ML111540525

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

1NV-i8lA(B/A BlenderOtltToVCT)

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)

1 NV-i 81A (B/A Blender OtIt To VCT)

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 9of38

I Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 1 Page 10 of 38 Event

Description:

Power increase to 100% power.

Time Position 1 Applicants Actions or Behavior 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 previous concentration is acceptable AND the system was previously aligned per Enclosure 4.1 BOP (Automatic Makeup), perform the following:

3.17.2.1 Ensure the controller for INV-242A (RMWST To B/A Blender Ctrl) 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,)

END OF DILUTION NOTE TO EVALUATOR: The following steps are from 0P111B163001001, Turbine Generator, starting at step 212 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 Select ENTER or OK and verify LOAD RATE goes dark.

2.1.24 Select TARGET and verify it illuminates.

RO 2.1.2.5 Input the desired load target.

21.2.6 Select ENTER and verify TARGET goes dark.

2.1.2.7 Verify new load target appears on Target Display.

2.1.2.8 Select GO 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 TURB1NE PANEL Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 10 of 38

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 2 Page 11 of 38 Event

Description:

Pzr PORV 1 NC34A fails open.

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

Indications: 1AD6, E-1O PZR PORV DISCH HI TEMP 1AD6, F-8 PZR LO PRESS CONTROL 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.

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

NOTE TO EVALUATOR: An HVAC Trouble alarm will come in requiring the BOPto leave the horse shoe area NOTE TO EVALUATOR: The following steps are fromAPI1IN55OO1O1 1, Pressurizer Pressure Anomalies Case I (Pressurizer Pressure Oereasing).

RO 1. Verify all Pzr PORVs CLOSED.

1. RNO Perform the following:

RO a. Manually close Pzr PORV(s).

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

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

NOTE: Control rods may withdraw on decreasing NC pressure.

RO 2. Verify Pzr spray valve(s) CLOSED.

RO 3. Verify all Pzr heaters - ENERGIZED.

RO 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.

RO 5. Verify NC pressure STABLE OR INCREASING.

6. WHEN NC pressure is stable, THEN:

El Stabilize unit at appropriate power level.

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

LI Turbine load LI Control rods El Boron concentration.

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

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 11 of 38

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # I Event # 2 Page 12 of 38 Event

Description:

Pzr PORV 1 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 I and 2)

LI 3.4.5 (RCS Loops MODE 3)

LI 3.4.6 (RCS 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 determine entry into T,S. 3.4.11 action A.1 is required.

END OF EVENT2.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 12 of 38

Appendix D Required Operator Actions Form ES-D-Op Test No.: NRC Scenario # 1 Event # 3 Page 13 of 38 Event

Description:

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

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

Indications: KC B header cross connect valves go closed.

1AD7, D-3 NV PMP B OIL COOLER LO FLOW Crew enters AP/1/N5500/021, Loss of Component Cooling Recognize a failure of the KC level transmitter going to the KC CREW header cross-connect valves.

NOTE TO EVALUATOR: The following steps are from AP!11N55001021 , Loss of Component Cooling.

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

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

BOP 2. Verify at least one KC pump ON. -

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

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

4. Verify the following:

BOP El IAD-7, F13 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 BOP LIT, THEN perform Step 4 RNO.

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

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

NOTE TO EVALUATOR: The first KG pump started will not start. The 801 will start the second KC pump on B train.

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

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 13 of 38

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 3 Page 14 of 38 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:

Li 1AD-20, All KC SUPPLY HDR FLOW TO NCP BRGS LOW BOP -DARK Li 1AD-21, Ni KC SUPPLY HDR FLOW TO NCP BRGS LOW

- DARK.

9. Verify KC available as follows:

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

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

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

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

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

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

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

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

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

Li I KC-2B (Aux Bldg Non-Ess Ret Hdr Iso!).

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

9.b RNO NOTE The KC 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 level.

b. WHEN OAC alarm C1D2214 (KC Train B Low-Low Level Surge Tank Iso!) is NOT ACTUATED, THEN ensure the affected valve(s) are open.

10. Verify KC surge tank levels normal as follows:

BOP a. Verify both KC 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 38

Appendix D Required Operator Actions Form ES-D-2 I Op Test No.: NRC Scenario# 1 Event# 3 Page 15 of 38 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 I Applicants Actions or Behavior

14. Ensure KC heat exchanger outlet mode switches BOP -

PROPERLY ALIGNED.

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

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

LI SLC 169-7 (Boration Systems Flow Path Shutdown)

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

Li SLC 16.9-9 (Boration Systems Pumps Shutdown)

LI SLC 16.9-10 (Boration Systems Charging Pumps SRO -

Operating)

LI 3.5.2 (ECCS Operating)

LI 3.5.3 (ECCS Shutdown)

LI 3.6.6 (Containment Spray System)

LI 3.7.5 (Auxiliary Feedwater (AFW) System)

LI 3.7.7 (Component Cooling Water (CCW) System).

NOTE TO EVALUATOR: The SRO should determine T.S. 3.7.7 Condition A should be entered.

17. Determine required notifications:

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

LI REFER TO RPIOIB/5000/013 (NRC Notification Requirements).

NOTE TO EVALUATOR: Step 18 will be N!Ad.

18. IF KC Hx leak to RN is suspected, THEN perform the SRO following:

19. Verify KC 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/I /A/6400/005 (Component Cooling Water System).

LI Return NV Pump 1A to normal cooling as applicable. REFER TO_Enclosure_4_(Alternate_Cooling_To_NV_Pump_IA).

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 15 of 38

I Appendix D Required Operator Actions Form ES-D2 Op Test No.: NRC Scenario # I Event # 3 Page 16 of 38 Event

Description:

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

Time I Position I Aonlicants Actions or Behavior

21. Verify the following:

Li 1AD-7, Ff3 LETDN HX OUTLET HI TEMP DARK -

BOP El IAD-7, Hf3 VCT HI TEMP - DARK Li Normal letdown IN SERVICE.

22. Ensure VCT and letdown path aligned as follows:

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

1) Open the following valves:

El 1NV-188A (VCT OtIt Isol)

El 1NV-189B (VCT OtIt Isol).

2) Close the following valves:

El INV-252A (NV Pumps Suct From FWST)

BOP Li INV-253B (NV Pumps Suct From FWST).

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

c. IF desired to restore letdown flow through the NV demineralizers, THEN momentarily place INV-153A (Letdn Hx OtIt 3-Way Vlv) to the DEMIN position and return to AUTO.

23. Determine long term plant status. RETURN TO procedure in CREW effect.

END OF EVENT 3 Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 16 of 38

L Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 4 and 5 Page 17 of 38 Event

Description:

SIG 1 D develops a tube leak. Auto rod control is failed.

Time Position Applicants Actions or Behavior Booth Operator will insert Event 4 at discretion of lead examiner.

Indications: 1 RAD-1, B-I 1 EMF 33 CSAE EXHAUST HI RAD IRAD-I, B-4 1EMF71 S/GALEAKAGEHI RAD 1RAD-I, E-5 IEMF 74 SIG D LEAKAGE HI RAD CREW Recognizes a SIG tube leak.

NOTE TO EVALUATOR: The folJowing steps are from AP11155001010, Reactor Coolant Leak, Case L

1. Monitor Enclosure I (Case I Steam Generator Tube Leak RO/BOP Foldout_Page).

BOP 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 SIG is a S/G with primary to secondary leakage.

4. Identify the affected S!G(s) as follows:

LI Notify RP to frisk all cation columns.

OR LI Any S/G N/R level INCREASING IN AN UNCONTROLLED MANNER.

OR NOTE The S/G 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:

LI 1 EMF-71 (S/G A Leakage)

El 1 EMF-72 (S/G B Leakage)

El 1 EMF-73 (S/G C Leakage)

El 1 EMF-74 (S/G D Leakage).

OR El Verify any of the following S/G steamline EMF indication(s) -

INCREASING OR IN ALARM:

El IEMF-26 (Steamline 1A)

El 1EMF-27 (Steamline IB)

El IEMF-28 (Steamline 1C)

El IEMF-29 (Steamline 1D).

(Continued)

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 17 of 38

Lpendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 and 5 Page 18 of 38 Event

Description:

SIG 1 D develops a tube leak. Auto rod control is failed.

Time Position Applicants Actions or Behavior OR LI Verify CF flow - LOWER TO ANY S/G AS COMPARED TO OTHERS.

OR LI Notify Secondary Chemistry to determine affected SIG by sampling.

5. Verify VCT level able to be maintained by normal makeup as follows:

a. One of the following conditions exists:

LI SIG tube leak is less than 90 gpm.

OR LI Automatic makeup stabilizes or increases VCT level.

OR BOP LI Manual makeup stabilizes or increases VCT level.

b. IF AT ANY TIME the following conditions exist:

LI 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 11 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 ITL-8 (Aux Stm To Stm Seal Reg).

b) Close ITL-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 38

Appendix D Required Operator Actions Form ES-D-2 I Op Test No.: NRC Scenario # 1 Event # 4 and 5 Page 19 of 38 Event

Description:

S!G 1 D develops a tube leak. Auto rod control is failed.

Time Position Applicants Actions or Behavior NOTE Li Tritium sampling may be the most effective method for determining leak rate for small tube leaks when in Mode 2 or3.

Li The OAC calculated leak rate may be invalid during mode changes and/or transient conditions unless there is current, coordinated sampling data available.

7. Determine SIG leak rate by any of the following methods:

Li Monitor the following computer points:

Li Cl P0187 (Estimated Total Pri To Sec Leakrate)

Li Cl P0189 (Pri To Sec Leakrate 15 Mm Running Avg)

Li EROSLEAK (Primary To Secondary Leakage).

OR NOTE The S/G Leakage EMF5 are highly sensitive which may cause the EMFs located on the adjacent steamline to be increasing or in alarm.

Li S/G leakage EMF indication(s):

Li 1EMF-71 (S/G A Leakage)

BOP Li IEMF-72 (S/G B Leakage)

Li IEMF-73 (S/G C Leakage)

Li IEMF-74 (S/G D Leakage).

OR Li Compare charging flow and letdown flow OR Li Monitor OAC NV Graphic OR Li Initiate OAC Program NSNCLEAK OR Li Monitor OAC point Cl P0976 (Gross NC System Leak Rate, Ten Mm Run Avg).

OR Li Secondary Chemistry performance of PT/1/B/4600/028 (Determination of Steam Generator Tube Leak For Unit 1).

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 19 of 38

I Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 and 5 Page 20 of 38 Event

Description:

SIG 1 D develops a tube leak. Auto rod control is failed.

Time I Position I Applicants Actions or Behavior

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

LI 3.4.13 (RCS Operational Leakage)

LI 3.4.14 (RCS Pressure Isolation Valve SRO (PIV) Leakage)

LI 3.5.5 (Seal Injection Flow)

LI 3.7.17 (Secondary Specific Activity)

LI SLC 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. Condition A applies.

RO 9. Verify Unit in Mode 1.

NOTE D The following leak rates are iased on leakage in one SIG.

LI 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 GREATER 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:

LI Leak rate is greater than or equal to 100 gpd.

OR LI 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 LI All of the following:

LI Leak Rate is greater than or equal to 75 gpd LI Cl P01 87 (Estimated Total Pri To Sec Leakrate) - INVALID LI Any main steam line N-16 radiation monitor INOPERABLE.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 20 of 38

I Appendix D Required Operator Actions Form ES-D-2 I Op Test No.: NRC Scenario # 1 Event # 4 and 5 Page 21 of 38 Event

Description:

SIG 1 D develops a tube leak. Auto rod control is failed.

Time 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 indication:

El IEMF-71 (SIG A Leakage)

Li 1 EMF-72 (SIC B Leakage)

[11 EMF-73 (SIG C Leakage)

El IEMF-74 (SIC D Leakage).

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 El Unit shutdown may be suspended El RETURN TO Step 8.

NOTE EMFs should be monitored every 15 minutes.

c. Monitor the following EMFs:

LI 1 EMF-33 (Condenser Air Ejector Exhaust)

El 1 EMF-71 (SIG A Leakage)

El 1 EMF-72 (S/G B Leakage)

El I EMF-73 (S/G C Leakage)

El I EMF-74 (S/C D Leakage).

d. Notify RP of the following:

1) The current value of leakage.

2) Perform H P10/B/i 009/003 (Radiation Protection Response Following A Primary To Secondary Leak).

e. Evaluate secondary contamination potential. Review PT/1/B/4150/OO1G (Turbine Buildinq Sump Isolation).

14. Determine unit shutdown requirements as follows:

a. IF AT ANY TIME leak rate is greater than or equal to 100 gpd, THEN perform the following:

SRO

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.

NOTE TO EVALUATOR: The rest of step 14 will be N/A.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 21 of38

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 and 5 Page 22 of 38 Event

Description:

SIG ID develops a tube leak. Auto rod control is failed.

Time Position Applicants Actions or Behavior 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 15%.

c. Initiate unit shutdown. REFER TO:

Li 0P111N61001003 (Controlling Procedure For Unit RO/BOP Operation)

OR LI AP/11N55001009 (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 AP111A155001009 (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 RPIOIAI5000IOO1 (Classification Of SRO Emergency)

Li REFER TO RPIOIBI5000IO13 (NRC Notification Requirements).

3. IF AT ANY TIME prompt separation from the grid is required, CREW THEN GO TO Step 26.

4. IF load reduction is due to grid instability, THEN perform the RO following:

NOTE TO EVALUATOR: Step 4 will be NIA RO 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 RO EQUAL TO 15 MINUTES.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 22 of 38

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 and 5 Page 23 of 38 Event

Description:

SIG ID develops a tube leak. Auto rod control is failed.

Time Position Applicants Actions or Behavior NOTE The following tables are estimates only arid can be used for rapid entry into the turbine control panel.

8. Determine the required power reduction rate (MWIMin) from RO/BOP the table below:

NOTE TO EVALUATOR: The SRO and BOP will refer to the table in this step and determine the appropriate load reduction rate.

SRO/BOP 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/Mm (5%/minute) will meet C-7A interlock and may result in steam dump actuation.

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.

11. IF AT ANY TIME the turbine load reduction rate OR the RO/SRO target_load_must_be_changed,_THEN_RETURN_TO_Step_5.

12. Adjust power factor as necessary. REFER TO Unit I Revised RO Data_Book_Figure_43.

13. Attempt to control T-Avg as follows:

RO 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 RO manually insert control rods as required to maintain T-Avg within_1°F_of T-Ref.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 23 of 38

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 and 5 Page 24 of 38 Event

Description:

SIG 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 restore Tavg.

13.c. Maintain T-Avg greater than or equal to 551°F.

RO 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 BOP (section 4.8).

2) GO TO Step 13.f.

13. f. Ensure operator monitors Enclosure 2 (Rod Insertion Limit BOP Boration).

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

BOP a. All Pzr PORVs CLOSED.

b. Normal Pzr spray valves CLOSED.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 24 of 38

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 4 and 5 Page 25 of 38 Event

Description:

S/G 1 D develops a tube leak. Auto rod control is failed.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The following steps are from APII5, RodControl Malfunctions.

The crew may refer to this AP due to the 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:

1 IF auto and manual rod control not available, THEN perform one of the following:

E Borate to maintain T-Avg at T-Ref and RETURN TO procedure in effect.

OR 1 Trip reactor and GO TO EP/IIAI5000IE-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 EPI1IAI5000IE-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 38

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 26 of 38 Event

Description:

S/G 1 D Tube Rupture with a stuck open SIG 1 D PORV. Phase A fails to actuate Automatically.

Time Position Applicants Actions or Behavior NOTETO EVALUATOR: After step 14 of AP-09, the booth instructor can insert Event 6 at the lead instructors 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 S/G 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 EPI1IAI5000IE-O (Reactor Trip Or Safety_Injection).

NOTE TO EVALUATOR: The following actions are from EPIIIAI5000IE-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)

RO 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 38

I Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 27 of 38 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

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

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

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

RD 6. Announce Unit I Safety Injection.

7. Determine required notifications:

SRO El REFER TO RP/01A150001001 (Classification Of Emergency)

El REFER TO RP101B150001013 (NRC Notification Requirements).

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

9. Verify Phase A Containment Isolation status as follows:

BOP a. Phase A RESET lights - DARK.

b. Monitor Light Panel Group 5 St lights LIT.

CRmCAL BOP 9. RNO a. Manually initiate Phase A Isolation.

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:

RD 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.

BDP 13. Verify all KC pumps ON. -

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

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 27 of 38

f Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 28 of 38 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

15. Verify proper ventilation systems operation as follows:

u REFER TO Enclosure 2 (Ventilation System Verification).

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

RD 16. Verify all S!G pressures GREATER THAN 775 PSIG.

17. Verify proper S/I flow as follows:

RD 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.-

BOP 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.

RD

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 S/I equipment status based on monitor light panel -

BOP IN PROPER ALIGNMENT.

21. Control NC temperature. REFER TO Enclosure 4 (NC RD 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 PDRV isolation valve - OPEN.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 28 of 38

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 29 of 38 Event

Description:

SIG 1 D Tube Rupture with a stuck open S/G ID PORV. Phase A fails to actuate Automatically.

Time Position Applicants Actions or Behavior

23. Verify NC subcooling based on core exit T/Cs GREATER RO -

THAN 0°F.

24. Verify main steam lines are intact as follows:

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

NOTE TO EVALUATOR: If the crew has not identified the ID SIG PORV failure they may identify SIG pressureas decreasing in an uncontrolled manners This would send them to E-2, Faulted Steam. Generator lsolatiojt

25. Verify SIG tubes are intact as follows:

Li Verify the following EMF trip 1 lights DARK:

LI 1 EMF-33 (Condenser Air Ejector Exhaust)

LI 1EMF-26 (Steamline 1A)

BOP LI 1EMF-27 (Steamline 1B)

Li 1EMF-28 (Steamline 1C)

LI 1EMF-29 (Steamline 1D).

LI All S/G 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 LI Implement EPI1IN5000IF-O (Critical Safety Function Status Trees).

LI GO TO EPI1/AI5000IE-3 (Steam Generator Tube Rupture).

Appendix D Catawba NRC Exam Dec2010 NUREG 1021 Revision 9 Page 29 of 38

Appendix D Required Operator Actions Form ES-D-Op Test No.: NRC Scenario 1 Event # 6, 7 and 8 Page 30 of 38 Event

Description:

S/G 1 D Tube Rupture with a stuck open SIG ID PORV. Phase A fails to actuate Automatically.

Time Position I Applicants Actions or Behavior NOTE TO EVALUATOR: The following actions are from EPI1IAI6000IE-3.

CREW 1. Monitor Enclosure I (Foldout Page).

2. Identify ruptured SIG(s) as follows:

LI SIG level INCREASING IN AN UNCONTROLLED MANNER.

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

OR LI The following EMF trip I lights LIT: -

LI IEMF-26 (Steamline 1A)

LI IEMF-27 (Steamline IB)

SOP LI IEMF-28 (Steamline 1C)

LI IEMF-29 (Steamline 1D).

OR LI IF SIG Sampling is required to identify ruptured SIG(s), THEN:

a. Ensure the following signals - RESET:

1) Phase A Containment Isolations.

2) CA System valve control.

3) KC NC NI NM St signals.

b. Align all S/Gs for Chemistry sampling.

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

3. Verify at least one intact SIG AVAILABLE FOR NC SYSTEM RO COOLDOWN.

4. Isolate steam flow from ruptured SIG(s) as follows:

a. Verify all ruptured SIG(s) PORV CLOSED.-

b. Verify S/G(s) lB and IC - INTACT.

c. Isolate blowdown and steam drain on all ruptured SIG(s) as RO follows:

LI SIG 1D:

1) Close ISM-74B (SIG 1D OtIt Hdr Bldwn CIV).

2) Verify the following blowdown isolation valves CLOSED:

a) IBB-8A (SIG 1D Bldwn Cont Isol Insd).

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 30 of 38

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 31 of 38 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 b) I BB-147B (SIG 1 D Bldwn Cont Isol Byp).

c) 1BB-IOB (SIG 1D Bldwn Cont lsol Otsd).

5. Close the following valves on all ruptured SIG(s):

RD LIMSIV El MSIV bypass valve.

6. Control ruptured SIG(s) level as follows:

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

ACC).

b. Isolate feed flow to all ruptured SIG(s) as follows:

RD ElS!GID:

1) Close ICA-42B (CA Pmp B Disch To SIG ID lsol).

2) Close 1CA-38A (CA Pmp 1 Disch To SIG ID Isol).

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

(29% ACC), THEN perform_Step 6.

BOP 7. Verify at least one NC pump ON. -

8. WHEN P-Il PZR SII BLOCK PERMISSIVE status light (ISI

18) is lit, THEN:

a. Depress ECCS steam pressure BLOCK pushbuttons.

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

BOP 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.

C After the low steamline pressure main steam isolation signal is blocked Main Steam Iso1aton will occur if the high steam pressure rate setpoint s exceeded.

9. Initiate NC System cooldown as follows:

a. Verify all ruptured SIG(s) pressure GREATER THAN 320 RD PSIG.

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

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 31 of38

Appendix D Required Operator Actions Form ES-D-2 I Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 32 of 38 Event

Description:

S/G 1 D Tube Rupture with a stuck open SIG 1 D PORV. Phase A fails to actuate Automatically.

Time Position Applicants Actions or Behavior 7 NOTE TO EVALUATOR: The .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 SIG(s) -

CLOSED:

RD ElMSIV El MSIV bypass valves.

2) Verify SIG PORV on ruptured SIG(s) CLOSED OR ISOLATED.

NOTE TO EVALUATOR: Step 9c3 will be N/Nd.

d. Verify the condenser is available as follows:

El C-9 COND AVAILABLE FOR STM DUMP status light (ISI-18) LIT El MSIV on intact SIG(s) OPEN.

e. Verify steam dumps IN PRESSURE MODE.

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

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

2) Manually adjust STM DUMP CTRL M/A station output to match I%

STM DUMP DEMAND 1

(ISMP5211).

3) WHEN output on the STM DUMP CTRL MIA station RO/BOP is equal to the % STM DUMP DEMAND (ISMP52I 1), THEN place the steam dumps in pressure mode.

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

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

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

LIT.

I. WHEN core exit T/Cs are less than required temperature, THEN stabilize core exit TICs less than required temperature.

10. Control intact SIG levels as follows:

a. Verify N/R level in all intact S/Gs GREATER THAN 1 1%

RD (29% ACC).

b. Throttle feed flow to maintain all intact SIG NJR levels between 16% (29%ACC) and 50%.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 32 of 38

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 33 of 38 Event

Description:

S/C 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

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 EPI1IN5000IECA-3.l (SGTR With Loss Of Reactor Coolant Subcooled Recovery Desired).

12. Ensure SIl - RESET:

a. ECCS.

BOP b. D/G load sequencers.

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

13. Ensure the following containment isolation signals RESET: -

BOP LI Phase A El Phase B.

14. Establish VI to containment as follows:

BOP [I Ensure 1VI-77B (VI 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.

BOP 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.

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

17. Verify if NC System cooldown should be stopped:

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

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 33 of 38

I Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 34 of 38 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

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 crew will hold per the RNO for step 17.a.

I 7.a RNO Do not continue in this procedure until core exit T/Cs are SRO less than required temperature.

18. Verify ruptured SIG(s) pressure is under operator control as follows:

RO a. All ruptured SIG(s) pressure STABLE OR INCREASING.

b. IF AT ANY TIME ruptured SIG(s) pressure is decreasing while in this procedure, THEN perform Step 18.

19. Verify NC subcooling based on core exit TICs GREATER -

RO 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 Li Ruptured SIG(s) NR level is approaching 83% (82%

BOP ACC).

THEN GO TO Step 21.

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

El NC subcooling based on core exit T/Cs LESS THAN 0°F OR Li Pzr level GREATER THAN 76% (73% ACC)

OR LI Both of the following:

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 34 of 38

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 35 of 38 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 Li NC pressure - LESS THAN RUPTURED S/G(s)

PRESSURE AND Li 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).

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

NOTE TO EVALUATOR: After ensuring critical task criteria (C2), scenario may be terminated t this point. Examiner may want to allow crew to continue terminating safety injections forihe purpose of evaluating whether they can maintain level less than 92% (CT critieria).

CAUTION S/I must be terminated when termination criteria are satisfied to prevent overfilling the ruptured S/G(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 least one intact SIG - GREATER THAN RO/BOP 11% (29% ACC)

OR Li Total feed flow available to SIG(s) - GREATER THAN 450 GPM.

c. NC pressure - STABLE OR INCREASING.

d. Pzr level - GREATER THAN 11% (20% ACC).

24. Stop 511 pumps as follows:

BOP a. Stop NI pumps.

b. Ensure only one NV pump ON. -

25. Isolate NV Sf1 flowpath as follows:

a. Verify the following valves - OPEN:

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

Li I NV-253B (NV Pumps Suct From FWST).

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 35 of 38

Appendix D Required Operator Actions Form ES-D2 Op Test No.: NRC Scenario # 1 Event # 6, 7 and 8 Page 36 of 38 Event

Description:

S/G 1 D Tube Rupture with a stuck open SIC 1 D PORV. Phase A fails to actuate Automatically.

Time I Position Applicants Actions or Behavior

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. Close the following valves:

U INI-9A (NV Pmp CIL Inj lsol)

U INI-IOB (NV Pmp CIL lnj Isol).

END OF EVENTS 6AND 7.

END OF SCENARIO.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 36 of 38

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

SUMMARY

SAT IJNSAT 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 S/G i D reaches 92% narrow range level.

Comments:

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 37 of 38

ATTACHMENT 2

SHWT TURNOVER INFORMATION Unit I Status Power. Level Power History NCS Boron Xenon 50% BOL 1412 PPM perOAC Controlling Procedure

OPI1/A161001003 (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

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 reactor power to 100%.

NEOs Avadable Six NEOs 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 December 2010 NUREG 1021 Revision 9 Page 1 of 37

Catawba Nuclear Station NRC Exam December 2010 Facility: Catawba NRC Exam 2010 Scenario No.: 2 Op Test No.:

Examiners Operators: SRO RO BOP Initial Conditions: IC#144; Unit 1 reactor power is just below POAH 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 I-RD ENBOO9B Intermediate range NI N-36 high voltage failure.

TS-SRO 4 SG098199 I-RD W/R S/G 1 C level failure.

I-SRD C-BDP Reactor Coolant pump 1A Hi/Hi vibration requiring reactor trip and pump NCPOO3A C-SRD trip 6 NCO13A M-ALL Large Break LOCA on A loop.

7 ISEOO6NB C-RD Main Steam Isolation failure.

8 C-RD NDO14/15 1A and lB ND pumps trip causing a loss of emergency coolant recirc.

C-SRD 9

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 2 of 37

Catawba Nuclear Station NRC Exam December 2010 Scenario 2 Summary Initial Condition Unit 1 is just below POAH during startup. 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 reactor power to 10%.

Event 1 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 API1IA/55001016 (Malfunction of Nuclear Instrumentation System) Case 3 to remove this channel from service. TS evaluation by SRO is required.

Event 4 2 of 3 W/R SIG level channels on 1 C SIG begin to slowly fail to 40% level. This will cause the feedwater regulating bypass valve to slowly open up to maintain SIG 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 AP111A155001006 (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-1.3 (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.i (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 EncL 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 3of37

Catawba Nuclear Station_NRC Exam December 2010 EXERCISE GUIDE WORKSHEET I INITIAL CONDITIONS:

1.1 ResettoICl4l SART TIME:

v v Instructor Action Delay Ramp Delete. Event Final in MAL-NIOO4A (ESS HDR ISOL VLV N19 ACTIVE FAILS TO OPEN)

ANN-ADII-E03 (TRANSFORMER B ON TROUBLE)

MAL-ISEOO6B (AUTO SM ISOL SIGNAL BLOCK 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 1 OFF PB)

RACK-LOA-NDOI4 (RACKOUT ND PMP IA) 10 R.

LOA-NDOI5(RACKOUTNDPMPIB) 11 XMT-SG098 (XCF_5631 SIG C WIR LVL CH I TO DCSIELSEWHERE 40 2:00 3:30 3 (CFAA563I))

MAL-ENBOO9B (LOSS OF hR CH 36 HI VOLT) 3 XMT-SG099 (XCF_5632 SIG C WIR LVL CH 2 TO DCS/ELSEWHERE 40 2:00 3:30 3 (C FAA5632))

MAL-NCPOO3A (NCP A VIBRATION) 30 3:00 7 MAL-NCOI3A (NC COLD LEG A LEAK) 27.5 :10 20 MAL-NCOI3A (NC COLD LEG A LEAK) 3 9 LOA-CNTOO2 H2 ANALYZERS BOTH 5:00 13 Ensure EVENT 9 = XIOII5IF 9 Ensure EVENT 10 = Ifw_5000 < 42 10 Ensure EVENT 11 = Ifw_5000 < 36.5 11 Ensure EVENT 20 = xlOil8Gf or xlOil89f 20 MAL-NCOI3A (NC COLD LEG A LEAK) 3 9 Place a red collar on IA LH pump.

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

Catawba Nuclear Station NRC Exam December 2010 2 SIMULATOR BRIEFING 2.1 Control Room Assignments:

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

3 EXERCISE PRESENTATION 3.1 Familiarization Period 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.

v BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT EVENT I to trip 2A RN pump.

V. BOOTH INSTRUCTOR ACTION IF an NEC is dispatched to investigate the loss of 2A RN pump repeat the order.

V., BOOTH INSTRUCTOR ACTION IF an NEC is dispatched to check out the RN pump that was started wait 3 minutes and report the pump is running normally.

v : BOOTH INSTRUCTOR ACTION

[ IF asked what the flows on the Unit 2 RN pumps are refer to the XtremeView RN graphic.

BOOTH INSTRUCTORACTION F IF the SWM is called to investigate the loss of the 2A RN pump repeat the order.

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 5of37

Catawba Nuclear Station NRC Exam December 2010 v BOOTH INSTRUCTOR ACTION -

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 S/G C W/R level to DCS.

v BOOTH INSTRUCTOR ACTION I WHEN directed by the lead examiner, THEN INSERT SIMULATOR EVENT 3 to fail N-36 high voltage and fail S/G C W/R level.

BOOTH INSTRUCTOR ACTION WHEN the reactor qroup enqineer is notified of the occurrence repeat back the information.

BOOTH INSTRUCTOR ACTION 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 SIG 1C level failure.

V., BOOTH INSTRUCTOR ACTION NOTE: SCENARIO EVENT 4 was activated by SIMULATOR EVENT 3.

i BOOTH INSTRUCTOR ACTION 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..

-BOOTH INSTRUCTOR ACTION I 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 NUREG 1021 Revision 9 Page 6 of 37

Catawba Nuclear Station NRC Exam December 2010 V BOOTH INSTRUCTOR ACTION WHEN dispatched to secure all ice condenser air handling units and place the H2 analyzers in service, repeat the order. ACTIVATE EVENT 13 (LOA-CNTO02 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.

V BOOTH INSTRUCTOR ACTION 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.

V BOOTH INSTRUCTOR ACTION WHEN an operator is dispatched to initiate makeup to the FWST repeat back the order I

V BOOTH INSTRUCTOR 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 NUREG 1021 Revision 9 Page 7 of 37

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 1 Page 8 of 37 Event

Description:

Increase reactor power to 10%.

Time 1 Position 1 Applicants Actions or Behavior CREW Crew will begin increasing power to 1%, then to 100%.

NOTE TO EVALUATOR: The following actions are taken from OP1I 1A161 001001, Controlling Procedure for Unit Startup The crew will start at step 3,176.

NOTE: 1. Control rod withdrawal shall NOT exceed the temporary rod withdrawal limits specified in Unit One R.O.D. Section 2.3.

2. Refer to Unit One R.O.D. Section 2.4 for the rate at which reactor power can be changed.

3. The throttling of a SIG bypass reg valve affects the other S/G bypass reg valves. Therefore, SM/CF AP 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. Referto Unit One R.O.D. Section 5.10 for the MTC at the current conditions.

5. When approaching the beginning of the Power Range NI indication (.1% on the PR), a startup rate of< 0.2 dpm is required.

The < .2 dpm rate shall NOT be exceeded, except when performing PT/0/A14150/001 J (Zero Power Physics Testing), until the turbine is placed on line. (SOMP 01-02). (R.M.)

RO 3.175 Increase reactor power to 1%. (R.M.)

3.176 Begin reviewing the items listed in Step 3.184 so that Unit I CREW will NOT enter Mode 1 until all substeps of 3.184 are signed off.

RO 3.177 IF necessary, continue heatup to no load T-AVG (557°F).

3.178 Increase S/G blowdown flowrate as recommended by BOP Secondary Chemistry for S/C chemistry control.

3.179 WHILE increasing reactor power coordinate with Chemistry to CREW determine when blowdown flowrate can be subsequently reduced.

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

I Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 1 Page 9 of 37 Event

Description:

increase reactor power to 10%.

Time Position I Applicants Actions or Behavior 3.180 Verify S/G(s) reverse purge flow by performing the following:

3180.1 Record the temperature for the following OAC points:

(OAC Group Display GD OPCFTEMP)

CIAO141 (SIG A After CF Isol Vlv Line Temp)

C1A0148 (SIG A Inlet Temp (Feedwater))

C1A0125 (SIG B After CF Isol Vlv Line Temp)

C1A0154 (SIG B Inlet Temp (Feedwater))

C1A0275 (SIG C After CF Isol Vlv Line Temp)

CIAOI6O (S/G C Inlet Temp (Feedwater))

C1A0815 (SIG D After CF lsol Vlv Line Temp)

C1A0166 (SIG D Inlet Temp (Feedwater))

3180.2 Compare the values recorded above to the values recorded in steps 3.80.15.7, 3.104.1, 3.119.1, 3127.1 and 3.147.1 to verify reverse purge (increasing temperature).

3180.3 IF no sign of reverse purge, determine what is causing the loss of reverse purge and correct the problem.

3180.4 Monitor OAC Group Display OPCFTEMP for increasing temperatures as a sign of reverse purge while continuing with the procedure.

NOTE TO EVALUATOR: Step 3.181 and 182 will be NIAd.. IA CFPTis in service in AUTO.

3.183 WHEN the CF bypass valves are approximately 40% open, unisolate the CF reg valves by opening the following valves:

SIG IA 1CF-29 (SIG IA CF CN Otit lsol) 1CF-27 (SIG 1A CF CN mit Isol)

SIG I B 1 CF-38 (SIG 1 B CF CN Otlt Isol)

BOP 1CF-36 (SIG lB CF CN mIt Isol)

SIG 1C 1CF-47 (SIG 1C CF CN Otlt Isol) 1CF-45 (SIG 1C CF C/V mIt Isol)

SIG 1 D 1 CF-56 (SIG 1 D CF C/V Otit Isol) 1CF-54 (SIG 1D CF C/V InIt Isol)

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 9 of 37

Appendix D Required Operator Actions Form ES-D-2 OpTestNo.: NRC Scenario# 2 Event# 1 Page 10 of 37 Event

Description:

Increase reactor power to 10%.

Time Position Applicants Actions or Behavior 3.184 Prior to entering Mode 1, do the following:

NOTE: Appropriate Chemistry Supervisor shall confirm any administrative holds preventing a power increase.

3184.1 Ensure PT/1/A/4700/002 (Periodic Test Performance Verification For Mode Change) Premode 1 PT Checklist is completed.

3.1 84.2 Verify with Primary Chemistry that NC System H2 concentration and Dose Equivalent Iodine are in spec to allow entry into Mode 1.

Person notified 3184.3 Verify the PCMC data base has been reviewed for items required for Mode 1 entry.

3.1 84.4 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.

3184.5 Ensure the CF temperatures between each feedwater BOP isolation valve and SIG is greater than 107°F: (QAC Group Display GD OPCFTEMP)

S/G IA:

C1AO141 (S/G A After CF Isol Vlv Line Temp)

C1A0148 (S/G A Inlet Temp. (Feedwater))

S/G IB:

C1A0125 (S/G B After CF Isol Vlv Line Temp)

C1A0154 (S/G B Inlet Temp. (Feedwater))

SIG 1C:

C1A0275 (S/G C After CF Isol Vlv Line Temp)

CIAOI6O (S/G C Inlet Temp. (Feedwater))

S/G 1D:

C1A0815 (S/G D After CF Isol Vlv Line Temp)

C1AO 166 (S/G D Inlet Temp. (Feedwater))

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 10 of 37

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 1 Page 11 of 37 Event

Description:

Increase reactor power to 10%.

Time Position Applicants Actions or Behavior 3.185 Prior to entering Mode 1, perform the following to ensure the primary to secondary leakage program inputs are current:

. 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 BOP Equivalent in the Chemistry Database is current.

Person Notified_____________________

Record current air ejector off gas flowrate.

Update EMF33 Prim/Sec Leakage program on the Unit I OAC.

3.186 Record Mode 1 entry time below:

SRO Mode 1 END OFEVENTI 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 # 2 Event # 2 Page 12 of 37 Event

Description:

2A RN pump trips. Requires AP/20 entry. (Loss of Nuclear Serv. Water)

Time I Position I Applicants Actions or Behavior NOTE TO EVALUATOR: The Booth Operator will enter Event 2 at discretion of lead examiner.

INDICATIONS: IADI2, A2 RN ESSENTIAL HDR A PRESSURE LO IAD12, A5 RN ESSENTIAL HDR B PRESSURE LO SOP Recognize the loss of 2A RN pump.

CREW Crew enter AP101N55001020, Loss of Nuclear Service Water NOTE TO EVALUATOR: The following actions are taken from AP!01A155001020, Loss of Nuclear Service Water, Case 1.

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

2. Ensure Unit I and Unit 2 OATC monitors Enclosure I CREW (Foldout Page).

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

4. Verify each operating RN pump discharge flow GREATER -

BOP THAN 8,600 GPM.

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

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

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

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

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

8. Verify each operating RN pump discharge flow GREATER -

BOP THAN 8,600 GPM.

BOP 9. Verify RN - AVAILABLE TO ALL UNIT I AND UNIT 2 DIG(S).

10. Determine VC/YC status as follows:

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

Verify YC Chiller RUNNING.

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

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 2 Page 13 of 37 Event

Description:

2A RN pump trips. Requires AP/20 entry. (Loss of Nuclear Serv. Water)

Time Position Applicants Actions or Behavior

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: SRQ should determine that entry into T.S. 3.7.8 Condition A is applicable.

13. Determine required notifications:

Li REFER TO RPIOIAI5000IOO1 (Classification Of Emergency)

SRO Li REFER TO RPIOIBI5000IOI3 (NRC Notification Requirements)

NOTE TO EVALUATOR: SRO should determine that no notifications are required.

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

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

END OFEVENT2 Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 13 of 37

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 will enter Event 3 at discretion of lead examiner. Event 4 (SIG level instrument) is also entered with a 2 minute time delay INDICATIONS: IAD2, CI hR HI VOLTAGE FAILURE N-36 INDICATION FAILS TO 10-11 AMPS.

RO RO recognize failure of N-36 SRO CREW ENTERS AP/11A15500116, CASE 3 NOTE TO EVALUATOR: The following actions are taken from AP1015500!016, Malfunction of Nuclear Instrumentation System, Case 3.

RO 1. Verify reactor power GREATER THAN 10%.

RO 1. RNO Stop any power increase RO 2. Verify IAD-2, C!3 hR HI FLUX LEVEL ROD STOP - DARK.

3. Identify affected hR channel:

El N-35 RO OR El N-36.

BOP 4. Verify affected hR channel CONTROL POWER ON light LIT -

NOTE IAD-2, C14 N/I SYS S/R & hR TRIP BYPASS will actuate in the following step.

5. At the affected hR drawer, perform the following:

SRO 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 RO

19) LIT.

RO 7. Verify IAD-2, CI4 Nil SYS SIR & hR TRIP BYPASS LIT. -

8. Ensure operable hR channel selected to record on NIS RO RECORDER.

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 3 Page 15 of 37 Event

Description:

Intermediate Range NI N-36 high voltage failure.

Time Position Applicants Actions or Behavior

9. WHEN the operable hR channel is less than 10-10 Amps, CREW THEN ensure SIR channels are reset.

SRO 10. Determine and correct cause of hR malfunction.

11. Ensure compliance with Tech Spec 3.3.1 (Reactor Trip SRO System (RTS) Instrumentation).

NOTE TO EVALUATOR: The SRO should determine that T.S. Table 3.3.1 item 4 is applicable and apply Condition F.

12. Determine required notifications:

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

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

NOTE TO EVALUATOR: No notifications are required at this time.

SRO 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 P/R rate trip due to voltage spikes.

14. WHEN the affected hR channel is repaired, THEN ensure IAE SRO returns the channel to service.

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

END OF EVENT 3 Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 15 of 37

Appendix D Required Operator Actions Form ES-D-21 Op Test No.: NRC Scenario # 2 Event # 4 Page 16 of 37 Event

Description:

W/R S/G 1C level failure Time 1 Position Aoolicants Actions or Behavior NOTE TO EVALUATOR: Event 4(2 minute delay with a 3 1/2 minute ramp) was entered concurrentwith Event 3.

INDICATIONS: 1C Level Channels I and 2 slowly fail to 40%.

SIG 1C FRVB begins to open.

SIG IC Level begins to increase.

1AD4, E5, CFCV ISOL VLVS CLSD RO Recognize the failure of S/G 1C level channels Take manual control of the IC FRV and FRVB and control SIG level RO at normal level.

NOTE TO EVALUATOR: The following actions are taken from AP111A155001006, Loss of SIG Feedwater Case 4 CF Control Not in AutoS I. IF AT ANY TIME SIG levels approaching:

Li 83% N/R level (SIG HI-HI Level Turb Trip)

OR Li 11% NIR level (SIG LO-LO Level Rx Trip).

THEN:

a. Manually trip reactor.

b. GO TO EPIIIN5000IE-0.

2. Verify the following:

Li At least one CF pump - IN SERVICE Li IAD-3, C/6 CF ISOL TRN A DARK -

Li 1AD-3, D/6 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.

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 16 of 37

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario# 2 Event# 4 Page 17 of 37 Event

Description:

W/R SIC 1C level failure

[ Time Position U Applicants Actions or Behavior

5. Verify all SIG CF control valves:

LI IN AUTO El 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/G level(s) STABLE

. S/G level(s) APPROXIMATELY AT PROGRAM

. Malfunction CORRECTED.

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

b. WHEN all the following conditions met:

. S/G level(s) STABLE

. S/G level(s) APPROXIMATELY AT PROGRAM

. Malfunction CORRECTED.

THEN GO TO Step 7.

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

END OF EVENT 4.

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 17 of 37

Appendix D Required Operator Actions Form ES-D-2 I Op Test No.: NRC Scenario # 2 Event # 5 Page 18 of 37 Event

Description:

Reactor Coolant Pump 1A Hi/Hi vibration requiring reactor trip and pump trip.

Time I Position Applicants Actions or Behavior NOTE TO EVALUATOR: The Booth Operator will enter Event 5 at discretion of lead examiner.

Indications: 1AD6, A5 NCP HI VIBRATION 1AD6,C5 NCP VIBRATION MON TROUBLE 1AD6, B5 NCP HI HI VIBRATION BOP Identifies the affected pump as 1A.

RO Manually trip the reactor.

Manually trip the 1A NCP and ensure INC-27 is closed.

NOTE TO EVALUATOR: The foliowing actions are from the Supplementary Actions of ARP OPII!BI6IOOIOIOG, 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 OR 2:

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/N5000/E-O (Reactor Trip or Safety Injection).

END OF EVENT 5.

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 18of37

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 19 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: EVENT 6, 7 and 8 will 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 EPIIIAI5000!E-O.

CREW 1. Monitor Enclosure I (Foldout Page).

2. Verify Reactor Trip: (Immediate action step)

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

3. Verify Turbine Trip: (Immediate action step)

RO C All turbine stop valves - CLOSED BOP 4. Verify IETA and IETB ENERGIZED. (Immediate action step)

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

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

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

NOTE TO EVALUATOR: The following actions are from EPIIIAI5000IE-O, Enclosure 1. The crew should trip all NCPs when subcooling is lost arid hAs are

. completeS

2. NC Pump Trip Criteria:

D IF the following conditions are satisfied, THEN trip all NC CRITICAL pumps while maintaining seal injection flow:

TASK L At least one NV or NI pump ON -

ii 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 Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 20 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: The following actions are from EP!11A15000!E-O.

RO 6. Announce Unit I Safety Injection.

7. Determine required notifications:

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

El REFER TO RPIOIBI5000IO13 (NRC Notification Requirements).

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

9. Verify Phase A Containment Isolation status as follows:

BOP 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 PSIG.

a. RNO Note: RNO actions are extensive. See attachment at the back of this SIm Guide.

EVALUATOR NOTE: The operating KF (SFP) pump loses cooling water during a Phase B.

Operator may then secure the pump.

11. Verify proper CA pump status as follows:

RO a. Motor driven CA pumps - ON.

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

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

El NV pumps BOP El ND pumps El NI pumps.

BOP 13. Verify all KC pumps - ON.

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

15. Verify proper ventilation systems operation as follows:

El REFER TO Enclosure 2 (Ventilation System Verification).

BOP Note: Enclosure 2 is provided as an attachment at the back of this Sim Guide.

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

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 20 of 37

I Appendix D Required Operator Acflons Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 21 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time Position Applicants Actions or Behavior RD 16. Verify all S!G pressures GREATER THAN 775 PSIG.

17. Verify proper SIl flow as follows:

a. NV S/I FLOW INDICATING FLOW.

b. NC pressure - LESS THAN 1620 PSIG.

c. NI pumps INDICATING FLOW.

d. NC pressure - LESS THAN 285 PSIG.

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

18. Control SIG levels as follows:

a. Verify total CA flow GREATER THAN 450 GPM.

RD

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 SII equipment status based on monitor light panel IN BOP -

PROPER ALIGNMENT.

21. Control NC temperature. REFER TO Enclosure 4 (NC RD 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 -

RD THAN 0°F.

23. RNO IF any NV OR NI pump is on, THEN:

BOP a. Ensure all NC pumps OFF. -

b. Maintain seal injection flow.

24. Verify main steamlines are intact as follows:

RD D All S/G pressures STABLE OR INCREASING J ALL S/Gs - PRESSURIZED.

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 21 of37

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 22 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time Position Applicants Actions or Behavior

25. Verify S!G tubes are intact as follows:

LI Verify the following EMF trip I lights - DARK:

LI I EMF-33 (Condenser Air Ejector Exhaust)

LI 1 EMF-26 (Steamline 1A)

BOP LI IEMF-27 (Steamline IB)

LI IEMF-28 (Steamline IC)

LI IEMF-29 (Steamline ID).

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 IAD-6, Eli, NCP A THERMAL BARRIER KC OUTLET HIILO FLOW LI 1AD-6, E/2, NCP B THERMAL BARRIER KC OUTLET HI/LO FLOW LI 1AD-6, E13, NCP C THERMAL BARRIER KC OUTLET BOP HI/LO FLOW LI IAD-6, E14, NCP D THERMAL BARRIER KC OUTLET HIILO FLOW.

a. RNO Note: Actions are extensive, and included as an aftachment at the back of this Sim Guide.

b. Verify NC System is intact as follows:

LI Containment pressure - LESS THAN 1 PSIG.

26b RNO I) 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 0P111A164501010 (Containment Hydrogen Control Systems).

3) IF both the following conditions exist:

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 22 of 37

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 23 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps: also with a failure of Main Steam Isolation and Loss of Emeraencv recirc.

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: Step 26b.3) will be NIAd.

26.b RNO 4) Concurrently:

LI Implement EPI1IAI5000IF-0 (Critical Safety Function Status Trees).

Note: There will be a RED path on Integrity. Applicant will read the first step of FR-P. 1 which will send them back to procedure in effect.

LI GO TO EP/1IA/5000/E-1 (Loss Of Reactor Or Secondary_Coolant).

NOTE TO EVALUATOR: The following actions are from EPIIIAI5000IE-1 (Loss of Reactor or Secondary Coolant).

CREW 1. Monitor Enclosure I (Foldout Page).

2. Verify main steamlines are intact as follows:

RD LI All S/G pressures STABLE OR INCREASING LI All SIGs - PRESSURIZED.

3. Control intact SIG levels as follows:

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

RD ACC).

b. Throttle feed flow to maintain all intact SIG 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.

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

c. Perform at least one of the following:

LI 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 I lights - DARK:

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 23 of 37

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 24 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time Position Applicants Actions or Behavior L 1 EMF-33 (Condenser Air Ejector Exhaust)

LI 1EMF-26 (Steamline IA)

LI 1EMF-27 (Steamline IB)

El 1EMF-28 (Steamline IC)

LI I EMF-29 (Steamline 1 D).

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 Sf1 termination criteria as follows:

C REW

a. NC subcoo!ing based on core exit T/Cs GREATER THAN 0°F.

SRO 6.a RNO GO TO Step 6.f.

6f. Monitor S/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 LI I FW-27A (ND Pump IA Suct From FWST)

El 1FW-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: (done only if cont. press. is <2.4psig.)

BOP 1)ECCS.

2) DIG load sequencers.

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

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 24 of 37

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario# 2 Event # 6, 7 and 8 Page 25 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time Position Applicants Actions or Behavior

f. Reset NS.

g, Stop NS pumps.

h. Close the following valves:

0 1 NS-29A (NS Spray Hdr 1A Cont Isol) 0 1 NS..32A (NS Spray Hdr IA Cont*lsol) 0 INS-15B (NS Spray Hdr lB Cont Isol)

LI INS-12B (NS Spray Hdr lB Cont Isol).

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

a. NC pressure GREATER THAN 285 PS 1G.

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 1 ETA is energized by offsite power as follows:

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

c. WHEN S/I is reset, THEN dispatch operator to stop IA D/G and place in standby readiness. REFER TO OP/i /A/6350/002 (Diesel Generator Operation).

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

BOP 0 D/G I B BKR TO ETB OPEN 0 1ETB - ENERGIZED.

e. WHEN SII is reset, THEN dispatch operator to stop I B D/G and place in standby readiness. REFER TO OP/i /A16350/002 (Diesel Generator Operation).

f. 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 previously on.

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 25 of 37

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 26 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time Position Applicants Actions or Behavior 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.

BOP 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 (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:

E 1FW-27A (ND Pump 1A Suct From FWST) lNl-185A (ND Pump IA Cont Sump Suct)

D 1 ND-28A (ND Supply To NV & 1A NI Pmps)

L IFW-55B (ND Pump lB Suct From FWST) 1 1NI-184B (ND Pump lB Cont Sump Suct)

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

BOP E INI-333B (NI Pump Suct From ND) ii INI-334B (NI Pump SuctX-Over From ND)

L 1NI.-136B (ND Supply To NI Pump 1B).

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

D INI-115A(NI Pump lAMiniflowlsol)

[ 1NI-144A (NI Pump lB Miniflow Isol) 1 1NI-147B (NI Pump Miniflow HdrTo FWST Isol).

4) Verify the ENABLE lights for the following switches - LIT:

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

El C-LEG RECIR FWST TO CONT SUMP SWAP TRN B.

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 26 of 37

I Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 27 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time I Position I Applicants Actions or Behavior

c. Verify auxiliary building radiation is normal as follows:

Li EMF-41 (Aux Bldg Ventilation) trip Ilight 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 RPIOIAI5000IO15 (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 OPIOIA/64501003 (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 PSIG.

13.a RNO IF ND flow to C-Legs is greater than 675 GPM, THEN GO SRO/BOP TO Step 14.

14. Verify transfer to Cold Leg Recirc as follows:

a. FWST level LESS THAN 37% (IAD-9, D/8 FWST 2/4 LO SRO LEVEL LIT).

b. S/I systems ALIGNED FOR COLD LEG RECIRC.

NOTE TO EVALUATOR: Depending on the speed of the crew, if FWST level has reached 37% prior to this step they will have transferred to ES-1.3. If not at 37%, they will enter step 14.a RNO and loop back to step 11 until FWST is at 37%

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 27 of 37

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 28 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time Position Applicants Actions or Behavior NOTE To EVALUATOR: The following actions are from EPI1!A15000!ES-1.3, Transfer to Cold Leg Recirculation CREW 1. Monitor Enclosure I (Foldout Page).

CAUTION SII 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:

LI IAD-20, B13 CONT. SUMP LEVEL >3.3 ft BOP OR El 1AD-21, B13 CONT. SUMP LEVEL >3.3 ft BOP

3. Verify KC flow to ND heat exchangers - GREATER THAN 5000 GPM.

4. Ensure SIl RESET:

a. ECCS.

b. DIG load sequencers.

c. IF AT ANY TIME a B/O 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 IA Cont Sump Suct)

LI 1 NI-i 84B (ND Pump I B Cont Sump Suct).

5. b. Verify following valves - CLOSED:

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

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

c. Verify ND pumps - ON.

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 28 of 37

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 29 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time Position Applicants Actions or Behavior 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 BOP 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/A15000/ECA-1.1 (Loss Of Emergency Coolant Recirculation).

NOTE TO EVALUATOR: At this step. the crew will transitin to ECA-1 1, Loss of Emergency Coolant Recirculation. .

NOTE TO EVALUATOR: The following actions are from ECA-1.1.

1. IF loss of Emergency Coolant Recirculation is due to sump CREW blockage, THEN GO TO EPIIIAI5000!ECA-1.3 (Containment Sump_Blockage).

CREW 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 El 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 BOP and correct cause of pump failure. REFER TO EM/11A152001005 (Troubleshooting Cause For ND, NI, or NV Pump(s) Failing to Start).

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 29 of 37

Appendix D Required Operator Actions Form ES-D-2 I Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 30 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time j Position Applicants Actions or Behavior 3.b. Verify the following valves AVAILABLE TO BE OPERATED FROM THE CONTROL ROOM:

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

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

c. Verify containment sump level adequate as follows:

LI 1AD-20, B12 CONT. SUMP LEVEL >2.5 ft - LIT OR LI IAD-21, B/2 CONT. SUMP LEVEL >2.5 ft - LIT BOP OR LI All of the following:

LI FWST level - LESS THAN 8%

LI NC temperature GREATER THAN 200°F LI Containment Spray - PREVIOUSLY IN SERVICE LI 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:

LI Power restoration LI Local valve operation LI Obtain maintenance assistance as required. REFER TO EM/1/A15200/006 (Troubleshooting Cause For FW, ND, NI, or NV Valves(s) Failing to Operate).

BOP LI Other actions as specified by station management.

2) WHEN emergency coolant recirc capability is restored during this procedure, THEN:

a) IF transfer to Cold Leg Recirc is required, THEN perform the following:

(1) Ensure the following valves OPEN:

LI 1 NS-29A (NS Spray Hdr 1A Cont Isol)

LI 1 NS-32A (NS Spray Hdr IA Cont Isol)

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 30 of 37

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 31 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time Position Applicants Actions or Behavior E 1NS-15B (NS Spray Hdr lB Cont Isol)

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

(2) GO TO EPI1IA/5000IES-1.3 (Transfer To Cold Leg Recirculation).

b) RETURN TO procedure and step in effect.

3) GO TO Step 4.

4. Ensure SlI RESET:

a. ECCS.

BOP b. D/G load sequencers.

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

5. Depress the DEFEAT pushbuttons on the following switches:

BOP u C-LEG RECIR FWST TO CONT SUMP SWAP TRN A U 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: -

LI I NS-20A (NS Pump 1A Suct From FWST) i I NS-3B (NS Pump 1 B Suct From FWST).

BOP b. Determine number of NS pumps required from the following table:

c. Verify the number of NS pumps on - EQUAL TO NUMBER REQUIRED.

Note: NS pumps may have been previously secured. If not,_they will be secured in this step.

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 # 2 Event # 6, 7 and 8 Page 32 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time Position Applicants Actions or Behavior 9.a RNO Perform the following:

1) Ensure NS Train A RESET.

BOP 2) Close the following valves:

El INS-29A(NS Spray Hdr lACont iso!)

El INS-32A (NS Spray Hdr IA Cont iso!).

BOP 9.b. Verify NS Pump lB ON. -

9.b RNO Perform the following:

I) Ensure NSTrain B RESET. -

BOP 2) Close the following valves:

El 1NS-15B (NS Spray Hdr lB Cont Iso!)

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

c. IF AT ANY TIME NS pumps are stopped or started, THEN:

El Ensure associated NS Train - RESET.

C REW El Close associated spray valves after securing a pump.

El Open associated spray valves prior to starting a pump.

CRITICAL 10. Initiate makeup to FWST. REFER TO 0P111A162001014 BOP TASK (Refueling Water System).

Evaluator Note: Scenario may be terminated here, at examiner discretion.

11. Control intact S!G levels as follows:

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

RO (29% ACC).

b. Throttle feed flow to maintain all intact 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 OP/01N61001006 (Reactivity Balance Calculation).

2) Verify NC boron concentration GREATER THAN OR EQUAL TO REQUIRED BORON CONCENTRATION.

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 32 of 37

I Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 33 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emerqency recirc.

Time I Position Aoolicants Actions or Behavior

13. WHEN P-Il PZR SIl BLOCK PERMISSIVE status light (IS!

18) is lit, THEN:

BOP a. Depress ECCS steam pressure BLOCK pushbuttons.

b. Verify main steam isolation blocked status lights (ISI-13) -

LIT.

NOTE 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.

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 RO light (ISI-18) LIT.

RO b. Verify MSIVs on all intact S/Gs 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.

RO 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 MSIV5).

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

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 33 of 37

I Appendix D Required Operator Actions Form ES-D-2 I Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 34 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time Position I Applicants Actions or Behavior a) Open all MSIVs on intact SIGs.

b) Close all MSIV bypass valves.

c) Perform Steps 14.c through 14.e.

6) GO TO Step 15.

14. c. WHEN P-12 LO-LO TAVG status light (151-I 8) is lit, THEN place the steam dump interlock bypass switches in BYP INTLK.

RD d. Verify steam dumps IN PRESSURE MODE.

e. Dump steam to condenser while e. Perform the following:

maintaining cooldown 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:

LI 1NI-9A (NV Pmp CIL lnj Isol) OPEN -

OR LI INI-IOB (NV Pmp CIL lnj Isol)- OPEN OR LI At least one ND pump on with suction aligned to either of the BOP following:

LI FWST OR LI Containment sump.

OR LI At least one NI pump - ON.

16. Establish one train of SI! 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.

BOP 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.

RD

d. Verify only one ND pump - ON.

Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 34 of 37

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NRC Scenario # 2 Event # 6, 7 and 8 Page 35 of 37 Event

Description:

Small Break LOCA develops into a Large Break after loss of subcooling and tripping NC pumps; also with a failure of Main Steam Isolation and Loss of Emergency recirc.

Time i Position I ApIicants Actions or Behavior 16.d RNO Perform the following:

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

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

17. Verify no backflow from FWST to containment sump as follows:

a. A Train:

1) Verify INI-185A (ND Pump 1A Cont Sump Suct) - OPEN.

2) Verify IFW-27A (ND Pump 1A Suct From FWST)

BOP CLOSED.

b. B Train:

1) Verify 1NI-184B (ND Pump lB Cont Sump Suct) - OPEN.

2) Verify IFW-55B (ND Pump lB Suct From FWST) -

CLOSED.

18. Verify NC pump status as follows:

a. All NC pumps - OFF.

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

SRO 18.bRNO GOTO Step 19.

19. Verify SIl termination criteria as follows:

a. Verify RVLIS indication is adequate as follows:

RO L IF all NC pumps are off, THEN verify REACTOR VESSEL LR LEVEL GREATER THAN 61%.

SRO 19.a RNO GO TO Step 26.

END OF SCENARIO Appendix D Catawba NRC Exam December 2010 NUREG 1021 Revision 9 Page 35 of 37

- CNS - - REACTOR TRIP OR SAFETY INJECON FPAGE NO 1 EPIIIAI5000IE-0 6 of 61 Revision 36 ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

7. Determine required notifications:

. REFER TO RPIOIAI5000/001 (Classification Of Emergency)

. REFER TO RP/O/B150001013 (NRC Notification Requirements).

8. Verify all Feedwater Isolation status Perform the following:

lights (lSl-5) LIT.

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. a. Manually initiate Phase A Isolation.

b. Monitor Light Panel Group 5 St lights - b. Manually align valves.

LIT.

10. Verify proper Phase B actuation as follows:

a. Containment pressure HAS - a. Perform the following:

REMAINED LESS THAN 3 PSIG.

NOTE This time may be used later to determine when to align ND Aux spray.

1) Record approximate time of reactor trip.

2) Verify NS pumps - INDICATING FLOW.

3) IF flow is not indicated, THEN manually initiate Phase B Isolation for affected train(s).

(RNO continued on next page)

CNS - REACTOR TRIP OR SAFETY INJECTION PAGl EP/1/N5000/E-0 7 of 61 Revision 36 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

10. (Continued)

4) Verify Phase B Isolation has actuated as follows:

a) Phase B Isolation RESET lights DARK.

b) I Phase B Isolation RESET lights are lit, THEN manually initiate Phase B Isolation.

c) Verify following monitor light panel lights LIT:

. Group I Sp lights

. Group 5 Sp lights

. Group 5 St lights L/11 and Lu 2.

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

e) If NS pump(s) did not start, THEN perform the following for the affected train(s):

(1) Reset ECCS.

(2) Reset D/G load sequencer.

(3) Manually start affected NS pump.

_(4) NATANYTIMEaB/O occurs, THEN restart S/I equipment previously on.

5) Stop all NC pumps.

6) Maintain seal injection flow.

7) Energize H2 igniters.

(RNO continued on next page)

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO.

EPI1IAJ5000/E-0 8 of 61 Revision 36 RESPONSE RESPONSE NOT OBTAINED ACTION/EXPECTED

10. (Continued)

8) 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 1Q OP/1/A16450/010 (Containment Hydrogen Control Systems).

9) WHEN 9 minutes has elapsed, THEN verify proper VX system operation. REFER ] Enclosure 7 (VX System Operation).

_10) TQ Step 11.

b. if J 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.

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

1) Reset ECCS.

2) Reset D/G load sequencer.

3) Manually start affected motor driven CA pump.

_4) IFATANYTIME a BIO occurs, THEN restart S/I equipment previously on.

b. 3 S/G N/R levels - GREATER THAN b. Ensure CA Pump #1 - RUNNING.

11%.

ii CNS EP/1 IA50001E-O I

REACTOR TRIP OR SAFETY INJECTION Enclosure 2-. Page 1 of 7 Ventilation System Verification PAGE NO.

33of61 Revision 36 ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED Verify proper VCIYC operation as follows:

a. Verify one train of the following a. Perform the following:

equipment is in operation:

1) Shift operating VC/YC trains.

v6 YC chiller REFER ]Q Enclosure 6 (Shifting V CR AHU-1 Operating VC/YC Train).

V. CRAAHU-1 V. CRA PFT-1. 2) IF no train can be properly aligned, THEN dispatch operator and IAE/Maintenance to restore at least one train of VC/YC. REFER TO the following:

. 011645001 (Control Room Area Ventilation/Chilled Water System)

. EM/O/A15200/OO1 (Troubleshooting Cause For Improper Operation of VC/YC System).

CNS REACTOR TRIP OR SAFETY INJECTION PAGE N1 EPII/A15000/E-O Enclosure 2 Page 2 of 7 Ventilation System Verification Revision 36 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. (Continued)

b. Verify the following alarms DARK:

- b. if chlorine odor is detected in the

/ Control Room, THEN perform the V

IAD-18, A18 UNIT I INTAKE HI following based on the status of given CHLORINE IA alarms:

IAD-18, B18 UNIT I INTAKE HI 1) IF detectors on both unit intakes are CHLORINE IB in alarm, THEN:

lAD-I 8, D18 UNIT 2 INTAKE HI a) Ensure the following VC intake CHLORINE 2A dampers CLOSED:

1AD-18, E18 UNIT 2 INTAKE HI

1VC-5B (CRA FlIt Inlet)

CHLORINE 2B. . IVC-6A (CRA Filt Inlet)

. 2VC-5B (CRA Filt Inlet)

. 2VC-6A (CRA Filt Inlet).

_b) ]QStep1.d.

2) IF Unit I intake HI chlorine detector(s) in alarm, THEN:

a) Ensure the following VC dampers CLOSED:

. IVC-5B (CRA Filt Inlet)

. IVC-6A (CRA Filt Inlet).

b) Ensure the following dampers -

OPEN:

2VC-5B (CRA FlIt Inlet)

2VC-6A (CRA FlIt Inlet).

_c) GOTOStepI.d.

(RNO continued on next page)

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NOl -

EPIIIAI5000IE-O 35.0! 61 Enclosure 2- Page 3 of 7 Ventilation System Verification Revision 36 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. (Continued)

3) IF Unit 2 intake Hi chlorine detector(s) in alarm, THEN:

a) Ensure the following VC dampers CLOSED:

. 2VC-5B (CRA Filt Inlet)

. 2VC-6A (CRA Filt In let).

b) Ensure the following dampers -

OPEN:

. IVC-5B (CRA Filt Inlet)

. 1VC-6A (CRA Filt Inlet).

_c) TQStep1.d.

c. Ensure the following VC dampers -

OPEN:

IVC-5B (CRA Filt Inlet)

IVC-6A (CRA Filt Inlet)

. 2VC-5B (CRA Filt Inlet) 6 2VC-6A (CRA Filt Inlet).

d. Repeat Step 1 of this enclosure until notified by station management as follows:

least once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR

/ Any time VC/YC related annunciators on 1AD-18 actuate.

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO.

EPIIIAI5000IE-O Enclosure 2 Page 4 of Revision 36 Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2. Ensure proper VA System operation as follows:

Ensure the following fans - OFF:

Z ABUXF IA

j. ABUXFIB.

Ensure VA System filter is in service as follows:

1ABF-D-12 & 19 (VA Filter A Bypass Dampers) CLOSED lAB F-D-5 & 20 (VA Filter B Bypass Dampers) CLOSED.

Ensure the following fans ON:

V. ABFXF-IA

j. ABFXFIB.

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO.

EP/11A15000/E-0 37o 61 Enclosure 2 Page 5 of 7 Revision 36 Ventilation System Verification ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

3. Verify proper VE System operation as follows:

i VE fans ON.

- a. Manually start fan(s).

Annulus pressure BETWEEN

- b. Perlorm the following:

-1.4 IN. WCAND -1.8 IN. WC.

1) if annulus pressure is more positive than -1.4 in. WC, THEN:

a) Verify flow indicated on the following indications:

. yE 1A FLOW TO STACK

. VE lB FLOW TO STACK.

b) IF flow is not indicated, THEN dispatch operator to verify status of the following dampers based on their local indication or their operating piston rods being extended 4 to 6:

. 1AVS-D-2 (VE A Tm Recirc Damp) (AB-603, JJ-51, Rm 500) CLOSED

. 1AVS-D-7 (VE B Tm Recirc Damp) (AB-603, HH-52, Rm 500) CLOSED

. IAVS-D-3 (VE A Tm Exh Damp) (AB-603, JJ-52, Rm 500) OPEN

. 1AVS-D-8 (VE B Tm Exh Damp) (AB-603, HH-52, Rm 500) OPEN.

c) Consult plant engineering staff and notify IAE/Maintenance to troubleshoot and repair. REFER EM/i /N5200/002 (Troubleshooting Cause For VE System Hi/Lo Pressure).

d) ] Step 3.c.

(RNO continued on next page)

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO.

EPIIIAI5000IE-O Enclosure 2 Page 6 of Ventilation System Verification Rio36 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

3. (Continued)

2) if annulus pressure is more negative than -1.8 in. WC, THEN:

a) Determine which VE train indicates highest discharge flow to stack.

b) Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , ensure VE train that indicates highest discharge flow to stack is secured.

c) Consult plant engineering staff and notify IAE/Maintenance to troubleshoot and repair. REFER

]Q EM/i /A/5200/002 (Troubleshooting Cause For VE System Hi/Lo Pressure).

Repeat Step 3.b every 30 minutes until notified by station management.

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1

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO.

EPIIIAI5000IE-O Enclosure 4 Page 1 of NC Temperature Control Revision 36 I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. Verify at least one NC pump - ON. _-_- Perform the following:

a. Use NC T-Colds to determine NC temperature as required in subsequent steps.

b. IQStep4.

2. Use NC T-Avg to determine NC temperature as required in subsequent steps.

/

3. if J ANY TIME NC pumps are tripped, THEN use NC T-Colds to determine NC /

temperature as required in subsequent/

steps.

4. Verify one of the following: TO Step 7.

NC temperature STABLE AT LESS THAN OR EQUAL TO 557° F.

NC temperature TRENDING TO 557°F.

5. Continue to monitor NC temperature.

5 7

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO.

EPII/AI5000IE-O Enclosure 4 Page 2 of 4 NC Temperature Control Revisn36 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

6. Do not continue in this enclosure until one of the following occurs:

NC temperature GREATER THAN 557°F AND INCREASING IN AN UNCONTROLLED MANNER.

NC temperature GREATER THAN 557°F AND STABLE.

NC temperature LESS THAN 557° F AND DECREASING IN AN UNCONTROLLED MANNER.

Verify NC temperature LESS THAN

- Perform the following:

557°F AND DECREASING.

a. IF NC temperature is greater than 557°F increasing, THEN stabilize NC temperature at 557°F as follows:

1) IF steam dumps are available, THEN use steam dumps.

2) IF steam dumps are not available, THEN use S/G PORVs.

b. IF the following conditions exist:

NC temperature is greater than 557° F and stable

Time and manpower is available, THEN stabilize NC temperature at 557°F as follows:

1) IF steam dumps are available, THEN use steam dumps.

2) if steam dumps are not available, THEN use S/G PORVs.

c. QTQStep9.

CNS REACTOR TRIP OR SAFE INJECTION PAGE N EP/IIAJ5000IE-O Enclosure 4 Page 3 of 4 6136 NC Temperature Control Revil S Ofl ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1

8. Attempt to stop the NC cooldown as follows:

a. Ensure all steam dumps - CLOSED.

b. Ensure all S/G PORVs CLOSED.

- b. IF any SIG PORV cannot be closed, THEN close its isolation valve.

c. Ensure S/G blowdown is isolated.

d. Close the following valves:

ISM-77A (S/G 1A OtIt Hdr Bldwn CN)

ISM-76B (S/G lB Otlt Hdr Bldwn CN)

ISM-75A (S/G IC OtIt Hdr Bldwn CN)

ISM-74B (SIG ID OtIt Hdr Bldwn CN).

e. Depress and hold S/V BEFORE SEAT DRN CLOSE pushbutton (1MC-3) to close the following valves:

1SM-41 (Stop Vlv #1 Before Seat Drn)

1SM-44 (Stop Vlv #2 Before Seat Drn)

I SM-43 (Stop Vlv #3 Before Seat Drn)

1SM-42 (Stop Vlv #4 Before Seat Drn).

CNS REACTOR TRIP OR SAFETY INJECTION EP/1/A15000/E-O Enclosure 4 Page 4 of 4 NC Temperature Control ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

8. (Continued)

f. Verify NC cooldown - STOPPED. IF cooldown continues, THEN throttle feed flow as follows:

1) IFS/GN/Rlevelislessthan 11%

(29% ACC) in all SIGs, THEN throttle feed flow to achieve the following:

Minimize cooldown

Maintain total feed flow greater than 450 GPM.

2) WHEN NIR level is greater than 11% (29% ACC) in at least one SIG, THEN throttle feed flow further to achieve the following:

Minimize cooldown

Maintain at least one SIG N/R level greater than 11%

(29% ACC).

3) IF cooldown continues, THEN close the following valves:

All MSIVs

All MSIV bypass valves.

9. Continue to perform the actions of this enclosure as required to ensure one of the following:

NC temperature STABLE AT LESS THAN OR EQUAL TO 557°F.

NC temperature TRENDING TO 557°F.

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO.

EP/IIA/50001E-O 16 of 61 Revision 36 ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED

26. Verify NC System is intact as follows:

a. Verify the following NC pump thermal a. Perform the following:

barrier alarms DARK:

1) Ensure the valve for the affected

. 1AD-6, Eli, NCP A THERMAL NC pump(s) CLOSED:

BARRIER KC OUTLET HI/LO FLOW . I KC-394A (NC Pump IA Therm Bar OtIt)

. 1AD-6, E12, NCP B THERMAL BARRIER KC OUTLET HI/LO . IKC-364B (NC Pump lB Therm FLOW Bar OtIt)

. IAD-6, E/3, NCP C THERMAL . 1KC-345A (NC Pump IC Therm BARRIER KC OUTLET HI/LO Bar OtIt)

FLOW

. IKC-413B (NC Pump 1D Therm

. 1AD-6, E14, NCP D THERMAL Bar OtIt).

BARRIER KC OUTLET HI/LO FLOW. 2) IF the valve for the affected NC pump will not close, THEN perform the following:

a) Trip all NC pumps.

(RNO continued on next page)

I ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

26. (Continued) b) Perform the following:

(1) Dispatch operator with radio to standby at IKC-425A (NC Pumps Ret Hdr Cont Isol) (AB-588, GG-52, Rm 419) (Ladder needed).

(2) Close I KC-425A (NC Pumps Ret Hdr Cont Isol) from Control Room.

(3) if 1 KC-425A (NC Pumps Ret Hdr Cont Isol) will not close completely from Control Room, THEN have operator locally close 1 KC-425A (NC Pumps Ret Hdr Cont Isol) (AB-588, GG-52, Rm 419).

(4) WHEN I KC-425A (NC Pumps Ret Hdr Cont Isol) has been closed, THEN close 1KC-424B (NC Pumps Ret Hdr Cont Iso!).

(5) WHEN IKC-425A (NC Pumps Ret Hdr Cont Isol) is closed, THEN notify the dispatched operator to return.

(6) Close the following valves:

. IKC-338B(NC Pumps Sup Hdr Cont iso!)

. 1KC-430A (Rx Bldg Drn Hdr Cont isol)

. IKC-429B (Rx Bldg Drn Hdr Cont iso!).

Catawba Nuclear Station NRC Exam December 2010 ATTACHMENT 1

CREWCRITICAL TASK

SUMMARY

SAT LJNSAT CT# CRIT1CAL TASK C-i Trip all reactor coolant pumps on a loss of subcooling per E-0 End. 1 guidance within 5 minutes of criteria being met.

C-2 Makeup to the FWST and minimize FWST outflow.

Comments:

Appendix D Catawba NRC Exam December2010 NUREG 1021 Revision 9 Page 36 of 37

ATTACHMENT 2

.SHIFTTURNOVER INFORMATION Unit I Status Power Level Power History. NCS Boron Xenon Just below POAH Per IC 680 PPM per OAC Controlling Procedure

OPII/A/61001001 (Controlling Procedure for Unit Startup), Enclosure 4.1 (Unit Startup).

Begin at step 3.175.

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 10%.

NEOs Available Six NEOs 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 # SPARE Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 1 of 36

Catawba Nuclear Station NRC Exam December 2010 FadllUy: - Catawba N-RC Exam 201G oenario No.: Spare- Op Test No Examiners: Operators: SRD RD BOP Initial Conditions: IC#142; Unit 1 is at 100% power EDL. 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 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-BDP NVO56D NV pump 1 B trip.

TS-SRD 3 1-BOP ENBO1 3B PR N-42 blown control power fuse.

TS-SRO 4 C-SRD FWPO12C 1A CFPT trip with failure of automatic turbine runback.

R-RD 5 FWPO1 5C C-RD 1 B CFPT trip (Loss of all CF flow to SIGs) requiring reactor trip.

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

7 CAOO5 C-RD CAPT # I overspeed trip, motor driven CA pumps fail to start.

CAOO4NB C-SRD 8 -- M-ALL Loss of secondary heat sink.

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 2 of 36

Catawba Nuclear Station NRC Exam December 2010 Scenario SPARE Summary -

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

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

Event 2 lB NV pump trips, causing a loss of charging and letdown. AP/1/A15500/012 (Loss of Charging or Letdown) Cases 1 & 2 will be entered to restore charging and letdown. TS evaluation by SRO is required.

Event 3 Power range N-42 control power fuse blows. Crew will enter AP/1/N5500/016 (Malfunction of Nuclear Instrumentation) Case 4 will be entered to remove this channel from service. TS evaluation by SRO is required..

Event 4 IA CFPT trips. An automatic turbine runback to 65% does not occur and requires RO to manually decrease turbine load. AP/1/A15500/003 (Load Rejection) will be entered Event 5 I B CFPT trips, causing a loss of all feed flow to the SIGs. Immediate actions of AP/1/N5500/006 (Loss of S/G 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 I B motor driven CA pumps fail to start automatically and cannot be started manually. CAPT

I will trip on a mechanical overspeed.

Event 8 Once all SIG 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 I 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 of All S/Gs), 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 36

Catawba Nuclear Station NRC Exam December 2010 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 ResettoICl42 START TIME:________

V v Instructor Action Delay Ramp Delete Event Final 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 OVR-FWPOI2C (CFPT IA TRIP_

ON RESET TRIP PB)

MAL-ENBOI3B (PIR 42 BLOWN FUSE) CONTROL 5 OVR-FWPOI5C (CFPT lB TRIP_RESET ON 7 TRIP PB)

MAL-CAOO5 (CA PUMP OVERSPEED MECHANICAL TRIP)

LOA-EHCOI4 (RACKOUT EHC PMP IA) RACKOUT Place a red tag collar on IA LH pump.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 4 of 36

Catawba Nuclear Station NRC Exam December 2010

2. SIMULATOR BRIEFING 2.1 Control Room Assignments:

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

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

3.2 Scenario EVENT 1, Swap of NV pumps.

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

3.3 Scenario EVENT 2, the 1 B NV pump trips.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR EVENT I to trip the 1 B NV pump.

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

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 5 of 36

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, Power Range N42 blown control power fuse.

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

V I BOOTS INSTRUcTOR ACTION WHEN IAE is directed to place bistables in the tripped condition REPEAT back the order.

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

3.5 Scenario EVENT 4, 1A CFPT trips.

V BOOTH INSTRUCTORACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR EVENT 3 to trip 1A CFPT.

V., BOOTH INSTRUCTOR ACTION WHEN the SOC is contacted REPEAT back the information.

V BOOTH INSTRUCTOR ACTION IF an NED is dispatched to investigate the cause of the 1A CFPT tripping, REPEAT back the order. No reason will be given for the trip.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page6of36

Catawba Nuclear Station NRC Exam December 2010 V BOOTH INSTRUCTOR ACTION WHEN Radition Protection is notified to sample and analyze gaseous effluents REPEAT back the information.

WHEN Primary Chemistry is notified to sample for isotopic analysis of iodine REPEAT back the information.

V 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.

V BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR EVENT 7 to cause the 1 B CFPTtotrip.

V BOOTH INSTRUCTOR ACTION IF an NEO is dispatched to investigate why the I B CFPT tripped REPEAT back the order. No reason will be given.

V SOOTH 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.

V 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 NUREG 1021 Revision 9 Page 7 of 36

Appendix 1) - RequedOperatorAotkns Form ES-D2 Op Test No.: NRC Scenario # Spare Event # 1 Page 8 of 36 Event

Description:

Crew will shift operating NV pumps by starting lB NV pump and securing 1A NV pump.

Time Position Applicants Actions or Behavior CREW ASSUMES THE WATCH:

NOTE TO EVALUATOR: the following actions are taken from 0P111A16200100l, Chemical andVlume Control System, Enclosure 413. 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 lB 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 1 NVP5500 (VCT 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 1AAUX OIL PUMP

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

NV PUMP IA

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

(1) 2.1.5 Stop the previously running NV pump:

NV PUMP IA

NV PUMP lB 2.1.6 Verify proper charging flow rate.

END OF EVENTI Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 8 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test Na.: NRC- &enaTio# Spare event # 2 Page 9- at 3 Event

Description:

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

Indications: El 1AD-7, C14 NCP SEAL WATER LO FLOW alarm LIT -

El 1AD-7, Eli CHARGING LINE HI/LO FLOW alarm LIT El Pzr level DECREASING El Letdown Isolates NOTE TO VALUATOR No operator actions are required outside of the AR NOTE TO EVALUATOR: The following actions are taken from APIIIAI5500!012, Case 1, Loss of Charging.

RO 1. Stop any power changes.

2. Ensure the following letdown isolation valves CLOSED: -

El 1NV-IOA (Letdn Orif lB OtIt Cont Isol)

BOP El 1NV-11A(Letdn Orif 1C OtltCont Iso!)

El 1NV-i3A(Letdn Orif IA OtIt Cont Isol).

BOP 3. Ensure any malfunctioning NV pump SECURED. -

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

SOP 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 BOP 124B (Excess Letdn Press Ctrl) ADJUSTED TO 0%.

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

6. Verify NV pump status as follows:

BOP El At least one NV pump ON.

El Charging flow ADEQUATE FOR PLANT CONDITIONS.

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

b. Ensure the following valves OPEN:

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 9 of 36

Appendix D Required Operator Actions Form ES-D-2 OpTestN NRC Scenario Spare vent# 2E Page TO of - S6 -

Event

Description:

Time Position Applicants Actions or Behavior Li I NV-203A (NV Pumps A&B Recirc isol)

Li 1 NV-202B (NV Pmps A&B Recirc iso!).

c. Ensure only one suction source as follows:

Li VCT Li 1 NV-I 88A (VCT OtIt Iso!) OPEN Li INV-189B (VCT Otlt Isol)- OPEN Li VCT level GREATER THAN 23%

Li I NV-252A (NV Pumps Suct From FWST) 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 Pumps Suct From FWST).

Li Either of the following valves CLOSED:

Li 1 NV-i 88A (VCT OtIt Isol)

Li 1NV-189B (VCT Otlt Iso!).

NOTE TO EVALUATOR: Step 64 should be NIAd

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

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

2) Close I NV-294 (NV Prnps 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 AP111A155001009 (Rapid Downpower)

OR Li OPI1IA/61001003 (Controlling Procedure For Unit Operation).

NOTE TO EVALUATOR: Step 6.f should be NIPd The SRO will continue with step 7

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

a. INV-312A (Chrg Line Cont iso!) OPEN. -

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 10 of 36

Appendix D Required Operator Actions Form ES-D-2 OpTestN.. NRC Scfin# Sfe EVen# 2 Page H of 36 Event

Description:

Time Position Applicants Actions or Behavior

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

c. Verify one of the following valves OPEN LI I NV-32B (NV Supply To Loop A Isol)

OR LI I NV-39A (NV Supply To Loop D Isol).

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 LI I NV-309 (Seal Water Injection Flow) IN AUTO.

8. RNO Perform the following:

a. Slowly throttle 1NV-3O9 (Seal Water Injection Flow) to establish 32 BOP GPM TOTAL SEAL WTR FLOW.

b. Place INV-309 in auto.

BOP 9. Verify Pzr level GREATER THAN 17%.

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

BOP 11. Ensure PZR HTR GROUP IC ON. -

12. Control VCT level as follows:

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

CONCENTRATION.

b. Verify NC MAKEUP MODE SELECT IN AUTO. -

13. Verify normal letdown IN SERVICE.

13. RNO Perform the following:

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

BOP 1) Establish excess letdown. REFER TO OP/i /A/6200/00i (Chemical and Volume Control System)

2) GO TO Step 14.

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

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 11 of 36

Appendix D Required Operator Actions Form ES-D-2 Op TestNu.: NRC Scenari# Spare Evunt# 2 Page 12 of 3 Event

Description:

Time Position Applicants Actions or Behavior NOTE TO EVALUATOR: Restoration of LID is performed in Case 2 of AP111A15500I012 following the end of this case.

14. Ensure compliance with appropriate Tech Specs:

E] 3.4.13 (RCS Operational Leakage)

El 3.4.14 (RCS Pressure Isolation Valve (PIV) Leakage)

El 3.5.2 (ECCS Operating)

SRO El 3.5.3 (ECCS Shutdown)

El 3.5.5 (Seal Injection Flow)

El 3.6.3 (Containment Isolation Valves)

El SLC 16.9-9 (Boration Systems Charging Pump Shutdown)

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

NOTE TO EVALUATOR: T.S. 35.2 (Condition A) and SLC 16.9-10 (Condition A) apply.

15. Determine required notifications:

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

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

BOP 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 OPIOIBI6I 001013 (Standby Shutdown Facility Operations).

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

END OF CASE 1.

NOTE tO EVALUATOR: APII!A155001012, Case 2, begins here.

RD 1. Stop any power changes.

2. Ensure the following letdown isolation valves CLOSED: -

El I NV-I OA (Letdn Orif 1 B OtIt Cont lsol)

BOP El 1 NV-I IA (Letdn Orif 1C Otit Cont Isol)

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

BOP 3. Verify Pzr level GREATER THAN 17%.

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

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 12 of 36

Appendix D Required Operator Actions Form ES-D-2 Opfest Na.: NRC Scenario# Spare EveT1t 2 Page 13 of 36 -

Event

Description:

Time Position Applicants Actions or Behavior BOP 5. Ensure PZR HTR GROUP IC ON. -

6. Control VCT level as follows:

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

CONCENTRATION.

b. Verify NC MAKEUP MODE SELECT IN AUTO. -

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 OPII!N62001001 (Chemical and Volume Control System).

9. Verify proper VCIYC system operation. REFER TO Enclosure 5 BOP (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 Tech.Specs. apply for this case.

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

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

BOP OR El INV-2A (NC Letdn To Regen Hx Isol).

SRO 11. RNO GO TO Step 16.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 13 of 36

Appendix D Required Operator Actions Form ES-D-2 013 TEst N N1C Scenario # Spare EVetlt# 2 Pe 14 of 36 Event

Description:

Time Position Applicants Actions or Behavior

16. Establish letdown as follows:

a. Verify ability to establish normal letdown RESTORED.

b. Ensure I NV-849 (Letdn Flow Var Crlf CtrI) valve demand position -

0%.

c. Verify the following valves OPEN:

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

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-b 1320)

d. Open the following valves:

El 1NV-15B (Letdn Cont Isol)

El INV-1OA (Letdn Orif lB OtIt Cont Isol)

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

f. Throttle INV-148 (Letdn Press Control) to 45% demand.

g. Throttle open INV-849 (Letdn Flow Var Orif Ctrl) in 1% to 5%

increments until one of the following conditions is met:

BOP 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 PSIG.

NOTE TO EVALUAtOR: Time compression cue may be used for the next step; i,e, 5 minutes have eiapsed

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 C1P0097) 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.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 14 of 36

Appendix D Required Operator Actions Form ES-D-2 Oy Test Na.: NRC Scenrlo #- Spare EVetlt# 2 Pace 15 Of 36 Event

Description:

Time Position Applicants Actions or Behavior 16.

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

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

a) Adjust I NV-i 48 (Letdn Press Control) to maintain letdown pressure at 350 PSIG.

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

BOP -

4) IF AT ANY TIME additional letdown flow desired, THEN establish letdown with the 45 or 75 GPM orifice. REFER TO OP/1/N6200/00i (Chemical and Volume Control System).

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

I) 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/A/5000/001 (Classification Of Emergency)

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

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

END OF EVENT 2 Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 15 of 36

Appendix D Required Operator Actions Form ES-D-2 OpTestNa: NRC Scnarto# Spare Event# 3 Page 16 at 36 Event

Description:

Power Range NI N42 fails low, requiring removing channel from service.

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

Indications: AD2, Al P!R NEUTRON FLUX RATE ALERT A02, A3 P!R HI NEUTRON FLUX HI SET POINT ALERT AD2, B5 PIR HI VOLTAGE FAILURE AD2, E8 OVER POWER ROD STOP AD2, FlO OCS TROUBLE INDICATING LIGHTS ON N-42 PANEL GO DARK RD Verifies all rod motion is stopped.

Enters AP111A155001016, Malfunction of Nuclear Instrumentation System, SRO Case IV Power Range Malfunction.

EVALUATOR NOTE: The following actions are from AP!11A155001016, Malfunction of Nuclear Instrumentation System, Case IV Power Range Malfunction.

RD 1. Verify all rod motion STOPPED.

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

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

3. Identify failed P/R channel:

LI N-41 OR LI N-42 RD DR LI N-43 OR LI N-44.

RD 4. Ensure unaffected channels OPERABLE.

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

REFER TO Model WIO #00874531:

BOP LIDTDELTAT LI OP DELTAT.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 16 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: NfC Scenario # Spare Everit# 7 Page iT of - 3&

Event

Description:

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 (ISI-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 defeat switch to the affected channel.

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

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

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

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

NOTE The following annunciators will actuate in the following step:

1AD-2, Ni PIR HI NEUTRON FLUX RATE ALERT SRO 1AD-2, N3 PIR HI NEUTRON FLUX HI SET POINT ALERT 1AD-2, B15 PIR HI VOLTAGE FAILURE.

9. Do-energize the affected channel as follows:

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

BOP 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 BOP Enclosure I (PIR Bistables That Must Be Tripped).

BOP 11. Ensure operable PIR channel selected to record on NIS RECORDER.

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

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

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

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 17 of 36

Appendix D Required Operator Actions Form ES-D-2 O Test NO.: NRC SceriatiO # Sare Evern # 2 Page 18 of 3 Event

Description:

Time Position Applicants Actions or Behavior

15. Ensure compliance with appropriate Tech Specs:

SRO C 3.2.4 (Quadrant Power Tilt Ratio (QPTR))

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

Note to Evaluator:The crew will enter tS. 33.1 (Conditions D.1 1 and Di ;2, E.1, Ri, and Si).

16. Determine required notifications:

SRO Li REFER TO RPIOIAI5000IOO1 (Classification Of Emergency).

Li REFER TO RPIOIBI5000IOI3 (NRC Notification Requirements).

BOP 17. Notify Reactor Group Engineer of occurrence.

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

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

END OF EVENT4 Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 18of36

Appendix D Required Operator Actions Form ES-D-2 TestN.: NRC ScerirIo # Spare EVerIt# 3 P 19 - Of 3 Event

Description:

Power Range NI N42 fails low, requiring removing channel from service.

Time Position Applicants Actions or Behavior Booth Operator can insert Event 4 at the discretion of the lead examiners Indications: AD5, Al CFPT A TRIPPED AD5, A4 CFPT A COMMON TROUBLE 1AD1, F4 TURB RUNBACK INITIATED 1AD2, A4 T-REF/T-AVG HI/LO Generator MW will NOT be decreasing.

Main Turbine Control Valves will NOT be closing.

RO Manually decreases turbine load.

RO Ensures control rods are operating properly.

SRO Enter AP/l IA/55001003 (Load Rejection).

NOTE TO EVALUATOR: The following actions are taken from APII!A15500!003, Case 1 Load Rejections RO 1. Verify turbine load DECREASING IN AUTOMATIC.

I. RNO Perform the following:

RO a. Select MANUAL on turbine control panel.

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

2. Verify proper reactor response:

RO 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 (1SI- 18) LIT. -

c. Verify the following:

BOP El C-7A LOSS OF LOAD INTLK COND DUMP status light (I SI-I 8) -

LIT.

LI Steam dump valves MODULATING.

d. i-Avg DECREASING TO T-REF.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 19 of 36

Appendix D Required Operator Actions Form ES-D-2 O Tét No.: NRC SónriO # - Spr Evht if 2 Page - 20 of 36 Event

Description:

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.

BOP 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 Li lAD-il, C/i GEN BKR A OVER CURRENT Li lAD-il, F/i GEN BKR B OVER CURRENT.

7. Verify SIG levels are adequate as follows:

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

RO 8. Verify reactor power GREATER THAN 20%.

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

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

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

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

RO 13. Verify reactor power LESS THAN 30%.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 20 of 36

Appendix D Required Operator Actions Form ES-D-2 OpTestNa.: - NRC Sceriario# Spar9 Event# 2 - Page 21 of 36 -

Event

Description:

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 at current 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:

II Turbine load fl Control rods El Boron concentration.

c. GO TO Step 15.

15. Verify the following PCBs CLOSED:-

El Generator breaker IA El Generator breaker I B BOP EPCB14 El PCB 15 El PCB 17 El PCB 18.

16. Adjust power factor as necessary. REFER TO Unit I Revised Data Book RD Figure43.

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

El Stabilize unit at appropriate power level.

El Maintain control rods above insertion limits.

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

El Turbine load El Control rods El Boron concentration.

18. Notify System Operating Center (SOC) using the red dispatcher BOP 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 21 of 36

Appendix D Required Operator Actions Form ES-D-2 OTéfNO.f NRC SennO# Sp( EvéntW 2 Page 22 of 36 Event

Description:

Time Position N Applicants Actions or Behavior

20. Shut down unnecessary plant equipment as follows:

a. Restore CM and CF as follows:

1) Verify C-htr drain pumps ON. -

2) Verify both CF Pumps IN SERVICE.

3) Shutdown one CF pump as necessary. REFER TO 0P111N6250/00i (Condensate and Feedwater System).

4) Shutdown excess Condensate Booster Pumps. REFER TO OP/i/A/6250/001 (Condensate and Feedwater System).

5) Shutdown excess Hotwell Pumps. REFER TO OP/1/A16250/00i (Condensate and Feedwater System).

b. RC pump(s) and cooling tower fans. REFER TO OP/i /B/6400/OOIA (Condenser Circulating Water System).

21. Reset steam dump valves as follows:

a. Verify reactor power STABLE.

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

c. Verify steam dump valves CLOSED.

Note to Evaluator: Depending on the speed of the crew the steam dumps 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 RO through 21 .g.

2) GO TO Step 22.

d. Reset steam dump valves.

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

Li C-7A LOSS OF LOAD INTLK COND DUMP RO Li C-7B LOSS OF LOAD INTLK ATMOS DUMP.

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

g._Verify STM DUMP CTRL IN AUTO.-

RO 22. Verify reactor power GREATER THAN 15%.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 22 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test N NR Sceriario-# Spare - EVelit # - 2 P 23 - Of 36 Event

Description:

Time Position Applicants Actions or Behavior RO 23. Verify CA pumps OFF. -

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

25. Notify the following sections to take appropriate samples:

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

BOP Li 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:

Li 3.1.1 (Shutdown Margin (SDM))

SRO Li 3.1.6 (Control Bank Insertion Limits)

Li 3.8.1 (AC Sources Operating).

Note to Evaluator: T.S. 3.1.6 Conditions A.t2 and A.2 (Control Bank Insertion Limits) apply.

BOP 27. Notify Reactor Group Engineer of occurrence.

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

END OF EVENT 3 Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 23 of 36

Appendix D Required Operator Actions Form ES-D-2 Op TestNo. NRC Scenario Spare- Everrt# 5, 6, and 7- Page 24 of 36 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 Booth Operator can insert Event 5 at the discretion of the lead examiner.

Indications: AD5, Ci CFPT B TRIPPED ADI, A6 TURB TRIP ON LOSS OF BOTH CFPTS NUMEROUS AD1 ALARMS AD4, Ci - C4 S/G A D FLOW MISMATCH LO CF FLOW AD4, Bi B4 SIG A D LEVEL DEVIATION ENTER AP/11A15500/006 (LOSS OF SIG FEEDWATER)

RO Manually trip the reactor SRO Go to EPI1IN5000IE-O (Reactor Trip or Safety Injection)

RO Manually reduce Turbine Load EVALUATOR NOTE: The following actions are taken from APIIIAI5500IOO6 (LOSS OF SIG

. FEEDWATER) Case I.

RO i. Verify reactor power LESS THAN 5%.

i. RNO IF AT ANY TIME all CF supply to SIG(s) lost, THEN perform the following:

a. Manually trip reactor.

b. GO TO EPIiIAI5000IE-O (Reactor Trip Or Safety Injection).

EVALUATOR NOTE: The following actions are taken from EPIIIAI5000IE-O (Reactor Trip Or -

- Safety Injection). The RO and BOP will perform the immediate actions, RO/

1. Monitor Enclosure I (Foldout Page).

2. Verify Reactor Trip:

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

3. Verify Turbine Trip:

RO LI All turbine stop valves CLOSED Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 24 of 36

Appendix D Required Operator Actions Form ES-D-2 OpTestNo NRC -Scenariot Spare Event# 5-6:, ant7 Page 25 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

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 cpntrol panel.

CRITICAL .

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

3) IF turbine will not runback, THEN close:

Li All MSIVs Li All MSIV bypass valves.

BOP 4. Verify IETA and IETB ENERGIZED.

5. Verify SII is actuated:

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

5.a RNO a. Perform the following:

1) Verify conditions requiring S/I:

Li Pzr pressure - LESS THAN 1845 PSIG OR Li 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:

LI Implement EP/11N5000/F-O.

(Critical Safety Function Status Trees).

Li GO TO EPII/A/5000IES-O.1 (Reactor Trip Response).

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 25 of 36

I Appendix D Required Operator Actions Form ES-D-2 OpTeNo.:- FtRG Scenario# Spare- Everit# , , andT Page 2S cf 3S 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 EVALUATOR NOTE: The following actions are taken from EP!1!N5000!ES-O.i (Reactor Trip Response).

ROI

1. Monitor Enclosure I (Foldout Page).

2. Verify the following:

BOP El All 6.9 KV busses - ENERGIZED.

LI VI pressure GREATER THAN 85 PSIG.

RD 3. Announce Unit I Reactor Trip.

4. Determine required notifications:

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

El REFER TO RPIO/B150001013 (NRC Notification Requirements).

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

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

6. Verify feedwater status as follows:

a. T-Avg LESS THAN 564°F.

RD

b. All Feedwater Isolation status lights (ISI-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 SIG N/R level greater than 11% OR total feed flow greater than 450 GPM using one of the following:

BOP! LiCApumps RD OR LI Main Feedwater System. REFER TO 0P111A162501001 (Condensate and Feedwater System).

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 26 of 36

ADoendix D Required Operator Actions Form ES-D-2 Op Test Nt,.: NR Scenario It Spare Evurit# - 5, , arid Page 27Gf 36 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.

RD 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%.

BOP b. Charging and letdown IN SERVICE.

c. Pzr level TRENDING TO PZR REF LEVEL.

9. Verify proper Pzr pressure control as follows:

BOP a. Pzr pressure GREATER THAN 1845 PSIG.

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

10. Control SIG levels as follows:

RD a. Verify N/R level in any S/G GREATER THAN 11%.

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

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

12. Verify all AC busses are energized by offsite power as follows:

ATrain:

E FTA BIO NORM FDR FRM ATC- CLOSED El DIG IA BKR TO ETA OPEN -

BOP U IETA-ENERGIZED.

U B Train:

U FTB B!O NORM FDR FRM ATD CLOSED -

DIG lB BKR TO ETB - OPEN El IETB ENERGIZED.

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

RD a. Verify C-9 COND AVAILABLE FOR STM DUMP status light (1 SI-I 8) -

LIT.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 27 of 36

Appendix D Required Operator Actions Form ES-D-2 Op TestPo.: NRC - Scenario # Spare Event# 5,6, and 7 Pane 2 of 36 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 RD b. Verify all MSIVs OPEN.

c. Ensure STM DUMP CTRL SET AT 1090 PSIG STEAM HEADER RD PRESSURE.

d. WHEN the steam dump valves are closed, THEN:

1) Reset C-7A and C-7B.

2) Place STM DUMP CTRL in manual.

RD

3) Adjust STM DUMP CTRL to 0% demand.

4) Place steam dumps in pressure mode.

5) Place STM DUMP CTRL in auto.

BDP 14. Verify lB NC pump ON. -

15. Determine status of NtIs as follows:

a. Verify hR channels LESS THAN 10-10 AMPS.

RD

b. Verify SIR channels ENERGIZED.

c. Transfer one channel of the NIS RECDRDER to SIR instrumentation.

16. Maintain stable plant conditions as follows:

a. Pzr pressure at 2235 PSIG.

RO! b. Pzr level at PZR REF LEVEL.

BDP c. SIG NIR levels between 11% and 50%.

d. Verify at least one NC pump DN -

e. NC T-Avg at 557°F.

EVALUATOR NOTE: Depending on the speed of the crew in closing the main turbine stop valves. The rest of ES-0.1 is verification of proper plant responses FR-Hi will be entered when SJG NR levels are <11% and total CA flow is <

450 GPM,.

Appendix D Catawba NRC Exam Dec 2010 NUREG 1021 Revision 9 Page 28 of 36

Appendix D Required Operator Actions Form ES-D-2 OpTestNo. NR& 5cenancr# Spare Event# rage 29 ut Event

Description:

Loss of secondary heat sink.

Time Position Applicants Actions or Behavior EVALUATOR NOTE: The following steps are from EP1IIA!5000!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 SRO RETURN TO procedure and step in effect.

2. Verify secondary heat sink is required as follows:

a. NC pressure GREATER THAN ANY NON-FAULTED S/G RO PRESSURE.

b. Any NC T-Hot GREATER THAN 350°F.

RO/BOP 3. Monitor Enclosure I (Foldout Page).

BOP 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 Step6.

6. Ensure SIG BB and NM valves closed. REFER TO Enclosure 16 (SIG RO 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 1CA-4 (CA Pmps Suct From UST) OPEN. -

BOP c. Verify proper CA pump status as follows:

I) Power to both motor driven CA pumps AVAILABLE.

2) 1AD-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 29 of 36

Appendix D Required Operator Actions Form ES-D-2 Op Test No NRC Scenario# Spare Everrt# & - rage 30 - of 36 Event

Description:

Loss of secondary heat sink.

Time Position 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/N5200/007 (Troubleshooting Cause For CA Pump(s) Failing to Start).

b) Dispatch operator to verify proper CA valve alignment. REFER TO Enclosure 2 (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 (ISI-18) LIT.

Li Any MSIV OPEN.

b. Verify Steam Dumps in T-AVG MODE.

c. Place steam dumps in pressure mode as follows: