated: (Immediate action step)

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

- LIT.

b. Both EIS load sequencer actuated status lights{ISI-14)

- LIT.

RD

6. Announce Unit I Safety Injection.

7. Determine required notifications:

SRO REFER TO RPIOIAI5000IOO1.(Classification Of Emergency) ii REFER TO RP/01B150001013 (NRC Notification Requirements).

RD

8. Verify all Feedwater Isolation status lights (ISI-5) - LIT.

9. Verify Phase A Containment Isolation status as follows:

a. Phase A RESET lights

- DARK.

b. Monitor Light Panel Group 5 St lights - LIT.

CRITICAL BOP

9. RNO a. Manually initiate Phase A Isolation.

f

10. Verify proper Phase B actuation as follows:

a. Containment pressure HAS REMAINED IESS THAN 3 BOP PSIG.

b. IF AT ANY TIME containment pc.essure exceeds 3 PSIG while in this procedure, THEN perform Step l0.a.

11. Verify proper CA pump status as follows:

RD

a. Motor driven CA pumps - ON.

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

12. Verify all of the following S/I pumps

- ON:

u NV pumps BDP i ND pumps NI pumps.

BDP

13. Verify all KC pumps - ON.

14. Verify all Unit I and Unit 2 RN pumps - ON.

15. Verify proper ventilation systems operation as follows:

1 REFER TO Enclosure 2 (Ventilation System Verification).

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

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 27 of 37

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

NRC Scenario #

3 Event #

6, 7 and 8 Page 28 of 37 Event

Description:

S/G 1 D Tube Rupture with a stuck open SIG 1 D PORV. Phase A fails to actuate Automaticajy.

Time I

Position I

Applicants Actions or Behavior RO

16. Verify all SIG pressures GREATER THAN 775 PSIG.

17. Verify proper Sit flow as follows:

a. NV S/I FLOW

- INDICATING FLOW.

b. NC pressure

- LESS THAN 1620 PSIG.

17.b RNO 1) Ensure ND pump miniflow valve on operating ND pump(s)

- OPEN.

2) IF the ND pump miniflow valve(s) cannot be opened, THEN perform the following for affected train(s):

3) GO TO Step 18.

18. Control SIG 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 11% (29%

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

RD

19. Verify all CA isolation valves

- OPEN.

20. Verify Sit equipment status based on monitor light panel IN PROPER ALIGNMENT.

21. Control NC temperature. REFER TO Enclosure 4 (NC Temperature Control).

22. 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.

23. Verify NC subcooling based on core exit TICs - GREATER THAN 0°F.

24. Verify main steamlines are intact as follows:

RO El All SIG pressures

- STABLE OR INCREASING El ALL S/Gs

- PRESSURIZED.

NOTE TO EVALUATOR: If the crew has not identified the ID SIG PORV failure theymáy identify SIG pressure as decreasingin an uncontrolled mannerS This would send thim to E-2, Faulted Steam Generator Isolation.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 28 of 37

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

NRC Scenario #

3 Event #

6, 7 and 8 Page 29 of 37 Event

Description:

SIG 1 D Tube Rupture with a stuck open SIG 1 D PORV. Phase A fails to actuate Automatically.

Time Position Applicants Actions or Behavior

25. Verify SIG tubes are intact as follows:

El Verify the following EMF trip I lights DARK:

El 1 EMF-33 Condenser Air Ejector Exhaust)

El 1EMF-26 (Steamline 1A)

BOP El 1EMF-27 (Steamline I B)

El 1EMF-28 <Steamline 1C)

El 1 EMF-29 (Steamline 1 D).

El All SIG levels

- STABLE OR INCREASING IN A CONTROLLED MANNER.

25. RNO IF any EMF trip I light is lit OR any SIG level is increasing in an uncontrolled manner, THEN concurrently:

SRO El Implement EPI1IN5000/F-O (Critical Safety Function Status Trees).

El GO TO EP/11A15000/E-3 <Steam Generator Tube Rupture).

NOTE TO EVALUATOR: The following actions are from EPIIIA!50001E-3.

CREW I. Monitor Enclosure I (Foldout Page).

2. Identify ruptured SIG(s) as follows:

El SIG level

- INCREASING IN AN UNCONTROLLED MANNER.

OR El RP determines ruptured SIG by frisking the cation columns in the CT lab.

OR El The following EMF trip I lights

- LIT:

BOP El 1EMF-26 (Steamline 1A)

El 1EMF-27 (Steamline 1B)

El 1EMF-28 (Steamline 1C)

El 1EMF-29 (Steamline ID).

OR El IF S/G Sampling is required to identify ruptured SIG(s), THEN:

a. Ensure the following signals

- RESET:

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 29 of 37

Appendix D Required Operator Actions Form ES-D-2 I

NRC Scenario #

Op Test No.:

3 Event #

6, 7 and 8 Page 30 of 37 Event

Description:

SIG 1 D Tube Rupture with a stuck open SIG 1 D PORV. Phase A fails to actuate Automatically.

Time Position Applicants Actions or Behavior

1) Phase A Containment Isolations.

2) CA System valve control.

3) KC NC NI NM St signals.

b. Align all S/Gs for Chemistry sampling.

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

P0

3. Verify at least one intact SIG - AVAILABLE FOR NC SYSTEM

COOLDOWN.

4. Isolate steam flow from ruptured SIG(s) as follows:

a. Verify all ruptured S/G(s) PORV - CLOSED.

b. Verify SIG(s) 1 B and IC

- INTACT.

c. Isolate blowdown and steam drain on all ruptured SIG(s) as follows:

RD LIS/G1D:

1) Close I SM-74B (SIG 1 D OtIt Hdr Bldwn CN).

2) Verify the following blowdown isolation valves - CLOSED:

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

b) 1BB-147B (SIG ID BldwnCont Isol Byp).

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

5. Close the following valves on all ruptured S1G(s):

RD LIMSIV LI MSIV bypass valve.

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

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

ACC).

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

RD LIS!GID:

1) Close ICA-42B (CA Pmp B Disch To SIG ID Isol).

2) Close 1 CA-38A (CA Pmp I Disch To S/G ID Isol).

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

(29% ACC), THEN perform Step 6.

Appendix D Catawba NRC Exam Dec2010 Page 30 of 37 NUREG 1021 Revision 9

I Appendix D Required Operator Actions Form ES-D-2 1 Appendix D Catawba NRC Exam Dec 2010 Page 31 of 37 NUREG 1021 Revision 9 Op Test No.:

NRC Scenario #

3 Event #

6, 7 and 8 Page 31 of 37 Event

Description:

SIG 1 D Tube Rupture with a stuck open SIG 1 D PORV. Phase A fails to actuate Automatically.

Time Position Applicants Actions or Behavior BOP

7. Verify at least one NC pump - ON.

8. WHEN P-Il PZR Sil BLOCK PERMISSIVE status light (IS!

18) is lit, THEN:

a. Depress ECCS steam pressure BLOCK pushbuttons.

b. Verify main steam isolation blocked status lights (ISI-13) -UT.

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

El Pzr spray OR El Pzr PORV.

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

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

9. Initiate NC System cooldown as follows:

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

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

NOTE TO EVALUATOR: Thé.SRO and BOP will Use the table in step 9 to determine target core exit temperature.

c. Ensure ruptured SIG(s) isolated as follows:

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

CLOSED:

RO El MSIV El MSIV bypass valves.

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

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

Appendix D Required Operator Actions Form ES-D-2

d. Verify the condenser is available as follows:

[ C-9COND AVAILABLE FOR STM DUMP status light (1SI-18)

- LIT L MSIV on intact SIGs)

- OPEN.

e. Verify steam dumps - IN PRESSURE MODE.

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

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

h. Verify main steam isolation blocked status lights (151-i 3)

LIT.

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

10. Control intact SIG 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 NIR levels between 16% (29% ACC) and 50%.

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

a. Power to all Pzr PORV isolation valves

- AVAILABLE.

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 BOP while in this procedure, THEN perform the following:

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

2) IF Pzr PORV cannot be closed OR isolated, THEN GO TO EP/1/N5000/ECA-3.1 (SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired).

Appendix D Catawba NRC Exam Dec 2010 Page 32 of 37 NUREG 1021 Revision 9 Op Test No.:

Position NRC Scenario #

3 Event #

6, 7 and 8 Page 32 of 37 Event

Description:

SIG 1 D Tube Rupture with a stuck open SIG 1 D PORV. Phase A fails to actuate Automatically.

Time Applicants Actions or Behavior

Lppendix D Required Operator Actions Form ES-D-2 I

Op Test No.:

NRC Scenario #

3

Event #

6, 7 and 8 Page 33 of 37 Event

Description:

SIG 1 D Tube Rupture with a stuck open S/G 1 D PORV. Phase A fails to actuate Automatically.

Time Position Applicants Actions or Behavior

12. Ensure SI!

- RESET:

j r a.

b. D/G load sequencers.

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

13. Ensure the following containment isolation signals - RESET:

BOP EIPhaseA LI Phase B.

14. Establish VI to containment as follows:

BOP LI Ensure 1VI-77B{Vl Cont Isol)

- OPEN.

LI Verify VI pressure -GREATER THAN 85 PSIG.

15. Verify criteria to stop operating ND pumps as follows:

a. At least one ND pump

- ON.

b. Verify ND pump(s) suction ALIGNED TO FWST.

c. NC pressure

- GREATER THAN 285 PSIG.

d. Stop 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.

16. Verify ruptured SIG(s)

- IDENTIFIED.

17. Verify if NC System cooldown should be stopped:

a. Verify core exit T/Cs

- LESS THAN REQUIRED RO TEMPERATURE.

b. Stabilize core exit T/Cs

- LESS THAN REQUIRED TEMPERATURE.

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

SRO 1 7.a RNO Do not continue in this procedure until core exit T/Cs are less than required temperature.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 33 of 37

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

NRC Scenario #

3 Event #

6, 7 and 8 Page 34 of 37 Event

Description:

SIG ID Tube Rupture with a stuck open SIG 1 D PORV. Phase A fails to actuate Automatically.

Time Position Applicants Actions or Behavior

18. Verify ruptured SIG(s) pressure is under operator-control as follows:

RD

a. All ruptured S/G(s) pressure

- STABLE OR INCREASING.

b. IF AT ANY TIME ruptured SIG(s) pressure is decreasing while in this procedure, THEN perform Step 18.

RD

19. Verify NC subcooling based on core exit TICs - GREATER THAN 20°F.

CRITICAL

20. Depressurize NC System using PZR Spray as follows:

TASK

a. Verify normal Pzr spray flow - AVAILABLE.

b. Verify Pzr level

- LESS THAN 76% (73% ACC)

-c. Depressurize NC System with maximum available spray.

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

El Spray valves are not effective in reducing NC pressure OR El Ruptured SIGs) NR level is approaching 83%.82%

THEN GO TO Step 21.

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

BOP El NC subcooling based on core exit T/Cs - LESS THAN 0°F OR El Pzr level GREATER THAN 76% (73% ACC)

OR El Both of the following:

El NC pressure

- LESS THAN RUPTURED S/G(s)

PRESSURE AND El Pzr level

- GREATER THAN 11% (20% ACC).

f. Close the following valve(s):

1) Pzr spray valves.

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

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 34 of 37

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

NRC Scenario #

3 Event #

6, 7 and 8 Page 35 of 37 Event

Description:

SIG 1 D Tube Rupture with a stuck open SIG 1 D PORV. Phase A fails to actuate Automatically.

Time Position Applicants Actions or Behavior

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

CAUTION S/I must be terminated when termination criteria are satisfied to prevent overfilling the ruptured SIG(s).

23. Verify SIl termination criteria as follows:

a. NC subcooling based on core exit T/cs

- GREATER THAN 0°F.

b. Verify secondary heat sink as follows:

LI N/R level in at [east one intact SIG -GREATER THAN RO/BOP 11%.(29% ACC)

OR LI Total feed flow available to S/G(s)

- GREATER THAN 450 GPM.

c. NC pressure

- STABLE OR INCREASING.

d. Pzr level - GREATER THAN 11% (20% ACC).

24. Stop S/I pumps as follows:

a. Stop NI pumps.

b. Ensure only one NV pump

- ON.

25. Isolate NV SIl flowpath as follows:

a. Verify the following valves

- OPEN:

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

LI INV-253B (NV Pumps Suct From FWST).

b. Ensure the following valves

- OPEN:

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

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

c. Close the following valves:

LI INI-9A (NV Pmp C/L Inj Iso!)

LI 1NI-IOB (NV PmpC/L lnj Isol).

END OF EVENTS 6AND 7.

END OF SCENARIO.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 35 of 37

Catawba Nuclear Station NRC Exam December 2010 ATTACHMENT 1 CREWCR1T1CALTAS.K

SUMMARY

SAT UNSAT CT#

CRITICAL TASK C-I Close containment isolation valves such that at least one valve is closed on each critical phase-A penetration before the end of the scenario.

C-2 Depressurize the RCS to meet SI termination criteria before SIG 1 D reaches 92% narrow range level.

Comments:

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 36 of 37

ATTACHMENT 2

SHIFTTURNOVER iNFORMATION Unit I Status Power Level Power History I

NCS Boron Xenon 50%

BOL 1412 PPM per OAC Controlling Procedure OP/1/A/61 00/003 (Controlling Procedure for Unit Operation), Enclosure 4.1 (Power Increase). The steps through step 3.41 are complete.

Other Information Needed to Assume the Shift 1A LH pump is tagged out to repair a leak on the motor cooler.

Maintenance estimates that repairs will take 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to complete.

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

NLOs Available Six NLOs are available as listed on the status board flETEOROLOGlCAL CONlTlQNS Upper wind direction 315 degrees, speed = 10mph 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 December 2010 HLP NRC EXAM SCENARIO #4 Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 1 of 37

Catawba Nuclear Station NRC Exam December 2010 Facility:

Catawba NRC Exam 2010 Scenario No.: Spare Op Test No.:

Examiners Operators:

SRO RO BOP Initial Conditions:

IC#144; Unit 1 is at 10-8 amps taking critical data during startup. 1A LH pump is tagged out.

Turnover:

1A LH pump is tagged out to repair a leak on the motor cooler. Maintenance estimates that repairs will take 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to complete. Direction for the crew is to increase reactor power to 10%.

Event Maif. No.

Event Event No.

Type*

Description 1

N-BOP NSRO Increase reactor power to 10%.

R-RO 2

C-BOP RNO59D 2A RN pump trips.

TS-SRO 3

1-RO ENBOO9B Intermediate range NI N-36 high voltage failure.

TS-SRO 4

SG098199 1-RO W/R SIG 1 C level failure.

I-SRO P0O3A CBOP Reactor Coolant pump 1A Hi/Hi vibration requiring reactor trip and pump C-SRO trip 6

NCO13A M-ALL Large Break LOCA on A loop.

7 ISEOO6NB C-RO Main Steam Isolation failure.

8 C-RO NDO14/15 CSRO IA and lB ND pumps trip causing a loss of emergency-coolant recirc.

9 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent,

{M)ajor Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page2of37

Catawba Nuclear Station NRC Exam December 2010 Scenario I

- Summary Initial Condition Unit 1 is at 10-8 amps taking critical data during startup.

1A LH pump is tagged out.

Turnover:

1A LH pump is tagged out to repair a leak on the motorcooler. Maintenance estimates that repairs will take 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to complete. Direction for the crew is to increase reactor power to 10%.

Event I BOP performs an NC system dilution to offset Xenon buildup. RO withdraws control rods to establish a positive startup rate to increase reactor power.

Event 2 2A RN pump trips. Crew will enter AP/0/A/5500/020 (Loss of Nuclear Service Water) to address this issue. TS evaluation by SRO is required.

Event 3 Intermediate range nuclear instrument N-36 experiences a high voltage failure. Crew will enter AP/11A155001016 (Malfunction of Nuclear Instrumentation System) Case 3 to remove this channel from service. TS evaluation by SRO is required.

Event4 2 of 3 W/R SIG level channels on IC S/G begin to slowly fail to 40% level. This will cause the feedwater regulating bypass valve to slowly open up to maintain S/G level. This will cause an increase in actual level, and will require the RO to take manual control of the bypass valve to decrease SIG level back to program level. Crew will enter AP/1/A15500/006 (Loss of SIG Feedwater) to address this issue.

Event 5 Reactor coolant pump 1A vibration begins to increase to 30 mils on the shaft. This is above the trip criteria for the pump and will require the crew to trip the reactor and trip the reactor coolant pump.

Event 6 As soon as the IA reactor coolant pump is secured a large break LOCA occurs on A loop. Crew will enter E-0 (Reactor Trip or Safety Injection), make a transition to E-i (Loss of Reactor or Secondary Coolant), and when FWST level decreases to 37% will transition to ES-i.3 (Transfer to Cold Leg Recirculation).

Event 7 Automatic Main Steam Isolation trains A and B fails to actuate on containment pressure> 3 psig. This will require manual initiation by the RO.

Event 8 At 45% FWST level, 1A ND pump will trip. When FWST level decreases to 37% (transfer to cold leg recirc setpoint), 1 B ND pump trips. This will require the crew to transition from ES-i.3 to ECA-I.1 (Loss of Emergency Coolant Recirc) to address this issue.

Critical task I Trip all reactor coolant pumps on a loss of subcooling per E-O End. I guidance within 5 minutes of criteria being met.

Critical task 2 Makeup to the FWST and minimize FWST outflow.

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 3 of 37

Catawba Nuclear Station NRC Exam December 2010 EXERCISE GUIDE WORKSHEET I

INITIAL CONDITIONS:

1.1 Reset to IC 141 START TIME:

Jn.strLictorActión Delay Ramp..

Delté Event In MAL-NIOO4A (ESS HDR ISOL VLV N19 ACTIV FAILS TO OPEN)

E ANN-ADII-E03 (TRANSFORMER B ON TROUBLE)

MAL-ISE0O6B (AUTO SM ISOL SIGNAL Bl..OCK TRN B)

MAL-ISEOO6A (AUTO SM ISOL SIGNAL BLOCK TRNA)

ANN-ADII-B03 (TRANSFORMER A ON TROUBLE)

OVR-RN59D (RN PMP 2A PB (UNIT 2)

ON OFF PB)

I LOA -NDOI4 (RACKOUT ND PMP IA)

RACK-10 LOA-NDOI5 (RACKOUT ND PMP IB)

RACK-11 XMT-SG098 (XCF_5631 S!G C WIR LVL CH I TO DCSIELSEWHERE 40 120 210 3

(CFAA563I))

MAL-ENBOO9B (LOSS OF hR CH 36 HI 3

VOLT)

XMT-SG099 (XCF_5632 SIG C WIR LVL CH 2 TO DCSIELSEWHERE 40 120 210 3

(CFAA5632))

MAL-NCPOO3A (NCP A VIBRATION) 30 180 7

MAL-NCOI3A (NC COLD LEG A LEAK) 27.5 9

LOA-CNTOO2 H2 ANALYZERS BOTH 13 Ensure EVENT 9 = XIOII5IF Ensure EVENT 10 = Ifw_5000 < 42 Ensure EVENT 11 = Ifw_5000 < 36.5 L...J..... Place_a_red_collar on_IA_LH_pump.

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page4of37

Catawba Nuclear Station NRC Exam December 2010 2

SIMULATOR BRIEFING 2.1 Control Room Assignments:

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

3 EXERCISE PRESENTATION 3.1 Familiarization Period 3.2 Allow examinees time to familiarize themselves with Control Board alignments.

3.3 Scenario EVENT 1, Increase reactor power to 10%.

3.4 Scenario EVENT 2, 2A RN pump trips.

BOOT! INSTRUCTOR ACTlON WHEN directed by the lead examiner, THEN INSERT EVENT I to trip 2A RN pump.

VI IF an NED is dispatched to investigate the loss of 2A RN pump repeat the order.

a BOOTH INSTRUCTOR ACTION I

1 IF an NED is dispatched to check out the RN pump that was started wait 3 minutes and report the pump is running normally.

BOOTINSTRUCTORAC.TION BOOTH INSTRUcIOR ACTION IF asked what the flows on the unit 2 RN pumps are refer to the XtremeView RN graphic.

BOOTH INSTRUCTOR ACTION IF the SWM is called to investigate the loss of the 2A RN pump repeat the order.

Appendix D Catawba NRC Exam December2010 Page5of37 NUREG 1021 Revision 9

Catawba Nuclear Station NRC Exam December 2010

BOOTH INSTRUCTORACTION IF environmental chemistry is called for RN pump shift repeat back the information.

3.5 Scenario EVENT 3, Loss of N-36 high voltage and failure of SIG C W/R level to DCS.

..BOOThINSTRUCTOACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR EVENT 3 to fail N-36 high voltage and fail SIG C W/R level.

I I

v BOOTH 1NSTRUCTORACTION WHEN the reactor group engineer is notified of the occurrence repeat back the information.

1/

BOOTHINSTRUCTORACTION IF the SWM is called to investigate the reason for the loss of N-36 repeat back the information.

3.6 Scenario EVENT 4, W/R S/G 1 C level failure.

I: j BOOTH:lNSRUCTORACTION r

I NOTE: SCENARIO EVENT 4 was activated by SIMULATOR EVENT 3.

H; BOOTHINSTRUCTORACTION IF the SWM is called to investigate the failure of the 1 C SIG W/R level channels repeat back the orders.

3.7 Scenario EVENT 5, NCP 1A Hi-Hi vibration..

I BbOT iNsTRucToRAcTION.:

WHEN directed by the lead examiner, THEN INSERT SIMULATOR EVENT 7 to cause a Hi Hi vibration on NCP IA.

3.8 Scenario EVENT 6, and 7 will activate when the IA NCP OFF PB is depressed. This will cause a LOCA and SM isolation failure.

Appendix D Catawba NRC Exam December 2010 Page6of37 NUREG 1021 Revision 9

Catawba Nuclear Station NRC Exam December 2010 BOOTHINSTRUCTOACTION WHEN dispatched to secure all ice condenser air handling units and place the H2 analyzers in service, repeat the order. ACTIVATE EVENT 13 (LOA-CNTOO2 H2 ANALYZERS).

AFTER 5 minutes call and report that the ice condenser AHUs are secured and the H2 analyzers are in service.

3.9 Scenario EVENT 8, both ND pumps trip will be automatically initiated by SIMULATOR EVENTS 10 and 11.

8OOTHINSTRUCTORACTIO[

WHEN an operator and maintenance are dispatched to determine and correct the cause o the ND pump failure repeat back the request. No reason for the trip will be given.

-*r zBOOTHINSTRUCTORAT1ON WHEN an operator is dispatched to initiate makeup to the FWST repeat back the order.

BOOTHINSTRUCTOR.ACTiON WHEN station management is notified to monitor shutdown margin repeat back the order.

WHEN periodic NC boron samples are requested repeat back the request.

Appendix D Catawba NRC Exam December 2010 Page 7 of 37 NUREG 1021 Revision 9

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

NRC Scenario #

Spare Event #

I Page 8

of 37 Event

Description:

Increase reactor power to 10%.

Time Position Applicants Actions or Behavior 2.167 WHEN reactor power has been stabilized at 10-8 amps, RO ensure at least one power range channel is selected on 1.ENCR5000 (Startup, Intermediate, & Power Range Nis).

2.168 Ensure Steps 2.139 -2.141 have been completed to ensure automatic steam dump control has been established.

NOTE: 1. Control rod withdrawal shall NOT exceed the temporary rod withdrawal limits specified in Unit One R.O.D. Section 2.3.

2. Refer to Unit One R.O.D. Section 2.4 for the rate at which reactor powercan be changed.

3. The throttling of a SIG bypass reg valve affects the other SIG bypass reg valves. Therefore, SM/CF tiP needs to be monitored as the unit approaches POAH.

CREW

4. If NC boron concentration is greater than 1000 ppmB, T-AVG control may be very sensitive above the POAH due to a positive MTC. Refer to Unit One R.O.D. Section 5.10 for the MTC at the currentconditions.

5. When approaching the beginning of the Power Range NI indication (.1% on the PR), a startup rate of < 0.2 dpm is required.

The <.2 dpm rate shall NOT be exceeded, except when performing PT/0/A/4150/001 J (Zero Power Physics Testing), until the turbine is placed on line. (SOMP 0 1-02). (R.M.)

RO 2.169 Increase reactor power to 1%. (R.M.)

2.170 Begin reviewing the items listed in Step 2.178 so that Unit 1 CREW will NOT enter Mode I until all substeps of 2.178 are signed off.

RO 2.171 IF necessary, continue heatup to no load T-AVG (557°F).

BOP 2.172 Increase SIG blowdown flowrate as recommended by Secondary_Chemistry_for SIG chemist 2.173 WHILE increasing reactor power coordinate with Chemistry to CREW determine when blowdown flowrate can be subsequently reduced.

CREW j Crew will begin increasing power to 1%, then to 100%.

I I

NOTE TO EVALUATOR: The following actions are taken from OPIIIA!610ó1001, Controlling Procedure for tJnitStartup. The crew will start at step 2.167.

Appendix D Catawba NRC Exam December 2010 Page 8of37 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 OpTestNo.:

NRC Scenario #

Spare Event #

1 Page 9

of 37 Event

Description:

Increase reactor power to 10%.

Time Position Applicants Actions or Behavior 2.174 Verify SIG(s) reverse purge flow by performing the following:

2.174.1 Record the temperature for the following OAC points:

OAC Group Display GD OPCFTEMP)

C1AO141 (SIG A AfterCF Isol Vlv Line Temp)

C1A0148 (S/G A Inlet Temp (Feedwater))

C1A0125(SIG B After CF Isol VIv Line Temp)

C1A0154 (SIG B Inlet Temp (Feedwater))

C1A0275(SIGC AfterCF Isol VIv Line Temp)

CIAO16O {S/G C Inlet Temp Feedwater))

C1AO815SIG D After CF Isol Vlv Line Temp)

Cl A0166 (SIG D In let Temp (Feedwater))

2.1 74.2 Compare the values recorded above to the values recorded in steps 2.79.15.7, 2.102.1, 2.116.1, 2.124.1 and 2.143.1 to verify reverse purge (increasing temperature).

2.174.3 IF no sign of reverse purge, determine what is causing the loss of reverse purge and correct the problem.

2.174.4 Monitor OAC Group Display OPCFTEMP for increasing temperatures as a sign of reverse purge while continuing_with the_procedure.

NOTE TOEVALUATOR: Step 2.175 and 176 will be N!Ad. IA CFPT is in servicein AUTO 2.177 WHEN the CF bypass valves are approximately 40% open, unisolate the CF reg valves by opening the following valves:

SIG IA ICF-29 (SIG IA CF C/V OUt Isol)

I CF-27 (SIG IA CF C/V mit Isol)

S/G 1 B ICF-38 (SIG I B CF C/V Otit isol)

ICF-36(S/G IBCF C/V mit Isoi)

SIG IC 1CF-47 (SIG 1C CF C/V Otit Isol)

ICF-45 (SIG 1C CF C/V mit Isoi)

S/G I D 1CF-56 (S/G 1D CF C/V Otit Isol)

ICF-54{SIG ID CF C/V mit Isoi)

BOP BOP Appendix D 2.178 Prior to entering Mode 1, do the following:

Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 9of37

I Appendix D Required Operator Actions Form ES-L5j Op Test No.:

NRC Scenario #

Spare Event #

1 Page 10 of 37 Event

Description:

Increase reactor power to 10%.

Time j

Position Applicants Actions or Behavior NOTE: Appropriate Chemistry Supervisor shall confirm any administrative holds preventing a power increase.

2.178.I Ensure PT/I /A/4700/002 (Periodic Test Performance Verification For Modechange) Premode I PT Checklist is completed.

2.178.2 Verify with Primary Chemistry that NC System H2 concentration and Dose Equivalent Iodine are in spec to allowentry into Mode 1.

Person notified 2178.3 Verify the PCMC data base has been reviewed for items required for Mode 1 entry.

2.1 78.4 Review the OAC points that will be in alarm in Mode 1 by using the OAC Plant Mode application to perform an alarm look ahead.

2.178.5 Ensure the CF temperatures between each feedwater isolation valve and S/G is greater than 107°F: (OACGroup DisplayGD OPOFTEMP)

SIG 1A:

C1AO141 (SIG A After CF iso! Vlv Line Temp)

C1A0148 (SIG A Inlet Temp. (Feedwater))

S/G IB:

C1A0125 (SIG B AfterCF [so! Vlv Line Temp)

C1A0154 (S/G B Inlet Temp. (Feedwater))

SIG 1C:

C1A0275 (S/G C After CF iso! Vlv Line Temp)

CIAOI6O (SIG C Inlet Temp. {Feedwater))

SIG ID:

01A0815 (S/G D After CF iso! VIv Line Temp)

Cl AOl 66 {SIG D Inlet Temp. (Feedwater))

BOP 2.179 Prior to entering Mode 1, perform the following to ensure the primary to secondary leakage program inputs are current:

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 10 of 37

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

NRC Scenario Spare Event #

1 Page 11 of 37 Event

Description:

Increase reactor power to 10%.

Time Position L

Applicants Actions or Behavior Notify RP to ensure EMF-33 background counts in the EMF

33 Background

Spreadsheet is current.

Person Notified____________________

Notify Primary Chemistry to ensure the NC Xenon Equivalent in the Chemistry Database is current.

Person Notified____________________

lecord current air ejector off gas flowrate.

Update EMF33 Prim/Sec Leakage program on the Unit 1 OAC.

2.180 Record Mode 1 entry time below:

SRO Mode 1 END OF EVENT I Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 11 of 37

Appendix D Required Operator Actions Form ES-D-2 I

Op Test No.:

NRC Scenario #

Spare Event #

2 Page 12 of 37 Event

Description:

2A RN pump trips.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The booth operator may begin event 2 when directed by the lead evaluator.

INDICATIONS: IAD12, A2 RN ESSENTIAL HDR A PRESSURE LO 1AD12, A5 RN ESSENTIAL HDR B PRESSURE - LO BOP Recognize the loss of 2A RN pump.

CREW Crew enter APIO/55001020, Loss of Nucleac Service Water NOTE TO EVALUATOR: The following actions aretaken from.AP1015501020, Loss of Nuclear Service Water, Case I.

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

2. Ensure Unit I and Unit 2 OATC monitors Enclosure I Rt:W (Foldout Page).

3. Verify RN System

- IN NORMAL DUAL SUPPLY HEADER ALIGNMENT.

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

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

6. Ensure RN pumps

- IN OPERATION AS NEEDED.

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

a. Verify RN

- ALIGNED TO IN SERVICE KG HX(S).

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

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

9. Verify RN

- AVAILABLE TO ALL UNIT I AND UNIT 2 DIG(S).

10. Determine VCIYC status as follows:

BOP Verify VCIYC

- ALIGNED TO OPERATING RN TRAIN.

0 Verify YC Chiller - RUNNING.

CREW

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

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 12 of 37

Appendix D Required Operator Actions Form ES-D-2 I

Op Test No.:

NRC Scenario Spare Event#

2 Page 13 of 37 Event

Description:

2A RN pump trips.

Position Applicants Actions or Behavior Time

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

LI SLC 16.7-6 (RN Discharge Instrumentation)

LI 3.6.5 (Containment Air Temperature)

LI 3.6.6 (Containment Spray System)

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

SRO LI 3.7.5 (Auxiliary Feedwater (AFW) System)

LI 3.7.7 (Component Cooling Water (CCW) System)

LI 3.7.8 (Nuclear Service Water System (NSWS))

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

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

LI 3.8.1 (A.C. Sources

- Operating)

LI 3.8.2 (A.C. Sources

- Shutdown).

NOTE TO EVALUATOR: SRO should determine that entry into T.S. 3.7.8 is applicable.

13. Determine required notifications:

SRO LI REFER TO RPIO/AJ5000IOO1 (Classification Of Emergency)

LI REFER TO RPIOIBI5000IO1 3 (NRC Notification Requirements)

NOTE TO EVALUATOR: SRO should determine that no notifications are required.

BOp

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

CREW

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

END OF EVENT2 Appendix D Catawba NRC Exam December 2010 Page 13 of 37 NUREG 1021 Revision 9

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

NRC Scenario #

2 Event #

3 Page 14 of 37 Event

Description:

Intermediate Range NI N-36 high voltage failure.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The booth operator may begin event 3 when directed by the lead evaluator.

INDICATIONS: 1AD2, Cl hR HI VOLTAGE FAILURE N-36 lNDlCATIONFAILSTO 10-11 AMPS.

RO RO recognize failure of N-36 SRO CREW ENTERS AP111A15500116, CASE 3

-1 NOTE TO EVALUATOR: The following actions are taken from AP1015500!016, Malfunction of Nuclear InstrumeAtation System, Case 3.

1. Verify reactor power - GREATER THAN 10%.

1. RNO Stop any power increase.

2. Verify IAD-2, C13 hR HI FLUX LEVEL ROD STOP - DARK.

3. Identify affected hR channel:

Li N-35 OR Li N-36.

4. Verify affected hR channel CONTROL POWER ON light - LIT NOTE 1AD-2, CI4 Nil SYS SIR & hR TRIP BYPASS will actuate in the following step.

5. At the affected hR drawer, perform the following:

a. Place the LEVEL TRIP switch for affected channel in BYPASS.

b. Verify the LEVEL TRIP BYPASS light on the affected hR drawer - LIT.

6. Verify the affected hR channel trip bypass status light (ISI

19) - LIT.

7. Verify IAD-2, C14 Nil SYS S/R & hR TRIP BYPASS - LIT.

8. Ensure operable hR channel selected to record on NIS RECORDER.

9. WHEN the operable hR channel is less than 10-10 Amps, Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 14 of 37

Appendix D Required Operator Actions Form ES-D-2

10. Determine and correct cause of hR malfunction.

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

12. Determine required notifications:

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

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

13. Notify Reactor Group Engineer of occurrence.

CAUTION Installing hR fuses with any P/R channel inoperable or in a tripped condition, may result in a reactor trip on PIR rate trip due to voltage spikes.

14. WHEN the affected hR channel is repaired, THEN ensure IAE returns the channel to service.

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

Op Test No.:

NRC Scenario #

2 Event #

3 Page 15 of 37 Event

Description:

Intermediate Range NI N-36 high voltage failure.

Time II Position Applicants Actions or Behavior I

THEN ensure SIR channels are reset.

NOTE TO EVALUATOR: The SRO should determine that tS. Table 3.3.1 item 4 is applicable and apply Actions F, G.

NOTE TO EVALUATOR: No notifications arerequiredat this time.

END OF EVENT3 Appendix D Catawba NRC Exam December 2010 Page 15 of 37 NUREG 1021 Revision 9

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

NRC Scenario #

Spare Event #

4 Page 16 of 37 Event

Description:

W/R SIG 1 C level failure Time j

Position Applicants Actions or Behavior NOTE TO EVAIJJATOR: The booth operator may begin event 4 when directed by the lead evaluator.

INDICATIONS: 1C Level Channels 1 and 2 slowly fail to 40%.

SIG 1CFRVB begins to open.

SIG 1C Level begins to increase.

1AD4, E5, CFCV ISOL VLVS CLSD RO Recognize the failure of SIG 1C level channels RO Take manual control of the 1 C FRV and FRVB and control SIG level at normal level.

NOTE TO EVALUATOR: The following actions are taken from AP111A155001006, Loss of SIG Feedwater,, Case 4 CF Control Not in Auto.

1. IF AT ANY TIME SIG levels approaching:

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

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

THEN:

a. Manually trip reactor.

b. GO TO EP/1/A/5000/E

2. Verify the following:

LI At least one CF pump

- IN SERVICE LI 1AD-3, C16 CF ISOL TRN A - DARK LI 1AD-3, D16 CF ISOL TRN B

- DARK

3. IF AT ANY TIME any CF Main Feed Reg valve in manual, THEN ensure associated Main Feed Reg Bypass valve in manual.

4. Verify CF pump speed controller for in service CF pump(s):

LI IN AUTO LI RESPONDING ADEQUATELY.

5. Verify all SIG CF control valves:

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 16 of 37

Appendix D Required Operator Actions Form ES-D-2 OpTestNo.:

NRC Scenario#

Spare Event#

4 Page 17 of 37 Event

Description:

W/R S/G 1C level failure Time Position Applicants Actions or Behavior END OF EVENT 4.

D IN AUTO Li RESPONDING ADEQUATELY.

5. RNO a. Ensure affected controller(s)

IN MANUAL.

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

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

6. Verify the following:

S/C level(s)

STABLE SIG level(s)

- APPROXIMATELY AT PROGRAM Malfunction

- CORRECTED.

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

b. WHEN all the following conditions met:

SIG level(s)

- STABLE SIG level(s) - APPROXIMATELY AT PROGRAM Malfunction

- CORRECTED.

THEN GO TO Step 7.

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

Appendix D Catawba NRC Exam December2010 Page 17 of 37 NUREG 1021 Revision 9

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

NRC Scenario #

Spare Event #

5 Page 18 of 37 Event

Description:

ReactorCoolant Pump 1A Hi/Hi vibration requiring reactor trip and pump trip.

Time I

Position Applicants Actions or Behavior NOTE TO EVALUATOR: The booth operator may begin event5 when directed by the lead evaluator.

Indications: 1AD6, A5 NCP HI VIBRATION 1AD6,C5 NCP VIBRATION MON TROUBLE IAD6, B5 NCP HI HI VIRATION BOP Identifies the affected pump as 1A RO Manually trip the reactor Manually trip the 1A NCP and ensure I NC-27 is closed.

NOTE TO EVALUATOR: The following actions are from the-Suppiementaiy Actions of ARP OPIIIB!6100!OIOG, Panel AD6.

1. Verify which pump has Hi-Hi vibration, from REACTOR COOLANT PMP VIBRATION MONITOR PNL (back of 1MC6).

2. Read all 4 vibration channels for the alarming pump and -compare readings to determine if a real vibration problem exists.

3. IF a valid frame or shaft vibration indication exists, then perform the following:

3.1 IF in Modes 1 0R2:

3.1.1 Trip reactor.

3.1.2 WHEN reactor power less than 5%, THEN trip the affected NC pump.

3.1.3 IF A OR B NCP is tripped, ensure that the spray valve associated with the pump is closed.

3.1.4 Go to EPII/A/50001E-O (Reactor Trip or Safety Injection).

END OFEVENT 5.

Appendix D Catawba NRC Exam December 2010 NUR-EG 1021 Revision 9 Page 18 of 37

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

NRC Scenario #

Spare Event #

6, 7 and 8 Page 19 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergency recirc capability.

Time Position J Applicants Actions or Behavior NOTE TO EVALUATOR: EVENT 6,7 and 8wiIl begin when the IA NCP OFF pushbutton is depressed.

INDICATIONS:

NC pressure rapidly decreases to 0 psig.

Containment pressure increases rapidly.

Safety Injection actuates.

RO/BOP Perform E-0 immediate actions.

SRO Enter E-0.

NOTE TO EVALUATOR: The following actions are from EPIIIAI500JE-O.

CREW

1. Monitor Enclosure I (Foldout Page).

2. Verify Reactor Trip: (Immediate action step)

D All rod bottom lights LIT RO u All reactor trip and bypass breakers OPEN hR amps

- DECREASING.

3. Verify Turbine Trip: (Immediate action step) u All turbine stop valves

- CLOSED BOP

4. Verify IETA and IETB - ENERGIZED. (Immediate action step)

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

a. SAFETY INJECTION ACTUATED status light (I SI-I 3)

- LIT.

b. Both EIS load sequencer actuated status lights (ISI-14)

- LIT.

NOtE TO EVALUATOR:The following actions are from EPJI/AI5000IE-O, Enclosure I. The crew should tripali NCPs when subcooling is lost and I/As are complete.

2. NC Pump Trip Criteria:

LI IF the following conditions are satisfied, THEN trip all NC CRITICAL pumps while maintaining seal injection flow:

STEP LI At least one NV or NI pump - ON LI NC subcooling based on core exit T/Cs - LESS THAN OR EQUAL TO 0°F.

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 19 of 37

I Appendix D Required Operator Actions Form ES-D-2 NOTE TO EVALUATOR: The following actions are from EPII 1A!5OOOIE-O RO

6. Announce Unit I Safety Injection.

7. Determine required notifications:

SRO L REFER TO RPIO/A/50001001 (Classification Of Emergency)

REFER TO RP/OIB/50001013 (NRC Notification Requirements).

8. Verify all Feedwater Isolation status lights (ISI-5) - LIT.

9. Verify Phase A Containment Isolation status as follows:

a. Phase A RESET lights

- DARK.

b. Monitor Light Panel Group 5 St lights

- LIT.

10. Verify proper Phase B actuation as follows:

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

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

11. Verify proper CA pump status as follows:

a. Motor driven CA pumps - ON.

b. 3 S/G N/R levels

- GREATER THAN 11%.

12. Verify all of the following Sf1 pumps - ON:

NV pumps BOP Li ND pumps Li NI pumps.

13. Verify all KC pumps - ON.

14. Verify all Unit I and Unit 2 RN pumps

- ON.

15. Verify proper ventilation systems operation as follows:

BOP Li REFER TO Enclosure 2 (Ventilation System Verification).

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

16. Verify all SfG pressures GREATER THAN 775 PSIG.

Op Test No.:

Time Position NRC Scenario #

Spare Event #

6, 7 and 8 Page 20 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergy recirc capability.

Applicants Actions or Behavior Appendix D Catawba NRC Exam December 2010 Page 20 of 37 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

Spare Event #

6, 7 and 8 Page 21 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergency recirc capability.

Applicants Actions or Behavior Op Test No.:

Time Position

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 - IND[CATINGFLOWTO C-LEGS.

18. Control S1G 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 1 1% 29%

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

19. Verify all CA isolation valves - OPEN.

20. Verify SIl equipment status based on monitor light panel - IN PROPER ALIGNMENT.

21. Control NC temperature. REFER TO Enclosure 4 (NC Temperature Control).

22. 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.

23. Verify NC subcooling based on core exit T/Cs

- GREATER THAN 0°F.

23. RNO IF any NV OR NI pump is on, THEN:

a. Ensure all NC pumps

- OFF.

b. Maintain seal injection flow.

24. Verify main steamlines are intact as follows:

RO u All SIG pressures

- STABLE OR INCREASING E ALL S/Gs

- PRESSURIZED.

Appendix D Catawba NRC Exam December2010 Page 21 of 37 NUREG 1021 Revision 9

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

NRC Scenario #

Spare Event #

6, 7 and 8 Page 22 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergency recirc capability.

Time Position Applicants Actions or Behavior

25. Verify SIG tubes are intact as follows:

Li Verify the following EMF trip I lights - DARK:

Li 1 EMF-33 (Condenser Air Ejector Exhaust)

Li 1EMF-26 (Steamline IA)

BOP Li 1EMF-27(Steamline 1B)

Li 1EMF-28.(Steamline IC)

Li 1EMF-29 (Steamline 1 D).

LI All SIG levels

- STABLE OR INCREASING IN A CONTROLLED MANNER.

26. Verify NC System is intact as follows:

a. Verify the following NC pump thermal barrier alarms - DARK:

Li 1AD-6, Eli, NCP A THERMAL BARRIER KC OUTLET HIILO FLOW Li 1AD-6, E/2, NCP B THERMAL BARRIER KC OUTLET HIILO FLOW BOP Li IAD-6, E13, NCP C THERMAL BARRIER KCOUTLET HIILO FLOW Li 1AD-6, E14, NCP D THERMAL BARRIER KC OUTLET HIILO FLOW.

b. Verify NC System is intact as follows:

Li Containment pressure - LESS THAN I PSIG.

26b RNO 1) Energize H2 igniters.

2) Dispatch operator to perform the following:

a) Secure all ice condenser air handling units. REFER TO Enclosure 13 Securing All Ice Condenser Air Handling Units).

BOP b) Place containment H2 analyzers in service.

REFER TO OPlilN645OlOIOContainment Hydrogen Control Systems).

3) IF both the following conditions exist:

Appendix D Catawba NRC Exam December 2010 Page 22 of 37 NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 I

Op Test No.:

NRC Scenario #

Spare Event #

6, 7 and 8 Page 23 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergency recirc capability.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: Step 26.b.3) will be NIAd.

26.b RNO

4) Concurrently:

El Implement EPI1 /N5000/F-0 (Critical Safety Function Status Trees).

El GO TO EP/1/A/5OO0/E1 (Loss Of Reactor Or Secondary Coolant).

NOTE TO EVALUATOR: The following actions are from EPi1IAI5OOOiEi (Loss of Reactor or Secondary Coolant).

CREW

1. Monitor Enclosure I (Foldout Page).

2. Verify main steamlines are intact as follows:

RO El AIIS/G pressures - STABLE OR l1CREASlNG El All S/Gs - PRESSURIZED.

3. Control intact SIG levels as follows:

a. Verify N/R level in all intact S/Gs

- GREATER THAN 11% (29%

RO ACC).

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

4. Verify secondary radiation is normal as follows:

a. Ensure the following signals - RESET:

1) Phase A Containment Isolations

2) CA System valve control

3) KC NC NI NM St signals.

b. Align all SIGs for Chemistry sampling.

c. Perform at least one of the following:

BOP El Notify Chemistry to sample all S/Gs for activity.

OR El Notify RP to frisk all.cation columns for activity.

d. Verify the following EMF trip 1 lights

- DARK:

El 1EMF-33 (Condenser Air Ejector Exhaust)

El IEMF-26 (Steamline IA)

El 1.EMF-27(Steamline IB)

El 1EMF-28 (Steamline 1C)

El 1 EMF-29 (Steamline 1 D).

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 23 of 37

I Appendix D Required Operator Actions Form ES-D-2 NRC Scenario #

Spare Event #

6, 7 and 8 Page 24 of 37

e. WHEN activity results are reported, THEN verify all SIGs indicate no activity.

5. 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, THEN, after Pzr pressure decreases to less than 2315 PSIG, ensure the valve closes or is isolated.

6. Verify S/I termination criteria as follows:

CREW

a. NC subcooling based on core exit TICs

- GREATER THAN 0°F.

SRO 6.a RNO GO TO Step 6.f.

6f. MonitorS/I termination criteria. REFER TO Enclosure 2 (S/I Termination Criteria).

CREW 6g.

IF AT ANY TIME S/I termination criteria is met while in this procedure, THEN RETURN TO Step 6.

7. Verify proper NS pump operation as follows:

a. At least one NS pump

- ON.

b. Verify the following valves

- OPEN:

BOP El IFW-27A (ND Pump 1A Suct From FWST)

El IFW-55B (ND Pump lB Suct From FWST).

c. Containment pressure - LESS THAN 2.4 PSIG.

7. d. Verify operating NS pump(s)

HAVE REMAINED RUNNING SINCE INITIAL PHASE B SIGNAL.

e. Ensure S/I

- RESET:

1) ECCS.

2) D/G load sequencers.

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

f. Reset NS.

g. Stop NS pumps.

h. Close the following valves:

El 1NS-29A (NSSpray Hdr 1A Cont Isol)

El INS-32A (NS Spray Hdr IA Cont Isol)

Appendix D Catawba NRC Exam December 2010 Page 24 of 37 NUREG 1021 Revision 9 Op Test No.:

Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergency recirc capability.

Time Position Applicants Actions or Behavior

I Appendix D Required Operator Actions Form ES-D-2 OpTestNo.:

Event

Description:

Large Break LOCA with a faiure of the Main Steam Isolation and loss of Emergency recirc capability.

Time Position I

Applicants Actions or Behavior NRC Scenario #

Spare Event #

6, 7 and 8 Page 25 of 37 LI 1 NS-1 5B NS Spray Hdr 1 B Cont Isol)

LI INS-12B (NS Spray Hdr lB Cont Isol).

8. Verify criteria to stop operating ND pumps as follows:

a. NC pressure GR-EATER THAN 285 PSIG.

SRO 8.a. RNO GO TO Step 10.

10. Verify conditions to stop operating DIGs as follows:

a. At least one DIG

- ON.

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

LI DIG 1A BKR TO ETA OPEN LI I ETA - ENERGIZED.

c. WHEN S/I is reset, THEN dispatch operator to stop 1A D/G and place in standby readiness. REFER TO OP/11A163501002 (Diesel Generator Operation).

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

[I D/G lB BKRTOETBOPEN LI IETB-ENERGIZED.

e. WHEN S/I is reset, THEN dispatch operator to stop I B D/G and place in standby readiness. REFER TO OP/I /A/6350/002

-(Diesel Generator Operation).

f. Ensure S/I

- RESET:

1) EC-CS.

2) D/G load sequencers.

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

Appendix D Catawba NRC Exam December 2010 Page 25 of 37 NUREG 1021 Revision 9

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

Spare Event #

6, 7 and 8 Page 26 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergency recirc capability.

Position Applicants Actions or Behavior Time H

NRC Scenario #

Catawba NRC Exam December2010 Page 26 of 37

11. Obtain containment H2 concentration as follows:

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

b. Verify containment H2 analyzers IN SERVICE BOP

c. Verify containment H2-concentration

- LESS THAN 6%.

d. Verifycontainment H2 concentration

- d. Dispatch operator to place H2 LESS THAN 0.5%.

e. WHEN the ice condenser air handling units are off AND H2 concentration is less than 6%, THEN energize the H2 igniters (1 MC-7).

12. Initiate evaluation of plant status as follows:

a. Verify S/I systems

- ALIGNED FOR INJECTION MODE.

b. Verify Cold Leg Recirc capability as follows:

1) At least one ND pump

- AVAILABLE.

2) Verify power to all of the following valves

- AVAILABLE:

LI tFW-27A (ND Pump IA Suct From FWST)

LI 1 NI-i 85A (ND Pump IA Cont Sump Suct)

LI 1ND-28A (ND Supply To NV & iA NI Pmps)

LI 1FW-55B (ND Pump lB Suct From FWST)

LI 1NI-i84B (ND Pump iBCont Sump Suct)

LI 1 N1-332A (NI Pump Suct X-Over From ND)

BOP LI iNI-333B (NI Pump Suctfrom ND)

LI 1NI-334B (NI PumpSuctX-Overfrom ND)

LI 1NI-136B (ND Supply To NI Pump 18).

3) Verify power to all of the following valves - AVAILABLE:

LI 1NI-i i5A (NI Pump IA Miniflow Isol)

LI iNI-i44A (NI Pump lB Miniflow Isol)

LI INI-147B (NI Pump Miniflow HdrTo FWST Isol).

4) Verify the ENABLE lights for the following switches

- LIT:

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

LI C-LEG RECIR FWST TO CONT SUMP SWAP TRN B.

Appendix D NUREG 1021 Revision 9

Appendix D Required Operator Actions Form ES-D-2 I

Op Test No.:

NRC Scenario #

Spare Event #

6, 7 and 8 Page 27 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergency reciro capability.

Time Position Applicants Actions or Behavior

c. Verify auxiliary building radiation is normal as follows:

LI EMF-41 (Aux Bldg Ventilation) trip I light DARK Li All area monitor EMF trip 1 lights

- DARK.

d. WHEN the TSC is activated AND staffed, THEN:

1) Notify the Reactor Engineer to assess core damage.

REFER TO RP/0/A/5000/015 (Core Damage Assessment).

2) Notify Chemistry to obtain current NC boron concentration.

3) WHEN ND is aligned for Cold Leg Recirc, THEN notify BOP/SRO Chemistry to obtain current containment sump boron concentration.

4) Notify Operating Engineer of the following:

a) VA is required to be aligned to normal AND filter mode within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the event.

b) Evaluate aligning VA to normal AND filter mode.

REFER TO 0P101N64501003 (Auxiliary Building Ventilation System).

e. Notify-station management to evaluate starting additional plant equipment to assist in recovery.

13. Verify NC System cooldown and depressurization is required BOP as follows:

a. NC pressure -GREATER THAN 285 PSI-G.

SRO/BOP 13.a RNO IF ND flow to C-Legs is greater than 675 -GPM, THEN GO TO Step 14.

14. Verify transfer to Cold Leg Recirc as follows:

a. FWST level - LESS THAN 37% (1AD-9, D18 FWST 2/4 LO LEVEL - LIT).

b. S/I systems

- ALIGNED FOR COLD LEG RECIRC.

- NOTE TO EVALUATOR; Depending an the speed of the crew, if FWST level has reached 37% prior to this step they wilIhavetransferred to ES-1.3. If not at 37%,-they will enter step 14.a RNO and loop back t step 11 untiIFWST is at 37%.

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 27 of 37

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

NRC Scenario #

Spare Event #

6, 7 and 8 Page 28 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emgçy recirc capability.

Time josition Applicants Actions or Behavior NOTE TO EVALUATOR: The following actions are from EPII!AI5000IES-1.3, Transfer to Cold Leg Recirculation CREW

1. Monitor Enclosure I (Foldout Page).

CAUTION Sil recirculation flow to NC System must be maintained at all times.

NOTE El Steps 2 through 8 should be performed without delay.

El CSF should not be implemented until directed by this procedure.

2. Verify at least one of the following annunciators - LIT:

El 1AD-20, B/3 CONT. SUMP LEVEL >3.3 ft BOP OR El IAD-21, B/3 CONT. SUMP LEVEL >3.3 ft SOP

3. Verify KC flow to ND heat exchangers - GREATER THAN 5000 GPM.

4. Ensure SIl - RESET:

a. EOCS.

b. DIG load sequencers.

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

5. Align S!I system for recirc as follows:

a. Verify following valves - OPEN:

BOP El iNl-185A (ND Pump lACont Sump Suct)

El 1 NI-i 84B (ND Pump 1 B Cont Sump Suct).

5. b. Verify following valves

- CLOSED:

El 1FW-27A (ND Pump IA SuctFromFWST)

BOP El IFW-55B (ND Pump I B Suct From FWST).

c. Verify ND pumps

- ON.

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 28 of 37

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

NRC Scenario #

Spare Event #

6, 7 and 8 Page 29 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergency recirc capability.

Time Position 1

Applicants Actions or Behavior f_____________

BOP CREW CREW BOP 5.c RNO c. Perform the following:

1) Start ND pump(s) with suction aligned to an open containment sump suction valve.

2) IF no ND pump can be started OR no ND train can be aligned for recirc, THEN:

a) IF a valid red OR orange path procedure is in effect, THEN RETURN TO procedure in effect.

b) GO TO EP/1/A/5000/ECA-1.1 Loss Of Emergency Coolant Recirculation).

NOTE TO EVALUATOR: At this step the crew will transition to ECA-ti, Loss of Emergency Coolant Recirculation.

NOTE TbEVALUATOR: The following actins are from ECA-1.1.

1. IF loss of Emergency Coolant Recirculation is due to sump blockage, THEN GO TO EP!1!AI5000IECA-1.3 (Containment Sump Blockage).

2. Monitor Enclosure I (Foldout Page).

3. Restore recirc capability as follows:

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

[1 ND pumps

[1 NV pumps El NI pumps.

3.a RNO If power is available to the affected essential bus(s),

THEN dispatch operator and maintenance to determine and correct cause of pump failure. REFER TO EM/1/A/5200/005 (Troubleshooting Cause For ND, NI, or NV Pump(s) Failing to Start).

Appendix D Catawba NRC Exam December 2010 Page 29 of 37 NUREG 1021 Revision 9

I Appendix D Required Operator Actions Form ES-D-2 I 3.b. Verify the following valves

- AVAILABLE TO BE OPERATED FROM THE CONTROL ROOM:

El INI-185A (ND Pump 1A ContSump Suct)

El 1NI-184B{ND Pump 1B-ContSump Suct).

c. Verify containment sump level adequate as follows:

El 1AD-20, B/2 CONT. SUMP LEVEL >2:5 ft

- LIT OR El 1AD-21, B12 CONT. SIJMP LEVEL >2.5 ft

- LIT BOP OR El All of the following:

El FWST level

- LESS THAN 8%

El NC temperature GREATER THAN 200°F El Containment Spray - PREVIOUSLY IN SERVICE El Indicated containment sump level

- GREATER THAN 0.5 FT.

d. Verify Cold Leg Recirc-capability

- RESTORED.

3.d RNO Perform the following:

1) Continue attempts to restore recirc capability as follows:

El Power restoration El Local valve operation El Obtain maintenance assistance as required. REFER TO EM/1/A15200/006 (Troubleshooting Cause ForEW, ND, NI, or NV Valves(s) Failing to Operate).

El Other actions as specified by station management.

2) WHEN emergency coolant recirc -capability is restored BOP during this procedure, THEN:

a) IF transfer to Cold Leg Recirc is required, THEN perform the following:

(1) Ensure the following valves

- OPEN:

El 1NS-29A (NS Spray Hdr lACont Isol)

El 1NS-32A{NS Spray Hdr lACont lsol)

El INS-15B (NS Spray Hdr lB Cont Isol)

El 1 NS-12B (NS Spray Hdr 1 B Cont Isol).

(2) GO TO EP/1/N5000/ES-1.3 (Transfer To Cold Leg Recirculation).

Op Test No.:

NRC Scenario #

Spare

-Event #

6, 7 and 8 Page 30 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergency recir-c capability.

Time Position Applicants Actions or Behavior Appendix D Catawba NRC Exam December2010 Page 30 of 37 NUREG 1021 Revision 9

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

NRC Scenario #

Spare Event #

6, 7 and 8 Page 31 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergency recirc capability.

Time Position Applicants Actions or Behavior b) RETURN TO procedure and step in effect.

3) GO TOStep 4.

4. Ensure S!l - RESET:

a. ECCS.

b. DiG load sequencers.

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

5. Depress the DEFEAT pushbuttons on the following switches:

BOP u C-LEG RECIR FWST TOCONT SUMP SWAP TRN A D C-LEG RECIR FWST TO CONT SUMP SWAP TRN B.

6. Verify adequate FWST level as follows:

a. FWST level

- GREATER THAN 5%.

b. IF AT ANY TIME FWST level is less than 5%, THEN GO TO Step 33.

7. Determine NS requirements as follows:

a. Verify following NS pump suction valves

- OPEN:

1 1 NS-20A (NS Pump 1A Suct From FWST)

BOP E INS-3B (NS Pump lB Suct From FWST).

b. Determine number of NS pumps required from the following table:

c. Verify the number of NS pumps on

- EQUAL TO NUMBER REQUIRED.

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

a. Any NS pump - ON.

SRO 8.a RNO GO TO Step 9.

9. Align NS spray valves as follows:

a. Verify NS Pump IA - ON.

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 31 of 37

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

NRC Scenario #

Spare Event #

6, 7 and 8 Page 32 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergency recirc capability.

Time Position Applicants Actions or Behavior 9.a RNO Perform the following:

1) Ensure NS Train A

- RESET.

2) Close the following valves:

El 1 NS-29A (NS Spray Hdr 1A Cont Isol)

LI 1 NS-32A (NS Spray Hdr IA Cont Isol).

BOP 9.b. Verify NS Pump lB

- ON.

9.b RNO Perform the following:

1) Ensure NS Train B

- RESET.

2) Close the following valves:

El 1 NS-15B {NS Spray Hdr 1 B Cont Isol)

El 1NS-12B (NS Spray Hdr lB Cont Isol).

c. IF AT ANY TIME NS pumps are stopped or started, THEN:

El Ensure associated NS Train

- RESET.

CREW El Close associated spray valves after securing a pump.

El Open associated spray valves prior to starting a pump.

CRITICAL BOP

10. Initiate makeup to FWST. REFER TO 0P111A16200!014 STEP (Refueling Water System).

11. Control intact SIG 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 SIG N/R levels between 11% (29% ACC) and 50%.

12. Monitor shutdown margin during cooldown as follows:

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

b. Request periodic NC boron samples from Primary Chemistry.

CREW

c. WHEN each NC boron sample obtained, THEN:

1) Perform shutdown margin calculation. REFER TO OPIOIN6 100/006 (Reactivity Balance Calculation).

2) Verify NC boron concentration

- GREATER THAN OR EQUAL TO REQUIRED BORON CONCENTRATION.

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 32 of 37

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

NRC Scenario #

Spare Event #

6, 7 and 8 Page 33 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergency recirc capability.

Time Position Applicants Actions or Behavior

13. WHEN P-Il PZR SIl BLOCK PERMISSIVE status light (ISI

18) is lit, THEN:

a. Depress ECCS steam pressure BLOCK pushbuttons.

b. Verify main steam isolation blocked status lights -(1>51-i 3)

LIT.

NOTE El After 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.

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

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

a. Verify C-9 COND AVAILABLE FOR STM DUMP status light (151-18)

- LIT.

b. Verify MSIVs on all intact SIGs - OPEN.

14.b.2 RNO

2) Reset Main Steam Isolation signal as follows:

a) Ensure manual loaders for all MSIV bypass valves ADJUSTED TO 0%.

b) Reset SM Isolation.

c) Reset SIG PORVs.

3) Place steam dumps in pressure mode as follows:

a) Place STM DUMP CTRL in manual.

b) Manually adjust the STM DUMP CTRL to 0% demand.

c) Place steam dumps in pressure mode.

4) Perform the following to equalize pressure across MSIVs on intact SIGs:

a) Open MSIV bypass valve on intact SIGs.

b) IF AT ANY TIME pressure does not equalize as required, THEN isolate steam loads off main steam header.

REFER TO Enclosure 8 (Equalizing Across MSIVs).

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

a) Open all MSIVs on intact SfGs.

b) Close all MSIV bypass valves.

c) Perform Steps 14.c through 14.e.

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 33 of 37

Appendix D Required Operator Actions Form ES-D-1 Op Test No.:

NRC Scenario #

Spare Event #

6, 7 and 8 Page 34 of 37 Event

Description:

Large Break LOCA with a failure of the Main Steam Isolation and loss of Emergency recirc capability.

Time J Position Applicants Actions or Behavior

[

6) GO TO Step 15.

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

d. Verify steam dumps

- IN PRESSURE MODE.

e. Dump steam to condenser while e. Perform the following:

maintaining cooTdown rate based on NC T-Colds as close as possible without exceeding 100°F in an hour.

15. Verify S/I aligned by one of the following:

El 1 NI-9A (NV Pmp CIL lnj Isol)

- OPEN OR El lNl-1OB{NV PmpC/L lnj lsol)-OPEN OR BOP El At least one ND pump on with suction aligned to either of the following:

El FWST OR El Containment sump.

OR El At least one NI pump

- ON.

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

a. Verify only one NV pump - ON.

16.a RNO Perform the following:

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

16. b. Verify only one NI pump

- ON.

16.b RNO Perform the following:

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

16.

C Verify NC pressure - LESS THAN 285 PSIG.