ML14290A321

2014-301 Final Simulator Scenarios

ML14290A321
Person / Time
Site:	Catawba
Issue date:	10/27/2014
From:	Division of Reactor Safety II
To:	Duke Energy Corp
Shared Package
ML14290A363	List: CNS-14-056, 301 General Correspondence ML14240A626 ML14240A660 ML14240A666 ML14240A671 ML14240A675 ML14290A076 ML14290A304 ML14290A321 ML14290A326 ML14290A330 ML14290A332
References
50-413/14-301, 50-414/14-301
Download: ML14290A321 (197)

Text

Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 1 of 42 NRC INITIAL LICENSE EXAM SCENARIO # 1 Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 2 of 42 Facility: Catawba NRC Exam 2014 Scenario No.: 1 Op Test No.: 2014301 Examiners: Operators: SRO RO BOP Initial Conditions: IC#176; Unit 1 is just below POAH, MOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance. Turnover: Unit 1 is just below POAH, MOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance. The crew is to shift operating KC (Component Cooling) pumps by starting the 1B2 KC pump and securing the 1B1 KC pump and then increase power to1% by withdrawing control rods. LCO 3.0.4.(b) has been assessed for the 1B NI Pump inoperability and Mode change has been authorized. Event No. Malf. No. Event Type* Event Description 1 --- N-BOP N-SRO Shift operating Component Cooling pumps. 2 --- R-RO N-SRO Withdraw control rods to increase reactor power to 1% 3 XMT-SG101 XMT-SG102 I-RO I-SRO 1D S/G W/R signal fails low. Feed reg. bypass valve opens. AP/06 4 RN001B C-BOP C-SRO RN (Nuclear Service Water) Pit B Screen Hi D/P. AP/20 5 FWP015C CA004B C-RO C-SRO TS-SRO 1B CF (Main Feed) Pump trips, 1B CA (AFW Pump fails to start) AP/06 6 NV066 C-BOP C-SRO TS-SRO 1A NV pump trips. Requires manual start of 1B NV pump. AP/12 7 NC008F NC009F M-ALL PZR PORV fails open. Manual closure attempt is unsuccessful. Manual block valve will not close. 8 NI001A C-BOP C-SRO 1A NI (Safety Injection) Pump fails to start in AUTO. 9 CA022A C-RO 1CA-152 fails to close on Feedwater Isolation * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 3 of 42 Scenario 1 Summary Initial Condition Unit 1 is just below POAH, MOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance. Turnover: Unit 1 just below POAH, MOL. Unit 2 at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump tagged out. The crew is to shift operating KC (Component Cooling) pumps by starting the 1B2 KC pump and securing the 1B1 KC pump and then increase power to 1% by withdrawing control rods. LCO 3.0.4.(b) has been assessed for the 1B NI Pump inoperability and Mode change has been authorized. Event 1 Shift operating Component Cooling pumps per OP/1/A/6400/005 (Component Cooling System), Enclosure 4.17 (Shifting KC Pumps). Event 2 Raise reactor power to 1%. Crew will use rods since unit is below POAH. Event 3 1D S/G W/R level signal fails LOW; associated Feed Reg. Bypass Valve opens. RO takes manual control to stabilize and restore 1D S/G level. AP/06 (Loss of SG Feedwater) Case III entry. This failure is internal to the DCS and does not indicate on the W/R level board indication. Event 4 AP/20 (Loss of Nuclear Service Water) entry. TS evaluation will indicate no LCO entry required. Event 5 1B Main Feedwater Pump trips, along with the failure of the 1B AFW pump to auto start. AP/06 Case I entry. A TS evaluation required due to failure of the 1B AFW pump to start. Event 6 1A NV Pump (Charging) trips. BOP manually starts the 1B NV pump to restore charging and letdown. AP/12 (Loss of Charging or Letdown) will be entered. TS evaluation required. Event 7 1NC-36B (PZR PORV) fails open. RO attempts manual closure of the PORV. This will not be successful. AP/11 (Pressurizer Pressure Anomalies) entry. This is the major event because the PZR PORV cannot be closed, nor will the manual block isolation close. Recognizing a LOCA, the crew will determine that the reactor must be tripped. Event 8 1A NI (Safety Injection) Pump fails to auto start on the SI signal. BOP manually starts to establish intermediate head injection flow. Event 9 1CA-152 (S/G 1D CF BYP TO CA NOZZLE) fails to close on the feedwater isolation. RO manually closes the valve. Critical Task 1 Establish flow from at least one intermediate head ECCS pump prior to transition from E-0.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 4 of 42 Critical Task 2 Trip NC pumps on loss of subcooling with S/I flow verified per E-0 within 5 minutes of criteria met. Critical Task 3 and 4 - Control S/G level to avoid RPS actuation. EXERCISE GUIDE WORKSHEET 1. INITIAL CONDITIONS: 1.1 Reset to IC 176 START TIME:__________ Trigger Instructor Action Final Delay Ramp Delete In Event 1 XMT-SG101 [XCF_5641 S/G D W/R LVL CH 1 TO DCS/ELSEWHERE (CFAA5641)] 40 3 MIN 3 1 XMT-SG102 [XCF_5642 S/G D W/R LVL CH 2 TO DCS/ELSEWHERE (CFAA5642)] 40 3 MIN 3 3 MAL-RN001B (RN PIT SCREEN B HI D/P) 97 4 5 OVR-FWP015C (CFPT 1B TRIP_RESET TRIP PB) ON 5 n/a MAL-CA004B FAILURE OF CA PUMP B TO START) BOTH 5 7 LOA-NV066 (RACKOUT NV PMP 1A) RACKOUT 6 9 VLV-NC009F (NC36B PZR PORV FAIL TO POSITION) 1 7 n/a VLV-NC008F (NC35B PORV ISOL VLV FAIL TO POSITION) 1 7 n/a MAL-NI001A (NI PUMP A FAILURE) AUTO 8 n/a VLV-CA022A (CA152 S/G MAIN CF BYP TO CA NOZ FAIL AUTO ACTIONS) 9 n/a LOA-NI004 (RACKOUT NI PMP 1B) RACKOUT n/a LOA-RC068 (RACKOUT RC PMP 1D) RACKOUT Place red collars on the 1B NI Pump and the 1D RC Pump.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 5 of 42 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, Shift KC Pumps BOOTH INSTRUCTOR ACTION IF Operator dispatched to perform a pre-operational pump checkout, REPEAT the information. BOOTH INSTRUCTOR ACTION WHEN one minute has elapsed from the start of the 1B2 KC Pump, CALL the control room and inform them that the 1B2 KC Pump looks good for a continuous run. 3.3 Scenario EVENT 2, Increase reactor power to 1% 3.4 Scenario EVENT 3, 1D S/G W/R Level Failure BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 1 to give a failure of 1D S/G W/R level. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with 1D S/G W/R level instrumentation REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Operator is dispatched to verify S/G level indication on the Aux Shutdown Panels, REPORT 1D S/G Level is reading 40%.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 6 of 42 3.5 Scenario EVENT 4, RN Pit B Screen Hi D/P BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause the RN Pit B Hi D/P. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with RN Pit B, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF an Operator and/or Maintenance are dispatched to investigate RN Pit B, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Operator dispatched to check out the RN pump that was started, REPEAT the information. BOOTH INSTRUCTOR ACTION IF Environmental Chemistry is contacted, REPEAT back the information. 3.6 Scenario EVENT 5, 1B CFPT trips, 1B CA Pump fails to start BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to cause the 1B CFPT to trip. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with 1B CFPT, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF an Operator and/or Maintenance are dispatched to investigate the 1B CA pump and/or breaker, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with 1B CA Pump, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF an Operator is dispatched to perform the alarm response for the 1B CFPT, REPEAT back the information.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 7 of 42 3.7 Scenario EVENT 6, 1A NV Charging Pump trips BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 7 to cause the 1A NV Charging Pump to trip. BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance are dispatched to investigate the 1A NV Pump and/or breaker, Repeat back the information. BOOTH INSTRUCTOR ACTION IF an Operator dispatched to breaker and/or pump, after 10 minutes REPORT: No relays are present on the breaker and no abnormal conditions are noted at the pump. BOOTH INSTRUCTOR ACTION IF NEO dispatched to check the 1B NV Pump, after 5 minutes REPORT: The 1B NV Pump looks good for continuous run. BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with 1A NV Pump, REPEAT back the information. 3.8 Scenario EVENTS 7,8,AND 9 1NC-36B fails open, 1NC-35B will not close, 1B NI Pump will not start on Safety Injection, 1CA-152 (S/G 1D CF BYB TO CA NOZZLE) fails to close on feedwater isolation. BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 9 to cause the 1NC-36B to fail open. BOOTH INSTRUCTOR ACTION IF SWM is contacted to investigate 1NC-36B and/or 1NC-35B, REPEAT back the order. BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance are dispatched to investigate the 1A NI Pump and/or breaker, REPEAT the order. BOOTH INSTRUCTOR ACTION IF Operator is dispatched to secure all ice condenser air handling units and place Hydrogen Analyzers in service, REPEAT the order. BOOTH INSTRUCTOR ACTION IF Secondary Chemistry is notified to sample all S/Gs for activity, REPEAT the order.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 8 of 42 BOOTH INSTRUCTOR ACTION IF RP is notified to frisk all cation columns for activity, REPEAT the order.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 9 of 42 Event

Description:

Shift operating KC (Component Cooling) Pumps. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 9 of 42 EVENT 1 NOTE TO EVALUATOR: Crew begins by shifting the operating Component Cooling pumps per OP/1/A/6400/005 (Component Cooling System), Enclosure 4.17 (Shifting KC Pumps). NOTE TO EVALUATOR: The crew may have a Focus Brief and then make a plant page announcing the start of the 1B2 KC Pump. BOP Start 1B2 KC Pump BOP Secure 1B1 KC Pump NOTE TO EVALUATOR: The following actions are from OP/1/A/6400/005 (Component Cooling System), Enclosure 4.17 (Shifting KC Pumps). BOP 3.2 IF shifting KC Train 1B pumps, perform the following: 3.2.1 Start the idle KC Train 1B pump: "KC PUMP B1" "KC PUMP B2" NOTE: 1KC-C40B (Train B Miniflow Isol) may open during performance of the next step. BOP 3.2.2 Adjust the following flow controllers on 1MC11 to zero gpm flow: 1KC-149 (KF Hx 1A Cool Wtr Otlt) 1KC-156 (KF Hx 1B Cool Wtr Otlt) BOP 3.2.3 Stop the desired KC Train 1B pump: "KC PUMP B1" OR "KC PUMP B2" BOP 3.2.4 IF KC Train 1B flow approaches 5700 gpm while performing the next step, ensure 1KC-C40B (Train B Miniflow Isol) is closed.

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

Description:

Shift operating KC (Component Cooling) Pumps. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 10 of 42 BOP 3.2.5 Perform the following for the KF cooling loops that are in service: Adjust 1KC-149 (KF Hx 1A Cool Wtr Otlt) flow controller on 1MC11 to 3000 gpm or as necessary to maintain Spent Fuel Pool temperature < 125F. Adjust 1KC-156 (KF Hx 1B Cool Wtr Otlt) flow controller on 1MC11 to 3000 gpm or as necessary to maintain Spent Fuel Pool temperature < 125F. END OF EVENT 1 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 11 of 42 Event

Description:

Increase reactor power to 1% Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 11 of 42 EVENT 2 RO Withdraw control rods to increase reactor power. NOTE TO EVALUATOR: The following actions are from OP/1/A/6100/001 (Controlling Procedure for Unit Startup), Enclosure 4.1 (Unit Startup). 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 S/G bypass reg valve affects the other S/G bypass reg valves. Therefore, SM/CF to be monitored as the unit approaches POAH. 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. Unit One R.O.D. Section 5.10 provides 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/A/4150/001 J (Zero Power Physics Testing), until the turbine is placed on line. (SOMP 01-02). (R.M.) 6. Per SOER 07-01 (Reactivity Management) it is recommended that Plant Operators monitor multiple indications such as Thermal Power Best Estimate, Nuclear Instrumentation, Steam Pressure. , CF Flowrate, and Turbine Load when making at power reactivity changes. (R.M.) RO 3.178 Increase reactor power to 1%. (R.M.) END OF EVENT 2 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 12 of 42 Event

Description:

1D S/G W/R Level Failure Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 12 of 42 EVENT 3 Indications: 1CF-57 (S/G 1D CF BYB CTRL) begins to open 1CAP5120 (CA FLOW TO S/G 1D) indication increases to top of scale. S/G 1D Level begins to increase. 1AD- 1AD-2, F- RO Recognizes 1CF-57 (S/G 1D CF BYP CTRL) opening. RO Take manual control of 1CF-55 (S/G 1D CF CTRL) and 1CF-57 (S/G 1D CF BYP CTRL) and control 1D S/G level at normal level. SRO Crew enters AP/1/A/5500/006, CASE III. NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/006, Loss of S/G Feedwater. NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/006, Loss of S/G Feedwater, Case III (CF Control Not in Auto) CREW 1. IF AT ANY TIME S/G levels approaching: 83% N/R level (S/G HI-HI Level Turb Trip) OR 11% N/R level (S/G LO-LO Level Rx Trip). THEN: a. Manually trip reactor. b. GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection). RO or BOP 2. Verify the following: At least one CF pump - IN SERVICE 1AD-3, C/6 "CF ISOL TRN A" - DARK 1AD-3, D/6 "CF ISOL TRN B" - DARK. RO or BOP 3. IF AT ANY TIME any CF main feed reg valve in manual, THEN ensure associated feed reg bypass valve in manual. RO or BOP 4. Verify CF pump speed controller for in service CF pump(s): IN AUTO RESPONDING ADEQUATELY RO or BOP 5. Verify all S/G CF control valves: IN AUTO RESPONDING ADEQUATELY Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 13 of 42 Event

Description:

1D S/G W/R Level Failure Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 13 of 42 CRITICAL TASK #3 RO or BOP 5. RNO Perform the following for the affected S/G(s): a. Ensure affected controller(s) IN MANUAL. b. IF AT ANY TIME S/G level not on program, THEN 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. RO or BOP 6. Verify the following: S/G level(s) - STABLE S/G level(s) - APPROXIMATELY AT PROGRAM Malfunction - CORRECTED CREW 6. RNO Perform the following: a. Continue to control CF/SM D/P and S/G CF Flow rates to stabilize level in affected S/G(s) approximately at program level. b. WHEN all the following conditions met: S/G level(s) - STABLE S/G level(s) - APPROXIMATELY AT PROGRAM Malfunction - CORRECTED. THEN GO TO Step 7. c. Do not continue in this procedure until all conditions met. NOTE TO EVALUATOR: The SRO may address Tech Spec 3.3.3 [Post Accident Monitoring (PAM) Instrumentation], but it does not apply. Tech Spec 3.3.4 (Remote Shutdown System) does not apply because Aux Feedwater Flow instrumentation is available summarize the event. END OF EVENT 3 Booth Operator will insert Trigger 3 for EVENT 4 at the discretion of the lead examiner.

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

Description:

RN Pit Screen B Hi D/P Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 14 of 42 EVENT 4 Indications: 1AD-12, B/5 B OAC PT. C1A1006 B BOP B CREW Enter AP/0/A/5500/020 (Loss of Nuclear Service Water) BOP Swap suctions and discharges to the SNSWP NOTE TO EVALUATOR: The crew may choose to use the annunciator response to address this event. REFER to Attachment 4. NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/020, Loss of Nuclear Service Water. NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/020, Loss of Nuclear Service Water, Case II (Loss of RN Pit Level) BOP 1. Verify the following alarms - DARK: 1AD-12, B/2 "RN PIT A SCREEN HI D/P" 1AD-12, B/5 "RN PIT B SCREEN HI BOP 1. RNO IF the operating RN pump is on the affected pit with high D/P, THEN align RN to SNSWP. REFER TO Enclosure 2 (RN Valve Alignment for RN Swap to SNSWP). NOTE TO EVALUATOR: The SRO may choose to read Enclosure 2 or hand Enclosure 2 to the BOP to perform. NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/020, Loss of Nuclear Service Water, Enclosure 2 (RN Valve Alignment for RN Swap to the SNSWP). BOP 1. Ensure the following valves - OPEN: 1RN-3A (RN P/H Pit A Isol From SNSWP) 1RN-4B (RN P/H Pit B Isol From SNSWP) 1RN-58B (RN Hdr B Ret To SNSWP) 1RN-63A (RN Hdr A Ret To SNSWP) 1RN-846A (D/G 1A Hx Ret To SNSWP) 1RN-848B (D/G 1B Hx Ret To SNSWP) 2RN-846A (D/G 2A Hx Ret To SNSWP) 2RN-848B (D/G 2B Hx Ret To SNSWP).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 15 of 42 Event

Description:

RN Pit Screen B Hi D/P Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 15 of 42 BOP 2. Ensure the following valves - CLOSED: 1RN-1A (RN P/H Pit A Isol From Lake) 1RN-2B (RN P/H Pit A Isol From Lake) 1RN-5A (RN P/H Pit B Isol From Lake) 1RN-6B (RN P/H Pit B Isol From Lake) 1RN-53B (Station RN Disch Hdr X-Over) 1RN-54A (Station RN Disch Hdr X-Over) 1RN-57A (Station RN Disch To RL Sys) 1RN-843B (Station RN Disch To RL Sys) 1RN-49A (Non-Ess Supply Hdr Isol) 1RN-50B (Non-Ess Supply Hdr Isol) 2RN-49A (Non-Ess Supply Hdr Isol) 2RN-50B (Non-Ess Supply Hdr Isol) 1RN-847A (D/G 1A Hx Ret To Lake) 1RN-849B (D/G 1B Hx Ret To Lake) 2RN-847A (D/G 2A Hx Ret To Lake) 2RN-849B (D/G 2B Hx Ret To Lake). NOTE TO EVALUATOR: Step 3 will not apply. NOTE TO EVALUATOR: Step 4 will not apply. BOP 5. IF RN Pit B initiated the auto or manual swap to the SNSWP, THEN ensure the following valves are closed: 1RN-47A (RN Supply X-Over Isol) 2RN-47A (RN Supply X-Over Isol). NOTE TO EVALUATOR: End of Enclosure 2 BOP 2. Start idle RN pump(s) on the unaffected train. BOP 3. Verify affected pit level adequate as follows: 1AD-12, B/1 "RN PUMP INTAKE PIT A LEVEL-LO" - DARK 1AD-12, B/4 "RN PUMP INTAKE PIT B LEVEL-LO" - DARK 2AD-12, B/1 "RN PUMP INTAKE PIT A LEVEL-LO" - DARK 2AD-12, B/4 "RN PUMP INTAKE PIT B LEVEL-LO" - DARK Affected pit level indication - STABLE OR INCREASING. BOP 4. Verify each operating RN pump discharge flow - LESS THAN 23,000 GPM.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 16 of 42 Event

Description:

RN Pit Screen B Hi D/P Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 16 of 42 NOTE After automatic swapover to SNSWP on emergency-low RN pit level, RN swap to SNSWP annunciators will only be lit for 2 minutes following swapover. BOP 5. IF any of the following alarms are lit OR were previously lit: 1AD-12, E/2 "RN PIT A SWAP TO SNSWP" OR 2AD-12, E/2 "RN PIT A SWAP TO SNSWP" OR 1AD-12, E/5 "RN PIT B SWAP TO SNSWP" OR 2AD-12, E/5 "RN PIT B SWAP TO SNSWP". THEN perform the following: a. Ensure all RN pumps - ON. b. Ensure correct RN valve alignment. REFER TO Enclosure 2 (RN Valve Alignment for RN Swap to SNSWP). c. IF AT ANY TIME RN pump(s) running on RN pit with LO-LO level, THEN secure affected pump(s). d. IF WL discharge in progress, THEN coordinate with Radwaste Chemistry to secure all controlled WL discharges. e. IF any RN chemical addition is in progress, THEN have Chemistry secure it. BOP 6. Verify SNSWP level adequate and stable as follows: 1AD-12, A/3 "SNSWP LEVEL LO" - DARK SNSWP level indication - STABLE. NOTE TO EVALUATOR: BOP 7. Ensure proper alignment of RN to KC Hxs as follows: a. Verify RN - ALIGNED TO KC HX(S) IN SERVICE. b. Ensure KC Hx Otlt Mode switches - PROPERLY ALIGNED.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 17 of 42 Event

Description:

RN Pit Screen B Hi D/P Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 17 of 42 BOP 8. Verify each operating RN pump discharge flow - GREATER THAN 8,600 GPM. CREW 9. Determine and correct cause of loss of RN pit level. BOP 10. Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual: SLC 16.7-6 (RN Discharge Instrumentation) 3.3.2 (Engineered Safety Features Actuation System (ESFAS) Instrumentation). 3.6.5 (Containment Air Temperature) 3.7.8 (Nuclear Service Water System (NSWS)) 3.7.9 (Standby Nuclear Service Water Pond (SNSWP)). NOTE TO EVALUATOR: No Tech Spec Actions need to be entered. Booth Operator will insert Trigger 5 for EVENT 5 at the discretion of the lead examiner. SRO 11. Determine required notifications: REFER TO RP/0/A/5000/001 (Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). CREW 12. WHEN corrective action for loss of pit level taken, THEN restore RN to normal alignment. REFER TO Enclosure 3 (Returning RN alignment To Normal After Transfer To SNSWP). BOP 13. Ensure RN pumps - IN OPERATION AS NEEDED. BOP 14. Verify each operating RN pump discharge flow - GREATER THAN 8,600 GPM. BOP 15. Notify Environmental Chemistry of any RN pump shifts that have occurred. SRO 16. Determine long term plant status. RETURN TO procedure in effect. summarize the event. END OF EVENT 4 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 5 Page 18 of 42 Event

Description:

1B CF (Main Feedwater) Pump Trips, 1B CA (Auxiliary Feedwater) Pump fails to start Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 18 of 42 INDICATIONS: 1AD- 1AD- 1AD-- 1AD- 1AD- 1AD-5, CB 1AD/5, CB RO Recognize 1B CFPT Trip and subsequent loss of feedwater. RO Recognize failure of 1B CA Pump to start and attempts to start it. CREW ENTERS AP/1/A/5500/006, CASE I NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/006, Loss of S/G Feedwater. NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/006, Loss of S/G Feedwater, Case I (Loss of CF Supply To S/Gs) RO 1. Verify reactor power - LESS THAN 5%. RO 2. Verify all S/G hi-hi level alert alarms (1AD-4) - DARK. RO 3. Verify 1AD-2, F/9 "DCS ALTERNATE ACTION" - DARK. RO 4. Verify total CA flow - GREATER THAN Perform the following: 450 GPM. RO 5. Control S/G levels as follows: a. Verify all S/G N/R levels GREATER THAN 11%. RO 5.a. RNO a. Maintain total feed flow greater than 450 GPM to intact S/Gs until at least one S/G N/R level greater than 11%. CRITICAL TASK #4 RO b. WHEN at least one S/G N/R level is greater than 11%, THEN throttle feedflow to maintain all S/G N/R levels between 11% - 50%. SRO 6. REFER TO Case II (Loss of Normal CA Supply). NOTE TO EVALUATOR: The crew may initiate a makeup to the UST per step 2 of Case II. No other actions from Case II are necessary.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 5 Page 19 of 42 Event

Description:

1B CF (Main Feedwater) Pump Trips, 1B CA (Auxiliary Feedwater) Pump fails to start Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 19 of 42 SRO 7. Ensure compliance with appropriate Tech Specs and SLCs: 3.3.2 (ESFAS Instrumentation) 3.7.5 (Auxiliary Feedwater System) SLC 16-7.1 (AMSAC). SLC 16-7.14 (Trip of All Main Feedwater Pumps Turbine Trip Instrumentation). NOTE TO EVALUATOR: T.S 3.7.5 Auxiliary Feedwater (AFW) System Condition B (Restore AFW train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) should be entered. Per T.S. 3.7.5, LCO 3.0.4.(b) does not apply and Mode change is not allowed now. Tech Spec conditions that have been entered. Booth Operator will insert Trigger 7 for EVENT 6 at the discretion of the lead examiner. SRO 8. Determine required notifications: REFER TO RP/0/A/5000/001 (Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). CREW 9. Determine and correct cause of loss of CF supply. RO 10. Verify at least one CF Pump - ON. NOTE TO EVALUATOR: It is not intended for the next step to be performed in this scenario. BOP 10. RNO Perform a hot restart of one CF Pump. REFER TO OP/1/A/6250/001 (Condensate and Feedwater System). NOTE TO EVALUATOR: Due to the likelihood that the scenario will progress to the next event prior to completing all of the steps of the AP, the SRO will END OF EVENT 5 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 20 of 42 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 20 of 42 EVENT 6 Indications: 1AD- 1AD- 1AD- BOP Recognizes 1A NV pump tripped CREW Enters AP/1/A/5500/012, Loss of Charging or Letdown NOTE TO EVALUATOR: The following steps are taken from AP/1/A/5500/012, Loss of Charging or Letdown, Case I (Loss of Charging). RO 1. Stop any power changes. BOP 2. Ensure the following letdown isolation valves - CLOSED: 1NV-10A (Letdn Orif 1B Otlt Cont Isol) 1NV-11A (Letdn Orif 1C Otlt Cont Isol) 1NV-13A (Letdn Orif 1A Otlt Cont Isol). BOP 3. Ensure any malfunctioning NV pump - SECURED. BOP or RO 4. Monitor conditions for continued NC pump operation as follows: NC pump #1 seal outlet temperature - LESS THAN 235°F NC pump lower bearing temperature - LESS THAN 225°F. NOTE TO EVALUATOR: Step 5 will not apply. 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. BOP 6. Verify NV pump status as follows: At least one NV pump - ON. BOP 6. RNO Perform the following: a. Ensure any malfunctioning NV pump - SECURED. b. Ensure the following valves - OPEN: 1NV-203A (NV Pumps A&B Recirc Isol) 1NV-202B (NV Pmps A&B Recirc Isol).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 21 of 42 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 21 of 42 BOP c. Ensure only one suction source as follows: VCT 1NV-188A (VCT Otlt Isol) - OPEN 1NV-189B (VCT Otlt Isol) - OPEN VCT level - GREATER THAN 23% 1NV-252A (NV Pumps Suct From FWST) - CLOSED 1NV-253B (NV Pumps Suct From FWST) - CLOSED. NOTE TO EVALUATOR: The crew will determine that step 6 RNO d. does not apply BOP e. Start the available NV pump as follows: 1) OPEN 1NV-309 (Seal Water Injection Flow) to full open. 2) CLOSE 1NV-294 (NV Pmps A&B Disch Flow Ctrl). 3) Start NV pump aux oil pump. 4) Start available NV pump. 5) Stop NV pump aux oil pump. NOTE TO EVALUATOR: The crew will determine that step 6 RNO e.6) does not apply NOTE TO EVALUATOR: The crew will determine that step 6 RNO f. does not apply BOP 7. Verify charging header aligned to NC loop as follows: a. 1NV-312A (Chrg Line Cont Isol) - OPEN. b. 1NV-314B (Chrg Line Cont Isol) - OPEN. c. Verify one of the following valves - OPEN: 1NV-32B (NV Supply To Loop A Isol) OR 1NV-39A (NV Supply To Loop D Isol). d. Verify the following NC pump conditions: #1 seal outlet temperatures less than or equal to 180°F Lower bearing temperatures less than or equal to 180°F. e. Verify 1NV-294 (NV Pmps A&B Disch Flow Ctrl) - OPEN. BOP 7.e. RNO e. Perform the following: 1) OPEN 1NV-309 (Seal Water Injection Flow). 2) THROTTLE 1NV-294 (NV Pmps A&B Disch Flow Ctrl) to establish greater than 32 GPM "N/R CHRG LN FLOW" Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 22 of 42 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 22 of 42 BOP 8. Verify the following: "TOTAL SEAL WTR FLOW" - GREATER THAN 32 GPM 1NV-309 (Seal Water Injection Flow) IN AUTO. BOP 8. RNO Perform the following: a. IF any NC pump #1 seal outlet temperature OR lower bearing temperature greater than 180°F, THEN maintain cooldown rate less than or equal to 1°F per minute. b. Slowly THROTTLE 1NV-309 (Seal Injection Flow) to establish 32 GPM "TOTAL SEAL WTR FLOW" c. Place 1NV-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 1C" - ON. BOP 12. Control VCT level as follows: a. Verify NC system makeup - SET FOR DESIRED BORON CONCENTRATION. b. Verify "NC MAKEUP MODE SELECT" - IN AUTO. BOP 13. Verify normal letdown - IN SERVICE. NOTE TO EVALUATOR: Step a. will not be performed and step b. will be applicable. The SRO may wait to evaluate Tech Specs until after the restoration of letdown. NOTE TO EVALUATOR: To shorten the scenario, the Booth Operator can insert Trigger 9 to start the Major at the discretion of the lead examiner and the Tech Specs can be covered by follow up questioning. SRO 13. RNO Perform the following: b. Restore normal letdown. REFER TO Case II (Loss of Letdown).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 23 of 42 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 23 of 42 SRO 14. Ensure compliance with appropriate Tech Specs: 3.4.13 (RCS Operational Leakage) 3.4.14 (RCS Pressure Isolation Valve (PIV) Leakage) 3.5.2 (ECCS - Operating) 3.5.3 (ECCS - Shutdown) 3.5.5 (Seal Injection Flow) 3.6.3 (Containment Isolation Valves) SLC 16.9-9 (Boration Systems Charging Pump - Shutdown) SLC 16.9-10 (Boration Systems Charging Pump - Operating). NOTE TO EVALUATOR: SRO will determine that Tech Spec 3.5.2 (ECCS-Operating) Condition A (Restore train to OPERABLE status 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) continues to apply and SLC 16.9-10 (Borating Systems Charging Pump Operating) Condition A (Restore non-functional pump to FUNCTIONAL status 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) should be entered. SRO 15. Determine required notifications: REFER TO RP/0/A/5000/001 (Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). 16. Verify at least one NV pump - ON. NOTE TO EVALUATOR: Step 17 will not apply SRO 18. Determine long term plant status. RETURN TO procedure in effect.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 24 of 42 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 24 of 42 NOTE TO EVALUATOR: The following steps are taken from AP/1/A/5500/012, Loss of Charging or Letdown, Case II (Loss of Letdown). RO 1. Stop any power changes. BOP 2. Ensure the following letdown isolation valves - CLOSED: 1NV-10A (Letdn Orif 1B Otlt Cont Isol) 1NV-11A (Letdn Orif 1C Otlt Cont Isol) 1NV-13A (Letdn Orif 1A Otlt Cont Isol). BOP 3. Verify Pzr level - GREATER THAN 17%. BOP 4. Control charging to stabilize Pzr level at program level while maintaining seal injection flow. BOP 5. Ensure "PZR HTR GROUP 1C" - ON. BOP 6. Control VCT level as follows: a. Verify NC system makeup - SET FOR DESIRED BORON CONCENTRATION. b. Verify "NC MAKEUP MODE SELECT" - IN AUTO. BOP 7. Determine and correct cause of loss of letdown. BOP 8. IF AT ANY TIME excess letdown required, THEN establish excess letdown. REFER TO OP/1/A/6200/001 (Chemical and Volume Control System). BOP 9. Verify proper VC/YC system operation. REFER TO Enclosure 3 (Control Room Ventilation System Verification).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 25 of 42 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 25 of 42 NOTE TO EVALUATOR: The SRO may wait to evaluate Tech Specs until after the restoration of letdown. SRO 10. Ensure compliance with appropriate Tech Specs: 3.3.1 (Reactor Trip System (RTS) Instrumentation) 3.3.3 (Post Accident Monitoring (PAM) Instrumentation) 3.3.4 (Remote Shutdown System) 3.4.1 (RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits) 3.4.12 (Low Temperature Overpressure Protection (LTOP) System) 3.4.13 RCS (Operational Leakage). 3.6.3 (Containment Isolation Valves). NOTE TO EVALUATOR: The SRO will determine that no Tech Specs apply for the loss of letdown. BOP 11. Verify at least one of the following valves - CLOSED: 1NV-1A (NC Letdn To Regen Hx Isol) OR 1NV-2A (NC Letdn To Regen Hx Isol). SRO 11. RNO GO TO Step 16. BOP 16. Establish letdown as follows: a. Verify ability to establish normal letdown - RESTORED. b. Ensure 1NV-849 (Letdn Flow Var Orif Ctrl) valve demand position - 0%. c. Verify the following valves - OPEN: 1NV-1A (NC Letdn To Regen Hx Isol) 1NV-2A (NC Letdn To Regen Hx Isol). NOTE If LTOP is in service, then 1NC-34A will be made inoperable when the only letdown path aligned is NV system normal letdown. 1NC-34A LTOP operability is based on the letdown alignment. (PIP C-10-1320)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 26 of 42 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 26 of 42 BOP d. OPEN the following valves: 1NV-15B (Letdn Cont Isol) 1NV-10A (Letdn Orif 1B Otlt Cont Isol). e. Adjust 1NV-294 (NV Pmps A&B Disch Flow Ctrl) as necessary to maintain letdown subcooled in following steps. f. THROTTLE 1NV-148 (Letdn Press Control) to 45% demand. g. THROTTLE open 1NV-849 (Letdn Flow Var Orif Ctrl) in 1% to 5% increments until one of the following conditions met: Letdown flow and letdown pressure increases OR Valve demand position is 60% open. SRO h. Do not continue until one of the above conditions met. BOP i. Verify letdown flow and letdown pressure - HAS INCREASED. BOP j. Adjust 1NV-148 (Letdn Press Control) to maintain letdown pressure between 150 - 200 PSIG. NOTE TO EVALUATOR: Time compression may be used in the following step at the discretion of the lead examiner. BOP k. WHEN 5 minutes have elapsed, THEN perform the following: 1) Adjust 1NV-849 (Letdn Flow Var Orif Ctrl) in 1% to 5% increments to desired letdown flow. 2) WHEN letdown at desired flow, THEN perform the following: a) Adjust 1NV-148 (Letdn Press Control) to maintain letdown pressure at 350 PSIG. b) Ensure 1NV-148 (Letdn Press Control) - IN AUTO. Booth Operator will insert Trigger 9 for EVENT 7 at discretion of lead examiner. BOP 3) IF AT ANY TIME additional letdown flow desired, THEN establish letdown with the 45 or 75 GPM orifice. REFER TO OP/1/A/6200/001 (Chemical and Volume Control System).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 27 of 42 Event

Description:

1A NV (Chemical and Volume Control) Charging Pump Trips, Loss of Charging and Letdown Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 27 of 42 BOP l. WHEN Pzr level restored to programmed level, THEN perform the following: 1) Ensure 1NV-294 (NV Pmps A&B Disch Flow Ctrl) - IN AUTO. 2) Ensure "PZR Level Master" IN AUTO. SRO 17. Determine required notifications: REFER TO RP/0/A/5000/001 (Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). BOP 18. Verify excess letdown - ISOLATED. SRO 19. Determine long term plant status. RETURN TO procedure in effect. END OF EVENT 6 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7 Page 28 of 42 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 28 of 42 EVENT 7 Indications: 1AD- 1AD- 1AD- BOP Recognize 1NC-36B open BOP Attempt to close 1NC-36B BOP Attempt to close 1NC-35B RO Manually Trip the Reactor BOP Manually initiate Safety Injection. NOTE TO EVALUATOR: Due to the immediate action nature of the event, it is not anticipated that the crew will have time to make a plant page announcing the entry into AP/1/A/5500/0011, Pressurizer Pressure Anomalies. NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/011, Pressurizer Pressure Anomalies, Case I (Pressurizer Pressure Decreasing). BOP 1. Verify all Pzr PORVs - CLOSED. BOP 1. RNO Perform the following: a. Close Pzr PORV(s). b. IF any Pzr PORV cannot be closed, THEN: 1) Close the affected PORV(s) isolation valve. 2) IF the Pzr PORV isolation valve cannot be closed, THEN perform the following: a) IF in Mode 3 with CLAs isolated OR in Mode 4, THEN GO TO AP/1/A/5500/027 (Shutdown LOCA). RO b) Trip reactor. BOP c) WHEN reactor tripped OR S/I setpoint reached, THEN ensure S/I initiated. EVENTS 8 AND 9 CREW d) GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection). TRANSITION TO E-0 (Reactor Trip or Safety Injection)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8 and 9 Page 29 of 42 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close, 1B NI Pump fails to auto start on SI signal, 1CA-152 (S/G 1D CF BYP TO CA NOZZLE) fails to close on feedwater isolation. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 29 of 42 NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) RO and BOP 1. Monitor Enclosure 1 (Foldout Page). RO 2. Verify Reactor Trip: Perform the following: All rod bottom lights - LIT All reactor trip and bypass breakers - OPEN I/R power - DECREASING. RO 3. Verify Turbine Trip: Perform the following: All turbine stop valves - CLOSED BOP 4. Verify 1ETA and 1ETB - ENERGIZED. RO 5. Verify S/I is actuated: a. "SAFETY INJECTION ACTUATED" status light (1SI-13) LIT b. Both E/S load sequencer actuated status lights (1SI-14) - LIT. NOTE TO EVALUATOR: will trip the NC (Reactor Coolant) pumps within 5 minutes per Enclosure 1 guidance. This satisfies Critical Task # 2 RO 6. Announce "Unit 1 Safety Injection". SRO 7. Determine required notifications: REFER TO RP/0/A/5000/001(Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). RO or BOP 8. Verify all Feedwater Isolation status lights (1SI-5) - LIT RO 8. RNO Perform the following: a. Initiate Feedwater Isolation. b. IF proper status light indication not obtained, THEN CLOSE valves END OF EVENT 9 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7 and 8 Page 30 of 42 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close, 1B NI Pump fails to auto start on SI signal Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 30 of 42 BOP 9. Verify Phase A Containment Isolation status as follows: a. Phase A "RESET" lights - DARK. BOP b. Monitor Light Panel Group 5 St lights on energized train(s) - LIT. BOP 10. Verify proper Phase B actuation as follows: a. Verify Containment pressure - HAS REMAINED LESS THAN 3 PSIG RO or BOP b. IF AT ANY TIME containment pressure exceeds 3 PSIG while in this procedure, THEN perform Step 10.a. RO 11. Verify proper CA pump status as follows: a. Motor driven CA pumps - ON. b. 3 S/G N/R levels - GREATER THAN 11%. RO 11.a. RNO a. Perform the following for affected train(s): 1) Reset ECCS. 2) Reset D/G load sequencer(s), 3) Start affected pump(s). RO and BOP 4) IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on. BOP 12. Verify all of the following S/I pumps - ON: Perform the following for affected train(s): NV pumps ND pumps NI pumps. CRITICAL TASK #1 BOP 12. RNO Perform the following for affected train(s): a. Reset ECCS. b. Reset D/G load sequencer(s) c. Start affected pump(s). RO and BOP d. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on. END OF EVENT 8 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7 Page 31 of 42 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 31 of 42 BOP 13. Verify all KC pumps - ON. BOP 14. Verify all Unit 1 and Unit 2 RN pumps BOP 15. Verify proper ventilation systems operation as follows: REFER TO Enclosure 2 (Ventilation System Verification). Notify Unit 2 operator to perform Enclosure 3 (Opposite Unit Ventilation Verification). NOTE TO EVALUATOR: SRO will state that they will hand Enclosure 3 to a Unit 2 operator and set Enclosure 3 off to the side. RO 16. Verify all S/G pressures - GREATER THAN 775 PSIG. RO 17. Verify proper S/I flow as follows: a. "NV S/I FLOW" - INDICATING FLOW. b. NC pressure - LESS THAN 1620 PSIG. c. NI pumps - INDICATING FLOW. d. NC pressure - LESS THAN 285 PSIG. RO 17.d. RNO d. Perform the following: 1) Ensure ND pump miniflow valve on operating ND pump(s) - OPEN. NOTE TO EVALUATOR: Step 17 RNO d. 2) will not apply SRO 3) GO TO Step 18. RO or BOP 18. WHEN time and manpower permit (within two hours of event), THEN monitor Spent Fuel Pool level and temperature. REFER TO EP/1/A/5000/G-1(Generic Enclosures), Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring). RO 19. Control S/G levels as follows: a. Verify total CA flow - GREATER THAN 450 GPM. NOTE TO EVALUATOR: Total CA flow may not be > 450 gpm due to being under operator control, in which case, the RNO for 19 a. will not apply. RO b. WHEN each S/G N/R level greater than 11% (29% ACC), THEN control feed flow to maintain that S/G N/R level between 11% (29% ACC) and 50%. RO 20. Verify all CA isolation valves - OPEN.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7 Page 32 of 42 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 32 of 42 BOP 21. Verify S/I equipment status based on monitor light panel - IN PROPER ALIGNMENT. BOP 21. RNO Align equipment. NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance. RO 22. Control NC temperature. REFER TO Enclosure 4 (NC Temperature Control). BOP 23. Verify Pzr PORV and Pzr Spray Valve status as follows: a. All Pzr PORVs - CLOSED. BOP 23. RNO a. IF Pzr pressure is less than 2315 PSIG, THEN perform the following: 1) CLOSE Pzr PORV(s). 2) IF any Pzr PORV cannot be closed, THEN CLOSE its isolation valve. NOTE TO EVALUATOR: RNO step 23.a.3) will not apply Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7 Page 33 of 42 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 33 of 42 RO or BOP 4) IF any Pzr PORV cannot be closed OR isolated, THEN perform the following: a) Energize H2 igniters. b) Dispatch operator to perform the following: (1) Secure all ice condenser air handling units. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 11(Securing All Ice Condenser Units). (2) Place containment H2 analyzers in service. REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems). c) IF both the following conditions exist, Containment pressure HAS REMAINED LESS THAN 3 PSIG Containment pressure - BETWEEN 1 PSIG AND 3 PSIG THEN start one VX fan and secure normal containment ventilation. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 18 (VX and Containment Ventilation Control). CREW d) Concurrently: Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees GO TO EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant. TRANSITION TO EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant) summarize the event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7 Page 34 of 42 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 34 of 42 NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant) RO and BOP 1. Monitor Enclosure 1 (Foldout Page). RO or BOP 2. Verify NC subcooling based on core exit T/Cs - GREATER THAN 0°F. NOTE TO EVALUATOR: Depending on the pace of the crew, subcooling may be greater than 0ºF in which case the crew would continue to step 3. RO or BOP 2. RNO IF any NV OR NI pump is on, THEN perform the following: a. Ensure all NC pumps - OFF. b. Maintain seal injection flow. BOP 3. Verify main steamlines intact: All S/G pressures - STABLE OR INCREASING All S/Gs - PRESSURIZED RO 4. Control intact S/G N/R levels as follows: a. Verify N/R level in all intact S/Gs - GREATER THAN 11% (29% ACC). b. THROTTLE feed flow to maintain all intact S/G N/R levels between 11% (29% ACC) and 50%. BOP 5. Reset the following: a. ECCS. b. D/G load sequencers. c. Phase A d. Phase B. RO or BOP e. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on. BOP 6. Establish VI to Containment as follows: Ensure 1VI-77B (VI Cont Isol) - OPEN. Verify VI pressure - GREATER THAN 85 PSIG. RO 7. Verify secondary radiation - NORMAL: a. Ensure the following signals - RESET: 1) CA System valve control BOP 2) KC NC NI NM St signals.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7 Page 35 of 42 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 35 of 42 NOTE TO EVALUATOR: The BOP opens the following valves when aligning the S/Gs for chemistry sample in step b. below: 1NM-191B (S/G 1A SMPL HDR CONT ISOL) 1NM-201A (S/G 1B SMPL HDR CONT ISOL) 1NM-211B (S/G 1C SMPL HDR CONT ISOL) 1NM-221A (S/G 1D SMPL HDR CONT ISOL) 1NM-190A (S/G 1A BLDWN SMPL CONT ISOL) 1NM-200B (S/G 1B BLDWN SMPL CONT ISOL) 1NM-210A (S/G 1C BLDWN SMPL CONT ISOL) 1NM-220B (S/G 1D BLDWN SMPL CONT ISOL) BOP b. Align all S/Gs for Chemistry sampling. RO or BOP c. Perform at least one of the following: Notify Chemistry to sample all S/Gs for activity. OR Notify RP to frisk all cation columns for activity. BOP d. Verify the following EMF trip 1 lights - DARK: 1EMF-33 (Condenser Air Ejector Exhaust) 1EMF-26 (Steamline 1A) 1EMF-27 (Steamline 1B) 1EMF-28 (Steamline 1C) 1EMF-29 (Steamline 1D). RO e. Verify all S/Gs - INTACT All S/G pressures - STABLE OR INCREASING All S/Gs - PRESSURIZED RO or BOP f. WHEN activity results are reported, THEN verify all S/Gs indicate no activity. BOP 8. Verify Pzr PORVs and Isolation Valves: a. Power to all Pzr PORV isolation valves - AVAILABLE. b. All Pzr PORVs CLOSED.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7 Page 36 of 42 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 36 of 42 BOP 8.b. RNO b. IF Pzr pressure is less than 2315 PSIG, THEN perform the following: 1) CLOSE Pzr PORV(s). 2) IF any Pzr PORV cannot be closed, THEN CLOSE its isolation valve. NOTE TO EVALUATOR: RNO step 8.B.3) will not apply BOP c. Any Pzr PORV isolation valve - OPEN. RO or BOP d. IF AT ANY TIME any Pzr PORV opens due to high pressure, THEN after Pzr pressure decreases to less than 2315 PSIG, ensure PORV closes or is isolated. RO or BOP 9. Verify S/I termination criteria: a. NC subcooling based on core exit T/Cs - GREATER THAN 0°F. b. Secondary heat sink:. Any intact S/G N/R level GREATER THAN 11% (29% ACC) OR Total feed flow to intact S/Gs - GREATER THAN 450 GPM. c. NC pressure - STABLE OR INCREASING. d. Pzr level - GREATER THAN 11% (30% ACC). CREW e. GO TO EP/1/A/5000/ES-1.1 (Safety Injection Termination). TRANSITION TO EP/1/A/5000/ES-1.1 (Safety Injection Termination)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7 Page 37 of 42 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 37 of 42 NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/ES-1.1 (Safety Injection Termination) RO and BOP 1. Monitor Enclosure 1 (Foldout Page). BOP 2. Reset the following: a. ECCS. b. D/G load sequencers. c. Phase A. d. Phase B. e. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on. BOP 3. Establish VI to Containment as follows: Ensure 1VI-77B (VI Cont Isol) - OPEN. Verify VI pressure - GREATER THAN 85 PSIG. BOP 4. Ensure only one NV pump - ON. RO or BOP 5. Verify NC pressure - STABLE OR INCREASING. NOTE TO EVALUATOR: The crew may determine that NC pressure is decreasing and go to the RNO, ensure Pzr spray valves CLOSED and transition to EP/1/A/5000/ES-1.2 (Post LOCA Cooldown and Depressurization.) BOP 6. Verify VI pressure - GREATER THAN 50 PSIG. BOP 7. Isolate NV S/I flowpath as follows: a. Verify the following valves - OPEN: 1NV-252A (NV Pumps Suct From FWST) 1NV-253B (NV Pumps Suct From FWST). b. Verify the following valves - OPEN: 1NV-203A (NV Pumps A&B Recirc Isol) 1NV-202B (NV Pmps A&B Recirc Isol). BOP 7.b. RNO b. Perform the following: 1) OPEN affected valve(s). 2) IF 1NV-203A AND 1NV-202B are open, THEN GO TO Step 7.c. BOP c. CLOSE the following valves: 1NI-9A (NV Pmp C/L Inj Isol) 1NI-10B (NV Pmp C/L Inj Isol).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7 Page 38 of 42 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 38 of 42 NOTE TO EVALUATOR: The crew may determine that subcooling is < 0ºF and use Enclosure 1 guidance to realign the NV S/I flow path per EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 14 (NV Alignment to S/I Mode). See Attachment 12. BOP 8. Establish charging as follows: a. Verify all of the following valves - OPEN: 1NV-44A (NC Pmp A Seal Supply Cont Isol) 1NV-55A (NC Pmp B Seal Supply Cont Isol) 1NV-66A (NC Pmp C Seal Supply Cont Isol) 1NV-77A (NC Pmp D Seal Supply Cont Isol). b. THROTTLE 1NV-294 (NV Pmps A&B Disch Flow Ctrl) for 32 GPM charging line flow. c. CLOSE 1NV-309 (Seal Water Injection Flow). d. Ensure one of the following valves OPEN: 1NV-32B (NV Supply To Loop A Isol) OR 1NV-39A (NV Supply To Loop D Isol) e. Ensure 1NV-37A (NV Supply To Pzr Aux Spray) - CLOSED f. OPEN the following valves: 1NV-312A (Chrg Line Cont Isol) 1NV-314B (Chrg Line Cont Isol). g. Verify 1NV-309 - ABLE TO BE OPERATED FROM CONTROL ROOM. h. Place 1NV-309 - IN AUTO. i. Perform the following: Maintain charging flow less than 180 GPM. Maintain 32 GPM seal water flow. BOP 9. Control charging as follows: a. Control charging flow to maintain Pzr level stable. b. Verify Pzr level - STABLE OR INCREASING. BOP or RO 10. Determine if NI pumps should be stopped: a. Verify the following: NC pressure - STABLE OR INCREASING NC pressure - GREATER THAN 1620 PSIG.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7 Page 39 of 42 Event

Description:

1NC-36B (PZR PORV) fails open, 1NC-35B (PZR PORV ISOL) will not close Time Position Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 39 of 42 BOP 10.a. RNO a. Perform the following: 1) IF Pzr level decreasing, THEN increase charging flow to stabilize Pzr level while maintaining less than 180 GPM. NOTE TO EVALUATOR: RNO Step 10.a.2) will not apply. SRO 3) GO TO Step 10.d BOP d. Verify Pzr spray valves - CLOSED RO e. Verify main steamlines intact as follows: ALL S/G pressures STABLE OR INCREASING ALL S/Gs - PRESSURIZED NOTE If Pzr heaters are off, NC pressure may decrease slowly due to Pzr spray bypass BOP f. Verify NC pressure STABLE OR INCREASING BOP or RO g. Verify NC pressure GREATER THAN 1620 PSIG SRO 10.g. RNO g. Perform the following: 1) Do not continue until one of the following met: NC pressure GREATER THAN 1620 PSIG OR NC pressure STABILIZES LESS THAN 1620 PSIG OR NC pressure - DECREASING NOTE TO EVALUATOR: RNO Step 10.g.2) will not apply. SRO 3) IF NC pressure remains less than 1620 PSIG, THEN GO TO EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Depressurization). TRANSITION TO EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Depressurization) END OF SCENARIO Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 40 of 42 Attachment List Scenario 1 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 OP/1/A/6400/005 Enclosure 4.17 (Shifting KC Pumps) ATTACHMENT 4 OP/1/A/6100/010M (Annunciator Response For Panel 1AD-12), B/2 (RN PIT A SCREEN HI D/P) rev. 040 ATTACHMENT 5 AP/1/A/5500/012 Enclosure 3 (Control Room Ventilation System Verification), Rev. 033 ATTACHMENT 6 EP/1/A/5000/E-0 Enclosure 1 (Foldout Page), Rev. 042 ATTACHMENT 7 EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification), Rev. 042 ATTACHMENT 8 EP/1/A/5000/G-1 Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring), Rev.7 ATTACHMENT 9 EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control), Rev. 042 ATTACHMENT 10 EP/1/A/5000/E-1 Enclosure 1 (Foldout Page), Rev. 028 ATTACHMENT 11 EP/1/A/5000/ES-1.1 Enclosure 1 (Foldout Page), Rev. 033 ATTACHMENT 12 EP/1/A/5000/G-1 Enclosure 14 (NV Alignment To S/I Mode), Rev. 7 Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 1 NUREG 1021 Revision 9 Page 41 of 42 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK 1 Establish flow from at least one intermediate head ECCS pump prior to transition from E-0. 2 Trip NC pumps on loss of subcooling with S/I flow verified per E-0 within 5 minutes of criteria met. 3 Control S/G level to avoid an RPS actuation. 4 Control S/G level to avoid an RPS actuation Comments:

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 3.30e² % MOL 1468 PPM per OAC Controlling Procedure OP/1/A/6100/001 (Controlling Procedure for Unit Startup), Enclosure 4.1 (Unit Startup). The steps up to step 3.178 are complete. Other Information Needed to Assume the Shift Unit 1 is at 3.30e² % power, MOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump is tagged out for preventative maintenance. The crew is to shift operating KC (Component Cooling) pumps by starting the 1B2 KC pump and securing the 1B1 KC pump and then increase power to 1% by withdrawing control rods. LCO 3.0.4.(b) has been assessed for the 1B NI Pump inoperability and Mode change has been authorized. NEOs Available Six NEOs are available as listed on the status board METEOROLOGICAL CONDITIONS Upper wind direction = 315 degrees, speed = 10 mph Lower wind direction = 315 degrees, speed = 10.5 mph Forecast calls for clear skies over the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 1 of 41 NRC INITIAL LICENSE EXAM SCENARIO # 2 Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 2 of 41 Facility: Catawba NRC Exam 2014 Scenario No.: 2 Op Test No.: 2014301 Examiners: Operators: SRO RO BOP Initial Conditions: IC# 177; Unit 1 is at 100% power, EOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance. Turnover: Unit 1 is at 100% power, EOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance. Direction for the crew is to decrease power per the reactivity management plan to ~98% in preparation for removing the 1C1 C Heater Drain Pump for maintenance. Event No. Malf. No. Event Type* Event Description 1 --- N-BOP R-RO N-SRO Decrease power to 98%. 2 KC024F C-BOP C-SRO 1KC-425A fails closed. AP/21 3 RN025 C-BOP C-SRO TS-SRO 2B RN (Nuclear Service Water) Pump trips. AP/20 4 EPD003D EHC011A C-RO C-SRO TS-SRO Zone B Lockout with auto turbine runback failure. AP/03 5 MT005A MT007 EHC002 C-RO C-SRO Main Turbine Loss of Lube Oil Pressure with a failure of the Turbine to trip or runback. Manual Reactor Trip required. 6 SM007A M-ALL Loop A steam line break inside containment. 7 NI001F NI002A C-BOP 1NI-9A will not open, 1NI-10B fails to open in Auto 8 ISE007A ISE007B C-RO C-SRO Both trains auto CF isolation fail. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 3 of 41 Scenario 2 Summary Initial Condition IC #177 IC# 177; Unit 1 is at 100% power, EOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance. Turnover: Unit 1 is at 100% power, EOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance. Direction for the crew is to decrease power per the reactivity management plan to ~98% in preparation for removing the 1C1 C Heater Drain Pump for maintenance. Event 1 Decrease power to 98%. Event 2 1KC-425A fails closed. AP/21 (Loss of Component Cooling) entry. Event 3 (Nuclear Service Water) 2B RN Pump trips. AP/20 (Loss of Nuclear Service Water) entry. BOP manually starts another RN pump (there is no auto start feature of the RN pumps for these conditions). TS evaluation required. Event 4 Zone B lockout with auto turbine runback failure. AP/03 (Load Rejection) entry. Event 5 Main Turbine Loss of Lube Oil pressure with a failure of the turbine to trip or runback. Manual reactor trip required. Event 6 Loop A steam line break inside containment. Event 7 1NI-9A (Cold Leg Injection Valve) will not open. 1NI-10B (Cold Leg Injection Valve) fails to open in Auto. Manual opening of 1NI-10B will be successful. Event 8 Both trains of auto CF (Main Feedwater) isolation fail to actuate. Manual actuation will be successful. Critical Task 1 Isolate feed/steam to/from faulted S/G before a transition out of E-2. Critical Task 2 Manually trip the main turbine before a severe (orange-path) challenge develops to either subcriticality or the integrity CSF or before transition to ECA-2.1, whichever happens first. If turbine cannot be tripped, manually trip reactor. Critical Task 3 - Re-establish component cooling flow to the reactor coolant pumps prior to reaching reactor coolant pump trip criteria. Critical Task 4 - Reduce turbine load as required to prevent a valid reactor trip signal.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 4 of 41 EXERCISE GUIDE WORKSHEET 1. INITIAL CONDITIONS: 1.1 Reset to IC #177 START TIME:__________ Trigger Instructor Action Final Delay Ramp Delete In Event 1 VLV-KC024F (KC425A RTN HDR CONTISOL OUTSIDE VLV FAIL TO POSITION) 0 2 4 VLV-KC024F (KC425A RTN HDR CONTISOL OUTSIDE VLV FAIL TO POSITION) 0 1 SEC 2 7 LOA-RN025 (U2 RN PMP 2B OVER-CURRENT) TRIP 3 12 LOA-VC039 (MNL RST OF LATCH FOR CHILLER B HI COND PRESS TRP DUE TO LOSS RN) RESET 20 SEC 3 9 MAL-EP003D (ZONE 1B LOCKOUT) 4 n/a MAL-EHC003F (ALL TURBINE AUTO RUNBACK FAILURE) BLOCK 4 9 MAL-EHC011A (MAIN TURBINE CTRL VLV CV1 FAILS) AS_IS 3 MIN 5 15 MAL- MT005A (TURBINE VIBRATION 2) 20 20 SEC 5 15 MAL-MT007 (LOSS OF TURBINE LUBE OIL PRESSURE) 15 SEC 5 n/a MAL-EHC002 (TURBINE TRIP FAILURE) BOTH 5 18 MAL-SM007A (STM LINE BRK ISIDE CONTAINMENT LOOP A) 8.25e5 6 n/a VLV-N1001F (NI9A B.I.T. DISCHARGE ISOL VLV FAIL TO POSITION) 0 7 n/a VLV-NI002A (NI10B B.I.T. DISCHARGE ISOL VLV FAIL AUTO ACTIONS) 7 n/a MAL-ISE007A (AUTO CF ISOL SIGNAL TRN A) BLOCK 8 n/a MAL-ISE007B (AUTO CF ISOL SIGNAL TRN B) BLOCK 8 Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 5 of 41 n/a LOA-NI004 (RACKOUT NI PMP 1B) RACK OUT n/a LOA-RC068 (RACKOUT RC PMP 1D) RACK OUT Ensure TRIGGER 4 =x11i223o Ensure TRIGGER 12 = x11o038r I x11o374r I x14o013r Ensure TRIGGER 18 = x01o063g I x01o066g Place red collars on the 1B NI Pump and the 1D RC Pump.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 6 of 41 2. SIMULATOR BRIEFING 2.1 Control Room Assignments: Position Name CRS RO BOP 2.2 Give a copy of Attachment 2 (Shift Turnover Information) to the CRS. 3. EXERCISE PRESENTATION 3.1 Familiarization Period A. Allow examinees time to familiarize themselves with Control Board alignments. 3.2 Scenario EVENT 1, decrease reactor power to 98%. BOOTH INSTRUCTOR ACTION IF the SOC is called to be informed of the power increase, REPEAT the information. 3.3 Scenario EVENT 2, 1KC-425A fails closed BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 1 to 1KC-425A to go closed BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance is dispatched to investigate 1KC-425A, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with 1KC-425A, REPEAT back the information. 3.4 Scenario EVENT 3, 2B RN Pump trips BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 7 to cause the 2B RN Pump to trip.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 7 of 41 BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with the 2B RN Pump and/or breaker, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF an Operator and/or Maintenance are dispatched to investigate the 2B RN Pump and/or breaker, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Environmental Chemistry is contacted, REPEAT back the information. 3.5 Scenario EVENT 4, Zone B Lockout BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 9 to cause a Zone B Lockout. BOOTH INSTRUCTOR ACTION IF the TCC is notified of the load reduction, REPEAT back information as required. BOOTH INSTRUCTOR ACTION IF the SOC is notified of current unit status, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the Zone B lockout, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with the turbine control system, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Radiation Protection is notified to sample and analyze gaseous effluents, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Primary Chemistry is notified to sample for isotopic analysis of iodine, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF the Reactor Group Engineer is notified of the occurrence, REPEAT back the information.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 8 of 41 3.6 Scenario EVENTS 5, 6, 7 and 8 BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 15 to cause a loss of lube oil pressure to the main turbine. BOOTH INSTRUCTOR ACTION IF Operator is dispatched to secure all ice condenser air handling units, REPEAT back the information BOOTH INSTRUCTOR ACTION IF Operator is dispatched to place containment hydrogen analyzers in service, REPEAT back the information BOOTH INSTRUCTOR ACTION IF Chemistry is notified to sample all S/Gs for activity, REPEAT the order. BOOTH INSTRUCTOR ACTION IF RP is contacted to frisk the cation columns for activity, REPEAT back the order.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 9 of 41 Event

Description:

Power decrease to 98% power. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 9 of 41 NOTE TO EVALUATOR: Crew begins with a power decrease. BOP performs a boration per OP/1/A/6150/009, Enclosure 4.2. Amount of boration is determined by the power decrease plan. The RO inputs turbine target data. These two evolutions may be performed concurrently. Initial conditions are complete. A reactivity management brief was performed during turnover. Step 3.1 is complete. BOP Perform a boration. RO Input target into the main turbine control panel. NOTE TO EVALUATOR: Applicant may perform a boration per OP/1/A/6150/009, Boron Concentration Control, Enclosure 4.5 (Manual Operation Of The Makeup Controls). Refer to Attachment 3. NOTE TO EVALUATOR: The following actions are from OP/1/A/6150/009, Boron Concentration Control, Enclosure 4.2 (Boration). BOP 3.2 Ensure the following valve control switches in "AUTO": 1NV-238A (B/A To Blender Ctrl Vlv) 1NV-186A (B/A Blender Otlt To VCT Otlt) BOP 3.3 Ensure 1NV-238A (B/A Xfer Pmp To Blender Ctrl) controller in auto. BOP 3.4 Ensure at least one boric acid transfer pump is in "AUTO" or "ON". BOP 3.5 Record the desired volume of boric acid to be added. _________ gallons BOP 3.6 Adjust the boric acid counter to the desired volume of boric acid to be added. (R.M.) BOP 3.7 IF the blender is set up for automatic makeup per Enclosure 4.1 (Automatic Makeup), record the setpoint of the controller for 1NV-238A (B/A Xfer Pmp To Blender Ctrl). _______gpm BOP 3.8 Place the "NC MAKEUP MODE SELECT" switch in "BORATE". NOTE: Boric Acid flow rates > 32 gpm may result in a boric acid flow deviation annunciator.

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

Description:

Power decrease to 98% power. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 10 of 41 BOP 3.9 IF required, adjust the controller for 1NV-238A (B/A Xfer Pmp To Blender Ctrl) to the desired flow. NOTE TO EVALUATOR: Step 3.10 will BOP 3.11 IF AT ANY TIME it is desired to divert letdown to the RHT manually operate 1NV-172A (3-Way Divert To VCT-RHT) as follows: 3.11.1 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) to the "RHT" position. 3.11.2 Ensure VCT level is monitored continuously while diverting to the RHT. NOTE: Procedure may continue while performing the following step. 3.11.3 WHEN desired VCT level is reached return 1NV-172A (3-Way Divert To VCT-RHT) to auto as follows: 3.11.3.1 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) in the "VCT" position. 3.11.3.2 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) in the "AUTO" position. BOP 3.12 IF AT ANY TIME during the makeup it becomes necessary to change the makeup flow rate, adjust the setpoint for 1NV-238A (B/A Xfer Pmp To Blender Ctrl) as necessary to achieve the desired flow.

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

Description:

Power decrease to 98% power Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 11 of 41 BOP 3.13 IF AT ANY TIME while boration is in progress it becomes necessary to stop the boration, perform the following: 3.13.1 Place the "NC MAKEUP CONTROL" switch to the "STOP" position. 3.13.2 Ensure the following valves close: (R.M.) 1NV-238A (B/A To Blender Ctrl Vlv) 1NV-186A (B/A Blender Otlt To VCT Otlt) 3.13.3 Record boric acid volume added as indicated on the Boric Acid counter. ____________ gallons 3.13.4 WHEN conditions allow resuming the boration, perform the following: 3.13.4.1 Determine remaining volume to be added by subtracting the amount previously added (Step 3.13.3) from the desired volume to be added (Step 3.5). ____ ____ - __________ = _______ gallons (Step 3.5) (Step 3.13.3) 3.13.4.2 Adjust boric acid counter to the volume of boric acid determined in Step 3.13.4.1. (R.M.) 3.13.4.3 Place the "NC MAKEUP CONTROL" switch in the "START" position. (R.M.) 3.13.4.4 Verify the following: 1NV-238A (B/A To Blender Ctrl Vlv) modulates to establish desired flow 1NV-186A (B/A Blender Otlt To VCT Otlt) opens 3.13.4.5 IF in "AUTO", verify the boric acid pump starts. BOP 3.14 WHILE makeup is in progress, monitor the following for expected results: Control rod motion NC System Tavg Reactor Power BOP 3.15 Place the "NC MAKEUP CONTROL" switch to the "START" position. (R.M.)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 12 of 41 Event

Description:

Power decrease to 98% power Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 12 of 41 BOP 3.16 Verify the following: 1NV-238A (B/A To Blender Ctrl Vlv) modulates to establish desired flow 1NV-186A (B/A Blender Otlt To VCT Otlt) opens BOP 3.17 IF in "AUTO", verify the boric acid transfer pump starts. BOP 3.18 Verify proper flow by observing the Boric Acid Counter. {PIP 96-0137} NOTE: The boric acid counter may count up 1 - 5 gallons after termination. BOP 3.19 WHEN the desired volume of boric acid is reached on the boric acid counter, ensure the following valves close: (R.M.) 1NV-238A (B/A To Blender Ctrl Vlv) 1NV-186A (B/A Blender Otlt To VCT Otlt) NOTE TO EVALUATOR: Step 3.20 will BOP 3.21 IF automatic makeup is desired, perform one of the following: 3.21.1 IF it is desired to change the blender outlet boron concentration, refer to Enclosure 4.1 (Automatic Makeup). OR 3.21.2 IF makeup at the previous concentration is acceptable AND the system was previously aligned per Enclosure 4.1 (Automatic Makeup), perform the following: 3.21.2.1 Ensure the controller for 1NV-238A (B/A Xfer Pmp To Blender Ctrl) is set to the value recorded in Step 3.7. (R.M.) 3.21.2.2 Place the "NC MAKEUP MODE SELECT" switch in "AUTO". 3.21.2.3 Place the "NC MAKEUP CONTROL" switch to the "START" position. (R.M.) NOTE TO EVALUATOR: Step 3.22 END OF BORATION Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 13 of 41 Event

Description:

Power decrease to 98% power Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 13 of 41 NOTE TO EVALUATOR: The following steps are from OP/1/B/6300/001, Turbine Generator, Enclosure 4.2 (Load Changing) starting at step 3.2.2. RO 3.2.2 Decrease turbine generator load by performing the following: 3.2.2.1 Select "LOAD RATE" and verify it illuminates. 3.2.2.2 Input the desired load rate. 3.2.2.3 Select "ENTER" and verify "LOAD RATE" goes dark 3.2.2.4 Select "TARGET" and verify it illuminates. 3.2.2.5 Input the desired load target. 3.2.2.6 Select "ENTER" and verify "TARGET" goes dark. 3.2.2.7 Verify new load target appears on Target Display. 3.2.2.8 Select "GO" and verify it illuminates to start load decrease. 3.2.2.9 Coordinate with Secondary Chemistry to adjust S/G blowdown flowrates to obtain maximum blowdown for the appropriate load END OF PREPARATION FOR POWER DECREASE ON THE TURBINE PANEL. Booth Operator will insert Trigger 1 for EVENT 2 at the discretion of the lead examiner. END OF EVENT 1 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 14 of 41 Event

Description:

1KC-425A fails closed. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 14 of 41 EVENT 2 Indications: 1AD-6, C/1- 1AD-6, D/1- 1AD-6, E/1- 1AD- 1AD- BOP Recognize 1KC-425A SRO Enters AP/1/A/5500/021(Loss of Component Cooling) BOP Opens 1KC-425A NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/021, Loss of Component Cooling. NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/021, Loss of Component Cooling. CAUTION Failure to restore NC pump seal cooling via thermal barrier cooling or NV seal injection within 10 minutes will cause damage to the NC pump seals resulting in NC inventory loss. RO and BOP 1. Monitor Enclosure 1 (Foldout Page). BOP 2. Verify the following: At least one KC pump - ON. AND Flow to KC loads presently in service. BOP 2. RNO Perform the following: a. Start additional KC pump(s) as necessary. NOTE TO EVALUATOR: Step 2 RNO b. will not apply NOTE TO EVALUATOR: Immediate action step 3 will not apply. SRO 3. IF AT ANY TIME all KC pumps are lost, THEN RETURN TO STEP 2. NOTE Uncooled letdown may result in loss of NV pumps within a matter of minutes. BOP 4. Verify the following: 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK AND At least one KC pump - ON.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 15 of 41 Event

Description:

1KC-425A fails closed. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 15 of 41 SRO 5. IF AT ANY TIME 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" LIT, THEN perform Step 4 RNO. BOP 6. Verify both KC surge tank levels - 50% - 90% AND STABLE. BOP 7. Start additional KC pump(s) as necessary to supply any KC loads presently in service. CAUTION A loss of KC cooling to the NC pumps results in a gradual approach to an overheated condition in approximately 10 minutes which will result in shaft seizure. BOP 8. Verify KC flow to NC pumps as follows: 1AD-20, A/1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK 1AD-21, A/1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK. CRITICAL TASK #3 BOP 8. RNO Perform the following: a. Ensure the following valves - OPEN: 1KC-425A (NC Pumps Ret Hdr Cont Isol) 1KC-338B (NC Pumps Sup Hdr Cont Isol) 1KC-424B (NC Pumps Ret Hdr Cont Isol). NOTE TO EVALUATOR: It is not anticipated that step RNO 8.b. will apply BOP 9. Verify KC available as follows: a. Verify the following Train A KC non-essential header isolation valves - OPEN: 1KC-230A (Rx Bldg Non-Ess Hdr Isol) 1KC-3A (Rx Bldg Non-Ess Ret Hdr Isol) 1KC-50A (Aux Bldg Non-Ess Hdr Isol) 1KC-1A (Aux Bldg Non-Ess Ret Hdr Isol). BOP 9. b. Verify the following Train B KC non-essential header isolation valves -OPEN: 1KC-228B (Rx Bldg Non-Ess Hdr Isol) 1KC-18B (Rx Bldg Non-Ess Ret Hdr Isol) 1KC-53B (Aux Bldg Non-Ess Hdr Isol) 1KC-2B (Aux Bldg Non-Ess Ret Hdr Isol). BOP 9. c. Start additional KC pump(s) as necessary to supply any KC loads presently in service.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 16 of 41 Event

Description:

1KC-425A fails closed. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 16 of 41 BOP 10. Verify KC surge tank levels normal as follows: a. Verify both KC surge tank levels - 50% - 90% AND STABLE. SRO 10. b. GO TO Step 14. NOTE TO EVALUATOR: BOP 14. Ensure KC heat exchanger outlet mode switches - PROPERLY ALIGNED. CREW 15. Determine and correct cause of loss of KC. SRO 16. Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual: SLC 16.9-7 (Boration Systems Flow Path- Shutdown) SLC 16.9-8 (Boration Systems Flow Path- Operating) SLC 16.9-9 (Boration Systems Pumps -Shutdown) SLC 16.9-10 (Boration Systems Charging Pumps - Operating) 3.5.2 (ECCS - Operating) 3.5.3 (ECCS - Shutdown) 3.6.6 (Containment Spray System) 3.7.5 (Auxiliary Feedwater (AFW) System) 3.7.7 (Component Cooling Water (CCW) System). NOTE TO EVALUATOR: No Tech Spec Actions need to be entered. Booth Operator will insert Trigger 7 for EVENT 3 at the discretion of the lead examiner. SRO 17. Determine required notifications: REFER TO RP/0/A/5000/001(Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). NOTE TO EVALUATOR: Step 18 will not apply. BOP 19. Verify KC surge tanks level as follows: Greater than 50% Stable or increasing Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 17 of 41 Event

Description:

1KC-425A fails closed. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 17 of 41 BOP 20. WHEN plant conditions permit, THEN perform the following: Return KC pumps to normal operation. REFER TO OP/1/A/6400/005 (Component Cooling Water System). Return NV Pump 1A to normal cooling as applicable. REFER TO Enclosure 2 (Alternate Cooling To NV Pump 1A). BOP 21. Verify the following: 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK 1AD-7, H/3 "VCT HI TEMP" - DARK Normal letdown - IN SERVICE. BOP 22. Ensure VCT and letdown path aligned as follows: a. IF desired to align NV pump suction to VCT, then perform the following: 1) OPEN the following valves: 1NV-188A (VCT Otlt Isol) 1NV-189B (VCT Otlt Isol). 2) CLOSE the following valves: 1NV-252A (NV Pumps Suct From FWST) 1NV-253B (NV Pumps Suct From FWST). b. WHEN NV suction aligned to VCT, THEN momentarily place 1NV-172A (3-Way Divert To VCT-RHT) to "VCT" position and return to "AUTO". c. IF desired to restore letdown flow through NV demineralizers, THEN momentarily place 1NV-153A (Letdn Hx Otlt 3-Way Valve) to "DEMIN" position and return to "AUTO". SRO 23. Determine long term plant status. RETURN TO procedure in affect. summarize the event. END OF EVENT 2 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 18 of 41 Event

Description:

2B RN (Nuclear Service Water) Pump Trips Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 18 of 41 EVENT 3 Indications: 1AD-12, 1AD- BOP Start an idle RN (Nuclear Service Water) pump NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/0/A/5500/020, Loss of Nuclear Service Water NOTE TO EVALUATOR: The following steps are from AP/0/A/5500/020, Loss of Nuclear Service Water, Case I (Loss of RN Train). BOP 1. Start idle RN pump(s) as required. SRO 2. Ensure Unit 1 and Unit 2 OATC monitors Enclosure 1 (Foldout Page). BOP or SRO 3. Verify RN System in normal alignment as follows: Both RN Supply headers - ALIGNED AND Both RN Discharge headers - ALIGNED. BOP 4. Verify each operating RN pump discharge flow - GREATER THAN 8,600 GPM. BOP 5. Verify each operating RN pump discharge flow - LESS THAN 23,000 GPM. BOP 6. Ensure RN pumps - IN OPERATION AS NEEDED. NOTE TO EVALUATOR: BOP 7. Ensure proper alignment of RN to KC Hxs as follows: a. Verify RN - ALIGNED TO IN SERVICE KC HX(S). b. Ensure KC Hx Otlt Mode switches -PROPERLY ALIGNED. BOP 8. Verify each operating RN pump discharge flow - GREATER THAN 8,600 GPM. BOP 9. Verify RN - AVAILABLE TO ALL UNIT 1 AND UNIT 2 D/G(S).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 19 of 41 Event

Description:

2B RN (Nuclear Service Water) Pump Trips Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 19 of 41 NOTE TO EVALUATOR: The BOP determines that no changes have occurred to the VC/YC (Control Room Ventilation and Chilled Water System) via the OAC or on rear of 1MC-3 in the following step. BOP 10. Determine VC/YC status as follows: Verify VC/YC - ALIGNED TO OPERATING RN TRAIN. Verify YC Chiller - RUNNING. CREW 11. Determine and correct cause of loss of RN train. SRO 12. Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual: SLC 16.7-6 (RN Discharge Instrumentation) 3.6.5 (Containment Air Temperature) 3.6.6 (Containment Spray System) 3.6.17 (Containment Valve Injection Water System (CVIWS)) 3.7.5 (Auxiliary Feedwater (AFW) System) 3.7.7 (Component Cooling Water (CCW) System) 3.7.8 (Nuclear Service Water System (NSWS)) 3.7.10 (Control Room Area Ventilation System (CRAVS)) 3.7.11 (Control Room Area Chilled Water System (CRACWS)) 3.8.1 (A.C. Sources - Operating) 3.8.2 (A.C. Sources - Shutdown). NOTE TO EVALUATOR: T.S. 3.7.8 [(Nuclear Service Water System (NSWS)] Condition A (Restore train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) should be entered. Tech Spec conditions that have been entered. Booth Operator will insert Trigger 9 for EVENT 4 at the discretion of the lead examiner. SRO 13. Determine required notifications: REFER TO RP/0/A/5000/001(Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 20 of 41 Event

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2B RN (Nuclear Service Water) Pump Trips Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 20 of 41 BOP 14. Notify Environmental Chemistry of any RN pump shifts that have occurred. SRO 15. Determine long term plant status. RETURN TO procedure in effect. summarize the event. END OF EVENT 3 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 21 of 41 Event

Description:

Zone B Lockout with failure of automatic Turbine runback Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 21 of 41 EVENT 4 Indications: 1AD- 1AD-11, F/3 1AD- RO Recognize failure of the Turbine to runback. RO Manually decrease turbine load. CREW Enter AP/1/A/5500/003, Load Rejection NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/003, Load Rejection. RO 1. Verify turbine load - DECREASING IN AUTOMATIC. CRITICAL TASK #4 RO 1. RNO Perform the following: a. Select "MANUAL" on turbine control panel. b. Depress "CONTROL VALVES LOWER" pushbutton and reduce turbine load as required. RO 2. Verify proper reactor response: Control rods - IN "AUTO" AND STEPPING IN P/R neutron flux - DECREASING. RO or BOP 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: "C-7A LOSS OF LOAD INTLK COND DUMP" status light (1SI 18) - LIT. Steam dump valves - MODULATING. d. T-Avg - DECREASING TO T-REF. BOP 4. Verify Pzr PORV and Pzr spray valve status as follows: a. All Pzr PORVs - CLOSED. b. Normal Pzr spray valves - CLOSED.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 22 of 41 Event

Description:

Zone B Lockout with failure of automatic Turbine runback Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 22 of 41 BOP 5. Verify proper CM System operation as follows: a. WHEN reactor power is less than 75%, THEN ensure both C-htr drain pumps - OFF. b. Verify reactor power - GREATER THAN 56% PRIOR TO THE EVENT. c. Verify standby hotwell pump(s) - ON. NOTE TO EVALUATOR: The crew will determine that the RNO for step 5.c. will not be necessary BOP d. Verify standby condensate booster pump(s) - ON NOTE TO EVALUATOR: The crew will determine that the RNO for step 5.c. will not be necessary BOP 6. Verify the following generator alarms - DARK: 1AD-11, C/1 "GEN BKR A OVER CURRENT" 1AD-11, F/1 "GEN BKR B OVERCURRENT". RO 6. RNO Ensure turbine generator load - REDUCED TO APPROXIMATELY 48% AND THE ALARM CLEARS. RO 7. Verify S/G levels are adequate as follows: All S/G low level alert alarms (1AD-4) - DARK All S/G low CF flow alarms (1AD-4) - DARK. RO 8. Verify reactor power - GREATER THAN 20%. RO 9. IF AT ANY TIME reactor power is less than or equal to 20%, THEN perform Step 8 RNO. BOP 10. Verify AS header pressure - GREATER THAN OR EQUAL TO 140 PSIG. BOP 10. RNO Adjust 1AS-2 (Main Stm To Aux Steam) as required to maintain AS header pressure between 140 PSIG and 150 PSIG. RO 11. Adjust 1TL-4 (Stm Seal Reg Byp) as necessary to maintain steam seal pressure between 4 PSIG - 6 PSIG. BOP 12. Monitor Enclosure 3 (Rod Insertion Limit Boration).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 23 of 41 Event

Description:

Zone B Lockout with failure of automatic Turbine runback Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 23 of 41 RO 13. Verify reactor power - LESS THAN 30%. RO and BOP 13. RNO Perform the following: 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 appropriate power level. 2) Maintain control rods above insertion limits. 3) Adjust the following as required to maintain T-Avg within 1°F of T-Ref: Turbine load Control rods Boron concentration. c. GO TO Step 15. BOP 15. Verify the following PCBs - CLOSED: Generator breaker 1A Generator breaker 1B PCB 14 PCB 15 PCB 17 PCB 18. NOTE When separated from the grid turbine reverts to speed. NOTE TO EVALUATOR: The crew will determine that the RNO step 15.c. will apply BOP 15. RNO Perform the following: c. IF load rejection caused by loss of main busline 1A or 1B, THEN: 1) Notify Transmission Control Center (TCC), using one of the following methods, to investigate and repair cause of the loss of busline: 704-382-9403 704-382-9404 704-399-9744 704-382-4413 (System Operating Center).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 24 of 41 Event

Description:

Zone B Lockout with failure of automatic Turbine runback Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 24 of 41 BOP 15. RNO c. 2) WHEN notified by TCC that the affected busline is ready to be reenergized, THEN restore power to the affected busline. REFER TO Enclosure 1 (Offsite Power Restoration). RO 16. Adjust power factor as necessary. REFER TO Unit 1 Revised Data Book Figure 43. RO and BOP 17. WHEN the appropriate runback target load is reached, THEN: Stabilize unit at appropriate power level. Maintain control rods above insertion limits. Adjust the following as required to maintain T-Avg within 1°F of T-Ref: Turbine load Control rods Boron concentration. RO or BOP 18. Notify System Operating Center (SOC) using the red dispatcher telephone of current unit status. CREW 19. Determine and correct cause of load rejection. Booth Operator will insert Trigger 15 for EVENT 5 at discretion of lead examiner. BOP 20. Shut down unnecessary plant equipment as follows: a. Restore CM and CF as follows: 1) Verify C-htr drain pumps - ON. BOP 20.a.1) RNO 1) WHEN time and manpower permit, THEN complete the shutdown of the C-htr drain pumps. REFER TO OP/1/B/6250/004 (Feedwater Heater Vents, Drains and Bleed System). 2) Verify both CF Pumps - IN SERVICE. 3) Shutdown one CF pump as necessary. REFER TO OP/1/A/6250/001 (Condensate and Feedwater System). 4) Shutdown excess Condensate Booster Pumps. REFER TO OP/1/A/6250/001 (Condensate and Feedwater System). 5) Shutdown excess Hotwell Pumps. REFER TO OP/1/A/6250/001 (Condensate and Feedwater System).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 25 of 41 Event

Description:

Zone B Lockout with failure of automatic Turbine runback Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 25 of 41 RO 21. Reset steam dump valves as follows: a. Verify reactor power - STABLE. b. Verify steam dump valves - IN "T-AVG" MODE. c. Verify steam dump valves - CLOSED. d. Reset steam dump valves. e. Verify the following status lights (1SI-18) - DARK: "C-7A LOSS OF LOAD INTLK COND DUMP" "C-7B LOSS OF LOAD INTLK ATMOS DUMP". f. IF "T-AVG" mode of operation is available, THEN ensure steam dump valves in "T-AVG" mode. g. Verify "STM DUMP CTRL" - IN AUTO. RO 22. Verify reactor power - GREATER THAN 15%. RO 23. Verify CA pumps - OFF. RO 24. Verify reactor power change GREATER THAN OR EQUAL TO 15% IN A 1 HOUR PERIOD. RO or BOP 25. Notify the following sections to take appropriate samples: Radiation Protection to sample and analyze gaseous effluents. REFER TO Selected Licensee Commitments Manual, Section 16.11-6. 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following last power change greater than or equal to 15% rated thermal power within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 26 of 41 Event

Description:

Zone B Lockout with failure of automatic Turbine runback Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 26 of 41 SRO 26. Ensure compliance with appropriate Tech Specs: 3.1.1 (Shutdown Margin (SDM)) 3.1.6 (Control Bank Insertion Limits) 3.8.1 (AC Sources - Operating) SLC 16.8-2 (230 KV Switchyard Systems). NOTE TO EVALUATOR: The SRO will determine that the following Tech Spec Conditions should be entered: 3.1.6 (Control Bank Insertion Limits) Condition A (Verify SDM is within limit specified in the COLOR - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR Initiate boration to restore SDM to within limit 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, AND Restore control banks within limits - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />), 3.8.1 (AC Sources Operating) Condition A (Perform SR 3.8.1.1 for OPERABLE offsite circuit - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and Restore offsite circuit to OPERABLE status - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />), SLC 16.8-2 (230 kV Switchyard Systems) Condition A (Return switchyard equipment to normal COMMITMENT alignment - In accordance with the Electronic Risk Assessment Tool). BOP 27. Notify Reactor Group Engineer of occurrence. SRO 28. Determine long term plant status. RETURN TO OP/1/A/6100/003 (Controlling Procedure For Unit Operation). END OF EVENT 4 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 27 of 41 Event

Description:

Main Turbine Loss of Lube Oil Pressure with a failure of the turbine to trip or runback. Manual reactor trip required. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 27 of 41 EVENT 5 Indications: 1AD- 1AD- 1AD- RO Recognize Turbine trip failure RO Attempt to trip the turbine RO Attempt to manually decrease turbine load RO Recognize Control Valve #1 failure. RO Manually trip the reactor. CRITICAL TASK #2 RO or BOP Close all MSIVs and MSIV Bypass valves. CREW Enter EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) NOTE TO EVALUATOR: Due to the immediate action nature of the event, it is not anticipated that the crew will have time to make a plant page announcing the entry into AP/1/A/5500/002, Turbine Generator Trip. NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/002, Turbine Generator Trip RO 1. Verify reactor power - LESS THAN 69%. RO 2. Verify Turbine Trip: All turbine stop valves - CLOSED. RO 2. RNO Perform the following: a. Trip turbine. b. IF turbine will not trip, THEN: 1) Depress "MANUAL" pushbutton on turbine control panel. 2) Rapidly unload turbine by simultaneously depressing "CONTROL VALVE LOWER" and "FAST RATE" pushbuttons. 3) IF turbine will not runback, THEN: a) Trip reactor.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 28 of 41 Event

Description:

Main Turbine Loss of Lube Oil Pressure with a failure of the turbine to trip or runback. Manual reactor trip required. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 28 of 41 RO or BOP b) CLOSE: All MSIVs All MSIV bypass valves. CREW c) GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection). TRANSITION TO E-0 (Reactor Trip or Safety Injection) END OF EVENT 5 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7 and 8 Page 29 of 41 Event

Description:

A Loop Steam Line Break Inside Containment, 1NI-9A (NV PUMP C/L INJ ISOL) will not open and 1NI-10B (NV PUMP C/L INJ ISOL) opens in manual, Both trains of auto Feedwater Isolation fail. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 29 of 41 EVENTS 6, 7 and 8 NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) RO or BOP 1. Monitor Enclosure 1 (Foldout Page). RO 2. Verify Reactor Trip: All rod bottom lights - LIT All reactor trip and bypass breakers - OPEN I/R power - DECREASING. RO 3. Verify Turbine Trip: All turbine stop valves - CLOSED RO 3. RNO Perform the following: a. Trip turbine. b. IF turbine will not trip, THEN: 1) Depress "MANUAL" pushbutton on turbine control panel. 2) Rapidly unload turbine by simultaneously depressing the "CONTROL VALVE LOWER" and "FAST RATE" pushbuttons. 3) IF turbine will not runback, THEN CLOSE: All MSIVs All MSIV bypass valves. BOP 4. Verify 1ETA and 1ETB - ENERGIZED. RO 5. Verify S/I is actuated: a. "SAFETY INJECTION ACTUATED" status light (1SI-13) LIT b. Both E/S load sequencer actuated status lights (1SI-14) - LIT. RO 6. Announce "Unit 1 Safety Injection". SRO 7. Determine required notifications: REFER TO RP/0/A/5000/001(Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7 and 8 Page 30 of 41 Event

Description:

A Loop Steam Line Break Inside Containment, 1NI-9A (NV PUMP C/L INJ ISOL) will not open and 1NI-10B (NV PUMP C/L INJ ISOL) opens in manual, Both trains of auto Feedwater Isolation fail. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 30 of 41 RO or BOP 8. Verify all Feedwater Isolation status lights (1SI-5) - LIT RO 8. RNO Perform the following: a. Initiate Feedwater Isolation. NOTE TO EVALUATOR: Step 8.b. RNO will not apply. END OF EVENT 8 BOP 9. Verify Phase A Containment Isolation status as follows: a. Phase A "RESET" lights - DARK. BOP b. Monitor Light Panel Group 5 St lights on energized train(s) - LIT. BOP 10. Verify proper Phase B actuation as follows: a. Verify Containment pressure - HAS REMAINED LESS THAN 3 PSIG NOTE TO EVALUATOR: Depending on the speed of the crew, containment pressure may not have exceeded 3 psig at this time. BOP 10. RNO a. Perform the following: 1) Verify Phase B Isolation has actuated as follows: a) Phase B Isolation "RESET" lights - DARK. NOTE TO EVALUATOR: Step 10 RNO a.1) b) will not apply. BOP c) Verify following monitor light panel lights - LIT: Group 1 Sp lights Group 5 Sp lights Group 5 St light L/11. NOTE TO EVALUATOR: Step 10 RNO a.1) d) will not apply. RO or BOP 10. RNO a. 2) Stop all NC pumps. BOP 10. RNO a. 3) Maintain seal injection flow. BOP 10. RNO a. 4) Energize H2 igniters.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, and 7 Page 31 of 41 Event

Description:

A Loop Steam Line Break Inside Containment, 1NI-9A (NV PUMP C/L INJ ISOL) will not open and 1NI-10B (NV PUMP C/L INJ ISOL) opens in manual. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 31 of 41 RO or BOP 10. RNO a. 5) Dispatch operator to perform the following: a) Secure all ice condenser air handling units. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 11 (Securing All Ice Condenser Units). b) Place containment H2 analyzers in service. REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems). BOP 10. RNO a. 6) WHEN 9 minutes has elapsed, THEN verify proper VX system operation. REFER TO Enclosure 5 (VX System Operation). SRO 10. RNO a. 7) GO TO Step 11. RO 11. Verify proper CA pump status as follows: a. Motor driven CA pumps - ON. b. 3 S/G N/R levels - GREATER THAN 11%. BOP 12. Verify all of the following S/I pumps - ON: NV pumps ND pumps NI pumps. NOTE TO EVALUATOR: The crew may decide to not transition to the RNO due to 1A NI Pump tagged out. BOP 13. Verify all KC pumps - ON. BOP 14. Verify all Unit 1 and Unit 2 RN pumps - ON. BOP 14. RNO Perform the following: a. IF any Unit 2 RN pump off, THEN start affected pump(s). NOTE TO EVALUATOR: RNO Step 14.b. will not apply. BOP 15. Verify proper ventilation systems operation as follows: REFER TO Enclosure 2 (Ventilation System Verification). Notify Unit 2 operator to perform Enclosure 3 (Opposite Unit Ventilation Verification). NOTE TO EVALUATOR: SRO hands Enclosure 3 to a Unit 2 operator and sets Enclosure 3 off to the side. RO 16. Verify all S/G pressures - GREATER THAN 775 PSIG.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, and 7 Page 32 of 41 Event

Description:

A Loop Steam Line Break Inside Containment, 1NI-9A (NV PUMP C/L INJ ISOL) will not open and 1NI-10B (NV PUMP C/L INJ ISOL) opens in manual. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 32 of 41 RO 16. RNO Perform the following: a. Verify Main Steam Isolation as follows: All MSIVs - CLOSED All MSIV bypass valves - CLOSED All S/G PORVs - CLOSED. NOTE TO EVALUATOR: Step 16 RNO b. will not apply RO 17. Verify proper S/I flow as follows: a. "NV S/I FLOW" - INDICATING FLOW. RO b. NC pressure - LESS THAN 1620 PSIG. RO 17.b. RNO b. Perform the following: 1) Ensure ND pump miniflow valve on operating ND pump(s) - OPEN. NOTE TO EVALUATOR: Step 17 RNO b. 2) will not apply SRO 3) GO TO Step 18. RO or BOP 18. WHEN time and manpower permit (within two hours of event), THEN monitor Spent Fuel Pool level and temperature. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring). RO 19. Control S/G levels as follows: a. Verify total CA flow - GREATER THAN 450 GPM. NOTE TO EVALUATOR: Total CA flow may not be > 450 gpm due to being under operator control, in which case, the RNO for 19 a. will not apply. RO b. WHEN each S/G N/R level greater than 11% (29% ACC), THEN control feed flow to maintain that S/G N/R level between 11% (29% ACC) and 50%. RO 20. Verify all CA isolation valves - OPEN. BOP 21. Verify S/I equipment status based on monitor light panel - IN PROPER ALIGNMENT. NOTE TO EVALUATOR: If not previously addressed, the BOP will address the 1NI-10B (NV PUMP C/L INJ ISOL) failure in the following step. BOP 21. RNO Align equipment. END EVENT 7 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6 Page 33 of 41 Event

Description:

A Loop Steam Line Break Inside Containment. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 33 of 41 NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance. RO 22. Control NC temperature. REFER TO Enclosure 4 (NC Temperature Control). BOP 23. Verify Pzr PORV and Pzr Spray Valve status as follows: a. All Pzr PORVs - CLOSED. BOP 23. b. Normal Pzr spray valves - CLOSED. BOP 23. c. At least one Pzr PORV isolation valve - OPEN. RO or BOP 24. Verify NC subcooling based on core exit T/Cs - GREATER THAN 0°F. RO or BOP 25. Verify main steamlines intact: All S/G pressures - STABLE OR INCREASING ALL S/Gs - PRESSURIZED. CREW 25. RNO IF pressure in any S/G is decreasing in an uncontrolled manner OR any S/G is depressurized, THEN perform the following: a. Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees). b. GO TO EP/1/A/5000/E-2 (Faulted Steam Generator Isolation). TRANSITION TO EP/1/A/5000/E-2 (Faulted Steam Generator Isolation) NOTE TO EVALUATOR: The SRO will summarize the event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6 Page 34 of 41 Event

Description:

A Loop Steam Line Break Inside Containment. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 34 of 41 EP/1/A/5000/E-2 (Faulted Steam Generator Isolation) NOTE TO EVALUATOR: The following steps are from E-2 (Faulted Steam Generator Isolation RO or BOP 1. Monitor Enclosure 1 (Foldout Page). RO or BOP 2. Maintain any faulted S/G or secondary break isolated during subsequent recovery actions unless needed for NC System cooldown. RO or BOP 3. Verify the following valves - CLOSED: All MSIVs All MSIV bypass valves. RO or BOP 4. WHEN TSC staffed, THEN notify TSC of the following: IF feedline OR steamline break has occurred inside doghouse, THEN ensure affected doghouse curtains are opened within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of rupture inside of the doghouse. RO or BOP 5. Verify any S/G pressure - STABLE OR INCREASING. RO or BOP 6. Identify faulted S/G(s) as follows: Verify any S/G pressure - DECREASING IN AN UNCONTROLLED MANNER OR Verify any S/G - DEPRESSURIZED. RO or BOP 7. Maintain at least one intact S/G available for NC System cooldown in subsequent steps. RO or BOP 8. Verify faulted S/G(s) PORV - CLOSED. RO or BOP 9. Ensure CA System valve control - RESET.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6 Page 35 of 41 Event

Description:

A Loop Steam Line Break Inside Containment. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 35 of 41 NOTE TO EVALUATOR: The actions of step 10.c.1) may have been performed by the RO during performance of Enclosure 4 (NC Temperature Control) of EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection) CRITICAL TASK #1 RO or BOP 10. Isolate all faulted S/G(s) as follows: S/G 1A: a. Verify S/G 1A Feedwater Isolation status light (1SI-5) - LIT. b. CLOSE the following valves: 1) 1SM-77A (S/G 1A Otlt Hdr Bldwn C/V). 2) 1CA-62A (CA Pmp A Disch To S/G 1A Isol). 3) 1CA-66B (CA Pmp 1 Disch To S/G 1A Isol). c. Verify the following blowdown isolation valves - CLOSED: 1) 1BB-56A (S/G 1A Bldwn Cont Isol Insd). 2) 1BB-148B (S/G 1A Bldwn Cont Isol Byp). 3) 1BB-57B (S/G 1A Bldwn Cont Isol Otsd). RO 11. WHEN NC T-Hots start to increase, THEN dump steam from intact S/G PORVs to stabilize NC T-Hots. BOP 12. Verify secondary radiation 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. NOTE TO EVALUATOR: CA System valve control was previously reset by the RO in order to throttle S/G N/R levels as directed by E-0.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6 Page 36 of 41 Event

Description:

A Loop Steam Line Break Inside Containment. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 36 of 41 NOTE TO EVALUATOR: The BOP opens the following valves when aligning the S/Gs for chemistry sample in step b. below: 1NM-191B (S/G 1A SMPL HDR CONT ISOL) 1NM-201A (S/G 1B SMPL HDR CONT ISOL) 1NM-211B (S/G 1C SMPL HDR CONT ISOL) 1NM-221A (S/G 1D SMPL HDR CONT ISOL) 1NM-190A (S/G 1A BLDWN SMPL CONT ISOL) 1NM-200B (S/G 1B BLDWN SMPL CONT ISOL) 1NM-210A (S/G 1C BLDWN SMPL CONT ISOL) 1NM-220B (S/G 1D BLDWN SMPL CONT ISOL) BOP b. Align all S/Gs for Chemistry sampling. RO or BOP c. Perform at least one of the following: Notify Chemistry to sample all S/Gs for activity. OR Notify RP to frisk all cation columns for activity. BOP d. Verify the following EMF trip 1 lights - DARK: 1EMF-33 (Condenser Air Ejector Exhaust) 1EMF-26 (Steamline 1A) 1EMF-27 (Steamline 1B) 1EMF-28 (Steamline 1C) 1EMF-29 (Steamline 1D). BOP e. Verify S/G(s) fault - INSIDE CONTAINMENT. RO or BOP f. WHEN activity results are reported, THEN notify station management to evaluate SG(s) activity results.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6 Page 37 of 41 Event

Description:

A Loop Steam Line Break Inside Containment. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 37 of 41 RO 13. Verify S/I termination criteria: a. NC subcooling based on core exit T/Cs - GREATER THAN 0°F. RO b. Verify secondary heat sink as follows: Any intact S/G N/R level GREATER THAN 11% (29% ACC) OR Total feed flow to intact S/Gs - GREATER THAN 450 GPM. RO c. NC pressure - STABLE OR INCREASING. BOP d. Pzr level - GREATER THAN 11% (30% ACC). NOTE TO EVALUATOR: If the BOP was slow to open 1NI-10B (NV PUMP C/L INJ ISOL), Pzr level may be less than 30% in which the CREW will transition to E-1 per the RNO. REFER to Attachment 14. CREW e. GO TO EP/1/A/5000/ES-1.1 (Safety Injection Termination). summarize the event. TRANSITION TO EP/1/A/5000/ES-1.1 (Safety Injection Termination)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6 Page 38 of 41 Event

Description:

A Loop Steam Line Break Inside Containment. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 38 of 41 EP/1/A/5000/ES-1.1 (Safety Injection Termination) NOTE TO EVALUATOR: The following steps are from ES-1.1 (Safety Injection Termination) RO and BOP 1. Monitor Enclosure 1 (Foldout Page). BOP 2. Reset the following: a. ECCS. b. D/G load sequencers. c. Phase A. d. Phase B. e. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on. NOTE TO EVALUATOR: Phase A was previously reset by the BOP as directed by E-2. BOP 3. Establish VI to Containment as follows: Ensure 1VI-77B (VI Cont Isol) - OPEN. Verify VI pressure - GREATER THAN 85 PSIG. BOP 4. Ensure only one NV pump - ON. NOTE TO EVALUATOR: BOP will secure one NV pump. RO or BOP 5. Verify NC pressure - STABLE OR INCREASING. BOP 6. Verify VI pressure - GREATER THAN 50 PSIG. BOP 7. Isolate NV S/I flowpath as follows: a. Verify the following valves - OPEN: 1NV-252A (NV Pumps Suct From FWST) 1NV-253B (NV Pumps Suct From FWST). BOP b. Verify the following valves - OPEN: 1NV-203A (NV Pumps A&B Recirc Isol) 1NV-202B (NV Pumps A&B Recirc Isol) BOP c. CLOSE the following valves: 1NI-9A (NV Pmp C/L Inj Isol) 1NI-10B (NV Pmp C/L Inj Isol) END OF EVENT 6 END OF SCENARIO Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 39 of 41 Attachment List Scenario 2 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 OP/1/A/6150/009 Enclosure 4.5 (Manual Operation of the Makeup Controls), rev. 079 ATTACHMENT 4 AP/1/A/5500/021 Enclosure 1 (Foldout Page), rev. 042 ATTACHMENT 5 AP/0/A/5500/020 Enclosure 1 (Foldout Page), rev. 043 ATTACHMENT 6 AP/1/A/5500/003 Enclosure 3 (Rod Insertion Limit Boration), rev. 041 ATTACHMENT 7 EP/1/A/5000/E-0 Enclosure 1 (Foldout Page), rev. 042 ATTACHMENT 8 EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification), rev. 042 ATTACHMENT 9 EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control), rev. 042 ATTACHMENT 10 EP/1/A/5000/E-0 Enclosure 5 (VX System Operation), rev. 042 ATTACHMENT 11 EP/1/A/5000/G-1 Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring), rev. 007 ATTACHMENT 12 EP/1/A/5000/E-2 Enclosure 1 (Foldout Page), rev. 015 ATTACHMENT 13 EP/1/A/5000/ES-1.1 Enclosure 1 (Foldout Page), rev. 033 Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 2 NUREG 1021 Revision 9 Page 40 of 41 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK 1 Isolate feed/steam to/from faulted S/G before a transition out of E-2. 2 Manually trip the main turbine before a severe (orange-path) challenge develops to either subcriticality or the integrity CSF or before transition to ECA-2.1, whichever happens first. 3 Re-establish component cooling flow to the reactor coolant pumps prior to reaching reactor coolant pump trip criteria. 4 Reduce turbine load as required to prevent a valid reactor trip signal. Comments:

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 100% EOL 90 PPM per OAC Controlling Procedure OP/1/A/6100/003 (Controlling Procedure for Unit Operation), Enclosure 4.3 (Unit Operation Between 85% and 100% Power) is in progress up to step 3.21. Other Information Needed to Assume the Shift 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance. Direction for the crew is to decrease power per the reactivity management plan to ~98% in preparation for removing the 1C1 C Heater Drain Pump for maintenance. NEOs Available Six NEOs are available as listed on the status board METEOROLOGICAL CONDITIONS Upper wind direction = 315 degrees, speed = 10 mph Lower wind direction = 315 degrees, speed = 10.5 mph Forecast calls for Severe Thunderstorm Watch for the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 1 of 40 NRC INITIAL LICENSE EXAM SCENARIO # 3 Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 2 of 40 Facility: Catawba NRC Exam 2014 Scenario No.: 3 Op Test No.: 2014301 Examiners: Operators: SRO RO BOP Initial Conditions: IC# 178; Unit 1 is at 100% power, BOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance. Turnover: Unit 1 is at 100% power, BOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance. Borate the NC (Reactor Coolant) System in preparation for swapping Hotwell pumps and Condensate Booster pumps. Event No. Malf. No. Event Type* Event Description 1 --- N-BOP N-SRO Borate the NC (Reactor Coolant) System 2 IRX003A C-RO C-SRO Continuous rod motion (insertion). AP/15 3 IPE003B C-BOP TS-SRO 1NC-27 (Pzr Spray from Loop A) fails open. AP/11 4 RN002B C-BOP C-SRO TS-SRO 1B RN (Nuclear Service Water) Strainer Hi D/P. AP/20 5 EGB003 IRX009 R-RO C-SRO TS-SRO KG (Stator Cooling) Turbine runback, Manual Rod Insertion AP/03 6 IRX007D1 C-RO C-SRO Multiple Control Rods drop 7 NC005D4 M-ALL Rod Ejection, LOCA 8 CA004A CA004B C-RO Both CA (Auxiliary Feedwater) pumps fail to start. 1A starts in manual. 9 ISE011B C-BOP Aux Building Unfiltered Exhaust fans fail to stop on S/I * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 3 of 40 Scenario 3 Summary Initial Condition IC 178 IC# 178; Unit 1 is at 100% power, MOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance. Turnover: Unit 1 is at 100% power, MOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance. Borate the NC (Reactor Coolant) System in preparation for swapping Hotwell pumps and Condensate Booster pumps. Event 1 Borate the NC system in preparation for swapping Hotwell Pumps and Condensate Booster Pumps. Event 2 Continuous rod motion (insertion). AP/15 Event 3 1NC-27 (Pzr Spray from Loop A) fails open. AP/11 Event 4 1B RN (Nuclear Service Water) strainer Hi D/P. AP/20 Event 5 KG (Stator Cooling) turbine runback, manual rod insertion AP/03 Event 6 Multiple control rods drop Event 7 Rod ejection, LOCA Event 8 Both CA (Auxiliary Feedwater) pumps fail to auto start. 1A starts in manual. Event 9 Aux. Bldg. Unfiltered Exhaust fans fail to stop on SI. Critical Task 1 Manually close Pzr spray valve prior to ESF actuation or Rx trip. Critical Task 2 - Manually trip reactor for two or more rods dropped. Critical Task 3 - Manually insert control rods on the turbine runback as necessary to prevent an RPS actuation.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 4 of 40 EXERCISE GUIDE WORKSHEET 1. INITIAL CONDITIONS: 1.1 Reset to IC #178 START TIME:__________ Trigger Instructor Action Final Delay Ramp Delete In Event 1 MAL-OV0797B (IREDJ5040 RODS IN DEMAND fail to FALSE/TRUE) TRUE 2 n/a MAL-IRX003A (UNCONTROLLED ROD INSERTION) AUTO 2 5 IPE003B (PZR SPRAY VLV NC-27 FAIL, NO MAN CTRL) 100 3 7 MAL-RN002B (RN STRAINER 1B HI D/P) 100 4 16 LOA-VC038 (MNL RST OF LATCH FOR CHILLER A HI COND PRESS TRP DUE TO LOSS RN) RESET 4 9 LOA-EGB003 (KG PUMPS) STOP BOTH 5 2 IRX009 (RODS FAIL TO MOVE) AUTO 5 11 MAL-IRX007D1 (DROP ROD GROUP CBD1) 6 14 MAL-NC005D4 (ROD D4 EJECTION) 2000 3 SEC 7 14 MAL-EDA001C5 (ROD C5 DRPI-OPEN/SHORTED COIL) BOTH 3 SEC 7 14 MAL-EDA001E3 (ROD E3 DRPI-OPEN/SHORTED COIL) BOTH 3 SEC 7 14 MAL-EDA001D4 (ROD D4 DRPI-OPEN/SHORTED COIL) BOTH 3 SEC 7 n/a MAL-CA004A (FAILURE OF CA PUMP A TO START) AUTO 8 n/a MAL-CA004B (FAILURE OF CA PUMP B TO START) BOTH 8 n/a MAL-ISE011B (AUX BLDG FANS FAIL TO AUTO STOP) 9 n/a LOA-NI004 (RACKOUT NI PMP 1B) RACKOUT n/a LOA-RC068 (RACKOUT RC PMP 1D) RACKOUT Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 5 of 40 Ensure TRIGGER 2 = x01i123g Ensure TRIGGER 14 = x01o063g I x01o066g Ensure TRIGGER 16 = x11o038r I x14o013r I x14o014r Place red collars on the 1B NI Pump and the 1D RC Pump.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 6 of 40 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, Borate the NC System 3.3 Scenario EVENT 2, Continuous Rod Motion BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 1 to give the control rods a signal to start stepping in. BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with the control rods, REPEAT back the information. 3.4 Scenario EVENT 3, 1NC-27 fails open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to cause 1NC-27 to fail open. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with 1NC-27, REPEAT the information. 3.5 Scenario EVENT 4, 1B RN Strainer Hi D/P BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 7 to cause the 1B RN Strainer Hi D/P.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 7 of 40 BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with 1B RN Strainer and/or breaker, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF an Operator and/or Maintenance are dispatched to investigate the 1B RN Strainer and/or breaker, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Environmental Chemistry is contacted, REPEAT back the information. 3.6 Scenario EVENT 5, KG Turbine Runback BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 9 to cause the KG Pumps to trip. BOOTH INSTRUCTOR ACTION IF SWM is contacted to write a w/r on the KG pump, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance is dispatched to investigate the KG pump, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF the SOC is notified of current unit status, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF RP is notified to sample and analyze gaseous effluents, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Primary Chemistry is notified to sample for isotopic analysis of iodine, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF the Reactor Group Engineer is notified of the occurrence, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Operator dispatched to complete the shutdown of the C Heater Drain Pumps, REPEAT back the information.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 8 of 40 3.7 Scenario EVENTS 6, 7, 8, and 9 BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 11 to cause Control Bank D Group 1 rods to drop. BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance are dispatched to investigate the 1B CA Pump and/or breaker, REPEAT the order. BOOTH INSTRUCTOR ACTION IF Operator is dispatched to secure all ice condenser air handling units and place Hydrogen Analyzers in service, REPEAT the order. BOOTH INSTRUCTOR ACTION IF Chemistry is notified to sample all S/Gs for activity, REPEAT the order. BOOTH INSTRUCTOR ACTION IF RP is notified to frisk all cation columns for activity, REPEAT the order.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 9 of 40 Event

Description:

NC (Reactor Coolant) System boration Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 9 of 40 NOTE TO EVALUATOR: Crew begins with a power decrease. BOP performs a boration per OP/1/A/6150/009, Enclosure 4.2. Initial conditions are complete. A reactivity management brief was performed during turnover. Step 3.1 is complete. BOP Perform a boration. NOTE TO EVALUATOR: Applicant may perform a boration per OP/1/A/6150/009, Boron Concentration Control, Enclosure 4.5 (Manual Operation Of The Makeup Controls). Refer to Attachment 3. NOTE TO EVALUATOR: The following actions are from OP/1/A/6150/009, Boron Concentration Control, Enclosure 4.2 (Boration). BOP 3.2 Ensure the following valve control switches in "AUTO": 1NV-238A (B/A To Blender Ctrl Vlv) 1NV-186A (B/A Blender Otlt To VCT Otlt) BOP 3.3 Ensure 1NV-238A (B/A Xfer Pmp To Blender Ctrl) controller in auto. BOP 3.4 Ensure at least one boric acid transfer pump is in "AUTO" or "ON". BOP 3.5 Record the desired volume of boric acid to be added. _________ gallons BOP 3.6 Adjust the boric acid counter to the desired volume of boric acid to be added. (R.M.) BOP 3.7 IF the blender is set up for automatic makeup per Enclosure 4.1 (Automatic Makeup), record the setpoint of the controller for 1NV-238A (B/A Xfer Pmp To Blender Ctrl). _______gpm BOP 3.8 Place the "NC MAKEUP MODE SELECT" switch in "BORATE". NOTE: Boric Acid flow rates > 32 gpm may result in a boric acid flow deviation annunciator.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 10 of 40 Event

Description:

NC (Reactor Coolant) System boration Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 10 of 40 BOP 3.9 IF required, adjust the controller for 1NV-238A (B/A Xfer Pmp To Blender Ctrl) to the desired flow. NOTE TO EVALUATOR: Step 3.10 will BOP 3.11 IF AT ANY TIME it is desired to divert letdown to the RHT manually operate 1NV-172A (3-Way Divert To VCT-RHT) as follows: 3.11.1 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) to the "RHT" position. 3.11.2 Ensure VCT level is monitored continuously while diverting to the RHT. NOTE: Procedure may continue while performing the following step. 3.11.3 WHEN desired VCT level is reached return 1NV-172A (3-Way Divert To VCT-RHT) to auto as follows: 3.11.3.1 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) in the "VCT" position. 3.11.3.2 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) in the "AUTO" position. BOP 3.12 IF AT ANY TIME during the makeup it becomes necessary to change the makeup flow rate, adjust the setpoint for 1NV-238A (B/A Xfer Pmp To Blender Ctrl) as necessary to achieve the desired flow.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 11 of 40 Event

Description:

NC (Reactor Coolant) System boration Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 11 of 40 BOP 3.13 IF AT ANY TIME while boration is in progress it becomes necessary to stop the boration, perform the following: 3.13.1 Place the "NC MAKEUP CONTROL" switch to the "STOP" position. 3.13.2 Ensure the following valves close: (R.M.) 1NV-238A (B/A To Blender Ctrl Vlv) 1NV-186A (B/A Blender Otlt To VCT Otlt) 3.13.3 Record boric acid volume added as indicated on the Boric Acid counter. ____________ gallons 3.13.4 WHEN conditions allow resuming the boration, perform the following: 3.13.4.1 Determine remaining volume to be added by subtracting the amount previously added (Step 3.13.3) from the desired volume to be added (Step 3.5). ____ ____ - __________ = _______ gallons (Step 3.5) (Step 3.13.3) 3.13.4.2 Adjust boric acid counter to the volume of boric acid determined in Step 3.13.4.1. (R.M.) 3.13.4.3 Place the "NC MAKEUP CONTROL" switch in the "START" position. (R.M.) 3.13.4.4 Verify the following: 1NV-238A (B/A To Blender Ctrl Vlv) modulates to establish desired flow 1NV-186A (B/A Blender Otlt To VCT Otlt) opens 3.13.4.5 IF in "AUTO", verify the boric acid pump starts. BOP 3.14 WHILE makeup is in progress, monitor the following for expected results: Control rod motion NC System Tavg Reactor Power BOP 3.15 Place the "NC MAKEUP CONTROL" switch to the "START" position. (R.M.)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 12 of 40 Event

Description:

NC (Reactor Coolant) System boration Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 12 of 40 BOP 3.16 Verify the following: 1NV-238A (B/A To Blender Ctrl Vlv) modulates to establish desired flow 1NV-186A (B/A Blender Otlt To VCT Otlt) opens BOP 3.17 IF in "AUTO", verify the boric acid transfer pump starts. BOP 3.18 Verify proper flow by observing the Boric Acid Counter. {PIP 96-0137} NOTE: The boric acid counter may count up 1 - 5 gallons after termination. BOP 3.19 WHEN the desired volume of boric acid is reached on the boric acid counter, ensure the following valves close: (R.M.) 1NV-238A (B/A To Blender Ctrl Vlv) 1NV-186A (B/A Blender Otlt To VCT Otlt) NOTE TO EVALUATOR: Step 3.20 will BOP 3.21 IF automatic makeup is desired, perform one of the following: 3.21.1 IF it is desired to change the blender outlet boron concentration, refer to Enclosure 4.1 (Automatic Makeup). OR 3.21.2 IF makeup at the previous concentration is acceptable AND the system was previously aligned per Enclosure 4.1 (Automatic Makeup), perform the following: 3.21.2.1 Ensure the controller for 1NV-238A (B/A Xfer Pmp To Blender Ctrl) is set to the value recorded in Step 3.7. (R.M.) 3.21.2.2 Place the "NC MAKEUP MODE SELECT" switch in "AUTO". 3.21.2.3 Place the "NC MAKEUP CONTROL" switch to the "START" position. (R.M.) NOTE TO EVALUATOR: Step 3.22 END OF BORATION END OF EVENT 1 Booth Operator will insert Trigger 1 for EVENT 2 at discretion of lead examiner.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 2 Page 13 of 40 Event

Description:

Continuous rod motion (insertion) Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 13 of 40 EVENT 2 Indications: An audible clicking noise will be heard as the control rods begin to insert without a demand signal present. RO Recognize rod motion without demand NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/015, Rod Control Malfunctions, Case II (Continuous Rod Movement). RO 1. Ensure "CRD BANK SELECT" switch - IN MANUAL. RO 2. Verify all rod motion - STOPS. NOTE For T-Ref failures, T-Ref will need to be determined for current power level. RO 3. Manually adjust control rods as necessary to maintain T-Avg within 1°F of T-Ref BOP or RO 4. Verify the following channels - NORMAL FOR EXISTING PLANT CONDITIONS: NC Loop A T-Avg NC Loop B T-Avg NC Loop C T-Avg NC Loop D T-Avg BOP or RO 5. Determine and correct cause of continuous rod movement. SRO 6. Ensure compliance with appropriate Tech Specs: 3.1.1 (Shutdown Margin (SDM)) 3.1.4 (Rod Group Alignment Limits) 3.1.5 (Shutdown Bank Insertion Limits) 3.1.6 (Control Bank Insertion Limits) 3.3.1 (Reactor Trip Instrumentation) 3.3.2 (ESFAS Instrumentation) 3.4.2 (RCS Minimum Temperature for Criticality). NOTE TO EVALUATOR: The SRO will determine that no Tech Spec entries are required. Booth Operator will insert Trigger 5 for EVENT 3 at discretion of lead examiner.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 2 Page 14 of 40 Event

Description:

Continuous rod motion (insertion) Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 14 of 40 SRO 7. Determine required notifications: REFER TO RP/0/A/5000/001 (Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). CREW 8. WHEN rod control problem is repaired, THEN perform the following: a. Ensure T-Avg - WITHIN 1°F OF T-REF. b. WHEN desired, THEN place control rods in "AUTO". c. Ensure steam dumps - IN DESIRED MODE FOR EXISTING PLANT CONDITIONS. SRO 9. Determine long term plant status. RETURN TO procedure in effect. summarize the event. END OF EVENT 2 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 15 of 40 Event

Description:

1NC-27 (Pzr Spray Valve) fails open Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 15 of 40 EVENT 3 Indications: 1AD- BOP Recognizes 1NC-27 (PZR SPRAY CTRL FRM LOOP A) is open BOP Verifies Pressurizer pressure is normal BOP Places controller for 1NC-27 in Manual. BOP Places key switch for 1NC-27 (PZR SPRAY VLV MODE SELECT) to FAIL CLOSED. NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/011, Pressurizer Pressure Anomalies. NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/011, Pressurizer Pressure Anomalies, Case I (Pressurizer Pressure Decreasing) BOP 1. Verify all Pzr PORVs CLOSED. NOTE Control rods may withdraw on decreasing NC pressure. BOP 2. Verify Pzr spray valve(s) CLOSED. CRITICAL TASK #1 BOP 2.a. RNO Perform the following: a. CLOSE affected spray valve(s). b. IF affected spray valve(s) will not close, THEN perform the following: 1) Select "FAIL CLOSED" for affected spray valve(s) mode select switch: "1 NC-27 PZR SPRAY VLV MODE SELECT" "1 NC-29 PZR SPRAY VLV MODE SELECT". NOTE TO EVALUATOR: Step 2 RNO b. 2) may apply. BOP 2) IF AT ANY TIME the Control Room Supervisor determines that a reactor trip is required, THEN: a) Trip reactor. b) WHEN reactor power less than 5%, THEN stop NC Pumps 1A and 1B. c) GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection). SRO 3) IF NC pressure is stable OR increasing, THEN GO TO Step 3.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 16 of 40 Event

Description:

1NC-27 (Pzr Spray Valve) fails open Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 16 of 40 BOP 3. Verify all Pzr heaters ENERGIZED. BOP 4. Ensure 1NV-37A (NV Supply To Pzr Aux Spray) CLOSED. NOTE Positive reactivity is inserted during an increase in NC pressure which may cause auto rod insertion. BOP 5. Verify NC pressure STABLE OR INCREASING. RO and BOP 6. WHEN NC pressure is stable, THEN: Stabilize unit at appropriate power level. Adjust the following as required to maintain T-Avg within 1°F of T-Ref: Turbine load Control rods Boron concentration. NOTE TO EVALUATOR: Step 7 does not apply. BOP 8. Ensure compliance with appropriate Tech Specs: 3.3.1 (Reactor Trip System (RTS) Instrumentation) 3.3.2 (Engineered Safety Features Actuation System (ESFAS) Instrumentation) 3.3.3 (Post Accident Monitoring (PAM) Instrumentation) 3.3.4 (Remote Shutdown System) 3.4.1 (RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits) 3.4.4 (RCS Loops MODES 1 and 2) 3.4.5 (RCS Loops MODE 3) 3.4.6 (RCS Loops MODE 4) 3.4.9 (Pressurizer) 3.4.10 (Pressurizer Safety Valves) 3.4.11 (Pressurizer Power Operated Relief Valves (PORVs)) 3.4.13 (RCS Operational Leakage). NOTE TO EVALUATOR: Tech Spec 3.4.1 (RCS Pressure, Temperature and Flow Departure From Nucleate Boiling (DNB) Limits) Condition A (Restore DNB parameter(s) to within limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) should be entered. This condition is likely to be cleared by the time Tech Specs are reviewed per the AP.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 17 of 40 Event

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1NC-27 (Pzr Spray Valve) fails open Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 17 of 40 Tech Spec conditions that have been entered. SRO 9. Determine long term plant status. RETURN TO procedure in effect. summarize the event. Booth Operator will insert Trigger 7 for Event 4 at the discretion of the lead examiner. END OF EVENT 3 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 18 of 40 Event

Description:

1B RN (Nuclear Service Water) Strainer Hi D/P Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 18 of 40 EVENT 4 Indications: 1AD- 1AD-- 1AD- 1AD- BOP Recognize 1B RN Pump Strainer Hi D/P. CREW Enter AP/0/A/5500/020, Loss of Nuclear Service Water BOP Start an RN Pump BOP Stop 1B RN Pump NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/0/A/5500/020, Loss of Nuclear Service Water NOTE TO EVALUATOR: The crew will may initially choose to take actions of the annunciator response per OP/1/A/6100/010 M, C/5 (RN PMP B STRAINER HI D/P). See Attachment NOTE TO EVALUATOR: The following steps are from AP/0/A/5500/020, Loss of Nuclear Service Water, Case I (Loss of RN Train). BOP 1. Start idle RN pump(s) as required. SRO 2. Ensure Unit 1 and Unit 2 OATC monitors Enclosure 1 (Foldout Page). BOP or SRO 3. Verify RN System in normal alignment as follows: Both RN Supply headers - ALIGNED AND Both RN Discharge headers - ALIGNED BOP 4. Verify each operating RN pump discharge flow - GREATER THAN 8,600 GPM.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 19 of 40 Event

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1B RN (Nuclear Service Water) Strainer Hi D/P Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 19 of 40 BOP 4. RNO Perform the following: a. Stop any RN pump(s) not required to support system operation. b. Ensure the following suction valves to lake - OPEN: 1RN-1A (RN P/H Pit A Isol From Lake) 1RN-2B (RN P/H Pit A Isol From Lake) 1RN-5A (RN P/H Pit B Isol From Lake) 1RN-6B (RN P/H Pit B Isol From Lake) c. Ensure the following essential header isolation valves for required trains - OPEN: 1RN-67A (RN Hdr 1A Supply Isol) 1RN-69B (RN Hdr 1B Supply Isol) 2RN-67A (RN Hdr 2A Supply Isol) 2RN-69B (RN Hdr 2B Supply Isol) d. Ensure the following RN to RL discharge valves - OPEN: 1RN-57A (Station RN Disch To RL Sys) 1RN-843B (Station RN Disch To RL Sys) e. Ensure one of the following RL discharge valves - OPEN: 1RL-54 (RN System Disch To A RL Header) OR 1RL-62 (RN System Disch To B RL Header) f. Ensure the following station RN discharge header crossover valves - OPEN: 1RN-54A (Station RN Disch Hdr X-Over) 1RN-53B (Station RN Disch Hdr X-Over) NOTE TO EVALUATOR: Step 4 RNO 4.g. will not apply. BOP 4. RNO h. Verify the following alarms - DARK: 1AD-12, C/2 "RN PMP A STRAINER HI D/P" 1AD-12, C/5 "RN PMP B STRAINER HI D/P" 2AD-12, C/2 "RN PMP A STRAINER HI D/P" 2AD-12, C/5 "RN PMP B STRAINER HI D/P".

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 20 of 40 Event

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1B RN (Nuclear Service Water) Strainer Hi D/P Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 20 of 40 NOTE TO EVALUATOR: It is anticipated that the CRS will read step 4 RNO 4.i., but the action will not be taken at this time BOP 4. RNO i. IF any of the previous alarms lit, THEN backflush affected strainer. REFER TO OP/0/A/6400/006C (Nuclear Service Water System). BOP 5. Verify each operating RN pump discharge flow - LESS THAN 23,000 GPM. BOP 6. Ensure RN pumps - IN OPERATION AS NEEDED. NOTE TO EVALUATOR: BOP 7. Ensure proper alignment of RN to KC Hxs as follows: a. Verify RN - ALIGNED TO IN SERVICE KC HX(S). b. Ensure KC Hx Otlt Mode switches -PROPERLY ALIGNED. BOP 8. Verify each operating RN pump discharge flow - GREATER THAN 8,600 GPM. BOP 9. Verify RN - AVAILABLE TO ALL UNIT 1 AND UNIT 2 D/G(S). NOTE TO EVALUATOR: The BOP determines that no changes have occurred to the VC/YC (Control Room Ventilation and Chilled Water System) via the OAC or on rear of 1MC-3 in the following step. BOP 10. Determine VC/YC status as follows: Verify VC/YC - ALIGNED TO OPERATING RN TRAIN. Verify YC Chiller - RUNNING. CREW 11. Determine and correct cause of loss of RN train.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 21 of 40 Event

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1B RN (Nuclear Service Water) Strainer Hi D/P Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 21 of 40 SRO 12. Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual: SLC 16.7-6 (RN Discharge Instrumentation) 3.6.5 (Containment Air Temperature) 3.6.6 (Containment Spray System) 3.6.17 (Containment Valve Injection Water System (CVIWS)) 3.7.5 (Auxiliary Feedwater (AFW) System) 3.7.7 (Component Cooling Water (CCW) System) 3.7.8 (Nuclear Service Water System (NSWS)) 3.7.10 (Control Room Area Ventilation System (CRAVS)) 3.7.11 (Control Room Area Chilled Water System (CRACWS)) 3.8.1 (A.C. Sources - Operating) 3.8.2 (A.C. Sources - Shutdown). NOTE TO EVALUATOR: T.S. 3.7.8 Condition A (Restore train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) should be entered. Tech Spec conditions that have been entered. Booth Operator will insert Trigger 9 for EVENT 5 at the discretion of the lead examiner. SRO 13. Determine required notifications: REFER TO RP/0/A/5000/001(Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements) BOP 14. Notify Environmental Chemistry of any RN pump shifts that have occurred. SRO 15. Determine long term plant status. RETURN TO procedure in effect. summarize the event. END OF EVENT 4 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 22 of 40 Event

Description:

KG (Stator Cooling) Turbine runback, Manual rod insertion Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 22 of 40 EVENT 5 Indications: 1AD-1, D/6 1AD- 1AD-- RO Recognize Turbine runback RO Recognize Control Rods fail to insert RO Ensure RO Insert Control Rods to maintain Tavg within 1 deg of Tref CREW Enter AP/1/A/5500/003, Load Rejection NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/003, Load Rejection, Case 1 (Switchyard Available) RO 1. Verify turbine load - DECREASING IN AUTOMATIC. RO 2. Verify proper reactor response: Control rods - IN "AUTO" AND STEPPING IN P/R neutron flux - DECREASING. CRITICAL TASK #3 RO 2. RNO IF T-Avg is greater than 1.5°F higher than T-Ref, THEN insert control rods as required to maintain T-Avg within 1°F of T-Ref. NOTE TO EVALUATOR: The intent of EVENT 5 is for a reactivity manipulation for the RO position. The scenario will continue at the discretion of the lead examiner. Booth Operator will insert Trigger 11 for EVENT 6 at the discretion of the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 23 of 40 Event

Description:

KG (Stator Cooling) Turbine runback, Manual rod insertion Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 23 of 40 RO 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: "C-7A LOSS OF LOAD INTLK COND DUMP" status light (1SI 18) - LIT. Steam dump valves - MODULATING. d. T-Avg - DECREASING TO T-REF. BOP 4. Verify Pzr PORV and Pzr spray valve status as follows: a. All Pzr PORVs - CLOSED. b. Normal Pzr spray valves - CLOSED. BOP 5. Verify proper CM System operation as follows: a. WHEN reactor power is less than 75%, THEN ensure both C-htr drain pumps - OFF. b. Verify reactor power - GREATER THAN 56% PRIOR TO THE EVENT. c. Verify standby hotwell pump(s) - ON. NOTE TO EVALUATOR: The crew will determine that the RNO for step 5.c. will not be necessary BOP d. Verify standby condensate booster pump(s) - ON NOTE TO EVALUATOR: The crew will determine that the RNO for step 5.d. will not be necessary BOP 6. Verify the following generator alarms - DARK: 1AD-11, C/1 "GEN BKR A OVER CURRENT" 1AD-11, F/1 "GEN BKR B OVERCURRENT". RO 7. Verify S/G levels are adequate as follows: All S/G low level alert alarms (1AD-4) - DARK All S/G low CF flow alarms (1AD-4) - DARK. RO 8. Verify reactor power - GREATER THAN 20%. RO 9. IF AT ANY TIME reactor power is less than or equal to 20%, THEN perform Step 8 RNO.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 24 of 40 Event

Description:

KG (Stator Cooling) Turbine runback, Manual rod insertion Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 24 of 40 BOP 10. Verify AS header pressure - GREATER THAN OR EQUAL TO 140 PSIG. BOP 10. RNO Adjust 1AS-2 (Main Stm To Aux Steam) as required to maintain AS header pressure between 140 PSIG and 150 PSIG. RO 11. Adjust 1TL-4 (Stm Seal Reg Byp) as necessary to maintain steam seal pressure between 4 PSIG - 6 PSIG. BOP 12. Monitor Enclosure 3 (Rod Insertion Limit Boration). RO 13. Verify reactor power - LESS THAN 30%. RO 13. RNO Perform the following: a. IF the runback target load is less than 30%, THEN: 1) WHEN time and personnel permit, THEN perform applicable steps of OP/1/A/6100/003 (Controlling Procedure For Unit Operation). SRO 2) Do not continue in this procedure until reactor power is less than 30%. 3) WHEN reactor power is less than 30%, THEN GO TO Step 14. RO 14. Verify the "RESET" light on "AMSAC FOR CF VALVES" switch - DARK. BOP 15. Verify the following PCBs - CLOSED: Generator breaker 1A Generator breaker 1B PCB 14 PCB 15 PCB 17 PCB 18. RO 16. Adjust power factor as necessary. REFER TO Unit 1 Revised Data Book Figure 43.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 25 of 40 Event

Description:

KG (Stator Cooling) Turbine runback, Manual rod insertion Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 25 of 40 RO and BOP 17. WHEN the appropriate runback target load is reached, THEN: Stabilize unit at appropriate power level. Maintain control rods above insertion limits. Adjust the following as required to maintain T-Avg within 1°F of T-Ref: Turbine load Control rods Boron concentration. RO or BOP 18. Notify System Operating Center (SOC) using the red dispatcher telephone of current unit status. CREW 19. Determine and correct cause of load rejection. BOP 20. Shut down unnecessary plant equipment as follows: a. Restore CM and CF as follows: 1) Verify C-htr drain pumps - ON. BOP 20.a.1) RNO 1) WHEN time and manpower permit, THEN complete the shutdown of the C-htr drain pumps. REFER TO OP/1/B/6250/004 (Feedwater Heater Vents, Drains and Bleed System). BOP 2) Verify both CF Pumps - IN SERVICE. 3) Shutdown one CF pump as necessary. REFER TO OP/1/A/6250/001 (Condensate and Feedwater System). 4) Shutdown excess Condensate Booster Pumps. REFER TO OP/1/A/6250/001 (Condensate and Feedwater System). 5) Shutdown excess Hotwell Pumps. REFER TO OP/1/A/6250/001 (Condensate and Feedwater System). BOP b. RC pump(s) and cooling tower fans. REFER TO OP/1/B/6400/001A (Condenser Circulating Water System).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 26 of 40 Event

Description:

KG (Stator Cooling) Turbine runback, Manual rod insertion Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 26 of 40 RO 21. Reset steam dump valves as follows: a. Verify reactor power - STABLE. b. Verify steam dump valves - IN "T-AVG" MODE. c. Verify steam dump valves - CLOSED. d. Reset steam dump valves. e. Verify the following status lights (1SI-18) - DARK: "C-7A LOSS OF LOAD INTLK COND DUMP" "C-7B LOSS OF LOAD INTLK ATMOS DUMP". f. IF "T-AVG" mode of operation is available, THEN ensure steam dump valves in "T-AVG" mode. g. Verify "STM DUMP CTRL" - IN AUTO. RO 22. Verify reactor power - GREATER THAN 15%. RO 23. Verify CA pumps - OFF. RO 24. Verify reactor power change GREATER THAN OR EQUAL TO 15% IN A 1 HOUR PERIOD. RO or BOP 25. Notify the following sections to take appropriate samples: Radiation Protection to sample and analyze gaseous effluents. REFER TO Selected Licensee Commitments Manual, Section 16.11-6. 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following last power change greater than or equal to 15% rated thermal power within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period). SRO 26. Ensure compliance with appropriate Tech Specs: 3.1.1 (Shutdown Margin (SDM)) 3.1.6 (Control Bank Insertion Limits) 3.8.1 (AC Sources - Operating) SLC 16.8-2 (230 KV Switchyard Systems). NOTE TO EVALUATOR: The SRO will determine that Tech Spec 3.1.6 Condition A (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) should be entered. BOP 27. Notify Reactor Group Engineer of occurrence. SRO 28. Determine long term plant status. RETURN TO OP/1/A/6100/003 (Controlling Procedure For Unit Operation). END OF EVENT 5 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6 Page 27 of 40 Event

Description:

Multiple Control Rods drop Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 27 of 40 EVENT 6 INDICATIONS: 1AD-2, D/9 1AD-2, E/9 RPI TWO OR MORE RODS AT BOTTOM RO Recognize multiple dropped control rods and perform the Immediate Actions of AP/1/A/5500/014 (Control Rod Misalignment), Case II (Dropped Control Rod) NOTE TO EVALUATOR: Due to the immediate action nature of the event, it is not anticipated that the crew will have time to make a plant page announcing the entry into AP/1/A/5500/014 (Control Rod Misalignment). NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/014 (Control Rod Misalignment). The actions will be taken, however the procedure will not be read by the CRS, since these are Immediate Actions. RO 1. Verify only one rod - DROPPED OR MISALIGNED CRITICAL TASK #2 RO 1. RNO IF two or more rods are dropped OR misaligned by greater than 24 steps, THEN: a. Manually trip Reactor. CREW b. GO TO EP/1/A/5000/E-0 (Reactor Trip or Safety Injection). END OF EVENT 6 TRANSITION TO EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7, 8 and 9 Page 28 of 40 Event

Description:

Rod Ejection, LOCA, Both CA (Auxiliary Feedwater) pumps fail to start. 1A starts in manual. Aux Building Unfiltered Exhaust fans fail to stop on S/I. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 28 of 40 EVENTS 7, 8 AND 9 NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) RO and BOP 1. Monitor Enclosure 1 (Foldout Page). RO 2. Verify Reactor Trip: Perform the following: All rod bottom lights - LIT All reactor trip and bypass breakers - OPEN I/R power - DECREASING. RO 2. RNO Perform the following: a. Trip reactor. NOTE TO EVALUATOR: RNO Step 2.b. will not apply RO 3. Verify Turbine Trip: Perform the following: All turbine stop valves - CLOSED BOP 4. Verify 1ETA and 1ETB - ENERGIZED. RO 5. Verify S/I is actuated: a. "SAFETY INJECTION ACTUATED" status light (1SI-13) LIT b. Both E/S load sequencer actuated status lights (1SI-14) - LIT. RO 6. Announce "Unit 1 Safety Injection". SRO 7. Determine required notifications: REFER TO RP/0/A/5000/001(Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). RO or BOP 8. Verify all Feedwater Isolation status lights (1SI-5) - LIT BOP 9. Verify Phase A Containment Isolation status as follows: a. Phase A "RESET" lights - DARK. BOP b. Monitor Light Panel Group 5 St lights on energized train(s) - LIT. BOP 10. Verify proper Phase B actuation as follows: a. Verify Containment pressure - HAS REMAINED LESS THAN 3 PSIG Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7, 8 and 9 Page 29 of 40 Event

Description:

Rod Ejection, LOCA, Both CA (Auxiliary Feedwater) pumps fail to start. 1A starts in manual. Aux Building Unfiltered Exhaust fans fail to stop on S/I. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 29 of 40 RO or BOP b. IF AT ANY TIME containment pressure exceeds 3 PSIG while in this procedure, THEN perform Step 10.a. RO 11. Verify proper CA pump status as follows: a. Motor driven CA pumps - ON. BOP 11.a. RNO a. Perform the following for affected train(s): 1) Reset ECCS. 2) Reset D/G load sequencer(s). RO 3) Start affected pump(s). RO AND BOP 4) IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on. END OF EVENT 8 RO b. 3 S/G N/R levels - GREATER THAN 11%. BOP 12. Verify all of the following S/I pumps - ON: NV pumps ND pumps NI pumps. NOTE TO EVALUATOR: The crew may decide to not transition to the RNO due to 1A NI Pump tagged out.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7 and 9 Page 30 of 40 Event

Description:

Rod Ejection, LOCA, Aux Building Unfiltered Exhaust fans fail to stop on S/I. Time Position Actions or Behavior Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 30 of 40 BOP 13. Verify all KC pumps - ON. BOP 14. Verify all Unit 1 and Unit 2 RN pumps - ON. NOTE TO EVALUATOR: The SRO may have the BOP secure the 1B (Nuclear Service Water) Pump due the Hi strainer D/P BOP 15. Verify proper ventilation systems operation as follows: REFER TO Enclosure 2 (Ventilation System Verification). Notify Unit 2 operator to perform Enclosure 3 (Opposite Unit Ventilation Verification). NOTE TO EVALUATOR: SRO hands Enclosure 3 to a Unit 2 operator and sets Enclosure 3 off to the side. NOTE TO EVALUATOR: The BOP will correct Event 9 while performing Enclosure 2 END OF EVENT 9 RO 16. Verify all S/G pressures - GREATER THAN 775 PSIG. RO 17. Verify proper S/I flow as follows: a. "NV S/I FLOW" - INDICATING FLOW. b. NC pressure - LESS THAN 1620 PSIG. c. NI pumps - INDICATING FLOW. d. NC pressure - LESS THAN 285 PSIG. RO 17.d. RNO d. Perform the following: 1) Ensure ND pump miniflow valve on operating ND pump(s) - OPEN. NOTE TO EVALUATOR: Step 17 RNO b. 2) will not apply SRO 3) GO TO Step 18. RO or BOP 18. WHEN time and manpower permit (within two hours of event), THEN monitor Spent Fuel Pool level and temperature. REFER TO EP/1/A/5000/G-1(Generic Enclosures), Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring). RO 19. Control S/G levels as follows: a. Verify total CA flow - GREATER THAN 450 GPM. b. WHEN each S/G N/R level greater than 11% (29% ACC), THEN control feed flow to maintain that S/G N/R level between 11% (29% ACC) and 50%.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7 Page 31 of 40 Event

Description:

Rod Ejection, LOCA, Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 31 of 40 RO 20. Verify all CA isolation valves - OPEN. BOP 21. Verify S/I equipment status based on monitor light panel - IN PROPER ALIGNMENT. BOP 21. RNO Align equipment. NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance. RO 22. Control NC temperature. REFER TO Enclosure 4 (NC Temperature Control). BOP 23. Verify Pzr PORV and Pzr Spray Valve status as follows: a. All Pzr PORVs - CLOSED. BOP 23. b. Normal Pzr spray valves - CLOSED. BOP 23. c. At least one Pzr PORV isolation valve - OPEN. RO or BOP 24. Verify NC subcooling based on core exit T/Cs - GREATER THAN 0°F. RO or BOP 24. RNO IF any NV OR NI pump on, THEN perform the following: a. Ensure all NC pumps - OFF. b. Maintain seal injection flow. RO or BOP 25. Verify main steamlines intact: All S/G pressures - STABLE OR INCREASING ALL S/Gs - PRESSURIZED. BOP 26. Verify S/G tubes are intact as follows: Verify the following EMF trip 1 lights - DARK: 1EMF-33 (Condenser Air Ejector Exhaust) 1EMF-26 (Steamline 1A) 1EMF-27 (Steamline 1B) 1EMF-28 (Steamline 1C) 1EMF-29 (Steamline 1D). All S/G levels - STABLE OR INCREASING IN A CONTROLLED MANNER. BOP 27. Verify NC System intact as follows: Containment pressure - LESS THAN 1 PSIG.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7 Page 32 of 40 Event

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Rod Ejection, LOCA, Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 32 of 40 BOP 27. RNO Perform the following: a. Energize H2 igniters. b. Dispatch operator to perform the following: 1) Secure all ice condenser air handling units. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 11(Securing All Ice Condenser Units). 2) Place containment H2 analyzers in service. REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems). c. IF both the following conditions exist, Containment pressure BETWEEN 1 PSIG AND 3 PSIG Containment pressure HAS REMAINED LESS THAN 3 PSIG THEN start one VX fan and secure normal containment ventilation. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 18 (VX and Containment Ventilation Control). CREW d. Concurrently: Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees GO TO EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant. TRANSITION TO EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant) NOTE TO EVALUATOR: The SRO summarize the event.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7 Page 33 of 40 Event

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Rod Ejection, LOCA, Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 33 of 40 NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant) RO and BOP 1. Monitor Enclosure 1 (Foldout Page). RO or BOP 2. Verify NC subcooling based on core exit T/Cs - GREATER THAN 0°F. RO or BOP 2. RNO IF any NV OR NI pump is on, THEN perform the following: a. Ensure all NC pumps - OFF. b. Maintain seal injection flow. BOP 3. Verify main steamlines intact: All S/G pressures - STABLE OR INCREASING All S/Gs - PRESSURIZED RO 4. Control intact S/G N/R levels as follows: a. Verify N/R level in all intact S/Gs - GREATER THAN 11% (29% ACC). b. THROTTLE feed flow to maintain all intact S/G N/R levels between 11% (29% ACC) and 50%. BOP 5. Reset the following: a. ECCS. b. D/G load sequencers. c. Phase A d. Phase B. e. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on. BOP 6. Establish VI to Containment as follows: Ensure 1VI-77B (VI Cont Isol) - OPEN. Verify VI pressure - GREATER THAN 85 PSIG. RO 7. Verify secondary radiation - NORMAL: a. Ensure the following signals - RESET: 1) CA System valve control BOP 2) KC NC NI NM St signals.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7 Page 34 of 40 Event

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Rod Ejection, LOCA, Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 34 of 40 NOTE TO EVALUATOR: The BOP opens the following valves when aligning the S/Gs for chemistry sample in step b. below: 1NM-191B (S/G 1A SMPL HDR CONT ISOL) 1NM-201A (S/G 1B SMPL HDR CONT ISOL) 1NM-211B (S/G 1C SMPL HDR CONT ISOL) 1NM-221A (S/G 1D SMPL HDR CONT ISOL) 1NM-190A (S/G 1A BLDWN SMPL CONT ISOL) 1NM-200B (S/G 1B BLDWN SMPL CONT ISOL) 1NM-210A (S/G 1C BLDWN SMPL CONT ISOL) 1NM-220B (S/G 1D BLDWN SMPL CONT ISOL) BOP b. Align all S/Gs for Chemistry sampling. RO or BOP c. Perform at least one of the following: Notify Chemistry to sample all S/Gs for activity. OR Notify RP to frisk all cation columns for activity. BOP d. Verify the following EMF trip 1 lights - DARK: 1EMF-33 (Condenser Air Ejector Exhaust) 1EMF-26 (Steamline 1A) 1EMF-27 (Steamline 1B) 1EMF-28 (Steamline 1C) 1EMF-29 (Steamline 1D). RO e. Verify all S/Gs - INTACT All S/G pressures - STABLE OR INCREASING All S/Gs - PRESSURIZED Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7 Page 35 of 40 Event

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Rod Ejection, LOCA, Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 35 of 40 RO or BOP f. WHEN activity results are reported, THEN verify all S/Gs indicate no activity. BOP 8. Verify Pzr PORVs and Isolation Valves: a. Power to all Pzr PORV isolation valves - AVAILABLE. b. All Pzr PORVs CLOSED. BOP c. Any Pzr PORV isolation valve - OPEN. RO or BOP d. IF AT ANY TIME any Pzr PORV opens due to high pressure, THEN after Pzr pressure decreases to less than 2315 PSIG, ensure PORV closes or is isolated. RO or BOP 9. Verify S/I termination criteria: a. NC subcooling based on core exit T/Cs - GREATER THAN 0°F. SRO 9.a. RNO a. GO TO Step 9.f. RO or BOP f. Monitor S/I termination criteria. REFER TO Enclosure 2 (S/I Termination Criteria). CREW g. IF AT ANY TIME S/I termination criteria met while in this procedure, THEN RETURN TO Step 9. RO or BOP 10. Determine if ND pumps should be stopped: a. NC pressure - GREATER THAN 285 PSIG. b. NC pressure - STABLE OR INCREASING SRO 10.b. RNO b. GO TO Step 11. RO 11. Verify NC and S/G pressures as follows: a. All S/G pressures - STABLE OR INCREASING. RO or BOP b. NC pressure - STABLE OR DECREASING.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7 Page 36 of 40 Event

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Rod Ejection, LOCA, Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 36 of 40 BOP 12. Verify D/Gs should be stopped: a. Any D/G - ON. b. Verify 1ETA is energized by offsite power as follows: "D/G 1A BKR TO ETA" - OPEN 1ETA - ENERGIZED. c. Dispatch operator to stop 1A D/G and place in standby readiness. REFER TO OP/1/A/6350/002 (Diesel Generator Operation). d. Verify 1ETB is energized by offsite power as follows: "D/G 1B BKR TO ETB" - OPEN 1ETB - ENERGIZED. e. Dispatch operator to stop 1B D/G and place in standby readiness. REFER TO OP/1/A/6350/002 (Diesel Generator Operation). BOP 13. Obtain containment H2 concentration as follows: a. Ensure operator dispatched to secure all ice condenser air handling units. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 11 (Securing All Ice Condenser Units). b. Verify containment H2 analyzers - IN SERVICE CREW 13.b. RNO b. Perform the following: 1) Dispatch operator to place containment H2 analyzers in service. REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems). 2) WHEN H2 analyzers are in service, THEN perform Steps 13.c through 13.e. 3) GO TO Step 14. BOP 14. Initiate evaluation of plant status as follows: a. Verify Cold Leg Recirc capability from at least one train: A Train: 1A ND pump - AVAILABLE 1NI-185A (ND Pump 1A Cont Sump Suct) POWER AVAILABLE OR B Train: 1B ND pump - AVAILABLE 1NI-184B (ND Pump 1B Cont Sump Suct) POWER AVAILABLE Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 7 Page 37 of 40 Event

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Rod Ejection, LOCA, Time Position Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 37 of 40 BOP b. Determine if leak is in auxiliary building: 1) Verify auxiliary building radiation: All area monitor EMF trip 1 lights - DARK. EMF-41 (Aux Bldg Ventilation) trip 1 light DARK NOTE The following step is checking for a significant NC leak into the ND System. 2) Verify NC to ND pressure boundary intact as follows: ND Pressure - NORMAL ND Temperature - NORMAL ND Flow NORMAL c. Determine if NC is leaking into KC system: 1EMF-46A (COMPONENT COOLING TRAIN A) trip 1 light - DARK. 1EMF-46B (COMPONENT COOLING TRAIN B) trip 1 light - DARK. d. Ensure KC NC NI NM St signals - RESET e. WHEN TSC is staffed, THEN notify TSC to perform Enclosure 4 (TSC Actions). RO or BOP 15. Determine if NC System cooldown and depressurization is required: a. NC pressure - GREATER THAN 285 PSIG CREW b. GO TO EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Depressurization TRANSITION TO EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Depressurization) END OF SCENARIO Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 38 of 40 Attachment List Scenario 3 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 OP/1/A/6150/009 Enclosure 4.5 (Manual Operation of the Makeup Controls), rev. 079 ATTACHMENT 4 AP/0/A/5500/020 Enclosure 1 (Foldout Page), rev. 043 ATTACHMENT 5 AP/1/A/5500/003 Enclosure 3 (Rod Insertion Limit Boration), rev. 041 ATTACHMENT 6 EP/1/A/5000/E-0 Enclosure 1 (Foldout Page), rev. 042 ATTACHMENT 7 EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification), rev. 042 ATTACHMENT 8 EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control), Rev. 042 ATTACHMENT 9 EP/1/A/5000/G-1 Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring), rev. 007 ATTACHMENT 10 EP/1/A/5000/G-1 Enclosure 18 (VX and Containment Ventilation Control), rev. 007 ATTACHMENT 11 EP/1/A/5000/E-1 Enclosure 1 (Foldout Page), rev. 028 ATTACHMENT 12 EP/1/A/5000/E-1 Enclosure 2 (S/I Termination Criteria), rev. 028 Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 3 NUREG 1021 Revision 9 Page 39 of 40 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK 1 Manually close Pzr spray valve prior to ESF actuation or Rx trip. 2 Manually trip reactor for two or more rods dropped. 3 Manually insert control rods on the turbine runback as necessary to prevent an RPS actuation. Comments:

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 100% BOL 1162 PPM per OAC Controlling Procedure OP/1/A/6100/003 (Controlling Procedure for Unit Operation), Enclosure 4.3 (Unit Operation Between 85% and 100% Power) is in progress through step 3.16. Other Information Needed to Assume the Shift Unit 1 is at 100% power, BOL. Unit 2 is at 100%. 1B NI (Safety Injection) Pump and the 1D RC (Condenser Circulating Water) Pump are tagged out for preventative maintenance. Borate the NC (Reactor Coolant) System in preparation for swapping Hotwell pumps and Condensate Booster pumps. NEOs Available Six NEOs are available as listed on the status board METEOROLOGICAL CONDITIONS Upper wind direction = 315 degrees, speed = 10 mph Lower wind direction = 315 degrees, speed = 10.5 mph Forecast calls for Severe Thunderstorm Watch for the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 1 of 36 NRC INITIAL LICENSE EXAM SCENARIO # 4 Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 2 of 36 Facility: Catawba NRC Exam 2014 Scenario No.: 4 Op Test No.: 2014301 Examiners: Operators: SRO RO BOP Initial Conditions: IC# 179; Unit 1 is at 25% power, MOL. Unit 2 is at 100%. The 1A KF (Fuel Pool Cooling) Pump is tagged out for preventative maintenance. The 1A2 CFPT MOP is tagged out for motor replacement. Turnover: Unit 1 is at 25% power, MOL. Unit 2 is at 100%. The 1A KF (Fuel Pool Cooling) Pump is tagged out for preventative maintenance. The 1A2 CFPT MOP is tagged out for motor replacement. Increase Power per the reactivity plan. Event No. Malf. No. Event Type* Event Description 1 --- N-BOP R-RO N-SRO Power increase. 2 VLVNC005F C-BOP TS-SRO 1NC-32B (PZR PORV) fails open. AP/11 3 KC029 C-BOP C-SRO TS-SRO 1B1 KC (Component Cooling) Pump trips. AP/21 4 SGL005C C-RO C-SRO 1CF-46 (S/G 1C CF CTRL) fails open. AP/06 5 SG001B C-RO C-SRO 1B S/G tube leak 6 SG001B M-ALL 1B S/G tube rupture 7 SM002B C-RO 1SV-13 (S/G 1B PORV) fails open 8 ISE003A NV025A C-BOP A Train Phase A Failure, 1NV-91B (NC PUMPS SEAL RET CONT ISOL) failure to close * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 3 of 36 Scenario 4 Summary Initial Condition IC 179 IC# 179; Unit 1 is at 25% power, MOL. Unit 2 is at 100%. The 1A KF (Fuel Pool Cooling) Pump is tagged out for preventative maintenance. The 1A2 CFPT MOP is tagged out for motor replacement. Turnover: Unit 1 is at 25% power, MOL. Unit 2 is at 100%. The 1A KF (Fuel Pool Cooling) Pump is tagged out for preventative maintenance. The 1A2 CFPT MOP is tagged out for motor replacement. Increase Power per the reactivity plan. Event 1 Increase power per turnover. Event 2 1NC-32B (PZR PORV) fails open. AP/11 Event 3 1B1 KC (Component Cooling) Pump trips. AP/21 Event 4 1CF-46 (S/G 1C CF CTRL) fails open. AP/06 Event 5 1B S/G tube leak. Event 6 Tube leak increases to a tube rupture and requires a reactor trip. Event 7 1SV-13 (S/G 1B PORV) fails open. Event 8 A Train Phase A fail to complete; 1NV-91B (NC Pumps Seal Ret Cont Isol) failure to close. Critical Task 1 Manually control feedwater to prevent reaching an S/G Hi Hi level Turbine trip or Lo Lo level Rx trip. Critical Task 2 Close the block valve upstream of the stuck open PZR PORV. Critical Task 3 Isolate feed/steam to/from ruptured S/G before a transition to ECA-3.1. Critical Task 4 - Terminate S/I before water release occurs from the ruptured S/G PORV or safety. Critical Task 5 - Start a Component Cooling pump prior to reaching any RPS trip criteria. Critical Task 6 - Isolate the containment penetration flow path prior to exit out of E-0.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 4 of 36 EXERCISE GUIDE WORKSHEET 1. INITIAL CONDITIONS: 1.1 Reset to IC #179 START TIME:__________ Trigger Instructor Action Final Delay Ramp Delete In Event 3 VLV-NC005F (NC32B PZR PORV FAIL TO POSITION) 1 2 5 LOA-KC029 (RACKOUT KC PMP 1B1) RACK OUT 3 1 MAL-SGL005C (S/G C HI PWR LVL CONTROLLER FAILURE) -100 2 MIN 4 7 MAL-SG001B (S/G B TUBE LEAK) 370 3 MIN 5 12 MAL-SM002B (S/G PORV SV13 FAILURE) 100 7 14 MAL-SM002B (S/G PORV SV13 FAILURE) 100 1 SEC 7 n/a MAL-ISE003A (AUTO PHASE A ISOL SIGNAL TRN A) BLOCK 8 n/a VLV-NV025A (NV-91B SEAL RTN ISOL CONT VLV FAIL AUTO ACTIONS) 8 n/a OVR-FWP019A (CFPT 1A MOP 1A2 OFF LT) OFF n/a OVR-FWP019B (CFPT 1A MOP1A2 ON LT) OFF n/a LOA-KF004 (RACKOUT KF PMP A) RACK OUT Ensure TRIGGER 12 = x01o063g I x01o066g Ensure TRIGGER 14 = x02o091b Place red collars on the 1A KF Pump and the 1A2 CFPT MOP Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 5 of 36 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, Power Increase BOOTH INSTRUCTOR ACTION IF the SOC is called to be informed of the power increase, REPEAT the information. 3.3 Scenario EVENT 2, 1CF-46 Fails Open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 1 to fail 1CF-46 (S/G 1C CF CTRL) open. BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with 1CF46, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Operator is dispatched to locally investigate 1CF-46, REPEAT back the information. 3.4 Scenario EVENT 3, 1NC-32B Fails Open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 1NC-32B to fail open. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to write a w/r for the 1NC-32B, REPEAT back the information..

Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 6 of 36 3.5 Scenario EVENT 4, 1B1 KC Pump Trips BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to trip the 1B1 KC pump. BOOTH INSTRUCTOR ACTION IF Operator is dispatched to investigate the 1B1 KC Pump/ Breaker, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with 1B1 KC Pump/Breaker, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Operator is dispatched to Check out the 1B2 KC Pump, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Operator is dispatched to Check out the 1B NV Pump, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Engineering contacted per the annunciator response for 1AD-7, F/3, REPEAT back the information. 3.6 Scenario EVENT 5, 6, 7 and 8 BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 7 to cause a tube leak on the 1B S/G. BOOTH INSTRUCTOR ACTION IF Chemistry is contacted to verify chemistry valves per 1EMF-33 alarm response, REPEAT back the order BOOTH INSTRUCTOR ACTION IF Operator is dispatched to unlock and close 1SA-1, REPEAT back the order BOOTH INSTRUCTOR ACTION IF RP is notified to frisk all cation columns for activity, REPEAT the information and order. BOOTH INSTRUCTOR ACTION If Chemistry is notified to sample all S/Gs for activity, REPEAT back the information.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 7 of 36 Event

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Power Increase Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 7 of 36 NOTE TO EVALUATOR: Crew begins with a power increase. BOP performs a dilution per OP/1/A/6150/009, Enclosure 4.3. Amount of dilution will be determined by the power increase plan. The RO will input turbine target data. These two evolutions may be performed concurrently. Initial conditions are complete. A reactivity management brief will be performed during turnover. Step 3.1 is complete. BOP Perform a dilution. RO Input targets into the main turbine control panel. NOTE TO EVALUATOR: The crew may decide to input targets to the main turbine prior to performing a dilution. NOTE TO EVALUATOR: Applicant may perform a dilution per OP/1/A/6150/009, Boron Concentration Control, Enclosure 5 (Manual Operation Of The Makeup Controls). Refer to Attachment 3. NOTE TO EVALUATOR: The following actions are taken from OP/1/6150/009, Boron Concentration Control, Enclosure 4.3 (Dilution). BOP 3.2 IF the blender is set for automatic makeup per Enclosure 4.1 (Automatic Makeup), record the setpoint on 1NV-242A (RMWST To B/A Blender Ctrl): ___________gpm BOP 3.3 Ensure the following valve control switches in "AUTO": 1NV-242A (RMWST To B/A Blender Ctrl) 1NV-181A (B/A Blender Otlt To VCT) BOP 3.4 Ensure 1NV-242A (RMWST To B/A Blender Ctrl) controller in auto. BOP 3.5 Ensure at least one reactor makeup water pump is in "AUTO" or "ON". BOP 3.6 Record the desired volume of reactor makeup water to be added. _________ gallons BOP 3.7 Adjust the total makeup counter to the desired volume of reactor makeup water to be added. (R.M.) BOP 3.8 Place the "NC MAKEUP MO2DE SELECT" switch to the "DILUTE" position.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 8 of 36 Event

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Power Increase Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 8 of 36 NOTE: High letdown flow rates result in increased backpressure on the letdown line. If letdown flow is > 90 gpm, it may be desirable to reduce flow rate to 80 gpm to avoid the Rx Make-up Flow Deviation alarm and associated automatic actions. BOP 3.9 IF required, adjust the setpoint for 1NV-242A (RMWST To B/A Blender Ctrl) to the desired flow. NOTE TO EVALUATOR: Step 3.10 will not apply. BOP 3.11 IF AT ANY TIME it is desired to divert letdown to the RHT manually operate 1NV-172A (3-Way Divert To VCT-RHT) as follows: 3.11.1 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) to the "RHT" position. 3.11.2 Ensure VCT level is monitored continuously while diverting to the RHT. NOTE: Procedure may continue while performing the following step. 3.11.3 WHEN desired VCT level is reached return 1NV-172A (3-Way Divert To VCT-RHT) to auto as follows: 3.11.3.1 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) in the "VCT" position. 3.11.3.2 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) in the "AUTO" position. BOP 3.12 IF AT ANY TIME during the makeup it becomes necessary to change the makeup flow rate, adjust the setpoint for 1NV-238A (B/A Xfer Pmp To Blender Ctrl) as necessary to achieve the desired flow.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 9 of 36 Event

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Power Increase Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 9 of 36 BOP 3.13 IF AT ANY TIME while dilution is in progress it becomes necessary to stop the dilution, perform the following: 3.13.1 Place the "NC MAKEUP CONTROL" switch to the "STOP" position. 3.13.2 Ensure the following valves close: 1NV-242A (RMWST To B/A Blender Ctrl) 1NV-181A (B/A Blender Otlt To VCT) 3.13.3 IF in "AUTO", verify the reactor makeup water pump stops. 3.13.4 Record reactor makeup water volume added as indicated on the total makeup counter. ____________ gallons 3.13.5 WHEN conditions allow resuming the dilution, perform the following: 3.13.5.1 Determine remaining volume to be added by subtracting the amount previously added (Step 3.13.4) from the desired volume to be added (Step 3.6). _______ - _____ = ____ gallons (Step 3.6) (Step 3.13.4) 3.13.5.2 Adjust total makeup counter to the volume of reactor makeup water determined in Step 3.13.5.1. (R.M.) 3.13.5.3 Place the "NC MAKEUP CONTROL" switch in the "START" position. (R.M.) 3.13.5.4 Verify the following: 1NV-242A (RMWST To B/A Blender Ctrl) modulates to establish desired flow 1NV-181A (B/A Blender Otlt To VCT) opens 3.13.5.5 IF in "AUTO", verify the reactor makeup water pump starts. BOP 3.14 WHILE makeup is in progress, monitor the following for expected results: Control rod motion NC System Tavg Reactor Power Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 10 of 36 Event

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Power Increase Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 10 of 36 NOTE: If a small makeup is being performed, placekeeping for Steps 3.15 through 3.17 may be performed after Step 3.18 is performed. BOP 3.15 Place the "NC MAKEUP CONTROL" switch to the "START" position. (R.M.) BOP 3.16 Verify the following: 1NV-242A (RMWST To B/A Blender Ctrl) modulates to establish desired flow 1NV-181A (B/A Blender Otlt To VCT) opens BOP 3.17 IF in "AUTO", verify the reactor makeup water pump starts. NOTE: The boric acid counter may count up 1 - 5 gallons after termination. BOP 3.18 WHEN the desired volume of reactor makeup water is reached on the total makeup counter, ensure the following valves close. (R.M.) 1NV-242A (RMWST To B/A Blender Ctrl) 1NV-181A (B/A Blender Otlt To VCT) BOP 3.19 IF automatic makeup is desired, perform one of the following: 3.19.1 IF it is desired to change the blender outlet boron concentration, refer to Enclosure 4.1 (Automatic Makeup). OR 3.19.2 IF makeup at the previous concentration is acceptable AND the system was previously aligned per Enclosure 4.1 (Automatic Makeup), perform the following: 3.19.2.1 Ensure the controller for 1NV-242A (RMWST To B/A Blender Ctrl) is set to the value recorded in Step 3.2. (R.M.) 3.19.2.2 Place the "NC MAKEUP MODE SELECT" switch in "AUTO". 3.19.2.3 Place the "NC MAKEUP CONTROL" switch to the "START" position. (R.M.) NOTE TO EVALUATOR: Step 3.20 will END OF DILUTION Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 11 of 36 Event

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Power Increase Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 11 of 36 NOTE TO EVALUATOR: The following steps are from OP/1/B/6300/001, Turbine Generator, Enclosure 4.2 (Load Changing) starting at step 3.1.2. RO 3.1.2 Increase turbine generator load by performing the following: 3.1.2.1 Select "LOAD RATE" and verify it illuminates. 3.1.2.2 Input the desired load rate. 3.1.2.3 Select "ENTER" or "OK" and verify "LOAD RATE" goes dark. 3.1.2.4 Select "TARGET" and verify it illuminates. 3.1.2.5 Input the desired load target. 3.1.2.6 Select "ENTER" and verify "TARGET" light goes dark. 3.1.2.7 Verify new load target appears on Target Display. 3.1.2.8 Select "GO" and verify it illuminates to start load increase. 3.1.2.9 Coordinate with Secondary Chemistry to adjust S/G blowdown flowrates to obtain maximum blowdown for the appropriate load. Booth Operator will insert Trigger 1 for EVENT 2 at the discretion of the lead examiner. END OF EVENT 1 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 2 Page 12 of 36 Event

Description:

1NC-32B (Pzr PORV) fails open. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 12 of 36 EVENT 2 Indications: 1AD- 1AD- OAC pt C1Q0758 32B - OPEN BOP Attempt to close 1NC-32B (PZR PORV) CRITICAL TASK #2 BOP Close 1NC-31B (PZR PORV ISOL) NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/011, Pressurizer Pressure Anomalies. NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/011, Pressurizer Pressure Anomalies, Case I (Pressurizer Pressure Decreasing). BOP 1. Verify all Pzr PORVs - CLOSED. BOP 1. RNO Perform the following: a. CLOSE Pzr PORV(s). CRITICAL TASK #2 BOP b. IF any Pzr PORV cannot be closed, THEN: 1) Close the affected PORV(s) isolation valve. NOTE TO EVALUATOR: Step 2) of RNO will not apply. NOTE Control rods may withdraw on decreasing NC pressure. BOP 2. Verify Pzr spray valve(s) CLOSED. BOP 3. Verify all Pzr heaters ENERGIZED. BOP 4. Ensure 1NV-37A (NV Supply To Pzr Aux Spray) CLOSED. NOTE Positive reactivity is inserted during an increase in NC pressure which may cause auto rod insertion. BOP 5. Verify NC pressure STABLE OR INCREASING. RO and BOP 6. WHEN NC pressure is stable, THEN: Stabilize unit at appropriate power level. Adjust the following as required to maintain T-Avg within 1°F of T-Ref: Turbine load Control rods Boron concentration.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 2 Page 13 of 36 Event

Description:

1NC-32B (Pzr PORV) fails open. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 13 of 36 NOTE TO EVALUATOR: Step 7 does not apply. BOP 8. Ensure compliance with appropriate Tech Specs: 3.3.1 (Reactor Trip System (RTS) Instrumentation) 3.3.2 (Engineered Safety Features Actuation System (ESFAS) Instrumentation) 3.3.3 (Post Accident Monitoring (PAM) Instrumentation) 3.3.4 (Remote Shutdown System) 3.4.1 (RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits) 3.4.4 (RCS Loops MODES 1 and 2) 3.4.5 (RCS Loops MODE 3) 3.4.6 (RCS Loops MODE 4) 3.4.9 (Pressurizer) 3.4.10 (Pressurizer Safety Valves) 3.4.11 (Pressurizer Power Operated Relief Valves (PORVs)) 3.4.13 (RCS Operational Leakage). NOTE TO EVALUATOR: Tech Spec 3.4.1 (RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits) Condition A (Restore DNB parameter(s) to within limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) should be entered. This condition is likely to be cleared by the time Tech Specs are reviewed per the AP. Tech Spec 3.4.11 (Pressurizer Power Operated Relief Valves (PORVs)) Condition B (Close associated block valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Remove power from associated block valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Restore PORV(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Tech Spec conditions that have been entered. SRO 9. Determine long term plant status. RETURN TO procedure in effect. NOTE TO summarize the event. Booth Operator will insert Trigger 5 for Event 3 at the discretion of the lead examiner. END OF EVENT 2 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 14 of 36 Event

Description:

1B1 KC (Component Cooling) pump trips Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 14 of 36 EVENT 3 Indications: 1AD-6, C/1- 1AD-6, D/1- 1AD-6, E/1- 1AD- 1AD-7, D/3 B 1AD- 1AD- 1AD- 1AD- 1AD- BOP BOP recognizes trip of 1B1 KC pump. SRO CREW ENTERS AP/1/A/5500/021 NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/021, Loss of Component Cooling. NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/021, Loss of Component Cooling. CAUTION Failure to restore NC pump seal cooling via thermal barrier cooling or NV seal injection within 10 minutes will cause damage to the NC pump seals resulting in NC inventory loss. RO and BOP 1. Monitor Enclosure 1 (Foldout Page). BOP 2. Verify the following: At least one KC pump - ON. AND Flow to KC loads presently in service. CRITICAL TASK #5 BOP 2. RNO Perform the following: a. Start additional KC pump(s) as necessary. NOTE TO EVALUATOR: Step 2 RNO b. will not apply SRO 3. IF AT ANY TIME all KC pumps are lost, THEN RETURN TO STEP 2.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 15 of 36 Event

Description:

1B1 KC (Component Cooling) pump trips Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 15 of 36 NOTE Uncooled letdown may result in loss of NV pumps within a matter of minutes. BOP 4. Verify the following: 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK AND At least one KC pump - ON. SRO 5. IF AT ANY TIME 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" LIT, THEN perform Step 4 RNO. BOP 6. Verify both KC surge tank levels - 50% - 90% AND STABLE. BOP 7. Start additional KC pump(s) as necessary to supply any KC loads presently in service. CAUTION A loss of KC cooling to the NC pumps results in a gradual approach to an overheated condition in approximately 10 minutes which will result in shaft seizure. BOP 8. Verify KC flow to NC pumps as follows: 1AD-20, A/1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK 1AD-21, A/1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK. BOP 9. Verify KC available as follows: a. Verify the following Train A KC non-essential header isolation valves - OPEN: 1KC-230A (Rx Bldg Non-Ess Hdr Isol) 1KC-3A (Rx Bldg Non-Ess Ret Hdr Isol) 1KC-50A (Aux Bldg Non-Ess Hdr Isol) 1KC-1A (Aux Bldg Non-Ess Ret Hdr Isol). BOP 9. b. Verify the following Train B KC non-essential header isolation valves -OPEN: 1KC-228B (Rx Bldg Non-Ess Hdr Isol) 1KC-18B (Rx Bldg Non-Ess Ret Hdr Isol) 1KC-53B (Aux Bldg Non-Ess Hdr Isol) 1KC-2B (Aux Bldg Non-Ess Ret Hdr Isol). BOP 9. c. Start additional KC pump(s) as necessary to supply any KC loads presently in service. BOP 10. Verify KC surge tank levels normal as follows: a. Verify both KC surge tank levels - 50% - 90% AND STABLE. SRO 10. b. GO TO Step 14.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 16 of 36 Event

Description:

1B1 KC (Component Cooling) pump trips Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 16 of 36 NOTE TO EVALUATOR: BOP 14. Ensure KC heat exchanger outlet mode switches - PROPERLY ALIGNED. CREW 15. Determine and correct cause of loss of KC. SRO 16. Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual: SLC 16.9-7 (Boration Systems Flow Path- Shutdown) SLC 16.9-8 (Boration Systems Flow Path- Operating) SLC 16.9-9 (Boration Systems Pumps -Shutdown) SLC 16.9-10 (Boration Systems Charging Pumps - Operating) 3.5.2 (ECCS - Operating) 3.5.3 (ECCS - Shutdown) 3.6.6 (Containment Spray System) 3.7.5 (Auxiliary Feedwater (AFW) System) 3.7.7 (Component Cooling Water (CCW) System). NOTE TO EVALUATOR: T.S 3.7.7 (Component Cooling Water (CCW) System) Condition A (Restore CCW train to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />) should be entered. to inform the crew of any Tech Spec conditions that have been entered. Booth Operator will insert Trigger 1 for EVENT 4 at the discretion of the lead examiner. SRO 17. Determine required notifications: REFER TO RP/0/A/5000/001(Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). NOTE TO EVALUATOR: Step 18 will not apply. BOP 19. Verify KC surge tanks level as follows: Greater than 50% Stable or increasing Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 17 of 36 Event

Description:

1B1 KC (Component Cooling) pump trips Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 17 of 36 BOP 20. WHEN plant conditions permit, THEN perform the following: Return KC pumps to normal operation. REFER TO OP/1/A/6400/005 (Component Cooling Water System). Return NV Pump 1A to normal cooling as applicable. REFER TO Enclosure 2 (Alternate Cooling To NV Pump 1A). BOP 21. Verify the following: 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK 1AD-7, H/3 "VCT HI TEMP" - DARK Normal letdown - IN SERVICE. BOP 22. Ensure VCT and letdown path aligned as follows: a. IF desired to align NV pump suction to VCT, then perform the following: 1) OPEN the following valves: 1NV-188A (VCT Otlt Isol) 1NV-189B (VCT Otlt Isol). 2) CLOSE the following valves: 1NV-252A (NV Pumps Suct From FWST) 1NV-253B (NV Pumps Suct From FWST). b. WHEN NV suction aligned to VCT, THEN momentarily place 1NV-172A (3-Way Divert To VCT-RHT) to "VCT" position and return to "AUTO". c. IF desired to restore letdown flow through NV demineralizers, THEN momentarily place 1NV-153A (Letdn Hx Otlt 3-Way Valve) to "DEMIN" position and return to "AUTO". SRO 23. Determine long term plant status. RETURN TO procedure in affect. summarize the event. END OF EVENT 3 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4 Page 18 of 36 Event

Description:

1CF-46 (S/G 1C CF CTRL) fails open. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 18 of 36 EVENT 4 Indications: 1AD- 1AD- RO Place 1CF-46 (S/G C necessary to control 1C S/G level. NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/006, Loss of S/G Feedwater. NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/006, Loss of S/G Feedwater, Case III (CF Control Not in Auto). CREW 1. IF AT ANY TIME S/G levels approaching: 83% N/R level (S/G HI-HI Level Turb Trip) OR 11% N/R level (S/G LO-LO Level Rx Trip). THEN: a. Manually trip reactor. b. GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection). RO or BOP 2. Verify the following: At least one CF pump - IN SERVICE 1AD-3, C/6 "CF ISOL TRN A" - DARK 1AD-3, D/6 "CF ISOL TRN B" - DARK. RO or BOP 3. IF AT ANY TIME any CF main feed reg valve in manual, THEN ensure associated feed reg bypass valve in manual. Booth Operator will insert Trigger 7 for EVENT 5 at the discretion of the lead examiner. RO or BOP 4. Verify CF pump speed controller for in Perform the following: service CF pump(s): IN AUTO RESPONDING ADEQUATELY RO or BOP 5. Verify all S/G CF control valves: IN AUTO RESPONDING ADEQUATELY Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4 Page 19 of 36 Event

Description:

1CF-46 (S/G 1C CF CTRL) fails open. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 19 of 36 CRITICAL TASK #1 RO or BOP 5. RNO Perform the following for the affected S/G(s): a. Ensure affected controller(s) IN MANUAL. b. IF AT ANY TIME S/G level not on program, THEN 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 RO or BOP 6. Verify the following: S/G level(s) - STABLE S/G level(s) - APPROXIMATELY AT PROGRAM Malfunction - CORRECTED. CREW 6. RNO Perform the following: a. Continue to control CF/SM D/P and S/G CF Flow rates to stabilize level in affected S/G(s) approximately at program level. b. WHEN all the following conditions met: S/G level(s) - STABLE S/G level(s) - APPROXIMATELY AT PROGRAM Malfunction - CORRECTED. THEN GO TO Step 7. c. Do not continue in this procedure until all conditions met. NOTE TO EVALUATOR: RNO Step 6.b will not be met during this scenario. NOTE TO EVALUATOR: The SRO will conduct a summarize the event. END OF EVENT 4 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 5 Page 20 of 36 Event

Description:

1B S/G Tube Leak Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 20 of 36 EVENT 5 Indications: 1RAD- 1RAD--72 S/G B 1RAD--73 S/G C 1RAD- 1EMF 27 CREW Recognizes symptoms of a S/G tube leak BOP CSAE EXH switch on panel 1MC-13 per the annunciator response for 1RAD-1, B/1 (1EMF CSAE EXHAUST HI RAD). CREW Enter AP/1/A/5500/010, Reactor Coolant Leak, Case I (Steam Generator Tube Leak) NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/010, Reactor Coolant Leak. NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/010, Reactor Coolant Leak, Case I (Steam Generator Tube Leak) RO and BOP 1. Monitor Enclosure 1 (Case I Steam Generator Tube Leak Foldout Page). BOP 2. Verify Pzr level - STABLE OR INCREASING. BOP 2. RNO: Perform the following: a. Maintain charging flow less than 180 GPM. b. THROTTLE 1NV-294 (NV Pmps A&B Disch Flow Ctrl) to stabilize Pzr level. NOTE TO EVALUATOR: Crew determines that step 2 RNO c. does not apply BOP c. IF Pzr level stable OR increasing, THEN GO TO Step 3.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 5 Page 21 of 36 Event

Description:

1B S/G Tube Leak Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 21 of 36 NOTE TO EVALUATOR: The crew will eventually recognize that pressurizer level cannot be maintained and manually trip the reactor and manually initiate safety injection per Enclosure 1, and then transition to E-0 (Reactor Trip or Safety Injection). BOP d. IF Pzr level continues to decrease, THEN perform the following: 1) Reduce letdown flow to 45 GPM as follows: a) IF 1NV-10A (Letdn Orif 1B Otlt Cont Isol) open, THEN perform the following: (1) Control 1NV-148 (Letdn Press Control) to establish letdown pressure between 375 400 PSIG. (2) THROTTLE 1NV-849 (Letdn Flow Var Orif Ctrl) for 45 GPM letdown flow. (3) WHEN 45 GPM letdown flow established, THEN adjust 1NV-148 (Letdn Press Control) to maintain letdown pressure at 350 PSIG. (4) WHEN letdown pressure is stable at 350 PSIG, THEN place 1NV-148 (Letdn Press Control) in auto. BOP 2) IF Pzr level continues to decrease, THEN ensure the following valves closed: 1NV-10A (Letdn Orif 1B Otlt Cont Isol) 1NV-11A (Letdn Orif 1C Otlt Cont Isol) 1NV-13A (Letdn Orif 1A Otlt Cont Isol). NOTE TO EVALUATOR: Crew determines that step 2 RNO d.3) does not apply. CREW 4) IF Pzr level continues to decrease OR Pzr level cannot be maintained greater than 4%, THEN perform the following: a) Trip reactor. b) WHEN reactor tripped verified, THEN initiate S/I. c) GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection). END EVENT 5 give the crew direction. TRANSITION TO EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6, 7 and 8 Page 22 of 36 Event

Description:

1B S/G Tube Rupture, 1SV-13 (S/G PORV) fails open, A Train Phase A failure with 1NV-91B (NC PUMPS SEAL RET CONT ISOL) failure to close. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 22 of 36 EVENTS 6, 7, AND 8 NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) RO and BOP 1. Monitor Enclosure 1 (Foldout Page). RO 2. Verify Reactor Trip: All rod bottom lights - LIT All reactor trip and bypass breakers - OPEN I/R power - DECREASING. RO 3. Verify Turbine Trip: All turbine stop valves - CLOSED BOP 4. Verify 1ETA and 1ETB - ENERGIZED. RO 5. Verify S/I is actuated: a. "SAFETY INJECTION ACTUATED" status light (1SI-13) LIT b. Both E/S load sequencer actuated status lights (1SI-14) - LIT. RO 6. Announce "Unit 1 Safety Injection". SRO 7. Determine required notifications: REFER TO RP/0/A/5000/001(Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). RO or BOP 8. Verify all Feedwater Isolation status lights (1SI-5) - LIT BOP 9. Verify Phase A Containment Isolation status as follows: a. Phase A "RESET" lights - DARK. CRITICAL TASK #6 BOP 9. a. RNO a. Initiate Phase A Isolation. BOP b. Monitor Light Panel Group 5 St lights on energized train(s) - LIT. CRITICAL TASK #6 BOP 9. b. RNO b. Align valves as necessary to ensure each penetration isolated by at least one isolation valve. END OF EVENT 8 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 and 7 Page 23 of 36 Event

Description:

1B S/G Tube Rupture, 1SV-13 (S/G PORV) fails open Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 23 of 36 BOP b. Monitor Light Panel Group 5 St lights on energized train(s) - LIT. BOP 10. Verify proper Phase B actuation as follows: a. Verify Containment pressure - HAS REMAINED LESS THAN 3 PSIG RO or BOP b. IF AT ANY TIME containment pressure exceeds 3 PSIG while in this procedure, THEN perform Step 10.a. RO 11. Verify proper CA pump status as follows: a. Motor driven CA pumps - ON. b. 3 S/G N/R levels - GREATER THAN 11%. BOP 12. Verify all of the following S/I pumps - ON: NV pumps ND pumps NI pumps. BOP 13. Verify all KC pumps - ON. BOP 13. RNO Perform the following for affected train(s): a. Reset ECCS. b. Reset D/G load sequencer(s). c. Start affected pump(s). RO and BOP d. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on. NOTE TO EVALUATOR: RNO Step 13.e. will not apply BOP 14. Verify all Unit 1 and Unit 2 RN pumps - ON. BOP 15. Verify proper ventilation systems operation as follows: REFER TO Enclosure 2 (Ventilation System Verification). Notify Unit 2 operator to perform Enclosure 3 (Opposite Unit Ventilation Verification). NOTE TO EVALUATOR: SRO hands Enclosure 3 to a Unit 2 operator and sets Enclosure 3 off to the side. RO 16. Verify all S/G pressures - GREATER THAN 775 PSIG. RO 17. Verify proper S/I flow as follows: a. "NV S/I FLOW" - INDICATING FLOW.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 and 7 Page 24 of 36 Event

Description:

1B S/G Tube Rupture, 1SV-13 (S/G PORV) fails open Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 24 of 36 RO b. NC pressure - LESS THAN 1620 PSIG. RO 17.b. RNO b. Perform the following: 1) Ensure ND pump miniflow valve on operating ND pump(s) - OPEN. NOTE TO EVALUATOR: Step 17 RNO b. 2) will not apply SRO 3) GO TO Step 18. RO or BOP 18. WHEN time and manpower permit (within two hours of event), THEN monitor Spent Fuel Pool level and temperature. REFER TO EP/1/A/5000/G-1(Generic Enclosures), Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring). RO 19. Control S/G levels as follows: a. Verify total CA flow - GREATER THAN 450 GPM. NOTE TO EVALUATOR: Total CA flow may not be > 450 gpm due to being under operator control, in which case, the RNO for 19 a. will not apply. RO b. WHEN each S/G N/R level greater than 11% (29% ACC), THEN control feed flow to maintain that S/G N/R level between 11% (29% ACC) and 50%. RO 20. Verify all CA isolation valves - OPEN. BOP 21. Verify S/I equipment status based on monitor light panel - IN PROPER ALIGNMENT. NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance. RO 22. Control NC temperature. REFER TO Enclosure 4 (NC Temperature Control). BOP 23. Verify Pzr PORV and Pzr Spray Valve status as follows: a. All Pzr PORVs - CLOSED. BOP 23. RNO a. IF Pzr pressure is less than 2315 PSIG, THEN perform the following: 1) CLOSE Pzr PORV(s). 2) IF any Pzr PORV cannot be closed, THEN CLOSE its isolation valve. NOTE TO EVALUATOR: Step 23 RNO.a.3) will not apply Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 and 7 Page 25 of 36 Event

Description:

1B S/G Tube Rupture, 1SV-13 (S/G PORV) fails open Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 25 of 36 BOP 23. b. Normal Pzr spray valves - CLOSED. BOP 23. c. At least one Pzr PORV isolation valve - OPEN. RO or BOP 24. Verify NC subcooling based on core exit T/Cs - GREATER THAN 0°F. RO or BOP 25. Verify main steamlines intact: All S/G pressures - STABLE OR INCREASING ALL S/Gs - PRESSURIZED. NOTE TO EVALUATOR: If the crew has not addressed the failed open S/G PORV, they may transition to the RNO and go to EP/1/A/5000/E-2 (Faulted Steam Generator Isolation). REFER to Attachment 10. BOP 26. Verify S/G tubes are intact as follows: Verify the following EMF trip 1 lights - DARK: 1EMF-33 (Condenser Air Ejector Exhaust) 1EMF-26 (Steamline 1A) 1EMF-27 (Steamline 1B) 1EMF-28 (Steamline 1C) 1EMF-29 (Steamline 1D). All S/G levels - STABLE OR INCREASING IN A CONTROLLED MANNER. CREW 26. RNO IF any EMF trip 1 light is lit OR any S/G level is increasing in an uncontrolled manner, THEN concurrently: Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees). GO TO EP/1/A/5000/E-3 (Steam Generator Tube Rupture). NOTE TO EVALUATOR: Due to the time critical nature of the event, the SRO will not TRANSITION TO EP/1/A/5000/E-3 (Steam Generator Tube Rupture)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 and 7 Page 26 of 36 Event

Description:

1B S/G Tube Rupture, 1SV-13 (S/G PORV) fails open Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 26 of 36 NOTE TO EVALUATOR: The following actions are from EP/1/A/5000/E-3 (Steam Generator Tube Rupture). RO and BOP 1. Monitor Enclosure 1 (Foldout Page). CREW 2. Identify ruptured S/G(s) as follows: S/G level - INCREASING IN AN UNCONTROLLED MANNER. OR Chemistry or RP has determined ruptured S/G OR Any of the following EMF trip 1 lights - LIT: 1EMF-26 (Steamline 1A) 1EMF-27 (Steamline 1B) 1EMF-28 (Steamline 1C) 1EMF-29 (Steamline 1D). RO 3. Verify at least one intact S/G - AVAILABLE FOR NC SYSTEM COOLDOWN. RO 4. Isolate flow from ruptured S/G(s) as follows: a. Verify all ruptured S/G(s) PORV - CLOSED. CRITICAL TASK #3 RO 4.a. RNO a. WHEN ruptured S/G(s) pressure less than 1090 PSIG, THEN perform the following: 1) Ensure ruptured S/G(s) PORV - CLOSED. END OF EVENT 7 NOTE TO EVALUATOR: RNO Steps 4.a.2) and 4.a.3) will not apply. RO b. Verify S/G(s) 1B and 1C - INTACT. CRITICAL TASK #3 RO 4.b. RNO b. Perform the following: 1) IF both motor driven CA pumps available, THEN CLOSE "CAPT TRIP T/V CTRL". NOTE TO EVALUATOR: RNO Step 4.b.2) will not apply.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 Page 27 of 36 Event

Description:

1B S/G Tube Rupture Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 27 of 36 RO or BOP 3) IF S/G 1B ruptured, THEN perform the following: a) Dispatch two operators to unlock and close 1SA-1 (1B S/G Main Steam to CAPT Maintenance Isol) (DH-624, FF-53, Rm 572) (Breakaway lock). NOTE TO EVALUATOR: The Crew may determine that radiation may be too high to perform RNO step 4.b.3)a) and perform 4.b.3)b) instead. RO or BOP b) IF 1SA-1 cannot be closed, THEN dispatch two operators to unlock and close 1SA-3 (1B S/G Main Steam to CAPT Stop Check) (AB-551, DD-53, Rm 217) (Breakaway lock). NOTE TO EVALUATOR: RNO Step 4.b.4) will not apply RO 5) WHEN ruptured S/G steam supply to CA Pump #1 isolated, THEN OPEN "CAPT TRIP T/V CTRL". CRITICAL TASK #3 RO c. Isolate blowdown and steam drain on all ruptured S/G(s) as follows: S/G 1B 1) Close 1SM-76B (S/G 1B Otlt Hdr Bldwn C/V). 2) Verify the following blowdown isolation valves - CLOSED: a) 1BB-19A (S/G 1B Bldwn Cont Isol Insd). b) 1BB-150B (S/G 1B Bldwn Cont Isol Byp). c) 1BB-21B (S/G 1D Bldwn Cont Isol Otsd). CRITICAL TASK #3 RO 5. Close the following valves on all ruptured S/G(s): MSIV MSIV bypass valve. CRITICAL TASK #3 RO 6. Control ruptured S/G(s) level as follows: a. Verify ruptured S/G(s) N/R level - GREATER THAN 11% (29% ACC). b. Isolate feed flow to all ruptured S/G(s) as follows: S/G 1B: 1) CLOSE 1CA-58A (CA Pmp A Disch To S/G 1B Isol). 2) CLOSE 1CA-54B (CA Pmp 1 Disch To S/G 1B Isol). c. IF AT ANY TIME ruptured S/G(s) N/R level is less than 11% (29% ACC), THEN perform Step 6. RO 7. Verify all ruptured S/G(s) pressure - GREATER THAN 320 PSIG.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 Page 28 of 36 Event

Description:

1B S/G Tube Rupture Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 28 of 36 BOP 8. Verify any NC pump - ON. BOP 9. Verify Pzr pressure - GREATER THAN 1955 PSIG. NOTE NC pump trip criteria based on NC subcooling does not apply after starting a controlled cooldown. After the low steamline pressure main steam isolation signal is blocked, maintaining steam pressure negative rate less than 2 psig per second will prevent a Main Steam Isolation. OAC graphic SMRATES to monitor S/G pressure rates can be accessed via a hot button in the center of the SM graphic. RO 10. Initiate NC System cooldown as follows: a. Determine required core exit temperature based on lowest ruptured S/G pressure from table below: NOTE TO EVALUATOR: SRO and BOP will use the table in step 10 to determine target core exit temperature. Refer to Attachment 12. RO b. Ensure ruptured S/G(s) isolated as follows: 1) Verify the following valves on all ruptured S/G(s) - CLOSED: MSIV MSIV bypass valves. 2) Verify S/G PORV on ruptured S/G(s) - CLOSED OR ISOLATED. NOTE TO EVALUATOR: Step 10.b.3) will not apply. RO c. Verify the condenser is available as follows: "C-9 COND AVAILABLE FOR STM DUMP" status light (1SI-18) - LIT MSIV on intact S/G(s) - OPEN. d. Verify steam dumps - IN PRESSURE MODE. RO 10.d. RNO Place steam dumps in pressure mode as follows: 1) Place "STM DUMP CTRL" M/A station in manual. 2) Adjust "STM DUMP CTRL" M/A station output to match "% STM DUMP DEMAND" (1SMP5211). 3) WHEN output on the "STM DUMP CTRL" M/A station is equal to the "% STM DUMP DEMAND" (1SMP5211), THEN place the steam dumps in pressure mode.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 Page 29 of 36 Event

Description:

1B S/G Tube Rupture Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 29 of 36 RO e. WHEN "P-12 LO-LO TAVG" status light (1SI-18) is lit, THEN place the steam dump interlock bypass switches in "BYP INTLK." f. Dump steam to condenser from intact S/G(s) at maximum rate while attempting to avoid a Main Steam Isolation. BOP g. Verify main steam isolation blocked status lights (1SI-13) - LIT. BOP 10.g. RNO Perform the following: 1) Depressurize NC System to less than 1955 PSIG using one of the following: Pzr spray OR Pzr PORV. 2) WHEN "P-11 PZR S/I BLOCK PERMISSIVE" status light (1SI-18) is lit, THEN perform the following: a) Depress ECCS steam pressure "BLOCK" pushbuttons. b) Verify main steam isolation blocked status lights (1SI-13) - LIT. 3) Maintain NC pressure less than 1955 PSIG. RO h. WHEN core exit T/Cs are less than required temperature, THEN stabilize core exit T/Cs less than required temperature. RO 11. Control intact S/G levels as follows: a. Verify N/R level in all intact S/Gs - GREATER THAN 11% (29% ACC). b. Throttle feed flow to maintain all intact S/G N/R levels between 16% (29% ACC) and 50%. BOP 12. Verify Pzr PORV and isolation valve status as follows: a. Power to all Pzr PORV isolation valves - AVAILABLE. b. All Pzr PORVs - CLOSED. BOP 12.b. RNO b. IF Pzr pressure is less than 2315 PSIG, THEN perform the following: 1) CLOSE Pzr PORV(s). 2) IF any Pzr PORV cannot be closed, THEN CLOSE its isolation valve.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 Page 30 of 36 Event

Description:

1B S/G Tube Rupture Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 30 of 36 NOTE TO EVALUATOR: RNO Steps 12.b.3) and 12.b.4) will not apply. BOP c. At least one Pzr PORV isolation valve - OPEN. RO or BOP d. IF AT ANY TIME a Pzr PORV opens due to high pressure, WHEN Pzr pressure decreases to less than 2315 PSIG, ensure the valve closes or is isolated. BOP 13. Reset the following: a. ECCS. b. D/G load sequencers. c. Phase A d. Phase B. RO or BOP e. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on. BOP 14. Establish VI to containment as follows: Ensure 1VI-77B (VI Cont Isol) - OPEN. Verify VI pressure - GREATER THAN 85 PSIG. BOP 15. Determine if ND pumps should be stopped: a. Any ND pump - ON. b. Any running ND pump suction ALIGNED TO FWST. c. NC pressure - GREATER THAN 285 PSIG. d. Stop all ND pump(s) with suction aligned to FWST. e. IF AT ANY TIME NC pressure decreases to less than 285 PSIG in an uncontrolled manner, THEN restart ND pumps. RO 16. Verify ruptured S/G(s) - IDENTIFIED. RO 17. Verify if NC System cooldown should be stopped: a. Verify core exit T/Cs - LESS THAN REQUIRED TEMPERATURE. NOTE TO EVALUATOR: At this point the required temperature may not have been reached. The crew will hold per the RNO for step 17.a. SRO 17.a RNO Do not continue in this procedure until core exit T/Cs are less than required temperature. RO b. Stop NC System cooldown. c. Stabilize core exit T/Cs - LESS THAN REQUIRED TEMPERATURE.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 Page 31 of 36 Event

Description:

1B S/G Tube Rupture Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 31 of 36 RO 18. Verify ruptured S/G(s) pressure is under operator control as follows: a. All ruptured S/G(s) pressure - STABLE OR INCREASING. b. IF AT ANY TIME ruptured S/G(s) pressure is decreasing while in this procedure, THEN perform Step 18. RO or BOP 19. Verify NC subcooling based on core exit T/Cs - GREATER THAN 20°F. BOP 20. Depressurize NC System using PZR Spray as follows: a. Verify normal Pzr spray flow - AVAILABLE. b. Initiate NC depressurization using maximum available spray. c. IF AT ANY TIME during this step one of the following conditions exists, THEN GO TO Step 21: Spray valves not effective in reducing NC pressure OR Ruptured S/G(s) NR level approaching 83% (75% ACC). d. Do not continue until at least one of the following conditions satisfied: Both of the following: NC pressure - LESS THAN RUPTURED S/G(s) PRESSURE Pzr level - GREATER THAN 11% (30% ACC) OR Both of the following: NC pressure - WITHIN 300 PSIG OF RUPTURED S/G(s) PRESSURE Pzr level - GREATER THAN 41% (50% ACC) OR Pzr level - GREATER THAN 68% (50% ACC) OR NC subcooling based on core exit T/Cs - LESS THAN 0°F. e. CLOSE normal Pzr spray valves. f. Verify 1NV-37A (NV Supply To Pzr Aux Spray) CLOSED SRO g. Observe Caution prior to Step 23 and GO TO Step 23. NOTE TO EVALUATOR: The crew may decide that spray valves are not effective and transition to step 21.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 Page 32 of 36 Event

Description:

1B S/G Tube Rupture Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 32 of 36 BOP 21. Depressurize NC System using Pzr PORV as follows: a. Verify at least one Pzr PORV - AVAILABLE. b. OPEN one Pzr PORV. c. Do not continue until at least one of the following conditions satisfied: NC subcooling based on core exit T/Cs - LESS THAN 0°F OR Pzr level - GREATER THAN 68% (50% ACC) OR Both of the following: NC pressure - LESS THAN RUPTURED S/G(s) PRESSURE Pzr level - GREATER THAN 11% (30% ACC). d. CLOSE Pzr PORV. e. CLOSE Pzr spray valves. BOP 22. Verify NC pressure - INCREASING. CAUTION S/I must be terminated when termination criteria are satisfied to prevent overfilling the ruptured S/G(s). RO or BOP 23. Verify S/I termination criteria as follows: a. NC subcooling based on core exit T/Cs - GREATER THAN 0°F. b. Verify secondary heat sink as follows: N/R level in at least one intact S/G - GREATER THAN 11% (29% ACC) OR Total feed flow available to S/G(s) - GREATER THAN 450 GPM. c. NC pressure - STABLE OR INCREASING. d. Pzr level - GREATER THAN 11% (30% ACC). BOP 24. Stop S/I pumps as follows: a. Stop NI pumps. b. Ensure only one NV pump - ON.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 Page 33 of 36 Event

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1B S/G Tube Rupture Time Position Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 33 of 36 CRITICAL TASK #4 BOP 25. Isolate NV S/I flowpath as follows: a. Verify the following valves - OPEN: 1NV-252A (NV Pumps Suct From FWST) 1NV-253B (NV Pumps Suct From FWST). b. Ensure the following valves - OPEN: 1NV-203A (NV Pumps A&B Recirc Isol) 1NV-202B (NV Pmps A&B Recirc Isol). c. Close the following valves: 1NI-9A (NV Pmp C/L Inj Isol) 1NI-10B (NV Pmp C/L Inj Isol). END OF EVENT 6 END OF SCENARIO Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 34 of 36 Attachment List Scenario 4 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 OP/1/A/6150/009 Enclosure 4.5 (Manual Operation of the Makeup Controls), rev. 079 ATTACHMENT 4 AP/1/A/5500/021 Enclosure 1 (Foldout Page), rev. 042 ATTACHMENT 5 AP/1/A/5500/010 Enclosure 1 (Foldout Page), rev. 057 ATTACHMENT 6 EP/1/A/5000/E-0 Enclosure 1 (Foldout Page), rev. 042 ATTACHMENT 7 EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification), rev. 042 ATTACHMENT 8 EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control), rev. 042 ATTACHMENT 9 EP/1/A/5000/G-1 Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring), rev.007 ATTACHMENT 10 EP/1/A/5000/E-2 (Faulted Steam Generator Isolation), rev. 015 ATTACHMENT 11 EP/1/A/5000/E-3 Enclosure 1 (Foldout Page), rev. 043 ATTACHMENT 12 EP/1/A/5000/E-3 page 23 (Step 10 table)

Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 4 NUREG 1021 Revision 9 Page 35 of 36 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK 1 Manually control feedwater to prevent reaching an S/G Hi Hi level Turbine trip or Lo Lo level Rx trip. 2 Close the block valve upstream of the stuck open PZR PORV prior to RPS actuation. 3 Isolate feed/steam to/from ruptured S/G before a transition to ECA-3.1. 4 Terminate S/I before water release occurs from the ruptured S/G PORV or safety. 5 Start a Component Cooling pump prior to reaching any RPS trip criteria. 6 Isolate the containment penetration flow path prior to exit out of E-0 Comments:

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 25% MOL 1168 PPM per OAC Controlling Procedure OP/1/A/6100/003 (Controlling Procedure for Unit Operation), Enclosure 4.1 (Power Increase) is in progress up to step 3.21. Other Information Needed to Assume the Shift Unit 2 is at 100%. The 1A KF (Fuel Pool Cooling) Pump is tagged out for preventative maintenance. The 1A2 CFPT MOP is tagged out for motor replacement. Increase Power per the reactivity plan. NEOs Available Six NEOs are available as listed on the status board METEOROLOGICAL CONDITIONS Upper wind direction = 315 degrees, speed = 10 mph Lower wind direction = 315 degrees, speed = 10.5 mph Forecast calls for Severe Thunderstorm Watch for the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 1 of 38 NRC INITIAL LICENSE EXAM SCENARIO # 5 Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 2 of 38 Facility: Catawba NRC Exam 2014 Scenario No.: 5 Op Test No.: 2014301 Examiners: Operators: SRO RO BOP Initial Conditions: IC# 180; Unit 1 is at 75% power, BOL. Unit 2 is at 100%. The 1A KF (Fuel Pool Cooling) Pump is tagged out for preventative maintenance. The 1A2 CFPT MOP is tagged out for motor replacement Turnover: Unit 1 is at 75% power, BOL. Increase power to 100% per the reactivity management plan. Event No. Malf. No. Event Type* Event Description 1 --- N-BOP R-RO N-SRO Power increase. 2 IDE005G C-RO C-SRO 1SV-42 (SM ATMOS DUMP #7) fails open. AP/28 3 ENB013A C-BOP C-SRO TS-SRO N41 fails low. AP/16 4 NV015 C-BOP C-SRO 1NV-309 (SEAL WATER INJECTION FLOW) fails open. AP/08 5 FW003 TS-SRO FWST Level Ch 3 fails low 6 NCP008A C-RO C-SRO 1A NC (Reactor Coolant ) Pump #1 Seal Failure. AP/08 7 NC013A M-ALL LBLOCA 8 CA013 C-RO C-SRO 1SA-5 fails open. 9 VV003A VX004 C-BOP Both Hydrogen Skimmer fans fail to start. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 3 of 38 Initial Condition IC #180 IC# 180; Unit 1 is at 75% power, BOL. Unit 2 is at 100%. The 1A KF (Fuel Pool Cooling) Pump is tagged out for preventative maintenance. The 1A2 CFPT MOP is tagged out for motor replacement. Turnover: IC# 180; Unit 1 is at 75% power, BOL. Unit 2 is at 100%. The 1A KF (Fuel Pool Cooling) Pump is tagged out for preventative maintenance. The 1A2 CFPT MOP is tagged out for motor replacement. Increase power to 100% per the reactivity management plan. Event 1 Increase power. Event 2 1SV-42 (SM ATMOS DUMP #7) fails open. AP/28 Event 3 N41 fails low. AP/16 Event 4 1NV-309 (SEAL WATER INJECTION FLOW) fails open. AP/08 Event 5 FWST Level Ch 3 fails low. Event 6 1A NC (Reactor Coolant ) Pump #1 Seal Failure. AP/08. Event 7 LBLOCA Event 8 1SA-5 fails open. Event 9 Both Hydrogen Skimmer fans fail to start.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 4 of 38 EXERCISE GUIDE WORKSHEET 1. INITIAL CONDITIONS: 1.1 Reset to IC #180 START TIME:__________ Trigger Instructor Action Final Delay Ramp Delete In Event 1 MAL-IDE005G (ATM STEAM DUMP SV42 UNCONDITIONAL FAILURE) 100 2 3 MAL-ENB013A (P/R 41 BLOWN FUSE) INST 3 5 MAL-NV015 (SEAL INJ FLOW CTRLR NV-309 FAILURE) 100 2 MIN 4 8 MAL-NV015 (SEAL INJ FLOW CTRLR NV-309 FAILURE) 100 1 SEC 4 11 XMT-FW003 [LFW_5120 WR FWST LVL CH 3 TO DCS (FWAA5120)] 0 5 13 MAL-NCP008A (NCP A NO.1 SEAL FAILURE) 9 30 SEC 6 16 MAL-NC013A NC COLD LEG A LEAK) 27.5 7 18 VLV-CA031F (SA5 CA PMP TURB STM SPLY VL FAIL TO POSITION) 1 8 n/a MAL-VV003A (HYDROGEN SKIMMER FAN A AUTO FAILURE) 9 18 LOA-VX004 (RACKOUT HYD SKIMMER FAN 1B) RACK OUT 9 MIN 9 n/a OVR-FWP019A (CFPT 1A MOP 1A2 OFF LT) OFF n/a OVR-FWP019B (CFPT 1A MOP1A2 ON LT) OFF n/a LOA-KF004 (RACKOUT KF PMP A) RACK OUT Ensure TRIGGER 8 = DCS_SLIM9ManLight Ensure TRIGGER 16 = x10o151g Ensure TRIGGER 18 = x01o063g I x01o066g Place red collars on the 1A KF Pump and the 1A2 CFPT MOP Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 5 of 38 2. SIMULATOR BRIEFING 2.1 Control Room Assignments: Position Name CRS RO BOP 2.2 Give a copy of Attachment 2 (Shift Turnover Information) to the CRS. 3. EXERCISE PRESENTATION 3.1 Familiarization Period A. Allow examinees time to familiarize themselves with Control Board alignments. 3.2 Scenario EVENT 1, increase reactor power to 100%. BOOTH INSTRUCTOR ACTION IF the SOC is called to be informed of the power increase, REPEAT the information. 3.3 Scenario EVENT 2, 1SV-42 Fails Open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 1 to cause 1SV-42 to fail open. BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with 1SV-42, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance is dispatched to investigate the problem with 1SV-42, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF RP is notified of the leak, REPEAT back the information. 3.4 Scenario EVENT 3, N-41 blown instrument fuse. BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause the instrument fuse for N-41 to blow.

Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 6 of 38 BOOTH INSTRUCTOR ACTION IF IAE is contacted to fail bistables per model W/O #00874531, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF SWM is contacted to write a w/r for N41, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF the Reactor Group Engineer is notified of N41 failure, REPEAT back the information. 3.5 Scenario EVENT 4, 1NV-309 Fails Open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to fail 1NV-309 open. BOOTH INSTRUCTOR ACTION IF SWM is called to investigate the problem with 1NV-309, REPEAT back the information. 3.6 Scenario EVENT 5, FWST Level Channel 3 Fails Low BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 11 to cause FWST Level Channel 3 to fail low. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to issue Model W/O 01069041 to have IAE provide emergency repairs, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to write a w/r for the FWST Level Channel 3, REPEAT back the information. 3.7 Scenario EVENT 6, 7, 8 and 9 BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 13 to cause 1A NC Pump #1 Seal failure. BOOTH INSTRUCTOR ACTION IF Operator is dispatched to secure all ice condenser air handling units, REPEAT back the information Catawba Nuclear Station NRC Exam May 2014 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 7 of 38 BOOTH INSTRUCTOR ACTION IF Operator is dispatched to place containment hydrogen analyzers in service, REPEAT back the information BOOTH INSTRUCTOR ACTION IF Chemistry is notified to sample all S/Gs for activity, REPEAT the order. BOOTH INSTRUCTOR ACTION IF RP is notified to frisk all cation columns for activity, REPEAT the order. BOOTH INSTRUCTOR ACTION IF Operator dispatched to stop the 1A/1B D/G and place in standby readiness, REPEAT the order.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 1 Page 8 of 38 Event

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Power Increase Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 8 of 38 NOTE TO EVALUATOR: Crew begins with a power increase. BOP performs a dilution per OP/1/A/6150/009, Enclosure 4.3. Amount of dilution will be determined by the power increase plan. The RO will input turbine target data. These two evolutions may be performed concurrently. Initial conditions are complete. A reactivity management brief will be performed during turnover. Step 3.1 is complete. BOP Perform a dilution. RO Input targets into the main turbine control panel. NOTE TO EVALUATOR: The crew may decide to input targets to the main turbine prior to performing a dilution. NOTE TO EVALUATOR: Applicant may perform a dilution per OP/1/A/6150/009, Boron Concentration Control, Enclosure 5 (Manual Operation Of The Makeup Controls). Refer to Attachment 3. NOTE TO EVALUATOR: The following actions are taken from OP/1/6150/009, Boron Concentration Control, Enclosure 4.3 (Dilution). BOP 3.2 IF the blender is set for automatic makeup per Enclosure 4.1 (Automatic Makeup), record the setpoint on 1NV-242A (RMWST To B/A Blender Ctrl): ___________gpm BOP 3.3 Ensure the following valve control switches in AUTO: 1NV-242A (RMWST To B/A Blender Ctrl) 1NV-181A (B/A Blender Otlt To VCT) BOP 3.4 Ensure 1NV-242A (RMWST To B/A Blender Ctrl) controller in auto. BOP 3.5 Ensure at least one reactor makeup water pump is in AUTO or ON. BOP 3.6 Record the desired volume of reactor makeup water to be added. _________ gallons BOP 3.7 Adjust the total makeup counter to the desired volume of reactor makeup water to be added. (R.M.) BOP 3.8 Place the NC MAKEUP MODE SELECT switch to the DILUTE position.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 1 Page 9 of 38 Event

Description:

Power Increase Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 9 of 38 NOTE: High letdown flow rates result in increased backpressure on the letdown line. If letdown flow is > 90 gpm, it may be desirable to reduce flow rate to 80 gpm to avoid the Rx Make-up Flow Deviation alarm and associated automatic actions. BOP 3.9 IF required, adjust the setpoint for 1NV-242A (RMWST To B/A Blender Ctrl) to the desired flow. NOTE TO EVALUATOR: Step 3.10 will not apply. BOP 3.11 IF AT ANY TIME it is desired to divert letdown to the RHT manually operate 1NV-172A (3-Way Divert To VCT-RHT) as follows: 3.11.1 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) to the RHT position. 3.11.2 Ensure VCT level is monitored continuously while diverting to the RHT. NOTE: Procedure may continue while performing the following step. 3.11.3 WHEN desired VCT level is reached return 1NV-172A (3-Way Divert To VCT-RHT) to auto as follows: 3.11.3.1 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) in the VCT position. 3.11.3.2 Place the control switch for 1NV-172A (3-Way Divert To VCT-RHT) in the AUTO position. BOP 3.12 IF AT ANY TIME during the makeup it becomes necessary to change the makeup flow rate, adjust the setpoint for 1NV-242A (RMWST To B/A Blender Ctrl) as necessary to achieve the desired flow.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 1 Page 10 of 38 Event

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Power Increase Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 10 of 38 BOP 3.13 IF AT ANY TIME while dilution is in progress it becomes necessary to stop the dilution, perform the following: 3.13.1 Place the NC MAKEUP CONTROL switch to the STOP position. 3.13.2 Ensure the following valves close: 1NV-242A (RMWST To B/A Blender Ctrl) 1NV-181A (B/A Blender Otlt To VCT) 3.13.3 IF in AUTO, verify the reactor makeup water pump stops. 3.13.4 Record reactor makeup water volume added as indicated on the total makeup counter. ____________ gallons 3.13.5 WHEN conditions allow resuming the dilution, perform the following: 3.13.5.1 Determine remaining volume to be added by subtracting the amount previously added (Step 3.13.4) from the desired volume to be added (Step 3.6). _______ - _____ = ____ gallons (Step 3.6) (Step 3.13.4) 3.13.5.2 Adjust total makeup counter to the volume of reactor makeup water determined in Step 3.13.5.1. (R.M.) 3.13.5.3 Place the NC MAKEUP CONTROL switch in the START position. (R.M.) 3.13.5.4 Verify the following: 1NV-242A (RMWST To B/A Blender Ctrl) modulates to establish desired flow 1NV-181A (B/A Blender Otlt To VCT) opens 3.13.5.5 IF in AUTO, verify the reactor makeup water pump starts. BOP 3.14 WHILE makeup is in progress, monitor the following for expected results: Control rod motion NC System Tavg Reactor Power Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 1 Page 11 of 38 Event

Description:

Power Increase Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 11 of 38 NOTE: If a small makeup is being performed, placekeeping for Steps 3.15 through 3.17 may be performed after Step 3.18 is performed. BOP 3.15 Place the NC MAKEUP CONTROL switch to the START position. (R.M.) BOP 3.16 Verify the following: 1NV-242A (RMWST To B/A Blender Ctrl) modulates to establish desired flow 1NV-181A (B/A Blender Otlt To VCT) opens BOP 3.17 IF in AUTO, verify the reactor makeup water pump starts. NOTE: The total makeup counter may count up 1 - 5 gallons after termination. BOP 3.18 WHEN the desired volume of reactor makeup water is reached on the total makeup counter, ensure the following valves close. (R.M.) 1NV-242A (RMWST To B/A Blender Ctrl) 1NV-181A (B/A Blender Otlt To VCT) BOP 3.19 IF automatic makeup is desired, perform one of the following: 3.19.1 IF it is desired to change the blender outlet boron concentration, refer to Enclosure 4.1 (Automatic Makeup). OR 3.19.2 IF makeup at the previous concentration is acceptable AND the system was previously aligned per Enclosure 4.1 (Automatic Makeup), perform the following: 3.19.2.1 Ensure the controller for 1NV-242A (RMWST To B/A Blender Ctrl) is set to the value recorded in Step 3.2. (R.M.) 3.19.2.2 Place the NC MAKEUP MODE SELECT switch in AUTO. 3.19.2.3 Place the NC MAKEUP CONTROL switch to the START position. (R.M.) NOTE TO EVALUATOR: Step 3.20 will END OF DILUTION Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 1 Page 12 of 38 Event

Description:

Power Increase Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 12 of 38 NOTE TO EVALUATOR: The following steps are from OP/1/B/6300/001, Turbine Generator, Enclosure 4.2 (Load Changing) starting at step 3.1.2. RO 3.1.2 Increase turbine generator load by performing the following: 3.1.2.1 Select LOAD RATE and verify it illuminates. 3.1.2.2 Input the desired load rate. 3.1.2.3 Select ENTER or OK and verify LOAD RATE goes dark. 3.1.2.4 Select TARGET and verify it illuminates. 3.1.2.5 Input the desired load target. 3.1.2.6 Select ENTER and verify TARGET light goes dark. 3.1.2.7 Verify new load target appears on Target Display. 3.1.2.8 Select GO and verify it illuminates to start load increase. 3.1.2.9 Coordinate with Secondary Chemistry to adjust S/G blowdown flowrates to obtain maximum blowdown for the appropriate load Booth Operator will insert Trigger 1 for EVENT 2 at the discretion of the lead examiner. END OF EVENT 1 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 2 Page 13 of 38 Event

Description:

1SV-42 (SM ATMOS DUMP #7) fails open Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 13 of 38 EVENT 2 Indications: OPEN RO Recognize 1SV-42 open RO RO Close 1SV-51 (SM ATMOS DUMP #7 ISOL) CREW Enter AP/1/A/5500/028 (Secondary Steam Leak) NOTE TO EVALUATOR: The following actions are from AP/1/A/5500/028 (Secondary Steam Leak). RO and BOP 1. Monitor Enclosure 1 (Foldout Page). RO 2. Verify turbine ONLINE. RO 3. Verify the following: Reactor power LESS THAN OR EQUAL TO 100% POWER T-Avg WITHIN 1.5°F OF T-Ref. RO 3. RNO Perform the following: a. Select MANUAL on turbine control panel. b. Depress CONTROL VALVES LOWER pushbutton and reduce turbine load to maintain: Reactor power LESS THAN OR EQUAL TO 100% POWER T-Avg WITHIN 1.5°F OF T-Ref. RO 4. Verify proper reactor response as follows: Control rods IN AUTO AND STEPPING IN P/R neutron flux DECREASING. RO 4 RNO IF T-Avg is greater than 1.5°F higher than T-Ref, THEN insert control rods as required to maintain T-Avg within 1°F of T-Ref. RO 5. IF AT ANY TIME reactor power is greater than 100%, THEN perform Step 3 RNO.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 2 Page 14 of 38 Event

Description:

1SV-42 (SM ATMOS DUMP #7) fails open Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 14 of 38 BOP 6. Verify Pzr level STABLE OR INCREASING. CRS 7. IF AT ANY TIME while in this procedure Pzr level is decreasing in an uncontrolled manner, THEN RETURN TO Step 6. RO or BOP 8. IF AT ANY TIME VCT level goes below 23%, THEN align NV pump suction to FWST as follows: a. OPEN the following valves: 1NV-252A (NV Pumps Suct From FWST) 1NV-253B (NV Pumps Suct From FWST). b. CLOSE the following valves: 1NV-188A (VCT Otlt Isol) 1NV-189B (VCT Otlt Isol). RO or BOP 9. Attempt to identify and isolate leak as follows: a. Verify the following conditions NORMAL: Containment temperature Containment pressure Containment humidity Containment floor & equipment sump level. b. Dispatch operators to locate and identify source of steam leak. c. Verify S/G PORVs CLOSED. d. Verify condenser dump valves CLOSED. e. Verify atmospheric dump valves CLOSED. RO 9.e. RNO e. Perform the following: 1) Select OFF RESET on the following switches: STEAM DUMP INTLK BYP TRN A STEAM DUMP INTLK BYP TRN B. 2) IF valve will not close, THEN CLOSE affected atmospheric dump valve isolation valve. NOTE TO EVALUATOR: RNO Step 9.e.3) will not apply RO f. Verify CA PMP #1 OFF. NOTE TO EVALUATOR: The crew will determine step 9.g. does not apply Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 2 Page 15 of 38 Event

Description:

1SV-42 (SM ATMOS DUMP #7) fails open Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 15 of 38 SRO 10. Determine required notifications: REFER TO RP/0/A/5000/001 (Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). BOP 11. Notify RP of leak. RO 12. Verify LEAK ISOLATED. SRO 13. Determine long term plant status. RETURN TO procedure and step in effect. NOTE TO EVALUATOR: Tech Spec 3.4.1 (RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits) Condition A (Restore DNB parameter(s) to within limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) may need to be entered if the crew was slow to isolate the leak. This may need to be addressed during follow up questioning. Booth Operator will insert Trigger 3 for Event 3 at the discretion of the lead examiner. END OF EVENT 2 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 3 Page 16 of 38 Event

Description:

N-41 blown instrument fuse. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 16 of 38 EVENT 3 Indications: 1AD- 1AD- 1AD- 1AD- 1AD- 1AD- 1AD- 1AD- NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/016, Malfunction of Nuclear Instrumentation System. NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/016 Malfunction of Nuclear Instrumentation System, Case IV (Power Range Malfunction). RO 1. Verify all rod motion STOPPED. RO 2. Verify 1AD- DARK. 2. RNO Adjust Turbine load to maintain T-Avg at T-Ref. RO 3. Identify failed P/R channel: N-41 (failed low) OR N-42 OR N-43 OR N-44. RO 4. Ensure unaffected channels OPERABLE. BOP 5. Request IAE to place the following bistables in the tripped condition. REFER TO Model W/O #00874531: OT DELTA T OP DELTA T.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 3 Page 17 of 38 Event

Description:

N-41 blown instrument fuse. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 17 of 38 BOP 6. Perform the following actions at the Miscellaneous Control And Indication Panel: a. Place the appropriate ROD STOP BYPASS switch to the affected channel position. b. Verify the affected nuclear overpower rod stop channel bypassed status light (1SI-19) LIT. c. Place POWER MISMATCH BYPASS switch to the affected channel position. BOP 7. Perform the following actions at the Detector Current Comparator panel: a. Place UPPER SECTION channel defeat switch to the affected channel. b. Verify the CHANNEL DEFEAT light for the upper section LIT. c. Place LOWER SECTION channel defeat switch to the affected channel. d. Verify the CHANNEL DEFEAT light for the lower section LIT. BOP 8. At the Comparator And Rate panel NOTE The following annunciators will actuate in the following step: 1AD-2, A/1 P/R/HI NEUTRON FLUX RATE ALERT 1AD-2, A/3, P/R/ HI NEUTRON FLUX HI SET POINT ALERT 1AD-2, B/5, P/R HI VOLTAGE FAILURE BOP 9. De-energize the affected channel as follows: a. Remove the control power fuses at Power Range A drawer. NOTE Replacement of the affected P/R control power fuses shall not occur without authorization of the Superintendent of Operations or his designee. BOP 9.b. Request the OSM to maintain the control power fuses under his control. c. Verify the affected Power Range cabinet shows no physical signs of damage. CREW 10. Ensure affected channel bistables are in the required state. REFER TO Enclosure 1 (P/R Bistables That Must Be Tripped). RO 11. Ensure operable P/R channel selected to record on NIS RECORDER.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 3 Page 18 of 38 Event

Description:

N-41 blown instrument fuse. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 18 of 38 RO 12. Adjust control rods to maintain T-Ave at T-Ref. RO 13. WHEN T-avg within 1°F of T-Ref, AND auto rod control desired, THEN return control rods to auto. CREW 14. Determine and correct cause of P/R malfunction. SRO 15. Ensure compliance with appropriate Tech Specs: 3.2.4 (Quadrant Power Tilt Ratio (QPTR)) 3.3.1 (Reactor Trip System (RTS) Instrumentation). NOTE TO EVALUATOR: The SRO should determine that the following Tech Spec 3.3.1 (Reactor Trip System (RTS) Instrumentation) conditions for associated functions should be entered: 2. Power Range Neutron Flux a. High Condition D (Perform SR 3.2.4.2 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when > 75 % RTP and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to place the channel in trip) 3. Power Range Neutron Flux High Positive Rate Condition D (Perform SR 3.2.4.2 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when > 75 % RTP and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to place the channel in trip) 6. Condition E (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to place the channel in trip) 7. Condition E (72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to place the channel in trip) 16. Reactor Trip System Interlocks b. Low Power Reactor Trips Block, P-7, Condition S (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to verify interlock is in required state for existing conditions) c. Power Range Neutron Flux, P-8, - Condition S (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to verify interlock is in required state for existing conditions) d. Power Range Neutron Flux, P-9, - Condition S (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to verify interlock is in required state for existing conditions) e. Power Range Neutron Flux, P-10, - Condition R (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to verify interlock is in required state for existing conditions) Tech Spec conditions that have been entered.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 3 Page 19 of 38 Event

Description:

N-41 blown instrument fuse. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 19 of 38 SRO 16. Determine required notifications: REFER TO RP/0/A/5000/001 (Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). BOP 17. Notify Reactor Group Engineer of occurrence. SRO 18. WHEN the affected P/R channel is repaired, THEN ensure IAE returns the channel to service. SRO 19. Determine long term plant status. RETURN TO procedure in effect. Booth Operator will insert Trigger 5 for EVENT 4 at the discretion of the lead examiner. summarize the event. END OF EVENT 3 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 4 Page 20 of 38 Event

Description:

1NV-309 (SEAL WATER INJECTION FLOW) fails open. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 20 of 38 EVENT 4 Indications: 1AD-7, BOP Recognize 1NV-309 failing open BOP Take manual control of 1NV-309 and control seal water flow. CREW Enter AP/1/A/5500/008, Malfunction of Reactor Coolant Pump, Case II (Loss of Seal Water Injection) NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/008, Malfunction of Reactor Coolant Pump NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/008, Malfunction of Reactor Coolant Pump, Case II (Loss of Seal Water Injection). RO and BOP 1. Monitor Enclosure 1 (Foldout Page). CAUTION Failure to restore NC pump seal cooling within 10 minutes will cause damage to the NC pump seals resulting in NC inventory loss. BOP 2. Verify the following parameters for all NC Pumps: #1 seal outlet temperature LESS THAN 235°F Lower bearing temperature LESS THAN 225°F #1 seal delta P GREATER THAN 200 PSID. BOP 3. Verify 1AD-7, C/1 NCP #1 SEAL LEAKOFF HI FLOW DARK. NOTE In the following steps, seal injection flow should be established slowly to any NC pump that suffered a total loss of seal injection. BOP 4. Verify N/R CHRG LN FLOW GREATER THAN OR EQUAL TO 32 GPM. BOP 5. Verify the following seal injection filter alarms DARK: 1AD-7, B/4 SEAL INJECTION FILTER A HI D/P 1AD-7, E/4 SEAL INJECTION FILTER B HI D/P. BOP 6. Verify TOTAL SEAL WTR FLOW GREATER THAN OR EQUAL TO 32 GPM.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 4 Page 21 of 38 Event

Description:

1NV-309 (SEAL WATER INJECTION FLOW) fails open. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 21 of 38 BOP 6. RNO Perform the following: a. Slowly adjust 1NV-309 (Seal Water Injection Flow) to establish 32 GPM TOTAL SEAL WTR FLOW. b. IF seal water injection flow is established, THEN: 1) Determine and correct the cause of loss of seal water injection. SRO 2) GO TO Step 9. BOP 9. Verify the following NC pump seal return isolation valves OPEN: 1NV-52A (NC Pump 1A Seal Return) 1NV-63B (NC Pump 1B Seal Return) 1NV-74A (NC Pump 1C Seal Return) 1NV-85B (NC Pump 1D Seal Return). BOP 10. WHEN plant conditions allow, THEN perform PT/1/A/4150/001C (NC Pump Seal Injection Flow Verification). SRO 11. Ensure compliance with appropriate Tech Specs: 3.4.5 (RCS Loops MODE 3) 3.4.6 (RCS Loops MODE 4) 3.4.13 (RCS Operational Leakage) 3.5.5 (Seal Injection Flow) SLC 16.7-9 (Standby Shutdown System). NOTE TO EVALUATOR: No Tech Spec conditions need to be entered. SRO 12. Determine required notifications: REFER TO RP/0/A/5000/001 (Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). CREW 13. Determine long term plant status. RETURN TO procedure in effect. Booth Operator will insert Trigger 11 for EVENT 5 at the discretion of the lead examiner. summarize the event. END OF EVENT 4 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 5 Page 22 of 38 Event

Description:

FWST Level channel 3 fails low. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 22 of 38 EVENT 5 Indications: 1AD- 1AD-- 1AD-9, FWST LO- BOP Recognize 1FWP5120 (FWST WR LEVEL CH 3) failed low. SRO Enter Tech Spec 3.3.2 (Engineered Safety Feature Actuation System (ESFAS) Instrumentation) Condition N NOTE TO EVALUATOR The following actions are taken from the annunciator response BOP IMMEDIATE ACTIONS: Verify low level by checking against the other channels. NOTE TO EVALUATOR Supplementary Actions 1 and 2 will not apply and action 3 will not be necessary. SRO 4. IF a channel failure has occurred, perform the following: 4.1 Refer to Tech Spec 3.3.2 for minimum operable channel requirements. NOTE TO EVALUATOR: Tech Spec 3.3.2 (Engineered Safety Feature System (ESFAS) Instrumentation), Condition N (Place channel in bypass within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, OR Be in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Be in MODE 5 within 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />) should be entered. Booth Operator will insert Trigger 13 for EVENT 6 at the discretion of the lead examiner. Tech Spec conditions that have been entered. BOP 4.2Issue the appropriate Model W/Os to have IAE provide emergency repairs on the affected channel(s): 01069039 1FWLT5000: Repair CH 1 FWST Level 01069040 1FWLT5010: Repair CH 2 FWST Level 01069041 1FWLT5120: Repair CH 3 FWST Level 01069042 1FWLT5130: Repair CH 4 FWST Level BOP 4.3 Initiate a work request to have the channel repaired. summarize the event. END OF EVENT 5 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 6 Page 23 of 38 Event

Description:

1A NC (Reactor Coolant) Pump #1 seal failure. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 23 of 38 EVENT 6 Indications: 1AD- CREW Recognize 1A NC Pump seal failure. CREW Enter AP/1/A/5500/008, Malfunction of Reactor Coolant Pump, Case I (NC Pump Seal Malfunction) RO Trip the Reactor BOP Trip the 1A NC (Reactor Coolant) Pump CREW GO TO EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/008, Malfunction of Reactor Coolant Pump NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/008, Malfunction of Reactor Coolant Pump, Case I (NC Pump Seal Malfunction). RO AND BOP 1. Monitor Enclosure 1 (Foldout Page). BOP 2. Verify the following parameters for all NC Pumps: #1 seal outlet temperature - LESS THAN 235°F Lower bearing temperature - LESS THAN 225°F #1 seal delta P - GREATER THAN 200 PSID. NOTE If seal maintenance has been performed, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of NC pump operation may be required before seals seat and operate properly. BOP 3. Verify any NC pump #1 seal leakoff flow - GREATER THAN 6 GPM. BOP 4. WHEN NC loop flow indicates the affected NC pump(s) is stopped, THEN close the affected NC pump(s) seal return isolation valve. REFER TO Enclosure 1 (Foldout Page). BOP 5. Ensure the KC thermal barrier isolation valve for the affected NC pump(s) - OPEN: 1KC-394A (NC Pump 1A Therm Bar Otlt) 1KC-364B (NC Pump 1B Therm Bar Otlt) 1KC-345A (NC Pump 1C Therm Bar Otlt) 1KC-413B (NC Pump 1D Therm Bar Otlt).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 6 Page 24 of 38 Event

Description:

1A NC (Reactor Coolant) Pump #1 seal failure. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 24 of 38 BOP 6. Verify #1 seal leakoff flow - LESS THAN 7.5 GPM. SRO 6. RNO GO TO Step 12. RO 12. Shutdown the affected NC pump(s) within 5 minutes as follows: a. Verify Unit - IN MODE 1 OR 2. NOTE TO EVALUATOR: Step 12.b will not apply RO c. Trip reactor. BOP d. WHEN reactor power less than 5%, THEN perform the following: 1) Trip the affected NC pump(s). 2) Ensure the normal spray valve associated with the tripped NC pump(s) - IN MANUAL AND CLOSED. SRO e. GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection). Transition to EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) END OF EVENT 6 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 7, 8 and 9 Page 25 of 38 Event

Description:

LBLOCA, 1SA-5 (S/G 1C SM TO CAPT) fails open, Both Hydrogen Skimmer fans fail to start. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 25 of 38 EVENTS 7, 8 AND 9 NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) RO and BOP 1. Monitor Enclosure 1 (Foldout Page). RO 2. Verify Reactor Trip: Perform the following: All rod bottom lights - LIT All reactor trip and bypass breakers - OPEN I/R power - DECREASING. RO 3. Verify Turbine Trip: Perform the following: All turbine stop valves - CLOSED BOP 4. Verify 1ETA and 1ETB - ENERGIZED. RO 5. Verify S/I is actuated: a. "SAFETY INJECTION ACTUATED" status light (1SI-13) LIT b. Both E/S load sequencer actuated status lights (1SI-14) - LIT. RO 6. Announce "Unit 1 Safety Injection". SRO 7. Determine required notifications: REFER TO RP/0/A/5000/001(Classification Of Emergency) REFER TO RP/0/B/5000/013 (NRC Notification Requirements). RO or BOP 8. Verify all Feedwater Isolation status lights (1SI-5) - LIT BOP 9. Verify Phase A Containment Isolation status as follows: a. Phase A "RESET" lights - DARK. BOP b. Monitor Light Panel Group 5 St lights on energized train(s) - LIT. BOP 10. Verify proper Phase B actuation as follows: a. Verify Containment pressure - HAS REMAINED LESS THAN 3 PSIG Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 7, 8 and 9 Page 26 of 38 Event

Description:

LBLOCA, 1SA-5 (S/G 1C SM TO CAPT) fails open, Both Hydrogen Skimmer fans fail to start. Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 26 of 38 BOP 10. RNO a. Perform the following: 1) Verify Phase B Isolation has actuated as follows: a) Phase B Isolation "RESET" lights - DARK. NOTE TO EVALUATOR: RNO Step 10.a.1)b) will not apply BOP c) Verify following monitor light panel lights - LIT: Group 1 Sp lights Group 5 Sp lights Group 5 St light L/11. NOTE TO EVALUATOR: RNO Step 10.a.1)d) will not apply RO or BOP 10. RNO a. 2) Stop all NC pumps. BOP 10. RNO a. 3) Maintain seal injection flow. BOP 10. RNO a. 4) Energize H2 igniters. RO or BOP 10. RNO a. 5) Dispatch operator to perform the following: a) Secure all ice condenser air handling units. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 11 (Securing All Ice Condenser Units). b) Place containment H2 analyzers in service. REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems). BOP 10. RNO a. 6) WHEN 9 minutes has elapsed, THEN verify proper VX system operation. REFER TO Enclosure 5 (VX System Operation). NOTE TO EVALUATOR: The BOP will correct Event 9 while performing Enclosure 5 by starting the 1A Hydrogen Skimmer Fan. END OF EVENT 9 SRO 10. RNO a. 7) GO TO Step 11. RO 11. Verify proper CA pump status as follows: a. Motor driven CA pumps - ON. b. 3 S/G N/R levels - GREATER THAN 11%.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 7 and 8 Page 27 of 38 Event

Description:

LBLOCA, 1SA-5 (S/G 1C SM TO CAPT) fails open Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 27 of 38 BOP 12. Verify all of the following S/I pumps - ON: NV pumps ND pumps NI pumps. BOP 13. Verify all KC pumps - ON. BOP 14. Verify all Unit 1 and Unit 2 RN pumps ON. BOP 15. Verify proper ventilation systems operation as follows: REFER TO Enclosure 2 (Ventilation System Verification). Notify Unit 2 operator to perform Enclosure 3 (Opposite Unit Ventilation Verification). NOTE TO EVALUATOR: SRO will state that they will hand Enclosure 3 to a Unit 2 operator and set Enclosure 3 off to the side RO 16. Verify all S/G pressures - GREATER THAN 775 PSIG. RO 17. Verify proper S/I flow as follows: a. "NV S/I FLOW" - INDICATING FLOW. b. NC pressure - LESS THAN 1620 PSIG. c. NI pumps - INDICATING FLOW. d. NC pressure - LESS THAN 285 PSIG. e. ND pumps - INDICATING FLOW TO C-LEGS. RO or BOP 18. WHEN time and manpower permit (within two hours of event), THEN monitor Spent Fuel Pool level and temperature. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring). RO 19. Control S/G levels as follows: a. Verify total CA flow - GREATER THAN 450 GPM. b. WHEN each S/G N/R level greater than 11% (29% ACC), THEN control feed flow to maintain that S/G N/R level between 11% (29% ACC) and 50%. NOTE TO EVALUATOR: The RO will address Event 8 by closing the CAPT TRIP T/V CTRL, or by closing the CA PUMP #1 FLOWS to the S/Gs (1CA-64, 1CA-52, 1CA-48, 1CA-36, or by closing the CA PUMP 1 DISCH TO S/Gs ISOL (1CA-66B, 1CA-54B, 1CA-50A, 1CA-38A). END OF EVENT 8 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 7 Page 28 of 38 Event

Description:

LBLOCA Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 28 of 38 NOTE TO EVALUATOR: ACC values are used for the remainder of the scenario. RO 20. Verify all CA isolation valves - OPEN. BOP 21. Verify S/I equipment status based on monitor light panel - IN PROPER ALIGNMENT. NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance. RO 22. Control NC temperature. REFER TO Enclosure 4 (NC Temperature Control). BOP 23. Verify Pzr PORV and Pzr Spray Valve status as follows: a. All Pzr PORVs - CLOSED. b. Normal Pzr spray valves - CLOSED. c. At least one Pzr PORV isolation valve - OPEN. RO or BOP 24. Verify NC subcooling based on core exit T/Cs - GREATER THAN 0°F. RO or BOP 24. RNO IF any NV OR NI pump is on, THEN perform the following: a. Ensure all NC pumps - OFF. b. Maintain seal injection flow. RO or BOP 25. Verify main steamlines intact: All S/G pressures - STABLE OR INCREASING ALL S/Gs - PRESSURIZED. NOTE TO EVALUATOR: The Crew may determine that the 1C S/G is faulted due to the failure of 1SA-5 (S/G 1C SM TO CAPT) and transition to E-2 to isolate the S/G. REFER to Attachment 11. BOP 26. Verify S/G tubes are intact as follows: Verify the following EMF trip 1 lights - DARK: 1EMF-33 (Condenser Air Ejector Exhaust) 1EMF-26 (Steamline 1A) 1EMF-27 (Steamline 1B) 1EMF-28 (Steamline 1C) 1EMF-29 (Steamline 1D). RO or BOP All S/G levels - STABLE OR INCREASING IN A CONTROLLED MANNER.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 7 Page 29 of 38 Event

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LBLOCA Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 29 of 38 BOP 27. Verify NC System is intact as follows: Containment pressure - LESS THAN 1 PSIG. IF normal off-site power is available, THEN verify containment pressure less than 0.3 PSIG. Containment high range EMFs - LESS THAN 3 R/HR: 1EMF-53A (Containment Trn A) 1EMF-53B (Containment Trn B). Containment EMF trip 1 lights - DARK: 1EMF-38 (Containment Particulate) 1EMF-39 (L) (Containment Gas (Lo Range)). Containment sump level - STABLE. BOP 27. RNO Perform the following: a. Energize H2 igniters. RO or BOP 27. RNO b. Dispatch operator to perform the following: 1) Secure all ice condenser air handling units. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 11(Securing All Ice Condenser Units). 2) Place containment H2 analyzers in service. REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems). NOTE TO EVALUATOR: Step 27. RNO c. will not apply CREW d. Concurrently: Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees). GO TO EP/1/A/5000/E-1 (Loss Of Reactor Or Secondary Coolant).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 7 Page 30 of 38 Event

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LBLOCA Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 30 of 38 NOTE TO EVALUATOR: The crew will address the challenge to the NC (Reactor Coolant) System Integrity per EP/1/A/5000/FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition) if not done previously. NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition) RO or BOP 1. Verify NC pressure - GREATER THAN 285 PSIG. CREW 1. RNO IF ND flow to C-Legs is greater than 675 GPM, THEN RETURN TO procedure and step in effect. summarize the event. TRANSITION TO EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant) NOTE TO EVALUATOR: The following steps are from EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant) RO and BOP 1. Monitor Enclosure 1 (Foldout Page). RO or BOP 2. Verify NC subcooling based on core exit T/Cs - GREATER THAN 0°F. RO or BOP 2. RNO IF any NV OR NI pump is on, THEN perform the following: a. Ensure all NC pumps - OFF. b. Maintain seal injection flow. BOP 3. Verify main steamlines intact: All S/G pressures - STABLE OR INCREASING All S/Gs - PRESSURIZED RO 4. Control intact S/G N/R levels as follows: a. Verify N/R level in all intact S/Gs - GREATER THAN 11% (29% ACC). b. THROTTLE feed flow to maintain all intact S/G N/R levels between 11% (29% ACC) and 50%.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 7 Page 31 of 38 Event

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LBLOCA Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 31 of 38 BOP 5. Reset the following: a. ECCS. b. D/G load sequencers. c. Phase A d. Phase B. RO or BOP e. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on. BOP 6. Establish VI to Containment as follows: Ensure 1VI-77B (VI Cont Isol) - OPEN. Verify VI pressure - GREATER THAN 85 PSIG. RO 7. Verify secondary radiation - NORMAL: a. Ensure the following signals - RESET: 1) CA System valve control BOP 2) KC NC NI NM St signals. NOTE TO EVALUATOR: The BOP will open the following valves when aligning the S/Gs for chemistry sample in step b. below: 1NM-191B (S/G 1A SMPL HDR CONT ISOL) 1NM-201A (S/G 1B SMPL HDR CONT ISOL) 1NM-211B (S/G 1C SMPL HDR CONT ISOL) 1NM-221A (S/G 1D SMPL HDR CONT ISOL) 1NM-190A (S/G 1A BLDWN SMPL CONT ISOL) 1NM-200B (S/G 1B BLDWN SMPL CONT ISOL) 1NM-210A (S/G 1C BLDWN SMPL CONT ISOL) 1NM-220B (S/G 1D BLDWN SMPL CONT ISOL) BOP b. Align all S/Gs for Chemistry sampling. RO or BOP c. Perform at least one of the following: Notify Chemistry to sample all S/Gs for activity. OR Notify RP to frisk all cation columns for activity.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 7 Page 32 of 38 Event

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LBLOCA Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 32 of 38 BOP d. Verify the following EMF trip 1 lights - DARK: 1EMF-33 (Condenser Air Ejector Exhaust) 1EMF-26 (Steamline 1A) 1EMF-27 (Steamline 1B) 1EMF-28 (Steamline 1C) 1EMF-29 (Steamline 1D). RO e. Verify all S/Gs - INTACT All S/G pressures - STABLE OR INCREASING All S/Gs - PRESSURIZED RO or BOP f. WHEN activity results are reported, THEN verify all S/Gs indicate no activity. BOP 8. Verify Pzr PORVs and Isolation Valves: a. Power to all Pzr PORV isolation valves - AVAILABLE. b. All Pzr PORVs CLOSED c. Any Pzr PORV isolation valve - OPEN. RO or BOP d. IF AT ANY TIME any Pzr PORV opens due to high pressure, THEN after Pzr pressure decreases to less than 2315 PSIG, ensure PORV closes or is isolated. RO 9. Verify S/I termination criteria: a. NC subcooling based on core exit T/Cs - GREATER THAN 0°F. SRO 9.a. RNO a. GO TO Step 9.f. Terminate the scenario at the discretion of the Lead Examiner. RO or BOP f. Monitor S/I termination criteria. REFER TO Enclosure 2 (S/I Termination Criteria). CREW g. IF AT ANY TIME S/I termination criteria is met while in this procedure, THEN RETURN TO Step 9. RO or BOP 10. Determine if ND pumps should be stopped: a. NC pressure - GREATER THAN 285 PSIG. SRO 10.a. RNO a. GO TO Step 12.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 7 Page 33 of 38 Event

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LBLOCA Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 33 of 38 BOP 12. Verify D/Gs should be stopped: a. Any D/G - ON. b. Verify 1ETA is energized by offsite power as follows: "D/G 1A BKR TO ETA" - OPEN 1ETA - ENERGIZED. c. Dispatch operator to stop 1A D/G and place in standby readiness. REFER TO OP/1/A/6350/002 (Diesel Generator Operation). d. Verify 1ETB is energized by offsite power as follows: "D/G 1B BKR TO ETB" - OPEN 1ETB - ENERGIZED. e. Dispatch operator to stop 1B D/G and place in standby readiness. REFER TO OP/1/A/6350/002 (Diesel Generator Operation). BOP 13. Obtain containment H2 concentration as follows: a. Ensure operator dispatched to secure all ice condenser air handling units. REFER TO Enclosure 3 (Securing All Ice Condenser Air Handling Units). b. Verify containment H2 analyzers - IN SERVICE CREW 13.b. RNO b. Perform the following: 1) Dispatch operator to place containment H2 analyzers in service. REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems). 2) WHEN H2 analyzers are in service, THEN perform Steps 13.c through 13.e. 3) GO TO Step 14.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 7 Page 34 of 38 Event

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LBLOCA Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 34 of 38 BOP 14. Initiate evaluation of plant status as follows: a. Verify Cold Leg Recirc capability from at least one train: A Train: 1A ND pump - AVAILABLE 1NI-185A (ND Pump 1A Cont Sump Suct) POWER AVAILABLE OR B Train: 1B ND pump - AVAILABLE 1NI-184B (ND Pump 1B Cont Sump Suct) POWER AVAILABLE b. Determine if leak is in auxiliary building: 1) Verify auxiliary building radiation: All area monitor EMF trip 1 lights - DARK. EMF-41 (Aux Bldg Ventilation) trip 1 light DARK NOTE The following step is checking for a significant NC leak into the ND System. 2) Verify NC to ND pressure boundary intact as follows: ND Pressure - NORMAL ND Temperature - NORMAL ND Flow NORMAL c. Determine if NC is leaking into KC system: 1EMF-46A (COMPONENT COOLING TRAIN A) trip 1 light - DARK . 1EMF-46B (COMPONENT COOLING TRAIN B) trip 1 light - DARK . d. Ensure KC NC NI NM St signals - RESET e. WHEN TSC is staffed, THEN notify TSC to perform Enclosure 7 (TSC Actions). RO or BOP 15. Determine if NC System cooldown and depressurization is required: a. NC pressure - GREATER THAN 285 PSIG RO 15. RNO a. IF ND flow to C-Legs is greater than 675 GPM, THEN GO TO Step 16.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 5 Event # 7 Page 35 of 38 Event

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LBLOCA Time Position Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 35 of 38 BOP 16. Verify Containment pressure - GREATER THAN 3 PSIG. CRS 16. RNO Perform the following: a. IF starting of any VX fan has previously been attempted, THEN GO TO Step 17. BOP 17. Determine if transfer to Cold Leg Recirc is required: a. FWST level - LESS THAN 20% (1AD-9, D/8 "FWST 2/4 LO LEVEL"). CREW 17. RNO a. RETURN TO Step 14. END OF EVENT 7 END OF SCENARIO Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 36 of 38 Attachment List Scenario 4 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 OP/1/A/6150/009 Enclosure 4.5 (Manual Operation of the Makeup Controls), rev. 079 ATTACHMENT 4 AP/1/A/5500/028 Enclosure 1 (Foldout Page), rev. 007 ATTACHMENT 5 AP/1/A/5500/008 Enclosure 1 (Foldout Page), rev. 018 ATTACHMENT 6 EP/1/A/5000/E-0 Enclosure 1 (Foldout Page), rev. 042 ATTACHMENT 7 EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification), rev. 042 ATTACHMENT 8 EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control), rev. 042 ATTACHMENT 9 EP/1/A/5000/E-0 Enclosure 5 (VX System Operation), rev. 042 ATTACHMENT 10 EP/1/A/5000-G-1 Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring), rev.007 ATTACHMENT 11 EP/1/A/5000/E-2 (Faulted Steam Generator Isolation), rev. 015 ATTACHMENT 12 EP/1/A/5000/E-1 Enclosure 1 (Foldout Page), rev. 028 Catawba Nuclear Station NRC Exam May 2014 Appendix D Catawba NRC Exam May 2014 Scenario 5 NUREG 1021 Revision 9 Page 37 of 38 ATTACHMENT 1 CREW CRITICAL TASK

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SAT UNSAT CT # CRITICAL TASK Comments:

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 75% BOL 1298 PPM per OAC Controlling Procedure OP/1/A/6100/003 (Controlling Procedure for Unit Operation), Enclosure 4.1 (Power Increase) is in progress up to step 3.62. Other Information Needed to Assume the Shift Unit 2 is at 100%. The 1A KF (Fuel Pool Cooling) Pump is tagged out for preventative maintenance. The 1A2 CFPT MOP is tagged out for motor replacement. Increase power to 100% per the reactivity management plan. NEOs Available Six NEOs are available as listed on the status board METEOROLOGICAL CONDITIONS Upper wind direction = 315 degrees, speed = 10 mph Lower wind direction = 315 degrees, speed = 10.5 mph Forecast calls for Severe Thunderstorm Watch for the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.